ML17333A323

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Proposed TS 5.6.2 Re Increase in Max Nominal Fuel Assembly Enrichment Limit,Taking Credit for Use of Integral Fuel Burnable Absorber Matl
ML17333A323
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 02/26/1996
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17333A324 List:
References
NUDOCS 9603010076
Download: ML17333A323 (18)
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Text

5.0 DESIGN FEATURES 5.2 CONTAINMENT Continued DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maimained in accordance with the original design provisions contained in Section 5.2.2 of the FSAR.

PEN ETRATIONS 5.2.3 Penetrations through the reactor containment building are designed and shall bc maintained in accordance with the original design provisions contained in Section 5.4 of the FSAR with allowance for normal degradation pursuant to the applicable Survcillancc Requirements.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 204 fuel rods clad with Zircaloy<, except that limited substitutions of zirconium alloy or stainless steel Gller rods, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assembli'es shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblics that have not completed representative testing may be placed in non-limiting core regions. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial cote loading shall have a maximum enrichment of 3.35 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum nominal enrichment of 4.95 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control tod assemblics. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 petcent cadmium. All control rods shall bc clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM lADU4- ~~F7 DESIGN PRESSURE AND TEMPERATURE J~ T~P ot-5.4.1 The reactor coolant system is designed and shall be maintained:

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P PDR COOK NUCLEAR PLANT-UNIT 1 Page &4 AilIEND~402. 440. 199

lgsckF KX< l&a DEI N T (~A pILEViov~ p8-66

a. In accordance with the code requirements specified in Section 4.1.6 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,
b. For a pressure of 2485 psig, and C. For a temperature of 650'F, except for the pressurizer which is 680'F.

V(~LME 5.4.2 The total contained volume of the reactor coolant system is 12,612 + 100 cubic feet at a nominal T,, of 70'F.

5.5 MER EN Y RE LIN SY TEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section 6.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements, with one exception. This exception is the CVCS boron makeup system and the BIT.

5.6 LTRAE CRITICALITY- SPENT L 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. A ~ equivalent to less than 0.95 when flooded with unborated water.
b. A nominal 8.97 inch center-to-center distance between fuel assemblies placed in the storage racks.

C. The fuel assemblies will be classified as acceptable for Region 1, Region 2, or Region 3 storage based upon their assembly average burnup versus initial nominal enrichment. Cells acceptable for Region I, Region 2, and Region 3 assembly storage are indicated in Figures 5.6-1 and 5.6-2. Assemblies that are acceptable for storage in Region 1, Region 2, and Region 3 must meet the design criteria that

/Enough define the regions as follows:

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COOK NUCLEAR PLANT - UNIT I 5-5 AMENDMENT NO. 1,,

CORRECTED PAGE 169

1. Region 1 is designed to accommodate new fuel with a maximum nominal enrichment of 4.95 wt% U-235, or spent fuel regardless of the discharge fuel burnup.

2..Region 2 is designed to accommodate, fuel of 4.954 initial nominal enrichment burned to at least 50,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.

3. Region 3 is designed to accommodate fuel of 4.95%

initial nominal enrichment burned to at least 38,000 IQD/MtU, or fuel of other enrichments with equivalent reactivity.

pohlf The equivalent reactivity criteria for Region 2 and c t/hg68 Region 3 is defined via the following equations and graphically depicted in Figure 5.6-3.

For Re ion 2 Stora e Minimum Assembly Average Burnup in MWD/MTU 22,670 + 22,220 E - 2,260 + 149 E For Re ion 3 Stora e Minimum Assembly Average Burnup in NPD/MTU 26,745 + 18,746 E - 1,631 E + 98.4 E

@here E Xnitial Peak Enrichment IllS~mW YKWi ~A COOK NUCLEPR. PLANT - UN1T 1 5-6 AMENDMEVZ NO. $ 7'N p 768t 169

DESIGN FEATURES 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 E

Descriotion Vt. 0 235..

1) '<<estinghouse 15 x 15 STD 15 x 15 OFA
2) Exxon/ANF 15 x 15 4.95
3) Res inghouse 17 x 17 STD 4.95 17 x 17 OFA 17 x 17 V5
4) Exxon/AVF 17x 17 4.95 CRITICALIT - Nc.4 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 ff vill not exceed 0.98 vhen fuel assemblies are placed in the pit and aqueous foam moderat'on is assumed.

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

Maximum Nominal Fuel Assembly Enrichment Desc stion Vt.  % 235.

1) Mestinghouse 15 x 15 STD 4.55 15 x 15 OFA
2) Exxon/ANF 15 x 15 3.50
3) Vestinghouse 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 belov elevation 629'4".

COOK NUCLEAR PLANT - UNIT 1 5-8 ~arose mo.gag, !

169

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

a. Fuel assemblies having a maximum enrichment in accordance with Table 5.6-1; k ff 6 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; C. keff K 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; and a nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

Table 5.6-1 MAXIMUMNOMINALFUEL ASSEMBLY ENRICHMENT FOR NEW FUEL STORAGE RACKS Maximum Nominal Fuel Description Assembly Enrichment Wt. % U-235

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

. A maximum nominal enrichment of 4.95 weight percent U-235 for Westinghouse fuel types is acceptable provided that sufficient integral fuel burnable absorber is present in each fuel assembly stored in the new fuel storage racks such that the maximum reference fuel assembly k~ is less than or equal to 1.4857 at 68'F.

The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations and graphically depicted in Figure 5.6-3.

For Re ion 2 Stora e Minimum Assembly Average Burnup in MUD/MTU 22,670 + 22,220 E - 2,260 E + 149 E For Re ion 3 Stora e Minimum Assembly Average Burnup in MWD/MTU 26,745 + 18,746 E - 1,631 E + 98.4 E Where E - Initial Peak Enrichment 5 '.1.2 Fuel stored in the spent fuel storage racks shall have a nominal fuel assembly enrichment as follows:

Maximum Nominal Fuel Assembly Enrichme Descrintion t. a 235U

1) Westinghouse 15 x 15 STD 4.95 15 x 15 OFA
2) Exxon/ANF 15 x 15 4.95
3) Westinghouse 17 x 17 STD 4.95 17 x 17 OFA 17 x 17 V5
4) Exxon/ANF 17 x 17 4.95 COOK NUCLEAR PLANT - UNIT 2 5-6 AMENDMEitT NO. $ 7, fgf, ggj 152

5.0 . DESIGN PEATKUH 5.6 FUEL STORAGE Continued CRITICALITY- NEW FUEL / PLRCC MITn.

g 5.6.2.1 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-s t~ter distance between new fuel assemblies such that ~ 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 follows:

Maximum Nominal Fuel Assembly Enrichment

~

Description Wt. % 235U I) 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 17x 17OFA 17x17 V5
4) Exxon/ANF 17x 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.

COOK NUCLEAR PLANT-UNIT2 Page 5-9 AMENDMENTA, 448, ~, XSAM, 186

ATTACHMENT 3 TO AEP:NRC: 1071U PROPOSED REVISED TECHNICAL SPECIFICATION PAGES

5.0 DESIGN FEATURES 5.2 CONTAINMENT Continued DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained in accordance with the original design provisions contained in Section 5.2.2 of the FSAR.

PENETRATIONS 5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions contained in Section 5.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 204 fuel rods clad with Zircaloy4, except that limited substitutions of zirconium alloy or stainless steel filler rods, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum nominal enrichment of 4.95 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control'rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

COOK NUCLEAR PLANT-UNIT 1 Page 5A AMENDMENTQQ, 449, 4',

5.0 DESIGN FEATURES 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 4.1.6 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,
b. For a pressure of 2485 psig, and
c. For a temperature of 650'F, except for the pressurizer which is 680'F.

VOLUME 5.4.2 The total contained volume of the reactor coolant syst'e m is 12,612 g 100 cubic feet at a nominal T,~ of 70oF 5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section 6.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements, with one exception. This exception is the CVCS boron makeup system and the BIT.

5.6 FUEL STORAGE CRITICALITY- SPENT FUEL 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

A k,<<equivalent to less than 0.95 when flooded with unborated water.

A nominal 8.97 inch center-to-center distance between fuel assemblies placed in the storage racks.

The fuel assemblies will be classified as acceptable for Region 1, Region 2, or Region 3 storage based upon their assembly average burnup versus initial nominal enrichment. Cells acceptable for Region 1, Region 2, and Region 3 assembly storage are indicated in Figures 5.6-1 and 5.6-2.

Assemblies that are acceptable for storage in Region 1, Region 2, and Region 3 must meet the design criteria that define the regions as follows:

COOK NUCLEAR PLANT-UNIT I Page 5-5 AME<NDMENT 4', 463, 449,

5.0 DESIGN FEATURES 5.6 FUEL STORAGE Continued

1. Region 1 is designed to accommodate new fuel with a maximum nominal enrichment of 4.95 wt% U-235, or spent fuel regardless of the discharge fuel burnup.
2. Region 2 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 50,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.
3. Region 3 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.

I The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations and graphically depicted in Figure 5.6-3.

For Re ion 2 Stora e Minimum Assembly Average Burnup in MWD/MTU =

-22,670 + 22,220 E -2,260 E2 + 149 E3 For Re ion 3 Stora e Minimum Assembly Average Burnup in MWD/MTU =

- 26,745 + 18,746 E - 1,631 E~ + 98.4 E3 Where E = Initial Peak Enrichment 5.6.1.2: Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:

Maximum Nominal Fuel Assembly Enrichment Description Wt. % U-235

1) Westinghouse 15 x 15 STD 4.95 15 x 15 OFA
2) Exxon/ANF 15 x 15 4.95
3) Westinghouse 17 x 17 STD 4.95 17 x 17 OFA 17 x 17 VS
4) Exxon/ANF 17 x 17 4.95 COOK NUCLEAR PLANT-UNIT 1 Page 5-6 AMENDMENTW, 436, 463, 469,

5.0 DESIGN FEATURES 5.6 FUEL STORAGE Continued CRITICALITY- NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with:

Fuel assemblies having a maximum enrichment in accordance with Table 5.6-1; keff 6 0.95 iffully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; keff 6 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; and a nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

Table 5.6-1 MAXIMUMNOMINALFUEL ASSEMBLY ENRICHMENT FOR NEW FUEL STORAGE RACKS Maximum Nominal Fuel Description Assembly Enrichment Wt. % U-235

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 629'4".

A maximum nominal enrichment of 4.95 weight percent U-235 for Westinghouse fuel types is acceptable provided that sufficient integral fuel burnable absorber is present in each fuel assembly stored in the new fuel storage racks such that the maximum reference fuel assembly k~ is less than or equal to 1.4857 at 68'F.

COOK NUCLEAR PLANT-UNIT 1 Page 5-8 AMENDMENT463, 469

5.0 DESIGN 1<<<.ATURES 5.6 FUEL STORAGE Continued CRITICALITY- SPENT FUEL Continued Thc equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations and graphically depicted in Figure 5.6-3.

For Re ion 2 Stora e Minimum Assembly Average Burnup in MWD/MTU =

- 22,670 + 22,220 E - 2,260 E + 149 E For Re ion 3 Stora e Minimum Assembly Average Burnup in MWD/MTU =

- 26,745 + 18,746 E - 1,631 E + 98.4 E Where E = Initial Peak Enrichment 5.6.1.2 Fuel stored in the spent fuel storage racks shall have a nominal fuel assembly enrichment as follows:

Maximum Nominal Fuel Assembly Enrichment Description Wt. % U-235

1) . Westinghouse 15 x 15 STD 4.95 15 x 15 OFA
2) Exxon/ANF 15 x 15 4.95
3) Westinghouse 17 x 17 STD 4.95 17 x 17 OFA 17 x 17 V5
4) Exxon/ANF 17 x 17 4.95 COOK NUCLEAR PLANT-UNIT2 Page 5-6 AME<NDMENT41, 424, 442, 45K

5.0 DESIGN KZATURES 5.6 FUEL STORAGE Continued CRITICALITY- NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with:

Fuel assemblies having a maximum enrichment in accordance with Table 5.6-1; keff 6 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; keff 6 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; and

d. a nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

Table 5.6-1 MAXIMUMNOMINALFUEL ASSEMBLY ENRICHMENT FOR NEW FUEL STORAGE RACKS Maximum Nominal Fuel Description Assembly Enrichment Wt. % U-235

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 629'4".

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.

A maximum nominal enrichment of 4.95 weight percent U-235 for Westinghouse fuel types is acceptable provided that sufficient integral fuel burnable absorber is present in each fuel assembly stored in the new fuel storage racks such that the maximum reference fuel assembly k~ is less than or equal to 1.4857 at 68'F.

COOK NUCLEAR PLANT-UNIT2 Page 5-9 'MENDMENTA, 448, 447., 483, 48Ci,

ATTACHMENT 4 TO AEP:NRC:1071U CDB-95-175 "CRITZCALZTY ANALYSIS OF THE DONALD C. COOK NUCLEAR PLANT NEW FUEL STORAGE VAULT WITH CREDIT FOR INTEGRAL FUEL BURNABLE ABSORBES NOVEMBER 1995 PREPARED BY WESTINGHOUSE ELECTRIC CORPORATION (NON-PROPRIETARY)

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