Letter Sequence Withdrawal |
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Category:Acceptance Review Letter
MONTHYEARML21294A0792021-10-22022 October 2021
Withdrawal of Requested Licensing Action License Amendment and Regulatory Exemption for Risk-Informed Approach to Address Generic Safety Issue 191 & Respond to Generic Letter 2004-02
ML18143B3922018-05-21021 May 2018
Acceptance Review - License Amendment Request for Revision to Emergency Plan
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
ML12321A3092012-11-16016 November 2012
Acceptance Review for License Amendment Request, Revise Paragraph 2.C(5)(a) of Facility Operating License NPF-42 and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves
ML12286A0452012-10-11011 October 2012
Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test
ML12200A0812012-07-18018 July 2012
Acceptance Review Email, License Amendment Request to Revise Physical Security License Condition to Support Cyber Security Plan Implementation Schedule Change
ML1116101862011-06-10010 June 2011
Acceptance Review Email, License Amendment Request, Administrative Changes to Technical Specification 5.3, Unit Staff Qualifications
ML1100502262011-01-0505 January 2011
Acceptance Review Email, License Amendment Request, Revise TS 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criterion
ML1031900982010-11-15015 November 2010
Acceptance Review Email, License Amendment Request, Correction of Typographical Error in Technical Specification 5.7.2, Administrative Controls High Radiation Area
ML1021702992010-08-0505 August 2010
Acceptance Review Email License Amendment Request for Approval of the Cyber Security Plan
ML1013700912010-05-20020 May 2010
Non-Acceptance with Opportunity to Supplement License Amendment Request, Revise Approved Fire Protection Program to Remove High/Low Pressure Designation from Pressurizer Power Operated Relief Valves
ML1013702642010-05-14014 May 2010
Acceptance Review E-mail, License Amendment Request to Revise TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 to Identify Functions and Modes for Reactor Trip P-4 Interlock Function
ML1006302372010-03-0303 March 2010
Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.6.3, Containment Isolation Valves Limiting Condition for Operation
ML1002505762010-01-25025 January 2010
Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.8.4, DC Sources - Operating, for Battery Connection Resistance Acceptance Criteria
ML1000702452010-01-0707 January 2010
Acceptance Review E-mail, Exemption from 10 CFR Part 73 Physical Security Requirements
ML0935800682009-12-23023 December 2009
Acceptance Review E-mail License Amendment Request to Revise Technical Specification 3.8.1, AC Sources-Operating.
ML0915902212009-06-0808 June 2009
Acceptance Review Email, License Amendment Request, Revise Technical Specifications 5.5.9, Steam Generator Program, and 5.6.10, Steam Generator Tube Inspection Report, for Permanent Alternate Repair Criteria
ML0908901552009-03-30030 March 2009
Acceptance Review Email, License Amendment Request, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
ML0829102482008-10-15015 October 2008
Acceptance Review Email, Relief Request 13 R-06, Alternatives to Requirements of ASME Code, Section XI for Class 1 Piping Welds Examined from Inside Reactor Vessel
ML0826102092008-09-17017 September 2008
Acceptance Review Email, License Amendment Request to Revise Technical Specifications 3.3.2 and 3.7.2, and Addition of TS 3.7.19
ML0826101852008-09-17017 September 2008
Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.5.2, ECCS - Operating, in Accordance with TSTF-325A
ML0825403192008-09-10010 September 2008
Acceptance Review Email Re Application to Revise Technical Specification 3.3.2 - Wolf Creek
ML0713805112007-05-29029 May 2007
Acceptance Review of Licensee'S Application for Main Steam and Feedwater Isolation System Controls Modification
2021-10-22
[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
[Table view] |
Text
October 22, 2021 Mr. Cleveland Reasoner Chief Executive Officer and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION, UNIT 1 - WITHDRAWAL OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT AND REGULATORY EXEMPTION FOR A RISK-INFORMED APPROACH TO ADDRESS GENERIC SAFETY ISSUE 191 AND RESPOND TO GENERIC LETTER 2004-02 (EPID L-2021-LLA-0152 AND EPID L-2021-LLE-0039)
Dear Mr. Reasoner:
By letter dated August 12, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21224A118), as supplemented by letter dated October 11, 2021 (ADAMS Accession No. ML21284A013), Wolf Creek Nuclear Operating Corporation (the licensee) submitted an application requesting a license amendment that would revise the licensing basis as described in the Wolf Creek Generating Station Updated Safety Analysis Report to allow the use of a risk-informed approach to address potential issues discussed in Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on PWR [Pressurized-Water Reactor] Sump Performance, and respond to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, dated September 13, 2004 (ADAMS Accession No. ML042360586).
Additionally, the licensee requested an exemption from certain requirements in Section 50.46(a)(1) of Title 10 of the Code of Federal Regulations (10 CFR) in accordance with the provisions of 10 CFR 50.12, Specific exemptions. The licensees application was submitted following the guidance in Regulatory Guide 1.174, Revision 3, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, dated January 2018 (ADAMS Accession No. ML17317A256).
The U.S. Nuclear Regulatory Commission (NRC) staff has been performing an acceptance review of the application. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. By letter dated September 23, 2021 (ADAMS Accession No. ML21253A090), the NRC staff identified that information addressing details and quality of probabilistic risk assessment (PRA) was needed to begin its technical review.
C. Reasoner Consistent with 10 CFR 50.90, an application for an amendment to a license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal addresses the design and operating characteristics, unusual or novel design features, and principal safety considerations.
Consistent with 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of the regulations of this part, which are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense, and security. The Commission will not consider granting an exemption unless special circumstances are present, as specified in 10 CFR 50.12(a)(2).
By letter dated October 20, 2021 (ADAMS Accession No. ML21294A051), the licensee requested to withdraw the application from NRC review. The NRC acknowledges the licensees request to withdraw the application. NRC staff activities on the review have ceased and the associated Cost Activity Code numbers have been closed.
The NRC staff notes that its review to date has identified that the quality of the PRA analysis used to support this application in terms of its appropriateness with respect to scope, level of detail, and technical acceptability is indeterminate. Therefore, should the licensee decide to resubmit the request, it should follow the guidance in Regulatory Guide 1.174 as stated in its October 20, 2021 letter.
If you have any questions, please contact me at 301-415-3168 or via e-mail at Samson.Lee@nrc.gov.
Sincerely,
/RA/
Samson S. Lee, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 cc: Listserv
ML21294A079 *concurrence via e-mail OFFICE NRR/DORL/LPL4/PM* NRR/DORL/LPL4/LA* NRR/DRA/APLB/BC* NRR/DORL/LPL4/BC*
NAME SLee PBlechman JWhitman JDixon-Herrity DATE 10/20/2021 10/21/2021 10/20/2021 10/22/2021 OFFICE NRR/DORL/LPL4/PM*
NAME SLee DATE 10/22/2021
