ML20137A420
| ML20137A420 | |
| Person / Time | |
|---|---|
| Issue date: | 01/06/1986 |
| From: | King T Office of Nuclear Reactor Regulation |
| To: | Speis T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8601140369 | |
| Download: ML20137A420 (4) | |
Text
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5 JAN 6 1986 MEMORANDUM FOR:
Themis P. Speis, Director Division of Safety Review and Oversight THRU:
Karl Kniel, Chief Safety Program Evaluation Branch Division of Safety Review and Oversight FROM:
Thomas L. King, Section Leader Safety Program Evaluation Branch Division of Safety Review and Oversight
SUBJECT:
BRIEFING BY EPRI ON APPROACH TO ACCIDENT SELECTION AND EVALUATION FOR LMRS l
On November 19, 1985 the DOE and its contractors briefed us on the approach they are using to select and evaluate accidents including both design basis accidents (DBAs) and beyond the design basis accidents (BDBAs) for the liquid i
metal reactor design concepts.
Examples of the approach were provided using the Large Scale Prototype Breeder (LSPB) design developed for DOE by the l
Electric Power Research Institute (EPRI).
A copy of the agenda and a list of attendees are enclosed.
A copy of the view graphs used in the presentation is available for inspection at the section office.
Highlights of the meeting are summarized below.
DBA accident sequences are selected based on experience and judgement aided by review of fault tree and failure mode effects analyses.
Systematic review of l
historical precedence is also used.
Events are classified by frequency and l
consequence and are tested against various acceptance criteria.
The criteria of primary interest to us are the radiological criteria which we based on 10 CFR 20 for normal and anticipated events and 10 CFR 100 for the most limiting l
DBA.
A structural criteria is also used requiring that the containment l
structure will not exceed design pressure and temperature for any DBA.
Other important criteria include fuel temperature limits and relatad reactor shutdown and decay heat removal requirements.
The proposed approach for dealing with accidents beyond the design basis addresses both the Commission's policy statements on severe accidents and its trial safety goals.
The structure for the evaluation includes five steps in which the Shutdown Heat Removal System and the Reactor Shutdown System i
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4 T. Speis JAN 6 1986 reliooility are establishea, PHAs performed, comparison to safety goals are made, residual risxs are evaluated (botn internal events and external events) and a source tenn is established.
If the triol safety goals are met, then the designers propose no changes to the design be made, inis entire subject wili ue reviewed further as it is applied to the spec 1ric liquid metal reactor concepts under development by Rockwell and Gt.
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inomas L. King, Section Leader Safety Program tvaluation Branch Division of Safety Review ana uversight
Enclosures:
ns stated DISTRIBUTION Centras tile DSR0/CHRON SPEB Rag.
CAllen R/r CAllen ining NKniel BSheron ZRosctoczy JSwift HHolz ntolmar LSoffer RJohnson Ftitawila DThatcher SShaukat PNorian EChellian RCurtis, Hts RAudette, xts MEl-Zeftawy, ACR$
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Enclosure LMR Approach to Postulated Accidents DOE /EPRI/GE/RI Meeting with NRC November 19, 1985 Phillips Building - Room P110 Presentation Subjects Responsibility 1:00 - 2:00 LMR Approach to DBAs W for CoM0 o Defense-in-Depth Event Classification o Frequency of Occurrence o DBA Definition and Evaluation
- DBA Sequence Selection
- Acceptance Criteria Analyses 3:00 LMR Approach to BDBAs CoM0 2:00 4:00 General Discussion All 3:00
LO LSPB Accident Selection i
November 19, 1985 Name Organization Telephone C. L. Allen NRC/NRR/ DST 301-492-8345 R. Gluck GE/NST0 408-738-7537 G. Sherwood D0E/NE-43 FTS-233-4162 R. Lange 00E/NE-53 FTS-233-5338 Richard E. Johnson NRC/NRR/ DST 301-492-4715 Charles Kelber NRC/RES 301-427-4338 Thomas King NRC/NRR 301-492-7347 Farouk Eltawila NRC/NRR 301-492-9488 William C. Horak BNL FTS-666-2627 Rene Audette NRC/RES FTS-427-4688 Khalid Shaukat NRC/ DST 301-492-4216 Neil W. Brown GE/NST0 408-738-7787