ML17325A019
| ML17325A019 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/27/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17325A020 | List: |
| References | |
| NUDOCS 8704060084 | |
| Download: ML17325A019 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 102 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated Decembe~
22, 1986, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
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; D.
The issuance of this amendment will not be inimical to the conTIIon 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-58 is hereby amended to read as follows:
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(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.>o~, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The Technical Specification is effective within 60 days of issuance.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 2/,
1987 Dave L. Wigginton, Project Manager PWR Project Directorate 0'4 Division of PWR Licensing-A PWRg4/DPWR-A DWigg nton/rad 03/
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-74 1.
The Nuclear Regulatory Commission (the Cormission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated December 22, 1986, 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; B.
The facility will operate in conformity with the aoplication, the provisions of the Act, and the rules and regulations of the Commission; C.
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; D.
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:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 88, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The Technical Specification is effective within 60 days of issuance.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
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$987 Dave L. Wigginton, Project Manager PWR Project Directorate ¹4 Division of PWR Licensing-A PWR 4/DPWR-A DWigginton/rad 03/P/87 PWR$4/$ PWR-A 03/g /87 GC-ggthesda
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT N0,102 FACILITY OPERATING LICENSE NO.
DPR-58 AMENDMENT NO, 88 FACILITY OPERATING LICENSE NO.
DPR 74 DOCKET NOS. 50-315 AND 50-316 Revi se Appendi x A as follows:
Remove Pa es Unit 1
5-4 Unit 2 5-4 Insert Pa es 5-4 5-4
DESIGN FEATURES 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.
PENE RATIONS 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 ASSEMBL'IES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 204 fuel rods clad with Zircaloy -4.
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 enrichment of 4.0 weight percent U-235.
CONTROL ROD ASSEMBL ES 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.
5 4 REACTOR COOLANT S STEM DESIG E SURE D TEMP 5.4.1 The reactor coolant system is designed and shall be maintained:
D.
C.
COOK - UNIT 1 5-4 Amendment No.
102
DESIGN FEATURES 3
REAC OR CORE EL ASSE BLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy -4.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum enrichment of 3.3 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 3.84 weight percent U-235.
CO TROL ROD AS EMBLIES 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.
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.
C.
For a pressure of 2485 psig, and For a temperature of 650 F, except for the pressurizer which is 680 F.
D.
C.
COOK - UNIT 2 5-4 Amendment No. 88