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List of results

• ML25139A530  + (LTR-25-0210 Todd Abrajano, President and Ceo,Nuclear Industry Council (Usnic), Et Al., Letter Re Endorsement for Clearpath, the Clean Air Task Force, and Veriten, on Transformative Regulatory Reform for New Reactors)
• ML25139A429  + (LTR-25-0211 Peter Hastings, PE, Vice President, Regulatory, Quality, and Public Affairs, Kairos Power, LLC, Letter Endorsement for Letter from Clearpath, the Clean Air Task Force, and Veriten on Transformative Regulatory Reform for New Reac)
• ML25175A323  + (LTR-25-0233 Joe Williams, Et Al., Former NRC Employees, Concerns Unprecedented Decision by the President to Fire Commissioner Hanson)
• ML25176A205  + (LTR-25-0236 Adam Croglia, Managing Director, Trysail Strategies, E-mail Joint Statement from Orano Group and Nrd, LLC, Regarding Partnership Agreement to Expand Americium-241 Production Capacity and Capabilities)
• ML25190A003  + (LTR-25-0244 Elizabeth Brackett, Certified Health Physicist, President, Health Physics Society, Specialists in Radiation Protection, Expresses Concern Regarding Scheduling of NRC Public Meeting on Executive Order 14300 Section 5(b))
• ML25192A194  + (LTR-25-0248 Elizabeth Brackett, Certified Health Physicist, President, Specialists in Radiation Protection, Health Physics Society, Letter Continued Independence of the Nuclear Regulatory Commission Is Essential to Reinvigorating the Nuclea)
• ML25198A101  + (LTR-25-0251 Karen Hadden, Texas Nuclear Watchdogs, Et Al., E-mail Request for Public Comment Period, Public Meeting, Deadline Extension and Environmental Impact Statement Requirement for Long Mott Energy Application)
• ML25204A176  + (LTR-25-0257 Judith M. Greenwald, President and CEO, Nuclear Innovation Alliance, Ltr Commends NRC for Progress in Implementation of the Advance Act and Executive Orders)
• ML25212A217  + (LTR-25-0263 Douglas True, Sr. Vice President & Chief Nuclear Officer, Nuclear Energy Institute, Ltr Industry Recommendations on Accelerating NRC Reform)
• ML25223A314  + (LTR-25-0271 Senator Cynthia Lummis, Et Al., Ltr Appreciation for the U.S. NRCs Efforts to Enable the Deployment of Innovative Technology to Help Remediate Abandoned Uranium Mines)
• ML25223A315  + (LTR-25-0271 Senator Cynthia Lummis, Et Al., Ltr Appreciation for the U.S. NRCs Efforts to Enable the Deployment of Innovative Technology to Help Remediate Abandoned Uranium Mines)
• ML25239A090  + (LTR-25-0275 - Enclosure - Information About Staffing at the NRC Report)
• ML25226A248  + (LTR-25-0275 Senator Sheldon Whitehouse, Ranking Member, Committee on Environment and Public Works, Ltr Request for Information About Staffing at the NRC)
• ML25226A249  + (LTR-25-0275 Senator Sheldon Whitehouse, Ranking Member, Committee on Environment and Public Works, Ltr Request for Information About Staffing at the NRC)
• ML25227A209  + (LTR-25-0276 Representative Robert Garcia, Ranking Member, Committee on Oversight and Government Reform, Et Al., Ltr the Independence and Mission of Federal Inspector Generals)
• ML25230A172  + (LTR-25-0278 Judi Greenwald, President and CEO, Nuclear Innovation Alliance, Letter Provides Recommendations on Priorities for Near-Term NRC Reforms)
• ML25241A102  + (LTR-25-0285 Cy Mcneill, Director, Federal Affairs, Data Center Coalition, Letter Encourages NRC to Support Streamlining Nuclear Regulation to Ensure Nuclear Remains a Safe Viable Option to Meet Growing Energy Demand and Power the Economy)
• ML14269A323  + (LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data)
• ML14269A325  + (LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process)
• L-MT-14-075, LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set 8.  + (LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #8.)
• L-MT-14-075, LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set 8  + (LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set 8)

• ML21204A079  + (LTR-Byron 73.55 Exemption)
• EPID:L-2020-LLE-0154  + (LTR-Byron 73.55 Exemption)

• ML050740027  + (LTR-CDME-04-148, Rev 1, Application of W* Alternate Repair Criteria to Sequoyah Unit 2. (Non-Proprietary Version))
• ML053630145  + (LTR-CDME-05-180-NP, Rev 2, Steam Generator Tube Alternate Repair Criteria for the Portion of the Tube within the Tubesheet at Catawba 2)
• ML051540343  + (LTR-CDME-05-32-NP, Rev. 1, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet at Byron 2 & Braidwood 2)
• RS-05-129, LTR-CDME-05-32-NP, Rev. 2, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet at Byron 2 & Braidwood 2  + (LTR-CDME-05-32-NP, Rev. 2, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet at Byron 2 & Braidwood 2)
• ML051120341  + (LTR-CDME-05-82-NP, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet at Wolf Creek Generating Station)
• ML060670436  + (LTR-CDME-06-17-NP, Steam Generator Tube Alternate Repair Criteria for the Portion of the Tube within the Tubesheet at Catawba 2 in Support of Cycle 15 Operation)
• ML061240326  + (LTR-CDME-06-27-NP, Revision 0, Responses to NRC Request for Addition Information on License Amendment Request for Proposed Technical Specification Change Regarding Repair Criteria and Inspection Depth for Steam Generator Tubes)
• ET 07-0043, LTR-CDME-07-198 NP-Attachment, Response to NRC RAI Relating to LTR-CDME-07-72 P-Attachment and LTR-CDME-05-209-P of the Wolf Creek Generating Station (WCGS) Permanent B* License Amendment Request  + (LTR-CDME-07-198 NP-Attachment, Response to NRC RAI Relating to LTR-CDME-07-72 P-Attachment and LTR-CDME-05-209-P of the Wolf Creek Generating Station (WCGS) Permanent B* License Amendment Request)
• ML070640062  + (LTR-CDME-07-22-NP, Revision 0, Responses to NRC Requests for Additional Information Re the Application of WCAP-16208-P, Revision 1, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions, to the Palisades Nuclear)
• NL-08-0148, LTR-CDME-08-11 Np, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone  + (LTR-CDME-08-11 Np, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone)
• RS-08-075, LTR-CDME-08-11, Rev. 3 Np, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone  + (LTR-CDME-08-11, Rev. 3 Np, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone)
• ET 08-0016, LTR-CDME-08-43 NP-Attachment, Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment  + (LTR-CDME-08-43 NP-Attachment, Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment)
• ML14125A091  + (LTR-LaCrosse ISFSI Security 05000409, 07200046 Acknowledgement Letter - Response to NOV EA-14-027)
• ML043280626  + (LTR-ME-02-15, Rev 00, MNSA2 Belleville Washer Data)
• ML19288A174  + (LTR-NRC-18-30 U.S. Nuclear Regulatory Commission 10 CFR 50.46 Annual Notification and Reporting for 2017 (Non-Proprietary))
• ML24037A020  + (LTR-NRC-2024-01 Mackson-Duke 10CFR Part 21 Final Notification and Closure 2.2.2024)
• NOC-AE-15003250, LTR-PAFM- 15-27-NP, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary)  + (LTR-PAFM- 15-27-NP, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary))
• ML15133A131  + (LTR-PAFM- 15-27-NP, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary))
• ML070660129  + (LTR-PAFM-07-12, Technical Basis for Relaxation Request from NRC Order EA-03-009 for Millstone Unit 3)
• NL-08-019, LTR-PAFM-08-4, Revision 0, Technical Basis to Support Extension of Surveillance Interval for Planned Visual Inspection of the Indian Point, Unit 2 Bmi Nozzles  + (LTR-PAFM-08-4, Revision 0, Technical Basis to Support Extension of Surveillance Interval for Planned Visual Inspection of the Indian Point, Unit 2 Bmi Nozzles)
• LIC-10-0065, LTR-PAFM-10-123-NP, Rev. 0, Technical Justification to Support Alternative Visual Examination Intervals for Fort Calhoun Reactor Vessel Outlet Nozzle to Safe End Dissimilar Metal Welds, Enclosure 2  + (LTR-PAFM-10-123-NP, Rev. 0, Technical Justification to Support Alternative Visual Examination Intervals for Fort Calhoun Reactor Vessel Outlet Nozzle to Safe End Dissimilar Metal Welds, Enclosure 2)
• ML14006A319  + (LTR-PAFM-10-50-NP, Rev. 0, Section XI Flaw Evaluation of Indication Recorded on RC-32-MRCL-ALL-03 of the Point Beach Unit 1 Inlet Nozzle to Pipe Weld)
• NL-11-123, LTR-PAFM-11-136-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds  + (LTR-PAFM-11-136-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds)
• RC-12-0170, LTR-PAFM-12-137-NP, Rev. 1, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer, Unit 1, Reactor Vessel Head Penetration Nozzles  + (LTR-PAFM-12-137-NP, Rev. 1, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer, Unit 1, Reactor Vessel Head Penetration Nozzles)