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List of results

• Research and Test Reactors Licensing Projects Branch  + (Research and Test Reactors Licensing Projects Branch)
• Research and Test Reactors Oversight Branch  + (Research and Test Reactors Oversight Branch)
• Research and Test Reactors Oversight Projects Branch  + (Research and Test Reactors Oversight Projects Branch)
• 10 CFR 26.25, Reserved  + (Reserved)
• 10 CFR 52.161, Reserved  + (Reserved)
• P.3  + (Resolution)
• EPID:L-2017-LLA-0414  + (Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A)
• NRC Generic Letter 80-19, Resolution of Enhanced Fission Gas Release Concern  + (Resolution of Enhanced Fission Gas Release Concern)
• NRC Generic Letter 89-11, Resolution of Generic Issue 101 "Boiling Water Reactor Water Level Redundancy"  + (Resolution of Generic Issue 101 "Boiling Water Reactor Water Level Redundancy")
• NRC Generic Letter 85-20, Resolution of Generic Issue 69: High Pressure Injection/Make-up Nozzle Cracking in Babcock And Wilcox Plants  + (Resolution of Generic Issue 69: High Pressure Injection/Make-up Nozzle Cracking in Babcock And Wilcox Plants)
• NRC Generic Letter 92-02, Resolution of Generic Issue 79, "Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown"  + (Resolution of Generic Issue 79, "Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown")
• NRC Generic Letter 91-06, Resolution of Generic Issue A-30, "Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54(f)  + (Resolution of Generic Issue A-30, "Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54(f))
• NRC Generic Letter 91-11, Resolution of Generic Issues 48, "LCOs for Class 1E Vital Instrument Buses," and 49, "Interlocks and LCOs for Class 1E Tie Breakers," Pursuant to 10 CFR 50.54  + (Resolution of Generic Issues 48, "LCOs for Class 1E Vital Instrument Buses," and 49, "Interlocks and LCOs for Class 1E Tie Breakers," Pursuant to 10 CFR 50.54)
• NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs"  + (Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs")
• NRC Generic Letter 88-03, Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps"  + (Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps")
• NRC Generic Letter 83-10f, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"  + (Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps")
• NRC Generic Letter 83-10e, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"  + (Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps")
• NRC Generic Letter 83-10d, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"  + (Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps")
• NRC Generic Letter 83-10c, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"  + (Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps")
• NRC Generic Letter 83-10b, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"  + (Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps")
• NRC Generic Letter 83-10a, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"  + (Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps")
• NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants"  + (Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants")
• 10 CFR 30.2  + (Resolution of conflict)
• 10 CFR 2.3, Resolution of Conflict  + (Resolution of conflict)
• 10 CFR 51.3, Resolution of Conflict  + (Resolution of conflict)

• 10 CFR 4.44, Resolution of Matters  + (Resolution of matters)

• NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f)  + (Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f))
• TSTF-536  + (Resolve CE Digital TS Inconsistencies Regarding Cpcs and Ceacs)
• H.1  + (Resources)
• 10 CFR 20.1701  + (Respiratory Protection and Controls to Restrict Internal Exposure in Restricted Areas)
• Response Coordination Branch  + (Response Coordination Branch)
• EPID:L-2024-LLA-0103  + (Response by Beyond Nuclear and Sierra Club to Joint Motion for Protective Order)
• EPID:L-2018-JLD-0003  + (Response to 03/12/2012 Information Request, Seismic Probabilistic Risk Assessment Supplement for Recommendation 2.1)
• EPID:L-2020-LLA-0131  + (Response to Final Request for Additional Information Regarding Revise Technical Specifications Requirements for High Pressure Coolant Injection System Inoperability)
• EPID:L-2019-JLD-0008  + (Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal)
• EPID:L-2018-JLD-0172  + (Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding: Integrated Assessment Submittal)
• EPID:L-2022-LLR-0053  + (Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(1) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review.)
• EPID:L-2020-JLD-0000  + (Response to March 12, Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal)
• EPID:L-2021-LLR-0045  + (Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 3)
• EPID:L-2019-LLA-0266  + (Response to Request for Addition Information Regarding Application to Adopt Title 10 of Code of Federal Regulations (CFR) 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and ...)
• EPID:L-2017-LLA-0406  + (Response to Request for Additional Information for Acceptance of License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years)
• EPID:L-2019-LLA-0004  + (Response to Request for Additional Information - License Amendment Request to Revise Existing Facility Operating License Conditions Regarding NFPA 805 Modifications)
• EPID:L-2021-LLA-0066  + (Response to Request for Additional Information Regarding License Amendment Request to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 0)
• EPID:L-2019-LLA-0232  + (Response to Request for Additional Information for the License Amendment Request to Change Technical Specifications to Increase Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance)
• EPID:L-2018-LLR-0051  + (Response to Request for Additional Information Pertaining to Relief Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds)
• EPID:L-2025-LLR-0035  + (Response to Request for Confirmatory Lnformation Regarding Relief Request RP-01)
• EPID:L-2018-LLM-0000  + (Response to Request for Withdrawal of COLs)
• EPID:L-2023-LRO-0052  + (Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line)
• EPID:L-2017-LLA-0420  + (Response to Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01)
• EPID:L-2018-LLA-0080  + (Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update)
• EPID:L-2020-LLA-0122  + (Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6)