ML17058A770

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Grants 901115 Inservice Testing Relief Requests CTS-RR-2 (Containment Spray Sys) & VG-2 (General Relief Request for Containment & Pressure Isolation Valves).Safety Evaluation Encl
ML17058A770
Person / Time
Site: Nine Mile Point 
Issue date: 05/30/1991
From: Capra R
Office of Nuclear Reactor Regulation
To: Sylvia B
NIAGARA MOHAWK POWER CORP.
Shared Package
ML17058A771 List:
References
TAC-79447, NUDOCS 9106040290
Download: ML17058A770 (6)


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~ +*ac" Docket No. 50-220 I

UNITED STATES NUCLEAR REGULATORY COMMISSION

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= 'ASHINGTON, D.C. 20555 May 30, 1991 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road

Syracuse, New York 13211

Dear Mr. Sylvia:

SUBJECT:

NINE MILE POINT NUCLEAR STATION UNIT NO.

1 IST RELIEF REQUESTS CTS-RR-2 AND VG-2 (TAC NO. 79447)

By letter dated November 5,

1990, Niagara Mohawk Power Corporation (NMPC) submitted Inservice Testing Relief Requests CTS-RR-2 (for the Containment Spray System) and VG-2 (a general relief request for containment and pr essure isolation valves) for Nine Mile Po'int Nuclear Station Unit No.

1.

Relief Request CTS-RR-2 would provide relief from the full-stroke exercising requirement of ASME Code,Section XI, paragraph IWV-3522, for four containment spray pump discharge check valves.

NMPC determined that full-stroke exercising of these valves would be impractical and burdensome.

Accordingly, NMPC proposed that full-stroke exercising of these valves in accordance with the requirements of ASME Code,Section XI, paragraph IWX-3522, would not be required.

Relief Request VG-2 would provide relief from the trending requirements of ASME Code,Section XI, paragraph IWV-34227(b), for containment isolation valves designated LJ and LA and relief from the leak rate testing requirements of paragraphs IWV-3421 through 3425 as well as the trending requirements of IWV-3427(b) for pressure isolation valves designated LK.

NMPC determined that these trending and leak rate testing requirements would be impractical and burdensome.

Accordingly, these trending and leak rate testing requirements would not be required; however, alternative testing requirements would be implemented.

The NRC staff has reviewed the relief requests and has provided the enclosed safety evaluation.

The staff has concluded that the burden placed on NMPC by the requirements of the Nine Mile Point Unit 1 Inservice Testing Program Plan for quarterly fu'Il-stroke exercising of the containment spray pump dischar'ge check valves 80-05, 80-06, 80-25 and 80-26 is unwarranted.

Therefore, pursuant to 10 CFR 50.55a(g)(6)(i); Relief Request CTS-RR-2, which provides for partial flow tests, is granted for a interim period of one year or until the next (1992) refueling outage, whichever is longer.

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Hr. B. Ralph Sylvia May 30, 1991 The staff has also concluded that the burdens placed on NNPC by the trending and leak test requirements for containment isolation valves designated LJ and LA and for pressure isolation valves designated LK are unwarranted.

NNPC has proposed an alternate testing program which provides an acceptabl'e level of quality and safety for these valves.

Therefore, pursuant to 10 CFR 50.55a(a) (3) (i), Relief Request VG-2 i s granted.

For the relief that is being granted the staff has determined that the Code requirements 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 were imposed on the facility.

The request for relief complies 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 1.

Accordingly, relief from certain provisions of Section XI of the ASNE 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 submittal as listed above and its associated TAC No. 79447.

Sincer ely,

Enclosure:

Safety Evaluation of Relief Request cc w/enclosure:

See next page Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects

- I/II Office"of Nuclear Reactor Regulation

1

Mr. B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No.

1 CC Hr. Mark J. Wetterhahn, Esquire Winston 5 Strawn 1400 L Street, NW.

Washington, D.C.

20005-3502 Supervisor Town of Scriba R.

D. 84

Oswego, New York 13126 l1r. Joseph F. Firlit Vice President

- Nuclear Generation Niagara Mohawk Power Corporation 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 Mr. 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 Hs.

Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor

Albany, New York 12223 Mr. Kim Dahlberg Unit 1 Station Superintendent Nine Mile Point Nuclear Station Post Office Box 32
Lycoming, New York 13093 Mr. David K. Greene Manager Licensing Niagara Mohawk Power Corporation 301 P la infiel d Road
Syracuse, New York 13212 Charlie Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Mr. Paul D.

Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza

Albany, New York 12223