ML20137V581
| ML20137V581 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/15/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137V528 | List: |
| References | |
| NUDOCS 9704170348 | |
| Download: ML20137V581 (4) | |
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 30866 4001 NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.100 License No. DPR-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company (the licensee) dated September 5, 1996, complies with the l
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 s0ch activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment Will not be inimical to the common l
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.
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9704170348 970415 PDR ADOCK 05000245 P
'. l 2.
Accordingly, the license is amended as indicated in the attachment to this licensa amendment, and paragraphs 2.C.(2) and 2.C.(5) of Facility Operating License No. DPR-21 are hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.100, are hereby incorporated in the 1
license. The licensee shall operate the facility in accordance with the Technical Specifications.
4 (5)
Deleted 3.
This license amendment is effective as of the date of issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
Phillip F. McKee i
Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Page 4 of Facility Operating License (included for convenience)
Date of Issuance: April 15, 1997 i
I
ATTACHMENT TO LICENSE AMENDMENT NO.100 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following page of Operating License No. DPR-21 with the attached page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
Remove Insert 4
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i November 9, 1995 i
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(5) Deleted i
(6) Scent F9e1 Pool Doerations i
NNECO shr.11 conduct refueling operations that inc1;Je full-core offload as a nomal end-of-cycle event in accordance with the controls proposed in Attachw ~ 4 of the application for amendment dated July. a 1995, as supplemented September 12, 1995.
l NNECO shall update the UFSAR to reflect the hardware modifications, heat load analysis, and operational controls consistent with the application for amendment dated July 28, 1995, as supplemented September 12, 1995, in accordance with 10CFR50.71(e).
I D.
The facility has been granted certain exemptions from the requirements of 10 CFR Part 50 as set forth below:
c (1)Section III.G of Appendix R to 10 CFR Part 50, " Fire I
Protection Program for Nuclear Power Facilities Operating 4
i Prior to January 1, 1979.' This section relates to fire protectfon features for ensuring the systems and associated i
circuits used to achieve and maintain safe shutdown are free of fire damage. The staff safety evaluation, dated i
November 6,1985, concluded that the licensee's existing i
fire-protection configuration with proposed modifications i
achieves an equivalent level of safety. Exemption granted November 6, 1985.
l (2) Appendix J to 10 CFR Part 50, " Primary Reactor Containment Leakage Testing for Water-cooled Power Reactors.' Appendix J relates to containment leakage test requirements, specifically periodic verification by tests of the leak-i tight integrity of the primary reactor containment and systems and components which penetrate containment. Three e) =ptions were granted on May 10, 1985, on the basis of the 4'
staff safety evaluation. The two which remain in effect i
relate to testing of expansion bellows at containment j
penetrations and main steam isolation valves.
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i Amendment Nos. JJ, J/, ##, $$,100
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