Methods and Assumptions for Evaluating Radiological Consequences of Design-Basis Accidents at Light-Water Nuclear Power Reactors
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SECY-19-0079, Staff Approach to Evaluate Accident Source Terms for the Nuscale Power Design Certification Application
NRC 2005-0067, Response to Request for Additional Information Regarding Request for Exigent Review of Heavy Load Analysis
NRC 2005-0072, To Request for Exigent Review of Heavy Load Analysis and Response to Request for Additional Information
NL-16-0784, Units 1 and 2 - Response to Request for Additional Information for TSTF-312. Enclosure 2 Excerpts from Calculation SM-96-1064-001
NL-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application
NL-16-0098, Response to Request for Additional Information for Adoption of Technical Specifications Task Force Traveler 312
ULNRC-05793, Application for Amendment to Facility Operating License NPF-30 (LDCN 10-0036) Revision of Technical Specification 3.3.8,
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 15, Accident Analyses
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2 Decrease in Heat Removal by the Secondary System, Redacted
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 3
NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 3
NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 3
DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term. Part 1 of 8
NRC 2010-0075, License Amendment Request 265 Revision to the Reactor Vessel Head Drop Methodology
DCL-16-101, Diablo Canyon, Units 1 and 2, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term
NL-16-0388, Draft License Amendment Request Regarding Alternative Source Team
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
RC-07-0156, Response to NRC Request for Additional Information Regarding Lead Test Assemblies
NL-07-0067, License Amendment Request to Technical Specification 3.9.3, Containment Penetrations, Personnel Air Locks Doors Open During Fuel Movement
0CAN020701, Supplemental Response to GL 2003-01 Regarding Control Room Habitability
CPSES-200602131, License Amendment Request 06-011, to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process
ULNRC-05281, Application for Amendment to Facility Operating License NPF-30, Adoption of Industry Traveler TSTF-490
NRC 2006-0038, Supplemental Response to Generic Letters (GL) 98-04 and GL 2004-02 Licensee Event Report 266/301/2005-006-00
WO 05-0025, Revision to Technical Specification (TS) 1.1, Definitions, and TS 3.4.16, RCS Specific Activity
NL-05-2002, Revised Schedule for Response to Generic Letter 2003-01 Control Room Habitability
NRC 2005-0094, Request for Review of Heavy Load Analysis
RC-05-0003, Response to NRC Generic Letter 2003-01 Control Room Habitability - Change to Activity Schedule
ND-18-0096, Supplement to Request for License Amendment and Exemption Regarding Improvements to Main Control Room (MCR) Post-Accident Radiological Consequences (LAR-17-023S1)
ULNRC-04928, Responses to RAIs on the Proposed Revision to Technical Specification (TS) 1.1, Definitions, TS 3.7.3, Main Feedwater Isolation Valves (Mfivs), and Steam Generator Tube Rupture with Overfill Re-Analysis
NL-04-0780, Units I and 2, Response to Second Request for Additional Information Related to Request to Revise Technical Specifications - Containment Equipment Hatch
NL-04-0979, Revised Response to Selected Questions from Second NRC Request for Additional Information Related to Request to Revise Technical Specifications - Containment Equipment Hatch
W3F1-2004-0035, Supplemental to Amendment Request for Extended Power Uprate
CNL-17-044, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2
PLA-5711, Follow-Up Response to Generic Letter 2003-01, Control Room Habitability
1CAN120301, ANO, Unit 1 - Supplement to Amendment Request to Add a New Control Room Emergency Ventilation System Surveillance Requirement
NL-03-1740, Request to Revise Technical Specifications Containment Equipment Hatch
RC-03-0167, (VCSNS) 60-Day Response to NRC Generic Letter 2003-01 Control Room Habitability
CNL-21-019, License Amendment Request to Revise Updated Final Safety Analysis Report Section 15.5.5 - Steam Generator Tube Rupture Dose Analysis (WBN-TS-20-04)
CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel
WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of .
05000341/LER-2016-012, Regarding Unanalyzed Condition for Control Rod Drop Accident at Low Reactor Power
AEP-NRC-2014-42, Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions
TSTF-12-06, Transmittal of TSTF-538, Revision 0, Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
05000395/LER-2008-002, Re Control Room Normal and Emergency Air Handling Systems Inoperable Due to Pressure Boundary Breach
CPSES-200601897, License Amendment Request (LAR) 05-005, Revision to Technical Specification 3.7.10, Control Room Emergency Filtration/Pressurization System (Crefs)
CPSES-200060390, Revision to Technical Specification 1.1, Definitions and 3.5.16, RCS Specific Activity
DCL-06-008, License Amendment Request 06-01 Revision to Technical Specification 1.1, Definitions, and Technical Specification 3.4.16, RCS Specific Activity
CPSES-200501556, License Amendment Request (LAR) 05-005 Revision to Technical Specification 3.7.10, Control Room Emergency Filtration/Pressurization System (Crefs)
05000483/LER-2003-007, Engineering Evaluations Incorrectly Approved Leaving Health Physics Access Doors Open
NOC-AE-040169, Request for Enforcement Discretion for Technical Specifications 3/4.7.7 and 3.8.1.1
ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis