ML20004E623
| ML20004E623 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/03/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004E619 | List: |
| References | |
| IEB-79-05A, IEB-79-05B, IEB-79-5A, IEB-79-5B, TAC-11950, NUDOCS 8106120405 | |
| Download: ML20004E623 (2) | |
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O jl gv SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR FLORIDA POWER CORPORATION CRYSTAL RIVER NUCLEAR GENERATING PLANT, UNIT NO. 3 t
DOCKET NO. 50-302 INTRODUCTION l
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 B&W reactors. On April 1, l
1979, IE Bulletin 79-05 was sent to all B&W 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 similar occurrence at their facilities. This bulletin was superseded and expanded by IE Bulletin 79-05A dated April 5,1979, and by IE Bulletin i
l 79-058 dated April 21, 1979. By letters dated April 9 and 12 and May 4, 1979, Florida Power Corporation provided responses in conformance with the l
requirements of the Bulletins.
EVALUATION i
In the two year period since the Bulletins have 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 Bulletins:
- Understanding of the TMI-2 sequence of events.
- Review of Davis-Besse transient.
- Review Plant Procedures for coping with accidents and transients.
- By review of procedures and training instructions:
(1) to avoid overriding automatic action of ESF, (2) to keep high pressure injection (HPI) system in operation for at least 20 minutes and to maintain 50 F subcooling margin, l
(3) to correlate HPI initiation with reactor coolant pump (RCP) opera-l l
tion, and (4) to train operators not to rely on pressurizer level only, to deter-mine primary coolant inventory.
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- Verification of emergency feedwater (EFW) valve positions and all safety-related valve positions to ensure proper operation of EFW and ESF.
8106120 905 i
By review of containment isolation initiation and design for avoidance of isolating lines that are needed to avoid degraded core cooling capability.
Ey preparing and implenenting procedures for all valves which could defeat or compromise flow of EFW.
By preparing and implementing procedures to ensure that two independent steam generator EFW flow paths, each with 100% flow capacity, are operable when heat removal is through steam generators.
By reviewing operating modes and procedures to prevent inadvertent pumping of radioactive gasses and liquids out of the primary containment.
By reviewing procedures related to maintenance and test of safety-related systems to:
l (1) verify operability of red'ndant 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 system is removed from or returned to service.
- 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 performing analyses and design modifications to reduce the likelihood of automatic PORV actuation during anticipated transients.
By providing procedures and training operators for a prompt manual reactor trip for transients that result in a pressure increase in the reactor coolant system.
By providing for prompt reporting within one hour of the time the reactor is not in a controlled or expected condition of operation.
By proposing any needed Technical Specification changes to implement any of the above parts of the Bulletins.
CONCLUSIONS Based on our review of the information provided by the licensee in response to IE Bulletins79-05A and 79-05B, we conclude that the licensee has The actions taken by the licensee acceptably responded to these Bulletins.aemonstrate its understanding of th These actions accident as they relate to the Crystal River Unit No. 3.
have resulted in added assurance for the continued protection of the puolic health and safety during plant operation.
Dated: June 3,1981 4-
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