ML20127B072

Application for Amend to License DPR-36,consisting of Proposed Change 117 Re Cycle 9 Operation. Cycle 9 Core Performance Analysis Encl.Fee Paid

ML20127B072
Person / Time
Site:	Maine Yankee
Issue date:	06/14/1985
From:	Randazza J Maine Yankee
To:	NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation
Shared Package
ML20127B075	List: ML20127B072 ML20127B077 ML20127B083
References
5706L-HFJ, MN-85-117, NUDOCS 8506210351
Download: ML20127B072 (3)

Text

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• EDISON DRIVE MAME HARHEE ATOMICPOWERCOMPARUe suausra. uannE oasas

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(207) 623-3521 1

June 14, 1985 MN-85-ll7 Proposed Change #117 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk

References:

(a) License No. [PR-36 (Docket No. 50-309)

(b) MYAPCo Letter to USNRC dated November 29, 1984 (MN-84-204)

RETRAN-02 Main Steam Line Break Model Application for Maine Yankee (c) MYAPCo Letter to USNRC dated January 14, 1985 (MN-85-09)

Modified Method for CEA Ejection Analysis

Subject:

Proposed Changes to the Maine Yankee Technical Specifications for Cycle 9 Gentlemen:

Maine Yankee expects to start up its ninth operating cycle as early as October 1, 1985, following the Cycle 8/9 refueling outage.

This letter transmits licensing material supporting Cycle 9 operation for USNRC review and Proposed Technical Specification which require your prior approval. Enclosed are the following:

Enclosure A: Summary Description of Cycle 9 Technical Specification Changes.

B: Proposed Cycle 9 Technical Specification Change pages.

C: Cycle 9 Core Performance Analysis Report.

The Cycle 9 Core Performance Analysis Report presents design and analysis results pertinent to the operation of Cycle 9. These include core fuel loading, fuel description, reactor power distributions, control rod worths, reactivity coefficients, the results of the safety analyses performed to define and justify plant operational limits, and the Reactor Protective System (RPS) setpoints assumed in the safety analyses. The report also describes the startup test program which is planned for Cycle 9. This program is identical to the program conducted for Cycle 8. The analysis results, in conjunction with the startup test results, RPS setpoints and Technical Specifications, serve as the basis for ensuring safe operation of Maine Yankee during Cycle 9.

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MAINE YANKEE ATOMIC POWER COMPANY

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United States Nuclear Regulatory Commission. Page Two

' Attention: Document Control Desk *-85-117

-The Proposed Technical Specification. Changes for Cycle 9 operation are submitted in accordance.with 10 CFR 50.59. These changes are itemized below:

0 ~ Replace page 1.3-1 of Specification 1.3 with the enclosed page 1.3-1.

• Replace pages 2.1-1 and 2.1-4 through 2.1-6 of Specification 2.1 with the enclosed pages 2.1-1 and 2.1-4 through 2.1-6.

• Replace page 2.2-1 of Specification 2.2 with the enclosed page 2.2-1.

o - Replace pages 3.10-8 through 3.10-14 and 3.10-16 through 3.10-19 of Specification 3.10 with the enclosed pages 3.10-8 through 3.10-14 and 3.10-16 through 3.10-19.

We are submitting this reload package so as to provide more than the customary ninety days allowed for NRC review in response to a request from your staff. .We request NRC approval to these proposed technical specifications by' late September, 1985 so as not to delay startup.

This proposed change has been reviewed by the Maine Yankee Plant

-Operations Review Committee and the Nuclear Safety Audit and Review Committee. The Plant Operations Review Committee has concluded that the modifications associated with Cycle 9 and the enclosed proposed technical Especifications do not constitute an unreviewed safety question.

Maine Yankee has evaluated the Cycle 9 reload and concluded that it does not involve a-significant hazards consideration. A summary of our evaluation follows.

The fuel assemblies' used in the Cycle 9 design are not significantly

.different than those previously used at Maine Yankee and found to be

acceptable byL the'l@C. l The acceptance criteria for the technical specifications ~ associated with the Cycle 9 design are the same as the acceptance criteria associated with the current technical specifications. The methods used to demonstrate conformance of the Cycle 9 design with applicable technical specifications either have been previously.found acceptable by the NRC, _ or have been submitted for approval' in References (b) and (c).

This proposed change does not involve a significant increase in the probability or consequences of an accident previously--evaluated, the possibility of a new or different kind of accident from any accident previously evaluated or a-significant reduction in a margin of safety.

Therefore, this proposed ' amendment does not ' involve a 'significant hazards consideration as defined in 10 CFR 50.92.

An application fee for $150.00 is enclosed with this. submittal.

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-5706L-HFJ

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. ... . MAINE YANKEE ATOMIC POWER COMPANY

' United States Nuclear Regulatory Commission Page Three Attention: Document Control Desk W-85-ll7 A State of Maine representative is being notified of this proposed change by a copy of this letter.

Very truly yours, MAIE YANKEE ATOMIC POWER COWANY M. ti _

JohnB3anda'zM Executive Vice President HFJ/bjp cc: Mr. Edward J. Butcher, Jr.

Dr. Thomas E. Murley Mr. Cornelius F. Holden Mr. Clough Toppan

Enclosures:

(A) Summary Description of Cycle 9 Technical Specification Changes.

(B) Proposed Cycle 9 Technical Specification Change pages.

(C) Cycle 9 Core Performance Analysis Report STATE OF MAIE )

COUNTY OF LINCOLN )

Then personally appeared before me, John B. Randazza, who being duly sworn did state that he is Executive Vice President of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on behalf of Maine Yankee Atomic Power Company, and that the-statements therein are true to the best of his knowledge and belief.

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