05000530/LER-2015-004, Condition Prohibited by Technical Specifications 3.0.4 and 3.7.2 Due to an Inoperable Main Steam Isolation Valve
RS-17-051, Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
L-MT-17-016, Risk-Informed Request for Exemption from 10 CFR 50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves
CNL-17-071, Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A
L-MT-13-062, Response to an Apparent Violation in NRC Inspection Report 05000263/2013008 (EA-13-096)
L-15-150, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
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
NG-13-0182, 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 Generating Plants
W3F1-2012-0064, Response to Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 License Amendment Request
ULNRC-05908, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives
L-11-150, Offsite Dose Calculation Manual, Rev. 24
SBK-L-11001, Response to Request for Additional Information, NextEra Energy License Renewal Application
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 7, Instrument and Control
NG-17-0235, Duane Arnold Energy Center, Calc No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 06
TMI-10-021, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
RS-09-121, License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time
ULNRC-05621, 2008 Annual Radioactive Effluent Release Report
NUREG/CR-2907 Volume 16, Radioactive Effluents from Nuclear Power Plants - Annual Report 2010
NRC-07-0034, Response to Request for Additional Information Regarding License Amendment Request for Extension of Completion Time for an Inoperable Emergency Diesel Generator
CNRO-2007-00022, Request for Alternative GG-ISI-002, Response to Requests for Additional Information
PLA-6154, Response to SAMA Request for Additional Information
NRC-06-0040, Proposed License Amendment Request to Extend the Completion Time for Technical Specification 3.8.1 for an Inoperable Emergency Diesel Generator
3F0506-05, 2005 Technical Specifications Bases Control Program
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
CPSES-200500921, Transmittal of the Annual Radiological Environmental Operating Report for 2004
3F1003-09, Emergency Response Data System
ULNRC-04840, Annual Radioactive Effluent Release Report
L-03-072, Annual Radioactive Release Report for 2002, Table of Contents Through Attachment E
L-2002-239, Proposed License Amendments Request for Additional Information Response on Risk Informed One Time Increase in Integrated Leak Rate Test Surveillance Interval
NUREG/CR-2907 Volume 24, Radioactive Effluents from Nuclear Power Plants - Annual Report 2018
2CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
NUREG/CR-2907 Volume 25, Radioactive Effluents from Nuclear Power Plants: Annual Report 2019
BECO-94-126, Application for Amend to License DPR-35,increasing Current EDG Allowed out-of-svc Time in Specification 3.5.F from 72 H to 7 Days
NUREG/CR-2907 Volume 26, Radioactive Effluents from Nuclear Power Plant - Annual Report 2020
A000364, Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of ABWR Design
3F0702-07, License Amendment Request 257, Revision 0, Emergency Diesel Generator Allowed Outage Time Extension.
NUREG/CR-2907 Volume 27, Radioactive Effluents from Nuclear Power Plants: Annual Report 2021
05000362/LER-1994-001-01, :on 940416,channel B Containment Emergency Sump Level Lumigraph Indicator 3LI-9389-2 Observed W/No Light Bars Illuminated.Caused by Failure of Level Signal Converter 3LY-9389-2.Failed Signal Converter Replaced
RAIO-0218-58544, LLC Response to NRC Request for Additional Information No. 301 (Erai No. 9236) on the NuScale Design Certification Application
05000315/LER-1999-010, :on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
GO2-97-001, Submits Supplemental Info & Corrective Actions to Insp Rept 50-397/96-18.Corrective Actions:Problem Evaluation Rept 296-0802 Generated to Document & Resolve Failure to Link PSA Results W/Maint Rule Reliability Criteria
GO2-94-215, Requests Enforcement Discretion from TS 3.6.3.a,for 14 Days Starting on 940915 to Allow Time to Process TS Amend Under Emergency Conditions
NUREG/CR-2907 Volume 19, Radioactive Effluents from Nuclear Power Plants - Annual Report 2013
05000370/LER-2010-001, Regarding Loose Connection in a Panel Board Serving a Solid State Protection System Train Maintenance Could Have Prevented Fulfillment of a Safety Function
NL-09-1570, Response to Request to Request for Additional Information Related to Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 and 2 Piping, VEGP-ISI-ALT-02, Version 1
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
W3F1-2004-0095, To Amendment Request NPF-38-256 Alternate Source Term
3F0702-07, License Amendment Request 257, Revision 0, Emergency Diesel Generator Allowed Outage Time Extension
RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency
05000361/LER-1994-012, :on 940126,inadequacies in Electrical Distribution Sys Design Calculations.Caused by Incorrect Engineering Judgement.C/A:Upgraded MCC Control Circuit for 2HV9303 by Replacing Transformer
L-25-160, Emergency License Amendment Request for Technical Specification 3.3.9 to Allow Use of Alternate Neutron Instrumentation