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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20212A2471999-09-15015 September 1999
Summary of 990902 Meeting with Westinghouse in Rockville,Md Re Changes That W Plan to Make in Rev 3 of AP600 Design Control Document (Dcd).List of Attendees & Handouts Encl
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
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
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
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
ML20249A7191998-06-16016 June 1998
Summary of 980611 Appeal Meeting W/Westinghouse in Rockville,Md Re Appeal of NRC Position on Use of AP600 Bldg Figures in Section 3.3 of AP600 Tier 1 Matl.Attendance List, handouts,marked-up Page 3.3-1 & Note 2 Encl
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
ML20217K6281998-04-28028 April 1998
Summary of 980416 Meeting W/Westinghouse in Rockville,Md to Discuss AP600 TS Issues.List of Participants & Handouts & Markups Provided by Licensee During Meeting,Encl
ML20217P8441998-04-0707 April 1998
Summary of 980212 Meeting W/Westinghouse in Rockville,Md to Continue Discussion on Level 1 Probabilistic Risk Assessment Insights.Addl Telcon Was Held on 980217,due to Unresolved Issues During Meeting.List of Attendees Encl
ML20217J9321998-04-0303 April 1998
Summary of 980211 Meeting W/W in Rockville,Md Re Safety Classification of Coatings Inside Containment & on Exterior of Containment Shell.List of Attendees & Handout Encl
ML20216G6071998-03-12012 March 1998
Summary of 980211 Meeting W/Westinghouse in Rockville,Md Re Status of Open Issues Resulting from Design Certification Review of AP600.List of Attendess Encl
ML20216B1221998-03-0606 March 1998
Summary of 980122 Meeting W/Westinghouse in Rockville,Md Re Status of Open Issues Resulting from Design Certification Review of AP600.List of Attendees Encl
ML20216G1471998-03-0606 March 1998
Summary of 980224 Meeting W/Westinghouse Electric Co to Resolve Issues Re AP600 Fire Protection Design
ML20197B9091998-03-0606 March 1998
Summary of 971218 Meeting W/Westinghouse in Rockville,Md Re Open Issues Remaining on Analyses of Radiological Consequences of Design Basis Accidents for AP600 Design. List of Attendees & Handouts Provided at Meeting Encl
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
ML20203H8691998-02-19019 February 1998
Summary of 980211 Meeting W/W in Rockville,Md Re W Opportunity to Respond to NRC Insp Rept 99900404/97-02,dtd 980128.List of Attendees & Meeting Handouts Encl
ML20203A8991998-02-11011 February 1998
Summary of 980120 & 21 Meeting W/Westinghouse to Discuss AP600 Structural Calculations to Resolve FSER Open Items. List of Participants & Handouts Encl
ML20198Q1471998-01-13013 January 1998
Summary of 971104 Meeting W/Westinghouse in Rockville,Md Re AP600 Nuclear Island Basemat Design,Configuration of Shear Stirrups & Shear Capacity of Deep Slabs.List of Attendees & Handouts Encl
ML20198H5621998-01-0707 January 1998
Summary of 971218 Meeting W/Westinghouse in Rockville,Md to Discuss Design Certification Schedule for AP600 Review
ML20198A1861997-12-18018 December 1997
Summary of 971117 Meeting W/Westinghouse in Rockville,Md Re Design Certification Schedule for AP600.List of Attendees & Handouts Provided During Meeting Encl
ML20199B1211997-11-0606 November 1997
Summary of 971029 Meeting W/Westinghouse in Rockville,Md to Discuss Problems & Progress Affecting AP600 Review Schedule. List of Attendees Encl
ML20198R6601997-10-30030 October 1997
Summary of 971109 Telcon W/Westinghouse to Discuss RAI Responses Related to TS & Sys Level Testing
ML20198R9261997-10-30030 October 1997
Summary of 971009 Meeting W/Westinghouse in Rockville,Md Re Design Certification Schedule for AP600.List of Attendees & Handouts Encl
ML20212B7491997-10-20020 October 1997
Summary of 971007 Meeting W/Westinghouse in Rockville,Md Re AP600 General Design Features & Safety Philosophy.List of Attendees & Presentation Slides Provided by Westinghouse Encl
ML20217K7951997-10-17017 October 1997
Summary of 970929 Meeting W/W to Discuss Fire Protection Issues for AP600 Design.List of Attendees & Handouts Provided by Licensee Encl
ML20211L2751997-10-0707 October 1997
Summary of 970923 Meeting W/Westinghouse in Monroeville,Pa Re Status of Completion of AP600 Design Documentation in Several Review Areas in Order to Support Final QA Insp
ML20217E8141997-10-0202 October 1997
Summary of 970925 Meeting W/Westinghouse in Rockville,Md Re First Interdisciplinary Review of ITAAC for AP600 Design. Agenda & Listed of Attendees Encl
ML20217E9961997-10-0202 October 1997
Summary of 970911 Meeting W/Westinghouse Electric Corp Re Fire Protection Issues for AP600 Design
ML20211H9691997-09-30030 September 1997
Summary of 970804-15 Meeting W/W in Rockville,Md to Review Structural Design of Nuclear Island Structures.List of Participants & Agenda for 2 Wk Review Encl
ML20211G2681997-09-23023 September 1997
Summary of 970910 Meeting W/Westinghouse in Rockville,Md Re Design Certification Schedule for AP600.List of Attendees & Handouts Encl
ML20211C4891997-09-18018 September 1997
Summary of 970717,0805,0905 & 0911 Telcons Between Westinghouse & Staff Members Re Severe Accident & PRA Issues.List of Participants,Topics for Discussion & Disposition for Topics Encl
ML20198H5421997-09-11011 September 1997
Summary of 970828 Telcon W/W Re Proposed Design Changes to AP600 MCR Habitability Sys.List of Participants & Preliminary Sketch of Modified Design & Associated Temperature Response Encl
ML20210Q7641997-08-28028 August 1997
Summary of 970826 Telcon W/Westinghouse Re AP600 Emergency Response Guidelines.Summary of Actions from Telcon Listed. List of Telcon Participants Encl
ML20210Q7561997-08-22022 August 1997
Summary of 970808 Meeting W/Westinghouse Electric Corp in Monroeville,Pa Re Fire Protection Issues for AP600 Design. List of Attendees,Agenda & Slides Presented by Westinghouse Encl
ML20210Q1221997-08-22022 August 1997
Summary of 970807 Meeting W/Westinghouse Re Proposed Containment Spray Design for AP600 Design.List of Attendees & Slides Encl
ML20210M7361997-08-19019 August 1997
Summary of 970807 Meeting W/W in Rockville,Maryland Re AP600 MCR Habitability Sys Operational Parameters of Air Flow rates,CO2 Levels,Temperature & Humidity Needed to Establish Personnel Habitability of Design
ML20217K6741997-08-12012 August 1997
Summary of 970806 Safeguards Meeting W/Westinghouse to Discuss Safeguards Issues on AP600 Design
ML20217G8621997-07-31031 July 1997
Summary of 970708 Meeting W/Westinghouse in Rockville,Md to Discuss Design Certification Issues for AP600.List of Attendees & Handouts Encl
ML20151J6501997-07-31031 July 1997
Summary of 970723 Telcon W/W to Discuss 970709 Submittal of NSD-NRC-97-5227 Re Site Parameters.List of Attendees & Comments Prior to Telcon Encl
ML20151J6081997-07-31031 July 1997
Summary of 970709 Meeting W/Westinghouse in Rockville,Md Re Discuss Design Certification Issues for AP600.List of Attendees & Handouts Encl
ML20141D4321997-06-23023 June 1997
Summary of 970425 Meeting W/Westinghouse in Rockville,Md Re Resolution of Open Items for Reactor Sys AP600 Pirt/Scaling Closure rept,(WCAP-14727).List of Attendees,Meeting Agenda & Westinghouse Meeting Presentation Matl Encl
ML20141C4971997-06-23023 June 1997
Summary of 970609 Meeting W/W in Rockville,Md to Discuss Open Item Tracking Sys Issues Involving Instrumentation & Control Section of AP600 TSs Section 3.3.Highlights from Meeting & Summary of Results Listed
ML20149J2181997-06-16016 June 1997
Summary of 970416-18 Meeting W/Westinghouse in Monroeville, MD Re AP600 Piping Design Analysis.Meeting Attendees Listed in Encl 1
ML20140G4541997-06-12012 June 1997
Summary of 970520 Meeting W/Westinghouse in Monroeville,Pa Re AP600 Containment Hydrogen Control Sys.List of Attendees & Action Items Identified During Meeting Encl
ML20140B4251997-06-0404 June 1997
Summary of 970519 Meeting W/Westinghouse Re AP600 Fire Protection Issues
ML20141G5421997-05-15015 May 1997
Summary of 970422 Meeting W/W in Rockville,Md to Discuss Design Certification Issues for AP600.List of Meeting Attendees Encl
ML20141G3801997-05-15015 May 1997
Summary of 970414-18 Meeting W/W in Monroeville,Pa to Discuss W Ssar Sections 3.7 & 3.8 Re Design & Analysis of Structural Modules,Review Structural Design Calculations & Resolve Remaining Dser Open Items.List of Attendees Encl
ML20141D0361997-05-15015 May 1997
Summary of 970513 Meeting W/W to Discuss Safeguards Issues on AP600 Design.List of Attendees Encl
1999-09-15
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20212A2471999-09-15015 September 1999
Summary of 990902 Meeting with Westinghouse in Rockville,Md Re Changes That W Plan to Make in Rev 3 of AP600 Design Control Document (Dcd).List of Attendees & Handouts Encl
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
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
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
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
ML20249A7191998-06-16016 June 1998
Summary of 980611 Appeal Meeting W/Westinghouse in Rockville,Md Re Appeal of NRC Position on Use of AP600 Bldg Figures in Section 3.3 of AP600 Tier 1 Matl.Attendance List, handouts,marked-up Page 3.3-1 & Note 2 Encl
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
ML20217K6281998-04-28028 April 1998
Summary of 980416 Meeting W/Westinghouse in Rockville,Md to Discuss AP600 TS Issues.List of Participants & Handouts & Markups Provided by Licensee During Meeting,Encl
ML20217P8441998-04-0707 April 1998
Summary of 980212 Meeting W/Westinghouse in Rockville,Md to Continue Discussion on Level 1 Probabilistic Risk Assessment Insights.Addl Telcon Was Held on 980217,due to Unresolved Issues During Meeting.List of Attendees Encl
ML20217J9321998-04-0303 April 1998
Summary of 980211 Meeting W/W in Rockville,Md Re Safety Classification of Coatings Inside Containment & on Exterior of Containment Shell.List of Attendees & Handout Encl
ML20216G6071998-03-12012 March 1998
Summary of 980211 Meeting W/Westinghouse in Rockville,Md Re Status of Open Issues Resulting from Design Certification Review of AP600.List of Attendess Encl
ML20216B1221998-03-0606 March 1998
Summary of 980122 Meeting W/Westinghouse in Rockville,Md Re Status of Open Issues Resulting from Design Certification Review of AP600.List of Attendees Encl
ML20216G1471998-03-0606 March 1998
Summary of 980224 Meeting W/Westinghouse Electric Co to Resolve Issues Re AP600 Fire Protection Design
ML20197B9091998-03-0606 March 1998
Summary of 971218 Meeting W/Westinghouse in Rockville,Md Re Open Issues Remaining on Analyses of Radiological Consequences of Design Basis Accidents for AP600 Design. List of Attendees & Handouts Provided at Meeting Encl
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
ML20203H8691998-02-19019 February 1998
Summary of 980211 Meeting W/W in Rockville,Md Re W Opportunity to Respond to NRC Insp Rept 99900404/97-02,dtd 980128.List of Attendees & Meeting Handouts Encl
ML20203A8991998-02-11011 February 1998
Summary of 980120 & 21 Meeting W/Westinghouse to Discuss AP600 Structural Calculations to Resolve FSER Open Items. List of Participants & Handouts Encl
ML20198Q1471998-01-13013 January 1998
Summary of 971104 Meeting W/Westinghouse in Rockville,Md Re AP600 Nuclear Island Basemat Design,Configuration of Shear Stirrups & Shear Capacity of Deep Slabs.List of Attendees & Handouts Encl
ML20198H5621998-01-0707 January 1998
Summary of 971218 Meeting W/Westinghouse in Rockville,Md to Discuss Design Certification Schedule for AP600 Review
ML20198A1861997-12-18018 December 1997
Summary of 971117 Meeting W/Westinghouse in Rockville,Md Re Design Certification Schedule for AP600.List of Attendees & Handouts Provided During Meeting Encl
ML20199B1211997-11-0606 November 1997
Summary of 971029 Meeting W/Westinghouse in Rockville,Md to Discuss Problems & Progress Affecting AP600 Review Schedule. List of Attendees Encl
ML20198R6601997-10-30030 October 1997
Summary of 971109 Telcon W/Westinghouse to Discuss RAI Responses Related to TS & Sys Level Testing
ML20198R9261997-10-30030 October 1997
Summary of 971009 Meeting W/Westinghouse in Rockville,Md Re Design Certification Schedule for AP600.List of Attendees & Handouts Encl
ML20212B7491997-10-20020 October 1997
Summary of 971007 Meeting W/Westinghouse in Rockville,Md Re AP600 General Design Features & Safety Philosophy.List of Attendees & Presentation Slides Provided by Westinghouse Encl
ML20217K7951997-10-17017 October 1997
Summary of 970929 Meeting W/W to Discuss Fire Protection Issues for AP600 Design.List of Attendees & Handouts Provided by Licensee Encl
ML20211L2751997-10-0707 October 1997
Summary of 970923 Meeting W/Westinghouse in Monroeville,Pa Re Status of Completion of AP600 Design Documentation in Several Review Areas in Order to Support Final QA Insp
ML20217E8141997-10-0202 October 1997
Summary of 970925 Meeting W/Westinghouse in Rockville,Md Re First Interdisciplinary Review of ITAAC for AP600 Design. Agenda & Listed of Attendees Encl
ML20217E9961997-10-0202 October 1997
Summary of 970911 Meeting W/Westinghouse Electric Corp Re Fire Protection Issues for AP600 Design
ML20211H9691997-09-30030 September 1997
Summary of 970804-15 Meeting W/W in Rockville,Md to Review Structural Design of Nuclear Island Structures.List of Participants & Agenda for 2 Wk Review Encl
ML20211G2681997-09-23023 September 1997
Summary of 970910 Meeting W/Westinghouse in Rockville,Md Re Design Certification Schedule for AP600.List of Attendees & Handouts Encl
ML20211C4891997-09-18018 September 1997
Summary of 970717,0805,0905 & 0911 Telcons Between Westinghouse & Staff Members Re Severe Accident & PRA Issues.List of Participants,Topics for Discussion & Disposition for Topics Encl
ML20198H5421997-09-11011 September 1997
Summary of 970828 Telcon W/W Re Proposed Design Changes to AP600 MCR Habitability Sys.List of Participants & Preliminary Sketch of Modified Design & Associated Temperature Response Encl
ML20210Q7641997-08-28028 August 1997
Summary of 970826 Telcon W/Westinghouse Re AP600 Emergency Response Guidelines.Summary of Actions from Telcon Listed. List of Telcon Participants Encl
ML20210Q7561997-08-22022 August 1997
Summary of 970808 Meeting W/Westinghouse Electric Corp in Monroeville,Pa Re Fire Protection Issues for AP600 Design. List of Attendees,Agenda & Slides Presented by Westinghouse Encl
ML20210Q1221997-08-22022 August 1997
Summary of 970807 Meeting W/Westinghouse Re Proposed Containment Spray Design for AP600 Design.List of Attendees & Slides Encl
ML20210M7361997-08-19019 August 1997
Summary of 970807 Meeting W/W in Rockville,Maryland Re AP600 MCR Habitability Sys Operational Parameters of Air Flow rates,CO2 Levels,Temperature & Humidity Needed to Establish Personnel Habitability of Design
ML20217K6741997-08-12012 August 1997
Summary of 970806 Safeguards Meeting W/Westinghouse to Discuss Safeguards Issues on AP600 Design
ML20217G8621997-07-31031 July 1997
Summary of 970708 Meeting W/Westinghouse in Rockville,Md to Discuss Design Certification Issues for AP600.List of Attendees & Handouts Encl
ML20151J6501997-07-31031 July 1997
Summary of 970723 Telcon W/W to Discuss 970709 Submittal of NSD-NRC-97-5227 Re Site Parameters.List of Attendees & Comments Prior to Telcon Encl
ML20151J6081997-07-31031 July 1997
Summary of 970709 Meeting W/Westinghouse in Rockville,Md Re Discuss Design Certification Issues for AP600.List of Attendees & Handouts Encl
ML20141D4321997-06-23023 June 1997
Summary of 970425 Meeting W/Westinghouse in Rockville,Md Re Resolution of Open Items for Reactor Sys AP600 Pirt/Scaling Closure rept,(WCAP-14727).List of Attendees,Meeting Agenda & Westinghouse Meeting Presentation Matl Encl
ML20141C4971997-06-23023 June 1997
Summary of 970609 Meeting W/W in Rockville,Md to Discuss Open Item Tracking Sys Issues Involving Instrumentation & Control Section of AP600 TSs Section 3.3.Highlights from Meeting & Summary of Results Listed
ML20149J2181997-06-16016 June 1997
Summary of 970416-18 Meeting W/Westinghouse in Monroeville, MD Re AP600 Piping Design Analysis.Meeting Attendees Listed in Encl 1
ML20140G4541997-06-12012 June 1997
Summary of 970520 Meeting W/Westinghouse in Monroeville,Pa Re AP600 Containment Hydrogen Control Sys.List of Attendees & Action Items Identified During Meeting Encl
ML20140B4251997-06-0404 June 1997
Summary of 970519 Meeting W/Westinghouse Re AP600 Fire Protection Issues
ML20141G5421997-05-15015 May 1997
Summary of 970422 Meeting W/W in Rockville,Md to Discuss Design Certification Issues for AP600.List of Meeting Attendees Encl
ML20141G3801997-05-15015 May 1997
Summary of 970414-18 Meeting W/W in Monroeville,Pa to Discuss W Ssar Sections 3.7 & 3.8 Re Design & Analysis of Structural Modules,Review Structural Design Calculations & Resolve Remaining Dser Open Items.List of Attendees Encl
ML20141D0361997-05-15015 May 1997
Summary of 970513 Meeting W/W to Discuss Safeguards Issues on AP600 Design.List of Attendees Encl
1999-09-15
[Table view] |
Text
- - .
CERTIFIED: George Apostolakis, August 7, 1996 CERTIFB Issued: July 23, 1996 hkh8d l ADVISORY COMMITTEE ON REACTOR SAFEGUARDS JOINT SUBCOMMITTEE MEETING MINUTES:
PROBABILISTIC RISK ASSESSMENT AND WESTINGHOUSE STANDARD PLANT DESIGNS I JUNE 5, 1996 ROCKVILLE, MARYLAND The ACRS Joint Subcommittee on Probabilistic Risk Assessment (PRA) and Westinghouse Standard Plant Designs met on June 5, 1996, at l 11545 Rockville Pike, Rockville, Maryland, in Room T-2 B3. The purpose of the meeting was to gather information concerning the Westinghouse AP600 Level 1 and shutdown PRAs. 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 8:30 a.m. and adjourned at 2:35 p.m.
ATTENDEES ACRS G. Apostolakis, Chairman D. Powers, Member W. Lindblad, Member R. Seale, Member I. Catton, Member W. Shack, Member M. Fontana, Member C. Wylie, Member T. Kress, Member N. Dudley, ACRS staff INDUSTRY C. Monty, Westinghouse S. Sancaktar, Westinghouse T. Bueter, Westinghouse T. Schulz, Westinghouse C. Haag, Westinghouse There were no writte.n comments or requests for time to make oral statements received from members of the public. An attendance list of the NRC staff and public is available in the ACRS office files.
Public participation during this meeting was limited to the presentations by the above named industry representatives.
INTRODt'CTIOM:
Dr. George Apostolakis, the Subcommittee Chairman, convened the meeting at 8:30 a.m. He stated that the planned presentations would provide information to the Subcommittee concerning the AP600 Level 1 and shutdown PRAs. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions as appropriate for deliberation by the full Committee. ;
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Minutes: PRA/AP600 Joint Subcommittee June 5, 1996 WESTINGBOUSE PRESENTATION:
Mr. Bruce Monty, Manager Risk Assessment Services Group, Westinghouse, introduced the Westinghouse technical staff and outlined the presentation, which included an overview of the AP600 4 design, the design process, and the Level 1 and shutdown PRA 1
analyses.
All stages of the PRA were performed by the Westinghouse PRA group.
The main objectives of the PRA were to:
o support NRC requirements for a design specific PRA, e scope core damage frequency to less than the NRC safety goal e provide a tool for both design and operations, and e bound seismic events by using the seismic margins approach.
overview of AP600 Desian Mr. Terry Schulz, Westinghouse, provided the following overview of the key design features of the AP600 that affect the P.RA. The overall system design, which was developed using PRA insights, i reduces possible failure mechanisms and enhances overall safety.
The design for the reactor coolant loop piping reduces the number
- of welds and the potential for pipe failure. The reactor vessel, which is larger than present designs, reduces the power density of the core. The reactor vessel has no bottom penetrations, below the loop penetrations. This design improves vessel integrity. The pressurizer is oversized to reduce challenges to the safety valves from pressure transients. All major piping is designed as leak before break to reduce the probability of a loss-of-coolant-accident (LOCA). Valves that require electric power to change position are DC powered, eliminating the need for AC power from 3 either the diesels or off site power during accident scenarios.
The major decay heat . removal systems are passive in nature, further reducing the probability of system failure.
- The AP600 piping layout reduces the problems encountered during mid-loop operations at operating plants. Further, Mr. Selim 4
Sancaktar, Westinghouse, stated that conservative design and acceptance testing, combined with PRA insights, result in a robust design for the AP600.
Mr. Schulz, Westinghouse, and the Subcommittee discussed the defense-in-depth and diversity associated with the AP600 design.
- Backaround and PRA Methodoloav i
Dr. Sancaktar, Westinghouse, explained that since 1987 Westinghouse has used information from the AP600 PRA to improve the AP600 design. The Westinghouse PRA group has experience with the British e
i
Minutes: PRA/AP600 Joint Subcommittee June 5, 1996 Sizewell B PRA and more than 20 domestic and foreign IPE/PRA studies. Dr. Sancaktar explained the development of the Level 1 PRA, which includes initiating events, event trees and success criteria, thermal hydraulic analyses, plant systems analyses, common cause failures, human reliability, data analysis, fault tree and event tree quantification, and importance and sensitivity studies. He discussed the development of the low power and shutdown PRA.
I Dr. Sancaktar explained that the scope used for the AP600 PRA is
+
defined according to revision 5/6 of the Advanced Light Water Reactor Utility Requirements Document. The methods used are standard quantitative methods such as described in NUREG-2300.
Data used are mean values. Success criteria are derived from extensive thermal hydraulic analyses. Fault tree linking methods are used to quantify core damage sequence frequencies. Fault trees include system component failures, common cause faults, test and maintenance unavailability, and human errors.
Dr. Sancaktar stated that the AP600 design addressed PRA-related issues that dominate core damage frequency (CDF) at operating ,
plants and provided the following examples.
PRA Issue How AP600 addressed the Issue Station Blackout (Loss of all AC) Safety systems are not dependent on AC power.
Reactor Coolant Pump (RCP) seal LOCA RCPs have canned motors that do not have seals.
Loss of support systems Safety systems do not rely on AC power or
. . cooling water support systems.
Interfacing systems LOCA The reactor non-safety system pathways will be able to withstand reactor s coolant system pressure.
Susceptibility to human errors The design minimizes the importance of operator actions required to mitigate accidents. ,
ATWS A diverse actuation i system was added to the design to trip the reactor.
Minutes: PRA/AP600 Joint Subcommittee June 5, 1996 Reliability of reactor heat Administrative controls removal system (RHR) require testing of systems prior to shutdown. System design prevents pump cavitation and provides improved instrumentation.
Loss of decay heat removal at shutdown Passiye injection requires no operator action or electric power sources.
l Westinghouse and the Subcommittee discussed the schedule for I completing the PRA, and the codes, models, system based procedures, and cognitive failures used in developing the PRA. They also discussed the quantitative reliability and uncertainty of the PRA results.
Level 1 PRA (At-Power Conditions)
Dr. Sancaktar presented the initiating event frequencies, duminant initiating events, and CDF results for at-power events. He provided comparison of the Level 1 PRA results to other plant designs and sensitivity studies.
Westinghouse and the Subcommittee discussed the origin of values used in the Level 1 PRA, the event sequences, the sensitivity of l the analyses to operator actions, and the Idaho National l Engineering Laboratory review of the PRA. l Shutdown PRA Mr. Tim Bueter, Westinghouse, presented the dominant contributor to CDF during shutdown conditions. Shutdown risk is less than the at-power risk. Design features important to shutdown risk reduction are:
o Passive safety systems are available to back up normal decay heat removal functions, e Loss of off site power coincident with shutdown is not significant due to passive injection, which requires no off site or diesel generator supplied AC power.
Mr. Bueter stated that no credit is taken for the in-containment refueling water storage tank injection flow paths, and all operator actions are calculated conservatively. Credit is taken only for safety-related systems used in mitigation of events, even though, nonsafety-related systems are available.
s Minutes: PRA/AP600 Joint Subcommittee June 5, 1996 Westinghouse and the Subcommittee discussed normalizing the shutdown risk to an hourly basis, the seismic margins assumed, the need for a safety grade spent fuel pool cooling system, and the reliability of hot leg level instruments.
Conclusions Mr. Monty concluded that based on eight years of performing a detailed PRA of the AP600 design:
l e The AP600 design meets both the NRC and industry core damage frequency goals.
e The AP600 design demonstrates a significant core damage frequency improvement over current operating plants, e Iterative PRA application has allowed design enhancements that address significant PRA issues.
4 SUBCOMMITTEE DISCUSSION: l Mr. Lindblad inquired how friction losses were accounted for in the passive design fluid flows. Mr. Schulz responded that the design incorporates conservative calculations for estimating friction losses and in calculating accident analysis. Further, when a plant is built start up tests will verify the friction loss factors and in-service testing will confirm the friction loss factors throughout the life of the plant.
Mr. Lindblad inquired if water chemistry is a factor in preventing corrosion and biological growth. Mr. Schulz responded that with I the materials planned to be used, primarily stainless steel, corrosion was not expected to be a major concern. He noted that biological growth is a concern in the stagnant in-containment ;
reactor water storage tank. This will be resolved by performing a system flow test to ensure flow is within design limits.
Mr. Lindblad inquired if tank temperature can impede passive flow.
Mr. Schulz responded that there is a limit on standby tank temperatures, because subcooling plays a role in both flow and heat removal characteristics.
Mr. Lindblad questioned the design reliability of the startup feedwater pumps. Mr. Schulz described the startup feedwater as reliable but stated the system is not as reliable as the current safety grade auxiliary feedwater systems. There would be only two startup feedwater pumps in the AP600 design.
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Minutes: PRA/AP600 Joint Subcommittee June 5, 1996 l l
Dr. Seale asked if a fire PRA was available. Ms. Cindy Haa Westinghouse, responded that a fire assessment is in progress. g, The Subcommittee inquired if the same discipline used for designinq safety-related systems carried over to the design of nonsafety-related systems. Mr. Schulz replied that the nonsafety-related l areas are not designed to the same rigorous standards as safety-l related systems. However, Westinghouse cade scue informed design l l decisions for nonsafety-related systems, such as, separation of '
components.
Mr. Lindblad asked if there is a time limit for startup of the diesel generators. Mr. Schulz responded that approximately two minutes was chosen to allow diesel generator warm up in order to avoid diesel engine failures.
Mr. Wylie asked if there is adequate protection for a chemical volume control system line breaks outside the containry it. Mr.
Monty stated that there are isolation valves betwrx inside containment and outside containment, and that a detailed system drawing would contain details of the types of isolation valves.
SUBCOMMITTEE RECOMMENDATIONS:
The Joint Subcommittee proposed holding future Subcommittee meetings to hearing presentations on the AP600 Level 2 PRA and external events analyses.
BACKGROUND MATERIAL PROVIDED TO THE SUBCOMMITTEE:
- 1. SECY-96-128, " Policy and Key Technical Issues Pertaining to the Westinghouse AD600 Standardized Passive Reactor Design,"
dated June 12, 1996
- 2. Letter dated June 15, 1995, from T. S. Kress, Chairman, ACRS, to James M. Taylor, Executive Director for Operations,
Subject:
Proposed Commission Paper On Technical Issues Pertaining To The Westinghouse AP600 Standardized Passive Reactor Design
- 3. Letter dated August 8, 1995, from James M. Taylor, Executive Director for Operations, to T.S. Kress, Chairman, ACRS,
Subject:
Response To ACRS Comments On Commission Paper On Technical Issues Pertaining To The Westinghouse AP600 Design"
- 4. Memorandum date July 2, 1996, from August Cronenberg, Senior ACRS Fellow, to ACRS Members and Staff,
Subject:
NRC Staff and Westinghouse Positions on AP600 Design Review Issues l
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Minutes: PRA/AP600 Joint Subcommittee June 5, 1996 j
I NOTE: Additional details of this meeting can be obtained from l a transcript of this meeting available in the NRC Public l Document Room, 2120 L Street, N.W., Washington, D.C. l 20006, (202) 634-3274, or can be purchased from Nea R.
, Gross and Company Incorporated, Court Reporters and Transcribers,1323 Rhode Island Avenue, N.W. , Washington,
- D.C. 20005, (202) 234-4433.
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