ML17037C207

Letter Responding to a September 17, 1974 Letter Requesting a Response to Two ACRS Identified Items Concerning Main Steam Isolation Valve Leakage and Inservice Inspection of the Reactor Pressure Vessel and Advising That Inform.

ML17037C207
Person / Time
Site:	Nine Mile Point
Issue date:	09/25/1974
From:	Raymond P Niagara Mohawk Power Corp
To:	Lear G US Atomic Energy Commission (AEC)
References
Download: ML17037C207 (4)

Text

AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPORARY fORM)

CONTROL NO: '9992 FILE.

FROM Niagara 1@hawk Per Corp DATE OF DOC DATE REC'D LTR TWX RPT OTHE R Syracuse, N.Y. 13202 Hr. P.D. Ravmond 9-25-74 9-28-74 TO: ORIG CC OTHER SENT. AEC PDR G. Lear 1 signe'd SENT LOCAL PDR XXX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

XXX 1 50-220 DESCR IPTION: ENCLOSURES:

Ltr re our 9-17-74 ltr...furn info concerning Hain Steam Isolation Valve Leakage and Inservice Inspection of the reactor Pressure Vessel ~ ~ ~ ~

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PL'ANT NAME: Nine Hile Point (J'1

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W/ Copies CLARK (L)

W/ Copies W/ Copies STOLZ (L)

W/ Copies W/ Copies DICKER (E)

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W//Copies PARR (L) VASSALLO (L) KNIGHTON (E)

W/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L) PURPLE (L) YOUNGBLOOD (E)

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DENISE TEDESCO REGAN SMITH (L) KLECKER

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NIAGARA MOHAWK POWER CORPORATION NIAGARA i MOHAWK 300 ERIE BOULEVARD WEST SYRACUSE. N. Y. I3202 September 25, 1974 Mr. George Lear, Chief Operating Reactors Branch 83

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Directorate of Licensing SEP8819W ~

United States Atomic Energy Commission O.S. AIOIIIC EIIEIIQy

'COIIIINIOII 1P Washington, D. C. 20545 'ReIOIlatary Oi halt Sect!ac ~

Re: Nine Mile Point Unit 1

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Docket No. 50-220

Dear Mr. Lear:

Your letter of September 17, 1974, requested us to provide a response to two ACRS identified items. These items which are discussed in. the September 10, 1974, ACRS Report, concern main steam isolation valve leakage and inservice inspection of the reactor pressure vessel.

As stated at the ACRS meeting, we believe that planned changes to the main steam isolation valves will allow us to maintain acceptable leakage rates. Information concerning leakage from future t:ests will be forwarded to you in a timely manner to allow close consideration by your Staff.

Reactor vessel integrity and inservice inspection are under continuing review by our technical personnel. These investigations include possible improvements to vessel accessibility. Any improve-ments developed either within the industry or as a result of specific, Niagara Mohawk studies will be implemented to the degree practical.

Very truly yours, k g COCIIGEC

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