fpl. february 26, 2014 · l-2013-233 attachment 1 page 2 of 5 st. lucie unit 1 the following...

0FPL. February 26, 2014

L-2013-23310 CFR 50.90

U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D. C. 20555

Re: St. Lucie Units I and 2Docket Nos. 50-335 and 50-389Application for Technical Specification Change Regarding Mode Change LimitationsUsing the Consolidated Line Item Improvement Process

In accordance with the provisions of 10 CFR 50.90, Florida Power & Light Company (FPL) issubmitting a request for an amendment to the technical specifications (TS) for St. Lucie Unit Iand St. Lucie Unit 2.

The proposed amendment would modify TS requirements for mode change limitations in LCO3.0.4 and SR 4.0.4.

Attachment 1 provides a description of the proposed change (including tables of affected TS witha brief descriptor of the change), the requested confirmation of applicability, and plant-specificverifications. Attachment 2 provides the existing TS pages marked up to show the proposedchanges. Attachment 3 provides revised (clean) TS pages. Attachment 4 provides a summary ofthe regulatory commitments made in this submittal. Attachment 5 provides the existing TSBases pages marked up to show the proposed change.

FPL requests that the proposed License Amendment be processed normally and that theamendment be effective on the date of issuance with implementation within 60 days.

This license amendment proposed by FPL has been reviewed by the St. Lucie Plant OnsiteReview Group. In accordance with 10 CFR 50.91(b)(1), a copy of this application, withattachments, is being provided to the designated Florida State Official.

Florida Power & Light Company

6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2013-233

1 declare Linder penalty of perjury that the foregoing is true and correct.

Executed on %Lt, FaIJo 2.olq

If you should have any questions regarding this submittal, please contact Mr. Eric Katzman,Licensing Manager at 772-467-7734.

Sincerely,

""Jseph JensenSite Vice PresidentSt. Lucie Plant

Attachments: 1. Description and Assessment2. Proposed Technical Specification Changes3. Revised Technical Specification Pages4. Regulatory Commitments5. Proposed Technical Specification Bases Changes

cc: Ms. Cynthia Becker, Florida Department of Health

St. Lucie Units 1 and 2 L-2013-233Docket Nos. 50-335 and 50-389 Attachment 1

Page 1 of 5

ATTACHMENT 1

DESCRIPTION AND ASSESSMENT

1.0 DESCRIPTION

The proposed amendment would modify technical specifications (TS) requirements for modechange limitations in LCO 3.0.4 and SR 4.0.4.

The changes are consistent with Nuclear Regulatory Commission (NRC) approved Industry /Technical Specification Task Force (TSTF) STS change TSTF-359, Revision 9. On April 4,2003, the NRC published the Notice of Availability for TSTF-359, Revision 8 in FederalRegister Notice 68 FR 16585. That Federal Register Notice announced the availability of thisTS improvement through the consolidated line item improvement process (CLIIP). The NRCsubsequently made two modifications in response to comments, as well as one editorial change,which have been incorporated into TSTF-359, Rev. 9. The changes proposed in this submittalare; therefore, based. on TSTF-359, Rev. 9.

2.0 ASSESSMENT

2.1 Applicability of Published Safety Evaluation

FPL has reviewed the safety evaluation published in Federal Register Notice 68 FR 16585, datedApril 4, 2003, which supports the CLIIP. This review included a review of the NRC staff sevaluation, as well as supporting information provided to support TSTF-359, Revision 8 (andsubsequently, Revision 9 to TSTF-359). FPL has concluded that the justifications presented in theTSTF proposal and the safety evaluation prepared by the NRC staff are applicable to St. LucieUnit 1 and St. Lucie Unit 2 and justify this amendment for incorporation of the changes into theSt. Lucie Unit 1 and St. Lucie Unit 2 TS.

2.2 Optional Changes and Variations

Insofar as the TS for St. Lucie Unit 1 and St. Lucie Unit 2 are custom TS, FPL is not proposingany substantive changes or variations from the TS changes described in TSTF-3 59, Revision 9and the NRC staffs model safety evaluation dated April 4, 2003.

Additional information related to each affected St. Lucie Unit 1 and St. Lucie Unit 2 TS isprovided in the following tables.

St. Lucie Units 1 and 2Docket Nos. 50-335 and 50-389

L-2013-233Attachment 1

Page 2 of 5

St. Lucie Unit 1

The following Technical Specifications are changed to conform to TSTF-359, Revision 9.

TS No. Title Page3.0.4 APPLICABILITY - LIMITING CONDITION FOR OPERATION 3/4 0-14.0.4 APPLICABILITY - SURVEILLANCE REQUIREMENTS 3/4 0-23.4.8 SPECIFIC ACTIVITY 3/4 4-173.4.13 POWER OPERATED RELIEF VALVES 3/4 4-593.5.3 ECCS SUBSYSTEMS - SHUTDOWN 3/4 5-73.7.1.2 AUXILIARY FEEDWATER SYSTEM 3/4 7-43.8.1.1 A.C. SOURCES - OPERATING 3/4 8-3

The following Technical Specifications have pre-existing LCO 3.0.4 exceptions. TSTF-359,Revision 9 removes all existing LCO 3.0.4 exceptions; therefore, these exceptions are beingremoved.

TS No. Title Page(s)Table REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-23.3-1 3/4 3-3

3/4 3-4Table ENGINEERED SAFETY FEATURE ACTUATION SYSTEM 3/4 3-103.3-3 INSTRUMENTATION 3/4 3-11

3/43-123.3.3.1 RADIATION MONITORING INSTRUMENTATION 3/4 3-213.3.3.8 ACCIDENT MONITORING INSTRUMENTATION 3/4 3-413.4.6.1 REACTOR COOLANT SYSTEM LEAKAGE DETECTION 3/4 4-12

SYSTEMS3.6.1.3 CONTAINMENT AIR LOCKS 3/4 6-103.7.1.1 TURBINE CYCLE SAFETY VALVES 3/4 7-13.7.1.5 MAIN STEAM LINE ISOLATION VALVES 3/4 7-93.7.5.1 ULTIMATE HEAT SINK 3/4 7-183.7.9.1 SEALED SOURCE CONTAMINATION 3/4 7-273.9.12 FUEL POOL VENTILATION SYSTEM - FUEL STORAGE 3/4 9-123.11.2.5 EXPLOSIVE GAS MIXTURE 3/4 11-143.11.2.6 1 GAS STORAGE TANKS 3/4 11-15



Page 3 of 5

St. Lucie Unit 2

The following Technical Specifications are changed to conform to TSTF-359, Revision 9.

TS No. Title Page3.0.4 APPLICABILITY - LIMITING CONDITION FOR OPERATION 3/4 0-14.0.4 APPLICABILITY - SURVEILLANCE REQUIREMENTS 3/4 0-23.4.8 SPECIFIC ACTIVITY 3/4 4-253.4.9.3 OVERPRESSURE PROTECTION SYSTEMS 3/4 4-363.5.3 ECCS SUBSYSTEMS - SHUTDOWN 3/4 5-73.7.1.2 AUXILIARY FEEDWATER SYSTEM 3/4 7-43.8.1.1 A.C. SOURCES - OPERATING 3/4 8-3

The following Technical Specifications have pre-existing LCO 3.0.4 exceptions. TSTF-359,Revision 9 removes all existing LCO 3.0.4 exceptions; therefore, these exceptions are beingremoved.

TS No. Title PageTable REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-23.3-1 3/4 3-3Table ENGINEERED SAFETY FEATURES ACTUATION SYSTEM 3/4 3-123.3-3 INSTRUMENTATION 3/4 3-13

3/43-143/4 3-15

3.3.3.1 RADIATION MONITORING INSTRUMENTATION 3/4 3-243.3.3.5 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION 3/4 3-383.3.3.6 ACCIDENT MONITORING INSTRUMENTATION 3/4 3-413.4.4 PORV BLOCK VALVES 3/44-103.4.6.1 REACTOR COOLANT SYSTEM LEAKAGE DETECTION 3/4 4-18

SYSTEMS3.6.1.3 CONTAINMENT AIR LOCKS 3/4 6-93.7.1.1 TURBINE CYCLE SAFETY VALVES 3/4 7-13.7.1.5 MAIN STEAM LINE ISOLATION VALVES 3/4 7-93.7.5.1 ULTIMATE HEAT SINK 3/4 7-153.7.10 SEALED SOURCE CONTAMINATION 3/4 7-283.11.2.5 EXPLOSIVE GAS MIXTURE 3/4 11-143.11.2.6 GAS STORAGE TANKS 3/4 11-15


Page 4 of 5

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination

FPL has reviewed the proposed no significant hazards consideration determination (NSHCD)published in the Federal Register as part of the CLIIP. FPL has concluded that the proposedNSHCD presented in the Federal Register notice is applicable to St. Lucie Unit 1 and St. LucieUnit 2 and is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).

3.2 Verification and Commitments

As discussed in the notice of availability published in the Federal Register on April 4, 2003 forthis TS improvement, plant-specific verifications were performed as follows:

FPL has established TS Bases for LCO 3.0.4 and SR 4.0.4 which state that use of the TS modechange limitation flexibility established by LCO 3.0.4 and SR 4.0.4 is not to be interpreted asendorsing the failure to exercise the good practice of restoring systems or components tooperable status before entering an associated mode or other specified condition in the TSApplicability.

The modification also includes changes to the bases for LCO 3.0.4 and SR 4.0.4 that providedetails on how to implement the new requirements. The bases changes provide guidance forchanging Modes or other specified conditions in the Applicability when an LCO is not met. Thebases changes describe in detail how: LCO 3.0.4.a allows entry into a MODE or other specifiedcondition in the Applicability with the LCO not met when the associated ACTIONS to beentered permit continued operation in the MODE or other specified condition in theApplicability for an unlimited period of time; LCO 3.0.4.b allows entry into a MODE or otherspecified condition in the Applicability with the LCO not met after performance of a riskassessment addressing inoperable systems and components, consideration of the results,determination of the acceptability of entering the MODE or other specified condition in theApplicability, and establishment of risk management actions, if appropriate; and LCO 3.0.4.callows entry into a MODE or other specified condition in the Applicability with the LCO not metbased on a Note in the Specification, which is typically applied to Specifications which describevalues and parameters (e.g., Containment Air Temperature, Containment Pressure, MCPR,Moderator Temperature Coefficient), though it may be applied to other Specifications based onNRC plant-specific approval.. The bases also state that any risk impact should be managedthrough the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance,NRC Regulatory Guide 1.182. "Assessing and Managing Risks Before Maintenance Activities atNuclear Power Plants," and that the results of the risk assessment shall be considered indetermining the acceptability of entering the MODE or other specified condition in theApplicability, and any corresponding risk management actions. In addition, the bases state thatupon entry into a Mode or other specified condition in the Applicability with the LCO not met,LCO 3.0.1 and LCO 3.0.2 require entry in to the applicable ACTIONS until the condition isresolved, until the LCO is met, or until the unit is not within the Applicability of the TS. The


Page 5 of 5

bases also state that SR 4.0.4 does not restrict changing MODES or other specified conditions ofthe Applicability when a Surveillance has not been performed within the specified Frequency,provided the requirement to declare the LCO not met has been delayed in accordance with SR4.0.3. Finally, FPL has a bases control program consistent with Section 5.5 of the STS, and theequivalent of STS SR 3.0.1 and associated bases.

4.0 ENVIRONMENTAL EVALUATION

FPL has reviewed the environmental evaluation included in the model safety evaluation datedApril 4, 2003 as part of the CLIIP. FPL has concluded that the staff's findings presented in thatevaluation are applicable to St. Lucie Unit 1 and St. Lucie Unit 2 and the evaluation is herebyincorporated by reference for this application.

St. Lucie Units I and 2Docket Nos. 50-335 and 50-389


Page 1 of 54

ATTACHMENT 2

PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)


Page 2 of 54

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

3/4.0 APPLICABILITY

LIMITING CONDITiON FOR OPERATION

3.0.1 Compliance with the Limiting Conditions -for Operation. (LCO) contained.inthe succeeding. specifications is required during the OPERATIONAL MODES or otherconditions specified therein; except that upon:failure to meet the LimitingConditions for Operation, the associated ACTION :requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements ofthe Limiting Condition for Operation (LCO) and associated ACTION requirementsare not.met within the:specified time intervalsi If the Limiting Conditionfor Operation is restored prior to expiration.ofthe specified time intervals,completion of the ACTION requirements is not required.

3.0.3 When aLimiting Condition for Operation (LCO) is not met, except asprovided in the associated ACTION requirements, within 1 hour action shall beinitiated to place the unit in a MODE in which specification does notapply by placing it,. as: applicable in:

1.. At.. ieast.HOT STANDBY within the neXt 6 hours.,2. At::least HOT SHUTDOWN within the following, 6 hours, and3. At least COLD SHUTDOWN within the subsequent 24 hours.

Where corrective measures are completed that permit.operationwunder theACTION requirements, the ACTION may be taken in accordance with the specifiedtime limits as measured from the time of failure to meet the .LCO. Exceptions'to these requiremen.ts. are stated in. the individual specifications.

This specification is not applicable in MODES .5 or 6.8 . .4E n~try in to a n O P E R A T IO N A L M O D E o r o t hle r s p e c liie d "ia p p .ic a .bil .itY c o n d itio n "

hal o t be made when the conditions of .the..L imi~ting. Condition for. Operation. ,

are not met and the associated ACTION requires a~shutdown if they Are not met •

wihnaspecified timne interval. En~try into an OPERATIONAL MODE or specified |,

.ondiiomay be made in accordance with ACTION reu-r~mnt whe coformane..

to them permits continued operation of.the facility for an unli~m ited .period . ...

of;time.. This provision.shall not.prevent passage through or to OPERATIONALMODEs as-required. to comply with ACTION:statements. Exceptions to these,.: tq uirements are stated in.the individual. specifications..

. , ... .j ,. .... ... ... _ 7_ . .. ...... 7 .

ST. LUCIE -:UNIT 1 3/40o-1 Amendment No. 40, 08,103


Page 3 of 54

INSERT I (LCO 3.0.4)

When an LCO is not met, entry into a MODE or other specified condition in theApplicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operationin the MODE or other specified condition in the Applicability for anunlimited period of time;

b. After performance of a risk assessment addressing inoperable systemsand components, consideration of the results, determination of theacceptability of entering the MODE or other specified condition in theApplicability, and establishment of risk management actions, ifappropriate; exceptions to this Specification are stated in the individualSpecifications, or

c. When an allowance is stated in the individual value, parameter, or otherSpecification.

L-2013-233Attachment 2Page 4 of 54

APPLICABILITY

SURVEILLANCE REQUIREMENTS

4.0.1 Surveillance Requirements shall be applicable. during the OPERATIONAL MODES. orother conditions specified forindividual.Limiting Conditions.for Operation unless otherwisestated in an individual Surveillance Requirement. Failure to perform :a SurveillanceRequirement within the allowed surveillance interval, defined by Specification 4,0.2i shallconstitute.noncompliance With the OPERABILITY requirements for a Limiting. Condition forOperation. Surveillance Requirements do not have'to be: performed on inoperableequipment.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillancb.einterval with a .maximum allowable extension. not to exceed 25% of the specifiedsurveillance interval.

4.0.ý3 If it is.discovered that a Surveillance was not performed within its specified frequency,then compliance with the requirement to declare the Limiting Condition for Operation notmet may be delayed,: from the time of discovery, up to 24 hours: or up to the limit .6f thespecified frequency, whichever is greater. This delay period is permitted to allowperformance of the Surveillance. A risk. evaluation shall be performed for any Surveillancedelayed greater than 24.hours and the risk impact shall be managed.

If the Surveillance is not performed Within the delay period, the Limiting Condition forOperation must immediately be declared not met, and the applicable ACTION(s) must be:taken.

When the Surveillance is performed within the delay period and the Surveillance is notmet, the Limiting Condition for Operation must immediately be declared not met,. andtheapplicable ACTION(s) must be taken. .. 4C. .

4.0.4. Entryinto an OPERATIONAL MODE or other specified applicability condition sallýnotbemad :e.un~less the.Surveillance.Requirement(s) associated with the Limiting Condition for :Op rain ha e been performed within: the stated surveillance interval. or as otherwise )

E/pddiid. This provisoi. shall not predVet passage thro)ugh~ or46t OPERATIONAiL/,,MODSasrqitedt t'Comply: with.ACTION requirements. •/

4.0.5 Surveillance Requirements for inservice inspection of ASME Code Class 1, 2 and 3componhents shall be applicable:.as follows:

a.. Inservice inspection of ASME Code Class 1, 2 and 3 components shallbe performed in accordance with.Section XI of the ASME Boiler and PressureVessel Code and applicable Addenda as. required .by 1t0 .CFR 50,Section 50.55a(g), .extept.where:sp.ecific.written relief has been granted by theCommission purisuant to 1.0 CFR.50,:.Section 50.55a(g) (6) (i).

b. deleted

ST. LUCIE-.- UNIT 1 314 0-2 Amendment No 26,40,00, g408, 463, 18.6


INSERT 2 (SR 4.0.4)

Entry into a MODE or other specified condition in the Applicability of a LimitingCondition for Operation (LCO) shall only be made when the LCO's Surveillanceshave been met within their specified frequency, except as provided bySurveillance Requirement 4.0.3. When an LCO is not met due to Surveillancesnot having been met, entry into a MODE or other specified condition in theApplicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions inthe Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.

TABLE 3.3-1

REACTOR PROTECTIVE INSTRUMENTATION

.FUNCTIONAL: UNIT

1. Man.ual Reactor Trip

2. Power Level'- High

.3. Reactor Coolant Flow - Low

•4. Pressurizer Pressure - High

5. Containment.Pressure - High

6. Steam Generator Pressure - Low

7. Steam Generator WaterLevel - Low

8. Local Power Density - High

9. Thermal Margin/Low Pressure

9a. Steam Generator?.PressUre:Difference -High

10. Loss of Turbine - HydraulicFluid Pressure -..Low

TOTAL NO.OF CHANNELS

:

4

,4/SG:

4

4

4/S:G

4/SG

CHANNELSTO TRIP

1

.2(a)

2(a)/SG

2

2

2(b)/SG.

2/SG

MINIMUMCHANNELSOPERABLE

2:

3(T)

3/SG

3

3.3/SG

3/SG

APPLICABLEMODES

1, 2.and*

1, 2 (e)

1,2

1.,2

1,:2'

1,.2

ACTION

1

2B

4

4

4

4.

.2(c)

.2(a)

2(a)

3

3

3

,3

1

1, ::2 (e)

1,2. (e)

12(c)

>~

ST. LUCIE - UNIT 1 -3/4 3-2 Amendment No. 445,43

TABLE 3.3-1 (Continued)

REACTOR PROTECTIVE, INSTRUMENTATION


CHANNELSTO TRIP

MINIMUMCHANNELSOPERABLEFUNCTIONAL UNIT

11. Wide.Range LogarithmicNeutronFlux Monitor

a. Startup and Operating -Rate of.Change of Power -High

b. Shutdown

1.2.. Reactor'Protection SystemLogic

1:3. Reacto.r Trip.Breakers

APPLICABLEMODES ACTION

4

4

4

4

:2(d)

0

2

2

3

2

4

4

1, 2 and*

3, 4,.5

1, 2*

1., :2*

3

4

4

-U>

0,

CD,

ST. LUCIE - UNIT 1 314 3-3 •U3Amendment No...45 27


Page 8 of 54

TABLE 3.3-1. (Continued)

TABLE NOTATION

* With the protective system trip breakers 6n the closed position and the CEA&drive system capable:of CEA withdrawal.

-#-T-he-previsionsf-Speeif4eat4eno-..O4-afre9otapplioable,----

(a) Trip may be bypassed below 1% of RATED THERMAL POWER; bypass shall be automaticallyremoved when Wide Range Logarithmic Neutron Flux power is> 1% of RATED THERMALPOWER;

(b) Trip may be manually bypassed below 685 psig; bypass shall be automatically removed at orabove 685 psig.

(c). Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automaticallyremoved when Power Range Neutron Flux power is> 15% of RATED THERMAL POWER.

(d) Trip may be6bypassed beloW: 104%.and :above 15% of RATED THERMAL.POWER; bypassshall be automatically removed when Wide Range Logari.thmic Neutron Flux power is > 10"4%'and Power Range Neutron Flux power < 15% of RATED THERMAL POWER:..

(e) Deleted.

(f) There shall be at least two decades of overlap between the Wide Range Logarithmic NeutronFlux Monitoring Channels and the Power Range Neutron Flux .Monitoring Channels.

ACTION STATEMENTS

ACTION 1 With the number of channels OPERABLE one less than required by the Minimum

Channels.OPERABLE requirement, restore the inoperable channelItoOPERABLEstatus within 48 hours or be in HOT STANDBY within the next 6 hours and/oropen the protective system trip breakers.

ACTION 2: - With the number of OPERABLE channels one less than the Total. Number ofChannels, STARTUP and/or POWER OPERATION may proceed provided thefollowing conditions are satisfied:

a. The..inoperable channel is placed in.either the bypassed or tripped conditionwithin 1 .hour. For the purposes of testing and maintenance, the inoperablechannel may be bypassed for up to.48 hours from time of initial loss ofOPERABILITY; however, the inoperable channel shall then be eitherrestored. to OPERABLE status or placed, in the tripped condition.

ST..LUCIE - UNIT 1 3/43.-4 Amendment No. 46, 27, 45,402,159:

TABLE"3.3-3

"ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

TOTAL. NO.OF

CVANNELSCHANNELS'

TO TRIP

MINIMUMCHANNELSOPERABLEFUNCTIONAL UNIT I.

I, SAFETY INJECTION (SIAS).a. Manual (Trip Buttons)b. Containment Pressure -High

c. Pressurizer Pressure -

Low

2. CONTAINMENT SPRAY (CSAS).a. Manual: (Trip. Buttons)b.. Containment Pressure -

High-High

3. CONTAINMENT ISOLATION, (CIS)a...Manual. (Trip. Buttons):b.. Containment Pressu-re -

High,.c, Containment Radiation -

:Highd. SIAS

4. M.AN STEAM LINE ISOLATION(MSIS)

a. Manua.l .rip Buttons)

b. Steam GeneratorPressure.- Low


2

4

4

2

.4

2

.4.

1

2.

2,

1

2(b)

2

2

3

3

2

3:

.2

3

%1,2., 3,4

1,2,3

1,2, 3(a)

!,2,3,4

1,2,3

1,2,3,4.

8

.8

10a, 1.0bf. 10c

8

1, 2,3

.4 2 3 1,2,3,4 9•(S e e F u n ctio n a l U nit .1 a b o v e ) ---- ..... ........ ........-----

2/steam 1/steam 2/operatinggenerator generator steam

'generator4/steam 2/steam .3/steam.generator generator generator

1, 2, 3j 4

1, 2, 3(c)

8

CoCD

0

Amendment No..-4., -3,, 188

0

0LO

ST. LUCIE.-.UNIT 1 •3/4..3-10


ENGINEERED SAFETY .FEATURE ACTUATION SYSTEM INSTRUMENTATION

FUNCTIONAL UNIT.5. CONTAINMENT SUMP

RECIRCULATION (RAS)

a. Manual RAS (Trip Buttonss)

b, RefUeling Water Tank - Low

6. LOSS OF POWER

a. 4.16 kv Emergency Bus Under-.voltage (Loss.of Voltage).

b. :4.16 kv. Emergency Bus Under-voltage (Degraded Voltage)

c. 480 V Emergency: Bus Under-

voltage.(Degraded Voltage)

7.. AUXILIARY FEEDWATER (AFAS)

a. Manual (Trip Buttons)

b. Automatic Actuation Logic

c. SG.Level (1A/1B) -.Low

.8.. AUXILIARY FEEDWATER]ISOLATION

a. SG 1A-SG iB;DifferentialPressure:

b. Feedwater Header1A:-,.1 B DifferentialPressure

TOTAL NO,.OF CHANNELS

CHANNELSTO TRIP


APPLICABLEMODES

2

.4"

1

.2

.2:

3

1, 2,3, 4

1,2, 3

2/Bus

2/Bus

2/Bus

4/SG

.4/SG.4/SG

4/SG

4/SG

:2/Bus

2/Bus

2/Bus

2/SG

.21SG

2/SG

.2JSG

2/SG

1/Bus

1/Buls

1/Bus

4/SG

3/SG

3/SG

3/SG

3/SG

1,2,3

:1, 2, 3

1,2,3

1,2, 3

1.,2,3

1.,.2,..3

1,.2, 3

ACTION.

8

13

12

12

12

11

11

14a§ 14bc 14C

14ag, 14c

-D

o0

0J0•

ST. LUCIE - UNIT I 3/4 3-11. .Amendment No.. 4-,6 , 74, -2- 4 -24-, 188


Page 11 of 54

TABIE 3.3-3 (continued)

TABLE NOTATION

(a) Trip funclion.may be bypassed in this MODE when pressurizer pressureis 1725 psia; bypassshall be automnatically removed when pressurizerpressure.is > 1725 psia.

(b) An SIAS signal is first necessary to enable CSAS logic.

(c) Trip function may be bypassed in this MODE beloW 685 psig; bypassshall be automatically removed .at or above 685 psig.

ACTION STATEMENTS

ACTION 8 - With'the.number of. OPERABLE channels:one less than theTotal. Number Of Channels, restore the inoperable channelto OPERABLE status within 48 hours or be in at least HOTSTANDBY within .the.next 6 hours and in COLD SHUTDOWN withinthe following 30 hours.

ACTION 9 - With the number of OPERABLE channels.one less than.the.Total .Number of Channels, operation rmay proceed.providedthe following conditions are satisfied:.

a. The.inoperable channel is placed in either thiebypassed or tripped condition within 1 hour. Forthe purposes •of testing andmaintenance, the inoperablechannel may be. bypassed for up to 48 hours from timeof:initial loss of OPERABILITY; however, the inoperablechannel shall then be either restored to OPERABLEstatus or placed in the'tripped~condition.

b. W.thih one hour, all functional units receiving aninput from the inoperable channel are also bypassed or tripped..

c. The Minimum Channels OPERABLEirequirement. is rnet;however, one additional channel may be bypassed forup to 48 hours while performing tests and maintenanceon that channel provided the other inoperable channelis placed in the tripped condition.

.ST. LUCIE-ý.UNIT1l 314.3-12 Amendment No. 4-5, i45,202


Page 12 of 54IN5,TPI 'MENTATION

314.3.3 MONITORING INSTRUMENTATION

RADIATION MONITORING

LIMITING CONDITION FOR OPERATION

3.S.3.1 The radiation monitoring instrumentation channels shown inTable 3.3-6 shail be OPERABLE with their alarm/trip Setpbints withinthe specified limits.

APPLICABILITY: As shown: in Table,3.3-6.

ACTION:.

a. With a radiation monitoring channel alarm/trip setpoint exceedingthe value shown in Table 3.3-6, adjust the setpoint towithin the limit within 4 hours:or declare the. channelinoperable.

b. With one or more radiation monitoring channels inoperable,take:the ACTION shown in Table 3.3M6.

c. The provisions of Specification\ 3.0.3 efid&94 are notapplicable.,


4.3.3.1 Each radiation monitoring instrumentation channel shall bedemonstrated OPERABLE by the performance of the.CHANNEL CHECK, CHANNELCALIBRATION and. CHANNEL FUNCTIONAiL TEST operations during the modesand at the frequencies shown in. Table 4,.3-3.

4.3.3.2 At lease once per 18months, each Control. Room Isolation radiation monitoringinstrumentation channel shall be demnonstrated OPERABLE by verifying that theresponse time of the channel:is within limits.

.ST. LUCIE - UNIT I 314 3-21 Amendment No. 40, 4-7 206


Page 13 of 54

INSTRUMENTATION

ACCIDENT MONITORING INSTRUMENTATION

LM1ITGQN DTJ NREQRPRATION

3.3.3.8 The accident monitoring instrumentation channels shown in Table 3.3-11shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. Actions per Table 3.3-11.

,.b.---T-ho-provisions-ofSpeification_3OA-are-not-applicable... ..'-


4.3.3.8 Each accident monitoring instrumentation channel shall be demonstratedOPERABLE by performance of the CHANNEL CHECK and CHANNEL.CALIBRATION operationsat the frequencies shown in Table 4.3-7.,

S.Tý LUCIE - UNIT 1 3/4 3-41 Amendment No. 3, 118


Page 14 of 54

REACTOR COOLANT SYSTEM

W34.4.6 REACTOR COOLANT SYSTEM LEAKAGE

LEAKAGE DETECTION SYSTEMS

.LIMITING •ONDITION .OROPERfTItN

3.486:1 The following RCS leakage detection systems will be: OPERABILE:

a. The reactor cavity sump inlet flow. monitoring.system; and

.b: One containment atmosphere radioactivity monitor (gaseous. or particulate).

APPLICABILITY: MODES.1, 2, 3,,and 4.

.ACTION:.

a. With the reactor cavity sunmp inlet flow monitoring system inoperable with :anoperable containment particulate radioactivity monitor, perform a RCS waterinventory balance at least once per 24* hours and restore.the :sump inlet flowmonitoring.systemf to OPERABLE status within 30 days; otherwise, be in .at leastHOT STANDBY within the next&6 hours and in COLD SHUTDOWN within thefollowing 30 hours.

b. With the reactor cavity sump inlet flow monitoring system inoperable with only the:co.ntainment gaseous radioactivity monitor operable, perform an RCS waterinventory balance at least once per 24* hours and analyze grab samples 0f thecontainment atmosphere at least once per 1.2 hours; and either restore the sumpinlet flow monitoring: system to OPERABLE status within 7 days or restore thecontainment particulate radioactivity monitor to OPERABLE status within 7 days andenter action a. above with the time.in this action applied against the allowed outagetime of action a.'; otherwise, be in at least"HOT"STANDBY~within the next 6: hoursand in COLD SHUTDOWN within the following 30 hours.

c. With the required radioactivity monitor inoperable, analyze grab samples of thecontainment atmosphere or perform.a RCS water inventory balance at least.onceper 24*hours, and restore the required.radioactivity monitor to OPERABLE'status-within 30 days;. otherwise, :be inat least HOT STANDBY within the.next 6.hours andin COLD.SHUTDOWN within the following 30 hours.

d. With all.required monitors inoperable, enter LCO3.0.3 immediately.

-Riobor "c " ~A .•


4.4.6.1 The RCS leakage detection.:instruments shall be demonstrated OPERABLE by:

a. Pe.rfrmance.of t.he CHANNEL.CHECK, CHANNEL FUNCTIONAL TEST, and,CHANNEL CALIBRATION of the'required containment atmosphere radioactivitymonitor atthe frequencies specified in Table 4.3-3.

b: Performance of the CHANNEL CALIBRATION of the reactor cavity sump inlet flow.

monitoring system.at least once per 18 months..

t Not required to be performed until 12. hours after establishment of steady state operation.

ST., LUCIE - UNIT I. 3/4.41-12 SAmendment No. 4.44•.4, Z..212


RFACTOP rO. ANT SYSTEM Page 15 of 54

SPECIFIC ACTIVITY

LIMITING CONDITION" FOROPERATION

3.4.8 The specific activityof the primary coolant shall be limited to:.

a. < 1.0 piCi/gram DOSE EQUIVALENT 1-13.1, and

b. < 518.9 pCi/gram DOSE EQUIVALENT XE 133..

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:1

a. With.the.specific activity of the primary coolant >1.0 pCilgram DOSE.EQUIVALENT 1-131, verify DOSE EQUIVALENT I-131. is '60.0 pCi/gram once

per four hours.

b. With the. specific activity of the. 'primary coolant > 11.0. •.Ci/gram DOSEEQUIVALENT 1-131., but.<60.0 pCi/g.ram DOSE EQUIVALENT 1-.131, operationmay. continue for up to 48 hours while efforts are made to restore DOSEEQUIVALENT 1-131 to within .the 1.0 [lCi/gram limit. Speciftation-3.--4-i~s-.• e o -abi .. ,€.O i3 ".. .. .

c. :With the specific :a.ctivity of the primary coolant > 1.0 pCi'gram DOSEEQUIVALENT 1-1.31 for greater than 48 hours during one continuous time.interval, or > 60.0 pCi/gram DOSE EQUIVALENT 1-131, be in HOT STANDBYwithin 6 hours and COLD SHUTDOWN within the following30.hours.

d., With the specific activity of the primary coolant > 518.9 p.Ci/gram:DOSEEQUIVALENT XE-i33, operation maycontintue for' up to 48 hours while efforts.are made to restore DOSE.EQUIVALENT XE-1 33 to within the.518g9 itCi/gramDOSE EQUIVALENT XE-1 33 limit. L.,peefi -e-.'s a1lisale. Lo-O 3.0.4.

e. With the specific:activity of the primary coolant.> 518.9 jtCi/granm DOSEEQUIVALENT XE-133 for greatefrthan 48 hours during one continuous time..interval, be in HOT STANDBY Within 6 hours and COLD SHUTDOWN within thefolloWing 30 hours.


4.4.8 The specific, activity of the primary coolant shall be determinedto be within the limits by performance Of the sampling and analysis pro-g arafn of:Table 4.4-4.

S.T. LUCIE - UNIT 1 • 3/4 4-17 Amendment No. 69, 40-;, 213


REACTOR COOLANT SYSTEM Page 16 of 54

POWER OPERATED RELIEF VALVES

UIMIIIL _N.DJTOfN FOR OPERATION

34.13 Two power~operated relief valves (PORVs) shall be.OPERABLE, with theirsetpoints selected to the low temperature mode of operation as follows:

a. A setpoint of less than or equal to 350 psia shall be selected during heatup, cooldownand isothermal conditions when the temperature of any RCS cold leg is less than orequal to 2000 F.

.b. A setpoint of less than or equal to.530 psia shal.be selected during heatupý..cooldownand isothermal conditions. when. the temperature of any RCS cold leg isgreater than200OF and less than or equal to 300°F.

APPLICABILITY: MODE 4 when the temperature of any:RCS cold leg is:less thanor equal to 3001F, MODE.5, and MODE 6 When the head is on the reactor vessel;:and the RCS is not veihted through greater than a 1.75 square inch vent,

:ACTION:

a.. With ohe PORV inoperable in MODE 4, restore.the inoperable PORV toOPERABLE status within 7 days; or depressurize and vent the RCSthrough greater. than a 1.75 square.inch vent within the next 8hours.

b.. With one PO.RV inoperable, in MODES: 5 or 6, either (1) restore the.inoperable PORV to OPERABLE status within 24 hours; or (2), complete,depressurization and venting of.the RC.S through. greater than a 1.75square inch vent within a total of 32 hours.

c. With both PORVs inoperable, restore at least one PORV to operablestatus or complete dePressurizatio'nand venting of the. RCS throughgreater than a 1.75 squareinch vent within 24 hours.

d. With the RCS vented. per ACTIONS a,. b,. orc, verify the vent pathwayat least once"per'31 days when the pathway is provided by a valve(s)that is locked, sealed or otherwise secured in the open position;.

otherwise, verify the vent, pathway every 12 hours•.

e. .In the:event.either'the PORVs or the RCS.vent(s) are used tomitigate an RCS pressure transient, :a speial Report shall beprepared and submitted to the: Commission pursuant .to Specification6.9:2. within 30 days. The report shall describe the circumstancesinitiating the transient, the effect of the PORVs or RCS vent(s).onthe transient, and any corrective: action necessary to prevent.recurrence.

f. hp i LC 3.,, 446ppt~ecz,6t0 +c- POR\Js. Win"b elle4.h

SURVEILLANCE: REQUIREMENTS

4.4.13 Each PORV shall be demonstrated OPERABLE, by:

a. Verifying the PORV isolation valve is: open at least once per 72hours; and

b. Performance of a CHANNEL FUNCTION•TEST, but excluding valveoperation, at least once per 31 days; and.

c. Performance, of'a CHANNEL CALIBRATION at least once per 18 months.

ST. LUCIE - UNIT 1. 3V4 4-59 Amendment. No. 60, 84,i404, 432,213


Page 17 of 54

EMERGENCY CORE COOLING SYSTEMS

ECCS SUBSYSTEMS - SHUTDOWN


3.5.3 As a minimum, one ECCS subsystem comprised of the following shall beOPERABLE:

a. In MODES ,3* and 4#:, one EGGS subsystem composed of one OPERABLE. highpressure safety injection pump and one OPERABLE flow path capable oftaking suction fiom the. refueling water storage tank on a safety injectionactuationrsignal and automnaticallyitransferring suction to the containment sumpOn a sump recirculation actuation signal.

b. Prior to decreasing the reactor coolant system temperature below 270°F amaximum..of only one high pressuresafety injection pump shall be OPERABLEwithits associated header stop valve open.

c. Prior to decreasing the reactor coolant system temperature below 236*F.allhigh pressure safety. injection pumps :shall be disabled and their associatedheader stop valves closed except as allowed by:Specifications 3.1.2.1 and3.1.2.3.

APPLICABILITY: MODES 3* and 4.MODES 5 and 6 when the Pressurizer manway cover is in place and.the reactor vessel head is: on.

ACTION:

a. 'With no EGCS subsystems OPERABLE in MODES 3* and 4., immediatelyrestore one ECCS subsystem' to OPERABLE status or be in COLDSHUTDOWN within 20 hours.

b. With RCS temperature below. 2700F and'with more than the allowed highpressure safety injection pump OPERABLE or injection valves: ahd headerisolation valves open, immediately disable the high pressure safety injectionpump(s) or close the header isolation valves.

c. In the event the ECCS is actuated and :injects water into the Reactor CoolantSystem, a Special Reportshall be prepared and submitted to the. Commissionpursuant to Specification: 6.9.2 within 90 days describing the circumstances ofthe actuation and the total accumulated actuation cycles to date.:L L..O3.6.4..A at$ "i4~Pel4'"1 .6 ODS.V11 Pvelsuiv6

~kAIei~ 8dSYjS41 eý+AODC~ 4.SURVEILLANCE R~I1 EMENTS'

4.5.3.1 The ECCS subsystem shall be demnibstrated OPERABLE per the applicableSurveillance Requirements of 4.5.2.

4.5.3.? The high pressure safetyinjection pumps shall be verified inoperable and theassociated header stop valves closed prior to decreasing below the above. specifiedReactor Coolant System temiperature and once per month when the ReactorCoolant.System is at refueling temperatures.

* With .pressusrizer pressure < 1750 psia.

# REACTOR COQLANT SYSTEM'cold leg temperature above 2500F.

%ST. LUCIE -.UNIT 1 3/4 5-7 Amendmen.N0..28:60, 84-,404, 443. 177


Page 18 of 54

CONTAINMENT SYSTEMS:

CONTAINMENT AIR LOCKS

LIMITING.CONNDITION FOR OPERATION

.3.6.1.3 Each .containmeint air lock shall be. OPERABLE with:

a, Both doors closed except when the air lock is being used forrnormal transitentry and exit through thie. containment, then at least: one air lock door shallbe closed., and

b. An overall air lock leakage rate in accordance with the Containment LeakageRate Testing Program.

APPLICABILITY. MODES. 1, 2, 3 and 4.

ACTION:

a. With one containment air lock door inoperable*'

1. Maintain at least the OPERABLE air lock door closed and either restorethe inoperable air lock door to OPERABLE status within 24. hours or lockthe OPERABLE air lock door closed.

2' Operation may then continue until performance of the next requiredoverall air lock. leakage test provided that the. OPERABLE, air lock dooris verified to be closed at least• once per 31 days.

3. Otherwise, be in at least HOT"STANDBY'within the.next 6 hours and in

COLD SHUTDOWN .within the following. 30 hours.

b.. With the containment air lockinopefable, except as:the result of aninoperable air lock.door,. maintain at least one air lock door closed; restorethe inoperable air lock to.OPERABLE status within-24 hours or be in-atleastHOT STANDBY within the next 6 hours and in COLD SHUTDOWN withinthe following: 30 hours.

.SURVEILLANCE REQUIREMENTS,

.4.6.1.3 Each: containment air lock shall be. demonstrated OPERABLE:

If the inner air lock dooris inoperable, passage through the. OPERABLE outerair lock door

is permitted to effect, repairs to the inoperable inner air. lock door. No mhore than one airlockdoor shall be.open at- an.ytime.

•ST. LUCIEý-:UNIT•! •3/4 6A 10 Amendment No. 85, 149.


3/4.7 PLANT SYSTEMS Page 19 of 54

3.4.7,1 TURBINE CYCLE

SAFETY VALVES


3.7.1,1 All main steam line Code safety Valves shall be OPERABLE with lift settings as specifiedin'Table 4.7-1.

APPLICABILITY: MODES 1, 2 and .3.

ACTION:

a. With boih reactor coolant loops and associated steam generators in operation:andwith one or more main steam line code safety valves inoperable, operation inMODES 1, 2 and 3 may proceed provided that within 4 hours,. either the inoperable.valve is restored to OPERABLE status. or the Power Level-High trip. setpoint, isreduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next6:.hours and in COLD. SHUTDOWN within the following 30 hours.

,.-b.----T-he-povisions-ofS'pecifieation-3.-.4-are:not -applicable... _(.


4.7.1.1 Verify each main steam lin.e.. code safety valve is OPERABLE in accordance with theInservice Tessting Program. Following testing, as-left lift settings shall be within +1- 1/0 of1000 psia for Valves 8201 through 8208, and-within +/- 1% of 1040 psia for Valves 8209through 8216 specified in Table 4.7-1.

•ST., LUCIE.-..UNIT1.! 3/4 7:1 Amendmnent No. 90,453,166


PLANT SYSTEMS Page 2(

AUXILIARY FEEDWATER SYSTEM


3.7. 1.2 At least three independent steam generator.auxiliary feedwaterpumps and associated flow paths shall beOPERABLE with:

a. Two motor driven feedwater pumps, and

b. One feedwater pump capable of being powered from an OPERABLE

steam supply system.

APPLICABILITY: MODES 1,.2 and 3.

ACTION:

o.. With one auxiliary feedwater pump inoperable, restore at least threeauxiliary feedwater pumps (two motor driven pumps and one capable ofbeing powered by an OPERABLE steam supply system) to OPERABLE statuswithin 72 hours or be in HOT SHUTDOWN within the next,12 hours.

6b. LCO 3.O04.._ 6 ,IS,+ I Ica I6..SURVEILLANCE REQUIREMENTS

4.7.1.2 Each: auxiliary feedwater pump shall be demonstrated OPERABLE:

a. At least once per 31 days by:

) of 54

I

ST. LUCIE - UNIT I •3M4 7-4 Amendment No. 35, 90i 199

L-2013-233Antachnment 2

Page 21 of 54PLANT SYSTEMS

MAIN STEAM LINE ISOLATION VALVES

LIMIIN3 CNDITION FOR OPERATION

3.7.1.5 .Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1:, .2 and 3.

ACTION:

MODE I - With one main steam line isolation valve inoperable, POWER OPERATION maycontinue. provided the inoperable valve is either restored to OPERABLE~status orclosed within 4 hours; :otherwise, be in HOT STANDBY within the next 6 hours..

MODES 2 -and 3

With one or both main steamiso!atioh valve(s) inoperable, subsequent operation inMODES 2 or 3 may proceed provided the .isolation valve(s) is (are) maintainedclosed' Otherwise, be in at least. HOT STANDBY within the next 6 hours and inCOLD SHUTDOWN within the following 24 hours,

,,-4previs• oS-,.p~eeifieatortra, e~tap~li•ablae~

_S_3ELL __I•E.BEOUIREMENTS

4.7.1.5 Each main steam line isolation valve that is open shall .be demonstrated OPERABLE byVerifying full closure Within 6.0 seconds when tested pursuant to the I nservice TestingProgram.

.ST. LUCIE.- UNIT'! "3/4 7-9 Amendment. No. 69,.444, 153

L-2013-233PLANT SYSTEMS Attachment 2

314.7.5 ULTIMATE HEAT SINK Page 22 of 54

LIMITING CONDITION FOR OPERATION0.

3.7.5.1 The ultimate heat sink shall be OPERABLE with::

a Cooling water Ifrom the Atlantic Ocean providing a water level above-10.5 feet elevation, Mean Low Water,..at.theplant intake structure,and

b. Two OPERABLE valves in the barrier dam between Big .Mud Creek and.the intake structure.

APPLICABILITY: At all times.

ACTION:

a. With the water: level requirement of the above Specification notsatisfied, be in at least HOT STANDBY within six hours and providecooling water from Big Mud Creek within the next 12. hours.

b. With one isolation valve in the barrier dam between Big Mud Creek.and the intake structure inoperable, restore the inoperable valve.to.OPERABLE status within 72 hours. or, within the next 24 hours.install a temporary flow barrier, and open the barrier damn isola-tion valve. The availability of-the onsite equipment capable ofremoving the barrier shall be verified at least once per sevendays thereafter.

c.. With both of the isolation valves in the barrier dam between. the in-take•structure .and Big.Mud Creek inoperable, within 24 hours either:

1.) Install both temporary flow barriers and manually open bothbarrier dam isolation valves. The availability of.the onsiteequipment capable of removing the barriers. shall be verifiedat least once per seven days thereafter, or

2) Be in at least HOT STANDBY within.the. next 6.hours.and inCOLD SHUTDOWN within the following 30 hours.

d~hepvei~i~s-f- Beifpa'tierow-4)are-rnot-applieableý..

SURVEILLANCE REQUIREMENTS!

4.7.5.1.1 The ultimate heat sink shall be determined OPERABLE at least onceper 24 hours by verifying the average water level to be within the limits, J.

4.7.5.1.2 The isolation valves in the barrier dam between the intake structureand Big Mud Creek shall be demonstrated OPERABLE at least once per six months%by cycling each valve.,through, at leastoe.necomplete cycle of full. travel.

.ST. LUCIE - UNIT'1 .3/4 7o.18 Amendment No. 54

L-2013-233Attachrnent 2

PLANT SYSTEMS Page 23 of 54

314.7.9 SEALED SOURCE CONTAMINATION

LIMITING CONDITION FOR OPERATLON

3.7,9.1 Each sealed source containing.radioactive material either inex)cess of 100 microcuries :of beta;and/or gamma emitting material or 5microcuries of alpha emitting material shall be free of > 0.005 microcu-ries of removable. contamination.

APPLICABiLITY: At all timeS..

ACTION:

a. Each sealed source with removable contamination in excess ofthe above limit shall be immediately withdrawn from use and:

1. Either decontaminated and repaired, or

2. Disposed of inaccordance with Commission Regulations.

b. The provisions ofSpecificationk..3.0.3"ai-3.-4 are notapplicable.

.SURVEILLANCE RE.QUIREMENS .....

4.7.9.1.1 Test Requirements -.. Each.sealed source shall be tested forleakage and/or contamination by.:

a. The licensee, or

b. Other perso ns.specifically..authorized by the Commission or anAgreement State.

Theltest. method shall have ad.etection sensitivity of at.least 0.005microcuries per test sample.

4.7.9.1.2 Test Frequencies.- Each .category of:sealed sources shall betested at the frequencies described belOw.

a. :Sources in use (excludingq startup sources previously subjectedtoWcore, flux) - At least once per six.months forall sealed.sources containipng .radioactive material:.

ST. LUCIE - UNIT I 3141 7-27


Page 24 of 54

ELECTRICAL POWER SYSTEMS

ACTION (continued)

e. With two of the above required diesel generators inoperable, demonstrate theOPERABILITY of two offsite.A.C. circuits by performing Surveillance.Requirement 4.8.1.1.1 .a within 1. hour and at least once: per 8 hours thereafter;restore .one of thelinoperable.diesel generators. to OPERABLE status within2 hours or be in the at least HOT STANDBY within the.next 6 hours and .in COLDSHUTDOWN within the following 30 hours. Following restoration of.one dieselgenerator unit, follow ACTION Statement b, with the time requirement of thatACTION Statement:based on the time of initial loss of the remaining inoperablediesel. generator.

f. With one Unit 1 startup transformer (MA.or I B) inoperable and with %a Unit 2startup transformer (2A or 28) connected to the same A or B offsite powercircuit and administratively available to both units, then should. Unit 2 requirethe use of the startup transformer administratively available to both units,. Unit 1shalldemonstrate the OPERABILITY of the remaining A.C. :surces byperforming Surveillance Requirement 4.8.1.1.1 .a..within 1 hour and at leastonce per 8 hours thereafter.. Restore the inoperable startup transformer toOPERABLE status Within 72 hours or be in at least HOT STANDBY within thenext 6 hours and COLD SHUTDOWN within the following 30 hours.

LCO 3.0.4. .:b. .s MA poCae dsg

SURVELLLANCE REQUIREMENTS

4.8.1.1.1 Each of the above required independent:.circuits between the offsite.transmissionnetwork and the onsite Class 1 E distribution system shall be:

a. Determined OPERABLE at least once per 7 days by verifying correct breakeralignments, indicated power availability; .and

b. Demonstrated OPERABLE at least once per 18 months by transferring(manually and automatically) unit power supply from the auxiliary transformer tothe startup transfoi mer.

4.8.1.1.2% Each diesel generator shall be demonstrated OPERABLE-.

a. At least once per 31 days on. a STAGGERED TEST BASIS. by:.

1. V.erifying fuel level in the engine-mounted fuel tank,

2. Verifying the fuel level in the fuel storage tank,

3.. Verifying the fuel transfer pump can be started and transfers fuel from the.storage system to the engine-mounted tank,

S,.I4:UCIE .- U.NIT1 3/4 8-3; TNAmendment No. 4N3,442. 138


REFUELING OPERATIONS, Page 25 of 54

FUEL POOL VENTILATION SYSTEM - FUEL STORAGE

LIMITJNG CONDITION FOR OPERATION

3.9.12 At least one fuelpool Ventilation system sshall be OPERABLE.

APPLICABILITY: Whenever recently irradiated fuel is in the spent fuel pooi.

ACTION:

a., With.no fuel pool ventilation system OPERABLE, suspend. alloperations involving mrovement of recently irradiated fuel Within thespent fuel pool or crane operation with loads over the recently irradiatedspent.fuel until at least one fuel pool.Ventilation. system is restoredto OPERABLE status.

b. The provisions of Specification)V 3.0.3 ,ad,-4O ll are notapplicable.


4.9.12 The ýabove required fuel pool ventilation system.shall bedemonstrated OPERABLE:

a.. At least once per 31. days by initiating flow through the HEPAfilter and charcoal adsorber train.and verifying that thetrain operates for atleast 15 minutes.

b. At least once per 18 months or (1).after any structural maintenance.on the HEPA filter or charcoal adsorber housings, or(2) following painting, fire or chemical release in any ventilationzone communicating with the:system by:'

ST.. LUCIE - UNIT •1., 3/4 9-12, Amendment No. 184


Page 26 of 54

RADIOACTIVE EFFLUENTS

EXPLOSIVE. GAS MIXTURE


3.11.:2.5 The concentration of oxygen in the waste gas decay tanks shall be limited to. less than orequal to 2% by volume whenever the hydrogen concentration exceeds 4%.by volume.


ACTION:

a. With the concentration of oxygen in the waste gas decay tank greater than 2% byvolume but less .than or equal to 4 % :by volume, reduce the oxygen concentration tothe above limits within 48 hours.

b. With the concentration of oxygen in the waste gas decay tank greater than 4% byvolume and the hydrogen concentration greater than 2% by Volume, immediatelysuspend all: additions of Waste gases to the system and immediately commencereduction of the concentration of oxygen to less than or equal to 2% by volume.

c. The provisions of. Specificationý 3.0.3end-8-0-Ware not applicable.


4.11. 2.5.1 The concentration of oxygen in the waste: gas decay tank shall be determined to be withintheabove limits by continuously* ,monitoring the waste gases: in the on service waste gasdecay. tank.

4.11.2..5.2 With theoxygen concentration in the on service waste gas.decay tank greater than .2% byvolume.as determihed by Specification 4.11.2.5.1, the concentration of hydrogen in thewaste gas decay tank shall be determined to be within the above limits by gaspartitionersample at least once per 24 hours.

When continuous monitoring capability is: inoperable, waste gases shall be: monitored in

accordance with the actions specified for the:Waste"Gas Decay Tanks ExplosiVe Gas: MonitoringSystem i.n:Chapter 13 of the Updated Final Safety Analysis Report..

ST. LUCIE'- UNIT i :3/4 11-14 Amendment..No. 69,446, 4-52.156,


Page 27 of 54


GAS STORAGE TANKS


3.11.2.6 The quantity of radioactivity.contained in each gas storage.tank shall be limited toless than orequal to 1.65,090 curies noble gases (considered asXe-133).

APPLICABILITY: At all-times.

ACTION.:

a. With the quantity of radioactive material in any gas storage tank exceeding-.the above limit, immediately suspend all additions of radioactive material tothe tank,

b. The provisions of SpecificatioriN 3.0.3 e."d44are not applicable.


4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall bedetermined tobe within .the above limit at least once per 24 hours when radioactivematerials are being added to the tank-when reactor coolaht system activity exceeds,518.9 jtCi/grarn DOSE EQUIVALENT XE-1 33.

S•T. ILUCIE -" UNIT"I. 3/4 11-15 Amendment No. 5.,.69,.213


Page 28 of 54

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

314.0 APPLICABILITY

LIMITING cONDITION FOR OPERATION

3.0.1 Compliance with the Limiting Conditions for Operation .contained in the.succeeding specifications is required during the OPERATIONAL MODES or otherconditions specified therein;, except:that upon failure to meet the LimitirigConditions for Operation, the associated ACTION. requirerments.shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements ofthe Limiting Condition for Operation and/or associated ACTION requirements arenot met within the specifiedtime intervals. If the Limiting Condition forOperation is restored prior to expiration of the specified time intervals,completion of the ACTION requirements.is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as providedin the associated ACTION requirements, within 1 .hour, action shall be initiatedto place the unit in -a MODE in which specificati~on does.not apply byplacing it, as applicable,. in:

1. At least.HOT STANDBY within the next 6 hours,2. At least. HOT SHUTDOWN within the. following 6 hours, and3. At least COLD SHUTDOWN within the subsequent 24 hours.

Where corrective measures are-completed that permit operation under the ACTIONrequirements, the ACTION may be taken in accordance with the specified timelimits as measured from the time of failure to meet the Limiting Condition forOperation. Exceptions to these requirements are stated in the.individual..specifi -cations '..

This specification is not applicable in MODE'5 or 6.- . 4 t y i n o nO D or o th e r s p e .c ifie d c o n d i tio n s h a ll .not ' -

( 7 m d - h n t e c n ii n ft e L m t n ondition forO peration are :not :

e a dt ea s cae AC I Nrequires a shutdown.;if".they are not Met -within ...

a s e i i c t i m i t r a . E r y n o an .O . P .E R A T IO N A L M O D E o r s p e c ifi e d c o~ n d it io n .

| a~ b ma ei .a co'-~ t ih AT.ON .requirements: when conformance to them

••.or n !•imitdpri.0d of time, "

this provision shall not prevent passage through or to OPERATIONAL MODES asreq d t mements. Exceptions.tothese requirements;L are state~d:.in: the individ~ual .:s ecifications,.

thes ... ... . ...n

ST. LUCIE -,:UNIT 2 3/4 0-•1 Amendment No. 33 corrected


Page 29 of 54

INSERT I (LCO 3.0.4)

When an LCO is not met, entry into a MODE or other specified condition in theApplicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operationin the MODE or other specified condition in the Applicability for anunlimited period of time;

b. After performance of a risk assessment addressing inoperable systemsand components, consideration of the results, determination of theacceptability of entering the MODE or other specified condition in theApplicability, and establishment of risk management actions, ifappropriate; exceptions to this Specification are stated in the individualSpecifications, or



Page 30 of 54

.APPLICABILITY


4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES orother conditions specified for individual Limiting Conditions for Operation unless otherwisestated in an individual Surveillance Requirement. Failure to perform a SurveillanceRequirement within the allowable surveillance interval, defined.by ••Specification 4.0.2, shallconstitute noncompliance with the OPERABILITY requirements for a Limiting Condition for

Operation. Surveillance Requirements do hot have to be performed on inoperableequipment.

4.0.2 Each Surveillance Requirement shall be. performed within the. specified surveillanceinterval with a maximum allowable extension not to exceed 25% of the specifiedsurveillance interval.

4.0.3 Ifit is discovered that. a Surveillance was.not performed within its specified frequency,then compliance with the requirement to declare the Limiting Condition for Operation notmet may be. delayed, from the time of discovery, up to 24 hours or up to the limit of thespecified frequency, whichever is greater. This delay period is permitted. to allowperformance. of the Surveillance. A risk evaluation shall. be performed for any Survefilancedelayed greater than.24 hours and the :risk impact .shall be managed.

If the:Surveillance is not performed within the delay period, the Limiting Condition .forOperation must immediately be declared not met,.and. the-applicable ACTION(s) must betaken.

When the Surveillance is performed within the delay period.and the Surveillance is notmet, the Limiting: Condition for Operation must immediately be declared not met, and theapplicable ACTION(s)must be taken.. , . . S,..±._a_:;-;.

4.0.4 n ry into an. OPERATIONAL MODE or other specified applicability conditioifshall not be,made unless the Surveillance Requirement(s):associated with the Limiting Condition.forOperation have been performed within the stated surveillance interval or asotherwise:specified. This provision shall not prevent passage through.orto :OPERATIONALMODES as required to comply with ACTION requirements..

4.0.5 Surveillance Requirements .for ihservice inspection of ASME Code Class 1, 2 and3 components shall be applica.ble as. follows.:

a.. Inservice inspection of ASME Code Class.1, 2.and:.3 components shall beperformed in accordance with Section Xl of the.ASME Boiler and PressureVessel Code and applicable Addenda as required. by 10 CFR 50PSection 50:55a(g), except where specific written relief has been granted .by theCommission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

b. deleted

c.. deleted

:St. LUCIE.-;UNIT2 8/4 0-2• Amendment No. 33,.48, 94, 129


Page 31 of 54

INSERT 2 (SR 4.0.4)

Entry into a MODE or other specified condition in the Applicability of a LimitingCondition for Operation (LCO) shall only be made when the LCO's Surveillanceshave been met within their specified frequency, except as provided bySurveillance Requirement 4.0.3. When an LCO is not met due to Surveillancesnot having been met, entry into a MODE or other specified condition in theApplicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions inthe Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.

TABLE 3.3-1


FUNCTIONAL UNIT

1. Manual Reactor Trip

2. Variable Power Level - High

3. Pressurizer Pressure - High

4. Thermal Margin/Low. Pressure

5. Containment. Pressure - High

6. Steam. Generator Pressure - Low

7. Steam GeneratorPressureDifference - High

8. Steam Generator•Level - Low

9. Local Power Density- High

10. Loss of Component Cooling Waterto Reactor Coolant Pumps

11. Reactor Protection System Logic

12. Reactor Trip Breakers,

1.3. Wide Range Logarithmic NeutronFlux.Monitor.a. Startup and Operating -

Rate of Change of Power -

Highb. Shutdown

14. Reactor Coolant Flow - Low


44

4;4:

4

4.41SG.

4

4/SG

4

4

4.

4

CHANNELSTO TRIP

2

22(a) (d)

2

2(a) (d)

2

2/SG(b)

2(a):(d)

2/SG2(c) (d)

2

2

MINIMUM.CHANNELSOPERABLE

44

3

3

3

3

3/SG

3

3

3

4

APPLICABLEMODES

1,23*, 4*", 5*

11.2

1,2

1,2

1,2

1,2

1,2

112

1

1,2

1,2:3*, 4*, 5*

1,.23*, 4* ;5*

ACTION

1.5

45

4

4

4/SG'

4

2(e) (g)

0

2/SG(a)(d)

.2(c).

3

2

3/SG

3

1,2

3,4, 51,2

3

15.. Loss of Load (TurbineHydraulic Fluid Pressure -"Low) 1

>.L~

ST. LUCIE -.UNIT 2 W/4 3w2 Amendment No.. 60


Page 33 of 54

TABLE 3.3-1 (Continued)..

TABLE NOTATION

* With the protective system trip breakers.in the closed position, the CEA drive system capable of

CEA withdrawal, and fuel in the reactor vessel.

(a) Trip may be manually bypassed below 0.5% of RATED THERMAL POWER in conjunction with(d) below; bypass shall be automatically removed when Wide Range Logarithmic Neutron Fluxpower isigreater than or equal to 0.5% of RATED THERMAL POWER.


(c) Trip may be bypassed below 15% of RATED THERMAL PPOWER; bypass shall be automaticallyremoved when Power Range Neutron Flux power' is greaterthan or equal to 15% of RATEDTHERMAL POWER.

(d) Trip may be bypassed during testing pursuant to Special Test.Exception 3.10.3.1

(e) Trip may be bypassed below 1 0 -4% anhd above 15% of RATED THERMAL POWER; bypassshall be automatically removed when Wide Range Logarithmic Neutron Flux power is> 10%and Power Range Neutron Flux power < 1.5% of RATED THERMAL POWER.

(f): Each: channel shall be comprised .of two trip breakers; actual trip logicdshall be one-out-of-twotaken twice.

(g) There shall be: at least two decades of overlap between the Wide Range Logarithmic. Neutron.Flux Monitoring Channels and the Power.Ranrge Neutron Flux Moni.toring Channels.

ACTION STATEMENTS

ACTION i - With the number of channels OPERABLE one less than required by the MinimumChannels OPERABLE requirement, restore the inoperable channel to.OPERABLEstatus Within 48 hours or be in at least HOT STANDBY within the next 6 hoursand/or open the protective .sys-te.m. trip breakers.

ST. LUCIE - UNIT.23 3/43.-3 Amendment'No. 98

TABLE 3.3-3

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

MINIMUMTOTAL NO. CHANNELS CHANNELS APPLICABL

FUNCTIONAL UNIT

1. SAFETY INJECTION (SIAS)


b. Containment Pressure -High

c. Pressurizer Pressure -Low

d. Automatic Actuation -

Logic

2. CONTAINMENT SPRAY (CSAS)


b. Containment Pressure -

High-High

c. Automatic ActuationLogic

3. CONTAINMENT ISOLATION (CIAS)

a. Manual CIAS (TripButtons)

b. Safety Injection (SIAS)

c. Containment Pressure -

High

d. Containment Radiation -

High

e. Automatic ActuationLogic

OF CHANNELS TO TRIP OPERABLE MODESE

2

4

4

2

2

4

2

1

2

2

1

12

2

3

3

2

2

3

2

1,2,3,4,

1,2,3

1,2, 3(a)

1,2,3,4

1,2,3,4

1(b), 2(b), 3Jb)

1,2,3,4

ACTION

12

1§, 14

1 ,14

12

12

18 , 18 , 18c

12

2 1

See Functionaland Requirements

4 2

2 1,2,3,4 12

Unit 1 for all Safety Injection Initiating Functions

3 1,2,3 1 P, 14

3 1,2,3 1* 14

2 1,2,3,4 12

4 2

2 1

CD ~

ST. LUCIE - UNIT 2 3/4 3-12 Amendment No. 132



FUNCTIONAL UNIT

4. MAIN STEAM LINE ISOLATION (MSIS)


b. Steam GeneratorPressure - Low


High

d. Automatic Actuation Logic

5. CONTAINMENT SUMP RECIRCULATION(RAS)

a. Manual RAS (Trip Buttons)

b. Refueling Water StorageTank- Low

c. Automatic Actuation Logic


2

4/steamgenerator

4

2

2

4

2

CHANNELSTO TRIP

1

2/steamgenerator

2

1

1

2

1


2

3/steamgenerator

3

2

2

3

2

APPLICABLEMODES

1,2,3

1, 2, 3(c)

1,2,3

1,2,3

1,2,3,4

1,2,3

1,2,3

ACTION

16

1A 14

1A 14

12

12

19

12

Q 0

ST. LUCIE - UNIT 2 3/4 3-13 Amendment No. 69, 132



MINIMUMTOTAL NO. CHANNELS CHANNELS APPLICABLE

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

6. LOSS OF POWER (LOV)

a. (1) 4.16 kV Emergency BusUndervoltage (Loss of Voltage) 2/Bus 2/Bus 1/Bus 1, 2,3 17

(2) 480 V Emergency BusUndervoltage (Loss of Voltage) 3/Bus 2/Bus 2/Bus 1, 2, 3 17

b. (1) 4.16 kV Emergency BusUndervoltage (Degraded Voltage)

(2) 480 V Emergency Bus 3/Bus 2/Bus 2/Bus 1,2,3 17Undervoltage (Degraded Voltage)

7. AUXILIARY FEEDWATER (AFAS)

a. Manual (Trip Buttons) 4/SG 2ISG 4/SG 1, 2, 3 15

b. Automatic Actuation Logic 4/SG 2/SG 3/SG 1, 2, 3 15

c. SG Level (2A/2B) - Low 4/SG 2/SG 3/SG 1, 2, 3 20aQ, 20bg, 20c

8. AUXILIARY FEEDWATER ISOLATION

a. SG 2A - SG 2B Differential Pressure 4/SG 2/SG 3/SG 1,2, 3 20af, 201:, 20cb. Feedwater Header 2A - 2B 4/SG 2/SG 3/SG 20a, 20c

Differential Pressure 1,2, 3

>

ST. LUCIE - UNIT 2 3/4 3-14 Amendment No. 28, -, 132


Page 37 of 54TABLE 3.3•f (gContinuedJ

TABLE: NOTATION

(a) Trip function may be bypassed in this MODE.wlhen pressurizer pressure isless than 1836 psia; .bypass• shall be automiatically removed When pressurizerpressure .is greaterthan or equal to 1836 psia.


:(c) Trip function may be bypassed in this MODE below 700.psia.; bypass shallbe automatically removed at or above 700 psia&

-' ie-ovis ion s-ofýificatioTr-ý4are-nOt-aFSTAT bleME

ACTION OF STATEMENTS

ACTION 12 -

ACTION 13

With the number of OPERABLE channels one less:than the.Total.Number of Channels, restore the inoperable channel .to.OPERABLEstatus within 48 hours or be. in. at least.HOT STANDBY within thenext 6: hours and in COLD.SHUTDOWN within the following 30 hours.

With the number-of channels OPERABLE one less:than the TotalNumber of Channels, STARTUP and/or POWER.. OPERATION maycontinuieprovided the inoperable channel! is placed in the bypassed ortripped condition within 1 hour. :The channel.shall be returned toOPERABLE status no later than during the next COLD SHUTDOWN.

With a channel process measurement circuit that~affectsmultiple: functional units inoperable or in test,. bypass or tripall associated functional units :as listed below.

Process Measurement Circuit

1. Containment. Pressure.

2. Steam Generator Pressure -

3. Steam Generator Level -

4. Pressurizer Pressure -

Functional Unit Bypassed

Containment Pressure7- High (SIAS,CIAS, CSAS)Containment Presstlre.- High (RPS)

Steam Generator Pressure - Lows(MS.IS)AFAS-1 and AFAS-2 (AFAS).Thermal Margin/Low Pressure (RPS)Steam Generator Pressure.- Low (RPS)

Steam Generator Level - Low (R.PS)If SG-2A, then.AFAS-1 (AFAS)if SG-2B, then AFAS-2 (AFAS).

Pressurizer Pressure - High (RPS)Pressurizer Pressure =..Low (SIAS)Thermal Margin/Low"Pressure (RPS)

ST. LUCIE.7 UNIT 2 "3/4 '315 Amendment NO :8, 2.3,1 49


INSTRUMENTATION Page 38 of 54

314.3.3 MONITORING INSTRUMENTATION

RADIATION MONITORING INSTRUMENTATION


•323.3 1 The radiation moniloring instrumentation channels shown inTable 3.3-6 shall be OPERABLE with their ala.rm/trip setpoints within thespecified limits.

APPLICABILITY- As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm/trip setpoint..exceedingthe value shown in Table 3..3-6, adjust the setpoint to within thelimit.within 4 hours or d.eclare the channel inoperable.

bl With one or more radiation monitoring channels. inoperable, take theACTION shown. in Table 3.3-6.

c. The provisions. of Specification\ 3.03 eaod .4are not applicable.•


433.1 Each radiation monitoring instrumentation channel shall bedemonstrated OPERABLE by the performance of the..CHANNEL.CHECK, CHANNELCALIBRATION and CHANNEL. FUNCTIONAL TEST operations for the MODES and at the:frequencies shown in Table 4.3-3.

4.3.3.2 At least-onceper 18 months, each Control Room. Isolation radi ation monitoringinstrumentation channel shall .be demonstrated OPERABLE.by verifying that. theresponse. time of the channel is within limits..,

ST. LUCIE -••UNIT 2. •3/4 3ý24 Arnendment .No." 4412, 1.59


INSTRUMENTATION Page 39 of 54

REMOTE SHUTDOWN SYSTEM INSTRUMENTATION


3.3.3.5 The remote shutdown system transfer switches, control and.instrumientation channels shown. in Table 33-9[shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the number of OPERABLE: renote shutdown channels less than theRequired Number of Channels shown in Table 3:3-9,:either restore theinoperable, channel to OPERABLE:status within 30 days or be in HOT:SHUTDOWN within the next 12 hours.

b. With the number of OPERABLE remote shutdown channels less than theMihimum Channels OPERABLE requirements of Table 3.3-9, either restorethe inoperable channel to OPERABLE statusý within 7 days,: or be in HOTSHUTDOWN within the next 12 hours.

4 h iof pl

.URVEILLANCE REQUIREMENTS

4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNELCALIBRATION operations at the frequencies .shown in Table 4.3-6.

4.3.3.5.2 Each remote shutdown system instrumentation transfer switch andcontrol circuit shall be demonstrated.OPERABLE by verifying its capability toperformrits intended function(s) at least once per 18 months...

:ST. LUCIE - UNIT 2. -3/4 3-38


Page 40 of 54

INSTRUMENTATION



3.3.3.6 The accident' monitoring instrumentation channels shown in Table 3.3-10shall be OPERABLE.


ACTION:

a.,* With the number:of OPERABLE accident monitoring channels lessthan the Required: Number.of'Channels shown in Table 3.3-10,either restore the inoperable channel. to-OPERABLE status Within7 days,..or be. in HOT STANDBY in 6 hours and. HOT SHUTDOWN in.12 hours.

b.* With the number of OPERABLE accident.monitOring channels less-thanthe Minimum.Channels.OPERABLE requirements of Table 3.3-10, eitherrestore the inoperable channels to OPERABLE status within 48. h1ours orbe: in HOT STANDBY in 6 hours and HOT SHUTDOWN in. 12 hours.

6." With the number of OPERABLE Channels.one.less than the Total Number.of.Channels shown ,in Table 3.3-10, either restore the inoperablechannel to OPERABLE status within 7 days if repairs are feasibleWithout shutting down or prepare and submit.a.SpecialReport to theCommission.pursuant: to..Specification 6.9.2;within 30 days. followingthe event o.utlining the action 1taken, the cause of the inoperability.and the plans and schedule for restoring the system to OPERABLE status.

d.** With the number of OPERABLE Channels less than the Minimum ChannelsOPERABLE requirements of Table 3.3-10, eitherrestore the inoperablechannel(s) to OPERABLE status within 48 hours if repairs are feasiblewithout shutting down or:

1. Initiate an alternate method of monitoring the reactor Vesselinventory; and

2.. Prepare and submit a Special Reportto..the Commission pursuantto.Specification 6.9.2 within 30 days followingjthe event out-lining the action taken, the cause of the inoperability anpd theplans and .schedule for restoring :the-system to OPERABLE status,and

3. Restore the Channel to OPERABLE status at th.e.next scheduled.

refueling.

* Action statements, do not apply to .Reactor Vessel Level Monitoring System,

.Con 'tainment Sump Water Level (narrow range) and. Containment Sump WaterLeve-l(wide range) instruments.

** Action statements apply only to Reactor Vessel Level Monitoring System,Containrmient .Sump, Water Level (narrow range) and Containment Sump WaterLevel (wide range). instruments.

ST. LUCIE - UNIT 2 3/4 3A.1 SIAmendment No. 4.-, 45, 159


REACTOR COOLANT.SYSTEM Page 41 of 54

314.4.4 PORV 'BLOCK VALVES

LTINGCONDM2_IILONf QFROPERATION

3.4.4 Each Power Operated Relief Valve (PORV) Block valve shall be OPERABLE.No more than one block valve shall be open at any one time.

APPLICABILITY: MODES: 1, 2 and 3.

ACTION:

a. With one or more block valve(s) inoperabie, within 1 hour ei-therrestore..the block valve(s) to OPERABLE. status or close the blockvalve(s) and remove power.from the. block valve(s); otherwise, be inat least HOT STANDBY within thenext 6 hours and in COLD SHUTDOWNwithin the following 30 hours.

b. With both block valves open, close one block valve within 1 hour,otherwise be in at least HOT: STANDBY withinithe.next 6 hours.and inCOLD SHUTDOWN Within the followi.ng 30 hours.


4.4.4 Each block valve shall be demonstrated OPERABLE at least once per92 days by operating the valve through one complete cycle of full travelunless the block valve is closed with. power removed in order:to meet therequirements .of Action a. or b. above.

ST. LQJC.E, --UNIT 2 3.144-10. Amendmhent No. 34- 46


REACTOP COOI.ANT SYSTEM Page 42 of 54

3W4.4.6 REACTOR COOLANT SYSTEM LEAKAGE


LIMMUG-CONDITJON FOR OPERATION

3.4.6.1 The following.RCS.:.leakage detection..systems wilIlbe.OPERABLE:

:a. The reactor cavity sump inlet flowmonitoring system; and

b. One contaicinment.atmrospherle, ra.dioat:tivity: monitor (gaýeous or particulate).

APPLICABILITY:. MODES 1, 2, 3, and 4.

ACTION:

a. With the reactor: cavity sump inlet flow monitor ing system inoperable with anoperable containment particulate radioactivity monitor, perform a RCS water.inventory balance at least once per 24* hours and restore the sump inlet flowmonitoring systernto OPERABLE.status within 30 days; othierwise, be in at leastHOT STANDBY within the next.6 hours and in COLD SHUTDOWN within: the:following; 30: hours.

b.. With the reactor cavity sump in!et flow monitoring system inoperable with only thecontainment gaseous radioaclivity monitor operable, perform an RCS waterinventory. balance at least once per 24* .hours and analyze grab samples of thecontainment atmosphere at least once per 12 hours, and either restore the sumpinlet flow monitoring: system to OPERABLE:status within 7 daysorrestore the:containment particulate radioactivity monitor to OPERABLE status within 7 days andenter action a. above with the time in this action applied against the allowed outagetime of:.action.a:; otherwise,. bein~at least HOT STANDBY within the next6 hoursand in COLD SHUTDOWN within the following .30 hours.

c. With the required radioactivity monitor inoperable, analyze grab samples of thecontainment atmosphere or: perform a RCS water inventory balance at least onceper 24* hours, and restore the, required radioactivity monitor to OPERABLE statuswithin 30 days; otherwise; be in at least HOT STANDBY within the6next 6 hours andin COLD SHUTDOWN 'Within the following 30 hours.

d. With al :required monitors inoperable, enter LCO 3.0.3 immediately.~I

SLIRVEILLANCE REQUIREMENTS

4A4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:.

a. Performance of'the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and.CHANNEL CALIBRATION of the required containment atmosphere radioactivitymonitor at the frequencies, specified in Table 4.3-3.

b. Performance of the CHANNEL CALIBRATION of the reactor cavity sump inlet flowmonitoring. system at leastl once per 1&8 months.

Not required to be perfOrmed until 1.2 hours after establishrment..of steady state-operation.

S.S] LUCIE - UNIT 2 3/4 4-18 Amendment No. 84, 447, 161


Page 43 of 54


314.4.8 SPECIFIC ACTIVITY


3.4.8 The specific activity of the primary coolant shall be limited to:.

a. Less than or equal to 1.0. microcurie/gram DOSE EQUIVALENT1-131, and

b.. Less than or equal to 518.9 microcuries/gram DOSE EQUIVALENT XE-133..

APPLICABILITY: MODES 1., 2, 3, and 4

ACTION:

:a. With the specific activity of the primary coolant >. 1.0 pCi/gram DOSEEQUIVALENT 1-131, verify DOSE EQUIVALENT 1-131. is 5 6.00 pCi/gram onceper four hours.

b. With the specific activity of the primary coolant > 1.0 pCi/gram DOSEEQUIVALENT [.131 , but•. 60.0 pCi/gram DOSE EQUIVALENT. 17131, operationmay cor.ntinue for up to 4.8 hours while efforts are made to restore DOSEEQUIVALENT 1-131 to within the 1.0 pCi/gram limit. ,fecifcatiei4. tnet-

C. With the specific activity of the primary coolant:>1..0 pCi/gram DOSEEQUIVALENT -131 for greater than 48 hours during one continuous timeinterval, or.> 60.0 pCi/gram DOSE EQUIVALENT [k131, be in HOT STANDBYwithin 6 hours and COLD SHUTDOWN within the following 30 hours.

.d.. With the specific activity of the primary coolant > 518.9 pCi/gram DOSEEQUIVALENT XE-1 33, operation may continue for up to, 48 hours while effortsare made to restore DOSE EQUIVALENT XE-1 33 to within the 518.9 pCi/gramDOSE EQUIVALENT XE-133 limit. 1flatio f .u.- is-ot Pcatr=eN... LCO 3.C .-4.

e. With the specific activity of. the primary coolant ,>518.9 pCi/gram DOSEEQ0IUVALENTXE-1 33 for greater than 48 hhours during one continuous timeinterval, be in HOT STANDBY within 6 hours and COLD SHUTDOWNwithin thefollowing 30 hours.


44.8 The specific..activity of the primary coolant. shall.be determined to bewithin the.limits by performance of the sampling and analysis program ofTable 4.4-4..

ST. LUCIE - UNIT 2. 3/4 4-25. Amendment No, 44, 163


REACTOR COOi.ANT SYSTEM Page 44 of 54

OVERPRESSURE PROTECTION SYSTEMS

LIMITING: CONDITION FOR OPERATION

ACTION:. (Continued)

c. In the event either the PORVs, SDCRVs or the RCS vent(s) are used to mitigate a:RCS pressUre transient, a.Special Report shall.be. prepared and submnitted to theCommission pursuant to Specification 6.9.2 within 30 days. The report shalldescribe the circumstances initiating the transient,: the effect of the PORVs,SDCRVs or ven t(s) on the: transient and any corrective action necessary to preventrecurrence.

d.. T-h ,3-pe0f ieato -e4.t-applieab,. j. . 4. I>

i,-apppt6oL&,e6t, +6 IRVs e,,4e*[i MODE 4-.


4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a. In addition to the requirements of the Inservice Testing Program, operating thePORV through one complete cycle of full travel at least once per 18 months.

• ST, ILUCIE.- UNIT 2, 3/4 4-36 Amendment No. 46 .1, 91


Page 45 of 54

.EMERGENCY CORE. COOLING SYSTEMS

3/4.5.3 ECCS SUBSYSTEMS - SHUTDOWN


3.5•.3 As.a minimum, one ECCS subsystem comprised of the following shall beOPERABLE:

a. One QPERABLE. high-pressure safety. injection pump, and

b. An. OPERABLE flow path capable of taking suction from the refueling watertank on a Safety Injection Actuation Signal and automatically transferringsuction to the containment sump on a Sump Recirculation Actuation Signal.

APPLICABILITY: MODES 3*.andFootnote # shall remain applicable in.: MODES .5 and 6 when the.Pressurizer manway cover is in place and.the.reactor vessel head is on.

ACTION:

a. With. no. ECCS subsystems OPERABLE, restore at least one ECCS subsystemto OPERABLE status within 1 hour or be in COLD SHUTDOWN within the next20 hours.

b. In the event the ECCS is actuated and. injects water into the Reactor CoolantSystem, a Special Report shall be prepared and .submitted to the Commissionpursuant to Specification. 6.9.2 within 90 days describing the circumstances ofthe actuation and the total. accumulated actuation cycles to date. The currentvalue of the usage factor for each affected safety injection nozzle shall beprovided in this Special Report.whenever its value exceeds 0.70..•c .3..4.b ;' , ECCS Hto 'P tie.e

Sd~.+ e~~+o SaEy 4 J whkODE 4..SURVEILLANCE REOUiEMENTS

4.5.3 The ECCS subsystem shall be demonstrated OPERABLE per the applicableSurveillance. Requirements of 4.5.2.

* With pressurizer pressure. less than 1750 psia.

# One HPSl shall be rendered inoperable prior to entering MODE 5.

ST. LUCIE - UNIT:2 ,3/4 5m7 Amendment No. 46, 8,, 119


CONTAINMENT -SYSTEMS Page 46 of 54

CONTAINMENT AIR'LOCKS

,.LIMITING CONDITION FOR OPERATION

3.6.1.3 Each containment air lock:.shall be OPERABLE with:

a. Both doors closed except when the air lock is being. used for normal transitentry and exit through the containment then at least one air lock door shallbe closed, and.


APPLICABILITY: MODES I, 2, 3, and 4.

.ACTION::

a, With one containment air lock door inoperable*:1.. Maintain at least the OPERABLE air lock door closed and either restore

the inoperable air lock door to OPERABLE status within 24 hours or: lock,the OPERABLE air lock door closed.

2. Operation may then continue until performance Of the next requiredoverall air lock leakagetest provided, that the OPERABLE air lock door

is verified to be locked closed at least once per 31 days.

3.. Otherwise, be in at least HOT STANDBY withiin the next 6 hours.and inCOLD SHUTDOWN within the following 30 hours..

b, With the containment air lock inoperable,. except as the resultof anihoperable air..lock door, maintain at least one air lock door closed; restorethe inoperable.air lock to OPERABLE'status within 24 hours or be in at leastHOT STANDBY within the 'next"6 hours and in COLD SHUTDOWN withinthe following 30. hours..

I If the inner air l.ockdoor is inoperable, passage•throughthe OPERABLE outer air lockdoor .is permitted to effect repairs to the inoperable inner air lock door. No: more than oneairlock door shall be openi, at any time.

ST..I-UCIE .- UNIT 2 3/4.6ý9 .Amendment No..36, 88

L-2013-2333/4.7 PLANT SYSTEMS Attachment 2

Page 47 of 54

314.7.1 TURBINE CYCLE

SAFETY VALVES


3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settingsas shown in Table 3.7-2.


ACTION:

a. With .both reactor coolant loops and associated steam generators in. operation andwith one or more main steamr line code safety valves: inoperable, operation. inMODES 1, 2 and. 3 may proceed provided that, within 4 hours, either the inoperablevalve is restored to OPERABLE status or the Power Level-High trip setpoint: isreduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next6 hours and in COLD SHUTDOWN within the following 30 hours.

b-,.JThe-provisions-of:specification- 3-.0;4a'are-not-applicable.....


4.7.1.1 Verify each main steam.line code safety valve is OPERABLE in accordance with theInservice Testing Program. Following testing, as-left lift settings shall be within +1- 1%.of1000 psia for valves 8201 through 8208, and.within +1. 1 %.of.1040 psia for valves 8209through 8216 specified in Table 3.7-2.

ST. LUCIE"-UNIT 2: '3147-1 Amendment No. 8, 68, -94 ,110


Page 48 of 54

PLANT SYSTEMS



3.7.1.2 At least three independent steam generator auxiliary feedwater pumpsand associated flow paths shall be OPERABLE with:

a. Two feedwater pumps, each capable of being powered from separateOPERABLE emergendy buisses, and

b. One feedwaterpump capable of being powered from an OPERABLE steamsupply system.


ACTION:

'a. With one auxiliary feedwater pump inoperable, restore the requiredauxiliary feedwater pumps to OPERABLE status within 72 hours or bein at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWNwithin the following 6 hours.

b. W ith two auxiliary feedwater pumps inoperable be in at least. HOTSTANDBY within 6 hours and in HOT SHUTDOWN within the following6 hours.

c. With three auxiliary feedwater pumps inoperable, immediately initiatecorrective action to restoreat least one auxiliary feedwater pump toOPERABLE status.

SýLCO• ...6.. 4 ..SURVEILLANCE REOUi:QjANTS

4.7.1:2 Each auxiliary feedwaiter pump 'shai ,be demonstrated OPERABLE:

a. At least once per 31: daysby:

1. Verifying that each valve (manual, power-operated, or automatic)in the flow path that is not: locked, sealed, or otherwise securedin position, is in its correct position.

ST. LUCIE'- UNIT 2 3/4 7A4 ArS4endment No. 2-,. 146


Page 49 of 54P! ANT SYSTEMS


LIMTIN CNDITION EOR OPERATION____________

3.7.1.5 Each:.main steam line isolation valve shall!be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

MODE 1 With one main steam line isolation valve inoperable but open, POWER.OPERATION may continue providedthe inoperablevalve is restored: t.oOPERABLE status within. 4. hours*' otherwise, be in at least HOT STANDBY withinthe next 6. hours,

.MODES 2,j.3, and 4

With one or both main steam isolation valve(s) inoperable, subsequentoperation in..MODES 2,; 3: or 4 may proceed provided the isolation valve(s). is.(are)•maintained closed. Otherwise, be in at least HOT STANDBY within :the next6. hours and: in COLD SHUTDOWN •within the.following 24 hours...

'T he-provisirns-of-Speeifieationr. G4-afe-fnet-applieable-

.SUJRVELL ANCE REQUIREMENTS

4.7.1.5 Each Main steam lirie .isolation valve shall be.demonstrated 0PERABLE by-verifying fullclosure within 6.75 seconds;when tested pursuant.to the Inservice Testing Program.

ST. LUICIE .•UNIT2. 3/4.7-9: Amendment No. 35, 62, 91



314.7.5 ULTIMATE HEAT SINK

LMI_.NGO LQ Nf_ EORO PERATION

3.7.5.1 The ultimate heat sink shall be OPERABLE with:

a. Cooling.water from the.AtlanticOcean providing a.water level: above.-10:5 feet. elevation,. Mean LowWater, at the plant intake structure, and

b. Two OPERABLE valves.:in the barrier dam between Big Mud: Creek and theintake structure,


ACTION:

a. With the water level requirement of the above specification notsatisfied, be in at least HOT STANDBY within 6..hurs and providecooling water. from Big Mud Creek within the next 12 hours.

b. With one isolation.valve in the.barrier dam between Big Mud Creekand the intake structure inoperable, restore the inoperable valve.to OPERABLE status within 72 hours, or within.the next 24 hours,install a temporary flow barrier and open the barrier dam isola-tion valve. The availability of the onsite equipment capable of.removing theabarrier shall be.verified at least once per 7 daysthereafter.

c. With both of the isolation valves in the barrier'dam between the in-take•structure and Big Mud Creek inoperable, within 24 hours, either:

1.. Install both temporary flow barriers and manually open bothbarrier dam isolation valves. The availability of the 6nsiteequipment capable of removing the barriers shall be verifiedat .least once per 7 days thereafter., or

2. Be in at least HOT STANDBY within the next 6 hours and inCOLD SHUTDOWN within the following 30 .hours.

SURVEiLLANCE REQUIREMENTS

4.7.5.1.1 'The ultirmateheat sink shall be determined OPERABLE at least once per24 hours by verifying the average water level to be within the. limits...

4.7.5.1.2 The isolation valves in the barrier dam between the intake structureand Big Mud Creek shall be demonstrated OPERABLE at .least once: per six months bycycling each valVe through at leastone Complete cycle of full travel.

ST. LUCIE: - UNIT 2 314 7-15,





3.7.10 Each sealed source containingradioactive material either in excess .of1:00 microcuries of beta .a.nd/or gamma emitting material or 5 microcuries ofalpha emitting material shall be free of. greater than or equal to0.005 microcuries of removable contamination.


ACTION:

a. With a sealed source, having removable contamination in excess of theabove limit, immediately withdraw the sealed source from use and. either:.

1. Decontaminate and repair the sealed source,. or

2. Dispose of the sealed..source in accordance with Commission.Regulations.

b. The provisions of Specificatidn\•3.0.3 and-3," are not:applicable:


4.7.10.1 Test Requirements - Each sealed source shall be tested for, leakage.ahd/or cdntamination by:,

a. The licensee, or

b. Other persons specifically authorized. by the Commission or anAgree•ennt State.

The test method shall be a..detection sensitivity of at least.0,005 microcuries per test sample.

4.7.10.2 Test Frequencies - Each categry of sealed sources (excludingstartup sources a.nd'fission detectors previously subjected to core flux) shallbe tested at. the frequencies described below.

a.. Sources in use -At least once per 6 months for all sealed .sourcescontaining radioactive material.

1 With a half-life greater than 30.days (excluding Hydrogen.3),

and

2. In 'any form other than gas.

ST. LUCIE - UNIT 2 1314:7-28


Page 52 of 54


ACTION: (Continued)

d. With two of the required offsite A;C. circuits inoperable, restore one of theinoperable offsite sources to OPERABLE status within 24 hours or be in atleast HOT STANDBY within the next 6 hours. Following restoration of oneoffsite source, follow ACTION Statement a. with the time requirement of that.ACTION Statement based on the time of the initial loss of the remaining inoperable.offsite. A.C.. circuit.

e.; With two of the above required diesel generators inoperable, demonstrate theOPERABILITY of two offsite.A.C. circuits by performing SurveillanceRequirement 4.8.1 1.1..a within 1 hour and at least once per 8 hours thereafter;restore one of the inoperable diesel generators to OPERABLE status within2 hours or be in the at least HOT STANDBY within the next 6 hours and in COLDSHUTDOWN within the following 30 hours. Following.restorationof one. dieselgenerator unit, follow ACTION Statement b. with the time requirement of thatACTION Statement based on the time of initial'loss of the remaining inoperabledieslel!generator.

f. With one Unit 2 startup transformer (2A or 2B) inoperable and With a Unit 1startup transformer (IA or 1 B) connected to the same A or B offsite powercircuit.and administratively available to both units, then should Unit 1 require.the use of the startup transformer:administratively available to both units, Unit 2shall demonstrate the operability of the remaining A.C. sources by performingSurveillance Requirement 4.8.i. 1.1 a. within 1 hour and at least once per8 hours thereafter. Restore .the:inoperable startup transformer. to OPERABLEstatus within 72 hours or be in at least HOT'.STANDBY within the next 6 hoursand COLD SHUTDOWN within the following 30 hours.

Lto 6i6 3 .:61 'is" ,nio cppftcmzd@ý + , d~eseJ e-a 4oS

SURVEILLANCE REQUIREMENTS:

4.8.1.1.1 Each of the above required independent circuits between the offsite transmission,network:and. the:onsite Class 1. E distribution system shall be:

a.. Determined OPERABLE at least once per 7 days by verifying. correct breakeralignments, indicated power availability; and

b. Demonstrated OPERABLE at least once per 18 months.by transferring(manually and automatically) unit power supply from the normal circuit: totiiealternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated. OPERABLE:

a. At least.once per.31 days on a STAGGERED TEST BASIS BY:

ST. L:UCIE -UNIT 2. .3/4 8-3 Amendment No. 39, 43, 78


Page 53 of 54RADIOACTIVE EFFLUENTS.

EXPLOSIVE GAS MIXTURE


3.11.2.5 The concentration of oxygen in the waste gas decay tanks shallbe limited to less than orequal.to 2% by volume whenever the hydrogen: concentration exceeds.4% by volume,

APPLICABILITY: At alltimes.

ACTION:

a. With the concentration of oxygen. in the waste gas decay tank greater than 2% byvolume but less than or :equal to 4% by •volume, reduce the oxygen concentration tothe above limitswithin 48.hours.

b. With the concentration of oxygen in the waste gas decay tank greater than 4% byvolume and the hydrogen concentration greater than 2% by volume, immediatelysuspend all!additions of waste gases to the system and immediately commencereduction of the concentration of oxygen to less than or equal. to 2% by Volume.

C... The provisions of Specificationk 3.0.3 -and4-& are. not applicable

•SURVEILLANCE REQUIREMENTS

•4.11 i .2.5.1 The concentration of oxygen in the waste gas. decay tank; shall be deternmined to be Withinthe above limits by continuously" monitoring the waste gases in.the .on service waste gasdecay tank.

4.11.2.5.2 With the oxygen concentration.in.the..on service waste gas decay tank greaterthan 2% byvolume as determined by Specification,.4.11.2..5.1,. the: concentration of hydrogen. in thewas te:gas decay tank shall be determined to. be within the above irnmits by gas partitionersamPle .at least once per 24 hours.

• When continuous monitoring capability is inoperable, waste gases shall be monitored inaccordance with the actions specified for the Waste Gas..Decay Tanks:. Explosive Gas MonitoringSystem in. Chapter. 13 of the Updated Final .Safety Analysis Report.

ST. LUCE•-.UNIT 2. 314 1 -14 Amendment No.:57- 89,.94


Page 54 of 54RADIOACTIVE EFFLUENTS

GAS.STORAGE TANKS


3.11.2.6 The quant!ity. of radioactivity contained in each gas storage. tank..shall be limited .to less than or equal to 165,000 curies noble gases(considered as Xe-1.33).


ACTION:

a. With the quantity of radioactive material -in any gas storage tankexceeding the above limit, immediately Suspend.all additions ofradioactive materialto the tank.

b. The provisions of Specificatiorni 3.0.3 sR4_. are not applicable.


4.11.2.6 The quantity of radioactive material contained in each.gas storagetank shall be determined to be within the above limit at least once per24 hours when radioactive, materials are being added .to the tank. when reactorcoolant~system activity exceeds 518.9 pCi/gram..DOSE EQUIVALENT XE-1 33.

.STAUWIE - ONIT'2 3/4 11-15 STAmendment No. 43,163


Word-Processed Technical Specification Pages

Unit 1 Unit 23/4 0-1 3/4 0-13/4 0-2 3/4 0-23/4 3-2 3/4 3-23/4 3-3 3/4 3-33/4 3-4 3/4 3-12

3/4 3-10 3/4 3-133/43-11 3/4 3-143/4 3-12 3/4 3-153/4 3-21 3/4 3-243/4 3-41 3/4 3-383/4 4-12 3/4 3-413/4 4-17 3/4 4-103/4 4-59 3/4 4-183/4 5-7 3/4 4-25

3/4 6-10 3/4 4-363/4 7-1 3/4 5-73/4 7-4 3/4 6-93/4 7-9 3/4 7-1

3/4 7-18 3/4 7-43/4 7-27 3/4 7-93/4 8-3 3/4 7-15

3/4 9-12 3/4 7-283/4 11-14 3/4 8-33/4 11-15 3/4 11-14

3/4 11-15

Attachment 3 consists of 50 pages including this cover page.


314.0 APPLICABILITY


3.0.1 Compliance with the Limiting Conditions for Operation (LCO) contained .inthe succeeding specifications is required during the OPERATIONAL MODES or otherconditions specified therein; except that upon failure to meet the LimitingConditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of-the Limiting Condition for Operation (LCO) and associated ACTION requirementsare not met within the specified time intervals. If the Limiting Conditionfor Operation is restored prior to expiration of the specified time intervals,completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation (LCO) is not met, except asprovided in the associated ACTION requirements, within 1 hour action shall beinitiated to place the unit in a MODE in which specification does notapply by placing it, as applicable in:

1. At least HOT STANDBY within the next 6 hours,2. At least HOT SHUTDOWN within the following 6 hours, and3. At least COLD SHUTDOWN within the subsequent 24 hours.

Where corrective measures are completed that permit operation under theACTION requirements, the ACTION may be taken in accordance with the specifiedtime limits as measured from the time of failure to meet the LCO. Exceptionsto these requirements are stated in the individual specifications.

This specification is not applicable in MODES 5 or 6.

3.0.4 When an LCO is not met, entry into a MODE or other specified condition in theApplicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in theMODE or other specified condition in the Applicability for an unlimited period oftime;

b. After performance of a risk assessment addressing inoperable systems andcomponents, consideration of the results, determination of the acceptability ofentering the MODE or other specified condition in the Applicability, andestablishment of risk management actions, if appropriate; exceptions to thisSpecification are stated in the individual Specifications, or


ST. LUCIE - UNIT 1 .3/4 0-1 Amendment No. 40, 98, 4-0,

APPLICABILITY


4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES orother conditions specified for individual Limiting Conditions for Operation unless otherwisestated in an individual Surveillance Requirement. Failure to perform a SurveillanceRequirement within the allowed surveillance interval, defined by Specification 4.0.2, shallconstitute noncompliance with the OPERABILITY requirements for a Limiting Condition forOperation. Surveillance Requirements do not have to be performed on inoperableequipment.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillanceinterval with a maximum allowable extension not to exceed 25% of the specifiedsurveillance interval.

4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency,then compliance with the requirement to declare the Limiting Condition for Operation notmet may be delayed, from the time of discovery, up to 24 hours or up to the limit of thespecified frequency, whichever is greater. This delay period is permitted to.allowperformance of the Surveillance. A risk evaluation shall be performed for any Surveillancedelayed greater than 24 hours and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the Limiting Condition forOperation must immediately be declared not met, and the applicable ACTION(s) must betaken.

When the Surveillance is performed within the delay period and the Surveillance is notmet, the Limiting Condition for Operation must immediately be declared not met, and theapplicable ACTION(s) must be taken.

4.0.4 Entry into a MODE or other specified condition in the Applicability of a Limiting Condition forOperation (LCO) shall only be made when the LCO's Surveillances have been met withintheir specified frequency, except as provided by Surveillance Requirement 4.0.3. When anLCO is not met due to Surveillances not having been met, entry into a MODE or otherspecified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in theApplicability that are required to comply with ACTIONS or that are part of a shutdown ofthe unit.

4.0.5 Surveillance Requirements for inservice inspection of ASME Code Class 1, 2 and 3components shall be applicable as follows:

a. Inservice inspection of ASME Code Class 1, 2 and 3 components shallbe performed in accordance with Section Xl of the ASME Boiler and PressureVessel Code and applicable Addenda as required by 10 CFR 50,Section 50.55a(g), except where specific written relief has been granted by theCommission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

b. deleted

ST. LUCIE - UNIT 1 3/4 0-2 Amendment No. 2-, 40, 9G, 98,408, 4ý5, 486

TABLE 3.3-1


FUNCTIONAL UNIT


2. Power Level - High.



5. Containment Pressure - High


7. Steam Generator WaterLevel - Low



9a. Steam Generator PressureDifference - High

10. Loss of Turbine - HydraulicFluid Pressure - Low


2

4

4/SG

4

4

4/SG

4/SG

CHANNELSTO TRIP

1

2(a)

2(a)/SG

2

2

2(b)/SG

2/SG


2

3(f)

3/SG

3

3

3/SG

3/SG

APPLICABLEMODES

1, 2 and*

1,2

1, 2 (e)

1,2

1,2

1,2

1,2

ACTION

1

2

2

2

2

2

2

2

2

2

2

4

4

4

4

2(c)

2(a)

2(a)

2(c)

3

3

3

3

1

1, 2 (e)

1,2 (e)

1

ST. LUCIE - UNIT 1 3/4 3-2 Amendment No. 4-1, 43



TOTAL NO.FUNCTIONAL UNIT OF CHANNELS

CHANNELSTO TRIP



11. Wide Range Logarithmic NeutronFlux Monitor

a. Startup and Operating --Rate of Change of Power -High

b. Shutdown

12. Reactor Protection SystemLogic

13. Reactor Trip Breakers.

4

4

4

4

2(d)

0

2

2

3

2

4

4

1,2 and *

3,4,5

1,2*

1,2*

2

3

4

4

ST. LUCIE - UNIT 1 3/4 3-3 Amendment No. 45, 2-7


TABLE NOTATION

* With the protective system trip breakers in the closed position and the CEA drive system capable

of CEA withdrawal.

(a) Trip may be bypassed below 1% of RATED THERMAL POWER; bypass shall be automaticallyremoved when Wide Range Logarithmic Neutron Flux power is > 1% of RATED THERMALPOWER.


(c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automaticallyremoved when Power Range Neutron Flux power is > 15% of RATED THERMAL POWER.

(d) Trip may be bypassed below 10-4% and above 15% of RATED THERMAL POWER; bypass

shall be automatically removed when Wide Range Logarithmic Neutron Flux power is > 10-4%and Power Range Neutron Flux power < 15% of RATED THERMAL POWER.

(e) Deleted.

(f) There shall be at least two decades of overlap between the Wide Range Logarithmic NeutronFlux Monitoring Channels and the Power Range Neutron Flux Monitoring Channels.

ACTION STATEMENTS

ACTION 1 -

ACTION 2 -

With the number of channels OPERABLE one less than required by the MinimumChannels OPERABLE requirement, restore the inoperable channel to OPERABLEstatus within 48 hours or be in HOT STANDBY within the next 6 hours and/oropen the protective system trip breakers.

With the number of OPERABLE channels one less than the Total Number ofChannels, STARTUP and/or POWER OPERATION may proceed provided thefollowing conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped conditionwithin 1 hour. For the purposes of testing and maintenance, the inoperablechannel may be bypassed for up to 48 hours from time of initial loss ofOPERABILITY; however, the inoperable channel shall then be eitherrestored to OPERABLE status or placed in the tripped condition.

JNIT 1 3/4 3-4 Amendment No. 4-5, 2-7, 45, 4-02,459

ST. LUCIE - U

TABLE 3.3-3

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

TOTAL NO.OF

FUNCTIONAL UNIT CHANNELSCHANNELS

TO TRIP



1. SAFETY INJECTION (SIAS)a. Manual'(Trip Buttons)b. Containment Pressure -

Highc. Pressurizer Pressure-

Low

2. CONTAINMENT SPRAY (CSAS)a. Manual (Trip Buttons)b. Containment Pressure -

High-High

3. CONTAINMENT ISOLATION (CIS)a. Manual (Trip Buttons)b. Containment Pressure -

Highc. Containment Radiation -

Highd. SIAS

4. MAIN STEAM LINE ISOLATION(MSIS)



2

4

4

2

4

2

4

4

1

2

2

1

2(b)

2

3

3

2

3

2

3

1,2,3,4

1,2,3

1,2, 3(a)

1,2,3,4

8

9

9

I

8

10a, 10b, 10c1,2,3

1

2

- -(See

1,2,3,4

1,2,3

8

9

3 1,2,3,4 9Functional Unit 1 above) -----------------

2/steam 1/steam 2/operatinggenerator generator steam

generator4/steam 2/steam 3/steamgenerator generator generator

1,2,3,4

1,2, 3(c)

8

9

ST. LUCIE - UNIT 1 3/4 3-10 Amendment No. 41-, 37, 4-88


ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

FUNCTIONAL UNIT

5. CONTAINMENT SUMPRECIRCULATION (RAS)


b. Refueling Water Tank - Low

6. LOSS OF POWER

a. 4.16 kv Emergency Bus Under-voltage (Loss of Voltage)

b. 4.16 kv Emergency Bus Under-voltage (Degraded Voltage)

c. 480 V Emergency Bus Under-

voltage (Degraded Voltage)



b. Automatic Actuation Logic

c. SG Level (1A/1B) - Low


a. SG 1A- SG 1B DifferentialPressure

b. Feedwater Header1A- 1B DifferentialPressure


CHANNELSTO TRIP

-MINIMUMCHANNELSOPERABLE


2

4

1

2

2

3

1,2,3,4

1,2,3

8

13

2/Bus

2/Bus

2/Bus

4/SG

4/SG

4/SG

4/SG

4/SG

2/Bus

2/Bus

2/Bus

2/SG

2/SG

2/SG

2/SG

2/SG

1/Bus

1/Bus

1/Bus

4/SG

3/SG

3/SG

3/SG

3/SG

1,2,3

1,2,3

1,2,3

1,2,3

1,2,3

1,2,3

1,2,3

1,2,3

12

12

12

11

11

14a, 14b, 14c

14a, 14b, 14c

14a, 14c

ST. LUCIE - UNIT 1 3/4 3-11 Amendment No. 46, 5-, 78, 402, 4-24, -I88


TABLE NOTATION

(a) Trip function may be bypassed in this MODE when pressurizer pressureis < 1725 psia; bypass shall be automatically removed when pressurizerpressure is > 1725 psia.


(c) Trip function may be bypassed in this MODE below 685 psig; bypassshall be automatically removed at or above 685 psig.

ACTION STATEMENTS

ACTION 8 -

ACTION9 -

With the number of OPERABLE channels one less than theTotal Number of Channels, restore the inoperable channelto OPERABLE status within 48 hours or be in at least HOTSTANDBY within the next 6 hours and in COLD SHUTDOWN withinthe following 30 hours.

With the number of OPERABLE channels one less than theTotal Number of Channels, operation may proceed providedthe following conditions are satisfied:

a. The inoperable channel is placed in either thebypassed or tripped condition within 1 hour. Forthe purposes of testing and maintenance, the inoperablechannel may be bypassed for up to 48 hours from timeof initial loss of OPERABILITY; however, the inoperablechannel shall then be either restored to OPERABLEstatus or placed in the tripped condition.

b. Within one hour, all functional units receiving aninput from the inoperable channel are also bypassed or tripped.

c. The Minimum Channels OPERABLE requirement is met;however, one additional channel may be bypassed forup to 48 hours while performing tests and maintenanceon that channel provided the other inoperable channelis placed in the tripped condition.

ST. LUCIE - UNIT 1 3/4 3-12 Amendment No. 1-5, 45, 202

INSTRUMENTATION

3/4.3.3 MONITORING INSTRUMENTATION

RADIATION MONITORING


3.3.3.1 The radiation monitoring instrumentation channels shown inTable 3.3-6 shall be OPERABLE with their alarm/trip setpoints withinthe specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm/trip setpoint exceedingthe value shown in Table 3.3-6, adjust the setpoint towithin the limit within 4 hours or declare the channelinoperable.

b. With one or more radiation monitoring channels inoperable,take the ACTION shown in Table 3.3-6.

c. The provisions of Specification 3.0.3 is not applicable.

SURVEILLANCE REOUIREMENTS

4.3.3.1 Each radiation monitoring instrumentation channel shall bedemonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNELCALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modesand at the frequencies shown in Table 4.3-3.

4.3.3.2 At lease once per 18 months, each Control Room Isolation radiation monitoringinstrumentation channel shall be demonstrated OPERABLE by verifying that theresponse time of the channel is within limits.

ST. LUCIE - UNIT 1 3/4 3-21 Amendment No. 40, 4-7, 206

INSTRUMENTATION





ACTION:

a. Actions per Table 3.3-11.


4.3.3.8 Each accident monitoring instrumentation channel shall be demonstratedOPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operationsat the frequencies shown in Table 4.3-7.

Sf LUCIE - UNIT 1 3/4 3-41 Amendment No. 37, 4-1-8


3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE



3.4.6.1 The following RCS leakage detection systems will be OPERABLE:

a. The reactor cavity sump inlet flow monitoring system; and

b. One containment atmosphere radioactivity monitor (gaseous or particulate).


ACTION:

a. With the reactor cavity sump inlet flow monitoring system inoperable with anoperable containment particulate radioactivity monitor, perform a RCS waterinventory balance at least once per 24* hours and restore the sump inlet flowmonitoring system to OPERABLE status within 30 days; otherwise, be in at leastHOT STANDBY within the next 6 hours and in COLD SHUTDOWN within thefollowing 30 hours.

b. With the reactor cavity sump inlet flow monitoring system inoperable with only thecontainment gaseous radioactivity monitor operable, perform an RCS waterinventory balance at least once per 24* hours and analyze grab samples of thecontainment atmosphere at least once per 12. hours, and either restore the sumpinlet flow monitoring system to OPERABLE status within 7 days or restore thecontainment particulate radioactivity monitor to OPERABLE status within 7 days andenter action a. above with the time in this action applied against the allowed outagetime of action a.; otherwise, be in at least HOT STANDBY within the next 6 hoursand in COLD SHUTDOWN within the following 30 hours.

c. With the required radioactivity monitor inoperable, analyze grab samples of thecontainment atmosphere or perform a RCS water inventory balance at least onceper 24* hours, and restore the required radioactivity monitor to OPERABLE statuswithin 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours andin COLD SHUTDOWN within the following 30 hours.

d. With all required monitors inoperable, enter LCO 3.0.3 immediately.


4.4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:

a. Performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, andCHANNEL CALIBRATION of the required containment atmosphere radioactivitymonitor at the frequencies specified in Table 4.3-3.

b. Performance of the CHANNEL CALIBRATION of the reactor cavity sump inlet flow

monitoring system at least once per 18 months.

Not required to be performed until 12 hours after establishment of steady state operation.

ST. LUCIE - UNIT 1 3/4 4-12 Amendment No. 444, 200, 2-142


SPECIFIC ACTIVITY


3.4.8 The specific activity of the primary coolant shall be limited to:

a. < 1.0 iCi/gram DOSE EQUIVALENT 1-131, and

b. < 518.9 liCi/gram DOSE EQUIVALENT XE-133.


ACTION:

a. With the specific activity of the primary coolant >1.0 pCi/gram DOSEEQUIVALENT 1-131, verify DOSE EQUIVALENT 1-131 is < 60.0 jiCi/gram onceper four hours.

b. With the specific activity of the primary coolant > 1.0 p.Ci/gram DOSEEQUIVALENT 1-131, but < 60.0 jLCi/gram DOSE EQUIVALENT 1-131, operationmay continue for up to 48 hours while efforts are made to restore DOSEEQUIVALENT 1-131 to within the 1.0 I.LCi/gram limit. LCO 3.0.4.c is applicable.

c. With the specific activity of the primary coolant > 1.0 [tCi/gram DOSEEQUIVALENT 1-131 for greater than 48 hours during one continuous timeinterval, or > 60.0 pCi/gram DOSE EQUIVALENT 1-131, be in HOT STANDBYwithin 6 hours and COLD SHUTDOWN within the following 30 hours.

d. With the specific activity of the primary coolant > 518.9 .tCi/gram DOSEEQUIVALENT XE-1 33, operation may continue for up to 48 hours while effortsare made to restore DOSE EQUIVALENT XE-1 33 to within the 518.9 llCi/gramDOSE EQUIVALENT XE-1 33 limit. LCO 3.0.4.c is applicable.

e. With the specific activity of the primary coolant > 518.9 PtCi/gram DOSEEQUIVALENT XE-1 33 for greater than 48 hours during one continuous timeinterval; be in HOT STANDBY within 6 hours and COLD SHUTDOWN within thefollowing 30 hours.


4.4.8 The specific activity of the primary coolant shall be determinedto be within the limits by performance of the sampling and analysis program of Table 4.4-4.

ST. LUCIE - UNIT 1 3/4 4-17 Amendment No. 69, 4-4, 2-42


POWER OPERATED RELIEF VALVES


3.4.13 Two power operated relief valves (PORVs) shall be OPERABLE, with theirsetpoints selected to the low temperature mode of operation as follows:

a. A setpoint of less than or equal to 350 psia shall be selected during heatup, cooldownand isothermal conditions when the temperature of any RCS cold leg is less than orequal to 2000F.

b. A setpoint of less than or equal to 530 psia shall be selected during heatup, cooldownand isothermal conditions when the temperature of any RCS cold leg is greater than200°F and less than or equal to 3000F.

,APPLICABILITY: MODE 4 when the temperature of any RCS cold leg is less thanor equal to 3000F, MODE 5, and MODE 6 when the head is on the reactor vessel;and the RCS is not vented through greater than a 1.75 square inch vent.

ACTION:

a. With one PORV inoperable in MODE 4, restore the inoperable PORV toOPERABLE status within 7 days; or depressurize and vent the RCSthrough greater than a 1.75 square inch vent within the next 8hours.

b. With one PORV inoperable in MODES 5 or 6, either (1) restore theinoperable PORV to OPERABLE status within 24 hours, or (2) completedepressurization and venting of the RCS through greater than a 1.75square inch vent within a total of 32 hours.

c. With both PORVs inoperable, restore at least one PORV to operablestatus or complete depressurization and venting of the RCS throughgreater than a 1.75 square inch vent within 24 hours.

d. With the RCS vented per ACTIONS a, b, or c, verify the vent pathwayat least once per 31 days when the pathway is provided by a valve(s)that is locked, sealed, or otherwise secured in the open position;otherwise, verify the vent pathway every 12 hours.

e. In the event either the PORVs or the RCS vent(s) are used tomitigate an RCS pressure transient, a Special Report shall beprepared and submitted to the Commission pursuant to Specification6.9.2 within 30 days. The report shall describe the circumstances-initiating the transient, the effect of the PORVs or RCS vent(s) onthe transient, and any corrective action necessary to preventrecurrence.

f. LCO 3.0.4.b is not applicable to PORVs when entering MODE 4.


4.4.13 Each PORV shall be demonstrated OPERABLE by:

a. Verifying the PORV isolation valve is open at least once per 72*hours; and

b. * Performance of a CHANNEL FUNCTION TEST, but excluding valveoperation, at least once per 31 days; and

c. Performance of a CHANNEL CALIBRATION at least once per 18 months.

ST. LUCIE - UNIT 1 3/4 4-59 Amendment No. 60, 84, 404, 432,24-3


ECCS SUBSYSTEMS - SHUTDOWN



a. In MODES 3* and 4 one ECCS subsystem composed of one OPERABLE highpressure safety injection pump and one OPERABLE flow path capable oftaking suction from the refueling water storage tank on a safety injectionactuation signal and automatically transferring suction to the containment sumpon a sump recirculation actuation signal.

b. Prior to decreasing the reactor coolant system temperature below 270°F amaximum of only one high pressure safety injection pump shall be OPERABLEwith its associated header stop valve open.

c. Prior to decreasing the reactor coolant system temperature below 2360 F allhigh pressure safety injection pumps shall be disabled and their associatedheader stop valves closed except as allowed by Specifications 3.1.2.1 and3.1.2.3.

APPLICABILITY: MODES 3* and 4.MODES 5 and 6 when the Pressurizer manway cover is in place andthe reactor vessel head is on.

ACTION:

a. With no ECCS subsystems OPERABLE in MODES 3* and 4#, immediatelyrestore one ECCS subsystem to OPERABLE status or be in COLDSHUTDOWN within 20 hours.

b. With RCS temperature below 270°F and with more than the allowed highpressure safety injection pump OPERABLE or injection valves and headerisolation valves open, immediately disable the high pressure safety injectionpump(s) or close the header isolation valves.

c. In the event the ECCS is actuated and injects water into the Reactor CoolantSystem, a Special Report shall be prepared and submitted to the Commissionpursuant to Specification 6.9.2 within 90 days describing the circumstances ofthe actuation and the total accumulated actuation cycles to date.

d. LCO 3.0.4.b is not applicable to ECCS High Pressure Safety Injection subsystemwhen entering MODE 4.


4.5.3.1 The EGGS subsystem shall be demonstrated OPERABLE per the applicableSurveillance Requirements of 4.5.2.

4.5.3.2 The high pressure safety injection pumps shall be verified inoperable and theassociated header stop valves closed prior to decreasing below the above specifiedReactor Coolant System temperature and once per month when the ReactorCoolant System is at refueling temperatures.

* With pressurizer pressure < 1750 psia.

# REACTOR COOLANT SYSTEM cold leg temperature above 2500 F.

ST. LUCIE - UNIT 1 3/4 5-7 Amendment No. 2-, 60, 84,404, 14a, 4-7-7

CONTAINMENT SYSTEMS



3.6.1.3 Each containment air lock shall be OPERABLE with:

a. Both doors closed except when the air lock is being used for normal transitentry and exit through the containment, then at least one air lock door shallbe closed, and



ACTION:

a. With one containment air lock door inoperable*:

1. Maintain at least the OPERABLE air lock door closed and either restorethe inoperable air lock door to OPERABLE status within 24 hours or lockthe OPERABLE air lock door closed.

2. Operation may then continue until performance of the next requiredoverall air lock leakage test provided that the OPERABLE air lock dooris verified to be closed at least once per 31 days.

3. Otherwise, be in at least HOT STANDBY within the next 6 hours and inCOLD SHUTDOWN within the following 30 hours.

b. With the containment air lock inoperable, except as the result of aninoperable air lock door, maintain at least one air lock door closed; restorethe inoperable air lock to OPERABLE status within 24 hours or be in at leastHOT STANDBY within the next 6 hours and in COLD SHUTDOWN withinthe following 30 hours.


4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

If the inner air lock door is inoperable, passage through the OPERABLE outer air lock door

is permitted to effect repairs to the inoperable inner air lock door. No more than one airlockdoor shall be open at any time.

ST. LUCIE - UNIT 1 3/4 6-10 Amendment No. 85,449

3/4.7 PLANT SYSTEMS

3.4.7.1 TURBINE CYCLE

SAFETY VALVES


3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settings as specifiedin Table 4.7-1.


ACTION:

a. With both reactor coolant loops and associated steam generators in operation andwith one or more main steam line code safety valves inoperable, operation inMODES 1, 2 and 3 may proceed provided that within 4 hours, either the inoperablevalve is restored to OPERABLE status or the Power Level-High trip setpoint isreduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next6 hours and in COLD SHUTDOWN within the following 30 hours.


4.7.1.1 Verify each main steam line code safety valve is OPERABLE in accordance with theInservice Testing Program. Following testing, as-left lift settings shall be within +/- 1% of1000 psia for valves 8201 through 8208, and within +/- 1% of 1040 psia for valves 8209through 8216 specified in Table 4.7-1.

ST. LUCIE - UNIT 1 3/4 7-1 Amendment No. 90, 43, 466

PLANT SYSTEMS



3.7.1.2 At least three independent steam generator auxiliary feedwaterpumps and associated flow paths shall be OPERABLE with:

a. Two motor driven feedwater pumps, and

b. One feedwater pump capable of being powered from an OPERABLEsteam supply system.


ACTION:

a. With one auxiliary feedwater pump inoperable, restore at least threeauxiliary feedwater pumps (two motor driven pumps and one capable ofbeing powered by an OPERABLE steam supply system) to OPERABLE statuswithin 72 hours or be in HOT SHUTDOWN within the next 12 hours.

b. LCO 3.0.4.b is not applicable.


4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:


ST. LUCIE - UNIT 1 3/4 7-4 Amendment No. -,8, 99, 4-99

PLANT SYSTEMS



3.7.1.5 Each main steam line isolation valve shall be OPERABLE.


ACTION:

MODE 1 - With one main steam line isolation valve inoperable, POWER OPERATION maycontinue provided the inoperable valve is either restored to OPERABLE status orclosed within 4 hours; otherwise, be in HOT STANDBY within the next 6 hours.

MODES 2 - With one or both main steam isolation valve(s) inoperable, subsequent operation inand 3 MODES 2 or 3 may proceed provided the isolation valve(s) is (are) maintained

closed. Otherwise, be in at least HOT STANDBY within the next 6 hours and inCOLD SHUTDOWN within the following 24 hours.


4.7.1.5 Each main steam line isolation valve that is open shall be demonstrated OPERABLE byverifying full closure within 6.0 seconds when tested pursuant to the Inservice TestingProgram.

ST. LUCIE - UNIT I 3/4 7-9 Amendment No. G9, 1-44, 1-5

PLANT SYSTEMS

3/4.7.5 ULTIMATE HEAT SINK



a. Cooling water from the Atlantic Ocean providing a water level above-10.5 feet elevation, Mean Low Water, at the plant intake structure,and

b. Two OPERABLE valves in the barrier dam between Big Mud Creek and

the intake structure.


ACTION:

a. With the water level requirement of the above Specification notsatisfied, be in at least HOT STANDBY within six hours and providecooling water from Big Mud Creek within the next 12 hours.

b. With one isolation valve in the barrier dam between Big Mud Creekand the intake structure inoperable, restore the inoperable valveto OPERABLE status within 72 hours or, within the next 24 hours,install a temporary flow barrier and open the barrier dam isola-tion valve. The availability of the onsite equipment capable ofremoving the barrier shall be verified at least once per sevendays thereafter.

c. With both of the isolation valves in the barrier dam between the in-take structure and Big Mud Creek inoperable, within 24 hours either:

1) Install both temporaryflow barriers and manually open bothbarrier dam isolation Valves. The availability of the onsiteequipment capable of removing the barriers shall be verifiedat least once per seven days thereafter, or

2) Be in at least HOT STANDBY within the next 6 hours and inCOLD SHUTDOWN within the following 30 hours.


4.7.5.1.1 The ultimate heat sink shall be determined OPERABLE at least onceper 24 hours by verifying the average water level to be within the limits.

4.7.5.1.2 The isolation valves in the barrier dam between the intake structureand Big Mud Creek shall be demonstrated OPERABLE at least once per six monthsby cycling each valve through at least one complete cycle of full travel.

ST. LUCIE - UNIT 1 3/4 7-18 Amendment No. 6•4

PLANT SYSTEMS



3.7.9.1 Each sealed source containing radioactive material either inexcess of 100 microcuries of beta and/or gamma emitting material or 5microcuries of alpha emitting material shall be free of > 0.005 microcu-ries of removable contamination.


ACTION:

a. Each sealed source with removable contamination in excess ofthe above limit shall be immediately withdrawn from use and:

1. Either decontaminated and repaired, or

2. Disposed of in accordance with Commission Regulations.

b. The provisions of Specification 3.0.3 is not applicable.


4.7.9.1.1 Test Requirements - Each sealed source shall be tested forleakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or anAgreement State.

The test method shall have a detection sensitivity of at least 0.005microcuries per test sample.

4.7.9.1.2 Test Frequencies - Each category of sealed sources shall betested at the frequencies described below.

a. Sources in use (excluding startup sources previously subiectedto core flux) - At least once per six months for all sealedsources containing radioactive material:

ST. LUCIE - UNIT 1 3/4 7-27


ACTION (continued)

e. With two of the above required diesel generators inoperable, demonstrate theOPERABILITY of two offsite A.C. circuits by performing SurveillanceRequirement 4.8.1.1.1 .a within 1 hour and at least once per 8 hours thereafter;restore one of the inoperable diesel generators to OPERABLE status within2 hours or be in the at least HOT STANDBY within the next 6 hours and in COLDSHUTDOWN within the following 30 hours. Following restoration of one dieselgenerator unit, follow ACTION Statement b. with the time requirement of thatACTION Statement based on the time of initial loss of the remaining inoperablediesel generator.

f. With one Unit 1 startup transformer (1A or 1 B) inoperable and with a Unit 2startup transformer (2A or 2B) connected to the same A or B offsite powercircuit and administratively available to both units, then should Unit 2 requirethe use of the startup transformer administratively available to both units, Unit 1shall demonstrate the OPERABILITY of the remaining A.C. sources byperforming Surveillance Requirement 4.8.1.1.1 .a within 1 hour and at leastonce per 8 hours thereafter. Restore the inoperable startup transformer toOPERABLE status within 72 hours or be in at least HOT STANDBY within thenext 6 hours and COLD SHUTDOWN within the following 30 hours.

g. LCO 3.0.4.b is not applicable to diesel generators.


4.8.1.1.1 Each of the above required independent circuits between the offsite transmissionnetwork and the onsite Class 1 E distribution system shall be:

a. Determined OPERABLE at least once per 7 days by verifying correct breakeralignments, indicated power availability; and

b. Demonstrated OPERABLE at least once per 18 months by transferring(manually and automatically) unit power supply from the auxiliary transformer tothe startup transformer.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS by:

1. Verifying fuel level in the engine-mounted fuel tank,

2. Verifying the fuel level in the fuel storage tank,

3. Verifying the fuel transfer pump can be started and transfers fuel from thestorage system to the engine-mounted tank,

ST. LUCIE - UNIT 1 3/4 8-3 Amendment No. 4, 4-1-2, 438

REFUELING OPERATIONS

FUEL POOL VENTILATION SYSTEM - FUEL STORAGE


3.9.12 At least one fuel pool ventilation system shall be OPERABLE.

APPLICABILITY: Whenever recently irradiated fuel is in the spent fuel pool.

ACTION:

a. With no fuel pool ventilation system OPERABLE, suspend alloperations involving movement of recently irradiated fuel within thespent fuel pool or crane operation with loads over the recently irradiatedspent fuel until at least one fuel pool ventilation system is restoredto OPERABLE status.



4.9.12 The above required fuel pool ventilation system shall bedemonstrated OPERABLE:

a. At least once per 31 days by initiating flow through the HEPAfilter and charcoal adsorber train and verifying that thetrain operates for at least 15 minutes.

b. At least once per 18 months or (1) after any structural maintenanceon the HEPA filter or charcoal adsorber housings, or(2) following painting, fire or chemical release in any ventilationzone communicating with the system by:

ST. LUCIE - UNIT I 3/4 9-12 Amendment No. 484




3.11.2.5 The concentration of oxygen in the waste gas decay tanks shall be limited to less than orequal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.


ACTION:

a. With the concentration of oxygen in the waste gas decay tank greater than 2% byvolume but less than or equal to 4% by volume, reduce the oxygen concentration tothe above limits within 48 hours.

b. With the concentration of oxygen in the waste gas decay tank greater than 4% byvolume and the hydrogen concentration greater than 2% by volume, immediatelysuspend all additions of waste gases to the system and immediately commencereduction of the concentration of oxygen to less than or equal to 2% by volume.



4.11.2.5.1 The concentration of oxygen in the waste gas decay tank shall be determined to be withinthe above limits by continuously* monitoring the waste gases in the on service waste gasdecay tank.

4.11.2.5.2 With the oxygen concentration in the on service waste gas decay tank greater than 2% byvolume as determined by Specification 4.11.2.5.1, the concentration of hydrogen in thewaste gas decay tank shall be determined to be within the above limits by gas partitionersample at least once per 24 hours.

When continuous monitoring capability is inoperable, waste gases shall be monitored in

accordance with the actions specified for the Waste Gas Decay Tanks Explosive Gas MonitoringSystem in Chapter 13 of the Updated Final Safety Analysis Report.

ST. LUCIE - UNIT 1 3/4 11-14 Amendment No. 69, -46, 4-,1, 41


GAS STORAGE TANKS


3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited toless than or equal to 165,000 curies noble gases (considered as Xe-1 33).


ACTION:

a. With the quantity of radioactive material in any gas storage tank exceedingthe above limit, immediately suspend all additions of radioactive material tothe tank.


SURVEILLANCE REOUIREMENTS

4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall bedetermined to be within the above limit at least once per 24 hours when radioactivematerials are being added to the tank when reactor coolant system activity exceeds518.9 IiCi/gram DOSE EQUIVALENT XE-133.

ST. LUCIE - UNIT 1 3/4 11-15 Amendment No. 69, 69, 24-,


3/4.0 APPLICABILITY


3.0.1 Compliance with the Limiting Conditions for Operation contained inthe succeedingspecifications is required during the OPERATIONAL MODES or other conditionsspecified therein; except that upon failure to meet the Limiting Conditions for Operation,the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the LimitingCondition for Operation and/or associated ACTION requirements are not met within thespecified time intervals. If the Limiting Condition for Operation is restored prior toexpiration of the specified time intervals, completion of the ACTION requirements is notrequired.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associatedACTION, requirements, within 1 hour, action shall be initiated to place the unit in aMODE in which specification does not apply by placing it, as applicable, in:

1. At least HOT STANDBY within the next 6 hours,2. At least HOT SHUTDOWN within the following 6 hours, and3. At least COLD SHUTDOWN within the subsequent 24 hours.

Where corrective measures are completed that permit operation under the ACTIONrequirements, the ACTION may be taken in accordance with the specified timelimits as measured from the time of failure to meet the Limiting Condition forOperation. Exceptions to these requirements are stated in the individualspecifications.

This specification is not applicable in MODE 5 or 6.

3.0.4 When an LCO is not met, entry into a MODE or other specified condition in theApplicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in theMODE or other specified condition in the Applicability for an unlimited period oftime;

b. After performance of a risk assessment addressing inoperable systems andcomponents, consideration of the results, determination of the acceptability ofentering the MODE or other specified condition in the Applicability, andestablishment of risk management actions, if appropriate; exceptions to thisSpecification are stated in the individual Specifications, or


ST. LUCIE - UNIT 2 3/4 0-1 Amendment No. ,,3-ee3-eeted

APPLICABILITY


4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES orother conditions specified for individual Limiting Conditions for Operation unless otherwisestated in an individual Surveillance Requirement. Failure to perform a SurveillanceRequirement within the allowable surveillance interval, defined by Specification 4.0.2, shallconstitute noncompliance with the OPERABILITY requirements for a Limiting Condition forOperation. Surveillance Requirements do not have to be performed on inoperableequipment.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillanceinterval with a maximum allowable extension not to exceed 25% of the specifiedsurveillance interval.

4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency,then compliance with the requirement to declare the Limiting Condition for Operation notmet may be delayed, from the time of discovery, up to 24 hours or up to the limit of thespecified frequency, whichever is greater. This delay period is permitted to allowperformance of the Surveillance. A risk evaluation shall be performed for any Surveillancedelayed greater than 24 hours and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the Limiting Condition forOperation must immediately be declared not met, and the applicable ACTION(s) must betaken.

When the Surveillance is performed within the delay period and the Surveillance is notmet, the Limiting Condition for Operation must immediately be declared not met, and theapplicable ACTION(s) must be taken.

4.0.4 Entry into a MODE or other specified condition in the Applicability of a Limiting Condition forOperation (LCO) shall only be made when the LCO's Surveillances have been met withintheir specified frequency, except as provided by Surveillance Requirement 4.0.3. When anLCO is not met due to Surveillances not having been met, entry into a MODE or otherspecified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in theApplicability that are required to comply with ACTIONS or that are part of a shutdown ofthe unit.

4.0.5 Surveillance Requirements for inservice inspection of ASME Code Class 1, 2 and3 components shall be applicable as follows:

a. Inservice inspection of ASME Code Class 1, 2 and 3 components shall beperformed in accordance with Section XI of the ASME Boiler and PressureVessel Code and applicable Addenda as required by 10 CFR 50,Section 50.55a(g), except where specific written relief has been granted by theCommission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

b. deleted

c. deleted

ST. LUCIE - UNIT 2 3/4 0-2 Amendment No. 33, 48, 94-, 429

TABLE 3.3-1


FUNCTIONAL UNIT


2. Variable Power Level - High



5. Containment Pressure - High


7. Steam Generator PressureDifference - High

8. Steam Generator Level-- Low


10. Loss of Component Cooling Waterto Reactor Coolant Pumps

11. Reactor Protection System Logic


44

4

4

4

4

4/SG

4

CHANNELSTO TRIP

22

2(a)(d)

2

2(a)(d)

2

2/SG(b)

2(a)(d)

2/SG

2(c)(d)

2

2

2(f)


44

3

3

3

3

3/SG

3

3/SG

3

3

3

4

APPLICABLEMODES

1,23*, 4*, 5*

1,2

1,2

1,2

1,2

1,2

1,2

1,2

1

1,2

1,23*, 4*, 5*

1,23*, 4*, 5*

ACTION

15

2

2

2

2

2

2

2

2

2

25

45

4/SG

4

4

4

12. Reactor Trip Breakers 4

13. Wide Range Logarithmic NeutronFlux Monitora. Startup and Operating -

Rate of Change of Power -High

b. Shutdown


15. Loss of Load (TurbineHydraulic Fluid Pressure - Low)

4

4

4/SG

4

2(e)(g)

0

2/SG(a)(d)

2(c)

3

2

3/SG

3

1,2

3,4,5

1,2

2

3

2

21



TABLE NOTATION

* With the protective system trip breakers in the closed position, the CEA drive system capable of

CEA withdrawal, and fuel in the reactor vessel.

(a) Trip may be manually bypassed below 0.5% of RATED THERMAL POWER in conjunction with(d) below; bypass shall be automatically removed when Wide Range Logarithmic Neutron Fluxpower is greater than or equal to 0.5% of RATED THERMAL POWER.


(c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automaticallyremoved when Power Range Neutron Flux power is greater than or equal to 15% of RATEDTHERMAL POWER.

(d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

(e) Trip may be bypassed below 10-4% and above 15% of RATED THERMAL POWER; bypassshall be automatically removed when Wide Range Logarithmic Neutron Flux power is > 1 0 -%and Power Range Neutron Flux power < 15% of RATED THERMAL POWER.

(f) Each channel shall be comprised of two trip breakers; actual trip logic shall be one-out-of-twotaken twice.

(g) There shall be at least two decades of overlap between the Wide Range Logarithmic NeutronFlux Monitoring Channels and the Power Range Neutron Flux Monitoring Channels.

ACTION STATEMENTS

ACTION 1 - With the number of channels OPERABLE one less than required by the MinimumChannels OPERABLE requirement, restore the inoperable channel to OPERABLEstatus within 48 hours or be in at least HOT STANDBY within the next 6 hoursand/or open the protective system trip breakers.


TABLE 3.3-3


MINIMUMTOTAL NO. CHANNELS CHANNELS APPLICABLI

FUNCTIONAL UNIT

1. SAFETY INJECTION (SIAS)



High

c. Pressurizer Pressure -

Low

d. Automatic Actuation -

Logic

2. CONTAINMENT SPRAY (CSAS)



High-High

c. Automatic ActuationLogic

3. CONTAINMENT ISOLATION (CIAS)

a. Manual CIAS (TripButtons)

b. Safety Injection (SIAS)


High

d. Containment Radiation -

High

e. Automatic ActuationLogic

OF CHANNELS TO TRIP OPERABLE MODESE

2

4

4

2

2

4

2

1,

2

2

1

1

2

3

3

2

2

3

2

1,2,3,4

1,2,3

1,2, 3(a)

1,2,3,4

1,2,3,4

1(b), 2(b), 3(b)

1,2,3,4

ACTION

12

13, 14

13, 14

12

12

18a, 18b, 18c

12

2 1

See Functionaland Requirements

4 2

2 1,2,3,4 12

Unit 1 for all Safety Injection Initiating Functions

3 1,2,3 13, 14

3 1,2,3 13, 14

2 1,2,3,4 12

4

2

2

1

ST. LUCIE - UNIT 2 3/4 3-12 Amendment No. 4-32



FUNCTIONAL UNIT

4. MAIN STEAM LINE ISOLATION (MSIS)




High

d. Automatic Actuation Logic

5. CONTAINMENT SUMP RECIRCULATION(RAS)


b. Refueling Water StorageTank - Low

c. Automatic Actuation Logic


2

4/steamgenerator

4

2

2

4

2

CHANNELSTO TRIP

1

2/steamgenerator

2

1

1

2

1


2

3/steamgenerator

3

2

3

2

APPLICABLEMODES

1,2,3

1, 2, 3(c)

1,2,3

1,2,3

1,2,3,4

1,2,3

1,2,3

ACTION

16

13, 14

13, 14

12

12

19

12




MINIMUMTOTAL NO. CHANNELS CHANNELS APPLICABLE

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

6. LOSS OF POWER (LOV)

a. (1) 4.16 kV Emergency BusUndervoltage (Loss of Voltage) 2/Bus 2/Bus 1/Bus 1, 2, 3 17

(2) 480 V Emergency Bus 3/Bus 2/Bus 2/Bus 1,2,3 17Undervoltage (Loss of Voltage)

b. (1) 4.16 kV Emergency Bus 17Undervoltage (Degraded Voltage)

(2) 480 V Emergency Bus 3/Bus 2/Bus 2/Bus 1,2,3. 17Undervoltage (Degraded Voltage)


a. Manual (Trip Buttons) 4/SG 2/SG 4/SG 1,2,3 15

b. Automatic Actuation Logic 4/SG 2/SG 3/SG 1, 2, 3 15

c. SG Level (2A/2B) - Low 4/SG 2/SG 3/SG 1, 2, 3 20a, 20b, 20c


a. SG 2A - SG 2B Differential Pressure 4/SG 2/SG 3/SG 1, 2, 3 20a, 20b, 20cb. Feedwater Header 2A - 2B 4/SG 2/SG 3/SG 1, 2, 3 20a, 20c

Differential Pressure

ST. LUCIE - UNIT 2 3/4 3-14 Amendment No. 2-8, 7-9, 432


TABLE NOTATION

(a) Trip function may be bypassed in this MODE when pressurizer pressure isless than 1836 psia; bypass shall be automatically removed when pressurizerpressure is greater than or equal to 1.836 psia.


(c) Trip function may be bypassed in this MODE below 700 psia; bypass shallbe automatically removed at or above 700 psia.

ACTION OF STATEMENTS

ACTION 12 -

ACTION 13 -

With the number of OPERABLE channels one less than the TotalNumber of Channels, restore the inoperable channel to OPERABLEstatus within 48 hours or be in at least HOT STANDBY within thenext 6 hours and in COLD SHUTDOWN within the following 30 hours.

With the number of channels OPERABLE one less than the TotalNumber of Channels, STARTUP and/or POWER OPERATION may continueprovided the inoperable channel is placed in the bypassed ortripped condition within 1 hour. The channel shall be returned toOPERABLE status no later than during the next COLD SHUTDOWN.

With a channel process measurement circuit that affectsmultiple functional units inoperable or in test, bypass or tripall associated functional units as listed below.

Process Measurement Circuit

1. Containment Pressure -

2. Steam Generator Pressure -

3. Steam Generator Level -

4. Pressurizer Pressure -

Functional Unit Bypassed

Containment Pressure - High (SIAS,CIAS, CSAS)Containment Pressure - High (RPS)

Steam Generator Pressure - Low(MSIS)AFAS-1 and AFAS-2 (AFAS)Thermal Margin/Low Pressure (RPS)Steam Generator Pressure - Low (RPS)

Steam Generator Level - Low (RPS)If SG-2A, then AFAS-1 (AFAS)If SG-2B, then AFAS-2 (AFAS)

Pressurizer Pressure - High (RPS)Pressurizer Pressure - Low (SIAS)Thermal Margin/Low Pressure (RPS)


INSTRUMENTATION

3/4.3.3 MONITORING INSTRUMENTATION

RADIATION MONITORING INSTRUMENTATION


3.3.3.1 The radiation monitoring instrumentation channels shown inTable 3.3-6 shall be OPERABLE with their alarm/trip setpoints within thespecified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm/trip setpoint exceedingthe value shown in Table 3.3-6, adjust the setpoint to within thelimit within 4 hours or declare the channel inoperable.

b. With one or more radiation monitoring channels inoperable, take theACTION shown in Table 3.3-6.



4.3.3.1 Each radiation monitoring instrumentation channel shall bedemonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNELCALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at thefrequencies shown in Table 4.3-3.

4.3.3.2 At least once per 18 months, each Control Room Isolation radiation monitoringinstrumentation channel shall be demonstrated OPERABLE by verifying that theresponse time of the channel is within limits.

ST. LUCIE - UNIT 2 3/4 3-24 Amendment No. -Q, 4--9

INSTRUMENTATION

REMOTE SHUTDOWN SYSTEM INSTRUMENTATION


3.3.3.5 The remote shutdown system transfer switches, control andinstrumentation channels shown in Table 3.3-9 shall be OPERABLE.


ACTION:

a. With the number of OPERABLE remote shutdown channels less than theRequired Number of Channels shown in Table 3.3-9, either restore theinoperable channel to OPERABLE status within 30 days or be in HOTSHUTDOWN within the next 12 hours.

b. With the number of OPERABLE remote shutdown channels less than theMinimum Channels OPERABLE requirements of Table 3.3-9, either restorethe inoperable channel to OPERABLE status within 7 days, or be in HOTSHUTDOWN within the next 12 hours.


4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNELCALIBRATION operations at the frequencies shown in Table 4.3-6.

4.3.3.5.2 Each remote shutdown system instrumentation transfer switch andcontrol circuit shall be demonstrated OPERABLE by verifying its capability toperform its intended function(s) at least once per 18 months.


INSTRUMENTATION





ACTION:

a.* With the number of OPERABLE accident monitoring channels lessthan the Required Number of Channels shown in Table 3.3-10,either restore the inoperable channel to OPERABLE status within7 days, or be in HOT STANDBY in 6 hours and HOT SHUTDOWN in12 hours.

b.* With the number of OPERABLE accident monitoring channels less thanthe Minimum Channels OPERABLE requirements of Table 3.3-10, eitherrestore the inoperable channels to OPERABLE status within 48 hours orbe in HOT STANDBY in 6 hours and HOT SHUTDOWN in 12 hours.

c.** With the number of OPERABLE Channels one less than the Total Numberof Channels shown in Table 3.3-10, either restore the inoperablechannel to OPERABLE status within 7 days if repairs are feasiblewithout shutting down or prepare and submit a Special Report to theCommission pursuant to Specification 6.9.2 within 30 days followingthe event outlining the action taken, the cause of the inoperabilityand the plans and schedule for restoring the system to OPERABLE status.

d.** With the number of OPERABLE Channels less than the Minimum ChannelsOPERABLE requirements of Table 3.3-10, either restore the inoperablechannel(s) to OPERABLE status within 48 hours if repairs are feasiblewithout shutting down or:

1. Initiate an alternate method of monitoring the reactor vesselinventory; and

2. Prepare and submit a Special Report to the Commission pursuantto Specification 6.9.2 within 30 days following the event out-lining the action taken, the cause of the inoperability and theplans and schedule for restoring the system to OPERABLE status,and

3. Restore the Channel to OPERABLE status at the next scheduledrefueling.

* Action statements do not apply to Reactor Vessel Level Monitoring System,

Containment Sump Water Level (narrow range) and Containment Sump WaterLevel (wide range) instruments.

** Action statements apply only to Reactor Vessel Level Monitoring System,Containment Sump Water Level (narrow range) and Containment Sump WaterLevel (wide range) instruments.

.ST. LUCIE - UNIT 2 3/4 3-41 Amendment No. 1-9, 46, 469


3/4.4.4 PORV BLOCK VALVES


3.4.4 Each Power Operated Relief Valve (PORV) Block valve shall be OPERABLE.No more than one block valve shall be open at any one time.


ACTION:

a. With one or more block valve(s) inoperable, within 1 hour eitherrestore the block valve(s) to OPERABLE status or close the blockvalve(s) and remove power from the block valve(s); otherwise, be inat least HOT STANDBY within the next 6 hours and in COLD SHUTDOWNwithin the following 30 hours.

b. With both block valves open, close one block valve within 1 hour,otherwise be in at least HOT STANDBY within the next 6 hours and inCOLD SHUTDOWN within the following 30 hours.


4.4.4 Each block valve shall be demonstrated OPERABLE at least once per92 days by operating the valve through one complete cycle of full travelunless the block valve is closed with power removed in order to meet therequirements of Action a. or b. above.

ST. LUCIE - UNIT 2 3/4 4-10 Amendment No. 3-, 46


3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE



3.4.6.1 The following RCS leakage detection systems will be OPERABLE:

a. The reactor cavity sump inlet flow monitoring system; and

b. One containment atmosphere radioactivity monitor (gaseous or particulate).


ACTION:

a. With the reactor cavity sump inlet flow monitoring system inoperable with anoperable containment particulate radioactivity monitor, perform a RCS waterinventory balance at least once per 24* hours and restore the sump inlet flowmonitoring system to OPERABLE status within 30 days; otherwise, be in at leastHOT STANDBY within the next 6 hours and in COLD SHUTDOWN within thefollowing 30 hours.

b. With the reactor cavity sump inlet flow monitoring system inoperable with only thecontainment gaseous radioactivity monitor operable, perform an RCS waterinventory balance at least once per 24* hours and analyze grab samples of thecontainment atmosphere at least once per 12 hours, and either restore the sumpinlet flow monitoring system to OPERABLE status within 7 days or restore thecontainment particulate radioactivity monitor to OPERABLE status within 7 days andenter action a. above with the time in this action applied against the allowed outagetime of action a.; otherwise, be in at least HOT STANDBY within the next 6 hoursand in COLD SHUTDOWN within the following 30 hours.

c. With the required radioactivity monitor inoperable, analyze grab samples of thecontainment atmosphere or perform a RCS water inventory balance at least onceper 24* hours, and restore the required radioactivity monitor to OPERABLE statuswithin 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours andin COLD SHUTDOWN within the following 30 hours.

d. With all required monitors inoperable, enter LCO 3.0.3 immediately.


4.4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:

a. Performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, andCHANNEL CALIBRATION of the required containment atmosphere radioactivitymonitor at the frequencies specified in Table 4.3-3.

* b. Performance of the CHANNEL CALIBRATION of the reactor cavity sump inlet flowmonitoring system at least once per 18 months.

* Not required to be performed until 12 hours after establishment of steady state operation.

ST. LUCIE - UNIT 2 3/4 4-18 Amendment No. 84, 447-, 46-1-


3/4.4.8 SPECIFIC ACTIVITY


3.4.8 The specific activity of the primary coolant shall be limited to:

a. Less than or equal to 1.0 microcurie/gram DOSE EQUIVALENT1-131, and

b. Less than or equal to 518.9 microcuries/gram DOSE EQUIVALENT XE-133.

APPLICABILITY: MODES 1, 2, 3, and 4

ACTION:

a. With the specific activity of the primary coolant > 1.0 pCi/gram DOSEEQUIVALENT 1-131, verify DOSE EQUIVALENT 1-131 is <60.0 pCi/gram onceper four hours.

b. With the specific activity of the primary coolant > 1.0 pCi/gram DOSEEQUIVALENT 1-131, but <60.0 pCi/gram DOSE EQUIVALENT 1-131, operationmay continue for up to 48 hours while efforts are made to restore DOSEEQUIVALENT 1-131 to within the 1.0 pCi/gram limit. LCO 3.0.4.c is applicable.

c. With the specific activity of the primary coolant > 1.0 pCi/gram DOSEEQUIVALENT 1-131 for greater than 48 hours during one continuous timeinterval, or > 60.0 pCi/gram DOSE EQUIVALENT 1-131, be in HOT STANDBYwithin 6 hours and COLD SHUTDOWN within the following 30 hours.

d. With the specific activity of the primary coolant > 518.9 pCi/gram DOSEEQUIVALENT XE-1 33, operation may continue for up to 48 hours while effortsare made to restore DOSE EQUIVALENT XE-1 33 to within the 518.9 pCi/gramDOSE EQUIVALENT XE-1 33 limit. LCO 3.0.4.c is applicable.

e. With the specific activity of the primary coolant > 518.9 pCi/gram DOSEEQUIVALENT XE-1 33 for greater than 48 hours during one continuous timeinterval, be in HOT STANDBY within 6 hours and COLD SHUTDOWN within thefollowing 30 hours.


4.4.8 The specific activity of the primary coolant shall be determined to bewithin the limits by performance of the sampling and analysis program ofTable 4.4-4.



OVERPRESSURE PROTECTION SYSTEMS


ACTION: (Continued)

c. In the event either the PORVs, SDCRVs or the RCS vent(s) are used to mitigate aRCS pressure transient, a Special Report shall be prepared and submitted to theCommission pursuant to Specification 6.9.2 within 30 days. The report shalldescribe the circumstances initiating the transient, the effect of the PORVs,SDCRVs or vent(s) on the transient and any corrective action necessary to preventrecurrence.

d. LCO 3.0.4.b is not applicable to PORVs when entering MODE 4.


4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a. In addition to the requirements of the Inservice Testing Program, operating thePORV through one complete cycle of full travel at least once per 18 months.



3/4.5.3 ECCS SUBSYSTEMS - SHUTDOWN



a. One OPERABLE high-pressure safety injection pump, and

b. An OPERABLE flow path capable of taking suction from the refueling watertank on a Safety Injection Actuation Signal and automatically transferringsuction to the containment sump on a Sump Recirculation Actuation Signal.

APPLICABILITY: MODES 3* and 4Footnote # shall remain applicable in MODES 5 and 6 when thePressurizer manway cover is in place and the reactor vessel head is on.

ACTION:

a. With no ECCS subsystems OPERABLE, restore at least one EGOS subsystemto OPERABLE status within 1 hour or be in COLD SHUTDOWN within the next20 hours.

b. In the event the ECCS is actuated and injects water into the Reactor CoolantSystem, a Special Report shall be prepared and submitted to the Commissionpursuant to Specification 6.9.2 within 90-days describing the circumstances ofthe actuation and the total accumulated actuation cycles to date. The currentvalue of the usage factor for each affected safety injection nozzle shall beprovided in this Special Report whenever its value exceeds 0.70.

c. LCO 3.0.4.b is not applicable to ECCS High Pressure Safety Injectionsubsystem when entering MODE 4.


4.5.3 The ECCS subsystem shall be demonstrated OPERABLE per the applicableSurveillance Requirements of 4.5.2.

* With pressurizer pressure less than 1750 psia.

# One HPSI shall be rendered inoperable prior to entering MODE 5.

ST. LUCIE - UNIT 2 3/4 5-7 Amendment No. 4-6, 83, 44-9

CONTAINMENT SYSTEMS



3.6.1.3 Each containment air lock shall be OPERABLE with:

a. Both doors closed except when the air lock is being used for normal transitentry and exit through the containment, then at least one air lock door shallbe closed, and



ACTION:

a. With one containment air lock door inoperable*:

1. Maintain at least the OPERABLE air lock door closed and either restorethe inoperable air lock door to OPERABLE status within 24 hours or lockthe OPERABLE air lock door closed.

2. Operation may then continue until performance of the next requiredoverall air lock leakage test provided that the OPERABLE air lock dooris verified to be locked closed at least once per 31 days.

3. Otherwise, be in at least HOT STANDBY within the next 6 hours and inCOLD SHUTDOWN within the following 30 hours.

b. With the containment air lock inoperable, except as the result of aninoperable air lock door, maintain at least one air lock door closed; restorethe inoperable air lock to OPERABLE status within 24 hours or be in at leastHOT STANDBY within the next 6 hours and in COLD SHUTDOWN withinthe following 30 hours.

* If the inner air lock door is inoperable, passage through the OPERABLE outer air lock

door is permitted to effect repairs to the inoperable inner air lock door. No more than oneairlock door shall be open at any time.


314.7 PLANT SYSTEMS

314.7.1 TURBINE CYCLE

SAFETY VALVES


3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settingsas shown in Table 3.7-2.


ACTION:

a. With both reactor coolant loops and associated steam generators in operation andwith one or more main steam line code safety valves inoperable, operation inMODES 1, 2 and 3 may proceed provided that, within 4 hours, either the inoperablevalve is restored to OPERABLE status or the Power Level-High trip setpoint isreduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next6 hours and in COLD SHUTDOWN within the following 30 hours.


4.7.1.1 Verify each main steam line code safety valve is OPERABLE in accordance with theInservice Testing Program. Following testing, as-left lift settings shall be within +/- 1% of1000 psia for valves 8201 through 8208, and within +/- 1% of 1040 psia for valves 8209through 8216 specified in Table 3.7-2.

ST. LUCIE - UNIT 2 3/4 7-1 Amendment No. 8, 68, 94, 44-G-

PLANT SYSTEMS



3.7.1.2 At least three independent steam generator auxiliary feedwater pumpsand associated flow paths shall be OPERABLE with:

a. Two feedwater pumps, each capable of being powered from separateOPERABLE emergency busses, and

b. One feedwater pump capable of being powered from an OPERABLE steamsupply system.


ACTION:

a. With one auxiliary feedwater pump inoperable, restore the requiredauxiliary feedwater pumps to OPERABLE status within 72 hours or bein at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWNwithin the following 6 hours.

b. With two auxiliary feedwater pumps inoperable be in at least HOTSTANDBY within 6 hours and in HOT SHUTDOWN within the following6 hours.

c. With three auxiliary feedwater pumps inoperable, immediately initiatecorrective action to restore at least one auxiliary feedwater pump toOPERABLE status.

d. LCO 3.0.4.b is not applicable.


4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:


1. Verifying that each valve (manual, power-operated, or automatic)in the flow path that is not locked, sealed, or otherwise securedin position, is in its correct position.

ST. LUCIE - UNIT 2 3/4 7-4 Amendment No. 2-, 446

PLANT SYSTEMS.



3.7.1.5 Each main steam line isolation valve shall be OPERABLE.


ACTION:

MODE I - With one main steam line isolation valve inoperable but open, POWEROPERATION may continue provided the inoperable valve is restored toOPERABLE status within 4 hours; otherwise, be in at least HOT STANDBY withinthe next 6 hours.

MODES 2, 3 -

and 4With one or both main steam isolation valve(s) inoperable, subsequentoperation in MODES 2, 3 or 4 may proceed provided the isolation valve(s) is (are)maintained closed. Otherwise, be in at least HOT STANDBY within the next6 hours and in COLD SHUTDOWN within the following 24 hours.


4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying fullclosure within 6.75 seconds when tested pursuant to the Inservice Testing Program.

ST. LUCIE - UNIT 2 3/4 7-9 Amendment No. 3', 62, 94

PLANT SYSTEMS

3/4.7.5 ULTIMATE HEAT SINK



a. Cooling water from the Atlantic Ocean providing a water level above-10.5 feet elevation, Mean Low Water, at the plant intake structure,and

b. Two OPERABLE valves in the barrier dam between Big Mud Creek and the

intake structure.


ACTION:

a. With the water level requirement of the above specification notsatisfied, be in at least HOT STANDBY within 6 hours and providecooling water from Big Mud Creek within the next 12 hours.

b. With one isolation valve in the barrier dam between Big Mud Creekand the intake structure inoperable, restore the inoperable valveto OPERABLE status within 72 hours, or within the next 24 hours,install a temporary flow barrier and open the barrier dam isola-tion valve. The availability of the onsite equipment capable ofremoving the barrier shall be verified at least once per 7 daysthereafter.

c. With both of the isolation valves in the barrier dam between the in-take structure and Big Mud Creek inoperable, within 24 hours, either:

1. Install both temporary flow barriers and manually open bothbarrier dam isolation valves. The availability of the onsiteequipment capable of removing the barriers shall be verifiedat least once per 7 days thereafter, or

2. Be in at least HOT STANDBY within the next 6 hours and inCOLD SHUTDOWN within the following 30 hours.


4.7.5.1.1 The ultimate heat sink shall be determined OPERABLE at least once per24 hours by verifying the average water level to be within the limits.

4.7.5.1.2 The isolation valves in the barrier dam between the intake structureand Big Mud Creek shall be demonstrated OPERABLE at least once per six months bycycling each valve through at least one complete cycle of full travel.

ST. LUCIE - UNIT 2 3/4 7-i5

PLANT SYSTEMS



3.7.10 Each sealed source containing radioactive material either in excess of100 microcuries of beta and/or gamma emitting material or 5 microcuries ofalpha emitting material shall be free of greater than or equal to0.005 microcuries of removable contamination.


ACTION:

a. With a sealed source having removable contamination in excess of theabove limit, immediately withdraw the sealed source from use and either:

1. Decontaminate and repair the sealed source, or

2. Dispose of the sealed source in accordance with CommissionRegulations.



4.7.10.1 Test Requirements - Each sealed source shall be tested for leakage

and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or anAgreement State.

The test method shall be a detection sensitivity of at least0.005 microcuries per test sample.

4.7.10.2 Test Frequencies - Each category of sealed sources (excludingstartup sources and fission detectors previously subjected to core flux) shallbe tested at the frequencies described below.

a. Sources in use - At least once per 6 months for all sealed sourcescontaining radioactive material:

1. With a half-life greater than 30 days (excluding Hydrogen 3),and

2. In any form other than gas.



ACTION: (Continued)

d. With two of the required offsite A.C. circuits inoperable, restore one of theinoperable offsite sources to OPERABLE status within 24 hours or be in atleast HOT STANDBY within the next 6 hours. Following restoration of oneoffsite source, follow ACTION Statement a. with the time requirement of thatACTION Statement based on the time of the initial loss of the remaining inoperableoffsite A.C. circuit.

e. With two of the above required diesel generators inoperable, demonstrate theOPERABILITY of two offsite A.C. circuits by performing SurveillanceRequirement 4.8.1.1.1 .a within 1 hour and at least once per 8 hours thereafter;restore one of the inoperable diesel generators to OPERABLE status within2 hours or be in the at least HOT STANDBY within the next 6 hours and in COLDSHUTDOWN within the following 30 hours. Following restoration of one dieselgenerator unit, follow ACTION Statement b. with the time requirement of thatACTION Statement based on the time of initial loss of the remaining inoperablediesel generator.

f. With one Unit 2 startup transformer (2A or 2B) inoperable and with a Unit 1startup transformer (1A or 1 B) connected to the same A or B offsite powercircuit and administratively available to both units, then should Unit 1 requirethe use of the startup transformer administratively available to both units, Unit 2shall demonstrate the operability, of the remaining A.C. sources by performingSurveillance Requirement 4.8.1.1.la. within 1 hour and at least once per8 hours thereafter. Restore the inoperable startup transformer to OPERABLEstatus within 72 hours or be in at least HOT STANDBY within the next 6 hoursand COLD SHUTDOWN within the following 30 hours.

g. LCO 3.0.4.b is not applicable to diesel generators:


4.8.1.1.1 Each of the above required independent circuits between the offsite transmissionnetwork and the onsite Class 1 E distribution system shall be:

a. Determined OPERABLE at least once per 7 days by verifying correct breakeralignments, indicated power availability; and

b. Demonstrated OPERABLE at least once per 18 months by transferring(manually and automatically) unit power supply from the normal circuit to thealternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS BY:





3.11.2.5 The concentration of oxygen in the waste gas decay tanks shall be limited to less than orequal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.


ACTION:

a. With the concentration of oxygen in the waste gas decay tank greater than 2% byvolume but less than or equal to 4% by volume, reduce the oxygen concentration tothe above limits within 48 hours.

b. With the concentration of oxygen in the waste gas decay tank greater than 4% byvolume and the hydrogen concentration greater than 2% by volume, immediatelysuspend all additions of waste gases to the system and immediately commencereduction of the concentration of oxygen to less than or equal to 2% by volume.

c. The provisions of Specification 3.0.3 is not applicable


4.11.2.5.1 The concentration of oxygen in the waste gas decay tank shall be determined to be withinthe above limits by continuously* monitoring the waste gases in the on service waste gasdecay tank.

4.11.2.5.2 With the oxygen concentration in the on service waste gas decay tank greater than 2% byvolume as determined by Specification 4.11.2.5.1, the concentration of hydrogen in thewaste gas decay tank shall be determined to be within the above limits by gas partitionersample at least once per 24 hours.

When continuous monitoring capability is inoperable, waste gases shall be monitored in

accordance with the actions specified for the Waste Gas Decay Tanks Explosive Gas MonitoringSystem in Chapter 13 of the Updated Final'Safety Analysis Report.

ST. LUCIE - UNIT 2 3/4 11-14 Amendment No. 7., 89, 94


GAS STORAGE TANKS


3.11.2.6 The quantity of radioactivity contained in each gas storage tankshall be limited to less than or equal to 165,000 curies noble gases(considered as Xe-133).


ACTION:

a. With the quantity of radioactive material in any gas storage tankexceeding the above limit, immediately suspend all additions ofradioactive material to the tank.



4.11.2.6 The quantity of radioactive material contained in each gas storagetank shall be determined to be within the above limit at least once per24 hours when radioactive materials are being added to the tank when reactorcoolant system activity exceeds 518.9 pCi/gram DOSE EQUIVALENT XE-133.




ATTACHMENT 4

LIST OF REGULATORY COMMITMENTS

The following table identifies those actions committed to by FPL in this document. Any otherstatements in this submittal are provided for information purposes and are not considered to beregulatory commitments. Please direct questions regarding these commitments to Mr. EricKatzman, Licensing Manager at 772-467-7734.

Regulatory Commitment Due Date/EventFPL will establish the Technical Specification Bases for LCO To be implemented3.0.4 and SR 4.0.4 as adopted with this license amendment with the Technicalrequest. Specification

amendment

St. Lucie Units I and 2Docket Nos. 50-335 and 50-389


Page 1 of 37

ATTACHMENT 5

PROPOSED CHANGES TO TECHNICAL SPECIFICATION BASES PAGES


Page 2 of 37

SECT!ON NO.: TITLE: TECHNICAL SPECIFICATIONS. PAG. -

3.0 &.4.0 BASES ATTACHMENT 2 OF ADM-25.04 7 ofREVISION NO.: LIMITING CONDITIONS FOR- OPERATION 7

AND SURVEILLANCE REQUIREMENTS [7

ST. LUCIE UNIT 11 __._ _

3/4.0 APPLICABILITY (continued)

BASES (continued)

3.0.4 This specification establishes limitations on MODE changes when a LimitingCondition for Operation is not met. It precludes placing the facility in a higherMODE of operation when the requirements for a Limiting Condition forOperation are not met and continued noncompliance to these conditions wouldresult in. a shutdown to comply with the ACTION. requirements if a Change inMODES were permitted. The purpose of this specification is to ensure thatfacility operation is not initiated or that higher MODES of operation are notentered when corrective action is being taken to obtain compliance with aspecification by restoring equipment to OPERABLE. status or parameters tospecified limits. Compliance with ACTION requirements that permit continuedoperation of the facility for an unlimited period of time provides an accept-ablelevel of safety for continued operation without regard to the status of the plantbefore or after a MODE change. Therefore, in this case, entry into anOPERATIONAL MODE or other specified. condition may be made inaccordance with the provisions.of the ACTION requirements. The provisions ofthis specification should not, however, be interpreted as endorsing the failure toexercise good practice in restoring systems or components to OPERABLEstatus before plant startup.

When a shutdown is required to comply with the ACTION requirements, theprovisions of Specification 3.0.4 do not apply because they would delayplacing the facility in a lower MODE of operation.

Exceptions to this• provision have been provided .for a limited number ofspecifications when• startup with inoperable equipment would not affect plantsafety. These exceptions are stated-in the ACTION statements of theappropriate specifications.

The specifications of this section establish the general requirementsapplicable to Surveillance Requirements. These requirements are based onthe Surveillance Requirements stated in the Code of Federal Regulations,10 CFR 50.36(c)(3):

'Surveillance requirements are requirements relating to test, calibration, orinspection to ensure that the necessary quality of systems and components ismaintained, that facility operation will be within safety limits, and that the.limiting conditions of operation will be met."

o~e %Nth h sley+ 3


Page 3 of 37

INSERT 3 (BASES 3.0.4)

LCO 3:0'.4 establishes limitations on changes in MODES or other specifiedconditions in the Applicability when an LCO is not met. It allows placing the unitin a MODE or other specified condition stated in that Applicability (e.g., theApplicability desired to be entered) when unit conditions are such that therequirements of the LCO would not be met, in accordance with LCO 3.0.4.a, LCO3.0,4.b, or LCO 3.0.4.c.

LCO 3.0.4.a allows entry into a MODE or other specified condition in theApplicability with the LCO not met when the associated ACTIONS to be enteredpermit continued operation in the MODE or other specified condition in theApplicability for an unlimited period of time. Compliance with required Actionsthat permit continued operation of the unit for an unlimited period of time in aMODE or other specified condition provides an acceptable level of safety forcontinued operation. This is without regard to the status of the unit before orafter the MODE change. Therefore, in such cases, entry into a MODE or otherspecified condition in the Applicability may be made in accordance with theprovisions of the required Actions.

LCO 3.0.4.b allows entry into a MODE or other specified condition in theApplicability with the LCO not met after performance of a risk assessmentaddressing inoperable systems and components, consideration of the results,determination of the acceptability of entering the MODE or other specifiedcondition in the Applicability, and establishment of risk management actions, ifappropriate.

The risk assessment may use quantitative, qualitative, or blended approaches,and the risk assessment will be conducted using the plant program, procedures,and criteria in place to implement 10 CFR 50.65(a)(4), which requires that riskimpacts of maintenance activities to be assessed and managed. The riskassessment for the purposes of LCO 3.0.4.b, must take into account allinoperable Technical Specification equipment regardless of whether theequipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope.The risk assessments will be conducted using the procedures and guidanceendorsed by Regulatory Guide 1.182, "Assessing and Managing Risk BeforeMaintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline forMonitoring the Effectiveness of Maintenance at Nuclear Power Plants." Thesedocuments address general guidance for conduct of the risk assessment,quantitative and qualitative guidelines for establishing risk management actions,and example risk management actions. These include actions to plan andconduct other activities in a manner that controls overall risk, increased riskawareness by shift and management personnel, actions to reduce the duration ofthe condition, actions to minimize the magnitude of risk increases (establishmentof backup success paths or compensatory measures), and determination that the


Page 4 of 37

proposed MODE change is acceptable. Consideration should also be given tothe probability of completing restoration such that the requirements of the LCOwould be met prior to the expiration of ACTIONS completion times that wouldrequire exiting the Applicability.

LCO 3.0.4.b may be used with single or multiple systems and componentsunavailable. NUMARC 93-01 provides guidance relative to consideration ofsimultaneous unavailability of multiple systems and components.

The results of the risk assessment shall be considered in determining the.acceptability of entering the MODE or other specified condition in theApplicability, and any corresponding risk management actions. The LCO 3.0.4.brisk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipmentunavailable in MODE 1 for the duration of the completion time. Since this isallowable, and since in general the risk impact in that particular MODE boundsthe risk of transitioning into and through the applicable MODES or other specifiedconditions in the Applicability of the LCO, the use of the LCO 3.0.4.b allowanceshould be generally acceptable, as long as the risk is assessed and managed asstated above. However, there is a small subset of systems and components thathave been determined to be more important to risk and use of the LCO 3.0.4.ballowance is prohibited. The LCOs governing these systems and componentscontain notes prohibiting the use of LCO 3.0.4.b by stating LCO 3.0.4.b is notapplicable.

LCO 3.0.4.c allows entry into a MODE or other specified condition in theApplicability with the LCO not met based on a note in the Specification whichstates LCO 3.0.4.c is applicable. These specific allowances permit entry intoMODES or other specified conditions in the Applicability when the associatedACTIONS to be entered do not provide for continued operation for an unlimitedperiod of time and a risk assessment has not been performed. This allowancemay apply to all the ACTIONS or to a specific required Action of a Specification.The risk assessments performed to justify the use of LCO 3.0.4.b usually onlyconsider systems and components. For this reason, LCO 3.0.4.c is typicallyapplied to Specifications which describe values and parameters (e.g., ReactorCoolant System Specific Activity), and may be applied to other Specificationsbased on NRC plant-specific approval.

The provisions of this Specification should not be interpreted as endorsing thefailure to exercise the good practice of restoring systems or components toOPERABLE status before entering an associated MODE or other specifiedcondition in the Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or otherspecified conditions in the Applicability that are required to comply with


Page 5 of 37

ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes inMODES or other specified conditions in the Applicability that result from any unitshutdown. In this context, a unit shutdown is defined as a change in MODE orother specified condition in the Applicability associated with transitioning fromMODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 toMODE 5.

Upon entry into a MODE or other specified condition in the Applicability with theLCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicableConditions and Required Actions until the Condition is resolved, until the LCO ismet, or until the unit is not within the Applicability of the Technical Specification.

Surveillances do not have to be performed to be performed on the associatedinoperable equipment (or on variables outside the specified limits), as permittedby SR 4.0.4 Therefore, utilizing LCO 3.0.4 is not a violation of SR 4.0.1 or SR4.0.4 for any Surveillances that have not been performed on inoperableequipment. However, SRs must be met to ensure OPERABILITY prior todeclaring the associated equipment OPERABLE (or variable within limits) andrestoring compliance with the affected LCO.


Page 6 of 37

SECTION NO.:

3.0 & 4.0REVISION NO.:

2

TITLE: TECHNICAL SPECIFICATIONSBASES ATTACHMENT 2 OF ADM-25.04

LIMITING CONDITIONS FOR OPERATIONAND SURVEILLANCE REQUIREMENTS

ST. LUCIE UNIT 1

PAGE;',

12 of 12L . :'


BASES (continued)

4.03 (continued)

If a SR is not completed within the allowed delay period, then the equipmentis considered inoperable or the variable is considered outside the specifiedlimits and the completion times of the required ACTION(s) for the applicableLimiting Condition for Operation begin immediately upon expiration of thedelay period. If a surveillance is failed within the delay period, then theequipment is inoperable, or the variable is outside the specified limits and thecompletion times of the required ACTION(s) for-the applicable LimitingCondition for Operation begin immediately upon the failure of thesurveillance.

Completion of the SR within the delay period allowed by this specification, orwithin the completion time of the ACTIONS, restores compliance with SR4.01.

Re p ac*v,, i+/I -+, 4-4.0.4' 'his specification establishes the requirement that alltpplicable surveillancesý

must be met before entry into an OPERATIONAL MODE or other condition oroperation specified in the Applicability statement. The purpose of thisspecification is to ensure that system and component OPERABILITYrequirements or parameter limits are met before entry into a MODE or condition

for which these systems and components ensure safe operation of the facility.This provision, applies to changes in OPERATIONAL MODES or other specifiedconditions associated' with plant shutdown as well as startup.

Under the provisions of-this specification, the applicable SurveillanceRequirements must be performed within the specified. surveillance interval to.ensure that the Limiting Conditions for Operation are met during initial plantstartup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, theprovisions of Specification 4.0.4 do- not apply because: this-would delay

4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2and .3 components will be performed in accordance with a periodically updatedversion of Section XI of the ASME Boiler and Pressure Vessel: Code andAddenda as required by 10 CFR 50.55a. Relief from any of the above

.requirements has been provided in writing by the Commission and is not part ofthese Technical Specifications.


Page 7 of 37

INSERT 4 (BASES SR 4.0.4)

SR 4.0.4 establishes the requirement that all applicable SRs must be met beforeentry into a MODE or other specified condition in the Applicability.

This Specification ensures that system and component OPERABILITYrequirements and variable limits are met before entry into MODES or otherspecified conditions in the Applicability for which these systems and componentsensure safe operation of the unit. The provisions of this Specification should notbe interpreted as endorsing the failure to exercise the good practice of restoringsystems or components to OPERABLE status before entering an associatedMODE or other specified condition in the Applicability.

A provision is included to allow entry into a MODE or other specified condition inthe Applicability when an LCO is not met due to Surveillance not being met inaccordance with LCO 3.0.4.

However, in certain circumstances, failing to meet an SR will not result in SR4.0.4 restricting a MODE change or other specified condition change. When asystem, subsystem, division, component, device, or variable is inoperable oroutside its specified limits, the associated SR(s) are not required to beperformed, per SR 4.0.1, which states that surveillances do not have to beperformed on inoperable equipment. When equipment is inoperable, SR 4.0.4does not apply to the associated SR(s) since the requirement for the SR(s) to beperformed is removed. Therefore, failing to perform the Surveillance(s) within thespecified frequency does not result in an SR 4.0.4 restriction to changingMODES or other specified conditions of the Applicability. However, since theLCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may(or may not) apply to MODE or other specified condition changes. SR 4.0.4 doesnot restrict changing MODES or other specified conditions of the Applicabilitywhen a Surveillance has not been performed within the specified frequency,provided the requirement to declare the LCO not met has been delayed inaccordance with SR 4.0.3.

The provisions of SR 4.0.4 shall not prevent entry into MODES or other specifiedconditions in the Applicability that are required to comply with ACTIONS. Inaddition, the provisions of SR 4.0.4 shall not prevent changes in MODES or otherspecified conditions in the Applicability that result from any unit shutdown. In thiscontext, a unit shutdown is defined as a change in MODE or other specifiedcondition in the Applicability associated with transitioning from MODE 1 to MODE2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.


Page 8 of 37SETINNO:PAGE: --. :

SECTION.NO.: TITLE: TECHNICAL SPECIFICATIONS -A... -

3/4.4 BASES ATTACHMENT 6 OF ADM-25.04 of36REVISION NO.: REACTOR COOLANT SYSTEM

6 ST. LUCIE UNIT 1

3/4.4 REACTOR COOLANT SYSTEM (continued)

BASES (continued)

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE (continued)

314.4.6.1. LEAKAGE DETECTION SYSTEMS (continued)

The 24 hour' interval provides periodic information that is adequate to detectleakage. A Note is added allowing that the RCS water inventory balance isnot required to be performed until 12 hours after-establishing steady stateoperation (stable temperature, power level, pressurizer and makeup tanklevels, makeup and letdown, and RCP seal injection and return flows). The12 hour allowance provides sufficient time to collect and process allnecessary data after stable plant conditions are established. The 30 dayCompletion Time recognizes at least one other form of leakage detection isavailable.

ACTION d

If all required monitors are inoperable, no automatic means of monitoringleakage are available and immediate plantshutdown in accordance withLCO 3.0.3 is required.

isoeffN-e-

SURVEILLANCE SR 4.4.6:1

REQUIREMENTS

SR 4.4.6.1 requires the performance of CHANNEL CHECKs, CHANNELFUNCTIONAL TESTs, and CHANNEL CALIBRATIONs of the requiredleakage detection monitors. These checks give reasonable confidence thechannels are operating properly.


Page 9 of 37

SECTION NO.: TITLE:

3/4.4REVISION NO.:

6

TECHNICAL SPECIFICATIONSBASES ATTACHMENT 6 OF ADM-25.04

REACTOR COOLANT SYSTEMST. LUCIE UNIT 1

3/4.4 REACTOR COOLANT SYSTEM (continued). -_7

BASES (continued)

3/4.4.7 CHEMISTRY

The limitations on Reactor Coolant System chemistry ensure thatcorrosion of the Reactor Coolant System is minimized and reduce thepotential for Reactor Coolant System leakage or failure due to stresscorrosion. Maintaining the chemistry within the Steady State Limitsprovides adequate corrosion protection to ensure the structural integrity ofthe Reactor Coolant System over the life of the plant. The associatedeffects ofexceeding the oxygen, chloride and fluoride limits are time andtemperature dependent. Corrosion studies show that operation may becontinued with contaminant concentration levels in. excess of the SteadyState Limits, up to the Transient Limits, for the specified limit time intervalswithout having a significant effect on the. structural integrity of the ReactorCoolant System. The time .interval permitting .continued operation withinthe restrictions of the Transient Limits provides time for taking correctiveactions to restore the contaminant concentrations to within the SteadyState. Limits.

The surveillance requirements' provide adequate assurance that.concentrations in excess of the limits will be detected in sufficient time totake corrective action.

6t4^

3/4.4.8 SPECIFIC ACTIVITYe maximum allowable doses to an individual at the exclusion area

boundary (EAB) distance for 2 hours. following an accident, or at the lowpopulation zone (LPZ) outer boundary distance for the radiological releaseduration, are specified in 10 CFR 50.67 for design basis. accidents usingthe alternative source term methodology and in Branch Technical Position11-5 for the waste gas decay tank rupture accident. Dose limits to controlroom operators are given in 10 CFR 50.67 and in GDC 19.

0)

The RCS specific activity LCO limits the allowable concentration ofradionuclides in the reactor coolant to ensure that the dose consequencesof limiting accidents do not exceed appropriate regulatory offsite andcontrol room dose acceptance criteria. The LCO contains specific activitylimits for both DOSE EQUIVALENT (DE) 1-131 and DOSE EQUIVALENT(DE) XE-1 33.


Page 10 of 37

SECTION NO.: TITLE:

3/4.4REVISION.NO.:

6

TECHNICAL SPECIFICATIONSBASES ATTACHMENT 6 OF ADM-25.04

REACTOR COOLANT SYSTEMST. LUCIE UNIT 1


+

0.66LaK

BASES (continued)

3/44e8 PECIFIC ACTIVITY (continued)e radiological dose assessments assume the specific activity of the

reactor coolant is at the LCO limits, and an existing reactor coolant steamgenerator tube leakage rate at the applicable Technical Specification limit.The radiological dose assessments assume the specific activity of thesecondary coolant is at its limit as specified in LCO 3.7.1.4, "PlantSystems - Activity."

The ACTIONS allow operation when DOSE EQUIVALENT-I-131 is greaterthan 1..0 pCi/gram and less than 60 pCi/gram. The ACTIONS, require.samplinw*f, f . s and every four hours following to establish atrend. W s

One surveillance requires the determination of the DE XE-1 33 specificactivity as a measure of noble gas specific activity of the.reactor coolant atleast once per 7 days.

A second surveillance is performed to ensure that iodine- specific activityremains within the LCO limit onceper 1.4 days during normal operationand following rapid power changes when iodine spiking, is more apt tooccur. The frequency between two and six hours after a power change ofgreater than 15% RATED THERMAL POWER within a 1 hour period, isestablished because the iodine levels peak during this time followingiodine spike initiation.

The RCS specific activity satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).

3/4.4.9 PRESSURE/TEMPERATURE LIMITS

All. components in the Reactor Coolant System are designed to withstandthe effects of cyclic loads due to system temperature and pressurechanges. These cyclic loads are introduced by normal load transients,reactor trips, and startup and shutdown operations, The variouscategories of load cycles used for design purposes are provided inSection 5.2.1 of the FSAR. During startup and shutdown, the rates oftemperature and pressure changes are limited so that the maximumspecified heatup and cooldown rates. are consistent with the designassumptions and satisfy the stress limits for cyclic operation.


Page 11 of 37

INSERT 5 (BASES LCO 3.4.8)

A note permits the use of the provisions of LCO 3.0.4.c. This allowance permitsentry into the applicable MODE(S) while relying on the ACTIONS. Thisallowance is acceptable due to the significant conservatism incorporated into thespecific activity limit, the low probability of an event that is limiting due toexceeding this limit, and the ability to restore transient specific activity excursionswhile the plant remains at, or proceeds to power operations.


Page 12 of 37

SECIO N .:PAGE:-.,,SECTION NO.: TITLE: TECHNICAL SPECIFICATIONS PAGE

3/464 BASES ATTACHMENT'6 OF ADM-25.04 35.of.3635 of 3.6REVISION NO.: REACTOR COOLANT SYSTEM

6 ST. LUCIE UNIT 1


BASES (continued)

3/4.4.11 DELETED

3/4.4.12 PORV BLOCK VALVES

The opening of the Power Operating Relief Valves fulfills no safety relatedfunction. The electronic controls of the PORVs must be maintainedOPERABLE to ensure satisfaction of Specifications 3.4.12 and 3.4.13.Since it is impractical and undesirable to actually open the PORVs todemonstrate reclosing, it becomes necessary to verify operability of thePORV Block Valves to ensure the capability to isolate. a malfunctioningPORV.

3/4.4.13 POWER OPERATED RELIEF VALVES and3/4.4.14 REACTOR COOLANT PUMP - STARTING

The low temperature overpressure protection system (LTOP) is designedtoprevent RCS overpressurization above the 10! CFR 50 Appendix Goperating limit curves (Figures 3.4-2a and 3.4-2b) at RCS temperatures ator below 3000F. The LTOP system is based on. the use of the pressurizerpower-operated relief valves (PORVs) and the implementation ofadministrative and operational controls.

The PORVs aligned to the RCS with the low pressure setpoints of 350and 530 psia, restrictions. on RCP starts, limitations on heatup andrcooldown rates, and disabling of non-essential components; provideassurance that Appendix G P/T limits will not be exceeded during normaloperation or design basis overpressurization events due to mass orenergy addition to the RCS. The LTOP system.APPLICABILITY,ACTIONS, and SURVEILLANCE REQUIREMENTS are consistent withthe resolution of Generic Issue 94, "Additional Low-TemperatureOverpressure Protection for Light-Water Reactors," pursuant to GenericLetter 90-06.


Page 13 of 37

INSERT 6 (BASES Unit 1 LCO 3.4.13)

LCO 3.4.13 Action f prohibits the application of LCO 3.0.4.b to inoperable PORVsused for LTOP. There is an increased risk associated with entering MODE 4from MODE 5 with PORVs used for LTOP inoperable and the provisions of LCO3.0.4.b, which allow entry into a MODE or other specified condition in theApplicability with the LCO not met after performance of a risk assessmentaddressing inoperable systems and components, should not be applied in thiscircumstance.


Page 14 of 37

SECTION NO:.. TITLE: TECHNICAL SPECIFICATIONS PG

3/4.5 BASES ATTACHMENT 7 OF ADM-25.04. 4 oREVISION NO.: EMERGENCY CORE COOLING SYSTEMS (ECCS)

3 ST. LUCIE UNIT 1.

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) (continued) . .

BASES (continued)

3/4Z5.2 and 3/4.5.3 ECCS SUBSYSTEMS

The OPERABILITY of two separate and independent ECCS subsystemsensures that sufficient emergency core cooling capability will be available inthe event of a LOCA assuming the loss of one subsystem. through anysingle failure consideration. Either subsystem operating in conjunction withthe safety injection tanks is capable of supplying sufficient core cooling tolimit the peak cladding temperatures within acceptable limits for allpostulated break sizes ranging from the- double ended break of-the largestRCS cold leg pipe downward. In addition, each ECCS subsystem provideslong term core cooling capability in the- recirculation mode during theaccident recovery period'.

TS 35.2.c and 3.5.3.a require that, ECCS subsystem(s) have anindependent OPERABLE flow path capable of automatically transferringsuction to the containment sump on a Recirculation. Actuation Signal.The containment sump is defined as the. area of containment below theminimum flood level in the vicinity of the containment sump strainers.Therefore, the LCOs are satisfied when an independent OPERABLE flow.path to the containment sump strainer is available.

TS 3.5.2.d requires that an ECOS subsystem(s) have OPERABLE chargingpump and associated flow path from the BAMT(s). Reference to TS 3.1.2.2requires that the Train A charging pump flowpath is from the BAMT(s)through the boric. acid makeup pump(s). The Train B charging pumpflowpath is from.the BAMT(s) through the gravity feed valve(s).

TS 3.5.2, ACTION a.1. provides an allowed outage/action completion time(AOT) of up to 7 days from initial discovery of failure to meet the LCOprovided the affected ECCS subsystem is inoperable only because itsassociated LPSI train is inoperable. This 7 day AOT is based on thefindings of a deterministic and probabilistic safety analysis and is, referred toas a "risk-informed" AOT extension. Entry into this ACTION requires that arisk assessment be performed in accordance with the Configuration RiskManagement Program (CRMP) which is described in the AdministrativeProcedure (ADM-1 7.08) that implements the Maintenance Rule pursuant to

. F

Cae urve•iance Requirements provided to ensure OPERABILITY of eachcomponent ensure that at a minimum, the assumptions used in the accidentanalyses are met and that subsystem OPERABILITY is maintained.


Page 15 of 37

INSERT 7 (BASES Unit I LCO 3.5.3)

LCO 3.5.3 Action d prohibits the application of LCO 3.0.4.b to inoperable ECCSHigh Pressure Safety Injection subsystem. There is an increased risk associatedwith entering MODE 4 from MODE 5 with an inoperable ECCS High PressureSafety Injection subsystem and the provisions of LCO 3.0.4.b, which allow entryinto a MODE or other specified condition in the Applicability with the LCO not metafter performance of a risk assessment addressing inoperable systems andcomponents, should not be applied in this circumstance.


Page 16 of 37

SECTION NO.: TITLE: TECHNICAL SPECIFICATIONS PAGE' t,__

3/4.7 BASES ATTACHMENT 9 OF ADM-25.04 4.Of.13• ~4 of 1:3REVISION NO.: PLANT SYSTEMS

4 ST. LUCIE UNIT 1

3/4.7 PLANT SYSTEMS (continued) .

BASES (continued)

3/4.7'1 TURBINE CYCLE (continued)

106.5 = Power Level-High Trip Setpoint for two loop operation

X = Total relieving capacity of all safety valves per steam line inlbs/hour (6.192 x 1 06 lbs/hr.)

Y = Maximum relieving capacity of any one safety valve in lbs/hour(7.74.x 105 Ilbs/hr.).

Surveillance Requirement 4.7.1.1. verifies the OPERABILITY of theMSSVs by the verification of each MSSV lift setpoint..in. accordance withthe Inservice Testing Program. The MSSV setpoints are 1000. psia +/-3%.(4 valves each header) and 1040 psia +2/-3% (4 valves each header) forOPERABILITY; however, the valvesý are reset to 1000 psia +/-1% and1040 psia +/- 1 %,, respectively, during the Surveillance to allow for drift.The LCO is expressed in units of psig for consistency with implementingprocedures.

Shpois-oT of Sufeio-.0 dr noapl _Thbis iidws e~tyi4.._a4eer~atie4re9&E-7b-tiu ,t -If'rI I lt 1 ha-Svmei~kwG-..~.ath M Vs may De tested Underboteeed ,-

3/4.7A1.2 AUXILIARY FEEDWATER PUMPS

The OPERABILITY of the -auxiliary feedwater pumps ensures that theReactor Coolant System can be cooled down to less than 325°F fromnormal operating conditions in the event of a total loss of off-site power.

Any two of the three auxiliary feedwater pumps have the required capacityto provide sufficient feedwater flow to remove reactor decay heat andreduce the RCS temperature to 325°F where the shutdown cooling

, be placed into operation for continued cooldown.37ATE STORAGE TANKS

The OPERABILITY of the condensate storage tank with the minimumwater volume ensures that sufficient water is available to maintain HOTSTANDBY for one hour and then cooldown of the Reactor CoolantSystem to less than 3250F in the event of a total loss of off-site power.The minimum water volume is sufficient to maintain the RCS at HOTSTANDBY conditions for 8 hours with steam discharge to atmosphere.The minimum usable volume to satisfy the criteria stated above is 130,500gallons, which is ensured by the LCO for the CST volume of 153,400gallons.


Page 17 of 37

INSERT 8 (BASES Unit I LCO 3.7.1.2)

Action b prohibits the application of LCO 3.0.4.b to an inoperable AFW train.There is an increased risk associated with entering a MODE or other specifiedcondition in the Applicability with an AFW train inoperable and the provisions ofLCO 3.0.4.b, which allow entry into a MODE or other specified condition in theApplicability with the LCO not met after performance of a risk assessmentaddressing inoperable systems and components, should not be applied in thiscircumstance.

3/4J


Page 18 of 37

ION NO.: TITLE: TECHNICAL SPECIFICATIONS PAGE - :

3/4.8 BASES ATTACHMENT 10 OF ADM-25.04 '4 of. 63ON NO:: ELECTRICAL POWER SYSTEMS

3 ST. LUCIE UNIT 1

ELECTRICAL POWER SYSTEMS (continued)

BASES (continued)

TS 3.8.1.1,. ACTION "b" provides an allowed outage/action completion time(AOT) of up to 14 days toto restore a single inoperable diesel generator tooperable status. This AOT is based on the findings of a deterministic andprobabilistic safety analysis and is referred to as a "risk-informed" AOT.Entry into this action requires that a risk assessment be performed inaccordance with the Configuration Risk Management Program (CRMP),.which is described in the Administrative Procedure that implements theMaintenance Rule pursuant to 10 CFR 50.65.

All EDG inoperabilities must be investigated for common-cause failuresregardless of how long the EDG inoperability persists. When one dieselgenerator is inoperable, required ACTIONS 3.8.1A..b and 3.8.1.1.c provide.an allowance to avoid unnecessary testing of EDGs. If it can be determinedthat the cause of the inoperable EDG does not exist on the remainingOPERABLE EDG, then SR 4.8.1.1.2.a.4 does not have to be performed.Eight (8) hours is reasonable to confirm that the OPERABLE EDG is notaffected by the same problem as the inoperable EDG. If it cannot otherwisebe determined that the cause of the initial inoperable EDG does not exist onthe remaining EDG, then satisfactory performance of SR 4.8.1.1.2.a.4suffices to provide assurance of continued OPERABILITY of that EDG.If the cause of the initial inoperability exists on the remaining OPERABLE-EDG,, that EDG would also be declared inoperable upon discovery, andACTION 3.8.1.1.e would be entered. Once the failure is repaired (on either

E Dthe common-cause failure no longer exists.

m conditions are the normal standby conditions for the dieselengines. Any normally running. warmup systems should be in service andoperating, and manufacturer's recommendations for engine oil and watertemperatures and other parameters should be followed.

The OPERABILITY of the minimum specified A.C. and D.C. power sourcesand associated distribution systems during shutdown and refueling ensuresthat 1) the facility can be maintained in the shutdown or refueling conditionfor extended time periods and 2) sufficient instrumentation and controlcapability is available for monitoring and maintaining the facility status.


Page 19 of 37

INSERT 9 (BASES LCO 3.8.1.1)

Action g prohibits the application of LCO 3.0.4.b to an inoperable dieselgenerator. There is an increased risk associated with entering a MODE or otherspecified condition in the Applicability with an inoperable diesel generator and theprovisions of LCO 3.0.4.b, which allow entry into a MODE or other specifiedcondition in the Applicability with the LCO not met after performance of a riskassessment addressing inoperable systems and components, should not beapplied in this circumstance.


Page 20 of 37

'SECTION NO.: TITLE: TECHNICAL SPECIFICATIONS PAGr7E - .

3.0 & 4.0 BASES ATTACHMENT 2 OF ADM-25.04REVISION NO.: LIMJTING CONDITIONS FOR OPERATION - ,--,7 of 12T,:

AND SURVEILLANCE REQUIREMENTS2 ST. LUCIE UNIT 2 ' F77;


BASES (continued)

3.0.4 This specification establishes: limitations on MODE changes when a LimitingCondition for Operation is not met. It precludes placing the facility in a higherMODE of operation, when the requirements for a Limiting Condition forOperation are not.met and continued, noncompliance to these conditions wouldresult in a shutdown to comply with the ACTION requirements if.a change inMODES were permitted. The purpose of this specification is to ensure thatfacility operation is not initiated or that higher MODES of operation are notentered when corrective action is being taken to obtain compliance with aspecification by restoring equipment to. OPERABLE status or parameters tospecified limits. Compliance with ACTION requirements that permit continuedoperation of the facility for an unlimited period of time provides an acceptable

.level of safety for continued .operation without regard to the status of the plantbefore or after a MODE change. Therefore, in this case, entry into anOPERATIONAL MODE or other specified condition may be made inaccordance with the provisions of the ACTION requirements. The provisions ofthis specification should not, however, be interpreted as endorsing the failure, toexercise good practice in restoring systems or components to OPERABLEstatus before plant startup.

When a shutdown is required to. comply With the ACTION requirements, theprovisions of Specification 3.0.4 do not apply because they would. delayplacing the facility ih a lower MODE of operation.

Exceptions to this provision have been provided for a limited number ofspecifications when startup with inoperable equipment would rot affect plantsafety. These exceptions are stated in the ACTION statements of theappropriate specifications.

The specifications of this section establish the general requirementsapplicable to Surveillance Requirements. These requirements are based onthe Surveillance Requirements stated in the Code of Federal Regulations, 10CFR 50.36(c)(3): I"Surveillance requirements are requirements relating to test, calibration, orinspection to, ensure that the. necessary quality of systems and componentsmaintained, that facility operation, will be within safety limits, and that thelimiting conditions of operation will be met."

is

Re.~p~e ~~tk ~-4 3


Page 21 of 37

INSERT 3 (BASES 3.0.4)

LCO 3.0.4 establishes limitations on changes in MODES or other specifiedconditions in the Applicability when an LCO is not met. It allows placing the unitin a MODE or other specified condition stated in that Applicability (e.g., theApplicability desired to be entered) when unit conditions are such that therequirements of the LCO would not be met, in accordance with LCO 3.0.4.a, LCO3.0.4.b, or LCO 3.0.4.c.

LCO 3.0.4.a allows entry into a MODE or other specified condition in theApplicability with the LCO not met when the associated ACTIONS to be enteredpermit continued operation in the MODE or other specified condition in theApplicability for an unlimited period of time. Compliance with required Actionsthat permit continued operation of the unit for an unlimited period of time in aMODE or other specified condition provides an acceptable level of safety forcontinued operation. This is without regard to the status of the unit before orafter the MODE change. Therefore, in such cases, entry into a MODE or otherspecified condition in the Applicability may be made in accordance with theprovisions of the required Actions.

LCO 3.0.4.b allows entry into a MODE or other specified condition in theApplicability with the LCO not met after performance of a risk assessmentaddressing inoperable systems and components, consideration of the results,determination of the acceptability of entering the. MODE or other specifiedcondition in the Applicability, and establishment of risk management actions, ifappropriate.

The risk assessment may use quantitative, qualitative, or blended approaches,and the risk assessment will be conducted using the plantprogram, procedures,and criteria in place to implement 10 CFR 50.65(a)(4), which requires that riskimpacts of maintenance activities to be assessed and managed. The riskassessment for the purposes of LCO 3.0.4.b, must take into account allinoperable Technical Specification equipment regardless of whether theequipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope.The risk assessments will be conducted using the procedures and guidanceendorsed by Regulatory Guide 1.182, "Assessing and Managing Risk BeforeMaintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline forMonitoring the Effectiveness of Maintenance at Nuclear Power Plants." Thesedocuments address general guidance for conduct of the risk assessment,quantitative and qualitative guidelines for establishing risk management actions,and example risk management actions. These include actions to plan andconduct other activities in a manner that controls overall risk, increased riskawareness by shift and management personnel, actions to reduce the duration ofthe condition, actions to minimize the magnitude of risk increases (establishmentof backup success paths or compensatory measures), and determination that the


Page 22 of 37

proposed MODE change is acceptable. Consideration should also be given tothe probability of completing restoration such that the requirements of the LCOwould be met prior to the expiration of ACTIONS completion times that wouldrequire exiting the Applicability.

LCO 3.0.4.b may be used with single or multiple systems and componentsunavailable. NUMARC 93-01 provides guidance relative to consideration ofsimultaneous unavailability of multiple systems and components.

The results of the risk assessment shall be considered in determining theacceptability of entering the MODE or other specified condition in theApplicability, and any corresponding risk management actions. The LCO 3.0.4.brisk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipmentunavailable in MODE 1 for the duration of the completion time. Since this isallowable, and since in general the risk impact in that particular MODE boundsthe risk of transitioning into and through the applicable MODES or other specifiedconditions in the Applicability of the LCO, the use of the LCO 3.0.4.b allowanceshould be generally acceptable, as long as the risk is assessed and managed asstated above. However, there is a small subset of systems and components thathave been determined to be more important to risk and use of the LCO 3.0.4.ballowance is prohibited. The LCOs governing these systems and componentscontain notes prohibiting the use of LCO 3.0.4.b by stating LCO 3.0.4.b is notapplicable.

LCO 3.0.4.c allows entry into a MODE or other specified condition in theApplicability with the LCO not met based on a note in the Specification whichstates LCO 3.0.4.c is applicable. These specific allowances permit entry intoMODES or other specified conditions in the Applicability when the associatedACTIONS to be entered do not provide for continued operation for an unlimitedperiod of time and a risk assessment has not been performed. This allowancemay apply to all the ACTIONS or to a specific required Action of a Specification.The risk assessments performed to justify the use of LCO 3.0.4.b usually onlyconsider systems and components. For this reason, LCO 3.0.4.c is typicallyapplied to Specifications which describe values and parameters (e.g., ReactorCoolant System Specific Activity), and may be applied to other Specificationsbased on NRC plant-specific approval.

The provisions of this Specification should not be interpreted as endorsing thefailure to exercise the good practice of restoring systems or components toOPERABLE status before entering an associated MODE or other specifiedcondition in the Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or otherspecified conditions in the Applicability that are required to comply with


Page 23 of 37

ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes inMODES or other specified conditions in the Applicability that result from any unitshutdown. In this context, a unit shutdown is defined as a change in MODE orother specified condition in the Applicability associated with transitioning fromMODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 toMODE 5.

Upon entry into a MODE or other specified condition in the Applicability with theLCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicableConditions and Required Actions until the Condition is resolved, until the LCO ismet, or until the unit is not within the Applicability of the Technical Specification.

Surveillances do not have to be performed to be performed on the associatedinoperable equipment (or on variables outside the specified limits), as permittedby SR 4.0.4 Therefore, utilizing LCO 3.0.4 is not a violation of SR 4.0.1 or SR4.0.4 for any Surveillances that have not been performed on inoperableequipment. However, SRs must be met to ensure OPERABILITY prior todeclaring the associated equipment OPERABLE (or variable within limits) andrestoring compliance with the affected LCO.


Page 24 of 37

SECTION NO;: TITLE: TECHNICAL SPECIFICATIONS PAGE, -

3.0 & 4.0 BASES ATTACHMENT 2 OF ADM-25.04REVISION NO.: LIMITING CONDITIONS FOR OPERATION ',2 of 12.

AND SURVEILLANCE REQUIREMENTSST. LUCIE UNIT 2 ....

314.0 APPLICABILITY (continued)

BASES (continued)

4.03 (co.ntinued)

If a SR is not completed within the allowed delay period, then the equipmentis considered inoperable or the variable is. considered outside the specifiedlimits and the completion times of the required ACTION(s) for the applicableLimiting Condition for Operation begin immediately upon expiration of thedelay period. If a surveillance is failed within the delay period, then theequipment is inoperable, or the variable is outside the specified limits. and thecompletion times of the required ACTION(s). for the applicable LimitingCondition for Operation begin immediately upon the failure of thesurveillance.

Completion of the SR within the delay period. allowed by this specification, orwithin the completion time. of the ACTIONS, restores compliance with SR.S 4.0,1..

"v-"4-4.0.4• This specification establishes the requirement that all applicable surveillances.must be met before entry into .an OPERATIONAL MODE• or other condition, or

.operation specified in the Applicability statement... The purpose of this,specification is to -ensure that System and component OPERABILITYirequirements or parameter limits are met before entry into a MO DE or condition

'for which these systems and components ensure safe operation of the facility.This provision applies to changes in OPERATIONAL MODES or other specifiedconditions associated with plant shutdown as. well as startup.

Under the provisions of this specification, the applicable SurveillanceRequirements must be performed within the specified surveillance interval toensure that the Limiting Conditions for Operation are met during initial plantstartup or following a plant outage.When a shutdown is required to comply with ACTION requirements, the 1

Sprovisions of Specification 4.0.A do not apply because this would delay ,.placing the: facility in a lower MODE of oprtin

4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2and 3 components will be. performedin accordance with a periodically updatedversion of Section XI of the ASME. Boiler and Pressure Vessel Code andAddenda as, required by 10 CFR 50.55a. Relief from any of the aboverequirements .has been provided in writing by the Commission and is not part ofthese Technical Specifications.


Page 25 of 37

INSERT 4 (BASES SR 4.0.4)

SR 4.0.4 establishes the requirement that all applicable SRs must be met beforeentry into a MODE or other specified condition in the Applicability.

This Specification ensures that system and component OPERABILITYrequirements and variable limits are met before entry into MODES or otherspecified conditions in the Applicability for which these systems and componentsensure safe operation of the unit. The provisions of this Specification should notbe interpreted as endorsing the failure to exercise the good practice of restoringsystems or components to OPERABLE status before entering an associatedMODE or other specified condition in the Applicability.

A provision is included to allow entry into a MODE or other specified condition inthe Applicability when an LCO is not met due to Surveillance not being met inaccordance with LCO 3.0.4.

However, in certain circumstances, failing to meet an SR will not result in SR4.0.4 restricting a MODE change or other specified condition change. When asystem, subsystem, division, component, device, or variable is inoperable oroutside its specified limits, the associated SR(s) are not required to beperformed, per SR 4.0.1, which states that surveillances do not have to beperformed on inoperable equipment. When equipment is inoperable, SR 4.0.4does not apply to the associated SR(s) since the requirement for the SR(s) to beperformed is removed. Therefore, failing to perform the Surveillance(s) within thespecified frequency does not result in an SR 4.0.4 restriction to changingMODES or other specified conditions of the Applicability. However, since theLCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may(or may not) apply to MODE or other specified condition changes. SR 4.0.4 doesnot restrict changing MODES or other specified conditions of the Applicabilitywhen a Surveillance has not been performed within the specified frequency,provided the requirement to declare the LCO not met has been delayed inaccordance with SR 4.0.3.

The provisions of SR 4.0.4 shall not prevent entry into MODES or other specifiedconditions in the Applicability that are required to comply with ACTIONS. Inaddition, the provisions of SR 4.0.4 shall not prevent changes in MODES or otherspecified conditions in the Applicability that result from any unit shutdown. In thiscontext, a unit shutdown is defined as a change in MODE or other specifiedcondition in the Applicability associated with transitioning from MODE 1 to MODE2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.


Page 26 of 37

SECTION NO.: PAGE',,

TITLE: TECHNICAL SPECIFICATIONS3/4.4 BASES. ATTACHMENT 6 OF ADM-25.04 21 of 37 -REVISION NO.: REACTOR COOLANT SYSTEMo

9 ST. LUCIE UNIT 2


BASES (continued)

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE (continued)

3/4.4.6.1 LEAKAGE DETECTION SYSTEMS (continued)

ACTION c

With both gaseous and particulate containment atmosphere radioactivitymonitoring instrumentation channels inoperable, alternative action isrequired. Either grab samples of the containment atmosphere must betaken and analyzed, or water inventory balances, must be performed toprovide alternate periodic information. With a sample obtained andanalyzed or an inventory balance performed every 24 hours, the reactormay be operated for up to 30 days to allow restoration of at least one of theradioactivity monitors.

The 24 hour interval- provides periodic information that is adequate to detectleakage.. A Note is added allowing that the RCS water inventory balance isnot required to be performed until 12 hours after establishing steady stateoperation (stable temperature, power level, pressurizer and makeup tanklevels, makeup and letdown, and RCP seal injection and return flows). The12 hour allowance provides sufficient time to collect and process allnecessary data after stable plant conditions are established. The 30 dayCompletion Time recognizes at least one other form of leakage- detection isavailable.

ACTION d

If all required monitors are inoperable, no automatic means of monitoringleakage are available and immediate plant shutdown in accordance withLCO 3.0.3 is required.

tt t• -efT he--e.t0ed-m tr---.

.. s-epefar--le.

SURVEILLANCE SR 4.4.6.1

REQUIREMENTS

SR 4.4.6.1 requires the performance of CHANNEL CHECKs, CHANNELFUNCTIONAL TESTs, and CHANNEL CALIBRATIONs of the requiredleakage detection monitors, These checks give reasonable confidence thechannels are operating properly.

L-201 3-23 3Attachment 5

Page 27 of 37

SECTION NO::; TITLE: TECHNICAL SPECIFICATIONS

3/4.4 BASESAATTACHMENT 6 OF ADM-25.04REVISION NO.: REACTOR COOLANT SYSTEM

9 ST. LUCIE UNIT 2

3/4.4 REACTOR COOLANT SYSTEM (continued) . - '._BASES (continued)

3/4.4.8 SPECIFIC. ACTIVITY

The maximum allowable doses to an individual at the exclusion areaboundary. (EAB) distance for2 hours following an accident, or at the.low.population zone (LPZ) outer boundary distance for the radiological releaseduration, are specified in 10 CFR.50.67 for design basis accidents using thealternative source term methodology and in Branch Technical Position 11-5for the waste gas decay tank rupture accident. Dose limits to control. roomoperators are given in 10 CFR 50.67 and in GDC 19

The RCS specific activity LCO limits the allowable concentration ofradionuclides in the reactor coolant to ensure that the dose consequences oflimiting. accidents do not exceed appropriate regulatory offsite and Control roomdose acceptance criteria. The LCO contains specific activity limits for bothDOSE EQUIVALENT (DE) 1-131 and DOSE EQUIVALENT (DE) XE-1.33.

The radiological dose assessments assume the specific activity of the reactorcoolant is at the LCO limits, and an existing reactor coolant steam generatortube leakage rate at the applicable Technical Specification limit. Theradiological dose assessments, assume the specific activity of the secondarycoolant is at its limit as specified in LCO 3.7.1.4, "Plant Systems - Activity."

The ACTIONS allow operation when DOSE EQUIVALENT 1-1.31 is greaterthan 1.0 pCi/gram and less than 60 pCi/gram. The ACTIONS require ,ns1within four hours and every four hours fdllowing to establish a trend. se.r4

One surveillance requires the determination of the DE.XE-133 specific activityas a measure of noble gas. specific activity of the reactor coolant at least onceper 7 days.

A second surveillance.is performed to ensure that iodine specific activityremains within the LCO limit once per 14 days during normal operation andfollowing rapid power changes when iodine spiking is more apt to occur. Thefrequency between two and six hours after a power change of greater than15% RATED THERMAL POWER within a 1 hour period, is, establishedbecause the iodine levels peak during this time following iodine spikei.nitiation.

The RCS specific activity satisfies Criterion 2 of 1O.CFR 50.36(c)(2)(ii).


€CD


Page 28 of 37

INSERT 5 (BASES LCO 3.4.8)

A note permits the use of the provisions of LCO 3.0.4.c. This allowance permitsentry into the applicable MODE(S) while relying on the ACTIONS. Thisallowance is acceptable due to the significant conservatism incorporated into thespecific activity limit, the low probability of an event that is limiting due toexceeding this limit, and the ability to restore transient specific activity excursionswhile the plant remains at, or proceeds to power operations.


Page 29 of 37

SECTION NO;: TITLE: TECHNICAL SPECIFICATIONS' PAGE:,---'

3/4.4 BASES ATTACHMENT 6 OF ADM-25.04 35 of 37REVISION NOý: REACTOR COOLANT SYSTEM

9 ST. LUCIE UNIT 2

3/4.4 REACTOR COOLANT SYSTEM (continued) . .

BASES (continued)

3/4.4.9 PRESSUREITEMPERATURE LIMITS (continued)

The limitations imposed on the pressurizer heatup and cooldown rates andspray water temperature differential are provided to assure that thepressurizer is operated within the design criteria assumed for the fatigueanalysis performed in accordance with the ASME Code requirements.

The .OPERABILITY of two PORVs, two SDCRVs or an RCS vent opening ofgreater than 3.58 square inches ensures that the RCS will be protected' frompressure transients which could exceed the liniits of Appendix G to 10 CFRPart 50 when one or more of the RCS cold leg temperatures are less than orequal to the LTOP temperatures. The Low Temperature OverpressureProtection System has adequate relieving capability to protect the RCS fromoverpressurization when the transient is limited to either (1) a safety injectionactuation in a water-solid RCS with the pressurizer heaters energized or (2)the start of.an idle RCP with the secondary water temperature of the steamgenerator less than or equal to 40°F above the RCS cold leg temperatures

,._bý ýizer water-solid.

3/4.4.10 ýXO ýOLANT SYSTEM VENTS

Reactor Coolant System vents are provided to exhaust noncondensiblegases and/or steam from the primary system that could inhibit naturalcirculation core cooling. The OPERABILITY of at least one Reactor CoolantSystem vent path from the reactor vessel head and the pressurizer steamspace ensures the capability exists to perform this function.

The. redundancy design of the Reactor Coolant System vent systems serves-to minimize the probability of.inadvertent or irreversible actuation whileensuring that a single failure of a vent valve, power supply, or control systemdoes not prevent isolation of the vent path.

The function, capabilities, and testing requirements of the Reactor CoolantSystem vent system are consistent with the requirements of Item ll.b.1 ofNUREG-0737, "Clarification of TMI Action Plan Requirements," November1980.


Page 30 of 37


LCO 3.4.9.3 Action d prohibits the application of LCO 3.0.4.b to inoperablePORVs used for LTOP. There is an increased risk associated with enteringMODE 4 from MODE 5 with PORVs used for LTOP inoperable and theprovisions of LCO 3.0.4.b, which allow entry into a MODE or other specifiedcondition in the Applicability with the LCO not met after performance of a riskassessment addressing inoperable systems and components, should not beapplied in this circumstance.


Page 31 of 37

SECTION NO.: TITLE: TECHNICAL SPECIFICATIONS PAGE" .

3/4.5. BASES ATTACHMENT 7 OF ADM-25.04 , of 7'. :REVISION NO.: EMERGENCY CORE COOLING SYSTEMS (ECCS).

2 ST. LUCIE UNIT 2

3/4.5 EMERGENCY-CORE COOLING SYSTEMS (ECCS) (continued)

BASES (continued)

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS

The OPERABILITY of two separate and independent ECCS subsystemsensures that sufficient emergency core: cooling capability will be availablein the event of a LOCA assuming the loss. of one subsystem through anysingle failure consideration. Either subsystem operating in conjunctionwith the safety injection tanks is capable of supplying sufficient corecooling to limit the. peak cladding temperatures within acceptable limits forall postulated break sizes ranging from the double-ended break of thelargest RCS hot leg pipe downward. In addition, each ECCS subsystemprovides long-term core cooling capability in the recirculation mode duringthe accident recovery period.

TS 3.5.2.c and 3.5.3 require that ECCS subsystem(s) have an independentOPERABLE flow path capable of'automatically transferring suction to thecontainment on a Recirculation Actuation Signal. The containment sump isdefined as the area of Containment below the minimum flood level in thevicinity of the Containment sump strainers. Therefore, the LCOs are satisfiedwhen an independent OPERABLE flow path to the containment sump straineris available.

TS 3.5.2.d requires that an ECCS subsystem(s) have an OPERABLEcharging pump and associated flow path from the BAMT(s). Reference to TS3.1.2.2 requires that the one charging pump flow path is from the BAMT(s)through the boric acid makeup pump(s). The second charging pump flowpathis from the BAMT(s) through the gravity feed valves.

TS 3.5.2, ACTION a. 1. provides an allowed outage/action completion time(AOT) of up to 7 days from initial discovery of failure to meet the LCOprovided the affected ECCS subsystem is inoperable only because itsassociated LPSI train is inoperable. This 7 day AOT is based on thefindings of a deterministic and probabilistic safety analysis and is referredto as a "risk-informed" AOT extension. Entry into thisACTION requiresthat a.risk assessment be performed in accordance with the ConfigurationRisk Management Program (CRMP) which is described in theAdministrative Procedure (ADM-17.08) that implements the MaintenanceRule pursuant to 10 CFR 50.65.

In Mode 3 with RCS pressure < 1750 psia and in. Mode 4, oneOPERABLE ECCS subsystem is acceptable without single failureconsideration on the basis of the stable reactivity Condition of the reactorand the limited core cooling requirements.


Page 32 of 37


LCO 3.5.3 Action c prohibits the application of LCO 3.0.4.b to inoperable ECCSHigh Pressure Safety Injection subsystem. There is an increased risk associatedwith entering MODE 4 from MODE 5 with an inoperable ECCS High PressureSafety Injection subsystem and the provisions of LCO 3.0.4.b, which allow entryinto a MODE or other specified condition in the Applicability with the LCO not metafter performance of a risk assessment addressing inoperable systems andcomponents, should not be applied in this circumstance.


Page 33 of 37

S C INNO:PAGE".-:.. . "'

SECTION:NO.: TITLE: TECHNICAL SPECIFICATIONS ..GE

3/4.7 BASES ATTACHMENT 9 OF ADM-25.04 4 of 16""REVISION NO.: PLANT SYSTEMS -

6 ST. LUCIE UNIT 2

3/4.7 PLANT SYSTEMS (continued)

BASES (continued)

3/4.7.1 TURBINE CYCLE (continued)

3/4.7.1.1 SAFETY VALVES (continued)

107.0 = Power Level-High Trip Setpoint for two loop operation.

0.9 = Equipment processing uncertainty

.X = Total relieving capacity of all safety valves per steam line inlbs/hour (6.247 x 106 lbs/hr)

Y = Maximum relieving capacity of any one safety valve in lbs/hour(7.74 x 10 lbs/hr)

Surveillance Requirement 4.7.1.1 verifies the OPERABILITY of the MSSVs. bythe. verification of each MSSV lift setpoint in accordance with the InserviceTesting Program. The MSSV setpoints are 1000 psia +/-3% (4 valves eachheader) and 1040 psia +2%/-3% (4 valves each header) for OPERABILITY;however, the. valves are reset to 1000 psia +/- 1 % and 1040 psia +/- 1 %,respectively, during the Surveillance to allow for drift. The LCO is expressedin units of psig for consistency with implementing procedures,

_The-MSSVi mie er4e tndefrio • ty-lhis'ttes-netryi.s ereta,,ý m in-Mef• -'p-• k toprerforrmie-n-: em ,• r t

3/4.7.1.2. AUXILIARY FEEDWATER SYSTEM

The Auxiliary Feedwater (AFW) System automatically supplies feedwater tothe steam generators to remove decay heat from the Reactor Coolant. Systemupon the loss of normal feedwater supply. The AFW System consists of twomotor driven AFW pumps and one steam turbine driven pump configured intothree trains.

Each motor driven pump provides 100% of AFW flow capacity; the turbine•driven pump provides 100% ,of the required capacity to the steam, generatorsas assumed in the accident analysis. Each motor driven AFW pump ispowered from an independent Class 1 E power supply and feeds one steamgenerator, although each pump has the capability to be-realigned from thecontrol room to feed the other steam generator. One pump at full flow issufficient to remove decay heat and cool the unit to Shutdown Cooling (SDC)System entry conditions.


Page 34 of 37

SECTION:NO.: TITLE: TECHNICAL SPECIFICATIONS PAGE. .

3/4.7 BASES ATTACHMENT 9 OF ADM-25.04 5 of 16,REVISION NO.: PLANT SYSTEMS -.

6 ST. LUCIE UNIT2 2

314.7 PLANT SYSTEMS (continued)

BASES (continued)

3/4.7.1 TURBINE CYCLE (continued)

3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (continued)

The steam turbine-driven AFW pup receives steam from either main steamheader upstream of the main steam, isolation valve. Each of the steam feedlines will supply 100% of the requirements of the turbine driven AFW pump.The turbine driven AFW pump supplies a common header capable of feedingboth steam generators, with DC powered control valves actuated to theappropriate steam generator by the Auxiliary Feedwater Actuation System(AFAS).

The. AFW System supplies feedwater to the steam generators during normalunit startup, shutdown, and hot standby conditions.

The: AFW System mitigates the consequences.of anyevent with a loss ofnormal feedwater. The limiting Design Basis Accidents and transients for theAFW System are as follows:

1. Feedwater Line Break, and

,,of normal feedwater.

u equirement (SR) 4.7.1.2.d verifies that each AFW pump'sdeveloped head at the flow test point is greater than or equal to the requireddeveloped head ensures that AFW pump performance has not degradedduring the cycle. Flow and differential head are normal tests of pumpperformance required by the ASME Code. Because it is. undesirable tointroduce cold.AFW into the steam generators while they are operating, thistesting is performed on recirculation flow. this test confirms one point on thepump design curve and is indicative of overall performance. Such inservicetests confirm component Operability, trend performance, and detect incipientfailures by indicating abnormal performance. Performance of-inservicetesting, discussed in the ASME Code, at 3 month intervals satisfies thisrequirement. This SR is modified to defer performance Until suitable testconditions are established for the steam turbine-driven AFW pump within 24hours after entering Mode 3 and prior to entering Mode 2.


Page 35 of 37

INSERT 8 (BASES Unit 2 LCO 3.7.1.2)

Action d prohibits the application of LCO 3.0.4.b to an inoperable AFW train.There is an increased risk associated with entering a MODE or other specifiedcondition in the Applicability with an AFW train inoperable and the provisions ofLCO 3.0.4.b, which allow entry into a MODE or other specified condition in theApplicability with the LCO not met after performance of a risk assessmentaddressing inoperable systems and components, should not be applied in thiscircumstance.


Page 36 of 37

SECTION NO.: PG,---TITLE: TECHNICAL SPECIFICATIONS PAGEN-.

3/4.8 BASES ATTACHMENT 10 OF ADM-25.04 4 of 8REVISIONNO,: ELECTRICAL POWER SYSTEMS

3 ST. LUCIE UNIT 2

3/4.8 ELECTRICAL POWER SYSTEMS (continued)

BASES (continued)

3/4.81A, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWERDISTRIBUTION. SYSTEMS (continued)

The four hour completion time upon discovery that an opposite trainrequired feature is inoperable is to provide assurance that a loss of offsitepower, during the period that a EDG is inoperable, does not result in acomplete loss of safety function of critical redundant required features.The four-hour completion time allows the operator time to evaluate andrepair any discovered inoperabilities. This completion time also allows foran exception to the normal "time zero" for beginning the allowed outagetime "clock." The four hour completion time 0nly begins on discovery thatboth an inoperable EDG: exists and a required feature on the other train isinoperable.

TS:3.8.1.1, ACTION "b" provides an allowed outage/action. completion time(AOT) of up to 1.4 days to restore a single inoperable diesel generator tooperable status. This AOT is based on the findings of a deterministic andprobabilistic safety analysis and is referred to as a "risk-informed" AOT.Entry into this action requires that a risk assessment be performed inaccordance with the Configuration. Risk Management Program (CRMP),which is described in the Administrative Procedure that implements theMaintenance Rule pursuant.to 1.0 CFR 50.65.

All EDG inoperabilities must be investigated for common-cause failuresregardless of how long the EDG inoperability persists. When one dieselgenerator is inoperable, required ACTIONS 3.8.1.lb and 3.8.1.1.c provide'an allowance to avoid unnecessary testing of EDGs. If it can bedetermined that the cause of the inoperable EDG does not exist on theremaining OPERABLE EDG, then SR 4.8.1.1.2.a.4 does not have to beperformed. Eight (8) hours is reasonable to confirm that the OPERABLEEDG is not affected by the same problem as the inoperable .EDG. If itcannot otherwise be determined that the cause of the initial inoperableEDG does not exist on the remaining EDG, then satisfactory performanceof SR 4.8.1.1.2.a.4 suffices to provide assurance of continuedOPERABILITY of that EDG. If the cause of the initial inoperability exists onthe remaining OPERABLE EDG, that EDG would also be declaredinoperable upon discovery, and ACTION 3.8.1.1.e would be entered. Oncethe failure is repaired (on either EDG), the common-cause failure no longerexists.

D9


Page 37 of 37

INSERT 9 (BASES LCO 3.8.1.1)

Action g prohibits the application of LCO 3.0.4.b to an inoperable dieselgenerator. There is an increased risk associated with entering a MODE or otherspecified condition in the Applicability with an inoperable diesel generator and theprovisions of LCO 3.0.4.b, which allow entry into a MODE or other specifiedcondition in the Applicability with the LCO not met after performance of a riskassessment addressing inoperable systems and components, should not beapplied in this circumstance.

fpl. february 26, 2014 · l-2013-233 attachment 1 page 2 of 5 st. lucie unit 1 the following...

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