Letter Sequence Request |
|---|
EPID:L-2022-LLR-0043, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads (Withdrawn, Closed) |
|
|
|
|---|
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
Michael T. Boyce Vice President Engineering May 12, 2022 ET 22-0009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Reference:
Letter ET 22-0003, dated April 6, 2022, from M. T. Boyce, WCNOC, to USNRC
Subject:
Docket No. 50-482: Withdrawal of 10 CFR 50.55a Request I4R-09, Relief from Examination of Reactor Vessel Flange Threads Commissioners and Staff:
The purpose of this submittal is to withdraw Wolf Creek Nuclear Operating Corporation (WCNOC) 10 CFR 50.55a Request originally provided by the Reference. The Reference transmitted 10 CFR 50.55a Request I4R-09 for an alternative to the requirement of the American Society of Mechanical Engineers (ASME) Code,Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange, to perform ultrasonic examinations of threads in reactor pressure vessel closure flange connections every inservice inspection (ISI) interval. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.147, Revision 20 was effective as of April 4, 2022.
In this revision, ASME Section XI Code Case N-864 was conditionally approved by the NRC.
Code Case N-864 allows that reactor pressure vessel threads in flange examinations be performed in at least every third 10-year ISI interval. The conditions include that monitoring and maintenance activities must be performed and documented to monitor the condition of the reactor pressure vessel threads in flange for signs of degradation and to mitigate any degradation that occurs. WCNOC plans to evaluate the use of this Code Case and implement appropriate necessary actions to meet these conditions. Therefore, WCNOC is withdrawing the proposed request and is no longer seeking NRC review and approval of I4R-09.
P.O. Box 411 l Burlington, KS 66839 l 620-364-8831
ET 22-0009 Page 2 of 2 This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-8831 x8687, or Ron Benham at (620) 364-4204.
Sincerely, Michael T. Boyce MTB/rlt cc: S. S. Lee (NRC)
S. A. Morris, (NRC)
G. E. Werner (NRC)
Senior Resident Inspector (NRC)
