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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20206S6461999-02-17017 February 1999
Summary of ACRS Reliability & Probabilistic Risk Assessment, Plant Operations & on Regulatory Policies & Practices Subcommittees 981119-20 Meeting in Rockville,Md Re Options Make 10CFR50 & 10CFR50.59 risk-informed
ML20206S4381999-01-25025 January 1999
Summary of 458th ACRS Meeting on 981203-05 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20206S6611999-01-11011 January 1999
Summary of 981215-17 ACRS Thermal Hydraulic Phenomena Subcommittee Meeting in Rockville,Md Re T/H Code Activities/ NRC T/H Research Status
ML20206S6101998-12-23023 December 1998
Summary of ACRS Reliability & Probabilistic Risk Assessment Subcommittee 981029 Meeting in Rockville,Md Re Options to Make 10CFR50 risk-informed,NEI Whole Plant Study & Options for Developing risk-informed Approach,Revising 10CFR50.59
ML20206S8501998-11-13013 November 1998
Summary of 456th ACRS Meeting on 980930-1002 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20206S2481998-11-12012 November 1998
Summary of 455th ACRS Meeting on 980902-04 in Rockville,Md Re Items Listed in Attached Agenda
ML20206S7621998-11-12012 November 1998
Summary of 980924 ACRS Submommittee on Reliability & PRA Open Meeting in Rockville,Md Re Proposed Options for Developing risk-informed Approach to Revising 10CFR50.59, Options for Broader Changes to 10CFR50
ML20206S4161998-09-29029 September 1998
Summary of 980826 Open ACRS Subcommittee on Reliability & PRA Meeting in Rockville,Md Re Issues in SRM on situation-specific Cases Where PRA Results & Insights Have Improved Existing Regulatory Sys
ML20206S3851998-09-0303 September 1998
Summary of 980729 Open ACRS Joint Meeting of Subcommittees on Plant Operations & Fire Protection in Atlanta,Ga Re Region II Activities & Other Items of Mutual Interest, Including Significant Operating Events & Fire Protection
ML20206S6831998-09-0101 September 1998
Summary of 453rd ACRS Meeting on 980603-05 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20206S3761998-08-24024 August 1998
Summary of 980716 ACRS Plant License Renewal Subcommittee Meeting in Rockville,Md Re Presentations by & Holding Discussions with NRC Staff Re License Renewal,Proposed Staff Plans & Schedule for Reviewing License Renewal Applications
ML20206S3811998-08-0404 August 1998
Summary of ACRS Safety Research Program Subcommittee Meeting on 980717 in Rockville,Md Re Comments & Recommendations in 980616 ACRS Rept, Core Research Capabilities & Associated Staff Response
ML20206S3721998-07-29029 July 1998
Summary of 980707 ACRS Advanced Reactor Designs Subcommittee Meeting in Rockville,Md Re Info on AP600 Test & Analysis Program & Responses to ACRS Questions Asked During Previous Meetings
ML20206S6721998-07-0808 July 1998
Summary of ACRS Safety Research Program Subcommittee 980601 Meeting in Rockville,Md Re Discussion with NRC Concerning SECY-98-076, Core Research Capabilities
ML20206S3671998-06-30030 June 1998
Summary of 980619 Open ACRS Meeting of Subcommittee on Plant Operations in Rockville,Md Re Proposed Changes to 10CFR50.59,status of Resolution of Issues Identified in 980324 SRM Related to SECY-97-205 & Related Matters
ML20206S3501998-06-26026 June 1998
Summary of 980617-18 ACRS Advanced Reactor Designs Subcommittee Meeting in Rockville,Md Re Review of Advance FSER Chapters 4,5,7,8,11,13 & 18,level 1 AP600 Pra,Itaac & Associated ACRS Open Questions
ML20206S5991998-06-23023 June 1998
Summary of ACRS Reactor Fuels,Onsite Fuel Storage & Decommissioning Subcommittee 980423-24 Meeting in Rockville, MD Re Basis of Proposed NRC Fuel Failure Criterion for High Burnup Conditions & Adequacy of NRC Fuel Codes
ML20206S3361998-06-22022 June 1998
Summary of 980611-12 Open ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommittee Meeting in Rockville,Md Re Continuance of Review of Results of W Test & Analysis Program in Support of AP600 Design Certification
ML20206S6411998-06-22022 June 1998
Summary of 980601 ACRS Matls & Metallurgy Subcommittee Meeting in Rockville,Md Re NRC Staff Concerns Related to ASME Boiler & Pressure Vessel Code,Section III Rule Revs
ML20206S2561998-06-17017 June 1998
Summary of 452nd ACRS Meeting on 980430-0502 in Rockville, MD Re Items Listed in Attached Agenda
ML20206S6301998-06-17017 June 1998
Summary of 980602 ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommitteemeeting in Rockville,Md Re GE Extended Power Uprate Program for Operating BWRs & NSP lead-plant Application for Power Uprate
ML20206S5761998-06-0404 June 1998
Summary of ACRS Reliability & Probabilistic Risk Assessment Subcommittee 980416 Meeting in Rockville,Md Re Subcommittees Review of Matters Related to Elevation of CDF & Possible Rev to Commissions Safety Goal Policy Statement
ML20206S5671998-05-30030 May 1998
Summary of ACRS Advanced Reactor Designs Subcommittee 980513-15 Meeting in Rockville,Md Re Review of AP600 Standard SAR & Associated Advanced FSER Chapters 3,6,14,16 & 17
ML20206S2521998-05-14014 May 1998
Summary of 451st ACRS Meeting on 980402-04 in Rockville,Md Re Items Listed in Attached Agenda
ML20206S2801998-04-30030 April 1998
Summary of 980219-20 ACRS Open Meeting of Subcommittee on Reliability & Probabilistic Risk Assessment in Rockville,Md Re Continuance of Review of Proposed Final SRP Sections & RGs for risk-informed,performance-based Regulation
ML20206S2951998-04-15015 April 1998
Summary of 450th ACRS Meeting on 980305-07 in Rockville,Md Re Items Listed in Attached Agenda
ML20206S2871998-04-15015 April 1998
Summary of 449th ACRS Meeting on 980302-04 in Rockville,Md Re Items Listed in Attached Agenda
ML20206S6481998-03-26026 March 1998
Summary of ACRS Fire Protection Subcommittee 980122 Meeting in Rockville,Md Re Staff Actions Taken Related to Development of Revised Fire Protection Rule
ML20196L0531998-03-20020 March 1998
Summary of 980205-07 ACRS 448th Meeting in Rockville,Md Re Items Listed in Attached Agenda
ML20206S6561998-03-13013 March 1998
Summary of ACRS Plant License Renewal Subcommittee 980123 Meeting in Rockville,Md Re License Renewal Implementation Issues & Proposed Industry Guidelines
ML20206S2751998-03-0909 March 1998
Summary of 980218 ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommittee Open Meeting in Rockville,Md Re Review of RES Program in Area of thermal-hydraulic Phenomena in Support of ACRS Planned Rept to Commission
ML20206S6791998-03-0505 March 1998
Summary of ACRS Plant Operations Subcommittee 980203 Meeting in Rockville,Md Re Subcommittee Review of Proposed Improvements to Senior Mgt Meeting Process
ML20217A8561998-03-0505 March 1998
Summary of ACRS 448th Meeting on 980205-07 Re Several Matters & Completed Listed Rept & Ltr.Committee Authorized Larkins,Executive Director,To Transmit Memoranda Listed
ML20206S2651998-02-23023 February 1998
Summary of 980203-04 ACRS Subcommittee on Advanced Reactor Designs Open Meeting in Rockville,Md Re Review of Chapters 1,4,5,7,8,11,13 & 18 of AP600 Ssar & AP600 Test & Analysis Program
IR 07100203/20064471998-02-0505 February 1998
Summary of 971203-06 447th ACRS Meeting in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20206S3931998-01-28028 January 1998
Summary of 980121 ACRS Subcommitee on Human Factors Meeting in Rockville,Md Re Human Performance & Reliability Plan & Integration of Human Factors Insights Into Insp Process
ML20217A8461998-01-0909 January 1998
Summary of ACRS Plant Operations Subcommittee 971202 Meeting in Rockville,Md Re SER on industry-sponsored Utility Resolution Guidance for Issue of Blockage of Suction Strainer in ECCS
ML20217A8771997-12-23023 December 1997
Summary of ACRS 446th Meeting on 971106-07 in Rockville,Md Re Appropriate Action on Items Listed on Attached Agenda.W/ Fr Notice,Meeting Schedule & Outline,List of Attendees, Future Agenda & List of Documents Provided to Committee
ML20217A9911997-12-23023 December 1997
Summary of 447th ACRS Meeting on 971203-06 Re Proposed Revs to 10CFR50.59 & Credit for Containment Overpressure to Provide Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal
ML20217A8651997-12-15015 December 1997
Summary of ACRS Reliability & PRA Subcommittee 971112-13 Meeting in Rockville,Md Re Proposed Final SRP for risk- informed,performance-based Regulation
ML20217A9831997-12-0303 December 1997
Summary of 971203 ACRS Meeting in Rockville,Md Re Conduct of ACRS Business
ML20217A8811997-12-0202 December 1997
Summary of ACRS Safety Research Program Subcommittee 971104- 05 Meeting in Rockville,Md Re NRC Safety Research Program & Draft Annual Rept to Congress
ML20217A5901997-12-0202 December 1997
Summary of 445th ACRS Meeting in Rockville,Md on 971002-03 Re Appropriate Action on Items Listed in Attached Agenda.W/ Fr Notice,Meeting Schedule & Outline,List of Attendees, Future Agenda & List of Documents Provided to Committee
ML20217A8221997-12-0101 December 1997
Informs That During 446th Meeting on 971106-07,ACRS Discussed Several Matters & Completed Listed Ltr. Committee Authorized Larkins,Executive Director,To Transmit Memoranda,Listed
ML20217A8901997-11-21021 November 1997
Summary of ACRS Reliability & PRA 971021-22 Meeting in Rockville,Md Re Matter Included in Staff Requirements Memo,
ML20217A6381997-11-0606 November 1997
Summary of 444th ACRS Meeting in Rockville,Md on 970903-05 Re Appropriate Action Items Listed in Attached Agenda.W/Fr Notice,Meeting Schedule & Outline,List of Attendees & List of Documents Provided to Committee
ML20217B1921997-11-0606 November 1997
Summary of ACRS Planning & Procedures Subcommitte 971105 Meeting in Rockville,Md Re Conduct of ACRS Business
ML20217A8001997-10-21021 October 1997
Informs That During 445th Meeting on 971002-03,ACRS Discussed Several Matters & Completed Listed Rept & Ltrs. Committee Authorized Larkins,Executive Director,To Transmit Memoranda Listed
ML20217A8141997-10-20020 October 1997
Summary of ACRS Subcommittees on Pra,Plant Operations & Fire Protection 970828-29 Meeting in Rockville,Md Re Review of Staff Requirements Memo
ML20217A7011997-10-20020 October 1997
Summary of 970826-27 ACRS Subcommittees on Matls & Metallurgy & on Severe Accidents Joint Meeting W/Nrc,Nei & Industry in Rockville,Md Re Review of Proposed Draft GL & Associated Draft Regulatory Guide Re SG Tube Integrity
1999-02-17
[Table view]Some use of "" in your query was not closed by a matching "".
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20206S6461999-02-17017 February 1999
Summary of ACRS Reliability & Probabilistic Risk Assessment, Plant Operations & on Regulatory Policies & Practices Subcommittees 981119-20 Meeting in Rockville,Md Re Options Make 10CFR50 & 10CFR50.59 risk-informed
ML20206S4381999-01-25025 January 1999
Summary of 458th ACRS Meeting on 981203-05 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20206S6611999-01-11011 January 1999
Summary of 981215-17 ACRS Thermal Hydraulic Phenomena Subcommittee Meeting in Rockville,Md Re T/H Code Activities/ NRC T/H Research Status
ML20206S6101998-12-23023 December 1998
Summary of ACRS Reliability & Probabilistic Risk Assessment Subcommittee 981029 Meeting in Rockville,Md Re Options to Make 10CFR50 risk-informed,NEI Whole Plant Study & Options for Developing risk-informed Approach,Revising 10CFR50.59
ML20206S8501998-11-13013 November 1998
Summary of 456th ACRS Meeting on 980930-1002 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20206S2481998-11-12012 November 1998
Summary of 455th ACRS Meeting on 980902-04 in Rockville,Md Re Items Listed in Attached Agenda
ML20206S7621998-11-12012 November 1998
Summary of 980924 ACRS Submommittee on Reliability & PRA Open Meeting in Rockville,Md Re Proposed Options for Developing risk-informed Approach to Revising 10CFR50.59, Options for Broader Changes to 10CFR50
ML20206S4161998-09-29029 September 1998
Summary of 980826 Open ACRS Subcommittee on Reliability & PRA Meeting in Rockville,Md Re Issues in SRM on situation-specific Cases Where PRA Results & Insights Have Improved Existing Regulatory Sys
ML20206S3851998-09-0303 September 1998
Summary of 980729 Open ACRS Joint Meeting of Subcommittees on Plant Operations & Fire Protection in Atlanta,Ga Re Region II Activities & Other Items of Mutual Interest, Including Significant Operating Events & Fire Protection
ML20206S6831998-09-0101 September 1998
Summary of 453rd ACRS Meeting on 980603-05 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20206S3761998-08-24024 August 1998
Summary of 980716 ACRS Plant License Renewal Subcommittee Meeting in Rockville,Md Re Presentations by & Holding Discussions with NRC Staff Re License Renewal,Proposed Staff Plans & Schedule for Reviewing License Renewal Applications
ML20206S3811998-08-0404 August 1998
Summary of ACRS Safety Research Program Subcommittee Meeting on 980717 in Rockville,Md Re Comments & Recommendations in 980616 ACRS Rept, Core Research Capabilities & Associated Staff Response
ML20206S3721998-07-29029 July 1998
Summary of 980707 ACRS Advanced Reactor Designs Subcommittee Meeting in Rockville,Md Re Info on AP600 Test & Analysis Program & Responses to ACRS Questions Asked During Previous Meetings
ML20206S6721998-07-0808 July 1998
Summary of ACRS Safety Research Program Subcommittee 980601 Meeting in Rockville,Md Re Discussion with NRC Concerning SECY-98-076, Core Research Capabilities
ML20206S3671998-06-30030 June 1998
Summary of 980619 Open ACRS Meeting of Subcommittee on Plant Operations in Rockville,Md Re Proposed Changes to 10CFR50.59,status of Resolution of Issues Identified in 980324 SRM Related to SECY-97-205 & Related Matters
ML20206S3501998-06-26026 June 1998
Summary of 980617-18 ACRS Advanced Reactor Designs Subcommittee Meeting in Rockville,Md Re Review of Advance FSER Chapters 4,5,7,8,11,13 & 18,level 1 AP600 Pra,Itaac & Associated ACRS Open Questions
ML20206S5991998-06-23023 June 1998
Summary of ACRS Reactor Fuels,Onsite Fuel Storage & Decommissioning Subcommittee 980423-24 Meeting in Rockville, MD Re Basis of Proposed NRC Fuel Failure Criterion for High Burnup Conditions & Adequacy of NRC Fuel Codes
ML20206S6411998-06-22022 June 1998
Summary of 980601 ACRS Matls & Metallurgy Subcommittee Meeting in Rockville,Md Re NRC Staff Concerns Related to ASME Boiler & Pressure Vessel Code,Section III Rule Revs
ML20206S3361998-06-22022 June 1998
Summary of 980611-12 Open ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommittee Meeting in Rockville,Md Re Continuance of Review of Results of W Test & Analysis Program in Support of AP600 Design Certification
ML20206S6301998-06-17017 June 1998
Summary of 980602 ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommitteemeeting in Rockville,Md Re GE Extended Power Uprate Program for Operating BWRs & NSP lead-plant Application for Power Uprate
ML20206S2561998-06-17017 June 1998
Summary of 452nd ACRS Meeting on 980430-0502 in Rockville, MD Re Items Listed in Attached Agenda
ML20206S5761998-06-0404 June 1998
Summary of ACRS Reliability & Probabilistic Risk Assessment Subcommittee 980416 Meeting in Rockville,Md Re Subcommittees Review of Matters Related to Elevation of CDF & Possible Rev to Commissions Safety Goal Policy Statement
ML20206S5671998-05-30030 May 1998
Summary of ACRS Advanced Reactor Designs Subcommittee 980513-15 Meeting in Rockville,Md Re Review of AP600 Standard SAR & Associated Advanced FSER Chapters 3,6,14,16 & 17
ML20206S2521998-05-14014 May 1998
Summary of 451st ACRS Meeting on 980402-04 in Rockville,Md Re Items Listed in Attached Agenda
ML20206S2801998-04-30030 April 1998
Summary of 980219-20 ACRS Open Meeting of Subcommittee on Reliability & Probabilistic Risk Assessment in Rockville,Md Re Continuance of Review of Proposed Final SRP Sections & RGs for risk-informed,performance-based Regulation
ML20206S2871998-04-15015 April 1998
Summary of 449th ACRS Meeting on 980302-04 in Rockville,Md Re Items Listed in Attached Agenda
ML20206S2951998-04-15015 April 1998
Summary of 450th ACRS Meeting on 980305-07 in Rockville,Md Re Items Listed in Attached Agenda
ML20206S6481998-03-26026 March 1998
Summary of ACRS Fire Protection Subcommittee 980122 Meeting in Rockville,Md Re Staff Actions Taken Related to Development of Revised Fire Protection Rule
ML20196L0531998-03-20020 March 1998
Summary of 980205-07 ACRS 448th Meeting in Rockville,Md Re Items Listed in Attached Agenda
ML20206S6561998-03-13013 March 1998
Summary of ACRS Plant License Renewal Subcommittee 980123 Meeting in Rockville,Md Re License Renewal Implementation Issues & Proposed Industry Guidelines
ML20206S2751998-03-0909 March 1998
Summary of 980218 ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommittee Open Meeting in Rockville,Md Re Review of RES Program in Area of thermal-hydraulic Phenomena in Support of ACRS Planned Rept to Commission
ML20206S6791998-03-0505 March 1998
Summary of ACRS Plant Operations Subcommittee 980203 Meeting in Rockville,Md Re Subcommittee Review of Proposed Improvements to Senior Mgt Meeting Process
ML20217A8561998-03-0505 March 1998
Summary of ACRS 448th Meeting on 980205-07 Re Several Matters & Completed Listed Rept & Ltr.Committee Authorized Larkins,Executive Director,To Transmit Memoranda Listed
ML20206S2651998-02-23023 February 1998
Summary of 980203-04 ACRS Subcommittee on Advanced Reactor Designs Open Meeting in Rockville,Md Re Review of Chapters 1,4,5,7,8,11,13 & 18 of AP600 Ssar & AP600 Test & Analysis Program
IR 07100203/20064471998-02-0505 February 1998
Summary of 971203-06 447th ACRS Meeting in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20206S3931998-01-28028 January 1998
Summary of 980121 ACRS Subcommitee on Human Factors Meeting in Rockville,Md Re Human Performance & Reliability Plan & Integration of Human Factors Insights Into Insp Process
ML20217A8461998-01-0909 January 1998
Summary of ACRS Plant Operations Subcommittee 971202 Meeting in Rockville,Md Re SER on industry-sponsored Utility Resolution Guidance for Issue of Blockage of Suction Strainer in ECCS
ML20217A9911997-12-23023 December 1997
Summary of 447th ACRS Meeting on 971203-06 Re Proposed Revs to 10CFR50.59 & Credit for Containment Overpressure to Provide Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal
ML20217A8771997-12-23023 December 1997
Summary of ACRS 446th Meeting on 971106-07 in Rockville,Md Re Appropriate Action on Items Listed on Attached Agenda.W/ Fr Notice,Meeting Schedule & Outline,List of Attendees, Future Agenda & List of Documents Provided to Committee
ML20217A8651997-12-15015 December 1997
Summary of ACRS Reliability & PRA Subcommittee 971112-13 Meeting in Rockville,Md Re Proposed Final SRP for risk- informed,performance-based Regulation
ML20217A9831997-12-0303 December 1997
Summary of 971203 ACRS Meeting in Rockville,Md Re Conduct of ACRS Business
ML20217A5901997-12-0202 December 1997
Summary of 445th ACRS Meeting in Rockville,Md on 971002-03 Re Appropriate Action on Items Listed in Attached Agenda.W/ Fr Notice,Meeting Schedule & Outline,List of Attendees, Future Agenda & List of Documents Provided to Committee
ML20217A8811997-12-0202 December 1997
Summary of ACRS Safety Research Program Subcommittee 971104- 05 Meeting in Rockville,Md Re NRC Safety Research Program & Draft Annual Rept to Congress
ML20217A8221997-12-0101 December 1997
Informs That During 446th Meeting on 971106-07,ACRS Discussed Several Matters & Completed Listed Ltr. Committee Authorized Larkins,Executive Director,To Transmit Memoranda,Listed
ML20217A8901997-11-21021 November 1997
Summary of ACRS Reliability & PRA 971021-22 Meeting in Rockville,Md Re Matter Included in Staff Requirements Memo,
ML20217A6381997-11-0606 November 1997
Summary of 444th ACRS Meeting in Rockville,Md on 970903-05 Re Appropriate Action Items Listed in Attached Agenda.W/Fr Notice,Meeting Schedule & Outline,List of Attendees & List of Documents Provided to Committee
ML20217B1921997-11-0606 November 1997
Summary of ACRS Planning & Procedures Subcommitte 971105 Meeting in Rockville,Md Re Conduct of ACRS Business
ML20217A8001997-10-21021 October 1997
Informs That During 445th Meeting on 971002-03,ACRS Discussed Several Matters & Completed Listed Rept & Ltrs. Committee Authorized Larkins,Executive Director,To Transmit Memoranda Listed
ML20217A7011997-10-20020 October 1997
Summary of 970826-27 ACRS Subcommittees on Matls & Metallurgy & on Severe Accidents Joint Meeting W/Nrc,Nei & Industry in Rockville,Md Re Review of Proposed Draft GL & Associated Draft Regulatory Guide Re SG Tube Integrity
ML20217A8141997-10-20020 October 1997
Summary of ACRS Subcommittees on Pra,Plant Operations & Fire Protection 970828-29 Meeting in Rockville,Md Re Review of Staff Requirements Memo
1999-02-17
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
CERTIFIED MINUTES DATE ISSUED: August 13, 1986 g, OMC-M51 p 9 I
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SUMMARY
/ MINUTES OF THE AUGUST 5,1986 MEETING 0F THE N 3 5 5M ACRS RELIABILITY ASSURANCE SUBCOMMITTEE WASHINGTON, D.C.
A meeting was held by the ACRS Reliability Assurance Subcomittee on August 5, 1986. The meeting ran from 8:30 a.m. until 1:40 p.m. The original purpose of the meeting was to review the final resolution of Unresolved Safety Issue A-46, " Seismic Qualification of Equipment in Operating Plants." The Subcommittee was also planning to hear a briefing by the Vendor Program Branch /IE on the status of a generic check valve program. However, the check valve program was heard by the Committee's Westinghouse Subcommittee in connection with the 11/21/85 loss of feedwater event at San Onofre Unit I and was deleted from the
~
day's agenda. Notice of this meeting was published in the Federal Register on Tuesday, July,22, 1986 (Attachment A). Attachment B is a schedule of presentations and Attachment C is a list of slides and handouts on file.in the ACRS office. The meeting was entirely open to the public. ~ Richard Major was the cognizant ACRS Staff member for this meeting.
Attendees ACRS NRC ;
C. Wylie, Chairman R. Bosnak R. Rothman J. Ebersole, Member N. Anderson Pei-Ying Chen C. Siess, Member T. Y. Chang G. Weidenhamer C. Michelson, Member G. Bagchi J. O'Brien G. Reed, Member J. Conran N. Thomasson l R. Major, ACRS Staff H. Reponen R. Hernan !
Industry Representatives Others J. Thomas, Duke Power Co. D. Tang, Westinghouse C. Smith, ANC0 C. Knowles, Ace G. Sliter, EPRI G. Pomy, NUS Corp.
R. Kennedy, SSRAP E. Fotopoulos, Serch Licensing, Schaffstall, KMC Bechtel M. Czarneck, URS/Blume R. Borsum, B&W W. Schmidt, MPR Assoc. G. Brown, Stone & Webster G. Hardy, EQE W. Stelm, Bishop, Liberman, Cook J. Betlack, MPR D. Varner, Boston Edison .
L. Toth, Gasser Assoc. I l
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RELIABILITYASSURANCE(A-46) 2 August 5, 1986 Meeting
- 1. NRC Staff Status Report - T. Y. Chang, NRC It was noted that A-46 was designated as an unresolved safety issue (USI) in December 1980. Seismic experience and test experience will be used by the Staff to resolve the question of seismic qualification of equipment in operating plants (those which were built prior to current seismic design requirements--this effort was initiated in lieu of backfitting). There were three main concerns that were addressed:
- 1) equipment anchorages,
- 2) relay functional capability, and
- 3) outliers (equipment not included in the seismic experience base).
f The proposed resolution for operating plants will use plant walkdown inspections to satisfy the concerns listed above. This resolution will be implemented on the relevant plants through the use of a generic letter.
The Staff plans to meet with the Comittee to Review Generic Requirements (CRGR)inSeptember1986. The issuance of the final resolution and generic letter is expected in October 198G.
- 2. Seismic Qualification Utility Group (SQUG) Presentation - J. Thomas
! The SQUG program was initiated in 1982 by a group of utilities to determine the feasibility of using actual earthquake experience in industrial facilities to demonstrate the seismic ruggedness of convest-fonal power plant equipment used in nuclear plants. With NRC suppohttheprogramwasexpandedtoprovidethetechnicalapproachfor the resolution of A-46.
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( , RELIABILITYASSURANCE(A-46) 3 August 5, 1986 Meeting The scope of the program has grown to include 21 classes of safe shutdown equipment. The current seismic experience data base contains data from: over twelve strong motion earthquakes, well over sixty facilities, hundreds of structures, thousands of equipment installations, and peak accelerations from 0.2 to 0.8g with durations up to 40 seconds. It is felt that after trial use in 1986 the generic implementation of the resolution will take place in 1987/1988.
Mr. Thomas noted that results indicate that piping and cable trays are not a problem area. He also stated that relay chatter has proven not to cause system problems.
- 3. Documentatien of Equipment Seismic Ruggedness - W. Schmidt, MPR Assoc.
The purpose of this effort is to assimilate and sumarize available experience on the performance of safe shutdown equipment in strong motion earthquakes. A description of the equipment in the experience data base (for the 21 classes of equipment) will be given. The documentation will contain a general discussion of observed seismic ruggedness along with a description of nuclear power plant applications.
Also included in the documentation is a sumary of the equipment inventory by earthquake and facility and a sumary of the observed seismic effects. The documentation will include recommended restrictions, exclusions, and caveats on the application of the data base to nuclear plant equipment.
- 4. EPRI Research Contributions to Resolution of USI A ,
rge Sliter, EPRI Mr. Sliter explained that EPRI conducted research in three main areas that contributed to the resolution of USI A-46. These areas were anchorage guidelines, equipment ruggedness, and relay functionality. It
D RELIABILITYASSURANCE(A-46) 4 August 5, 1986 Meeting was noted that in the entire SQUG data base there were only 360 cases of
- known anchorage damage. (Only 12 of these were in conventional power plants; the remainder were in other facilities such as refineries, wineries,etc.). It was observed that-performance of nuclear-plant-like anchorages are compatible with analytical guidelines. Siesmic effects on aged components were examined using shake table tests of side-by-side new and aged components (38 types tested, e.g., RES, CAP, TRANS, IC, relays, transmitters, switches, motors,etc.). There were no significant aging effects on post-test operability of all components.
There were no significant aging effects during shaking except for switches at relatively high G's.
- 5. Seismic Anchorage Guidelines for Nuclear Plant Equipment -
M. Czarneck, URS/BLUME This program analyzed equipment anchorage capacity compared with seismic input. Equipment considered included: pumps, motors, compressors, transformers, switch gear, battery rack, instrument racks, control room panels, inverters, battery chargers, distribution panels, and motor control centers. Tanks and heat exchangers are expected to be added later. Fastener strength criteria are based on the type of anchors used (98% of anchors fall into only three categories). Screening tables are being produced which give capacity as a function of equipment and fastener parameters. Also under development are inspection check lists to be used in the field for anchorage verification and inspection of workmanship. A computer code has been developed to analyzed those anchors not covered by the screening tables.
1
- 6. EtRI Generic Seismic Qualification of Equipment Using Existing Test ;
"bata-C. Smith,ANCOEngineers l
The objective of this was to demonstrate seismic ruggedness of as much l nuclear power plant equipment as possible by collating and evaluating l
l l
r RELIABILITYASSURANCE(A-46) 5 August 5, 1986 Meeting existing test response spectra. Generic Equipment Ruggedness Spectrums (GERS) were produced for the various equipment classes (21) considered in the program. Currently, results of this effort are under review and a draft final report has been prepared.
- 7. Development of Generic Implementation Procedure - W. Schmidt, MPR Assoc.
The purpose of this effort is to provide the methodology to define the scope of safe shutdown equipment to be evaluated on a plant-specific basis. The Generic Implementation Procedures will provide criteria, guidelines, and procedures for the application of seismic experience and test data to specific plants. Also to be included are review and walkdown criteria, guidelines and check lists. Standard data sheets to document the reviews, walkdowns and findings will be used.
- 8. Summary of Technical Approach for Seismic Evaluation of Relays in Nuclear Power Plants - W. Schmidt, MPR Assoc.
The objective of this program is to develop the methodology and procedures to evaluate and define seismic functionality requirements for relays in operating nuclear plants. A two-phased approach is being used. First, those systems, associated circuits and relays which must remain functional during and immediately after an earthquake are defined. Second, seismic ruggedness data which can be used to assess the seismic adequacy of essential relays will be provided.
Under certain conditions operator actions to reset or restore systems to operatton will be acceptable. The conditions include:
- the operator is provided with indications of system status, l
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l
i RELIABILITYASSURANCE(A-46) 6 August 5, 1986 Meeting
- there is adequate time to perfonn the resetting or restoring action,
- the number of systems that must be restored are small enough to be manageable, and procedures are available to assist the operator in carrying out the corrective actions.
- 9. Performance of Relays in Earthquakes: A Summary of Available Data, June 1986 - G. Hardy, EQE Inc.
This work documents relay performance in 23 data-based sites, representing nine strong-motion earthquakes. Of the estimated 5,000 relays existing at these data base sites, there were 23 documented cases of spurious relay actuations. The relay types that caused the spurious actuations are documented. It was also noted that operators have diagnosed and reset spurious relay actuations within two hours for the six cases where adequate documentation exists.
- 10. Conclusions - J. Thomas, SQUG Mr. Thomas noted that based on this effort the significance of seismic events in operating plants is lower than it was expected to be two years ago when this program began in earnest. He also explained that this program is not attempting to examine every piece of equipment in a plant, but rather is designed to look for weak links in the plant's seismic capability and solve those problems.
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- 11. 'Open Executive Session - Chairman Wylie In concluding the meeting Mr. Wylie explained that he would recomend the ACRS continue to endorse the resolution of A-46. He noted that the letter would probably contain other suggestions for the Staff to
s' .
RELIABILITY ASSURANCE (A-46) 7 August 5, 1986 Meeting consider. During the August 1986 meeting, Mr. Wylie intended to give a Chairman's report to the ACRS, allow the NRC Staff time to make a status report, and requested representation from the SQUG be available to field Comittee questions.
Future Meetings:
This matter was reported to the full ACRS during the August 7-9, 1986 full Comittee meeting. A letter to the Comission was begun during the August meeting. The letter is now scheduled for completion during the September full Comittee meeting, September 11-13, 1986.
NOTE: A transcript of the meeting is available in the NRC Public Document Room,1717 H St. , N.W. , Washington, D.C. , or can be purchased from ACE-Federal Reporters, 444 N. Capitol St.,
Washington, D.C. 20001 [(202) 347-3700]
- .,-n .,.-. -- -.. . , . - _ . _ - , ., - --
o nwawmewT M
.' 28318 Fedir:1 Regist:r / Vcl. 51, No.140 / Tuisday, July 22, 1986 / Notices. -g ,
cnd the time all b He: man Alderman (telephone 202/834- . Qairman'a rulingon requests foe'the .
. obtained byrepaid a p,otted therefor telephone call to- can1414)e between 8:15 A.M. and 5:00 P.M.- '; Ity to t oral statemenia ,
the cogniennt ACRS staff member. Mr. Persons planning to attend this meeting Ethe time a therefor can be <
"f pidio Igne (telephone 202/634-1414) are urged to contact the above named obtained by a propold telephone call to itween 8:15 A.M. and 500 P.M. Persona individual one or two days before the . the cobrdsant ACRS staff member, Mr.t *
,/anning to attend this meeting are scheduled meeting to be advised of any Richard Major (telephone 202/634-1414) -
changee in schedule, etc., which may between 8:15 A.M. and MD P.M.Pereena J urged to contact the above named individual one or two days before the have occurred. planning to attend this meeting ass .
scheduled meeting to be advised of any Dated: July le.1ges, armed to contact the above named .
changes in schedule, etc., which may Individual one or two days before the Morton W. Ube:Un.
b * * ****'" O' acheduled meeting to be advloed of any.
'Anistant hecutive Directorfor Pmject Dated. july 17.1986. Review, changes in schedule, etc.,which may have occurred.
Moston W. Ubarkin. [FR Doc e6-16451 Filed 7-et-se: tes sm)
Assistant Decutive Directorfor Project mwnezoon rene eur .- Deted; july 17.1988. - -
/ -
Morton W. Uberida, *" '
Review. ,
(FR Doc. 86-16441 F11ed 7-21-ast 545 em} / Auistant. becutive Directorfor Project saAmo coon rseus-as y Advisory Committee on Reector g,yj,,,
Safeguards; SubcommMtee on (FR Doc. as-leses rded 7-at-act e4s sm)
Reuabuity Assurance; Meeting _ ,, _
Advisory Committee on Reactor He ACRS Subcommittee on ,
Safeguards; Subcommittee on Reactor . Reliability Assurance win hold a OpwoWon" MeeHnI meeting on August 5,1986. Room 1046, [Doctiet No. 50-373 and 56-374)
He ACRS Subcommitiee on Reactor 1717 H Street. NW., Washington. DC. Commomessith Edison Co.;La Saee Operations wiD bold a meeting on %e entire meeting will be open to County Station, Unita 1 and 2; Denial of August 4.1986. Room 1048,1717 H public attendance. Amendmenta to Poemty OpereHng Street. NW., Wa shington. DC. The agenda for the subject meeting Uoense and Opportunity for Hearing The entire meeting will be open to shall be as follows:
public attendance. 7besday, August 5,1986-&JO AX. %e U.S. Nuclear Regulatory
. ne agenda for the subject meeting Commission (the Commission) hu Untilthe Coaclusion ofBusiness
" denied in part requests by the licensee
%e Subcommittee will review the for amendments to Facility Operating Afonday. August d.19ss-12PR until final resolution of USI A-46. " Seismic Ucense Nos. NPF-11 and NPF-18, issued the conclusion of busines' Qualification of Equipment in O erating to the Commonwealth Edison Company He Subcommittee will review recent Plants." He Subcommittee will also (licensee), for operation of the la Salle wents at operating plants. hear a briefing by the Vendor Program Branch NRC's Office ofInspection and County Station. Units 1 and 2 located in
[ Oral statements may be presented by La Salle County. Illinois.The Notice of gembers of the public with the Enforcement on the status of a generic check valve program. Consideration ofIssuance of concurrence of the Subcommittee Amendments was published in the Chairman; written statements will be Oral statements may be presented by Federal Registee on April S.1988 (51 FR cceepted and made available to the members of the public with the Committee. Recordings will be permitted concurrence of the Subcommittee 12247).
Chairman; written statements will be De amendments proposed by the only during those portions of the accepted and made avellable to the Ifeensee would change the Technical sneeting when a transcript is being kept, and questions may be asked only by Committee. Recordings will be permitted Specifications:(a)To add fire detectors those portions of the in fire zones 2C,4C2. 3C,4C3, and SE to
. members of the Subcommittee.its only d consultants, and Staff. Persons desiring meeting en a transcript is being kept, Unit 1 to demonstrate compliance with to make oral statements should notify and questions may be asked only by Operating Ucense NPF-11 Uoense the ACRS staff member named below as ' members of the Subcommittee,its Condition 2.C.(25)(c): and (b) for Units 1 far in advance as is p,cticable so that consultants, and Staff. Persons desiring and 2 to delete the Action Statement cppropriate arrangements can be made. to make oral statements should notify 3.3.7.9b.%e licensee's reason for this During the initial portion of the the ACRS staff member named below as proposed item b change is that: a) they meeting, the Subcommittee may far in advance as is practicable so that will have the required special fire watch cxchange preliminary views regarding appropriate arrangements can be made. patrol at least once per hour in each matters to be considered during the During the initial portion of the such area with a deficient number of fire meeting, the Subcommittee, along with detection instruments, and b) this balance of the meeting.%e any ofits consultants who may be change is consistent with the Ceneral Subcommittee will then bear presentations by and hold discussions present, may exchange preliminary Electric (GE) Standard Technical with representatives of the NRC Staff views regarding matters to be Specifications (STS). However, the and other interested persorplegarding considered during the balance of the presence of the required special fire this review. - meeting. watch (3.3.7.9e) does not address the Further information rem topics %e Subcommittee will then hear requirement for returning instruments to to be discussed.whether the meeting presentations by and hold discussions operable status or submitting a Special has been cancelled oc rescheduled, the with representatives of the NRC Staff. Report to describe the actions taken to Chairman's ruling on requesta for the its consultants, and other interested restore the operability, the cause of the opportunity to present oral statements persons regartling this review. Inoperability, and plans and schedule Further information regarding topics for restoring the instrumenta status if and the time a!Iotted therefor can be obtained by d prepaid telephone call to to be discussed, whether the meeting instruments are not operable after 14 th has been cancelled or rescheduled. the da,ys. In addition, the proposed change O e cognizant ACRS staRmember,Mr.
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j ATTACHMENT A l.
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I ATh e#eeeT S
TENTATIVE SCHEDULE FOR THE AUGUST 5, 1986 MEETING OF THE .
ACRS SUBCOMMITTEE ON RELIABILITY ASSURANCE 1 WASHINGTON, DC l (ResolutionofA-46) l Topic Speaker Minutes 8:30 1. Chairman's Opening Remarks C. Wylie/ACRS 5 l l
8:35 2. Status of USI A-46 NRC 10
- T. Y. Chang 8:45 3. Overview of SQUG Activities SQUG
- N. Smith / 15 J. Thomas 9:00 4. Documentation of Seismic Adequacy SQUG/EQE 15 of Safe Shutdown Equipment - W. Schmidt 9:15 5. Generic Implerrentation Plan SQUG/MPR 30
- W. Schmidt 9:45 6. Equipment Anchorage Review EPRI 30 Guid? lines - G. Sliter 10:15 BREAK 10:30 7. Generic Equipment Ruggedness EPRI 30 Spectra
- G. Sliter 11:00 8. Relay Evaluation Procedures EPRI/MPR 30
- W. Schmidt 11:30 9. Relay Seismic Experience Data .SQUG/EQE 30
- G. Hardy
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um,/HiV7; 55-Status g 7, ,f - E. Merschoff 12:55 11. Closing Remarks C. Wylie/ACRS 5 1:00 ADJOURN ATTACHMENT B
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o
. ATTACHMENT C LIST OF SLIDES AND HANDOUTS .
AUGUST 5, 1986 MEETING .
ACRS RELIABILITY ASSURANCE SUBCOMMITTEE -
WASHINGTON, D.C.
- 1. Slides from T. Y. Chang, NRC, USI A-46 CRGR Presentation August 5, 4
1986, 7 slides
- 2. Slides from J. Thomas, Duke Seismic Qualification Utility Group (SQUG) Progress Review Neeting, Advisory Committee on Reactor Safeguards (ACRS), August 5, 1986, 11 slides
- 3. Slides from W. Schmidt, MPR, Documentation of Equipment Seismic Ruggedness, 2 slides
- 4. Slides - G. Sliter, EPRI, EPRI Research Contributions to Resolution of USI A-46, 6 slides
- 5. Slides, M. Czarneck, URS/Blume, Seismic Anchorage Guidelines for Nuclear Plant Equipment, 14 slides i 6. Slides, C. Smith, ANCO, EPRI Generic Seismic Qualification of Equipment Using Existing Test Data, 16 slides 4
- 7. Slides, from W. Schmidt, MPR, Development of Generic Implementation Procedures, 5 slides 4
- 8. Slides from W. Schmidt, MPR, Summary of Technical Approach for Seismic Evaluation of Relays in Nuclear Power Plants, EPRI Project RP2849-1, 9 slides
- 9. Slides, G. Hardy, EQE, The Performance of Relays in Earthquakes: A Summary of Available Data 25 slides ATTACHMENT C
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