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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 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 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, 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 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 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 ML20206S2481998-11-12012 November 1998 Summary of 455th ACRS Meeting on 980902-04 in Rockville,Md Re Items Listed in Attached Agenda 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 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 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
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CERTIFIED COPY DATE ISSUED:12/10/85 MINUTES OF THE MEETING 0F THE ACRS SUBCOMMITTEE ON METAL COMP 0NENTS SEPTEMBER 4-5, 1985 WASHINGTON, D. C.
The ACRS Subcommittee on Metal Components met in Washington, D. C. on September 4-5, 1985.
The meeting dealt primarily with pressure boundary integrity, among other things it covered:
Proposed Rev. 2 to Reg. Guide 1.99 " Radiation Damage to t
Reactor Vessel Materials" Steam generators shell transition joint weld cracking Irradiation Assisted Stress Corrosion Cracking (IASCC)
Materials Research Program (NDE, RPV integrity and piping degradation)
Notice of the meeting was published in the Federal Register on August 19, 1985.
(AttachmentA) The schedule of items covered in the meeting is in Attachment B.
A list of handouts kept with the office copy of the minutes is included in Attachment C.
The meeting was entirely open to
~
the public. There were no written or oral statements received or presented from members of t h public at the meeting.
E. Igne was the cognizant ACRS Staff member for the meeting.
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' MIN. METAL COMP 0NE"TS 2
Sept. 4-5, 1985 Mtg.
Principal Attendees ACR5 NRC G. Shewmon, Chairman C Serpan W. Hazelton D. Ward, Member M. Vagins N. Randall R. Odette, Consultant A. Taboada R. Dillon, Consultant M..Mayfield B. Thompson, Consultant J. Mucara W. Johnston Other B. D. Liaw L. Willertz, PA. Power &
D. E. Smith Light Co.
Johnston, Liaw and Hazelton, NRR, briefed the subcommittee on steam generator shell transition joint-weld cracking.
In 1982 Indian Point, Unit 3, found leaks in the transition joint-weld examination and showed that the leaks resulted from extensive cracking in this joint. The problem stemed from a poorly understood interaction of corrosion and fatigue.
I&E sent out an information bulletin suggesting that other utilities with PWR's shell transition joint-weld should look for cracks in such joints at their next major' outage. Surry, Unit 2, among others did such an inspection and found that they had similar cracks. These cracks were subsequently ground out and repaired during a subsequent outage. The Materials Engineering Branch of NRR have suggested that each licensee of a Westinghouse or CE PWR steam generator with similar shell transition joint-weld be required to do an inspection and report back on what they find. A counter proposal by the Division of Licens-ing, NRR, is that since,1) any such cracks would probably leak before the upper shell portion of the steam generator fails catastrophically,
- 2) even a major rupture is within the design basis accident (main steam line break) and 3) a PRA study indicates that the increase in the probability of core melt is insignificant for this scenario, such an order is unnecessary. Mr. Denton's office will decide.
n,
MIN. METAL COMPONENTS 3
Sept. 4-5, 1985 Mtg.
L. Willertz, Penn. Power & Light presented a careful detailed report on the current knowledge on IASCC. The cracking appears in stainless steel 2
exposed to over 1E20 nyt/cm. Components that reach this exposure are top guides, orf tubes and maybe control blades and shroud. They have reviewed the fracture of each of these components, but cannot find how pieces of any of them would cause a safety problem. General Electric's current belief is that hydrogen water treatment will push the threshold for the appearance of IASCC to significantly higher fluence.
N. Randall, RES, discussed the proposed Rev. 2 to Regulatory Guide 1.99
" Radiation Damage to Reactor Vessel Materials." The main concern about reactor vessel integrity centers around the possible brittle behavior of the vessel at low temperatures.
Reg. Guide 1.99 defines a conservative bound for the shift in Reference Nil Ductility Temperature (defined as the mean plus 2 sigma) to be expected from exposure to fast neutrons.
This is used to define the maximum pressure to which a vessel can be pressurized on heatup and in set'.ing limits for the PTS rule.
Revision 2 incorporates the results of a good deal of research..The main changes of Rev. 2 are as follows:
It has now beeN found that' nickel has a substantial effect on the NDT, and this effect is reflected in the revised guide.
(Nickel content is added as variable and phosphorus removed).
There is a considerable range of nickel contents in the field, especially because the welds in most of the newer vessels have high nickel (up to 1%) which was added to improve strength and initial toughness, t
MIN. METAL COMPONENTS 4
Sept. 4-5, 1985 Mtg.
At high fluence the rate of shift of NDT with fluence de-creases relative to Rev. 2.
This helps some of the older high Cu, low Ni vessels.
A different curve is defined for welds which has a somewhat higher rate of rise in NDT with fluence than that of.the base metal.
Guidance is given for calculating attenuation of damage through the vessel wall.
The proposed Rev. 2 of Reg. Guide 1.99 has been carefully considered and is a significant change from Rev. 1.
The subcommittee recommends that it be allowed to go out for public comments.
J. Muscara, RES, briefed the subcommittee on the status of the NDE program. The acoustic emission / flaw relationship program is presently winding down to a 1987 completion. This system has been installed at Watts Bar for on-line acoustic emission (AE) monitoring of the primary pressure boundary.
It is the intent at the conclusion of this program to establish an approved ASTM standard and gain ASME Code acceptance.
Field tests during startup and early operation at Watts Bar are planned.
SAFT-UT laboratory studies are being performed for system optimization.
Field validation tests have been preliminarily run with satisfactory results. Cooperative effort with industrial organizations for technolo-gy transfer is in progress. Code case acceptance efforts have been initiated.
l l
s MIN. METAL. COMPONENTS 5
Sept. 4-5, 1985 Mtg.
Inspection of weld overlays is still a problem in that detection and sizing of IGSCC less than 50% of the original wall thickness is unreli-able, although if the overlay surface is machined, improved detection is possible. Tandem wave probes can determine the remaining ligament associated with deep IGSCC cracks with some degree of accuracy.
It was stated that qualification of sufficient numbers of ultrasonic inservice inspection personnel remains a serious problem. More work in this area is necessary.
Mr. Vagins, RES, provided highlights of the pressure vessel integrity program. The program continues to evaluate the effects of flaws,.
variations in material properties (including environmental effet.ts) stress risers and residual stress on the integrity of reactor pressure vessels under normal and upset conditions. The program results are being utilized to improve ASME codes, ASTM standards, regulatory guides, Federal regulations, and the supports of the NRC staff in its licensing and safety evaluation process.
It was pointed out that integrity of the secondary systems is not being addressed by this program because of lack of resources. The following are some significant items that have been confirmed by experiments performed under this program:
The effectiveness of warm prestressing which significantly increases the pressure vessel toughness under PTS environ-ments.
The applicability of linear elastic fracture mechanics in predicting the behavior of the pressure vessel under combined pressure and thermal shock environment.
l
MIN. METAL COMPONENTS 6
Sept. 4-5, 1985 Mtg.
Demonstrated that ASME Section III and Section XI flaw eval-uations are conservative.
In reply to H. Etherington's concern, M. Vagins stated that it is a legitimate concern, the NRC Staff is aware of. it and it does not affect normal plant operation.
It may affect some of the conservatism we have built into the PTS screening criteria for low upper shelf materials and that this matter would be determined fron tests.
M. Mayfield, RES, presented a brief di.scusrion on the piping degradation program. This program covers piping fracture, IWB-3640 and leak-before-break. This program through analyses and experiments will determine the toughness of piping systems and validate the leak-before-break concept. This program has been in effect for about a year and much work still needs to be performed.
The subcommittee at the conclusion of the meeting decided to present the matter of the proposed Rev. 2 to Reg. Guide 1.99 to the full ACRS at the 305th Meeting, and reconsnended that it be released for public comment.
NOTE:
A complete transcript of the meeting is on file at the NRC Public Document Room at 1717 H Street, NW., Washington, D. C.
or can be obtained at cost from Ann Riley & Associates, Court Reporters, 1625 I St., NW., Suite 921, Washington, D. C. 20006 (202)293-3950.
w.use r -
Federal Regist:r / Vol. 50. No. Ese f. Friday. Angest 16.1985 fMytises 'MM, c
,Y L8CrussE's Conasmeets on SupeLamptr,1... _ ; - --. ;-- n-- -,, _ _ - - -
W y
M*b k
Ors!alaangmenig4y
. Accordingly. pursuant toSections103,'
1611,161o. and 182 of the Atomic Energy 1me enomen e.i ohd d b, _ _ __,m -
I" w
- 7ui Act of1964, as amended, and the Commission's regulations in to CFR g- -
uma=+
, k-2.204 and to CHL Part 50. It is hereby '
'MN N
Y J*** D=r "' " ear'*ia es=
- 4 "ss*'"81... 'er'n'a*s*cr"ipt is be*"I O* *** "E C'd' red. effective lmmedi8tel ' that kept,and guesI6sies,
facility operating b. cense No. DPR-34 is g,
em mc.
.may b W WWdb -
modified to prtivide~thnt the bcensee m,
e,,,,,,,
gg,,,g gg,, g,,,,,,,,m,,,,,,ge,g, shall: Implement the specific items described in the Attachment to this
,', j ;y wi, somsM., has hiring h meh wel eseen--'a ~
order in the manner described in PSC's
%e,
',,,, j..etatements should motifythe ACRSstaff p
,,,,,%,,,, g,, g,,p,, f,,,,.
I late a t at s t e Atta nt. - a n.,[s,er, sa sa' hr w
Extensions of time for completing 8_",.'.8'-
.gQ' During blaidalporHonof the *. 5 -
these items may be granted by the.
a--, 9
" muting. die Submummittee.1mlung with
~
Director. Division of Licensing. NRR. for g
j,8 q i- ' A eny of ks consultants arbo meybe good cause shown.
- muus ors 7 present, may==4ione prelhainary :-
V U*n.*""
u w wiews regarding matame to be '- -
i considered during the balamos of the a essa -e a e animos The licensee or any other person with
. =ma== a'
..c.
, -meeting.
n -
cn adversely affected interest may ne
.a.n, ittee wSI then hear
s request a hearing on this Order within a use==
, as. _
= omm ni, presentatiansby and held disamseloos -
20 days of the date of publication of this W W~
' * ".. -with sepresentatives of the NRC StaE, -
Order in the Federal Reghter. Any P===en.
emme.e. e se its consultants, and other interested ~
request for a hearing should be
'ON
persons regardmg this review.
r ~
i addressed to the Regional
. 4.,
,. e.,
Furtherinformaton regarding @
,. sce.
Ar!ministre tor. Reg!on IV. U.S. Nuclear
& E"=e-=r
,,,,,,,[ 85,g =
to be <tiar- --' wkther b has been rmar=11ed ouesdne.%
Regula tory Commisslon. 611 Ryan Plar.a e
, ix.
luled,the Drive. Suite 2000. Arlington Texas
.' a on==m-d z
76011. A copy should also be sent to the skQ ".
Chairman's ruling on sequests for the opportunity to wel statensets Executive legal Director. U.S. Nuclear j j, 4 'se en s e,
' er. omisen, a*
Q 8,,85 ** **,and the Mmeobtained by a prepaid tele otto therefor sua be Regulatory Commission. Washington.
(,
DC 20555. A request for hearing shall the cognizant ACRS staff member Mr.
not stay the immediate effectiveness of
'g,q 8'=,g,',".'
. m.,e.s ei Elpidio Igne (telephone E2/834/1414)
{I 3
this order.
e=r mar.ww er.o a u isex me an -se a' between 8:15 a.m. and &$0 pm Persons If a hearing is to be held, the
""*"""'"'**'""""'",""*"'r'" ' '
~
planning to attend this meeting ase 3 ;
Commission willissue an Order
[m Doc. as.tes:2 %d s.ts.as; ass am).
arged to contact the above====<4 designating the time and place of any
', kufividual one of two days before tne emiamo cons vis m.m
? i such hearing.
/
scheduled meeting to be advised of any -
If a bearing is held concerning this t
Order, the issue to be considered at the / visory Committee on Reactor' changes in schedule.e'c,which many Ad hearing shaU be whether the licensee safeguards Subcommittee on Metal ~ have occuned..~
o should comply with the requirements set Componenta; Meeting Datd August 13 sess. ~#*MT L'.~...
,,,,,,,,,,3,u, g.L.
f, forth in Section IV of this Order.
De ACRS Subcommitteeb Metal Assisfarit Ersarcim gkruceerJhr Aufset i
his Order is effective upon issuance.
Components wiU hold a meeting on -.. Aeriew.
Dated at bethesda. Maryland this 2nd day September 4 and 5.1965. Room 1046
{FR Doc.as.1eam Fund HHe; eses am),
l Ef August.1985.
1717 H Street NW., Washington. DC.
- antaus cosa noses * "'* ' e" For the Nuclear Regulatory Commission.
To the extent practical the meeting Hush I.W le, will be open to public attendance. s -
However, portions of the meeting may.
Advloory Committee en Reactor T-I Director. Division ofLicensing Office of e
NuclearReactorRegulation, be closed to discuss GeneralElectnc '
safeguertes Sutnoommfttee en Remotor prcpr'stary information.
Operatione; bleeting s*!
IJctisset's Couurrutwrs oss Suppt.eutxt t 9,'g[,
%e ACRS Soboommittee on Raeetoe I
Wednesday. September 4.1965-8:30 Operations will hold a meeting en to NtJREG-0737 am am until the conclusion of businesa September 9.1965. Room 1046.1717 H.
l to.
ae
,",",,,'*y,
% ursd. September 5.1965-8.30 a.m.
Street NW, Washington.DC. *.: *-"--
-==.*
an the concluston of businesa
%e andre andag wClb hi public attendance.
ne Subcommittee willreview t meer.=
sa mim.
%e agenda foe b subject messing i,a c iii Reguls tory Guide 1.s9. Revision 2. and shaU be as foUows-
~ -
e me.,
i se.
cni, s, e
other related concerns and discuss the
'1
- ,.. isEc.
status of the NITT of piping program and Monday. September A 2sas-2.10ti m.
A n sees an,
- m n.er,.
the HSSTprogram. He Subcommittee
<. apr@e,cadus/mpfW ~.
.W W **
wiU also review steam generetoe girth -
%e Subcommittee will discuss secen weld creda....,.
1 e-.c
/. opereting occurrences...
~.
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g;.
y k
_.,__,___,,,___.,.,______,.m..#.,,w...
._._e..__,_
ATTACHMENT B A-TENTATIVE SCHEDULE REVISION 2 ACRS METAL COMPONENTS SUBCOMMITTEE MEETING SEPTEMBER 4-5, 1985 WASHINGTON, D. C.
September 4,-1985 I.' Clairman's Opening Statement and Coments P. Shewmon (15 min) 8:30-8:45 II. Steam Generator
- Shell girth weld cracks Surry
- Indian Point
- Others Safety Issues Causes, fixes, and generic implications Liaw (120 min)8:45-11:00
[with15-min.breakatabout10:00]
III. Irradiation Assisted Stress Corrosion Cracking (IASCC)
- Discussion of Internal Report on 1
i IASCC, summer 1984, by L. E. Willertz, Pa. Power & Light Co.
(Susquehanna)
(90 min)11:00-12:30
+++
LUNCH
+++
(60 min)12:30-1:30 IV. Irradiation Effects on Pressure Vessel Materials; Regulatory Guide 1.99, Rev. 2**
- Technical Basis, including differences with respect to Pressurized Thermal Shock RT I
N. Randall NDT (60 min) 1:30-2:30
- Implementation N. Randall (30 min) 2:30-3:00 V. Materials Research Programs A. Introduction and Foreign Interactions C. Serpan (30 min) 3:00-3:30 i
i
+++
BREAK
+++
(15 min) 3:30-3:45 l
[
B. NDE Acoustic Emission i
i SAFT-UT l
Eddy current, stm gen.
f Round~ robin Qualification J. Muscara (60 min) 3:45-4:45
~
i VI. Subcomittee Discussions and (15 min) 4:45-5':00 Recess 5:00 ATTACHMENT I l
N-
f.
2 September 5 1985 VII. ~~ Chairman's Remarks P. G. Shewmon (15 min) 8:30-8:45 VIII. Materials Research Program (Con't.)
C. HSST PTS results PTS future plans Wide plate crack arrest and crack growth rate I
Effects of cladding K
verification yc Irradiated crack arrest H. Etherington concerns on low upper shelf energy M. Vagins (120 min)8:45-11:00
[with15-min,breakabout10:00]
D. Piping Degradation Fracture IWB 3640 Leak Before Break Mike Mayfield (60 min) 11:00-12:00 a
IX. Subcommittee Discussions and (30 min) 12:00-12:30 Adjournment 12:30 e
4 e
ATTACHMENT C
.. ~
HAND 0UTS FOR METAL COMPONENTS SUBCOMMITTEE MEETING SEPTEMBER 4-5, 1985 1.
Steam Generator Shell Cracking - W. Hazelton 2.
Memo to J. P. Knight from H. L. Thompson, NRR
Subject:
Steam Generator Shell Transition Joint Cracking 2.a Regulatory Responses 3.
IASCC, PA Power & Light Co. - L. Willertz 4.
Draft Regulatory Guide 1.99, Revision 2 Radiation Damage to Reactor Vessel Materials 5.
Review of Materials Engineering Branch Budget and Research Program
- Foreign Interactions 6.
Overview of NRC Research Programs in NDE - Joseph Muscara 7.
A Review of Program Elements of the MEBR Pressure Vessel Research Program by Milton Vagins 8.
Piping Degradation by M. E. Mayfield l
' ~ ~. ~
+ ;_
E. IGNE ATTACHMENT D 9.
ACRS SUBCOMMITTEE MEETING ON METAL COMPONENTS LOCATION 1717 H St. NW., Washington, D.C. Room 1846 DATE SEPTEMBER 4-5, 1985 ATTENDANCE LIST PLEASE PRINT:NAME AFFILI ATIf1N P. % um< m Acts A R. ijJosul R.Od_tb A a s.
tow _3 reb S.
%ttnscu o
I b
N P_.53 Mk c-ua i
iv I
T 4
l t
1 1Hz
N ACRS SUBCOMMITTEE MEETING ON _ METAL COMPONENTS __
1)i7HSt.NW.,Washinoton.D.C..Dnnm ig46 L.OCATIOl: _
SEPTEMBER 4-5, 1985 MTE.
ATTENDANCE LIST PLEASE PRINT:
NAME BADGE NO.
AFFILIATION
_~
d 'O fC W US7N 'fh'dOSF f)). /). M A t f /'
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M ACRS SUBCOMMITTEE MEETING ON METAL COMPONENTS LOCATION 1717 H St. NW., Washington, D.C. Room.1846 DATE SEPTEMBER 4-5, 1985 ATTENDANCE LIST
~
PLEASE PRINT:
Charks 2 See p.* Jk A/R c / A N /v s B A.
0scro H YAGI H S AdC,lSd8lM6bK A
TA%oADA MA.c./n.rr/M6.44 G SM,t/
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E. IGNE ACRS SUBCOMMITTEE MEETING ON METAL COMPONENTS
(,,
LOCATION 1717 H St. NW., Washington, D.C. Room 1446 DATE SEPTEMBER 4-5, 1985 ATTENDANCE LIST PLEASE PRINT:NAME AFFILI ATION
%l, V' JOHNST0N NRC I HR R /o E-Ro linw Nat INait i os IHists
'Th 4 E Kn1%
Mc/MR/DE/istreB
/
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