ML20205E659
| ML20205E659 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/08/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20205E663 | List: |
| References | |
| DPR-22-A-034 NUDOCS 8510170361 | |
| Download: ML20205E659 (4) | |
Text
'o UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. DPR-22 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated April 10, 1985 as supplemented by letter dated June 16, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is ceasonable 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 conductec' in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission'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-22 is hereby amended to read as follows:
i 8510170361g5 j63 PDR ADOCK PDR P
. 2 Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 34, 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 NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 8,1985 g.
ATTACHMENT TO LICENSE AMENDMENT NO. 34 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 i
Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised area is indicated by a marginal line.
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It is designed to conform to ASME Boiler and Pressure Vessel Code Section III' Class B for an internal pressure of 56 psig at 281*F and an external pressure of 2 peig at 281*F.
B.
Fenetrations added to the primary containment shall be designed in accordance with standards set forth in Section 5.2.2.3 of the Final Safety Analysis Report. Piping passing through such penetrations shall have isolation valves in accordance with standards set forth in Section 5.2.2.4 of the Final Safety Analysis Report.
C.
The reactor building, standby gas treatment system and stack shall comprise a secondary 7
containment in such fashion to enclose the primary containment la order to provide for controlled elevated release of the reactor building atmosphere under accident conditions.
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5.5 Fuel Storage Normal storage for 'unirradiated fuel assemblies is in critically-safe new fuel storage A.
racks in the reactor building storage vault. Fuel shall be stored in arrays such that i
the Keff dry is less than 0.90 and flooded is less than 0.95.
In order to meet these limits, new fuel assemblies shall have an infinits lattice multiplication factor less than or equal to 1.31.
5.
The Keff of the spent fuel storage pool shall be less than or equal to 0.95.
In order to meet this limit, fuel assemblies stored in this pool shall have an infinite lattice multiplication factor less than or equal to 1.33.
j 5.6 Seismic Design l
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All Class I structures and equipment were analyzed to assure that a safe shutdown can be made j
during ground acceleration of 0.123 (Maximum Earthquake). Dynamic analysis was used to determine the earthquake acceleration applicable to the various elevations in the reactor building.
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Amendment No. 34
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