NRC 2017-0017, License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances
LR-N17-0109, Response to Final Request for Additional Information (Rai), Permanently Extend Type a and Type C Leak Rate Test Frequencies
NRC 2017-0043, License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Plants
GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A
BSEP 17-0098, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors
L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06)
L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 10.3 Through Section 15.1
2CAN061003, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years
LR-N10-0198, Supplemental Information for License Amendment Request: Emergency Diesel Generators (EDG) a and B Allowed Outage Time (AOT) Extension
LR-N10-0015, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
2CAN061003, Arkansas Nuclear One, Unit 2 - License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years
RS-06-048, ILRT Interval Extension Risk Assessment
CNL-18-068, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24)
NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
RS-20-011, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
SBK-L-18089, License Amendment Request 17-06, Change to the Technical Specification Requirements for Reactor Trip System Instrumentation and Engineered Safety Features Actuation System Instrumentation to Implement WCAP-14333 and WCAP-15376
L-05-104, Probabilistic Safety Review for License Amendment Request Nos. 302 and 173
LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities
NRC 2002-0059, Submittal of Request for Relief No. 3 Risk-Informed Inservice Inspection Program
RS-20-053, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
CNL-20-002, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529)
RA-19-0437, Nos. 1 & 2 - License Amendment Request to Modify Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Categorization Process
IA-85-199, Forwards Draft Rev of Policy Statement on Severe Reactor Accidents Re Future Designs & Existing Plants & Draft NUREG-1070,incorporating Policy Statement Rev,As Followup to Response to Commission Questions Per SECY-84-370
ULNRC-06550, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
2CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
B13180, Responds to NRC Station Blackout Rule Re Plant Capability for Maintaining Core Cooling & Containment Integrity
B13179, Responds to NRC Station Blackout Rule Re Capability of Plant to Maintain Core Cooling & Containment Integrity. Procedure Changes Identified in Part B of Attachment 1 Will Be Completed in 1 Yr After Notification Provided by NRR
JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
SBK-L-21104, Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension
GO2-21-133, License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,
ET-NRC-92-3789, Forwards Westinghouse Response to NRC 920923,1001,09 & 28 Requests for Addl Info on AP600
NSD-NRC-96-4748, Forwards Draft Copy of Chapter 57 of AP600 PRA Covering at- Power Internal Fire Analysis.Draft of AP600 PRA Submitted for NRC to Begin Review of Revised Internal Fire Analysis & Provide Feedback During 960624-26 Meeting W/Nrc
NSD-NRC-96-4795, Forwards Draft Markup of Chapter 57 of AP600 PRA Covering Internal Fire Analysis.Pra Chapter Revised to Incorporate Shutdown Fire Evaluation
3F1291-01, Responds to Generic Ltr 88-20,Suppl 4 Re Individual Plant Exam of External Events.As Result of Geographic Location of Plant & Bulk of Util Svc Area,Plant Grid & Plant Designed for Hurricanes & Tornados
B10887, Forwards Amend 1 to Probabilistic Safety Study
NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors
Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
RBG-48143, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
NRC-92-1106, Step 1 TER of Perry IPE Back End Submittal,Final Rept
RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
LD-88-066, Forwards DOE Advanced Reactor Severe Accident Program Proposed Resolutions for Severe Accident Issues,Topic Set 3. Resolutions to Listed Items Will Be Adopted in Development of Sys 80+ Std Design
LD-88-005, Draft C-E Sys 80+TM Std Design, Design Certification Licensing Review Bases.Response to NRC Comments on Licensing Document Encl
DCL-23-077, License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
JPN-92-024, Responds to Requesting That Util Review FitzPatrick IPE to Assess Accuracy of IPEs Underlying Evaluations & Conclusions & Reconcile W/Findings of Det
LIC-93-0301, Phase I Rept on IPEEE for FCS Re Tornado,Flooding, Transportation & Nearby Facilities Accidents & Others
B14476, Forwards Response to NRC 930326 Telcon Request for Addl Info Re Individual Plant Exam,Per GL 88-20.Info Submitted to Enable NRC to Review Util 930331 Individual Plant Exam Results
0CAN118906, Responds to 890829 Request for Proposed Program for Completion of Generic Ltr 88-20 Re Individual Plant Exam (IPE) for Severe Accident Vulnerabilities.Util Intends to Submit Results of Both Units by End of 1991
BECO-89-159, Responds to Generic Ltr 88-20,Suppl 1,describing Plan for Completing Individual Plant Exam for Severe Accident Vulnerabilities.Performance of Level 1 PRA Based on Current Plant Design & Operation Intended
DCL-23-054, License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
RAIO-0219-64684, LLC Supplemental Response to NRC Request for Additional Information No. 260 (Erai No. 9108) on the NuScale Design Certification Application
NUREG-2225, Basis for the Treatment of Potential Common-Cause Failure in the Significance Determination Process
NL-17-1962, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
LR-N18-0032, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension
HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors
L-2017-156, License Amendment Request 254, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
GO2-91-227, Responds to Generic Ltr 88-20,Suppl 4 Re Individual Plant Exam for External Events.Util Will Also Address Hazards Associated W/Volcanic Eruption.Events Initiated by Internal Fires Will Be Evaluated by Level 1 PRA
GO2-89-203, Responds to Generic Ltr 88-20,Suppl 1 Re Individual Plant Exam.Pra Will Be Completed to Level II as Described in NUREG/CR-2300 & Focused or Modified Only to Extent That NRC Concerns Addressed
L-84-133, Application for Amend to License NPF-16,revising Tech Specs to Extend Subgroup Test Interval from 6 to 18 Months
L-85-406, Forwards Addl Info Re 840522 Application for Amend to License NPF-16,increasing Esfas/Auxiliary Feedwater Actuating Sys Actuation Logic Surveillance Interval from 6 Months to 18 Months
NL-14-043, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima
TXX-1208, License Amendment Request (LAR) 12-004, Revision to Technical Specification 3.8.1, Ac Sources - Operating, for Two, 14-Day Completion Times for Offsite Circuits
RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
RS-10-015, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System
NOC-AE-060019, Proposed Amendment to Technical Specification 6.8.3.j for One-Time Extension of Integrated Leakage Rate Test Interval to 20 Years
SBK-L-05197, License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval
RS-05-001, Request for a License Amendment to Extend the Completion Times Related to Technical Specifications Associated with Residual Heat Removal Service Water, Diesel Generator Cooling Water and the Opposite Unit Division 2 Diesel
NG-02-0237, Response to Request for Additional Information (RAI) for Technical Specification Change Request TSCR-048 - One-Time On-Line Safety-Related Battery Replacement
LR-N04-0036, Correction PSEG Letter LR-N04-0036, Risk-Informed Inservice Inspection Submittal
RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program
L-MT-20-036, Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times
LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
DCL-24-111, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3.1 and 3.3.2
W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors
SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements
BECO-91-155, Describes Program Plan for Completing Individual Plant Exam of External Events for Severe Accident Vulnerabilities,Per Suppl 4 to Generic Ltr 88-20.Exam Will Include Seismic Events,Internal Fires,High Winds & External Floods
CP-202300270, (CPNPP) - Response to Request for Supplemental Information for License Amendment Request to Adopt 10 CFR 50.59, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants
RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors