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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 "". |
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CERTIFIED COPY M I i3 .3 DATE ISSUED: March IS, 1986 SUMPARY/ MINUTES ACRS SUBCOMMITTEE MEETING ON STANDARD PLANT DESIGN JANUARY 6, 1986 WASHINGTON, D. C.
l l
A meeting was held by the ACRS Standard Plant Design Subcommittee.
Notice of the meeting was published in the Federal Register on December 1 17, 1985 (Attachment A). The schedule of items covered in the meeting is in Attachment B. The list of attendees is in Attachment C. A list l
of the meeting handouts is in Attachment D. The handouts are filed with l 1
the office copy. H. Alderman was the designated ACRS Staff member. The ;
meeting was convened at 1:30 p. m.
I 1
Principal Attendees 1 ACRS NRC Staff C. Wylie, Subcommittee Chairman F. Miraglia, NRR C. P. Siess H. Berkow, NRR G. Reed C. Thomas, NRR i
C. Michelson D. Scaletti, NRR
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.- D SIGNAID ORIGINAL 8605290695 860315 PDR ACRS /
p Cert h b l
- e MINUTES /
SUMMARY
/ STANDARD , 2 PLANT DESIGN - Jan. 6, 1986 Opening Statement - Subcommittee Chairman C. Wylie Mr. Wylie noted that the purpose of the meeting was to review the NRC Staff proposed standardization policy statement to the Commission on nuclear power plants, and to be briefed by the staff regarding the status of the policy statement and the status of standardization in regard to nuclear power plants.
He also noted that the subcommittee eventually will consider what it wants to present to the full Committee and if there is a need for the ACRS to write a letter on the policy statement and what other future activities leading up to a letter on standard plants that the subcommittee would wish to consider.
F. Miraglia, Division Director of Pressurized Water Reactors Licensing-B Mr. Miraglia noted that within his scope he has the responsibility for the development of standardization policy. He remarked that the concept of standardization was basically developed in April 1972 when the Commission proposed development of a standardization policy.
In March 1973 the Commission announced three concepts that it would use in the context of standardization. These are:
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~
MINUTES /
SUMMARY
/ STANDARD ,
3 PLANT DESIGN - Jan. 6, 1986 s
o Reference Design System - application for approval of the design of an entire plant or major portion thereof, o Duplicate Plant Concept - this involves the application by one or more utilities for licenses to construct and/or operate a number of nuclear power plants of essentially the same design at different sites.
o Manufacturing license concept - The manufacturing license concept involves an application for a license to manufacture a number of identical nuclear power plants at a location other than those at which they are to be operated.
In August of 1974 the Replicate Plant Concept was added. The Replicate Plant Concept involves an application by a utility for a license to construct and/or operate one or more nuclear power plants of essentially the same design as one already licensed.
Mr. Miraglia explained that the current policy statement resulted from a need to update the 1978 policy statement to include the experience since that time and the Severe Accident Policy Statement.
Mr. Miraglia noted that the staff is proposing to retain the reference system design. The reference system is an application for approval or certification of an entire plant or substantial portion of a plant.
f MINUTES /
SUMMARY
/ STANDARD 4 PLANT DESIGN - Jan. 6,* 1986' A Comittee member asked if on a duplicate or replicate reference design
- would that have to be the whole plant? Mr. Miraglia replied that it would.
A Committee member asked Mr. Miraglia about how a substantial portion of a plant is interpreted? He asked if it means that the NRC staff will continue to accept NSSS and B0P as separate items like the old reference designs?
Mr. Miraglia replied that the thrust of the Commission's intent is that the reference design is what the Comission is after. However, the Staff retained the language of substantial or major portion because that language is used in the legislation.
There was considerable discussion regarding interfaces. Mr. Miraglia pointed out there are design interfaces and instruction interfaces. He noted that depending on the scope of the application, the interfaces could be narrow or broad.
Mr. Thomas pointed out that the review of a reference design is outside the context of a specific application. Part of the review is deferred to when a utility submits an application for a license that references it.
Mr. Miraglia noted that if it is a very broad scoped reference plant, if it covers the whole plant, then the amount of information and what you need to assure that the interfaces have been met is very small.
.i
. . MINUTES /SUMPARY/ STANDARD 5 PLANT DESIGN - Jan. 6; 1986-Mr. Thomas noted that interface requirements appear in the application for standard design and they are supplemented by interface requirements in the Staff Safety Evaluation Report. The two taken together consti-tute the set of interface requirements that must be addressed by a utility applicant.
A Comittee member asked if you take a complete plant to design certi-fication, does that mean that the final design is not subject to litiga-tion?
Mr. Miraglia responded that what it means is that the final design is not subject to litigation to the extent that the scope is covered.
Regarding the amount of review for a standard plant, Mr. Miraglia pointed out that an individual standard plant would not save review time. If a number of standard plants were built, then a considerable amount of review time would be saved.
Mr. Miraglis pointed out that in response to industry input, a replica-tion provision was put in the policy paper. This allows a plant to be replicated up to five years from the promulgation of the policy state-ment.
He also noted that deviations from some of the provisions of the policy statements would be considered on a case-by-case basis.
, , - - - , - - - - , - - , a
MINUTES /
SUMMARY
/ STANDARD 6 PLANT DESIGN - Jan. 6', 1986^
Another provision added to the policy statement is the Standard Review Plan (NUREG-0800). NUREG-0800 is the revision of the Standard Review Plan that incorporates all the TMI requirements. The policy statement indicates that if a plant was reviewed against NUREG-0800 then replication of that plant would be considered at any site. Also, an older plant that preceded NUREG-0800 would be considered for replication if it was supported by good design and a suitable operating history of that particular plant design.
Mr. Miraglia pointed out that Atomic Industrial Forum (AIF) wanted design approval and certification to be for 10 years. The NRC staff proposed 5 years for design approval and 10 years for certification.
The premise for the difference was to encourage the effort towards +
certification.
Regarding the level of design information for a final design approval or a design certification, NRC used the terms " equivalent to the FSAR."
AIF took the position that it could be less. Mr. Miraglia pointed out the need for further discussions between the staff and industry to better define the level of design information necessary for design approval and certification.
Regarding the application of the cost / benefit balance, AIF wanted to apply this to the lead plant. The staff did not agree.
The Subcommittee members had an informal discussion following the prepared presentation. One member expressed his opinion that the policy L
MINUTES /
SUMMARY
/ STANDARD 7 PLANT DESIGN - Jan. 6,' 1986' statement didn't give the assurance necessary that all the requirements are stated and a utility can order a reactor with confidence.
Mr. Miraglia noted that the policy statement provides options for the near term and other options for long term.
One member suggested that the NRC certify nuclear plants in a manner similar to Federal Aviation Authority (FAA).
One member noted that he was displeased with the overall policy state-ment but was pleased with many of the changes since the last policy statement.
One member suggested the Commission should concentrate on a complete design.
The meeting was adjourned at 4:35 p.m.
NOTE: Additional meeting details can be obtained from a transcript of this meeting available in the NRC Public Document Room, 1717 H St., NW., Washington, D. C., or can be purchased from ACE-Federal Reporters, 444 North Capitol Street, Washington, D. C. 10001, (202) 347-3700.
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- m. Ce , a . , t c: r..wan., ties Forma 3:.bm!D:d fer O:.13 T!eview meeting, the Subcommittee, alen; with any ofits consultar.ts who may be Cr_m C,mn.,g as C.U :s ts- ,
In acecrdance with the Paperwork present, may exchange preliminary Ccmmim.: Redat tion A::t and OM3 Guidelines, the views regarding matters to be p _ . ,. - ,b "' C C'] considered during the balance of the Na!! anal S:icnce Foundation is posting i[; e t : !i fo Feb.: nch 5Coi e Icn: A:mally.
, ' ion colle: tion that m' ."
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- q. .!q v ci,:;ns' committees y,.y C'carmce Officen Herman C. presentetions by and hold discussic:.s Use:'l ) nerfr the .Wtionel Endor.rnent Fhi W 3 4-9520. with representatives of the NRC Staff.
for ? . .H::a:n" ' DaI:!on of Ftate OM"1DM Offican Carlos Tellez. Its consultants, and other interested Prog ru ef th> Committec's (202)335-7343. Persons rrgarding this review.
copuct wi 't the Ecclewmenl's
Title:
S r.ey of Earned Doctorates Further information regarding topics authm:NlegEtion so that the Award >d in the United States. to be discussed, whether the meeting AffectedPsblic: Individuals. has been cancelled or rescheduled, the comm'ttee can r_=ain e!!gible for Numberof Responses:31.000 fundier. Chairman's ruling on request for tl.e responses; total of 10.300 burden hours, Estimal5IN& cf Renondents: 53 Abstract: Persons with doctorate-level opportunity to present oral statements Estimat:d Ho ::s f r Ft: pendents to education are key members of the labor and the time allotted therefor can be Pro. ide Inf :- f rce in scientific, engineering and obtained by a prepaid telephone call to reapader.tur:.m rir. .G hacrs per
- de tota! hours for at1 learred professions. Information of their the cognizant ACRS staff member. Mr.
n:<pondente. demegraphic and educational Herman Alderman (telephone 202/ti34-
- 2. Ti:'e: Divis .m uf S' ate P:cgram Plan background and immediate postdoctoral 1414} between 8:15 a.m.end 5.00 p.m.
for Compli. c., by State Humamties study or employment plans is essential Persons planning to attend this meeting are urged to contact the above named Council 2 Optating as State Agencies. for :nalyses of supply and demand. Individual one or two days befure the Form Ni 9,r:3136-407a Thde data also report on the flow of women and minorities into the fields. scheduled meeting to be advised of any Fraw7f Collection: Annually changes in schedule. etc., which may Rew n3ds: State humamtirs councils Dated: December 12.1985. have occurred.
cp uting as state agencies. Herman G. r!c: .!:g.
. Dated: December 12.1985.
Ilse: T2 ptify the National Enduwment NSFReports Cleomece Oficer.
Morton W.11barkin.
forine Humantiles Division of State [G Doc.
Programs of the agency a compliance ,w,, ,, , ,85-2Wm
, , , , , , ,Fded 12-16-a5. 8 45 am]g,yj,,,Assistant ExecutiveDimerorforPrvicet with the Endowment's authon,zmg -
legislation so that the agency can [FR Doc. ,, 85-29838 Fded 12-1645: 8.45 em) remain eligible for funding. NUCLEAR REGULATORY COMMISSION Estimated Number of Respondents: 53 i/
the maximum possible number of Advisory Ccmmittee on Resctor IDocket No. 50-312) respc .d*ts.To date the:v are none. SafcmrJ3; 2_ n.r- AM: on Estimated Hours for Respunants to S E2d ?.'d Pir.7.. MGui .'.tR!!n9 Sscramento i.We'.o.C '.h j We Provide Information: 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per Envi.onmcatal ksmmer.t snu respondent for 5.300 total hours if all The ACRS Subcommittee on Standard Finding of No Significant impact %
states were state agencies. Plant Design will hold a renting on l January 6.19ES. Room 10 0.1717 H The U.S. Nuclear Regulatory 3.
Title:
Division of State Programs Street. NW.. Washmgto,n. DC . Commission (the Commissior. is Interim Progress Report Format The entire meetm considering issuance of an exe)mption Form Number: 3136-0077 pubhc attendance. g will be open to from a requirement of 10 CFR Frequency of Co!!ection: Biennially The agenda for subject meetm.g shall 50.44(c)(3)(iii) to the Sacramento R;s ondents:Statehumanities councils be as follows: Mondoy.fanuary 6. hiunicipal Utility District (the licensee).
Use Provide progress update on the 1986-1-Jap.m. until the conclusion of for the Rancho Seco Nuclear Cencrating two-year grant approved for funding Station. located in Sacramento County, during the previous year and is he$u'bcommittee will review California.
the necessary to for use by the NRC Staff paper on standard plants and discuss the status of standard plants. Environmental Assessment Endowment's chairman to determine .
" adequacy ** (as required by NFAH Oral statements may be presented by Identificallon 0fProPosedAction: The Cuthorizing legislation) in order to members of the public with the exemptmn would permit the licensee not receive second-year funding. concurrence of the Subcommittee to install a reactor vessel head vent as
- Estimated Number of Respondents:26- Chairman: writtin statements will be required by to CFR 50.44(c)(3)(iii).
accepted and made available to the 28 .
The exemption is responsive to, the Estimated Hours for Respondents to Committee. Reccedings will be permitted licensee e application for exemption only during those portions of the dated April 12.1985.
Provide Information:20 hours per' meeting when a transcript is being kept.
respondent for 480-560 total hours for The Needforthe Propose,dActionr, and questions may be asked only by The licensee has performed tests using d ~
members of the Subcommittee. Its the Once.Through integral System 8"" M*" - consultants, and Staff. Persons desiring (OTIS) facility. The purpose of these ActingDirectorofAdatimstation. to make oral statements should notify tests was to determine if reactor core
[R Doc. 85-29815 Filed 12-1645; 8.45 emi the ACRS staff member named below as cooldown can be maintained in the
'aewo cooe ts**'-* far in' advance as is practicable so that appropriate arrangements can be made. absence of a vessel head vent to release noncondensible gases from the vessel I
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f W&fnVr /3 TENTATIVE SCHEDULE ACRS STANDARD PLANT DESIGN SUBCOMMITTEE JANUARY 6, 1986 1:30 p.m. Introductory Statement Subcommittee Chairman 1:40 p.m. Background of Nuclear Power NRC Staff Power Plant Standardization 2:15 p.m. Standardization Policy Statement of August 1978 3:00 p.m. BREAK 3:10 p.m. Standardization Policy Statement of December 4, 1985 3:40 p.m. Status and Implementation of Nuclear Power Plant l Standardization 4:00 p.m. Subcommittee Discussion 4:30 p.m. Adjourn 1
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H. ALDERMAN ACRS SUBCOMMITTEE MEETING ON RSTANDARD PLANT DESJGN LOCdTIO:1: Room 1046 - 1717 H St. NW.. Washinaton, D. C.
DATE: JANUARY 6,1986 ATTENDANCE LIST PLEASE PRINT:
NAME BADGE N0. AFFILIATION
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