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Category:Letter
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Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements
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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)
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License Amendment Request to Modify the Implementation Date of License Amendment No. 238
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Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version)
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Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information
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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
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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
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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
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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)
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2022 Annual Radioactive Effluent Release Report Report 46
2024-01-04
[Table view] |
Text
June 20, 2007 Alex Marion, Executive Director Nuclear Energy Institute Nuclear Operations and Engineering 1776 I Street, N.W.
Washington, DC 20006-3708
Dear Mr. Marion,
In a February 14, 2007, letter from Jay Thayer, Nuclear Energy Institute (NEI) to J.E. Dyer, U.S. Nuclear Regulatory Commission (NRC), he proposed that industry perform advanced finite element fracture mechanics analyses to address NRC staff concerns that rupture could occur in pressurizer dissimilar metal nozzle welds without prior evidence of leakage (ML070600672).
Consistent with the project plan described in Mr. Thayers letter, on March 20, 2007 the Electric Power Research Institute provided results of the Phase I draft calculation to the Expert Review Panel for Advanced Finite Element Analysis (FEA) Crack Growth Calculations (ML070940229).
This calculation was performed by Dominion Engineering, Inc.
On April 4, 2007, I sent you a letter (ML070940186) to document NRC staff comments and concerns regarding the Phase I draft calculation. In the letter, I indicated that a technical basis document would be provided with additional information related to an NRC staff concern regarding the industrys approach for calculating crack stability. This NRC staff document was provided to the industry prior to the meeting held on this subject on April 9, 2007. Since that time, the technical basis document has been finalized. This letter serves to formally provide you with the final version of that document. The content and scope of the enclosure is essentially unchanged in content and scope from the earlier version.
The NRC staffs final report on the Wolf Creek pressurizer nozzle weld scoping study is also attached. Work on this document was begun in early November 2006, and it contains the results of the staffs scoping fracture mechanics analyses on the pressurizer nozzle weld flaws found at Wolf Creek. The NRC staff discussed the analyses that are documented in this report
A. Marion during public meetings that took place on November 30, 2006, and December 20, 2006, and during Advisory Committee on Reactor Safeguards (ACRS) meetings held on February 2, 2007, and March 6, 2007. A draft version of this report was provided to the ACRS and has since been updated to include the results of leakage calculations.
Sincerely,
/RA/
Michele G. Evans, Director Division of Component Integrity Office of Nuclear Reactor Regulation
Enclosures:
- 1. Technical Note on Critical Flaw Size Evaluations for Circumferential Cracks in Dissimilar Metal Welds
- 2. Evaluation of Circumferential Indications in Pressurizer Nozzle Dissimilar Metal Welds at the Wolf Creek Power Plant CC: A. Marion, NEI J. Thayer, NEI C. King, EPRI C. Harrington, EPRI D. Weakland, MRP J. Gasser, MRP D. Rudland, EMCC G. Wilkowski, EMCC
A. Marion during public meetings that took place on November 30, 2006, and December 20, 2006, and during Advisory Committee on Reactor Safeguards (ACRS) meetings held on February 2, 2007, and March 6, 2007. A draft version of this report was provided to the ACRS and has since been updated to include the results of leakage calculations.
Sincerely,
/RA/
Michele G. Evans, Director Division of Component Integrity Office of Nuclear Reactor Regulation
Enclosures:
- 1. Technical Note on Critical Flaw Size Evaluations for Circumferential Cracks in Dissimilar Metal Welds
- 2. Evaluation of Circumferential Indications in Pressurizer Nozzle Dissimilar Metal Welds at the Wolf Creek Power Plant CC: A. Marion, NEI J. Thayer, NEI C. King, EPRI C. Harrington, EPRI D. Weakland, MRP J. Gasser, MRP D. Rudland, EMCC G. Wilkowski, EMCC ADAMS Package Accession No.: ML071560363 OFFICE NRR/DCI NRRA/DCI NAME ESullivan MEvans DATE 06/ 8 /07 06/ 20 /07 OFFICIAL RECORD COPY
