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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
lew 4 Gk p.u.m y . -t UNITED STATES
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NUCLEAR REGULATORY COMMISLION WASHINGTON D.C. 30eeH001
%4 August 19, 1997 APPLICANT: Westinghouse Electric Corporation PROJECT: AP600
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS OPERATIONAL ISSUES ASSOCIATED WITH THE AP600 MAIN CONTROL ROOM HABITABILITY SYSTEM The subject meeting was held on August 7,1997, at the Rockville, Maryland, offices of the Nuclear Regulatory Commission (NRC) between representatives of Westinghouse and the NRC staff. The purpose of the meeting was to discuss the AP600 Main Control Room (MCR) Habitability System operational parameters of air flow rates, CO, levels, temperature, and humidity needed to establish the personnel " habitability" of the design. The NRC staff stated at the beginning of the meeting that the MCR habitability system should provide a habitable '
operating environment as well as affording the control room operators protec- 'f tion from radiation exposure in accordance with GDC-19. In addition, the staff stated that it was not receptive to opening the control room doors and subjecting the operators to the conditions of the outside environment prior to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The MCR habitability system design should be capable of providing radiation protection and habitable conditions for the design basis time period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for up to eleven occupants.
Highlights from the meeting include the following items:
Westinghouse provided an update on its analyses related to steam infiltration into the auxiliary building from spent fuel pool boiling.
Bechtel has developed an analysis model which is being used to calculate the expected auxiliary building environment. Based on preliminary results, Westinghouse stated that some steam will penetrate areas of the aux building from the boiling spent fuel pool through room floor drains.
However, the temperature excursions are minimal and are withi' the environmental qualification of the equipment in the exposed rooms. In addition, Westinghouse will examine modifying the floor drains (putting in traps) to further mitigate any potential steam migratien. Westing-house noted that no path has been found which would permit steam from the spent fuel pool to migrate to the control room area via the aux building. Westinghouse also stated that the Bechtel model could also be used to predict humidity and radiation environments in rooms which were subjected to spent fuel pool boil-off steam.
Westinghouse stated that the design of the spent fuel pool area blow-out panel was being changed to open on temperature rather than pressure.
This design change was being implemented to assure that the blow-out panel would open when the spent fuel pool was boiling with very low heat loads which might be insufficient to generate pressures high enough to open the blow-out panel if it were pressure actuated.
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. - . . . . . . . . . _ , . _ , - . . , . _ . J
August 19, 1997 Westinghouse has obtained the official version of the ARCON96 code from Oak Ridge for determining atmospheric dispersion assessments (Chi /Qs) needed for main control room dose rate calculations. Some preliminary calculations indicate that the new results will not be more limiting than previous calculations (even when looking at different MCR orienta-tions at three representative sites).
The staff raised some issues involving disagreements between the staff and Westinghouse on assumptions used to calculate MCR dose.
-Specifically, the occupancy factor assumed by Westinghouse is-that the control room o>erators are inside the control room for no more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during tie first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of an accident and no more.than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per day thereafter during the entire period of an accident (30 days).
The staff wants Westinghouse to assume the operator is in the control room for the entire first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of an accident, followed by a 0.6 occupancy-factor for 1 to 4 days,- and 0.4 occupancy factor for the remaining period of an accident (up to 30 days . This is consistent with how MCR dose rate calculations have been c)alculated for both operating plants and for the evolutionary designs and the-standard review plan. The staff and Westinghouse can no longer ' agree to-disagree" on the. methodology used for dose rate calculations (which has been the historical practice). Based on recent understanding by the-staff on the licensing bases for a plant, it is no-longer sufficient for the staff to independently corroborate dose rate calculations. Instead, the staff must review the Westinghouse dose analysis methodology and
-evaluate its-acceptability since the Westinghouse methodology will become the-desifin basis for any future analyses (such as 10 CFR 50.59-
-changes). West'nghouse-believes this is a significant change to the
. approach taken to review the evolutionary reacter designs and will have a large impact in other areas of the AP600 design certification review.
The NRC staff took an action-to define the areas where there are currently differences between the staff and Westinghouse in performing
-dose calculations which must be reconciled before the final safety evaluation report (FSER) can be acceptably completed.
Westinghouse gava an update on its design efforts for improving the MCR habitability system operational characteristics Westinghouse believes it can make the design unsusceptible to a
-sintile active failure >..id, consequently, can take credit for both tra'ns of air. This would result-in a design based flow rate of 46 standard cubic feet per minute-assuming 11 persons for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ). (SCFM) total (4.2 SCFM per person i Westinghouse believes that it can demonstrate. acceptable temperature and humidity conditions by restricting the upper limit of the normal control room temperature range; taking credit for temperature reductions of the low moisture content compressed air as it expands from the bottles;- and refining the heat input and transfer calcula-tions..
August 19, 1997 Westinghouse stated that at a flow rate of 4.2 SCFM per person, the MCR CD, levels would not exceed 0.4 percent.
The NRC staff )rovided feedback to Westinghouse on what it expected from the MCR habita)ility system design. Specifically:
Westinghouse stated that it plans to modify the MCR habitability system design to take credit for both air bottle supply trains.
Westinghouse should thoroughly justify the basis for giving credit to both air bottle supply trains in terms of delivering air flow to the MCR (with the assumption of an active single failure). The staff is particularly concerned about any manual operator actions which may be necessary for mitigating an active single failure. In addition, Westinghouse should look at potential consequential single failure mechanisms such as ice blockage of an air line (due to expansion cooling effects).
The staff stated that although limiting the CO, to less than 0.5 percent was necessary for the design, it was not sufficient.
Westinghouse must also confirm that otlier air contaminants which are listed in MHRAE Standard 62 (1989) are also kept within limits or, if present, would not result in adverse effects on control room operator performance during the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> design basis period.
Analysis for these contaminants should consider MCR inleakage during the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> operational period, contaminants which may exist in the compressed air bottles and supplied to the MCR spaces, and contami- '
nants which may be reloksed from the control room environment (e.g.,
contaminants from equipment / hardware, MCR physical structures, personnel,etc).
Westinghouse did not necessarily have to limit the control room temperature to 85'F. It has to control both the temperature and humidity to give an effective temperature of 85*. A temperature-humidity curve from MIL-STD-1472C was provided to Westinghouse as an exam)1e of temperature-humidity conditions that would be acceptable to tie staff.
The staff's minimum value for a MCR habitability system fresh air replenishment flow rate is normally at least 15 SCFM per MCR occu-pant to ensure that appropriate human factors habitable environmen-
- tal conditions are maintained in the control room. This is consis-tent with the standards in both NUREG-0700 and ASHRAE. However, because this flow rate is related to comfort level more than perfor-mance level, the staff would be willing to accept air flow rates lower than 15 SCFM and as low as 5 SCFM per occupant for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (absolute minimum accounting for all uncertainties). Westinghouse should make every effort to maximize the design fresh air flow rate to establish ample margin above the 5 SCFM minimum acceptable limit.
' Westinghouse will need to provide rigorous justification, to be documented in the AP600 SSAR, as to why any deviation from the 15 SCFM standard is necescary and acceptable.
August 19, 1997 Westinghouse stated that the post-72 hour connections for establishing MCR ha6itability with use of external air conditioners and fans had been eliminated based on using ancillary fans and opening the contrcl room doors after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The staff stated that it would like to see the external connection capability re-established for the design.
The issue of tracer gas testing the MCR operating envelop was discussed.
The staff believes that this test is still necessary on a periodic basis. Westinghouse disagreed. The staff noted tiiat Westinghouse still needs to formally address this issue in response to the staff's post-72 hour comment letter of June 5,1997.
Attached is the list of meeting attendees.
A draft of this meeting summary was provided to Westinghouse to allow them the opportunity to ensure that the representation of comments and discussion was accurate, original signed by:
William C. Huffman, Project Manager Standardization Project Directorate Division of Reactor Program Management Office Of Nuclear Reactor Regulation Docket No.52-003
Attachment:
As stated cc w/att: See next page DISTRIBUTION:
-Docket File PP5i R/F SCollins/FMiraglia, 0-12 G18 PUBLIC- Rlic.nerman, 0-12 G18 TQuay TKenyon BHuffman JSebrosky DJackson WDean, 0-5 E23 ACRS (11)
JMoore. 0-15 B18 HWalker, 0-8 D1 JRaval. 0-8 D1 JLee, 0-10 D4 REmch, 0-10 D4 TMarsh, 0-8 01 SRubin, 0-9 HIS JBongarra, 0-9 HIS DEckenrode, 0-9 H15 Chiller, 0-10 D4 GHolahan, 0-8 E2 LSpessard, 0-9 E4 A:MCR-DOCUMENT NAME:n...iv....p,.eihi.
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F D:PDST:DRPM NAME WCHuffmanus %' SRutg d / C f. TMarsh 4F//C REmch # # TRQuay T74 DATE 08/N/97 08//f/17 /
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WESTINGHOUSE - NRC MEETING CN AP600 MAIN CONTROL ROOM HABITABILTY SYSTEM MEETING ATTENDEES AUGUST 7, 1997 NAME ORGANIZATION RON VIJUK WESTINGHOUSE BRIAN MCINTYRE WESTINCHOUSE MIKE CORLETTI WESTINGHOUSE HAROLD WALKER NRC JANAK RAVAL NRC TED QUAY NRC JAY LEE' NRC )
RICH EMCH NRC TAD MARSH NRC STU RUBIN NRC JIM BONGARRA NRC DICK ECKENRODE NRC BILL HUFFMAN NRC CHUCK THOMPSON DOE Attachment
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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. McIntyr. 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 Ms. Lynn Connor Ms. Cindy L. Haag Doc-Search Associates y 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 Curtaer Avenue, MC-754 Nuclear and Advanced Technology Division San Jos<t, 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 Thompson, Nuclear Engineer AP600 Certification NE-50 19901 Germantown Road Germantown, MD 20374
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