ML17263A159
| ML17263A159 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/24/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17263A158 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9303030296 | |
| Download: ML17263A159 (4) | |
Text
Enclosure 1
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t UNITED STATES NUCLEAR REGULATORY COMMISSION Vl WASHINGTON, D.C. 20555-0001 9
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S FETY EVALUA ION BY THE OFFICE OF NUCLEAR REACTOR REGULATION CONFORMANCE TO REGULATORY GUIDE 1.97 ROCHESTER GAS AND ELECTRIC CORPORATION R.
E.
GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244
- 1. 0 INTRODUCTION Rochester Gas and Electric Corporation (RG&E) was requested by Generic Letter 82-33 to provide a report to NRC describing how the post-accident monitoring instrumentation meets the guidelines of Regulatory Guide (RG) 1.97 as applied to emergency response facilities.
RG&E responded to Item 6.2 of the generic letter on January 31, 1984.
Additional information was provided by letters dated February 28,
- 1985, June 16,
- 1986, and July 13, 1990.
The NRC completed its review of RG&E's conformance to RG 1.97, Revision 3, and provided a safety evaluation (SE)'o the licensee on December 4,
1990.
The NRC found RG&E's design acceptable with respect to conformance to RG 1.97, except for the instrumentation that monitors neutron flux, containment isolation valve position, RHR heat exchanger outlet temperature, accumulator tank level and pressure, and emergency ventilation damper position.
Based on discussions with RG&E, the NRC determined that there was a
misunderstanding in the interpretation of RG 1.97 and RG&E was requested to submit new information.
This information was submitted by letters dated May 6,
- 1991, May 16,
- 1991, June 17,
- 1991, March 13,
- 1992, May 8,
- 1992, and October 14, 1992.
The review of RGBE's submittals were performed by EG&G Idaho, Inc., under contract with NRC.
This work was reported by EG&G in Technical Evaluation Report (TER),
"Conformance to Regulatory Guide 1.97:
. R.
E. Ginna," dated January 1993 (Attachment 1 to this SE).
2
~EV IIATIGN The NRC has reviewed the evaluation performed by EG&G contained in the attached TER and concurs with its bases and findings.
RG&E either conforms to, or has provided an acceptable justification for deviations from the guidance of RG 1.97, except for the instrumentation associated with post-accident neutron flux monitoring.
The subject of post-accident neutron flux monitoring is not included in this review.
Post-accident neutron flux monitoring will be discussed in a separate safety evaluation.
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Based on our review of the licensee's submittals, and the attached
- TER, we find the R.
E. Ginna Nuclear Power Plant design acceptable with respect to conformance to RG 1.97, Revision 3, except for the instrumentation associated with post-accident neutron flux monitoring.
Post-accident neutron flux monitoring is not included in this SSER and will be the subject of a sep'arate safety evaluation.
Principal Contributor:
B. Marcus Date:
February 24, 1993
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