ML20056F962

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Forwards GENE-A0003649-01, Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of ABWR Design, Per SRM Re SECY-91-229, Severe Accident Mitigation Design..
ML20056F962
Person / Time
Site: 05200001
Issue date: 08/26/1993
From: Quirk J
GENERAL ELECTRIC CO.
To: Joshua Wilson
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20056F963 List:
References
MFN-137-93, NUDOCS 9309010088
Download: ML20056F962 (2)


Text

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-c GENuclear Energy.

Genera!Decirit Company j

11$ Cartnet Avenue. Sen.kse, C435125 l

i August 26,1993 MFN No.137 !

Docket No. STN 52-001 l

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Document Control Desk

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U.S. Nuclear Regulatory Commission Washington, D.C. 20555 --

l Attention:

Jerry N. Wilson, Acting Director l

Standardization Project Directorate l

Subject:

NEPA/SAMI) A Submittal for the ABWR j

i In the Staff Requirements Memorandum (SRM) dated October 25,1991, related to 1

SECY-91-229," Severe Accident Mitigation Design Alternatives for Certified Standard Designs" (July 31,1991), the Commission directed the Staff to address severe accident mitigation design alternatives (SAMDAs) for certified designs in a single rulemaking process that considers both i

the 10CFR5034(f) and National Environmental Policy Act (NEPA) requirements, and to require applicants for a design certification to assess SAMDAs.

In accordance with this SRM, enclosed is a Tech 1ical Support Document (TSD) for the General Electric (GE) Advanced Boiling Water Reactor (ABWR). The TSD provides assessments of SAMDAs, severe accident prevention measures and radiological impacts from normal operation

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for the ABWR. This document is largely based upon the safety assessment of mitigative and

j preventive measures provided in Appendix 19P of the Standard Safety Analysis Report (SSAR) i for the ABWR. GE believes that the TSD provides a sufficient basis for NRC to issue an amendment to 10CFR51 which concludes:
1) that the probability of severe accidents in the ABWR is remote and -

speculative,

2) that the risks of severe accidents and the radiological impacts of normal operation of the ABWR do not constitute a significant impact to the quality of the human environment, and 1

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3) that there are no reasonable alternatives for reducing these risks or impacts.

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t If you have any questions on the attached TSD, please call Peter D. Knecht at (408)925-6215.

Sincerely,

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$ p i F. Quirk roject Manager ABWR Certification MC-782, (408)925-6219 cc:

R. C. Berglund (GE)

T. E. Murley (NRC)

D. M. Crutchfield (NRC)

N. D. Fletcher (DOE)

D. J. McGoff (DOE)

F. J. Miraglia, Jr.

(NRC)

C. Poslusny, Jr.

(NRC) l F. A. Ross (DOE)

K. E. Stahlkopf (EPRI)

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