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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
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g k UNITED STATES g j NUCLEAR REGULATORY COMMISSION I WASHINGTON, D.C. 20666-0001
,pg 4 # April 3, 1998 APPLICANT: Westinghouse Electric Corporation PROJECT: AP600 1
SUBJECT:
SUMMARY
OF AP600 MEETING TO DISCUSS AP600 CONTAINMENT COATINGS f
i The subject meeting was held on February 11,1998, at the Nuclear Regulatory Commission's office in Rockville, Maryland. Attachment 1 is a list of the participants. Attachment 2 contains l the handouts provided by Westinghouse during the meeting.
The purpose of the meeting was to discuss the safety classification of the coatings inside - - ~
containment and on the exterior of the containment shell. In preparation for the meeting the staff sent Westinghouse a list of items that were to be addressed during the meeting (Attachment 3).
Westinghouse provided a written response to these items in a February 10,1998, letter (NSD-NRC-98-5565). The responses contained in this letter were the focal point of the meeting. The discussion that occurred was broken down into four different areas of containment. These areas were: the outside of the containment shell above the 135 foot elevation, the inside of the containment shell above the operating deck, the area adjacent to the containment recirculation screens, and the rest of the inside of containment.
The staff was not persuaded by Westinghouse's argument that the coatings on the outside of the containment shell above the 135 foot elevation need not be censidered safety-related. The staff informed Westinghouse that they believed the coatings served a safety-related function, and therefore, they should be considered safety-related.
The staff expressed concem to Westinghouse regarding their position that the coatings on the ;
inside of the containment shell above the operating deck need not be considered safety-related. ,i The staff informed Westinghouse that it had insufficient information to come to the same \
conclusion. Specifically, the staff was concemed that it did not know of any passive containment r cooling system test data that existed with either degraded coatings or without coatings. It was -
not clear to the staff what effect the lack of coatings on the inside of the containment shell, or degraded coatings in this area, would have on the design basis properties of the containment
'( /
i shell and the passive containment cooling system performance. The staffindicated to Westinghouse that it would need to provide more information in this area or, as an alternative, consider these coatings safety-related.
The staff agreed with Westinghouse that the coatings in the area adjacent to the recirculation screens should be considered safety related. For the rest of the inside of containment, the staff agreed with Westinghouse that the coatings need not be considered safety-related. However, the staff stated that Westinghouse would have to provide an inspection, test, analyses, and acceptance criteria (ITAAC) for these coatings to ensure that they are consistent with the assumptions used in Westinghouse's standard safety analysis report.
.- t t, ) Y 9804070076 980403 )
- " ^" '" M ' NRC HLF CENTER CDPV l
April 3,1998 A draft of this meeting summary was provided to Westinghouse to allow them the opportunity to comment on the summary prior to issuance. I original signed by:
Joseph M. Sebrosky, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003
)
Attachments: As stated cc w/atts: See next page DISTRIBUTION w/ attachments:
Docket File PDST R/F TKenyon PUBLIC BHuffman JSebrosky DScaletti JNWilson SMagruder JHWilson MDunsaniwskyj DJackson j l
DISTRIBUTION w/o attachments:
SCollins/FMiraglia,0-5 E7 BSheron,0-5 E7 BBoger,0-5 E7 JRoe DMatthews TQuay '
ACRS (11) JMoore,0-15 B18 Glainas,0-7 D26 JStrosnider,0-7 D26 JDavis,0-7 D4 RRothman,0-7 H15 GGeorgiev,0-7 H15 GHolahan,0-8 E2 JLyons,0-8 D1 EThrom,0-8 H7 RLobel,0-8 H7 BGramm,0-9 A1 JPeralta,0-9 A1 l l
l 1
l DOCUMENT NAME:A:\ COATING. SUM To receive a copy of this document, inycat n the box: "C" = Copy without attachment / enclosure "E" = Copy with attacMent/ enclosure "N" = No cow OFFICE IPM:PDST:DRPM l BC;nCd@E l BC:HQMB:DRCH l6 PM:SCSB:DSSA l 6 NAME JMSebrosky:sg.jW GBagchi BGrarpm (l.h EThrom h b z= my num um ===r OFFICE PM:SCSB:DSSA c SOOG.DGGA - . DEPA/' Ab7' NAME RLobel N TRQuay #
DATE 03/2]/98 e /98 ()(rx-p OFFICIAL RECORD COPY
'I,
- Westinghouse Electric Corporation Docket No.52-003 cc: Mr. Nicholas J. Liparulo, Manager .
Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation ' 19901 Germantown Road P.O. Box 355 .
Germantown, MD 20874 Pittsburgh, PA 15230 .
Mr. Russ Bell Mr. B. A. McIntyre ' . Senior Project Manager, Programs Advanced Plant Safety & Licensing Nuclear Energy Institute Westinghouse Electric Corporation 1776 l Street, NW
- Energy Systems Business Unit Suite 300 Box 355 ' Washington, DC 20006-3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John,'MD 20818 Energy Systems Business Unit Box 355 Dr. Craig D. Sawyer, Manager Pittsburgh, PA 15230 Advanced Reactor Programs GE Nuclear Energy Mr. M. D. Beaumont .
175 Curiner Avenue, MC-754 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro Mr, Robert H. Buchholz 11921 Rockville Fike GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.
U.S. Department of Energy Eckert Seamans Cherin & Mellott NE-50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. Charles Thompson, Nuclear Engineer PWR Design Certification AP600 Certification Electric Power Research Institute y_ NE-50 3412 Hillview Avenue Palo Alto, CA .94303
- 19901 Germantown Road Germantown, MD 20874
. Mr. Robert Maiers, P.E.
Pennsylvania Department of
' : Environmental Protection -
Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469
e AP600 MEETING TO DISCUSS AP600 STRUCTURAL MODULES MEETING ATTENDEES FEBRUARY 11,1998 NAME ORGANIZATION TERRY SCHULZ WESTINGHOUSE RON VIJUK WESTINGHOUSE EUGENE PIPLICA . WC3TINGHOUSE DONALD LINDGREN WESTINGHOUSE:
BOB VlJUK WESTINGHOUSE BRIAN MCINTYRE - . WESTINGHOUSE JEFF SCHMUCKER CARBOLINE COMPANY l
GUS LAINAS . NRR/DE '
JACK STROSNIDER NRR/DE JAMES DAVIS NRR/DE/ECGB ROBERT ROTHMAN NRR/DE/ECGB GEORGE GEORGIEV NRR/DE/ECGB H.L.BRAMMER NRR/DE/ECGB l GARY HOLAHAN NRR/DSSA JIM LYONS NRR/DSSNSPSB ED THROM NRR/DSSA/SCSB RICHARD LOBEL NRR/DSSNSCSB BOB GRAMM NRR/DRCH/HQMB JUAN PERALTA NRR/DRCH/HQMB TED QUAY NRR/DRPM/PDST JERRY WILSON NRR/DRPM/PDST JOE SEBROSKY NRR/DRPM/PDST 1
1 Attachment 1 j
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PL 2T5C'=b P A"E f1' ~' L PROTCCTivE PL A ~ ~. (1) sc~ . v ' c v. s P Air s 7: as, ri rvaTrcs i 'rs apr rJrisn IN sLns::T ias 6.3.7.7.7.i .
Figure 6.3 8 Containment Recirculation Screen Plan Location Revision: 17 November 30,1997 6.3-88 W Westingh0Use
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Westingh0US8 6.3-89 November 30,1997 fa
Figura 1 - AP600 Crting Debris Settling e
This figure shows that the AP600 has significant margin to accomadate uncertainty in coating settling rates. This figure shows the sensitivity of coating settling to debris settling rates. The heavy solid line shows the AP600 design case, which includes a margin factor of 2.00 times the reference (Comanche Peak settling data). The light dashed lines represent sensitivity studies with greater margins. The margins applied were chosen to force the debris to settle out at the bottom of die screen (factor of 2.3), covering half of the screen (factor of 3.2) and covering 90% of the screen (factor of 4.7). The screen would still allow PXS operation with a factor of 4.7 margin applied to the Comanche Peak data. 'Ilie light solid line shows the Comanche Peak settling data. All of these cases assume the maximum RNS flow possible assuming one RNS ,
takes suction from one screen and is unthrottled (1600 gpm).
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AP600 Containment Coatings issues to be Addressed e Westinghouse has not provided a quantitative or experimental bases which demonstrate why failure of the containment coatings will not prevent functioning of the engineering safety features. Calculations are required to determine if failure of the coatings ws:1 result in blockage of strainers. The analysis must be reviewed by the NRC staff since there is uncertainty in the calculations. Even if Westinghouse were to perform a transport analysis, the staff is not likaly to accept it without additional experimental validation.
e Westinghouse provides some qualitative discussions on what it believes will occur upon failure of containment coatings (e.g., assumes only localized failure of coatings, assumes coating material will settle on the bottom of various compartments and will not get transported in sefNeient quantities - which are undefined - to the intake screens) but has not provided er/ Nidence of this mechanism besides engineering judgment.
e in addition to the staff's concems on debris transport to the containment sumps, the performance characteristics of the passive containment cooling system (PCS) are based on an experimental test progran) with the coating. No testing is known to exist with either degraded coatings or without con t;ngs. The justification for the mass and heat transfer correlations, the PCS fi!m .7.M;; and the water coverage model are all based on testing with the coating. In the Lage-Scale Test (LST), the coating exists on both the exterior and the interior surface of the vessel. Failure of the coating willimpact heat transfer, film formation and water coverage. Westinghouse has not provided any data or experimental evidence as to why deterioration of the containment coatings will not affect the design basis properties of the containment shell and the PCS performance e The evolutionary designs have effectively agreed to a safety-related coating program by committing to implement Reg Guide 1.54 to satisfy the requirements of Appendix B to 10 CFR Part 50. Westinghouse needs to demonstrate that protective coatings used in the AP600 are non-safety-related, and clearly substantiate the basis for its current exception
' (in SSAR Appendix 1A) to RG 1.54 and the endorsed ANSI standards (i.e., explain why the provisions of Appendix B to 10 CFR Part 50 and 10 CFR Part 21 do not apply to protective coatings in the AP600).
Attachment 3 i