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LR-N18-0053, Revision 30 to Updated Final Safety Analysis Report, Appendix a, TMI Lessons Learned11 May 2018Revision 30 to Updated Final Safety Analysis Report, Appendix a, TMI Lessons Learned
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-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned
ML17046A34730 January 2017Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML17046A41530 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 7.3, Engineered Safety Features Instrumentation
ML17046A58930 January 2017Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned
ML17046A39830 January 2017Revision 29 to Updated Final Safety Analysis Report, Section 5.6, Instrumentation Application
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 7.3, Engineered Safety Features Instrumentation30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 7.3, Engineered Safety Features Instrumentation
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 5.6, Instrumentation Application30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 5.6, Instrumentation Application
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems30 January 2017Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML15009A2863 December 2014Final Written Examination with Answer Key (401-5 Format) (Folder 2)
LR-N11-0217, Response to Requests for Additional Information (Rais) for Emergency Action Level Changes14 July 2011Response to Requests for Additional Information (Rais) for Emergency Action Level Changes
ML11006018914 October 2010Hope Creek, Bases Figure B 3/4 3-1, Reactor Vessel Water Level.
ML11005037514 October 2010Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)
ML11005040214 October 2010Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)
LR-N10-0355, Hope Creek, Bases Figure B 3/4 3-1, Reactor Vessel Water Level.14 October 2010Hope Creek, Bases Figure B 3/4 3-1, Reactor Vessel Water Level.
LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)14 October 2010Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)
ML11005039814 October 2010Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix
LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix14 October 2010Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix
LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)14 October 2010Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)
LR-N10-0355, Hope Creek, HC.OP-SO.BC-0002(Q), Rev. 25, Decay Heat Removal Operation.1 October 2010Hope Creek, HC.OP-SO.BC-0002(Q), Rev. 25, Decay Heat Removal Operation.
ML1100601571 October 2010Hope Creek, HC.OP-SO.BC-0002(Q), Rev. 25, Decay Heat Removal Operation.
ML11006023812 August 2010Salem, EAL Comparison Matrix
LR-N10-0355, Salem, EAL Comparison Matrix12 August 2010Salem, EAL Comparison Matrix
ML11006022030 July 2010EP-SC-1 11-200, Salem, Event Classification Guide, Emergency Action Level Technical Bases.
ML11215A18030 July 2010Attachment 1, Hope Creek Generating Stations EAL Technical Bases Document, EP-HC-111-201
ML11006022230 July 2010EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases.
LR-N10-0355, EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases.30 July 2010EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases.
LR-N10-0355, EP-SC-1 11-200, Salem, Event Classification Guide, Emergency Action Level Technical Bases.30 July 2010EP-SC-1 11-200, Salem, Event Classification Guide, Emergency Action Level Technical Bases.
ML11006014425 April 2009Hope Creek, HC.OP-IO.ZZ-0005(Q), Rev. 30, Cold Shutdown to Refueling.
LR-N10-0355, Hope Creek, HC.OP-IO.ZZ-0005(Q), Rev. 30, Cold Shutdown to Refueling.25 April 2009Hope Creek, HC.OP-IO.ZZ-0005(Q), Rev. 30, Cold Shutdown to Refueling.
IR 05000272/200800920 January 2009IR 05000272-08-009, on 10/21/2008-12/12/2008, Salem Nuclear Generating Station Unit No. 1, Special Inspection Report, Procedures, Operator Performance, Corrective Action
IR 05000272/20080035 August 2008IR 05000272-08-003, 05000311-08-003, on 04/01/2008 - 06/30/2008, Salem Nuclear Generating Station Units 1 and 2, Maintenance Risk Assessment and Emergent Work Control, Operability Evaluations, Surveillance Testing
ML0806704197 March 2008CDBI Findings
ML06128052725 May 2006License Amendments, Issuance of Amendments Containment Area High-Range Radiation Monitors
LR-N05-0392, Request for Change to Technical Specifications Accident Monitoring Instrumentation31 August 2005Request for Change to Technical Specifications Accident Monitoring Instrumentation
ML06058072614 October 2004Fax from K. Rutigliano to G. Cobey of USNRC, Regarding PSEG Nuclear Safety Notification
ML06222007514 October 2004E-mail from Schoppy to Various, PSEG Nuclear Safety Issue
ML06222007313 October 2004E-mail to Blough, Nuclear Safety Concerns at Salem/Hope Creek
ML0403704289 February 200401/21-22/2004 - Attachments 7 and 8, Questions & Answers
ML03065080427 February 2003Revision 16 Tto SECG-TOC-BASIS and Revision 2 to SECG-SECT.03.1
ML06059040616 April 2001Memorandum from H. Keiser of PSEG to All PSEG Nuclear Employees, Regarding PSEG Nuclear Management Expectations Memorandum Program
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
NRC Generic Letter 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
ML18102A79321 January 1997Event Classification Guide,Technical Basis, Salem Generating Station
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
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