ML20210V153

Amend 92 to License DPR-36,revising Tech Specs to Increase Fuel Enrichment Limit to 3.5 Weight Percent U-255 for Cycle 10 & Beyond

ML20210V153
Person / Time
Site:	Maine Yankee
Issue date:	02/09/1987
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210V096	List: ML20210V091 ML20210V153 ML20210V183
References
NUDOCS 8702180700
Download: ML20210V153 (4)

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p, NUCLEAR REGULATORY COMMISSION s j WASHINGTON, D. C. 20665

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MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 92 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 November 25, as supplemented December 8, 1986, complies 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 confomity 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 comon I defense and security or to the health and safety of the public;

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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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0702100700 070209 PDR ADOCK 05000309 P PDR l

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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 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. 92 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. Yais license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i

[hst M^

Ashok . T'hadani, Director

• r PWR Pr ject Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical i Specifications Date of Issuance: February 9, 1987 i

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To ATTACHMENT TO LICENSE AMEN 0 MENT NO. 91 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise Appendix A as follows:

Remove Page Insert Page Q 1.3-1 1.3-1

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7, 1.3 REACTOR Applicability Applies to the reactor vessel, vessel core and internals, as well as the Reactor Coolant System and components, including associated Emergency Core Cooling Systems.

Objectives To define those design criteria essential in providing for safe system operation which are not covered in Sections 2 and 3.

Specification A. Reactor Core The reactor core shall contain 217 fuel assemblies with each assembly containing 176 rods. Each fuel rod clad with Ziracloy-4 shall have a nominal active fuel length of 136.7 inches. The fuel shall have a maximum nominal , enrichment of 3.50 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.

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

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l Amendment No. 29,50,66,68,gJ,92 1.3-1 L _