ML19253C654
| ML19253C654 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Zion  |
| Issue date: | 11/29/1979 |
| From: | Zech G Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912060649 | |
| Download: ML19253C654 (4) | |
Text
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'o UNITED STATES E
N NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555
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NOV P.o ta79 MEMORANDUM FOR:
Darrell G. Eisenhut, Acting Director Division of Ope.1= ting Reactors FROM:
Gary Zech, Technical Assistant Division of Operating Reactors
SUBJECT:
FORTHCOMING MEETING WITH COMMONWEALTH EDIS0N CO.,
CONSOLIDATED EDIS0N COMPANY OF NEW YORK AND POWER AUTHORITY OF THE STATE OF NEW YORK REGARDING THE ZION STATION UNITS 1 AND 2 AND THE INDIAN POINT UNITS 2 AND 3 FACILITIES DATE AND TIME:
Wednesday, December 5,1979 10:30 AM LOCATION:
Maryland National Bank Building Room 6110 PURPOSE:
To discuss the staff's intended review of the subject facilities - to study alternatives that would be effective in reducing the probability and consequences of a severe reactor accident.
PARTICIPANTS:
NRC D. Eisenhut E. Reeves B. Grimes L. Olshan A. Schwencer T. Novak T. Speis P. Collins G. Zech L. Soffer, et al J. Olshinski CECO CONED C. Reed, et al W. Cahill, et al PASNY G. Berry, et al Gary Zec, Technical Assistant Division of Operating Reactors 1506 182 29uo60
AGENDA o
PURPOSE To discuss emergency preparedness procedures, improved interim operational activities, implementation of TMI-2 Lessons Learned - Bulletins and Orders matters related to mitigation of severe accidents o
INTRODUCTION o
BACKGROUND o
SPECIFIC AREAS OF REVIEW Improved Inte.-im Operations TMI-2 Lessor:s Learned Actions Bulletins and Orders Operator Training / Qualifications Emergency Procedures Human Factors Engineering Considerations Integrated Reliability Evaluation Program (IREP)
Current Performance and Licensing Action License Amendment Applications Generic Issues Unresolved Safety Issues Resident Inspector's Role Operating Experience Accident Mitigation Emergency Preparedness Considerations Degraded Core and Cora Melt Accident Scenarios Capability of Present Systems Site / Population Data Requirements Dose / Risk Evaluations With and Without System Design Changes 1506 183
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- Potential System Design Changes to be Considered for Risk Reduction
- Other (e.g., Plant Derating, Enhancing Reliability of Containment Heat Removal Systems, etc.)
o QUESTIONS AND DISCUSSIONS o
SUMMARY
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4 MEETIN2 NDTICE DISTRIB'JTION
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Docket files-una rur.u -
Local PDR ORBf3 Rd; NRR Rdc HDenton ECase DEisenhut WGammill BGrimes RVollmer LShao JMiller TIppolito l
RReid VNoonan GKnighton DZiemann ASchwencer DDavis PCheck GLainas
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RClark FPagano NHa31er DELD OI&E (3) 05D (3)
CThayer Receptionist ACRS (16)
NRC Participants SSheppard Project Manager TERA 1506 185 S
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