ML20126H422
| ML20126H422 | |
| Person / Time | |
|---|---|
| Issue date: | 12/29/1992 |
| From: | Sands S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-674A NUDOCS 9301050192 | |
| Download: ML20126H422 (7) | |
Text
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December 29, 1992 Project No. 674
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ORGANIZATION:
U.S. DEPARTMENT OF ENERGY (D0E)
SUBJECT:
MEETING WITH DOE ON PRISM SCHEDULES AND WORK PLAN On July 1,1992, the staff of the Advanced Reactors Project Directorate (PDAR) met with the U.S. Department cf Energy (DOE) at the-NRC headquarters office in Rockville, Maryland. A General Electric (GE) Company representative participated by telephone from the corporate office in California.
The list of attendees is provided in Enclosure 1.
The purpose of the meeting was to discuss, with DOE and GE, proposed changes to the preapplication review scope and schedule leading to a revision to the SECY-91-161 due dates for the preapplication safety evaluation report (PSER).
In the opening remarks by PDAR Project Director James Dyer, it was relayed to -
DOE /GE that NRC resources had decreased since SECY-91-161 was issued and the staff could no longer perform simultaneous reviews of proapplication designs.
In addition, preapplicant design certification schedules had changed such that a reordering of reviews may be appropriate. Therefore, PDAR was developing a Commission paper to revise the PSER schedule, in a letter (J. Dyer, NRC to N. Grossman, DOE) dated February 27, 1992, the NRC staff requested information on the schedule for standard design certif-ication (SDC) application dates. The DOE responded in a March 12, 1992, letter (N. Grossman, DOE to J. Dyer, NRC)-providing the following schedule information:
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Prototype Test Plan 1996
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Prototype FSAR 1996-1997 (time phased)
Standard Plant FSAR 2000-2003 (time Phased)
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Safety Test Report 2003
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Standard Plant Final Design Assessment 2004
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Standard Plant Design Certification 2005-
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Commercial Operation 2010
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The staff's preliminary assessment, bastd on SDC application and design information provided for review, was that the PRISM PSER review would continue and is expected to be completed and transmitted to the Commission by late June 1993. However, final decisions on resource commitment and schedule would-depend on Commission approval of the staff's proposed revised schedule.
In discussing the PSER with DOE, the staff presented the three objectives of the preapplication reviews and the process to final publication.
These objectives are:
(1) identify key policy issues to be presented in a Commission paper, (2) identify the key technical issues which develop as a 9301050192 921229 I
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U.S. Department of Energy December 29, 1992 result of the staff's technical review, and (3) identify necessary technology development.
The PDAR staff will develop the PSER and both NRR and the Oftice of Research (RES) will concur.
The Executive Director for Operations (ED0) will receive a draft of the PSER and send it to the Commission, asking to release the PSER to the 00E, the public, and the Advisory Committee on Reactor Safeguards (ACRS) simultaneously. The PDAR staff will inform the DOE what the important issues are prior to the PSER completion, both with the near-term policy paper, and with the PSER itself.
Following receipt of comments from the ACRS and 00E, the PSER would be presented in final form to the Commission.
After Commission approval, the PSER would be issued as a NUREG report.
In discussing the schedule, the DOE stated that the beginring of their schedule was dependent on receiving the staff's PSER.
The DOE also stated that they would build a prototype demonstrator modular unit (s), and that because the prototype demonstrator would not produce electricity, they would not initially ask for a license if the prototype ware to be built 0:1 government land as a DOE project. The DOE was planning to submit the Final Safety Analysis Report (FSAR) in segments between 2000 and 2003.
The DOE would have operated, or be operating a prototype demonstration plant by the time a standard plant FSAR was submitted.
The NRC staff did not comment on the FSAR submittal schedule, but, in general, a coordinated FSAR review could only begin when an entire FSAR is available.
Other topic areas which were discussed are highlighted below:
DOE was interested in the staff addressing the unique technical
{ mechanical engineering] features of the PRISM design such as, bellows connections in piping, sodium / water reaction mitigation, helical coil steam generators, etc.
DOE does not plan to test a full-size electromagnetic (EM) pump, only a segment of it.
The NRC staff will assume that the EM pump works as predicted for 40/60-year lifetime, but will state that there may be a need for continuing technology development.
The staff discussed the following policy issues and their applicability to the PRISM design:
Accident Evaluation Source Term Containment Emergency Planning
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Operator Staffing and Function
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Safety Classification of Structures, Systems & Components a
Control Room and Remote Shutdown Area Design Positive Void Coefficient RHR - Single Safety Grade Passive System
a U.S. Department of Energy December 29, 1992 The staff discussed the proposed revised schedule for PSER
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completion with the DOE.
In order to maintain the projected l-schedule, the staff planned to revise the work scope (Enclosure 2),
for the PSER review, to areas which the staff perceived as possible safety concerns. The staff's concerns were preliminary and commensurate with the level of '.itall in the PSID.
The staff discussed the " User Needs Request" memorandum NRR has transmitted to RES in the area of Technical Assistance. The staff is evaluating gas expansion module (GEM) performance and hypothetical core disruptive accidents / source term with the assistance of Brookhaven National Laboratory (BNL).
NRR has also requested RES to evaluate the following areas of the PRISM design-in the " User Needs Request" memorandum.
EM pumps materials (creep / creep rupture, etc.)
a seismic design and seismic isolation metallic fual behavior severe accidents and source term The staff pointed out that fuel performance would be a technical issue of importance to the ACRS and the Commission.
The DOE presented the staff with a copy of a DOE report titled, Report of Investiqation Into Alleaations of Retaliation For Raisina Safety and Quality of Work Issues Reaardina Arconne National Laboratory's Intearal Fajt Reactor Pro.iect, December 1991, U.S.
Department of-Energy, Office of Nuclear Safety, Document No.
00E/NS-0005P.
In closing, Mr. Dyer thanked the participants for their candor and thoughtful discussion points and reaffirmed the staff's commitment to provide the DOE with a copy of the policy issues paper once it had been signed by the EDO.
Original signed by:
Stephen D. Sands, Project Manager Advanced Reactors Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosures:
Distribution:
See attached list 1.
List of Attendees 2.
Proposed Revised Scope cc w/ enclosures:
See next page LA:PDLR:ADAR PM:P SC:PDA DAR D:PDAR:ADAR LLutherud
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-0FFICIAL ECORD COPY Document Name: SUMRY7.1
U.S. Department of Energy December 29, 1992 PRISM Project No. 674 cc: Robert Berglund Dr. John Herczeg Advance Nuclear Technology Division of LHRs Genaral Electric Company Office of Advanced Reactor Programs 6835 Via Del Oro U.S. Department of Energy P.O. Box 530954 NE 452 San J e, California 95153-5354 Washington, DC 20545 L.N. Salerno, Manager ALMR Program Control Dr. Lee Schroeder IJsance Nuclear Technology Assistant Director for Physical General Electric Company Sciences cad Engineering 6835 Via Del Oro Office of Science and Technology Policy P.O. Box 530954 Executive Office of the President-San Jose, California 95153-5354 Old Executive Office Building Room 432 1/2 Dr. Geza Gyorey Washington, DC 20506 Advance Nuclear Technology General Electric Company 6835 Via Del Oro P.O. Box 530954 San Jose, California 95153-5354 Richard Hardy Advance Nuclear Technology General Electric Company 6835 Via Del Oro P.O. Box 530954 San Jose, California 95153-5354 Dr. Sol Rosen, Director Office of Advanced Reactor Programs U.S. Department of Energy NE 45 Washington, DC 20545 Steve Goldberg, Budget Examiner Office of Management and Budget 725 17th Street, NW Washington, DC 20503 Nicholas Grossman, Director Division of LHRs Office of Advanced Reactor Programs U.S. Department of Energy NE 452 Washington, DC 20545
ENCLOSURE 1 List of Attendees NAME ORGANIZATION Nicholas Grossman DOE John Herczeg DOE James Dyer NRC/NRR/PDAR Edward Goodwin NRC/NRR/PDAR Beth Wetzel NRC/NRR/PDAR Richard Becker GE-Washington Stephen Sands NRC/NRR/PDAR Amy Blanford NRC/ACRS Tom Cox NRC/NRR/PDAR e
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REVISED PREAPPLICATION SAFETY EVALUATION REPORT (PSER) SCOPE CHAPTER TITLE / CONTENT I
INTRODUCTION AND
SUMMARY
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2 PRISM SITE CHARACTERISTICS 3
REVIEW AND APPROACH CRITERIA 4
CLASSIFICATION OF STRUCTURES SYSTEMS AND COMP 0NENTS 5
SEISHIC DESIGN SEISMIC ISOLATORS 6
PRISM REACTOR DESIGN NUCLEAR AND FUEL DESIGN SYSTEM THERMAL & HYDRAULIC DESIGN REACTIVITY CONTROL / SHUTDOWN SYSTEMS PASSIVE SAFETY CHARACTERISTICS 7
REACTOR COOLANT AND CONNECTED SYSTEMS RX VESSEL, CONTAINMENT VESSEL AND CLOSURE HEAD PRIMARY & INTERMEDIATE HEAT TRANSPORT STEAM GENERATOR SYSTEM RESIDUAL HEAT TRANSPORT SYSTEM 8
ENGINEERED SAFETY SYSTEMS CONTAINMENT SYSTEMS 9
INSTRUMENTATION AND CONTROL REACTOR PROTECTION SYSTEM-SAFETY RELATED INSTRUMENTATION OTHER INSTRUMENTATION MONITORING SYSTEMS CONTROL ROOM AND RSA DESIGN 10 ELECTRICAL SYSTEMS DESIGN SAFETY RELATED ELECTRICAL' POWER SYSTEMS ELECTROMAGNETIC PUMP POWER SYSTEM 11 PLANT FIRE PROTECTION SYSTEMS 12 STEAM AND POWER CONVERSION SYSTEMS l
13 SAFETY TEST PLAN - PROTOTYPE-14 ACCIDENT ANALYSIS INCLUDING PRA-l.
15 DESIGN BASIS EVENTS - B0UNDING EVENTS p-
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