ML17328A931

Proposed Tech Specs Reflecting marked-up Changes Re Spent Fuel Pool During Unit 2 Cycle 9 Operation

ML17328A931
Person / Time
Site:	Cook
Issue date:	02/15/1991
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17328A929	List: ML17328A928 ML17328A930 ML17328A931
References
NUDOCS 9102250133
Download: ML17328A931 (24)

Text

ATTACHMENT 4 TO AEP:NRC:1071N EXISTING TECHNICAL SPECIFICATIONS PAGES MARKED-UP TO REFLECT PROPOSED CHANGES DONALD C.

COOK NUCLEAR PLANT UNITS 1 AND 2 9'102250233 PDR ADOCKK 05000315 PDR

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Ce Za accordance vith the code requirements specified in Section 4.1.C yith allovance for normal degradation pursuant to th>>

applicable

$~eillance Requirements, For a pressure of 2485 psig 0

0 Por a temperature of 6SO P, except tor the preaaurixer vhich ia C40 Pe VOLDHE 5.4 '

5.5 The total contained volume of tho roacto$ coolant system ia 12, 612

+ 100 cubic feet at a nominal T of 70 P.

avg EMERCENCY CORE COOLIVQ SYSTEMS 5.5.1*

The emergency core cooling systems are designed and shall bo maintained in accordance vith the original design provisiona contained in Section 6.2 of the pSAR vith allovance for normal degradation pursuant to tho appl,icable Surveillance Requirements.

5. 6 FUEL STORAGE CRITICALITY -'PENT FUEL e

5.6.1.1:

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

a.

A k <<eq ivalent to 1.ass than 0:5 vhen flooded vith unborated

vater, b

~

A nominal 10,5 inch center-to-cen:er distance betveen fuel assemblies placed in the storage racks.

4%/4FR7 R c.

1.

h separate region vithin the spent fuel storage racks (defined as Region 1.) shall be established

=or storage of Westinghouse

ue 4

~ MSGR 6 CVl The boundezy beeveen the RedionSl

".eneioned ebove tee~HL

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shall be such that the shall be carried into Regio in Figurc 5.6-1.

storage requirement 2 by, at least, one rov as shovn

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COOK NUCLEAR PLANT - UNIT 1 5-5 AMENDMENT NO R~bb.

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DESI'XLTTHtXS tuel atored in the spent fuel storage racks shall have

~ max~

aCe&al fuel assembly enrichment aa follon:

a 4t Hasid%

Nominal tuel Aaaeably Enrichment 4 235

1) Veatinghouse 15 x 15 STD 15 x 15 OFA

2) Exxon/AHF

- 15 x 15 4.95

3. 50

3) Vestinghouse 17 x 17 STD 17 x 17 OFA 17 x 17 VS 4,95

4) Exxon/ANF 17 x 17 4,23 CRITICALITY-NEV FUEL 5.6.2.1 The ncv fuel pit storage racks are designed and shall be maintained vt.th a nominal 21 inch ccntcr-to-center distance betveen nev fuel assemblies such that k f vill not exceed 0.98 vhcn fuel asscmbli.es are placed in the pit cff and aqueous oam moderation i.s assu.ed.

5.6.2.2 Fuel stored 'n the ncv f cl storage ra=..s shall have a maximum nominal fuel assembly enrich.=cnt as follovs; Naximum No=.nal Fuel Assembly Enrichment Vt. \\ 235

1) Vcstinghousc 1.5 x 15 STD 15 x

15 OFA

4. 55

2) Exxon/ANF 15 x 15

3. 50

3) Vcsti.nghouse 17 x 1.7 STD 17 x 17 OFA 17 x 17 VS 4.55

4) Exxon/ANF 17 x 17 4.23 DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent drai.ni.ng of thc pool belov elevation 629'4".

COOK NUCLEAR PLANT - UNIT 1 AMENDMENT NO.

6

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C 4 aN 't 1 storage 1 is disig ed and sh il be mi tai ed vith a storage cap city i~ted to no more th n 2050 fuel assemblies.

5 7

SEISMIC C~SIPIChTIOH 5 7,]

noae structuree, systems and components in the PS'hall be designed and maintained to contained in the TSAR vith ellovance for normal applicant Surreillance Requirements, identified aa Category I Items original design provisions degradation pursuant to the

5. I NETEOROLOCICAL TOVER LOChTION 5.8.1 The meteorological tover shall be located as shovn in Figure 5.1-1.

5.9 COMPONENT CYCLIC OR TRANSIENT LIMIT

+Pl 5,9.1 The components identified in Table 5.9-1 are designed and shall be.

maintained vithin the cyclic or transient limits of Table 5.9-1.

V COOK NUCLEhR PEDANT - UNIT h.'KNDNENT NO.

1

4 1

~

TADLE 5.9-1 COHPONENT CYCLIC OR TRANSIENT LIHITS COHPONENT Reactor Coolant Systea CYCLIC OR TRANSIENT LIHIT 200 heatup cycles at

< 100'F/hr and 200 cooldown cycles at

< 100 F/hr (pressurizer cooldown at

< 200 F/hr).

80 loss of load cycles.

40 cycles of loss of offsite A.C. electrical power.

SO cycles of loss of flow in one reactor coolant loop.

400 reactor trip cycles.

200 large step decreases in load.

DES IlaN CYCLE OR TRANSIENT lleatup cycle - T frota < 200'F hr>.F.

Cooldown cycle - T froe > 5i7'F to

< 200'F Hlthout iasediate turbine or reactor trip.

Loss of offsite A.C. electrical power source supplying the onslte Class lE distribution systea.

Loss of only one reactor coolant pump.

lOOX to OC of RATEO TIIEHHAL PNER.

100K to 5X of RATEO TllERHAL POHER with steaa duep.

TABLE 5.9-1 LQHPONENT CYCLIC OR TRANSIENT LIMITS COHPONENT I(eactor Coolant System CYCLIC OR TRANSIENT LIHIT l a@in reactor coolant pipe break.

Operating Uasis Eartlviuakes 50 leak tests.

5 hydrostatic pressure tests DESIGN CYCLE OR TRANSIENT Ureak in a reactor coolant pipe

> 6 inches equivalent diameter.

400 cycles - 20 earthquakes of 20 cycles each.

I'ressurlzed to 2500 psia Pressurized to 3I07 pslg.

Secondary System l steam line break 5 hydrostat,ic pressure tests Break in a steam line > 5.5 inches equivalent dl arne ter.

Pressurized to l356 psig.

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5,4,2 The tal vater and steam volume of the reactor coolant ayate< ia 12,C12 + 100 cubic feet as a nominal T of 70 F.

5.5 LOOICAL TOWING LOCATION 5.5.1 Thi aateorologica]

cover shall be located as shovn oa Figure 5.1-1.

5,6 FOIL STORACE CRITICALITY SPENT FUEL 5.6,1.1 The spent fuel storage racks are designed and shall be maintained vith:

ae A K equivalent to less than 0.95 vhen flooded vith eff unborated vater, A nominal 10.5-inch center-to-center distance betveen fuel assemblies, placed in the storage racks.

c, 1.

A separate region vithin the spent fuel storage rac3cs (defined as Region

1) shall be established for storage of Vestinghouse fuel Io ce array va INSET

~A,S The boundary betveen the Region5'entioned above ea4-oh+

~ L shall be such that the storage requirement g shall be castled into Region 2 b:

at least, one too as sheen in F'gure 5.6-1.

5.6.1.2 Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as follovs:

Descri tion Maximum Nominal Fuel Assembly Enrichment Vt.

'4 235

1) Vestinghouse

2) Exxon/ANF

3) westinghouse 15 x 15 STD 15 x 15 OFA 15 x 15 17 x 17 STD 17 x 17 OFA 17 x 17 V5

4. 95 3.50 4.95

4) Exxon/ANF 17 x 17 4.23 COOK NUCLEAR PLANT - UNIT 2 5-5 ANENmZNT NO. 5 nMS

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lÃ5F PAT, 5.4.2 1 ~ nev f941 pit storage r ha are deailned and shall be aatnta ed with + eainal 21 inch ceater-to-center diatance betnen ner fuel bliea auch that I vill not exceed 0.90 rhea fuel aaaeRbliea are off placed in the pit and aqueous fora moderation ia aaaaaed.

5,6,2.2 tuel stored ia the ner fuel storage racks ahall han a aaxima noajnal fuel aaseably enrichment aa follow;

1) Vestinghouse 15 x 15 STD 15 x 15 OFA Maximum Nominal tuel Aaaeably Enrichment Vt. \\ 235 4.55

2) Exxon/ANF 15 x 15 3.50

3) Vestinghous ~

17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.55

4) Exxon/ANF 17 x 17 4.23 DRAINAGE 5.6.3 The spent fuel storage pool is designed and '"..all be maintained to prevent inadvertent draining of the pooL belov elevation 629'4".

CAPACITY 5.6.4 The spent fuel storage pool is designed and sh~all be maintained vit a storage capacity limited to no more than 2050 iuei assemblies.

5.7 CO'.iPONENT CYCLIC OR TRAVSIEVT LI'.iIT 5.7.1 The components identified in Table 5.7-1 are desi.gned and shall be.

maintained vithin the cyclic or transient limits of Table 5.7-1.

j COOK NUCLEAR PLANT - UNIT 2 5-6 A.'KNDMENT NO.,

1

V 0

0

4 EP COHPONENT Reactor Coolant System TABLE 5.7-1 COHPONENT CYCLIC OR TRANSIENT L IHITS CYCLIC OR TRANSIENT LIHIT 200 heatup cycles at

< 100'F/hr and 200 cooldown cycles at

< 100 F/hr (pressurizer cooldown at

< 200'F/hr).

80 loss of load cycles.

40 cycles of loss of offsite A.C. electrical power.

80 cycles of loss of flow in one reactor coolant loop.

400 reactor trip cycles.

200 large step decreases in load.

p

'I DESI(iN CYCLE OR TRANSIENT Ileatup cycle - T from < 200'F to

> 547'F.

CooTdown cycle -

T from > 547'F to

< 200 F.

Without immediate turbine or reactor trip.

Loss of offsite A.C. electrical power source supplying the onsite Class lE distribution system.

Loss of only one reactor coolant pump.

100K to OX of RATED TilERHAL POWER.

lOOX to 5X of RATED TllERHAL POWER with steam dump.

V I) 0

7 Thli~LE 5. -i {Conl inured rn~voNLNT CYCLIC OR TRRISIENT LiwiTS COMPONENT Reactor Coolant System Secondary System CYCLIC OA TRRNSIENT LllilT 1

mackin reactor coolant pipe break.

Operating Oasis Earthquakes 50 leak tests.

5 hydrostatic pressure tests 1

steam line break 5 hydrostatic pressure tests nCSlrN CYCLE OR TRR[ISIENT Break in a reactor coolant. pipe 6 inches equiva)ent diameter.

400 cyc I es - 20 earthquakes o f 20 cycl es each.

Pressurized to 2500 psia Pressurized to 3107 psig.

Break in a steam line

> 5.5 inches equivalent diameter.

Pressurized to 1356 psig.

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