ML19209C998
| ML19209C998 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/26/1979 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Zieman D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910180564 | |
| Download: ML19209C998 (2) | |
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iL%il "EMORANDUM FOR: Dennis L. Zier. ann, Chief Operating Reactors Branch No. 2, DOR FROM:
Dennis M. Crutchfield, Chief Systenatic Evaluation Progran Branch. 00R
SUBJECT:
REQUEST ADDITIONAL INFORMATION FOR SIG ROCK POINT PLANT CONTAI. TENT PURGE SYSTEM As followup to September 14, 1979 telecon with the Big Rock Point licensee, the following concerns on the electrical and instrumentation design area should be forwarded to the licansee.
1.
In the licensee's submittal on " additional infomation relative to fcel handling accident in containment" dated Mov mber 29, 1978, the licensee has recognized som single failures in electrical design. In addition, because of the autonatic vacuum relief systen circuits being integrated into the containment isolhtion system, there are several other single failure in the vacuum relief system that could block an isolation signil. A tech-nical evaluation report was prepared by our consultant, EG&G Idaho, Inc. on Big Rock Point plant containment isolation system (CIS}. The repcrt has cencluded that the lack of redundancy and independence in the air supply and exhaust portion of the containment isolation system and its 1-tegrated vacuum felief system, which leaves this CIS to numer dis-aabling single failures. The staff has reviewed this report and concur in its conclusions.
A copy of EG&G report No. RE-A-79-045 is attached. The licensee is requested to address each single failure postul-ated in the report and provide a.fustification and/or proposed nodification to the CIS.
2.
There is only one manual control 4 Witch (HS-9001) to close both air supply valves and both exhaust valves. In July 16, 1973. ILE Bulletin No. 73-2 require all licensees take action to determine whether the failure of a single centrol switch could result in thessimultanedus failure of the redundant supply valves or redundant exhaust valves. The licensee is requested to address their response to thisebulletin.
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The generic evaluation on containment purge system electrical design has established certain criteria. A copy of these criteria are attached for licensee's information.
Dennis M. Crutchfield, Chief Systematic Evaluation Program Branch Division of Operating Reactors :
EG&G Idaho, Inc. Re.r> ort No. RE-A-79-045 Attachaent 2:
Criteria for evaluation of containment purge system electrical design.
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