ML20206U900

Amend 96 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 10 Reload Core by Modifying steady-state Peak Linear Heat Rate to Reflect Acceptable Fuel Design Limits for Prevention of Centerline Melting

ML20206U900
Person / Time
Site:	Maine Yankee
Issue date:	04/09/1987
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206U833	List: ML20206U829 ML20206U900 ML20206U923
References
NUDOCS 8704230596
Download: ML20206U900 (7)

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.o UNITED STATES NUCLEAR REGULATORY COMMISSION 4 g :j WASHINGTON, D. C. 20555

%,*****.d MAINE YANKEE ATOMIC POWER COMPANY-DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96.

License No. DPR-36

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The applications for amendment by Maine Yankee Atomic Power Company (the licensee), dated January 12 and 21, 1987 comply 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 applications, 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 g-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.

l 8704230596 670409 PDR ADOCK 05000309 P PDR

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.B(6)(b) of Facility.0perating License No. DPR-36 is hereby amended to-reaa as follows:

(b) Technical Specifications The Technical Specifications contained'in Appendix A, as revised through Amendment No. 96 , 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'N CLEAR REGULATORY COMMISSION JRfadsw

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Ashok C 'ThadIi, Director PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: Aoril 9,1937

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-! . ATTACHMENT TO LICENSE AMENDMENT NO. 96 l

FACILITY OPERATING LICENSE NO. DPR-36 l

DOCKET NO. 50-309 I l

j Revise Appendix A as follows:

Remove Pages Insert Pages 2.2-1 2.2-1 3.10-9 3.10-9 3.10-12 3.10-12 3.10-13 3.10-13 4

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, 2.2 SAFETY LIMITS - REACTOR CORE Applicability Applies to the limiting combinations of reactor power, and Reactor Coolant System flow, temperature, and pressure during operation.

Objective 4

To maintain the integrity of the fuel cladding and prevent the release of significant amounts of fission products to the reactor coolant.

Specifications A. The reactor and the Reactor Protection System shall be operated such that the Specified Acceptable Fuel Design Limit (SAFDL) on the departure from nucleate boiling heat flux ratio (DNBR):

DNBR = 1.20 using the YAEC-1 DNB heat flux correlation is'not exceeded during normal operation and anticipated operational occurrences.

B. The reactor and the Reactor Protection System shall be. operated such that the SAFDLs for prevention of fuel centerline melting.

A steady-state peak linear heat rate equal to:

Fuel Type LHGR Limit, kw/ft BOC E0C E YT 3 20.6 M,L 20.9 19.8 N 22.2 20.9 P 23.1 22.2 are not exceeded during normal operation and anticipated operational occurrences. The LHGR limit for each fuel type decreases linearly with Core Av.erage.Burnup. (CA8). The E0C Burnup for purposes of establishing a lin~ ear relationship is 13,500 MWD /MTV CAB.

Basis To maintain the integrity of the fuel cladding, thus preventing fission product release to the Primary System, it is necessary to. prevent overheating of the cladding. This is accomplished by operating within the nucleate boiling regime of heat transfer, and with a peak linear heat rate that will not cause fuel i centerline melting in any fuel rod. First, by operating within the nucleate j boiling regime of heat transfer, the heat transfer coefficient is large enough  ;

so that the maximum clad surface temperature is only slightly greater than the I coolant saturation temperature. The upper boundary of the nucleate boiling regime is termed " Departure from Nucleate Boiling" (DNB). At this point, there is a sharp reduction of the heat transfer coefficient, which would result in higher cladding temperature and the possibility of cladding failure.

Amendment No. 29,fa$,7f,7$,pp,96 2.2-1 l

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