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List of results

• ML19266A640  + (Additional NextEra Non-Disclosure Affidavits)
• ML25028A013  + (Additional Notes for Non-Federal Representatives)
• ML25253A489  + (Additional Observation for HI-STAR 330 for CoC No. 9397, Model Number HI-STAR 330)
• ML031360600  + (Additional Open Item Regarding a Pressurizer Weld Repair at Fort Calhoun Station, Unit 1)
• ML072150363  + (Additional Oregon State University Response to RAI Regarding License Renewal, Oregon State University Triga Reactor Dated May 21, 2007)
• ENS 46965  + (Additional Penetration Identified for Mitigation During Walkdown)
• ML053390048  + (Additional Petitioners Declarations)
• ML12053A019  + (Additional Planned Fire Risk Reduction Modifications)
• ML25272A274  + (Additional Post Exam Comments)
• ML040210004  + (Additional Post Examination Comments for the Prairie Island Initial Examination - September 2003)
• ML101300348  + (Additional Preliminary RAIs (Relating to Fire Protection) for FSAR Chapter 14)
• ML052660267  + (Additional Proposed Changes for Technical Specification to Revise Frequency for Tadot of P-4 Interlock)
• ML20029D164  + (Additional Protocol No Changes Report for Reporting Year 2019 San Onofre Nuclear Generating Station (SONGS) Unit 2)
• 2CAN011202, Additional Protocol Report  + (Additional Protocol Report)
• ML22277A422  + (Additional Question for Es About WTB Sample Judgmental 16)
• ML080880475  + (Additional Question on the Proposed Recirculation Riser Differential Pressure Amendment)
• 0CAN019160, Additional Questions Associated with Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis-Basis External Events  + (Additional Questions Associated with Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis-Basis External Events)
• ML062850056  + (Additional Questions Draft RAI on Amendment for Kewaunee Tornado Design Basis)
• ML023650196  + (Additional Questions Re 11/15/02 Amendment Request)
• ML20127H446  + (Additional Questions Regarding Sims Potential Transfer of Control March 25, 2020)
• L-03-008, Additional Questions Related to Supplemental Blasts & Explosions Responses to Additional NRC Questions for Diablo Canyon Independent Spent Fuel Storage Installation Application  + (Additional Questions Related to Supplemental Blasts & Explosions Responses to Additional NRC Questions for Diablo Canyon Independent Spent Fuel Storage Installation Application)
• ML100980009  + (Additional Questions from the Containment and Ventilation Branch on the Proposed EPU Amendment)
• ML113130261  + (Additional Questions/Comments on the Monitoring Program, Documentation, Etc)
• ML19309F875  + (Additional RAI 2-9 for the Review of the Model No. HI-STAR 180 D Package)
• ML091740761  + (Additional RAI Question on GSI-191/GL 2004-02 Resulting from June 22, 2009, Phone Call)

• ML20042C425  + (Additional RAI Responses from DOE for Draft Wir Evaluation for WMA-C)

• ML101540003  + (Additional RAI for LaSalle AST)
• ML25093A072  + (Additional RAI for License Amendment to Add New Building to the Psu SNM License)
• ML101540001  + (Additional RAI for NETCO-Rack-Inserts LAR)
• ML101380525  + (Additional RAI for Ultimate Heat Sink License Amendment Request (ME1669-70))
• ML23201A126  + (Additional RAIs for Limerick Generation Station, Units 1 and 2 - LAR and Exemption Request for Digital I&C Installation Support)
• ML091330131  + (Additional RAIs to Support LaSalle LAR to Revise LPRM Calibration Frequency (MD9415, MD9415))
• 2CAN041303, Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations  + (Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations)
• ML16328A118  + (Additional Recommendations on the Development of De Minimis Level)
• NL-07-1179, Additional Request Regarding the NRC Approval Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays  + (Additional Request Regarding the NRC Approval Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays)
• ML082210454  + (Additional Request for Additional Information BWROG Licensing Topical Report (LTR) NEDO-33349, Revision 1, BWR Application to Regulatory Guide 1.97 Revision 4)
• ML091280095  + (Additional Request for Additional Information Regarding Amendment to Lower the Minimum Allowed Level of the Ultimate Heat Sink Main Reservoir)
• ULNRC-06625, Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs  + (Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs)
• EPID:L-2020-LLE-0242  + (Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs)
• ML17307A033  + (Additional Request to Make ASME Materials Available to Support Rulemaking R0)
• ML17310A186  + (Additional Request to Make ASME Materials Available to Support Rulemaking)
• ML051220351  + (Additional Requests on Rals)
• ML053570248  + (Additional Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• W3F1-2005-0084, Additional Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors  + (Additional Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML053550197  + (Additional Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML090540234  + (Additional Response to License Transfer Application Submitted by Exelon Corporation)
• ML14162A261  + (Additional Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.1, Flooding - Flood Hazard Reevaluation)
• ULNRC-05253, Additional Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors.  + (Additional Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors.)
• ML060380612  + (Additional Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors)
• ET 07-0041, Additional Response to NRC Letter Dated August 8, 2007, Regarding the Main Steam and Feedwater Isolation System Controls Modification  + (Additional Response to NRC Letter Dated August 8, 2007, Regarding the Main Steam and Feedwater Isolation System Controls Modification)
• ML22174A422  + (Additional Response to NRC Request for Additional Information Letter Dated June 3rd 2022 Regarding License Renewal Application for the University of California-Davis/McClellan Nuclear Research Center)