L-MT-17-029, Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan
HNP-17-049, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations
RA-17-0037, Transmittal of Emergency Plan Implementing ProceduSR/0/A/2000/003, Revision 14
CNL-16-204, Bellefonte, Units 1 and 2, Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 33
WO 16-0045, Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
DCL-16-026, ISFSI - Emergency Plan Implementing Procedure Update, Including Revision 33 to EP R-2, Release of Airborne Radioactive Materials Initial Assessment
CNL-17-154, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 34
ULNRC-06230, Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6
ULNRC-06227, Response to Request for Additional Information Related to License Amendment Request for Emergency Action Level Upgrade Adopting NRC-Endorsed NEI 99-01, Rev 6
PLA-7285, Revision (X) to EP-RM-004, EAL Classification Bases
SBK-L-13088, Submittal of 2012 Annual Radioactive Effluent Release Report
L-MT-18-024, Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
ONS-2017-030, Oconee Nuclear Station Emergency Plan Revision 2017-002. Part 1 of 2
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
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
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
ONS-2014-044, Oconee, Units 1, 2, and 3 - 2013 Annual Radioactive Effluent Release Report (ARERR)
NL-14-0659, Enclosure 2: Farley Annual Radioactive Effluent Release Report for 2013
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments Iii, Iv, V & Vi: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EA
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachment Ii: Technical Bases Document for the Proposed EALs (Marked-Up Copy)
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 1, Introduction and General Description of Plant
LR-N10-0355, Salem, EAL Comparison Matrix
LR-N10-0355, EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases.
LR-N10-0355, EP-SC-1 11-200, Salem, Event Classification Guide, Emergency Action Level Technical Bases.
LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)
LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix
LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)
NLS2009063, Response to Request for Additional Information for License Renewal Application
DCL-09-020, Updated Emergency Plan Implementing Procedures
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
NEI 99-01, Wolf Creek Generating Station Proposed Revised EAL Technical Basis Document
NEI 99-01, Wolf Creek Nuclear Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
LR-N07-0156, License Amendment Request LAR S07-05, Revision to Licensing Basis - NPSH Methodology for ECCS Pumps
NL-06-056, Offsite Dose Calculation Manual (ODCM)
RA-18-0248, Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change
CNL-19-043, Bellefont Nuclear Plant, Units 1 & 2; Browns Ferry Nuclear Plan, Units 1, 2 & 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, R
RA-20-0050, Emergency Action Levels CSD-EP-RNP-0101-02, Revision 0
RS-02-174, Co., Llc. (EGC) Application for Amendment to Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Related to Application of Alternative Source Term, Attachments a - E-1
M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems
CNL-20-039, Bellefonte Nuclear Plant, 1 & 2; Browns Ferry Nuclear Plant, 1 & 2; Clinch River Site; Sequoyah Nuclear Plant, 1 & 2; and Watts Bar Nuclear Station, Units 1 & 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 38
NRC-89-0138, Semiannual Radioactive Effluent Release Rept, Jan-June 1989
ST-HL-AE-2093, Forwards Revised FSAR Section 3.12, Conformance W/Nrc Reg Guides. Section Updated to Reflect Util Position on All Applicable Reg Guides
CNL-22-019, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Reduction in Commitment
LD-92-123, Forwards Section 17.3, Design Reliability Assurance Program Plan for Sys 80+ Standard Design, Rev 1 & Responses to 79 Issues Identified in Dser for Sys 80+
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
RBG-16-413, Forwards Response to Draft SER Open Item Re Reactor Vessel Matls Surveillance Program.Response Will Be Incorporated Into Future FSAR Amend
L-MT-22-026, Changes to the Emergency Plan
L-PI-18-016, Enclosure 1, Form 1576 Emergency Action Level (EAL) Matrix, Revision 10 and Emergency Action Level Technical Bases, Revision 13
HNP-99-149, Application for Amend to License NPF-63,implementing Selected Improvements Described in GL 93-05
CNL-22-027, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 40
CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN8
LR-N25-0003, Emergency Plan EAL Document Revisions Implemented December 18, 2024
LR-N25-0051, Emergency Plan EAL Document Revisions Implemented April 30, 2025
L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change