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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20132D8481996-12-18018 December 1996
Summary of 961212 Meeting w/ABB-CE & GE in Rockville,Md Re Changes to Design Control Documents for ABWR & Sys 80+ Standard Plant Designs.List of Attendees Encl
ML20148B5761996-10-0404 October 1996
Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents
ML20059D9701993-12-16016 December 1993
Summary of 404th Meeting of ACRS on 931209-11 W/Ge Re Diversity in Method of Measuring RPV Water Level in Advanced & Simplified BWR Designs
ML20059D9611993-12-15015 December 1993
Summary of 404th Meeting of ACRS on 931209-11 Re Schedule for Completing Review of NRC Staff Final SER for GE ABWR Ssar
ML20058L5061993-12-0707 December 1993
Notification of 940105 Meeting W/Bwrog in Rockville,Md to Discuss Generic Guidance & Repair Criteria for BWR Core Shrouds & Recent Cracking of BWR Jet Pump Holddown Beams
ML20058A6471993-11-18018 November 1993
Summary of 931025 Meeting & Followup Telcon on 931029 Re Test Program Activities Conducted at gravity-driven Integral full-height Test for Passive Heat Removal thermal-hydraulic Test Facility in Japan
ML20059G7551993-11-0101 November 1993
Summary of 930921 Meeting W/Ge Nuclear Energy (GE) in GE San Jose Office Re Resolution of Limited Number of Issues Involving Design of ABWR Fire Protection Sys.List of Meeting Attendees & Handouts Encl
ML20057B6401993-09-17017 September 1993
Submits Daily Highlight.Ge Will Not Be Able to Meet 930913 Date for Certified ABWR Ssar Submittal.Revised Submittal Date Is 930917 for Main Body of Ssar W/Document Control Room Receipt by 930920
ML20056E1511993-08-17017 August 1993
Summary of 930802 Meeting w/GE,C-E & Westinghouse in Rockville,Md Re Status of Design Certification Reviews for Each Revolutionary & Passive Reactor Design.List of Attendees & Handout Encl
ML20056E5271993-08-0505 August 1993
Summary of Meeting W/Ge in Rockville,Md on 930727 to Discuss Tier 1 Submittal for Bldg Designs & Primary Containment Design
ML20059C8451993-08-0404 August 1993
Summary of ACRS Subcommittee on BWRs (GE) 930615-17 Visit to GE Facility in San Jose,Ca to Gather Info Associated W/ Review of GE Ssar.Meeting Agenda Encl
ML20056D9421993-07-30030 July 1993
Summary of 930707-08 Meeting W/Bnl & GE in San Jose,Ca Re Review of ABWR Ts.Meeting Attendees Listed
ML20056D0971993-07-15015 July 1993
Summary of 930621-24 Meeting W/Ge in Livermore,Ca to Write Proof & Review Instrumentation Sys TS for GE Abwr.Meeting Attendees Listed in Encl 1
ML20056C3761993-05-10010 May 1993
Summary of 930426 Meeting W/Ge in Rockville,Md to Discuss Resolution of Severe Accident Issues for Advanced Bwr. Attendees Listed in Encl 1
ML20059C7421993-03-0202 March 1993
Summary of 392nd ACRS Meeting on 921209-11 in Bethesda,Md Re SBO Rule,Ts Improvement Program,Advanced BWR Design,River Bend Nuclear Plant Reliability Monitoring Program & Generic Issue 120,online Testability of Protection Sys
ML20128E8351993-02-0505 February 1993
Summary of 930120-21 Meeting W/Ge in San Jose,Ca Re Issues Related to ABWR PRA
ML20128E8531993-02-0505 February 1993
Summary of 921112-13 Meeting W/Ge Nuclear Energy in San Jose,Ca Re Issues Related to ABWR PRA
ML20128E8651993-02-0404 February 1993
Summary of 930121 Meeting W/Ge & Other Stated Companies in San Jose,Ca Re Status of ABWR Review.List of Attendees Encl
ML20128B7581993-01-27027 January 1993
Summary of 930111-21 Meeting W/Ge Re Development of ITAAC as Part of Certification Process.List of Attendees Encl
ML20127M6291993-01-25025 January 1993
Summary of 930108 Meeting W/Ge in Rockville,Md Re Status of Various Open Items in Chapter 14 of Draft Final SER for Abwr.List of Attendees Encl
ML20126F4041992-12-28028 December 1992
Summary of 921217 Meeting W/Ge Re Discussion on Status of Testing Programs Under Development by GE to Support Design of Sbwr.List of Attendees & RAI Responses Encl
ML20126M3881992-12-23023 December 1992
Summary of 921215 Meeting W/Ge in Rockville,Md to Discuss Issues Related to Industry & Staff Review of ABWR Insps, Tests,Analyses & Acceptance Criteria.List of Attendees & Viewgraphs Encl
ML20127D3211992-08-12012 August 1992
Summary of ACRS 388th Meeting on 920806-08 Re Insps,Tests, Analyses & Acceptance Criteria Program for GE ABWR Design. Design
ML20127D3221992-08-12012 August 1992
Summary of ACRS 388th Meeting on 920806-08 Re Plans for Reviewing GE Application for Certification of GE ABWR Design
1996-12-18
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20132D8481996-12-18018 December 1996
Summary of 961212 Meeting w/ABB-CE & GE in Rockville,Md Re Changes to Design Control Documents for ABWR & Sys 80+ Standard Plant Designs.List of Attendees Encl
ML20148B5761996-10-0404 October 1996
Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents
ML20059D9701993-12-16016 December 1993
Summary of 404th Meeting of ACRS on 931209-11 W/Ge Re Diversity in Method of Measuring RPV Water Level in Advanced & Simplified BWR Designs
ML20059D9611993-12-15015 December 1993
Summary of 404th Meeting of ACRS on 931209-11 Re Schedule for Completing Review of NRC Staff Final SER for GE ABWR Ssar
ML20058L5061993-12-0707 December 1993
Notification of 940105 Meeting W/Bwrog in Rockville,Md to Discuss Generic Guidance & Repair Criteria for BWR Core Shrouds & Recent Cracking of BWR Jet Pump Holddown Beams
ML20058A6471993-11-18018 November 1993
Summary of 931025 Meeting & Followup Telcon on 931029 Re Test Program Activities Conducted at gravity-driven Integral full-height Test for Passive Heat Removal thermal-hydraulic Test Facility in Japan
ML20059G7551993-11-0101 November 1993
Summary of 930921 Meeting W/Ge Nuclear Energy (GE) in GE San Jose Office Re Resolution of Limited Number of Issues Involving Design of ABWR Fire Protection Sys.List of Meeting Attendees & Handouts Encl
ML20057B6401993-09-17017 September 1993
Submits Daily Highlight.Ge Will Not Be Able to Meet 930913 Date for Certified ABWR Ssar Submittal.Revised Submittal Date Is 930917 for Main Body of Ssar W/Document Control Room Receipt by 930920
ML20056E1511993-08-17017 August 1993
Summary of 930802 Meeting w/GE,C-E & Westinghouse in Rockville,Md Re Status of Design Certification Reviews for Each Revolutionary & Passive Reactor Design.List of Attendees & Handout Encl
ML20056E5271993-08-0505 August 1993
Summary of Meeting W/Ge in Rockville,Md on 930727 to Discuss Tier 1 Submittal for Bldg Designs & Primary Containment Design
ML20059C8451993-08-0404 August 1993
Summary of ACRS Subcommittee on BWRs (GE) 930615-17 Visit to GE Facility in San Jose,Ca to Gather Info Associated W/ Review of GE Ssar.Meeting Agenda Encl
ML20056D9421993-07-30030 July 1993
Summary of 930707-08 Meeting W/Bnl & GE in San Jose,Ca Re Review of ABWR Ts.Meeting Attendees Listed
ML20056D0971993-07-15015 July 1993
Summary of 930621-24 Meeting W/Ge in Livermore,Ca to Write Proof & Review Instrumentation Sys TS for GE Abwr.Meeting Attendees Listed in Encl 1
ML20056C3761993-05-10010 May 1993
Summary of 930426 Meeting W/Ge in Rockville,Md to Discuss Resolution of Severe Accident Issues for Advanced Bwr. Attendees Listed in Encl 1
ML20059C7421993-03-0202 March 1993
Summary of 392nd ACRS Meeting on 921209-11 in Bethesda,Md Re SBO Rule,Ts Improvement Program,Advanced BWR Design,River Bend Nuclear Plant Reliability Monitoring Program & Generic Issue 120,online Testability of Protection Sys
ML20128E8351993-02-0505 February 1993
Summary of 930120-21 Meeting W/Ge in San Jose,Ca Re Issues Related to ABWR PRA
ML20128E8531993-02-0505 February 1993
Summary of 921112-13 Meeting W/Ge Nuclear Energy in San Jose,Ca Re Issues Related to ABWR PRA
ML20128E8651993-02-0404 February 1993
Summary of 930121 Meeting W/Ge & Other Stated Companies in San Jose,Ca Re Status of ABWR Review.List of Attendees Encl
ML20128B7581993-01-27027 January 1993
Summary of 930111-21 Meeting W/Ge Re Development of ITAAC as Part of Certification Process.List of Attendees Encl
ML20127M6291993-01-25025 January 1993
Summary of 930108 Meeting W/Ge in Rockville,Md Re Status of Various Open Items in Chapter 14 of Draft Final SER for Abwr.List of Attendees Encl
ML20126F4041992-12-28028 December 1992
Summary of 921217 Meeting W/Ge Re Discussion on Status of Testing Programs Under Development by GE to Support Design of Sbwr.List of Attendees & RAI Responses Encl
ML20126M3881992-12-23023 December 1992
Summary of 921215 Meeting W/Ge in Rockville,Md to Discuss Issues Related to Industry & Staff Review of ABWR Insps, Tests,Analyses & Acceptance Criteria.List of Attendees & Viewgraphs Encl
ML20127D3211992-08-12012 August 1992
Summary of ACRS 388th Meeting on 920806-08 Re Insps,Tests, Analyses & Acceptance Criteria Program for GE ABWR Design. Design
ML20127D3221992-08-12012 August 1992
Summary of ACRS 388th Meeting on 920806-08 Re Plans for Reviewing GE Application for Certification of GE ABWR Design
1996-12-18
[Table view] |
Text
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f k [ 'o UNITED STATES fw NUCLEAR REGULATORY COMMISSION ACRSR-1548
{ ;p ADVISORY COMMITTEE ON REACTOR SAFEGUARDS D, g WASHINGTON, D. C. 20555
%...../
December 16, 1993 Mr. James M. Taylor Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Taylor:
SUBJECT:
DIVERSITY IN THE METHOD OF MEASURING REACTOR PRESSURE VESSEL WATER LEVEL IN THE ADVANCED AND SIMPLIFIED BOILING WATER REACTOR DESIGNS During the 404th meeting of the Advisory Committee on Reactor Safeguards, December 9-11, 1993, we discussed a proposal, advanced by representatives of the NRC staff, that General Electric Nuclear Energy (GENE; be required to instal.1 reactor pressure vessel (RPV) water level instrumentation that is diverse in operation froi. that presently employed on the Advanced Boiling Water Reactor (ABWR) and Simplified Boiling Water Reactor (SBWR) designs. During this meeting, we had the benefit of discussions with representatives of the NRC staff and GENE. We also had the benefit of the referenced documents.
We heard opposing views from the staff and GENE on the need for diversity in the method of measuring RPV water level in the ABWR and SBWR. The staf f argues that ". . . two independent and diverse methods for measuring the RPV level should be required because of the importance of RPV level instrumentation to BWRs and because operating experience has shown the potential for failure of redundant level instruments due to common cause." The argument given by GENE is that the ABWR water level instrumentation is rugged, simple, and highly redundant with no known remaining operational problems. GENE further argues that alternate vessel level measurement technologies are unqualified for this application.
The staff has concluded that the differential pressure level measurement system employed in current BWRs provides adequate indication of reactor vessel water level. The staff has also concluded that the presently proposed ABWR level instrumentation meets the minimum requirements of all applicable General Design Criteria. It is the staff's interpretation, however, that this proposed instrumentation may not be in compliance with the relevant post-TMI requirement as codified in 10 CFR 50.34(f).
9401100167 931216 "
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'M r . James M. Taylor 2 December 16, 1993 l
We do not believe that a case has been made by the staff for a water level indication system in advanced BWRs that is different from that currently used in operating BWRs.
Additional comments by ACRS Member , Ivan Catton and Thomas S. Kress are presented below. 4 l
Sincerely, 4 '
J. Ernest Wilkins, Jr.
Chairman Additional Comments by ACRS Members Ivan Catton and Thomas S. Kress We agree that the present nethod of measuring vessel water level is sufficient for adequate protection for BWRs and that it is not appropriate to backfit new diversity into existing plants.
Nevertheless, an objective of advanced and passive plants is to provide a higher level of safety assurance. We believe that the availability of at least three alternative level measuring methods affords an opportunity to provide this higher level of assurance in this important area. We agree with the staff's recommendation that installation of diverse vessel level instrumentation be required for the ABWR and SBWR designs.
References:
- 1. Proposed Draft SECY Paper (undated), from James M. Taylor, EDO, for the Commissioners, Subjecc, Diversity in the Method of Measuring Reactor Pressure Vessel Level in Advanced Boiling Water Reactor and Simplified Boiling Water Reactor (Draft Predecisional)
- 2. Memorandum dated December 10, 1993, from P. Boehnert, ACRS, for ACRS Members,
Subject:
ACRS Review of Proposed Requirement for Diverse Vessel Water Level Instrumentation for ABWR/SBWR -
Additional Information on Diverse Level Instrumentation for German and Swedish BWR Plants l
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