|
---|
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
/ IggIFIg ann CERTIFIED: May 1. 1997 issued: April 28, 1997 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS MINUTES OF ACRS SUBCOMMITTEE MEETING ON MATERIALS AND METALLURGY APRIL 15-16, 1997 ROCKVILLE. MARYLAND The ACRS Materials and Metalluray Subcommittee held a meeting on April 15-16 1997, at 11545 Rockville Pike, flockville. Maryland, in Room T-2 B3. The purpose of the meeting was to hold discussions with representatives of the NRC staff and Consumers Energy cincerning generic letters associated with steam gercrator tube inspection techniques, effective use of ultrasonic testing techniques in inservice inspection programs, degradation of steam generator internals, and degradation of reactor vessel head penetrations: and the status of issues related to reactor pressure vessel integrity. The entire meeting '
was open to public attendance. Mr Noel Dudley was the cognizant ACRS staff engineer for this meeting. The meeting was convened at 1:00 p.m. on April 15 and adjourned at 2:40 p.m. on April 16. 1997.
ARENDIES:
625 W. Shack. Chairman R. Seale. Member T. Kress. Member NRC STAFF J. Strosnider. NRR M. Mayfield. RES E. Sullivan, Jr., NRR J. Muscara, RES R. Hermann. NRR C. Fairbanks. RES S. Coffin. NRR D. Jackson. RES P. Rush, NRR E. Hackett. RES L. Lois. NRR G. Carpenter NRR A. Lee. NRR j2.5 0/
INDUSTRY REPRESENTATIVES i
J. Hanson. Consumers Energy K. Cozens Nuclear Energy Institute R. Snuggerud. Consumers Energy S. Anderson. Westinghouse Electric Corporation There were no written comments or requests for time to make oral statements received from members of the public. A list of meeting attendees is available in the ACRS office files. Dr. Shack had a conflict of interest regarding steam generator tube inspections steam generator internals degradation, and inspection of reactor vessel head penetrations. He did not participate in the deliberations on these issues. p g 1 ? ?10 yc;g,--G,,wt- g ;
DUIcFATD OR!cINAL 9708130377 970811 AcRS U:od Dy_ [ -
3
. Minutes: .-April 15 16.-1997 2 Materials. & Metallurgy Subcomittee INTRODUCTION:
l Dr. William Shack. Materials and Metallurgy-Subcomittee Chairman, convened the meeting at 1:00 p.m. on April-15,-1997, explained the purpose of the meeting. and called on Mr. Jack Strosnider, Office of Nuclear Reactor Regulation (NRR), to provide opening comments for the staff. Mr. Strosnider explained the reorganization of the Materials and Chemical Engineering Branch, noted that several important topic would be presented by the staff, and comented on the good cooperation and coordination between the Offices of Nuclear Regulatory Research (RES) and NRR in the area of materials and metallurgy.
PROPOSED GENERIC LETTER REGARDING DEGRADATION OF STEAM GENERATOR INTERNALS -
Ms. Stephan1e Coffin. NRR
. Ms. Coffin stated that the purpose of the proposed generic letter concerning degradation of steam generator. internals was to-e communicate the types of damage found in foreign steam generators.
. . - emphasize the importance of examining steam generator internals, and e request information concerning the conditions of steam generator internals.
Ms. Coffin presented information on the damage found in foreign steam
. generators, the significance of possible events that could result from damaged internels, and the foreign response to the damage. She explained the results of domestic steam generator inspections, the regulatory requirements for conducting inspections, and the information requested by the proposed generic letter. Ms. Coffin summarized the public comments on the proposed generic letter and the staff responses. She concluded that after the generic letter is issued, the industry is expected to provide coordinated industry responses though the vendor owners groups, the Nuclear Energy Institute, or the Electric Power Research Institute. The Subcommittee members and the staff discussed the types of damage identified, the root cause of the degradation, and what the staff will do with the industry responses to the proposed generic letter.
ULTRASONIC INSPECTION RELIABILITY AND PERFORMANCE DEMONSTRATION -
Dr.. Joseph Muscara. RES Dr..Muscara presented the research program associated with the evaluation and improvement of nondestructive examination (NDE) reliability for inservice inspections at nuclear power plants. The objective of the program, which
- began in 1977, was to determine the reliability of ultrasonic inspections, recomend code changes, and formulate improved inservice inspection criteria.
- The results of the research program indicated that the ASME code prescriptive ultrasonic testing procedures were not providing adequate flow detection-reliability. Consequently, during the 1980s the staff, its contractors, and industry developed ASME code.Section XI. Appendices VII and-VIII, which require teams to demonstrate acceptabl.e flaw detection capabilities before-
-, ~. . . - - , -- , - - - - - , ,
t :
, Minutesi April 15-16, 1997 3 Materials'& Metallurgy Subcommittee
' performing field inspections. Dr. Muscara explained the Appendix VIII performance demonstration requirements for detection tests and crack. sizing .
tests, and the acceptance criteria.for wrought austenitic stainless steel piping. Dr. Muscara's summary and conclusions included the following points.
- Even as improvements have been made to techniaues and procedures, there is a large variability in the 3erformance of NDE systems for similar procedures and equipment used )y different inspectors.
- There is a need to qualify NDE systems, through 3erformance demonstrations, to screen poor performers from tie qualified pool of NDE systems that are used for inservice inspections. ,
- The acceptability-of missing deep flaws in a passing detection test should be addressed.
- The inclusion of a criterion to the sizing qualification test for the maximum acceptable undersizing of deep flaws, in addition to the root-mean square error requirement, should be considered.
The Subcommittee members and the staff discussed the following items:
e code requirements for ultrasonic testing examination of piping, e development of software to improve inspections.
- differences between foreign and domestic-inspection techniques, e techniques used during round robin tests, and
- European performance demonstrations.
PROPOSED GENERIC LETTER REGARDING ULTRASONIC TESTING IN INSERVICE INSPECTION PROGRAMS - Mr. Robert Hermann, NRR Mr. Rouert Hermann, NRR, presented background information related to the technical and regulatory issues associated with the ultrasonic testing of pipes feedwater nozzles, and reactor vessels. He explained the performance demonstration methods required by ASME code,Section XI. Appendix VIII. Mr.
Hermann provided justification for issuing a generic letter requesting information on how licensees were using Ap)endix VIII in their inservice ins)ection programs. The Subcommittee mem)ers and the staff discussed the lacc of-a statistical basis for the performance demonstration acceptance criteria and the different contributors to the performance demonstration paso-fail rates.
PROPOSED GENERIC LETTER REGARDING STEAM GENERATOR TUBE INSPECTION TECHNIOUES -
Mr. Phillip Resh, NRR Mr. Rush explained that eddy current methods are the 3rimary NDE technique for identifying steam generator tube defects. He noted tlat the technique has large uncertainties and in most cases is not qualified to size defects. Mr.
Rush presented the regulatory requirements for controlling special inspection processes and for repairing identified defects. He provided examples of how
- i. ;;
~
. Minutes:.-A 15 16, 1997 .4 Materials &pril Metallurgy Subcommittee
- - some licensees have used ' questionable inspection practices and noted the lack-
. of information available to the staff concerning the industry steam generator
- tube inspection programs.
Mr. Rush stated that the purpose of the proposed generic letter concerning
- steam generator. tube inspection techniques was to:
e notify licensees of the importance of using qualified inspection
-techniques, e request information on sizing techniques and the basis for those.
techniques -and e verify compliance with 10 CFR 50 Appendices A and B, and the technical specifications.
Mr. Rush summarized the public comments on the proposed generic-letter and the staff responses. He stated that the generic letter would be issued in May 1997. -
The Subcommittee members and the staff discussed the following items:
e how the staff will use the industry responses -to the proposed generic letter, e characterizing and sizing of defects, e the importance of staff and industry interaction in developing risk-informed and performance based regulatory criteria, e the differences between degradation mechanisms found in the different i . steam generator designs, and e the use of pulled tube data to develop statistical bases for alternate repair criteria.
MOM) SED GENERIC LETTER REGARDING DEGRADATION OF REACTOR VESSELCLOSURE HEAD -
)ENETRATIONS - Mr. C. E. Carpenter. Jr., NRR' 2 .
Mr. Carpenter presented background information on cracks identified in foreign reactor vessel control rod drive mechanism and other vessel closure head penetrations, and on domestic industry inspection-experience. He noted that the nuclear steam supply system vendors have developed susceptibility models
- for reactor vessel penetrations, but have not submitted the models or the results of analyses to the staff. ' Mr.- Carpenter stated that the purpose of the proposed generic letter was to:
e- verify licensee compliance with regulatory requirements, e determine if an augmented inspection program should be imposed, and
.-- ' request information concerning the potential for resin intrusion events.
- - y -- *v -r' *W M4- g w'v- F4--*y --e- - -
-r---v-m-evu-- M- W W+- --- *-- - -
wwvh--m%c-- N---w% e--ar-ed %- s y P-
i
- , Minutes
- A - 15 16. 1997- 5 :
Materials &prilMetallurgy Subcommittee '
-Mr. Carpenter summarized the public comments on the proposed ' generic-letter and-the staff responses. He concluded that' vessel head penetration cracking
, is not an immediate safety concern and that an integrated, long-term licensee program.- including periodic inspectione and monitoring, is necessary.
The Subcommittee members and the staff discussed the following items:
i e other possible vessel inspection techniques besides eddy-current inspections,-
- . metallurgical structure of the identified cracks.
[
- the availability of the results of the susceptibility studies performed by owners groups, and
- whether all reactor vessel head penetrations should be inspected.
PALISADES: PRESSURE VESSEL FLUENCE REEVALUATION - Mr. Lambros Lois, NRR Mr. Lois presented background information on and the staff position regarding a revised reactor vessel fluence analysis submitted-by Consumers Energy for the Palisades reactor vessel. The Palisades reactor vessel is calculated to exceed the pressurized thermal shock screening limits prior to the expiration of its license. The licensee revised its fluence analysis based on a reevaluation of four existing surveillance capsules, recalculation of early cycle neutron sources, new geometric and temperature data, cavity dos'.,etry data, and a new statistical analysis method. The submittal requestec 25
)ercent reduction of the fluence accepted in the 1993 staff review of the
)alisades pressure vessel fluence analysis.
. The staff prepared a safety evaluation report (SER) on the licensee submittal.
The staff accepted an 8 percent reduction due to the revised physical measurements of the plant. The staff, however, concluded that the licensee's i requested 17
> unacceptable. percentage reduction baser.' on a reevaluated bias wasThe bias, wh fluence. is derived from calculations, dosimetry data, and spectral-adjustments. The staff evaluation was based on the following concerns:
4
- no physical explanation for the requested deviations has been provided.
a plant-specific data are inconsistent. and
- - spectral least square-fitting does not represent a best-estimate value.
The current fluence value allows plant operation till 1999. The 8 percent reduction will allow plant operation through 2003. The Subcommittee members and the staff discussed the location-of vessel capsules and the uncertainties associated with the measurement-to-calculation ratio of fluence bias.
f i
,-u, , , - , ------,-,,,r ,.. y
1
. ' Minutes: A 6 >
Materials &pril-15 16, Subcommittee Metallurgy 1997
)RFT RIGJLATORY GUIDE DG 1053."CA.CULATIONAL AND DOSIMETRY METHODS FOR i
)ETERMI114G PRESSURE VESSEL NEUTR04 FLUENCf" .- Ms. Carolyn Fairbanks, NRR ,
Ms. Fairbanks explained that the purpose of the draft regulatory guide was to
_ provide an acceptable state-of the-art method for fluence determination and to standardize met 1odologies for determining vessel fluence. She presented the regulatory requirements for which the regulatory guide was developed, and summarized the schedule for issuance of the regulatory guide. Ms, Fairbanks noted that the present draft 'of the regulatory guide includes the application of Monte Carlo transport to pressure vessel fluence benchmark aroblems, The Subcomittee members and the staff discussed the relationship 3etween surveillance capsule data and reactor vessel fluence.
EALISADES REACTOR VESSEL INTEGRITY STATUS - Mr. Jack Hanson, Consumers Energy Mr. Hanson provided background on the licensee submittal regarding reactor vessel fluence. He presented the options available to Consumers Energy including vessel annealing, materials testing, regulatory guide 1.154 analysis, and early plant shutdown. He identified the location and number of in-vessel and ex vessel capsules used to generate the fluence data. He noted that Monte Carlo calculations were performed to provide an independent evaluation of vessel fluence.
Mr. Hanson explained the use of the least squares adjustment procedure for calculating a best estimate value for the measurement-to calculation ratio of fluence bias. He compared the individual ca)sule biases for Palisades and the best-estimate bias for Palisades to average aiases for other plants. Mr.
Hanson concluded that a default conservative value, rather than a best-estimate value, places an undue burden on Consumers Energy.
The Subcommittee members, representatives of- Consumers Energy, and the staff discussed the following items:
- types of material used in the dosimetry capsules.
- use of other basis besides fluence to extend plant operations. ,
- reasons for the 17 percent change in the calculated value for fluence.
- how plant-specific data can be taken into account without averaging.
- how damage to the reactor vessel is derived based on fluence, and
- whether the best-estimate value represents the true fluence.
NUREG 1411. SUPPLEMENT 1. " REACTOR PRESSURE VESSEL STATUS REPORT" -
Ms. Andrea Lee, NRR Ms. Lee explained that NUREG-1511. Supplement 1. " Reactor Pressure Vessel
-Status Report." incorporated information gathered from licensee responses to Generic letter (GL).92-01. Revision 1. Supplement 1, " Reactor Vessel
. Structural Integrity." and updated the NRC reactor vessel integrity database i (RVID). She noted that Babcock & Wilcox and Combustion Engineering have not yet responded to Supplement 1 of the generic letter-. ,
. -j i
4 .
. .~ _
.-- - Minutes:: Ai'il IS 16.' 1997 7 :
- MaterialsT Metallurgy Subcomittee- ,
- Ms. Lee presented the reasons for issuing the generic letter sup)lement.- '
sumarized the staff generic assessment of pressurized thermal slock based on the new data, and explained the features of the-RVID. She stated that some
- planned staff activities included reviewing new best-estimate chemistry data, t resolving discrepancies between the RVID and the industry database. and
! eventual approval of- a database maintained by the industry with oversight from
_the staff.
- Ms. Lee demonstrated the features of the RVID. She stated that the RVID would be made available to the industry and the public. Mr. Strosnider highlight d i the magnitude of the industry and staff effort expended in developing the RVID.
DOE REACTOR VESSEL ANNEALING PROJECT UPDATE - Ms. Deborah Jackson. RES
- - Ms. Jackson presented the objectives and present status of the Department of Energy annealing demonstration project involving the Marble Hill and Midland reactor vessels. She showed and provided commentary on a video tape, which
- included selected activities associated with the Marble Hill reactor vessel
' - annealing demonstration. Ms.-Jackson stated that the demonstration of annealing the Marble Hill vessel with an indirect gas fired heating method was successful. She explained that the annealing of the Midland vessel had been delayed. The Subcommittee members, the staff, and Mr. Hanson, who had observed "
n 4 the vessel annealing demonstration, discussed the associated stress analyses.
code cases, and procedures.
SUBCOMMITTEE COMMENTS Dr, Kress stated that the details contained in the presentations were at the appropriate' level. Dr. Seale expressed a desire to work in parallel with the staff in developing technical- and policy issues instead of waiting until the issues became intractable. Dr. Kress questioned whether the Comittee should review and.coment on the staff position related to the reevaluation of reactor vessel fluence. Dr. Seale mentioned that vessel fluence is an 7
interesting case since there are elements of risk in the regulatory decision. !
FOLLOWUP ACTIONS 1
These presentations were provided as information briefings. No followup actions were identified, i
SUBCOMMITTEE RECOMMENDATIONS 2 The'Subcomittee' decided that imediate Committee followup activities were unwarranted.
=
,e y -,,m ,.y. y, , ,
ew+-se-e., y. - rg wy--- %
1-w.,g , -.r.-w- , 9_, _, __
q.,,_.9
. Minutes: A 15 16. 1997 8 Materials &pril-Metallurgy Subcommittee BACKGROUND MATERIAL PROVIDED TO THE SUBCOMMITTEE:
- 1. Memorandum dated December 23, 1996, from Thomas Martin NRR. to David-Meyer. 0A.-
Subject:
Notice of Opportunity for Public Comment-for a Proposed Generic Communication Regarding Effectiveness of Ultrasonic testing Systems-in Inservice Inspection Programs.
- 2. CRGR presentation slides. "UT Reliability / Performance Demonstration."
dated November 19. 1996, t 3. Memorandum dated December 23. 1996, from Thomas Martin. NRR. to David Meyer,0A.
Subject:
Notice of Opportunity for Public Comment for a Proposed Generic Communication ~Regarding Degradation of Steam Generator Internal.
- 4. CRGR presentation slides, " Degradation of Steam Generator Internals."
dated November 19, 1996.
- 5. Memorandum dated December 23. 1996, from Thomas Martin, NRR. to David Meyer,OA.
Subject:
Notice of Opportunity for Public Comment for a Proposed Generic Communication Regarding Steam Generator Tube Ins)ection Techniques.
- 6. CRGR presentation slides. " Steam Generator Tube Inspection Techniques."
dated November 19, 1996.
7 SECY-97 063, " Proposed NRC Generic letter 97 ##, ' Degradation of Control Rod Drive Mechanism and Other Vessel Closure Head Penetrations'." dated February 20, 1997.
- 8. Memorandum undated. Lambros Lois, NRR. to Robert Schaff, NRR
Subject:
Safety Evaluation Report on Palisades: Pressure Vessel Fluence Reevaluation
- 9. U. 5. Nuclear Regulatory Commission NUREG-1511, Supplement 1,
" Reactor Pressure Vessel Status Report. October 1996 NOTE: Additional details of this meeting can be obtained from a transcript of this meeting available in the NRC Public Document Room. 2120 L Street.
N.W., Washington, D.C. 20006. (202) 634-3274. or can be purchased from Neal R. Gross and Company Incorporated, Court Reporters and Transcribers. 1323 Rhode Island Avenue, N.W., Washington, D.C. 20005.
(202) 234-4433.
i w-. - - . a -- --