ML20044H473
| ML20044H473 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 06/04/1993 |
| From: | Poslusny C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9306090064 | |
| Download: ML20044H473 (8) | |
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UNITED STATES
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i j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001
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June 4, 1993 Docket No.52-001 APPLICANT:
PROJECT:
Advanced Boiling Water Reactor (ABWR)
SUBJECT:
PUBLIC MEETING ON JANUARY 25, 1993, TO DISCUSS THE ABWR OPEN ISSUES IN CHAPTERS 2, 6, AND 15 A meeting was held on January 25, 1993, at the GE offices in San Jose, California, between representatives of the U.S. Nuclear Regulatory Commission (NRC) and GE. The purpose of the meeting was to review, discuss, and resolve the ABWR open issues in Chapters 2, 6, and 15 of the draft final safety evaluation report (DFSER). provides a list of attendees. The handouts used in the meeting are provided in Enclosure 2.
In this meeting, the following items were resolved and closed by reviewing the proposed changes to the ABWR standard safety analysis report (SSAR) (subse-quently, GE submitted formal documentation of the resolution in the recent amendments to the SSAR):
Confirmatory Items 2.3.1-1 Tornado design basis 15.4.4.1-1 Containment leak rate Combined License Items 2.1.1-1 Site information 2.1.2-1 Exclusion area 2.1.3-1 Population data 2.3.1-1 External hazard 2.3.2-1 Local meteorology 2.3.3-1 Meteorological program 2.3.4-1 Short-term dispersion estimates 2.3.5-1 Long-term dispersion estimates 15.4.4.2.1-1 Iodine removal credit The following open and technical specification items were also discussed and resolved, but these items did not require GE's formal documentation.
The NRC will revise the DFSER accordingly:
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m June 4,1993 Open items 15.4.4.2.1-1 Seismic analysis 15.4.4.2.2-1 10 CFR Part 100 exemption Technical Specification Item 15.4.4.1-1 Suppression pool leakage 15.5.1.2.1-1 Drain valve operability 15.4.4.3-1 Post-loss-of-coolant accident leakage Finally, the following comments from the Advisory Committee on Reactor Safeguards (ACRS) on the ABWR DFSER were discussed.
ACRS Items ACRS-17 Exfiltration of the standby gas treatment system ACRS-21 Heavy object drop accident (Original signed by)
Chester Poslusny, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page DISTRIBUTION w/ enclosures:
Docket File PDST R/F CPoslusny JNWilson PDR PShea JLee, 10D4 1
D1S.TRIBUTION w/o enclosures:
TMurley/FMiraglia DCrutchfield RBorchardt WRussell, 12G18 Skoenick JMoore, 15B18 ACRS (11)w/o enc 1.
J0'Brien, RES BHardin, RES L5nao, RES GGrant, ED0 EJordan, MNBB3701 OFC:
LA:PDST:
AR PM:PDST:ADAR P B
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NAME: PSh CPoslusny:tz JLe JN i on DATE:
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6 /3 /93
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/93 0FilCIAL RECORD COPY: MSM0125.CP
GE Huclear Energy Docket No.52-001 cc:
Mr. Patrick-W. Marriott, Manager Mr. Joseph Quirk Licensing & Consulting Services GE Nuclear Energy GE Nuclear Energy General Electric Company 175 Curtner Avenue 175 Curtner Avenue, Mail Code 782 San Jose, California 95125 San Jose, California 95125 Mr. Robert Mitchell General Electric Company 175 Curtner Avenue San Jose, California 95125 Mr. L. Gifford, Program Manager Regulatory Programs GE Nuclear Energy 12300 Twinbrook Parkway Suite 315 Rockville, Maryland 20852 Director, Criteria & Standards Division Office of Radiation Programs U. S. Environmental Protection Agency.
401 M Street, S.W.
Washington, D.C.
20460 Mr. Sterling Franks U. S. Department of Energy NE-42 Washington, D.C.
20585 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.
Room 8002 Washington, D.C.
20503 Mr. Frank A. Ross U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874 Mr. Raymond Ng 1776 Eye Street, N.W.
Suite 300 Washington, D.C.
20006 Marcus A. Rowden, Esq.
I Fried, Frank, Harris, Shriver & Jacobson 1001 Pennsylvania Avenue, N.W.
Suite 800 Washington, D.C.
20004 Jay M. Gutierrez, Esq.
Newman & Holtzinger, P.C.
1615 L Street, N.W.-
Suite 1000 Washington, D.C.
20036
1 l-b MEETING ATTENDEES January 25, 1993 j
Individual Oroanizational Affiliation Jay Lee NRC/NRR/PRPB H. Careway GE J. Fox GE.
G. Ehlert GE J. Powers GE T. Hosler GE t
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GE RESPONSIBLE ENGINEERS NRC/NRR MEETING WITH GE ON JANUARY 25,1993 ITEM NRC NUMBER GE RESPONSIBLE ENGINEER DESIGN BASIS TORNADO CFM 2.3.1-1 JACK FOX CHARACTERISTICS CONTROL ROOM ITAAC 6.4-1 MOREY MUNSON HABITABILITY CONTROL ROOM ITAAC 6.4-2 MOREY MUNSON HABITABILITY
_ CONTAINMENT LEAK RATE CFM 15.4.4.1-1 HAL CAREWAY IODINE REMOVAL ITAAC 15.4.4.2.1-HAL CAREWAY 1
10CFR100 EXEMPTION 15.4.4.2.2-1 JACK FOX HEAVY OBJECT DROP GARY EHLERT COL ITEMS 2.1.1 -1 JACK FOX 2.1.2-1 2.1.3-1 2.3.1 -1 2.3.2-1 2.3.4-1 2.3.5-1 15.4.4.2.1-1 TECHNICAL SPECIFICATION 15.4.4.1-1 HAL CAREWAY ITEMS 15.5.1.2-1 (??)
15.4.4.3-1 l
9
I CONTAINMENT LEAK RATE i
CFM 15.4.4.1-1 THE ABWR LEAK RATE IN SUBSECTION 15.6.5, AMENDMENT 24 IS 0.5% PER DAY FOR 30 DAYS ITEM CONFIRMED i
I
IODINE REMOVAL i
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ITAAC SHOULD INCLUDE OPERABILITY REQUIREMENT FOR MAIN STEAM DRAIN
[
LINE VALVE, and STRUCTURAL INTEGRITY REQUIREMENT f
FOR MAIN STEAMLINES, DRAIN LINES, AND MAIN CONDENSER 1
- NOTE: GE DOES NOT REQUIRE THESE BE LEAK TIGHT COMPONENTS STATUS:
- GE DAL # 1601 PENDING APPROVAL OF APPROACH BY NRC
- IF APPROACH OK, DAL WILL BE ACCEPTED, AND REQUIRED CHANGES-MADE.
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TECHNICAL SPECIFICATION 15.4.4.1-1 REQUIRES REVIEW OF TS ON
=
PERIODIC INSPECTION OF SUPPRESSION j
POOL AND DRYWELL LEAK TIGHTNESS.
- DOES NOT APPEAR TO BE AN ACTION ITEM ON GE l
- LEAKTIGHTNESS IS A REQUIREMENT OF APPENDIX J TESTING 15.5.1.2-1 UNKNOWN 15.4.4.3-1 REQUIRES COL APPLICANT TO SPECIFY TOTAL WATER LEAKAGE FOR ESF COMPONENTS
- GE ESTIMATES 0.0016 GPM
- NRC STAFF USES 1.0 GPM
- NOT REALLY CLEAR WHAT IS BEING SOUGHT l
.