ML20199D418
| ML20199D418 | |
| Person / Time | |
|---|---|
| Issue date: | 03/20/1986 |
| From: | King T Office of Nuclear Reactor Regulation |
| To: | Speis T Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-674A NUDOCS 8603240074 | |
| Download: ML20199D418 (3) | |
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MEMORANDUM FOR: Themis P. Speis, Director Division of Safety Review and Oversight Office of Nuclear Reactor Regulation THRU:
Karl Kniel, Chief Safety Program Evaluation Branch Division of Safety Review and Oversight Office of Nuclear Reactor Regulation FROM:
Thomas L. King, Section Leader Safety Program Evaluation Branch Division of Safety Review and Oversight Office of Nuclear Reactor Regulation
SUBJECT:
SU N RY OF~ MEETING WITH DOE AND GE WITH DRAFT PSID FOR THE POWER REACTOR INHERENTLY SAFE MODULE (PRISM) DESIGN AND ON POSSIBLE RULEMAKING FOR LICENSING BY TEST On January 7,1986 representatives from the General Electric Company briefed us on the contents of a draft version of the Preliminary Safety Information Document (PSID) for their PRISM (Power Reactor Inherently Safe Module) liquid metal reactor (LMR) design concept. They also discussed a possible approach to licensing which could utilize rulemaking changes to achieve licensing based on full scale test results.
A list of attendees is enclosed.
Copies of the viewgraphs used at the meeting are available for inspection at the section office.
The representatives from GE provided a discussion of a possible approach to licensing for their PRISM design that would rely on results from a full scale test. The approach may require changes in some of our regulations.
In particular GE suggests that a new appendix to Part 50 would be needed to. allow NRC approval of a standard design based on use of demonstrated performance.
Existing appendices (e.g., Appendix 0) address standard plant approval but do not explicity address application of results from full scale testing.
The main thrust of the test as proposed by GE would be to demonstrate the ability of a design to accommodate the traditional LWR severe accidents, specifically the loss of flow, transient overpower and loss of heat sink transients all with
. failure to-scram.
The rulemaking change to implement this approach would, of course, be subject to a public hearing process. Once approved the standard design could then be applied to' appropriate parts of the facility for licensing action with that aspect of the design exempt from challenge in individual licensing cases.
The staff responded generally favorably to the licensing by test approach but pointed out that many aspects need further development.
For example, discussions focused on the scope of the plant that would be covered by the standard plant application and on how the requirements on interfaces between various categories of plant systems and equipment would be specified and reviewed.
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T. Speis
-2 Og The staff recossended that the concept be carried along and developed as our review of the PRISM concept progresses.
i The latter half of the meeting was devoted to discussion of the Preliminary Safety Information Document (PSID) for the PRISM concept.
A two volume draft copy was provided for reference. The PSID was discussed chapter by chapter.
The following highlights are noted:
(1) Additional material will be provided by December 1986 on; (a) research and development test' program, (b) fuel design and (3) thermal-hydraulic water tests of natural circulation. This material may be provided in in topical reports.
(2) Consideration of a double ended pipe break is still considered an option in linu of leak before break.
(3) Trade off studies are in progress on seismic isolation requirements.
The designer may consider seismic tests on a full scale facility.
(4) Review of the control complex by human factors specialists will be i
needed.
l-(5)' Chapter 14 will include a prototypic safety test plan.
(6) As of now generic requirements for station blackout and application of TMI/USI/GSI items are being developed by EPRI in support of the Large Scale Prototype Breeder (LSPB) design and will also be applied to PRISM.
EWEIGNEDBra Thomas L. King, Section Leader Safety Program Evaluation Branch Division of Safety Review and Oversight Office of Nuclear Reactor Regulation DISTRIBUTION Central File SPEB R/F
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CAllen TKing KKniel PWilliams PDR
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- D5RO:5PEB TKk KKnkek CA in f DATE:03/FD'86
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- 03/2B/86 OFFICIAL RECORD COPY 4
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January 7, 1986 LICENSING BY TEST MEETING CE - DOE NUR NAME ORGANIZATION TELEPHONE C.'L. Allen NRR/DSR0/SPEB FTS 492-4727 G. J. Van Tuyle BNL FTS 666-7960 G. C. Lainas NRR/D8L FTS 492-9680 T. P. Spets NRR/DSR0 FTS 492-7517 K. Kniel NRR/DSR0/SPEB FTS 492-8907 R. E. Johnson NRR/DSR0/EIB T. L. King NRR/DSR0/SPEB FTS 492-7014 Neill Thomasson OPE /NRC 202-634-1427 George Sherwood DOE /NE FTS 233-4162 Rudy Villa GE 408-925-5722 E. S. Chelliah DSR0/0NRR 301-492-8048 R. Audette RES/DAE/CSR8 301-492-4689 V. Leung NRR/DSR0/ RIB 301-492-4707 Neil W. Brown GE 408-738-7787 Glenn Sherwood GE 408-925-5722 B
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