ML17059A263
| ML17059A263 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/06/1994 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML17059A264 | List: |
| References | |
| TAC-M83099, NUDOCS 9404180368 | |
| Download: ML17059A263 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 6, 1994 Docket No. 50-220 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, New York 13093
Dear Hr. Sylvia:
SUBJECT:
SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF NINE MILE POINT NUCLEAR STATION UNIT NO.
1 (TAC NO. H83099)
By letter dated March 30,
- 1992, Niagara Mohawk Power Corporation (NMPC),
submitted the Second 10-Year Interval Inservice Inspection Program Plan (NHPI-ISI-002, Revision 0), the Component Support Program Plan (NMPI-IWF-003 Revision 0), Pressure Testing Program Plan (NHP1-PT-004, Revision 0),
and associated requests for relief from the ASME Code requirements that NHPC had determined to be impractical to perform during the Second 10-Year Inservice Inspection Interval for Nine Mile Point Nuclear Station Unit No.
1 (NHP-1).
By letter dated February 5,
- 1993, NHPC responded to the NRC staff's December 3, 1992, request for additional information (RAI) regarding the Second 10-Year Inservice Inspection Program Plan.
Clarification to a relief request contained in the February 5,
1993, submittal was provided in a NMPC letter dated April 21, 1993.
An additional RAI to assess the proposed reclassification of the control rod drive hydraulic, high-pressure coolant injection, reactor feedwater, condensate pump inlet, and shutdown cooling systems from safety-related to nonsafety-related was issued by the NRC staff on September 29, 1993; NHPC responded to this RAI by letter dated November 3, 1993.
The NRC staff,; with technical assistance from its contractor, the Idaho National Engineering Laboratory, has reviewed and evaluated the Second 10-Year. Interval Inservice Inspection Program Plan, Component Support Program
- Plan, Pressure: Testing Program Plan, associated relief requests, and additional information submitted in response to our RAI.
The conclusions and recommendations of our contractor are presented in the enclosed Technical Evaluation Report (TER)
(EGG-MS-10769, June 1993).
Our contractor concluded in its TER that the NHP-1 Second 10-Year Interval Inservice Inspection Program Plan was unacceptable and not in compliance with 10 CFR 50.55a(g)(4),
because the control rod drive hydraulic, high-pressure coolant injection, reactor feedwater, condensate pump inlet, and shutdown cooling systems had been reclassified as nonsafety-related without prior NRC review and approval.
Upon further review of the reclassified
- systems, the NRC staff concluded that the proposed reclassifications were acceptable.
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Hr. B. Ralph Sylvia April 6, 1994 We have determined that certain ASHE Code Section XI requirements cited by NMPC are impractical to perform at NHP-1.
In such instances, we have granted relief from those requirements.
A summary of the requirements and the bases for granting relief are contained in the TER.
For the relief that is being granted, we have determined that the examination methods required by the ASHE Code, as indicated in the TER, are impractical and that the relief granted is authorized by law and will not endanger life, 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'esult if the requirements were imposed on the facility.
The requests for relief comply with the standards and the requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter 1.
Accordingly, relief from certain provisions of Section XI of the ASHE Boiler and Pressure Vessel Code and the applicable addenda is hereby granted, as described in the enclosed safety evaluation and TER.
Sincerely,
Enclosures:
1.
Safety Evaluation 2.
Technical Evaluation Report cc w/enclosures:
See next page Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
4
Hr. B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No.
1 CC; Mark J. Wetterhahn, Esquire Winston
& Strawn 1400 L Street, NW Washington, DC 20005-3502 Supervisor Town of Scriba Route 8, Box 382
- Oswego, New York 13126 Mr. Louis F. Storz Vice President - Nuclear Generation Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, New York 13093 Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 126
- Lycoming, New York 13093 Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Ms.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New Yor k 12223 Hr,. Richard B. Abbott Unit 1 Plant Manager Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, New York 13093 Hr. David K. Greene Manager Licensing Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, New York 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Hr. Paul D.
Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza
- Albany, New York 12223 Hr. Hartin J. HcCormick, Jr.
Vice President Nuclear Safety Assessment and Support Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, New York 13093
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