ML19350F168
| ML19350F168 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point, Crane File:Consumers Energy icon.png |
| Issue date: | 06/08/1981 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML19350F167 | List: |
| References | |
| IEB-79-08, IEB-79-8, NUDOCS 8106240308 | |
| Download: ML19350F168 (2) | |
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WASHING TON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGUt ATION CONSUMERS POWER COMPANY BIG ROCK p0 INT PLANT DOCKET NO. 50-155 INTRODUCTION On March 28, 1979 the Three Mile Island Nuclear Power Plant, Unit 2 (TMI-2) experienced core damage which resulted from a series of events which were initiated by a loss of feedwater transient. Several aspects of the acci-dent have generic applicability at operating boiling water reactors. On April 14,1979, IE Bulletin 79-08 was sent to all boiling water operating plant licensees. The purpose of the Bulletin was to provide information concerning the accident at TMI-2 and to request certain actions be taken by licensees to preclude a sinilar occurrence at their facilities. By letters dated May 4, May 16, and August 7,1979, Consumers Power Company provided responses in conformance with the requirements of the Bulletins.
EVALUATION In the two year period since the Bulletin has been implemented we have observed, in addition to our review of the responses enumerated above, that the licensee has complied with all the following provisions of the Bulletin :
- Understanding of the TMI-2 sequence of events.
- Review Plant Procedures for coping with accidents and transients.
- By review of procedures and training instructions to avoid over-riding automatic action of ESF.
- By review of containment isolation initiation and design for avoidance of isolating lines that are needed to avoid degraded core cooling capability.
- By reviewing operating modes and procedures to prevent inadvertent pumping of radica dive gasses and liquids out of the primary containment.
- By reviewing procedures related to maintenance and test of safety-related systems to:
(1) veri"y operability of redundant system prior to removal of any system from service, (2) verify operability of all systems following maintenance or testing, and (3) verification to operating personnel whenever a systemis removed from of returned to service.
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- By developing procedures and training operators to establish and maintain natural circulation.
By training operators to take into account reactor vessel integrity con-siderations during any. accident or transient.
- By providing. for prompt reporting within one hour of the time the reactor is not in a contro; led or expected condition of operation.1 By proposing any needed Technical Specification changes' to implement any of the above parts of the Bulletin.
CONCLUSI0BS Based on our review of the information provided by -the licensee in response -
to IE Bulletin 79-08, we conclude that the licensee has acceptably responded to this Bulletin. The actions taken by the licensee demonstrate 'its under-standing of the concerns and implications of the TMI-2 accident as they relate to the Big Rock Point Plant. These actions have resulted in added assurance for the continued protection of the public health and safety during-plant operation.
Dated:
June 8,1981
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