Letter Sequence Response to RAI |
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CAC:MF9307, Addition of New Tech Spec on RCS Boron Limits and Revisions to Tech Spec 3.3.1 to Address Rwfs (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
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MONTHYEARML17053B3932017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses Project stage: Request ML17054C2262017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WCAP-18083-NP, Rev 0, Westinghouse Revised Thermal Design Procedure Uncertainty Calculations. Project stage: Request ML17054C2292017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Responses to NRC RAIs on August 2013 Methodology Transition LAR Submittal Project stage: Response to RAI ML17054C2272017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Alternative Source Term, Rev 1 Project stage: Request ML17151A9972017-03-0909 March 2017 Wolf Creek Revision 30 to Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment, and Systems Project stage: Request WO 17-0026, Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses2017-03-22022 March 2017 Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Project stage: Request ML17100A2662017-04-18018 April 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Transition to Westinghouse Core Design and Safety Analyses Project stage: Acceptance Review ET 17-0011, Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Transition to Westinghouse Core Design and Safety Analyses2017-05-0404 May 2017 Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Transition to Westinghouse Core Design and Safety Analyses Project stage: Request ML17132A3632017-05-15015 May 2017 Acceptance of Requested Licensing Action License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses in Addition to Adopting of Alternative Source Term Project stage: Acceptance Review ML17136A3592017-05-22022 May 2017 Request for Withholding Information from Public Disclosure, 11/14/2016(CAW-16-4499), Affidavit Executed by James A. Gresham, Westinghouse Electric Company LLC Enclosure I of the Letter Dated 01/17/2017 Project stage: Withholding Request Acceptance ML17137A2862017-05-22022 May 2017 Request for Withholding Information from Public Disclosure, 11/14/16 (CAW-16-4500) Affidavit Executed by James A. Gresham, Westinghouse Electric Company LLC for Enclosure VI to the Letter Dated 1/17/17 Project stage: Withholding Request Acceptance ML17166A0382017-06-14014 June 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: RAI ET 17-0016, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses2017-07-13013 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Project stage: Response to RAI ML17265A0142017-09-21021 September 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Project stage: RAI ML17291A7102017-10-17017 October 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: RAI ET 17-0024, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-10-18018 October 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: Response to RAI ML17297B7972017-10-31031 October 2017 Request for Withholding Information from Public Disclosure (CAC No. MF9307; EPID L 2017-LLA-0211) Project stage: Withholding Request Acceptance ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: Response to RAI ML17331A1782017-12-0404 December 2017 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternate Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) Project stage: RAI WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ...2018-01-15015 January 2018 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ... Project stage: Response to RAI ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement L-2018-077, Schedule for Re-Analysis of Turkey Point Licensing Basis Analyses Affected by PAD5 Implementation2018-03-27027 March 2018 Schedule for Re-Analysis of Turkey Point Licensing Basis Analyses Affected by PAD5 Implementation Project stage: Request ML18114A1162018-04-19019 April 2018 SAP-18-34, Supplemental 30 Day Responses to NRC Request for Additional Information Regarding Wolf Creek Generating Station Transition to Westinghouse Safety Analysis and Alternate Source Term Methodologies. Project stage: Supplement ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement ML18115A3522018-05-0303 May 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated April 16, 2018 Supplemental 30 Day Responses to NRC RAI WCGS Transition to Westinghouse Safety AST Methodolgies Project stage: RAI ML18107A7562018-05-0303 May 2018 Regulatory Audit Summary License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term (CAC MF9307; EPID L-2017-LLA-0211) Project stage: Other ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement ML18183A5832018-07-23023 July 2018 Request for Withholding Information from Public Disclosure - 6/18/18 Affidavit Executed by Edmond J. Mercier, Westinghouse Electric Company Adoption of AST Amendment Request(Cac No. MF9307; EPID L-2017-LLA-0211) Project stage: Withholding Request Acceptance WO 18-0034, Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-08-0909 August 2018 Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement ML18270A0942018-10-0404 October 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Methodology for Selected Accident and Transient Analyses Project stage: RAI ML18332A1772018-10-25025 October 2018 Email Slides for 10/30 Public Meeting Project stage: Request ML18313A2252018-10-25025 October 2018 Westinghouse Affidavit CAW-18-4828 - Application for Withholding Proprietary Information from Public Disclosure Project stage: Request ML18299A0492018-10-30030 October 2018 Accident Analyses Methodology Transition LAR Public Meeting Project stage: Meeting ML18304A1052018-11-0505 November 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses and Alternative Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) Project stage: RAI WO 18-0047, Timeline for Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Timeline for Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Response to RAI WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Request ML18313A2542018-11-16016 November 2018 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation Regarding License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses for Wolf Creek Generating Station Project stage: Meeting ML18327A1342018-11-30030 November 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated October 25, 2018, Executed by Mr. Paul A. Russ, Westinghouse (CAC No. MF9307; EPID L-2017-LLA-0211) Project stage: Withholding Request Acceptance ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement ML18360A0342018-12-21021 December 2018 NRR E-mail Capture - Review Schedule for Wolf Creek Generating Station License Amend Request (LAR) for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: Other ML19070A1162019-03-0505 March 2019 Westinghouse, Responses to NRC Request for Additional Information Documented in ADAMS Accession No. ML 18270A094 on the Core Design and Safety Analyses Methodology Transition Program Project stage: Response to RAI ML19070A1392019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. Project stage: Request ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. Project stage: Response to RAI ML19099A1772019-04-16016 April 2019 Request for Withholding Information from Public Disclosure, 2/13/19 Affidavit Executed by Stephen Rigby, Westinghouse Electric Company LLC RAI Response Related to Adoption of Alternative Source Term (CAC MF9307; EPID L-2017-LLA-0211) Project stage: RAI ML19100A1222019-05-31031 May 2019 Issuance of Amendment No. 221 License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: Approval 2018-10-25
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Category:Response to Request for Additional Information (RAI)
MONTHYEARET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ML21168A1102021-06-0707 June 2021 4, Response to Request for Additional Information (RAI) ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ML19092A0932019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report. Responses to NRC Questions 005.1 Through 031.20 ML19070A1162019-03-0505 March 2019 Westinghouse, Responses to NRC Request for Additional Information Documented in ADAMS Accession No. ML 18270A094 on the Core Design and Safety Analyses Methodology Transition Program ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18331A2562018-11-19019 November 2018 Operating Corporation (Wcnoc), Unit 1 - Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Revision to the Emergency Plan ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ML18114A1162018-04-19019 April 2018 SAP-18-34, Supplemental 30 Day Responses to NRC Request for Additional Information Regarding Wolf Creek Generating Station Transition to Westinghouse Safety Analysis and Alternate Source Term Methodologies. ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ...2018-01-15015 January 2018 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ... ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ET 17-0024, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-10-18018 October 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ET 17-0016, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses2017-07-13013 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses ML17171A2332017-06-12012 June 2017 Response to Request for FLEX Audit Documentation ET 17-0011, Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Transition to Westinghouse Core Design and Safety Analyses2017-05-0404 May 2017 Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Transition to Westinghouse Core Design and Safety Analyses WO 17-0042, Operating Corporation Supplement to RAI Response Regarding Adopting New EAL Scheme2017-04-26026 April 2017 Operating Corporation Supplement to RAI Response Regarding Adopting New EAL Scheme ML17123A2022017-04-26026 April 2017 Enclosure to WO 17-0042 - WCNOC EAL Technical Basis Document WO 17-0013, Response to Request for Additional Information Regarding License Amendment Request for Adopting Revised Emergency Action Level Scheme2017-03-16016 March 2017 Response to Request for Additional Information Regarding License Amendment Request for Adopting Revised Emergency Action Level Scheme ET 17-0003, Operating Corporation'S Compliance Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and Final Integrated Plan2017-01-19019 January 2017 Operating Corporation'S Compliance Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and Final Integrated Plan ML17054C2292017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Responses to NRC RAIs on August 2013 Methodology Transition LAR Submittal ET 16-0036, Response to Request for Additional Information Regarding 10 CFR 50.55a Requests 13R-14 and 13R-152016-12-12012 December 2016 Response to Request for Additional Information Regarding 10 CFR 50.55a Requests 13R-14 and 13R-15 ET 16-0034, Operating Corporation - Response to Request for Additional Information Regarding 10 CFR 50.55a Request I3R-132016-11-30030 November 2016 Operating Corporation - Response to Request for Additional Information Regarding 10 CFR 50.55a Request I3R-13 ET 16-0031, Response to Request for Additional Information Related to Relief Request Number 14R-03, Request for Relief from Paragraph-3200(b) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds2016-11-0404 November 2016 Response to Request for Additional Information Related to Relief Request Number 14R-03, Request for Relief from Paragraph-3200(b) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds ET 16-0024, Response to NRC Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2016-11-0202 November 2016 Response to NRC Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ET 16-0026, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-11-0101 November 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ET 16-0028, Response to Request for Additional Information Re Relief Request Number I4R-03 for Reactor Vessel Head Penetration Nozzle Welds2016-10-20020 October 2016 Response to Request for Additional Information Re Relief Request Number I4R-03 for Reactor Vessel Head Penetration Nozzle Welds WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions2016-05-31031 May 2016 Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions ML16204A0132016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions ET 16-0016, Response to Request for Additional Information Re License Amendment Request to Allow Use of Optimized Zirlo2016-05-19019 May 2016 Response to Request for Additional Information Re License Amendment Request to Allow Use of Optimized Zirlo ET 16-0009, Response to Request for Additional Information Regarding Flood Hazard Reevaluation Report, Revision 12016-02-23023 February 2016 Response to Request for Additional Information Regarding Flood Hazard Reevaluation Report, Revision 1 WO 16-0003, Responses to Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-01-18018 January 2016 Responses to Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ET 15-0026, Response to Request for Additional Information Regarding the Expedited Seismic Evaluation Process Report2015-11-11011 November 2015 Response to Request for Additional Information Regarding the Expedited Seismic Evaluation Process Report ET 15-0015, Response to Request for Additional Information Regarding Expedited Seismic Evaluation Process (ESEP) Report2015-06-24024 June 2015 Response to Request for Additional Information Regarding Expedited Seismic Evaluation Process (ESEP) Report 2023-01-26
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ENCLOSURE II TO ET 19-0008 Westinghouse Responses to NRC Request for Additional Information Documented in ADAMS Accession No. ML18270A094 on the Core Design and Safety Analyses Methodology Transition Program
[Non-Proprietary]
(7 PAGES)
Westinghouse Non-Proprietary Class 3 Page 1 of 7 SAP-19-8 NP-Attachment Our Ref: SAP-19*8 Westinghouse Responses to NRC Request for Additional Information Documented in ADAMS Accession No. ML18270A094 on the Core Design and Safety Analyses Methodology Transition Program
[Non-Proprietary]
(7 pages including cover page)
©2019 Westinghouse Electric Company LLC All Rights Reserved
- This record was final approved on 2/14/2019 6:10:00 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Page 2 of 7 SAP-19-8 NP-Attachment Our Ref: SAP-19-8 Request Rod C/usrer Colltrol t\ssembl\' Eiection Accitle,u Please demonstrate that the CREA analysis re.wills discussed in Section 2.5.6 c~f E11clos11re I are cnmiste/11 with General Design Criterion (GDC) 28. "Reactiviry limits." of Appendix A. "Ge11eml Design Criteria for Nuclear Poll'er Piams." to Tirle 10 of The Codci of Fee/era/ Regulations ( /0 CFR) Part 50 for long Term cooling. and ll'ith the ass11111ptions employed ,rith the rm/iological analyses supporting the i111ple111e11tatio11 of the altematil'e source 1er111 in accordance ll'ith /0 CFR 50.67. "Accidem .1*nurce term." CDC 28 requires that rhe e.ffecrs of postulated reactivity acciclems neither damage !he 1w1cror coo/am pressure bomulary greater 1ha11 limited local yielding. nor impair 1!,e ability to cool !he core. ,\tlea11while. !he radiological consequence analysis of the CREA ass11111es no more than I 0-percelll ofji,el ce/1/erline melt m 1he hot spot.
Since the NRC position statcid i11 Regulatory Guide 1.77. "A.1*s11111ptio11s med for Emluating o Comrol Rod Ejeclion Accide111Jor Pressurized Water Reacwrs." May /974 (ADAMS Accession No. Ml003740279), indicating that acceptance criteria of280 calories per gram (cal/gm) should be applied to the e1*e111. and Westinghouse's position that 200 cal/gm and /0-percent fuel cellterline melt criteria contained in \VCAP-7588. "An Emlulllion of the Rod Ejection Ac:cide11t in \Vesti11gho11se Press11rizecl Water Rec1ctors Using Spatio/ Kinetics Methods," were eswblished.
the NRC staff deten11i11e,l that more restrictive occepta11ce criterio were needed to assure the core would re111oi11 in a coo/able geometry. given the potential for high tempemture cladding failure and pellet cladding intemctio11. This position is doc:11111e111ed in an NRC staffi11temol 111e1110 dated April 3. 20/5, titled. "Results of Periodic Re11iew of Regulat()I)' Guide /.77" (ADAMS Accession No. Ml/5075A3/ I). The positio11 is supported by the NRC staff i11temo/
memo dated January I 9. 2007. titled, "Technical and Regulatory Bosis for the Reac:til'ity Initiated Accide111 /111eri111 Acceptance Criteria and Guidance" (ADAMS Accession No. Ml070220400).
o) Please justijj' why 200 cal/gm 011d /0-percellt fuel melt are appropriate acceptance criteria gfren that much more is known 110w abo11T fuel damage beht1l'ior thm, when The method was approi*ed in /975.
b) Please discuss how the calculatio11s appropriotely include The effects of 1111dear fuel TCD in the evaluation against the acceptance criterio. The hot spot Juel melt limit of I0-percent relates to the prel'efl/io11 offuel dispersal imo the coolant. a11d is reflected in the assu111ptio11s employed in the mcliological analyses.
Response
As subsequently demonstrated by the responses to part a) and pan b) of this request. the Rod Cluster Control Assembly (RCCA) ejection accident analysis results discussed in Section 2.5.6 of WCAP-17658-NP Revision I are consistent with General Design Criterion (GDC) 28. **Reactivity limits." of Appendix A. Genernl Design Criteria for Nuclear Power Plants:* to Title IO of the Code of Federal Regulations (IO CFR) Part 50 for long term cooling.
and with the assumptions employed with the radiological analyses supporting the implementation of the alternative source term.
a) Ple<1se justify 1rhy 200 cal/gm and JO-percent fuel melt are appropriate accepllmce criterio given that much more-is k11ow1111011* abo11t fuel damage behavior thc111 whe11 the method u*as approved in 1975.
The WCAP-7588 Revision 1-A acceptance criteria arc a conservative replacement for the Regulatory Guide I. 77 criteria. as subsequently discussed. Specifically. the 200 cal/gm criterion is the conservative coolability limit utilized by Westinghouse relative to the Regulatory Guide I. 77 limit of 280 cal/gm. Additionally. the I0% fuel melt criterion is a conservative limit that has been used by Westinghouse for input to the radiological close calculations.
The 10% fuel melt limit is nm intended lo be used as the coolability limit.
As the NRC has stated. more restrii.:tive ai.:ceptam:e i.:riteria than the Regulatory Guide 1.77 criteria may be needed.
However. the existing 1-D analysis methodology is an overly-conservative method relative to more advanced 2-D or 3-D methods. The analysis documented in Section 2.5.6 of WCAP-17658-NP Revision I utilized the more restrictive WCAP-7588 Revision I-A acceptance criteria (200 i.:al/gm) along with the historical 1-D analysis method in order lfl maintain the overall conservatism or the analysis.
- This record was final approved on 2/14/2019 6:10:00 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Page 3 of 7 SAP-19-8 NP-Attachment Our Ref: SAP-19-8 It is noted that utilizing this approach (i.e .. the 200 cal/gm limit in combination with the conservative 1-0 am1lysis method) was discussed between Wolf Creek. Westinghouse. and the NRC during a clarification call associated with this request in order to ensure that there was understanding on how the evaluation of the RCCA ejection accident would be performed.
I>) Please discuss how rlie calculatiom appropriately i11cl11de the effi!cts of 1111clearf11el TCD in the el'al11alio11 against the acceptance criteria. The hot spot Juel melt limit of I 0-percelll relates to the preve111io11 offuel dispersal ii/to the coola11t. mu/ is reflected i11 the. assumptions employed in the radiological analyses.
Regarding the issue of fuel thermal conductivity degradation (TCD). WCAP-17658-NP Revision I referenced LTR-NRC-12-18 (ADAMS Accession No. MLI 2053Al05) as the basis for the continued safe operation of plants analyzed with Westinghouse codes and methods. consistent with the basis used for other plants analyzed with Westinghouse codes and methods. The rationale for referencing LTR-NRC-12-18 was due to the fact that the Westinghouse Performance Analysis and Design Model (PADS) submittal. WCAP-17642-P-A Revision 1. was still under review and had not yet been approved by the NRC at the time that the licensing report for the Methodology Transition, WCAP-17658-NP Revision I. was submitted.
Following the submittal of the Methodology Transition license amendment request, WCAP-17642-P-A Revision I was approved for use and provided the technical basis for utilizing the PADS model to address fuel TCD. However.
as documented within LTR-NRC-18-7 (ADAMS Accession No. ML18023B555), the schedule to perform all not-LOCA analyses required to transition to the PADS. models and methods is [ ]3-e Furthermore. [
J'"e Therefore, due to the timing of the approval of WCAP-17642-P-A Revision I relative to the timing of the Methodology Transition submittal, it was not feasible to fully incorporate the PADS models and methods into the not-LOCA analyses within the confines of the Methodology Transition submittal.
Nevertheless, in order to respond to this request and to demonstrate that the acceptance criteria (i.e., 200 cal/gm and I0% fuel melt) for the RCCA ejection accident will continue to be met once the effects of TCD are explicitly included within the licensing basis analysis, a demonstration analysis was performed. This demonstration analysis was based on the RCCA ejection analysis described in Section 2.5.6 of WCAP-17658-NP Revision I, but with analysis inputs revised to account for the effects ofTCD. The revised analysis inputs were based on the models and methods described in WCAP-17642-P-A Revision I. Specifically. the input changes included [
re for both the HFP and hot zero power (HZP) cases. The conservative ejected rod worth values used in the analysis described in WCAP-17658-NP Revision 1 continued to be used.
The burnup-dependent inputs for each of the cases in the demonstration analysis were based on [
]"". In addition, as the fuel melting temperature is burnup-dependent. it was decreased from 4900°F at beginning of cycle rBOC> and 4800°F at end or cycle (EOC) to r re for all cases. I 1
The Wolf Creek Generating Station (WCGS) Technical Specification Safety Limit 2.1.1.2 is 508D°F decreasing at 58°F per 10.000 MWD/MTU ofburnup.
- This record was final approved on 2/14/2019 6:10:00 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Page 4of 7 SAP-19*8 NP-Allachmenl Our Ref: SAP-19*8 As expected. with the effects of TCD included. the peak fuel average and centerline temperatures increased. For the HZPcases. [
)"" The results from the demonstration analysis are presented in Table I.
In summary. the demonstration analysis of the RCCA ejection accident utilized the same inputs as those used for the analysis described in Section 2.5.6 of WCAP-17658-NP Revision I. with the following exceptions:
a.c Table I: Wolf Creek RCCA Ejection Results a,c Based upon the results in Table I. all 111.:ceptance criteria continue to be met. Therefore. ii is concluded that the*
effects ofTCD can be accommod.ned for the RCCA ejection accident for Wolf Creek.
As previously stated. [
]3- Thus. the intent is to not incorporate the PADS models and methods into the licensing basis for the RCCA ejection accident at this time. as the remaining not-LOCA analyses have not yet been updated (with the exception of the Steamline Break (SLB) analysis. which is discussed in the subsequent response).
It is recognized that the demonstration analysis performed for this evaluaiion [
]""c Therefore. it has already been demonstrated that the analysis bounds the upcoming fuel cycle. Furthermore. to ensure that the results cominue to remain valid for future cycles. an additional check will be performed as part of the reload process to contil'm lhat the 1
[ ]' *< remain bounding on a cycle-specific basis until Wolf Creek fully implements the PAD5 models and methods into its licensing basis for the 1101-LOCA analyses. Once the PAD5 models and methods are fully incorporated into the Wolf Creek licensing basis. the PADS analysis will become the analysis of record and the [ ]""c will become the limits checked as part of the standard reload process.
- This record was final approved on 2/14/2019 6:10:00 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Page 5of 7 SAP-19-8 NP-Attachment Our Ref: SAP-19*8 Request S1ea111li11e Break Accidem Please demmwrate holl' the 111/SLB analyses co11tai11ed in Section 2.2.5 of Enclosure I are co11siste111 ll'ith the requiremellfs of /0 CFR Part 50. Appendix A. GDC 27. "Combined reactivity control systems cap,1bility. "and GDC 28. GDC 27 requires that the reactfrity comrol systems be designe,l to have a combined capability, ill co11j1111ctio11 11'ith poiso11 addition b.,* the emergency core cooling system. of reliably colllrolling reactivity changes w that. 1111der postulated accident comliliims a11d with ap11roprillle margin for st11ck rods. the capability to cool the core is mai111ai11ed. GDC 28 requires that the effects of postula1ed reactivity accitlems neither damage the reactor coola11111ress11re boundary greater than limited local yielding. nor i111pt1ir the ability to cool the core. Per the Westinghouse analytic met/wt!.~ proposed for i111pleme11tario11. /he 1'1/SLB is cmaly-;.ed to de111011strate that Juel damage criteria are smisjied. i11c/11di11g departure from 1111cleate boiling limits and f11el melt limits.
/11 cm/er for the NRC staff to determine whether the MSLB analyses t1ss111*e complit111ce with the requirements of GDC 27 and 28. please discus.1* /ww the MSLB results and acceptance criteria ap11ropriatelr include the effects of TCD. including:
a) The hot zero power and hot full power de11art11refro111 n11cleate boiling mtio. and b) The hot Juli power peak linear heat rare.
Response
As subsequently demonstrated by the responses to part a) and part b) of this request, the SLB analyses contained in Section 2.2.5 of WCAP-17658-NP Revision I are consistent with the requirements of IO CFR Part 50, Appendix A.
GDC 27, ,;Combined reactivity control systems capability."'.and GDC 28.
a) The hot zero poll'er a11d hot full power departure Jro1111111c/eate boiling ratio, and The response to part a) is combined with the response to part b).
b) The hot Juli power peak linear heat mte.
]".c there are no changes to the departure from nucleate boiling ratio (DNBR) results for the HZP SLB and HFP SLB accidents due to the effects ofTCD.
While the transient analysis of the system response for the HFP SLB accident is not impacted by the effects of TCD.
the power-to-melt limit (i.e .. peak fuel linear heat generation rate that would cause fuel melting. expressed in terms of [ ]"'") is affected by TCD. Therefore. the powcr-10-mclt lirnit used in the analysis of the HFP SLB transient was recalculated to explicitly consider the effects ofTCD and defined as a I
)"'" The transient analysis statepoints were then used to recalculate the corresponding peak linear heal generation rate observed during the HFP S~B evem. based on upon the upcoming fuel cycle (Cycle 24). for comparison to the revised power-to-melt limit. The results fi.)r the limiting HFP SLB c;ise are summarized in Table 2. The peak fuel linear heat generation rate does not exceed the value that would cause fuel melting.
- This record was final approved on 2/14/2019 6:10:00 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Page 6 of 7 SAP-19-8 NP-Attachment Our Ref: SAP-19-8 For the HFP SLB. the transient analysis of the system response is consistent with that described in Section 2.2.5.2 of WCAP-17658-NP Revision I. The calculation of the peak fuel linear heat generation rate is based upon the upcoming fuel cycle (Cycle 24). As the peak fuel linear heat generation rate can change on a cycle-specific basis. an additional check will be performed as part of the reload process to confirm that the r r*c power-to-melt limit with the effects ofTCD considered continues to be met for the HA> SLB accident until Wolf Creek fully implements the PAD5 models and methods into its licensing basis for the not-LOCA analyses. Once the PAD5 models and methods are fully incorporated into the Wolf Creek licensing basis. the PAD5 analysis will become the analysis of record and the r standard reload process.
r power-to-melt limit will be checked as part of the In addition to the HFP SLB accident. the SLB at power with coincident rod withdrawal (SLB w/RW AP) case was explicitly evaluated. While this case is not presented within the Wolf Creek Updated Safety Analysis Report (USAR). it is analyzed to address the concerns outlined in NRC Information Notice IE-79-22 related to non-safety grade equipment being subjected to an adverse environment from high-energy line breaks inside or outside containment.
The scenario is that a high-energy steamline break could fail the automatic rod control system cabling and/or equipment such that the RCCA banks begin to withdruw from the core simultaneous with the break. Such, a rod withdrawal. combined with the core power increase caused by the steamline break. may lead to a rapid power excursion and a potentially adverse core condition. RCCA bank withdrawal during the steamline break could only occur with the rod control system in the automatic mode. At zero power, the rod control system is in the manual mode, and therefore could not inadvertently withdraw rods du~ to equipment or cabling being exposed to an adverse condition. As a result. the coincident RCCA withdrawal can only be postulated for a steamline break from an at-power initial condition.
The input parameters. assumptions. and acceptance criteria for the transient analysis of the SLB w/RW AP accident are the same as those for the HFP SLB accident (Section 2.2.5.2.1.2 of WCAP-17658-NP Revision I). with the following additions or changes:
]a.~
- Cases were analyzed for both minimum (0 percent) and maximum ( l O percent) steam generator tube plugging (SGTP) conditions.
- Cases were*analyzed assuming both minimum and maximum reactivity feedback coefficients.
corresponding to BOC and EOC core conditions. [
] a.<
- Rod withdrawal was conservatively modeled to begin al the time of the break. with no credit taken for any delay. A constant [ J"' maximum differential rod worth was assumed for control bank D at hot full power <D-bank is the only one that is permitted to be inserted into the core at full power). The rods withdraw until reactor trip is actuated. or until the rods would be fully out of the core.
- This record was final approved on 2/14/2019 6:10:00 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Page 7 of 7 SAP-19-8 NP-Attachment Our Ref: SAP-19-8 Based upon the transient analysis results. the following limiting cases were selecled in Mder to demonstrate thal 1he DNBR and peak fuel linear heat generation rate criteria continue 10 be met:
A. 0% SGTP. maximum reactivity feedback. [
B. 10% SGTP. minimum reactivity feedback. [
Ja.c C. I0% SGTP. minimum reactivity feedback. [
t*c The results for the limiting cases are summarized in Table 3.
The results of the analysis of the SLB w/RW AP accident demonstrate that the DNB design basis continues to be met with the effects ofTCD explicitly included in the analysis. Additionally, the peak fuel linear heat generation rate does not exceed the value that would cause fuel centerline melting.
The analysis of the SLB w/RW AP accident assumed a maximum differential rod worth of [ i3.c to bound the value for the upcoming fuel cycle (Cycle 24). Also, the calculation of the peak fuel linear heat generation rate is based upon the upcoming fuel cycle (Cycle 24). As the maximum differential rod worth and peak fuel linear heat generation rate can change on a cycle-specific basis, additional checks will be performed as part of the reload process to confirm that the maximum differential rod worth limit remains bounding and the [ ye power-to-melt limit with the effects of TCD considered continues to be met for the SLB w/RW AP accident until Wolf Creek fully implements the PADS models and methods into its licensing basis for the not-LOCA analyses.
Once the PADS models and methods are fully incorporated into the Wolf Creek licensing basis, the PADS analysis will become the analysis of record and these limits will be checked as part of the standard reload process.
Table 2: Wolf Creek HFP SLB Results
[
Table 3: Wolf Creek SLB w/RW AP Results a.c
- This record was final approved on 2/14/2019 6:10:00 PM. (This statement was added by the PRIME system upon its validation)