05000317/LER-2008-002, Regarding Pressurizer Safety Valve Setpoint High Due to Low Torque and Misalignment
LIC-17-0024, Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 4 of 4)
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
NRC 2017-0017, License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances
L-16-345, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Cnfpa) Standard 805
2CAN101601, License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications
BVY 16-001, Submittal of 10 CFR 20.2002 Request for Alternate Waste Disposal at Us Ecology
PLA-3150, Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1988
PLA-3354, Semiannual Effluent & Waste Disposal Rept for Jul-Dec 1989
RNP-RA/15-0023, Response (60-Day) to Request for Additional Information Associated with License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805
PLA-7281, Response to Request for Additional Information on Relief Request 4RR-01
L-2014-230, License Amendment Request Application for Technical Specifications Change to Permanently Extend the Integrated Leak Rate Test (ILRT) Frequency to 15 Years
2CAN081401, Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805
W3F1-2014-0025, Updated Responses to Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 License Amendment Request (LAR)
L-2014-071, Response to Request for Additional Information License Amendment Request No. 216 - Transition 10 CFR 50.48(c)-NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants(2001 Edition)
NLS2012068, Response to Acceptance Review of Cooper Nuclear Station License Amendment Request to Adopt NFPA-805
NOC-AE-12002850, Submittal of Radioactive Effluent Release Report for the Year 2011
2CAN011105, Program Section SEP-ISI-105 for ASME Section XI, Division 1, Arkansas Nuclear One, Unit 2, Inservice Inspection Program
CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06)
L-18-085, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805
RC-18-0036, (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information
TSTF-17-19, TSTF Response to NRC Questions on TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics
L-2016-037, St. Lucie - Annual Radioactive Effluent Release Report - 2015
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 3 of 5
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5
PLA-6710, Radioactive Effluent Release Report, 2010
L-10-120, Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2009
RNP-RA/10-0033, Submittal of 2009 Annual Radioactive Effluent Release Report
NOC-AE-10002536, Submittal of Radioactive Effluent Release Report for 2009
GNRO-2008/00071, Inservice Inspection (ISI) Program Third 10-Year Interval, Rev. 0
L-2010-033, St. Lucie, Units 1 and 2, Combined Annual Radioactive Effluent Release Report for the Period January 1, 2009 Through December 31, 2009
2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
2CAN011001, Request for Alternative - Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
NL-09-1510, Vogtle Electric Generating Plant, Units 1 and 2 - Inservice Inspection Plan Third Inspection Interval Volume 1, Version 3.0
RBG-46922, Request for Alternative - Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
1CAN060902, Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
NL-09-0332, Request for Approval of Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 & 2 Piping, VEGP-ISI-ALT-02, Version 1
ULNRC-05598, Proposed Revision to Technical Specification 5.5.16 Containment Leakage Rate Testing Program, (License Amendment Request LDCN 09-0008)
NOC-AE-08002351, Revision 2 to Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
NOC-AE-08002319, Response to RAI Revision to Proposed Amendment to TS 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
1CAN050807, Inservice Inspection Plan for the Fourth 10 - Year Interval
NL-08-068, Indian Point, Units 1, 2 and 3 - 2007 Annual Radioactive Effluent Release Report
NRC-08-0031, Fermi 2- 2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report for the Period of January 1, 2007 Through December 31, 2007
2CAN020804, Responses to Request for Additional Information Request for Alternative ANO2-R&R-004, Revision 1
NOC-AE-07002234, Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
NRC 2018-0038, Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear
NUREG/CR-2907 Volume 16, Radioactive Effluents from Nuclear Power Plants - Annual Report 2010
W3F1-2007-0061, Supplement to Request for Alternative W3-ISI-005 Request to Use ASME Code Case N-716
CNRO-2007-00026, Request for Alternative GG-ISI-002, Response to Request for Additional Information
BVY 07-037, Annual 2006 Radioactive Effluent Release Report
NRC-07-0014, Response to Request for Additional Information Regarding License Amendment Request for Extension of Completion Time for an Inoperable Emergency Diesel Generator - Probabilistic Risk Assessment Questions
CPSES-200700130, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators
CPSES-200601634, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators
RS-06-039, Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
NL-06-056, Offsite Dose Calculation Manual (ODCM)
RNP-RA/06-0034, Annual Radioactive Effluent Release Report
RA-19-0007, License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications
GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval
W3F1-2019-0039, (Waterford 3) - Response to Request for Additional Information Regarding Relief Request W3-ISI-032
RA-19-0067, License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies
L-05-104, Probabilistic Safety Review for License Amendment Request Nos. 302 and 173
PLA-5768, Response to Request for Additional Information from NRC on Proposed Relief Request No. 3RR-01 to the Third 10-Year Inservice Inspection Program
3F1203-03, License Amendment Request No. 281, Revision 0 Regarding Revised Improved Technical Specification (ITS) 3.7.5, Emergency Feedwater System
L-04-072, License Amendment Request Nos. 306 and 176 Re Revision to Current 72 Hours Action Allowed Outage Time
L-15-188, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
NRC 2004-0010, Emergency Plan Implementing Procedures Manual and Emergency Plan Manual Revisions
CPSES-200400149, License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
NOC-AE-03001605, Response to NRC Questions Regarding a Proposed License Amendment to Eliminate the Turbine Missile Design Basis
NRC 2003-0081, Revised Emergency Plan Implementing Procedures
NLS2003051, Annual Radioactive Effluent Release Report, Appendix B, Pages B191 - 325 and Appendix C, Pages C1 - 53, References
ULNRC-04840, Annual Radioactive Effluent Release Report
RNP-RA/03-0053, Annual Radioactive Effluent Release Report, Section 3.6 Through Appendix C, Figure D-2
L-2003-033, 2002 Annual Radioactive Effluent Release Report, Section 2.0, Appendix A-D
L-2002-233, Westinghouse Report WCAP-15945-NP, Rev. 1, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: St. Lucie Unit 1
RC-02-0161, Application of the EPRI Risk-Informed ISI Methodology to: VC Summer (Class 1 and 2), Risk Ranking Results - Table 5-2
NRC 2003-0039, Annual Monitoring Report for Point Beach for 2002
TSTF-20-01, Transmittal of TSTF-IG-20-02, Guidance on Evaluating One-Time Surveillance Frequency Changes Under the Surveillance Frequency Control Program (TSTF-425M SFCP)
CNL-20-044, License Amendment Request to Incorporate Tornado Missile Risk Evaluation Into the Licensing Basis
IA-85-465, Partial Response to FOIA Request for Five Specified Summaries of Idcor/Nrc Technical Exchange Meetings.Forwards App a Documents.Records Placed in Pdr.Search Continuing for Other Meeting Summaries
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
NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)
2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods
NL-21-0918, License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 5
1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period
BSEP-82-1754, Semiannual Environ & Effluent Release Rept,Jan-June 1982
LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations
W3P89-0044, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1988
BECO-LTR-92-036, Annual Dose Assessment to General Public from Radioactive Effluents,1991
3F0907-03, License Amendment Request 295, Revision 0: Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Response to Request for Additional Information
05000370/LER-1996-002-02, :on 960306,past Inoperability of EDG 2B Occurred Due to Low Lube Oil Pressure Caused by Unanticipated Interaction of Sys & Components.Increased Frequency for Periodic Venting
05000445/LER-1990-006, :on 900412,P-6 Permissive Signal Received & Source Range Flux Doubling (Srfd) Actuation Occurred.Caused by Inadvertent Reset of Srfd Block.Integrated Plant Operations Procedures Changed
CNL-19-002, Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,
HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors
PLA-3739, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1991
L-93-216, Combined Semiannual Radioactive Release Rept for Jan-June 1993 for St Lucie Plant,Units 1 & 2
L-93-021, ERS-ATL-93-021, Rev. 4, Process Alarm Setpoints for Liquid Effluent Monitors
RNP-RA/16-0017, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants
SBK-L-14056, Response to Request for Additional Information Regarding License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency.
CPSES-200302754, License Amendment Request (LAR) 03-07 Revision to Technical Specification (TS) 3.8.1 and 3.8.9, Extension of Allowable Completion Times for Diesel Generators, Qualified Offsite Circuits and AC Electrical Power
NRC-2009-0435, Comment (12) of Barbara A. Oneal on Draft Environmental Assessment and Finding of No Significant Impact for Nuclear Fuel Services, Inc., Erwin, Tn, for 40-Year License Renewal
LR-N21-0066, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations
W3F1-2021-0003, Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B
GO2-20-104, On-Site Cooling System Sediment Disposal
RA-23-0282, Second Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement