ML20237L134

Summary of 870804 Meeting W/Util in Region II Ofc to Discuss Recent Studies Performed on Reliability of Both RCIC & HPCI Sys

ML20237L134
Person / Time
Site:	Brunswick
Issue date:	08/12/1987
From:	Frederickson P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20237L083	List: ML20237L081 ML20237L134
References
NUDOCS 8708270433
Download: ML20237L134 (2)

Text

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? . . g. - m ENCLOSURE 1 MEETING

SUMMARY

Licensee: Carolina Power and Light Company Facility: Brunswick Nuclear Station Docket: 50-325, 50-324 License Nos.: DRP-71 and DRP-62

SUBJECT:

RECENT STUDY PERFORMED TO DETERMINE THE RELIABILITY OF BOTH REACTOR CORE ISOLATION COOLING (RCIC) AND HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEMS.

A meeting was held in the NRC. Region II Office on August 4,1987, to discuss Brunswick's recent studies performed on the reliability of both the RCIC.and HPCI systems. ,

The licensee discussed the various programs initiated to increase ' plant reliability. The programs included a scram avoidance strategy, valve improvement initiatives, a study of Brunswick's transient responses, and the licensee's studies on the reliability of the HPIC and RCIC' systems. The end product of this ' effort is the establishment of reasonable assurance that the HPCI and RCIC systems would perform as required when called upon. The NRC concurred with the 'icensee that although . reduction of equipment failures is extremely important, reducing unnecessary challenges to safety systems is equally important. The licensee also addressed possible solutions to the safety system challenges, such as ESF setpoint changes. The NRC expressed a concern that the root cause for the recent HPCI/RCIC component failures did not appear to be adequately. factored into the reliability study. The licensee did discuss these events, but not as part of the. planned presentation. There i was also a concern over the effectiveness of the HPCI manual initiation.

training in that this activity caused a HPCI trip on July 1, 1987. In conclusion, the licensee also addressed the safety relief valve failures.

The NRC concluded the meeting by stating that the overall program appeared  !

satisfactory but that both reducing scrams and challenges to safety systems r and increasing the reliability of the HPCI system must be attained. Both the '

NRC and the licensee agreed that actual performance was the only measure of success for these improvements.

I B708270433 870012 Id

• 9 wf7 gDR ADOCK050g4 P. E. Fredrickson, Chief Date  !

Projects Section 1A Reactor Projects Branch 1 Division of Reactor Projects

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1 l ENCLOSURE 2 l LIST OF ATTENDEES Carolina Power and Light Company P. W. Howe, Vice President, Brunswick C. R. Dietz, General Manager, Brunswick l

S. R. Zimmerman, Manager, Nuclear Licensing l E. R. Eckstein, Manager, Technical Support i

K. E. Enzor, Director, Regulatory Compliance R. E. Helme, Director, On-site Nuclear Safety J. O'Sullivan, Manager, Maintenance R. B. Richey, Manager, Licensing and Nuclear Fuel Nuclear Regulatory Commission M. L. Ernst, Deputy Regional Administrator L. A. Reyes, Director, Division of Reactor Projects (DRP)

D. M. Verrelli, Chief, Reactor Projects Branch 1, DRP P. E. Fredrickse , Chief, Section 1A, DRP W. H. Ruland, Senior Resident Inspector, Brunswick, DRP S. J. Vias, Project Engineer Section IA, DRP C. A. Julian, Chief, Operations Branch, Division of Reactor Safety (DRS)

M. B. Shymlock, Chief, Operational Programs Section, DRS L. J. Watson, Reactor Engineer, DRS S. D. Statler, Reactor Engineer, DRS B. A. Breaslau, Reactor Engineer, DRS E. G. Adensam, Project Director, NRR T. Collins, Chief, Nuclear Performance Section, NRR

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