Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e) 992930009
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NEI 06-02, License Amendment Request Guidelines
L-MT-16-073, Submittal of Revision 34 to Updated Safety Analysis Report
W3F1-2016-0042, Final Safety Analysis Report - Revision 309
W3F1-2017-0078, Final Safety Analysis Report, Revision 310
L-15-269, Submittal of Revision 19 to the Updated Final Safety Analysis Report
W3F1-2015-0040, License Amendment Request to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.4
W3F1-2015-0026, Response to NRC Natural Circulation Cooldown Analysis Audit Request for Additional Information
CY-13-048, Redacted - Haddam Neck Plant Independent Spent Fuel Storage Installation, Biennial Update Final Safety Analysis Report
L-11-192, Submittal of Revision 19 to the Updated Final Safety Analysis Report
L-10-325, Submittal of Revision 26 to the Updated Final Safety Analysis Report
CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 13, Conduct of Operation
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, Section 13, Conduct of Operations
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
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 1.0 - Introduction and General Description of Plant
NRC-12-0067, Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the Technical Specifications Bases
L-MT-10-074, Submittal of Revision 27 to the Updated Safety Analysis Report
ULNRC-05551, Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
GNRO-2008/00063, UFSAR Update for Grand Gulf, Unit 1, Nuclear Station for September 2008
RA-08-057, Unit 1, Application for Approval of License Transfers
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 1.0 - Introduction and General Description of Plant
Press Release-99-161, Discusses Reports from ACRS Following Recent Committee Meetings
CY-05-167, Revision to Haddam Neck Plant Decommissioning Updated Final Safety Analysis Report
L-MT-04-068, Submittal of Revision 21 to the Updated Safety Analysis Report
L-MT-03-083, Submittal of Revision 20 to the Updated Safety Analysis Report
NEI 98-04, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello
PNP 2019-015, Submittal of Revision 34 to Updated Final Safety Analysis Report
PLA-7814, Submittal of Revision 69 to Updated Final Safety Analysis Report
ND-19-0384, Request for Approval to Apply NEI 98-03 Guidance to the Plant-specific DCD
CY-04-095, Update from Connecticut Yankee Atomic Power Company to Controlled Manual, Using the Attached Insertion Instructions (November 2004 Update, Attachment to RACY-04-095, Dated 11-22-04)
RS-02-207, Amendment 20 to Byron/Braidwood Stations Fire Protection Report, Tables 2.4-5 - 3-1
CPSES-200200192, License Amendment Request 02-02 Re Revision to Technical Specification (TS) 3.7.3
L-22-058, Submittal of Revision 26 to Updated Final Safety Analysis Report
L-23-241, Submittal of the Updated Final Safety Analysis Report, Revision 27
NRC-24-0064, Supplement to License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance
L-MT-19-058, 7 to Updated Safety Analysis Report
CPSES-200400179, 1OCFR50.59 Evaluation Summary Report 0011
PNP 2024-019, Updated Final Hazards Summary Report, Revision 19