ONS-2016-017, Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2)
L-MT-13-062, Response to an Apparent Violation in NRC Inspection Report 05000263/2013008 (EA-13-096)
PLA-7193, Request to Continue Use of a Risk-Informed Inservice Inspection Alternative in a Proposed Relief Request No. 4RR-01 to the Fourth 10-Year Inservice Inspection Program
CP-201400324, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
L-PI-14-028, PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
L-PI-13-102, License Amendment Request (LAR) to Revise Staff Augmentation Times in the Prairie Island Nuclear Generating Plant (PINGP) Emergency Plan
2CAN111301, Response to Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-805
RS-13-131, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
NG-12-0177, Response to Request for Additional Information, License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generational Plants
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 7, Instrument and Control
L-2016-037, St. Lucie - Annual Radioactive Effluent Release Report - 2015
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
NG-17-0235, Duane Arnold Energy Center, Calc No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 6
RS-10-108, Additional Information Supporting Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
LR-N10-0164, Response to NRC Request for Additional Information Dated April 12, 2010, Related to the Severe Accident Mitigation Alternatives Review
NLS2009048, Response to Request for Additional Information for License Renewal Application Severe Accident Mitigation Alternatives
RBG-46922, Request for Alternative - Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
NL-09-045, Indian Point, Units 1, 2, & 3, Offsite Dose Calculation Manual Changes and Justification Packages for 2008
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 8.0 - Electric Power
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 7.0 - Instrumentation and Control Systems
NL-08-068, Indian Point, Units 1, 2 and 3 - 2007 Annual Radioactive Effluent Release Report
ULNRC-05476, One-Time Completion Time Extension for Essential Service Water (ESW) System
NUREG/CR-2907 Volume 16, Radioactive Effluents from Nuclear Power Plants - Annual Report 2010
TSTF-03-11, Traveler - November 17, 2003, Transmits TSTF-372, R.3 Addition of LCO 3.0.8, Inoperability of Snubbers
NL-07-098, Request for Extension of Completion Date for Indian Point Unit 3 Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Press
CPSES-200700146, License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits
LR-N06-0358, Response to RAIs on LCR S06-03 Request for Change to Technical Specifications Accident Monitoring Instrumentation and Source Check Definition
RS-06-048, ILRT Interval Extension Risk Assessment
NL-06-056, Offsite Dose Calculation Manual (ODCM)
NOC-AE-06001994, Response to NRC Requests for Additional Information on STPNOC Proposed Risk-Informed Technical Specifications
NUREG/CR-2907 Volume 20, Radioactive Effluents from Nuclear Power Plants - Annual Report 2014
NUREG/CR-2907 Volume 21, Radioactive Effluents from Nuclear Power Plants - Annual Report 2015
ULNRC-06523, 2018 Annual Radioactive Effluent Release Report, Revision 1
NUREG/CR-2907 Volume 22, Radioactive Effluents from Nuclear Power Plants - Annual Report 2016
NUREG/CR-2907 Volume 23, Radioactive Effluents from Nuclear Power Plants - Annual Report 2017
NRC 2005-0070, Response to Request for Additional Information Regarding Request for Exigent Review of Heavy Load Analysis
CPSES-200300788, Additional Information Concerning CPSES Ninth Refueling Outage Steam Generator Tube Conditions
NOC-AE-14003105, Third Set of Responses to April, 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Licensing Application
RC-02-0123, Application for Renewed Operating License, Appendix F Severe Accident Mitigation Alternatives
NRC-02-0040, Proposed License Amendment for a One-Time Deferral of the Primary Containment Integrated Leak Rate Test
PLA-5470, To Proposed Amendment No. 239 to License NPF-14 & Proposed Amendment No. 204 to License NPF-22: HPCI Automatic Transfer to Suppression Pool Logic Elimination
NUREG/CR-2907 Volume 24, Radioactive Effluents from Nuclear Power Plants - Annual Report 2018
L-2021-110, Emergency Response Data System (ERDS) Changes
NUREG/CR-2907 Volume 25, Radioactive Effluents from Nuclear Power Plants: Annual Report 2019
BVY-98-114, Provides Response to Request for Addl Info Re Implementation of ASME Code N560 at Plant
L-2022-038, Emergency Response Data System (Eros) Changes
AECM-88-0174, Semiannual Radioactive Effluent Release Rept,Jan-June 1988
BECO-85-180, Provides Info to Close Remaining Open Issues Re NUREG-0737, Item I.D.2 Concerning Spds.Complete List of Radiation Monitors Which Will Be Used in SPDS for Monitoring Radioactivity Control Safety Provided
ST-HL-AE-4248, Forwards Changes to Emergency Response Data Sys (ERDS) Data Point Library (Dpl),Per 10CFR50 & NUREG-1394,rev 1
B14323, Forwards Dpl for Millstone Unit 1,2,3 & Haddam Neck Plant. Dpl Lists Data Points That Will Be Transmitted for Erds. Update to ERDS Will Incorporate Changes Identified During Sys Testing Performed W/Nrc Contractor
ET-NRC-92-3789, Forwards Westinghouse Response to NRC 920923,1001,09 & 28 Requests for Addl Info on AP600
L-06-221, Rev 0 to in Situ Operational Testing of HPCS Svc Water Pump for Grand Gulf Nuclear Power Station
ST-HL-AE-4028, Forwards ERDS Data Point Library,Rev a for Conformance W/ NUREG-1394 & ERDS Communications Description & Questionnaire
NUREG/CR-2907 Volume 26, Radioactive Effluents from Nuclear Power Plant - Annual Report 2020
3F0407-12, License Amendment Request 295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time
3F0105-02, License Amendment Request 289, Revision 0 Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling Systems - Operating, 3.6.6, Reactor Building Spray & Containment Cooling Systems, 3.7.8, Decay Heat Closed Cycle.
NUREG/CR-2907 Volume 27, Radioactive Effluents from Nuclear Power Plants: Annual Report 2021
05000318/LER-2023-001-01, Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power
05000309/LER-1996-035, :on 961018,requirement for Post Accident Iodine Sampling Inadvertently Removed from Procedure.Caused by Inadequate Control of Licensing Commitment.Procedure 9-304-1 Was Corrected
JAFP-23-0064, Emergency Plan Document Revision
RAIO-0518-60098, LLC - Response to NRC Request for Additional Information No. 397 (Erai No. 9238) on the NuScale Design Certification Application
GO2-84-465, Semiannual Effluent Rept,Jan-June 1984
GO2-90-144, Washington Nuclear Plant 2 Semiannual Effluent Release Rept,Jan-June 1990
L-94-220, Forwards Response to Addl Info Re Proposed License Amends on Flood Protection
NUREG/CR-2907 Volume 19, Radioactive Effluents from Nuclear Power Plants - Annual Report 2013
L-PI-12-007, Response to Requests for Additional Information for License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8, Cooling Water System & 3.8.3, Diesel Fuel Oil
L-09-143, License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation
RNP-RA/05-0048, Response to NCR Request for Additional Information Regarding Proposed Technical Specifications Changes to Section 3.3
RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program
NLS2003051, Annual Radioactive Effluent Release Report, Appendix B, Pages B191 - 325 and Appendix C, Pages C1 - 53, References
NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .
05000318/LER-2023-001, Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power
L-25-160, Emergency License Amendment Request for Technical Specification 3.3.9 to Allow Use of Alternate Neutron Instrumentation