Letter Sequence Other |
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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
- 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:Audit Report
MONTHYEARML18107A7562018-05-0303 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) ML18073A0892018-04-0202 April 2018 Regulatory Audit Summary Regarding License Amendment Request to Incorporate New Technical Specification 3.7.20 (CAC No. MF9961; EPID L-2017-LLA-0262) ML16152A1292016-08-12012 August 2016 Nuclear Regulatory Commission Report for Audit of Wolf Creek Nuclear Operating Corporation'S Flood Hazards Evaluation Reports Submittal Relating to the Near-Term Task Force Recommendation 2.1 -Flooding for Wolf Creek Generating Station ML16168A2542016-07-0606 July 2016 Report for the Audit Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 ML14042A2202014-02-21021 February 2014 Audit of the Licensee'S Management of Regulatory Commitments, Audit Performed December 16-18, 2013 ML14002A1902014-02-0606 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML0733404912008-02-14014 February 2008 Audit Summary Regarding the License Renewal for the Wolf Creek Generation Station ML0733403982008-02-14014 February 2008 Audit Questions & Answers Database ML0727800032007-10-31031 October 2007 Audit Report of Licensee Regulatory Commitment Management Program for Audit Performed August 20-21, 2007 ML0715005652007-05-25025 May 2007 Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application ML0710300772007-04-27027 April 2007 Summary of Site Audit Related to the Review of the License Renewal Application for Wolf Creek Generating Station, Unit 1 ML0702301662007-02-0606 February 2007 Audit and Review Plan for Plant Aging Management Reviews and Programs, Wolf Creek Generating Station 2018-05-03
[Table view] Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 3, 2018 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION, UNIT 1 - REGULATORY AUDIT
SUMMARY
REGARDING LICENSE AMENDMENT REQUEST FOR TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSES INCLUDING ADOPTION OF ALTERNATIVE SOURCE TERM (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 and January 29, 2018 (ADAMS Accession Nos. ML17088A635, ML17130A915, ML17200C939, ML17297A478, ML17325A982, ML18024A477, and ML180336024, respectively), Wolf Creek Nuclear Operating Corporation (the licensee) submitted a license amendment request for transition to Westinghouse Core Design and Safety Analyses including adoption of Alternative Source Term in accordance with Title 10 of the Code of Federal Regulations Section 50.67 for the Wolf Creek Generating Station, Unit 1.
To support its review of the license amendment request, the U.S. Nuclear Regulatory Commission staff conducted a regulatory audit at the Westinghouse facility in Rockville, Maryland from March 19, 2018, to March 20, 2018, to verify information submitted by the licensee and the supporting calculations. The regulatory audit summary is enclosed with this letter.
A. Heflin If you have any questions, please contact me at 301-415-3016 or via e-mail at Balwant.Singal@nrc.gov.
Sincerely,
~+0£,~&St Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Regulatory Audit Summary cc: Listserv
REGULATORY AUDIT
SUMMARY
FOR MARCH 19- MARCH 20. 2018, AUDIT IN SUPPORT OF THE REVIEW OF LICENSE AMENDMENT REQUEST FOR TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSES INCLUDING ADOPTION OF ALTERNATIVE SOURCE TERM WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION, UNIT 1 DOCKET NO. 50-482
1.0 BACKGROUND
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 and January 29, 2018 (ADAMS Accession Nos. ML17088A635, ML17130A915, ML17200C939, ML17297A478, ML17325A982, ML18024A477, and ML180338024, respectively), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) submitted a license amendment request (LAR) for transition to Westinghouse Core Design and Safety Analyses including adopting an Alternative Source Term (AST) for the Wolf Creek Generating Station, Unit 1 (WCGS).
The proposed amendment would revise the WCGS Technical Specifications (TSs) to replace the existing WCNOC methodology for performing core design, non-loss-of-coolant accident (non-LOCA) and LOCA safety analyses with standard Westinghouse developed and U. S. Nuclear Regulatory Commission (NRC)-approved analysis methodology. The proposed LAR would also change the TSs to revise WCGS licensing basis by adopting the AST radiological analysis methodology in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.67, "Accident source term."
The NRC staff reviewed the impact of implementing an AST on currently analyzed design-basis accidents in the WCGS licensing basis and identified the need for additional information in order to complete the review of the LAR. By letters dated January 15 and January 29, 2018, the licensee provided responses to the request for addition information (RAI). The NRC staff has performed a detailed review of the proposed TS changes and supporting calculations and determined that face-to-face interactions with the WCNOC staff can resolve complex technical issues more quickly than multiple rounds of RAls. Hence, the NRC staff determined the need for a regulatory audit to be conducted in accordance with the Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195), for the NRC staff to gain a better understanding of the licensee's calculations and other aspects of the LAR. An audit plan was issued by the NRC staff by letter dated March 8, 2018 (ADAMS Accession No. ML18066A050). The scope of the audit was primarily focused on changes to the WCGS licensing basis for adopting the AST radiological analysis methodology. In addition to examining the audit documents,
the NRC staff held discussions with the Westinghouse and WCNOC subject matter experts to better understand WCNOC's response to the RAls, provided by letters dated January 15 and January 29, 2018.
2.0 AUDIT DATES AND LOCATION The regulatory audit was held at the Westinghouse facility in Rockville, Maryland. The audit was originally planned for March 19, March 20, and March 21, 2018. However, the NRC staff was able to complete it in 2 days (March 19 and March 20, 2018).
3.0 AUDIT TEAM MEMBERS The following NRC audit team members consisted of:
- Mark Blumberg, Lead Technical Reviewer, NRR, Division of Risk Assessment (ORA), Radiation Protection and Consequences Branch (ARCB)
- Balwant Singal, Senior Project Manager, NRR, Division of Operating Reactor Licensing (DORL). Plant Licensing Branch IV (LPL4)
- Kevin Quinlan, Office of New Reactors, Division of Site and Environmental Analysis, Hydrology and Meteorology Branch, Meteorology Team (Part Time)
The following WCNOC and Westinghouse staff (in support of the licensee) participated in the audit:
- Nicole Good, Licensing Engineer, WCNOC
- Dustin Wirth, Westinghouse (WCGS Site Supervisor)
- Sean Kinnas, Containment Radiological Analysis, Westinghouse
- Alex Markivich, Radiation Engineering and Analysis, Westinghouse
- Jim Smith, Licensing Manager, Westinghouse
- Mike Watson, Project Manager, Westinghouse
4.0 DOCUMENTS AUDITED The following documents were reviewed at the Audit:
- a. The radiological calculations and documents which support the LAR and the RAI responses dated January 15 and January 29, 2018.
- b. The RADTRAD computer code input and output decks used to support the LAR.
5.0 AUDIT ACTIVITIES The audit consisted of the following activities:
- NRC's staff entrance briefing.
- A period in which the staff examined the documents and held discussions with WCNOC and Westinghouse participants as needed for technical understanding.
- Exit briefing for NRC to present observations in person and Westinghouse to seek clarification.
6.0 AUDIT
SUMMARY
The purpose of this regulatory audit was to determine if calculations performed by the licensee support the bases for the proposed changes to the TSs and the modifications to the design basis in accordance with 10 CFR 50.67. The area of focus during the audit was the licensee's response to RAls, by letters dated January 15 and January 29, 2018, and the calculations performed by the licensee in support of the proposed LAR (RAls were issued by the NRC staff by letter dated December 4, 2017 (ADAMS Accession No. ML17331A178)).
Results of the Audit
- a. Based on the review of the RAI responses, the NRC staff indicated that the NRC staff currently does not have any followup questions for the following RAls: 1 LOAC-2, LLBA-1, LOCA-2, LOCA-4, FHA-1, FHA-4, FHA-7, SGTR-1, SGTR-4, WT-1, WT-2, CREA-2, Control Room-5, and General-1
- b. Based on the clarifications provided by the licensee during the audit, the NRC staff indicated that the NRC staff currently does not have any further questions on the following RAls: 1 LLBA-3, SGTR-3, Control Room-1, Control Room-2, Control Room-6, General-3.
- c. Based on the review of the calculations and discussions during the audit, the licensee indicated that it understands the NRC staff concerns and intends to supplement its previous RAI response for the following RAI questions: 1 LOCA-1, LOAC-1, LLBA-2, LLBA-4, LOCA-1, LOCA-3, FHA-2, FHA-5, FHA-6, SGTR-2, SGTR-6, LRA-1, MSLB-1, MSLB-2, WT-3, WT-4, WT-5, CREA-1, Control Room-3, Control Room-4, and General-2.
1 All RAI numbers to be preceded by ARCB1
- d. The discussions could not be concluded on RAls ARCB1-LOCA-5, ARCB1-FHA-3, and ARCB1-SGTR-5. It was decided to have follow-up discussions on these RAls after the conclusion of the audit. Follow-up discussions may result in additional RAls.
7.0 EXIT BRIEFING As described in Section 6.0 of this summary, the exit discussion summarized the status of each RAI. As described in Section 6.0, either based on the RAI responses provided by the licensee by letters dated January 15 and January 29, 2018, or as a result of clarifications provided during the audit, the NRC staff currently has no followup questions for the RAls listed in 6a and 6b. The licensee intends to provide a supplemental response for RAls listed in item 6c to address the NRC staff concerns relating to the RAI responses provided earlier, and further discussions are needed to resolve the pending NRC staff concerns for RAls listed in 6d.
The licensee proposed to provide the supplemental response in two phases. The licensee proposed to provide the response to the first set of RAls (RAls not requiring additional analysis) within 30 days from the conclusion of the audit and requested for 60 to 90 days for responding to the RAls potentially requiring additional analysis. It was decided that the proposed schedule will be discussed with the DORL and DRA management before providing a final response.
ML18107A756 *via e-mail OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/STSB/BC* NRR/DRA/ARCB/BC*
NAME BSingal PBlechman VCusmano KHsueh DATE 04/19/18 04/19/18 04/25/18 04/24/18 OFFICE NRR/DRA/APHB/BC* NRO/DSEA/RHM/BC* NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME CFong CCook RPascarelli BSingal DATE 04/24/18 04/23/18 05/01/18 05/03/18 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 3, 2018 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION, UNIT 1 - REGULATORY AUDIT
SUMMARY
REGARDING LICENSE AMENDMENT REQUEST FOR TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSES INCLUDING ADOPTION OF ALTERNATIVE SOURCE TERM (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 and January 29, 2018 (ADAMS Accession Nos. ML17088A635, ML17130A915, ML17200C939, ML17297A478, ML17325A982, ML18024A477, and ML180336024, respectively), Wolf Creek Nuclear Operating Corporation (the licensee) submitted a license amendment request for transition to Westinghouse Core Design and Safety Analyses including adoption of Alternative Source Term in accordance with Title 10 of the Code of Federal Regulations Section 50.67 for the Wolf Creek Generating Station, Unit 1.
To support its review of the license amendment request, the U.S. Nuclear Regulatory Commission staff conducted a regulatory audit at the Westinghouse facility in Rockville, Maryland from March 19, 2018, to March 20, 2018, to verify information submitted by the licensee and the supporting calculations. The regulatory audit summary is enclosed with this letter.
A. Heflin If you have any questions, please contact me at 301-415-3016 or via e-mail at Balwant.Singal@nrc.gov.
Sincerely,
~+0£,~&St Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Regulatory Audit Summary cc: Listserv
REGULATORY AUDIT
SUMMARY
FOR MARCH 19- MARCH 20. 2018, AUDIT IN SUPPORT OF THE REVIEW OF LICENSE AMENDMENT REQUEST FOR TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSES INCLUDING ADOPTION OF ALTERNATIVE SOURCE TERM WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION, UNIT 1 DOCKET NO. 50-482
1.0 BACKGROUND
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 and January 29, 2018 (ADAMS Accession Nos. ML17088A635, ML17130A915, ML17200C939, ML17297A478, ML17325A982, ML18024A477, and ML180338024, respectively), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) submitted a license amendment request (LAR) for transition to Westinghouse Core Design and Safety Analyses including adopting an Alternative Source Term (AST) for the Wolf Creek Generating Station, Unit 1 (WCGS).
The proposed amendment would revise the WCGS Technical Specifications (TSs) to replace the existing WCNOC methodology for performing core design, non-loss-of-coolant accident (non-LOCA) and LOCA safety analyses with standard Westinghouse developed and U. S. Nuclear Regulatory Commission (NRC)-approved analysis methodology. The proposed LAR would also change the TSs to revise WCGS licensing basis by adopting the AST radiological analysis methodology in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.67, "Accident source term."
The NRC staff reviewed the impact of implementing an AST on currently analyzed design-basis accidents in the WCGS licensing basis and identified the need for additional information in order to complete the review of the LAR. By letters dated January 15 and January 29, 2018, the licensee provided responses to the request for addition information (RAI). The NRC staff has performed a detailed review of the proposed TS changes and supporting calculations and determined that face-to-face interactions with the WCNOC staff can resolve complex technical issues more quickly than multiple rounds of RAls. Hence, the NRC staff determined the need for a regulatory audit to be conducted in accordance with the Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195), for the NRC staff to gain a better understanding of the licensee's calculations and other aspects of the LAR. An audit plan was issued by the NRC staff by letter dated March 8, 2018 (ADAMS Accession No. ML18066A050). The scope of the audit was primarily focused on changes to the WCGS licensing basis for adopting the AST radiological analysis methodology. In addition to examining the audit documents,
the NRC staff held discussions with the Westinghouse and WCNOC subject matter experts to better understand WCNOC's response to the RAls, provided by letters dated January 15 and January 29, 2018.
2.0 AUDIT DATES AND LOCATION The regulatory audit was held at the Westinghouse facility in Rockville, Maryland. The audit was originally planned for March 19, March 20, and March 21, 2018. However, the NRC staff was able to complete it in 2 days (March 19 and March 20, 2018).
3.0 AUDIT TEAM MEMBERS The following NRC audit team members consisted of:
- Mark Blumberg, Lead Technical Reviewer, NRR, Division of Risk Assessment (ORA), Radiation Protection and Consequences Branch (ARCB)
- Balwant Singal, Senior Project Manager, NRR, Division of Operating Reactor Licensing (DORL). Plant Licensing Branch IV (LPL4)
- Kevin Quinlan, Office of New Reactors, Division of Site and Environmental Analysis, Hydrology and Meteorology Branch, Meteorology Team (Part Time)
The following WCNOC and Westinghouse staff (in support of the licensee) participated in the audit:
- Nicole Good, Licensing Engineer, WCNOC
- Dustin Wirth, Westinghouse (WCGS Site Supervisor)
- Sean Kinnas, Containment Radiological Analysis, Westinghouse
- Alex Markivich, Radiation Engineering and Analysis, Westinghouse
- Jim Smith, Licensing Manager, Westinghouse
- Mike Watson, Project Manager, Westinghouse
4.0 DOCUMENTS AUDITED The following documents were reviewed at the Audit:
- a. The radiological calculations and documents which support the LAR and the RAI responses dated January 15 and January 29, 2018.
- b. The RADTRAD computer code input and output decks used to support the LAR.
5.0 AUDIT ACTIVITIES The audit consisted of the following activities:
- NRC's staff entrance briefing.
- A period in which the staff examined the documents and held discussions with WCNOC and Westinghouse participants as needed for technical understanding.
- Exit briefing for NRC to present observations in person and Westinghouse to seek clarification.
6.0 AUDIT
SUMMARY
The purpose of this regulatory audit was to determine if calculations performed by the licensee support the bases for the proposed changes to the TSs and the modifications to the design basis in accordance with 10 CFR 50.67. The area of focus during the audit was the licensee's response to RAls, by letters dated January 15 and January 29, 2018, and the calculations performed by the licensee in support of the proposed LAR (RAls were issued by the NRC staff by letter dated December 4, 2017 (ADAMS Accession No. ML17331A178)).
Results of the Audit
- a. Based on the review of the RAI responses, the NRC staff indicated that the NRC staff currently does not have any followup questions for the following RAls: 1 LOAC-2, LLBA-1, LOCA-2, LOCA-4, FHA-1, FHA-4, FHA-7, SGTR-1, SGTR-4, WT-1, WT-2, CREA-2, Control Room-5, and General-1
- b. Based on the clarifications provided by the licensee during the audit, the NRC staff indicated that the NRC staff currently does not have any further questions on the following RAls: 1 LLBA-3, SGTR-3, Control Room-1, Control Room-2, Control Room-6, General-3.
- c. Based on the review of the calculations and discussions during the audit, the licensee indicated that it understands the NRC staff concerns and intends to supplement its previous RAI response for the following RAI questions: 1 LOCA-1, LOAC-1, LLBA-2, LLBA-4, LOCA-1, LOCA-3, FHA-2, FHA-5, FHA-6, SGTR-2, SGTR-6, LRA-1, MSLB-1, MSLB-2, WT-3, WT-4, WT-5, CREA-1, Control Room-3, Control Room-4, and General-2.
1 All RAI numbers to be preceded by ARCB1
- d. The discussions could not be concluded on RAls ARCB1-LOCA-5, ARCB1-FHA-3, and ARCB1-SGTR-5. It was decided to have follow-up discussions on these RAls after the conclusion of the audit. Follow-up discussions may result in additional RAls.
7.0 EXIT BRIEFING As described in Section 6.0 of this summary, the exit discussion summarized the status of each RAI. As described in Section 6.0, either based on the RAI responses provided by the licensee by letters dated January 15 and January 29, 2018, or as a result of clarifications provided during the audit, the NRC staff currently has no followup questions for the RAls listed in 6a and 6b. The licensee intends to provide a supplemental response for RAls listed in item 6c to address the NRC staff concerns relating to the RAI responses provided earlier, and further discussions are needed to resolve the pending NRC staff concerns for RAls listed in 6d.
The licensee proposed to provide the supplemental response in two phases. The licensee proposed to provide the response to the first set of RAls (RAls not requiring additional analysis) within 30 days from the conclusion of the audit and requested for 60 to 90 days for responding to the RAls potentially requiring additional analysis. It was decided that the proposed schedule will be discussed with the DORL and DRA management before providing a final response.
ML18107A756 *via e-mail OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/STSB/BC* NRR/DRA/ARCB/BC*
NAME BSingal PBlechman VCusmano KHsueh DATE 04/19/18 04/19/18 04/25/18 04/24/18 OFFICE NRR/DRA/APHB/BC* NRO/DSEA/RHM/BC* NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME CFong CCook RPascarelli BSingal DATE 04/24/18 04/23/18 05/01/18 05/03/18