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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
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
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
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
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 "".
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
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
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
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
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
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,
ML20217B1921997-11-0606 November 1997
Summary of ACRS Planning & Procedures Subcommitte 971105 Meeting in Rockville,Md Re Conduct of ACRS Business
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
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
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SUMMARY
/ MINUTES OF THE APRIL 23, 1985 MEETING OF THE ACRS SUBCOMMITTEE ON RELIABILITY ASSURANCE (VALVES)
WASHINGTON, DC A meeting was held by the ACRS Subcommittee on Reliability Assurance on April 23, 1985. The purpose of the meeting was to continue the Sub-comrnittee's investigation of valve reliability. The Subcommittee dis-cussed programs and initiatives underway by the NRC and industry.
Notice of the meeting was published in the Federal Register on April 4, 1985 (Attachment A). Attachment B is a schedule of presentations.
Attachment C is a listing of meeting slides and handouts on file in the ACRS office. The meeting was entirely open to the public. Richard Major was the cognizant staff member for this meeting.
Participants NRC C. Michelson, Chairman J. Lombardo C. Wylie, Member A. Masciantonio D. Ward, Member G. Bagchi G. Reed, Member B. Weidenhamer J. Ebersole, Member J. Vora H. Jones, Consultant F. Cherny R. Major, Staff G. Millman G. Hammer Others 0. Rothberg J. Page B. P. Brooks, EPRI R. Bosnak R. Raczynski, DOE E. Brown
- E. Oesterle, Bechtel R. Hernan R. Borsum, B&W B. Sheron L. Gifford, GE W. Knecht, Anchor / Darling Valve Co.
A. Charbonneau, Movats, Inc.
R. Lange, Wisconsin Public Service Corp.
G. Youngwirth, Wisconsin Public Service Corp.
H. Sonderegger, ITT Grinnell Mr. A. Masciantonio, NRC discussed environmental qualification of ASCO solenoid valves. He noted the purpose of environmental qualification is to provide assurance that equipment will be able to perform required functions under all postulated environmental conditions. Mr. Ebersole was concerned that the postulated rupture of instrument lines and the environment created by this rupture is not considered in enough detail.
8507110599 850429 PDR ACRS 2307 PDR'
RELIABILITY ASSURANCE (VALVES) 2 April 23, 1985 Meeting The Staff explained it is the owner's responsibility to define the environment in which equipment will be operated.
The Staff explained that there is margin built into most pieces of equipment. When a valve becomes qualified for nuclear service, it is done on the basis of a particular model.
Qualification testing is usually done by the manufacturers. It is done because of contractual requirements and for marketing leverage. Test parameters are chosen to envelop the worst conditions expected. Various test programs and the results of the programs were reviewed.
Currently the NRC position on ASCO Solenoid Valves is that valves with VITON seals are not suitable for applications in which valves are required to shift position after exposures greater than 20 MegaRADS.
Valves with EPDM Seals are not acceptable if oil contamination in the air system exists.
Brian Sheron discussed Generic Issue 70, PORV and Block Valve Reliability. The generic item is designed to answer the question "Are PORVs and Block Valves good enough or should additional steps be taken to improve tham?" This item has been assigned a medium priority.
Traditionally, the PORV and its block valves are provided for plant operational flexibility and to limit the number of challenges on pressurizer safety valves. For overpressure protection of the RCS, the operation of PORVs has not explicitly been considered as a sa'fety related function. The valve operators and their electrical control systems are normally designed to non-safety related standards. The Staff intends to use PRA to determine the maximum risk reduction benefit and maximum dollar amount that could be reasonably spent on PORV and block valve improvements. The Commission wants a briefing on whether PORVs need to be safety grade in July 1985. (G.I. 70 does not consider PORVs in beyond-the-design-basis context such as feed and bleed or ATWS.
RELIABILITY ASSURANCE (VALVES) 3 April 23, 1985 Meeting These topics are a part of USI A-45.) The Staff offered to present a more detailed presentation in the future.
Joel Page of NRC discussed ASME Section XI, Inservice Testing of Valves.
All operating commercial BWRs and PWRs are currently required to have a valve inservice testing program in accordance with a specific edition and addenda of the ASME Code,Section XI. Valve testing requirements are based on the valve's safety function. Various test requirements for the different categories of valves were reviewed. Acceptance criteria were discussed.
Mr. Roger Lange and Mr. Gary Youngwirth (Wisconsin Public Service) discussed their valve experience at the Kewaunee Nuclear Plant. They explained Kewaunee Nuclear Plant has valves from over 100 different manufacturers. There is a preventative maintenance program which schedules periodic testing, lubrication, inspection and repacking of many valves in the plant. During refueling outages, valves are inspected and repacked if it is determined that the amount of packing adjustment left would not be sufficient to last until the next outage.
During a typical outage, 200 valves will be repacked in addition to the valves repaired or replaced. It is felt that with the preventative maintenance and valve repacking program, valve problems have been kept to a minimum. The valve program's payoff is increased plant availability.
The largest problems with valves at Kewaunee are packing leaks, body to bonnet leaks, and leaking through the seat. Kewaunee is also facing problems in the area of obtaining spare parts or equipment replacements as manufacturers go out of business or get out of the nuclear business.
Mr. Reed commented on the MOVATS system for valve testing. If proven effective, it could, he believed, be used to reduce the amount of inservice testing of motor operators. The MOVATS system is not in use at Kewaunee plant.
RELIABILITY ASSURANCE (VALVES) 4 April 23, 1985 Meeting Boyd Brooks of EPRI discussed valve-related research and development conducted by the Electric Power Research Institute. He went through a list of relevant publications and discussed ongoing resaarch. He noted that EPRI is evaluating the M0 VATS device and expect; to publish an interim report in the next quarter. A final report is axpected by 1986.
Other key valve issues being addressed are: valve motor operator improvements and valve stem packing improvements.
Mr. W. Knecht of Anchor / Darling Valve Company discussed valve experience from a manufacturer's point of view. He noted his company has been making nuclear grade valves since 1956. Although valves are specified for nuclear service, he felt it is not a particularly severe type of service for the valves (as compared to super critical fossile or process applications). It was his experience that it was a much more severe test of a valve to close against break blowdown forces than to open against a static force. Mr. Knecht said that their experience is reported to customers directly, not to INP0 or to NRC. To get information to the NRC or INP0 the utility must act as the go-between.
Mr. H. Sonderegger, ITT-Grinell, discussed activities of the ASME Subcommittee on Qualification of Nuclear Valve Assemblies. The areas this group is working on include: "Self Operated and Power Operated Safety Related Valves Functional Specification Standard" and " Functional Qualification Requirements for Self Operated Check Valve Assemblies for Nuclear Power Plants." Other areas also under investigation are:
" Functional Qualification Requirements for Active Pressure Relief Valves for Nuclear Power Plants" and " Functional Qualification Requirements for Power Operated Active Valve Assemblies for Nuclear Power Plants."
The Subcommittee decided it wished to have another meeting. Items to be discussed include a risk perspective on valve performance and how well are PRAs really modeling valve performance. The Subcommittee will also look at valves in the context of overall plant safety and valves'
.o RELIABILITY ASSURANCE (VALVES) 5 April 23, 1985 Meeting contribution to plant safety. A presentation by Limitorque would also be desirable. Mr. Michelson will make an interim report on the Subcommittee's progress to the full Committee in June.
NOTE: A complete transcript of the meeting is on file at the NRC Public Document Room at 1717 H Street, N.W., Washington, DC or can be obtained at cost from Ace Federal Reporters, Inc., 444 North Capitol St., Washington, DC 20001, telephone (202) 347-3700.
l l
,.13436 hdcral Register / Vcl. 50, No. 65 / Thursd:y, April 4,1985 / Notic;s Datagram Identification Number 3737 Oral statements m:y be present:d by petitioner who fails to file Juch a members of the public with the j supplement which satisfies these and the following message addressed to
. irequirements with respect to at least one Domenic B. Vassallo: Petitioner's name concurrence of the Subcommittee and telephone number date petition Chairman; written statements will be contention will not be permitted to rticipate as a party. was mailed; plant name; and publication accepted and made available to the date and page number of this Federal Committee. Recordings will be permitted l' hose permitted to intervene become grties to the proceeding, subject to any Register nobce. A copy of the petition only during those portions of the limitations in the order granting leave to should also be sent to the Executive meeting when a transcript is being kept, and questions may be asked only by ;
intervene, and have the opportunity to legal Director, U.S. Nuclear Regulatory p rtiefpate fully in the conduct of the Commission. Washington, D.C. 20555. members of the Subcommittee,its :
and to Mr. Charles M. Pratt, Assistant consultants, and Staff. Persons desiring h:aring. including the opportunity to present evidence and cross-examine GeneralCounsel. Power Authority of the to make oral statements should notify wiinisses. Stsie of New York.10 Columbus Circle. the ACRS staff member named below as If a hearing is requested, the New York. New York 10019 attorney for far in advance as is practicable so that Ccmmission will make a final the licenses. appropriate arrangements can be made.
determination on the issue of no Nontimely filing of petitions forIcave During the initial portion of the ;
significant hazards consideration.%e to intervene, amended petitions, meeting, the Subcommittee, along with final determination will serve to decide supplemental petition and/or requests any of its consultants who may be ,
whrn the hearing is held. for bearing will not be entertained present, may exchange preliminary l If the final determination is that the absent a determination by the views regarding matters to be cmendment request involves no Commission, the presiding officer or the considered during the balance of the significant hazards consideration, the Atomic Safety and ucensing Board meeting. I Commission may issue the amendment designated to rule en the petition and/or The Subcommittee will then hear cnd make it effective, notwithstanding request, that the petitioner has made a presentations by and hold discussions the request for a hearing. Any hearing i substantial showing of good cause for with representatives of the NRC Staff, hild would take place after issuance of the granting of a late petition and/or its consultants, and other interested thz emendment. request.That determination will be persons regarding this review.
If the final determination is that the based upon a balance of the factors Further information regardmg topica cmendmen't involves a sigmficant specified in to CFR 2.714(a)(1)(i} {v) and to be discussed, whether the meeting hazards considersbon. any hearing held 2.714(d). has been cancelled or rescheduled. the would take place before the issuance of For further details with respect to this Chairman's ruling on requests for the cny amendment. acuon. see the app,lication for opportunity to present oral statements N:rmally, the Comm,ss, i ion will not amendment, dated March 21.1985, and the time allotted therefor can be issue the amendment until the which is available for public inspection obtained by a prepaid telephone call of Gxpirabon of the 30-day notice period. at the Commission's Public Document . the cognizant ACRS staff member.Mr.
Iowever, should circumstances change Room.1717 H Street. NW., Wa shington, Richard Major (telephone 202/634-1414) dng the nobce period such that failure D.C., and at the Penfield Ubrary. State between 8:15 a.m. and 500 p.m EST.
Cet in a timely way would result, for University CoPege of Oswego, Oswego. Persons planning to attend this meeting arample. in derating or shutdown of the New York. are urged to contact the above named
- "" 8 Dated at Bethesda, Maryland. this 29th day individual one of two days before the ce amen m t efore the . I M8"h 1985- scheduled meeting to be advised of any pa th da e For the Nuclear Regulatory Commission. changes in schedule, etc., which may
- fo p d tha rom Amunsana have occurred.
that the amendment involves no Acting Chief. Opemting Rector Emach No. 2, Dated: April 1.19s5.
significant hazards consideration. The final determination will consider all "# #N'#N##~ Morton W. Uharkin. .
public and State comments received. p Doc. 85-4052 Fded 4-3-85. E45 am] Assis tant Executive Directorfor Project Should the Commission take this action. g,yj,,,
- y cooc me-n as it will publish a notice ofissuance and .
p Doc 8o50 Filed 4-3-85, s 45 am]
provide for opportunity for hearing aftet Advisory Committee o'n Reactor an a o coot m oo w _
"'- "~ ~
issuance.The Comm,itsion expects that ~ Safeguards, Subcommittee on the need to take this schon will occur s very infrequently.
j Re!!ab!!!ty Assurance Meeting Veterans Administration Medical A request for a hearing or petition for '. De ACRS Subcommittee on Center; Order Modifying Ucense leave to intersene must be filed with the Secretary of the Commission. U.S., ] Reliability meeting on Aptll Assurance 23,1985. Room will hold 1046. a (Docket Noa. 30-0123,30-41314,70-2199, p 1717 H Street NW. Washington.DCJ Ucense Nos. 04-00942-04,06-00942-05, Nuclear Regulatory Commission.
SNie-1605, EA No. 85-31)
Washington. D.C. 20555. Attn: Docketing The entire me eting will be open to cod Service Branch, or may be delivered public attendance, g, .
13 the Commission's Public Document ne agenda for the subject meeting Room.1717 H Street. NW., Washington. ne Veterans Administration Medical D C., by the above date. Where petitions { shall be as follows:- Center, Washington. DC. (the cre filed during the last ten (to) daya of Tuesday. Ap U30 a.m. Until .. licensee"),is the bolder of specific the Condusw,ril 23.19 a of Bus 2 ness byproduct Material Ucense Nos. 06-the notice period. it is requested that the 00942-04 and 08-00942-05, and Special petitioner promptly to inform the i %e Subconunittee will continus Commission by a toll. free tefephone call discussions fmn the March 19 meeting Nuclear Material ueense No. SNM-1805 regarding metimds of enhance the issued by the Nuclear Regulatory t3 Wastern Union at (800) 325-6000 (in Commission (the "NRC") pursuant to to Missouri (800) 3154700). The Western reliability of atr. and motor-operated CFR Parts 30,33,35 and 70, which Union operator should be given . valves. . .
k T ftQ M 1El T
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.s TENTATIVE SCHEDULE I ACRS SUBCOMMITTEE ON RELIABILITY ASSURANCE (VALVES)
APRIL 23, 1985 WASHINGTON, DC
- 1. Chairman's Opening Remarks (15 min) 8:30 AM
- 2. NRC Staff Discussion of Experience (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 8:45 AM with Air Operated Valves Using Solenoid Valves to Control Actuator Air and Inservice Testing of Valves
- 3. Status of Generic Issue 70: PORV and (30 min) 9: 45 AM Block Valve Reliability (NRC Staff)
- 4. Utility Experience and Comments on Valve (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 10:15 AM 15 min.)
Performance - [ Roger Lang (Wisconsin Public Service - Kewaunee Plant)]
11:30 AM
Industry Efforts to Improve Valve (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 11:40 AM 5. 15 min.)
Reliability - Current Work at EPRI (Boyd Brooks, EPRI) 12:55 Noon
- LUNCH (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
- 6. Valve Experience: Manufacturer's Views: (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 2:00 PM Probleni Resolution, Experience Dissemination (W. Knecht, Ancher-Darling)
ASME Code Work - (Henry Sonderegger, (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 3:00 PM 7.
ITT Grinnell)
ASME Subcommittee on Valve Qualifications Standards Development Test Program on Valve Performance Future Activities (30 min) 4:00 PM 9.
4:30 PM ADJOURN fr /
ATTACHMENT C LIST OF MEETING SLIDES AND HAND 0UTS RELIABILITY ASSURANCE (VALVES)
APRIL 23, 1985 WASHINGTON, DC
- 1. Slides: Environmental Qualification of ASCO Solenoid Valves, A. Masciantonio, 13 slides.
- 2. Slides: GI 70 PORV & Block Valve Reliability, Brian Sheron, 2 slides.
{ 3. Generic Issue 70, "PORV and Block Valve Reliability" - Task Action
- Plan (TAC 55226), DRAFT
- 4. Slides: Inservice Testing of Valves, Joel Page, 7 slides.
- 5. Presentation Material from Roger Lange and Gary Youngwirth, Wisconsin Public Service, Kewaunee Plant.
- 6. Slides: Valve Related Research & Development Conducted by the Electric Power Research Institute, Boyd Brooks, 6 slides.
- 7. Slides: Activities of ASME Subcommittee on Qualification of Nuclear Valve Assemblies (SC-QV), H. R. Sonderegger, 13 slides.
- 8. Handout: Pseudo-Dynamic, Seismic Qualification Program, H. Sonderegger, 4 slides.
- 9. Handout, Paper: Pseudo-Dynamic Qualification of Seismic Category 1 Valve Assemblies, P. Avitabile and H. Sonderegger, ASME, 84-PVP-15.
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