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 ADOCK K 05000315 PDR

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

applicable $ ~eillance Requirements,

b. For a pressure of 2485 psig 0 0 Ce Por a temperature of 6SO P, except tor the preaaurixer vhich ia C40 Pe VOLDHE 5.4 ' The total contained volume of tho roacto$ coolant system ia 12, 612

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

avg 5.5 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.

c. 1. h separate region vithin the spent fuel storage racks (defined 4%/4FR7 R 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 storage requirement shall be carried into Regio 2 by, at least, one rov as shovn in Figurc 5.6-1.

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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 4.95 15 x 15 OFA

2) Exxon/AHF - 15 x 15 3. 50

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

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 and aqueous cff f vill not exceed 0.98 vhcn fuel asscmbli.es are placed in the pit 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 4. 55 15 x 15 OFA

2) Exxon/ANF 15 x 15 3. 50

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

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

5. I NETEOROLOC ICAL TOVER LOChTION

+Pl 5.8.1 The meteorological tover shall be located as shovn in Figure 5.1-1.

5.9 COMPONENT CYCLIC OR TRANSIENT LIMIT 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

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TADLE 5.9-1 COHPONENT CYCLIC OR TRANSIENT LIHITS CYCLIC OR DES IlaN CYCLE COHPONENT TRANSIENT L IHIT OR TRANSIENT Reactor Coolant Systea 200 heatup cycles at < 100'F/hr lleatup cycle - T frota < 200'F and 200 cooldown cycles at hr>.F.

< 100 F/hr (pressurizer cooldown Cooldown cycle - T froe > 5i7'F at < 200 F/hr). to < 200'F 80 loss of load cycles. Hl thout iasediate turbine or reactor trip.

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

SO cycles of loss of flow in one Loss of only one reactor reactor coolant loop. coolant pump.

400 reactor trip cycles. lOOX to OC of RATEO TIIEHHAL PNER.

200 large step decreases in load. 100K to 5X of RATEO TllERHAL POHER with steaa duep.

TABLE 5.9-1 LQHPONENT CYCLIC OR TRANSIENT LIMITS CYCLIC OR DESIGN CYCLE COHPONENT TRANSIENT L IHIT OR TRANSIENT I(eactor Coolant l a@in reactor coolant pipe break. Ureak in a reactor coolant pipe > 6 inches System equivalent diameter.

Operating Uasis Eartlviuakes 400 cycles - 20 earthquakes of 20 cycles each.

50 leak tests. I'ressurlzed to 2500 psia 5 hydrostatic pressure tests Pressurized to 3I07 pslg.

Secondary System l steam line break Break in a steam line > 5.5 inches equivalent dl arne ter.

5 hydrostat,ic pressure tests Pressurized to l356 psig.

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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 eff equivalent to less than 0.95 vhen flooded vith 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:

Maximum Nominal Fuel Assembly Enrichment Descri tion Vt. '4 235

1) Vestinghouse 15 x 15 STD 4. 95 15 x 15 OFA

2) Exxon/ANF 15 x 15 3.50

3) westinghouse 17 x 17 STD 4.95 17 x 17 OFA 17 x 17 V5

4) Exxon/ANF 17 x 17 4.23 COOK NUCLEAR PLANT - UNIT 2

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+ eainal 21 inch r ha are deailned and shall be pit storage ceater-to-center diatance betnen ner fuel bliea auch that Ioff vill not exceed 0.90 rhea fuel aaaeRbliea are 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; Maximum Nominal tuel Aaaeably Enrichment Vt. \ 235

1) Vestinghouse 15 x 15 STD 4.55 15 x 15 OFA

2) Exxon/ANF 15 x 15 3.50

3) Vestinghous ~ 17 x 17 STD 4.55 17 x 17 OFA 17 x 17 V5

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

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4 EP TABLE 5.7-1 COHPONENT CYCLIC OR TRANSIENT L IHITS

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CYCLIC OR DESI(iN CYCLE COHPONENT TRANSIENT L IHIT OR TRANSIENT Reactor Coolant System 200 heatup cycles at < 100'F/hr Ileatup cycle - T from < 200'F and 200 cooldown cycles at to > 547'F.

< 100 F/hr (pressurizer cooldown CooTdown cycle - T from > 547'F at < 200'F/hr). to < 200 F.

80 loss of load cycles. Without immediate turbine or reactor trip.

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

80 cycles of loss of flow in one Loss of only one reactor reactor coolant loop. coolant pump.

400 reactor trip cycles. 100K to OX of RATED TilERHAL POWER.

200 large step decreases in load. lOOX to 5X of RATED TllERHAL POWER with steam dump.

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7 Thli~LE 5. -i {Conl inured rn~voNLNT CYCLIC OR TRRISIENT LiwiTS CYCLIC OA nCSlrN CYCLE COMPONENT TRRNSIENT LllilT OR TRR[ISIENT Reactor Coolant 1 mackin reactor coolant pipe break. Break in a reactor coolant. pipe > 6 inches System equiva)ent diameter.

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

50 leak tests. Pressurized to 2500 psia 5 hydrostatic pressure tests Pressurized to 3107 psig.

Secondary System 1 steam line break Break in a steam line > 5.5 inches equivalent diameter.

5 hydrostatic pressure tests Pressurized to 1356 psig.

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