DCL-17-038, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 8, Electric Power
RNP-RA/16-0057, License Amendment Request to Modify the Licensing Basis Alternate Source Term
NRC 2016-0002, License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program
CNS-15-054, Submittal of Technical Specification Bases Changes 5.5.14
NL-14-0115, Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5
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DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 7
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DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 4, Reactor
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 2, Site Characteristics
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 12, Radiation Protection (Redacted)
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 11, Radioactive Waste Management
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 10, Steam and Power Conversion System
L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 1, Introduction and General Description of Plant Site Characteristics
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 4.3.1 to 4.3-61
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3D-137 Through 4.3-41
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 7, Instrument and Control
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DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8
NL-16-109, Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 7, Instrumentation and Control
NL-16-109, Indian Point, Unit 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 1, Introduction and Summary
NL-15-144, Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 4.0 - Reactor, Pages 4-i - 4.4-52
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 7 - Instrumentation and Control
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 1, Introduction and Summary
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 7 - Instrumentation and Control
NL-13-130, Indian Point, Unit 2 - Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 1 - Introduction and Summary
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate
NL-09-144, Proposed Technical Specification Change Regarding Ventilation Filter Testing Program
NL-09-062, Proposed Technical Specification Change Regarding RWST Surveillance Requirement
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
NRC 2008-0018, License Amendment Request 259, Application for Tech Spec Improvement to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to Reactor Coolant System (RCS) Specific Activity Technical Specification
TSTF-07-06, Response to NRC Request for Additional Information Regarding TSTF-486, Revision 0, Revise Mtc Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011), Dated November 20, 2006 and Submittal of Revision 1
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
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 9 - Auxiliary and Emergency Systems
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 1 - Introduction and Summary
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), List of Effective Pages
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
2CAN050702, License Amendment Requesting, Technical Specification 3.1.1.4, Moderator Temperature Coefficient
W3P81-1169, Forwards Itemized Reviews of Compliance W/Various Sections of 10CFR.Util Meets or Exceeds Requirements
NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis
ND-18-0057, Request for License Amendment Regarding Analytical Methods for Core Operating Limits Report and Consistency Changes (LAR-18-006)
NL-04-134, Proposed Change to Technical Specifications Regarding Elimination of Hydrogen Recombiner Requirements, and Relaxation of Hydrogen Monitor Requirements (TSTF-447)
CPSES-200402431, License Amendment Request 04-011, Revision to Technical Specification (TS 3.3.3) Post Accident Monitoring Instrumentation and 3.6.8 Hydrogen Recombiners
DCL-03-173, License Amendment Request 03-19 for Revision to Technical Specifications 3.3.3, Post-Accident Monitoring (PAM) Instrumentation and 3.6.8, Hydrogen Recombiners
L-2003-299, 180 Day Response to Generic Letter 2003-01 Re Control Room Habitability
RC-03-0155, License Amendment Request - LAR 02-3626 Reactivity Control Systems - Moderator Temperature Coefficient
NRC 2003-0028, License Amendment Request 234, Selective Scope Implementation of Alternative Source Term for Fuel Handling Accident
ULNRC-04721, Technical Specification Bases Revision 3
L-02-065, License Amendment Request No. 301 Re Positive Moderator Temperature Coefficient
NRC 2002-0019, License Amendment Request 224 Control Room Habitability
DCL-20-066, License Amendment Request 20-01 Exigent Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater System
NOC-AE-20003774, License Amendment Request to Revise Technical Specification Surveillance Requirement (SR) 4.1.1.3 A. and B. and Specification 6.9.1.6 B
NL-22-0288, License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel
LD-94-036, Forwards Comments of Chapter 4 of Sys 80+ Final SER, NUREG-1462 for Technical Accuracy & Consistency w/CESSAR-DC
NSD-NRC-97-5379, Forwards Responses & SSAR Revs to Address Three FSER Open Items Re Environmental Qualification of Mechanical & Electrical Equipment.W Status for Items 270.16F & 270.17F Will Be Changed to Confirm W Pending Formal SSAR Rev
AECM-81-202, Forwards Assurance That Facility Will Be in Compliance W/All Applicable NRC Regulations,In Response to NRC Request.Public Health & Safety Will Be Protected
AEP-NRC-2024-20, Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 3, Reactor (Unit 2)
DCL-18-066, 4 to Updated Final Safety Analysis Report, Chapter 8, Electric Power
BSEP 07-0053, Areva Np, Inc., Topical Report, ANP-2637, Revision 1, Boiling Water Reactor Licensing Methodology Compendium
TSTF-07-18, TSTF-486, Revision 2, Revise Mtc Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011)
BVY 06-080, Extended Power Uprate - License Amendment No. 229 Clarifications to NRCs Final Safety Evaluation
LIC-04-0097, License Amendment Request (Lar), Core Operating Limits Report and Application of CASMO-4 Methodology
NUREG-0754, Requests Commission Approval of Issuance of Draft Fr Notice Requiring Documentation of Deviations from SRP & Draft NUREG-0754, Plan for Systematic Safety Evaluation of Nuclear Power Reactors. Related Documentation Encl
RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
DCL-24-118, License Amendment Request 24-06, Revision to Technical Specification 1.1 and Addition of 5.5.21 to Use Online Monitoring Methodology
ND-21-0486, 0 to Updated Final Safety Analysis Report, Chapter 4, Reactor
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
RA-19-0424, 2 to Updated Final Safety Analysis Report, Chapter 4, Reactor