Letter Sequence RAI |
---|
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
|
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
[Table View] |
|
---|
Category:E-Mail
MONTHYEARML23360A1562023-12-26026 December 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise the Ventilation Filter Testing Program in Technical Specifications ML23166A0622023-06-15015 June 2023 NRR E-mail Capture - Acceptance Review - Wolf Creek Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded post-tensioning System Components ML23090A1042023-03-31031 March 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML23090A0072023-03-31031 March 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request for Relief for Follow-Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface ML23080A0652023-03-21021 March 2023 NRR E-mail Capture - Wolf Creek Generating Station Evacuation Time Estimate Analysis Review ML23026A0222023-01-25025 January 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ML23009A4082023-01-0909 January 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise TS to Adopt Technical Specification Task Force (TSTF)-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22361A0052022-12-27027 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 ML22251A1312022-09-0808 September 2022 NRR E-mail Capture - Acceptance Review - Wolf Creek Request for Deviation from Fire Protection Program Requirements to Allow Use of Portable Lighting ML22215A2742022-08-0202 August 2022 Inservice Inspection Request for Information ML22208A1322022-07-27027 July 2022 NRR E-mail Capture - Wolf Creek Table of Contents LAR ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22131A0522022-05-11011 May 2022 NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek Inservice Inspection Relief Request for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface 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 ML22026A4392022-01-26026 January 2022 NRR E-mail Capture - Wolf Creek Acceptance Review Results - Removal of TS Table of Contents (L-2022-LLA-0008) 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 ML21309A0332021-11-0505 November 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Revision of Technical Specification 3.8.1, AC Sources - Operating ML21307A4202021-11-0303 November 2021 NRR E-mail Capture - Acceptance Review - 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 ML21259A0652021-09-16016 September 2021 NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek License Amendment and Exemption Requests Regarding 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 ML21189A0252021-07-0101 July 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Request Revision to the Emergency Plan Related to on-shift Staffing ML21230A3922021-05-19019 May 2021 May 19, 2021 Dricks Response to Gurdziel Letter Dated May 13, 2021 - August 17, 2021 ML21102A3342021-04-12012 April 2021 Email 4-12-21 RFI for In-Office Rvw of Recent RERP and a Related EPIP Change ML21064A0342021-03-0404 March 2021 NRR E-mail Capture - Wolf Creek Generating Station Upcoming Steam Generator Tube Inservice Inspection ML20353A2712020-12-18018 December 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ML20349A3092020-12-14014 December 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request for Change to Owner Licensee Names ML20297A3022020-10-22022 October 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI 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 ML20191A0222020-07-0606 July 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request in Support of Replacement Engineered Safety Features Transformers with Load Tap Changers ML20162A1642020-06-0909 June 2020 Email June 9, 2020 - RFI in Preparation for Wolf Creek EP Program Inspection ML20149K4272020-05-22022 May 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ML20133J8972020-05-12012 May 2020 12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes ML20132A3442020-05-11011 May 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20009E4802020-01-0909 January 2020 Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information ML19273A0232019-09-30030 September 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, ML19268B7172019-09-25025 September 2019 NRR E-mail Capture - Acceptance Review - Inservice Inspection (ISI) Program Relief Request to Use Code Case N-666-1 ML19261A2272019-09-18018 September 2019 NRR E-mail Capture - Regulatory Audit Plan - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 3.3.5 ML19255H3032019-09-12012 September 2019 NRR E-mail Capture - Acceptance Review - Relief Request I4R-07 to Utilize Code Case N-513-4 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 ML19274D2752019-07-31031 July 2019 Request for Information-IR 05000482 2019-004, Dated 7/31/2019 ML19203A2362019-07-19019 July 2019 LTR-19-0291 Tom Gurdziel, E-mail July 18, 2019, Confirmatory Order on Wolf Creek ML19112A1772019-04-22022 April 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ML19091A0362019-03-29029 March 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ML19065A0982019-03-0606 March 2019 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request for Revision to Technical Specifications to Adopt TSTF-529 ML19036A6832019-02-0505 February 2019 LTR-18-0498 - Email Response - Sheryl Sweet, Licensing Engineer, Wolf Creek Nuclear, E-mail Acronyms for NRC Personnel 2023-06-15
[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 ML22165A0882022-06-14014 June 2022 Information Request, Security IR 2022403 ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information 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 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 ML14027A1622014-01-28028 January 2014 Redacted, Request for Additional Information, Round 2, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term 2022-06-29
[Table view] |
Text
NRR-PMDAPEm Resource From: Singal, Balwant Sent: Wednesday, June 14, 2017 1:15 PM To: Muilenburg William T (wimuile@WCNOC.com)
Cc: Good Nicole R
Subject:
Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses including Adoption of Alternative Source Term (CAC No. MF9307)
Attachments: MF9307-RAI (EICB&RHM1).docx The U.S. Nuclear Regulatory Commission (NRC) staff is in the process of reviewing the subject LAR and has identified the need for additional information described in the attachment to this e-mail. Draft request for additional information (RAI) was transmitted to Wolf Creek Nuclear Operating Corporation (WCNOC) on May 31, 2017 and a clarification call was held on June 13, 2017. WCNOC agreed to respond to the RAI request within 30 days from the date of this e-mail. Please note that Reference to Chapter 7 of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, has been updated from Revision 5 (March 2007) in the Draft RAI to Revision 7 (August 2016).
Also, please note that several technical branches have been assigned for review of this license amendment request and this is only a partial RAI request.
Thanks.
1
Hearing Identifier: NRR_PMDA Email Number: 3566 Mail Envelope Properties (c29675aab37a40a19bb69902d7bbb4ed)
Subject:
Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses including Adoption of Alternative Source Term (CAC No. MF9307)
Sent Date: 6/14/2017 1:15:25 PM Received Date: 6/14/2017 1:15:00 PM From: Singal, Balwant Created By: Balwant.Singal@nrc.gov Recipients:
"Good Nicole R" <nilyon@WCNOC.com>
Tracking Status: None "Muilenburg William T (wimuile@WCNOC.com)" <wimuile@WCNOC.com>
Tracking Status: None Post Office: HQPWMSMRS05.nrc.gov Files Size Date & Time MESSAGE 876 6/14/2017 1:15:00 PM MF9307-RAI (EICB&RHM1).docx 30587 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: ZZZ
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSIS INCLUDING ADOPTION OF ALTERNATIVE SOURCE TERM WOLF CREEK GENERATING STATION (CAC NO. MF9307)
By letter dated January 17, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17054C103), as supplemented by letters dated March 22 and May 4, 2017 (ADAMS Accession Nos. ML17088A635 and ML17130A915, respectively), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee), submitted a license amendment request (LAR) for the Wolf Creek Generating Station (WCGS) to transition to Westinghouse Core Design and Safety Analysis, including adoption of the alternative source term (AST).
The proposed LAR would replace the WCNOC methodology for performing core design, non-loss-of-coolant-accident (non-LOCA) and LOCA safety analyses to the standard Westinghouse methodologies for performing these analyses, and associated technical specification (TS) changes. The proposed amendment would also revise WCGS TSs and the Updated Safety Analysis Report Chapter 15 radiological consequence analyses using an updated accident source term consistent with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.67, Accident source term.
The U.S. Nuclear Regulatory Commission (NRC) staff requests for the following additional information for completing the review of the proposed LAR.
Instrument and Controls Branch (EICB)
NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition, Chapter 7, Instrumentation and Controls, August 2016 (ADAMS Accession No. ML16020A049), defines the acceptance criteria for this review. Standard Review Plan Chapter 7 addresses the requirements for instrumentation and control systems in light-water nuclear power plants. The regulatory requirements and guidance which the NRC staff considered in its review are as follows:
- 10 CFR 50.36(c)(1)(ii)(A) requires in part that where a limiting safety system setting is specified for a variable on which a safety limit has been placed, the setting must be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded. If, during operation, it is determined that the automatic safety system does not function as required, the licensee shall take appropriate action, which may include shutting down the reactor.
- 10 CFR 50.36 (c)(2)(i) requires that the TSs include limiting conditions for operation (LCOs) for equipment required to ensure safe operation of the facility. When an LCO for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.
- 10 CFR 50.36 (c)(3) states TS Surveillance Requirements (SRs) relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. 10 CFR 50.36, Technical specifications, states, Each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specifications in accordance with the requirements of this section. Specifically, 10 CFR 50.36(c)(2)(ii) sets forth four
criteria to be used in determining whether a limiting condition for operation is required to be included in the TS.
- 10 CFR 50.55a(h) requires that the protection systems must meet the requirements in Institute of Electrical and Electronics Engineers (IEEE) Std. 279-1968, "Proposed IEEE Criteria for Nuclear Power Plant Protection Systems," or the requirements in IEEE Std.
279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations," or the requirements in IEEE Std. 603-1991, "Criteria for Safety Systems for Nuclear Power Generating Stations, and the correction sheet dated January 30, 1995.
EICB-RAI 1 The LAR would replace the Allowable Value (AV) for Table 3.3.1-1 Function 10, Reactor Coolant Flow - Low, for Normalized Flow. This replacement is necessary for consistency with the assumptions of the new safety analysis methodology (i.e., the use of Normalized Flow, instead of design loop flow). WCAP-18083-P, Revision 0, Westinghouse Revised Thermal Design Procedure Uncertainty Calculations for the Wolf Creek Generating Station, November 2016 (Enclosure 1 to letter dated March 22, 2017) defines the Normalized Flow as the reactor coolant system (RCS) flow normalization to the RCS flow calorimetric. However, it is not clear how the formula describes in the enclosure are used.
Please describe how procedurally the normalization process is carried out. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance test pertains to RCS Flow is SR 3.4.1.3, Verify RCS total flow rate is > 3.71 x 104 gpm [gallons per minute] and greater than or equal to the limit specified in the COLR [core operating limit report]. Alternately, please provide the NRC staff with a copy of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance procedure.
EICB-RAI -2 The proposed amendment would add a new TS LCO 3.1.9, RCS Boron Limitations <500°F.
This modification necessities modification of the requirements for RTS trip Function 2.b, Power Range Neutron Flux - Low, in TS Table 3.3.1-1. Specifically, the Applicability for reactor trip system (RTS) trip Function 2.b will be revised and new Conditions V, W, and X will be added to LCO 3.3.1. The LAR states that Condition V will be similar to existing Condition E. However, the NRC staff notes the end state for the plant Condition V will require the initiation of actions aimed at precluding an uncontrolled rod cluster control assembly bank withdrawal event from occurring or providing sufficient shutdown margin should this event occur while the existing condition E does not contain this requirement.
Please provide additional information to justify inclusion of this additional requirement.
Hydrology and Meteorology Branch (RHM1)
RHM1-RAI-1 10 CFR 50.67(b)(2)(i) requires a licensee seeking to revise its current accident source term in design basis radiological consequence analyses to provide an evaluation of the consequences of applicable design basis accidents to demonstrate that adequate radiation protection is provided to permit access to and occupancy of the control room under accident conditions.
Methods acceptable to the NRC staff for determining atmospheric dispersion factors (or X/Q values) in support of design-basis control room radiological habitability assessments at nuclear power plants can be found in RG 1.194, Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants, June 2003 (ADAMS Accession No. ML031530505).
RG 1.194 provides guidance on the use of the ARCON96 atmospheric dispersion model for determining X/Q values to be used in design basis evaluations of control room radiological habitability analyses. Section 3.2 of RG 1.194 states that in order to determine source-receptor bounding combinations, it is necessary to consider the distance, direction, release mode, and height of the various release points to the environment in relation to the various control room intakes. Additional parameters, such as those used in establishing plume rise, may need to be considered in determining the bounding combination.
Section 4.1.2, Atmospheric Dispersion Factors - Control Room and Technical Support Center, Full Scope Implementation of Alternative Source Term, (Enclosure IV to letter dated January 17, 2017) describes the development of the X/Q values used in the control room (CR) and technical support center (TSC) radiological analysis. Tables 4.1.2-1(a), 4.1.2-1(b), and 4.1.2-2 in Enclosure 4 provide the ARCON96 input parameters for the Emergency Control Room Air Intake, Normal Control Room Air Intake, and the TSC Air Intake, respectively. The staff has identified 4 release heights in these tables that appear to conflict with each other. Please resolve the following potential conflicts by either updating the Enclosure 4 tables or justifying the use of the release heights listed below.
Source Release Heights Source Turbine-Driven Unit Vent MSSVs/ARVs AFW2 Exhaust 1 Radwaste Table No. Receptor Stack Vent Vent Building 4.1.2-1(a) Emergency 66.25 meters 34.29 m 13.87 m 6.10 m CR Air Intake (m) 4.1.2-1(b) Normal 66.17 m 34.29 m 14.05 m 17.07 m CR Air Intake 4.1.2-2 TSC Air Intake 66.25 m 35.71 m 13.87 m 2.84 m 1
Main Steam Safety Valves/Atmospheric Relief Valves 2
Auxiliary Feedwater