ML20196G680

Amend 105 to License DPR-36,changing Max Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core for Operating Cycle 11 & Beyond from 3.5 to 3.7% Nominal Weight U-235

ML20196G680
Person / Time
Site:	Maine Yankee
Issue date:	06/23/1988
From:	Wessman R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19318E104	List: ML20196G676 ML20196G680 ML20196G687 ML20196G693
References
NUDOCS 8807060003
Download: ML20196G680 (4)

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.r, k g UNITED STATES NUCLEAR REGULATORY COMMISSION 5 j WASHINGTON, D. C. 20555

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MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. DPR-36

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

A. The application for amendment by Maine Yankee Atomic Power Company (the licensee), dated March 74, 1988 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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; 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.

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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)Ib) of Facility Operating License No. DPR-36 is hereby amended to read as'follows:

(b) Technical. Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.105, 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

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Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: June 23,1988

ATTACHMENT TO LICENSE AMENDMENT N0.105 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET N0. 50-309 Revise Appendix A as follows:

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1.3 - 1 1.3 - 1 t

1.3 REACTOR ADolicability Applies to the raattor vessel, vessel core and internals, as well as the Reactor Coolant System and components, including associated Emergency Core Cooling Systems.

Obiectives To define those design criteria essential in providing for safe system operation wh'.ch are not covered in Sections 2 and 3.

SDecification A. Reactor Core

, The reactor core shall contain 217 fuel assemblies with each assembly containing 176 rods. Each fuel rod clad with Zircaloy-4 shall have a nominal active fuel length of 136.7 inches. The fuel shall have a maximum nominal enrichment of 3.70 weight percent U-235.

l The core excess reactivity shall be controlled by a combination of boric acid chemical shim, Control Element Assemblies (CEAs) and mechanically '

fixed non-fuel rods when required. The non-fuel rods may be fixed alumina-boron carbide, solid metal or open tubes.

There are a total of eighty-one (81) full-length, full-strength CEAs provided. Forty (40) of these are paired to form twenty (20) dual CEAs.

Seventy-seven (77) CEAs, including all dual CEAs, are trippable. Four (4) of the CEAs are nontrippable, e

1.3-1 Amendment No. SW#9,SS,63,83/A,105