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

931ii90278'93iii2 PDR ADOCK 05000315 P 'PDR

I,C INDEX DESIGN FEATURES SECTXON PAGE

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

5. 2 CONTAINMENT Configuracion 5-1 Design Pressure and Temperacure 5>>4 Penetrations 5.3 REACTOR CORE Fuel Assemblies ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Control Rod Assemb 1's ~ ~ ~ ~ ~ ~ ~ ~ ~

5 4 REACTOR COOg ~ i SYSTEM Design Pressure and Temperacure ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~

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

Drainage 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

C apacity ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-7 5.7 'EISMIC CLASSIFICATION 5-7 5.8 METEOROLOGICAL TOPER LOCATION 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

)~o

TABLE 5: 9- 1 COMPONENT CYCLIC OR TRANSIENT I.IMITS CYCLIC OR DESIGN CYCLE COMPOH T TRANSIENT LIMIT OR TRANSIENT Reaccor Cool t System 200 heacup cycles at less cliar) or lies tup cycle - T from less rt 0 equal to 100 F/hr and 200 cooldowr) than or equal t t)0 F to cycles 0

at less t:Iran or equ<<I t.o greater titan r equal co 547 0 F.

100 F/hr (pressurizer cooldourr <<t. Cooldown c Ie - T from less than or eqtr<<I to 200 0 ):/hr')

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

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

I'IDENT I

(:()t)h Nl ~ r ~

It - (IN I T ) AMEHI)MENT HO.163

TABI.I: 5.')- I COMPONENT CYCl.lC OR TRANSIENT 1.1MI'I'S CYCLIC OR DESIGN CYCLE COMPONENT TRANSIENT LIMIT OR TRANSIENT Reactor Coolant stem I main reactor coolant pipe break. Break in a actor coolant pi.pe greati.r P an 6 i.nches equivalent cliamet ~r.

Operating 8 >s is I:.'ii c liii<<.<k<<:; iC() <<yclus - 20 earthcluakes of

)0 c".yc I us Ullch.

50 lea tests. I c ussur izc'.cl to 2500 ps ia.

5 hydrostat pressur<< tos 1'r<<ssurlzed to 3107 psig.

Secondary System l steam line brea 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' At I I-'Nl)MEN'I'O.163

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INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE

.Exclusion Area ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

.. 5-1 Low Population Zone ................................,............ 5-1 Site Boundary for Gaseous and Liquid Effluents 5-1 5.2 CONTAIBNE'.iT Configuration ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Design Pressure and Temperature 5-1 5.3 REACTOR CORE Fuel Assemblies ~ ~ ~ ~ s 5 4

'Control Rod Assemblies ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

5.4 REACTOR COOLEST SYSTEM Design Pressure and Temperature 5-4 Volume ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

5. 5 HETEOROLOGICAL TO~a. LOCATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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

I

~, ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Criticality - New Fuel ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

D rainage ........,.....................,...,.................... 5 7 Capacity ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

COOK NUC~~ PLANT - UNIT 2 XVI

DESIGN FEATURES CRITICALITY NEW 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 0.98 when fuel assemblies are placed in foam moderation is assumed.

'IIe pit vill not exceed and aqueous 5.6.2.2 Fuel stored in the new fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:

Maximum Nominal Fuel Assembly Enrichment Descri tion Wt. 0 235U

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

2) Exxon/ANF 15 x 15 3.50

3) Westinghouse . 17 x 17 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 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 152 147,

. ~ - ~

TABI.E 5. 7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS CYCLIC OR DESICN CYCLE COHPONEHT TRANSIENT LIHIT OR TRANSIENT Re ac co r Coo 1 ant. Sys ceia 200 heatup cycles at less t:han or !Ieatup cycle T frora less equal to 100 F/hr and 200 cooldown than or e co 550 F to 0

cycles 0

at less t:han or equ tl to greater )an or equal to 547 F.

0 F/hr (pressurize) coo ltlow>> ac Co>>le n cycle - T frora les than or equal to 2t)t) o,1:/lir). ) ~ It or titan or equaravR 0 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. Loss of offslte A.C. electrical electrical power, power source supplying the onsl.te Class 1E discrlhution system.

80 cycles of oss of flow in one Loss of only one reactor coolanc reactor c lant loop.. 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 CYCLIC OR DESIGN CYCLE COHPONENT 'I'RANS I ENT LIHIT 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.

50 lea tests. Pressurized to 2500 psia.

5 hydrostat .c pressure costs l'ressurized to 3107 psig.

Secondary Syscem 1 steam line break 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?

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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 ~ o ~ ~ ~ 5 1 Low Population Zone ~ o ~ ~ ~ 5 1 Site Boundary for Gaseous and Licpxid Effluents ~ ~ ~ ~ ~ 5 1

5. 2 CONTAINMENT Configuration ~ ~ ~ 5 1 Design Pressure and Temperature ~ ~ ~ 5 4 Penetrations ~ ~ ~ 5 4 5.3 REACTOR CORE Fuel Assemblies . . . . . . . . . . . . . . ... . . . . ~ - 5-4 Control Rod Assemblies . . . . . . . . . . . . . . . . ~ ~ 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature . . . . . . . . . . . . . . 5-4 Volume. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-5 5.5 EMERGENCY CORE COOLING SYSTEMS ~ . . ~ ~ ~ . . . . ~ ~ 5-5 5.6 FUEL STORAGE Criticality ~ ~ ~ ~ 5 5 Drainage. ~ ~ ~ ~ 5 7 Capacity 0 ~ ~ ~ ~ ~ ~ ~ 5 7 5.7 SEISMIC CLASSIFICATION . . . . . . . . . . . . ~ 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, %&V, 469

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INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area o ~ ~ ~ ~ ~ 5 1 Low Population Zone ~ ~ ~ ~ ~ ~ 5 1 Site Boundary for Gaseous and Liquid Effluents ~ ~ ~ ~ ~ o 5 1 5.2 CONTAINMENT Configuration 5-1 Design Pressure and Temperature 5-1 5.3 REACTOR CORE Fuel Assemblies 5-4 Control Rod Assemblies ~ e ~ 5 4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature 5-4 Volume. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-5 5.5 METEOROLOGICAL TOWER LOCATION . . . . . . . o . . . . 5-5 5.6 FUEL STORAGE Criticality Spent Fuel ~ ~ ~ ~ 5 5 Criticality New Fuel ~ ~ ~ o 5 6 Drainage ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 7 Capacity 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 7 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 Maximum Nominal Fuel Assembly Enrichment Descri tion Wt. 0 235U

1) Westinghouse 15 x 15 STD 4.55 15 x 15 OFA

2) Exxon/ANF 15 x 15 3.50

3) Westinghouse 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 shall be maintained to prevent inadvertent draining of the pool below elevation 629'".

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.

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

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