ML17054A460
| ML17054A460 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/01/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17054A461 | List: |
| References | |
| NUDOCS 8402170063 | |
| Download: ML17054A460 (8) | |
Text
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UNITED STATES Ni LEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK PO'WER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
54 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application f'r amendment by Niagara Mohawk Power Corporation (the licensee) dated March 22,
- 1978, supplemented December 20 and 21, 1978, February 26,
- 1981, June 24, August 5, October 5, October 26, November 18 and December 21, 1983 and January 3, 1984, complies with the standards and requirements of the Atomic Enerqv Act of 1954, as amended tthe Act) and the Commission's rules and requlations 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 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.
Accordinglv, the license is amended by changes to the Technical Specifica6ons as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is hereby amended to read as follows:
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(2) Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 54, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NU EAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Oate of Issuance:
February 1,
1984 Domenic 8. Vassallo, Chief Operating Reactors Branch P2 Oivision of Licensing
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ATTACHMENT TO LICENSE AMENOMENT NO. 54 FACILITY OPERATING LICENSE NO.
DPR-63 OOCKET NO. 50-220 Revise the Appendix A Technical Specifications by removing and inserting the following pages:
Existing Pave 244 Revised
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244 The revised areas are indicated by marginal lines..
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5.5 Storage. of Unirradiated and S ent Fuel Unirradiated fuel assemblies will normally be stored in critically safe new fuel storage racks in the reactor building storage vault.
Even when flooded with water, the resultant keff is less than 0.95.
Fresh fuel may also be stored in shipping containers.
The unirradiated fuel storage vault is designed and shall be maintained with a storage capacity limited to no more than 200 fuel assemblies.
The spent fuel storage facility is designed to maintain fuel in a geometry such that keff is less than 0.95 under conditions of optimus water moderation.
The spent fuel storage facility is designed and shall be maintained with a storage capacity limited to no more than 2776 fuel assemblies.
Fuel assemblies stored in the 1066 spent fuel storage locations of the non-poison flux trap design are limited to 15.6 grams (3.0 weight percent) of Uranium-235 per axial centimeters of assembly.
Fuel assemblies stored in the 1,710 spent fuel storage positions of the poison type which use Boraflex as the neutron absorber are limited to 18.13 grams (3.75 weight percent) of Uranium-235 per axial centimeters
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of assembly.
Calculations for keff values have been based on methods approved by the Nuclear Regulatory Commission covering special arrays (10CFR70.55).
The reactor building and all contained engineered safeguards are des'igned for the maximum credible earthquake ground motion with an acceleration of ll percent of gravity.
Dynamic analysis was used to determine the earthquake acceleration, applicable to the various elevations in the reactor building.
244
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