ML17331B063

Proposed Tech Specs Reflecting Deletion of Component Cyclic or Transient Limits Tables 5.9-1 & 5.7-1 for Units 1 & 2, Respectively

ML17331B063
Person / Time
Site:	Cook
Issue date:	11/12/1993
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17331B062	List: ML17331B061 ML17331B063
References
NUDOCS 9311190278
Download: ML17331B063 (24)

Text

ATTACHMENT 2 TO AEP:NRC:0980U EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 1

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INDEX DESIGN FEATURES SECTXON PAGE

5. 1 SITE Exclusion Area Low Population Zone Site Boundary for Gaseous and Liquid Effluents

5. 2 CONTAINMENT Configuracion Design Pressure and Temperacure Penetrations 5.3 REACTOR CORE 5-1 5-1 5-1 5-1 5>>4 Fuel Assemblies Control Rod Assemb 1's 5

4 REACTOR COOg

~ iSYSTEM Design Pressure and Temperacure Volume

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5-5 5.5 EMERGENCY CORE COOLING SYST~'fS 5.6 FUEL STORAGE Criticality

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5.7 'EISMIC CLASSIFICATION 5.8 METEOROLOGICAL TOPER LOCATION 5-7 5-7 5-7

, COOK NUCLEAR PLANT - UNIT 1 XVI AMEmMEVr NO. py, yZP, Io3

DESIGN FEATURES CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies.

5.7 SEISMIC CLASSIFICATION 5.7.1 Those structures, systems and components identified as Category I Items in the FSAR shall be designed and maintained to the original design provisions contained in the FSAR with allowance for normal degradation pursuant to the applicant Surveillance Requirements.

5.8 METEOROLOGICAL TOUR LOCATION 5.8.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.9.1 The components identi xe re designed and shall be maintain cyc ic or transient limits of Ta e

COOK NUCL"- <R, PLANT - UNIT I 5-9 zvEvD..".v'v vo. S9, 121I

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TABLE 5: 9-1 COMPONENT CYCLIC OR TRANSIENT I.IMITS COMPOH T

Reaccor Cool t System CYCLIC OR TRANSIENT LIMIT 200 heacup cycles at less cliar) or equal to 100 F/hr and 200 cooldowr) cycles at less t:Iran or equ<<I t.o 0

100 F/hr (pressurizer cooldourr

<<t.

0 less than or eqtr<<I to 200 ):/hr').

DESIGN CYCLE OR TRANSIENT lies tup cycle

- T from less rt 0 than or equal t t)0 F to 0

greater titan r equal co 547 F.

Cooldown c Ie - T from avlr 0

~.,re<<t.er r<<n or equal co 547 F

0 cu le s clr<<o or equal co 200 F.

8 oss of load cycles.

tlrout immediate turbine or reactor trip.

40 cycles loss of offsice A.

electrical po r.

I~ss of offs ice A.C. electrical power source supplyi.ng the onsice Class 1E distribution systera.

80 cycles of loss af flo in one reactor coolant hop.

Loss of only one reactor coolant

pump, 400 reacto trip <<ycles.

100% to 0% of RATED TIIERMAL POWER.

20 arge step decreases in load.

1 Q% to 5% of RATED TIIERMAL POWR with steam dump.

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AMEHI)MENT HO.163

TABI.I: 5.')- I COMPONENT CYCl.lC OR TRANSIENT 1.1MI'I'S COMPONENT CYCLIC OR TRANSIENT LIMIT DESIGN CYCLE OR TRANSIENT Reactor Coolant stem I main reactor coolant pipe break.

Operating 8 >s is I:.'ii c liii<<.<k<<:;

Break in a actor coolant pi.pe greati.r P an 6 i.nches equivalent cliamet ~r.

iC() <<yclus

- 20 earthcluakes of

)0 c".yc I us Ullch.

Secondary System 50 lea tests.

5 hydrostat pressur<<

tos l steam line brea I c ussur izc'.cl to 2500 ps ia.

1'r<<ssurlzed to 3107 psig.

Break in a steam line greater than 5.5 inches equivalent diamet<<r.

5 hydrosta c pressure t<<sts Pressurized to l356 psig.

Cnl)Y, NIICI.I'.AR I'IAN'I' I)HI'I' AtII-'Nl)MEN'I'O.163

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INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE

.Exclusion Area

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.. 5-1 Low Population Zone................................,............

5-1 Site Boundary for Gaseous and Liquid 5. 2 CONTAIBNE'.iT Effluents 5-1 Configuration

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Design Pressure and Temperature 5.3 REACTOR CORE Fuel Assemblies

'Control Rod Assemblies 5.4 REACTOR COOLEST SYSTEM Design Pressure and Temperature 5-1

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5-4 Volume

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5. 5 HETEOROLOGICAL TO~a.

LOCATION

5. 6 FUEL STORAGE Criticality - Spent Fuel.....................

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Criticality - New Fuel

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rainage........,.....................,...,....................

5 7

D Capacity

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COOK NUC~~

PLANT - UNIT 2 XVI

DESIGN FEATURES CRITICALITYNEW FUEL 5.6.2.1 The nev fuel pit storage racks are designed and'shall be maintained vith a nominal 21'inch center-to-center distance between nev fuel assemblies such that K villnot exceed

'I 0.98 when fuel assemblies are placed in Ie pit and aqueous foam moderation is assumed.

5.6.2.2 Fuel stored in the new fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:

Descri tion Maximum Nominal Fuel Assembly Enrichment Wt.

0 235U 1)

Westinghouse 15 x 15 STD 1S x aS OFA 4.55 2)

Exxon/ANF 15 x 15 3.50 3)

Westinghouse

. 17 17 17 x 17 STD x 17 OFA 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 draining of the pool below elevation 629'4".

CAPACITY 5.6.4 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited. to no more than 3613 fuel assemblies.

's.7.a The component@".~

ified in Table e

esigned and shall be maintaine ecyc]Lc or transient limits of Ta COOK NUCLEAR PLANT - UNIT 2 5-9 AMENDMENT NO.

$f, f14 147, 152

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TABI.E 5. 7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS COHPONEHT CYCLIC OR TRANSIENT LIHIT DESICN CYCLE OR TRANSIENT Re ac co r Coo 1 ant. Sys ceia 200 heatup cycles at less t:han or equal to 100 F/hr and 200 cooldown cycles at less t:han or equ tl to 0

0 F/hr (pressurize) coo ltlow>> ac o,

les than or equal to 2t)t) 1:/lir).

!Ieatup cycle T

frora less than or e

co 550 F to 0

greater

)an or equal to 547 F.

Co>>le n cycle

- T frora avR 0

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~Itor titan or equar co 547 F

0 loss titan or equal co 200 F.

80 loss of ad cycles.

Wit.I)out knunediate turbine or reactor trip.

40 cycles of loss o

otfs e A.C.

electrical power, Loss of offslte A.C. electrical power source supplying the onsl.te Class 1E discrlhution system.

80 cycles of oss of flow in one reactor c

lant loop..

Loss of only one reactor coolanc plllllp 400 eaccor trip cycles.

'00% to 0% of RATED TIIERMAL POWX

)

200 large step decreases in load.

100% to of RATED TIIERHAL POWER with earn durap.

(:t)OK Ht)t:I.I:.Alt I'IDENT - UHI'I' 5.. I I)

AMI:.HDMEHI NO. lory

COHPQNENT CYCLIC OR TRANSlENT l.lHITS COHPONENT CYCLIC OR

'I'RANSIENT LIHIT DESIGN CYCLE OR TRANSIENT Reaccor Coolant stem 1 main reactor coolanc pip<< break.

Break in a reac r coolant pipe greater than inches equivalent diameter.

Operating Basis E))) rlwI)<<<k)~ ~

I)OO~ clos

- 20 earthquakes of 2tH<<yells each.

Secondary Syscem 50 lea tests.

5 hydrostat

.c pressure costs 1 steam line break Pressurized to 2500 psia.

l'ressurized to 3107 psig.

Break in a steam line greater than 5.5 inches equivalent diameter.

.5 hydrostatic ressure tests l'ressurized to 1356 psig.

K NUCI.I AR I'IANT - UNIT 2 AHENWI:NT NO. 14?

11.254 66.254

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ATTACHMENT 3 TO AEP:NRC:0980U PROPOSED REVISED TECHNICAL SPECIFICATION PAGES

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area Low Population Zone Site Boundary for Gaseous and Licpxid Effluents

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5-5 5.5 EMERGENCY CORE COOLING SYSTEMS

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5-5 5.6 FUEL STORAGE Criticality Drainage.

Capacity 0

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5.7 SEISMIC CLASSIFICATION

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5-7 5.8 METEOROLOGICAL TOWER LOCATION.

5-7 COOK NUCLEAR PLANT UNIT 1 XVI AMENDMENT NO. 6&g k90g

DESIGN FEATURES CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies.

5.7 SEISMIC CLASSIFICATION 5.7. 1 Those structures, systems and components identified as Category I Items in the FSAR shall be designed and maintained to the original design provisions contained in the FSAR with allowance for normal degradation pursuant to the applicant Surveillance Requirements.

5.8 METEOROLOGICAL TOWER LOCATION 5.8.1 The meteorological tower shall be located as shown on Figure 5.1-1.

COOK NUCLEAR PLANT UNIT 1 5-9 AMENDMENT NO. 69,

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1 5.2 CONTAINMENT Configuration Design Pressure and Temperature 5-1 5-1 5.3 REACTOR CORE Fuel Assemblies Control Rod Assemblies 5-4

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5-4 5-5 5.5 METEOROLOGICAL TOWER LOCATION.

o 5-5 5.6 FUEL STORAGE Criticality Spent Fuel Criticality New Fuel Drainage Capacity 0

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COOK NUCLEAR PLANT UNIT 2 XVI AMENDMENT NO 54@

k&Tg~

DESIGN FEATURES CRITICALITY NEW FUEL 5.6.2.1 The new fuel pit storage racks are designed and shall be maintained with a nominal 21-inch center-to-center distance between new fuel assemblies such that K,~ will not exceed 0.98 when fuel assemblies are placed in the pit and aqueous foam moderation is assumed.

5.6.2.2 Fuel stored in the new fuel storage racks shall have a maximum nominal fuel assembly enrichment as followss Descri tion Maximum Nominal Fuel Assembly Enrichment Wt.

0 235U 1)

Westinghouse 15 x 15 STD 15 x 15 OFA 2)

Exxon/ANF 15 x 15 3)

Westinghouse 17 x 17 STD 17 x 17 OFA 17 x 17 V5 4)

Exxon/ANF 17 x 17 4.55 3.50 4.55 4.23 DRAINAGE 5.6.3 CAPACITY The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 629'".

5.6.4 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies.

COOK NUCLEAR PLANT -UNIT 2 5-9 AMENDMENT NO 5k'k&~ 447, 45&

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