ML20080F793

Amend 91 to License DPR-65,modifying Tech Specs Re Total Planar Peaking Factor Limits.Changes Cover Power Levels Between 92.5% & 100% Limits

ML20080F793
Person / Time
Site:	Millstone
Issue date:	01/27/1984
From:	John Miller Office of Nuclear Reactor Regulation
To:
Shared Package
ML20080F797	List: ML20080F793 ML20080F802
References
NUDOCS 8402130154
Download: ML20080F793 (9)

Text

{{#Wiki_filter:/ 'o UNITED STATES 8 ~,, NUCLEAR REGULATORY COMMISSION o C WASHINGTON, O. C. 20555 j NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. DPR-65 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated January 20, 1984 as supplemented January 25, 1984, 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; 8. 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 reasonable assurance (1) 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied. 8402130154 840127 PDR ADOCK 05000336 P PDR

i \\ i 1. e, 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-65 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 91, are hereby incorporated in the 1.icense. The licensee shall operate the facility in accordance with the Technical Specifica-tions. 3. This license amendment is effective on the date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION ,/ fj f/lfl?k9 / James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes.to the Technical Specifications Date of Issuance: January 27, 1984

ATTACHMENT TO LICENSE'3MENDMENT N0. 91 FACILITY OPERATING LICENSE NO. DpR-65 DOCKET N0. 50-336 Remove and replace the following pages of the Appendix A Technical Specifica-tions with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corre-spnnding overleaf pages are provided to maintain document completeness. Remove Insert 3/4 2-4 3/4 2-4 3/4 2-6 3/4 2-6 3/4 2-8 3/4 2-8

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POWER DISTRIBUTION LIMITS _ TOTAL PLANAR RADIAL PEAKING FACTOR - F LIMITING CONDITION FOR OPERATION ThecalculatedvalueofF[y,definedasFfy=F,(1+T),shall 3.2.2 q be limited to 1 1.719 l APPLICABILITY: MODE 1*. ACTION: With F > 1.719, within 6 hours either: l Reduce THERMAL POWER to bring the combination of THERMAL POWER a. andF[y to within the limits of Figure 3.2-3 and withdraw the full length CEAs to or beyond the Long Term Steady State Insertion Limit of Specification 3.1.3.6, or b. Be in at least HOT STANDBY. SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable. T T xy( q) and 4 2.2.2 F shall be calculated by the expressicn F ,p xy F shall be detennir.ed to be within its limit at the following intervals: xy Prior to operation above 70 percent.of RATED THERMAL POWER after a. each fuel loading, b. At least once per 31 days of accumulated operation in MODE 1, and Within four hours if the AZIMUTHAL POWER TILT (T ) is > 0.02. c. q

• See Special Test Exception 3.10.2.

i MILLSTONE - UNIT 2 3/4 2-6 ' Amendment No. 38, M./p, gd 91

, POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) shallbedeterminedeachtimeacalculationofFfy is required 4.2.2.3 Fxy by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination. This determination shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects. shallbedeterminedeachtimeacalculationofFfy 4.2.2.4 T is required q and the value of T used to determine F shall be measured value of T. q xy q l MILLSTONE - UNIT 2 3/4 2-7 Amendment No. 7@, 90

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