Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
IR 05000272/2021004 | 10 February 2022 | Integrated Inspection Report 05000272/2021004 and 05000311/2021004 |
IR 05000272/2018001 | 14 May 2018 | Integrated Inspection Reports 05000272/2018001 and 05000311/2018001 |
ML17335A118 | 25 January 2018 | Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident |
ML20311A406 | 6 November 2017 | 2017 Q1-Q4 ROP Inspection Findings |
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 Reactors | 11 August 2017 | 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 Reactors |
IR 05000272/2016002 | 10 April 2017 | Revised Integrated Inspection Report 05000272/2016002 and 05000311/2016002 |
ML17046A450 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Sections 8.3, Onsite Power System |
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Sections 8.3, Onsite Power System | 30 January 2017 | Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Sections 8.3, Onsite Power System |
ML16266A224 | 22 September 2016 | Integrated Inspection Report 05000272/2016002 and 05000311/2016002 |
ML16235A471 | 26 August 2016 | Request for an Extension to Enforcement Guidance Memorandum 12-001 |
05000272/LER-2016-001 | 5 July 2016 | Unanalyzed Condition due to Degraded Reactor Baffle to Former Bolts LER 16-001-00 for Salem, Unit 1, Regarding Unanalyzed Condition due to Degraded Reactor Baffle to Former Bolts |
ML15105A346 | 23 March 2015 | NSAL-15-2 - Impact of a Break in the Reactor Coolant Pump No. 1 Seal Leak-off Line Piping on Seal Leakage During a Loss of Seal Cooling Event |
IR 05000272/2015007 | 12 March 2015 | IR 05000272/2015007, 05000311/2015007; on 01/26/2015 - 02/13/2015; Salem Nuclear Generating Station, Units 1 and 2; Triennial Fire Protection Inspection Report |
IR 05000272/2014003 | 4 August 2014 | IR 05000272-14-003 and 05000311-14-003, April 1, 2014 Through June 30, 2014, Salem Nuclear Generating Station, Units 1 and 2, NRC Integrated |
ML14140A307 | 16 June 2014 | Staff Assessment of Response to Enclosure 4 of the March 12, 2012, 10 CFR 50.54(f) Information Request - Flooding Walkdowns |
ML14113A236 | 14 May 2014 | Staff 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 |
ML14113A244 | 14 May 2014 | Staff 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) |
ML13308C286 | 6 February 2014 | Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident |
LR-N13-0172, Enclosure 1 - Salem Nuclear Generating Station Unit 1 Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic | 20 December 2013 | Enclosure 1 - Salem Nuclear Generating Station Unit 1 Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic |
ML13127A188 | 31 May 2013 | Plan for the Regulatory Audit Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident - Oyster Creek Nuclear Generating Station |
ML13127A455 | 20 May 2013 | Plan for the Regulatory Audit Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident |
ML12334A451 | 21 November 2012 | SL-2012-10795, Rev. 0, Sgs Flood Walkdown Report, 10 CFR 50.54(f) Section 2.3 (Flood) Response. |
ML12053A340 | 12 March 2012 | Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident |
ML12056A050 | 12 March 2012 | Enclosure 4 - Recommendation 2.3: Flooding |
ML12056A049 | 12 March 2012 | Enclosure 3 - Recommendation 2.3: Seismic |
LR-N11-0217, Response to Requests for Additional Information (Rais) for Emergency Action Level Changes | 14 July 2011 | Response to Requests for Additional Information (Rais) for Emergency Action Level Changes |
ML102430586 | 9 November 2010 | Audit Report Regarding the Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application (TAC Nos. ME1834 and ME1836) |
ML110050375 | 14 October 2010 | Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) |
ML110050402 | 14 October 2010 | Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) |
LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) | 14 October 2010 | Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) |
LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) | 14 October 2010 | Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) |
ML11215A180 | 30 July 2010 | Attachment 1, Hope Creek Generating Stations EAL Technical Bases Document, EP-HC-111-201 |
LR-N09-0034, License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical Specifications | 9 April 2009 | License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical Specifications |
IR 05000272/2006005 | 1 February 2007 | IR 05000272-06-005, 05000311-06-005; 10/01/2006 - 12/31/2006; Salem Generating Station Units 1 and 2; Equipment Alignment, Inservice Inspection, Refueling and Outage |
ML041200107 | 31 March 2004 | WCAP-16193-NP, Salem Units 1 and 2, Containment Response to LOCA and MSLB for Containment Fan Cooler Unit/Service Water System Enhancement Project. |
ML032890431 | 8 October 2003 | Event Classification Guide Technical Basis, 10/08/03, Change Pages for Revision No. 18 |
ML032810475 | 1 October 2003 | Transmittal of Salem Event Classification Guide Technical Basis |
ML032591160 | 10 September 2003 | Revision No. 44 to Salem Generating Station Event Classification Guide |
ML031990029 | 9 July 2003 | Revised Emergency Plan Implementing Procedures |
ML030650804 | 27 February 2003 | Revision 16 Tto SECG-TOC-BASIS and Revision 2 to SECG-SECT.03.1 |
ML030410018 | 31 January 2003 | Event Classification Guide Technical Basis |
ML030340164 | 23 January 2003 | Event Classification Guide |
ML022810630 | 26 September 2002 | Revisions to Event Classification Guide |
ML022270230 | 6 August 2002 | Revised Emergency Plan Implementing Procedures |
ML053220386 | 13 May 2002 | PSEG Nuclear L.L.C. SH.OP.AP.ZZ-0101 (Q) - Rev 6 Post-Transient Response Requirements |
ML021430011 | 7 May 2002 | Event Classification Guide May 7, 2002 |
ML021220553 | 19 April 2002 | Transmittal of Salem Generating Station Event Classification Guide Technical Basis PRC |
ML020720584 | 28 February 2002 | Event Classification Guide, February 28, 2002, Change Pages for Revision #35 |
ML18107A529 | 10 September 1999 | Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 |
ML18107A296 | 12 May 1999 | Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9 |