|
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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
, - .-.. . - .- . - -..-.- ...-- - - - . - - - - _ - _ - - . - - - - - - - . - - - . -
I
)62-003
{3 [f* "'%g\
) UNITED STATES l
, j o
,j
~f NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 8
{
k .... p January 3,1997 l
APPLICANT: Westinghouse Electric Corporation l PROJECT: AP600 i SU8 JECT: SupMARY OF MEETING TO DISCUSS AP600 APPLICATION OF WCOBRA/ TRAC FOR LONG TERM COOLING ANALYSES l
i The subject meeting was held on November 22, 1996, in the Nuclear Regulatory l Commission (NRC) Rockville, Maryland, offices between representatives of j Westinghouse and the NRC staff. A consultant to the Advisory Committee on
- Reactor Safeguards (Novak Zuber) was also present at the meeting. The purpose 1
- of the meeting was to discuss how the recently issued WCOBRA/ TRAC Oregon State i j University (OSU) Long Term Cooling Final Validation Report-(WCAP-14776) i addresses previous NRC staff concerns regarding the unique aspects of the 4
WCOBRA/ TRAC computer code application for AP600 long term cooling analyses.
Long term cooling calculations with WCOBRA/ TRAC are unique in that Westing-l house uses a " Window Mode" approach which represents the quasi-steady state !
j behavior of the AP600 at the most limiting, but discrete, times during long l term cooling transients.
f Highlights of the discussions include the following items: I i
Westinghouse reiterated that WCOBRA/ TRAC was chosen for long term i cooling (LTC) analyses because it was the most accurate, NRC approved, j low pressure code available.
l -
Westinghouse stated that while a continuous long term cooling analysis was possible with WCOBRA/ TRAC, it is not practical. The small time step i increments required by the code result in days of computer time even for l the relatively short 1000-second periods used for the window time periods.
Conservative boundary conditions such as core power, sump liquid level,
- and containment pressure are imposed on each window calculation. Other j initial window conditions that existed at the end of the design basis LOCA analyses (such as vessel water levels) are obtained from previous calculations using NOTRUMP or WCOBRA/ TRAC-LBLOCA. Westinghouse notes that WCOBRA/ TRAC - LTC calculations will converge to the same steady-
! state conditions from any reasonable values assumed for initial condi-
! tions. The WCOBRA/ TRAC - OSU Long Term Cooling Final Validation Report provides a sensitivity study showing that the long term cooling analysis is essentially independent from initial conditions and that the results j are basically driven by the boundary conditions.
Westinghouse cannot predict the oscillations observed at OSU with 3[f WCOBRA/ TRAC and did not perform any window calculations during the oscillation periods. Westinghouse believes that it understands the physics of the OSU oscillations and that the reasons the oscillations
\
OO NRC File CENTER M 97 970103 PDR ADOCK 05200003 A PDR
? ;
i !
January 3, 1997 f
are not a concern for the AP600. Westinghouse stated that discussions
- of these oscillations are provided in the OSU Test Analysis Report and '
the AP600 Scaling and PIRT Closure Report. l l <
i Westinghouse stated that the single most important challenge to long term cooling is the ability to achieve and maintain adequate steam *
- venting.
I The meeting was productive and helped alleviate some concerns the staff had 1 regarding the window appro:ch. However, the staff still expressed some uncer- ,
tainty about various aspects of the long term cooling analyses which are at i clearly explained in the documentation. These items are summarized below.
- -- How the GOTHIC code is relied upon to establish containment conditions ,
for the long term cooling boundary conditions, such as containment !
pressure and sump levels, and exactly how the thermal-hydraulics of the reactor coolant system have been decoupled from the containment analy-sis. In addition, it was unclear if the in-containment refueling water storage tank drain-down and switchover to the sump (recirculation) cooling mode was performed with NOTRUMP, WCOBRA/ TRAC, or GOTHIC.
Is the calculation of the best estimate containment pressure by GOTHIC conservative high or low? That is, were the calculational assumptions used in GOTHIC chosen to result in a higher than expected, containment pressure or lower than expected, containment pressure? j What assumptions were made for flooding of the normally non-flooded volumes in containment for determining the long term containment floodup level?
The staff felt that the key assumptions and their bases for the long term cooling analyses of the AP600 were not well documented. Westing-house stated that the revision to Chapter 15 of the standard safety analysis report should cover these concerns. The staff requested some kind of " executive summary" of how the long term cooling methodology and assumptions are utilized and justified for analyses of the AP600.
Westinghouse stated it would consider putting together a summary report but did not explicitly commit to submit such a report to the staff.
Westinghouse also addressed some of the SDSER open items. The staff stated that its review of the WCOBRA/ TRAC - OSU Long Term Cooling Final Validation Report had not reached a point where discussions or closeout of the SDSER
~ issues would be possible.
1 J
4 .
a Ganuary 3, 1997 4.
Attachment 1 is the list of meeting attendees. Attachment 2 is a copy of the presentation handouts with the proprietary material removed. Westinghouse stated that the proprietary material presented during the meeting is from the
, WCOBRA/ TRAC - OSU LTC Final Validation Report and that the proprietary affidavit for that report is applicable.
. original signed by:
William C. Huffman, Project Manager Standardization Project Directorate Division of Reactor Program Management Office Of Nuclear Reactor Regulation l Docket No.52-003 Attachments: As stated cc w/ attachments:
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- DOCUMENT NAME: A:ll-2LTC. SUM n *. . c.,y .* w. m . mac.= w m. wm c - copy e u.et.n.nu.new.w. r - copy wwi n.ct.n.no.now.w. r - No copy 0FFICE PM:PDST:DRPM l SC:DSSAf48XBl D:PDST;DRP)Wu / l NAME WHuffman:ia) W Alevi4M/\ TRQuay / / 'ted DATE 12/;)f96 12//u/96'l) 42/ /9A
0FFICIAL RECORD COPY
)
l 1
l I:
[ Westinghouse Electric Corporation Docket No.52-003
- I 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 j P.O. Box 355 Germantown, MD 20874
- Pittsburgh, PA 15230
[ Mr. Ronald Simard, Director Mr. B. A. McIntyre Advanced Reactor Program
- Advanced Plant Safety & Licensing Nuclear Energy Institute
- - Westinghouse Electric Corporation 1776 Eye Street, N.W.
l Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 i Ms. Lynn Connor
, Mr. John C. Butler Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 i Westinghouse Electric Corporation Cabin John, MD 20818
! Energy Systems Business Unit J Box 355 Mr. James E. Quinn, Projects Manager
! Pittsburgh, PA 15230 LMR and SBWR Programs j GE Nuclear Energy 1 Mr. M. D. Beaumont 175 Curtner Avenue, M/C 165 Nuclear and Advanced Technology Division San Jose, CA 95125 i Westinghouse Electric Corporation .
! One Montrose Matro Mr. Robert H. Buchholz i 11921 Rockville Pike GE Nuclear Energy j Suite 350 175 Curtner Avenue, MC-781 j Rockville, MD 20852 San Jose, CA 95125
- Mr. Sterling Franks Barton Z. Cowan, Esq.
j U.S. Department of Energy Eckert Seamans Cherin & Mellott 1 NE-50 600 Grant Street 42nd Floor
- 19901 Germantown Road Pittsburgh, PA 15219 j Germantown, MD 20874
- Mr. Ed Rodwell, Manager I Mr. S. M. Modro PWR Design Certification Nuclear Systems Analysis Technologies Electric Power Research Institute Lockheed Idaho Technologies Company 3412 Hillview Averoe '
Post Office Box 1625 Palo Alto, CA 94303 Idaho Falls, ID 83415 Mr. Charles Thompson, Nuclear Engineer l AP600 Certification '
NE-50 19901 Germantown Road Germantown, MD 20874 i
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- WESTINGHOUSE - NRC NEETING
' DN APPLICATION OF WCOBRA/ TRAC TO THE AP600
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LONG TERM COOLING ANALYSES 2
NOVEMBER 22, 1996
- MEETING ATTENDEES
, i HAME ORGANIZATION
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John Butler Westinghouse Larry Hochreiter Westinghouse Dan Garner Westinghouse i Lambros Lois NRC 2
Alan Levin NRC
- Farouk Eltawila NRC (Part Time) i Norm Lauben NRC Bill Huffman NRC Novak Zuber NRC Consultant i
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i Attachment I l,
AP600 Plant Long Term Cooling Calculations L. E. Hochreiter Nuclear Safety Analysis Westinghouse Electric Company R November 22,1996 3
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Westinghouse /NRC Meeting on AP600 Long Term Cooling November 22,1966 AGENDA
- 1. Introduction Westinghouse
- 2. WCOBRAfrRAC OSU LTC Validation Report Westinghouse
- 3. NRC Comments on Validation NRC
- 4. W SAR Analysis Method . Westinghouse
- 5. Conclusion / Actions All
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a mem-mum NRC REQUEST FOR ADDITIONAL INFORMATION i
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l Pro LTC LOCA Anahsis i Result M&E Releases NOTRUMP or WCOBRA/ TRAC
--+.
- ~WGOTHIC code Conditions at U IRWSTinitiation Ref
- WCAP- 14382 j
> , Pro-LTC Containment IWRST Draindown Pressure and Core Decay Standard Assur.wion Heat Boiloff *'*'**
Calculation M&E _
Condensate RetumGutters Releases ~
. . . . . . . ."'. . . . . . . . ' Containtnent 1
. Pressure. Surnp
- Mass and Energy Calculation Level /
Temperature Conditions , ,
l WCOBRA/ TRAC code. *nitiaS ~ ~ ~ ~ " 's/ " ~ " ~ ~
l Sump injoction Containment wig g Calculation calculation Ref: WCAP-12945, Volumes 15, and OSU LTC Validation Report J
RCS and Core conditions durin0 LTC Figure 440.554-1 Long Tenn Cooling Calculation Code Stream 1
440.554RI-4 Wm Westinghouse
4 AP600 LONG TERM COOLING SSAR CALCULATIONS WITH WCOBRA/ TRAC LONG TERM COOLING OF AP600 IS UNIQUE PASSIVE SAFETY-RELATED SYSTEMS PERFORM THE FUNCTION i OF ACTIVE SYSTEMS, QUASI-STEADY-STATE CONDITIONS EXIST IN THE RCS AND CONTAINMENT A SIMPLIFIED WCOBRA/ TRAC MODEL IS USED WCOBRA/ TRAC HAS AMPLE LOW PRESSURE, GRAVITY REFLOOD VALIDATION (CCTF, SCTE, FLECHT, FLECHT-SEASET, LOFT)
VESSEL CHANNELS USED FOR HOT LEGS, COLD LEGS TO BETmR CALCULATE THE FLOW REGIMES, AND PRESSURE DROPS OSU LONG TERM TEST RESULTS USED FOR VALIDATION CALCULATE AP600 PERFORMANCE AT MOST LIMITING, DISCRETE
. TIMES; USING WINDOW MODE APPROACH TO VERIFY CORE COOLING
METHODOLOGY TO PERFORM A WINDOW MODE ANALYSIS 1.
DETERMINE THE LIMITING PORTION OF THE LTC PHASE:
THAT IS MOST DEMANDING ON THE SAFETY SYSTEMS J 2.
SELECT INITIAL CONDITIONS FOR CALCULATION FROM PREVIOUS CALCULATIONS.
- 3. USE 1971 ANS + 20% DECAY HEAT TO MAXIMIZE STEAM GENERATION.
l MAXIMIZES " STEAM BINDING" EFFECT CHALLENGES RCS VENTING CAPABILITY MINIMIZES IRWST/ SUMP FLOW i
4.
PERFORM WINDOW MODE CALCULATION FOR ~ 1000 SECONDS UNTIL '
SYSTEM IS STEADY.
4 VEnIFY THAT THE CORE REMAINS COOLABLE VERIFY SYSTEM MASS BALANCE; IE, WHERE DOES THE SYSTEM !
FLOW GO. '
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"- 9 Oke.-6_.A4.L_%% m e t . a. A A=^5.-- L44-*~4*hb-*AN'Ei# '^4'AhM3**AM**'- -L"b'*4hN*4 mm A4_a A4 5 %.A.4 ,_4 44h-* 44L4W&___844.-__
o INITIAL CONDITIONS FOR WINDOW CALCULATION INITIAL CONDITIONS WHICH CAN BE ESTIMATED AND DO NOT '
DETERMINE THE QUASI-STEADY STATE OBTAINED PRIMARY CIRCUIT LIQUID LEVELS AND TEMPERATURE STEAM GENERATOR SECONDARY SIDE LIQUID LEVEI.S AND TEMPERATURE STRUCTURE TEMPERATURES WINDOW APPROACH ASSUMES THAT AN EQUIVALENT QUASI-STEADY STATE WILL BE REACHED FROM ANY REASONABLE VALUES FOR THESE INITIAL CONDITIONS AP600 CASES ARE ANALYZED USING INITIAL CONDITIONS FROM EARLIER NOTRUMP OR WCOBRA/ TRAC CALCULATIONS g N
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BOUNDARY CONDITIONS FOR WINDOW CALCULATION t
BOUNDARY CONDITIONS WHICH DETERMINE THE QUASI-STEADY STATE CORE POWER i
IRWST LIQUID LEVEL AND TEMPERATURE l
CMT LIQUID LEVEL AND TEMPERATURE SUMP LIQUID LEVEL AND TEMPERATURE !
CONTAINMENT PRESSURE t
THE IMPOSED BOUNDARY CONDITIONS WILL " FLUSH-OUT" THE l SELECTED INITIAL CONDITIONS AND THE SOLUTION WILL REACH A ,
QUASI-STEADY STATE
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i CRITERIA FOR ACHIEVING A QUASI-STEADY STATE !
KEY VARIABLES EFFECTIVELY ACHIEVE A STEADY STATE i
CORE LIQUID LEVEL DOWNCOMER LIQUID LEVEL UPPER PLENUM LIQUID LEVEL UPPER PLENUM PRESSURE DVI INJECTION RATE BREAK FLOW l -
ADS STAGE 4 FLOW QUASI-STEADY CONDITIONS HAVE BEEN SUCCESSFULLY DEMONSTRATED IN THE OSU WINDOW MODE VALIDATION f
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AP600 LONG-TERM COOLING CASES FOR SSAR REVISION 8 ANALYSIS BASES NO CREDIT FOR CONTAINMENT GUTTERS SINGLE FAILURE OF ONE FOURTH STAGE ADS VENT PATH APPENDIX K MODELING, INCLUDING DECAY HEAT MAXIMUM SUMP LINE DESIGN RESISTANCES ANALYSIS SELECTS TIME PERIODS AND CONDITIONS TilAT MINIMIZES SAFEIY INJECTION AND MAXIMIZES STEAM BINDING POSSIBILITIES 1T) CHALLENGE THE AP600 LIMITING CASES WILL BE PERFORMED - SUMP INJECTION DVI AND SMALL COLD LEG BREAK LOCA WINDOW MODEL CASES MODELING PER THE WC/T OSU FINAL VALIDATION REPORT CONTAINMENT CONDITIONS AS CALCULATED BY WGOTHIC CASES TO SHOW ADEQUATE CORE COOLING IN THE LONG TERM rowenstatmyt
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l AP600 SSAR LONG-TERM COOLING WINDOW MODE CASES CASE ' - DESIGN BASIS DOUBLE -ENDED DVI PIPE BREAK WINDOW INCLUDES THE LATE IRWST INJECTION PHASE AND THE SWITCHOVER INTO STABLE SUMP INJECTION !
REPRESENTS EARLIEST SWITCHOVER TO SUMP INJECTION AND, ;
THEREFORE, THE HIGHEST DECAY POWER FOR SUMP INJECTION CASE II - DOUBLE-ENDED DVI PIPE BREAK, RNS OPERATION' INITIALLY f i
RNS FAILURE ASSUMED AT THE TIME OF SUMP SWITCHOVER, AFTER IRWST HAS BEEN DISCHARGED RAPIDLY BY PUMPS ,
IN THIS WINDOW, SUMP INJECTION BEGINS EVEN EARLIER THAN IT '
DOES IN CASE I i
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AP600 SSAR LONG-TERM COOLING WINDOW MODE CASES (CONT'D)
CASE III - TWO-INCH COLD LEG BREAK AT SUM.P INJECTION INITIATION WINDOW INCLUDES THE LATE IRWST INJECTION PHASE AND THE SWITCHOVER INTO STABLE SUMP INJECTION REPRESENTATIVE OF SMALL BREAK LOCA SWITCHOVER TO INJECT FROM A NEAR-SATURATED SUMP CASE IV - TWO-INCH COLD LEG BREAK BEYOND 24 HOURS l LONG-TERM PASSIVE LEAKAGE INTO FORMERLY DRY COMPARTMENTS DIMINISHES SUMP LEVEL BELOW THE INITIAL FLOODUP VALUE havessisty
CONCLUSION I WINDOW MODE APPROACH HAS BEEN VERIFIED BY THE OSU/WCOBRATI'RAC VALIDATION EFFECT AP600 PLANT CALCULATIONS ARE SPECIFICALLY SELECTED: ;
USING CONSERVATIVE ASSUMPTIONS i
CHOOSING THE TIME PERIODS WHICH WILL CHALLENGE THE AP600 PASSIVE SAFETY SYSTEMS 4 RESULTS CONTINUE TO SHOW AMPLE CORE . COOLING, WITH MARGIN, AS SEEN IN OSU TESTS wistatwyr '