Letter Sequence 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) EPID:L-2017-LLA-0211, 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, 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 ML18075A0242018-03-0808 March 2018 Changes to Technical Specification Bases - Revisions 76 and 77 Project stage: Request ML18066A0502018-03-0808 March 2018 Regulatory Audit Plan for March 19-21, 2018, in Support of the LAR for Transition to Westinghouse Core Design and Safety Analyses Including Alternative Source Term (CAC No. MF9307;EPID L-2017-LLA-0211) Project stage: Approval 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 ML18313A2252018-10-25025 October 2018 Westinghouse Affidavit CAW-18-4828 - Application for Withholding Proprietary Information from Public Disclosure Project stage: Request ML18332A1772018-10-25025 October 2018 Email Slides for 10/30 Public Meeting 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 Adoption2019-03-0505 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:Letter
MONTHYEARML24352A0322024-12-17017 December 2024 Notification of Post Approval Site Inspection for License Renewal and Request for Information IR 05000482/20240142024-12-17017 December 2024 Comprehensive Engineering Team Inspection Report 05000482/2024014 05000482/LER-2024-002-01, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-12-11011 December 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve IR 05000482/20244022024-12-0505 December 2024 Security Baseline Inspection Report 05000482/2024402 ML24337A0132024-12-0202 December 2024 Cycle 27 Core Operating Limits Report, Revision 1 ML24306A2192024-11-0101 November 2024 Results of the Steam Generator Tube Inservice Inspection During the 26th Refueling Outage to Reflect TSTF-577 Reporting Requirements IR 05000482/20240032024-11-0101 November 2024 Integrated Inspection Report 05000482/2024003 IR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications 2024-09-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22361A0052022-12-27027 December 2022 NRR E-mail Capture - Request for Additional Information Wolf Creek Request for Deviation from Fire Protection Program Requirements ML22321A2662022-11-16016 November 2022 January 2023 Emergency Preparedness Program Inspection - Request for Information ML22307A1372022-11-0202 November 2022 August 2022 Emergency Preparedness Exercise Inspection Unresolved Item - Request for Information ML22249A2552022-06-29029 June 2022 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000482/2022012 ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22165A0882022-06-14014 June 2022 Information Request, Security IR 2022403 ML22055A1142022-02-23023 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Request to Revise Diesel Generator Completion Time ML22045A4512022-02-14014 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Steam Generator Inspection Report 24th Refueling ML22025A3612022-01-21021 January 2022 PI&R RFI Final ML21327A2602021-11-23023 November 2021 NRR E-mail Capture - Request for Additional Information - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21271A1952021-09-28028 September 2021 E-mail 9-28-21 RFI for Wc EP Inspection Nov 2021 ML21253A0902021-09-23023 September 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment and Regulatory Exemption for a Risk-Informed Approach to Address GSI-191 (EPIDs L-2021-LLA- 0152 and L-2021-LLE-0039) ML21221A1282021-08-0505 August 2021 NRR E-mail Capture - Urgent: Draft Request for Additional Information - Wolf Creek one-time Request for Exemption from the Biennial Emergency Preparedness Exercise ML21132A1032021-05-12012 May 2021 Document Request List, Paperwork Reduction Act Statement ML20302A4782020-10-28028 October 2020 OPC R1 Request for Information ML20262A7512020-09-17017 September 2020 NRR E-mail Capture - Requests for Additional Information: Wolf Creek Amendment Request to Modify Technical Specification Surveillance Frequency Consistent with TSTF-425 ML20195A2712020-07-13013 July 2020 Generation Station - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2020012) and Request for Information ML20133J8972020-05-12012 May 2020 12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes ML20009E4802020-01-0909 January 2020 Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information ML19346E6052019-11-0404 November 2019 Target Set Request for Information for Week of November 4, 2019 ML19224A5242019-08-12012 August 2019 NRR E-mail Capture - Request for Additional Information - License Amendment Request to Revise Wolf Creek Generating Station Technical Specification 3.3.5 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) ML18282A6402018-10-0909 October 2018 NRR E-mail Capture - Request for Additional Information - Wolf Creek Generating Station License Amendment Request for Revision to the Emergency Plan ML18270A0942018-10-0404 October 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Methodology for Selected Accident and Transient Analyses ML18207A4332018-07-24024 July 2018 NRR E-mail Capture - (External_Sender) Draft Request for Additional Information Relief Request from ASME Code N-666-1 Alternate Repair of Essential Service Water Piping Wolf Creek Generating Station, Unit 1 EPID No.:L-2018-LLR-0101 ML18116A6132018-04-25025 April 2018 Operating Corporation - Notification of Inspection (NRC Inspection Report 05000482/2018002) and Request for Information ML18074A3102018-04-0606 April 2018 Request for Additional Information License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning System (CAC No. MF9961; EPID L-2017-LLA-0262) 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) 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 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 ML17170A3152017-06-19019 June 2017 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2017008) and Request for Information 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 ML17052A0282017-02-15015 February 2017 NRR E-mail Capture - Wolf Creek Generating Station - Official EAL RAIs ML16319A4282016-11-14014 November 2016 NRR E-mail Capture - Request for Additional Information (RAI) - Relief Requests 13R-14 and 13R-15 ML16300A2662016-10-21021 October 2016 Request for Additional Information - Relief Request I3R-13 Regarding Weld Examination Coverage IR 05000482/20160022016-08-0303 August 2016 NRC Integrated Inspection Report 05000482/2016002 ML16110A3722016-04-25025 April 2016 Request for Additional Information, License Amendment Request to Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized ZIRLO as Approved Fuel Rod Cladding ML16020A1392016-01-15015 January 2016 Notification of NRC Component Design Bases Inspection (05000482/2016007) and Initial Request for Information ML15135A4862015-05-14014 May 2015 Wc 2015007 17T RFI ML15082A0052015-03-27027 March 2015 Request for Additional Information, Round 2, Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML15079A0762015-03-23023 March 2015 Request for Additional Information, Round 2, Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML15040A6252015-02-10010 February 2015 Request for Additional Information, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML14323A5742014-12-0404 December 2014 Request for Additional Information, License Amendment Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in USAR ML14230A7572014-08-21021 August 2014 Request for Additional Information, Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval ML14206A0122014-08-0101 August 2014 Request for Additional Information, Relief Requests I3R-08, RPV Interior Attachments and I3R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval ML14197A3362014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220, Third 10-Year Inservice Inspection Interval ML14148A3872014-06-0202 June 2014 Request for Additional Information Related to Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML14111A1002014-04-30030 April 2014 Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14083A4002014-04-0303 April 2014 Request for Additional Information, Nrr/Dra/Arcb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14058A0882014-03-0505 March 2014 Request for Additional Information, Nrr/De/Eeeb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term 2022-06-29
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Text
Mr. Adam C. Heflin UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 4, 2018 President and Chief Executive Officer, Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION, UNIT 1-REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST FOR TRANSITION TO WESTINGHOUSE METHODOLOGY FOR SELECTED ACCIDENT AND TRANSIENT ANALYSES (CAC NO. MF9307; EPID L-2017-LLA-0211)
Dear Mr. Heflin:
By letter dated January 17, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17054C103), as supplemented by letters dated March 22, May 4, July 13, October 18, and November 14, 2017; and January 15, January 29, April 19, June 19, and August 9, 2018 (ADAMS Accession Nos. ML17088A635, ML17130A915, ML17200C939, ML17297A478, ML17325A982, ML18024A477, ML180338024, ML18114A115, ML18177A198, and ML18232A058, respectively), Wolf Creek Nuclear Operating Corporation (WCNOC) submitted a license amendment request to transition to Westinghouse methodology for selected accident and transient analyses for Wolf Creek Generating Station, Unit 1 (WCGS).
On September 25, 2018, the staff from WCNOC/Westinghouse and the U.S. Nuclear Regulatory Commission (NRC) participated in a conference call to clarify a draft request for additional information (RAI) that was sent to the licensee by e-mail on September 5, 2018. At the conclusion of the call, it was agreed that the NRC staff would revise the draft RAI to further clarify the request. The final RAI is enclosed with this letter. You are requested to respond to this RAI request within 30 days from the date of the letter.
If you have any questions, please contact me at 301-415-3016 or via e-mail at Balwant.Singal@nrc.gov.
Docket No. 50-482 Enclosure RAI cc: Listserv Sincerely,
'£:, ~:+ t-&, ~--~
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO TRANSITION TO WESTINGHOUSE METHODOLOGY FOR SELECTED ACCIDENT AND TRANSIENT ANALYSES WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION, UNIT 1 DOCKET NO. 50-482 By letter dated January 17, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17054C103), as supplemented by letters dated March 22, May 4, July 13, October 18, and November 14, 2017; and January 15, January 29, April 19, June 19, and August 9, 2018 (ADAMS Accession Nos. ML17088A635, ML17130A915, ML17200C939, ML17297A478, ML17325A982, ML18024A477, ML18033B024, ML18114A115, ML18177A198, and ML18232A058, respectively), Wolf Creek Nuclear Operating Corporation submitted a license amendment request to transition to Westinghouse methodology for selected accident and transient analyses for Wolf Creek Generating Station, Unit 1 (WCGS). The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to complete its review, as described below.
Background
Attachment I, "Evaluation," and Enclosure I, WCAP-17658-NP, Revision 1, "Wolf Creek Generating Station Transition of Methods for Core Design and Safety Analyses - Licensing Report," to the letter dated January 17, 2017, refer to Westinghouse Letter L TR-NRC-12-18, dated February 17, 2012, "Westinghouse Response to December 16, 2011 NRC Letter Regarding Nuclear Fuel Thermal Conductivity Degradation (Proprietary)" (ADAMS Accession No. ML12053A105).
In Attachment I of the letter dated January 17, 2017, the licensee stated in part:
Regarding the impact of the issue of fuel thermal conductivity degradation (TCD) on the Westinghouse codes and methods, Westinghouse... justified continued operation of the plants analyzed with Westinghouse codes and methods. The Westinghouse codes and methods applied in the non-LOCA analyses discussed in Enclosure I are consistent with those evaluated for TCD in [LTR-NRC-12-18],
and therefore the conclusions presented in [L TR-NRC-12-18] are applicable to theWCGS.
Section 2, "Accident and Transient Analysis," of Enclosure I of the letter dated January 17, 2017, contains a similar passage.
Section 2 of Enclosure I also presents results for two specific design-basis accidents, among others, that are the subject of this request. The first is the Rod Cluster Control Assembly (RCCA) ejection accident (CREA), discussed in Section 2.5.6 of Enclosure 1. The second is the main steamline break (MSLB) accident, discussed in Section 2.2.5 of Enclosure I.
Enclosure Request for Additional Information Rod Cluster Control Assembly Ejection Accident Please demonstrate that the CREA analysis results discussed in Section 2.5.6 of Enclosure I are consistent with General Design Criterion (GDC) 28, "Reactivity limits," of Appendix A, "General Design Criteria for Nuclear Power Plants," to Title 10 of the Code of Federal Regulations (10 CFR) Part 50 for long term cooling, and with the assumptions employed with the radiological analyses supporting the implementation of the alternative source term in accordance with 10 CFR 50.67, "Accident source term." GDC 28 requires that the effects of postulated reactivity accidents neither damage the reactor coolant pressure boundary greater than limited local yielding, nor impair the ability to cool the core. Meanwhile, the radiological consequence analysis of the CREA assumes no more than 10-percent of fuel centerline melt at the hot spot.
Since the NRC position stated in Regulatory Guide 1.77, "Assumptions used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors," May 1974 (ADAMS Accession No. ML003740279), indicating that acceptance criteria of 280 calories per gram (cal/gm) should be applied to the event, and Westinghouse's position that 200 cal/gm and 10-percent fuel centerline melt criteria contained in WCAP-7588, "An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods," were established, the NRC staff determined that more restrictive acceptance criteria were needed to assure the core would remain in a coolable geometry, given the potential for high temperature cladding failure and pellet cladding interaction. This position is documented in an NRC staff internal memo dated April 3, 2015, titled, "Results of Periodic Review of Regulatory Guide 1. 77" (ADAMS Accession No. ML15075A311 ). The position is supported by the NRC staff internal memo dated January 19, 2007, titled, "Technical and Regulatory Basis for the Reactivity Initiated Accident Interim Acceptance Criteria and Guidance" (ADAMS Accession No. ML070220400).
a) Please justify why 200 cal/gm and 10-percent fuel melt are appropriate acceptance criteria given that much more is known now about fuel damage behavior than when the method was approved in 1975.
b) Please discuss how the calculations appropriately include the effects of nuclear fuel TCD in the evaluation against the acceptance criteria. The hot spot fuel melt limit of 10-percent relates to the prevention of fuel dispersal into the coolant, and is reflected in the assumptions employed in the radiological analyses.
Main Steamline Break Accident Please demonstrate how the MSLB analyses contained in Section 2.2.5 of Enclosure I are consistent with the requirements of 10 CFR Part 50, Apendix A, GDC 27, "Combined reactivity control systems capability," and GDC 28. GDC 27 requires that the reactivity control systems be designed to have a combined capability, in conjunction with poison addition by the emergency core cooling system, of reliably controlling reactivity changes so that, under postulated accident conditions and with appropriate margin for stuck rods, the capability to cool the core is maintained. GDC 28 requires that the effects of postulated reactivity accidents neither damage the reactor coolant pressure boundary greater than limited local yielding, nor impair the ability to cool the core. Per the Westinghouse analytic methods proposed for implementation, the MSLB is analyzed to demonstrate that fuel damage criteria are satisfied, including departure from nucleate boiling limits and fuel melt limits.
In order for the NRC staff to determine whether the MSLB analyses assure compliance with the requirements of GDC 27 and 28, please discuss how the MSLB results and acceptance criteria appropriately include the effects of TCD, including:
a) The hot zero power and hot full power departure from nucleate boiling ratio, and b) The hot full power peak linear heat rate.
ML18270A094 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/SRXB/BC NAME BSingal PBlechman w/comment JWhitman DATE 10/2/18 9/28/18 10/2/18 OFFICE NRR/DSS/SNPB/BC NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME RLukes RPascarelli BSingal DATE 10/3/18 10/4/18 10/4/18