ML17263A634

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Discusses Util Revised MOV Program Description,Requiring That design-basis Dp Testing Be Required to Be Performed on Only One MOV in Parallel Train of Identical MOVs
ML17263A634
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/28/1994
From: Butler W
Office of Nuclear Reactor Regulation
To: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
References
GL-89-10, TAC-M83206, NUDOCS 9405040298
Download: ML17263A634 (7)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-000I April 28, 1994 Docket No. 50-244 Dr. Robert C. Mecredy Vice President, Nuclear Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649

Dear Dr. Mecredy:

SUBJECT:

PARALLEL TESTING OF MOTOR OPERATED VALVES (MOV) - R.

E.

GINNA NUCLEAR POWER PLANT (TAC NO. M83206)

By letter dated March 27,

1991, you indicated that the NRC staff's response to Generic Letter 89-10, Supplement 2, question 29, stated that test data from an MOV tested under design-basis conditions could be used to demonstrate operability of an identical MOV in a parallel train if justified properly.

Based on this response RGKE revised the MOV Program description to require that design-basis (differential pressure)

DP testing be required to be performed on only one MOV in a parallel train of identical MOVs, provided adequate margin above the thrust required to overcome DP is demonstrated.

If DP test results are satisfactory but adequate margin does not exist, the other valves in the parallel train will be DP tested.

During a Generic Letter (GL) 89-10 inspection in April, 1992, twelve DP tests were completed and eight were scheduled to be, completed prior to startup from the 1992 outage.

For those valves where in situ full flow and DP tests are not practicable, the licensee indicated that partial flow and partial DP tests would be conducted as part of the two stage approach.

The intention was to test only one of the valves in a parallel train of identical valves.

The team observed that this was not consistent with the GL recommendations to test all safety-related valves where practicable.

This observation was acknowledged and it was stated that the program will be changed to clarify that all valves will be tested where practicable.

You stated that written notification of this clarification would be provided.

In the enclosed letter, dated September 25, 1992, clarification was provided as requested as a result of the GL 89-10 inspection.

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Dr. Robert C. Hecredy April 28, 1994 This completes the staff's activities on TAC No. H83206.

Sincerely,

'riginal signed by:

Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosure:

Letter dated September 25, 1992 cc w/enclosure:

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April 28, 1994 Or. Robert C. Mecredy This completes the staff's activities on TAC No. M83206.

Sincerely,

Enclosure:

Letter dated September 25, 1992 Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc w/enclosure:

See next page

Dr. Robert C. Mecredy R.E.

Ginna Nuclear Power Plant CC:

Thomas A. Moslak, Senior Resident Inspector R.E.

Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road

Ontario, New York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Ms. Donna Ross Division of Policy Analysis 8 Planning New York State Energy Office Agency Building 2 Empire State Plaza
Albany, New Yor k 12223 Charlie Donaldson, Esq.

Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Nicholas S.

Reynolds Winston L Strawn 1400 L St.

N.W.

Washington, DC 20005-3502 Ms. Thelma Wideman

Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7370 Route,31
Lyons, New York 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Fall Road, Room ll Rochester, New York 14620

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