Summary of 961231 & 970103 Telephone Conference Between J Winters of W,J Holmes & D Jackson of NRC Re Certain Unresolved Open Items Involving Std Safety Analysis Rept Section 9.5.1 & 9A| ML20133E677 |
| Person / Time |
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| Site: |
05200003 |
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| Issue date: |
01/08/1997 |
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| From: |
Diane Jackson
NRC (Affiliation Not Assigned) |
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| To: |
NRC |
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| References |
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| NUDOCS 9701130106 |
| Download: ML20133E677 (8) |
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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
_ _ __ . _ - . . ---~ - - - - - - - - - --
l . '
p F2 - M f2
%* UNITED STATES NUCLEAR REGULATORY COMMISSION f WASHINGTON, D.C. 20066-0001 i
January 8,1997 j k %* * * [
APPLICANT: Westinghouse Electric Corporation FACILITY: AP600 1
SUBJECT:
SUMARY OF TELEPHONE CONFERENCES TO DISCUSS WESTINGHOUSE AP600 l FIRE PROTECTION ANALYSIS OPEN ITEMS l
The subject telephone conferences were held on December 31, 1996, and Janu-ary 3, 1997, between Jim Winters of Westinghouse and Jeff Holmes and Diane Jackson of the Nuclear Regulatory Commission (NRC) staff. The purpose of the meeting was to discuss certain unresolved open items related to standard safety analysis report (SSAR) Section 9.5.1 and 9A in preparation for an upcoming meeting on January 7, 1997. The open item tracking system (0ITS) should be updated to reflect these telephone conferences.
OITS# 306 - Action Westinghou:e (a) Westinghouse is continuing to investigate the change to the passive containment cooling system (PCS) discussed at the November 19, 1996, meeting. The non-safety-related, high flow, firemain would be the initial water supply for fire protection, rather than the PCS tank. A manual valve would be available to supply water from the PCS. A COL action item would be added to instruct the operator to open the connec-tion valve.
(b) Westinghouse clarified for the staff the sefe shutdown evaluation demon-strated that safe shutdown can be achieved by utilizing safety related systems after a " worst case fire," that is the fire in an entire fire area that is the worst area. Westinghouse will revise the wording in SSAR 9A.2.7.1.
(c) The staff requested clarification on SSAR 9A.2.7.1, " Availability of Non-safety Related Systems," to include a list of fire areas how the safe shutdown evaluation considers the fire areas. Westinghouse pointed out the Emergency pesponse Guidelines instructs the operator to use the "available non-safety related equipment." The staff would like to know what equipment that would be given a fire in any given fire area.
Westinghouse stated that this was not required. The staff will discuss.
Action N (d) The staff expressed a concern regarding non-safety related cabling f affecting safety related cabling. Westinghouse clarified that no non- M O g safety related cabling was located in a IE cable tray outside of the U main control room. The staff expressed a specific concern that the emergency lighting for the main control room and the remote shut down panel should be independent. g I I l
730024 gg HLE CENTER COPY 9701130106 970108 PDR ADOCK 05200003 A PDR
a g
- l l
^
l January 8, 1997 l i
I OITS# 309 - Action Westinghouse
- I i (a) j On December 30, 1996, Westinghouse provided a draft markup (attached) of i the S3AR on the definition of the " zone of influence." It did not i address all of the staff concerns. It needs to clearly state that the term, " zone of influence" is only used inside containment. And inside i
containment, zone of influence is defined as a fire zone. Westinghouse should state, in the SSAR, fire areas that are not separated by fire ;
d barriers and how they use other fire protection or separation methods, '
such as distance. Westinghouse should also include a definition of fire area and fire barrier in the SSAR.
(b) Westinghouse is continuing to work on a description of fire zone separa- l tion for Appendix 9A, including a discussion of 3-hour fire barriers around main cable runs. Westinghouse will include a definition of fire area and fire barrier in the SSAR.
(c) Westinghouse is continuing work on the sketch of the automatic l depre surization system (ADS) module indicating the valve arrangement and structural steel thickness.
(d) Westinghouse is continuing work to review the SSAR description to ensure the use of 3-hour fire barriers that are non-combustible inside the containment.
OITS# 308 - Action Westinghouse The staff expressed a concern regarding the assurance of sufficient fire protection water designated in post-72 hour consumables. Westinghouse is continuing to work on this response.
OITS# 312 - Action Westinghouse Westinghouse will provide a description of the cabling routing inside of the containment.
OITS# 314 - Action Westinghouse Westinghouse will provide a written response with the justification why PCS water should be considered a dedicated source of water following an earth-quake.
OITS# 316 - Action NRC The staff has questions regarding this open item and will discuss them with Westinghouse at the upcoming meeting.
OITS# 317 - Closed This item is administrative 1y closed. The issue will be technically resolved under DSER 9.5.1.3-4 (0ITS# 1996).
- l 1
January 8, 1997 OITS# 319 - Action Westinghouse Westinghouse will revise the SSAR to indicate that the main control room and l the remote shutdown workstation are on different and physically separated cir-cuits. ,
1 OITS# 321 - Action NRC The staff has concerns ragarding the turbine building fire zones, specifically the areas that contain the air compressors and fire pumps. These concerns will be discussed at the upcoming meeting.
OITS# 322 - Action NRC The staff has concerns regarding this open item and would like to discuss these at the upcoming meeting.
OITS# 323 - Action Westinghouse The staff requested clarification of the design considerations for smoke control. Westinghouse is continuing working on this concern.
OITS# 1114 - Action Westinghouse Resolve related open items OITS# 1120 - Action Westinghouse Resolve OITS #321 OITS# 1122 - Action NRC Staff will discuss open. item at upcoming meeting.
OITS# 1124 - Ac'. ion NRC Staff will discuss concerns at upcoming meeting.
QJIS# 1919 - Resolved SSAR revision acceptable.
OITS# 1921 - Resolved SSAR revision acceptable.
OITS# 1996 - Action Westinghouse Westinghouse will revise SSAR 3.4.1 to address f A 'ag from the main control room to the remote shut down panel area.
- l January 8, 1997
- OITS# 3438 - Resolved Westinghouse response acceptable.
QllSf 3439 - Action Wcstinghouse
- Westinghouse will revise RAI response 280.10 (0ITS# 3439) i OITS# 3440 - Resolved Westinghouse response acceptable.
- OITS# 3442 - Action NRC OITS# 3443 - Action NRC 3 OITS# 3444'- Action NRC l OlTS# 3445 - Action HRC i OITS# 3446 - Action NRC OITS# 3447 -~ Action NRC OITS# 3448 - Action NRC OITS# 3456 - Action NRC OITS# 3457 - Action NRC OITS# 3458 - Action NRC OITS# 3459 - Action NRC OITS# 3460 - Action NRC original signed by
Diane T. Jackson, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003
Attachment:
As stated cc w/ attachment:
See next page DISTRIBUTION: See next page DOCUMENT NAME: A:SPL FP T. SUM (A AP600 DISK)
Ta receive e copy of this document,in3ceteh the bes: 'C' = Copy without ettechment/er. closure *E' = Copy wMh attachment / enclosure *N* = No copy 0FFICE PM:PDST:DRPM _ SPLB:DSSA, D:PDST:DRPM l 7 NAME DJackson:sg 1/v JLyons //sv'/m TRQuay -Th'6 l DATE 01/>/97 /> 01/ 7 /97 01/4 /97 l OFFICIAL RECORD COPY
1 l Westinghouse Electric Corporation Docket No.52-003 cc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross l Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42
, Nuclear and Advanced Technology Division Office of LWR Safety and Technology i
) Westinghouse Electric Corporation l d 19901 Germantown Road 1 P.O. Box 355 Germantown, MD 20874 l Pittsburgh, PA 15230 Mr. Ronald Simard, Director j Mr. B. A. McIntyre Advanced Reactor Program Advanced Plant Safety & Licensing Nuclear Energy Institute l
] Westinghouse Electric Corporation 1776 Eye Street, N.W.
Energy Systems Business Unit Suite 300 l
- Box 355 Washington, DC 20006-3706 '
j Pittsburgh, PA 15230 j Ms. Lynn Connor Mr. John C. Butler Doc-Search Associates
! Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 Energy Systems Business Unit Box 355 Mr. James E. Quinn, Projects Manager Pittsburgh, PA 15230 LMR and SBWR Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, M/C 165 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 & Mellott NE-50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. S. M. Modro 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 Thapson, Nuclear Engineer AP600 Certification NE-50 19901 Germantown Road Germantown, MD 20874
' ' '* 412 374 4837
,, DEC 30 '96 13:59 F R Of1 AP600 DESIGN CERT TO NRC p AM . 001 Westinghouse FAX COVER SHEET i
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I bEC 30 '96 13:59 FROM AP600 DESIGN CERT TO NRC PAGE.002
- TA. Fire Proeection Aanlysis A= "' y Systems -
5 Any damage which the fire is capable of causing is assumed to occur immediarely. No , .Jcredit is taken for proper operation of equipment or proper positioning of valves wh;ch are not protected from the effects of a postulated fue,
)
Zone of Influence V'p9 '^ p ., od '" p.,
O areas outsis i the I A postulated fire does not exceed the boundary of the fire area.
I main control room, remote shutdown workstation, and containment fire areas, a!! equipment I in any one fue area is assumed to be rendered inoperable by the fut and re-entry into the fire I
area for repairs and operator actions is assumed to be impossible. However; no credit is taken for complete fue damage in cases in which complete damage is benafwial and partial damag is not. Chases for electrical cables, piping or ducts that pass fthrough the fire area but are W y C, fuem I e separated from it by 3-hour fire barriers are inf I ,%outsMe ws the zone $,Jt.luence for that area Y -
1 Inside the containment fire ama, potential fire damage is evaluated by fire zo i equipment in any one fire zone is assumed to be randered inoperable by the fire unle I
fire protection analysis demonstrates otherwise. Class IE electrical cables that are lo I
or pass throu5 h the fire zone but are separated frun it by a 3-hour fire barner are outs I zone of influence for that frie zone.
Independence of Affected Mre Areas l
i Only systems, cea.yoscots, and circuits five of fire damage are credited for achievin l I
shutdown for a given fue. Systans, components, and circuits outside the zone of influence '
1 are considered free of fue damage if the effects of the fue do not prevent them from I performing their required safe shutdown functicas.
Event Assumptions l
Plast accidents and severe natural phenomena are not assumed to occur concurwntly wi post alated fire. Furthennore, a concurient single active cv %.est failure (ind fue) is not assumed.
Ottsite Power i
A loss of offsite power is assumed concurrent with the postulated fue only when the shutdown evaluation indicates the fire could initiate the loss of offsite power.
I I
Availability of Nonsafety Related Systems I ,
I Only safety-related components and systems are assumed to be availab e (This is more stringent than required by B'IP CMES 9.51.) Fire 1 shutdown functions.
i protection and smoke control systems are assurned to function as desig i mitigate the effects of the fue.
Revision: 8 Jane 19,1996 9A-5 y Westingh0Use
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