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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20216J0681999-09-29029 September 1999 Forwards Rev 3 of AP600 Design Control Document, Incorporating Documentation Changes Resulting from Final Review Performed to Check Consistency of Implementation of Approved Design Change Proposals.With Summary of Changes ML20207G5411999-06-0808 June 1999 Discusses Request Made by Westinghouse on 981109 That Proprietary WCAP-14252,Rev 1,be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20195D5201999-06-0404 June 1999 Discusses Westinghouse Request That Change Pages Submitted on 980921 to WCAP-14292 Be Withheld from Public Disclosure. Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20196G2431999-05-21021 May 1999 Informs That USNRC Has Published in Fr Encl Notice of Proposed Rulemaking Re AP600 Design Certification Rule. Rulemaking Allows Applicants or Licensees to Construct AP600 Std Plant Design by Referencing Design Certification Rule ML20206G5411999-05-0505 May 1999 Forwards Draft Environ Assessment Re Proposed Certification of AP600 Std Plant Design.Environ Assessment Will Be Used as Basis for NRC Finding of No Significant Environ Impact Resulting from Certification of AP600 Design ML20205J3351999-04-0707 April 1999 Informs That USNRC Staff Has Completed Review of Rev 2 of AP600 Design Control Document,Verified That All of Changes in Rev 2 Are Acceptable & Determined That AP600 Dcd,Rev 2, Can Now Be Used in Proposed Design Certification Rule NSD-NRC-99-5827, Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document1999-03-31031 March 1999 Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document ML20205D3051999-03-25025 March 1999 Requests Amend to 920626 Application for Design Certification of AP600,including AP600 Ssar & AP600 Dcd,To Reflect Sale of CBS Commercial Nuclear Business to W ML20203C5481999-02-10010 February 1999 Forwards Rev 1 to AP600 Design Control Document (DCD) for Docket File.Dcd Provides Reference Basis for AP600 Design Certification ML20199H8671999-01-20020 January 1999 Forwards Comments on AP600 Design Control Document,Submitted by Westinghouse ML20199B1121999-01-0707 January 1999 Advises That Info Contained in NSRA-APSL-92-0268 & Containing Presentation Matl Used in 921209-10 Meeting,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20198B4601998-12-14014 December 1998 Discusses W Ltr NTD-NRC-95-4556,dtd 950918,provided as Status Rept on Proprietary Matl Submitted to NRC to Support AP600 Design Review Effort.Proprietary Info in Encl Have Been Removed from AP600 Docket File & Being Returned ML20197G3501998-11-30030 November 1998 Forwards AP600 Design Control Document, Vols 1-12 for Docket File.Submittal Closes Confirmatory Items 1.5-1 & 1.5-2 from Sept 1998 Final SER Re Certification of AP600 Std Design ML20195E9331998-11-0909 November 1998 Requests That Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept, Vols I- Iv,Be Withheld (Ref 10CFR2.790) NSD-NRC-98-5806, Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.7901998-11-0909 November 1998 Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.790 ML20155G9021998-11-0303 November 1998 Advises That Info Contained in 981012 ltr,NSD-NRC-98-5795, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) & Section 103(b) of AEA of 1954,as Amended ML20155G9271998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design.Staff Completed Review of Design & Issued Final Design Approval & FSER on 980903.Without Encl ML20155G7591998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design,Per Discussion at Sept 1997 Meeting.Staff Completed & Issued Final Design Approval of FSER on 980903.Without Encl NSD-NRC-98-5795, Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar1998-10-12012 October 1998 Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar ML20154A4091998-09-29029 September 1998 Advises That Certain Info Contained in Westinghouse Ltr NTD-NRC-95-4506,dtd 950713,submitting WCAP-14425,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Figure 3-1 Will Be Placed Into Public Record ML20153G2521998-09-25025 September 1998 Advises That Proprietary Matl Discovered by NRC in NSD-NRC-97-4966 & Proprietary Matl Noted by W in NSD-NRC-98-5772 Will Be Withhheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20153C1001998-09-15015 September 1998 Advises That Matls Re AP600 Notrump Final Validation Rept, WCAP-14807,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended NSD-NRC-98-5788, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided1998-09-15015 September 1998 Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided ML20151X4381998-09-15015 September 1998 Informs That Staff Has Decided to Accept Claim That Info in WCAP-14135,Rev 1 Is Proprietary & Will Be Withheld from Public Disclosure,Per W 980821 & 26 Ltrs ML20151X4041998-09-11011 September 1998 Discusses Revised Tier 2 Info for AP600 Design.Staff Revised Decision on Whether Fire Protection Should Expire at First Full Power Encl ML20151V1711998-09-0808 September 1998 Advises That Info Re Westinghouse AP600 Std Safety Analysis Rept Through Rev 4 & PRA Through Rev 5 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Disposition of Ssar & PRA Proprietary Info Encl ML20151V2231998-09-0808 September 1998 Informs That NRC Determined That WCAP-14132 Encl in Westinghouse Ltr NTD-NRC-94-4244,dtd 940729 & Marked as Proprietary,Will Be Withheld from Public Disclosure,Per to 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20151S9181998-09-0303 September 1998 Advises That Info Marked as Proprietary Re Westinghouse AP600 Design Ltrs Concerning Pxs Scaling & Pirt Closure Rept WCAP-14727,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20239A1481998-09-0303 September 1998 Forwards Notice of Issuance of Final Design Approval & Final SER for AP600.FDA Allows AP600 Design to Be Referenced in Application for Construction Permit or Operating License Under 10CFR50 or Application for Combined License ML20239A3111998-09-0303 September 1998 Forwards Final SER Which Summarizes Staff Safety Review of AP600 Design Against Requirements of Subpart B of 10CF5R52 & Delineates Scope of Technical Details Considered in Evaluating Proposed Design ML20151V8521998-09-0101 September 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse NSD-NRC-98-5781, Informs That W Determined That AP600 FSER Contains No Proprietary Info1998-09-0101 September 1998 Informs That W Determined That AP600 FSER Contains No Proprietary Info ML20151V2201998-08-31031 August 1998 Informs That EPRI Documents, GOTHIC Containment Analysis Package Qualification Rept, GOTHIC Containment Analysis Qualification Manual, & Listed Documents Dtd Sept 1993 Will Be Withheld from Public Disclosure ML20151V8431998-08-31031 August 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse ML20238F3241998-08-31031 August 1998 Advises That AP600 RAI Responses Encl in Westinghouse Ltrs NTD-NRC-95-4598,dtd 951117,as Modified by NSD-NRC-98-5776, Dtd 980826,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) ML20238F5991998-08-31031 August 1998 Refers to W 980821 Revised Response to Insp Rept 99900404/97-01 That Contained All Substantive Info Provided w/DCP/NRC-1074 Ltr.Nrc Will Destroy DCP/NRC-1074,as Requested NSD-NRC-98-5783, Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys1998-08-28028 August 1998 Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys NSD-NRC-98-5782, Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'1998-08-28028 August 1998 Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.' NSD-NRC-98-5778, Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized1998-08-27027 August 1998 Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized ML20237E4421998-08-27027 August 1998 Advises That Info Contained in Ltr DCP/NRC-0985,dtd 970821, Sought to Be Withheld,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended NSD-NRC-98-5777, Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-141381998-08-26026 August 1998 Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-14138 NSD-NRC-98-5776, Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld1998-08-26026 August 1998 Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld ML20237E0731998-08-26026 August 1998 Advises That Info in WCAP-14812,revs 1 & 2, Accident Spec & Phenomena Evaluation for AP600 PCS, Will Be Withheld from Public Disclosure ML20238F8031998-08-26026 August 1998 Requests That Proprietary W Revised Response to NRC Ltrs Re Requests for Withholding Info,Be Withheld from Public Disclosure IAW 10CFR2.790 NSD-NRC-98-5774, Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open It1998-08-24024 August 1998 Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open Item NSD-NRC-98-5773, Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W1998-08-21021 August 1998 Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W ML20237E7991998-08-21021 August 1998 Forwards non-proprietary Results of AP600 Design Assurance Review (Dar) That Was Commitment in W Response to NRC Insp Rept 99900404/97-02.Info Should Assist in Closing Nonconformances & Unresolved Item Identified in Insp Rept NSD-NRC-98-5771, Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W1998-08-21021 August 1998 Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W NSD-NRC-98-5769, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of1998-08-21021 August 1998 Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of Ssar NSD-NRC-98-5772, Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.7901998-08-21021 August 1998 Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.790 1999-09-29
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20207G5411999-06-0808 June 1999 Discusses Request Made by Westinghouse on 981109 That Proprietary WCAP-14252,Rev 1,be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20195D5201999-06-0404 June 1999 Discusses Westinghouse Request That Change Pages Submitted on 980921 to WCAP-14292 Be Withheld from Public Disclosure. Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20196G2431999-05-21021 May 1999 Informs That USNRC Has Published in Fr Encl Notice of Proposed Rulemaking Re AP600 Design Certification Rule. Rulemaking Allows Applicants or Licensees to Construct AP600 Std Plant Design by Referencing Design Certification Rule ML20206G5411999-05-0505 May 1999 Forwards Draft Environ Assessment Re Proposed Certification of AP600 Std Plant Design.Environ Assessment Will Be Used as Basis for NRC Finding of No Significant Environ Impact Resulting from Certification of AP600 Design ML20205J3351999-04-0707 April 1999 Informs That USNRC Staff Has Completed Review of Rev 2 of AP600 Design Control Document,Verified That All of Changes in Rev 2 Are Acceptable & Determined That AP600 Dcd,Rev 2, Can Now Be Used in Proposed Design Certification Rule ML20199H8671999-01-20020 January 1999 Forwards Comments on AP600 Design Control Document,Submitted by Westinghouse ML20199B1121999-01-0707 January 1999 Advises That Info Contained in NSRA-APSL-92-0268 & Containing Presentation Matl Used in 921209-10 Meeting,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20198B4601998-12-14014 December 1998 Discusses W Ltr NTD-NRC-95-4556,dtd 950918,provided as Status Rept on Proprietary Matl Submitted to NRC to Support AP600 Design Review Effort.Proprietary Info in Encl Have Been Removed from AP600 Docket File & Being Returned ML20155G9021998-11-0303 November 1998 Advises That Info Contained in 981012 ltr,NSD-NRC-98-5795, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) & Section 103(b) of AEA of 1954,as Amended ML20155G7591998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design,Per Discussion at Sept 1997 Meeting.Staff Completed & Issued Final Design Approval of FSER on 980903.Without Encl ML20155G9271998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design.Staff Completed Review of Design & Issued Final Design Approval & FSER on 980903.Without Encl ML20154A4091998-09-29029 September 1998 Advises That Certain Info Contained in Westinghouse Ltr NTD-NRC-95-4506,dtd 950713,submitting WCAP-14425,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Figure 3-1 Will Be Placed Into Public Record ML20153G2521998-09-25025 September 1998 Advises That Proprietary Matl Discovered by NRC in NSD-NRC-97-4966 & Proprietary Matl Noted by W in NSD-NRC-98-5772 Will Be Withhheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20151X4381998-09-15015 September 1998 Informs That Staff Has Decided to Accept Claim That Info in WCAP-14135,Rev 1 Is Proprietary & Will Be Withheld from Public Disclosure,Per W 980821 & 26 Ltrs ML20153C1001998-09-15015 September 1998 Advises That Matls Re AP600 Notrump Final Validation Rept, WCAP-14807,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20151X4041998-09-11011 September 1998 Discusses Revised Tier 2 Info for AP600 Design.Staff Revised Decision on Whether Fire Protection Should Expire at First Full Power Encl ML20151V1711998-09-0808 September 1998 Advises That Info Re Westinghouse AP600 Std Safety Analysis Rept Through Rev 4 & PRA Through Rev 5 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Disposition of Ssar & PRA Proprietary Info Encl ML20151V2231998-09-0808 September 1998 Informs That NRC Determined That WCAP-14132 Encl in Westinghouse Ltr NTD-NRC-94-4244,dtd 940729 & Marked as Proprietary,Will Be Withheld from Public Disclosure,Per to 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20151S9181998-09-0303 September 1998 Advises That Info Marked as Proprietary Re Westinghouse AP600 Design Ltrs Concerning Pxs Scaling & Pirt Closure Rept WCAP-14727,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20239A3111998-09-0303 September 1998 Forwards Final SER Which Summarizes Staff Safety Review of AP600 Design Against Requirements of Subpart B of 10CF5R52 & Delineates Scope of Technical Details Considered in Evaluating Proposed Design ML20239A1481998-09-0303 September 1998 Forwards Notice of Issuance of Final Design Approval & Final SER for AP600.FDA Allows AP600 Design to Be Referenced in Application for Construction Permit or Operating License Under 10CFR50 or Application for Combined License ML20151V8521998-09-0101 September 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse ML20151V2201998-08-31031 August 1998 Informs That EPRI Documents, GOTHIC Containment Analysis Package Qualification Rept, GOTHIC Containment Analysis Qualification Manual, & Listed Documents Dtd Sept 1993 Will Be Withheld from Public Disclosure ML20151V8431998-08-31031 August 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse ML20238F5991998-08-31031 August 1998 Refers to W 980821 Revised Response to Insp Rept 99900404/97-01 That Contained All Substantive Info Provided w/DCP/NRC-1074 Ltr.Nrc Will Destroy DCP/NRC-1074,as Requested ML20238F3241998-08-31031 August 1998 Advises That AP600 RAI Responses Encl in Westinghouse Ltrs NTD-NRC-95-4598,dtd 951117,as Modified by NSD-NRC-98-5776, Dtd 980826,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) ML20237E4421998-08-27027 August 1998 Advises That Info Contained in Ltr DCP/NRC-0985,dtd 970821, Sought to Be Withheld,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20237E0731998-08-26026 August 1998 Advises That Info in WCAP-14812,revs 1 & 2, Accident Spec & Phenomena Evaluation for AP600 PCS, Will Be Withheld from Public Disclosure ML20237C4801998-08-20020 August 1998 Informs That Staff Will Withhold from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended, Presentation Matl from 970212-14 ACRS Meeting Encl in W Ltr NSD-NRC-98-5744 Dtd 980803,until Policy Matter,Clarified ML20237D4391998-08-18018 August 1998 Confirms Phone Conversation Between NRC & W Re Submittal of Final Portions of Documentation Necessary to Complete Review & Issue Final SER & Final Design Approval for AP600 ML20236V6671998-07-30030 July 1998 Advises That Info Contained in WCAP-14601,rev 2,submitted in Westinghouse Ltr NSD-NRC-98-5712,dtd 980616 & Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20236V8621998-07-30030 July 1998 Informs That Proprietary Info Encl in Westinghouse Ltr NSD-NRC-98-5736,dtd 980713 Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20236U7811998-07-29029 July 1998 Advises That WCAP-14270,rev 1, AP600 LP Integral Sys Test Facility Scaling Rept, Encl in Ltr NSD-NRC-98-5718,dtd 980619 & Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20236U7831998-07-29029 July 1998 Informs That Certain Info in AP600 Ssar,If Proposed for Change That Refs AP600 Std Design,Will Require Prior NRC Approval Before Proposed Change Can Be Implemented.Tier 2* Info for AP600 Design & Staff Decision Encl ML20236U8131998-07-29029 July 1998 Advises That WCAP-14471,rev 0, Steam Condensation Events at Osu AP600 Facility Submitted in Ltr NSD-NRC-96-4661,dtd 960306 & Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20236V0511998-07-29029 July 1998 Informs That AP600 Boron Dilution Transient Analysis Encl in Westinghouse Ltrs NSD-NRC-96-4792,dtd 960808 & NSD-NRC-98-5739,dtd 980720 & Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790 ML20236V0411998-07-28028 July 1998 Discusses Return of Proprietary Matl to Westinghouse Docketed Under AP600 Design Review.Proprietary Documents Listed in Encl 1 Removed from AP600 File & Returned for Disposition or Retention ML20236T3101998-07-22022 July 1998 Discusses W 941031 Submittal by Ltr (NTD-NRC-94-4330) of AP600 Notrump Core Makeup Tank Preliminary Validation Rept & Requests That Info Be Withheld from Public Disclosure. Determined Info Proprietary & Will Be Withheld from Public ML20236T4091998-07-22022 July 1998 Informs That Info Related to Wgothic lumped-parameter & Distributed Parameter Nodalization of AP600 & Wgothic Heat Sink & Flow Path Description Including Areas,Thickness & Evaluations Will Be Withheld,Per 10CFR2.790(b)(5) & 103(b) ML20236T1691998-07-22022 July 1998 Advises That Proprietary Matl Encl in NSD-NRC-96-4700,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)5) & Section 103(b) of AEA of 1954,as Amended ML20236T1361998-07-22022 July 1998 Advises That Info Contained in TRs WCAP-12945-P-A & WCAP-14747,respectively Submitted in Ltr NTD-NRC-95-4406, Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEC of 1954,as Amended ML20236T0591998-07-22022 July 1998 Informs That Staff Plans to Return NSD-NRC-96-4762, NSD-NRC-96-4763,NSD-NRC-96-4790,... Transmittals to Westinghouse W/O Proprietary Determination,Due to Info Being Provided in Documents Submitted at Later Date ML20236S9841998-07-22022 July 1998 Informs That Staff Plans to Return NSD-NRC-94-4246, NSD-NRC-94-4327 & NSD-NRC-94-4318 Transmittals to Westinghouse W/O Proprietarty Determination,Due to Info Being Provided in Documents Submitted at Later Date ML20236S9621998-07-22022 July 1998 Advises That Info in NSD-NRC-97-5424 on AP600 Passive Containment Cooling Sys Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20236S9321998-07-22022 July 1998 Advises That Info in on AP600 Large Scale Test Facility Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20236S9131998-07-22022 July 1998 Informs That WCAP-14776 (Rev 2) Encl in Westinghouse Ltr NSD-NRC-97-5202,dtd 970620 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1601998-07-22022 July 1998 Informs That Encl Table,Associated W/Westinghouse AP600 Ltrs,Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1511998-07-22022 July 1998 Informs That Matl Encl in NTD-NRC-94-4215 & NTD-NRC-95-4436, Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1431998-07-22022 July 1998 Informs That Encl Table Associated W/Westinghouse AP600 Design Ltrs Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1321998-07-22022 July 1998 Informs That Matls Documented in Encl Table,Associated W/Westinghouse AP600 WCAPs Submitted in Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended 1999-06-08
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March 4,1997 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
AP600 PAS $1VE CONTAINMENT COOLING SYSTEM (PCS) AND WG0THIC COMPUTER CODE REVIEW
Dear Mr. Liparulo:
There are three key reports related to-the AP600 PCS and WG0THIC computer code that are needed to support the Nuclear ~ Regulatory Commission (NRC) staff's licensing review of the PCS and the acceptability of the WG0THIC computer program for the performance of the DBA analyses. The three reports are i WCAP-14783 (scaling), WCAP-14812.(PIRT), and WCAP-14407 (WG0THIC Application to AP600). The staff has performed reviews and provided comments and requests for additional information.on preliminary and draft versions of these reports.
These reports must be consistcnt'in' scope, content,.&nd terminology, and l provide sufficient technical detail to adequately summarize issues. Because there has been difficulty in reaching closure on a' number of issues associated I with WG0THIC, two meetings have been scheduled for March 5 and 6, 1997, to l discuss the closure path for this review. j In order to facilitate your preparation for the.Marci, 5 and 6, 1997, and i future meetings on the WG0THIC computer code, we are providing staff comments '
on the three key reports, WCAP-14783 (scaling) in Enclosure 1, WCAP-14812 (PIRT) in Enclosure 2, and WCAP-14407 (WG0THIC Application to AP600).
If you have any questions regarding this matter, you can contact Diane Jackson ~
at (301) 415-8548.
1 Sincerely, i
gg g {gg QQ% original signed by:
Theodore R. Quay, Director Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 fj '
Enclosures:
)I 1 As Stated cc w/a,ulasures:
See next page DOCUMENT NAME: A:PCSCLOSE.LET T2 somehse a sepy of this document,inacote in the teen: *C" = Copy without ettschment/ enclosure 'E" = Copy with attachment / enclosure 'St* = No copy 0FFICE PM:PDST:DRPM D:PDST:DRPM l l l l NAME DTJackson y t TRQuay 'lN)
DATE M/.4/97 T) 3 / 4 /97
~~ NIAL RECORD COPY 9703100174 970304 PDR ADOCK 05200003 E PDR j
1 1 Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600
{
- cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Programs l
Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 Eye Street, N.W.
P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706
{ Ms. Cindy L. Haag Ms. Lynn Connor
. Advanced Plant Safety & Licensing Doc-Search Associates l Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager LMR and SBWR Programs Mr. M. D. Beaumont GE Nuclear Energy Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 Westinghouse Electric Corporation San Jose, CA 95125 One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz Suite 350 GE Nuclear Energy Rockville, MD 20852 175 Curtner Avenue, MC-781 San Jose, CA 95125 Mr. Sterling Franks U.S. Department of Energy Barton Z. Cowan, Esq.
NE-50 Eckert Seamans Cherin & Mellott 19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear Systems Analysis Technologies PWR Design Certification Lockheed Idaho Technologies Company Electric Power Research Institute Post Office Box 1625 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303 Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 19901 Germantown Road 19901 Germantown Road Germantown, MD 20874 Germantown, MD 20874 I
l Comments on WCAP-14783 The following are the staff's recommendations for the final scaling report:
. The scaling study, which is expected to be submitted in late-February or early-March 1997, must be sufficiently detailed and complete so that it demonstrates the following:
The MGOTHIC code is applicable at the scale of the AP600, consistent i with the requirements of 10 CFR 52.47(2)(1)(A)(1)-(3). This should be a a
stated object' e of the scaling analysis.
Calculated values of r-groups support the PIRT rankings given in WCAP-14811/14812; values (mass, volume, area, etc.) used to evaluate the r-groups are consistent between the scaling report (WCAP-14783), the PIRT report (WCAP-14811/14812) and the DBA EM model in Section 4 of WCAP-14407.
Sufficient information is included to allow independent verification of the scaling equations and the calculated values of r-groups.
The draft scaling report submitted by letter NSD-NRC-96-4790, d'ated July 8, 1996, "Retransmittal: Scaling Analysis for AP600 Containment Pressure During Design Basis Accidents," (except as noted in discussion items previ-ously provideri to Westinghouse) contains sufficient detail regarding the derivation c; the scaling equations. The final report needs to contain the same level of detail. Due to the need for revisions of some equations, i verification of numerical values for r-groups was not performed. When the :
scaling report is submitted, it must include numerical values of input parameters, so that the calculation of r-group numerical values can be ,
verified.
The scaling study must include the numerical values of r-groups for the AP600, as well as for relevant scaled test facilities, and sufficient justification for the applicability of the WG0THIC models at the AP600 scale. The justifi-cation for application of MGOTHIC to AP600 should be based on similitude and show that the range of test data supporting the WG0THIC models includes the range for AP600 application.
I Enclosure 1
1
~
Comments on WCAP-14811/14812 WCAP-14811, " Accident Specification and Phenomena Evaluation for AP600 '
I Containment Cooling System," Revision 0, December 1996, was submitted to the staff by Westinghouse letter NSD-NRC-96-4921, dated December 19, 1996, as a proprietary report. Westinghouse later determined that this report did not contain any proprietary information and resubmitted it as non-proprietary, as i WCAP-14812 by Westinghouse letter NSD-NRC-97-4971, dated February 3, 1997. l Westinghouse stated that the report content did not change. The following are '
the staff's recommendations for WCAP-14812, " Accident Specification and ,
Phenomena Evaluation for AP600 Passive Containment Cooling System": ,
The staff believes that WCAP-14812 should serve as the closure vehicle. When i finalized, the WCAP should provide the specific information concerning, as '
appropriate, (1) how scaling (WCAP-14783) supports the rank for each PIRT phenomena or parameter, (2) how testing and separate effects experiments support the rank for each PIRT phenomena or parameter, (3) what are the first principles and what type of engineering judgement provide the basis to support the rank for each PIRT phenomena or parameter, and (4) how the WG0THIC DBA EM i (WCAP-14407) addresses each phenomena or parameter. l The present content of Section 4.4, " Ranking of Phenomena Liste'd in the PIRT",
is not sufficiently detailed to complete the technical review. The content
- needs to be revised and expanded to include technical justification for the rankings.
With regard to the use of scaling as a basis for establishing PIRT rankings, general statements such as the following did not establish an adequate technical basis:
" Scaling shows that the mass and energy releases from the break source are the driving forces for the containment response for both LOCA and .
MSLB events, ......, therefore these parameters were all ranked High." t "At 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> energy scaling indicates that the steel is a small heat .
source." (Note: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is not used as a time phase in WCAP-14811/ i 14812, it has been replaced by "Long Term".)
In each case where information from the scaling study is used as the basis for i establishing a PIRT rank, the specific r-groups involved in the justification and their numerical values must be cited, as was done in the February 12, 1996, draft PIRT report (letter NSD-NRC-96-4643, " Accident Specification and Phenomena Evaluation for AP600 Passive Containment Cooling System"). ,
A general reference to a test report or dcta analysis report without specifi-cally identifying the applicable information, as is done in the present report, is unacceptable for a technical basis. Where test data or test data analysis information is used as the basis for a PIRT ranking, the test case (s) and/or specific data analysis which supports the argument must be cited and summarized. An explanation of how the data or data analysis supports the ranking must be included. t Enclosure 2
. l 4
1 Examples of adequate closure statements would contain the following informa-i 1
tion: 1
- 1) For the scaling analysis: The scaling report, in Section X.Y "(Para-meter) Pi Group Values", shows that r for the (phenomena or para-
- meter) group has a value of x.xx whicb'isupport (or confirms) a (high, medium or low) rank.
- 2) For test results: (a) In the Large Scale Test (LST) test xxx.y, which is representative of (LOCA or MSLB), measurements of (parameter) shows (or confirms) that (phenomena or parameter) is ranked as (high, medium or low). (b) In WCAP-nnnnn Section X.Y "(Parameter)," data from (experiments a, b, c, etc) for (dimensionless number or physical parameter) are shown to cover the range of (dimensionless number or physical parameter) for the AP600.
- 3) For first principles: If the perfect gas law is assumed then it can be shown that the (phenomena or parameter) should be ranked (high, medium o: low). (Provide or reference any detailed calculation which were performed with the assumption.)
'4) For engineering judgement: Discuss the field of expertise and related l process, such as heat transfer or mass transfer as applied to similar i situations but not necessarily containment or nuclear power plants.
- 5) For DBA EM modeling: To account for the (high, medium or low) ranking of (phenomena or parameter), (a) the input value for (parameter) is set to a value of (value) as shown in Section 4.Y of WCAP-14407, or (b) (parameter) is conservatively accounted by (reducing, increasing, omitting) as discussed in Section 4.Y of WCAP-14407.
- 6) For WG0THIC sensitivity analyses: To confirm the ranking, a sensitivity analyses was performed and is provided in Section X.Y of WCAP-14407 which shows that (reducing, increasing, omitting) results is a conserva-tive (or bounding) analysis.
1
I. .
I
~
- Comments on WCAP-14407 i*
The following are the staff's recommendations for WCAP-14407, "WG0THIC
! Application to AP600":
i
! Section 2 of WCAP-14407 is not consistent with the PIRT in WCAP-14811/14812, 4
and the scaling study in WCAP-14783. These reports need to be consistent in
- terminology, organization of_ phenomena, and PIRT rankings.
- In Section 4, modeling assumptions and input values or parameters which are i related to the PIRT are not clearly identified. For example
- (a) To account
! for mixing which is ranked as high, the break location is placed high in the above deck region for the MSLB. This conservatively addresses the mixing i issue. (b) Mass transfer is ranked high and a value of x.xx is used as a '
multiplier on the mass transfer coefficient to conservative bound the avail-able experimental data as shown in Section X.Y of WCAP-nnnnn.
- In addition, the following calculational issues should be addressed (note that f some of these issues have been previously identified as RAIs).
{ 1) For each section of WCAP-14407, please identify all computational results
! which have been obtained through the strict application of the AP600 DBA
{ EM specified in Section 4. If results were obtained using models i different from the AP600 EM, identify each of the model differences. A
- justification for the use of the alternate model and an evaluation of the
! impact on the calculational results needs to be provided. If there is a
- concern that the difference could impact the current calculational l results, additional studies with the DBA EM should be performed to reach closure.
- 2) For the DBA-LOCA, a comparison of results from SATAN and WCOBRA/ TRAC
, computer code computations for break mass flow and energy rates, and the rates used as inputs for the AP600 containment. analysis needs to be provided.
- 3) Provide a sensitivity study which evaluates the containment pressure response of increasing the steel Jacket-to-air gap thicknesses up to 0.125 inches. This study should cover the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Relevant construction data to justify the use of values less than 0.125 inches for the steel jacket-to-air gap thicknesses needs to be provided. (Current value is 0.005 inches.)
- 4) Justify the selected constant values for the quantities:
a) frictional length - 1 ft; b) forward loss coefficient - 1.5; and c) reverse loss coefficient - 1.5, for below operating deck compartments for DBA-LOCA for the:
a) blowdown phase (0 to ~30 sec);
Enclosure 3
l
~
t b) transition phase (30 to ~1500 sec); and c) long-term (1500 see to ~24 hours).
Also, justify the values for the MSLB.
- 5) Justify the selected constant values for the quantities:
a) frictional length - 1 ft (except of outer quarter annuli);
b) forward loss coefficient = 0; and c) reverse loss coefficient - 0, for above operating deck compartments for DBA-LOCA for the:
a) blowdown phase (0 to ~30 sec);
b) transition phase (30 to ~1500 sec); and c) long-term (1500 see to ~24 hours).
Also, show that the same values hold for the MSLB.
I
- 6) For DBA-LOCA, provide superpositions of temperature histories over the total time span of interest for:
a) break compartment; b) equivalent compartment in opposite SG-compartments; '
c) midway in affected SG-compartment; d) top of affected SG-compartment; e) affected quarter inner dome volume; and f) affected quarter outer dome volume. ;
- 7) For DBA-LOCA, provide superpositions of steam concentrations over the l total time span of interest for: )
a) break compartment; b) equivalent compartment in opposite steam generator-compartments; c) midway in affected SG-compartment; d) top of affected SG-compartment; e) affected quarter inner dome volume; and j affected quarter outer dome volume.
- 8) For DBR-LOCA and the relevant affected dome quarter, provide superposi-tions sf temperature histories for all relevant quantities of a clime (e.g. condensate, inside steel surface, outside steel surface, film temperature, air temperature) for:
a) top position; b) upper cylindrical part; and c) lower cylindrical part.
- 9) Provide the information listed under (8) for the opposite quarter.
- 10) Show axial temperature distributions of the most important clime element stacks for relevant instances in time (30 sec, 90 sec, 1500 sec, etc.).
- 11) Provide axial atmospheric temperature distributions in the center of the AP600 containment over the height of the control cylindrical room, respective quarter inner and outer dome compartments for relevant d
instances in time (30 sec, 90 sec, 1500 sec. etc.).
- 12) Provide the transient liquid level histories for the below operating deck compartments.
- 13) Provide the transient histories of energy transferred into:
a) heat sinks below operating deck; b) heat sinks above operating; i
c) to containment atmosphere; d) over steel shell; e) to PCS coolant;
} f) rising air flow;
, g) to baffle; and h) shield building.
- 14) Show transient histories of accumulated condensate in below-operating l deck compartments.
- 15) Show transient histories of accumulated condensate above the operating deck.
4
- 16) Show superpositions of hydrogen concentrations in the break compartment
] and upper most dome region over the total time of interest.
- 17) Show comparisons of temperatures, steam concentrations, " velocities" in volumes at the same height of the affected and unaffected SG, which show
- global circulation patterns over the total time of interest.
The status of the revision to Section 9 of WCAP-14407 is uncertain. The current discussion on mixing and stratification is based on arguments which seems to apply to a distributed-parameter type model where momentum is treated. There are concerns with the information being used to support the lumped-parameter type model for licensing.
Because of the unique importance of mixing and stratification issues to the analysis of the MSLB event, information regarding potential steam line break positions and related containment response should be provided.
- 18) Identify any differences between the MG0THIC AP600 DBA EM and the MSLB model which has been used for bounding computations. Provide information about the heat sink assumptions used for the Core Makeup Tanks (CMT)-
positioned MSLB calculations.
l
!* . i l
i
- I l
I 19) Provide computational results, and comparisons, from the WG0THIC AP600 l l DBA EM for MSLB at two representative break positions (top of the steam generator and vicinity of operating deck) for:
- a) containment pressure;
! b) axial temperature distribution inside containment; i
{ c) axial steam concentration distribution; d) representative temperatures along major flow (s) path below operating deck; and !
- e) representative steam concentrations along major flow (s) path
- below operating deck. l i 20) Justify the assumption that high Froude number steam release jets of l short duration mix the atmosphere in the regions above and below the jet '
i source elevation. It could be helpful to provide comparisons between j computational results of distributed-parameter and lumped-parameter
- network WGOTHIC calculations which demonstrate that the lumped parameter
- treatment of jet and plume characteristics is conservative.with regard to i the predicted containment pressure history. Compare these calculations i i to LST test 222.4 and the LST test results which span the Froude number '
l range experimentally examined. Show that the lumped parameter network t model has : conservative bias as stated in Section 9 of WCAP-14407.
l 21) The LST data examined covers a very limited range of Froude numbers to characterize the potential AP600 behavior. Provide evidence that the
.i same bias holds for Froude numbers expected in the AP600, which are by ,
two orders higher and by two orders lower. Provide experimental and/or computational evidence for the behavior of very high and very low Froude number releases and associated mixing characteristics.
- 22) Show the MGOTHIC' predicted entrainment as a function of time for the :
complete range of Froude numbers covering the AP600 MSLB-conditions. l Show results for the time period required for a highly energetic steam '
jet to reach the dome apex. Compare experimental data to WG0THIC calculated entrainment rates for momentum driven jets and buoyancy-driven plumes in order to demonstrate under what conditions mixing is most effective.
- 23) Provide information on how " numerical mixing in lumped-parameter net-works" contributes to the bias or counteracts a conservative bias.
- 24) The relatively small mass flow rate into compartments below the operating deck may be an artifact of the lumped-parameter approach and insufficient axial nodalization of the compartments below the operating deck. Provide LST experimental data for the mass f'ows entering the below-operating deck compartments as a function of time for the highest and lowest MSLB elevations above the operating deck. Compare these values to MG0THIC computed results.
- ~
{-
3 l
- 25) It could be helpful to provide comparisons between a distributed- '
parameter and a lumped-parameter network WGOTHIC computation which demonstrates that the lumped-parameter network calculations are always bounding for any break location, elevation, and discharge orientation (e.g., CMT-room, low positioned break and high positioned break of sterm pipe, vertical or horizontal discharge). ]
- 26) Provideinfpraation,orareforence,whichshowsthataMSLB-breaksize of 1.388 ft at 30 percent power is bounding under all circumstances and list all parameter changes which were examined to reach this conclusion. ,
1
- 27) Show the effect which the asymmetric MSLB-location has on: )
l a) the containment pressure history; l b) temperature distribution above the operating deck, c) heat sink utilization; and d) energy ree. oval at the steel outside surface over its axial height.
Provide these results for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period for all three break elevatic..s. ,
- 28) Show that the selected bounding approach also meets the bounding require-ments for determining conservative temperatures.
The following concerns need to be addressed for the LOCA: !
- 29) Describe the treatment of the break liquid phase in the WG0THIC model for !
AP600. Demonstrate that this model is conservative with regard to I containment pressure, mass of condensate collected in the in-containment refueling water storage tank (IRWST), the sumps, the dead end compart-ments, and the predicted condensate at the inside surface of the steel shell.
- 30) Show the effects of the release of hydrogen (Ref: WCAP-14811/14812) on heat sinks and PCS cooling in the presence of non-condensable gases and demonstrate the conservatism of the model chosen for the WG0THIC AP600 DBA EM. Present figures which show the following:
a) axial steam concentration distribution; b) axial air concentration distribution; c) axial hydrogen concentration distribution; and d) axial distribution of condensate at inside steel shell surface over the height of the quarter outer dome nodes.
- 31) Demonstrate the validity of the MGOTHIC treatment of buoyancy forces for the lumped-parameter network AP600 DBA EM and show what time periods during the LOCA and MSLB events these forces dominate.
1 4
- 32) Provide information how the selection of control volumes in the specific i
containment regions benefitted from the mixing considerations presented in Section 9.3.1.
Provide information how jet momentum considerations can affect the 33) i nodalization scheme chosen for the lumped-parameter network AP600 DBA EM.
) Lumped-parameter models completely dissipates momentum in each control l
volume.
- 34) Show how CMT-specific entrainment considerations are accounted for in a
. lumped-parameter model, which has no compartment specific phenomeno-
- logical models for jet and plume phenomena.
l 35) Provide comparisons between data and computational results from the
! WG0THIC AP600 DBA EM which demonstrate that the lumped-parameter network
! model correctly predicts large-scale circulations throughout the contain-ment. Consider that circulation may be affected by increasing liquid levels in the compartments below operating deck.
- 36) Show how stratification effects are superimposed on the large-scale l circulation pattern and compare this result with experimental data.
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