ML17333A797
| ML17333A797 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/27/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17333A798 | List: |
| References | |
| NUDOCS 9703050492 | |
| Download: ML17333A797 (15) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISS)ON WASHINGTON, D.C. 2005&4001 DIANA MICHIGAN POWER COMPANY
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OOK NUCLEAR ANT UNIT NO.
E DMENT TO FACILIT OPERATING LICENSE Amendment No. 2i3 License No.
DPR-58 The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Indiana Michigan Power Company (the licensee) dated February 26,
- 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Coml ssi on'here is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9703050492 970227 PDR ADQCK 05000315 P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
Technical S ec ications 3.
The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 213
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of issuance, with full implementation within 45 days.
I FOR THE NUCLEAR REGULATORY COMMISSION Wohn B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changesto the Technical Specifications Date of Issuance:
February 27, 1997
T C
2i3 TO FACILITY 0 ERATING LICENSE NO.
DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 5-4 5-5 5-6 5-8 NSER 5-4 5-5 5-6 5-8 e
h
5.0.
DESIGN FEATURES 5.2 CONTAINMENT Continued DESIGN PRESSURE AND TEMPERATURE 5.22 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.
ENETRATIONS 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 offuel 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 of3.35 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. Allcontrol rods shall be clad with stainless steel tubing.
COOK NUCLEAR PLANT-UNIT1 Page 5Q AMENDMENTQQ, 449, 4',
~~ 3
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:
In accordance with the code requirements specified in Section 4.1.6 ofthe FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
C.
For a pressure of 2485 psig, and 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 system is 12,612 J 100 cubic feet at a nominal T,~ of 70'F.
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 FUELSTORAGE 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.
Anominal 8.97 inch center-to~nter distance between fuel assemblies placed in the storage racks.
The fuel assemblies willbe 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-UNIT1 Page 5-5 AMENDMENT4$8, 4%, 449, 2~ 3
0 5.0.
DESIGN FEATURES 5.6 FUEL STORAGE Continued 2.
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.
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.
The equivalent reactivity criteria for Region 2 and Region 3 is defined via the followingequations 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 Ei + 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:
Description Maximum Nominal Fuel Assembly Enrichment Wt. % U-235 1)
Westinghouse 2)
Exxon/ANF 3)
Westinghouse 4)
Exxon/ANF 15 x 15 STD 15 x 15 OFA 15 x 15 17 x 17 STD 17 x 17 OFA 17 x 17 V5 17 x 17 4.95 4.95 4.95 4.95 COOK NUCLEAR PLANT-UNIT1 Page 5-6 AMENDMENT$7, 436, 448, 469, 2~ 3
t 5.0 DEBIGN 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 S.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; C.
keff E 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 Description Maximum Nominal Fuel Assembly Enrichment Wt. % U-235 1)
Westinghouse 2)
Exxon/ANF 3)
Westinghouse 4)
Exxon/ANF 15 x 15 STD 15 x 15 OFA 15 x 15 17 x 17 STD 17 x 17 OFA 17x17VS
'7 x 17 4.55 3.50 4.55 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 1.4&57 at 68'F.
COOK NUCLEAR PLANT-UNITI Page 54 AMENDMENT4N, 449~ ~~ 3
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UNlTED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DIANA M CHIGAN POWER COMPANY ILODfET 5 ->>
ONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 ENDMENT TO ACILITY OPERATING L C
NSE Amendment No. i 98 License No. DPR-74 The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
The application for amendment by Indiana Michigan Power Company (the licensee) dated February 26,
- 1996, complies with the standards and requirements of the Atomic Energy Act of 1954; as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with tPe application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-74.is hereby amended to read as follows:
echnical S ecifications 3.
The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
198
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications ohn B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reac'tor Regulation Date of Issuance:
February 27, 1997
TTACHMENT TO LICENSE AMENDMENT No.i98 CILI Y OPER TING LICENSE NO.
DPR-74 OCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 5-6 5-9 INSERT 5-6 5-9
5.0 DESIGN FEATUtuH 5.6 FUEL STORAGE Continued CRITICALITY-SPENT FUEL Continued
'he 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 2Stora 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:
Description Maximum Nominal Fuel Assembly Enrichment Wt. % U-235 1)
Westinghouse 2)
Exxon/ANF 3)
Westinghouse 4)
Exxo'n/AN F 15 x 15 STD 15 x 15 OFA 15 x 15 17 x 17 STD 17 x 17 OFA 17 x17 V5 17 x 17 4.95 4.95 4.95 4.95 COOK NUCLEAR PLANT-UNIT2 Page 5A AMENDMENTW, ku, ~, ~ 198
5.6 FUEL STORAGE Continued CRITICALITY-NEW FUEL 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; keff 6 0.95 iffully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; k ff S 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 Description Maximum Nominal Fuel Assembly Enrichment Wt. % U-235 1)
Westinghouse 2)
Exxon/ANF 3)
Westinghouse 4)
Exxon/ANF 15 x 15 STD 15 x 15 OFA 15 x 15 17 x 17 STD 17 x 17 OFA 17 x 17 V5 17 x 17 4.55 3.50 4.55 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 AMENDMENTa, uS, ~, ~, eX, < 98
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