ML17250A898
| ML17250A898 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/26/1989 |
| From: | Andrea Johnson Office of Nuclear Reactor Regulation |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17250A899 | List: |
| References | |
| GL-83-28, TAC-53985, NUDOCS 8908020389 | |
| Download: ML17250A898 (5) | |
Text
Docket No. 50-244 Dr. Robert C. Mecredy General
- Manager, Nuclear Production Rochester Gas Im Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Dr. Mecredy:
July 26, 1989 DISTRIBUTION:
~Docket ~File NRC PDR Local PDR PDI-3 Reading SVarga BBoger BGrimes EJordan
- SWessman, DHaverkamp, RI AJohnson MRushbrook ACRS (10)
SUBJECT:
SAFETY EVALUATION FOR GENERIC LETTER 83-28, ITEM 4.5.3, REACTOR TRIP RELIABILITY-ON-LINE FUNCTIONAL TESTING OF THE REACTOR TRIP SYSTEM (TAC NO. 53985)
Generic Letter 83-28, Item 4.5.3, required confirmation from all licensees and applicants that on-line functional testing of the reactor trip system, includ-ing independent testing of the diverse trip feature, was being performed.
RG8E was required by Generic Letter 83-28, Item 4.5.3 to perform on-line functional testing of the reactor trip system, including independent testing of the diverse trip feature.
Existing intervals for on-line functional testing required by Technical Specifications were to be reviewed to determine that the intervals are consistent with achieving high reactor trip system availability when accounting for considerations such as:
(1) uncertainties in component failure rates; (2) uncertainty in common mode failure rates; (3) reduced redun-dancy during testing; (4) operator errors during testing; and (5) component "wear-out" caused by the testing.
The Westinghouse (NSSS Supplier)
Owners Group have submitted analyses to the NRC to respond to Generic Letter 83-28, Item 4.5.3 (Enclosure 3).
The NRC staff, with the assistance of our contractor Idaho National Engineering Laboratory, have reviewed the Owners Group reports listed in" Enclosure 2.
The enclosed Safety Evaluation Report (Enclosure I) is submitted to you as being applicable to the R.
E. Ginna Nuclear Power Plant.
You are hereby requested to indicate your endorsement of the Westinghouse Owners Group Reports applicable to Ginna, thus enabling us to complete our review of Item 4.5.3.
Sincerely,
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As stated cc w/enclosures:
See next page PDI-3 DIR/PD 3
AJo nson:mw RWessman 7/
89 7/4(0/89 Original Signed By Allen R. Johnson, Project Manager Project Directorate I-3 Division of Reactor Projects I/II
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Dr. Robert C. Mecredy July-.,26,, 19 B 9 cc w/enclosures:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire
- Avenue, N.W.
Suite 1100 Washington, D.C. '0036 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 York 12223 Mr. Bruce A. Snow, Superientendent Nuclear Production Rochester Gas Im Electric Corporation S9 East Avenue Rochester, New York 14649-0001 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271
Dr. Robert C
Mecredy July'6,'989 DISTRIBUTION:
NRC PDR Local PDR PDI-3 Reading NRushbrook SVarga
- BBoger, JZwolinski DHaverkamp, RI EJordan RWessman AJohnson ACRS (10)