boric acid concentration reduction technical bases

BORIC ACID CONCENTRATION REDUCTION

TECHNICAL BASES

AND

OPERATIONAL ANALYSIS

PREPARED FOR

FLORIDA POWER & LIGHT COMPANY

TURKEY POINT NUCLEAR UNITS 3 AND 4

NOVEMBER 1990

Cem leted B :

ngineer

Reviewed B : W

A roved B :

ngineer

anage

Date l/ z6

Date I( (~',t 'fO.

ABB COMBUSTION ENGINEERING NUCLEAR POWER

MECHANICAL PRODUCTS AND SERVICES iWindsor, Connecticut

9iOi3i0092 eiOi24PDR *DOCK 05000250P PDR

Report No. 849963-MPS-5MISC-003 REV 0 Title Page

Section

1.0 INTRODUCTION

TABLE OF CONTENTS

Title ~Pa e No.

2.0

3.0

4.0

5.0

1. 1 PURPOSE AND OBJECTIVES1.2 BACKGROUND1.3 BASIS OF BORIC ACID CONCENTRATION REDUCTION

PERFORMANCE RE UIREMENTS

2.1 DESIGN BASIS PERFORMANCE REQUIREMENTS:SAFETY-RELATED

2. 2 DESIGN BASIS PERFORMANCE REQUIREMENTS:QUALITY-RELATED

2.3 SAFETY ANALYSIS REQUIREMENTS

2.4 10CFR50 APPENDIX R REQUIREMENTS

2.4. 1 Safe Shutdown2.4.2 Cold Shutdown

ANALYSIS SCENARIOS

3.1 LICENSING BASIS SCENARIOS

3. 1. 1 Operating Modes 1, 2, 3, and 4

3. 1.2 Operating Modes 5 and 63. 1.3 Operating Modes 1, 2, 3, and 4:

Peak Xenon

3.2 OPERATIONS ANALYSES

METHOD OF ANALYSIS AND ASSUMPTIONS

4. 1 ANALYSIS METHODOLOGY

4. 2 PHYSICS ANALYSIS ASSUMPTIONS

4.3 SYSTEM ANALYSIS ASSUMPTIONS

4.4 ADDITIONAL ASSUMPTIONS, MODE 5 COOLDOWN

DESIGN BASIS ANALYSES

5.1 REQUIRED RCS BORON CONCENTRATION

5.2 COOLDOWN FROH HOT STANDBY, EQUILIBRIUMXENON, EOC

1-11-11-2

2-1

2-1

2-7

2-102-11

2-112-12

3-1

3-1

3-13-33-5

3-6

4-1

4-14-24-94-14

5-1

5-15-10

5.2.15.2.25.2.35.2.4

PurposeAnalysesResultsRWST Boration Requirements,Modes 1, 2, 3, and 4

5-105-105-135-15

Report No. 849963-HPS-5HISC-003 REV 0 Page

Section

6.0

TABLE OF CONTENTS (continued)

Title5.3 COOLDOWN FROM COLD SHUTDOWN TO REFUELING

TEMPERATURE, MODE 5

5.3.1 Purpose5.3.2 Analyses

5.3.2. 1 Mode 5 Cooldown with BoricAcid Tank

5.3.2.2 Mode 5 Cooldown with RWST

5.3.3 Results

OPERATIONS ANALYSES

6.1 BLENDED MAKEUP OPERATIONS6.2 FEED AND BLEED OPERATIONS6.3 COOLDOWN TO REFUELING - MODE 66.4 COOLDOWN TO COLD SHUTDOWN - MODE 56. 5 BATCHING OPERATIONS6.6 RESPONSE TO EMERGENCY SITUATIONS

Pacae No.

5-29

5-295-29

5-31

5-32

5-34

6-1

6-46-66-96-126-136-15

6.6.16.6.26.6.36.6.46.6.5

Accident ResponseShutdown Margin RecoveryEmergency BorationFast Cooldown TransientsTechnical Specification ActionStatements

6-166-166-166-186-20

7.0

8.0

9.0

10.0

6.7 IMPACT OF RCS LEAKAGE6.8 LONG TERM COOLING AND CONTAINMENT SUMP pH

TECHNICAL SPECIFICATION CHANGES

7.1 RECOMMENDED CHANGES7.2 NO SIGNIFICANT HAZARDS EVALUATION

~5AFF Y EVALUA ioNf

8. 1 RECOMMENDED UFSAR CHANGES

8.2 NO UNREVIEWED SAFETY QUESTIONSDETERMINATION

OPERATING PROCEDURE GUIDELINES

REFERENCES

6-226-23

7-1

7-17-13

8-1

8-18-6

9-1

10-1

Report No. 849963-MPS-5MISC-003 REV 0 Page

Section

APPENDIX 1

APPENDIX 2

APPENDIX 3

APPENDIX 4

TABLE OF CONTENTS (continued)

Title

DERIVATION OF THE REACTOR COOLANT SYSTEM

FEED AND BLEED EQUATION

A PROOF THAT FINAL SYSTEM CONCENTRATION

IS INDEPENDENT OF SYSTEM VOLUME

METHODOLOGY FOR CALCULATING DISSOLVED BORIC

ACID PER GALLON OF WATER

METHODOLOGY FOR CALCULATING THE CONVERSION

FACTOR BETWEEN WEIGHT PERCENT BORIC ACIDAND PPM BORON

~Pa e No.

Al-1

A2-1

A3-1

A4-1

APPENDIX 5 BOUNDING PHYSICS DATA INPUTS

APPENDIX 6 PROPOSED MARKED-UP TECHNICAL SPECIFICATIONS

APPENDIX 7 PROPOSED MARKED-UP SAFETY ANALYSIS REPORT

A5-1

A6-1

A7-1

APPENDIX 8 FUTURE FUEL CYCLE REVIEW FOR COMPARISON OF

BOUNDING PHYSICS PARAMETERS

A8-1

APPENDIX 9 ANALYSIS OF PEAK XENON SCENARIO

APPENDIX 10 COMPUTER CODE CERTIFICATE AND INPUT

A9-1

A10-1

Report No. 849963-MPS-5MISC-003 REV 0 Page iii

INTRODUCTION

PURPOSE AND OBJECTIVES

The purpose of this project, as proposed by Reference 10.7 and

authorized by Reference 10.8, is to perform the necessary

engineering work and to generate the necessary license amendment

documents that would allow Florida Power & Light (FPL) to "reduce the

boron concentration required to be maintained in the concentrated

boric acid tanks at the Turkey Point Nuclear Units 3 and 4 to a

concentration of 3.0 to 3.5 weight percent boric acid. At the new

boric acid concentrations the need to heat the boric acid tanks and

the need to heat trace the boric acid makeup system piping and

valves would no longer be required since the ambient temperatures

that normally exist in the plant's auxiliary building are sufficientto prevent boric acid precipitation.

1.2 BACKGROUND

The General Design Criteria contained in the Code of Federal

Regulations specifies that concentrated sources of borated water ar'

to be available for charging into the Reactor Coolant System (RCS)

of pressurized water reactor (PWR) plants as needed for reactivitycontrol. Although these borated sources are required to be

available, the concentration of the solutions contained in them isdetermined by the designers. The basis for determining the boric

acid concentration is the ability to safely control reactivity at

any time during core life. Boric acid is used to offset slow

reactivity changes caused by normal changes in reactor power level,or to establish hot shutdown, cold shutdown or refueling conditions.

In the original plant design process for PWRs, two sources of

borated water are typically provided, each having different boron

concentrations. A refueling water storage tank is available which

has a specified minimum concentration of 1950 ppm. In addition to

Report No. 849963-HPS-5HISC-003 REV 0 Page 1-1

the refueling water storage tank three concentrated boric acid tanks

are available. Each boric acid tank has a specified minimum levelof 3,080 gallons with a specified concentration of 20,000 to 22,500

ppm boric acid. In order to keep the boric acid in solution atthese high boron concentrations, extensive heating networks are

required. These heating networks maintain the temperature of the

tanks and associated pipes, pumps, and valves at greater than 145'F

in order to prevent boric acid precipitation.

The requirement to maintain a highly concentrated boric acid

solution in the boric acid tanks can place an undue burden on plantmaintenance and operational personnel. Significant problems can be

encountered in keeping the boric acid makeup system operable as

required in the plant technical specifications. These problems

include heat tracing failures, plugging problems due to crystallineboric acid deposits, and various corrosion problems such as seal

failures, fitting leaks, and valve failures. In addition, the

presence of crystalline boric acid deposits on the exterior of

piping, valves, etc. can present a cleanliness problem. One

solution to these problems would be to reduce the concentration

requirements in the boric acid tanks by a factor of three or more

below the present value. This reduction is justifiable based on the

analyses presented in this report which demonstrate the ability to

safely control reactivity throughout core life. At low enough

concentration levels the system would no longer need to be heated

since boric acid would remain in solution at temperatures below the

normally anticipated ambient temperatures in the auxiliary building.Additionally, problems with corrosion and cleanliness associated

with concentrated boric acid could be greatly improved.

1.3 BASIS OF BORIC ACID CONCENTRATION REDUCTION

The boric acid tank level and boron concentration minimum values

specified in the current Turkey Point Technical Specifications are

Report No. 849963-MPS-5HISC-003 REV 0 Page 1-2

based on the ability to borate the RCS to the required cold shutdown

boron concentration by utilizing avialable pressurizer volume or

through a feed and bleed process. The current method is to borate

the RCS to the boron concentration required to provide the requiredshutdown margin of IX ak/k at 200'F prior to commencing the plantcooldown. The boration subsystem is then required to providesufficient boric acid to first achieve this shutdown margin and,

second, to provide blended makeup to compensate for the contractionof the coolant throughout the cooldown. Since boron concentration

typically has to be increased by 700 to 800 ppm prior to commencing

cooldown, highly concentrated boric acid solutions are required toachieve this in a reasonable period of time with limited storage

volume capability.

The required boron concentration in the boric acid tanks can be

reduced with a simple change in the methodology of accomplishing

plant boration and cooldown. This report analyzes a number of plantcooldown scenarios where boration is accomplished concurrently withcooldown as part of the normal inventory makeup required as a resultof coolant contraction during the cooldown. By identifying the

exact RCS boron concentration required to maintain proper shutdown

margin at each temperature during a plant cooldown and applying the

makeup capacity limitations of the system, the exact volume of boricacid required from the boric acid tank can be identified. By

eliminating the boric acid loss associated with the feed and bleed

process and by utilizing boric acid available from the refuelingwater storage tank (in addition to the boric acid tank), the

concentration of boric acid required for the boric acid tanks can be

reduced. Effectively, the concentration required for the boric acid

tanks to perform a cooldown to cold shutdown conditions can be

decreased to the range of 3.0 to 3.5 weight percent where heat

tracing af the boric acid system is no longer required.

Figure 1-1 is a plot showing the solubility of boric acid in water

for temperatures ranging from 32'F to 160'F. (Data for Figure l-l

Report No. 849963-NPS-5HISC-003 REV 0 Page 1-3

were obtained from Reference 10.9 and are reprinted in Table 1-1.)Note that the solubility of boric acid at 32'F is 2.52 weight

percent and at 50'F is 3.49 weight percent. At or below a

concentration of 3.5 weight percent boric acid, the ambient

temperature that normally exists in the auxiliary building will be

sufficient to prevent precipitation within the boric acid makeup

system.

This report presents the technical justification for reduction ofthe boric acid concentrations required to be maintained in the boricacid tanks which will then support the elimination of all boric acid

system heat tracing. Section 2.0 presents the results of a detailedreview of the Turkey Point boration design basis. Section 3.0

presents the analysis scenarios that were chosen to demonstrate the

capability of the boration system to comply with these design basis

requirements with reduced boric acid concentration. Sections 4.0,5.0, and 6.0 present the results of the analyses completed for the

scenarios identified in Section 3.0. Sections 7.0 and 8.0 identifythe necessary changes to Turkey Point licensing documentation, while

Section 9.0 identifies general changes that will be required forTurkey Point operating procedures.


Table 1-1

Boric Acid Solubility in Water'(1)

Temperature

('F)H3B03

(Wt.X)

32.0

41.0

50.0

59.0

68.0

77.0

86.0

95.0

104.0

113.0

122.0

131.0

140.0

149.0

158.0

167.0

176.0

2.52

2.98

3.49

4.08

4.72

5.46

6.23

7.12

8.089.12

10.27

11.55

12.97

14.42

15.75

17.91

19.10

Solubility from Technical Data Sheet IC-11, US Borax 8 ChemicalCorporation, 3-83-J.W. These data have been empirically derived andare supported by WCAP-1570 "Literature Values for SelectedChemical/Physical Properties of Aqueous Boric Acid Solutions".

Report No. 849963-MPS-5MISC-003 REV 0 Page 1-5

Figure 1-1 Boric Acid Solubility in Water

(We+%)I I

H I

0>0

9—I

8 —;

7 —.

6 —,

5 —'-

.~

I

(

1—'

I1

I

TIII(IIItae(DW(F(


PERFORMANCE REQUIREMENTS

To technically justify a significant reduction in the concentrationof boric acid in the boration subsystem of the Chemical and Volume

Control System (CVCS), a careful review of the boration design and

licensing basis of the CVCS is required. It is necessary that thespecific design basis and licensing performance requirements be

clearly identified and understood to ensure that one or more

analyses can be completed that will demonstrate these requirementscontinue to be met.

References 10. 1 through 10.6 were reviewed to identify allperformance requirements/limitations related to RCS boration and

core reactivity control that should be factored into the boric acidconcentration reduction analyses. This section identifies the

system design basis performance requirements and the expected impact

of a reduction in the concentration of stored boric acid. The need

for analyses to demonstrate compliance with these system

requirements is assessed and appropriate reference made to the

specific analysis scenarios outlined in Section 3. The intent isnot necessarily to conduct a specific analysis for each system

requirement but, instead, to identify the minimum number of limitinganalysis scenarios, the results of which will bound all establishedboration requirements.

2.1 DESIGN BASIS PERFORMANCE REQUIREMENTS: SAFETY-RELATED

This section addresses each of the safety-related design basis

performance requirements presented in Section 3. 1 of Reference 10. 1.

All requirements are addressed regardless of any impact created by a

reduction in boric acid concentration. For ease of cross reference,

these requirements are presented in the same order as they appear in

the design basis document with the same last two digits of the

section numbers used in this evaluation (i.e., Section 2.1.2 here

corresponds to Section 3. 1.2 of Reference 10. 1).


2.1.1 The CVCS charging line and the individual Reactor Coolant Pump (RCP)

seal injection lines (one for each RCP) are required to satisfycontainment boundary isolation requirements.

~im act: None

~Anal sis: Not Applicable.

2.1.2 The CVCS shall be capable of making and holding the core subcriticalfrom any hot operating condition including those resulting from

power changes. Clarifications of Section 2. 1.3 (Reference 10. 1)

state that the boration system is required to be capable of shuttingdown the reactor from a hot full power condition (with no controlrod insertion) and adding sufficient boric acid subsequent to the

shutdown to compensate for the eventual decay of all xenon, thereby

maintaining the required shutdown margin.

~lm act: References 10.1, 10.2 and lb.3 state that the required

boration can be accomplished in less than 16 minutes and that, in

less than 16 additional minutes, RCS boron can be increased

sufficiently to fully account for the decay of xenon, thereby

maintaining the required shutdown margin. (A total of 155 minutes

would be required if the source of water were the refueling water

storage tank instead of the boric acid tanks.) This is recognized

to be a statement of system capability and does not represent a

licensing requirement. A reduction in boric acid tank boron

concentration will only increase the amount of time it will take and

will not impact the system's ability to accomplish this task.

Analysis: Although an exponential relationship exists; the time to

borate to the hot shutdown, xenon free condition is roughly

inversely proportional to the boric 'acid concentration of the water

source (at low initial concentrations and assuming one source with

constant concentration and addition rate). Reduction in boron

concentration by a factor of 3 to 4, therefore, is expected to


increase the completion time by a factor on the order of 3 to 4.

Previous reactivity analyses have analyzed this capability with

boron concentrations from 4.0 to 3.0 weight percent boric acid

resulting in times to shutdown of 30 to 40 minutes, respectively.In any case, the shutdown capability of 155 minutes using the

refueling water storage tank remains as the upper limit on time to

achieve boration. Volume of boric acid is not considered a

limitation in this instance since a stated design basis variation in

the boration lineup is to use the refueling water storage tank as a

sole source. The volume requirement in this instance is bounded by

that required by post LOCA emergency core cooling. See Section

6.6.3.

2.1.3 The CVCS boration system is required to be capable of maintaining

shutdown margin during a 100'F/hr cooldown initiated from a hot zero

power subcritical condition, with the RCS borated sufficiently for a

cold shutdown (= or < 200'F), xenon free condition and the most

reactive control rod stuck in the fully withdrawn position.

~lm act: A reduction in boron concentration of the water used to

provide boration and makeup under these conditions will effectivelyrequire that a greater volume be added to the RCS for reactivitycontrol. Additionally, greater boric acid flow rates to the blender

will be required to provide blended makeup that will maintain the

RCS boron concentration established prior to initiating the

cooldown. The required boric acid flow rates for fast cooldowns

will be available via the normal flow path with the proposed

modification of flow control valve FCV-113A discussed in Section 6. 1

or via the emergency boration flow path using one or both transfer

pumps.

~Anal sis: See Section 6.6.4.

2.1.4 The CVCS charging system must be capable of satisfying the technical

specification requirements to be in various stages of hot or cold


shutdown during varying time periods. Accordingly, the CVCS must:

1) meet the RCS boration requirements such that the shutdown boron

concentration can be achieved prior to (and maintained during) plantcooldown; 2) satisfy RCS fluid inventory control requirements

during cooldown by making up for shrinkage of the reactor coolant

with blended makeup water of the correct boron concentration. The

clarification of Section 3. 1.4 (Reference 10. 1) states that the

limiting requirement in this respect is to achieve cold shutdown

(1% z k/k shutdown, 200'F) in 30 hours from a hot zero power

condition, including allowances for RCP seal leakage and

identified/unidentified RCS leakage.

~lm act: An exception to this design basis statement is that the

methodology presented in this report involves boration in

conjunction with the cooldown to minimize the boron loss that would

occur during the feed and bleed process suggested (i.e., boration

prior to cooldown). Such an approach is used in the licensing

analysis of Section 5.0 to establish the minimum technical

specification volume/concentration requirements for the boric acid

tanks.

~Anal sis: See Sections 5.0 and 6.0.

2.1.5 The CVCS charging system must be capable of satisfying safe shutdown

fire protection criteria imposed as a result of 10CFR50, Appendix R.

Boration to the cold shutdown boron concentration and cooldown to

350'F must be achieved within 19 hours with suction from the

refueling water storage tank. Cold shutdown is to be achieved

during the ensuing period from 19 to 72 hours. Accordingly, the

CVCS must: 1) meet the RCS boration requirements such that the

shutdown boron concentration can be achieved prior to (and

maintained during) plant cooldown; 2) satisfy RCS fluid inventory

control requirements during cooldown by making up for shrinkage of

reactor coolant with blended makeup water of the correct boron

Report No. 849963-HPS-5MISC-003 REV 0 Page 2-4

concentration. The 19-hour time requirement is based on condensate

storage tank capacity as the water source for auxiliary feedwater.RCP seal leakage and identified/unidentified RCS leakage are

assumed.

~Im act: An exception to this design basis statement is that the

methodology presented in this report involves boration inconjunction with the cooldown to minimize the boron loss that would

occur during the feed and bleed process suggested (i.e., borationprior to cooldown). Such an approach is used in the licensinganalysis of Section 5.0 to establish the minimum technicalspecification volume/concentration requirements for the boric acid

tanks. The 19 and 72 hour limitations are not considered limitingfrom the perspective of boric acid tank inventory since the

refueling water storage tank is the stated source for reactivity and

inventory control.

A~nal sis: See Sections 5.0 and 6.0.

2.1.6 The CVCS boration system is required to insert negative reactivityat a rate that is sufficient to compensate for the maximum xenon

burnout rate which occurs during a return to power at a peak xenon

condition following a short period at hot standby.

~im act: A reduction in the boron concentration in the boric acid

tanks will require greater boric acid flow rates to add the same

amount of boron in a given period of time. The preferred method ofreactivity control in these circumstances is to provide a mixture ofconcentrated boric acid from the boric acid tank and pure makeup

water from the primary water system. Water from these sources would

be mixed in the blender at an established ratio to provide boric

acid at the desired concentration.

If the current range of reactivity control is to be maintained using

the boric acid blender as the preferred boration flow path (as

opposed to the emergency boration flow path), an increase in the


flow rate of boric acid will be required. This will be necessary tobe able to provide the same amount of boron to the blender in a

given period of time using the reduced boric acid tank boron

concentrations as compared to the existing concentrations. FPL

already plans to replace the valve trim for Flow Control Valve

FCV-113A to increase the achievable boric acid flow rates into the

blender and, hence, satisfy this requirement.

~Anal sis: No additional analyses are necessary since previous

analyses have shown it is possible to meet this requirement withboron concentrations in the range of 3.0 to 4.0 weight percent.

2.1.7 The CVCS boration system is required to insert negative reactivityat a rate that is sufficient to compensate for decay of xenon.

~im act: A reduction in the boron concentration of the boric acid

tanks will require greater boric acid flow rates to add the same

amount of boron in a given period of time. Greater boric acid flowrates to the boric acid blender will be achievable with modificationof FCV-113A as discussed in Section 2. 1.6 above.

'Anal sis: See Section 5.0.

2. 1.8 The CVCS boration system is required to be available post-LOCA foruse in controlling recirculation fluid pH.

~lm act: None

A~nal sis: Not Applicable.


DESIGN BASIS PERFORMANCE REQUIREMENTS: EQUALITY-RELATED

This section addresses each of the quality-related (important to

safety) design basis performance requirements presented in Section

3.2 of Reference 10. 1. All requirements are addressed regardless ofany impact created by a reduction in boric acid concentration. For

ease of cross reference, these requirements are presented in the

same order as they appear in the design basis document with the same

last two digits of the section numbers used in this evaluation

(i.e., Section 2.2.2 here corresponds to Section 3.2.2 ofReference 10. 1).

2.2.1 One charging pump is required to deliver a charging line flow of 45

gpm and a total RCP seal injection flow of 24 gpm to three RCPs fora total pump flow of 69 gpm with a normal RCS pressure of 2235 psig.

~lm act: None


2 '.2 The CVCS must provide adequate letdown and charging flow forpurification, cleanup and degassing operations.

~lm act: None


2.2.3 The CVCS is required to provide seal water injection flow, nominally

8 gpm, to each RCP No. 1 seal. The temperature of the seal

injection water is required to be 130'F or lower. It is required

that suspended solid particles larger than 5 microns be removed from

the injection stream.

~lm act: None



2.2.4 The CVCS is required to provide a means for cooling the RCP lower

bearing under low RCS pressure conditions when all of the RCP No. 1

seal injection may flow directly into the RCS through the labyrinthseals instead of upward past the lower bearing.

~im act: None

A~nal sis: Not Applicable.

2.2.5 The CVCS is required to makeup for shrinkage during a 100'F/hr

cooldown of the RCS from hot zero power (mode 3, 547'F) to 350'F.

This is considered to be an original design basis function of the

CVCS.

~Im act: This criterion is independent of boron concentration.Since the charging system capacity is not being altered, the abilityof the system to provide sufficient makeup capacity under these

conditions is not impacted. Boration requirements are specified in

Section 2. 1.3 of this evaluation.

~Anal sis: See Section 6.6.4.

2.2.6 In modes 1 through 4, the CVCS is required to ensure that sufficientboric acid is available to bring each unit to cold shutdown with the

required shutdown margin from a hot zero power peak xenon condition

(mode 3, 547 F). It should be noted that the clarification ofSection 3.2.6 (Reference 10. 1) recognizes the refueling water

storage tank as an alternate source of water to satisfy this design

basis requirement (i.e., 70,000 gallons feed and bleed at 1950 ppm

boron).

~lm act: A reduction in the boron concentration of the boric acid

tanks will effectively decrease the rate of RCS boration by

Report No. 849963-UPS-5MISC-003 REV 0 Page 2-8

decreasing the amount of boron in every gallon charged to the RCS.

An additional consequence will be the corresponding increase in the

makeup volume required to add the total amount of boron required tocompensate for xenon decay and moderator cooldown. Boration inconjunction with the cooldown, however, will significantly reduce

the amount of boron lost during the traditional feed and bleed by

taking advantage of the contraction of the RCS. The effectivecooldown rate utilized in Section 5.0 is selected conservatively low

to allow for significant xenon decay during the cooldown scenario.

The methodology presented in this report and approved by the NRC on

previous plants did not assume boration starting at the

post-shutdown xenon peak as stated in this design criterion. A more

conservative approach was taken that assumed xenon had returned toits full power equilibrium level prior to initiation of the

cooldown. In this manner, the negative reactivity inserted by the

buildup of xenon after shutdown was not credited. The end of cycle

was chosen since it presented the worst case xenon and moderator

temperature reactivity effects to be compensated for through

boration. This approach has been reviewed in detail and fullyapproved by the NRC. To conservatively account for this design

basis requirement, however, a peak xenon transient is presented in

Appendix 9.

A~nal sis: See Section 5.0 and Appendix 9.

2.2.7 In modes 5 and 6, the CVCS is required to ensure that sufficientboric acid is available to compensate for coolant contraction and

the reactivity added due to moderator temperature effects in

proceeding from mode 5 at 200'F to ambient conditions.

~Im act: A reduction in the boron concentration of the boric acid

tanks will effectively increase the volume of boric acid and time

required to accomplish this task.


Since this final phase of the RCS cooldown goes beyond the

requirement to achieve cold shutdown, the volume of boric acid

required to achieve this can be batched and added to the boric acid

tank(s) after cold shutdown is achieved. This volume does not need

to be considered in the boric acid tank volume requirement for modes

1, 2, 3, and 4. In accordance with the Hode 5 and 6 boric acid

inventory requirement bases in the technical specifications, a

cooldown to 140 F is the licensing basis for the tanks.

A~nal sis: See Section 5.3.

2.3 SAFETY ANALYSIS REOUIREHENTS

A reduction in the concentration of boric acid in the boric acid

tanks and elimination of the heat tracing associated with the

bor ation subsystems will require several changes to the Turkey Point

Technical Specifications as described in Section 7.0. Accordingly,

Reference 10.3 was reviewed in detail to ensure the bases behind

these technical speci,fications were understood and addressed.

A principal concern when reducing the available boric acid

concentration is the possible impact on the accident analyses of

Chapter 14 of the Final Safety Analysis Report (FSAR). A careful

review of this chapter has shown that the Turkey Point accident

analyses do not rely on any injection of concentrated boric acid.

The only boron injection credited is the relatively low

concentration from the refueling water storage tank. The boron

injection tank boron concentration, as well, has been reduced to a

level corresponding to the refueling water storage tank

concentration. The accident analyses of Chapter 14, therefore, are

not impacted by a reduction in the boron concentration of the boric

acid tanks.

Several sections of the FSAR, however, describe the boration

capabilities and procedures in terms of the high boron concentration


that is currently available for reactivity control. Changes tothese sections are recommended through markups of the appropriatepages provided as Appendix 7. The principal areas of change are inChapter 1 (brief descriptions of boration capability), Chapter 3

(more detailed descriptions of boration reactivity controlmeasures/capabilities), and Chapter 9 (CVCS system description and

required functions).

2.4 10CFR50 APPENDIX R REQUIREMENTS

Reference 10.5 provides a detailed assessment of the capabilities ofthe plant to achieve and maintain both hot and cold shutdown

conditions. Safe shutdown is defined as hot subcritical conditionsas a minimum (T>540'F), with the capability to proceed to cold

shutdown should conditions warrant. Hot shutdown (per technical

specification mode definition) is specifically defined as the

initiation of Residual Heat Removal (RHR) system operation (350 F).

Although the capability exists to bring the plant to cold shutdown

conditions, the preferred approach appears to be to keep the plantat hot zero power (T>540'F) for as long as practically possible

(while the fire and any resulting damage are dealt with). The plant

would be brought to cold shutdown if, and only if, a plant

configuration resulted that required such action (e.g., a technical

specification limiting condition of operation not satisfied).

2.4.1 Safe Shutdown

The Turkey Point reactivity control system consists of two

independent reactivity control subsystems: 1) rod cluster control

assemblies (RCCAs), and 2) boric acid injection via the charging

system (CVCS). It is clear from the discussions of References 10.3

and 10.5, however, that the RCCAs alone are capable of achieving and

maintaining subcritical conditions during long term hot conditions.

The principal reasons for the boric acid injection capability are:

1) to provide a backup to this capability, and 2) to assure adequate


reactivity control during the subsequent cooldown from the hot plantconditions. RCS makeup may or may not be required while maintainingthe plant in a hot condition depending upon RCS leakage and the

length of time. Adequate makeup capability exists, however, toaccount for normal leakage under these conditions for a reasonable

period of time. Given the limited volume available in the boricacid tanks, however, provisions should be made to preserve theconcentrated boric acid for the design basis cooldown scenario by

providing RCS makeup during long term hot plant conditions from therefueling water storage tank.

2.4.2 Cold Shutdown

If the plant is forced to go to a cold shutdown condition,reactivity control via boric acid injection will be required. This

will be necessary to compensate for the positive reactivity insertedby the reduction in core moderator temperature. In this manner,

adequate shutdown margin will be maintained preventing an

inadvertent return to criticality.

Boron addition and RCS makeup for contraction are possible using one

of three charging pumps and one of two independent sources of a

boric acid solution. The preferred source of boric acid is the

three (shared) boric acid tanks containing a solution of reduced

concentration boric acid via one of four shared boric acid transferpumps. The backup source of boric acid is the charging pump directgravity feed line from the refueling water storage tank containing a

lower concentration of boric acid. Additional provisions exist toalign either unit's refueling water storage tank to the suction ofeither unit's charging pumps.

4

The current methodology for conducting a plant cooldown is toinitiate a feed and bleed process to bring the RCS boron


concentration to a level corresponding to the required shutdown

margin for a cold xenon free core. Once this has been accomplished,

the plant is cooled down with makeup for plant volume contractionprovided with a combination of makeup water and boric acid blended

to the new RCS concentration. This will effectively maintain a

constant RCS boron concentration throughout the cooldown process.

Such a feed and bleed process requires that a bleed path be

available. Turkey Point Units 3 and 4 have several design featuresthat assure the availability of RCS letdown under a variety ofconditions. The following potential letdown paths are described in

the Turkey Point FSAR (Reference 10.3):

(1) letdown via the non-regenerative heat exchanger (normal path);

(2) letdown directly to the VCT or holdup tanks bypassing the non-

regenerative heat exchanger (in the event of a loss ofcomponent cooling water —requires temperature to be maintained

<120'F) in conjunction with balanced letdown and charging flow

through the regenerative heat exchanger;

(3) letdown to the pressurizer relief tank via the letdown linesafety valve (achieved by isolating the letdown line outside ofcontainment);

(4) letdown via the RCP seal water return line to the VCT (normal)

or drain tank/pressurizer relief tank (emergency).

A revised approach for conducting a plant cooldown without letdown

consists of borating the plant in conjunction with the cooldown. In

this manner, no feed and bleed would be necessary since all the

boric acid injection would occur during the makeup provided to

compensate for contraction of the reactor coolant. Such an approach

allows a significant reduction in the concentration of boric acid

maintained in the boric acid tanks and the elimination of boration


subsystem heat tracing. The use of letdown, however, will be

evaluated in the Operations Analyses of Section 6.0.

Implementation of a boric acid concentration reduction will impact

the Turkey Point Appendix R commitments since the use of the

methodology presented in this report will require a change from

boration prior to plant cooldown to ~durin plant cooldown.

Additionally, reduced boric acid concentrations will invalidate the

times to achieve the required boron concentration presented in

Reference 10.5 (which appear to be applicable to Fuel Cycle No. 8).All other aspects of the post-fire shutdown to hot standby

conditions and subsequent cooldown to cold shutdown conditions willremain the same. The 19 and 72 hour limitations are not considered

limiting from the perspective of boric acid tank inventory since the

refuelikng water storage tank is the stated source for reactivityand inventory control.


ANALYSIS SCENARIOS

This section outlines the three basic scenarios proposed fordetailed analysis of the Turkey Point Units 3 and 4 borationcapabilities. These scenarios have been picked based on a carefulreview of the CVCS design and licensing basis for the currentbor ation capability as outlined in Section 2.0 of this evaluation.Specifically, the first two scenarios of Section 3. 1 are the ones

that have been approved by the NRC and used successfully for eightC-E designed plants. The basic scenario has been updated toinclude the plant specific data obtained from Turkey Point design

documents. The third scenario of Section 3. 1 is included toaddress the CVCS design basis requirement to support cold shutdown

from a peak xenon condition. Section 3.2 describes thenon-licensing analyses performed to evaluate the impact of reduced

boric acid concentration on normal plant activities.

3.1 LICENSING BASIS ANALYSES

3.1.1 Operating Nodes 1, 2., 3, and 4: Equilibrium Xenon

The cooldown methodology proposed herein has been developed toallow a significant reduction in the boric acid concentration thatis required to be maintained in the boric acid tanks while

operating in Nodes 1, 2, 3, and 4. The proposed cooldown

methodology differs from the current methodology employed at

Turkey Point in that boration of the reactor coolant system isperformed concurrently with cooldown as opposed to borating priorto initiating plant cooldown. This approach can be justified ifit can be demonstrated through conservative analyses that proper

shutdown margin can be maintained when concentrated boron is added

as part of normal system makeup during the cooldown process. To

accomplish this, the exact boron concentration required to be

present in the RCS must be known at any temperature during the

cooldown process. In addition, in order to ensure applicability

Report No. 849962-UPS-5HISC-003 REV 0 Page 3-1

for an entire cycle, a cooldown scenario must be developed which

is conservative in that it places the greatest burden on an

operator's ability to control reactivity (i.e., this scenario must

define the boration requirements for the most limiting time incore cycle). The limiting scenario is as follows:

(1) Conservative core physics parameters are used to determine

the required boron concentration and the required boric acid

tank volumes to be added during plant cooldown. End of cycle

(EOC) initial boron concentration is assumed to be zero. EOC

moderator cooldown effects normalized to the most negative

technical specification Hoderator Temperature Coefficient(HTC) limit are used to maximize the reactivity insertionrate during the plant cooldown. EOC Inverse Boron Worth

( IBW) data are used in combination with the EOC reactivityinsertion rates, since this yields results that are more

limiting than the combination of specific HTC and IBW values

at any fuel cycle exposure prior to EOC. These assumptions

ensure that the required boron concentration and the boric

acid tank minimum volume requirements conservatively bound

all plant cooldowns during corelife.'2)

The most reactive rod is stuck in the full out position.

(3) Prior to time zero, the plant is operating at 100X power with

100X equilibrium xenon and with zero RCS leakage. Assuming

zero RCS leakage conservatively limits the boron addition to

that which is added to the RCS to make up for contraction

during the cooldown. Additionally, slow cooldown rates willfurther reduce the boron addition by limiting the rate ofreactor coolant concentration change.

(4) At time zero, the plant is shutdown and held at hot zero

power (547 F) conditions for 23.5 hours. The xenon peak

after shutdown will have decayed back to the 100X power


equilibrium xenon level by this time. Further xenon decay

will add positive reactivity to the core during the

subsequent plant cooldown. No credit is taken for the negativereactivity effects of the peak xenon concentration followingthe reactor shutdown.

(5) At 23.5 hours, offsite power is lost and the plant goes intonatural circulation. The non-safety grade letdown is lost.During the natural circulation the RCS average temperature

rises 25'F due to decay heat in the core. The initialtemperature at the start of the cooldown is 572'F.

(6) Approximately 0.5 hours later, at 24 hours, the operatorscommence a cooldown to cold shutdown.

The scenario outlined above is used to generate the borationrequirements for Modes 1, 2, 3, and 4. It produces a situationwhere positive reactivity will be added to the RCS simultaneously

from two sources at the time that a plant cooldown from hot

standby is commenced. These two reactivity sources result from a

temperature effect due to an overall negative isothermal

temperature coefficient of reactivity, and a poison effect as the

xenon-135 level in the core starts to decay below its 100X power

equilibrium value. This scenario, therefore, represents the

greatest challenge to an operator's ability to borate the RCS and

maintain the required technical specification shutdown margin

while cooling the plant from hot standby to cold shutdown

conditions.

3. 1.2 Operating Modes 5 and 6

The methodology developed for Modes 5 and 6 is similar to the

method proposed for Modes 1, 2, 3 and 4 in that boration of the

RCS is performed concurrently with cooldown. Concentrated boric

acid is added as part of normal system makeup during the cooldown

Report No. 849962-HPS-SHISC-003 REV 0 Page 3-3

process. To accomplish this, the exact boron concentrationrequired to be present in the RCS must be known at any temperatureduring the cooldown process. The following scenario was developed

to identify the most limiting cooldown transient for Modes 5 and 6.

(1) EOC conditions with the initial RCS boron concentrationnecessary to provide shutdown margins of 1000 pcm (IX ak/k)at 200'F and xenon free. EOC moderator cooldown effects are

used to maximize the reactivity change during the plantcooldown. EOC IBW data are used in combination with EOC

reactivity insertion rates normalized to the most negativetechnical specification HTC limit since this yields resultsthat are more limiting than the combination of actual HTC and

actual IBW values at all periods through the fuel cycle priorto EOC.

(2) The most reactive rod is stuck in the full out position.

(3) There is zero RCS leakage.

(4) RCS feed and bleed can be used to increase boron .

concentration (for the case where the refueling water storage

tank is the source).

(5) RCS makeup is supplied either from the refueling water

storage tank alone or from the boric acid tank.

(6) The most limiting scenario for boration in Mode 5 requiresthat a 1000 pcm (IX sk/k) shutdown margin be maintained

during the cooldown from 200'F to 135'F. The boration

requirements for Mode 6 only address maintaining a previouslyestablished shutdown margin.


The scenario outlined above was used to determine the borationrequirements for Hodes 5 and 6. It produces a situation where

positive reactivity will be added to the RCS due to the overallnegative isothermal temperature coefficient of reactivity; Since

the core is already assumed to be xenon free there is no

contribution to core reactivity due to xenon decay.

3. 1.3 Operating Hodes 1,2,3, and 4: Peak Xenon

The basic elements of this analysis scenario consist of the

following:

(1) the cooldown transient is initiated eight hours followinga reactor trip from extended full power operation(corresponding to the peak xenon condition instead of the

full power equilibrium xenon concentration) and,

(2) the subsequent cooldown boration must compensate for the

decay of the entire xenon inventory from its peak value

(instead of its full power equilibrium value).

This scenario presents a worst case near the end of the cycle when

sufficient RCS boron concentration (>0 ppm) is available to allow

RCS boron concentration to be diluted by the operator tocompensate for the post-shutdown xenon buildup in anticipation ofa rapid return to power. Starting a design basis cooldown to cold

shutdown from the peak xenon condition under these conditions willeffectively increase the amount of boron required to be charged to

the RCS to compensate for the decay of the xenon peak.

Specifically, the boration required to maintain shutdown margin

will be completed from the boric acid tank and refueling water

storage tank in conjunction with the plant cooldown such that the

volume of boric acid charged into the plant will make up forcooldown contraction. The proposed scenario for this analysis isdiscussed further in Appendix 9.


OPERATIONS ANALYSES

A series of analyses are presented in Section 6.0 in order todemonstrate the general impact of a reduction in boric acid tankboron concentration on a variety of plant operations. The

specific areas that will be addressed will include operatorresponse to emergency situations, typical plant feed and bleed

operations, typical plant blended makeup operations, plantshutdown to refueling, and plant shutdown to cold shutdown. It is a

difficult and unnecessary task to evaluate each of these five areas

and consider all possible combinations of plant conditions.Instead, initial plant parameters and analyses assumptions will be

selected in a conservative manner to give worst case responses. As

a consequence, the results (i.e., the volumes and finalconcentrations that are obtained) should be bounding for any event

or any set of initial plant conditions.


METHOD OF ANALYSIS AND ASSUMPTIONS

4.1 ANALYSIS METHODOLOGY

The basis for the proposed methodology for reduction in the boricacid concentrations required to be maintained in the boric acid

tanks is a more efficient use of available boric acid sources. The

current cooldown methodology in use at Turkey Point accomplishes RCS

boration to the required cold shutdown concentrations before the

cooldown begins by utilizing available volume in the pressurizer orthrough a feed and bleed process. Plant cooldown is initiated withmakeup for contraction provided from the reactor makeup water

system. This makeup water is blended with boric acid from the boricacid tank to the new RCS concentration. In this manner, RCS

concentration is held constant during the cooldown process.

A proposed cooldown methodology is analyzed that will cover a worst

case cooldown scenario without letdown (Section 3. 1. 1). This

methodology makes two simple changes to the current approach:

(1) Borate the RCS in conjunction with plant cooldown by using a

concentrated boric acid solution as makeup for coolant

contraction.

(2) Utilize the refueling water storage tank as an additionalsource of boric acid makeup.

The basis for the minimum volume specified for the boric acid tank

will be such that injection of the boric acid tank contents in the

early phase of the cooldown will raise the RCS boron concentration

to a sufficient level such that subsequent makeup from the lower

concentration refueling water storage tank will maintain adequate

shutdown margin throughout the completion of the cooldown. (See

Section 5.0.)


Justification for this approach is accomplished in two steps. The

first step is to calculate the actual RCS boron concentrationrequirements during each temperature increment of a plant cooldown

that will ensure maintenance of adequate shutdown margin. The next

step is to model a plant cooldown and to identify the expected boron

delivery to the RCS as makeup for coolant contraction is provided

from the boric acid tank and refueling water storage tank. As longas boron delivered to the RCS is always greater than the boron

required, shutdown margin is assured. Selection of conservativephysics and plant system parameters and the conservative modeling ofboron injection ensure that a bounding analysis is presented thatwill cover those cooldown reactivity control scenarios reasonably

expected to occur.

4.2 PHYSICS ANALYSIS ASSUHPTIONS

This section describes the assumptions utilized in the calculationof the required RCS boron concentration during the cooldown. The

basic approach of balancing core reactivity effects with boron

addition has been devised to conservatively bound the reactivityeffects of the design basis cooldown scenarios described in Section

3. 1. 1 and 3. 1.2. This is intended to ensure that these analyses

conservatively bound any similar cooldown which may occur any time

during the fuel cycle.

The following presents an item-by-item discussion of the specificcore reactivity effects that have been accounted for in the physics

analysis. Appendix 5 presents the physics data provided by FPL as

input to this analysis. Table 4-1 summarizes the important physics

parameters utilized in this analysis and compares them to similarvalues used for a typical plant that has implemented this change.

Where applicable, all uncertainties and cycle to cycle variances

have been applied in a conservative manner to maximize the

reactivity control requirements. Appendix 8 provides a checklist ofthese key physics parameters to allow cycle to cycle confirmation

that these prarameters remain bounding for future cycles.


1. Time in cycle

Positive reactivity is added to the core as the moderator

temperature is lowered during plant cooldown. The reactivityeffects associated with this cooldown vary over core life so itis important to analyze the most restrictive case. The EOC (orend of life) case was selected for the following reasons:

a. Moderator Tem erature Coefficient

The MTC indicates the expected change in core reactivitywith a change in moderator temperature. A negative HTC

indicates that a positive reactivity effect will resultfrom a decrease in core temperature. The HTC varieswidely over core life with the most negative value

occurring at EOC. A value of -3.5 x 10 ak/k/'Fcorresponds to the most negative technical specificationlimit per Specification 3. 1. 1.3 of Reference 10.6 and was

used for this analysis.

b. Re uired Shutdown Har in

The shutdown margin requirements for Turkey Point are

specified in Figure 3. 1-1 of Reference 10.6, and, likeMTC, varies with core life as a function of fueldepletion, RCS boron concentration and RCS average

temperature.

A sufficient shutdown margin ensures that: 1) the reactor

can be made subcritical from all operating conditions, 2)

the reactivity transients associated with postulated

accident conditions are controllable within acceptable

limits, and 3) the reactor will be maintained sufficientlysubcritical to preclude inadvertent criticality in the

shutdown condition.


The most restrictive condition, again, occurs at EOC withRCS average temperature at no load operating temperature

and is associated with a postulated steam line break

accident and resulting uncontrolled RCS cooldown. This

results in a shutdown margin of 1.77X ak/k fortemperatures above 200'F (corresponding to an RCS boron

concentration of 0 ppm) and 1.0X ak/k for temperatures

below 200'F. The reduction in margin requirements at200'F is due to the fact that the reactivity transientsresulting from inadvertent RCS cooldown or dilution are

minimal. Hence, 1X ak/k is adequate protection at these

lower temperatures.

c. Boron Concentration

Hany of the physics parameters used for this analysis vary

with boron concentration. In particular, the smaller

boron concentration associated with EOC gives the most

negative HTC over cycle life. Consequently, an EOC boron

concentration of 0 ppm is selected as the most limitingfrom a core physics perspective.

d. Inverse Boron Worth

IBW data were extracted from the physics data of Appendix

5. EOC IBW data were used in combination with EOC

reactivity insertion rates normalized to the most negative

technical specification HTC limit since it was known that

this yields results that are more limiting than the

combination of actual HTC and actual IBW values at allperiods through the fuel cycle prior to EOC. The specific

IBW values utilized for the EOC analyses are presented in

Table 4-2.


2. Scram Worth

A conservative scram worth was used in the physics analysis.Specifically, the available scram worth was computed utilizingthe hot zero power scram worth for all rods in, minus the worstrod stuck full out. From this value the rod bank insertionlimit worths were subtracted to obtain a net available scram

worth. An uncertainty of 10X was subtracted from the availablescram worth for added conservatism. This scram worth isfurther reduced by subtracting an EOC reactivity value

associated with the Full Power Defect.

3. Determination of Excess Scram Worth

Excess scram worth was determined by comparing the availablescram worth at zero power (Item 2 above) to the requiredtechnical specification shutdown margin presented in Item lbabove.

It was determined that there is a 0.697X sk/k excess scram

worth available for temperatures above 200'F and an excess

scram worth of 1.468X ak/k for temperatures below 200'F.

4. Core Reactivity Effects

A reactivity calculation has been performed to account for the

addition of positive reactivity due to both the decay of xenon

and the cooldown of the moderator and fuel. Uncertainties were

applied to all reactivity effects as indicated in Table 4-1.

Table 4-1 summarizes the uncertainties used in this calculationand compares them to the values used for the calculation of a

previous unit .


a. Xenon Reactivit Effects

As shown in the data presented in Appendix 5, the xenon

worth peaks at its most negative reactivity worth around

eight hours after the reactor is shutdown. Xenon decay

reduces the negative reactivity of the xenon back to itsfull power steady state operating value at approximately

24 hours after shutdown. At times after 24 hours, the

plant must be borated to compensate for the positivereactivity addition provided by further reductions inxenon concentration. As an added conservatism, the

reactivity calculation does not credit the extra negative

reactivity inserted by the xenon peak that occurs aftershutdown. Instead, the plant is assumed to remain at hot

standby for 24 hours to allow xenon to return to the 100/o

steady state value so that further xenon decay will add

net positive reactivity simultaneously with the moderator

cooldown effects. The data presented in Appendix 5 was

used to determine the positive reactivity inserted intothe core for times after 24 hours at discrete time

intervals. Note that a slow cooldown rate will prolong

the time required to reach Mode 5 where the shutdown

margin drops to IX sk/k and, therefore, would require a

larger boron concentration to counteract xenon decay

during the cooldown. A 10 F/hr cooldown rate has been

utilized in this calculation. It should be noted thatthis method accounts for xenon decay for a full 61 hours

from its full power equilibrium level. This is a much

longer time frame than is expected to actually achieve

cold shutdown.

The analysis of Appendix 9, however, considers the impact

of borating from a peak xenon condition as discussed in

Section 3. 1.3.


b. Reactor Cooldown Effects

The effect of the reactor cooldown was calculated by

determining the fuel temperature and moderator temperaturereactivity effects for each incremental temperaturedecrease. Data from Appendix 5 were utilized to determine

these effects. It should be noted that these reactivityeffects are independent of time and solely dependent on

the change in temperature of the core.

5. Effective Cooldown Rate

As discussed above, positive reactivity is added simultaneouslyfrom two sources at the time that the plant cooldown from hot

standby is commenced. The component resulting from an overallnegative isothermal temperature coefficient of reactivity isindependent of time, but is directly dependent upon the net

change in moderator temperature. In contrast, the component

that results from the decay of xenon below its full power

equilibrium value is independent of temperature, but directlydependent upon time. The reactivity contribution from the

moderator cooldown is fixed given the fixed temperature

endpoints (e.g., 572'F to 200'F). The reactivity contributionfrom xenon decay, however, will vary depending upon the time

interval required to achieve the cooldown (i.e., the effectivecooldown rate). As a result, a slower cooldown rate willrequire more boron to be added to the RCS than a fast cooldown

rate for a given temperature decrease. This is because the

cooldown will take a longer period of time allowing more

positive reactivity to be added to the core from the decay ofxenon.

Additionally, since the boration is being accomplished through

makeup for coolant contraction, the addition rate of boron iscontrolled by the rate of coolant contraction. Slower cooldown


rates will result in slower makeup rates which, in turn, resultin slower boron addition rates. Superimposing this effect over

the temperature independent xenon decay will assure that the

most limiting reactivity control scenario is analyzed.

The effective cooldown rate, therefore, is an important inputparameter for these analyses. A lower limit of 10'F/hr was

selected as the limiting case based on the considerations ofTable 4-3.

6. Core Temperature Endpoints

a. Startin Tem erature

The normal hot zero power RCS temperature corresponds to547'F. For the purpose of the analyses presented in

Section 5.0 it is assumed that the cooldown initiates from

a temperature 25 F higher to conservatively model the

expected thermal hydraulic response to a natural

circulation condition. This temperature increase also

corresponds with natural circulation tests completed at

plants of similar size. The cooldown startingtemperature, therefore, will be assumed to be 572'F.

b. Endin Tem erature

The ending temperature for the cooldown from Hot Standby

to Cold Shutdown is chosen to coincide with the 200'F

transition from Mode 4 to Mode 5. At this temperature,

the shutdown margin requirement is decreased to 1.0X nk/k

and the boration source and flow path requirements are

relaxed.

The additional cooldown while in Mode 5 is analyzed

separately since the boration requirements while in thismode are independent of the Mode I, 2, 3, 4 boration


requirements (source and flow path). The Bases section ofReference 10.6 indicates that the Mode 5 borationrequirement in terms of volume and boron concentration isbased on performing a Mode 5 cooldown to 140'F. For the

purpose of these analyses with reduced boric acid concen-

tration, the endpoint temperature is assumed to be 135'F

to conservatively maximize the core reactivity effects.

Appendix 8 provides a checklist of the key physics parameters thatcan be used to evaluate subsequent fuel cycle data to ensure the

data utilized in these analyses remain bounding.

4.3 SYSTEM ANALYSIS ASSUMPTIONS

Table 4-4 presents a list of the specific parameters utilized in the

analysis of boron delivery during the design basis cooldown

described in Section 3.0. A comparison is made to the St. Lucie

Unit 2 data so that differences in the analyses input and output can

be identified. The basic approach in conducting the cooldown

analysis is identical to that used for all previous CE units. A few

minor changes have been made to make the analysis more conservative.

The following paragraphs describe the specific analysis assumptions

in greater detail.

1. System Volumes

a. RCS Volume

The total coolant volume is listed in Reference 10.3 as

9343 ft . Subtracting the total pressurizer volume leaves

8015 ft for the RCS alone. The pressurizer water volume

is listed as 808 ft for 100X power and 520 ft for OX3 3

power. As a conservatism, the 100X power pressurizer

volume will be utilized in the analyses of Section 5.0.

This will provide a higher total system mass to dilute the


boric acid added during the plant cooldown. The OX power

pressurizer volume will be used in the analyses of Section

6.0, however, since this represents the expected volume

following a shutdown. Note that a basic assumption

throughout the analyses of Section 5 and 6 is that the

operators charge to the plant to maintain pressurizerlevel throughout the cooldown transient.

b. Residual Heat Removal S stem Volume

The RHR system is brought into service below 465 psia and

below 350'F. As shown by Appendix 2, the volume of the

RHR system will not impact the final boron concentrationwhen its concentration is assumed to be equal to the RCS

boron concentration.

Also, because it is connected to the RCS after the C-E

methodology has shifted the RCS makeup to the refuelingwater storage tank, the RHR volume will not factor intothe boric acid tank minimum volume requirements. However,

in order to identify the specific refueling water storage

tank volume requirements for each case analyzed the RHR

volume must be included in the calculations for coolant

contraction. To place a conservative upper bound on these

volumes an RHR volume equal to the RCS volume (8015 ft )3

is assumed in the Section 5.0 analyses. The operations

analyses of Section 6.0, however, assume a closer, yet

still conservatively high, volume of 2000 ft .3

2. Residual Heat Removal System Boron Concentration

For the conservative analyses of Section 5.0, the RHR system isassumed to be at the low concentration equal to the RCS

concentration at the time it is lined up to the RCS. In thismanner, the system model does not credit boron addition from

this system.


3. Hakeup Source Temperatures

Appendix 3 presents the derivation of the mass of boric acidthat is added to the RCS with every gallon of water charged tothe system as makeup for coolant contraction. Although thereis a very slight variation in boron delivery with temperature,the effect of source temperature on the required volume is more

significant. This makes the higher temperature the limitingcase, because it is makeup water density that converts the RCS

shrinkage mass into a makeup volume requirement. A highertemperature requires a greater volume to provide the same mass.

A temperature of 120'F was selected because it is above the

technical specification limit of 100'F for the refueling water

storage tank and provides for the possibility of high ambient

temperatures in the vicinity of the boric acid tank.

RCS Leakage

Zero RCS leakage is assumed throughout the analyses of Section

5.0. This is 'a conservative assumption because it limits the

available boron addition to the RCS to that which is provided

by makeup for coolant contraction alone. The effect of RCS

leakage on top of the cooldown analyses presented in Section

5.0 would be a feed and bleed in conjunction with the makeup

for contraction resulting in a net increase in the boric acid

added to the system. Even though boric acid is being lost, the

concentration of the makeup water is always higher than thatwhich is lost assuming the boric acid tank or refueling water

storage tank is the source of. makeup. With RCS leakage, the

contents of the boric acid tank will be added to the RCS sooner

causing the transition to the refueling water storage tank

sooner. The refueling water storage tank would continue tomake up for leakage and coolant contraction with an effectivelyhigher boron addition rate. The net result is that the finalboron concentration in the RCS will be significantly higher

than that which is indicated by the results of Section 5.0.


RCS leakage, however, will impact the total volume used from

the refueling water storage tank throughout the cooldown. The

refueling water storage tank volumes indicated in the tables ofSection 5.0 are based on zero RCS leakage and should be

adjusted accordingly. Technical specification limit leakage of11 gpm over a 24 hour hold and a 37 hour cooldown equates to a

maximum expected leakage volume of approximately 42,000

gallons. When added to the contraction makeup volumes, the

refueling water storage tank volumes required to support plantcooldown are well within the volume limit of 320,000 gallonsfor Modes 1 through 4 (supporting emergency core coolingrequirements) and need not be accounted for separately.

5. Letdown

Letdown is assumed not to be available for this analysis. The

basis for this is that attempted boration is more difficultwithout it. The availablility of letdown would provide the

opportunity to control reactivity changes (xenon and cooldown)

through one or more feed and bleed operations. However, the

use of letdown at 45 gpm and 60 gpm is evaluated in the Section

6.0 operations analyses to evaluate system boration capabilityvia a feed and bleed process.

6. Boron Mixing in the RCS

Throughout the plant cooldowns analyzed in Section 5.0, a

constant pressurizer level is always assumed (i.e., plant

operators charge to the RCS only as necessary to makeup forcoolant contraction). Under these conditions, the drivingforce for the mixing of fluid between the RCS and the

pressurizer is relatively small. As a conservatism, however,

complete and instantaneous mixing is assumed between all makeup

fluid added to the RCS through the loop charging nozzles and

the pressurizer. Further, a pressure reduction is performed

during the plant cooldown process as indicated in Section 5.0.


This pressure reduction is necessary since the shutdown coolingsystem is a low pressure system and is normally aligned at orbelow an RCS pressure of 465 psia. Typically, such

depressurizations are performed using the auxiliary pressurizerspray system under conditions where the RCPs are not running.As an added conservatism, any boron added to the pressurizervia the spray system is assumed to stay in the pressurizer and

not be available for mixing with the fluid in the remainder ofthe RCS. In the analyses of Section 6.0, however, the boron

added to the plant to account for pressurizer mass shrinkage

during the depressurization from 2250 psia to 465 psia iscredited since plant procedures call for regular pressurizersprays to equalize boron concentration between the RCS and the

pressurizer.

7. RHR Pressure

In accordance with Reference 10. 10, RCS pressure will be

controlled in the range of 375 to 400 psig. A pressure of 350

psia was chosen for the RCS pressure while on RHR cooldown toconservatively bound the allowable range. Lowering the

pressurizer pressure has the effect of causing more pressurizershrinkage mass that dilutes the RCS when no credit is taken forthe bor ation of this shrinkage mass make up.

8. Final RCS Pressure

As one final dilution step, the RCS is assumed to be

depressurized to atmosheric pressure in preparation forrefueling.

9. Final Boron Concentration

Final boron concentration is arbitrarily selected as 50 ppm

over the highest value for the 200'F shutdown margin

requirement. This provides ample margin to support possible

physics parameter changes in future cycles.

Repor t No. 849963-MPS-5MISC-00$ REV 0 Page 4-13

ADDITIONAL ASSUMPTIONS, MODE 5 COOLDOMN

I

The following additional assumptions are applicable to the cooldown

analysis for Mode 5 (i.e., cooldown from 200'F to 135'F). The

assumptions of Section 4.3 remain applicable, as well

1. Pressurizer Volume

The OX power pressurizer level is assumed for this phase of the

cooldown analysis since it is a more realistic representation

of the plant operations.

2. Initial RCS Boron Concentration

The analyses of Section 5.0 indicate a final boron

concentration in excess of the required boron concentration at

the completion of the cooldown to 200 F. However, the initialconcentration is assumed to be equal to the 200'F xenon free

boron requirement. This will assess the ability of the

boration system to recover and maintain a degree of margin

above the absolute minimum.

For the case where the refueling water storage tank is utilizedfor cooldown makeup, a feed and bleed is necessary at the startof the cooldown to ensure shutdown margin is maintained. The

amount of boron added to the system during this feed and bleed

was calculated to bring the final RCS boron concentration

exactly to the 135'F shutdown margin requirement.


Table 4-1

Boric Acid Concentration Reduction AnalysisComparison of Physics Parameters

Parameter

Core Power (100X)

Shutdown Margin T>200'F

Shutdown Margin T<200'F

RCS Average Temperature (OX Power)

RCS Cooldown Starting Temperature

Moderator Temperature Coefficient

TypicalC-E Unit

2560 HWt

5.0X ak/k

3.5X ak/k

532 F

557'F (1)

-2.7E(-4)Gk/k/'F

Moderator Data Uncertainty (Bias)

Doppler Data Uncertainty (Bias)

IBW Data Uncertainty (Bias)

Effective Cooldown Rate

10X (OX)

15X (15X)

10.9X (-3.1X)

12.5 F/hr

Scram Worth Data Uncertainty (Bias) 13X (-9X)

Turkey PointUnits 3 and 4

2200 HWt

1.77X nk/k

1.0X ak/k

547'F

572'F (1)

-3.5E(-4)ak/k/ F

10X (OX)

10X (OX)

20X (OX)

10.9X (OX)

10'F/hr

Start of Cooldown (time afterShutdown)

Excess Scram Worth (T>200'F)

Excess Scram Worth (T<200'F)

26 hrs

0.08X ak/k

1.58X nk/k

24 hrs (2)

0.697X b,k/k

1.468X nk/k

(1) Based on 25'F heat up from hot zero power condition uponinitiation of natural circulation.

(2) The analysis of Appendix 9 starts from the peak xenon condition at 8

hours after a full power shutdown.


Table 4-2

Inverse Boron Morth

Tem erature 'F IBM

572.0

552.0

532.0

512.0

492.0

472.0

452.0

432.0

412.0

392.0

372.0

352.0

332.0

312.0

292.0

272.0

252.0

232.0

212.0

202.0

200.0

98.65

95.88

93.44

91.26

89.33

87.61

86.06

84.66

83.39

82.21

81.12

80.08

79.10

78.16

77.24

76.34

75.46

74.60

73.76

73.34

73.26


Table 4-3

Derivation of Limiting Cooldown Rate (*)(Modes 1, 2, 3, and 4)

Action

1. Plant Shutdown to Hot Standby

2. Initial Hold at Hot Standby

3. Plant Cooldown 572'F to approx. 350'F

4. Hold for upper Head Cooling

5. Plant Cooldown from approx. 350'F to 200'F

6. Additional Conservatism

TlmB Total

13

22

28

37

7. Effective Cooldown Rate: (372'F)/(37 hr) 10'F/hr

(1) Per NRC Branch Technical Position (BTP) RSB 5-1

(2) Cooldown rate limited to 25'F/hr per Reference 10. 10 (normally limited to

6 hours by technical specification ACTION statements)

(3) Per Reference 10. 10

(4) Allows for actual plant cooldown rates during Steps 3 and 4 as low as

15'F/hr

(*) This represents a conservative estimate of the time required to complete

a cooldown to COLD SHUTDOWN to maximize xenon decay reactivity effects.


Table 4-4

Boric Acid Concentration Reduction AnalysisComparison of System Analysis Parameters

Parameter

RCS Volume

Pressurizer Water Volume (100X Power)

Pressurizer Water Volume (OX Power)

RCS Normal Operating Pressure

RCS Hinimum Operating Pressure

RCS Cooldown Starting Pressure

RCS Cooldown Final Pressure (Mode 5)

RCS Average Temperature (100X Power)

RCS Average Temperature (OX Power)

Post-Shutdown RCS Temperature Increase

RCS Cooldown Starting Temperature

RCS Cooldown Final 'Temperature (Mode 2 to 5)

RCS Cooldown Final Temperature (Modes 5 and 6)

Effective Cooldown Rate

Shutdown Cooling System Entry Pressure

Shutdown Cooling System Entry Temperature

RWST Minimum Volume (Modes 1-4)

RWST Minimum Boron Concentration

RWST Temperature (Assumed)

Boric Acid Tank Temperature (Assumed)

RCS Leakage (Assumed)

Letdown UtilizedInitial RCS Boron Concentration

Pressurizer Condition

TypicalC-E Unit

9398 ft600 ft450 ft2250

2200

2200 psia275 psia572 F

532'F

25 F

557'F

200 F

135'F

12.5'F/hr275 psi a

325'F

417,100 gal1720 ppm

50 F

70'F

0 gpm

No

0 ppm

Saturated

Turkey PointUnits 3 and 4

8015 ft (1)808.0 ft (2)520.0 ft2250

2200

2250 psia14.7 psia574.2'F547'F

25'F

572'F

200'F

135'F

. 10'F/hr350 psia350'F

320,000 gal

1950 ppm

120'F

120'F

0 gpm

No

0 ppm

Saturated

(1) Loop and vessel volumes only(2) Pressurizer water volume only (the total capacity of the loops, vessel,

and pressurizer is listed as 9343.

Report No. 849963-MPS-SHISC-003 REV 0 Page 4-18

. 5.0 DESIGN BASIS ANALYSES

This section presents the results of the analyses completed for thescenarios outlined in Sections 3. 1. 1 and 3. 1.2. These specificscenarios were chosen on the basis that they represent the most

limiting reactivity control conditions during a design basis

cooldown of the plant. Section 5. 1 presents the actual RCS boron

concentration requirements that conservatively maintain the requiredshutdown margin at discrete temperature increments. Section 5.2

discusses the conservative analysis of the cooldown from the hot

standby condition to cold shutdown. Section 5.3 completes the

cooldown analysis by presenting the conservative cooldown from cold

shutdown conditions to refueling temperatures.

5.1 RE(UIRED RCS BORON CONCENTRATION

Using the physics data of Appendix 5 and the assumptions of Section

4.2, a detailed reactivity balance calculation was completed. The

output of this calculation is a specified minimum boron

concentration change that must occur in the core (i.e., in the RCS)

to maintain the specified shutdown margin. This reactivity balance

specifically takes into account the positive reactivity addition ofxenon decay below its initial full power equilibrium concentration

and positive reactivity addition of moderator cooldown. With the

uncertainties of Section 4.2 conservatively applied, shutdown margin

will be assured if the RCS boron concentration is maintained above

the levels indicated in Tables 5. 1-1 through 5. 1-6 for each

temperature step. The data in these tables are presented in

Figure 5.1-1.

As can be seen from the tables and Figure 5. 1-1, the slower cooldown

rates have higher boron concentration requirements. This is because

in the time to get to 200'F, more xenon will have decayed, adding a

greater amount of reactivity that must be compensated for.


It should also be noted that three different boron concentrationrequirements are specified for the 200'F temperature endpoint. The

E

first corresponds to the endpoint of the cooldown and corresponds toa shutdown margin of 1.77X sk/k. At 200'F, however, the shutdown

margin requirement drops to 1.0X ak/k, effectively requiring less

boron to be in the system. The third entry corresponds to the

boron concentration required to maintain a 1.0X ak/k shutdown margin

at 200 F with all xenon decayed away (xenon free). Xenon requires

approximately 150 hours after shutdown to effectively decay away tothis level. It should be noted that all of the tables indicate the

same xenon free required boron concentration at 200'F.

The results of the peak xenon calculation are presented in Appendix

9. Since the Appendix 9 final concentration for 200 degrees at a

10'F/hr cooldown rate is the higher value, the acceptance criteriafor the cooldown evaluations will be a final concentration 50 ppm

higher than the identified limit of 840 ppm boron.


Table 5.1-1

Required Boron Concentration vs. Temperature

Equilibrium Xenon, EOC, 10'F/hr Cooldown Rate

Tem erature 'F Re ui red Boron m

572.0

552.0

532.0

512.0

492.0

472.0

452.0

432.0

412.0

392.0

372.0

352.0

332.0

312.0

292.0

272.0

252.0

232.0

212.0

202.0

200.0 (1.77X ak/k)200.0 (1.0X nk/k)200.0 (Xenon Free)

-180.81

-63.90

48.22

147.89

233.39

307.02

370.73

426.15

474.64

517.38

555.32

589.29

619.98

647.95

673.68

697.57

719.94

741.05

761.12

770.81

772.73

710.17

730.70


Table 5. 1-2



Tem erature 'F Re uired Boron m

572.0

522.0

472.0

422.0

372.0

322.0

272.0

222.0

200. 0 (1. 77X nk/k)200.0 (1.0X nk/k)200.0 (Xenon Free)

-180.81

61.05

243.12

373.13

471.12

549.62

616.31

675.63

700.05

637.49

730.70

I


Table 5.1-3




572

522

472

422

372

322

272

222

200.0 (1.77X ak/k)200.0 (1.0X ak/k)200.0 (Xenon Free)

-180.81

47.11

218.02

339.06

429.91

502.89

565.54

622.11

645.68

583.12

730.70


Table 5.1-4

l




572

482

392

302

212

200.0 (1.77K ak/k)200.0 (1.0X nk/k)200.0 (Xenon Free)

-180.81

177.91

377.29

503.38

602.42

614.50

551.94

730.70


Table 5.1-5


Equilibrium Xenon, EOC, 100 F/hr Cooldown Rate


572

472

372

272

200.0 (1.77X b,k/k)

200.0 (1.0X nk/k)200.0 (Xenon Free)

-180.81

204.79

406.67

534.57

610.44

547.88

730.70


Table 5.1-6


Mode 5 Cooldown to Refueling


200 (Xenon Free)

180

160

140

135

730.70

746.83

762.95

779.08

783.11


Figure S.l—l Required Boron Concentration

00

ED

l

C/lI

.j

-200

0 10 'F/'hrTemperature t Des, F )

+ 50 'Ff'hr 0 100 'F/hr

5.2 COOLDOWN FROH HOT STANDBY, EgUILIBRIUH XENON, EOC,

5.2.1 Purpose

The purpose of this analysis is to model a plant cooldown from hot

standby to cold shutdown to determine the actual expected boron

delivery to the RCS. The criterion for this analysis is that a

shutdown margin of 1.77X hk/k must be maintained throughout the

cooldown process down to a temperature of 200'F. (At 200'F and

below, the shutdown margin requirement is reduced to I.OX zk/k.)Haintenance of these shutdown margins will be assured as long as

the actual boron delivered with the makeup provided for coolant

contraction maintains RCS boron concentration above the required

boron concentration of Tables 5. 1-1 through 5. 1-5 of Section 5 and

Appendix 9.

5.2.2 Analyses

The assumptions and initial conditions for this analysis are

discussed in Section 4.0 and are summarized in Table 5.2-1. Since

the boron delivery to the RCS is limited to the makeup. that is

provided to compensate for coolant contraction, the expected

coolant contraction must be determined for discrete temperature

changes. A known boron content of the makeup water leads to an

accounting of the accumulated boron at each temperature increment

which, in turn, leads to a determination of the boron concentration.

The calculations are performed in the following manner.

To begin, boron concentration in terms of weight fraction is

defined as follows:

(boron concentration) = mass of boron in system

where, if complete mixing is assumed between the RCS and the

pressurizer, the total system mass is the sum of the boron

mass in the system, the RCS water mass, and the pressurizer water


mass. Mass of boron in the system will be determined by identifyingthe boron added with each temperature increment.

Therefore, the initial total system mass of 393,572. 1 ibm in Tables

5.2-2 through 5.2-4 was calculated as follows:

(Total System Mass). - (Boron Mass). + (RCS Water Mass). + (PZR

Water Mass),.

or

08015 ft3

1)0.022042 ft /ibm

808 ft(2)

0.02698 ft /lb01

The total system mass is then corrected for each temperature

increment by accounting for both water and boron addition as makeup

is provided for the contraction of the reactor coolant. The amount

of coolant contraction (or shrinkage) with each temperature

increment is found by comparing the specific volume at the startingtemperature (v.) of each increment to the specific volume at the

1

final temperature (vf) of each increment.

The following represents a summary of the calculations for each

temperature increment of the plant cooldown:

Initial Temperature

Final Temperature

Initial Specific Volume v.i

Final Specific Volume = v (4)f

(1)(2)(3)

(4)

SpecificSpecificObtainedpressureObtainedpressure

volume of compressed water at 572 degrees and 2250 psia.volume of saturated water at 2250 psia.from Reference 10. 11 for compressed liquid at givenand T.from preference 10. 11 for compressed liquid at givenand Tf


Shrinkage Hass (System Volume) (1/vf — 1/v.)

BAT Makeup Volume (Shrinkage Mass) / (8.2498 ibm/gallon)

RWST Makeup Volume - (Shrinkage Mass) / (8.2498 ibm/gallon)( '5)

Boric Acid Added (BAT Vol.) x (mass of boric acid/gallon)or

(RWST Vol . ) x (mass of bori c

acid/gallon)

Total Boric Acid = (Initial Boric Acid) + (Boric Acid Added)

Total System Hass = (RCS water mass)( ) + (PZR water mass)( )(7)

+ (Total boric acid)

trat'o - Total Boric Acid 100 1748.34 (9)Final Concentration -

ota ystem Mass)

This calculation process is completed for several temperature

increments (assuming constant plant pressure) until a temperature of350'F is reached. At this temperature two things happen:

1. The RCS is depressurized to 465 psi a to correspond with the

maximum pressure for connecting the RHR system to the RCS.

This pressure reduction actually entails a cooldown of the

pressurizer and, hence, a pressurizer shrinkage mass. This iscalculated by comparing the specific volumes for a saturated

liquid at 2250 psia and 465 psia. The volume to accommodate

this, in all cases, comes from the refueling water storage

tank. As a conservatism, this volume addition is assumed not

to add any boron to the RCS.

(5)

(6)(7)(8)(9)

Density of water at assumed tank temperature 120'F. (Reference10.13)See Appendix 3 for values3of dissolved boric acid in water.RCS water mass = (8015 ft3) / (specific volume)PZR water mass (808 ft ) / (specific volume at indicated P t).See Appendix 4 for the conversion factor between wt.X and ppm.


2. The RCS is lined up to the RHR system which increases the totalsystem volume and mass for the remainder of the cooldown. The

RHR system is conservatively assumed to have a boron

concentration equal to the RCS concentration so that no boron

addition is credited. Also, the RHR system volume is assumed

to be equal to the RCS volume to conservatively estimate the

refueling water storage tank makeup requirements for the latterstages of the plant cooldown ~

The remainder of the cooldown analysis is handled in the same manner

as described above. To complete the analysis, the final boron

concentration is compared to the required concentration identifiedin Tables 5. 1-1 through 5. 1-5 of Section 5.0 and Appendix 9. An

arbitrary margin of 50 ppm is added to the 200'F, 1.77K ak/k

shutdown margin required boron concentration of Appendix 9 to define

the acceptance criteria for the cooldown analysis.

The purpose of this analysis is to identify the minimum acceptable

volume required from the boric acid tank as input to the plant

technical specifications. This is accomplished by adjusting the

temperature at which the source of makeup water is switched from the

boric acid tank to the refueling water storage tank. This is

accomplished through an iterative process until the switch over

temperature is identified that results in a final concentration justequal to or slightly higher than the established acceptance

criterion. The design basis of the boric acid tank concentration

and minimum volume requirement, therefore, is established. It is

that volume and concentration that is necessary to raise RCS boron

concentration such that subsequent makeup for coolant contraction

supplied by the lower concentration refueling water storage tank

alone will still maintain the required shutdown margin per Tables

5.1-1 through 5.1-5.

5.2.3 Results

A detailed parametric analysis was performed to identify the minimum

acceptable boric acid tank volume for a range of concentrations. In


particular, boric acid tank concentration was varied from 3.0 weight

percent boric acid to 3.5 weight percent boric acid. This

concentration range strikes the optimum balance between the need tokeep the concentration low (to keep the solubility temperature limitas low as possible) and the need for a higher concentration to keep-

the corresponding volume requirements well within the currentcapacity of the tanks. An optimum concentration of 3.25 +0.25

weight percent achieves this with a control band that is well withinthe accuracy of the boron concentration measurement analysis.

The analyses described in Section 5.2-2 were completed utilizing theCE Utility Code BACR. A Computer Code Certificate and the Turkey

Point Code input are provided as Appendix 10. Tables 5.2-2 through5.2-4 represent the output of this code for the indicated boric acidtank and refueling water storage tank concentrations.

The boron concentration results of Tables 5.2-2 through 5.2-4 were

compared to the required concentrations at each temperatureincrement during a plant cooldown identified in Tables 5. 1-1 through5. 1-5. In each case, the actual system boron concentrations are

greater than that necessary for the required shutdown margin. Thisis illustrated graphically by combining the curves for required

boron�

.concentration and delivered concentration for three separate

cases in Figure 5.2-1 through 5.2-3.

To set the minimum technical specification boric acid tank volume

corresponding to the various boric acid tank and refueling water

storage tank concentrations, the tank volumes from Tables 5.2-2

through 5.2-4 were extracted and are tabulated in Table 5.2-5. The

volumes contained in Table 5.2-5 are the minimum boric acid tank

volumes needed (in conjunction with the refueling water storage

tank) to borate the RCS to the required shutdown margin. These

volumes must be contained in the region of the boric acid tank above

zero percent indicated level. The refueling water storage tank

volumes corresponding to each boric acid tank required volume are

Report No. 849963-HPS-5NISC-003 REV 0 Page 5-14

provided for information only and are not intended for incorporationinto the plant technical specifications. These volumes are wellwithin the volume requirements for emergency core cooling and need

not be included separately.

Table 5.2-6 summarizes the makeup flow rates that could be expected

during the transient analyzed. For the limiting cooldown rate of10'F/hr, the required boric acid flow rate ranges from 8 to 10 gpm.

Such flow r ates are just within the 10 gpm capacity of flow controlvalve FCV-113A for the manual and blended boric acid flow paths

(normal boration) and well within the 60 gpm (nominal) capacity ofthe emergency boration flow path via motor operated valve HOV-350.

Faster cooldown rates will require even greater makeup capacity tocompensate for the faster contraction rate of the coolant. Table5.2-6 shows the effective makeup capacity requirements for a

cooldown rate of 25'F/hr, as well. This is the maximum cooldown

rate allowed for natural circulation cooldowns in accordance withReference 10.10. While the flow rates of 21 to 24 gpm are wellwithin the emergency boration flow path capacity of 60 gpm

(nominal), they exceed the current 10 gpm limit of FCV-113A. A

modification is planned for this valve, however, to ensure the

availability of the normal boration flow path for the cooldown

scenarios evaluated thus far. Two transfer pumps supplying borated

water via the normal or emergency boration flow path will be

adequate for the faster cooldown transients.

5.2.4 Refueling Water Storage Tank Boration Requirements, Modes 1,2,3

and 4

The refueling water storage tank provides an independent source ofborated water that can be used to compensate for core reactivitychanges and expected transients throughout core life. lt should be

noted that in Nodes 1, 2, 3 and 4, the minimum refueling water

storage tank water volume is 320,000 gallons as required by

emergency core cooling considerations. The purpose of this section


is to demonstrate that the refueling water storage tank minimum

inventory requirements (in modes 1, 2, 3 and 4) required tocompensate for the reactivity changes during a shutdown and cooldown

(using the refueling water storage tank as the only source ofborated water) are much less than the emergency core coolingrequirements.

This calculation derives the minimum volume of refueling waterstorage tank water necessary to bring the plant from hot standby tocold shutdown while maintaining the plant at a 1.77/ sk/k shutdown

margin. The calculation approach is identical to that of the

cooldown described in Section 5.2.2. The major difference is thatall RCS makeup is supplied from the refueling water storage tank ata boron concentration of 1950 ppm. This cooldown is performed as

described below:

1. Perform a feed and bleed with the refueling water storage tankto raise RCS boron concentration from 0 ppm to 535 ppm boron.

This is a 255 minute feed and bleed using 60 gpm letdown.

2. Perform a plant cooldown from an initial RCS temperature and

pressure of 572'F (547'F + 25'F as described in Section

4.2.6.a) and 2250 psia to 350'F and 350 psia. Charge from the

refueling water storage tank only as required to make up forcoolant contraction.

3. Align the RHR system to the RCS. Assume that its volume is8015 ft . Assume that the concentration of the RHR system isequal to that of the RCS at the time of initiation.

4. Continue cooldown from 350'F and 350 psia to a final RCS

condition of 200'F and 14.7 psia. Charge only as necessary to

make up for coolant contraction.


Table 5.2-7 contains the results of the calculated volumes in steps

1 through 4 above. The refueling water storage tank boration

requirement for Modes 1, 2, 3 and 4 is estimated to be 37, 155

gallons. This value does not account for any RCS leakage during

this process. Figure 5.2-4 shows the RCS boron concentration forthis special case. As expected, the boration requirements impose a

refueling water storage tank minimum volume which is much smaller

than the minimum volume requirements placed on the tank by emergency

core cooling requirements (320,000 gallons). Even with a bounding

assumption of 11 gpm RCS leakage during a 24 hour hold and a 37 hour

cooldown, the maximum expected refueling water storage tank makeup

volume requirement is 77,415 gallons.


Table 5.2-1

Summary of Initial Conditions and Assumptions

Cooldown from 572'F to 200'F

(Mode 3 to 5)

Parameter Value

RCS Volume

Pressurizer Volume (100% Power Level)

Initial RCS Pressure

Final RCS Pressure

Initial RCS Temperature

Final RCS Temperature

Pressurizer Condition

Pressurizer Level

RCS Leakage

Initial RCS Boron Concentration

Initial Pressurizer Boron Concentration

RHR Volume

RHR Boron Concentration

Letdown AvailableRefueling Water Storage Tank Temperature

Boric Acid Tank Temperature

8015 ft (1)808 ft (2)2250 psia14.7 psia572'F

200'F

Saturated

Constant

0

0

0

8015 ft[= RCS]

(4)

No

120'F

120'F

(1)(2)

(3)(4)

Loop and vessel volumes onlyPressurizer water volume only. In combination with note (1) above,

this corresponds to a total inventory 9343 cubic feet.Overestimated for conservatismUnderestimated for conservatism


TABLE 5.2-2PLANT COOLDOMH FROH 572 F TO 200 F; BAT AT 3.50 wtX BORIC ACID; RWST AT 1950 ppm BORON

AVG.SYS. TEMP ~

(F)Ti Tf

PZR PRESS SPECIFIC VOLUHE SHRINKAGE BAT VOL Q RMST VOL 9 8/A ADDED TOTAL 8/A TOTAL SYS. HASS FIHAL CONC. i

(psia) (cu.ft./Ibm) HASS(ibm) 120 F (gal) 120 F (gal) (ibm) (ibm) ( lbm) (ppm boron) [

Vi Vf I-I

2250225022502250

2250225022502250225022502250

350350

350350350350

14.75,871.3

13 691.4

572

572560540520500

480467440420390350350

350300260

230200

ITOTAL BAT

TOTAL RMST

572560540520500480467440420390350350350300260230200200

VOLUHE

VOLUHE

1 F 00000 1.000000-02204 0.021650.02165 0.021060.02106 0.020550.02055 0.020090.02009 0.019690.01969 0.019450.01945 0.019000.01900 0.018690.01869 0.018280.01828 0.017810-02698 0.019120.01781 0.017810.01781 0.017430.01742 0.017070.01706 0.016830.01682 0.016620.01912 0.016719

GALLOHS

GALLONS

0.06,669.4

10,376.39,449.68,835.58, 104 ~ 75,001.79,892.16,885.89,738.3

11,577.212,311.3

0.019,369.818,867.712,841.011,468.56,068.8

0.0808.4

1,257.81,145.41,071.0

982.4606.3

0.00.00.00.00.00.00.00.00.00.00.0

0.00.00.00.00.00.00.0

1,199.1834.7

1, 180.41,403.31,492.3

0.02,347.92,287.11,556.51,390.2

735.6

0.0241.9376.3342.7320.5294.0181.4111.677.7

109.8130.6

0.00.0

218.5212.8144.8129.4

0.0

0.0241.9618.2961. 0

1,281.41,575.41,756.81,868.41,946.12,055.92,186.52,186.54, 177.74,396.24,609.04,753.84,883.24,883.2

393,572.1400,483.4411,236.0421,028.3430,184.3438,582.9443,766.0453,769.6460,733.1470,581.3482,289.0494,600.3945,042.1964,630.3983,710.9996,696.7

1,008,294.61,014,363.4

0.0 i105.6 I262.8 /399.1520.8 I628.0 I

692.1 I719.9 I738.5 i763 8 I792.6 i772.9 /772.9 )

796.8 /819.2 /833.9 I846.7 )841.7 i

I

I

TABLE 5.2-3 PLANT COOLDOWN FROM 572 F TO 200 F; BAT AT 3.25 MtX BORIC ACID; RWST AT 1950 ppm BORON

IAVG.SYS. TEMP.

(F)Ti Tf

PZR PRESS SPECIFIC VOLUHE SHRINKAGE BAT VOL Q RWST VOL 9 8/A ADDED TOTAL 8/A TOTAL SYS. MASS FINAL CONC.I

(psia) (cu.ft./Ibm) HASS(lbm) 120 F (98l) 120 F (Bsi) (Ibn) (ibm) ( lbm) (ppn boron) i

Vi Vf I

572

572560540520500470452440420

390350350350300260

230200

ITOTAL BAT

TOTAL RWST

572560540520500470452440420390350350350300260

230200200

VOLUME

VOLUHE

22502250225022502250225022502250225022502250

350350350350

350350

14.76,553.3

13 009.5

1.000000.022040.021650.021060.020550.020090.019510.019190.019000.018690.018280.026980.01781O.O1781

0.017420.017060.016820.01912

GALLONS

GALLONS

1.000000.021650.021060.020550.020090.019510.019190.019000.018690.018280.017810.019120.017810.017430.017070.016830.01662

0.016719

0.06,669.C

10,376.39,449.68,835.5

11,965.66,766.94,265.96,885.89,738.3

11,577.212,311.3

0.019,369.818,867.712,841.011,468.56,068.8

0.0808.4

1,257.81,145.41,071.01,450.4

820.30.00.00.00.00.00.00.00.00.00.00.0

0.00.00.00.00.00.00.0

517.1834.7

1,180.C1,403.31,492.3

0.02,347.92,287.11,556.51,390.2

735.6

0.0224.0348.6317.4296.8401.9227.348.177.7

109.8130.6

0.00.0

218.5212.8144.8129.4

0.0

0.0224.0572.6890.0

1,186.81,588.71,816.01,864.21,941.82,051.72,182.22,182.24,169.74,388.14,600.94,745.84,875.14,875.1

393,572.1400,465.5411, 190.4420,957.4430,089.6442,457.1449,451.4453,765.4460,728.9470,577.1482,284.8494,596.1945,034.0964,622.3983,702.8996,688.6

1,008,286.51,014,355.3

o.o i97.8

243.5 I369.6 I482.4 I627.8 I706.4 I718.3 i736.9 I

7623 I791 1 I771.4 I

771.4 I

795'3 I817.7 i832.5 i845.3 i840.3 i

I

I

TABLE 5.2-4 PLANT COOLDOMN FROH 572 F TO 200 F; BAT AT 3.00 MtX BORIC ACID; RWST AT 1950 ppm BORON

IAVG SYS. TEHP.

(F)Tf

PZR PRESS SPECIFIC VOLUHE SHRINKAGE BAT VOL cI RNST VOL 9 B/A ADDED TOTAL 8/A TOTAL SYS. HASS FINAL CONC.i

(psia) (cu.ft./ibm> HASS(lbn) 120 F (gal) 120 F (gal> (Ibn) (lbn) ( ibm) (ppn boron) iVi Vf I

572 -572572 -560560 -540540 -520520 -500500 -480480 -460460 -431

431 -420420 -390390 -350350 350350 350350 300300 260

260 230

230 200200 200

ITOTAL BAT VOLUHE

ITOTAL RWST VOLUHE

2250225022502250

22502250

22502250225022502250

350350350350350350

14.77,448.8

12,114.0

1.000000.022040.021650.021060.020550.020090.019690.019330.018860.018690.018280.026980.017810.017810.017420.017060.016820.01912

GALLONS

GALLONS

1.000000.021650.021060.020550.020090 '19690.019330.018860.018690.018280.017810.019120.017810.017430.017070.016830.01662

0.016719

0.06,669.4

10,376.39,449.68,835.58,104.77,688.3

'I0,327.23,764.09,738.3

11,577.212,311.3

0.019,369.818,867.712,841.011,468.56,068.8

0.0808.4

1,257.81 ~ 145.41,071.0

982.4931.9

1,251.80.00.00.00.00.00.00.00.00.00.0

0.00.00.00.00.00.00.00.0

456.31,180.41,403.31,492.3

0.02,347.92,287.11,556.51,390.2

735.6

0.0206.3320.9292.3273.3250.7237.8319.442.5

109.8130.6

0.00.0

218.5212.8144.8129.4

0.0

0.0206.3527.2819.4

1,092.71,343.41,581.21,900.61,943 '2,052.82,183.42,183.44,171.94,390.44,603.24,748.04,877.44,877.4

393,572.1400,447.8411, 145.0420,886.8429,995.5438,350.9446,277.0456,923.6460,730.1470,578.3482,286.0494,597.3945,036.3964,624.5983,705.1996,690.9

1,008,288.8'I,O I4,357.6

0.0 (

90.1 I224.2 i340'4 I444.3 Is3s.e i619.4 I727.2 I7373 I762.7 i791.5 )

771.8 i771.e i79S.7 i818.1 I

832.9 I845.7 (

840.7 (

Table 5.2-5

Minimum Required Boric Acid Tank Volumes

Modes 1, 2, 3, and 4

(RWST 9 1950 ppm)

BAT Concentration'(11

wt% m

BAT Volume(

allonsRWST Volume

allons

3.5 (6119)

3.25 (5682)

5,900

6,600

14,000

14,000

3'.0 (5245) 7,500 13,000

(1)

(2)

(3)

The conversion factor between wt% and ppm boron is 1.0 wt/ equals1748.34 ppm boron (Appendix 4).Includes analysis value rounded up to nearest 100 gallons. Thesevolumes doe not include instrument error/inaccuracy since the lowlevel alarm setpoint will be set to accommodate instrument looperrors.Rounded up to nearest 1000 gallons (this volume does not include themakeup for any RCS leakage).


Table 5.2-6

Summary of Effective Flow Rate Requirements

Source

(BAT wtX)

RuST m

BAT 3.50

RMST 1950

RCSnT(1)

('F)

90

282

(2)Time To Achieve AT

minutes

~10'F hr ~25'F hr ~100'F hr

540 216 54

1692 676.8 169.2

(3)Hekeup

Volume

Effective (4)

Flow Rate m

5,165

14,539

9.6

8.6

23.9

21.5

95.6

85.9

~sl lshs ~10'F hr ~25'5 hr ~100'5 hr

BAT 3.25

R'WST 1950

102

270

612 244.8 61.2

1620 648 162

5,733 9.4 23.4 93.7

13,971 8.6 21.6 86.2

BAT 3.00

RMST 1950

119

253

714 285.6 71.4

1518 607. 2 151.8

6,508

13, 196

9.1

8.7

22.8

21.7

91.1

86.9

(2)(3)(4)

Extracted from Tables 5.2-2 through 5.2-4 corresponding to aT fromcooldown start to switchover temperature (BAT) and from switchovertemperature to finish (RWST)

Time (RCS sT) / (Cooldown Rate)Extracted from Table 5.2-2 through 5.2-4Effective Flow Rate = (Hakeup Volume) / (Time)


ITABLE 5.2-7I

PLANT COOLDOMH FROM 572 F TO 200 F; RlST FEED AHD BLEED AND MAKEUP AT 1950 ppa BORON

IAVG.SYS. TEMP

(F)Ti Tf

PZR PRESS SPEClFIC VOLUME SHRlHKAGE BAT VOL O RUST VOL c)

(psia) (cu.ft./ibm) MASS(ibm) 120 F (gal) 120 F (gal)Vi Vf

8/A ADDED TOTAL 8/A TOTAL SYS. MASS FINAL COHC.

( ibm) ( ibm) (ibm) (ppn boron) I

572 572572 560

560 540540 520

520 500

500 480480 453

453 440440 420420 390390 350350 350

350 350

350 300

300 260

260 230

230 200

200 200

IFEED AHD BLEED RUST

ITOTAL RNST VOLUME

22502250225022502250225022502250225022502250

350350350350350350

14.7VOLUME

1.000000.022040.021650.021060.020550.020090.019690.019210.019000.018690.018280.026980.0'1781

0.017810.017420.017060.016820.01912

(Oppm to

1.000000.021650.021060.020550.020090.019690.019210.019000.018690.018280.017810.019120.017810.017430.017070.016830.01662

0.016719535ppm) =

0.06,669.4

10,376.39,449.68,835.58,104.7

10,258.14,635.66,885.89,738.3

11,577.212,311.3

0.019,369.818,867.712,841.011,468.56,068.8

17,592.037,154.8

0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0

GALLONS (255GALLONS

0.0808.4

1,257.81,145.41,071.0

982.41,243.4

561.9834.7

1,180.41,403.31,492.3

0.02,347.92,287.11,556.51,390.2

735.6minUtes at

0.075.2

117.0106.699.791.4

115.752.377.7

109.8130.6

0.00.0

218.5212.8144.8129.4

0.069gpm)

1,207.01,282.21,399.31,505.81,605.51,696.91,812.61,864.91,942.62,052.42,183.02,183.04,171.14,389.54,602.34,747.24,876.54,876.5

394,779.1401,523.7412,017.0421,573.2430,508.3438,704.4449,078.2453,766.2460,729.6470,577.8482,285.5494,596.8945,035.4964,623.7983,704.2996,690.1

1,008,287.91,014,356.7

534.5558.3 I

593.8 I

624.5 I6S2.0 I676.3 I705.7 I

718.S I737.1 I762.5 I791.4 I771.7 I771.7 I

795.6 I

818.0 I

832.7 I845.6 I

840.S I

900

Figure 5.2 —1 RGS Boron Goncentration

Equlllbrlum Xenon, EOC

800

700

600

500

300

200

100

-100

-200600 500 400 300 200

0 Required(10 F/hr Cooldown)Temperature(Deg F)

+ Delivered(BAT 3.0 wing RIST 1950ppm)

900

Figure 5.2 —2 RCS Boron ConcentrationEqulllbrlum Xenon, EOC

800

700

600

300

100

5000

p .4000

Ql

0K

-100

600 500 400 300 200

0 Required(10 F/hr Cooldown)Temperature (Deg F}

+ Delivered(BAT 3.25 wtX RWST 1950pprn)

900

Figure 5.2 —3 RCS Boron ConcentrationEquilibrium Xenon, EOC

800

700

600

500

300

200

100

-100

-200600 500 300 200

0 Required(10 F/hr Cootdown)Temperature (Deg F)

+ Delivered(BAT 3.5 wtX RNST 1950ppm)

900

Figure 5.2 —4 RCS Boron ConcentrationEqulllbrlum Xenon, EOC

800

700

600

500

400

300

200

100

-100

-200600 500 300 200

0 Required(10 F/hr Cooldown)Temperature (Deg F)

+ Oellvered(RWST 1950ppm)

5.3 COOLDOWN FROM COLD SHUTDOWN TO REFUELING TEMPERATURE, MODE 5

5.3. 1 Purpose

As stated in the plant Revised Technical Specifications (Reference

10.6), the boration capacity required below an average RCS

temperature of 200'F is based upon providing a shutdown margin of 1/

ak/k following xenon decay and a plant cooldown from 200'F to 140'F.

(A cooldown to 135'F will be analyzed for additional conservatism.)

The boron concentration requirements of Table 5. 1-6 are the minimum

required to maintain shutdown margin above the limit of 1.0/ zk/k.This analysis will demonstrate that a cooldown from 200'F to 135'F

can be completed using the boric acid tank or refueling water

storage tank as the source of makeup water to compensate for coolant

contraction and that, accordingly, the RCS boron concentration willbe maintained greater than these requirements.

5.3.2 Analyses

The assumptions and initial conditions for these analyses are

discussed in Section 4.0 and are summarized in Table 5.3-1. They

are essentially identical to those of Section 5.2. A few minor

differences are required to account for the unique circumstances ofthis cooldown. The principal differences are summarized below:

1. The 0/ power pressurizer level is used instead of the 100/

power level.

2. The initial boron concentration coincides with the 200'F, xenon

free 1.0/ ak/k shutdown margin requirement.

3. The RHR system is in service with a volume equal to that of the

RCS to conservatively maximize the total system mass.


The analysis methodology is identical to that presented in Section

5.2 in that an initial total system mass is calculated and RCS

shrinkage mass increments are calculated based on temperature

increments during the cooldown. The shrinkage mass is then

converted to a makeup water volume that, when added to maintain a

constant pressurizer level, will add incremental amounts of boron.

Changes in total system mass and boric acid content are then broughttogether to determine the resulting RCS boron concentration at each

increment. This process is summarized below:

The exact system volume used in the calculation is determined as:

2 x (RCS volume) + (PZR volume at Oh power),

or

2(8015 ft ) + (520 ft ) = 16,550 ft

Knowing the initial mass of boron in the system, the exact

concentration and makeup requirements can be calculated for discretetemperature increments.

Shrinkage Mass (RCS and RHR Volume) (1/vf - 1/v,.)

Makeup Water Volume = (Shrinkage Mass) / (8.2498 ibm/gallon) (10)

Boric Acid Added = (Water Vol.) x (0.21153 ibm/gallon) (11)

Total Boric Acid (Initial Boric Acid) + (Boric Acid Added)

Total System Mass

Final Concentration =

(Total Initial Mass) + (Shrinkage Mass) +

(Boric Acid Added)

Total Boric Acid 100 1748.34 '12)(Total System Mass)

(10)(11)(12)

Water density at 120'F. (Reference 10. 13)See Appendix 3 for values of dissolved boric acid in water.See Appendix 4 for the conversion factor between wt.% and ppm.


Only one of two possible boration flow paths and borated water

sources need be available at any given time while in Mode 5 (i.e.,either the boric acid tank or the refueling water storage tank). A

minimum volume and concentration must be specified for each,

therefore, to ensure that either one can be used for the cooldown

and still maintain adequate shutdown margin per the requirements ofTable 5. 1-6. Two separate calculations were performed as discussed

below.

5.3.2. 1 Mode 5 Cooldown with Boric Acid Tank

This analysis starts with an initial boron concentration of 730.70

ppm corresponding to the minimum requirement for a xenon free core

(see Table 5. 1-1), In order to calculate the initial total system

mass, the contribution of the boric acid must be calculated.

From Equation 2.0 of Appendix 3 and the conversion factor that isderived in Appendix 4, the initial boric acid mass in the system can

be calculated as follows:

788.2 m x~

16 030 ft + 520 ft3 3

1748.34 m wt.% 0.01664 ft ibm~ ~0.016719 ftlb'a

100 - (788.2 ppm)/(1748.34 ppm/wt.%)

or

mb= 4503.5 ibm boric acid

ba

The initial total system mass is then obtained as follows:

TSM = (Boric Acid Mass). + (System Water Mass). + (PZR Water Mass).

= 4503.5 ibm + (16,030 ft / 0.01664 ft /ibm) +

(520 ft / 0.016791 ft /ibm)

= 998,947.2 lb01

(13) Specific volume of compressed water at 200'F and 14.7 psia(14) Specific volume of saturated water at 14.7 psia


The incremental changes in the total system mass and the resultingchanges in boron concentration are accounted for during each

discrete temperature change during the cooldown as discussed

previously.

5.3.2.2 Mode 5 Cooldown with Refueling Water Storage Tank

The refueling water storage tank will not provide enough boric acidto compensate for the reactivity inserted during the cooldown ifcharging is restricted to makeup for coolant contraction only. A

system feed and bleed must be performed to raise the RCS

concentration before the cooldown is commenced. The initial feed

and bleed ensures that the actual RCS boron concentration ismaintained above the required boron concentration for a 1.0% ak/kshutdown margin while the plant is cooled from 200'F to 135'F.

The endpoint RCS boron concentration for the initial feed and bleed

is determined through an iterative process. This process identifiesthe cooldown starting concentration that results in an acceptable

final concentration when boron addition is accomplished only through

makeup for coolant contraction. The acceptable final concentration

was chosen to coincide with the shutdown margin limit for the low

end of the cooldown (135'F)

In order to identify the required time and volume to complete the

initial system feed and bleed, Equation 9.0 of Appendix 1 is used

with values as follows:

C 788.2 ppm0

Cin = 1950 ppm


16 030 ft 0.01664 ft ibm + 520 ft 0.016719 fl ibm

60 gallons „ 8.2498~ ~ lb(smin gallon

T 2009 min.

C(t) C e + C,.n(l-e )

If one charging pump at 69 gpm and 60 gpm letdown (as assumed incalculating the value of T above) are used to conduct the system

feed and bleed, 47 minutes are required. 'his equates to a feed and

bleed volume of 3235 gallons.

From Equation 2.0 of Appendix 3 and the conversion factor derived inAppendix 4, the mass of boric acid in the system corresponding to a

concentration of 805. 1 ppm can be calculated as follows:

CH„

ba 100 - C

(~81 5

1748.34

(~81 51748.34 ppm/wt%

m 16030 ft 520 ftm wt% 0.01664 ft ibm 0.016719 fX ibm

= 4657.4 ibm boric acid

Knowing the mass of boric acid in the system following the feed and

bleed, the exact concentrations and makeup requirements can be

calculated for each 10 degrees of cooldown from 200'F to 135'F in

the same manner as described in Section 5.3.2.

(15)(16)(17)

Specific volume of compressed water at 200'F and 14.7 psiaSpecific volume of saturated water at 14.7 psiaDensity of water at 120'F (Reference 10. 13)

Report No. 849963-UPS-5HISC-003 REV 0 Page 5-33

5.3.3 Results

The results of these analyses are presented in Tables 5.3-2 and

5.3-3 The resulting minimum volume requirements for the boric acid

tank and the refueling water storage tank for Nodes 5 and 6 are

summarized in Table 5.3-4

The delivered boron vs. required boron concentration is shown

graphically in Figures 5.3-1 and 5.3-2. The initial feed and bleed

of the refueling water storage tank case is shown by the verticalline at the origin in Figure 5.3-2.


Table 5.3-1


Cooldown From 200'F to 135'F

(Mode 5 to 6)

Parameter Value

RCS Volume

Pressurizer Volume (0/ Power Level)

Initial RCS Pressure

Final RCS Pressure

Initial RCS Temperature

Final RCS Temperature

Pressurizer ConditionPressurizer Level

RCS Leakage

Initial RCS Boron Concentration

Initial Pressurizer Boron Concentration

RHR Volume

RHR Boron Concentration

Letdown AvailableRefueling Water Stot age Tank Temperature

Boric Acid Tank Temperature

Total System Volume

8015 ft520 ft14.7 psia14.7 psia200'F

135'F

Saturated

Constant

0

788 ppm

788 ppm

8015 ft ( )

[= RCS)(')

(3)120'F

120'F

16550 ft

(1)(2)(3)

Overestimated for conservatismUnderestimated for conservatismNo letdown assumed fo} boric acid tank analysis. Letdown is assumedfor RWST analysis.


TABLE 5.3-2PLANT COOLOONN FROH 200 F to 135 F - BAT AT 3.0 Nt. X BORIC ACID AT 120 F

I AVG.SYS. TEHP.

(F)Ti Tf

PZR PRESS SPECIFIC VOLUHE SHRINKAGE BAT VOL 9

(psia) (cu.f t./Ibm) HASS(ibm) 120 F (gal)Vi Vf

B/A ADDED TOTAL 8/A TOTAL SYS ~ HASS FINAL CONC.

( ibm) ( ibm) (ibm) (ppm boron) )

I

I

200 200200 190

190 180

180 170

170 160

160 150

150 140

140 135

14.7 0.01664 0.0166414.7 0.01664 0.0165714.7 0.01657 0.0165114.7 0.01651 0.01645'14.7 0.01645 0.0163914.7 0.01639 0.0163414.7 0.01634 0.0162914.7 0.01629 0.01627

0.04,069.63,515.73,541.43,567.32,992.83,011.11,209.6

0.0493.3426.2429.3432.4362.8365.0146.6

0.0125.9108.7109.5110.392.693.137.4

4,503.74,629.64,738.34,847.84,958.25,050.75, 143.85,181.3

998,945.51,003,141 ~ 0

1,006,765.51,010,416.41,014,094.01,017,179.31,020,283.61,021,530.7

7882 I

806.9 [

822.8 f838.8

J

854.8 I868.1881.4 /

886.8 [

TOTAL BAT VOLUHE= 2,655.5 gallons

TABLE 5.3-3PLANT COOLDOHH FRY 200 F TO 135 F - RHST AT 1950ppm BORON AT 120 F

IAVG.SYS. TEHP

(F)Ti Tf

200 200200 190190 180

180 170

170 160

160 150

150 140

140 135

815.4 I820 0 I824 0 I828.0 I832.0 (

835.3 )

838.7 )

840.0 /

4,659.54,705.44,745 '4,785.04,825.24,859.04,893.04,906.6

0.0493.3426.2429.3432.4362.8365.0146.6

0.045.939.739.940.233.834.013.6

0.04,069.63,515.73,541.43,567.32,992.83,011.11,209.6

999,101.31,003,216.91,006,772.21,010,353.61,013,961 F 1

1,016,987.61,020,032.71,021,256.0

14.7 0.01664 0.0166414.7 0.01664 0.0165714.7 0.01657 0.0165114.7 0.01651 0.0164514.7 0.01645 0.0163914.7 0.01639 0.0163414.7 0.01634 0.0162914.7 0.01629 0.01627

PZR PRESS SPECIFIC VOLUHE SHRINKAGE RllST VOL 9 B/A ADDED TOTAL B/A TOTAL SYS. HASS FINAL CONC.

(psia) (cu.ft./ibm) HASS(ibm) 120 F (gal) (ibm) (lbm) (lbm) (ppm boron) ]Vi Vf I

I

)FEED 8 BLEED VOLUHE (788ppm to 815ppm) =

]RllST VOLUHE FOR COOLDOOI COHTRACTIOH

I

)TOTAL REQUIRED RWST VOLUHE =

3,260.0 gallons (44 minutes at 69 gpm)2,655.5 gallons

5,915 ' gallons

Table 5.3-4

Minimum Borated Water Source Volumes

(Mode 5)

Boric Acid Tank:

(z 3.0 wt/.)

2,900 gallons

Refueling Water Storage Tank:

(a 1950 ppm)

10,000 Gallons( )

(1)

(2)

Includes analysis value plus 212 gallons for level instrumentinaccuracy (2.5/. of full range) rounded up to nearest 100 gallons.Includes analysis value plus 2% instrument error and approximately3600 gallons unusable volume below the suction tap, all rounded upto nearest 1000 gallons


890

Figure 5.3 —1 RCS Boron ConcentrationEquillbrlum EOC, Mode 5 Cooldoen

880

870

860

850

830

820

810

790

780200 190

0 Required

180 170 160

Temperature(oeg F)+ Deltv~(S.O wry)

150

Figure 5.3 —2 RCS Boron ConcentrationEquilibrium EOC, Mode 5 Cooldown

830

820

810

800

790

780200

0 Required

180 160

Temperature(Oeg F)+ Delivered(RWST 1950ppm)

. 6.0 OPERATIONS ANALYSES

Section 5.0 presented the design basis analyses for the boric acidconcentration reduction program to support the licensing effortsrequired to fully implement it. A worst case (slow) cooldown tocold shutdown conditions was analyzed to establish the requiredboric acid tank concentration and volume limits to enable operatorcontrol of a challenging reactivity control scenario: borationduring cooldown without the benefit of letdown. A reduction inboric acid concentration will have other effects on plantoperations. This section presents the results of a detailedevaluation of plant operations with reduced concentration boric acidto identify these effects. The specific areas that will be

discussed include blended makeup, feed and bleed, shutdown to coldshutdown, shutdown to refueling and operator response to emergency

situations. Obviously it is an impossible task to evaluate each ofthese five areas and consider all possible combinations of plantconditions. Therefore, initial plant parameters and analyses

assumptions were selected in a conservative manner to present a

worst case analysis.

A number of options exists as to how the three boric acid tanks can

be aligned to provide the required minimum volume for both plantsand to provide operational flexibility in meeting day-to-day

boration demands. Considering the volumes required per Table 5.2-5,

most, if not all, of the operating margin will have to come from the

spare tank. One possible tank configuration is to align all three

tanks to the suctions of all four pumps to utilize the tanks as a

common source. In this manner all three tanks will stay at the same

level with the minimum required volume for both units spread across

all three tanks. This arrangement offers the following advantages:

1. Haximizes volume available for day-to-day boration demands;

Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-1

2. Offers lower risk of going below technical specificationminimum volume;

3. Offers redundant level indication; and,

4. No manual valve manipulations required to access all availablevolumes.

Another option is for one tank to be dedicated to each unit with theshared tank serving as the source of makeup for both units on a

day-to-day basis. The discussions in this section apply to eitherof these options.

Figure 6-1 presents a flow diagram of the Turkey Point CVCS

extracted from Reference 10. 1. Four flow paths to the charging pump

suction will be considered in the evaluation:

2.

3.

4,

Volume Control Tank (VCT)

Normal Boration (Blended or Hanual)

Emergency BorationRefueling Water Storage Tank

Charging pump discharge will go one of two places: into the RCS orback to the VCT via the reactor coolant pump seal leakoff line. The

flow back to the VCT is important to note because it is not

available for charging, into the plant in those instances when the

VCT is isolated (isolation valve closed or check valve seated) from

the charging pump suction. In this instance, the seal leakoff would

collect in the VCT until, upon high level, it is directed to the

holdup tank via the VCT pressure relief valve. Under normal

conditions with appropriate charging pump speed selection, however,

this seal leakage (nominally 9 gpm) can be expected to recycle back

to the charging pump suction so that it will not constitute a loss.In the calculation of volumes required for blended makeup and feed

and bleed operations, the 9 gpm is assumed to be lost to

Report No. 849963-HPS-5HISC-003 Rev. 0 Page 6-2

conservatively overestimate the volumes required to support the

evolutions under consideration.

Table 6-1 presents the plant parameters used in the analysis of thissection. In general, these parameters differ from those of the

licensing analyses of Section 5.0 in that they are based on normal

plant operations and are chosen to provide a realistic best estimateof plant boration performance while still remaining conservative. A

few of the more important assumptions are discussed below.

1. Pressurizer Volume

Pressurizer volume is assumed to remain constant at the OX

power level (i.e., operators charge to the plant to maintain

pressurizer level) during the cooldown- scenarios analyzed.

2. RCS Leakage

As in Section 5.0, RCS leakage is assumed to be zero since

leakage aids boron delivery to the plant. However, it does

require greater makeup volumes, so that leakage assumptions

should be applied to final results. This can be accomplished

by multiplying an assumed leakage rate by an estimated time forcompletion of the cooldown evolution. This volume is then

added to the contraction makeup volume to derive the totalrequired volume. A more specific analysis of the impact of RCS

leakage on the boric acid inventory requirements is presented

in Section 6.7

3. RHR Volume and Concentration

The concentration is assumed to be at the cold shutdown, 200'F,

xenon free 1.77X ak/k shutdown margin concentration of 775 ppm

(equilibrium xenon scenario per Section 5.5). RHR

concentration is expected to be near, if not equal to, the cold


shutdown boron concentration since shutdown margins must be

maint'ained during a Mode 4 heat up for a transition into Mode

3. RHR concentrations resulting from mid-cycle shutdown, forexample, should be close to the appropriate shutdown marginrequirement. Also, to conservatively estimate the contractionmakeup contribution of this system, a volume of 2000 ft isassumed for the RHR system flow paths.

4. Boric Acid Tank Concentration

Section 5 ' justified a concentration range of 3.0 to 3.5weight percent boric acid to support a safe shutdown to coldshutdown conditions. This will result in a plant technicalspecification boric acid tank operability requirement statingminimum acceptable volumes for this concentration range. It isrecommended that plant operations maintain the concentration inthe middle of the control band. For this reason, theconcentration of 3.25 weight percent will be utilized in theoperations analyses of this section.

5. Cooldown Starting Temperature

The analysis of this section assumes the cooldown initiatesfrom the hot zero power value of 547'F.

The following sections review specific plant operations with reduced

boric acid concentration.

6.1 BLENDED MAKEUP OPERATIONS

During typical plant blended makeup operations, concentrated boricacid from the boric acid tanks is supplied to the blending tee via a

boric acid transfer pump (0 to 60 gpm) and flow control valveFCV-113A (0 to 10 gpm) where it is mixed with pure makeup water

supplied via flow control valve FCV-114A (0 to 150 gpm). The


blended boric acid is then added to the suction of the charging

pumps via flow control valve FCV-1138.

A reduction in the concentration of boric acid in the boric acidtank will decrease the maximum boron concentration available at theoutlet of the blending tee by a factor directly proportional to thedecrease in the boric acid tank concentration. This results in a

decrease in the boron delivery capability of the blending tee duringnormal RCS makeup and reactivity control operations.

This impact, however, can be compensated for by increasing the boricacid delivery rate to the blending tee. A corresponding decrease inthe pure makeup water into the tee will raise the concentration ofthe boric acid mix to levels corresponding to the current boration

capability of the system using 12 weight percent boric acid. This

will be achievable with the modification that is currently planned

for flow control valve FCV-113A. The trim of this valve will be

modified to allow higher flow rates of the reduced concentrationboric acid. Specifically, since a factor of four reduction in the

boric acid concentration is anticipated (12 weight percent to 3

weight percent) a factor of four increase in boric acid flow to the

boric acid blender will be required. In other words, the trim ofFCV-113A must be modified to allow up to 40 gpm. This would assure

the blended boration capability remained identical to the current

system configuration with 12 weight percent boric acid with respect

to the timing of boron delivery.

With this flow control valve upgrade in mind, all further analyses

of the blended makeup capability (i.e., during fast cooldowns) willassume that 40 gpm will be available to the blender.

Hathematically, blended makeup operations are modeled as follows:

F C

Co t (100)(1748'34)a a t w

Report No. 849963-HPS-5MISC-003 Rev. 0 Page 6-5

where:

Co ut c o n c e ntra t i o n of b or i c a c id e x i t i n g th e b 1 e n d i n g te e

F = flow rate of concentrated boric acid from the boric acida

tank

C = concentration of boric acid entering the blending teea

FT - total flow rate exiting the blending tee

D = density of makeup water (assumed at 120'F)

1748.34 = conversion factor for weight percent to ppm

6.2 FEED AND BL'EED OPERATIONS

During a feed and bleed operation to increase system boron content,the charging pumps are used to inject concentrated boric acid intothe RCS with the excess inventory normally being diverted to the

liquid waste system via letdown. The rate of increase in boron

concentration is proportional to the difference between the system

concentration at any given time and the concentration of the

charging fluid. From this basic relationship, an equation

describing feed and bleed can be derived. (Appendix 1 contains the

derivation of the RCS feed and bleed equation.) In general, if the

concentration within the boric acid tanks is reduced to the pointwhere heat tracing is no longer required, the maximum rate of change

of RCS boron concentration that an operator can expect to see duringfeed and bleed will be less than currently achievable.

The purpose of the evaluation performed in this section is to show

the hot zero power feed and bleed rates that can be expected using

boric acid tanks with a reduced concentration. The analysis is done

Report No. 849963-HPS-SHISC-003 Rev. 0 Page 6-6

assuming hot zero power conditions with other key parameters and

conditions as shown in Table 6-1. A one charging pump feed and

bleed was evaluated from two initial system concentrations: zero

ppm and 1100 ppm. The results are presented in Tables 6-2 to 6-5.

Equation 9.0 of Appendix 1 was used to generate the results in these

tables. The value of the system mass used to obtain the timeconstant in Equation 9.0 was calculated as follows:

w RCS w RCS w PZR

or

8015 ft 520 ft0.021251 ft. /ibm 0.02698 ft /ibm

From this system mass (396,432.3 ibm), the value of the feed and

bleed time constant for one charging pump using the 45 gpm letdown

orifice is:

396,432.3 ibm

45 gpm x 8.2498 ibm/gallon

or

T45= 1,067.9 min.

The value of the feed and bleed time constant for one charging pump

using the 60 gpm letdown orifice is:

396,432.3 ibm

60 gpm x 8.2498 ibm/gallon

or

T60 800 ~ 9 mi n ~

(2)(3)

Specific volume of compressed water at 547'F and 2250 psia (assumingHZP).Specific volume of saturated water at 2250 psia (assuming HZP).Water density at 120'F.

Report No. 849963-NPS-5MISC-003 Rev. 0 Page 6-7

For the case where a feed and bleed is conducted while the RHR

system is in operation, a new time constant will result. Using theequation above and substituting the RHR + RCS water mass for the RCS

water mass, the following result is obtained for a 60 gpm feed andbleed at 200'F:

System Massw RCS ( w RHR w PZR

10015 ft 520 ft.01662 ft /ibm .01912 ft /ibm

= 629,783.9 ibm

629 783.9 ibm60 60 gpm x 8.2498 ibm/gallon

Tables 6-2 through 6-5 include the expected boric acid volume to

accomplish the given boration. Two values are presented: one

assuming no loss due to RCP seal leakage (45 gpm and 60 gpm) and the

other assuming the 9 gpm nominal seal leakoff is collected in the

VCT so that it does not immediately contribute to the desired

boration (54 gpm and 69 gpm).

To identify specific changes in boron content through feed and bleed

operations, the values in these tables can be used (interpolated) to

provide reasonable estimates. Analytically, the time to achieve a

specific change in boron content can be calculated as follows.

Appendix 1 presents boron concentration as a function of time as:

C = C/ + C. (1 - e /

)f o in

where:

CfC

0

inT

final system boron concentration

initial system concentration

concentration of feed source

feed and bleed time constant

time

(4) Specific volume compressed water at 200'F and 350 psia(5) Specific volume saturated water at 350 psia


Solving this equation for time yields:

f inn

C -C.o in

Feed and bleed operations will be incorporated into some of the

operations scenarios discussed in later sections utilizing Tables

6-2 through 6-5 and the equations above.

6.3 COOLDOWN TO REFUELING - MODE 6

The plant cooldown to refueling is typically the most limitingevolution that an operator must perform with respect to system

boration (ice., this evolution normally requires the maximum amount

of boron to be added to the RCS). A cooldown to refueling normally

occurs at the end of core cycle when the critical boron

concentration is low and requires an increase to the refueling boron

concentration. In the most limiting case, boron concentration must

be raised from zero ppm to the specified refueling concentration of1950 ppm (2000 ppm).

This section presents the evaluation results of a plant shutdown to

refueling. The evaluation was performed specifically to demonstrate

the effect on makeup inventory requirements of a reduction in boric

acid storage tank concentration. A list of key parameters and

conditions assumed in the analysis is contained in Table 6-1. The

evaluation was performed for EOC conditions in order to maximize the

amount of boron that must be added to the RCS. As a result, the

boron concentration within the RCS was required to be increased from

zero ppm to the present refueling concentration of 1950 ppm. The

shutdown for refueling was assumed to take place as follows:

1. The reactor is shut down via rod insertion to hot zero power

conditions.


2. Following shutdown, at time zero, operators commence a system

feed and bleed using one or more charging pumps and a boricacid transfer pump. (Tables 6-2 through 6-5 show the expectedfeed and bleed volumes and times to complete for variousblended concentrations.)

3. The feed and bleed is conducted for about 180 minutes assuming

60 gpm letdown, after which time it is secured.

4. A plant cooldown and depressurization is commenced from an

average coolant temperature and system pressure of 547'F and

2250 psia to an average coolant temperature and system pressureof 350'F and 465 psia. Unblended boric acid is supplied from

the boric acid tanks.

5. The RHR system is placed in operation at approximately 350'F

and 465 psia.

6. The plant cooldown is continued following RHR initiation from350'F to 135'F at 465 psia.

Evaluation results showing the system concentrations as a functionof time and total boric acid tank inventory requirements are

contained in Table 6-6. Concentrations during the initial feed and

bleed operation were calculated using the methodology discussed inSection 6.2 above. Concentrations during the subsequent plantcooldown were calculated in the same manner as the concentrationsfor the plant cooldowns in Section 5.2. Note that the boron content

of the RCS was raised from zero ppm at the start of the evolution to

greater than 1950 ppm by the time the plant had been cooled and

depressurized to 135'F and 465 psia. A total volume of 27, 188.8

gallons of a 3.25 weight percent boric acid solution was required.Of this volume, 10,800 gallons were used during the initial 180

minute plant feed and bleed operation and 16,388.8 gallons were

charged into the system to compensate for shrinkage during the

cooldown process.

Report No. 849963-HPS-5NISC-003 Rev. 0 Page 6-10

As can be seen from the results in Table 6-6, the volume of a 3.25

weight percent boric acid solution required to perform the shutdown

to refueling is approximately 3.6 times the current capacity of one

boric acid tank (7500 gallons). A plant modification is planned,however, that will increase the capacity of the tank. Assuming

approximately 8500 gallons will be available, the volume requiredfor this evolution will be 3.2 times available capacity. Note thatthis result is conservative, and, therefore, represents the maximum

volume that would be required to be available assuming a refuelingconcentration of 1950 ppm boron and a boric acid tank concentrationof 3.25 weight percent boric acid. Since there is essentially onlyone boric acid tank dedicated to each plant and a third tank shared

between the two plants, additional provisions or operator actionscould be utilized to place the plant in Mode 6. These provisionscould include some combination of the following:

1. Prior to conducting the evolution, all three boric acid tanks

are full and available for use (minus the volume dedicated tothe operating unit).

2. Concurrent with continued cooldown, replenish inventory in the

tanks.

3. Borate as much of the RHR system as possible to the refuelingconcentration of 1950 ppm prior to initiating'he RHR system

cooldown at 350'F.

These provisions, or operator actions, would need to be considered

only once during core cycle: just prior to conducting a shutdown

for refueling. Note that they are relatively simple actions thatshould be well within the current plant operating capabilities. In

addition, they can be planned for in advance so as to have no impact

on maintenance activities or the plant refueling schedule.

Report No. 849963-NPS-5HISC-003 Rev. 0 Page 6-11

6.4 COOLDOWN TO COLD SHUTDOWN — MODE 5

As discussed in the previous section, the shutdown to refueling isthe most limiting evolution that an operator must perform withrespect to system boration from the perspective of available boricacid inventory. This evolution is normally performed once during a

fuel cycle just prior to refueling. Situations (such as unscheduled

plant maintenance, etc.) can occur during a fuel cycle, however,

that would require an operator to perform a plant shutdown to coldshutdown conditions. Although not limiting with respect to borationrequirements, it is important for an operator to be able to performsuch a shutdown quickly and efficiently.

This section presents the evaluation results of a plant shutdown and

cooldown to cold shutdown conditions using only the boric acidtanks. This analysis was performed specifically to demonstrate theeffect of a reduction in boric acid tank concentration on makeup

inventory requirements . A list of key parameters and conditionsassumed in the analysis is contained in Table 6-1. In addition tothe parameters in Table 6-1, the evaluation was performed for EOC

conditions assuming a cold shutdown concentration requirement of 775

ppm boron. As a result, boron concentration had to be increased

from 0 ppm to 775 ppm boron. The operations scenario employed inthe cooldown to cold shutdown is as follows:

l. The reactor is shut down to hot zero power conditions via rod

insertion.

2. A plant cooldown and depressurization is immediately commenced

from an average coolant temperature and system pressure of547'F and 2250 psia to 350 F and 465 psia. Makeup inventory issupplied from the boric acid tanks.

3. The RHR system is placed in operation at 350 F and 465 psia.


4. The plant cooldown is continued following RHR initiation from350'F to 135'F at 465 psia. Makeup inventory is supplied from

the boric acid tanks.

Evaluation results showing the system concentrations as a function=

of time and total boric acid makeup tank inventory requirements are

contained in Tables 6-7 and 6-8. Note that two cases were analyzed

for comparison. In Case 1 the concentration within the RHR system

was assumed to be equal to the concentration of the RCS at the time

of RHR system initiation. In Case 2 the concentration within theRHR system was assumed to be equal to 775 ppm (the maximum 200'F,

xenon free, required boron concentration) at the time of RHR

initiation. Concentrations during the plant cooldown were

calculated using the methodology discussed in Section 5.2. Ouring

those portions of the plant cooldown in which blended makeup was

used, values were calculated using the methodology contained inSection 6. 1.

A total volume of 9,246.0 gallons of a 3.25 weight percent boricacid solution was required in order to perform the shutdown to coldshutdown for Case 1. In Case 2, a total volume of 9,033.6 gallonswas required.

6.5 BATCHING OPERATIONS

As the results of Sections 6.3 and 6.4 demonstrate, more than one

boric acid tank will be required to complete these cooldown and

boration evolutions. This section will evaluate the expected

batching process and how this will impact the overall timing of the

cooldown.

The Turkey Point batching system consists of an 800 gallon batching

tank that is blended to the desired concentration and added to the

boric acid tank via a boric acid transfer pump. The batching

process consists of the following (with time estimates):


1. Fill the batching tank with pure water and increase the water

temperature from 40'F to 90'F (45 minutes).

2. Add the required quantity of boric acid and mix the tankcontents (20 minutes).

3. Transfer boric acid mixture to boric acid tank (20 minutes).

4. Repeat as necessary

The total time to prepare a single 800 gallon batch, therefore, isestimated to take about 1.5 hours. Given that the batching can be

accomplished in only 800 gallon increments, it will take

approximately 10 batches (or 15 hours) to refill a boric acid tank.The availability of a third tank that is shared between the two

units suggests the possibility of using a second tank for one unitwhile the first tank is refilled. For the case where all threetanks are aligned to the transfer pumps and are full to maximum

capacity, however, a total of about 16,000 gallons[(8500x3)-2900-6600] would be available to accommodate a unitshutdown and cooldown without operator action to realign the tanks.

Looking at the results of Section 6.3, the shutdown and cooldown torefueling required a total boric acid tank volume of 27, 188.8

gallons. Assuming the tanks were at the minimum volume for 3.25

weight percent to support two operating units (13,200 gallons)leaving 6,600 gallons to support the shutdown and cooldown, a totalof 20,588 gallons would have to be provided through batching. Ifbatched, this would require about 26 batches for a total of 39

hours. However, if the tanks are full and shared, or at leastfilled prior to initiating the shutdown to refueling evolution, only

11, 188 gallons would have to be batched. This would require 14

batches for a total of 21 hours.

The shutdown to cold shutdown conditions of Section 6.4 required a

total of 9,246.0 gallons. Again, assuming 6,600 gallons in the tank

at the start of the cooldown a total of 2,646 gallons must be


provided from the spare tank or batched. If batched, approximately3.5 batches would be required which would take 5 hours at 1.5 hours

per batch. If the tanks are kept full, however, this evolutionwould require no batching to complete.

The shutdown/cooldown evolutions analyzed thus far have assumed

boration in conjunction with cooldown as analyzed in Section 5.0.This will not be a requirement for normal cooldown evolutions.In some instances FPL may have to conduct these evolutions inessentially. the same manner as they are conducted now (i.e., borate

the plant to the required cold shutdown concentration through feed

and bleed prior to initiating the cooldown, and provide blended

makeup for the coolant contraction).

This evolution is illustrated in Table 6-9 for a 50 F/hr cooldown.

The feed and bleed process can be completed from either the boricacid tank or the refueling water storage tank. For the case where

the boric acid tank alone is utilized, a total of 10,573.2 gallonswill be required. Assuming 6,600 gallons were available, a total of3,973.2 gallons would have to be provided through the batch process

or the spare boric acid tank. At 800 gallons and 1.5 hours a batch,

a total of 5 batches would be required taking approximately 7.5

hours. If the tanks are kept full, however, this evolution would

not require any batching to complete.

6.6 RESPONSE TO EMERGENCY SITUATIONS

This section evaluates several of the operating evolutions that may

have to be completed in response to a variety of emergency

situations. Specifically, accident boration requirements, shutdown

margin recovery, emergency boration, and fast cooldown scenarios

will be evaluated to ensure the operator can continue to operate the

plant safely with reduced boric acid tank concentrations.


6.6. 1 Accident Response

In general, credit is not taken for boron addition to the RCS from

the boric acid tanks for the purpose of reactivity control in theaccidents analyzed in Chapter 14 of the plants'inal SafetyAnalysis Report. The consequences of such events as steam linebreak, overcooling, boron dilution, etc. will not be affected by a

reduction in boric acid tank concentration. Any action to borate

the plant from the boric acid tank will likely improve the

reactivity control margins over those already analyzed and found

acceptable in the safety analysis report.

6.6.2 Shutdown Hargin Recovery

The action statements associated with Technical Specifications3. l. 1. 1, 3. 1. 1.2, 3.9. 1, and 3. 10. 1 require that boration be

commenced at greater than 4 gpm using a solution of at least 20,000

ppm boron in the event that shutdown margin is lost. A reduction inboric acid concentration by a factor of four will require a corres-

ponding increase in delivery capacity to ensure the same amount ofboron is added in the same period of time. Such a deliverycapability will be available with the proposed modification of the

blended makeup flow control valve so that this reactivity control

recovery capability remains unaffected. Specifically, the flow

control valve FCV-113A will be modified to increase its control

range from 0 — 10 gpm to 0 — 40 gpm. The availability of a 40 gpm

flow of boric acid to the blender exceeds the requirement for a fourtimes increase of 4 gpm to 16 gpm in this instance.

6.6.3 Emergency Boration

An emergency boration flow path is available from the discharge ofthe boric acid transfer pump directly to the suction of the charging

pumps via motor operated valve HOV-350. In the event that a reactor

shutdown to hot zero power is required and control rods are not

available (i.e., two or more rods stuck out), an alternate shutdown


capability exists through emergency boration. According to

Reference 10.3, the CVCS (with 12 weight 'percent boric acid) iscurrently capable of making the reactor subcritical in 16 minutes

assuming 60 gpm through the emergency boration flow path to the

charging pumps.

According to Reference 10. 12, emergency boration is achieved by

charging 537 gallons via the emergency boration flow path (withoutletdown —taking advantage of the surge volume available in the

pressurizer) and raising the boron concentration by 195 ppm. This

is stated as requiring 9 minutes at 60 gpm. The effect of reduced

concentration boric acid on this capability is evaluated below.

Analysis of the method of achieving emergency boration by charging

pressurizer level up, without letdown, requires a mass balance ofboron. Assuming a conservatively high BOC boron concentration of1100 ppm, the mass of boric acid required to increase thisconcentration by 195 ppm is calculated. This boric acid mass

addition is equated to the boric acid mass per gallon of makeup

water using the values of Appendix 3. Then this volume of makeup

water is converted to a volume of water at RCS temperature to

compare to the available volume in the pressurizer.

For a conservative analysis of the above, the following is assumed:

l. Boric Acid Tank Temperature

2. Boric Acid Tank Concentration

3. Transfer Pump Delivery4. RCP Seal Injection5. RCP Seal Leakoff

6. VCT Isolated7. Initial RCS Concentration

8. Boration Required

9. RCS Temperature10. Mixing within RCS and Pressurizer

ll. Pressurizer Steam Bubble

120'F

3.0 wtX

69 gpm

24 gpm

9 gpm

(-9 gpm)

1100 ppm

195 ppm

547'F

Uniform

Available

Report No. 849963-MPS-5HISC-003 Rev. 0 Page 6-17

The results of this calculation show that approximately 2024 gallonsof water at 3.0 weight percent boric acid will be required from theboric acid tank and will result in a pressurizer level change wellwithin the available volume when level is initially within the levelcontrol band. At 69 gpm, this will achieve a 195 ppm increase inRCS boron concentration within 29.4 minutes. This volume reduces to1760 gallons if 9 gpm seal leakoff is not a factor. This equates toapproximately 300 cubic feet in the pressurizer which corresponds tothe change from the OX Power programmed level to the lOOX Power

programmed level.

A second option consists of conducting a system feed and bleed toaccomplish the boration objective. Using the method of Section 6.2,approximately 2,670 gallons of 3.0 weight percent boric acid will be

required. At 69 gpm (60 gpm letdown), this will achieve a 195 ppm

increase in RCS boron concentration within 38.7 minutes.

6.6.4 Fast Cooldown Transients

Section 5.0 focused on slow cooldown evolutions since they presented

the worst case boration requirement in compensating for a greateramount of xenon decay. Faster cooldowns are important from a

boration perspective when the limited capacities of the normal

boration flow path (currently limited to 10 gpm boric acid) and the

emergency boration flow path (nominally 60 gpm) are consider ed,

especially when the preferred boration flow path will likely be the

lower capacity normal flow path (manual or blended boration). As

discussed previously, however, it is anticipated that flow controlvalve FCV-113A will be modified to increase its capacity from 10 gpm

to about 40 gpm. This will increase the flow rate. of reduced

concentration boric acid to the point where the boron addition ratethrough the normal boration flow path matches that of the currentsystem configuration with 12 weight percent boric acid. The

remaining consideration, therefore, is the limited volume availableto provide the total boron requirement.

Report No. 849963-UPS-SMISC-003 Rev. 0 Page 6-18

Two specific cases are presented here: 1) makeup with the boricacid tank, and 2) makeup with the refueling water storage tank. The

first case considers a fast cooldown (100'F/hr) for which the normal

process of borating to the cold shutdown limit prior to initiatingthe cooldown has been completed. This case will evaluate thecapability of the boration subsystem to maintain this boron

concentration during the cooldown while blending the boric acid withpure water. This particular evaluation uses the same assumptionsand methodology as discussed in Section 6.4. The results are

presented in Table 6-10.

As shown in Table 6-10, a total boric acid volume of 10,323.4gallons would be required. Of this, 8, 122.7 gallons would be

required to accomplish the feed and bleed from 0 ppm to 775 ppm in117.7 minutes (assuming 69 gpm charging flow and 60 gpm letdown).The remaining volume of 2,200.7 gallons would be required to make up

for coolant contraction. The blend ratio of 6.5 throughout thetransient ensures just enough boric acid is used to maintain the RCS

concentration. fven with the addition of 9 gpm seal leakoff(assumed unavailable for makeup), the required boric acid flow rate(<15 gpm) remains less than the 40 gpm upper limit anticipated forflow control valve FCV-113A.

Under ideal conditions, such a feed and bleed and cooldown could be

accomplished using the available capacity of one full dedicated tankand a portion of the shared tank. Under less ideal conditions, the

minimum allowable volume of 6,600 gallons (Table 5.2-5) would be

available requiring 3,723.4 gallons to be provided by the shared

tank or batched. If batched, a total of 5 batches would be requiredfor a total time of about 7.5 hours.

A variation of the above is to conduct a limited feed and bleed (0

ppm to 446 ppm, for example) and complete the fast cooldown using

the refueling water storage tank as the source of makeup water.

Such an approach would minimize the amount of boric acid tank volume

required and, hence, the amount of batching potentially required.


The results of this evaluation are illustrated in Table 6-11.

Compared to Table 6-10, only 4,485.0 gallons of boric acid at 3.25weight percent would be required to complete the feed and bleed

(well within the required minimum volume of 6,600 gallons per Table5.2-5). The entire evolution could be completed with the refuelingwater storage tank alone using a total of 30,841.3 gallons of waterat 1950 ppm (exclusive of RCS leakage).

6.6.5 Technical Specification Action Statements

Recovery from loss of shutdown margin per the action statements ofTechnical Specifications 3. 1. 1. 1, 3. 1. 1.2, 3.9. 1 and 3. 10. 1 has been

discussed in Section 6.6.2. The purpose of this section is toreview the capability of the boration system to meet the actionrequirements of the remaining technical specifications with reduced

boric acid concentration.

Generally, the action statements of principal concern, with respectto boration capability, occur with Technical Specifications 3. 1.2.2(Flow Paths), 3. 1.2.3 (Charging Pumps), and 3. 1.2.5 (Borated Water

Sources). These action statements follow the sequence outlinedbelow.

2.

3.

Restore (flow path, pump, source) to operable status within 72

hours, orBe in hot standby borated to the shutdown margin for 1.0%%u sk/kat 200 F;

Restore the inoperable condition within an additional 72 hours,

or4. Be in cold shutdown within the next 30 hours.

If the two 72 hour periods are removed, the most limiting action

statement requirement is presented:

1. Be in hot standby, borated to 1.0X nk/k shutdown margin at200'F within 6 hours and,

2. Be in cold shutdown within the following 30 hours.


The timing of the above coincides with the more restrictive actionstatements of Technical Specifications 3. 1.3.5.b (RWST inoperable),3. 1.2.6 (boric acid tank and/or flow paths below specifiedtemperature limit for boric acid solubility), and 3.5.4 (RWST

inoperable). The above specifications do not specifically require-boration to the cold (200'F) shutdown margin of 1.0X a,k/k prior toinitiating the cooldown (within the first 6 hour action). However,

these actions will be assumed in this evaluation so that the actionsof the flow path, source, and charging pump specifications discussedpreviously, are bounded.

As an additional conservatism, the 1.77K sk/k shutdown margincoinciding with the EOC 0 ppm boron condition will be evaluated tomaximize the required boration. The analysis discussed in Section6.5, therefore, is applicable and bounding for the action statementsunder consideration.

The limiting component of the action requirement is the boration to775 ppm within 6 hours in that this action must be performed witheither, the boric acid tank or refueling water storage tank in theworst case. As shown in Table 6-9, a feed and bleed from 0 ppm to775 ppm will require 8, 122.7 gallons of 3.25 weight percent boricacid. Assuming a full boric acid tank (8, 126 gallons per Reference

10.4) is available and 9 gpm is lost to RCP seal leakoff to the VCT,

such a feed and bleed boration could be accomplished inapproximately two hours with 60 gpm letdown and 69 gpm via the

emergency boration flow path (or, more likely, 60 gpm emergency

boration and 9 gpm from the VCT). If, however, only the minimum

required boric acid inventory was available (6,600 gallons per Table

5.2-5), the feed and bleed would require 1522.7 gallons from the

spare tank or from a batching process. If batching is required, 2

batches would be needed, bringing the total time to 5 hours if theoperations were performed in series. If, instead, the batching

operations (if required) are performed in parallel with the feed and

bleed, this very conservative scenario will achieve boration (inexcess of that required) within the allotted time of 6 hours.

Report No. 849963-MPS-5HISC-003 Rev. 0 Page 6-21

The remaining cooldown to Mode 5 would require approximately 2,451

gallons for a 50 F/hr cooldown (Table 6-9). Assuming no availableboric acid at this point, approximately 3 batches (4.5 hours) would

be required to provide the necessary volume for boration at a 6.5blending ratio. Continued batching at 800 gallons every 1.5 hours

would provide the necessary makeup for 9 gpm RCS leakage. Periodicpump down of the VCT, as well, will provide additional leakage

makeup and added boration. Altogether, the 50'F/hr cooldown would

require approximately 7 hours of cooldown and 4.5 hours of initialbatching for a series total of 11.5 hours. This is well within the30 hour limit even with consideration of preparation time, RHR

lineup time, etc.

For the case where only the refueling water storage tank isavailable, the required actions have not been affected by a

reduction of the boric acid concentration in the boric acid tanks.No additional evaluation, therefore, is needed for this case.

6.7 IMPACT OF RCS LEAKAGE

Previous evaluations of the cooldown to cold shutdown conditionshave not included RCS leakage as discussed in Section 4.3 Item 4.

The impact of RCS leakage on total makeup inventory requirements can

be significant, however. Estimates of the total inventory require-ment can be made by assuming a constant leakage rate and multiplyingby an estimated time to complete the cooldown evolution. A 347'F

cooldown (547'F to 200'F), for example, completed at an effectivecooldown rate of 50 'F/hr with a constant leakage rate of 11 gpm,

would require a total of 4,580 gallons to replace the RCS leakage.

This volume added to the refueling water storage tank volumes ofTable 5.2-5 could possibly result in available refueling water

storage tank volumes going below the 320,000 gallon limitingcondition for operation for Modes 1 through 4.


Given the total capacity of the three boric acid tanks of about

25,500 gallons, as much as 16,000 gallons could be available to a

unit being shut down and cooled down (after subtracting the minimum

volume for one unit operation). Assuming the boric acid tanks are

maintained as full as possible (i.e., filled to capacity followingeach significant boric acid demand), most, if not all, of the RCS

contraction and leakage makeup can be provided by the boric acid

tanks and/or the pure water system (for blended makeup).

Table 6-12 illustrates a specific case where the effect of RCS

leakage is accounted for during a cooldown using the boric acidtanks for direct and blended makeup. A constant leakage rate isassumed. This is accounted for in .the analysis by adding the

leakage mass to the shrinkage mass term described in Section 5.2.The boron addition provided during the makeup for this new

"shrinkage mass" term is adjusted (decreased) to account for the

mass of boric acid lost with the leaking coolant. This adjustment

is made by taking the RCS boron mass fraction (concentration) times

the water mass that leaks out during each t'ime (temperature)increment.

As shown by Table 6-12, RCS leakage is accommodated during the

specified cooldown using a total of 7,484,7 gallons of boric acid

and 14,969.3 gallons of pure water. The blending ratio varies from

0 to 2. The blending ratio of 2 in this case corresponds to a

blended boric acid solution that is close to the concentration in

the RWST. In this example, therefore, blended boric acid makeup has

replaced the RWST makeup assumed in Section 5.2.

6.8 LONG TERM COOLING AND CONTAINMENT SUMP pH

The impact of the Boric Acid Reduction Effort on post-LOCA long term

cooling and containment sump pH control was reviewed. Each analysis

is discussed qualitatively below.


Performance of the Emergency Core Cooling System (ECCS) duringextended periods of time following a LOCA is typically analyzed toaddress residual heat removal via continuous boil-off of fluid inthe reactor vessel. As borated water is delivered to the coreregion via safety injection and virtually pure water escapes as

steam, high levels of boric acid may accumulate in the reactorvessel. As an input to this analysis, boric acid tank boron

concentration is typically assumed to be at the maximum of 12 weightpercent. Any such calculation will conservatively bound the maximum

boric acid tank boron concentration of 3.5 weight percent proposed

as a result of the analyses of this report.

The containment sump pH analysis is not impacted since it has notassumed injection of boric acid from the boric acid tanks during thedesign basis accident.


Table 6-1


Operations Analysis

Parameter Value

Reactor Coolant System Volume

RHR System Volume

Pressurizer Volume

Reactor Coolant System Pressure

Reactor Coolant System Hot Zero Power Temperature

Pressurizer ConditionReactor Coolant System Leakage

Boric Acid Makeup Tank Temperature

Hakeup Water Temperature

Pressurizer Level

Letdown

Letdown Flowrate From One OrificeLetdown Flowrate From One OrificeEOC Boron ConcentrationBOC Boron Concentration

BAT Boron ConcentrationRWST Boron ConcentrationInitial RHR System Concentration

RCS Boron Concentration (Refueling)

8015 ft2000 ft520 ft2250 psia547'F.

Saturated

0

120'F

120'F

Constant

Available45 gpm

60 gpm

0 ppm

1100 ppm

3.25 wtX

1950 ppm

775 ppm

1950 ppm

Report No. 849963-NPS-5MISC-003 Rev. 0 Page 6-25

TABLE 6 2CB FEEO'Ne BLEED UBINO ONE LETOOUN ORIFICE (45 CPN) FROI AN INITIAL CONCENTRATION Of 0 PPN BORON (SOURCE 0 120 F)

EXPONENTIAL

TINE (l.~ ( AT/Tao)RUST AT

(Nlmtoo) 19SO PPN

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BAT AT

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2 F 50 UT N

BAT AT

3.00 UT N

BAT AT

3.25 UT XBAT AT TOTAL VOL TOTAL VOL

3 ~ So UT N AT CS CPN AT S4 CPN

010

2030405060708090

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TARLE d 3

CR fEEO ANO RLEEO USINO ONE LETOOMN OR! fICE I60 GPFI) fROI AN INITIAL CONCENTRATION OF 0 PPN SORON IROMRCE 8 120 f)

EXPONENTIAL

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RAT AT TOTAL VOL TOTAL VOL

3.SO MT X AT 60 GPN AT 69 GPN

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ZSHO26220269102(6002d29026980296?0

303603105031740324303!120

3361034500

TABLE 6-4RCS FEED AHD BLEED: OHE LETDOMN ORIFICE (45 GPN) INITIAL COHCEHTRATION OF 1100 PPH BORON (SOURCE 9 120 F)

I TINE

i (min)EXP. VALUE

Y=T-XEXP. VALUE

X

RlST AT

1950 PPH

BAT AT

1.5 MT X

BAT AT BAT AT

1.75 MT X 2.25 IIT X

BAT AT

2.50 MT X

BAT AT

3.00 IIT X

BAT A'I

3.25 IIT X

BAT AT TOTAL VOL TOTAL VOL

3.50 III' AT 45 GPH AT 54 GPN I

-I

0

10

20

304050

60

70ao

i 1OO

I 110

I 120

i 13o

1

0.9907020.9814900.9723640.9633230.9543660.9454930.9367020.9279920.9193640.9108160.9023470.8939570.885645

i lroI 180

I 190

I 200

i 21O

i 22O

i 23O

i 24O

i 2SO

i 26O

I 270

i 2SO

i 290

I 300

i 310

I 320

i 330

i 340

i 350

I 360

i 370380

0.8531630.8452300.8373710.829585o.e21sr20.8142300.8066600.7991590.7917290. 784367

0.7770740.7698490.7626910.7556000.7485740. 741614

0.7347190.7278870.7211190.7144140.7077720.701191

I 140 0'877C10

I 150 0.869252

I 160 0.861170

0.000000.009300.018510.027640.036680.045630.054510 '63300.072010.080640.089180.097650.106040.114350.122590 ~ 13075

0 ~ 13S83

0.146840.154770.162630.170410 ~ 17813

0.185770 '93340.200840.208270.215630.222930.230150.237310.244400.251430.258390.265280.272110.278880.285590.292230.29881

RCS BORON

1100

1107.9031115.7331123.4891131.1741138.7881146.3301153.8031161.2061168.5401175.8061183.0041190.1361197.2011204.2001211.1351218.0051224.8111231.5531238.23C1244.8511251.4081257.9031264.3381270.7141277.0301283.2871289.4861295.6271301.7121307. 739

1313.7111319.6271325.4881331.2951337.0481342.7471348.3931353.987

CONCENTRAT

1100

1114.1561128.1801142.0741155.8391169.4761182.9871196.3711209.6311222.7681235 '831248.6771261.4501274.1051286.6431299.0641311.3691323.5601335.6371347.6031359.4571371.2001382.8351394.3611405.7811C17.094

1428.3021439.4051450.4061461.3041472.1011482.7971493.3941503.8921514. 293

1524.5971534.8061544.919'I554.938

ION RESULT I1100

1118.2201136.2701154.1531171.8701189.4221206.8111224.0381241.1051258.0131274.7641291.3591307.8001324.0881340.2251356.2111372.0491387.7401403.2851C18.6851433.9421449.0571464.0321478.8671493.5651508.1261522 ~ 551

1536.8421551.0011565.0281578.9241592.6911606.3301619.8431633.2301646.4921659.6311672.6471685.543

on)1100

1130.4121160.5411190.3901219.9621249.2591278.2831307.0381335 '251363.7471391.707'I419.4071446.8491474.0361500.9701527.6541554.09015S0.2801606.2271631.9321657.3981682.6281707.6231732.3851756.91S1781.2221805.3001829.1541852.7871876.1991899.3951922.3741945.1401967.6941990.0382012.1752034.1062055.8332077.357

NG (ppm bor1100

1126.3481152.4511178.3111203.9311229.3131254.4591279.3711304.0511328.5021352.7261376.7241400.4991424.0531447.3891470.5071493.4101516.1001538.5791560.8501582.9131604.7711626.4261647.8791669.'l331690.1901711.0501731.7171752.1911772.4761792.5711812.4801832.2031851.7441871.1021890.2S11909.2811928.1041946.753

1100

1138.540

1176.7211214.548

1252 '231289.1501325.931

1362.3711398.471

1434.2361469.6691504.7721539.5481574.001

1608.1341641.9501675.4511708.6411741.5221774.0971806.3691838.3C21870.0171901.3971932.4861963.2861993.7992024.0292053.9772083.6472113.0422142.1622171.0132199.5952227.9112255.9642283.756231'1.289

2338.567

1100

1142.6041184.8121226.6271268.0541309.095'13C9.755

1390.0371429.9451469.4811508.6501547.4541585.8981623.9841661.7161699.09S

1736.1311772.8211809.1691845. 179

1880.8551916.1981951.2141985.9032020.2702054.318208S.0492121.4662154.5722187.3712219.8652252.0572283.9492315.5452346.8472377.8582408.5812439.0182469.172

1100

1146.6681192.9021238.7061284.0841329.0411373.5791417.7041461 ~ 41S

1504.7261547.6311590.1371632.2471673.9671715.2981756.2451796.8121837.0011876.8161916.2621955.3401994.0552032.4112070.4092108.0542145.3502182 '982218.9032255 '682291.0952326.6892361.9512396.SS62431.4952465.7832499.7522533.4062566.7C62599.776

0

450

900

1350

1800

2250

2700

3150

3600

4050

4500

49505400

5850

6300

6750

7200

7650

8100

8550

9000

94509900

10350

10800

11250

11700

12150

12600

13050

13500

13950

14400

14850

15300

15750

16200

16650

17100

I

oi54o i

1OSO )

1620 I216O i27oo i3240 i3780 i4320 [486O iscoo )

5940 I64ao iro2o ir56o i8100 I

Mco /

9180 I9720 /

1O26O /losoo t11340 I11880 i12420 I

12960 [13500 I

1404O i14580 i15120 I

1566O i162OO i16740 /172so /17820 I18360 /18900 I

19440 I19980

J

20520

TABLE 6-5RCS FEED-AHD BLEED USING OME LETDOMM ORIFICE (60 GPH) FROM AM INITIAL CONCENTRATION OF »00 PPH BORON (SOURCE Q 120 F)

I TINE

i(min)

0

10

20

30

co

50

80

) 1OO

I »0I 120

I 130

I 140

i 1SO

I 160

i 1ro

i 180

i 190

[ zoo

i 21O

i 22O

/ Z3O

i 24O

i zso

i 260

i zro

/ zeo

/ Z90

i 300

I 310

/ 320

) 330

I 340

i 350

i 370

3SO

1

0.9876200.9753940.9633200.9513950.9396170.9279860.9164980.9051530.8939480.8828810.8719520.86»580.8504970.8399690.8295710.8193020.8091590.7991430.7892500.779CBO

0.7698300.7603010.7508890.7415930.7324130.7233C60.7143920.7055CS0.6968140.6881880.6796690.6712550.6629460.6547390.6466340.6386290.6307240.622916

0.000000.012380.024610.036680.048600.060380.072010.083500.09C85

0.106050.»7120.128050.13MC0.149500.160030.170430.180700.190840.200860.210750.220520.230170.239700.249»0.258410.267590.276650.285610.294450.303190.3»810.320330.328740.337050.345260.353370.361370.369280.37708

EXP. VALUE EXP. VALUE

T=1-X X RMST AT

1950 PPH

RCS BOROH

»00»10.522»20.914»31.177»41.313»51.324»61.2»»70.976»80.619»90.144»99.5501208.8401218.0151227.0761236.02512C4.864

1253.5931262.2141270.7281279.1371287.4411295.6431303.744

13» .7441319.6451327.4481335.1551342.7661350.2831357.7071365.0391372.2SO

1379.43213S6.4951393.4711400.3601407.1641413.8841420.521

BAT AT

1.50 'MT X

CONCENTRAT

»00»18.847»37.461»55.845»74.001»91.9321209.641

1227.1311244 405

1261.4651278.313129C.953

13» .3871327.6181343.6471359.479

1375. »41390 ~ 5561C05.806

1C20.8681435.7431450.4341C64.944

1479.2731493.4261507.C03

1521.20T1534.8401548.3041561.602157C.735

1587.7061600.5161613 ~ 167

1625.6621638.0021650.189

BAT AT BAT AT

1.75 MT X 2.25 MT X

BAT AT

2.50 llT X

HG (ppn boron)»00»00-»35.079 »40.490»69.724»80.4791203.9C1 1219.9731237.734 1258.9781271.108 1297.5001304.070 1335.5C6

1336.623 1373.1201368.773 1C10.230

1C00.526 14C6.880

1431.885 1CB3.076

1462.856 1518.8241493.444 1554.1301523.653 1588.9981553.488 1623.4351582.954 1657.4461612.055 1691.0351640.796 1724.2091669.181 1756.9721697.21C 1789.3301724.901 1821.2871752.245 1S52.S48

1779.250 1884.019

1805.921 1914.8041832.262 1945.2081858.277 1975.2351M3.970 2004.8911909.34C 2034.1791934.405 2063.1051959.155 2091.6731983.599 2»9.8872007.741 2147.7522031 ~ 583 2175.2722055.130 2202.4522078.386 2229.2942101.354 2255.8052124.038 2281-988

ION RESULTI

»00»24.258»48.215»Ti.err»95.2451218.3241241.»71263.62912S5.861

1307.8181329.50C

1350.9211372.0731392.9631413.5941433.9701CSC.094

1473.9691493.5981512.9831532.1291551.0381569.712158S.1561606.3711624.3611642.1281659.6751677.0051694.12017».0231727.7171744.2051760.4881776.5701792.4531808.139

BAT AT

3.00 IIT X

»00»51.3»1201.9881252.0371301.4671350.2851398.4981446. »51493.1421539.5871585.4571630.7591675.5011719.6881763.3291806.42918C8.9961891.0361932.5551973.5612014 ~ 0592054.0552093.5572132.5692171.0982209.1512246.7322283.8492320.5052356.7082392.4632427.7752462.6502C97.0942531. »12564.7072597.887

BAT AT

3.25 llT X

»00»56.7221212.7421268.0691322.7»1376.67T1429.9741482.6121534.5981585.9411636.6481686.7271736.1861785.0331833.2761880.9211927.9761974.4492020.3472065.6762»0.4452154.6592198.3252241.4522284.0442326.1092367.6532408.6832449.2062489.2262528.7512567.7S72606.3402644.4152682.0192719.1572755.836

»00»62.1331223.4971284.101

1343.9561403.0691461.4501519.1091576.0541632.2941687.8381742.6951796.8721850.3791903.2231955.C13

2006.9572057.8632108.1382157.7922206.8312255 '622303.0942350.3342396.9892443.0672488.5742533.5182577.9062621.7442665.0392707.7992750.0292791.7362832.9272873.6082913.786

0

600

1200

1800

2400

3000

3600

42004800

5COO

6000

6600

7200

7800

8400

9000

960010200

10S00

»40012000

12600

13200

13800

14400

15000

15600

16200

16800

17400

18000

18600

19200

'980020400

2100021600

22200

22800

BAT AT TOTAL VOL

3.50 MT X AT 60 GPN

TOTAL VOL

AT 69 GPH i-I

Io i

690 I

13eo (

zoro i2760 I3450 I41CO I483O

J

5520 i6ZIO i6900 I

TS90 i8280 I8970 I

9660 /10350 I»040 /»73o (

12420 I13»0 I13800 (

14490 I1s1eo

J

15870 I16S6O )

Irzso /17940 /18630 /19320 I20010 I20700 /

21390 I22080 I

22770 /23460 /24150 I24840 iZSS3O i .

26220

TABLE 6 6PLANT COOLDOLIN TO REFUELING: BAT AT 3.25 IIEIGHT X BORIC ACID; RHR = 775 ppm (RHR VOLUME = 2000 FT3)

IAVG~ SYS.TEMP. PZR PRESS SPECIFIC VOLUME SHRINKAGE BLEND BAT VOL 9 RUST VOL Q B/A ADDED TOTAL B/A TOTAL SYS. FINAL CONC TOTAL RCS TOTAL PURE TOTAL BAT

(F) (psia) (cu.ft./tbm) MASS(ibm) RATIO 120 F (gal) 120 F (gal) (tbm) (tbm) - MASS (ibm) (ppm boron) MAKEUP MATER llATER

Ti . Tf Vi Vf 120 F (gal) 120 F (gal) 120 F (gal)

547 547547 500500 450450 400400 370370 350350 350350 350350 300300 250250 200200 160

160 130

22502250

2250225022502250

465465

465465

465465

465

1.000000.021250.020090.019160.018420.018040.026980.017810.017810.017420.016980.016610.01637

1.000000 '20090.019160.018420.018040.017810.019610.017810.017420 ~ 01698

0.016610.016370.01622

0.021,796.019,473.916,814.49,170.65,740.87,243.5

0.012,431.414,897.713,138.58,839.85,657.7

0

0

0

0

0

0

0

0

0

0

0

0

0

0.02,642.02,360.52,038.21,111.6

695.9878.0

0.01,506.91,805.81,592.61,071.5

685.8

0.00.00.00.00.00.00.00.00.00.00.00.00.0

0.0 2,894.0 445,622.6732.2 3,626.2 468, 150.7654.2 4,280.3 488,278.7564.8 4,845.1 505,658.0308.1 5,153.2 515,136.6192.8 5,346.0 521,070.3243.3 5,589.3 528,557.2495.8 6,085.2 636,526.6417.6 6,502.7 649,375.6500.4 7,003.2 664,773.7441.3 7,444.5 678,353.5296.9 7,741.4 687,490.3190.0 7,931.5 693,338.1

1,135.41,354.21,532.61,675.21,749.01,793.71,848.81,671.41,750.81,841.81,918.71,968.72,000.0

0.02,642.05,002.57,040.78,152.38,848.29,726.29,726.2

11,233.113,038.914,631.515,703.016,388.8

0.00.00.00.00.00.00.00.00.00.00.00.00.0

0.02,642.05,002.57,040.78, 152.38,848.29,726.29,726.2

11,233.113,038.914,631.515,703.016,388.8

iCONTRACTION MAKEUP BAT VOLUHE

)FEED 8 BLEED BAT VOLUME (Oppn to 1135ppn)iTOTAL BAT VOLUME

16,388.8 gat lons10,800 ~ 0 gallons (180 min at 60 gpm) ROUNDED UP

27,188.8 gatlons

ITABLE 6-7

)PLANT COOLDOMN TO COLD SMUTDOMN (CASE 1): BLENDED MAKEUP; BAT AT 3.25 MEIGHT )l BORIC ACID; RHR (ppm) = RCS (ppm) (RHR VOLUHE = 2000 FT3) (CASE 1)

[AVG.SYS ~ TEHP. PZR PRESS SPECIFIC VOLUME SHRINKAGE BLEND BAT VOL 9 RUST VOL ol B/A ADDED TOTAL 8/A TOTAL SYS. FINAL CONC. TOTAL RCS TOTAL PURE TOTAL BAT

(F) (psia) (cu.ft./ibm) HASS(ibm) RATIO 120 F (gal) 120 F (gal) (ibm) (ibm) HASS (ibm) (ppm boron) HAKEUP HATER IIATER

Ti 'f Vi Vf 120 F (gal) 120 F (gal) 120 F (gal)

547 547547 . 500500 450

450 400400 370370 350350 350350 350350 320320 290290 260260 230230 200

2250 1 ~ 00000

2250 0.021252250 0.020092250 0.019162250 0.018C2

2250 0. 01804

465 0.02698465 0.01781465 0.01781465 0.01763C65 0.01733465 0.01706465 0.01682

1.000000.020090.019160.018420.018040.017810.019610.017810.017630.017330.017060.016820.01661

0.021,796.019,473.916,814.49,170.65,740.87,243.5

0.05,583.39,833.89,146.18,376.47,527.9

0.30.30.30.30.30.30.30.30.32.42.42.42.4

0.02,032.31,815.81,567.8

855.1535.3675.4

0.0520.6350.6326.1298.6268.C

0.00.00.00.00.00.00.00.00.00.00.00.00.0

0.0563.2503.2434.5237.0148.3187.2426.1144.397.290.482.874.4

0.0563.2

1,066.41,500.91,737.81,8S6.22,073.32,499.42,643.72,740.82,831 ~ 2

2,914.02,988.3

442,728.6465,087.74S5,064.S502,313.7511,721.3517,610.4525,041.2632,940.9638,668.5648,599.4657,835.9666,295.1673,897.4

0.0211.7384.4522.4593.7637.1690.4690.4723.7738.8752.5764.6775.3

0.02,642.05,002.57,040.78,152.38,848.29,726.29,726.2

10,403.011,595.012,703.613,719.014,631.5

0.0609.7

1,154.41,624.81,881.32,041.92,244.52,244.52,400.73,242.14,024.74,741.45,385.5

0

2,032.33,848.15,415.96,271.06,806.37,481.77,481.78,002.38,352.98,679.08,977.69,246.0

ITOTAL BAT VOLUME

iTOTAL RIIST VOLUHE

9,246.0 gallons0.0

I TABLE 6-8

/PLANT COOLDNN TO COLD SHUTDOMN (CASE 2): BLENDED MAKEUP BAT AT 3.25 MEIGHT X BORIC ACIDI RHR (ppm) "- 775 ppm (RHR VOLUME = 2000 FT3) (CASE 2)

JAVG.SYS.TEMP. PZR PRESS SPECIFIC VOLUME SHRINKAGE BLEND BAT VOL 9 RUST VOL 9 B/A ADDED TOTAL B/A TOTAL SYS. FINAL CONC TOTAL RCS TOTAL PURE TOTAL BAT

(F) (psia) (cu.ft./tbm) MASS(ibm) RATIO 120 F (gat) 120 F (gal) (ibm) (ibm) MASS (ibm) (ppm boron) MAKEUP MATER MATER

Ti Tf Vi Vf 120 F (gal) 120 F (gal) 120 F (gal)

547 547547 500500 450

450 400400 370370 350350 350350 350

350 320320 290290 260260 230

230 200

2250

2250

2250

2250

2250

2250

465

465

465

465

465

465

465

1.000000.021250.020090.019160.018420.018040.026980.017810.017810.017630.017330.017060.01682

1.000000.020090.019160.018420.018040.017810.019610.017810.017630.017330.017060.016820.01661

0.021,796.019,473.916,814.49,170.65,740.87,243.5

0.05,583.39,833.89,146.18,376.47,527.9

0.30.30.30.30.30.30.30.30.33.13.13.13.1

0.02,032.31,815.81,567.8

855.1535.3675.4

0.0520.6290.7270.4247.6222.6

0.00.00.00.00.00.00.00.00.00.00.00.00.0

0.0563.2503.2434.5237.0148.3187.2495.8144.380.674.968.661. 7

0.0563.2

1,066.41,500.91,737.81,886.22,073.32,569.22,713.42,794.02,868.92,937.62,999.2

442,728.6465,087.7485,064.8502,313.751'I,721.3517,610.4525,041.2633,010.6638,738.2648,652.6657,S73.6666,318.7673,908.3

0.0211.7384.4522.4593.7637.1690.4709.6742.7753.1762.4770.8778.1

0

2,642.05,002.57,040.78,152.38,848.29,726.29,726.2

10,403.011,595.012,703.613,719.014,631.5

0.0609.7

1,154.41,624.81,881.32,041.92,244.52,244.52,400.73,302.04,140.24,907.95,597.8

0.02,032.33,848.15,415.96,271.06,806.37,481.77,481.78,002.38,293.08,563.48,811.19,033.6

ITOTAL BAT VOLUME

ITOTAL RIIST VOLUME =

9,033.6 gatlons0.0

TABLE 6.9PLANT COOLDOWN To COLD SHUTDOWN: FEED AND BLEED AND BLENDED IIAKEUP FOR 50 F/HR COOLDOWNI BAT AT 3 '5 WT XI RHR (ppm) = 775 m ---------(9 gpa SEAI. LEAKAGE)--------

AVG.STSTEHP. PZR PRESS

(F) (psia)Ti Tf

SPECIFIC VOLUHE

(cu.ft./Ibm)Vi Vf

SHRINKAGE

I(ASS(ibm)BLEND

RATIO

BAT VOL a RuSt VOI. O 8/A ADDEO

120 F (gal) 120 F (gal) (Ibm)TOTAL 8/ TOTAL SYS. FINAL CONC TOTAL RCS TOTAL PURE TOTAL BAT

(Ibm) IIASS (Ibm) (ppa boron) HAKEUP WATER MATER

120 F (gal) 120 'F (gal) 120 F (gal)

547547540530520510500490480470460450440430420410400390380370360350350350

330310290

270250

230210

5475CO

530

520510500490480470460450440430420410400

390380370360350350350330

310290270

250

230

210200

2250

2250

2250

2250

2250

22502250

2250

2250

225022502250

2250

22502250

2250

2250

22502250

22502250

465

465

465

465

465

465

465

465

465

465

1.000000.021250.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.018840.018690.018550.018420.018280.018160.018040.017920.026980.017810.01781

0.017730.017630.017420.017240.017060.016900.01675

1.000000.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.018840.018690.018550.018420.01828o.oie160.018040.017920.017810.019610.017810.017730.01T630.017420.017240.017060.016900.016750.01661

0.03,511.04,852.24,597.44,513.94,321.54,011.64,093.13,860.93,827.53,680.93,524.53,471.53,414.33,353.03,051.03,334.32,898.92,937.52,976.82,764.07,2C3 as

0.02,379.43,204.06,848.16,002.66,129.25,557.85,306.95,039.6

6.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.5

0.056.778.474.373.069.864.866.262.461.959.557.056.155.254.249.353.946.947.548.144.7

117.10.0

38.551.8

110.797.099.189.885.881.4

0.00.00.00.00.00.00.00.00.00.00.00.0-0.00.00.00 ~ 0

0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0

0.015.721.720.620.219.418.018.317.317.116.515.815.515.315.013.71C.913.013.213.312.432.4

495.810.714.430.726.927.524.923.822.6

1,962.51,978.22,000.02,020.52,040.82,060.12,078.12,096.C2,113.72,130.92,147.32,163.12,178.72,194.02,209.02,222.62,237.62,250.62,263.72,277.12,289.42,321.9z,eir.r2,828.42,842.72,873.42,900.32,927.72,952.62,976.42,998.9

442,728.6446,255.2451,129.2455,747.1460,281.3464,622.2468,651.7472,763.2C76,641.3480,485.9484,183.3487,723.6491,210.6494,640.2498,008.3501,073.0504,422.2507,334.1510,284.7513,274.8516,051.2523,327.2633,259.1635,649.2638,867.5645,746.3651,775.7657,932.4663,515 '668,845.8673,908.0

775.0775.0775.1775.1775.2775.2775.2775.3775.3775 ~ C

775.4775.47T5.4775 ~ 5

775 ~ 5

775.5775.6775.6775.6775.6775.6775.7777.9777.97T7.97TS.O

rre.o778.0778.0778.0778.0

0501.2

1,197.31,862.62,517.83,149.63,743.94,348.04,924.05,496.06,050.16,585.47,114.27,636.08,150.58,628.39,140.59,599.8

10,063.910,532.710,975.811,853.811,853.812,358.212,962.614,008.71C,952.315,911.216,800.917,660.218,379.1

0.0434.4

1,037.71,614.32,182.12,729.73,24C.73,768.34,267.54,763.25,243.45,707.36,165.66,617.97,063.77,477.97,921.78,319.98,722.19,128.49,512.3

10,273.310,273.310,710.51'1,23C.2

12,140.912,958.713,789.714,560.815,305.515,928.5

o.o I66.8 I

159.6 I

248.3 I335.7 I

419.9 I

499.2 I579.7 I

6s6.s I73z.s I

806.7 Isrs.o I

948.6 I

1,018.11,086.7 I

1,150.4 I

1,218.7 I

1,280.0 I

1,341.9 I

I,co4.4 I

1,463.4 I1,580.5 I

1,Seo.S I1,647.8 I

1,728.3 I

1,867.8 I

1,993.6 I

2,121.5 I

2,240.1 I

2,354.7 I

z,4so.s I

FEED AND BLEED BAT VOLUHE (Oppm to 775ppm)FEED AND BLEED RWST VOLUNE (Oppm to 775ppm)

8,122.7 gallons28,060.0 gallons

(117.7 minutes at 69 gpm, 3.25 wt X)(406.7 minutes at 69 gpm, 1950 ppm)

TOTAL BAT VOLUIIEt FEED AND BLEED PLUS HAKEUP 10,573.2 gallons

TABLE 6-10

PLANT COOLDOWN TO COLD SHUTDOWN: BLENDED MAKEUP FOR 100 F/HR COOLDOWN; BAT AT 3.25 WEIGHT X BORIC ACID; RHR (ppm) = 775 ppm ---------(9 gpm SEAL LEAKAGE)-------

AVG.SYSTEMS PZR PRESS

(F) (psia)Ti Tf

SPECIFIC VOLUME

(cu.ft./Ibm)Vi Vf

SHRINKAGE BLEND

MASS( ibm) RATIO

BAT VOL 9 RWST VOL 9 8/A ADDED

120 F (gal) 120 F (gal) ( ibm)

TOTAL B/ TOTAL SYS ~

(ibm) MASS (ibm)FINAL CONC TOTAL RCS TOTAL PURE TOTAL BAT

(ppm boron) MAKEUP WATER WATER

120 F (gal) 120 F (gal) 120 F (gal)

SC7

547540

530520510500490480470460450440430420410400390380370360350350350

330320300280260240220

547540530520510500490480470460450440430420410400390380370360350350350330320300280260240

220200

225022502250

22502250

22502250

22502250225022502250

225022502250

22502250

2250225022502250

465465465

465

465465

465465

465465

1.00000 1.000000.02125 0.021060.02106 0.020790.02079 0.020550.02055 0.02031

0.02031 0.020090.02009 0.019890.01989 0.019690.01969 0.019510.01951 0.019330.01933 0.019160.01916 0.019000.01900 0.018840.01884 0.018690.01869 0.018550.01855 0.018420.01842 0.018280.01828 0.018160.01816 0.018040.01804 0.017920.01792 0.017810.02698 0.019610.01781 0.017810.01781 0.017730.01773 0.017630.01763 0.017420.01742 0.017240.01724 0.017060.01706 0.016900.01690 0.016750.01675 0.01661

0.03,511.04,852.24,597.44,513.94,321.54,011.64,093.13,860.93,827.53,6S0.93,524.53,/71.53,414.33,353.03,051.03,334.32,898.92,937.52,976.82,764.07,243.5

0.02,379.43,204.06,848.16,002.66,129.25,557.85,306.95,039.6

6.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.5

0.056.778.474.373.069.864.S66 '62.461.959.557.056.155.254.249.353.946.947.548.144.7

117.10.0

38.551.8

110.797.099.189.885.881.4

0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0

0.015.721.720.620.219.418.018.317.317.116.515.815 ~ 5

15.315.013.714.913.013.213.312.432.4

495.810.714.430.726.927.524.923.822.6

1,962.51,978.22,000.02,020.52,040.82,060.12,078.12,096.42,113.72,130.92, 147.32,163.12, 178.72,194.02,209.02,222.62,237.62,250.62,263.72,277.12,289.42,321.92,817.72,828.42,842.72,873.42,900.32,927.72,952.62,976.42,998.9

442,728.6446,255.2451,129.2455,747.1460,281.3C64,622.2468,651.7472,763.2476,641.3480,485.9484, 183.3487,723.6491,210.6494,640.2498,00S.3501,073.0504,422.2507,334.1510,284.7513,274.8516,051.2523,327.2633,259.1635,649.2638,867.5645,746.3651,775.7657,932.4663,515.2668,845.8673,908.0

775 ~ 0

775.0775.1775 ~ 1

775.2775.2775.2775.3775.3775.4775. C

775.4775.4775.5775.5775.5775.6775.6775.6775.6775.6775.7777.9777.9777.9778.0778.0rre.o778.0778.0778.0

0.0463.4

1,105.51,716.82,318.02,895.83,436.13,986.24,508.25,026.25,526.36,007.66,482.46,950.27,410.77,834.58,292.78,698.09,108.19,522.99,912.0

10,790.010,790.011,186.411,62e.e12,566.913,402.514,253.415,035.115,786.416,505.3

0.0401.6958.1

1,487.92,008.92,509.72,977.93,454.73,907.14,356.04,789.55,206.65,618.06,023.56,422.66,789.97, 187.07,538.37,893.78,253.28,590.49,351.39,351.39,694.9

10,078.310,891.311,615.512,353.013,030.513,681.614,304.6

0.0 i61.8 i

1474 I

228.9 I309.1 I

386.1458 1 I531.5 I

601.1 I

670.2 I736.8 /801.0 I

864.3 i926.7 I

988.1 I

1,044.6 I

1,105.7 i1,159.7 I

1,214.4 i1,269.7 I

1,321.6 i1,438.7 I

1,438.7 i1,491.5 I

1,550 5 I

1,675.6 i1 787.0 I

1,900.5 I2,004.7 (

2,104.9 J

2,200.r /

FEED AND BLEED BAT VOLUME (Oppm to 775ppm)

FEED AND BLEED RWST VOLUME (Oppm to 775ppm)

8,122.7 gallons2S,060.0 gallons

(117.7 minutes at 69 gpm, 3.25 wt )l)(406.7 minutes at 69 gpn, 1950 ppm)

TOTAL BAT VOLUME: FEED AND BLEED PLUS MAKEUP 10,323.4 gallons

TABLE 6-11PLAN'I COOLDOMN TO COLD SHUTDONN: FEED AND BLEED AND RNST HAKEUP FOR 100 F/HR COOLDONNI RWST AT 1950 ppm BORONI RHR (ppm) = 775 ppn -----(9 gpm SEAL LEAKAGE)------

AVG.SYSTEHP. PZR PRESS

(F) (psia)Ti Tf

SPECIFIC VOLUME

(cu.ft./Ibm)Vi Vf

SHRINKAGE

MASS( ibm)BLEND BAT VOL 9 RUST VOL 8 B/A ADDED

RATIO 120 F (gal) 120 F (gal) (lbn)TOTAL B/ TOTAL S'YS.

(ibm) MASS (ibm)FINAL CONC TO'IAL RCS TOTAL PURE TOTAL BAT

(ppn boron) MAKEUP MATER MATER

120 F (gal) 120 F (gal) 120 F (gal) (

-I547547540

530520

510500490480470460450440430420

410400

390380370360350350350330320300280260240220

54754053052051050049D

4804704604504CO

430420410400390380370360350350350330320300280260240220200

22502250

2250

22502250

225022502250

225022502250225022502250225022502250

225022502250

2250465465

465

465465465

465465465

465

1.000000.021250.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.01MC0.01S690.018550.01S420.018280.01816o.oleoc0.017920.026980.017810.017810.017730.017630.017420.017240.017060.016900.01675

1.000000.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.018840.018690.018550.018420.018280.018160.018040.017920.017810.019610.017810.017730.017630 ~ 01742

0.017240.017060.016900.016750.01661

0.03,511.04,852.24,597.44,513.94,321.54,011.64,093.13,860.93,827.53,6S0.93,524.53,471.53,414.33,353.03,051.03,334.32,898.92,937.52,976.82,764.07,243.5

0.02,379.43,204.06,848.16,002.66,129.2s,ssr.e5,306.95,039.6

0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00 ~ 0

0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0

0.0425.6588.2557.3547.2523.8486.3496.1468.0463.9446.2427.2420.8413.9406.4369.8404.2351.4356.1360.8335.0ere.o

0.0288.4388.4830.1727.6743.0673.7643.3610.9

0.039.654.751.950.948.745.246.243.543.241.539.839.238.537.834 '37.632.733.133.631.281.7

495.826.836.177.267.769.162.759.9s6.e

1,130.01,169.61,224.31,276.21,327.11,375.81,421.11,467.31,510.81,554.01,595.51,635.21,674.41,712.91,750.71,785.11,822.71,855.41,888.61,922.11,953.32,035.02,530.82,557.72,593.82,671.12,738.82,807.92,870.62,930.42,987.3

442,728.6446,279.1451,186.0455,835.3460,400.1464,770.4468,827.2472,966.5476,870.94S0,7C1 as

484,463.9488,028.2491,538.9494,991.7498,382.5501,468.0504,839.9507,771.5510,742.0513,752.4516,547.6523,872.9632,972.3635,378.5638,618.6645,543.9651,614.2657,812.6663,433.1668,799.9673,896.3

446.2458.2474.4489.5504.0517.6529.9542.4553.9565.1575.8585.8595.6605.0614.2622.4631.2638.9646.5654.1661.1679.2699.0703.8710.1723.4734.8746.3756.5766.1775.0

0.0463.4

1,105.51,716.82,318.02,895.83,436 '3,986.24,508.25,026.25,526.36,007.66,482.46,950 '7,410.77,834.58,292.78,698.09,108.19,522.99,912.0

10,790.010,790.011,186.C11,628.812,566.913,402.514,253.415,035.115,786.416,505.3

0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

o.o (

FEED AND BLEED BAT (3.25llTX) VOLUHE (oppm to 446ppn)FEED AND BLEED RMST (1950ppm) VOLUME (Oppn to 446ppm)Tol'AL RIIST VOLUME: FEED AND BLEED PLUS MAKE UP

4,485.0 gallons14,336.0 gallons30,841.3

(65 minutes at 69 gpn)(207 minutes at 69 gpm)

PLAHT COOLDOMN TO COLD SNUTDOMN: 11 gpm RCS LEAKAGE;

TABLE 6-12BLENDED NAKEUP FOR 50 F/NR COOLDOMH; BAT AT 3.25 MT X; RNR = rrsppm R ---------(9 gpm SEAL LEAKAGE)---"--

(TINE AVG.SYSTENP. PZR PRESS

((min) (F) (psia)Ti . Tf

SPEC IF I C VOLUNE

(cu.ff./Ibm)Vi Vf

SNRINKAGE BLEND

HASS( ibm) RATIO

BAT VOL 9 RMST VOL oi B/A ADDED TOTAL B/A TOTAL STS.

120 F (gal) 120 F (gal) (ibm) (ibm) MASS (ibm)FINAL CONC TOTAL RCS

(ppm boron) MAKEUP

120 F (gal)

TOTAL PURE TOTAL BAT (

MATER MATER I

120 F (gal) 120 F (gal)(-I

0.00.00.00.00.00.00.00.00.00.0

3,543.95,157.15,585.36,009.56,429.36,825.37,244.77,629.58,017.98,410.08,785.49,370.89,370.S9,867.9

10,279.611,140.711,935.112,741.613,503.414,246.4'14,969.3

0

8.412

12

12

12

12

12

12

12

12

12

12

12

12

12

12

12

12

12

12

00

24

12

24

24

24

24

24

24

547547

547540

530520

510500490

480470460450

440430420

410400

390380370360350350350

330320300280260

240220

520510500

490480

4704604504404304204104003903803703603503503503303203002eo260240220200

540 530

2250

2250

2250

22502250

2250

2250

2250

22502250

22502250

2250

22502250

2250

22502250

2250

22502250

465

465

465

465465

465

465465465465

1.000000.021250.021060.020790.020550.020310.020090.019890 ~ 01969

0.019510 '19330.019160.019000.018840.018690.018550.018420.018280.018160.018040.017920.026980.017810.017810.017730.017630.017420.017240.017060.016900.01675

1.000000.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.018840.018690.018550.018420.018280.018160.018040 ~ 01792

0.017810.019610.017810.017730.017630.017420.017240.017060.016900.016750.01661

0.04,097.45,700.75,456.05,382.55,199.64,898.54,989.04,765.24,740.34,601.84,453.24,407.84,358.14,304.24,009.04,299.53,870.53,915.63,961.53,754.77,243.5

0.04,369.24,204.58,873.48,049.08,197.27,645.47,413.27,163.6

0.0496.7691.0661.3652.4630.3593.8604.7577.6574.6278.9179.9178.1176.1173.9162.0173.7156.4158.2160.1

151.7292.7

0.0176.5169.9358.5325.2331.2308.9299.5289.4

0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0

0.0137.6191.2182.6179.8173.C

162.9165.6157.8156.774.546.946.345.745.041.644.839.940.340.838.481.1

495.840.843.090.981.482.976.473.670.6

0.0137.6328.9511.5691.4864.7

1,027.61, '193.3

1,351.11,507.81,582.21,629.11,675.41,721.11,766.01,807.61,852.41,892.21,932.61,973.32,011.72,092.82,588.62,629.42,672.32,763.32,844.72,927.63,00C.O3,077.63, 148.3

442,728.6446,963.6C52,855.5458,494.2464,056.5469,429.4474,490.8479,645.4484,568.5489,465.4494, 141.7498,641.8503,095.8507,499.6511,848.8515,899.4520,243.7524,154.1528,109.9532 112.1

535,905.2SC3,229.9633,030.1637,440.1641,687.6650,651.8658,782.2667,062.3674,784.2682,271.0689,505.2

0.053.8

127.0195.1

'60.5

322.0378.6435.0487.5538.6559.8571.2se2.2592.9603.2612.6622.5631.2639.8648.4656.3673.5714.9721.2728.1742.5755.0767.3778.3788.7798.3

0.0572.3

1,371.32,140.62,901 ~ 1

3,639.34,341.15,053.85,739.56,422.07,087.97,735.68,377.99,014.29,643.9

10,237.910,S67.111,444.212,026.912,615.013,178.214,056.214,056.214,801.815,419.516,711.117,902.719,112.320,255.121,369.722,454.0

o.o (

572 3 I

1 371 3 I

2,140.6 I

2,901.13,639.3 (

4,341.1 I

5,053.8 (

5,739.5 (

6,422.O (

3,543.9 I

2,578.5 I

2,792.6 (

3,004.7 (

3,214.6 I

3,412.6 I

3,622.4 (

3,814.7 I

4,009.0 (

4,205.0 (

4,392.r (

4,68S.C (

4,68S.4 (

4,933.9 (

5,139.8 (

s,sro.4 (

5,967.6 I

6,370.8 I

6,751.7 (

7,123.2 (

7,484.7 (

Figure 6-1 CVCS Flow Diagram

I Namd Opereboa -~ kiowa I

lOENT1F IEOLEAKAGE

GPM

UH IOENT 1 f1EOLEAKAGE

RCS

60 GPM

LETDOWN L lNE

LABYR1NTHSEAL

9 GPM

IS NO I SEALGP M LEAKAGE

SEALINJECT lQN

0 GPMHOLOUP TANK

LC V - I I 5A60 GPM

VCT

RMWLCV-IISC 0 GPhl

0 GPMBLENOER

CHAR G lN GL INK

W5 GPM

Z+ GPM

69 GPM

0 GPM

CHAR 6 lN 8PUMPS

0 GPM

0PM

350

FCV-II3A

RWST

BAT

LCV- I ISB

7.0 TECHNICAL SPECIFICATIONS

7.1 RECOMMENDED CHANGES

1. TECHNICAL SPECIFICATION 3/4.1 - REACTIVITY CONTROL SYSTEM

S ecification 3. 1. 1. 1 - Action Statement

Substitute "16 gpm" for "4 gpm" and "3.0 wt./ (5245 ppm)

boron" for "20,000 ppm boron."

Evaluation: The required flow rate is increased by a factorof four to conservatively accommodate the decrease in the

boric acid tank minimum concentration by a factor ofapproximately four (20,000 ppm, or 11.4 weight percent (wt.%),

down to 3.0 weight percent). This adjustment ensures equal

boration capability for shutdown margin recovery. The 16 gpm

will be available via the emergency boration path or the

manual boration path following the modification of FCV-113A.

The required boron concentration is adjusted to reflect the

minimum concentration of 3.0 weight percent to be available

from the boric acid tank.

S ecification 3. 1. 1.2 - Action Statement

Substitute "16 gpm" for "4 gpm" and "3.0 wt.% (5245 ppm)" for"20,000 ppm."

Evaluation: Same as Specification 3. 1. l. l.

S ecification 4. 1.2. 1 - Surveillance Re uirement

Change Surveillance Requirement 4. 1.2. l.a :

"... by verifying that the temperature of the heat traced

portion of the flow path is greater than or equal to 145'F

when a flow path from the boric acid tank is used"


to read,

"... by verifying that the temperature of the rooms containing

flow path components is greater than or equal to 55'F when a

flow path from the boric acid tanks is used"

Evaluation: The boration system flow path surveillance

requirement is modified to reflect the reduced boric acid

solubility temperature. The maximum boric acid concentration

to be specified is 3.5 weight percent with a solubilitytemperature limit of 50'F. A margin of 5'F is added to thisto make 55'F the critical temperature for boric acid

solubility. The 7 day surveillance interval is justifiedbecause the temperature of the rooms containing boration

system flow paths and components will be provided with an

alarm in the control room. The actions required in the event

that temperature decreases below the critical temperature are

identical to the current specification (i.e., if temperature

is less than 55'F, the flow path in question becomes

inoperable and the appropriate actions carried out).

S ecification 3. 1.2.2 - L'imitin Condition for 0 eration

Add the following words to the footnote:

"from the boric acid transfer pump discharge to the charging

pump suction."

Evaluation: The footnote regarding flow path separation is

modified to reflect the recommended boric acid tank lineup

where all three tanks are interconnected via the transfer pump

suction lines. This lineup maximizes the available volume

from the boric acid tanks with no valve manipulations required

to access the entire inventory. Boric acid tank inventory

control in accordance with Technical Specification 3. 1.2.5


will ensure that the tanks shared between the two units willhave the total minimum required volume necessary to support

both units. Haintaining the separation criteria for the

remaining flow path from the boric acid transfer pumps to the

charging pumps assures the appropriate level of activecomponent redundancy for each unit.

S ecification 4. 1.2.2 - Surveillance Re uirement

Change Surveillance Requirements 4. 1.2.2.a :

"... by verifying that the temperature of the heat traced

portion of the flow path from the boric acid tanks is greater

than or equal to 145'F when it is a required water source;"

to read,

"... by verifying that the temperature of the rooms containing

flow path components are greater than or equal to 55'F when a

flow path from the boric acid tank is used;"

Substitute "16 gpm" for "4 gpm" in Surveillance Requirement

4.1.2.2.c

Evaluation: Same as Specification 4.1.2. 1. This change also

makes Surveillance Requirement 4. 1.2.2.c consistent with

Limiting Conditions for Operation 3. 1.1. 1 and 3. 1. 1.2.

S ecification 3. 1.2.4 - Limitin Condition for 0 eration

For the Horic Acid Storage System (3. 1.2.4.a) change:

1. "A minimum indicated borated water volume of 500

gallons,"


to read,

1. "A minimum indicated borated water volume of 2,900

gallons per unit,"

change:

2. "A boron concentration between 20,000 ppm and 22,500

ppm, and"

to read,

2. "A boron concentration between 3.0 wt./ (5245 ppm) and

3.5 wt./ (6119 ppm), and"

change:

3. "A minimum solution temperature of 145'F."

to read,

3. "A minimum boric acid tanks room temperature of 55'F."

Evaluation: The boric acid tank operability requirements are

revised to reflect the analysis of Reference 1. A minimum

volume of 2,900 gallons per unit is specified, and includes an

instrument accuracy of 2.5%%u of full range for the tank level

instrument. Unusable volume is not accounted for here since

the tank level instrumentation will have its indicated range

calibrated to account for unusable volumes at the bottom ofthe tank. The concentration is limited to the recommended

band of 3.0 weight percent to 3.5 weight percent. The

temperature limit corresponds to the solubility limit for 3.5

weight percent boric acid (50'F) with 5'F added margin.


The minimum refueling water storage tank volume is not changed

since this is known to be conservative from the analysis ofReference 1.

S ecification 4. 1.2.4 - Surveillance Re uirement

Change Surveillance Requirement 4.1.2.4.a.3):

"Verifying the boric acid storage tank solution temperature

when it is the source of borated water."

to read,

"Verifying that the temperature of the boric acid tanks room

is greater than or equal to 55'F, when it is the source ofborated water."

Evaluation: The borated water source surveillance requirement

is modified to reflect the reduced boric acid solubilitytemperature. The maximum boric acid concentration to be

specified is 3.5 weight percent with a solubility temperature

limit of 50'F. A margin of 5'F is added to this to make 55'F

the critical temperature for boric acid solubility. The 7 day

surveillance interval is justified because the temperature ofthe room containing the boric acid tanks will be provided with

an alarm in the control room. Action statement requirements

for temperatures below 55'F remain identical to the current

required actions for temperatures below the current limit of145'F. In this respect, the required actions remain as

limiting as the current Technical Specifications.


For the Boric Acid Storage System (3. 1.2.5.a) change:

1. "A minimum indicated borated water volume of 3080

gallons,"

Report No. 849963-MPS-5NISC-003 REV 0 Page 7-5

to read,

1. "A minimum indicated borated water volume in accordance

with Figure 3. 1.2.5,"

change:

2. "A boron concentration between 20,000 ppm and 22,500

ppm, and"

to read,

2. "A boron concentration in accordance with Figure

3. 1.2.5, and"

change:

3. "A minimum solution temperature of 145'F."

to real,

3. "A minimum boric acid tanks room temperature of 55'F."

Action Statement

Add an asterisk (*) to ACTION 'a'o reference a note at the

bottom of the page.

Add note at the bottom of the page:

"* If this action applies to both units simultaneously, be in

at least HOT STANDBY within the next 12 hours."

Add the following:

I


C. With the boric acid tank inventory concentration greaterthan 3.5 wt./, verify that the boric acid solutiontemperature for boration sources and flow paths isgreater than the solubility limit for the concentration.

Add Figure 3.1.2.5 as provided

Evaluation: The boric acid tank operability requirements

regarding volume and concentration will consist of a

concentration vs. volume curve. Note that the volumes

represent the combined volumes in all three tanks withallowance for the minimum required volume for two operatingunits (Modes 1-4) and for one operating and one shutdown unit(Mode 5 or 6). The minimum temperature for boric acid tank

operability coincides with the solubility limit for 3.5 weight

percent boric acid (50'F) plus 5'F margin. ACTION times allow

for an orderly sequential shutdown of both units when the

inoperability of a component(s) affects both units with equal

severity. When a single unit is affected, the time to be in

HOT STANDBY is 6 hours. When an ACTION statement requires a

dual unit shutdown, the time to be in HOT STANDBY is 12 hours.

S ecification 4. 1.2.5 - Surveillance Re uirements

Change Surveillance Requirement 4.1.2.5.a.3) :

"Verifying the Boric Acid Storage System solution temperature

when it is the source of borated water."

to read,

"Verifying that the temperature of the boric acid tanks room

is greater than or equal to 55'F, when it is the source ofborated water."


Evaluation: The borated water source surveillance requirement

is modified to reflect the reduced boric acid solubilitytemperature. The maximum boric acid concentration to be

specified is 3.5 weight percent with a solubility temperature

limit of 50'F. A margin of 5'F is added to this to make 55'F

the critical temperature for boric acid solubility. The 7 day

surveillance interval is justified because the temperature ofthe room containing the boric acid tanks will be provided withan alarm in the control room. Action statement requirements

for temperatures below 55'F remain identical to the currentrequired actions for temperatures below the current limit of145'F. In this respect, the required actions remain as

limiting as the current technical specifications.


Add note at the bottom :

"This is no longer applicable once boric acid tanks inventoryand boric acid source and flow path inventories have been

diluted to less than or equal to 3.5 weight percent (wt.%)."

Evaluation: This specification is retained to allow the

concentration transition (from 12 weight percent boric acid to3.5 weight percent boric acid) of the boric acid tank

inventory and boric acid source and flow path inventories.The boric acid tank operability requirements regarding volume

and concentration will remain in accordance with specification3. 1.2.5. Action statement requirements regarding temperature

and heat tracing remain identical to the current Technical

Specifications. As identified in reference 1, a reduction in

the boric acid concentration corresponds to a reduction in the

solubility limit. FPL remains conservative by maintaining the

boric acid storage tank and flow path temperatures greater

than the appropriate solubility limit.


2. TECHNICAL SPECIFICATION 3/4.9 - REFUELING OPERATIONS

S ecification 3.9. 1 - Action Statement

Substitute "16 gpm" for "4 gpm" and "3.0 wt.% (5245 ppm)" for"20,000 ppm"

Evaluation: Same evaluation as provided for in Specification

3.1.1.1.

3. TECHNICAL SPECIFICATION 3/4.10 - SPECIAL TEST EXCEPTIONS

S ecification 3. 10. 1 - Action Statement


Evaluation: Same evaluation as provided for in Specification3.1.1.1.

4. TECHNICAL SPECIFICATIONS BASES 3/4.1 - REACTIVITY CONTROL

SYSTEMS

S ecification Bases 3 4. 1. 1 - Boration Control


Evaluation: The increase in the required flow rate by a

factor of four (4 gpm to 16 gpm) conservatively accommodates

the decrease in the minimum boric acid tank concentration by a

factor of approximately four (20,000 ppm, or 11.4 weight

percent, down to 3.0 weight percent). This adjustment assures

equal minimum boration capability for shutdown margin recovery

as compared to the current capability at 11.4 weight percent.


The capability to restore the shutdown margin with one

OPERABLE charging pump is consistent with the current

Technical Specifications.

S ecification Bases 3 4. 1.2 - Boration S stems

o Delete the wording:

"(5) associated Heat Tracing Systems, and (6) an

emergency power supply from OPERABLE diesel generators."

Evaluation: Wording revised to reflect the basis ofthis program and the Emergency Power System (EPS)

Enhancement Project submittal.

Insert the wording:

"ACTION times allow for an orderly sequential shutdown

of both units when the inoperability of a component(s)

affects both units with equal severity. When a singleunit is affected, the time tobe in HOT STANDBY is 6

hours. When an ACTION statement requires a dual unitshutdown, the time to be in HOT STANDBY is 12 hours."

Evaluation: Wording inserted to reflect the basis of

the previous EPS Enhancement Project submittal.


"with independent power supplies", and

"However, the ACTION Statement restrictions allow 7 days

to restore an inoperable pump provided that two charging


pumps are available. This restriction is acceptable

based on the low probability of losing the power source

common to both charging pumps."

Substitute the words "Each bus" for "The bus" and the

words "a startup transformer." for "the startuptransformer."

Evaluation: Wording revised to reflect the basis of the

previous EPS Enhancement Project submittal.


"... BOL from full power equilibrium xenon conditions

and require 3080 gallons of 20,000 PPH borated water

from the boric acid storage tanks or 320,000 gallons of1950 PPN borated water from the refueling water storage

tank (RWST)."

and replace with the wording:

"... EOL peak xenon conditions without letdown such thatboration occurs only during the makeup provided forcoolant contraction. This requirement can be met for a

range of boric acid concentrations in the boric acid

tank and the refueling water storage tank. The range ofboric acid tank requirement is defined by Technical

Specification 3. 1.2.5."

o Substitute "2,900 gallons of at least 3.0 wt.% (5245

ppm) borated water per unit" for "500 gallons of 20,000

ppm borated water"


Substitute the wording "... requirement of 55'F and

corresponding surveillance intervals..." for the wording

"... of the redundant heat tracing channels..."

o Insert the wording - "The temperature limit of 55'F

includes a 5'F margin over the 50'F solubility limit of3.5 wt.%%u boric acid. Portable instrumentation may be

used to measure the temperature of the rooms containing

boric acid sources and flow paths."

o Add the footnote - "This is no longer applicable once

boric acid tanks inventory and boric acid source and

flow path inventories have been diluted to less than or

equal to 3.5 weight percent."

Evaluation: The basis for the boric acid tank minimum

volume required for modes 1 through 4 is modified to

reflect the analyses of Reference 1. Specifically, the

worst case expected plant boration requirement occurs at

EOL peak xenon conditions without letdown such thatboration occurs only during the makeup provided forcoolant contraction. This requirement can be met for a

range of boric acid concentrations in the boric acid

tank and the refueling water storage tank. This range

is bounded by Figure 3. 1.2.5.

Below 200'F, the boric acid tank minimum volume

requirement is based on the minimum volume of 3.0 weight

percent boric 'acid required to maintain a 1.0/ ak/k

shutdown margin during a cooldown from 200'F to 140'F.

(The analysis of Reference 1 conservatively assumed

135'F as the cooldown endpoint.) The refueling water

storage tank minimum volume with RCS temperature less

than 200'F remains unchanged since it is conservative

with respect to the cooldown analysis. Reference to


heat tracing in this section is deleted since it isanticipated that all heat tracing will be removed. The

basis of the 55'F temperature limit is established as

the 50'F solubility limit for 3.5 weight percent boricacid plus 5'F margin. Continuous surveillance of the

temperature of the rooms containing boration system flowpaths and components is provided and verified by an

alarm in the control room. A footnote is added to the

heat tracing discussion. This identifies the heat

tracing as not being applicable once boric acid tanks

inventory and source and flow path inventories have been

diluted to less than 3.5 weight percent.

5. TECHNICAL SPECIFICATION BASES 3/4.9 - REFUELING OPERATIONS

S ecification 3 4.9. 1 - Boron Concentration Bases

Substitute the wording "16 gpm of 3.0 wt.h (5245 ppm)" for "4

gpm of 20,000 ppm".

Evaluation: Same as Specification Bases 3/4. 1. 1

7.2 NO SIGNIFICANT HAZARDS EVALUATION

The proposed changes have been deemed not to involve a significanthazards consideration focusing on the three standards set forth in

10 CFR 50.92(c) as quoted below:

The Commission may make a final determination, pursuant to the

procedures in 50.91, that a proposed amendment to an operating

license for a facility licensed under 50.21(b) or 50.22 or for a

testing facility involves no significant hazards considerations, ifoperation of the facility in accordance with the proposed amendment

would not:


1. Involve a significant increase in the probability or

consequences of an accident previously evaluated; or

2. Create the possibility of a new or different kind of accident

from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety.

It has been determined that the activities associated with thisamendment request do not meet any of the significant hazards

consideration standards of 10 CFR 50.92(c) and, accordingly, a no

significant hazards consideration finding is justified. A

discussion of each of the above three significant hazards

consideration standards is provided below.

Introduction

The current Turkey Point CVCS design employs three boric acid tanks,

containing 12 weight percent (wt.l) boric acid, for the two units.One tank is dedicated to each unit and the third is available as a

backup for either dedicated tank. Each dedicated tank has adequate

volume to store the cold shutdown boric acid volume required for one

unit. The boric acid tanks provide a source of concentrated boric

acid to the reactor to offset slow reactivity changes caused by

normal changes in power level, or to establish hot shutdown, cold

shutdown or refueling shutdown conditions. The safety function ofthe boric acid tanks is to maintain adequate boric acid volume and

concentration to borate the RCS to a cold shutdown concentration at

any time during the core cycle, with a shutdown margin consistent

with the Technical Specifications.

A reduction in the boric acid concentration to 3.0 to 3.5 weight

percent provides the opportunity to delete the system heat tracing

presently required for 12 weight percent boric acid. The basis fordeletion is the corresponding reduction in the solubility


temperature from 135'F for 12 weight percent boric acid to 50'F for3.5 weight percent boric acid. At this lower solubilitytemperature, the normally occurring ambient room temperatures are

adequate to maintain fluid temperatures above the solubility limitrather than relying on tank heaters or heat tracing.

This proposed amendment improves the availability of the boration

system and, therefore, improves plant safety. It also reduces

routine maintenance requirements by eliminating the need for boricacid tank internal heaters and boration flow path heat tracingchannels. Furthermore, potential problems associated with boricacid crystalization, flow path blockage, and component corrosion are

significantly reduced.

Evaluation

The following evaluation demonstrates that the proposed amendment

involves no significant hazards considerations.

1. Involve a si nificant increase in the robabilit or

conse uences of an accident reviousl evaluated.

The operation of the facility in accordance with the proposed

changes does not involve a significant increase in the

probability or consequences of any accident previouslyevaluated. Deleting the requirement for a heat tracingcircuit by reducing the boron concentration in the boric acid

tank is accounted for by increasing the volume of boric acid

solution that must be contained in the tanks and also by

crediting borated water from the refueling water storage tank.

Since the components (or their function) necessary to perform

a safe shutdown have not been changed or modified, this change

does not significantly increase the probability or

consequences of any accident previously evaluated. In


addition, technical specification controls on the boric acid

tank temperature and boron concentration ensure that the lackof heat tracing does not result in precipitation of the boron.

Credit is not taken for boron addition to the RCS from the

boric acid tanks for the purpose of reactivity control in theaccidents analyzed in Chapter 14 of the Final Safety AnalysisReport. Response to such events as steam line break, over-

cooling, boron dilution, etc. will not be affected by a

reduction in the boric acid tank concentration.

The action statements associated with Technical Specification3. l. l. 1 currently require that boration be commenced atgreater than 4 gallons per minute using a solution of at least20,000 ppm boron in the event that shutdown margin is lost.This Specification has been changed to 16 gpm at 3.0 weight

percent (5245 ppm) to accomplish the same minimum borationrate. A plant modification to flow control valve FCV-113A

will increase blended makeup capacity and assure this system's

capability to deliver this flow rate. Boration via the

emergency boration flow path already exits at a rate of 60 gpm

(nominal).

2. Create the ossibilit of a new or different kind of accident

from an accident reviousl evaluated.


changes does not create the possibility of a new or differentkind of accident from any accident previously evaluated. This

is because such operation will not increase the likelihood ofboric acid source or flow path failure nor will such failuresinitiate any new or different kind of accident from any

previously evaluated. The boron dilution analysis performed

for Turkey Point Units 3 and 4 is not impacted by a reduction

from a nominal 12 weight percent boric acid to 3.0 to 3.5


weight percent. The boron concentration in the boric acid

tanks is greater than any anticipated RCS boron concentration,thus, an inadvertent RCS boron dilution due to the addition ofboric acid from the boric acid tanks is precluded.

The reason for requiring a heat tracing circuit was to ensure

that the dissolved boric acid remained in solution and, hence,

available for injection into the RCS to adjust core reactivitythroughout core life. By lowering the boron concentration toa maximum of 3.5 weight percent, chemical analyses have shown

there is no possibility of the boron precipitating out ofsolution as long as the temperature of the boric acid solutionremains above 50'F. Normal ambient temperatures in the

vicinity of these components remain above this temperature.

Therefore, there is no longer a need for heat tracing. Since

the boron will be in solution when the boric acid tank flowpaths are credited for reactivity control during a cooldown tocold shutdown scenario, heat tracing is no longer required tomaintain the boric acid storage system operable. In

conclusion, this change does not create the possibility of a

new or different kind of accident from those previouslyevaluated.

3. Involve a si nificant reduction in a mar in of safet .


Technical Specification changes does not involve a significantreduction in the margin of safety. The intent of these

Technical Specifications is to ensure that there are two

independent flow paths from the two independent borated water

sources (boric acid tanks and refueling water storage tank) to

the RCS to allow control of core reactivity throughout core

life. This requires that sufficient quantities of boron be

stored in the tanks, and that this borated water can be


delivered to the RCS when required. Reducing the maximum

boric acid concentration to less than or equal to 3.5 weightpercent has been compensated for by increasing the requiredvolumes of borated water. Elimination of the separationcriteria for the flow paths for the two units between thethree shared boric acid tanks and the boric acid transferpumps has been compensated for by technical specificationvolume control that accounts for the needs of both units.

In addition to the boric acid transfer pumps delivering theboric acid tank contents to the charging pumps, the charging

pumps also can take suction from the refueling water storagetank. Since these independent boration capabilities controlthe RCS boron inventory, the original licensing basis of theplant does not require the boric acid tanks to meet singlefailure criteria.

Additionally, reducing the maximum boron concentration allowsa deletion of the requirement to heat trace the boric acid

storage system since chemical analyses have shown that a 3.5weight percent solution of boric acid will remain in solutionat temperatures above 50'F. An operability requirement of55'F minimum temperature for the rooms containing borationsources and flow paths includes a 5'F margin above the

solubility limit of 50'F. Technical Specification controls on

the boric acid tank and boration flow path room temperatures

and boron concentration ensure that a lack of heat tracingdoes not result in precipitation of the boron.

In conclusion, the reduction of boric acid concentration and

the deletion of heat tracing in the Horic Acid Makeup System

does not cause a significant reduction in the margin of safetyfor this plant.


~Summar

In summation, it has been shown that the proposed

modifications and proposed Technical Specifications do not:

I. Involve a significant increase in the probability orconsequences of an accident previously evaluated; or

2. Create the possibility of a new or different kind ofaccident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety.

Therefore, it is determined that the proposed amendment

involves no significant hazards considerations.


8.0 SAFETY EVALUATION

Operation with reduced boric acid concentration in a manner similarto that analyzed in Sections 5 and 6 will involve a change in themanner in which the facility is operated as compared to the currentdescriptions in the updated Final Safety Analysis Report (FSAR).

Reference 10.3 was reviewed in detail to identify the necessary

changes to reflect full implementation of reduced boric acidconcentration. Although, changes are required in several locations,the changes consist of the following basic elements:

1. Revision of boric acid tank concentration range (3.0 to 3.5weight percent);

2. Revision of boric acid tank minimum volume design basis toinclude:

a. Boration completed in conjunction with the makeup forcoolant contraction during cooldown,

b. Credit given to refueling water storage tank volume;

3. Revision of alternate shutdown capability (boration rate);

4. Deletion of heat tracing and boric acid tank heaters; and,

5. Revision of boric acid evaporator bottoms concentration.

Specific descriptions of each of these changes is provided in

Section 8. 1. This will be followed by a No Unreviewed Safety

guestion evaluation in Section 8.2.

8.1 RECOMMENDED FSAR CHANGES

Recommended markups of the specific pages to be changed are provided

in Appendix 7. The following is a page by page discussion of the

recommended changes.


Pa e 1.3-13

The design basis of the minimum volume maintained in the boric acidtank is revised to reflect the analyses of Section 5.0.Specifically, the minimum volume maintained in this tank is thatvolume necessary to increase the RCS boron concentration during thecourse of a cooldown, through makeup for coolant contraction alone,such that subsequent use of the refueling water storage tank forcontraction makeup will maintain adequate shutdown margin throughoutthe remaining cooldown.

Additionally, the alternate shutdown capability is revised toreflect the analysis of Section 6.6.3. Less than forty minutes offeed and bleed would be required to raise the RCS boron

concentration from 1100 ppm to 1295 ppm. Since both sixteen minuteperiods listed in the FSAR are feed and bleeds per Reference 10. 1,forty minutes should be required to accomplish the second borationrequirement to compensate for xenon decay.

Outside power is corrected to Offsite power and reference to hotshutdown is corrected to hot standby.

Pa e 3.1.2-6

Same as page 1.3-13.

Pa e 8.2-18

Reference to the boric acid tank heaters is deleted since these

heaters will be electrically deenergized.

Pa e 9.2-3



Pa e 9.2-6

The boric acid tank concentration is revised to 3.0 to 3.5 weightpercent and all reference to heat tracing is deleted. It isanticipated that all heat tracing circuits will be disconnectedsince the ambient temperatures within the auxiliary building willmaintain boric acid tank and boration flow path temperatures above

the solubility limit of 50'F.

Pa e 9.2-6a

Same as page 9.2-6.

Pa e 9.2-7

Same as page 9.2-6.

Pa e 9.2-8

Operation of the boric acid evaporator must be revised such that theboric acid that remain's within the evaporator as the bottoms of thedistillation process does not concentrate above the boric acid tankcontrol band of 3.0 to 3.5 weight percent.

Pa e 9.2-11

The discussion of boration without letdown is modified toincorporate the analyses of Section 5.0 and Section 6.6.3.Specifically, since the boric acid tank concentration is reduced by

a factor of four, the volume required to be charged using the

available volume in the pressurizer has increased by a factor offour. Achieving boration to the cold shutdown concentration through

this method, therefore, is not possible with reduced concentrations.Per the analysis of Section 6.6.3, however, boration to hot zero

power is achievable using the available volume in the pressurizer.


Boration to cold shutdown is still achievable without letdown usingthe methodology outlined in Section 5.0. Specifically, if boricacid is injected to maintain constant pressurizer level during a

cooldown to cold shutdown (using a boric acid tank and the refuelingwater storage tank to make up for coolant contraction) sufficientboric acid will be added to the RCS to maintain the requiredshutdown margins.

Pa e 9.2-23

The design basis of the boric acid tank minimum volume is modifiedper the discussion for page 1.3-13 changes. Batching tankcapabilities are revised to reflect the impact of reduced

concentrations.

Pa e 9.2-24

The batching tank steam jacket design basis is modified to maintainthe boric acid batching solutions above the solubility limit withoutspecific reference to temperature limits. The addition of the perunit qualifier to the boric acid transfer pump description reflectsthe actual redundancy of the pumps.

Pa e 9.2-27

Same as page 9.2-8.

Pa e 9.2-29

Reference to boration system heat tracing is deleted since it isanticipated that all heat racing will be removed. This isachievable since the normally expected ambient temperatures withinthe auxiliary building will maintain system temperatures above thesolubility limit of

50'F.'eport

No. 849963-MPS-5MISC-003 REV 0 Page 8-4

Pa e 9.2-30


Pa e 9.2-31


Table 9.2-2

The maximum rate of boration is revised based on the analysis ofSection 6.2. A feed and bleed of 60 gpm will establish a borationrate of 5.4 ppm per minute starting from the 1800 ppm initialconcentration listed in the table. Should the available volume inthe pressurizer be utilized in accordance with the analysis ofSection 6.6.3, a boration of 195 ppm in 29.4 minutes (6.6 ppm perminute) is achievable starting from the assumed maximum BOC

concentration of 1100 ppm. The equivalent cooldown rate was dividedby the same factor of reduction shown for the maximum boration rate.

The boric acid tank minimum volume is revised per the analyses ofSection 5.0 as discussed for changes to page 9.2-3. A curve similarto the recommended technical specification is suggested forinclusion in the FSAR.

Table 9.2-3

The boric acid tank is being modified to maximize the usable volume.

This table should be updated once the maximum available volume isidentified.

Additionally, the refueling water storage tank is added to the listof tanks available to the CYCS. This reflects the possible use ofthis tank for contraction makeup during the design basis cooldown

analyzed in Section 5.0.


8.2 NO UNREVIEMED SAFETY QUESTIONS DETERHINATION

Introduction

The current Turkey Point CVCS design employs three boric acid tankscontaining 12 weight percent boric acid shared between the two

units. One tank is currently dedicated to each unit and the thirdis currently available as a backup for either dedicated tank. Each

dedicated tank has adequate volume to store the cold shutdown boricacid volume required for one unit.

The boric acid tanks provide a source of concentrated boric acid tothe reactor to offset slow reactivity changes caused by normal

changes in power level, or to establish hot shutdown, cold shutdown

or refueling shutdown conditions. The safety function of the boricacid tanks is to maintain adequate boric acid volume and

concentration to borate the RCS to a cold shutdown concentration atany time during the core cycle, with a shutdown margin consistentwith the technical specifications.

The high boron solubility temperature required by 12 weightpercent boric acid (135'F minimum) is maintained by internal tankheaters and flow path heat tracing. The need to perform maintenance

on the heaters and heat tracing affects the'availability of the

boric acid tanks. Therefore, the capability to perform maintenance

on the boric acid tank without taking the units off-line was

considered necessary for the present CVCS design. This capabilityis currently accomplished by the backup tank. The third boric acid

tank, as a backup tank, permits either dedicated tank to be taken

out-of-service for maintenance while both units remain on-line.

A reduction in the boric acid concentration to 3.0 to 3.5 weight

percent provides the opportunity to delete system heat tracing,presently required for 12 weight percent boric acid. The basis fordeletion is the corresponding reduction in the solubility


temperature from 135 F for 12 weight percent boric acid to 50 F for3.5 weight percent boric acid. At this lower concentration, thenormally occurring ambient room temperatures are adequate tomaintain fluid temperatures above the solubility limit without usingtank heaters or heat tracing.

The proposed modification would improve plant availability and

reduces maintenance requirements by eliminating the demand of theboric acid tank internal heaters and boration flow path heat tracingchannels.

Evaluation

An evaluation of the Turkey Point CVCS boration capabilities was

completed in Sections 5.0 and 6.0 of this report. Specifically, theanalysis of Section 5.0 justified a reduction in the concentrationof boric acid maintained in the boric acid tanks from 12 weightpercent down to a range of 3.0 to 3.5 weight percent. This was

accomplished by demonstrating that the required shutdown margin

could be maintained during a cooldown if boration was accomplished

in conjunction with the makeup for coolant contraction. This

analysis was completed with the following significant changes from

the current manner in which a cooldown to cold shutdown isaccomplished:

1. Basis: Cooldown transient initiated from peak xenon

concentration (8 hours) without the use of letdown;

2. Heans: Boration accomplished only through the makeup provided

for coolant contraction; and,

3. Sources: Credit given to the availability of refueling water

storage tank volume to supplement the boron addition of the

boric acid tanks.


4. Configuration: Tank lineup consisting of all three tanks linedup to the common suction header for the boric acid transferpumps.

The acceptability of these considerations from the perspective ofplant safety is reviewed in the following safety evaluation. The

considerations discussed above, in conjunction with the reduced

boric acid tank inventory concentrations, have been found not toraise an unreviewed safety question as documented in the following.

As defined in IOCFR50.59, an unreviewed safety question exists: (i)if the probability of occurrence or the consequences of an accidentor malfunction of equipment important to safety previously evaluated

V

in the Updated Final Safety Analysis Report (FSAR) may be increased;or (ii) if a possibility of an accident or malfunction of a

different type than any previously evaluated in the FSAR may be

created; or (iii) if the margin of safety as defined in the basis ofany Technical Specification is reduced.

In accordance with IOCFR50.59, the following evaluation serves todetermine whether this modification constitutes an unreviewed safetyquestion:

1. Does the ro osed chan e increase the robabilit of occurrence

of an accident reviousl evaluated in the FSAR?

The probability of occurrence of an accident previouslyevaluated in the FSAR will not increase because thismodification does not affect any equipment whose malfunction ispostulated in the FSAR to initiate an accident. Specifically,maintenance of shutdown margin in accordance with technicalspecification limits during plant cooldowns assures the

acceptability of reactivity excursions analyzed in the FSAR.

Borating the plant through the makeup for coolant contractionduring a plant cooldown has been shown to maintain RCS boron

Report No. 849963-NPS-5NISC-003 REV 0 Page 8-8

concentration well above that required to maintain adequate

shutdown margin.

The boron dilution analysis performed for Turkey Point Units 3

and 4 is not impacted by a reduction in boric acidconcentration from a nominal 12 weight percent down to 3.0 to3.5 weight percent. The boron concentration in the boric acidtanks is greater than any anticipated RCS boron concentrationand thus, an inadvertent RCS boron dilution due to the additionof boric acid from the boric acid tanks is precluded.

Therefore, the probability of an accident previously evaluatedin the FSAR would not be increased.

2. Does the ro osed chan e increase the conse uences of an

accident reviousl evaluated in the FSARP

The consequences of an accident previously evaluated in theFSAR will not increase because the equipment affected by these

modifications is not credited for operation during any

accidents analyzed in the FSAR. System operation ormalfunction will not impact the consequences of any of these

analyses nor will it affect any other equipment whose

malfunction could adversely affect any safety relatedstructures, systems, or components. With the proposed

modification to FCV-113A, an equivalent boration capability has

been retained such that response to any event requiringemergency boration is not adversely impacted.

Therefore, the consequences of an accident previously evaluated

in the FSAR would not be increased.


3. Does the ro osed chan e increase the robabilit of an

occurrence of a malfunction of e ui ment im ortant to safetreviousl evaluated in the FSAR7

The pr'oposed reduction in boric acid concentration for TurkeyPoint Units 3 and 4, will not adversely impact the structuralintegrity or performance capability of the boric acid tanks,heaters, pumps, and associated piping, valves and

instrumentation. A reduction in the boric acid concentrationto 3.0 to 3.5 weight percent provides the opportunity to deletesystem heat tracing, and subsequently, provides the potentialto reduce maintenance requirements. In addition, since thecorrosive property of boric acid is accelerated at higherconcentrations and temperatures, nominal 3.25 weight percentboric acid actually decreases the potential for corrosion ofequipment, valves and piping surfaces.

Thus, the probability of a malfunction of equipment importantto safety previously evaluated in the FSAR would not be

increased.

4. Does the ro osed chan e increase the conse uences of a

malfunction of e ui ment im ortant to safet reviouslevaluated in the FSAR?

The consequences of a malfunction of equipment important tosafety are not increased by this modification from thatpreviously evaluated in the FSAR. This is because the

oper ation of the equipment affected by this modification is not

credited in any of the equipment malfunctions analyzed in the

safety analysis report. The consequences of these events,

therefore, remain unchanged.

Therefore, the boric acid tanks continue to provide a source ofconcentrated boric acid to the reactor for offsetting slow


reactivity changes caused by normal changes in power level, orto establish hot shutdown, cold shutdown or refueling shutdown

conditions, and the consequences of a malfunction of equipment

important to safety previously evaluated in the FSAR would not

be increased.

5. Does the ro osed chan e create the ossibilit of an accidentof a different t e than an reviousl evaluated in the FSAR?

While this approach modifies the system configuration(interconnection and sharing of all three tanks) and the design

basis of the boration sources, it does not introduce failuremodes of a different type than any previously analyzed in the

FSAR. Specifically, the likelihood of a boric acid tank,transfer pump, flow path or charging pump failure is not

increased. In addition, none of these failures initiates a new

and different kind of accident from any previously evaluated.

Therefore, there is no possibility that an accident may be

created that is different from any already evaluated in the

FSAR.

6. Does the ro osed chan e create the ossibilit of .a

malfunction of e ui ment im ortant to safet of a differentt e than an reviousl evaluated in the FSAR?

While this approach modifies the system configuration(interconnection and sharing of three tanks) and the design

basis of the boration sources, it does not introduce failuremodes of a different type than any previously analyzed in the

FSAR.

A reduction from nominal 12 weight percent boric acid to 3.0 ton

3.5 weight percent boric acid concentration will not adversely

impact the structural integrity or performance capability of


the boric acid tanks, heaters, pumps, associated piping,valves, instrumentation, or related equipment. A reduced boricacid concentration provides the opportunity to delete systemheat tracing. Elimination of the technical specificationrequirement for heat tracing will eliminate the time spent inaction statements due to inoperability of the heat tracingchannels.

In addition, a reduction in boric acid concentration reduces

the potential for precipitation of boric acid crystals.Elimination or reduction of precipitation will reduce

maintenance requirements on equipment susceptible to boron

precipitation.

Therefore, the possibility of a malfunction of equipment

important to safety different than any already evaluated in theFSAR will not be created.

7. Does the ro osed chan e reduce the mar in of safet as definedin the basis for an Technical S ecifications?

The design basis of the boration subsystem of the CVCS is toprovide a sufficient volume of boric acid at a concentrationthat will maintain shutdown margin during a design basiscooldown. While the design basis cooldown has been modifiedwith regard to boration methodology, the design basis, functionor operating logic of any safety related equipment has not been

changed. Additionally, this change does not adversely affectany other safety related structures, systems and components.

Therefore, this modification does not reduce the margin ofsafety as defined in the bases for the TechnicalSpecifications. The technical specifications of particularinterest include: 3.4. 1. 1, Boration Control; 3/4. 1.2, Boration

systems; 3/4.9. 1, Boron Concentration (Refueling); and 3/4. 10. 1

Shutdown margin (Special Test Exceptions). Changes to these


Specifications have been recommended in Section 7.0 and are

required to implement the analysis results of Section 5.0.

Complete implementation of the boric acid concentrationreduction will entail some plant modification. Specifically,the proposed flow control valve modification increases its flowcapacity so that the boration rate achievable through thisvalve for the normal blended or manual boration flowpath atleast matches the current boration rate achievable with higherboric acid concentrations.

Removal of heat tracing does not lower any margins of safetyfor boration source and flow path requirements because theconcentration of boric acid has been decreased sufficiently toallow Auxiliary Building ambient temperatures to maintain boron

solubility. The 5'F margin on top of the 50'F solubility limittemperature for the maximum allowable boric acid concentrationassures that ambient temperatures will maintain source and flowpath operability with the same margin of safety as theinstalled heat tracing used for 12 weight percent boric acid.

In addition to the boric acid transfer pumps delivering the

boric acid tank contents to the charging pumps, the charging

pumps also can take suction from the refueling water storagetank. Due to these redundant sources of boration capabilityprovided by the Turkey Point CVCS to control the RCS boron

inventory, the original licensing basis of the plant does not

require the boric acid tanks to meet single failure criteria.Sharing the three boric acid tanks, therefore, is acceptable

with appropriate technical specification controls over the

minimum available volume to account for the needs of both

units.


Plant Restrictions

None.

Conclusions

This modification has been reviewed against the requirements of10CFR50.59 and has been found not to constitute an unreviewed safetyquestion.


9.0 OPERATING PROCEDURE GUIDELINES

Section 5.0 provides technical justification for reduction of boricacid tank concentrations and minimization of required volumes.

These analyses were based on a worst case cooldown scenario where

letdown was not available. Hence, boration to cold shutdown limitshad to occur in conjunction with the cooldown evolution (i.e.,through makeup for coolant contraction).

Normal'ooldowns, however, do not have to be conducted in thismanner. FPL may opt to minimize the impact on operating proceduresand continue the current practice of borating to the cold shutdown

limit through a feed and bTeed process (prior to initiatingcooldown). Then a blended makeup will be provided during thecooldown process to maintain the boron concentration. This processwill require greater volumes from the boric acid tank(s) and, hence,

more frequent boric acid batching as discussed in Section 6.5.

If this is the option FPL selects, procedure changes will be limitedto such items as the following:

1. Delete heat tracing related procedures to the extent that allheat tracing is disconnected and removed.

2. Revise all procedures that reference the boric acid tankavailable (usable) volume, minimum required volumes, and boricacid concentration ranges.

3. Revise the emergency boration procedure (Reference 10. 12) toreflect the analysis of Section 6.6.3.

4. - Revise procedures for operation of the boric acid evaporator tomaintain the boric acid concentration of the bottoms of thedistillation process within the new boric acid tank controlband of 3.0 to 3.5 weight percent.

Report No. 849963-MPS-5NISC-003 Rev. 0 Page 9-1

5. Revise procedures for boric acid blender operation (or ones

that reference blender capacity) to reflect the proposedmodification to FCV-113A (PC/H as-building).

6. Revise procedures for boric acid batching to reflect the new

boric acid concentration range of 3.0 to 3.5 weight percent.

7. Develop a procedure to conduct a cooldown in response to thescenario analyzed in Section 5.0. Such a procedure would be

required for cases where a cooldown would be necessary on one

boric acid tank (and the refueling water storage tank) or forcases where letdown is not available. Such a procedure should

make provisions for more frequent boron sampling during thecooldown process.

8. The analysis presented in Sections 5 and 6 assumed an RHR boron

concentration in the range of 500 to 800 ppm boron. This is a

realistic assumption given that cold shutdown boron

concentrations are maintained in the RCS/RHR until after theRCS is disconnected from the RHR. Efforts should be made toensure the RHR concentration is maintained as high as

reasonably possible so that the boron addition from this system

will help minimize batching requirements. This would entailrecirculating portions of the system that have this capabilityand refilling it with borated water whenever the system isdrained for maintenance.

If all subsequent cooldowns are to be completed in the manner

described in Section 5 (i.e., boration in conjunction with cooldown)

all shutdown, cooldown, and boration related procedures will requiremodification in addition to the changes discussed above. Provisionsshould be made, however, to accommodate the use of letdown, batching

to replenish boric acid, and desired plant lineups to accommodate

this mode of operation.

Report No. 849963-NPS-SNISC-003 Rev. 0 Page 9-2

Optimum use can be made of the available boric acid by considerationof the following:

l. Haintain boric acid tanks as full as possible. Align thesuctions of all transfer pumps to all three tanks, therebyinterconnecting the three tanks. Allow the technicalspecification minimum allowable volume for both units to be

spread among the three tanks. This will maximize the volume

available in the tanks for day to day boration needs.

2. When using one or more boric acid tanks as the source ofboration (emergency, manual, or blended) with RCP seal

injection in service, borated water will be lost to the VCT viaRCP seal leakoff (nominally 9 gpm) if the VCT is isolated(isolation valve shut or check valve seated). The batchingevaluation of Section 6.5 assumed this to be the case tomaximize the volumes required for feed and bleeds and blended

makeup operations. By adjusting charging pump speed

accordingly to provide seal injection flow from the VCT, theconcentrated boric acid diverted to the VCT will be utilized.In this manner, VCT level should remain roughly constant, and

eventual loss of RCP seal leakoff to the holdup tank (via VCT

pressure relief) will not occur.


10.0

10.1

10.2

10.3

10.4

10.5

10.6

10.7

10.8

10.9

REFERENCES

Turkey Point Units 3 and 4 Design Basis Document, Chemical andVolume Control System, 5610-046-DB-001, Revision l.Turkey Point Units 3 and 4 Design Basis Document, Chemical andVolume Control System, 5610-046-DB-002, Revision l.Turkey Point Units 3 and 4 Updated Final Safety Analysis Report(UFSAR), Revision 8.

Deleted

Turkey Point Units 3 and 4 10CFR50 Appendix R Fire ProtectionReview.

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251, RevisedTechnical S ecifications, Amendments 137 and 132.

C-E Letter F-CE-10852, J. H. Westhoven (CE) to S. T. Hale (FPL)dated February 23, 1990; Proposal 90-241-55A.

FPL Purchase Order No. B90671-10032, DWA No. 626610.

Technical Data Sheet IC-ll, US Borax and Chemical Corporation,3-83-J. W.

10. 10 Turkey Point Emergency Operating Procedure 3/4-EOP-ES-0.2, NaturalCirculation Cooldown.

10. 11 ASHE Steam Tables, Third Edition.

10. 12 Turkey Point Operating Procedure 3/4-ONOP-046. 1, Emergency Boration.

10. 13 Crane, Flow of Fluids Through Valves, Fittings and Pipe TechnicalPaper No. 410, 1981.

Report No. 849963-NPS-5NISC-003 Rev. 0 Page 10-1

BORIC ACID CONCENTRATION REDUCTION

TECHNICAL BASES

AND

OPERATIONAL ANALYSES

APPENDICES

Report No. 849963-HPS-5HISC-003 Rev. 0

Appendix 1

Derivation of the Reactor Coolant System

Feed-and-Bleed Equation

Pur ose of Definitions

This appendix presents the detailed derivation of an equation which can

be used to compute the reactor coolant system (RCS) boron concentrationchange during a feed and bleed operation. For this derivation, thefollowing definitions were used:

m,.n = mass flowrate into the RCS

mout mass f1 owrate out of the RCS

mb= boron mass flowrate

mw water mass flowrate

mb- boron mass

mw- water mass

C,.n = boron concentration going into RCS

Gout boron concentrati on go ing out of RCS

C - initial boron concentration0

C(t) = boron concentration as a function of time

CRCS= RCS boron concentration

Sim lif in Assum tions

During a feed and bleed operation, the RCS can be pictured as a closed

container having a certain volume, a certain mass, and an initial boron

concentration. Coolant is added at one end via the charging pumps. The

rate of addition is dependent on the number of charging pumps that are

running with the concentration being determined by the operator. Coolant

is removed at the other end via letdown at a rate that is approximately

equal to the charging rate and at a concentration determined by fluidmixing within the RCS. The mass flowrate into the RCS is given by the

following equation:

in b w in

For typical boron concentrations within the chemical and volume controlsystem, m„ is very much greater than mb. (For example, a 3.5 weightpercent boric acid solution contains only 0.04 ibm of boric acid per ibmof water). Therefore, the above equation can be simplified to thefollowing:

ln W 1tl (I.0)

In a similar manner, the mass flowrate coming out of the RCS, given by

~ ~

out b ™wout

can be simplified by again realizing that m is very much greater than mb

or

out~ ™w out (2 0)

For a feed and bleed operation with a constant pressurizer level and a

constant system temperature, the mass flowrate into the RCS will be equal

to the mass flowrate out of the RCS, or

in out w in w out (3.0)

Finally, if it assumed that the boron which is added to the RCS mixes

completely and instantly with the entire RCS mass, the concentration ofthe fluid coming out of the system will be equal to the system

concentration, or

out RCS(4.0)

Derivation

THe rate of change of boron mass within the RCS is equal to the mass ofboron being charged into the system minus the mass of boron leaving vialetdown. In equation form, this becomes

AI-2

b RCS min in-

mout outdt

From Equation 3.0,

b RCS m. (CD - C ut) — (m )i„(Ci„ - C ut)1 1(5.0)

The concentration of boron in the RCS, (i.e., the weight fraction ofboron), is defined as follows:

m

RCS =

b w RCS

Since mw » mb,

C mbRCS =—

w RCS

Where (mRCS

is a constant for a constant system temperature. The rateof change of the RCS concentration is, therefore:

d( b)RCSdc dt

(4) RCS

(6.0)

Substituting Equation 5.0 into Equation 6.0 yields the following:

dC ( w in ( in out)RCS =

dt w RCS

and from Equation 4.0,

dC w)in (C,.n -CRCS

RCS—dt w RCS

(7.0)

Solving Equation 7.0 for concentration yields:

dCRCS (m ).dt

Cin-

CRCS (mw RCS

C(t)

RCS ( w)in

in RCS w RCS

C

Integrating from some initial concentration C to some finalconcentration C(t) and multiplying through by negative one gives the

following:

or

ln (CRCS- CIN)

C(t)

C

(S)in( w)RCS

C(t) - C,.n (mw),.nln =- t

o in (w) RCS

Continuing to solve for C(t), this equation becomes:

or

~Ct -Ci e win wRCS-(I ). t/ (m )

o in

-(m„..)in t / (m„., )RCSC(t) = C,.n + (C - C,.n) e

" " " (8.0)

If we define the time constant T to be as follows:

( w) RCS

(m„)in

then Equation 8.0 becomes

C(t) = C, e t/T+C,.n (1

-t/T) (g 0)

Appendix 2

A Proof that Final System Concentration isIndependent of System Volume

Pur ose of Definitions

This appendix presents a detailed proof that during a plant cooldown

where an operator is charging only as necessary to makeup for coolantcontraction, the final system concentration that results using a givenboration source concentration will be independent of the total system

volume. For this proof, the following definitions were used:

c. = initial boron concentration Plant 11

mb. = initial boron mass Plant 1bimw,. initial water mass Plant 1

cf = final boron concentration Plant 1

c = boron concentration of makeup solution Plant 1a

mb= mass of boron added Plant 1

ba

mw- mass of water added Plant 1

mbf final boron mass Plant 1

CD = initial boron concentration Plant 21

Hb. = initial boron mass Plant 2biH . = initial water mass Plant 2

wiCf = final boron concentration Plant 2

C = boron concentration of makeup solution Plant 2a

Hb = mass of boron added Plant 2ba

N„ = mass of water added Plant 2

Proof

For this proof, consider two plants at the same initial temperature, the

same initial pressure, and the same initial boron concentration. One

plant, Plant 2, has exactly twice the system volume as the other plant,Plant l. Initially, boron concentration Plant 1 boron concentration

Plant 2,

or

c -C- bib,. * ~ . ~b. ~

1 w1(1.0)

Since the volume of Plant 2 is twice that of Plant 1 M = 2mWl wl

Substituting this relationship into Equation 1.0 and solving yieldsthe following:

bimbi + wi bi wib''™i bi b' bi

and

Mbi 2mbi (2.0)

Therefore, the initial boron mass in Plant 2 is exactly twice the initialboron mass in Plant 1.

During the cooldown process for Plant 1, the final boron mass in thesystem will equal the initial boron mass plus the added boron mass, or

mbf mbi + mba (3.0)

If, during this cooldown process, operators charge only as necessary tomakeup for coolant contraction, water and boron will be added only as

space is made available in the system due to coolant shrinkage. The

final boron concentration from Equation 3.0 can therefore be expressed as

follows:m bf

bf bi ba™wi wa m .+m +m . +mbi ba mwi wa

If concentration is expressed in terms of weight percent, this lastequation becomes

mbf =mbi ™ba + mwi + mwa cf (4.0)

A2-2

Similarly, the remaining two components of Equation 3.0 become

IAb ~ =mba

+ Al ~ cd (5.0)

and

ba ™ba wa a (6.0)

Substituting Equations 4.0, 5.0, and 6.0 into Equation 3.0 and solvingfor the final concentration yields the following:

m' +m''+ IAb +Al cbl Wl 1

Aiba+ mb + .+ (7.0)

For Plant 2, Equation 7.0 becomes

bl wl 1Mb. + M . C. + Mb + M C

bi ba wi wa(8.0)

During a cooldown, the shrinkage mass, (i.e., the mass of fluid that must

be added to the system in order to keep pressurizer level constant), iscalculated by dividing the system volume by the change in specificvolume, or

and

S stem Volume Plant 1

wa a peel 1 c vo UAle

S stem Volume Plant 2wa a peel lc vo ume

(9 0)

(10.0)

where System Volume Plant 1 = (1/2) System Volume Plant 2.

For a given cooldown, dividing Equation 9.0 by Equation 10.0 gives the

following:

Mw= 2mw (11.0)

A2-3

In addition, if the charging source for both plants is at the same

concentration and temperature,

Ca ca (12.0)

and

Mb 2mb (13.0)

Substituting Equations 2.0, 11.0, 12,0, and 13.0 into Equation 8.0yields the following:

2mbi + Mwi C. + 2mba + 2mw

+ + M . +

Since the initial concentrations are the same, C. - c., and since1 1

Plant 2 is twice as large as Plant 1, M„. = 2mw.,wi wi

Cf =2mbi + 2mwi i + 2mba + 2mwa ca -'

mba+

b+ ~ + m

or

(14.0)

Therefore, for a cooldown where pressurizer level is maintained

constant, the final boron concentration for Plant 2 is equal to thefinal boron concentration for Plant 1 (i.e., the change in boron

concentration is independent of the exact system volume).

A2-4

Appendix 3

Methodology for Calculating Dissolved Boric Acid

per Gallon of Water

~Pur ose

The purpose of this appendix is to show the methodology used to calculatethe mass of boric acid dissolved in each gallon of water for solutions ofvarious boric acid concentrations. Two solution temperatures are

presented corresponding to the maximum expected refueling water tank and

boric acid tank temperature of 120 F and a nominal temperature of 70 F.

Methodolo and Results

Boric acid concentration expressed in terms of weight percent is definedas follows:

or

Cmass of boric acid „ 100tota so u >on mass

mass of boric acidmass o oretc aci + mass o water (1 0)

If we define mb to be the mass of boric acid and mw to be the mass

of water, and if we substitute these defined terms into Equation 1.0

and solve for the mass of boric acid we have the following:

'ba 'wor

A3-1

From Appendix A of the Crane Company Manual (Flow of Fluids Through

Valves, Fittings, and Pipe, Crane Co., 1981, Technical Paper No. 410),

the density of water at 70'F is 8.3290 ibm/gallon and at 120'F is 8.2498

ibm/gallon. Using these water masses and Equation 2.0 above, the mass ofboric acid per gallon of solution is as follows:

Concentrat on

Mass of acid per gallonof solution at

source wt.% boric acid m boron 70'F 120'F

RWST

RWST

RWST

boric acid tankboric acid tankboric acid tankboric acid tankboric acid tankboric acid tankboric acid tankboric acid tank

1.11534

1.22974

1.34413

1.50

2.50

2.75

3.00

3.25

3.50

3.75

4.00

1950

2150

2350

2622

4371

4808

5245

5682

6119

6556

6993

0.09394

0.10370

0.11348

0.12684

0.21356

0.23552

0.25760

0.27979

0.30209

0.32451

0.34704

0.09305

0.10271

0.11240

0.12563

0.21153

0.23328

0.25515

0.27712

0.29922

0.32142

0.34374

A3-2

Appendix 4

methodology for Calculating the Conversion FactorBetween Weight Percent Boric Acid and ppm Boron

~Pur use

The purpose of this appendix is to show the methodology used to derivethe conversion factor between concentration in terms of weight percentboric acid and concentration in terms of parts per million (ppm) ofnaturally occurring boron.

Results

For any species (solute) dissolved in some solvent, a solution having a

concentration of exactly 1 ppm can be obtained by dissolving 1 ibm ofsolute in 999,999 ibm of solvent. An aqueous solution having a

concentration of 1 ppm boric acid, therefore, can be obtained by

dissolving 1 ibm of boric acid in 999,999 ibm of water, or

1 ibm boric acid 119 9 1 dd

9 1 19 999,999 11 1 19 11

For any species (solute) dissolved in some solvent, a solution having a

concentration of 1 weight percent (wt.X) can be obtained by dissolving 1

ibm of solute in 99 ibm of solvent. An aqueous solution having a

concentration of 1 wt.X boric acid, therefore, can be obtained by

dissolving 1 ibm of boric acid in 99 ibm of water, or

1 wt.XTR

1 ibm boric acidm orle acl + 99 m water

1 ibm boric acidm so Utlon

Dividing these last two equations yields a ratio of 10 , or

1 wt.X boric acid = 10,000 ppm boric acid (1 0)

A4-1

To convert from ppm boric acid (weight fraction) to ppm boron (weightfraction), multiply Equation 1.0 by the ratio of the molecular weight ofboric acid (naturally occurring H3B03) to the atomic weight of naturallyoccurring boron. From the Handbook of Chemistry and Physics, CRC Press,

or

1 wt.X boric acid (10,000) ~'~ ppm boron10.81

1 wt.X boric acid 1748.34 ppm boron.

A4-2

Appendix 5

Bounding Physics Data Inputs

A5-I

APL

P.O. 8ox14000, Juno Beach, FL 33408-0420

(Pffft)

JPN-PTP-90-1248

ASH ap tggg

Combustion Engineering, Inc.1000 Prospect Hill RoadWindsor, Connecticut 06095

Attention: Hr. J. H. Westhoven

TURKEY POINT UNITS 3'L 4BORIC ACID CONCENTRATION REDUCTION

REA TPN-88-733 IS MOD 1311CCO NO. 30383 PC/H: N/A

FILE: TPN-88-733-2

Reference: C-E letter F-CE-10852 dated February 23, 1990

Gentlemen:

Table II in the letter referenced above described the type of data you requirefrom FPL to develop the technical documents to support a technical specificationchange to reduce boron concentration. Table II was subsequently updated by youafter conversations between your Hr. Carl Gimbrone and Hr. Abe Ortega. We areenclosing the data requested in the updated version of Table II.The data was generated by our Fuel Technology Department and has been reviewedand approved for release to you. If you have any questions strictly regardingthe nature of the data, please contact Mr. Modesto Jimenez at (305)552-3427.

Ifyou have any other questions, please contact Mr. Abe Ortega at (407)694-5094.

Very truly yours,

~NO/lh

Copies:H.J.C.J.R.A.

S. BowlesKruminsL. Larsen (w/)PorterS. Sanders (w/)T. Zielonka

S. T. HaleEngineering Project Manager

an FPL Group company

!neer-Otfics Correspondence

To:NF-90-140

Date: April 3, 1990

From: M. Jimenez Department: Nuclear Fuel

Subject: Turkey Point Units 3 & 4 Boric AcidConcentration Reduction Pro'ect - Ph sics Data

Attached is the physics data requested in RAA 3065 to support the boric acidconcentration reduction project at Turkey Point. The information provided consistsof best estimate calculated average values covering several fuel cycles. Uncertaintiesnoted in the attachment represents the range of variation among the cycles and donot include calculational uncertainty, Additional conservatisms should be applied tothese results to envelope all future cycles. The data provided in the attachment havebeen reviewed in accordance to Nuclear Fuel's Quality Instructions.

If you have any questions or comments, please contact me at 552-3427.

M. JimenezReactor Support

Approved By:J.. FerrymanReactor Support Supervisor

Copies To: T3. CahillG.l MarshJ.l Petry manD.C. PoteralskiLS. Rudicel ~~W. SkelleyD.G. Weeks

fqre 1001 (Qockad) Rev. X1$

TURKEY POINT UNITS 3 & 4BORIC ACID CONCENTRATION REDUCTION PROJECT

RE UIRED PHYSICS DATA

1. Required shutdown margins:

Gzuhtion

a T-avg > 200'F.

b. T-avg ( 200'F.

See Figure 1

1000

2. Moderator cooldown curve from Hot Full Power (HFP) equilibriumconditions to 68 'F for the rodded condition when all rods are insertedminus the most worthy rod (ARI/wrso). The moderator cooldown curveshould be normalized such that the corresponding All Rods Out (ARO) HFPModerator Temperature Coefficient (MTC) is equal to the most negativeTechnical Specification limit.

Figure 2

3. Doppler curve down to 68'F.

Table 1

4. Xenon worth versus time (100 hours) after shutdown Qom 100% power.

Tables 2 & 3 presents xenon worth versus time after shutdown from100% at EOC 11 for Turkey Point Units 3 and 4, respectively. Thesexenon worth tables are representative of all recent cycles at TurkeyPoint. As shown in these tables, the xenon worth is negligible after 100hoar@

5. HZP scaun worths for the ARI/wrso condition. (Moderator and Dopplerdistribution and xenon concentration held constant between the rodded andunrodded calculation).

6500+/- 5% ctn. The 5% uncertainty in this value represents the range ofvariation or the most recent cycles at Turkey Point and does not includecalculational uncertainty of 10%.

6. Differential Boron Worth (DBW) versus Temperature from HZP to CZP.

Figurc 3. The following data points were used to generate this figure:

68350547

-145 +/-1.0-125 +/45-105 +/4.4

7. PPM measurement uncertainty for the boronometer (or measurement methodused during normal and off-normal shutdowns).

19o or 5 ppm, whichever is greater.

8. Power Defect (Moderator and Doppler) for ARO, 0% to 100% power,constant HFP equilibrium xenon concentration at EOC EFPH.

Figure 4. The following data points were used to generate this figure:

0305070100

0- 800+/- 50-1270 +/- 50-1700 +/-100-2300 +/-100

9. Beta-Eff. ifreactivity data is given in terms of dollars ($).

Allreactivities given in pcm.

10. HFP PDIL

The HFP PDIL or Insertion Limit is control Bank D at 171 stepswithdrawn (75%). The calculated worth to this insertion limit is240 +I- 50 m. The rod insertion allowance in the calculation ofs ut wn margm is conservatively estimated at 500 pcm by the fuelvendor.

TABLE 1

TURKEY POINT UNITS 3 & 4DOPPLER ONLY FUEL TEMPERATURE COEFFICIENTVs. FUEL TEMPERATURE

Fuel Temperature (oF)

68100200300400500600700800900

10001100120013001400150016001700180019002000

Doppler Coefficient(pcm/oF)

-2 90-2 ~ 75

2 ~ 37-2 '7-1.84-1 ~ 67-1. 54-1.45-1 '8

1 ~ 33-1. 30-1.26-1. 24

1 ~ 2 1-1. 17-1 '4-1 '0-1 '7-1.04-1.02-1 '2

TABLE 2

HR AFf'SD"n.o2. rj4.o6). 08.0

10.012.014.016.0lid.n20.022.024.026.0

TURKEY POINT UNIT 3 CYCLE 11

XE WRTH(PCN)2775.13709.54261 '4532.44h00.34525.14352.241)5.0.)041. 53548.1)249. 32954.62670.62401.7

HR AFT SD56.058.060.062.064.066.068.070.075.080.085.090.095.0

100.0

XENON WORTH AFTER TRIP AT EOL (12000)ENTER PRE TRIP POWER LEVEL (X) OR ENTER -E- 10 END

)00SUHNARY OF RESULTS

HR AFT SD XE WRTH(PCN)28.0 2150.430.0 1918 ~ 132.0 1705.334. 0 1511.636.0 133h.438.0 11/8.840.0 1037.642. 0 911.744.0 799 746.0 7nO.34A.O 6.l2.550.0 535.052.0 466.854.0 406.8

XF. WRTH(PCN)354.3308.2267.9232./202.0175.2151.9131.h

'Yl 8'3.8

44.330.721.214.7

FNTFR 0 TO CONTINUE CALCULATIONS, 0 1'n 8RAPH OR -E- TO END

TABLE

>If<.AFT.SD.0.02.04.06.08.0

10.012.014.016.018.020. CI

22.024.026.0

TURKEY POINT UNIT 4 CYCLE 11

XE.WRTH(PCN)2874.63834 '4401.34678.64747.14668.34489.14244.7.>961. 43658.6>350. 2

3046>.22753 ..>2475

HR.AFT.SD.56.058.'060. 062.064.0

~ 66 068.070.07S.Q80.085.090. Il'4S. 0

100.0

XENON WORTH AFTER TRIP AT EOL (12000)ENTER PRE-TRIP POWER LEVEL (X) OR ENTER -E- TO END

100SUNNAI<Y OF RESULTS

HR.AFT.SD. XE.Wf(TH(PCN)28.0 2;?16.030 ' i~rr.332.0 1757.834.0 1558.136.0 1377.538.0 1215.040.0 1069.542.0 939.7nn.ontj.O 7:? I. 848. 0 631.350 ' 551.452.0 481.J54.0 4Ja

XI";.WRTI I(PCH)r 1317.627~.12&9 8208.2180.6156.5135;694.665.845.631.621 9I 5>. 1

f='NTFR C TA CONTINLII.. CALCULATIONS, G TO GfIAPH OR -E- IO END

FIGURE 1

Turkey Point Units 3 R 4Required Shutdown Margin Vs. Boron Concentration

For T-Avg o 200 oF2,000

~ ~ ~ ~ ~ ~ ~ ~ OO ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ \ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ IA1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

g 1400

W 1,000

500

~ ~ ~ ~ ~ ~ OO ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ \ ~ ~ ~ ~ ~ ~ ~ A

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0

~ ~ ~ ~ ~ I~ ~ 0

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ 0

~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ Ot&O~ ~ ~

1,500

0 00 500 1,000 1,500 2,000

RCS Boron Concentration (pptn)

FISH& 2

10

Turkey Point Units 3 8c 4Moderator TemperatUre Coefficient Vs. Moderator Temperanue

( 0

-50

Average Moderator Temperature ('F)

FIGUIM3

Turkey Point Units 3 & 4Diffe

-8rential Boron Worth Vs. Temperature

~ -108

-12

8Og -14

CtQ

-16

~ ~ ~ ~ ~ Qo ~

~ ~ ~ ~ ~ ~ ~ ~o

~ ~ ~ ~ ~ do ~

~ $ ~

l ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0oo ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ Ao

~ ~ ~ ~ ~ oo ~

o

~ 'o ~

o~ ~ ~ ~ ~ oo ~

o~ ~ ~ ~ ~ +o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~

~ 1o~ ~ ~ ~ ~ ooo ~

~ ~ ~ ~ ~ 4o ~ ~ to

o

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ( ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~

( ~ ~

I ~ ~

~ o ~

~ ~ ~

~ ~

} ~ ~

l ~ ~

~ ~ ~

~ ~ ~

~ op

~ ~ ~

~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ohio ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ + ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ooo

~ op

~ ~ ~o

~ ~ 0

~ oOo

o

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ )o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ +o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~

-180 100 200 300 400 500

Moderator Temperature (oF)

FIGUI&4

"-turkey Point Units 3 4 4Total Power Defect Vs. Percent of Full Power

0At EOC, EQ. XE, ARO.

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ + ~ ~ ~ $ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ \ ~

0

-500 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~

o -1000

0 -1500

\~ ~ ~ ~ 4t

~ ~ ~ ~ tO

~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ 1 ~ ~

~ ~ e ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ to ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ J ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ J ~ ~ ~ ~ ~ ~

~ ~ ~ ~ $ ~

~ ~ ~ ~ ~ 0

\

~ ~ ~ ~ ~ f ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

-2000

~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 10 ~ ~ 1 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

-25000 20 40 60 80

Percent Of Full Power

Appendix 6

Harked-Up Revised Technical Specifications

These draft technical specification revisions reflect the

proposed boric acid tank configuration where all threetanks are tied together via the transfer pump suctionlines. In this manner, the combined volume of these tanks

is shared between the two units. Required minimum

volumes, therefore, have been doubled to ensure adequate

volume is available to either unit.

A6-I

Technical S ecification Inserts

Insert A:

...EOL peak xenon conditions without letdown such that boration occurs onlyduring the makeup provided for coolant contraction. This requirement can be

met for a range of boric acid concentrations in the boric acid tank and the

refueling water storage tank. The range of boric acid tank requirements isdefined by Technical Specification 3.1.2.5.

Insert B:

...requirement of 55'F and corresponding surveillance intervals...

Insert C:

The temperature limit of 55'F includes a 5'F margin over the 50'F solubilitylimit of 3.5 wt./ boric acid. Portable instrumentation may be used to measure

the temperature of the rooms containing boric acid sources and flow paths.

Insert D:

ACTION times allow for an orderly sequential shutdown of both units when the

inoperability of a component(s) affects both units with equal severity. When

a single unit is affected, the time to be in HOT STANDBY is 6 hours. When an

ACTION statement requires a dual unit shutdown, the time to be in HOT STANDBY

is 12 hours.

Insert E:

...by verifying that the temperature of the rooms containing flow path

components is greater than or equal to 55'F when a flow path from the boric

acid tanks is used;

A6-2

Insert F:

Verifying that the temperature of the boric acid tanks room is greater than or

equal to 55'F when it is the source of borated water.

A6-3

3/4. 1 REACTIVITY CONTROL SYSTEMS

3/4. 1. 1 BORATION CONTROL

SHUTDOWN MARGIN - T GREATER THAN 200 Fav

LIHIT ING COND IT ION FOR OPERATION

3. 1. l. 1 The SHUTDOWN MARGIN shall be greater than or equal to the applicablevalue shown in Figure 3.1-1.

APPLICABILITY: MODES 1, 2", 3, and 4.

ACTION:

With the SHUTDOWN MARGIN less than the applicable value shown in Figure 3.1-1,immediately initiate and continue boration at greater than or equal togpm of a solution containing greater than or equal to boron requivalent until the required SHUTDOWN MARGIN is restored.

a.o w'f,(etA6 g~)SURVEILLANCE RE UIREHENTS

4. l. 1. l. 1 The SHUTDOWN MARGIN shall be determined to be greater than or equalto the applicable value shown in Figure 3. 1-1:

a. Within 1 hour after detection of an inoperable control rod(s) andat least once per 12 hours thereafter while the rod(s) is inoperable.If the inoperable control rod is immovable or untrippable, the aboverequired SHUTDOWN MARGIN shall be verified acceptable with an increasedallowance for the withdrawn worth of the immovable or untrippablecontrol rod(s);

b. When in MODE 1 or MODE 2 with K ff greater than or equal to 1 ateffleast once per 12 hours by verifying that control bank withdrawal iswithin the limits of Specification 3. 1.3 ';

c. When in MODE 2 with K ff less than 1, within 4 hours prior to achievingreactor criticality b$ verifying that the predicted critical controlrod position is within the limits of Specification 3. 1.3.6;

d. Prior to initial operation above 5X RATED THERMAL POWER after eachfuel loading, by consideration of the factors of Specification4. l.l.l.le. below, with the control banks at the maximum insertionlimit of Specification 3. 1.3.6; and

"See Special Test Exceptions Specification 3. 10.1.

TURKEY POINT - UNITS 3 6 4 3/4 1-1 AMENDMENT NOS.l37 AND 132

REACTIVITY CONTROL SYSTEMS

SHUTDOWN MARGIN - T LESS THAN OP ""EQUAL TO 200 Fav

LIMITING CONDITION FOR OPERATION

3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to lX ~k/k.

APPLICABILITY: MODE 5.

ACT10M:

With the SHUTDOWN MARGINboration at great thanthan or equal toMARGIN is restore .

less than 'k/k, immedi ately initiate and continueor equal to pm of a solution containing greater

oron or equivalent until the required SHUTDOWN

a.o W'I (~iW~)SUR",El'ANCE RE UIREMENTS

4. 1. 1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equalto 1 Dk/k:

Within 1 hour after detection of an inoperable control rod(s) and atleast once per 12 hours thereafter while the rod(s) is inoperable.If the inoperable control rod is immovable or untrippable, theSHUTDOWN MARGIN shall be verified acceptable with an increasedallowance for the withdrawn worth of the immovable or untrippablecontrol rod(s); and

b. At least once per 24 hours by consideration of the following factors:

1) Reactor Coolant System boron concentration,

2) Control rod position,

3) Reactor Coolant System average temperature,

') Fuel burnup based on gross thermal energy generation,\

5) Xenon concentration, and

6) Samarium concentration.

TURKEY POINT - UNITS 3 8' 3/4 1-4 AMENDMENT NOS.137AND 132


3/4. 1. 2 BORATION SYSTEMS

FLOW PATH - SHUTDOWN

LIMITING CONOITION FOR OPERATION

3.1.2.1 As a minimum, one of the following boron injection flow paths shallbe OPERABLE and capable of being powered from an OPERABLE emergency powersource:

A flow path from the boric acid storage tanks via a boric acidtransfer pump and a charging pump to the Reactor Coolant System ifthe boric acid storage tank in Specification 3. 1.2.4a. isOPERABLE. or

b. The flow path from the refueling water storage tank via a chargingpump to the Reactor Coolant System if the refueling water storagetank in Specification 3. 1.2.4b. is OPERABLE.

APPLICABILITY: MODES 5 and 6.

ACTION:

With none of the above flow paths OPERABLE or capable of being powered from anOPERABLE emergency power source, suspend all operations involving COREALTERATIONS or positive reactivity changes.

SURVEILLANCE RE UIREMENTS

4.1.2.1 At least one of the above required flow paths shall be demonstratedOPERABLE:

a. At leas once er 7 d s

and

b. At least once per 31 days by verifying that each valve (manual,power-operated, or automatic) in the flow path that is not locked,sealed, or otherwise secured in position, is in its correctposition.

MHitCT

TURKEY POINT - UNITS 3 8; 4 3/4 1-8 AMENOMENT NOS. l37AND 132


FLOW PATHS - OPERATING


3.1.2.2 The following boron injection flow paths shall be OPERABLE:

a. The source path from a boric acid storage tank via a boric acidtransfer pump to the charging pump suction", and

b. At least one of the two source paths from the refueling water storagetank to the charging pump suction; and,

c. The flow path from the charging pump discharge to the ReactorCoolant System via the regenerative heat exchanger.

APPLICAEILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With no boration source path from a boric acid storage tank OPERABLE,

1. Demonstrate the OPERABILITY of the second source path from therefueling water storage tank to the charging pump suction byverifying the flow path valve alignment; and

2. Restore the boration source path from a boric acid storage tankto OPERABLE status within 72 hours or be in at least HOT STANDBY

and borated to a SHUTDOWN MARGIN equivalent to at least 1X b,k/kat 200'F within the next 6 hours; restore the boration sourcepath from a boric acid storage tank to OPERABLE status withinthe next 72 hours or be in COLD SHUTDOWN within the next 30hours.

b. With only one boration source path OPERS E or the regenerative heatexchanger flow path to the RCS inoperable, restore the required flowpaths to OPERABLE status'ithin 72 hours or be in at 'least HOT

STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least lXb,k/k at 200'F within the next 6 hours; restore at least twoboration source paths to OPERABLE status within the next 72 hours orbe in COLD SHUTDOWN within the next 30 hours.

~The flow require ithe other uni

With the'boration source path from a boric acid storage tank and thecharging pump discharge path via the regenerative heat exchangerinoperable, within one hour initiate boration to a SHUTDOWN MARGIN

equivalent to lX hk/k at 200'F and go to COLD SHUTDOWN as soon as

possible within the limitations of the boration and pressurizerlevel control functions of the CVCS.

+ Iso sec maid femme a ssw tt' ~''~ ~pec ica son 3. 1.2.2.a above shall be isolated from

TURKEY POINT - UNITS 3 8 4 3/4 1-9 AMENDMENT NOS. 137AND 132


SURVEILLANCE RE UIREHENTS

4.1.2.2 The above required flow paths shall be demonstrated OPERABLE:

a. At least once er 7 da s

b. At least once per 31 days by verifyihg that each valve (manual,power-operated, or automatic) in the flow path that is not locked,sealed, or otherwise secured in position, is in its correct position;

c. At least once per 18 months by verifying that the fl w path requiredby Specification 3. 1.2.2a. and c. delivers at least pm to the RCS.

TURKEY POiNT - UNITS 3 & 4 3/4 1-10 AMENDMENT NOS.l37AND l32


BORATED WATER SOURCE - SHUTDOWN


3. 1.2 ' As a minimum, one of the following borated water sources shall beOPERABLE:

z,ceo 1lwc Pt m<ipa. A Boric Acid Storage System with:

1) A minimum indicated borated water volume of

2) A boron concentration between

3)

and

b. The refueling

1) A minimum

2) A minimum

3) A minimum

water storage tank (RWST) with:

indicated borated water volume of 20,000 gallons,

boron concentration of 1950 ppm, and

solution temperature of 39'F.suwkf (sz4sH )

OAAQ 3.6 l4t li (gill~)and 6.APPLICABILITY: MODES

ACTION: 4 w'wiiiiVmloAACaii44414~ tc+emvutc of ~'P.With no borated water source OPERABLE, suspend all operations involving COREALTERATIONS or positive reactivity changes.

SURVErLLANCE RE UIREMENTS

4. 1.2.4 The above required borated water source shall be demonstrated OPERABLE:

a. At least once per 7 days by:

1) Verifying the boron concentration of the water,

2) Verifying the indicated borated water volume, and

3)

TURKEY POINT - UNITS 3 5 4 3/4 1-12i.

AMENDMENT QQ5.137AND 132


BORATED WATER SOURCES - OPERATING

LIMITING CONOITION FOR OPERATION

3. 1.2.5 The following borated water sources shall be OPERABLE:'llcdssIC wl%

Vi use. 8.L2.5>a. A Boric Acid Storage System with:

1) A minimum indicated borated water volume

2) A boron concentration and

3) illCIAO~(CwitVttwss

p ~ ~ ggb. The refueling water storage tank (RWST) with:

1) A minimum indicated borated water volume of 320,000 gallons,

2) A minimum boron concentration of 1950 ppm,

3) A minimum solution temperature of 394F, and

ACTION

With the required Boric Acid Storage System inoperable verify thatthe RWST is OPERABLE; restore the system to OPERABLE status wigh'n72 hours or be in at least HOT STANDBY within the next 6 hourPandborated to a SHUTDOWN MARGIN equivalent to at least A Dk/k at 200'F;reo .re the Boric Acid Storage System to OPERABLE status within thenex. 72 hours or be in COLD SHUTDOWN within the next 30 hours.

b. With the RWST inoperable, restore the tank to OPERABLE statuswithin 1 hour or be in at least HOT STANDBY within the next6 hours and in COLD SHUTDOWN within the following 30 hours.

IPli'4 '6 Lscc oci g tohK. ITAlcll~ooli co<el T~l's L> < alt%, qcoc'f~ 'ALA( 0 Hoes clcclt &4agp

o. J)scot'a~ sou ccc cAAAl. 4sw IA~~ ls )ocotcc. <4so44ggh 4 L 4 r ~cc~tost'os.

4) A maximum solution temperature of 100'F.

APPLICABILITY: MODES 1, 2, 3, and 4. P WialWSW ~ ACC +C~~ tink! A~%w SAfikSC, 0) ~ T ~

TUR YP IN - NITS3K 3/4 1-14 AMENDMENT NOS.l37AND l

WXf44csc ma)) 'co a Iso us'Tt'c sIlNu.,+scoos l c. wl

to14ig 'f4. we+ LQU4 4,ovlLs .

Figure 3. 1.2.5BORIC ACID TANK MINIMUM VOLUME (1)

Modes 1,2,3 and 4

0

0

I—

CQ

E

E

16

1515,000

o UnitAcceptable TwOperationn

14

13

12

11

10

9

8

10,400

AcceptaOpe

Una c ceptable..........O.p.e.r..aj.j q.o..................

13,200

ble One Unitration (2)

9,500

1 1,800

8,800

3.0 wt.%(5245ppm)

3.25 wt.% 3.5 wt.% )3.5 WT.%(5682ppm) (6119ppm)

BAT Inventory ConcentrationMinimum Acceptable Minimum AcceptableTwo Unit Operation One Unit Operation

Notes:(1) Combined volume of all available boric acid

tanks assuming RWST boron concentrationgreater than or equal to 1950 ppm.

(2) Includes 2900 gallons for shutdown unit.



4. 1.2.5 Each borated water source shall be demonstrated OPERABLE:

a. At least once per 7 days by:

1) Verifying the boron concentration in the water,

2) Verifying the indicated borated water volume of the watersource, and

3)

b. By verifying the Rk'ST temperature is within limits whenever theoutside air temperature is less than 39'F or greater than 100'F atthe following frequencies:

1) within one hour upon the outside temperature exceeding its limitfor 23 consecutive hours, and

2) At least once per 24 hours while the outside temperature exceedsits limits.

TURKEY POINT - UNITS 3 6 4 3/4 1-15 AMENDMENT NOS. l37AN0 l3


HEAT TRACING


(0'. 1.2.6 At least two independent channels of heat tracing sha'll be OPERAOLEfor the boric acid storage tank and for the heat traced portions of theassociated flow paths required by Speci fication 3. 1. 2. 2.

APPLICABILITY: MODES 1, 2, 3 and 4MODES 5 and 6 (when the boric acid storage tank is the borated,water source per Specification 3. 1.2.4)

ACTjON:

MODES 1 2, 3 and 4

With only one channel of heat tracing on either the boric acid storage tank oron the heat traced portion of an associated flow path OPERABLE, operation maycontinue for up to 30 days provided the tank and flow path temperatures areverified to be greater than or equal to 145'F at least once per 8 hours;otherwise, be in at least HOT STANDBY within 6 hours and in COLO SHUTDOWN

within the following 30 hours.

MODES 5 and 6

With only one channel of heat tracing on either the boric acid storage tank oron the heat traced portion of an associated flow path OPERABLE, operationsinvolving CORE ALTERATIONS or positive reactivity additions ma>f continue forup to 30 days provided the tank and flow path temperatures are verified to begreater than or equal to 145'F at least once per 8 hours; otherwise, suspendall activities involving CORE ALTERATIONS or positive reactivity changes.

SURVEILl ANCE RE UIRE!lENTS

a. At least once per 31 days by energizing each heat tracing channel,and

At least once per 7 days by verifying the tank and flow pathtemperatures to be greater than or equal to 145 F. The tanktemperature shall be determined by measurement. The flow pathtemperature shall be determined by either measurement orrecirculation flow until establishment of equilibrium temperatures

b.

within the tank.

'ticno ion st+ W ohck~ikkt4+anW i vc o i~kck ctng [ood )ogo inytntoaaks. 4avt >En i!A'twttk<

k ~ %.68 lest.$% taktsnC (Nt 'fo) ~

4. 1.2.6 Each heat tracing channel for the boric acid stnrag tank andassociated flow path required by Specification 3. 1.2.2 shall be demonstratedOPERABLE:

TURKEY POINT - UNITS 3 8c 4 3/4 1 16 AMENDMENT NOS.137ANP 132

3/4. 9 REFUELING OPERATIONS

3/4.9. 1 BORON CONCENTRATION


3.9.1 The boron concentration of all filled portions of the Reactor CoolantSystem and the refueling canal shall be maintained uniform and sufficient toensure that the more restrictive of the following reactivity conditions is met;either:

a. A K ff of 0.95 or less, oreffb. A boron concentration of greater than or equal to 1950 ppm.

APPLICABILITY: HODE 6. "

ACTION:

With the requirements of the above specification not satisfied, immediatelysuspend all operations involving CORE ALTERATIONS or positive reactivitchanges and initiate and continue boration at greater han or equal t gpmof a solution containing greater than or equal to oron or > sequivalent until K ff is reduced to less than or eq o .95 or the boroneffconcentration is restored to greater than or equal to 1950 m whichever isthe more restrictive.

S.O INt'I, (SNS ~'ISURVEILLANCE RE UIREMENTS

4.9. 1. 1 The more restrictive of the above two reactivity conditions shall bedetermined prior to:

a. Removing or unbolting the reactor vessel head, and

b. Withdrawal of any full-length control rod in excess of 3 feet fromits fully inserted position within the reactor vessel.

4.9.1.2 The boron concentration of the Reactor Coolant System and the refuelingcanal shall be determined by chemical analysis at least once per 72 hours.

4.9. 1.3 Valves isolating unborated water sources*" shall be verified closedand secured in position by mechanical stops or by removal of air or electricalpower at least once per 31 days.

4.9.1.4 The spent fuel pit boron concentration sh'all be determined at leastonce per 31 days.

"The reactor shall be maintained in NODE 6 whenever fuel is in the reactorvessel with the vessel head closure bolts less than fully tensioned or withthe head removed.

" The primary water supply to the boric acid blender may be opened unde~administrative controls for makeup.

TURKEY POINT - UNITS 3 4 4 3/4 9-1 AMENDMENT NOS.137AND 132

3/4.10 SPECIAL TEST EXCEPTIONS

3/4. 10. 1 SHUTDOWN MARGIN


APPLICABILITY: MODE 2.

ACTION:

With any full-length control rod not fully inserted and with lessthan the above reactivity equivalent available for trip insertion,i ediately initiate and continue boration at greater than o" equal

m of a solution containing greater than or equal toboron or its equivalent until the SHUTDOWN MARGIN required

by pecification 3. l. 1.1 is restored.

ao

B.O oN:fo(sa4s p~)

b. With all full-length control rods fully inserted and the reactorsubcritical by less than the above reactivity 'eouivalent, i~edi-tely initiate and continue boration at greater than or ual o

m of a solution containing greater than or equal tooron or its equivalent until the SHUTDOWN MARGEN requir y

Specification 3. 1.1.1 is restored.9.0 laEels ~h


3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may besuspended for measurement of control rod worth and SHUTDOWN MARGIN providedreactivity equivalent to at least the highest estimated control rod worth isavailable for trip insertion froa OPERABLE control rod(s).

4.10.1.1 The position of each full-length control rod either partially orfully withdrawn shall be determined at least once per 2 hours.

4. 10. 1.2 Each full-length control rod not fully inserted shall be demonstratedcapable of full insertion when tripped from at least the 50K withdrawn positionwithin 24 hours prior to reducing the SHUTMWN MARGIN to less than the limits of.Specification 3.1.1.1.

TURKEY POINT - UNITS 3 Ea 4 3/4 10-1 AMENDMENT NOS J37 AND 132

3/4.1 REACTIVITY CONTROL SYSTEMS

BASES

3/4. 1. 1 BORATION CONTROL

3/4. 1. 1. 1 and 3/4. 1.1. 2 SHUTDOWN MARGIN

A sufficient SHUTDOWN MARGIN ensures that: (1) the reactor can be made

subcritical fr'om all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptablelimits, and (3) the reactor will be maintained sufficiently subcritical topreclude inadvertent criticality in the shutdown condition.

SHUTDON MARGIN requirements vary throughout core life as a function offuel depletion, RCS boron concentration, and RCS T „ . The most restrictivecondition occurs at EOL, with T „ at no load operating temperature, and isassociated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown. Figure 3. 1-1 shows the SHUTDOWN MARGIN equivalent to1.77X 4k/k at the end-of-core-life with respect to an uncontrolled cooldown.Accordingly, the SHUTDOWN MARGIN requirement is based upon this limitingcondition and is consistent with FSAR safety analysis assumptions. With T

less than 2004F, the reactivity transients resulting from an inadvertentcooldown of the RCS or an inadvertent dilution of RCS boron 'mal anda 1% ak/k SHUTOONN MARGIN ProvIdee ade te Protection.

The boron rate requirement of m of boron or equivalentensures the capability to restore the shutdown margin with one OPERABLE

char ging pump.

3/4. 1. 1. 3 MODERATOR TEMPERATURE COEFFICIENT

The limitations on aoderator temperature coefficient (h. ') are providedto ensure that the value of this coefficient reNains within the limitingcondition assumed in the FSAR accident and transient analyses.

The MTC values of this specification are applicable to a specific set ofplant conditions; accordingly, verification of MTC values at conditions otherthan those explicitly stated will require extrapolation to those conditions inorder to permit an accurate comparison.

The most negative MTC, value equivalent to the most positive aoderatordensity coefficient (MOC), was obtained by increaentally correcting the MOC

used in the FSAR analyses to nominal operating conditions. These corrections

TURKEY POINT - UNITS 3 4 4 B 3/4 1-1 AMENDMENT NOS 137AND 132


BASES

MODERATOR TEMPERATURE COEFFICIENT (Continued)

involved subtracting the incremental change in the MDC associated with a corecondition of all rods inserted (most positive MDC) to an all rods withdrawncondition and, a conversion for the rate of change of moderator density withtemperature at RATED THERMAL POWER conditions. This value of the MDC was thentransformed into the limiting MTC value -3.5 x 10-~ hk/k/4F. The MTC valueof -3.0 x 10-~ bk/k/4F represents a conservative value (with corrections forburnup and soluble boron) at a core condition of 300 ppm equilibrium boronconcentration and is obtained by making these corrections to the limiting MTCvalue of -3.5 x 10-~ hk/k/4F.

The Surveillance Requirements for measurement of the MTC at the beginningand near the end of the fuel cycle are adequate to confirm that the MTC remainswithin its limits since this coefficient changes slowly due principally to thereduction in RCS boron concentration associated with fuel burnup.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY

This specification ensures that the reactor will not be made criticalwith the Reactor Coolant System average temperature less than 5414F. Thislimitation is required to ensure: (1) the moderator temperature coefficientis within it analyzed temperature range, (2) the trip instrumentation is withinits normal operating range, (3) the pressurizer is capable of being in anOPERABLE status with a steam bubble, and (4) the reactor vessel is above itsminimum RTNDT temperature.

3/4. 1. 2 BORATION SYSTEMS

The Boron Injection System ensures that negative reactivity control isavailable during each mode of facility operation. The components required to

0~4 erform this function include: (1) borated water sources 2 char ',separa e ow a s 4 boric acid transfer pcs,

With the RCS average temperature above 2004F, a minimum of two boroninjection flow'paths are required to ensure single functional capability inthe event an assumed failure renders one of the flow paths inoperable. Oneflow path from the charging pump discharge is acceptable since the flow pathcomponents subject to an active failure are upstream of the charging pumps.

TURKEY POINT - UNITS 3 4 4 B 3/4 1-2 AMENDMENT NOS 137AND 132


BASES

BORATION SYSTEMS (Continued)

The boration flow path specification allows the RWST and the boric acidstorage tank to be the boron sources. Oue to the lower boron concentration inthe RWST, borating the RCS from this source is less effective than boratingfrom the boric acid tank and additional time may be required to achie e thedesired SHUTDOWN MARGIN required by ACTION statement restrictions.

The ACTION statement restrictions for the boration flow paths allowcontinued operation in mode 1 for a limited time period with either borationsource flow path or the normal flow path to the RCS (via the regenerative heatexchanger) inoperable. In this case, the plant capability to borate andcharge into the RCS is limited and the potential operational impact of thislimitation on mode 1 operation must be addressed. With both the flow pathfrom the boric acid tanks and the regenerative heat exchanger flow pathinoperable, immediate initiation of action to go to COLD SHUTDOWN is requiredbut no time is specified for the mode reduction due to the reduced plantcapability with these flow paths inoperable.

Two charging pumps are required to beOPERABLE to ensure single unctlona capabs s y >n t e event an assumefa'1 re e ders one of the pumps or power su lies inoper ble.

us su >n the pumps can be ed rom e> er t eEmergency Diesel enera or o he offsite grid through %Ac tar tuptransformer. c4

The boration capability of either flow path is sufficient to provide the.required SHUTDOWN MARGIN in accordance with Figure 3.1-1 from expectedoperating conditions after xenon d cay and cooldown to 2004F. The maximum A

p cte bor tion capabilit re ui :ment occurs at

With the RCS temperature below 2004F, one boron infection source flowpath is acceptable without single failure consideration on the basis of thestable reactivity condition of the reactor and the additional restrictionsprohibiting CORE ALTERATIONS and positive reactivity changes in the event thesingle boron injection system source flow path becomes inoperable.

The boron capability required belowSHUTDOWN MARGIN of lX dk/k after xenon1404F. This condition requires of thefrom the borfc acid storage tanks orfrom the RWST.

2004F is sufficient to provide aay and cooldown from 2004F to

allons ofgallons o ppa borated water

TURKEY POINT - UNITS 3 4 4 B 3/4 1-3

44ak a.s wt3. 5'&+3h~*~n. )ca u 'itNENOMENT NOSZ3 AND 132

REACTIVITY CONTROL SYSTEHS

BASES

BORATION SYSTEHS (Continued)

The charging pumps are demonstrated to be OPERABLE by testing as requiredby Section XI of the ASME code or by specific surveillance requirements in thespecification. These requirements are adequate to determine OPERABILITYbecause no safety analysis assumption relating to the charging pump performanceis more restrictive than these acceptance criteria for the pumps.

The boron concentration of the RWST in conjunction with manual addition ofborax ensures that the solution recirculated within containment after a LOCA

will be basic. The basic solution minimizes the evolution of iodine andminimizes the effect of chloride and caustic stress corrosion on mechanicalsystems and components. The temperature requirements for the RWST are basedon the containment integrity and large break LOCA analysis assumptions.

The OPERABILITY of one Boron Injection System during REFUELING ensuresthat this system is available for reactivity control while in

N QjCLTThe OPERABILITY associa e with the

boric acid tank e ensures t at he so ubl >ty of the oron solution willbe maintained. mdiv Q

(+)One channel of heat tracing is sufficient to maintain the specifiedtemperature limit. Since one channel of heat tracing is sufficient to maintainthe specified temperature> operation with one channel out-of-service ispermitted for a period of 30 days provided additional temperature surveillancei s per formed..

3/4. 1. 3 MOVABLE CONTROL ASSEHBLIES

The specifications of this section ensure that: (1) acceptable power distri-bution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and(3) the potential effects of rod misalignment on associated accident analyses

are'imited.OPERABILITY of the control rod position indicators is required todetermine control rod positions and thereby ensure compliance with the controlrod alignment and insertion limits continue. OPERABLE condition for theanalog rod position indicators is defined as being capable of indicating rodposition to within RI2 steps of the demand counter position. For the ShutdownBanks and Control Banks A and B, the Position Indication requirement is definedas the group demand counter indicated position between 0 and 30 steps withdrawninclusive, and between 200 and 228 steps withdrawn inclusive. This permitsthe operator to verify that the control rods in these banks are either fullywithdrawn or fully inserted, the normal operating modes for these banks.Knowledge of these bank positions in these two areas satisfies all accidentanalysis assumptions concerning their position. For Control Banks C and 0, the.Position Indication requirement is defined as the group demand counter indicatedposition between 0 and 228 steps withdrawn inclusive.

s ss 'no (omit )4, ~ sat g ml4 I Ys<f $ mal c+ci'O'-'NI,"" I ">'s-' %a e"k 0mL ~ ti S.S sm

'I cattnt Csdt ls) .

3/4. 9 REFUELING OPERATIONS

BASES

3/4.9. 1 BORON CONCENTRATION

The limitations on reactivity conditions during REFUELING ensure that:(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a

uniform boron concentration is maintained for reactivity control in the watervolume having direct access to the reactor vessel. These limitations areconsistent with the initial conditions assumed for the boron dilution incidentin the safety analyses. With the required valves closed during refuelingoperations the possibility of uncontrolled boron dilution of the filled portionof the RCS is precluded. This action prevents flow to the RCS of unboratedwater by closing flo aths f sources of unborated water. The borationrate requirement of pm of boron or equivalent ensures thecapability to restore th SHU ARG N with one OPERABLE charging pump.

3/4. 9. 2 INSTRUMENTATION 0 <1I (sdsH )The OPERABILITY of the Source Range Neutron Flux Monitors ensures that

redundant monitoring capability is available to detect changes in the reactivitycondition of the core. There are four source range neutron flux channels, twoprimary and two backup. All four channels have visual and alarm indication inthe control room and interface with the containment evacuation alarm system.The primary source range neutron flux channels can also generate reactor tripsignals and provide audible indication of the count rate in the control room

and containment. At least one primary source range neutron flux channel toprovide the required audible indication, in addition to its other functions,and one of the three remaining source range channels shall be OPERABLE tosatisfy the LCO.

3/4 ~ 9. 3 DECAY TIME

The minimum requirement for reactor subcriticality pi.or to movement ofirradiated fuel assemblies in the reactor vessel ensures that sufficient timehas elapsed to allow the radioactive decay of the short-lived fission products.This decay time is consistent with the assumptions used in the safety analyses.

3/4. 9. 4 CONTAINMENT BUILDING PENETRATIONS

The requirements on containment building penetration closure and OPERABILITY

ensure that a release of radioactive material within containment will be

restricted from leakage to the environment. The OPERABILITY and closurerestrictions are sufficient to restrict radioactive material release from a

fuel element rupture based upon the lack of containment pressurization potentialwhile in the REFUELING HODE.

3/4. 9. 5 COHHUNICATIONS

The requirement for coaeunications capability ensures that refuelingstation personnel can be promptly informed of significant changes in thefacility status or core reactivity conditions during CORE ALTERATIONS.

TURKEY POINT - UNITS 3'8 4 8 3/4 9-1 AHENDHENT NOS.137 AND 132

Appendix 7

Marked-up Safety Analysis Report Pages

A7-1

Safet Anal sis. Re ort Inserts

Insert A

...to support a cooldown to cold shutdown conditions without letdown. Under

these conditions, adequate boration can be achieved simply by providing makeup

for coolant contraction from a boric acid tank and the refueling water storage

tank. The minimum volume maintained in the boric acid tanks, therefore, isthat volume necessary to increase the RCS boron concentration during the earlyphase of the cooldown of each unit such that subsequent use of the refuelingwater storage tank for contraction makeup will maintain the required shutdown

margin throughout the remaining cooldown. In addition, the boric acid tanks

have sufficient boric acid solution to achieve cold shutdown for each unit ifthe most reactive RCCA is not inserted.

Insert B

...forty minutes when a feed and bleed process is utilized (less than 30

minutes when the available pressurizer volume is utilized). In forty...

Insert C

The solubility limit for 3.5 weight percent boric acid is reached at a

temperature of 50'F. This temperature is sufficiently low that the normally

expected ambient temperatures within the auxiliary building will maintain

boric acid solubility.

Insert 0

Boration to the cold shutdown concentration is also achievable without letdown

when boration is performed in conjunction with the plant cooldown through the

required makeup for coolant contraction. Specifically, if boric acid is

A7-2

injected first from the boric acid tanks and then from the refueling water

storage tank to maintain constant pressurizer level during the cooldown,

sufficient boric acid will be added to the RCS to maintain the required

shutdown margins.

A7-3

The reactivity control systems provided are capable of making and

holding the core subcritical from any hot standby or hot operating

condition, including those resulting from power changes.

The Rod Cluster Control (RCC) assemblies are divided into two

categories comprising control and shutdown rod groups. One control

group of RCC assemblies is used to compensate for short term reactivitychanges at power such as those produced due to variations in reactor

power requirements or in coolant temperature. The chemical shim controlis used to compensate for the more slowly occurring changes in reactivitythroughout core life such as those due to fuel depletion and fissionproduct buildup and decay.

The shutdown groups are provided to supplement the control groups

of RCC assemblies to make the reactor at least one per cent subcritical(k 0.99) following trip from any credible operating conditioneffto the hot, zero power condition assuming the most reactive RCC assembly

remains in the fully withdrawn position.

Any time that the reactor is at power, the quantity of boric acid retained

in the boric acid tanks and ready for injection will always exceed

that quantity require Wns e.rj

cfgSik

Boric acid is pumped from the boric acid tanks by one of two boric

acid transfer pumps to the suction of one of three charging pumps

which inject boric acid into the reactor coolant. Any charging pump

and either boric acid transfer pump can be operated from diesel generator

power on loss o ower. Boric acid can be injected by oneS>o.mlo

pump at a rate which takes the reactor to hot ~th no rods

inserted in less than additional minutes,KA,5<'tT

enough boric acid can be injected to compensate for xenon decay although

xenon decay below the equilibrium operating level does not begin untilapproximately I5 hours after shutdown. If two boric acid pumps are

available, these time periods are reduced..Additional boric acid

injection is employed if it is desired to bring the reactor to cold

shutdown conditions.

1.3-13

Z'e.rk 8Any time that the reactor is at pover, the quantity of boric acid 'retained inthe boric acid tanks an ready for injection alvays exceeds that required

This quantity also exceeds that required to bring thereactor to hot and to compensate for subsequent xenon decay.

oPfsi 4Boric acid is pumped from the, boric acid tanks by one ofpumps to the suction of one of three charging pumps vhichthe reactor coolant. Any charging pump and either boric

tvo boric acid transferinject boric acid intoacid trans fer pump can

be operated from diesel generator pover on loss of ~~ pover. Boric ac'd

can be injected by one pump at a rate vhich takes the reactor to hot

vith no rods inserted in less than additionalminutes, enough boric acid can be injected to compensate for xenon decay

although xenon decay belov the equilibrium operating level does not begin untilC

approximately 15 hours a fter shu tdovn. If tvo boric acid pumps are available,these time periods are reduced. Additional boric acid injection is employed ifit is desired to bring the reactor to cold shutdovn conditions.

. Znsmt'

On the basis of the above, thc injection of boric acid is shovn to afford backup

reactivity shutdovn capability, independent of control zod clusters vhich

normally serve this function in the short term situation. Shutdown for long

term and reduced temperature conditions can be accomplished vith boric acid

injection using redundant components, thus achieving thc measure of reliabilityimplied by the criterion.

Alternately, boric acid solution at lover concentration

refueling vater tank. This solution can bc transferred

pumps. The zeduced boric concentration lengthens the

equivalent shutdown.

can bc supplied from the

directly by the charging

time required to achieve

If pressuzc is reduced in the primary, a second alternative method comprises the

injection of boric acid solution by operation of the safety injection pumps

taking suction from thc zefueling water storage tank.

3.1.2-6 Rev. 1-11/83

Event specific analyses were performed to evaluate the acceptability of securingvarious loads at given times for the one EDG available case. It is acceptable, forthe operator to secure the RHR pump at about 30 minutes after accident initiatibnor both small break and large break loss of coolant accidents (LOCA). The

operator may also secure one containment spray pump at approximately 30 minutes

following initiation of a LOCA. These actions serve to reduce EDG loading.

The normal containment coolers (NCCs) which are required for normal operation are

tripped on loss of offsite power and are blocked from automatically restarting upon

restoration of bus voltage. Manual control capabilities are provided in the

control room. Operator actions required to manually load the NCCs for a unit in a

non-accident condition are specified in the EOPs which includes assessing the

available capacity of the EDGs. Containment heat removal for a unit in an accidentcondition is accomplished via the Emergency Containment Coolers and Containment

Spray Systems.

The Boric Acid (BA) transfer pump upon Loss of OffsitePower (LOOP) remain deenergized for the short term (up to 8 hours). Manual controlis available in the control room for the BA transferpumps. The EOPs specify operator actions required to manually load the BA transfer

umps which include assessing the available capacity of the EDG.

The Instrument Air Compressors (IACs) are blocked (by administrative control ofbreakers) from automatic starting whenever offsite power is not available. The

unavailability of the IACs following a LOOP is adequately compensated for through

the use of air receivers, nitrogen accumulators, and non-safety related,self-contained air compressors that do not require the EDG for power.

The turbine auxiliaries such as the turbine turning gear oil pump, turbine bearinglift pump, and turbine turning gear drive provide a protective function to the main

turbine generator. Accordingly, these turbine auxiliaries are blocked from

automatic starting whenever offsite power is not available. While these loads are

not required to be powered following a LOOP, the operator may manually initiatethese as specified in the EOPs which include assessing the available capacity ofthe

EDG'he

CRDM cooler fans are required for normal operation only and are shed during

diesel loading. If required, CRDM cooler fans can be manually loaded onto the

EDGs. Strict administrative controls must be used in the addition of manual loads

in this condition of plant operation to ensure that the EDGs are not overloaded.

8.2-18 Rev 5 7/87

Criterion: The reactivity control systems provided shall be capable of makingthe core subcritical under credible accident conditions vithappropriate margins for contingencies and limiting any subsequentreturn to pover such that there will be no undue risk to thehealth and safety of the public. (GDC 30)

Normal reactivity shutdovn capability is provided by RCC assemblies, withboric acid injection used to compensate for the long term xenon decaytransient and for cooldown. Any time that the unit is at power, the quantityof boric acid retained in the boric acid tanks and ready for injection villalways exceed that quantity required Thisquantity vill alvays exceed the quantity of boric acid required to bring thereactor to hot d to compensate for subsequent xenon decay.

sf~>4 Z~se& AThe boric acid solution is trans erred from the boric acid tanks by boric acidpumps to the suction of the charging pumps vhich inject boric acid into thereactor coolant. Any charging pump and any boric acid transfer pump can be

operated from diesel generator power on loss of power. Boric acid can be

injected by one charging pump and one boric acid transfer pump at a rate whichshuts the reactor down vith no rods inserted in less than

~s4eoa additional minutes, enough boric acid can be injected to compensate

for xenon decay although xenon decay bolos the equilibrium operating levelvillnot begin until approximately 12-15 hours after shutdown. Zf tvo boric Mec-acid pumps and tvo charging pumps are available, these time periods are

treduced. Additional boric acid is employed if it is desired to bring the

reactor to cold shutdown conditions.

On the basis of the above, the injection of boric acid is shown to affordbackup reactivity shutdown capability, independent of control rod clustersvhich normally serve this function in the short term situation. Shutdown forlong term and reduced temperature conditions can be accomplished vith boric

acid injection using redundant components.

0134F 9.2-3 Rev 8 7/90 '

Hydrogen is automatically supplied, as determined by pressure control, to the

vapor space in the volume control tank, vhich i.s predominantly hydrogen an'd

atcr vapor. The hydrogen supply line has an excess flov valve (Fig 11.1-2)

upstream and outside of the Charging Pump Room which vill automatically close

if the hydrogen flov increases beyond its specific flow setting due to a

downstream pipe rupture. The hydrogen wi.thin this tank i.s supplied to the

reactor coolant for maintainiag a low oxygen concentration. Fission gases are

periodically removed from the system by ventiag the volume control tank to the

Waste Disposal System.

The charging pumps take suction from the volume control tank and return the

coolant to thc Reactor Coolant System through the tube side of the

regcncrative heat exchanger.

The cation bed dcmineraliser, located downstream of the mixed bed

demincralisers, is used intermittently to control cesium activity ia the

coolant and also to remove excess li.thium vhich i.s fozmed from B (n, o, )10

Li reaction.7Q.O 4o 3.S

Boric acid is di.ssolved in hot vatcr in the batching tank to a concentration

of approximately +9- percent by vcight. The lover portion of the batching tank

i.s jacketed to permit heating of thc hatching tank solution «ith lov pressure

steain. A transfer pump is used to transfer the batch to the boric acid

tanks. Small quantities of boric acid solutioa are aetered from the discharge

of an operating transfer puap for blending vith priInary vatcr as makeup fornormal leakage or for increasing the reactor coolant boroa concentration

during normal operation.

'

0081F 9.2-6 Rev 8 7/90

9.2-6aRev 4 7/86

Excess liquid effluents containing boric acid flow from the Reactor Coolant

System through the letdown line and are collected in the holdup tanks. As

liquid enters the holdup tanks, the nitrogen cover gas is displaced to the gas

decay tanks in the Waste Disposal System through the waste vent header. The

concentration of boric acid in the holdup tanks varies throughout core life from

the refueling concentration to essentially zero at the end of the core cycle. A

recirculation pump is provided to transfer liquid from one holdup tank to

another and to recirculate the contents of individual holdup tanks.

9 '-7 Rev. l-ll/5

Liquid effluent in the holdup tanks is processed as a batch operation.Thj.s ljquid is pumped through the evaporator base and cation exchangerswhich primarily remove lithium and fission-products such as long-livedcesium. It then flows through the ion exchanger filter and into the gas

stripper where dissolved gases are removed from the liquid. The gases

are vented to the Waste Disposal System. The liquid effluent from thegas stripper enters the boric acid evaporator.

The vapor produced in the boric acid evaporator leaves the evaporator condenser

and is pumped through a condensate cooler where the distillate is cooled tothe operating temperature of the evaporator condensate demineralizers. Afternon-volatile evaporator carry over is removed by one of the two evaporatorcondensate demineralizers the condensate flows through the condensate

filter and accumulates in one of two monitor tanks. The dilute boricacid solution originally in the boric acid evaporator remains as the bottomsof the distillation process and is concentrated to approximately ~skisper cent boric acid.

3. 4 3.w ~e'%Subsequent handling of the condensate is dependent on the results of sample

'I

analysis. Discharge from the monj.tor tanks may be pumped to the primary

water storage tank, recycled through the evaporator condensate demineralizers,returned to the holdup tanks for reprocessing in the evaporator trainor discharged to the environment with the condenser circulating water when

within the allowable activity concentration as discussed in Section 11.

If the sample analysis of the monitor tank contents indicates that itmay be discharged safely to the environment, two valves must be opened to

provide a discharge path. As the effluent leaves, it is continuously

monitored by the waste disposal system liquid effluent monitor. If an

unexpected increase in radioactivity is sensed, one of the valves in the

discharge line to the condenser circulating water closes automatically and

an alarm sounds in the control room.

Boric acid evaporator bottoms are discharged through a concentrates filterto the concentrates holding tank. Solution collected in the concentrates

holding tank is sampled and then transferred to the boric acid tanks j.f

9. 2-8

Reactor Makeu Control

The reactor makeup control consists of a group of instruments arrangedto provide a manually pre-selected makeup composition to the chargingpump suction header or the volume control tank. The makeup controlfunctions are to maintain desired operating fluid inventory in thevolume control tank and to adjust reactor coolant boron concentrationfor reactivity and shim control.

Makeup for normal leakage is regulated by the reactor makeup

control which is set by the operator to blend water from the primarywater storage tank with concentrated boric acid to match the reactorcoolant boron concentration.

The makeup system also provides concentrated boric acid or primary water toeither increase or decrease the boric acid concentration in the ReactorCoolant System. To maintain the reactor coolant volume constant, an

equal amount of reactor coolant is let down to the holdup tanks; Should

the letdown line be out of service during operation, sufficient volume

exists in the pressurizer to accept the amount of boric acid necessary

for ho& sf~ 4'4g.

Makeup water to the Reactor Coolant System is provided by the Chemical

and Volume Control System from the following sources:

a) The primary water storage tank, which provides water for dilutionwhen the reactor coolant boron concentration is to be reduced

b) The boric acid tanks, which supply concentrated boric acid solutionwhen reactor coolant boron concentration is to be increased

c) The refueling water storage tank, which supplies borated water

for emergency makeup ~r~(d) The chemical mixing tank, which is used to inject small quantities

of solution when additions of hydrazine or pH control chemical

are necessary.

9.2-11

Boric Acid Tanksense.r+ 6

The boric acid tank capacities are sized to store sufficient boric acidsolutio

3,SThe concent n o r ac solut on in storage is maintained between

by weight. Periodic manual sampling is performed and cor-rective action is taken, if necessary, to ensure that these limitsare maintained. Therefore, measured amounts of boric acid solution can

be delivered to the reactor coolant to control the concentration. The

combination overflow and breather vent connection has a water loop sealto minimize vapor discharge during storage of the solution. The tanks are

constructed of austenitic stainless steel.

Batchin Tank

solution for the boric acid tank. The basis for makeup is reactor coolant

leakage of 1/2 gpm at beginning of core life. The tank may also be used

for solution storage. A local sampling point is provided for verifyingthe solution concentration prior to transferring it to the boric acid tank

or for draining the tank.

9.2-23 Rev. 3-7/85

The tank manway is provided with a removable screen to prevent entry of foreignparticles. In addition, the tank is provided with an agitator to improve mixingduring batching operations'he tank 'is constructed of austenitic stainlesssteel, and is not used 'to handle radioactive substances'he tank is providedwith a steam jacket for heating the boric acid solution to+A~

Boric Acid Transfer Pum s

P8.r ~i[Two 100X capacity centrifugal pumps are used to circulate or transfer chemical

solutions. The pumps circulate boric acid solution through the boric acid tanks

and inject boric acid into the charging pump suction headers

Although one pump is normally used for boric acid batching and transfer and the

other for boric acid ,injection, either pump may function as standby for the

other. The design capacity of each pump is equal to the normal letdown flowrate. The design head is sufficient, considering line and valve losses, todeliver rated flow to the charging pump suction header when volume control tank

pressure is at the maximum operating value (relief valve setting) ~ All parts incontact with the solutions are austenitic stainless steel and other adequately

corrosion-resistant materials

The transfer pumps are operated either automatically or manually from the

control room or from a local control panel. The reactor makeup control operates

one of the pumps automatically when boric acid solution is required for makeup

or boration.

Boric Acid Blender

The boric acid blender promotes thorough mixing of boric acid solution and

reactor makeup water from the reactor coolant makeup circuit. The blender

consists of a conventional pipe fitted with a perforated tube inserts Allmaterial is austenitic stainless steel. The blender decreases the pipe 1ength

required to homogenize the mixture for taking a representative local sample.

9.2-24 Rev. 3-7/85

The gas strippers consist of a hot well with heating coil to stare strippedwater, a stripping section packed with pall rings, a spray type liquid inletheader and an overhead integral reflux condenser. Liquid flowing to the gas

strippers is controlled to constant rate by a flow controller. The gas

strippers are designed for the same flow rate as the evaporator and are5

designed to reduce the influent gas concentration by a factor of 10

Two gas stripper bottom pumps per gas stripper, operated from level control,transfer effluent from the gas stripper hot wells to the boric acid evapor-

ator via the gas stripper preheaters. Each centrifugal pump is rated

at the evaporator processing rate. The pumps are austenitic stainless

steel and one is an installed standby for the operating pump.

Boric Acid Eva orator E ui ment

Two boric acid evaporators concentrate boric acid for reuse in the Reactor

Coolant System. Borated water enters the evaporator and the liquid isconcentrated to approximately +R. eight per cent boric acid. Vapors leave

the evaporator and are condensed. The solids decontamination factor between6

the condensate and the bottoms is approximately 10 . All evaporator equipmer

is constructed of austenitic stainless steel and is supplied as a unit.Each boric acid evaporator package consists of the boric acid evaporator

feed tank, two boric acid evaporator concentrates pumps, boric acid evaporate

boric acid evaporator condenser, two boric acid evaporator condensate pumps,

boric acid evaporator condensate cooler, two vacuum pumps and associated

pi'ping. and instrumentatioe.

The boric acid evaporator feed tank has sufficient capacity to hold one

production of per cent boric acid solution produced from refueling

concentration feed. The evaporator and condenser heat transfer area is

sufficient to maintain the required feed rate. The evaporator is steam

heated. Component cooling water flows through the tube of the condenser.

9.2-27

Concentrates Filters

Two disposable synthetic cartridge type filters remove particulates from

the evaporator concentrates. Design flow capacity of each filter is equal

to the boric acid evaporator concentrates transfer pump capacity. The

vessels are made of austenitic stainless steel.

Concentrates Holdin Tank

The concentrates holding tank is sized to hold the production of concentrates

from one batch of evaporator operation. The tank is supplied with an

electrical heater which prevents boric acid precipitation and is constructed

of austenitic stainless steel.

Concentrates Holdin Tank Transfer Pum s

Two holding tank transfer pumps discharge boric acid solution from the

concentrates holding tank to the boric acid tanks or the hold up tanks. Each

canned centrifugal pump is sized to empty the concentrates holding tank in

approximately 10 minutes. The wetted surfaces are constructed of authen=ic

stainless steel and other adequately corrosion-resistant material.~ g

9.2-29

Valves

Valves that perform a modulating function are equipped with two sets of packingand an intermediate leakoff connection that discharges to the Waste Disposal

System. All other valves have stem leakage control. Globe valves are installedwith flow over the seats when such an arrangement reduces the possibility ofleakage. Basic material of construction is stainless steel for all valves

except the batching tank steam jacket valves which are carbon steel.

Isolation valves are provided at all connections to the Reactor Coolant System.

Lines entering the reactor containment also have check valves inside the

containment to prevent reverse flow from the containment.

9.2-30 Rev. 1-11/83

Relief valves are provided for lines and components that might be pressurizedabove design pressure by improper operation or component malfunction.Pressure relief for the tube side of the regenerative heat exchanger isprovided by the auxiliary spray line isolation valve which is designed to openwhen pressure under the seat exceeds reactor coolant pressure by 250 psi.Relief valves settings and capacities are given in Table 9.2-3.

Turkey Point Unit 3 has installed manual operating features to selectedair-operated valves (Table 9.6A-ll) in the Chemical and Volume ControlSystem. The installation of these features provides an alternate means ofoperating these valves if the valve misoperates due to receipt of a spuriouselectrical signal resulting from a postulated fire. These changes implementrecomnendations made as part of the Appendix R Safe Shutdown Analysis in orderto met the licensing coamitments of 10CFR50 Appendix R (see Subsection9.6A-5.6).

I~ne

All Chemical and Volume Control System piping handling radioactive liquid isaustenitic stainless steel. All piping joints and connections are welded,except where flanged connections are required to facilitate equipment removalfor maintenance and hydrostatic testing.

9 2 3 SYSTEM DESIGN EVALUATION

A high degree of functional reliability is assured in this system by providingstandby components where performance is vital to safety and by assuringfail-safe response to the most probable mode of failure.

The system has three charging pumps, each capable of supplying the normal

reactor cool'ant pump seal and makeup flow.

0081F 9.2-31 Rev 8 7/90

TABLE 9 ~ 2-2

NOMINAL CHEMICAL AND VOLUME CONTROL SYSTEM PERFORMANCE

Unit design life, years

Seal water supply flow rate, gpm*~

Seal water return flow rate, gpm

Normal letdown flow rate, gpm

Maximum letdown flow rate, gpm

Normal charging pump flow (one pump), gpm

Normal charging line'low, gpm

40

24

60

120

69

45

Maximum rate of boration with one transfer andone charging pump, ppm/min, (from inititalRCS concentration of 1800 ppm)

Equivalent cooldown rate to above rate ofboration, P/min

Maximum rate of boroa dilution (two chargingpumps) ppm/hour rom initial RCSconcentration of 2500 ppm) 350

Two~ump rate of boration, using refuelingwater, ppm/min (from initial RCSconcentration of 10 ppm) 6.2

Equivalent cooldown rate to above rate ofboration, P/min

1,7

Temperature of reactor coolant entering systemat full power, P (design) 555.0

Temperature of coolant return to ReactorCoolant System at &QJ. power, F (design) 493.0

Normal coolant discharae temperature toholdup taaks, P

3.'C) wa,lAmount of ron so ution uired to

meet cold utdown requirements

gallons nc ding considera on or one stu rod) 98ee- 7WV0

Sl Ml 42-

*eVolumetric flow rates in gpe are based on 130 F and 2350 psig.

0133P Rev 8 7/90

TABLE 9.2-3

PRINCIPLE COHPONENT DATA SUH HARY

Sheet 1 of 2

Quantity1

HeatTransferBtu/hr

Letdown LetdownFlow QTlb/hr F

Design DesignPressure Temperaturepsig,shell/tube F,shell/tube

Heat ExchangersRegenerativeNon regenerativeSeal waterExcess letdown

8.65 x 10614.8 x 1062.17 x 1064.75 x 106

29,826 26529,826 163126,756 1712,400 360

2485/2735150/600150/150150/2485

650/650250/400250/250250/650

Quantity Type

CapacityEachgpm Head

DesignPressurePslg

DesignTemperatureF

PumpsChargingBoric acid transferHoldup tank recirculationH onitor tankConcentrates holdingtank transferGas stripper feedGas stripper bottom

34*1*2*

2*3*2

Pos. disp].C entrifugalCentrifugalCentrifugal

CannedCannedC entrifugal

7760500100

202512.5

2385 psi235 ft.100 ft.150 ft.

150 ft.185 ft.93 ft

3000150150150

7515075

250250200200

250200300

P7

TanksVolumeBoric acid.Chemical mixingBatchingHo du

Q uantity1

1

3*1

1*3*

Type

Vert.Vert.Vert.Jacket Btm.

ert.

Volume, Each

300 ft3gal

6.0 gal800 ga]13 000

Q3$ ',oM p~l

DesignPressurePslg

75 Int/15ExtAtmos+150.Atmos.15

//~os.

DesignTemperatureF

250250250250

00

Appendix 8

Future Fuel Cycle Review for Comparison of Bounding Physics Parameters( )

Parameter

Core Power (100%%uo)

Shutdown Margin T>200'F

Shutdown Margin T/200'F

RCS Average Temperature (0/ Power)

Moderator Temperature Coefficient

Hot Zero Power Net Rod Worth

Hot Zero Power Rod Insertion Limit (%%uDq)

Hot Full Power Rod Insertion Limit (%%uDq)

Power Defect (/Dq)

Xenon Worth

Doppler Coefficient

Moderator Cooldown Curve

Differential Boron Worth

Scram Worth Data Uncertainty

Moderator Data Uncertainty

Doppler Data Uncertainty

IBW Data Uncertainty

Excess Scram Worth (T>200'F)

Excess Scram Worth (T$200'F)

Turke Point Units 3 and 4

<2200 MWt

<1.77%%u Dk/k

<1.0/ Dk/k

<547'F

<-3.5E(-4)Dk/k/'F (less negative)

>6.175

<2.0

<0.5

<2.4

<Table 3 (2)

Table 1 (2) (less negative)

Figure 2 (2) (less negative)

Figure 3 (2) (more negative)

<10/

<10/

<20/

<10. 9%%

>0.697% Dk/k

>1.468/ Dk/k

Notes:

(1) This table allows cycle to cycle comparison of core reload physicsparameters to those utilized in the boric acid concentration analyses.

(2) Extracted from bounding physics data provided by FPL and included as

Appendix 5 of the base report. Uncertainties and cycle to cyclevariations included in this data where applied in the conservativedirection.

Appendix 9

Analysis of Peak Xenon Scenario

1. 0 INTRODUCTION

This appendix presents the results of an analysis that is identical tothat presented in Section 5.0 of the base report with the exception ofhow the xenon transient is accounted for. Similar analyses have been

reviewed by other boric acid concentration reduction evaluations and are

included here for consideration of the reactivity design basis of theplant (see Section 2.2.6 of the base report). The final RCS boron

concentration required to maintain adequate shutdown margin is actuallyhigher in this analysis, the peak xenon case establishes the boric acidtank inventory requirement. This is discussed in greater detail in thesections that follow. Table and figure numbers in this appendix are

assigned in a manner that matches those in Section 5 of the base report.This allows direct comparison of the results of the two analyses.

2.0 BASIS

The basic differences between this analysis and the analysis of the base

report is the following:

(1) the cooldown transient is initiated at eight hours of 24 hours

(corresponding to the peak xenon condition instead of the full power

equilibrium xenon concentration) and,

(2) the subsequent cooldown boration must compensate for the decay of the

entire xenon inventory from its peak value (instead of its full power

equilibrium value).

This scenario presents a worst case near the end of the cycle when

sufficient RCS boron concentration (>0 ppm) is available to allow RCS

boron concentration to be diluted by the operator to compensate for the

post-shutdown xenon buildup in anticipation of a rapid return to power.

Starting a design basis cooldown to cold shutdown from the peak xenon

condition under these conditions will effectively increase the amount ofboron required to be charged to the RCS to compensate for the decay ofthe xenon peak back to its full power equilibrium value where theanalysis of Section 5.0 of the base report started. This is a

conservative assumption but is still achievable with reduced boric acidconcentration and the appropriate balance of boration from the boric acidtank and the refueling water storage tank during cooldown (contractionmakeup).

3.0 ANALYSIS SCENARIO

This scenario is suggested for analysis in response to the worst case

shutdown, cooldown, and boration scenario presented in References 10. 1

and 10.3 of the base report. Although it is a conservative assumption/scenario it has been analyzed in a similar manner as the scenarios ofSection 3. 1 of the base report to assess the boration system capabilitywith reduced boric acid concentration. Specifically, the borationrequired to maintain shutdown margin will be completed from the boricacid tank and refueling water storage tank in conjunction with the plantcooldown such that the volume of boric acid charged into the plant willmake up for cooldown contraction. The proposed scenario for thisanalysis is discussed below:

SHUTDOWN AND COOLDOWN AT PEAK XENON

(1) The conservative physics parameters of the base report will be used

to maximize the xenon and moderator cooldown reactivity effects.

(2) Reactor initially at hot full power (574.2 F), all rods out,equilibrium xenon at an equilibrium cycle exposure corresponding toa critical boron concentration of approximately 100-200 ppm. The

boron concentration is arbitrarily chosen to allow for dilution to 0

ppm presenting the worst case (EOC) physics parameters.

A9-2

(3) Reactor brought to hot zero power (547'F) with rods initiatingxenon transient (increase).

(4) While at hot zero power (547'F), operator maintains criticalityby diluting RCS boron to compensate for xenon buildup(anticipating a quick return to full power).

(5) At hot zero power (547'F), peak xenon condition, core is criticalwith approximately 0 ppm boron..

(6) Plant forced to go to cold shutdown (200 F): cooldown rates of100 F/hr, 90'F/hr, 50'F/hr, 25 F/hr, and 10'F/hr will be

analyzed.

(7) Zero RCS leakage (conservatively limits boron addition tocontraction makeup).

(8) Boric acid tank and refueling water storage tank used to make up forRCS contraction during cooldown and to maintain shutdown margin.

4. 0 ANALYSIS ASSUMPTIONS

Other than the variation in the treatment of xenon and the starting pointof the cooldown transient, the assumptions for this analysis are

identical to those presented in Section 4.0 of the base report.

5.0 ANALYSIS RESULTS

The analysis methodology is identical to that presented in Section 5.0 ofthe base report. The results of the peak xenon reactivity analysis are

presented in Tables 5. 1-1 through 5. 1-6. Because the endpoint boron

concentration requirement is higher in this scenario the value presented

here is used as the basis for determining the minimum boric acid tankinventory. The boron delivery analysis of Section 5.2 is based on

providing a 50 ppm margin over the minimum required cold shutdown boron

concentration of 788 ppm.

A9-3

Table 5.1-1


Peak Xenon, Near EOC, 10'F/hr Cooldown Rate


572.0

552.0

532.0

512.0

492.0

472.0

452.0

432.0

412.0

392.0

372.0

352.0

332.0

312.0

292.0

272.0

252.0

232.0

212.0

202.0

200.0

200.0

200.0

-321.94-222.14-114.12

-10.0085.31

171.90

250.19

320.79

384.39

441.72

493.48

540.34

582.90

621.71

657.25

689.94

720.14

748.16

774.26

786.67

789.10

726.54

788.15

A9-4

Table 5.1-2




572.0

522.0

472.0

422.0

372.0

322.0

272.0

222.0

200.0

200.0

200.0

-321.94-91.31

90.91

227.79

336.66

428.35

509.38

583.32

614.08

551.52

788.15

A9-5

Table 5.1-3



Tem erature F Re uired Boron m

572.0

472.0

372.0

272.0

222.0

200.0

200.0

200.0

-321.94

73.43

288.98

433.46

495.98

522.37

459.81

788.15

A9-6

Table 5.1-4


Peak Xenon, Near EOC, 90 F/hr Cooldown Rate

Tem erature F Re uired Boron m

572.0

482.0

392.0

302.0

212.0

200.0

200.0

200.0

-321.94

39.94

241.61

370.69

474.27

487.07

424.51

788.15

A9-7

Table 5.1-5




572.0

472.0

372.0

272.0

200.0

200.0

200.0

-321.94

68.13

272.80

404.19

483.58

421.02

788.15

A9-8

Table 5.1-6


Mode 5 Cooldown to Refueling(Near EOC Peak Xenon Scenario)


200 (Xenon Free)

180

160

140

135

788.15

803.68

819.21

834.74

838.62

A9-9

Appendix 10

Computer Code Certificate and Input

A10-1

COIIBUSTIOX KXCIXKEiBXC

COMPUTER CODE CERTIFICATE

The following code, as noted by its name, version number, and permanent file identification, is herebyapproved for design application.

Code NameBACR

Version Number REV. 00

Permanent File Identification BACR (00)

C IBII PC OR IBM PC COMPATIBLE

I CODE CLASSiFICATION

0 C-E Proprietary Code

Q C-E UtilityCode

0 C-E NRC Approved Code

0 Non C-E IState of the Art) Code

DESIGNATED PROGRAM ENGINEER

G.F. CAIIUTIIERS 9421/Iiechanical P I S

Msnger 5 Oept/Section Name

9421-423CEP Code

Code TestingCompleted By

W. E.. IIIGGIIISIndependent Reviewer

Date 0-

r 0 -(3 815

C.E 0013183 (5/ddt

7/Z/90 FPSL - (120 F BAT AHD RMST)

TURKEY POINT SORIC ACID COHCEHI'RATION REDUCTION EFFORT

EQUILIBRIUN XEHOH SCENARIO RUST AT 1950 PPN

TABLE I THROUGH TABLE X PARAHETERS

RCS vatet voluneNODES 1-4Specific volune ofconpressed vater at572 F 4 2250 psia

PZR vater vol.(100K PONER)

Specific voLLsne ofsatul'ated vater at2250 psia

Specific volune ofccrrpressed vater at200F S 3SO psia

RCS pressure

PZR OX POMER (NOOFSS-6)

Specific vol. of vater200F 8 14.7 psia

Specific voL, ofsaturated eater0 14.7 psia

RCS vater voluneNCOES 5-6

RCS NASS NODES 5 6

RUST terperature

BAT tenpcrature

Density of vaterat 120 F

Nass of boric acidper gal of solutiona 120 dog F, 1950 PPN

Density of vater0 120 deg F

Ness of boric acidper gal of solution8 120 dcg F, 3.5 vt.y.

Ness of boric acid

8,015.00000 cu.ft

0.02204

808,0000

cu.ft./Lbn

cu.ft

0.0269 cu.ft./Lbm

0.01662 cu.ft./ibm

400.00000f

520.00000 cu.ft.

0.01664 cu.ft./Lbm

0.016?2

8,015.00000

cu. ft./Lbrn

cu.ft

LSN

deg. F

degy F

8.24980 ibm/gal

0.0930S

8.24980 Lbm/sal

0.29922

963,341.34615

120.00000

120.00000

RtÃ ¹10

11

12}31415

16

1718

192021

22232425

26272829303'1

32333435363738394041

42434445

464748495051

52535455

565?585960

per gaL of solutionQ 120 deg F, 3.25 xt.X

Hass of boric acidper gal of solutionQ 120 degF, 3.0 xt.X

Hase of boric acidper gal of solutionQ 120 F, 2350 pprn

Density of xaterat 120 deg.F

Nasa of boric acidper gaL of solutionQ 120 F, 2150 ppm

Xass of boric acidper gaL of solutionQ 120 F, 3.75 xtX

Nasa of boric acidper gal of solutionQ 120 F, 4.00 xt)L

IHLTlhi. SYSTEH HASS

COHYERSLOM FACTOR BETMEEN

xt.X b/a 8 ppm boron

RCS MATER NASS =H(RlES1-4

PZR INTER NASS ~NOOES1 4

(Q2250 psia)

PZR MATER NASS =modes'i-4

(Q350 psia)

PZR WLTER NASS modes5-6

(Q14.7 pain)

LXITIALTOTAL STS HASS

NOES 5 6

Kass of boric acidper gaL of solutionQ 120 F, 2.75 xtX

Hans of boric acidper gal of solutionQ 'l20 F, 2.50 xtX

IHLT)AL TOTAL SYS NASS

8 c0.27712 Lbm

0.25515 Lbn

0.11240 Lbn

8.24980i lbn/gal

0.10271 Lbn

0.32142i Lbn

0.343?4 lbn

363,623.99056 Lbm

29,948.109?1 Lbm

48,325.35885 Lbn

31,100.4?84?I ibm

994,441. 82462 LSH

0.23328

0.21153

393, 572. 10027; lbnl

1,748 '4000 ppn

61

62636465666768697071

727374

?5767778?9eo81

82838485868?88899091

929394

95

96979899

100101

102103104

105106107108109

110

111

112113

114

115

116

117118119120

HOOSS 5 6after fCb

TOTAL RCS/SDCS MATER HASS

AT SDCS START

TOTAL MATER NSSAT SDCS START

994,441 .82462

892538.9755

940864.33435

LBN 'l21

122123'l24125

126

127128129

130131

132'lt t $$ ttt » ttt Qttt tttt t t It

TOTAL PAGE 885

boric acid concentration reduction technical bases

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