Rev 1 Evaluations of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants
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RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
RBG-47695, Response to Request to Additional Information Regarding RBS License Amendment Request to Extend Type a and Type C Test Frequencies
L-PI-16-002, Submittal of 50.59 Evaluation Summary Report
NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project
NL-14-106, 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project Indian Point Nuclear Generating Unit Nos. 2 & 3
CY-13-048, Redacted - Haddam Neck Plant Independent Spent Fuel Storage Installation, Biennial Update Final Safety Analysis Report
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)
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
NL-14-106, 10CFR50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project, Indian Point Nuclear Generating Station, Unit Nos. 2 & 3
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features
RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 2.0 - Site Characteristics, Table of Contents Through Table 2.5.53
L-MT-10-080, Correction to Appendix C of the Monticello Individual Plant Examination of External Events
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
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
NRC Generic Letter 79-05, Information Relating to Categorization of Recent Regulatory Guides by the Regulatory Requirements Review Committee
ST-HL-AE-3682, Provides Addl Info on External Events Analysis in Probabilistic Safety Assessment Issued by NRC & Sandia
BVY 05-067, NRC GL-03-001 Control Room Habitability - Final Response
CNL-18-072, Comments on Safety Evaluations
L-03-008, Additional Questions Related to Supplemental Blasts & Explosions Responses to Additional NRC Questions for Diablo Canyon Independent Spent Fuel Storage Installation Application
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)
NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline
SECY-20-0108, Enclosure 1 - Status of the Decommissioning Program - 2020 Annual Report
NRC-87-0003, Forwards Confirmatory Analysis of Effects of Blasting Activities at Rockwood Stone,Inc Quarry & Design Calculations & Detailed Evaluation for Offsite Blasting in Relation to Unit 2,in Response to
U-600627, Forwards Reassessment of Hazardous Matls Shipped Near Plant, Based on CY85 Survey Data for Illinois Central Gulf Railroad Gilman Line Per Sser 3 (NUREG-0853).Risks Associated W/Railroad Transportation Hazards Acceptably Low
AECM-88-0156, Final Special Rept on Events Re Interaction of Activities Associated W/Units 2 & 1,including Control of Chlorine Stored in Unit 2 Controlled Area & Leakage of Const Water Sys in Control Bldg
CNL-22-080, Request for Enforcement Discretion from the Requirements of Technical Specification 3.5.2, ECCS - Operating
RBG-21444, Forwards Revs to FSAR Section 2.2.3.1,resulting from Confirmation of Parameters Used in Original Analysis.Revs to SER or Proposed Tech Specs Unnecessary.Revs Will Be Included in Future FSAR Amend
0CAN079207, Addresses Three Separate Initiatives That Impact Util Reg Guide 1.97 Position Statements,Per Response to Generic Ltr 82-33 (NUREG-0737,Suppl 1).Encl Addresses Accumulator Instrumentation Safety Functions
LIC-95-0007, Responds to NRC RAI to Assist Closure of NRR Staff Review of Plant Revised Evaluation of CR Habitability.W/One Oversize Encl
RBG-48143, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
TXX-6745, Forwards Revised Environ Qualification Program,Addressing Mild Environs for Plant
SECY-21-0100, Enclosure 1 - Status of the Decommissioning Program 2021 Annual Report
05000344/LER-1989-015, :on 890713,determined That Existing Ventilation Flow Rates & High Closure Setpoints on Hydrogen Gas Supply Excess Flow Valves Could Result in Excessive Accumulation of Hydrogen.Storage Tanks Relocated
LIC-93-0301, Phase I Rept on IPEEE for FCS Re Tornado,Flooding, Transportation & Nearby Facilities Accidents & Others
A02151, Comments on SEP Topic II-1.C Re Potential Hazards Due to Nearby Transportation,Institutional,Industrial & Military Facilities.No Conceivable Path Propane Could Follow to Facility
CNL-19-002, Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,
NL-17-1962, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
PNP 2024-019, Updated Final Hazards Summary Report, Revision 19
L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors