ML20138P627

Application for Amend to License DPR-36,consisting of Suppl 1 to Proposed Change 110,revising Tech Spec Pages 4.6-1,4.6-3 Through 4.6-6 & 4.1-9 Re Emergency Feedwater Sys

ML20138P627
Person / Time
Site:	Maine Yankee
Issue date:	12/13/1985
From:	Randazza J Maine Yankee
To:	NRC OFFICE OF ADMINISTRATION (ADM)
Shared Package
ML20138P631	List: ML20138P627 ML20138P636
References
6545L-SDE, MN-85-186, NUDOCS 8512260200
Download: ML20138P627 (9)

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%(fje (207) 623-3521 December 13, 1985 MN-85-186 Proposed Change No. 110 Supplement 1 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk

References:

(a) License No. OPR-36 (Docket No. 50-309)

(b) MYAPCo Letter to USNRC dated January 14, 1985 (MN-85-10)

Proposed Change No. 110 - Emergency Feedwater System Technical Specifications (c) USNRC Letter to MYAPCo dated May J4, 1985 - AFW Evaluation (d) MYAPCo Letter to USNRC dated September 6, 1985 (MN-85-160)

Subject:

Emergency Feedwater System Technical Specification, Proposed Change No. 110, Supplement 1 Gentlemen: '

This submittal supplements and replaces the proposed change to Maine Yankee's Technical Specifications submitted in Reference (b).

The specific change is as follows:

Replace pages 4.6-1, 4.6-3 through 4.6-6 and 4.1-9 of the Maine Yankee Technical Specifications with the enclosed pages. Add the enclosed page 4.1-9a to Specification 4.1.

This supplementary proposed change requires monthly operability testing of the turbine driven auxiliary feedwater pump. This proposed change would result in the frequency of operability testing of the turbine driven auxiliary feedwater pump in conformance with the Staff's recommendation 1 (at page 16) of Reference (c).

Title 10 of the Code of Federal Regulations, Section 50.92 states in part, that a proposed technical specification involves a significant hazards consideration if it (1) involves a significant increase in the probability or consequences previously analyzed; (2) creates the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involves a significant reduction in a margin of safety.

We have performed an evaluation to determine whether this proposed change 00 involves a significant hazards consideration as defined by 10 CFR 50.92. A q summary of our evaluation follows. 3 8512260200 851213 9 ADOCK 0500 M.

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• MAINE YANKEE ATOMIC POWER COMPANY United States Nuclear Regulatory Commission Page Two

-Attention: Document Control Desk M4-85-186 The proposed change does not involve a significant increase in the

_ probability _ or consequences _ of an accident previously analyzed nor does it

- create the. possibility of.a different kind of accident. from any previously analyzed. . As indicated in Reference (d), the turbine driven auxiliary feedwater pump is not necessary to mitigate design basis accidents, however, it is capable of_ mitigating certain non-design basis accidents such as the loss of all main feedwater and auxiliary feedwater which could result from

-multiple independent events or the loss of all AC power.

. The requirement for monthly testing of the turbine driven auxiliary feedwater pump verifles its operability by recirculating water to the

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demineralized water _ storage tank. This does not result in a significant reduction in a margin of safety.

Based on.the above, we have concluded that the proposed change does not involve a significant hazards consideration as defined by 10 CFR 50.92.

This proposed change has been reviewed by the Plant Operations Review Committee and the Nuclear Safety Audit and Review Committee.

2 A State of Maine representative is being notified of this requested change

~ to the Technical Specifications by, a copy of.this letter.

Very truly yours, MAINE YAtKEE ATOMIC POWER COWANY

$?e c John B. Randazza Executive Vice President JBR/bjp

Enclosure:

( Pages) cc: Mr. Ashok Thadani Dr. Thomas E. Murley-Mr. Cornelius F. Holden Mr. Clough Toppan STATE OF MINE 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, h lh0 G D. WH MY COMMIS ON P S0T R 19,1991

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