ML20133C205

From kanterella
Revision as of 19:47, 4 July 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Application for Amend to License DPR-36,consisting of Suppl 1 to Proposed Change 120,replacing Pages of Tech Specs Re turbine-driven Auxiliary Feedwater Pump
ML20133C205
Person / Time
Site: Maine Yankee
Issue date: 10/03/1985
From: Randazza J, Ransazza J
Maine Yankee
To:
NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation
Shared Package
ML20133C207 List:
References
6465L-GDW, MN-85-172, NUDOCS 8510070268
Download: ML20133C205 (2)


Text

-- -- - -- - - - - - - - - - - - - -

I 4

O MAmE HARHEE AMMICPOWERCOMPARUe ruausra$ain"e5 ky October 3, 1985 (20a 623-3521 g MN-85-172 Proposed Change # 120 l Supplement 1 l

Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk

References:

(a) License No. 03R-36 (Docket No. 50-309)

(b) MYAPCo Letter to US mC dated September 6, 1985 (MN-85-160)

Subject:

Proposed Change to Maine Yankee Technical Specifications - Turbine Driven Auxiliary Feedwater Pump, Supplement 1 Gentlemen:

This submittal replaces the proposed change forwarded by Reference (b) in its enti?.ety.

The specific change is as follows:

Replace pages 3.8-2 and 3.8-3 of the Maine Yankee Technical Specifications with the enclosed pages 3.6-2, 3.8-3 and 3.8-4.

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 involves a significant hazards consideration as defined by 10 CFR 50.92. A summary of our evaluation follows.

The accidents analyzed in the Maine Yankee Final Safety Analysis Report (FSAR) were evaluated. It was concluded that the proposed change could require a plant shutdown and affect the postulated loss of main feedwater.

The requirement to shut down the plant in the event the turbine driven auxiliary feedwater pump is not available involves securing the turbine driven main feedwater pump and eliminating one source of AC power to the motor driven main feedwater pumps. Tnus, main feedwater reliability would be reduced during the plant shutdown. However, the effect on the probability of a loss of main feedwater is not expected to be significant. The consequences of a loss of main feedwater are not affected by the proposed specification, since the turbine driven auxiliary feedwater pump is not required to mitigate this event.

5 h00N68851003 p ADOCK 05000309 00 6465L-GOW PDR h

MAINE YANKEC ATOMIC POWER COMPANY United States Nuclear Regulatory Commission Page Two Attention: Mr. Edward J. Butcher, Jr. MN-85-172 The proposed change does not create the possibility of a different kind of accident from any previously analyzed. As indicated in Reference (b), 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 the turbine driven auxiliary feedwater pump to be operable assures the availability of an additional and diversely powered feedwater supply to the steam generators. 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.

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 YANKEE ATOMIC POWER COWANY John B. Randazza Executive Vice President JBR/bjp

Enclosure:

(3 Pages) cc: Mr. Edward J. Butcher, Jr.

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.

d fG//M '

/

p' Notary Public s y . .a

.c. e i$ aup.'

$ i U MMt .!

  • i. ( ! Did 6465L-GDW

_ - _ - _ _ _ _ - _ - - _ _ _ _ _