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List of results

• ML20107F068  + (Response to NRC Questions Radwaste Mod Oyster Creek Nuclear Power Station)
• ML18086B145  + (Response to NRC Questions Re Endangered & Threatened Species of Sea Turtles Collected at Salem Nuclear Generating Station in 1981)
• W3F1-2007-0027, Response to NRC Questions Regarding Acceptability of Degraded Batwings  + (Response to NRC Questions Regarding Acceptability of Degraded Batwings)
• ML071630521  + (Response to NRC Questions Regarding Kewaunee Request for Approval of Topical Report DOM-NAF-5, Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (Kps))
• ML072050344  + (Response to NRC Questions Regarding Kewaunee Request for Approval of Topical Report DOM-NAF-5, Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (Kps))
• ML080350053  + (Response to NRC Questions Regarding License Amendment Request 215, Modification of Internal Flooding Design Basis)
• DCL-03-077, Response to NRC Questions Regarding License Amendment Request 02-03, Spent Fuel Cask Handling  + (Response to NRC Questions Regarding License Amendment Request 02-03, Spent Fuel Cask Handling)
• DCL-03-114, Response to NRC Questions Regarding License Amendment Request 02-03, Spent Fuel Cask Handling  + (Response to NRC Questions Regarding License Amendment Request 02-03, Spent Fuel Cask Handling)
• RC-03-0028, Response to NRC Questions Regarding Request for Revision to ASME Boiler & Pressure Vessel Code, Section XI Relief Request  + (Response to NRC Questions Regarding Request for Revision to ASME Boiler & Pressure Vessel Code, Section XI Relief Request)
• NL-04-1981, Response to NRC Questions Regarding Request to Revise Technical Specifications and Pressure and Temperature Limits Report  + (Response to NRC Questions Regarding Request to Revise Technical Specifications and Pressure and Temperature Limits Report)
• ML090780251  + (Response to NRC Questions Regarding Request for Temporary Exemption from the Provisions of 10 CFR 50.46 and 10 CFR 50, Appendix K for Lead Fuel Assemblies, and Proposed Change Number -589, Amendment Application Numbers 254)
• RC-07-0143, Response to NRC Questions Regarding Response to Generic Letter 96-06  + (Response to NRC Questions Regarding Response to Generic Letter 96-06)
• RC-06-0204, Response to NRC Questions Regarding Response to Generic Letter 96-06  + (Response to NRC Questions Regarding Response to Generic Letter 96-06)
• RC-05-0204, Response to NRC Questions Regarding Response to Generic Letter 96-06  + (Response to NRC Questions Regarding Response to Generic Letter 96-06)
• ML073030031  + (Response to NRC Questions Regarding Response to Generic Letter 96-06)
• ML053490109  + (Response to NRC Questions Regarding Response to Generic Letter 96-06)
• ML090210075  + (Response to NRC Questions Regarding Unit 2 Technical Specifications (TS) Change 463-T One-Time Extension of Surveillance Requirements (Srs))
• NOC-AE-03001605, Response to NRC Questions Regarding a Proposed License Amendment to Eliminate the Turbine Missile Design Basis  + (Response to NRC Questions Regarding a Proposed License Amendment to Eliminate the Turbine Missile Design Basis)
• ML033140053  + (Response to NRC Questions Regarding a Proposed License Amendment to Eliminate the Turbine Missile Design Basis)
• NL-04-1045, Response to NRC Questions Regarding the 2002 Unit 2 (2R9) and the 2003 Unit 1 (1R11) Steam Generator Tube Inspection Reports  + (Response to NRC Questions Regarding the 2002 Unit 2 (2R9) and the 2003 Unit 1 (1R11) Steam Generator Tube Inspection Reports)
• ML023240448  + (Response to NRC Questions Related to License Amendment Request Regarding Drywell Leakage and Sump Monitoring System)
• ML16231A028  + (Response to NRC Questions Related to Request for 20.2002 Disposal of Contaminated Water)
• ML030150118  + (Response to NRC Questions for Proposed Technical Specification Amendment for Nuclear Service Water System Pipe Replacement)
• ML22049A066  + (Response to NRC Questions from 2/1/2022 Regulatory Conference on Failed Field Flash Selector Switch)
• DCL-03-113, Response to NRC Questions on 1R11 Steam Generator Tube Inspections  + (Response to NRC Questions on 1R11 Steam Generator Tube Inspections)

• DCL-03-076, Response to NRC Questions on 2R11 Steam Generator Tube Inspections  + (Response to NRC Questions on 2R11 Steam Generator Tube Inspections)

• ML20210D669  + (Response to NRC Questions on B&Wog Rept BAW-2127, Final Submittal for NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratifiction)
• ML20037A233  + (Response to NRC Questions on Calvert Cliffs Unit I,Cycle 4 Reload Submittal,App 1-NP, 790425,nonproprietary Version)
• ML20058D833  + (Response to NRC Questions on Fort Calhoun Refined Seismic Spectra)
• ML20235V795  + (Response to NRC Questions on Geologic & Seismologic Conditions. W/Five Oversize Drawings Encl)
• ML20237L306  + (Response to NRC Questions on LOCA Hydraulic Forces Analysis of Beaver Valley Power Station Unit 2)
• CNL-14-182, Response to NRC Questions on Nuclear Safety Culture Assessment  + (Response to NRC Questions on Nuclear Safety Culture Assessment)
• ML20036A413  + (Response to NRC Questions on Palo Verde Seismic Hazard Analysis)
• ML20069K584  + (Response to NRC Questions on Pressurizer Relief & Safety Valves)
• NOC-AE-02001402, Response to NRC Questions on Proposed Change to Loss of Power & AC Sources TS  + (Response to NRC Questions on Proposed Change to Loss of Power & AC Sources TS)
• ML023020296  + (Response to NRC Questions on Proposed Change to Loss of Power & AC Sources TS)
• NOC-AE-04001682, Response to NRC Questions on Proposed Change to Technical Specification 3/4.3.3.5 for Remote Shutdown System  + (Response to NRC Questions on Proposed Change to Technical Specification 3/4.3.3.5 for Remote Shutdown System)
• ML041890388  + (Response to NRC Questions on Proposed Change to Technical Specification 3/4.3.3.5 for Remote Shutdown System)
• ML20214D465  + (Response to NRC Questions on Steam Generator Tube Rupture Chapter of B&W Owners Group Emergency Operating Procedures Technical Bases Document)
• ML20199G548  + (Response to NRC Questions on Steam Generator Tube Rupture Chapter of B&W Owners Group Emergency Operating Procedures Technical Bases Document)
• ML17087A491  + (Response to NRC Questions on TSTF-541, Add Exceptions to Surveillance Requirements When the Safety Function Is Being Performed)
• RA-19-0280, Response to NRC RAI Clarifications Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1  + (Response to NRC RAI Clarifications Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1)
• NL-12-0498, Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01  + (Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01)
• ML120470084  + (Response to NRC RAI Dated Jan. 17, 2012 Re. Limerick Gen. Station LRA)
• ML19064B376  + (Response to NRC RAI Letter Dated 11/05/2018)
• ML19063A499  + (Response to NRC RAI Letter Dated 16-January-2019 Regarding License Amendment Request to Modify Technical Specifications 3.5 and 5.1.2 for License R-75 of the Ohio State University Research Reactor)
• RNP-RA/06-0105, Response to NRC RAI Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Integrity  + (Response to NRC RAI Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Integrity)
• RA-19-0010, Response to NRC RAI Re Application to Adapt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors  + (Response to NRC RAI Re Application to Adapt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors)
• ML20086D494  + (Response to NRC RAI Re IPE)
• ML20196E826  + (Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3)
• ML13102A033  + (Response to NRC RAI Regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis)