ML20126H607

Amend 135 to License DPR-36,making Two Corrections to Core Operating Limits Presented in TS 5.14.1

ML20126H607
Person / Time
Site:	Maine Yankee
Issue date:	12/29/1992
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126H592	List: ML20126H587 ML20126H607 ML20126H621
References
NUDOCS 9301050267
Download: ML20126H607 (4)

Text

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Q #lpsnauq'o, UNITE D STATES n NUCLEAR REGULATORY COMMISSION

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%, . . . p MAINE YANKEE ATJ)MIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.135 License No. DPR-36

1. The Nuclear Regulatory Comission (the Comission or the NRC) has found that:

A. The application for amendment filed by the Maine Yankee Atomic Power Company (the licensee) dated August 31, 1992, 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 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 Comission's regulations set forth in 10 CFR Chapter I; 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.B (6)(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:

9301050267 921229 9 DR ADOCK 0500

-l 2-Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.135, 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 its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION l -

Walter R. Butler, Director Project Directorate 1-3 Division of Reactor Projects - 1/!!-

0,ffice of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: December 29, 1992

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ATTACHMENT TO llCENSE AMENDMENT N0.135 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is-identified by Amendment-number and contains vertical lines indicating the areas of change.

Remove Insert 5.14-1 5.14-1 _

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5.14 (pre coeratina Limits Reoort 5.14.1 The core operating limits shall be established and documented in the Core Operating Limits Report before each reload cycle for the following:

a. Coefficients A, B, C, A, and QRi of the Thermal Margin / Low Pressure reactor trip limit as defined in Specification 2.1.1.b.

b. The Symmetric Offset trip function as defined in Specification 2.1.1.c.

c. (deleted)

d. The CEA insertion limits as defined in Specification 3.10 A.l.

e. The shutdown margin requirement as a function of percent power level ar,J RCS boron concentration as defined in Specification 3.10.B.I.

f. The peak linear heat generation limits as defined in Specification 3.10.C.1.

g. The maximum allowable unrodded radial power peaking factor as defined in Specification 3.10.C.2.

h. The excore symmetric offset limits (with the incore monitors inoperable), LOCA limiting, with and without CEAs restricted to above. the 100% rated power insertion limit as defined in Specification 3.10.C.2. -

i. The excore symmetric offset limits (with the incore l monitors operable), with and without turbine operation in the IMPIN mode as defined in Specification 3.10.C.2.

J. The allowable increase in the total radial peaking factor with the CEAs restricted to above the 100% rated power insertion limit as defined in Specification 3.10.C.2.

k. The coefficients R and CR as defined in Specification 3.10.C.3.

5.14.2 The analytical methods used to determine the core operating limits shall be limited to those previously reviewed and approved by thu NRC as follows:

Tech. Spec. 2.1

1. YAEC-1110 " Maine Yankee Reactor Protection System Setpoint-Methodology", dated September, 8.976.

2. YAEC-1296P, "0NBR Limit Methodology and Application to the Maine Yankee Plant", dated January, 1982.

Amendment No. J2f,135 5.14-1

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