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Category:Letter
MONTHYEARIR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230112024-08-0707 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20200012024-08-0606 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 - Integrated Inspection Report 05000237/2020001 and 05000249/2020001 ML24184A1712024-08-0202 August 2024 SLRA Schedule Letter RS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24193A0882024-07-24024 July 2024 Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Unit 1 Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations (Docket 50-10) ML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, “Safety Limit Mcpr” ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter ML24156A2332024-06-11011 June 2024 Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24145A0432024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel 10 CFR 72.212 ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel ML24158A0012024-05-22022 May 2024 License Amendment Request to Adopt TSTF-564 (EPID L-2023-LLA-0120) Illinois State Concurrence ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24135A0722024-05-10010 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report ML24129A1352024-05-0808 May 2024 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-59 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24092A3412024-05-0101 May 2024 SLRA - Receipt and Availability - Letter IR 05000237/20240012024-05-0101 May 2024 Integrated Inspection Report 05000237/2024001 & 05000249/2024001 ML24127A0982024-04-30030 April 2024 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24120A2032024-04-29029 April 2024 Operator Licensing Exam Approval - Dresden Nuclear Power Station, May 2024 IR 05000237/20244012024-04-18018 April 2024 – Security Baseline Inspection Report 05000237/2024401 and 05000249/2024401 ML24108A0082024-04-17017 April 2024 Application for Renewed Operating License RS-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24083A0022024-03-22022 March 2024 IEMA-OHS Comment Dresden HI-STORM Exemption EA & Fonsi SVPLTR 24-0010, Owners Activity Report (OAR-1) for D2R282024-03-15015 March 2024 Owners Activity Report (OAR-1) for D2R28 RS-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24061A1702024-03-0101 March 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230062024-02-28028 February 2024 Annual Assessment Letter for Dresden Nuclear Station, Units 2 and 3 (Report 05000237/2023006; 05000249/2023006) RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS ML24179A2232024-02-12012 February 2024 ILT 23-1 (2024-301) SVP Letter - 24-007 ILT Exam Submittal IR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) 2024-08-09
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RS-06-040 March 10, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249
Subject:
Additional Information Supporting Relief Request CR-28, Inservice Inspection Program Relief Regarding Reactor Pressure Vessel Longitudinal Shell Weld Examination Coverage for Third 10-Year Inservice Inspection Interval References
- 1. Letter from D. Bost (Exelon Generation Company, LLC) to U.S. NRC, "Relief Request CR-28, Inservice Inspection Program Relief Regarding Reactor Pressure Vessel Longitudinal Shell Weld Examination Coverage for Third 10-Year Inservice Inspection Interval," dated May 6, 2005 2. Letter from M. Banedee (U. S. NRC) to C. M. Crane (Exelon Generation Company, LLC), "Dresden Nuclear Power Station, Unit 3 - Request for Additional Information Related to Relief Request CR-28 (TAC No. MC7068)," dated February 22, 2006 In Reference 1, Exelon Generation Company, LLC (EGC) requested relief from American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," and the augmented examinations specified in 10 CFR 50.55a, "Codes and standards," paragraph (g)(6)(ii)(A)(2). Specifically, relief was requested for Unit 3 reactor pressure vessel longitudinal shell weld examinations where the inspection coverage achieved during the third 10-year inservice inspection interval was less than or equal to 90 percent. In Reference 2, the NRC requested additional information to complete review of the Reference 1 relief request. In response to this request, EGC is providing the attached information.
March 10, 2006 U. S. Nuclear Regulatory Commission Page 2 There are no regulatory commitments contained in this letter. Should you have any questions related to this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803. Respectfully, Patrick R. Simpson Manager - Licensing Attachment
- Response to Request for Additional Information NRC Request Response ATTACHMENT Response to Request for Additional Information By letter dated March 23, 2005, the NFIC approved an alternative Reactor Pressure Vessel (RPV) weld examination pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(1) and 10 CFR 50.55a(g)(6)(ii)(A)(5) for Dresden Nuclear Power Station, Units 2 and 3 (Dresden 2 and 3) that allows permanent deferral of the requirements to perform a volumetric examination of the RPV circumferential welds for the extended operating license terms for Dresden 2 and 3. This alternative requires examinations of essentially 100 percent of all longitudinal welds and examinations of approximately 2 to 3 percent of the circumferential welds at their points of intersection with the longitudinal welds. In proposed Relief Request CR-28, Exelon did not indicate the extent to which the reduced examination volumes for the RPV longitudinal welds, as specified in the attachment to their May 6, 2005, letter, included the points of intersection with the circumferential welds. Please provide supplemental information indicating whether the reduced examination volumes for the specified Dresden 3 RPV longitudinal welds included all of the points of intersection with the circumferential welds. In addition, please indicate whether 2 to 3 percent volumetric coverage of the circumferential welds in the vicinity of the points of intersection with the longitudinal welds was achieved. The reduced examination volumes for the specified RPV longitudinal welds did not include all the points of intersection with the circumferential welds. The examinations were completed to the extent practical and no unacceptable flaws were identified. The Unit 3 RPV has 14 longitudinal welds and five circumferential welds (i.e., four RPV circumferential shell welds and one RPV shell-to-flange weld). There are 28 intersections with the five circumferential welds. The determination of which intersections could be inspected was based on a review of outage reports for RPV examinations performed in the two most recent Unit 3 refueling outages, in conjunction with individuals who were involved with the inspections. Of the 28 intersections, 21 were examined, and the 2-3 percent coverage requirement was met for all circumferential welds except the 3-LHD-SC1 weld. Due to jet pump diffuser interferences, coverage was limited to 0.92 percent for the 3-LHD-SC1 weld. Additional coverage limitation details are provided in Table CR-28.1 of proposed Relief Request CR-28. The extent to which the reduced examination volumes for the RPV longitudinal welds included points of intersection with the circumferential welds is summarized in the following table. This table also identifies the percent volumetric coverage of the circumferential welds in the vicinity of the points of intersection with the longitudinal welds. Circumferential Weld Total Intersections In t rsections Inspected Percent Coverage 31HEYSC1 3 1 0.92% 3-SC 1-SC2 6 5 4.6% 3-SC2-SC3 7 4 3.6% 3-SC3-SC4 8 8 7.3% 3-SC4-FLG (RPV shell-to-flange weld) 4 3 2.7%