Category:Legal-Affidavit
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Agency
Pages in category "Legal-Affidavit"
The following 200 pages are in this category, out of 3,759 total.
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- 05000390/LER-2016-002, Regarding Technical Specification Action Not Met for Inoperable Containment Isolation Valve
- 0CAN022101, Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping
- 0CAN041401, NRC Augmented Inspection Team Follow-up Inspection Report 05000313/2013012 and 05000368/2013012; Preliminary Red and Yellow Findings
- 0CAN052103, Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency .
- 0CAN071303, Units 1 and 2, Augmented Inspection Team Information Request
- 0CAN092101, Unit 2 - Revised Proprietary Demarcation in Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping
1
- 1CAN031504, Arkansas Nuclear One, Unit 1 - Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits
- 1CAN031504, Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits
- 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)
- 1CAN121601, Arkansas Nuclear One Unit 1, Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan
- 1CAN121601, Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan
- 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)
2
- 2CAN010402, Revisions to Wesdyne Proprietary Reports in Support of Relaxation from Performing a Bare Metal Visual Inspection
- 2CAN032001, Response to Request for Additional Information Related to License Amendment Request to Revise the Control Element Assembly Drop Times
- 2CAN041402, Successive Examination Plans, Request for Relief ANO2-ISI-016. Weld Scan Plans & Preliminary Coverage Estimates, Pdqs Number 783 & Affidavit Enclosed
- 2CAN051504, Revised Affidavit for Request for Relief ANO2-ISI-016
- 2CAN102102, Relief Request ANO2-R&R-012: Support the Repair of the Reactor Vessel Closure Head Penetration 46
- 2CAN102402, Enclosure 2: Framatome Affidavit
- 2CAN111402, Unit 2, Revised Affidavit for Request for Relief ANO2-ISI-016
- 2CAN112403, Affidavit for Corrosion Evaluation of ANO-2 RVCH CEDM Idtb Weld Nozzle Penetration Repair, Document Number 51-9384397-001
- 2CAN122103, Relief Request ANO2-RR-21-002, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Submittal of Analyses - Affidavits and Calculation Summary Sheet
3
- 3F0112-11, Corrections to the Extended Power Uprate LAR 309 Vendor Affidavit and Technical Report
- 3F0120-01, Supplemental Information in Support of Crystal River Unit 3 (CR3) License Transfer Application - Focd Negation Action Plan
- 3F0219-03, Proprietary Document Affidavit for 50.83 Partial Site Release
- 3F0319-02, Request for Closed Pre-Submittal Meeting for a License Amendment Request
- 3F0524-03, Annual Financial Report and Certified Financial Statement
- 3F0525-02, Annual Financial Report and Certified Financial Statement
- 3F0612-05, Response to Request for Additional Information to Support NRC Nuclear Performance and Code Review Branch (Snpb) Technical Review of the CR-3 Extended Power Uprate LAR
- 3F0707-05, License Amendment Request 292, Revision 1: Additional Storage Patterns for Pools a and B and Response to Request for Additional Information
A
- AEP-NRC-2012-38, Response to Request for Information, 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with Thermal Conductivity Degradation
- AEP-NRC-2014-56, First Response to Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program
- AEP-NRC-2016-19, License Amendment Request to Revise the Cyber Security Plan Implementation Schedule
- AEP-NRC-2017-52, Enclosure 3: Donald C. Cook Nuclear Plant Unit 2, Application for Withholding Proprietary Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program from Public Disclosure
- AEP-NRC-2020-01, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
- AEP-NRC-2020-09, Unit 2, Application to Revise Technical Specifications to Adopt TSTF-412, Revision 3 Provide Actions for One Steam, Supply to Turbine Driven Afw/Efw Pump Inoperable
- AEP-NRC-2020-14, License Amendment Requests and Exemption Requests Regarding Changes to the Routine Reporting Requirements Subject to Plant Technical Specifications and 10 CFR 50.71(e)
- AEP-NRC-2020-33, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues
- AEP-NRC-2020-50, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency
- AEP-NRC-2020-72, License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency
- AEP-NRC-2021-24, Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation
- AEP-NRC-2021-28, 10 CFR 50.90 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
- AEP-NRC-2021-68, Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation
- AEP-NRC-2022-03, Final Supplemental Response to NRC Generic Letter 2004-02
- AEP-NRC-2022-12, Commitment Schedule Change Related to Seismic PRA Distributed Ignition Backup Power Source
- AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation
B
- BSEP 05-0132, Submittal of Supporting Calculations Regarding Revised Main Steam Isolation Valve Leakage Limit
- BSEP 05-0152, Re-Submittal of Calculation Supporting Revised Main Steam Isolation Valve Leakage Limit
- BSEP 08-0009, Additional Information in Support of Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Fuel
- BSEP 10-0133, Response to Additional Information Request Supporting License Amendment Requests for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859)
- BSEP 16-0098, Duke Energy- Transmit Information for NRC Model Development Per Licensee September 6, 2016 Request for License Amendment Regarding Core Flow Operating Range Expansion
- BSEP 16-0101, Response to Request for Supplemental Information for License Amendment Request Regarding Core Flow Operating Range Expansion
- BSEP 17-0093, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion
- BSEP 18-0034, Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion
- BVY 17-001, Response to Request for Supplemental Information Related to Exemption
- BVY 19-018, Annual Financial Report and Certified Financial Statement
- BVY 20-015, Annual Financial Report and Certified Financial Statement
- BVY 21-013, Submittal of Annual Financial Report and Certified Financial Statement
- BVY 25-017, Annual Financial Report and Certified Financial Statement
C
- CNL-14-181, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, Set 22, B.1.34-9c
- CNL-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical
- CNL-15-103, Enclosure 2, ANP-3414NP Revision 0, Areva RAI Responses for Browns Ferry, Unit 3, Cycle 18 MCPR Safety Limits (Non-proprietary), and Enclosure 3, Affidavit
- CNL-15-169, Electric Power Research Institute Affidavit
- CNL-15-204, Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit
- CNL-15-247, Brown Ferry Unit 1, Submittal of Response to NRC Request for Additional Information Re Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506). Enclosure 2 ANP-3458NP Enclose
- CNL-15-249, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information
- CNL-15-250, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 7
- CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory
- CNL-16-056, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 9, Responses to Requests for Additional Information
- CNL-16-145, Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30
- CNL-18-042, Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 1
- CNL-18-081, Request for Review and Approval of Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041, Revision 1
- CNL-18-103, Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041,
- CNL-18-106, Extended Power Uprate Replacement Steam Dryer Core Flow Sweep Test Report
- CNL-18-116, Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)
- CNL-18-124, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports
- CNL-18-125, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report
- CNL-18-131, Extended Power - Uprate Replacement Steam Dryer Core Flow Sweep Report - Supplemental Information
- CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4
- CNL-18-141, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report - Supplemental Information
- CNL-19-006, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information
- CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information
- CNL-19-028, Replacement Steam Dryer Revised Analysis and Limit Curves Report, Supplement 1
- CNL-19-042, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Report
- CNL-19-045, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 9, Additional Information Regarding Anticipate Transient Without Scram with .
- CNL-19-075, Extended Power Uprate - Unit 2 Replacement Steam Dryer Final Load Definition and Stress Report
- CNL-19-076, Extended Power Uprate: Unit 1 Replacement Steam Dryer Final Load Definition and Stress Report, Revision 1
- CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)
- CNL-19-117, Extended Power Uprate - Units 1 and 2 Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information
- CNL-19-125, Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition
- CNL-20-063, Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)
- CNL-21-011, Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)
- CNL-21-024, Partial Response to Additional Request for Information Re Application to Revise Updated Final Safety Analysis Report Re Changes to Hydrologic Analysis (TS-19-02)
- CNL-21-053, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535)
- CNL-21-061, Information Transmittal for NRC Confirmatory Calculations Regarding Transition to Atrium 11 Fuel
- CNL-21-076, Request for Alternative, 21-ISI-2, Alternative Inspection for Upper Head Injection J-groove Welds
- CNL-21-095, Submittal of Application to Revise Sequoyah Nuclear Plant, Units 1 and 2, 10 CFR 50.90 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Software Dedication Report 16-01 - Update .
- CNL-21-098, Supplement to Response to Request for Additional Information Regarding Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Operating License Condition 2.C.(4)
- CNL-22-056, Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)
- CNL-22-096, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)
- CNL-22-100, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)
- CNL-23-016, Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)
- CNL-23-043, – Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)
- CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out
- CNL-24-006, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (BFN-TS-550)
- CNL-24-011, Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology
- CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)
- CNL-25-032, Supplement to Application to Revise Browns Ferry Nuclear Plant, Units 1, 2, and 3 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (BFN-TS-550)
- CNL-25-035, Application for Subsequent Renewed Operating Licenses, Environmental Report RAI HCR-14 Response (EPID Number: L-2024-SLE-0000)
- CP-200700016, Supplemental Information to License Amendment Request (LAR) 07-004, Revision to the Operating License and Technical Specification 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage
- CP-201400503, Response to Requests for Additional Information on License Amendment Request 13-01 Spent Fuel Pool Criticality Analysis
- CP-201600117, Submittal of Fifteenth Refueling Outage (2RF15), Inservice Inspection (ISI) Summary Report (2007 Edition of ASME Code, Section XI, 2008 Addenda, Third Interval Start Date: August 3, 2014, Third Interval End Date: August 2, 2023)
- CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
- CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1
- CPSES-200701178, Supplement to Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change (TAC Nos. MD5289 and MD5280), Enclosures 1, 4, 5, 6 & 7
D
- DCL-02-066, Supplemental Answers to NRC Order for Interim Safeguards and Security Compensatory Measures
- DCL-03-133, Full Compliance with Order for Compensatory Measures Related to Fitness-For-Duty Enhancements Applicable to Nuclear Facility Security Force Personnel, Dated 04/29/03 (EA-03-038)
- DCL-04-066, Response to NRC Request for Additional Information Regarding License Amendment Request 03-12, Revision to Technical Specifications 3.3.1, RTS Instrumentation, and 3.3.2, ESFAS Instrumentation
- DCL-04-089, Response to June 14 and July 6, 2004, NRC Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9, Steam Generator (SG) Tube Surveillance Program, & 5.6.10
- DCL-04-095, 60-Day 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
- DCL-04-104, Response to NRC Request for Additional Information Regarding License Amendment Request 04-01, Revised Steam Generator Voltage-based Repair Criteria Probability of Detection Method for Plant
- DCL-04-123, License Amendment Request 04-06 Removal of Technical Specifications 5.6.1, Occupational Radiation Exposure Report, and 5.6.4, Monthly Operating Reports
- DCL-05-018, License Amendment Request 05-01 Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program, and 5.6.10, Steam Generator Tube Inspection Report. to Allow Use of the W* Alternate Repair Criteria
- DCL-05-121, Correction of Information Contained in License Amendment Request 05-04. Revision to Technical Specification 5.3.1. Unit Staff Qualifications
- DCL-12-069, Diablo Canyon, Units 1 and 2 - Submittal of Attachment 1, Quality Assurance Plan and Revised Phase 1 Documents for the License Amendment Request for Digital Process Protection System Replacement and Attachment 8 Affidavit 993754-AFF-38T
- DCL-13-021, Areva Affidavit for Areva Calculations 32-9199805-000, Diablo Canyon Power Plant Unit 2 Pzr Safety and Spray Nozzles Planar Flaw Analysis (Proprietary) and 32-9199937-000, DCPP Unit 2 - Evaluation of Laminar Indications in Pressurizer N
- DCL-13-061, CS Innovations - Application for Witholding Proprietary Information from Public Disclosure, Enclosure, Attachment 2
- DCL-14-034, Affidavit No. 993754-AFF-104T, Dated 03/12/2014, Signed by Mark Herschthal
- DCL-15-039, Independent Spent Fuel Storage Installation - Consent and Hearing Waiver Form
- DCL-16-020, Diablo Canyon, Units 1 and 2 - Submittal of Tricon Phase 2 Documents for the License Amendment Request for Process Protection System Replacement
- DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology
- DCL-23-022, 2023 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant
- DCL-25-001, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation Diablo Canyon Safety Review Pacific Gas and Electric Company
E
- ENOC-07-00036, Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses
- ENOC-07-00042, Supplemental Information 2 in Support of Application for Order Approving Indirect Transfer of Control of Licenses
- ET 07-0022, Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification
- ET 07-0050, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls
- ET 08-0017, Additional-Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
- ET 14-0009, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis
- ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology
- ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term
- ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information
- ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption
- ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191
- ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
G
- GNRO-2006/00064, Supplement to Amendment Request Changes to the Local Power Range Monitor (LPRM) Calibration Frequency
- GNRO-2011/00075, Supplemental Information Extended Power Uprate
- GNRO-2011/00088, Response to Request for Additional Information Regarding Extended Power Uprate
- GNRO-2012/00018, Response to Request for Additional Information Regarding Extended Power Uprate
- GNRO-2013/00050, Criticality Safety Analysis License Amendment Request - Responses to NRC Requests for Additional Information
- GNRO-2014/00015, Responses to NRC Requests for Additional Information Pertaining to the Final Report for the GGNS Replacement Steam Dryer
- GNRO-2014/00024, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 2/6/2014
- GNRO-2014/00064, Superseding Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014
- GNRO-2014/00080, Affidavits for the Proprietary MP Machinery and Testing, LLC (Mpm) Reports Attached in Letters GNRO-2014/00080 and GNRO-2015/00011
- GNRO-2015/00031, Response to Request for Additional Information Regarding Fluence License Amendment Request
- GNRO-2016/00024, Operating License Manual Update Submittal
- GO2-14-110, Response to Request for Additional Information on License Amendment Request to Change Emergency Core Cooling System Surveillance Requirements
- GO2-15-035, Global Nuclear Fuel - Americas Affidavit for Withholding Information
- GO2-20-127, Response to Request for Additional Information Related to Fourth Interval Inservice Inspection (ISI) Program Request 4ISI-09
- GO2-20-146, Erratum to Fourth Ten-Year Inservice Inspection (ISI) Program Relief Request 4ISI-09
- GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves
H
- HBL-05-026, Report of Full Compliance with NRC Order for Additional Security Measures Associated with Access Authorization, Fitness for Duty, and Behavior Observation
- HNP-15-038, License Amendment Request for Main Steam Safety Valve Lift Setting Tolerance Change
- HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval
L
- L-07-103, Supplemental Information for License Amendment Request Nos. 333 & 204 (Rev. 2 of WCAP-16518)
- L-07-106, License Amendment Request No. 07-007 Alloy 800 Steam Generator Tube Sleeving
- L-10-384, Extended Power Uprate Licensing Report, Attachment 6; Applications for Withholding Proprietary Information from Public Disclosure
- L-15-350, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 16
- L-16-028, Retrospective Premium Guarantee
- L-17-190, Response to Request for Information Regarding License Renewal Commitment No. 54
- L-19-009, Independent Spent Fuel Storage Installation Remaining Responses to NRC Letter Dated April 30, 2019, Request for Additional Information for the Technical Review of the Application for Renewal of the Humboldt Bay Independent Spent Fuel
- L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
- L-20-067, Retrospective Premium Guarantee - 2020 Internal Cash Flow Projection
- L-20-126, Request for Threshold Determination - Corporate Organization and Ownership
- L-20-161, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter .
- L-20-270, Electric Power Research Institute Affidavit
- L-2010-113, License Amendment Request for Extended Power Uprate, Attachment 13; Westinghouse Affidavit for Attachment 12
- L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 05; Westinghouse & Areva Affidavits for Attachment 4
- L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 09; Cameron Affidavit for Attachment 8
- L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 11; Westinghouse Affidavit for Attachment 10
- L-2010-259, St. Lucie, Unit 1 - Transmittal of Affidavits from Westinghouse, Areva and Caldon Ultrasonica Technology Center Re License Amendment Request for Extended Power Uprate
- L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate
- L-2011-100, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Nuclear Performance and Code Review Issues
- L-2011-413, Submittal of Attachment 2, Response to NRC Reactor Systems Branch Request for Additional Information Re Extended Power Uprate License Amendment Request
- L-2011-464, Response to NRC Instrumentation & Controls Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request
- L-2012-075, Response to NRC Mechanical and Civil Engineering Branch (Emcb) Request for Additional Information Regarding Extended Power Uprate License Amendment Request
- L-2012-171, Response to NRC Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request
- L-2012-207, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request
- L-2015-189, License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement
- L-2015-279, RAI Response Clarification for SRXB-RAI-1 and Snpb RAI-2 Thru RAI-20 for the Technical Specification LAR and Exemption Request Regarding the Transitioning to Areva Fuel
- L-2016-143, Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents
- L-2016-202, Notice of Intent to Pursue License Renewal, Request for Withholding from Public Disclosure
- L-2017-062, Request for Withholding Information from Public Disclosure Subsequent License Renewal Notification
- L-2018-039, License Renewal Application - Supplement 1
- L-2018-082, Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version)
- L-2018-193, Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review
- L-2019-013, Submittal to NRC Vessels & Internals Integrity Branch of Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results
- L-2019-130, Revised Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results