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Issue date | Title | |
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IR 05000272/2008003 | 5 August 2008 | IR 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 |
IR 05000272/2008009 | 20 January 2009 | IR 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 |
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
LR-N05-0392, Request for Change to Technical Specifications Accident Monitoring Instrumentation | 31 August 2005 | Request for Change to Technical Specifications Accident Monitoring Instrumentation |
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) |
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 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix | 14 October 2010 | Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix |
LR-N10-0355, EP-SC-1 11-200, Salem, Event Classification Guide, Emergency Action Level Technical Bases. | 30 July 2010 | EP-SC-1 11-200, 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 2010 | EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases. |
LR-N10-0355, Hope Creek, Bases Figure B 3/4 3-1, Reactor Vessel Water Level. | 14 October 2010 | Hope Creek, Bases Figure B 3/4 3-1, Reactor Vessel Water Level. |
LR-N10-0355, Hope Creek, HC.OP-IO.ZZ-0005(Q), Rev. 30, Cold Shutdown to Refueling. | 25 April 2009 | Hope Creek, HC.OP-IO.ZZ-0005(Q), Rev. 30, Cold Shutdown to Refueling. |
LR-N10-0355, Hope Creek, HC.OP-SO.BC-0002(Q), Rev. 25, Decay Heat Removal Operation. | 1 October 2010 | Hope Creek, HC.OP-SO.BC-0002(Q), Rev. 25, Decay Heat Removal Operation. |
LR-N10-0355, Salem, EAL Comparison Matrix | 12 August 2010 | Salem, EAL Comparison Matrix |
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 |
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned | 30 January 2017 | Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned |
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems | 30 January 2017 | Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems |
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 5.6, Instrumentation Application | 30 January 2017 | Salem 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, Section 7.3, Engineered Safety Features Instrumentation | 30 January 2017 | Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 7.3, Engineered Safety Features Instrumentation |
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 |
LR-N18-0053, Revision 30 to Updated Final Safety Analysis Report, Appendix a, TMI Lessons Learned | 11 May 2018 | Revision 30 to Updated Final Safety Analysis Report, Appendix a, TMI Lessons Learned |
ML030650804 | 27 February 2003 | Revision 16 Tto SECG-TOC-BASIS and Revision 2 to SECG-SECT.03.1 |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML040370428 | 9 February 2004 | 01/21-22/2004 - Attachments 7 and 8, Questions & Answers |
ML060580726 | 14 October 2004 | Fax from K. Rutigliano to G. Cobey of USNRC, Regarding PSEG Nuclear Safety Notification |
ML060590406 | 16 April 2001 | Memorandum from H. Keiser of PSEG to All PSEG Nuclear Employees, Regarding PSEG Nuclear Management Expectations Memorandum Program |
ML061280527 | 25 May 2006 | License Amendments, Issuance of Amendments Containment Area High-Range Radiation Monitors |
ML062220073 | 13 October 2004 | E-mail to Blough, Nuclear Safety Concerns at Salem/Hope Creek |
ML062220075 | 14 October 2004 | E-mail from Schoppy to Various, PSEG Nuclear Safety Issue |
ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
ML080670419 | 7 March 2008 | CDBI Findings |
ML110050375 | 14 October 2010 | Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) |
ML110050398 | 14 October 2010 | Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix |
ML110050402 | 14 October 2010 | Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) |
ML110060144 | 25 April 2009 | Hope Creek, HC.OP-IO.ZZ-0005(Q), Rev. 30, Cold Shutdown to Refueling. |
ML110060157 | 1 October 2010 | Hope Creek, HC.OP-SO.BC-0002(Q), Rev. 25, Decay Heat Removal Operation. |
ML110060189 | 14 October 2010 | Hope Creek, Bases Figure B 3/4 3-1, Reactor Vessel Water Level. |
ML110060220 | 30 July 2010 | EP-SC-1 11-200, Salem, Event Classification Guide, Emergency Action Level Technical Bases. |