ML17257A516
| ML17257A516 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/30/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TASK-08-01.A, TASK-8-1.A, TASK-RR LSO5-81-07-094, LSO5-81-7-94, NUDOCS 8108050379 | |
| Download: ML17257A516 (5) | |
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July 30, 1981 Docket No. 50-244 LS05 07-094 Mr. John E. Maier. Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Hr. Maier:
AUG 05 1981'
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SUBJECT:
SEP TOPIC VII-1.A, ENGINEERED SAFETY FEATURES (ESF)
SYSTEM CONTROL LOGIC AND DESIGN, REVISED SAFETY EVALUATION FOR R.
E.
GINNA The enclosed staff safety evaluation report (SER) has been revised to correct an editorial error in our transmittal of June 26, 1981.
Our previous SER contained an evaluation and conclusion that were not applicable to your plant and were inadvertehtly provided on page 2
of the SER.
Our new SER is the staff's position regarding design of your facility in the subject area.
With regard to the referenced topic, the staff has concluded your facility meets our current licensing criteria.
Sincerely,
Enclosure:
As stated cc w/enclosure:
See next page 8i08050379 810730,'DR ADOCK 05000244 P
PDR Dennis M. Crutchfield, Chief Operating Reactors Branch No.
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G manas 7/Q/81 NRC FORM 318110/80) NRCM 0240 OFFICIAL RECORD "COPY
- USGPO,"1980-329.824
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Mr. John E. Maier CC Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 Hew Hampshire
- Avenue, N.
W.
Suite 1100 Washington, D. C.
20036 Mr. Michael Slade 12 Trailwood Circle Rochester, Hew York 14618 Ezra Bialik Assistant Attorney General Envi ronmenta 1 Pro tee tion B ureau Hew York State Department of Law 2 World Trade Center Hew York, Hew York 10047 Jeffrey Cohen Hew York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223
- Director, Bureau of Nuclear Operations State of Hew York Energy Office Agency Building 2 Empire State Plaza
- Albany, Hew York 12223 Rochester Public Library 115 South Avenue Rochester, Hew York 14604 Supervisor of the Town of Ontario 107 Ridge Road West
- Ontario, Hew York 14519 Resident Inspector R.
E. Ginna Plant c/o U. S.
HRC 1503 Lake Road
- Ontario, Hew York 14519 Nr. Thomas B. Cochran Natural Resources Defense Council, Inc.
1725 I Street, N.
W.
Suite 600 Washington, D. C.
20006 U. S. Environmental Protection Agency Region II Office ATTN:
EIS COORDINATOR 26 Federal Plaza Hew York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr.
Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555
SYSTEMATIC EVALUATION PROGRAM TOPIC VII-l.A GINNA VII-l.A ISOLATION OF REACTOR PROTECTION SYSTEM FROM NOH-SAFETY
- SYSTEMS, INCLUDING QUALIFICATION OF ISOLATION DEVICES I.
Introducti on Non-safety systems generally receive control signals from the reactor protection system (RPS) sensor current loop.'..The non-safety circuits are required to have isolation devices to ensure the independence of the RPS channels.
Requirements for the design and qualification of isolation devices are quite specific.
Recent operating experience has shown that some of the earlier isolation devices or arrangements at operating plants may not be effective.
The objective of our review was to verify that operating reactors have RPS designs which provide effective and qualified isolation of non-safety systems from safety systems to assure that safety systems will function as required.
II.
Review Criteria The review criteria are presented in Section 2 of EG&G Report 1183-4155, "Review of NRC Safety Topic VII-l.AAssociated with the Electrical, Instru-mentation, and Control Portions of.the Isolation of the Reactor Protection System from Non-Safety Systems for the Ginna Nuclear Power Plant."
III.
Related Safet To ics and Interfaces The scope of review for this topic was limited to avoid duplication of effort si nce some aspects of the review were performed under related topics.
The related topics and the subject matter are identified below.
Each of the related topic reports contain the acceptance criteria and re-view guidance for its subject matter.
VI-7.C.l Independence of Onsite Sources VIII-l.A Degraded Grid IX-6 Fire Protection There are no safety topics dependent on the present topic information because proper isolation has been assumed.
IV.
Review Guidelines The review guidelines are presented in Section 3 of Report 1183-4155.
Y.
Evaluation As noted in Sections 5 and 6 of EGEG Report 1183-4155, Ginna satisfies current licensing. criteria.
YI.
Conclusion The staff's position is that suitably qualified isolators have been pro-vided at Ginna.