ML17054B659

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Forwards Safety Evaluation Granting Relief from ASME Boiler & Pressure Vessel Code,Section XI Concerning Repair or Component Replacement Based on Impracticality,Per Util 850513 & 14 Requests
ML17054B659
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/15/1985
From: Vassallo D
Office of Nuclear Reactor Regulation
To: Hooten B
NIAGARA MOHAWK POWER CORP.
Shared Package
ML17054B660 List:
References
NUDOCS 8505290755
Download: ML17054B659 (6)


Text

May 15, 1985 Docket No. 50-220 Mr. B. G. Hooten Executive Director, Nuclear Operations Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202

Dear Mr. Hooten:

SUBJECT:

RE(UEST FOR RELIEF FROM ASME BOILER AND PRESSURE VESSEL

CODE, SECTION XI, PARAGRAPH IWA-4210 Re:

Nine Mile Point Nuclear Station, Unit No.

1 By letter dated May 13, 1985 and supplemented by letter dated May 14, 1985, pursuant to 10 CFR 50.55a(g)(6)(i),

you submitted a request for relief from the provisions of Paragraph IWA-4210 of the ASME Boiler and Pressure Vessel Code which requires repairs be performed in accordance with the design and construction code for a component.

You stated that the performance of a Code repair or component replacement is not practical at this time in light of the complexity of the weld repair and the lead time necessary to get qualified replacement components.

We have reviewed the technical merits of your request and supporting information contained in your letters and provided by your staff at our meeting on May 14, 1985.

We have determined that the-Code repair requirement is impractical to perform and, pursuant to 10 CFR 50.55a(g)(6),

have determined that the proposed alternatives to the described requirements will provide an acceptable level of quality arid safety.

Accordingly, we have determined that this relief is authorized by law, and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.

A copy of our Safety Evaluation is enclosed.

8505290755 8505i5 PDR ADOCK 05000220I'",

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Mr. B. G. Hooten You are therefore authorized to consider the heat exchangers operable, with the interim repairs as described, if the surveillance testing is performed monthly and any associated leakage of raw water is less than 74 gallons per minute.

This relief is effective until the end of the Spring 1986 refueling outage.

Sincerely,

Enclosure:

As stated cc w/enclosure:

See next page DISTRIBUTION NRC PDR Local PDR ORBf/2 Reading HThompson OELD SNorris RHermann ELJordan JPartlow BGrimes ACRS (10)

Gray File FCherny BDLiaw JKudrick BSheron GLainas Original signed by/

Domenic B. Vassallo, Chief Operating Reactors Branch 82 Division of Licensing

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Mr. B. G. Hooten Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station, Unit No.

1 CC:

Troy R. Conner, Jr., Esquire Conner 5 Wetterhahn Suite 1050 1747 Pennsylvania

Avenue, N.

W.

Washington, D. C.

?0006 Frank R. Church, Supervisor Town of Scriba R.

D. 82

Oswego, New York 13126 Niagara Mohawk Power Corporation ATTN:

Mr. Thomas Perkins Plant Superintendent Nine Mile Point Nuclear Station Post Office Box 32

Lycoming, New York 13093 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126
Lycoming, New York 13093 John W. Keib, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard Hest
Syracuse, New York 13202 Thomas A. Murley Regional Administrator Region I Office U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza
Albany, New York 12223