ML20039C116

Defines Activities & Schedule for Action Plan to Resolve Severe Accident Licensing Issues for BWR/6 Mark III Gessar. Series of BWR Technology Update Meetings W/Nrc Proposed. Supporting Info Encl

ML20039C116
Person / Time
Site:	05000447, 05000531, 05000550
Issue date:	12/28/1981
From:	Sherwood G GENERAL ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
MFN-214-81, NUDOCS 8112280425
Download: ML20039C116 (4)

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GEN ER AL h ELECTRIC NUCLEAR POWER SYSTEMS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE.. SAN JOSE, CALIFORNIA 95125 MC 682, (408) 925-5040 4

e Mr. H. R. Denton, Director R fic*, . . .

Office of Nuclear Reactor Regulation N "

r U. S. Nuclear Regulatory Commission y OEC28 ;gg7N "I Washington, DC 20555 -

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4 ccwM y$p' 4 s

Dear Mr. Denton:

'O. _ ,8

SUBJECT:

SEVERE ACCIDENT LICENSING ISSUES FOR BWR/tttA8K91-GESSAR We were encouraged with the results of our meeting with you on November 10, 1981 where we proposed that the severe accident issue could be addressed on an accelerated schedule. Following our meeting, we have identified an action plan which we believe can lead to resolution of this issue for the BWR/6 Mark III Standard Plant in 1982. This letter defines the activities and schedule for this action plan.

As we discussed at our meeting, the GESSAR Docket appears to be an appropriate vehicle for GE submittal of information to address severe accident issues for the BWR/6 Mark III Standard Plant design. We plan to supplement GESSAR with a submittal which will document the BWR's capability to prevent and mitigate degraded core accidents and address specific severe accident issues. This submittal will include a prob-abilistic risk assessment of the BWR/6 Standard Plant. We plan to preceed this submittal with detailed technical presentations to support the information we presented on November 10. These activities and other portions of our action plan are defined in Attachment 1.

To move ahead on this aggressive schedule, it would be beneficial if you could identify a senior NRC Manager in your Division of Licensing to be the prime NRC contact to interface with us on this program. We would plan to work through this contact to arrange meetings with NRC Staff members and to define the information requirements and review process for our GESSAR Supplement. Mr. J. F. Quirk of my staff, who is Manager of BWR Systems Licensing, will be the principal contact within GE.

As we discussed, we are proposing a series of BWR Technology Update Meetings with appropriate NRC Staff personnel to review technical infor-mation relating to severe accident issues to be included in the GESSAR submittal. Attachment 2 defines the topics and target dates proposed for these meetings. A more detailed list of topics and meeting times will be developed in discussions between Mr. Quirk and the cognizant NRC contact. g3 8112280425 011228 3 PDR ADOCK 05000447 A PDR I )

GENER AL h ELECTRIC Mr. H. R. Denton Page 2 We look forward to working with the NRC Staff to resolve severe accident i ssues for the BWR/6 Mark III Standard Plant design. I will contact you in the near future to answer any questions you may have on this proposal and to disuss your selection of an NRC contact.

Very truly yours, WM Gfinn S erwood, Manager Nuclear Safety & Licensing Operation GGS:hjr/54-5 1216 Attachment cc: L.S. Gifford J.F. Quirk

O Attachnent 1 -

ACTION PLAN FOR SEVERE ACCIDENT RULE BWR/6 fiARK III e INITIAL KICKOFF MEETING WITH NRC November 10, 1981 e GE-NRC LEGAL DISCUSSION December 1981 e GE-NRC LICENSING PLANNING MEETING January 1982 e BWR TECHNOLOGY UPDATE MEETINGS f1EETING #1 - PRA OVERVIEU, CORE MELT PROBABILITY February 1982 MEETIflG #2 - CONTAINMENT CAPABILITY, FISSION PRODUCT TRANSPORT fiarch 1982 MEETING #3 - CONTAINMENT EVENT TREE &

PRA RESULTS April 1982 MEETING #4 - BWR/6 fiK III & GENERIC ISSUES April 1982 e SUBf1IT GESSAR SUPPLEfiEliT May 1982 e RESOLVE OPEli ISSUES June 1982 e DRAFT SER July 1982 e ACRS APPROVAL August 1982 e COMf11SSIONERS APPROVAL September 1982

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n Attachment 2 BWR TECHNOLOGY UPDATE MEETINGS .

Schedule Subject February Overview of Probabilistic Risk Assessment -

Core Melt Probability e Overview of BWR/6 Risk Assessment e BWR/6 Standard Plant Description e Implementation of Features in PRA ,

e Si te' Description e PRA Success Criteria (General) e Core Melt Probability-March Cor.tainment Capability - Fission Produc t Transport e - Classification of Core Damage Sequences e Success Criteria Assumptions / Analysis e Core Melt Phenomenology & Hydrogen Generation e Containment Structural Analysis e CORRAL Code Assumptions & Modifications e Pool Scrubbing Decontamination Factors e Fission Product Retention & Containment Function e Containment Failure Modes April Consequence Analysis & PRA Results e Steam Explosion Probability e Release Categories e Consequence Analysis e Release Probabilities e External Events e PRA Results April BWR/6 MK III & Generic Issues e Assessment-Regulatory Guides & SRPs e TMI Requirements e Unresolved Safety Issues _

e Resolution of Severe Accident Issues Y

.,