ML17056B108
| ML17056B108 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/01/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | Burkhardt L NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML17056B109 | List: |
| References | |
| TAC-66071, TAC-75152, NUDOCS 9011190043 | |
| Download: ML17056B108 (6) | |
Text
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Docket No. 50-410 UNITED STATES NUCLEAR REGULATORY COMMtSSlON WASHINGTON, D. C. 20555 November 1,
1990 Mr. Lawrence Burkhardt III Executive Vice President - Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Burkhardt:
SUBJECT:
SAFETY EVALUATION OF FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN, NINE MILE POINT UNIT 2 (TAC NOS.
66071 AND 75152)
By letter dated July 30, 1987, (TAC No. 66071)
Niagara Mohawk Power Corporation (licensee) submitted to the NRC the Nine Mile Point Nuclear Station, Unit 2 First Ten-Year Interval Inservice Inspection (ISI) Program Plan.
Additional information was submitted by letter dated February 12, 1988.
The program plan was submitted for review and evaluation of its compliance with the require-ments of the 1983 Edition through Summer 1983 Addenda of Section XI of the ASME Boiler and Pressure Vessel code with the following exceptions:
(1) the extent of examination for Code Class 1 piping welds has been determined by the 1974 Edition through Sumer 1975 Addenda (74S75),
as permitted by 10 CFR 50.55a(b),
and (2) the extent of examination for Code Class 2 piping welds has been determined by ASME Code Case N-408, "Alternative Rules for Examination of Class 2 Piping."
The NRC staff, with technical assistance from EG&G Idaho, Inc.
(EG&G), has reviewed and evaluated the ISI program and requests for relief submitted for Nine Mile Point Unit 2.
The staff adopts the evaluations and conclusions contained in the enclosed Technical Evaluation Report (TER) as prepared by EG&G subject to the revisions discussed below for relief requests RR-IWB-4, RR-IWB-6, RR-IWB-12, RR-IWC-2, and RR-IWC-4.
The EG&G, Inc. review reported in the TER included the July 30, 1987, original submittal and the February 12, 1988, additional information.
The staff's review also included information submitted in letters dated May 19, 1989 and February 27, 1990 (TAC No. 75152) revising relief requests that were previously submitted (RR-IWB-4, RR-IWB-6, RR-IWB-12, RR-IWC-2, and RR-IWC-4).
The staff has evaluated the revised requests and has determined that they, in effect, either add additional welds to the program, change valve numbers, document increased examination coverage, or delete welds from the program for which relief from an examination requirement would not have been granted.
The staff's evaluation of these revised relief requests is included in the enclosed safety evaluation.
9011190043 901101
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Mr. Burkhardt III 2
The staff has denied relief from the code requirements where the necessary findings could not be made (RR-IWB-13, and RR-IWB-6 as initially submitted).
The relief requested in RR-IWB-6, as revised, has been granted.
For the relief that is being granted, we have determined that the Code require-ments are impractical and that the relief requests are authorized by law and will not endanger life, property or the common defense and security and are otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements wer e imposed on the facility.
The requests for relief comply with the standards and 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 l.
Accordingly, relief from certain provisions of Section XI of the ASME Boiler and Pressure Vessel Code and the applicable addenda is hereby granted, as described in the enclosed Safety Evaluation.
This completes our efforts in response to your submittals as listed above and their associated TAC Nos.
66071 and 75152.
Sincerely,
Enclosures:
1.
Safety Evaluation 2.
TER No.
EGG-ESM-7888 Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc w/enclosures:
See next page
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CC:
Mr. Mark J. Wetterhahn, Esquire
- Bishop, Cook, Purcell 8 Reynolds 1400 L. Street, N.W.
Washington, D. C. 20005-3502 Regional Administrator, Region I U.S. Nuclear Regulatory Comnission 475 Al lenda le Road King of Prussia, Pennsylvania 19406 Hr. Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus
- Syracuse, New York 12223 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.
Box 99
- Lycoming, New York 13093 Mr. Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New Yor k 13202 Mr. Peter E. Francisco, Licensing Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 Ms.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New York 12223 Supervisor Town of Scriba R. D. ¹4
- Oswego, New York 13126 Charlie Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Mr. Richard H. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue
- Albany, New York 12210 Mr. Richard Abbott, Unit 2 Station Superintendent Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P. 0.
Box 32
- Lycoming, NY 13093 Hr. Joseph F. Firlit, General Supt.,
Nuclear Generation Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P. 0.
Box 32 Lycoming, New York 13093
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