Semantic search

Jump to navigation Jump to search
 Issue dateTitle
CNL-22-027, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 4028 April 2022Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 40
ML20338A03823 February 2021Issuance of Amendment Nos. 336 and 317 Leak-Before-Break for Accumulator, Residual Heat Removal, Safety Injection, and Pressurizer Surge Lines
LR-N20-0010, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology24 April 2020License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology
LR-N19-0102, Revision 31 to Updated Final Safety Analysis Report, Chapter 4, Reactor5 December 2019Revision 31 to Updated Final Safety Analysis Report, Chapter 4, Reactor
ML17335A11825 January 2018Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident
ML17349A10818 January 2018Issuance of Amendments Containment Fan Coil Unit Allowed Outage Time Extension (CAC Nos. MF9364 and MF9365; EPID L-2017-LLA-0212)
LR-N17-0125, Response to Request for Additional Information Regarding Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors11 August 2017Response to Request for Additional Information Regarding Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
LR-N17-0091, Supplemental Information Needed for Acceptance of Requested Licensing Action Containment Fan Cooler Unit (Cfcu) Allowed Outage Time (AOT) Extension4 May 2017Supplemental Information Needed for Acceptance of Requested Licensing Action Containment Fan Cooler Unit (Cfcu) Allowed Outage Time (AOT) Extension
ML17101A60418 April 2017Staff Review of Mitigation Strategies Assessment Report of the Impact of the Reevaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(f) Letter
ML17164A31424 February 2017Enclosures 1 & 2: PSEG Nuclear, LLC Quality Assurance Topical Report, NO-AA-10, Revision 86
LR-N17-0088, Enclosures 1 & 2: Pseg Nuclear, LLC Quality Assurance Topical Report, NO-AA-10, Revision 8624 February 2017Enclosures 1 & 2: Pseg Nuclear, LLC Quality Assurance Topical Report, NO-AA-10, Revision 86
ML17046A27630 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 2.5, Figure 2.5-1 Through Figure 2.5-13
ML17046A24430 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 2, Table of Contents
ML17046A24330 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 1.6, List of Acronyms
ML17046A30230 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 3.10, Seismic Qualification of Seismic Category I Instrumentation and Electrical Equipment
ML17046A31230 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 4.2, Mechanical Design
ML17046A22930 January 2017Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85
ML17046A34830 January 2017Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.1 to 5.1-8
ML17046A40530 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 6.3, Emergency Core Cooling System
ML17046A40130 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 6.2, Containment Systems
ML17046A39530 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 5.5, Component and Subsystem Design
ML17046A27430 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 2.5, Geology and Seismology
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 6.3, Emergency Core Cooling System30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 6.3, Emergency Core Cooling System
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 6.2, Containment Systems30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 6.2, Containment Systems
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 5.5, Component and Subsystem Design30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 5.5, Component and Subsystem Design
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.1 to 5.1-830 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.1 to 5.1-8
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 4.2, Mechanical Design30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 4.2, Mechanical Design
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 3.10, Seismic Qualification of Seismic Category I Instrumentation and Electrical Equipment30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 3.10, Seismic Qualification of Seismic Category I Instrumentation and Electrical Equipment
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.5, Figure 2.5-1 Through Figure 2.5-1330 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.5, Figure 2.5-1 Through Figure 2.5-13
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.5, Geology and Seismology30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.5, Geology and Seismology
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2, Table of Contents30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2, Table of Contents
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 1.6, List of Acronyms30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 1.6, List of Acronyms
LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 8530 January 2017Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85
ML16351A23119 January 2017Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 and Staff Closure of Activities Associated with Recommendation 2.1
ML16351A18219 January 2017Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
LR-N16-0094, Spent Fuel Pool Evaluation Supplemental Report, 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 Accident6 December 2016Spent Fuel Pool Evaluation Supplemental Report, 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
LR-N16-0120, Compliance with March 12, 2012 NRC Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) and Final Integrated Plan28 September 2016Compliance with March 12, 2012 NRC Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) and Final Integrated Plan
ML16054A06828 March 2016Issuance of Amendments Regarding Revision to Reactor Trip System Instrumentation Technical Specifications
ML15364A54418 February 2016Staff Review of High Frequency Confirmation Associated with Reevaluated Seismic Hazard Implementating Near-Term Task Force Recommendation 2.1 Seismic for Specific Licensees
ML16041A03318 February 2016Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force
LR-N16-0012, Supplemental Response to Request for Additional Information License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems10 February 2016Supplemental Response to Request for Additional Information License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems
LR-N15-0255, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi..23 December 2015High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi..
LR-N15-0232, Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request Regarding Chilled Water System Modification5 November 2015Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request Regarding Chilled Water System Modification
IR 05000272/201500228 July 2015IR 05000272/2015002; 05000311/2015002: April 1, 2015 Through June 30, 2015, Salem Nuclear Generating Station, Units 1 & 2 - Integrated Inspection Report
LR-N15-0020, License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation27 March 2015License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation
ML14310A03315 December 2014NRC Response to Licensees Notification of Revised Regulatory Commitments Associated with Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Revie
ML14167A1592 September 2014Summary of Category 1 Public Meeting with Salem Nuclear Generating Station, Units 1 and 2 to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1 Seismic
ML14113A23614 May 2014Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident
ML14113A24414 May 2014Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident (Tac No. MF0172)
ML14111A1479 May 2014Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights