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List of results

• 10 CFR 72.74, Reports of Accidental Criticality Or Loss of Special Nuclear Material  + (Reports of accidental criticality or loss of special nuclear material)
• 10 CFR 60.73, Reports of Deficiencies  + (Reports of deficiencies)
• 10 CFR 63.73, Reports of Deficiencies  + (Reports of deficiencies)
• 10 CFR 20.2203  + (Reports of exposures, radiation levels, and concentrations of radioactive material exceeding the constraints or limits)
• 10 CFR 20.2206  + (Reports of individual monitoring)
• 10 CFR 74.11, Reports of Loss Or Theft Or Attempted Theft Or Unauthorized Production of Special Nuclear Material  + (General Reporting and Recordkeeping Requirements)
• 10 CFR 20.2204  + (Reports of planned special exposures)
• 10 CFR 20.2207  + (Reports of transactions involving nationally tracked sources)
• 10 CFR 7.17, Reports Required for Advisory Committees  + (Reports required for advisory committees)
• 10 CFR 20.2205  + (Reports to individuals of exceeding dose limits)
• 10 CFR 60.65, Representation  + (Representation)
• 10 CFR 63.65, Representation  + (Representation)
• 10 CFR 72.206, Representation  + (Representation)
• 10 CFR 63.332, Representative Volume  + (Representative volume)
• 10 CFR 55.59, Requalification  + (Requalification)
• EPID:L-2019-LLR-0013  + (Request Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (Request 2-TYP-4-RV-05, Revision 0))
• NRC Generic Letter 78-03, Request For Information On Cavity Annulus Seal Ring  + (Request For Information On Cavity Annulus Seal Ring)
• NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f)  + (Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f))
• NRC Generic Letter 87-05, Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells  + (Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells)
• EPID:L-2018-LLA-0270  + (Request for Additional Information License Amendment Request 18-04 Csa)
• EPID:L2020  + (Request for Additional Information Regarding Steam Generator Tube Inspection Reports (EPIDs L2020-LRO-0055, L-2020-LRO-0082, and L2020-LRO-0083))
• EPID:L-2017-TOP-0067  + (Request for Additional Information Regarding Topical Report ANP-10346P, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA)
• EPID:L-2023-LRO-0058  + (Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports)
• EPID:L-2018-LLA-0139  + (Request for Additional Information for License Amendment Request for Global Nuclear Fuel-Americas (Enterprise Project Identification L-2018-LLA-0139))
• EPID:L-2017-TOP-0064  + (Request for Additional Information for Westinghouse Electric Company Topical Report WCAP-16260-P/WCAP-16260-NP, Revision 2, the Spatially Corrected Inverse Count Rate Method for Subcritical Reactivity Measurement)

• NRC Generic Letter 80-15, Request for Additional Management and Technical Resources Information  + (Request for Additional Management and Technical Resources Information)

• EPID:L-2021-LLA-0204  + (Request for Alternate Disposal Approval and Exemption for Specific Columbia Fuel Fabrication Waste)
• EPID:L-2017-LLR-0126  + (Request for Alternative (VEGP 3 & 4-PSI/ISI-ALT-9))
• EPID:L-2021-LLR-0049  + (Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval)
• EPID:L-2018-LLR-0126  + (Request for Alternative Follow-up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2))
• EPID:L-2022-LLR-0079  + (Request for Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds)
• EPID:L-2021-LLR-0041  + (Request for Alternative Requirements for ASME Section III Remediation of Containment Vessel Unistrut Welding (VEGP 3-ALT-16))
• EPID:L-2021-LLR-0004  + (Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Intervals)
• EPID:L-2023-LLR-0028  + (Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037))
• EPID:L-2018-LLR-0027  + (Request for Alternative from Volumetric/Surface Examination Frequency Requirement of ASME Code Case N-729-4, Request Number Isir 04-5, Revision 1)
• EPID:L-2018-LLR-0388  + (Request for Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii) Proposed Alternative to CFR 50.55a Examination Requirements for Third Interval Volumetric Exams (RBS-ISI-021))
• EPID:L-2018-LLR-0042  + (Request for Alternative in Accordance with 10 CFR 50.55a (g)(5)(iii) Proposed Alternative to 10 CFR 50.55a Examination Requirements for Pressure Retaining Welds in Control Rod Housings (RR-RBS-ISI-016))
• EPID:L-2019-LLR-0119  + (Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period)
• EPID:L-2020-LLR-0150  + (Request for Alternative to 10 CFR 50.55a(g)(6)(ii)(D) Examination Requirements - Relief Request ANO2-ISI-022)
• EPID:L-2020-LLR-0036  + (Request for Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW) System Piping)
• EPID:L-2024-LLA-0081  + (Request for Alternative to Extend First Containment Inservice Inspection Interval)
• EPID:L-2024-LLR-0081  + (Request for Alternative to Extend First Containment Inservice Inspection Interval)
• EPID:L-2021-LLR-0019  + (Request for Alternative, 21-ISI-1 Alternative Repair and Examination for Mid Canopy Seal Weld Replacement)
• EPID:L-2021-LLR-0059  + (Request for Alternative, 21-ISI-2, Alternative Inspection for Upper Head Injection J-groove Welds)
• EPID:L-2022-LLR-0008  + (Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(b) and the Use of Case N-526)
• EPID:L-2019-LLR-0025  + (Request for Alternative: Alternative Requirements for Preservice Testing of Class 1 Safety Valves (VEGP 3&4-PST-ALT-02))
• EPID:L-2021-LLR-0006  + (Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2))
• EPID:L-2024-LLR-0022  + (Request for Approval of Alternative Request N1-I5-NDE-007 to Deter Additional Required Reactor Coolant Pump Casing Inspection)
• EPID:L-2022-LLT-0003  + (Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code)
• EPID:L-2018-LLA-0054  + (Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping)
• EPID:L-2019-LLL-0003  + (Request for Approval of Certified Fuel Handler Training Program)