ML18081B252
| ML18081B252 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/30/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18081B250 | List: |
| References | |
| NUDOCS 8003270095 | |
| Download: ML18081B252 (2) | |
Text
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SAFETY EVALUATION SALEM GENERATING.STATION UNITS 1 & 2
- OVERRIDE OF CONTAINMENT PURGE ISOLATION AND OTHER ENGINEERED SAFETY FEATURE ACTUATION SIGNALS INTRODUCTION As a result of Abnormal Occurrence #78-5, the NRC issued a generic letter requesting each licensee to take certain actions.
EVALUATION The attached interim report was prepared for use by EG&G Idaho, as part of our techn i ca 1 *assistance program. This report pro vi des a techni ca 1 evaluation of the electrical instrumentation and control design aspects of the override of containment purge valves isolation and other engineered safety feature actuation signals and is based upon review of the design aspects against the 6 staff review criteria provided for the review.
The isolation valves for venting and purging satisfy the staff review criteria cited above, with three exceptions. The exceptions are that:
- 1. Inadequate physical protection 1s provided for the containment ventilation isolation reset push button switches located in the control room,
- 2.
The bypassing of a Safety Injection (SI) signal at the contain-ment ventilation isolation (CVI) retentive memory is not annunciated, and
- 3.
The radiation monitors that initiate CVI are not safety grade.
CONCLUSION Based upon our review of the consultant's technical evaluation, we conclude that the electrical, instrumentation and control design aspects of the override of containment purge valve isolation and other en~ineered safety feature actuation signals are acceptable with the exception of the three items identified above.
We also consider the contractor's interim report to be a final report because there is to.be no further contractor effort on this subject for this plant.
The licensee should be required to provide:
- l. Spring loaded covers over the existing safety related containment ventilation isolation reset push buttons that are mounted on the control room panels within 30 days,
- 2.
System level annunciation of the bypassed status of contain-ment ventilation isolation within 90 days, and
- 3.
Radiation monitors that are safety grade and satisfy the requirements of IEEE Std. 279-1971.
This requirement has been incorporated into Regulatory Guide 1.141, Revision 1, "Containment Isolation Provisions for Fluid Systems," with a proposed implementation schedule of January 1, 1981. This revision has been endorsed by ACRS and will be required after final staff approval.
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