ML20195E392

Notification of 881102 Meeting in Rockville,Md to Continue Exchange of Info W/Numarc & EPRI Re Estimating Emergency Diesel (EDG) Reliability Levels & Industry EDG Reliability Programs

ML20195E392
Person / Time
Issue date:	10/24/1988
From:	Serkiz A NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Burns J, Butcher E, Chiramal M NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD), Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
NUDOCS 8811080007
Download: ML20195E392 (2)

Text

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OCT84 W w

MEMORAhDUM FOR:

J. Burns, RES/EME J. Knight, NRR/SELB E. Butcher, NRR/OSTB E. Lofgren, SAI M. Chiramal, AE00 A. Marion, NUMARC

0. Chopra, NRR/SELB A. Payne, SNL R. Colmar, NRR/lLRB J. Raval, NRR/SPLB J. Craig, NPR/SPLB F. Rosa, NRR/SELB S. Crockett, 0GC W. Schwink, NRR/lLRS M. El-Zeftaway, ACRS

0. Tondi, NRR/SELB J. Gaertner, EPRI H. Wyckoff, EPRI C. Johnson, RES/RHFB FROM:

A. W. Serkiz Reactor and Plant Safety issues Branch Division of Safety Issue Resolution S'JBJECT:

MEETittG fiOTICE - EDG RELIABILITY ESTIMATES AND MONITORING Date er.d Time:

Nov ar:ber 2, 1988, 9:00 a.m. - 4:00 p.m.

Location:

Room 013, Nictolson Lane South Rockville, Maryland

Purpose:

The general purpose of this meeting is to continue an exchange of information with NUMARC and EPRI related to estinating EDG reliability levels and industry EDG reliability programs.

This meeting is a follow-up meeting from the July 27, 1988 meeting wherein EPRI presented the results of their EDG reliability analysis.

This meeting will address the following topics:

1)

Review contents forwarded to NUMARC (see A. Serkiz to A. Marion transmittal dated 9/19/88),

2)

EPRI's views on combining individual EDG reliability into a plant-specific EDG reliability estimate.

3)

EPRI's views on actions to be taken when "trigger" reduced levels of EDG reliability are evident, a)

Industry feedback on survey of EDC reliability and maintenance programs being utilized.

5)

Identification of an EDG reliability progran which neets needs of 10 CFR 50.63, the station blackout rule.

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.o 2-Please call me on ext. 23923 if you have any questions.

will forward to you any material I receive in advance of this meeting, origina181&d** kf A A. W. Serkiz Reactor and Plant Safety Issues Branch Division of Safety Issue Resolution

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T. Speis R. W. Houston W. Minners A. Thadani

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DISTRIBUTION:

RES Circ RES Chron DCS DSIR C/F RPSIB R/F KKniel PNorian ASerkiz Central Files >

POR (191-RPtIB/DSIR a.,

RPSIB/05 OFC:

RPS18/OSIR NAME:

ASerLiz:sd PNorian KKniel

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DATE:

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