ML17250A952
| ML17250A952 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/31/1989 |
| From: | Andrea Johnson Office of Nuclear Reactor Regulation |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-74494, NUDOCS 8909060106 | |
| Download: ML17250A952 (4) | |
Text
August 1989 Docket No. 50-244 Dr. Robert C. Mecredy General
- Manager, Nuclear Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649-0001
Dear Dr. Mecredy:
SUBJECT:
NRC STAFF REVIEW OF PRESSURIZER LEVEL AND PRESSURE INSTRUMENTATION MODIFICATION PURSUANT TO 10 CFR 50.59 FOR R.
E.
GINNA (TAC 74494)
This letter documents the subject review of R.
E. Ginna Station modifications to pressurizer level and pressure instrumentation with regards to (I) the RGSE Design Criteria No.
EWR 4218, Revision 3, August 3, 1989; and (2) the RGEE Safety Analysis No. 4218, Revision 3, August 3, 1989.
The NRC staff understands this temporary modification was initiated to resolve instrument drift associated with one out of three pressurizer level indications.
Attempts to calibrate the defective channel failed, and a reference leg was believed to be restrictive.
The proposed modification isolates the defective pressurizer level reference leg and modifies an alternate channel reference line such that two level transmitters share a
common reference leg.
Additionally, since both level and pressure transmitters utilize the same reference leg, it was also necessary to relocate the pressure transmitter sensing 'line to a sensor tap that was independent of any other pressure channel.
An NRC staff review of the FSAR and Technical Specifications revealed no design basis that prohibits this modification.
The proposed modification maintains channel independence for all three level transmitters from the active sensor outward.
This is consistent with the design requirements identified in the FSAR.
Therefore, the use of a common reference leg for two of the three pressurizer level transmitters is acceptable.
Channel Pressure transmitter independence is maintained by the relocation of the transmitter sensor line to a tap not shared by the other pressure channels.
The referenced design does not require a
FSAR or Technical Specification revision and does not involve an unreviewed safety question and is therefore an acceptable change under 10 CFR 50.59.
It is our understanding that RGIIE intends to initiate a permanent repair during the next refueling outage.
This permanent repair should provide all three level channels with their own independent reference leg.
8909060fK~ 89083l PDR ADOCK 05000244
'P PDC cc:
See next page Sincerely,
- Origina f signed. by.
Allen R. Johnson, Project Manager Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
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Dr. Robert C. Mecredy CC:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire Avenue, N.W.
Suite 1100 Washington, D.C.
20036 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 Allenda le Road King of Prussia, Pennsylvania 19406 Ms. Donna Ross Division of Policy Analysis 5 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 5 Electric Corporation 89 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