ML20207F173
| ML20207F173 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1986 |
| From: | Speis T Office of Nuclear Reactor Regulation |
| To: | Buhl A INDUSTRY DEGRADED CORE RULEMAKING PROGRAM, INTERNATIONAL TECHNOLOGY CORP. |
| Shared Package | |
| ML20207F178 | List: |
| References | |
| CON-FIN-A-3825, CON-FIN-A-3828 NUDOCS 8701050475 | |
| Download: ML20207F173 (1) | |
Text
A 01 Q Dr. Anthony Buhl Program Manager IDCOR c/o International Technology Corporation 575 Oak Ridge Turnpike Oak Ridge, TN 37380
Dear Dr. Buhl:
Per your request, attached please find two NRC contractor's draft reports titled, " Prevention and Mitigation of Severe Accident in BWR with Mark II Containment," and " Prevention and Mitigation of Severe Accidents in a PWR with a large Dry Containment", these reports were prepared in support of the staff's implementation plan for the severe accident policy statement as set forth in SECY 86-76 dated February 28, 1986.
These are the last of five reports on guidelines and proposed criteria developed to assist nuclear plants utility owners to assess their plant capability to cope with severe accidents and to propose ways to reduce the frequency of occurrence and mitigate the consecuence of severe accident should one occur.
Each preliminary guidelines and criteria report has been developed from insights gained from our review of six reference plants and other available PRAs representative of the difference containment types in use throughout the U.S. commercial power plants.
Our schedule calls for issuance of all guidelines and criteria reports by March, 1987.
NRC contact is Dr. Zoltan R. Rosztoczy, (301) 492-8016.
Sincerely,
$W -- YW l.
hemis Spets, Director Division of Safety Review and Oversight DISTRIBUTION Central File DSR0 r/f RIB r/f INRCPDR?
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