nuclear regulatory commission · 2018. 7. 31. · l ist of figures index page 3.1-1 3.2-1 3.4-1...

R 1NFORMATION ONL

oESIGN FEATURES

INDEX

SECTION

5. 1 SITE LQ<L'YSW

PAGE

~ 0 ~ ~ 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~

0 ~ 001 ~ ~ ~ ~ ~ ~ ~ 000 ~ ~ 0 ~ ~ 0 ~ ~ ~ 0 ~ 0 ~ 00 ~ ~ ~ 0 ~ ~

~ ~ ~ ~ t 0 ~ 1 ~ 0 0 0 ~ 0 ~ ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ 0 ~ ~ 0 0 0 ~ 0 0 ~

~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 0 ~ 0 0 t 0 0 0 0 0 ~ \ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 t ~ ~ ~

5. REACTOR CORE

2.S.Q. 1

5.$ .2FUEL ASSEMBLIES.................00.0.0.0-0000-.0..00-- ~ ~

CONTROL ELEMENT ASSEMBLIES...............--....--.--- 5 Q

5. FUEL'TORAGE3

5.$ .1S.5.E

S.(.S

CRITICALITY.............................................RAINAGE0 ~ ~ 0 ~ ~ ~ ~ 0 0 ~ ~ ~ ~ 0 ~ 0 ~ ~ ~ 0 0 0 ~ 0 ~ 0 0 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 0 0 ~D

APACITY0 0 ~ 0 ~ ~ ~ ~ 0 0 ~ ~ ~ ~ ~ ~ ~ 0 0 t ~ 0 0 ~ ~ 0 ~ ~ ~ ~ ~ 0 ~ ~ 0 ~ 0 ~ ~ ~ 0 ~ ~ ~ ~ ~C

5-(5-(-Z,5-%,- 2..

~ ~ 0 \ 0 ~ ~ ~ ~ ~ 0 ~

9511150008 951107PDR ADQCK 05000528P, ',,PDR

PALO VERDE - UNIT 1 XV

L IST OF FIGURES

INDEX

PAGE

3.1-1

3.2-1

3.4-1

MINIMUM BORATED WATER VOLUMES....................

REACTOR COOLANT COLD LEG TEHPERATURE VS CORE POWER

LEVEL. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFICACTIVITY LIMIT VERSUS PERCENT OF RATED THERMALPOWER WITH THE PRIHARY COOLANT SPECIFIC ACTIVITY> 1.0 pCi/GRAM DOSE EQUIVALENT I-131......-....-

3/4 1-11

3/4 2-8

3/4 4-27

3.4-2a REACTOR COOLANT SYSTEM PRESSURE TEMPERATURELIMITATIONS FOR LESS THAN 8 EFPY OF OPERATION.......-.. 3/4 4-29

3.4-2b

3.4-2c

3.4-2d

REACTOR COOLANT SYSTEM PRESSURE TEMPERATURELIMITATIONS FOR 8 TO 32 EFPY OF OPERATION....

REACTOR COOLANT SYSTEM MAXIMUM ALLOWABLE HEATUPAND COOLDOWN RATES FOR LESS THAN 8 EFPY OFOPERATION.......

REACTOR COOLANT SYSTEM MAXIMUM ALLOWABLE HEATUPAND COOLDOWN RATES FOR 8 TO 32 EFPY OF'0 PERAT ION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4 4-29a

3/4 4-29b

"3/4 4-29c

4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST.............. 3/4 7-26

ASSEMBLY B>'RNUP VERSUS INITIAL ENRICHMENT 5W

PALO VERDE - UNIT 1 XIX AMENDMENT NO. SS, ~, 82

/

ST OF TABLES

307 2

4.7-1

4.7-2

4.8-1

3.8-1

4.8-2

MAXIMUMALLOWABLE STEADY STATE POWER LEVEL AND MAXIMUMVARIABLE OVERPOWER TRIP SETPOINT WITH INOPERABLE STEAMLINE SAFETY VALVES......................-.-....-... ~ ~ ~ . ~

SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITYSAMPLE AND ANALYSIS PROGRAM...... ~ -. ~ -- ~ ~ -- ~ ~ ~ -- ~ --- ~ - ~ ~

SNUBBER VISUAl. INSPECTION INTERVAL.."-..... -.-DIESEL GENERATOR TEST SCHEDULE.................""--D.C. ELECTRICAl. SOURCES..............................--.BATTERY SURVEILLANCE RE(UIREMENTS....................-..

B 3/4.4-1 REACTOR VESSEL TOUGHNESS................................

3/4 7-3

3/4 7-8

3/4 7-25a

3/4 8-7

3/4 8-11

3/4 8-12

B 3/4 4-8

6.2-1 MINIMUM SHIFT CREW COMPOSITION.......,..................... '6-5

PAlO VERDE - UNIT 1 XXII AMENDMENT NO. 44-,-&7, ~, 85

REACTOR CQQLANT SYSTE, a

PRESSURIZER HEATUP/CQOLDOWH LIMITS

LIMITING CONDITION FOR OPERATION

3. 4. 8. 2 The pressurizer temperature shall be limited to:

a. A maximum heatup rate of 200~F per hour, and

b. A maximum cooldown rate of 200 F per hour.

APPLICABILITY: At all times.

ACTION:

With the pressurizer temperature limits in excess of any of the above limits,restor e the temperature to within the limits within 30 minutes; perform anengineering evaluation to determine the effects of the out"of"limit conditionon the structural integrity of the pressurizer; determine that the pressurizer-emains acceptable for continued operation or be in at least HOT STANDBYwithin the next 6 hours and reduce the pressurizer pressure to less than500 psig within the following 30 hours.

SURVEILLANCE RE UIREHEHTS

4.4.8.2. 1 The pressurizer temperatures shall be deterained to be within thelimi:s at least once per 30 minutes during system heatup or cooldown.

4. 4. 8. 2. 2 The spray water temperature differential shall be deterrainedfor use for each cycle of main spray with less than fourreactor coolan pumps operating and for each cycle of auxiliary sprayoperation.

PALO VERDE - UHIT 1 3/4 4-31 AHEHOMEHT HO. 27

R INFORMATIONONL

5. 0 DESIGN FEATURES

5.1 SITE \ Omar xo~ ~~~ ~ ~«Mup

6

~ ~

PALO VERDE - UNIT 1 5-1

R INFOR

e'

IBuckeye.Satome

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G

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I

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Figure 5.1-1Site and Exclusion Boundaries

Scale ( miles )

Cenf affine ofConteinmenfo PropertyPurchasedExclusionBoundary

Site BoundaryD Prooerty Purchased I

Qutsioe ErIclusen Area(I

PALO VERDE " UNIT 1 5-2 AMENDMENT NO. 62

R INFORMATION ONLGraphic ScaMin Miles

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KEY TO MAP

Paved RoadUnpaved Road4WD RoadGas PipelineOil PipelinePower LineRailroad

Airstrip

SirenMilepost

Palo Verde NuclearGenerating StationBoundary

School

Palo Verde Nuclear Generating StationLOW POPULATION ZONE

0-5 Miles

FIgure 5.1-2

PP t I =~no l«)T l ~ ~ t ~ Ire ~ Ir a or ~ ~ Ia C os

Ollsitn Dose Cakuiialen Maniial Pa'lo Verde Nuclear Generating Slahon

Fuel Building

Fuel BuildingExhaust

Main StcamSupport

Conlainmcnt Structure

Condcnsor Vacuum andPlant Vent Exhaust

Oper ahonsSupportBuilding

WVQa-~

~ My- ~ ar j

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Control Oiesel GenRadwaste Buiiding Bu;l(fjngBuilding

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Plant Vent andCondensor Vacuum

t45'uel

Building f09'-9"

Palo Verde Nuclear Generating StationGASEOUS EFFLUENT RELEASE POINTS

Fig 5.t-3

ESIGN FEATURES

R5. REACTOR CORE

~FAS EMBL ES .'-

p5. . 1 reactor core shall contain 241 fuel assemblies with each fuelassembly no containing 236 fuel rods or burnable poison rods clad withZircaloy-4 except limited substitution of fuel rods by filler rodsconsisting of Zircaloy- stainless steel may be made if justified by a cyclespecific reload analysis. Ea el rod shall have a nominal active fuellength of 150 inches and contain a um total weight of approximately 1950grams uranium. Each burnable poison rod have a nominal active poisonlength of 136 inches. The initial core loading 1 have a maximum enrichmentof 3.35 weight percent U-235. Reload fuel shall be s

' in physical designto the initial core loading and shall have a maximum radia veragedenrichment of 4.30 weight percent U-235 at any axial location.

CONTROL E EMENT ASSEMBLIES2.

5.$ .2 The reactor core shall contain 76 full-length and 13 part-lengthcontrol element assemblies.

OVQ

PALO VERDE - UNIT I 5-5 AMENDMENT NO. 84 ~, 82

DESIGN FEATURES

FUEL STORAGE

3R T Sa.a- mm mrwKOP

5. .1.1 The spent fuel storage racks are designed and shall be maintainedwith:

a. The maximum calculated k « value, including margin for uncertaintyin calculational method and mechanical tolerances, less than or equalto 0.95 with a 95X probability at a 95X confidence level when floodedwith unborated water.

b. A nominal 9.5 inches center-to-center distance between adjacentstorage cell locations.

na

5.(. 1.2 The k,« for new fuel for the first core loading stored dry in thespent fuel storage racks shall not exceed 0.98 when aqueous foam moderation isassumed.

5.).1.3 The spent fuel storage pool is organized into three regions for spentfuel storage. Fuel shall be placed in the appropriate region based on appro-priate initial enrichment and existing burnup as designated in Figure 5 jK-I:

a. Region I: Fuel shall be stored in a checkerboard (two-out-of-four) storage pattern. Fuel that qualifies to be stored inRegions I, 2, or 3, in accordance with Figure S.p'-1, may bestored in Region 1.

b.

C.

Region 2: Fuel shall be stored in a three-out-of-four storagepattern. Fuel that qualifies to be stored in Regions 2 .or 3,in accordance with Figure 5.g-:, may be stored in Region 2.

5Region 3: Fuel shall be stored in a four-out-of-four storagepattern. Only fuel that qualifies to be stored in Region 3, inaccordance with Figure S.P-1, shall be stored in Region 3.

3~RA INAG

35.(.2 The spent fuel storage pool is designed and shall be maintained toprevent inadvertent draining of the pool below elevation 137 feet — 6 inches.

~CAPAC TY

5.$ .3 The spent fuel storage pool is designed and shall be maintained with a

storage capacity limited to no more than 1329 fuel assemblies.

~ ~

PALO VERDE - UNIT I 5-6 AMENDMENT NO. 82

3FIGURE 5.$ -1

ASSEMBLY BURNUP VERSUS INITIAL ENRICHMENT

50000 4.30

~ 45000

>40000U

W 35000REGIOH 3

~ 30000C~ 25000

CQ

~20000

E 15000Q

+ 10000

REGIOH 2

REGIOH 1

5000

02.00 2.50 3.00 3.50 4.00 4.50

Initial Fnrichment, wt %5.00

CXXXZ 4/4)csaaa g/4

PALO VERDE - UNIT IAMENDMENT NO, 82

TABLE 5. 7-1

COMPONENT CYCLIC OR TRANSIENT LIMITS

mClmI

~~

C:

COMPONENT

Reactor Coolant System

LIC OR

TRANSI T LIMIT

500 system eatup and cooldown

cycles at rate < 100 F/hr.

500 pressurizer hea p andcooldown cycles at ra s< 200 F/hr.

10 hydrostatic testing cycle

480 reactor trip cycles, turbinetrip cycles, and loss of reactorcoolant flow.

200 seismic stress cycles.

l complete loss of secondarypressure cycle.

OESIGN CYCLEOR TRANSIENT

Heatup cycle - Temperature from < 70oFto > 565 F.

cooldown cycle - Temperature from > 565'Fto< 70F

Heatup cycle - Pressurizer temperaturefrom < 70 F to > 653 F; cooldown cycle-Pressurizer temperature from > 653'F to< 70'F.

Ãzrl0

RCS pressurized to 3125 psia with XIRCS temperature between l20'Fand 400'F.

Includes combinations of reactor trips 0due to operator errors, equipment mal- Z

nctions, and total loss of reactorco lant flow. 0zSubje ion to a seismic event equal to one-half th design basis earthquake (OBE).

Loss of sec dary pressure from either steamgenerator due to a complete double-endedbreak of a ste generator steam or feedwaternozzle.

TABLE 5.7-1 (Continued)

HPONENT CYCLIC OR TRANSIENT LIMITS(mC7m

,plCOMPONENT

CYCLIC R

TRANSIENT L ITOESIGN CYCLEOR TRANSIENT

200 primary systeleak test cycles

Leak test primary system at a pressureof 2250 psia at a temperature from 120'Fto 400 F.

Hain spray (less than four RCPoperating) with fluid bT > 200'F.

Auxiliary spray with fluid AT > 200'F.a

Calculate usage factor p rTable 5.7-2.

Pressurizer Spray Nozzle

hT = The difference in temperaturecorrection factor.

bT = The difference in temperatureinstrument correction factor.

zTl.0r

between the pressurizer and main ray water as adjusted by the instrument

Zbetween the pressurizer and Auxiliary ray water as adjusted by the 0

Z

(IllR7C)mI

~\

M

"m

Main Spray

NA

TABLE 5.7-2

RESSURIZER SPRAY NOZZLE USAGE FACTOR

Auxiliary Spray

N/NA

201-250251-300301-350351-400401-450451-500501-550

79004500290019001200850555

Cumulative Usage Factor

XN/NA (Main Spray)

XN/N (Aux. Spray)

Total

E N/NA =

201-250251-300301-350

1-4064 -450451 00501- 0551-60

= Cumulative Usage Factor

5000022001300

850550375225150

E N/NA =

XI

z0Ã

0z0z

ICl

Mhere:

m

C

4T = (TIDI -T229) + 60

4T = (T>0I-

T>03* or ]0q*) + 70

NA = Allowable number of spray cycle

TABLE 5.7"2 (Continued)

I

C)

N = Number of cycles in 4T range indi ated

Calculational Method:

1. The spray cycle is defined as any initiatio and termination of main or auxil jarthroughout the pressurizer spray nozzle.or aux ary spray flow

2. If the difference between pressurizer water te erature and the spray water temp0 wa er emperatureexcee'ds 200 F each spray cycle and the correspo ing temperature difference is 1 d.nce s ogge .

3. The spray nozzle usage factor shall be calculated s follows:

A. Fill in Column "N" above.

B. Calculate "N/NA" (Divide N by NA).

C. Add Column "N/NA" to find XN/NA.

EN/NA is the cumulative spray nozzle usage factor. If the cumulative usage factor jsequal to or less than 0.65 no further action is required.

4. If the cumulative usage factor exceeds 0.65, subsequent press izer spray operationshall continue to be monitored and an engineering evaluation o nozzle fatigue shallbe performed within 90 days. The evaluation shall determine tha the nozzle remainsacceptable for additional service beyond the 90 day period or sub equent sprayoperation shall be restricted so that the difference between the p essurizer watertemperature and the spray water temperature shall be limited to les than or equal to200'F when spray is operated.

z0'7D

0z0Z

"Use lower of two temperatures.

FR lNFORMAT!ONONLY

DESIGN FEATURES

INDEX

SECTION

5.1 SITE QQCe&VX.O< . ~ 0 ~ ~ e. 0 0 0 . 0 0. ~ ~ - 0 0 i e, ~ ~ 0 ~ ~

PAGE

0 ~ ~ ~ ~ 0000 ~ 0 0e ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ \ ~ ~ \ ~ ~ ~ 0 ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 00 ~ ~ 0 ~ 0 +H

~ 00 ~ ~ ~ ~ ~ ~ 0 ~ 0 ~ ~ 0 ~ ~ 00 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ 0 ~ ~ ~ 0 ~ ~ ~ ~ ~ 0 ~

?~E. EEA T AEE

?5.a1 FUEL ASSEMBLIES.............................. ~ ~ ~ ~ ~ ~ ~ 0 ~ 0 \

5.3,. 22.

CONTROL ELEMENT ASSEMBLIES.............................. 5-5,

0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~5~ 0 ~ ~ ~ ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ 0 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~5

~ ~ ~ 0 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

35. FUEL STORAGE

5.$ .1

5.g 3

5./P. 3

CRITICALITY0 ~ ~ ~ 00 ~ 00 ~ ~ 00 ~ ~ 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ eo ~ . ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

RAINAGE00 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ 0 ~ ~ 000 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~D

APACITY0 ~ ~ 0 0 ~ ~ ~ 0 ~ 0 0 0 0 0 ~ 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ 0C

5 yQS" 2,

50( $

~ ~ ~ ~ 0 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~

PALO VEROE - UNIT 2 XV

.. gnat''r" 'O~~

~ 4 - ~

'

w ~

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S-P. yE

LIST OF FIGURES

~ND X

PAGE

3.1-1

3.2-1

3.4-1

3.4-2a

3.4-2b

3.4-2c

3.4-2d

I

MINIMUM BORATED WATER VOLUHES.......'...................REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POWER

LEVEL ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ + ~ ~ ~ ~

DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFICACTIVITY LIMIT VERSUS PERCENT OF RATED THERMALPOWER WITH THE PRIHARY COOLANT SPECIFIC ACTIVITY) 1.0 pC$ /GRAM DOSE E(UIVALENT I-131..............--...REACTOR COOLANT SYSTEM PRESSURE TEMPERATURELIHITATIONS FOR LESS TMAN 8 EFPY OF OPERATION..........

REACTOR COOLANT SYSTEM PRESSURE TEMPERATURELIMITATIONS FOR 8 TO 32 EFPY OF OPERATION..............

REACTOR COOLANT SYSTEM HAXIHUH ALLOWABLE HEATUPAND COOLDOWN RATES FOR LESS THAN 8 EFPY OF

PERATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~0

REACTOR COOLANT SYSTEM MAXIMUM ALLOWABLE HEATUPAND COOLDOWN RATES FOR 8 TO 32 EFPY OF0PERATION..............................................

3/4 l-ll

3/4 2-8

3/4 4-27

3/4 4-29

3/4 4-29a

3/4 4-29b

3/4 4-29c

4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST.............. 3/4 7-26

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

SPI

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

ASSEHBLY BURNUP VERSUS INITIAL ENRICHHENT.............. ~5> +-b

PALO VERDE - UNIT 2 XIX AMENDMENT NO. 42, ~ 69

W= s P ~ = t e - a ~ '

4 "C

ST OF TABLES

307 2

4.7-1

4.7-2

4.S-1

3.8-1

MAXIMUMALLOWABLE STEADY STATE POWER LEVEL AND HAXIMUHVARIABLE OVERPOWER TRIP SETPOINT 'WITH INOPERABLE STEAMLINE SAFETY VALVES........-.... ~ ~ - ~ ~ ~ -- ~ ~ ~ ~ ~ ~ - ~ " ~ ~ -- ~ ~ ~

SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITYSAMPLE AND ANALYSIS PROGRAH...........- ..".....".SNUBBER VISUAL INSPECTION INTERVAL-"-..."."..-.".DIESEL GENERATOR TEST SCHEDULE.................... " .-.-D.C. ELECTRICAL SOURCES............................ "...

3/4 7-3

3/4 7-8

3/4 7-25a

3/4 8-7

3/4 8-11

4.8-2 BATTERY SURVEILLANCE RE(UIREHENTS.......................B 3/4.4-1 REACTOR VESSEL TOUGHNESS................................

3/4 8-12

B 3/4 4-8

6.2-1 MINIMUM SHIFT CREW COHPOSITION.................'........ 6-5

PALO VERDE - UNIT 2 XXII AMENDMENT NO. ~ -44,'S

0

I

lf

tJ

REACTOR COOLAHT SYSTEM

PRESSURIZER HEATUP/COOLDOWH LIMITS


3.4.8.2 The pressurizer temperature shall be limited to:

a. A maximum heatup rate of 200 F per hour, and

b. A maximum cooldown rate of 200'F per hour.

APPLICABILITY: At all times.

ACTION:

With the pressurizer temperature limits in excess of any of the above limits,restore the temperature to within the limits within 30 minutes; perform anengineering evaluation to .determine the effects of the out-of-limit conditionon the structural integrity of the pressurizer; determine that the pressurizerremains acceptable for continued operation or be in at least HOT STANDBYwithin the next 6 hours,and reduce the pressurizer pressure to less than500 psig within the following 30 hours.

SURVEILLANCE RE UIREMENTS

4. 4. 8. 2. l The pressurizer temperatures shall be determined to be within thelimits at least once per 30 minutes during system heatup or cooldown.

4. 4. 8. 2. 2 The spray water temperature differential shall be determinedfor use for each cycle of main spray with less than fourreactor coolan pumps operating and for each cycle of auxiliary sprayoperation.

PALO VERDE - UNIT 2 3/4 4-31

+OR INFORMATIONONI+


5.1 SITE t bc.ATX0% 6 CLCL ~ SAIC lM lh p)

~4—14e —low-popu&Won-zone-shA-l—b

5.2.1 The re tor containmen. building is a steel lined, prestressed concretebuilding of cyls rical shape, with a dome roof and having the followingdesign features:

'a ~ Nominal inside iameter = 146 feet.

b.

C.

d.

e.

Nominal inside heig

Minimum thickness of concrete floor d = 10.5 feet.

06.5 feet.

Minimum thickness of conc +~walls = 3 feet, 8 inches.

Minimum thickness of concrete f = 3 feet, 8 inches.h

f. Nominal thickness of steel liner = 0.25 i

g. Net free volume = 2.6 x 106 cubic feet.

PALO VERDE " UNIT 2 5-1

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D'ORINFORMATIONONI+

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Figure 5. 1-1Site and Exclusion Boundaries

PALO VERDE -'NIT 2

I

0

Scale ( miles )

Centerline ofConrainmenl

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P~nyPu~~~ I"'utside Exctusion AreaiIII

Ai'iENDf1ENT NO. 48

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4~ 'I

~ aaasav I ~ ala

O+

. ~.c"lr/

;I

I

ALLt~TO+

SAV

QC

~4

~ IAQQTQI

s

I ss,

~ILQCTTCAIvt ~CAIICA

lv «L

~OWC15~ VTTt

~ LACK ~ TTTTC

WC ~ 1 IICAATTAQT

r -~ C~4

OILC Tat QAQ

II~IlnVIITSQal Cas COISa a VT Iaatlasl4~4»KEY TO MAP

.::. Palo Verde, Nuclear:..:Generating Station:": BoundaryIg School

~ SirenMilepost

Paved RoadUnpaved Road4WD Road

~ o t o h- Gas Pipeline~ o~ o —Oil Pipeline

' — Power LineRailroad

Airstrip

Palo Verde Nuclear Generating StationLOW POPULATION ZONE

K4RYC,

0-5 Miles

Figure 5.1-2

PALO VERDc - Ui'T'IT P S-3 A >.TchlnMChl'r MA 8 Ct

04 "g

W ~"

. p-r

Otlsite Dose Caiculaten Manual Palo Verde Nuclear Generating Station

Fuel Building

Fuel BuilduigExhaust

Containmenl

Main SteamSupport

Structure


OperationsSupportBuilding

~ ~e.;H, ~

III

CONI

E;ONI

sr r.

I


RadwasteBuilding

ControlBuilding

Oiesel GenBuilding

r i

Elevahon of ExhaustAbove Grade

Plant Vent andCondensor VacuumFuel Building

Point

145'09'-9"


Fig 5.1.3

v r,J

lp C

ESIGN FEATURES

85. R ACTOR RE

(S,a.w- nsw~5.P.1 reactor core shall contain 241 fue1 assemblies with each fuelassembly no 1 containing 236 fuel rods or burnable poison rods clad withZircaloy-4 excep t limited substitution of fuel rods by filler rodsconsisting of Zircaloy- stainless steel may be made if justified by a cycle "

specific reload analysis. Ea el rod shall have a nominal active fuellength of 150 inches and contain a um total weight of approximately 1950grams uranium. Each burnable poison rod s have a nominal active poisonlength of 136 inches. The initial core loading 1'have a maximum enrichmentof 3.35 weight percent U-235. Reload fuel shall be ss in physical designto the initial core loading and 'shall have a maximum radial eragedenrichment of 4.30 weight percent U-235 at any axial location.

CONTRO M N ASS MB S

R5..2 The reactor core shall contain 76 full-length and 13 part-lengthcontrol element assemblies.

5.4.1

a.

e Reactor Coolant System is designed and shall be maintained:

In a dance with the code requirements specified in Section 5.2 ofthe FSAR

'allowance for normal degradation pursuant of the

applicable su illance requirements,

b. For a pressure of 25 sia, and

C. For a temperature of 650' t for the pressurizer which is

VO UM

13,900 + 300/-0 cubic feet at a nominal T,„, of 593'F.

PALO VERQE - UNIT 2 AMENQMENT NO. ~N; 69

~c)m,oA mrs,d -(wa.o/l ..t~a. Z~

DESIGN FEATURES

e4eemkeg~~ew~a-'W-be-Wee;Ae3

FUEL STORAG

R C

5.(.1.1 The spent fuel storage racks are designed and shall tainedwith: ~%4~ Lsp

The maximum calculated k,« value, including margin for uncertaintyin calculational method and mechanical tolerances, less than or equalto 0.95 with a 95X'robability at a 95X confidence level when floodedwith unborated water.


5.5.1.2 The k,« for new fuel for the first core loading stored dry in thespent fuel storage racks shall not exceed 0.98 when aqueous foam moderation isassumed.

5.$ .1.3 .The spent fuel storage pool is organized into three regions for spentfuel storage. Fuel shall be placed in the appropriate region based on appro-priate initial enrichment and existing burnup as designated in Figure 5g-l:

5a. Region I: Fuel shall be stored in a checkerboard (two-out-of-

four) storage pattern. Fuel that qualifies to be stored inRegions I, 2, or 3, in accordance with Figure G.p'-I, may bestored in Region l.

b.

C.

Region 2: Fuel shall be stored in a three-out-of-four storagepattern. Fuel that qualifies to be stored in Regions 2 or 3,in accordance with Figure 5./-1, may be stored in Region 2.

Region 3: Fuel shall be stored in a four-out-of-four storagepattern. Only fuel that qualifies to be stored in Region 3, inaccordance with Figure 5..$ -1, shall be stored in Region 3.

QRA IMAGE

8 /

5.5.2 The spent fuel storage pool is designed and shall be maintained toprevent inadvertent draining of the pool below elevation 137 feet - 6 inches.

~CAPAC TY

5.p.3 The spent fuel storage pool is designed and shall be maintained with astorage capacity limited to no more than 1329 fuel assemblies.

I—74e-components —identi-fmd-ie-Tab.

PALO YERDE — UNIT 2 5-6 AMENDMENT NO. 69

II

VPi

'c".,"

CJ c! 4.~ iOe.lJ t.cJ ~~

A

ftI'

'

yl

h

l

FIGURE 5. -1ASSEMBLY BURNUP VERSUS NITIAL ENRICHMENT

50000 4.30

~ 45000

400OO0

W 35000~5

~ 30000C

D 25000CQ

~20000

E 15000Q

~> <0000

REGION 3

'REGION 2

REGION 1

5000

02.00 2.50 3.00 3.50 4.00 '.50

Initial Enrichment, wt w5.00

CQCGD 4/4Was)cg 5/4

PALO VERDE - UNIT 2 5-6a AMENDMENT NO. 69

P

TABLE 5.7-1

COM NENT CYCLIC OR TRANSIENT LIMITS

COMPONENT


CYCLIC OR

TRANSIENT LIMIT

500 system heatup an cooldowncycles at rates < 100 hr.

DESIGN CYCLEOR TRANSIENT

Neatup cycle - Temperature from < 70 Fto > 565'F; cooldown cycle - Temperaturefrom > 565'F to- < 70'F.

C'i

500 pressurizer heatup andcooldown cycles at rates< 200'F/hr.

10 hydrostatic testing cycles.



1 complete loss of secondarypressure cycle.

Inclu qs combinations of reactor tripsdue to > erator errors, equipment mal-functions and total loss of reactorcoolant flo .

Loss of secondary pr sure from either steamgenerator due to a corn lete double-endedbreak of a steam generat r steam or feedwaternozzle.

Neatup cycle — Pressurizer temperaturefrom < 70 F to > 653'F; cooldown cycle-Pressurizer temperature from > 653'F to

70oF zRCS pressurized to 3125 psia with 0RCS temperature between 120'F

XJd 400'F.

0s Z

0Subjection to seismic event equal to one-half the design sis earthquake (DBE).

n

'0

'apl „9 /

IED

m

COMPONENT

CYCL OR

TRANSIENT I HITDESIGN CYCLEOR TRANSIENT

TABLE 5.7-1 (Continued)

COMPONENT CYCLIC OR TRANSIENT LIMITS

200 primary syst n

leak test cyclesI eak test primary system at a pressure .

of 2250 psia at a temperatrrre from 120'Flo 400 F.

CflI.0)

Main spray (less than four RCP

operating) with fluid hT > 200'F.m

Pressurizer Spray Nozzle Calculate usage factor erTable 5.7-2.

hT = The difference in temperature betweencorrection. factor.

hT = The difference in temperature betweeninstrument correction factor.

Xl

zRrrxiliary spray wit.lr flrrid hT. > 200"F. 'Tl

o

t'e pressurizer and main ray water as adjusted by the instrument

Ztire lrressrrrizer arrd Ruxiliary ray water as adjusted by tire 0z

-TABLE 5.7-2

PRESSURI R SPRAY NOZZLE USAGE FACTOR

Hain Spray Auxiliary Spray

NA N N/NA A N/NA

201-250251-300301-350351-400401-45045]-500501-550

790045OO290019003200

0!)0555

Cumu1ative Usage Factor

}.N/NA (Hain Spray)

XN/N„ (Aux. Spray)

Tota1

X N/NA =

1-25025 -'100301 3")03)5J- (IO401-4. 04 ') (

- ')(I50 I- b)50

55 i-600

= Cumulalive Usage FacLor

50000220013000!)0550(/!)22!)150

X N/NA =

0XJ

R033

0z0

1

(0

'~/ E ~

TA E 5.7-2 (Continued)

mC7m

C:

Where:

a 101 229

hT = (T101—

T103* " 104"

NA = Allowable number of spray cycles

N = Number of cycles it) bl range indicaLed


1. The spray cycle is defined as any initiation and termina ion of main or auxiliary spray flowthroughout the pressurizer spray nozzle.

2. If the difference between pressurizer water temperature an( the spray water temperatureexceeds 200'F each spray cycle and Lhe corresponding Leoqi«ra ure diif«rence is logg«d.

3. The spray nozzle usage factor shall h«. calculated as fol'low:


B. Calculate "N/NA" (Divide N by NA).


XN/N is the cumulative spray nozzle usag« factor. If l.he cumulative isage factor isequal to or less than 0.65 no further action is require~i.

4. If the cumulative usage fact. or exceeds 0.65, iibsequ«nt pressu> izer spray operationshall continue to be monitored and an engineering evaluation of nozzle fat'gue shallbe performed within 90 days. The evaluation shall determine that the nozzl remainsacceptable for addiLiona'I service beyond Lhe 90 day period or subsequent sproperation shall be restricted so that Lhe difference between the pressurizer atertemperature and Lhe spray waL«r L«mperaLur e shall be limited Lo less than or e ual to200'F when spray is operated.

Xl

. z033

0z0z


t'gv

tg J

Q tt

0'1

~OR INFORMATIONONO

INDEX

DESIGN FEATURES

SECTION PAGE

5.1 SITE Lbcmv r.ow~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 ~ 4 ~ ~ ~ ~

2.5. REACTOR CORE

5.(. 2 CONTROL ELEMENT ASSEMBLIES..............................

z.5.$.1 FUEL ASSEMBLIES.........................'..............:. 5-3-i

5-5; \

35. FUEL STORAGE

5.(.15..25..3

CRITICALITY.................RAINAGE~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~0

APACITYo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~C

5-% i5"K 2.

5"5 Z

PALO VERDE - UNIT 3 XV

LIST OF FIGURES

NDEX

~AG

3.1-1

3.2-1

3.4-1

3.4-2a

3.4-2b

3.4-2c

'3.4-2d

4.7-1

MINIMUM BORATED WATER VOLUMES..........................REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POWERLEVEL ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

DOSE EQUIVALENT I-131 PRIHARY COOLANT SPECIFICACTIVITY LIMIT VERSUS PERCENT OF RATED THERMALPOWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY> 1.0 pC1/GRAM DOSE EQUIVALENT I-131...................REACTOR COOLANT SYSTEM PRESSURE TEHPERATURELIMITATIONS FOR LESS THAN 8 EFPY OF OPERATION..........

REACTOR COOLANT SYSTEM PRESSURE TEMPERATURELIMITATIONS FOR 8 TO 32 EFPY OF OPERATION..............

REACTOR COOLANT SYSTEM MAXIMUM ALLOWABLE HEATUPAND COOLDOWN RATES FOR LESS THAN 8 EFPY OFPERATION..................0

REACTOR COOLANT SYSTEM MAXIMUM ALLOWABLE HEATUPAND COOLDOWN RATES FOR 8 TO 32 EFPY 'OF

0 PE RAT ION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

'

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..............

3/4 l-ll

3/4 2-8

3/4 4-27

3/4 4-29

3/4 4-29a

3/4 4-29b

3/4 4-29c

3/4 7-26

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

5 j(-I3

ASSEMBLY BURNUP VERSUS INITIAL ENRICHMENT.............. 5-+3

PALO VERDE — UNIT 3 XIX AMENDMENT NO. 88, M ) 54

ST OF TABLES

3 ~ 7 2

4.7-1

4.7-2

4.8-1

3.8-1

MAXIMUMALLOWABLE STEADY STATE POWER LEVEL AND MAXIMUMVARIABLE OVERPOWER TRIP SETPOINT WITH INOPERABLE STEAMLINE SAFETY VALVES.......--.--"---.-.-" --"- ~ "".~ ~ ~

SECONDARY COOLANT SYSTEH SPECIFIC ACTIVITYSAMPLE AND ANALYSIS PROGRAM» ~ » ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

SNUBBER VISUAL INSPECTION INTERVAL..- - - ".".. - " - - -. -"DIESEL GENERATOR TEST SCHEDULE..... ".....-.-.--.-------D.C. ELECTRICAL SOURCES............."...........""".

4.8-2 BATTERY SURVEILLANCE REQUIREMENTS.......................

B 3/4.4-1 REACTOR VESSEL TOUGHNESS................................

3/4 7-3

3/4 7-8

3/4 7-25a

3/4 8-7

3/4 8-11

3/4 8-12

B 3/4 4-8

6.2-1 MINIMUM SHIFT CREW COMPOSITION.......................... 6-5

PALO VERDE - UNIT 3 XXII AHENDHENT NO. ~, 44

REACTOR COOLANT SYSTEM

PRESSURIZER HEATUP/COOLDOWN LIMITS


3.4.8.2 The pressurizer temperature shall be limited to:

a. A maximum heatup rate of 200~F per hour, and

b. A maximum cooldown rate of 200'F per hour.

APPLICABILITY: At al 1 times.

ACTION:

With the pressurizer temperature limits in excess of any of the above limits,restore the temperature to within the limits within 30 minutes; perform anengineering evaluation to determin. the effects of the out-of-limit conditionon the structural integrity of the pressurizer; determine that the pressurizerremains acceptable for continued operation or be in at least HOT STANDBY

within the next 6 hours and reduce the pressurizer pressure to less than500, psig within the following 30 hours.

SURVEILLANCE RE UIREMENTS

4.4.8.2. 1 The pressurizer temperatures shall be determined to be within thelimits at least once per 30 minutes during system heatup or cooldown.

4.4.8.2.2 The spray water temperature differential shall be determinedfor usereactor coolantoperation.

for each cycle of main spray with less than fourpumps operating and for each cycle of auxiliary spray

PALO VERDE - UNIT 3 3/4 4-31\

)R INFORMATIONONION.


5.1 'ITE c cd ~ VDwiCR ~y

PALO VERDE " UNIT 3 5-1

FORMATION ON

'uckeye-SalomeRoad

Winte rsburgRoad

Unit 1

MetTower

Unit 2

Unit 3

North

~ k ~

Legend

Centerline ofContainment

PropertyPurchasedExclusionBoundary

Eiliot Road(@dard Road)

Figure 5. 1-1Site and Exclusion Boundaries

PALO VERDE - UNIT 3 5-2

Sca:e ( miles )

Site Boundary

Prcoeity Purchased lOutside Ex"'usion Areai

l

AMEHDMEHT HO. 3~

4

)R INFORMATIONONGra "nic cale in Miles .

0 1 2 3 4 5

Ittaftaalft otIooolro4totef~atria fttffra

~IJC

L.oatT, \IC4 'C

TOIIOAAII

5 5

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fof V~

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~ S

'a.'ao I~ t 444 OICISIC

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fIat Oat42% TV~ T

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tor ISO

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OALO t51DS IIILLS

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~ OIA Itot

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5

5

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II rv ~

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~ aaa t OCOSwS

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or /

t~ MCm OSIS

totootaarI'IM

4~ ro

14$ 5ATActrA I Oa

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~4444\~4Qaot 4toaa

I444 I0 tl~ ofo I

~4\~ 4t ~ TaTT ~ ar

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,4~LAC1 ~ CITS 5

/OISOO SCOCCICTAOC

e

AOLAISTOII~C il I'.

~ +SO~t r OILS,aI'

OIIT1$~ itTT5

for5

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444 4ICOTSIrr ttLCASLAAAA

t /J ~)i q

~jr''

A'SIIC OofOf

~ \ ~ IIO 4 ottt444 CAS COII44ff AOCL441

KEYTO MAP

Paved RoadUnpaved Road

.4VlO RoadGas PipelineOil PipelinePower LineRailroad

Airstrip

IT Palo Verde Nuclear:: Generating Station!: Boundary

II School

~ Siren~ t,tilepost

Palo Yerde Nuclear Generating StationLOW POPULATlON ZONE

0-5 Miles

FI ure 5.1-2

PALO ""."".""- - '"'IT 3I Io~ ~ ICSIIr~ CV ~ a>

Ottsite Dnse Catcutaten Manual Palo Verde Nuclear Generating Station

Fuel Building

Fuel BuildingExhaust

Main SteamSupport

Containment Structure


OperationsSupportBuilding

.;bj4

leisC

i-'

corri

-q I

I—ro);r- I

l?r 0 ~

sr r.

(:OHt


RadwasteBuilding

Control Diesel Gen6uitding Building

EXltAUST POINTS ttEY PLAN

Elevation of Exhaust PointAbove Grade

Plant Vent andCondensor Vacuum

145'uel

Building 109'-9"


Fig 5.t.3

DESIGN FEATURES

25. R ACTOR CORE

FUEL ASSEMBLIES '~~ ~~ ~<'M~q.R C

5'..3,.l reactor core shall contain 241 fuel assemblies with each fuelassembly nor ly containing 236 fuel rods or burnable poison rods clad withZircaloy-4 excep at limited substitution of fuel rods by filler rods con-sisting of Zircaloy- . stainless steel may be made if justified by a cyclespecific reload analysis. stitution of up. to a total of 80 fuel rods cladwith zirconium-based alloys ot than Zircaloy-4 may also be made in two fuelassemblies for in-reactor performan 'aluation purposes during Cycles 4, 5and 6. Each fuel rod shall have a nomin active fuel length of 150 inches andcontain- a maximum total weight of approximate 1950 grams uranium. Eachburnable poison rod shall have a nominal active p

' length of 136 inches.The initial core loading shall have a maximum enrichme of 3.35 weight percentU-235. Reload fuel shall be similar in physical design to initial coreloading and shall have a maximum radially averaged enrichment o .30 weightpercent U-235 at any axial location.

CONTROL ELEMENT ASSEMBLIESz

5.3,.2 The reactor core shall contain 76 full-length and 13 part-lengthcontrol element assemblies.

~VP

.PALO VERDE - UNIT 3

1t

5-5 AMENDMENT NO. 8—, M, 46-, 54

DESIGN FEATURES

~ ~

5. FUE STO G

5..1 CRITICA Y +CZ CZ ~~ ~pa~ MP

5.6. l. I The spent fuel storage racks are designed and shall be maintainedwith:

a. The maximum calculated k,« value, including margin for uncertaintyin calculational method and mechanical tolerances, less than or equalto 0.95 with a 95X probability at a 95X confidence level when floodedwith unborated water.


35.||.1.2 The k,« for new fuel for the first core loading stored dry in thespent fuel storage racks shall not exceed 0.98 when aqueous foam moderation isassumed.

35.6.1.3 The spent fuel storage pool is organized into three regions for spent.fuel .storage. Fuel shall be placed in the appropriate region based on appro-priate initial enrichment and existing burnup as designated in Figure 5.8-1:

5a. Region 1: Fuel shall be, stored in a checkerboard (two-out-of-

four) storage pattern. Fuel that qualifies to be stored inRegions 1, 2, or 3, in accordance with Figure 5.jf-l, may bestored in Region 1. 5

'.

C.

Region 2: Fuel shall be stored in a three-out-of-four storagepattern. Fuel that qualifies to be stored in Regions 2 or 3,in accordance with Figure 5.$-1, may be stored in Region 2.

5'egion3: Fuel shall be stored in a four-out-of-four storage

pattern. Only fuel that qualifies to be stored in Region 3; inaccordance with Figure 5.P-I, shall be stored in Region 3.

~DRA I NAG

5.g.2 The spent fuel storage pool is designed and shall be maintained toprevent inadvertent draining of'the pool below elevation 137 feet - 6 inches.

CAPACITY,3

5.g.3 The spent fuel storage pool is designed and shall be maintained with astorage capacity limited to no more than 1329 fuel assemblies.

~ ~

PALO VERDE - UNIT 3 5-6 AMENDMENT NO. 54

FIGURE 5.5,-1ASSEMBLY BURNUP VERSUS INITIAL ENRICHMENT

50000 4.30

~ 45000

~4oooo

W 35OOO

~I

D 30000C

~ 25000CQ

~2oooo

E isooo

10000

REGION 3

REGION 2

REGION 1

5000

02.00 2.50 3.00 3.50 4.00

Initial Enrichment, wt %4.50 5.00

Qanao 4/4~@ass g/g

PALO VERDE - UNIT 3 5-6a AMENDMENT NO. 54

TABLE 5.7-1

COM NENT CYCLIC OR TRANSIENT LIMITS

COMPONENT


CYCLIC R

TRANSIENT LI T

500 system heat and cooldowncycles at rates < 1004F/hr.

500 pressurize heatu andcooldown cycles at rate.< 200'F/hr.

-10 hydrostatic testing cycles.



1 complete loss of secondarypressure cycle.


Heatup cycle - Temperature from < 70~Fto > 565 F, cooldown cycle Temperaturefrom > 565 F to < 70 F.

Heatup cycle - Pressurizer temperaturefrom < 70'F to > 653'F; cooldown cycle-Pressurizer temperature from > 653 F to< 700F.

RCS pressurized to 3125 psia with.RCS temperature between 120 F

and 400~F.

Includes combinations of reactor tripsdue to operator errors, equipment mal-

nctions, and total loss of reactorco lant f'low.

Subje tion to a seismic event equal to one-half th design basis earthquake (OBE).

Loss of se ondary pressure from either steamgenerator d to a complete double-endedbreak of a st am generator steam or feedwaternozzle.

Xl

R0

~ Q

0z0z

TAB E 5.7-1 (Continued)

COMPONENT CY IC OR TRANSIENT LIMITS

COMPONENT

CYCLIC OR

TRANSIENT LIHIT

=- 200 primary systemleak test cycles


Leak test primary system at a pressureof 2250 psia at a temperature from 120 Fto 400 F.

Pressurizer Spray Nozzle Calculate usage factor perTable 5.7-2.

bT —.— The difference in temperature between the pressurizercorrection factor.

hT = The difference in temperature between the pressurizerinstrument correction factor.

Main spray (less than four RCP

operating) with fluid hT > 200'F.m

Auxiliary spray with fluid hT > 200'F.a

zTl0Xl

and main s ray water as adjusted by the instrument 0zand Auxiliary spray water as adjusted by the Qz

TABLE 5.7-2

PRESSU ZER SPRAY NOZZLE USAGE FACTOR

Hain Spray Auxiliary Spray

"m

201-250251-300301-350351-400401-450451-500501-550

?9004500290019001200

850555

Cumulative Usage Factor

N/NA

201-250251-300301-350351"400401-45Q451-50Q

01-5501-600

5000022001300

850550375225150

X N/NA =

N/NA

x0

Qz0z

X N/NA (Hain Spray)

X N/NA (Aux. Spray)

Total = Cumulative Usage Factor

Where:

TA LE 5.7-2 (Continued)

hT =(TRODI

-T229) + 60

m 101 103" 104*)

NA = Allowable number of spray cycles

N = Number of cycles in bT range indicat


1. The spray cycle is defined as any initiation nd termination of main or auxiliary spray flowthroughout the pressurizer spray nozzle.

2. If the difference between pressurizer ~ater tern erature and the spray water temperatureexceeds 200'F each spray cycle and the correspon ing temperature difference is logged.

3. The spray nozzle usage factor shall be calculated as follows:


B. Calculate "N/N„" (Divide N by N ).


XN/N is the cumulative spray nozzle usage factor. If he cumulative usage factor isequal to or less than 0.65 no further action is required

z0g3

I

0z0r.

4. If the cumulative usage factor exceeds 0.65, subsequent p essurizer spray operationshall continue to be monitored and an engineering evaluati n of nozzle fatigue shallbe performed within 90 days. The evaluation shall determin that the nozzle remainsacceptable for additional service beyond the 90 day period f subsequent sprayoperation shall be restricted so that the difference between the pressurizer watertemperature and the spray water temperature shall be limited o less than or equal to200 F when spray is operated.


5.0 DESIGN FEATURES

5.1 SITE LOCATION The Palo Verde Nuclear Generating Station is located in Maricopa County,Arizona, approximately 50 miles west of the Phoenix metropolitan area. The site is comprised ofapproximately 4,050 acres. Site elevations range from 890 feet above mean sea level at the southernboundary to 1,030 feet above mean sea level at the northern boundary.. The minimum distance froma containment building to the exclusion area boundary is 871 meters.

5.2 REACTOR CORE

FUEL ASSEMBLIES

5.2.1 The reactor core shall contain 241 fuel assemblies. Each assembly shall consist of a matrixof Zircaloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uraniumdioxide (UO,) as fuel material. Limited substitutions of Zirconium alloy or stainless steel fillerrods for fuel rods, in accordance with approved applications of fuel rod configurations, may beused. Fuel assemblies shall be limited to those fuel designs that have been analyzed withapplicable NRC staff approved codes and methods and shown by tests or analyses to complywith all fuel safety design bases. A limited number of lead test assemblies that have notcompleted representative testing may be placed in non-limiting core regions. Other claddingmaterial may be used with an approved exemption.

CONTROL ELEMENT ASSEMBLIES

5.2.2 The reactor core shall contain 76 full-length and 13 part-length control element assemblies.

5.3 FUEL STORAGE

5.3.1 CRITICALITY

5.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum radially averaged U-235 enrichment of 4.30weight percent;

b. k,„< 0.95 if fully flooded with unborated water, which includes an allowance foruncertainties as described in Section 9.1.2 of the UFSAR.

t

c. A nominal 9.5 inch center-to-center distance between adjacent storage celllocations.

PALO VERDE - UNIT 5-1

5.3.1.2 The spent fuel storage pool is organized into three regions for spent fuel storage. Fuelshall be placed in the appropriate region based on appropriate initial enrichment andexisting burnup as designated in Figure 5.3-1:

a. Region 1: Fuel shall be stored in a checkerboard ( two-out-of- four ) storagepattern. Fuel that qualifies to be stored in'Regions 1, 2, or 3 in accordance withFigure 5.3-1, may be stored in Region 1.

b. Region 2: Fuel shall be stored in a three-out-of-four storage pattern. Fuel thatqualifies to be stored in Regions 2 or 3, in accordance with Figure 5.3-1, may bestored in Region 2.

c. Region 3: Fuel shall be stored in a four-out-of-four storage pattern. Only fuel thatqualiTies to be stored in Region 3, in accordance with Figure 5.3-1, shall be storedin Region 3.

5.3.1.3 The new fuel storage racks are designed and shall be maintained with:1

a. Fuel assemblies having a maximum radially averaged U-235 enrichment of 4.30weight percent;

b. k,„< 0.95 if fully flooded with uriborated water, which includes an allowance foruncertainties as described in Section 9.1.'1 of the UFSAR;

c. k,„< 0.98 if moderated by aqueous foam, which includes an allowance foruncertainties as described in Section 9.1.1 of the UFSAR; and

d. A no'minal 17 inch center-to-center distance between fuel assemblies placed in

the storage racks.

DRAINAGE

5.3.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent drainingof the pool below elevation 137 feet 6 inches.

CAPACITY

5.3.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited

to no more than 1329 fuel assemblies.

PALO VERDE - UNIT „ 5-2

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Design Features4.0

4.0 DESEGN FEATURES

I'.1Site Location [Text description of the site 1ocation.j "/

4.2 Reactor Core

4. 2. 1 Fue1 Assemblies2R(

The reactor sha11 contain tMj fue1 assemb1ies.'ach assemblyshall consist of a matrix of pirca11oy or ZIRLOj fuel rods withan initial composition of natural or slightly enriched uraniumdioxide (UO ) as fuel material. Limited substitutions ofzirconium aI1oy or stain1ess stee1 fi11er rods for fuel rods. inaccordance with approved applications of fuel rod configurations.may be used. Fuel assemblies shall be limited to those fueldesigns that have been analyzed with applicable NRC staff approvedcodes and methods and shown by tests or analyses to comply withall fuel safety design bases. A limited number of lead testassemblies that have not completed repreqentative testing may beplaced in nonlimiting core regions. Co44~~ ~4~k4'~~~ ~~k~~i~k~ay 'tea. NK~h ~~44 ~~ ~imspo~C h ~M~qriCWu

4.2. 2 Control Rod Assembli es7g E'~is(mph ~~ ia (~4-+0

The reactor core shall contain I 9@ control element assemblies(CEAs). t~ ~tfrte 344.%$

4.3 Fuel Storage

4.3.1 ~Citi 11t

4.3. 1. 1 The spent fuel storage racks are designed and shalil bemaintained with:

Fuel assemblies having a maximum U-235 enrichmentof [M3 weight percent;il 36k « ~ 0.95 if fully flooded with unborated water.which includes an allowance for uncertainties asdescribed in [Section ~ of the~]:u|-s~

(continued)

CEOG STS 4 '-1 Rev 1, 04/07/95

Design Features4 0


4.3 Fuel Storage

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(continued)

[c. A nomina1 53 inch center to center distancebetween

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[d. A nomina1 [10.43 inch center to center distancebetween fuel assemblies placed in [the low densityfue1 storage racks3:3

[e. New or partia'l1y spent fuel assemblies with adischarge burnup in the "acceptable range" ofFigure [3.7. 17-13 may be a11owed unrestrictedstorage in [either] fuel storage rack(s); and]

[f. New or partially spent fuel assemblies with adischarge burnup in the "unacceptable range" ofFigure [3.7.17-1] will be stored in compliance withthe NRC approved [specified document containing theanalytical methods. title. date, or specificconfiguration or figure],3

4.3. 1.2 The new fuel storage racks are designed and shall bemaintained with:

Fuel assemblies having a maximum U-235 enrichmentof [ ~ weight percent;

4 EO

k « ~ 0.95 if fully flooded with unborated water,which includes an allowance for uncertainties asdescribed in [Section ~ of the FSAA3;

k,« < 0.98 if moderated by aqueous foam. whictiincludes an allowance for uncertainties asdescribed in [Section ~ of the FSAR]: andops~A nominal inch center to center distancebetween fuel assemblies placed in the storageracks.

4.3.2 Oraina<re

The spent fuel storage pool is designed and shall be maintained toprevent inadvertent draining of the pool below elevation ~t].

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(continued)

CEOG STS 4.0-2 Rev 1, 04/07/95

Oesign Features4.0

4. 0 .OES IGN FEATJRES

4.3 Fuel Storage (continued)

4.3.3 ~Ca acit

The spent fue1 storage pool is designed and shall be maintainedwith a storage capacity limited to no more than I:ISQj fuelassemblies.

CEOG STS 4.0-3 Rev 1. 04/07/95

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nuclear regulatory commission · 2018. 7. 31. · l ist of figures index page 3.1-1 3.2-1 3.4-1...

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