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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 ML20210Q1221997-08-22022 August 1997 Summary of 970807 Meeting W/Westinghouse Re Proposed Containment Spray Design for AP600 Design.List of Attendees & Slides 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 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 ML20210Q1221997-08-22022 August 1997 Summary of 970807 Meeting W/Westinghouse Re Proposed Containment Spray Design for AP600 Design.List of Attendees & Slides 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 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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ihr l e l r,i ", ,
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y lt UNITED STATES C' J Jt j
- ! f NUCLEAR REGULATORY COMMISSION WAaHINGToN, D.o. 30eeHopt k * . . . . /j}
i August 22, 1997 APPLICANT: Westinghouse Electric Corporation FACILITY: AP600
SUBJECT:
SUMMARY
OF AUGUST 7, 1997, MEETING TO DISCUSS THE CONTAINMENT SPRAY DESIGN FOR THE AP600 1 I
On August 7,1997, representatives of the Nuclear Regulatory Commission (NRC) and Westinghouse met to discuss the proposed containment s) ray design for the AP600 design. Attachment 1 is a list of attendees. Attac1 ment 2 are the slides presented by Westinghouse.
Westinghouse described the containment spray design it proposed to incorporate into the AP600 design in response to the Commission's Staff Requirements Memorandum On SECY-97-044 dated June 30, 1997. In addition, Westinghouse discussed the impact of the containment spray system on aerosols in the :
containment atmosphere following a severe accident, i At the close of the meeting, the following action items were agreed to:
- 1. Westinghouse agreed to document key assumptions used in its su) porting analysis in its evaluation of the containment design. Westinglouse needs to demonstrate that its design is adequate to address the Commission's concerns.
- 2. Westinghouse agreed to reconsider whether selection of a failed-closed valve (V701) is appropriate based on its expected impact on reliability.
- 3. Westinghouse agreed to address the use of the spray system in WCAP-13914,
" Framework for AP600 Severe Accident Management Guidance."
- 4. The staff agreed to reconsider its concern that Westinghouse has not considered the effect of an inadvertent spray actuation on the maximum external pressure analysis due to the features of the proposed design.
- 5. Westinghouse agreed to consider a mechanism for assuring that the loca-tions of the locally-operated valves in the fire / spray system in the as-built design will be accessible during a severe accident.
- 6. Westinghouse agreed to address how the spray would affect the containment isolation mode and hydrogen combustion modeling in the Level 2 probablistic risk assessment for the AP600.
- 7. Westinghouse agreed to evaluate the effectiveness of the passive contain- x ment cooling system during a spray, G
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- M82aggg ggggge A PDR NRC RLE CENTER CD a
i August 22, 1997
- 8. The staff stated that it would determine the acceptability of Westinghouse's position that availability controls need not be imposed on the spray system.
Westinghouse indicated that the design of the containment spray rystem would be documented in Revision 16 to the standard safety analysis re) ort. A draft of this meeting summary was provided to Westinghouse to allow tiem the opportu'iity to comment on the summary prior to issuance, original signed by:
Thomas J. Kenyon, 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 plSTRIBUT10ff:
l Docket File PDST R/F SCollins/fHiraglia, 0-12 G18 PUBLIC RZimmerman, 0-12 G18 SWeiss 10uay TKenyon BHuffman DTJackson JSebrosky WDean, 0-5 E23 ACRS (11) JHoore, 0-15 B18 JNWilson DScaletti REmch, 0-10 D4 JLee, 0-10 D4 JKudrick 0-8 H7 MSnodderly, 0-8 H7 RPalla, 0-8 H7 KCampe, 0-8 E2 DOCUMENT NAME: A:CS.SUH
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DA1E 08/1L[97 08/'JN97 l I
OfflCIAL RECORD COPY
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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 Eye Street, N.W.
Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 Hs. Lynn Connor Hs. 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. H. D. Beaumont 175 Curtner Avenue, MC-754 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro Mr. Robert H. Buchholz 11921 Rockville Pike 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 & Hellott NE-50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Hr. Ed Rodwell, Manager Mr. S. H. Hodro PWR Design Certification Nuclear Systems Analysis Technologies Electric Power Research Institute Lockheed Idaho Technologies Company 3412 Hillview Avenue Post Office Box 1625 Palo Alto, CA 94303 Idaho falls, ID 83415 Mr. Charles Thompson, Nuclear Engineer AP600 Certification NE-50 19901 Germantown Road Germantown. HD 20874 4
)
NRC/ WESTINGHOUSE AP600 CONTAINMENT SPRAY MEETING PARTICIPANTS AUGUST 7, 1997 H&ME ORGANIZATION J. WILSON NRR/NRC/PDST C. THOMPSON DOE B. HUFFMAN NRR/NRC/PDST D. SCALETTI NRR/NRC/PDST R. EMCH NRR/NRC/PERB J. LEE NRR/NRC/PERB T. QUAY NRR/NRC/PDST J. KUDRICK NRR/NRC/SCSB M. SN00DERLY NRR/NRC/SCSB R. PALLA NRR/NRC/SCSB M. CORLETTI WESTINGHOUSE B. MCINTYRE WESTINGHOUSE R. V!JVCK WESTINGHOUSE J. GROVER WESTINGHOUSE T. KENYON NRR/NRC/PDST K. CAMPE NRR/NRC/SASG 4
i l
Att:chment 1
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AP600 Containment S rav s l4 Michael M. Corletti a August 7,1997 5
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Westinghouse 1 i
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SECY-97-044 -
"iii e NRC Commissioners Approved the NRC Staff Position e AP600 Shall include Containment Spray Severe Accident Management Not Required to be Safety-Related
- Westinghouse 2 1
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Containment Spray System
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l e Functional Requirements Provide a Containment Spray System to
. Enhance Severe Accident Management l
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! e Design Goals
! Minimize Changes to Plant 1 Minimize Adverse System Interactions
-Design Basis Events
-Flooding Westinghouse 3
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' 5 AP600 Containment Spray o System Design Two Containment Spray Ring-Headers
-Connected to Fire Protection System Header Inside Containment e Air-operated Isolation Valve e Normally Open ManualIsolation Valve
-44 Nozzles at Elev 235 ft.
-24 Nozzles at Elev 250'
-1033 gpm at 20 psig Containment Pressure
~82% Containment Coverage
~
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7 Westinghouse
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Containment Spray System ' i e System Operation Remote Operation From the MCR
-Severe Accident Management Guidelines e Core Exit Thermocouples > 1200oF e Emergency Procedures (AFR-C.1) Transitions to SAMG
-Continuous Operation (~3 hrs) e Maintain Containment Water Level (<109 ft.)
Westinghouse 8
~
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Containment Spray System '
e System Operation i
Manual Alignment of Two Valves '
- Auxiliary Building '
-Layout of Valve Room Modified to Minimize Radiation Exposure l e Estimate of Operator Exposure - 250 mR l e Applicable NUREG-0737 Limits-5000 mR l !
.l Westinghouse 9 i
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l Containment Spray Interactions "
- e Effect on Design Basis Evaluations ~
j Boron Dilution
-Severe accidents only l -Water in core is voided; loss of core geometry
-Boron dilution not a concern l
Containment pH Concentration
-Small effect on long-term pH e 300,000 gallons spray decreases 30 day pH ~0.14 j
-No significant increase in iodine re-evolution Westinghouse 10
~ w e - . - -
o Containment Spray Interactions
~
e Effect on Design Basis Evaluations (cont.) !
Inadvertent Containment Spray
-Number of random independent failures not
! credible e Requires misalignment of two manual valves (one lock-closed containment isolation valve) e Remote manual actuation of containment spray isolation valve
-Only used in severe accidents e Clear and unambiguous indication provided to operators
- Additional manual isolation valve provided for
, shutdown Westinghouse 11 1
it ':
Containment Spray Interactions " "
e Other Considerations Maximum Containment Spray
~300,000 gallons
- Containment water level ~109' elevation e Post-accidentlevelinstruments
-Containment air mixing patterns are maintained Westinghouse 12
~
e &
Containment Spray Testing =
e Initial Test Program
- Preoperational Testing
-Fire Protection System
-Pump Head / Flow Characteristics
- Air Testing of Spray Nozzles I oITAACS ;
-Inspection for Spray Nozzles i
Westinghouse 13
[
Containment Spray e Future Submittals SSAR - Revision 16
~
ITAACS - Revision 4 WCAP-13914, Revision 1
" Framework for AP600 Severe Accident Management Guidelines" Westinghouse 14
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Impact of Containment Spray on Aerosols In the Containment Atmosphere Following a Severe Accident August 7,1997 l
t Jim Grover Containment and Radiological Analysis Westinghouse Electric Corp.
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ASSUMPTIONS REGARDING SPRAY REMOVAL OF AEROSOLS Severe accident with source term as calculated by NRC using the MELCOR code No credit is taken for passive aerosol removal processes
- (sedimentation, diffusiophoresis, and thermophoresis) while
! sprays are in operation i
! The passive removal processes have a combined value of 0.4 hr-I (NRC value)
The rate of mixing between the sprayed and unsprayed regions is twice the unsprayed volume per hour (consistent with SRP) l Duration of sprays is three hours
~
t
( _ _ -
I Effect of Containment Spray on Aerosol lodine
, (Using MELCOR Generated Source Term and NRC Passive Removal Coefficient) m
,8 100 a.
m o 90 ^ -
E .
< 80 - - - - -
\
i c
e E 70 -
c.
B 60 - - - - - - - - - --- - - - - - - - - - -- - - - - - ---- - -
e o
O' ~
C 50 %w/*4~..., . .
\ ,
.E 40 o .
.9 30 E
- - --- - [r - - - - - - -
!i4-- - - - ^ .... ' ~. . . . 't ~
a .,
o o
20 -- --
ia c.,
s -
...~.....~-- ......,
,, tt o '
tu ...~.,,~~..-.-..
c 10 ,-- --m~--- .
-h n~
.'~.. c.,.'k
. . u . . ,., : . :.a : : z ., ,,: - -: -
g 0 ........ ,.........,.........,.........,.........,.........,.........,.........
n.
r 0 1 2 3 4 5 6 7 8 Time (hours)
- u. u. s,r.1 s,r.7 -
Removal Spray at 1.0 kr. at 2.5 hrs.
.............. ......- - . - fy . -
b.N RELEASES OF AEROSOL I-131 ACTIVITY Over the first 24 hours of the accident the release ofI-131 due to containment leakage is:
- 50,600 curies if there is no removal other than decay
- 6000 curies if onfy passive removal processes are credited 1300 curies if sprays are actuated at one hour
- 2400 curies if sprays are actuated at 2.5 hours l
l
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CONCLUSIONS l
The AP600 containment spray design provides an effective means for reducing airborne particulates resulting from a severe accident i}}