ML18040A252

Provides Supplemental Info Re Three Relief Requests VG-2,LP-RR-2 & CRD-RR-3

ML18040A252
Person / Time
Site:	Nine Mile Point
Issue date:	02/28/1997
From:	Mccormick M NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-1482 NMP1L-1189, NUDOCS 9703100006
Download: ML18040A252 (6)

Text

CATEGORY 1 REGULATC INFORMATION DISTRIBUTION +TEM (RIDE)

ACCESSIONQNBR:9703100006 DOC.DATE: 97/02/28 NOTARIZED: NO DOCKET FACIL4-;.50-~20 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 AUTH.NAAE AUTHOR AFFILIATION MCCORMICK,M.J. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides supplemental info re three relief requests VG-2,LP-RR-2 & CRD-RR-3.

DISTRIBUTION CODE: A047D TITLE: OR COPIES RECEIVED:LTR I Submittal: Inservice/Testing/Relief from ENCL 8 SIZE:

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NIAGARA MOHAWK G ENERATION NINE MILE POINT NUCLEAR STATION/LAKEROAD, P.O. BOX 63, LYCOMING, NEW YORK 13093/TELEPHONE (315) 349.2660 FAX (315) 349-2605 BUSINESS GROUP February 28, 1997 MARTINJ. McCORMICK JR. P.E. NMPlL 1189 Vice President Nuclear Engineering U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit 1 Docket No. 50-220

Subject:

Relief Requests Gentlemen:

This letter provides supplemental information to three relief requests submitted in a letter dated August 9, 1996 (5MP1L 1110). These relief requests were VG-2 (Rev. 1), LP-RR-2 (Rev.

1), and CRD-RR-3 (Rev. 1). The supplemental information provided by this letter is in response to matters discussed with the Staff during recent telephone conferences.

With regard to relief request VG-2 (Rev. 1), primary containment isolation valves will be leak tested in accordance with Option B of Appendix 3'f 10CFR50 and Part 10 of ASME/ANSI OMa-1988 (OM-10) Sections 4.2.2.2, 4.2.2.3(e) and 4.2.2.3(f).

Regarding relief requests LP-RR-2 (Rev. 1) and CRD-RR-3 (Rev. 1), Niagara Mohawk has proposed to verify valve closure during each refueling outage, either by performing a I

10CFR50 APPENDIX leak test or by applying differential pressure across the valve. This proposal is consistent with OM-10 Paragraph 4.3.2, which allows full-stroke exercising that is not practical during power operation or cold shutdown to be deferred to refueling outages.

Furthermore, the relief requests also document the justification for deferral of closure testing in accordance with OM-10, Paragraph 6.2(d). These two relief requests involve four check valves, and therefore, the provisions of OM-10 Paragraph 4.2.1, related to stroke time testing, is not applicable. Accordingly, Niagara Mohawk willrevise the IST Program to reference paragraph 3.1.1.3 of NUREG-1482, "De-inerting Containment of Boiling Water Reactors to Allow Cold Shutdown Testing," for these two relief requests, except that Paragraph 4.2.1 of OM-10, related to stroke time testing, does not apply.

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Page 2 Ifadditional information is needed with regard to these three relief requests, please contact Anthony Zallnick (315) 349-2428 of our Licensing staff.

Very truly yours, M.. McCormick Jr.

Vice President Nuclear Engineering AFZ/kap xc: Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. S. S. Bajwa, Acting Director, Project Directorate I-l, NRR Mr. B. S. Norris, Senior Resident Inspector Mr. D. S. Hood, Senior Project Manager, NRR Records Management

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