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List of results

• LR-N16-0015, Supplemental Information for License Amendment to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation  + (Supplemental Information for License Amendment to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation)
• L-2017-188, Supplemental Information for License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents  + (Supplemental Information for License Amendment Request 255, Relocate the Explosive Gas Monitoring, Gas Decay Tanks and Standby Feedwater System Technical Specifications to Licensee Controlled Documents)
• L-05-198, Supplemental Information for License Amendment Request  + (Supplemental Information for License Amendment Request)
• L-05-154, Supplemental Information for License Amendment Request Nos. 302 and 173  + (Supplemental Information for License Amendment Request Nos. 302 and 173)
• RA-03-160, Supplemental Information for License No. DPR-36, Request for Exemption from NRC Certificate of Compliance No. 1015, Amendment 2, Technical Specification B3.4.2.6  + (Supplemental Information for License No. DPR-36, Request for Exemption from NRC Certificate of Compliance No. 1015, Amendment 2, Technical Specification B3.4.2.6)
• GNRO-2007/00050, Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability  + (Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability)
• RBG-46722, Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability  + (Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability)
• ML20093B468  + (Supplemental Information for MCNP6 Area of Applicability and Qualification for NEDO-33866 Revision 6)
• EPID:L-2019-LLA-0168  + (Supplemental Information for MCNP6 Area of Applicability and Qualification for NEDO-33866 Revision 6)
• RA-20-0113, Supplemental Information for Measurement Uncertainty Recapture Power Uprate License Amendment Request  + (Supplemental Information for Measurement Uncertainty Recapture Power Uprate License Amendment Request)
• ML021910088  + (Supplemental Information for Meeting Summary for End-of-Cycle Performance Assessment)
• NMP2L2746, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2  + (Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2)
• NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2  + (Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2)
• ML16019A368  + (Supplemental Information for PVNGS License Amendment Request to Adopt TSTF-439-A)
• ML081970325  + (Supplemental Information for Partial Site Release)
• GO2-19-073, Supplemental Information for Plant Decommissioning Fund Status Report  + (Supplemental Information for Plant Decommissioning Fund Status Report)
• ML041270484  + (Supplemental Information for Plant License Renewal Application - Aging Management Program Audit)
• PLA-5586, Supplemental Information for Proposed Amendment No. 211 to Unit 2 License NPF-22:MCPR Safety Limits & Reference Changes  + (Supplemental Information for Proposed Amendment No. 211 to Unit 2 License NPF-22:MCPR Safety Limits & Reference Changes)
• ML102430164  + (Supplemental Information for Proposed License Amendment Request Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program)
• PLA-5743, Supplemental Information for Proposed Relief Requests No. 29 and 30 to the Second 10-Year Inservice Inspection Program for Susquehanna Ses Unit 1  + (Supplemental Information for Proposed Relief Requests No. 29 and 30 to the Second 10-Year Inservice Inspection Program for Susquehanna Ses Unit 1)
• ML12356A298  + (Supplemental Information for Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process)
• ML22160A411  + (Supplemental Information for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2)
• ML082060625  + (Supplemental Information for RCS Leakage Detection RAI License Amendment Request (Lbdcrs 07-MP2-012 and 07-MP3-032))
• ML040140510  + (Supplemental Information for Realistic Large Break Loss of Coolant Accident (Rlbloca) Containment Pressure Analysis Proposed Technical Specifications Change & Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel)
• ML032731445  + (Supplemental Information for Realistic Large Break Loss of Coolant Accident (Rlbloca) Analysis Results Proposed Technical Specifications Changes and Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel)
• LIC-05-0043, Supplemental Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors  + (Supplemental Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors)

• NL-03-0865, Supplemental Information for Relaxation Request to Order EA-03-009  + (Supplemental Information for Relaxation Request to Order EA-03-009)
• NL-04-0115, Supplemental Information for Relaxation Request to Order EA-03-009  + (Supplemental Information for Relaxation Request to Order EA-03-009)

• ML14051A166  + (Supplemental Information for Relief Request IP3-ISI-RR-07 for Code Case N-770-1 Weld Inspection Frequency Extension)
• RA-22-0025, Supplemental Information for Relief Request to Utilize an Alternative Acceptance Criteria for Code Case, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material  + (Supplemental Information for Relief Request to Utilize an Alternative Acceptance Criteria for Code Case, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material)
• ML12080A102  + (Supplemental Information for Relief Request, Dissimilar Metal Butt Welds Baseline Examinations (RR-ISI-04-06A))
• ML12264A591  + (Supplemental Information for Relief Request Number ISI-09 R. E. Ginna Nuclear Power Plant - Fifth Interval Inservice Inspection Program Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii) Component Cooling Water 1 Inch Half-Cou)
• ML031420481  + (Supplemental Information for Relief Request HC-RR-B11)
• ML12074A179  + (Supplemental Information for Relief for Unit 1 Dissimilar Metal Butt Welds Baseline Examinations (RR-ISI-04-06A))
• ML031680441  + (Supplemental Information for Request for Relief from American Society of Mechanical Engineers (ASME) Code for Replacement of ASME Class 3 Piping)
• RNP-RA/10-0019, Supplemental Information for Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria  + (Supplemental Information for Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria)
• RS-15-118, Supplemental Information for Request for Relaxation of Condition V(A)(A.1 (1) of Confirmatory Order EA-13-068  + (Supplemental Information for Request for Relaxation of Condition V(A)(A.1 (1) of Confirmatory Order EA-13-068)
• CNRO-2005-00017, Supplemental Information for Request for Alternative ANO2-R&R-003, Proposed Alternative to ASME Requirements for Weld Repairs  + (Supplemental Information for Request for Alternative ANO2-R&R-003, Proposed Alternative to ASME Requirements for Weld Repairs)
• ML090760827  + (Supplemental Information for Request for Amendment to Technical Specification 5.6.5b, Core Operating Limits Report)
• ULNRC-06920, Supplemental Information for Requests for Relief from Inservice Inspection Requirements of ASME Boiler Pressure Vessel Code, Section XI for the Instrument Tunnel Sump Liner  + (Supplemental Information for Requests for Relief from Inservice Inspection Requirements of ASME Boiler Pressure Vessel Code, Section XI for the Instrument Tunnel Sump Liner)
• LR-N17-0001, Supplemental Information for Response to Request for Additional Information, RAI-8- RAI-11, Aging Management Program Plan for Reactor Vessel Internals  + (Supplemental Information for Response to Request for Additional Information, RAI-8- RAI-11, Aging Management Program Plan for Reactor Vessel Internals)
• ULNRC-06591, Supplemental Information for Response to March, 2012 Information Request, Seismic Probabilistic Risk Assessment for Recommendation 2.1  + (Supplemental Information for Response to March, 2012 Information Request, Seismic Probabilistic Risk Assessment for Recommendation 2.1)
• ULNRC-06551, Supplemental Information for Response to March 12, 2012 Information Request, Seismic Probabilistic Risk Assessment for Recommendation 2.1  + (Supplemental Information for Response to March 12, 2012 Information Request, Seismic Probabilistic Risk Assessment for Recommendation 2.1)
• ML19325D662  + (Supplemental Information for Response to March 12, 2012 Information Request, Seismic Probabilistic Risk Assessment for Recommendation 2.1)
• LR-N17-0079, Supplemental Information for Response to Request for Additional Information, Aging Management Program Plan for Reactor Vessel Internals  + (Supplemental Information for Response to Request for Additional Information, Aging Management Program Plan for Reactor Vessel Internals)
• WO 14-0032, Supplemental Information for Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis  + (Supplemental Information for Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis)
• ML061380109  + (Supplemental Information for Response to NRC Request for Additional Information, Dated March 30, 2006, Related to Plant License Renewal Application)
• ML110490570  + (Supplemental Information for Review of Developmental Revision a of the Unit 2 Technical Specifications (TS) and Technical Specifications Bases (TS Bases))
• ML100470795  + (Supplemental Information for Review of License Renewal Application-Aging Management Review/Aging Management Program)
• L-09-243, Supplemental Information for Review of License Renewal Application and License Renewal Application Amendment No. 41  + (Supplemental Information for Review of License Renewal Application and License Renewal Application Amendment No. 41)
• ML103270580  + (Supplemental Information for Review of License Renewal Application)
• ML21361A222  + (Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 2, Site Characteristics, Sections 2.0 to 2.4 (Redacted))