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| Issue date | Title | Topic | |
|---|---|---|---|
| 05000272/LER-2015-002 | 16 November 2016 | Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable LER 15-002-002 for Salem, Unit 1, Regarding Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable | Time of Discovery Past operability |
| 05000272/LER-2015-007 | 29 January 2016 | Inoperable Control Room Emergency Air Conditioning System Due to Failed Charcoal Filter Surveillance Test LER 15-007-01 for Salem, Unit 1, Regarding Inoperable Control Room Emergency Air Conditioning System Due to Failed Charcoal Filter Surveillance Test | Time of Discovery |
| 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 | Safe Shutdown Unanalyzed Condition |
| 05000272/LER-2017-001 | 8 January 2018 | Containment Integrity Inoperable for Longer than Allowed by Technical Specifications LER 17-001-00 for Salem Generating Station, Unit 1 Regarding Containment Integrity Inoperable for Longer than Allowed by Technical Specifications | Safe Shutdown |
| 05000311/LER-2015-002 | 7 September 2017 | P.O. Box 236, Hancocks Bridge, NJ 08038-0236 PSEG Nadea, II,C OCT 0 2 2015 LR-N15-0205 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LER 311/2015-002-00 Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 SUBJECT: Licensee Event Report 311/2015-002-00 In accordance with the requirements of 10 CFR 50.73(a)(2)(iv), PSEG Nuclear LLC is submitting the enclosed Licensee Event Report (LER) Number 2015-002-00, "Reactor Trip Due to Loss of 4kV Non-Vital Group Bus." There are no regulatory commitments contained in this letter. If you have any questions or require additional information, please contact Mr. David Lafleur of Salem Regulatory Assurance at 856-339-1754. Sincerely, John F. Perry Site Vice President — alem Attachment OCT 0 2 2015 10 CFR 50.73 Page 2 LR-N15-0205 CC Mr. D. Dorman, Administrator— Region 1, NRC Mr. T. Wengert, Licensing Project Manager (acting) — Salem, NRC Mr. P. Finney, USNRC Senior Resident Inspector, Salem (X24) Mr. P. Mulligan, Manager IV, NJBNE Mr. R. Braun, President and Chief Nuclear Officer — Nuclear Mr. T. Cachaza, Salem Commitment Tracking Coordinator Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. D. Lafleur, Salem Regulatory Assurance NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 01-2014) t, , .1 • '., LICENSEE EVENT REPORT (LER) 'S ree Page 2 or required number of digits/characters for each block) APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0113112017 Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are Incorporated Into the licensing process and fed back to Industry. Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mall to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to Impose an information collection does not display a currentlyvaild OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. 1. FACILITY NAME Salem Generating Station - Unit 2 2. DOCKET NUMBER 05000311 3. PAGE 1 OF 4 4. TrrLE Reactor Trip Due to Loss of 4 kV Non-Vital Group Bus LER 15-002-01 for Salem, Unit 2, Regarding Reactor Trip Due to Loss of 4 kV Non-Vital Group Bus | Time of Discovery Coast down |
| 05000311/LER-2015-003 | 22 January 2016 | Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure LER 15-003-00 for Salem, Unit 2, Regarding Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure | |
| 05000311/LER-2016-001 | 21 March 2016 | AFW Loop Response Time Exceeded Technical Specifications LER 16-001-00 for Salem, Unit 2, Regarding AFW Loop Response Time Exceeded Technical Specifications | |
| 05000311/LER-2016-002 | 7 September 2017 | Automatic Reactor Trip due to Main Turbine Trip LER 16-002-01 for Salem, Unit 2, Regarding Automatic Reactor Trip Due to Main Turbine Trip | |
| 05000311/LER-2016-003 | 14 April 2016 | Automatic Reactor Trip due to Main Generator Protection Trip LER 16-003-00 for Salem, Unit 2, Regarding Automatic Reactor Trip due to Main Generator Protection Trip | |
| 05000311/LER-2016-005 | 29 August 2016 | Automatic Reactor Trip due to Main Generator Protection Trip LER 16-005-00 for Salem Generating Station, Unit 2 Regarding Automatic Reactor Trip due to Main Generator Protection Trip | |
| 05000311/LER-2016-006 | 31 October 2016 | Automatic Reactor Trip Due to Trip of the 21 Reactor Coolant Pump LER 16-006-00 for Salem, Unit 2, Regarding Automatic Reactor Trip Due to Trip of the 21 Reactor Coolant Pump | Safe Shutdown |
| 05000311/LER-2017-001 | 13 June 2017 | Emergency Diesel Generator Start Due to a Loss of Power to the 2C 4160 Volt Vital Bus LER 17-001-00 for Salem, Unit 2, Regarding Emergency Diesel Generator Start Due to a Loss of Power to the 2C 4160 Volt Vital Bus | |
| CNL-18-075, ISFSI, Sequoyah, Units 1 and 2, ISFSI, Watts Bar, Units 1 and 2, ISFSI - Service List Update for Documents Containing Official Use Only and Safeguards Information | 25 May 2018 | ISFSI, Sequoyah, Units 1 and 2, ISFSI, Watts Bar, Units 1 and 2, ISFSI - Service List Update for Documents Containing Official Use Only and Safeguards Information | |
| 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 40 | 28 April 2022 | 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 40 | Fitness for Duty Offsite Dose Calculation Manual Safe Shutdown Earthquake Coatings Nondestructive Examination Cyber Security B.5.b Process Control Program Subsequent License Renewal Fire Protection Program Grace period |
| CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 | 14 July 2011 | G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 | Fukushima Dai-Ichi Significance Determination Process Earthquake Backfit |
| DCL-14-067, Revision to Regulatory Commitment- Generator Circuit Breakers License Amendment Request Submittal Date | 28 July 2014 | Revision to Regulatory Commitment- Generator Circuit Breakers License Amendment Request Submittal Date | |
| IR 05000219/2012012 | 1 May 2014 | Nuclear Regulatory Commission Office of Investigations Investigation Summary of OI Report No. 3-2010-034 for Exelon Generation, LLC | |
| IR 05000219/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
| IR 05000237/2012012 | 1 May 2014 | Nuclear Regulatory Commission Office of Investigations Investigation Summary of OI Report No. 3-2010-034 for Exelon Generation, LLC | |
| IR 05000237/2013202 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
| IR 05000254/2012012 | 1 May 2014 | Nuclear Regulatory Commission Office of Investigations Investigation Summary of OI Report No. 3-2010-034 for Exelon Generation, LLC | |
| IR 05000254/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
| IR 05000272/2002001 | 1 March 2002 | 2002 Annual Assessment Letter - Salem Nuclear Station - Units 1 & 2 (Report Nos. 50-272/02-001, 50-311/02-001) | |
| IR 05000272/2002002 | 23 April 2002 | IR 05000272/2002-002, IR 05000311/2002-002; PSEG Nuclear LLC; Salem Nuclear Generating Station, Units 1 & 2, Inspection on 02/25-03/2001 and 03/11-25/2002; Engineering Team Inspection Report. No Violations Noted | |
| IR 05000272/2002003 | 19 April 2002 | IR 05000272/2002-003 & IR 05000311/2002-003, Salem Units 1 and 2, Inspection on 02/10 - 03/30/2002, Related to Reactor Safety. No Violations Noted | Safe Shutdown Shutdown Margin Fire Barrier Temporary Modification Significance Determination Process Fire Protection Program |
| IR 05000272/2002005 | 2 April 2002 | IR 05000272/2002-005, IR 05000311/2002-005, IR 05000354/2002-003, on 03/19-21/2002; PSEG Nuclear LLC, Salem Hope Creek Generating Stations. Emergency Preparedness Exercise | |
| IR 05000272/2002006 | 2 August 2002 | IR 05000272-02-006, IR 05000311-02-006, on 05/12 - 06/29/02, Public Service Electric Gas Nuclear LLC, Salem Units1 and 2, Maintenance Rule Implementation, Identification and Resolution of Problems and Performance Indicator Verification | Safe Shutdown Fitness for Duty Mission time Fire Barrier Stroke time Contraband Probabilistic Risk Assessment Temporary Modification Condition Adverse to Quality Significance Determination Process Operability Determination Fire Protection Program |
| IR 05000272/2002007 | 13 November 2002 | IR 05000272-02-007, 05000311-02-007, Public Service Electric Gas Nuclear LLC, Salem Units 1 & 2, on 6/30 - 9/30/02, Fire Protection, Emergent Work, Operability Determinations and Surveillance Testing | Safe Shutdown High Radiation Area Fire Barrier Locked High Radiation Area Condition Adverse to Quality Significance Determination Process Operability Determination Biofouling Fire Protection Program Operability Assessment |
| IR 05000272/2002008 | 4 November 2002 | IR 05000272-02-008, on 9/30-10/04/02, Salem Units 1&2; Supplemental Inspection. Inspection Procedure 95001, Inspection for One or Two White Inputs in a Strategic Performance Area | Probabilistic Risk Assessment Power change |
| IR 05000272/2002009 | 6 February 2003 | IR 05000272-02-009, 05000311-02-009, Public Service Electric Gas Nuclear LLC, Salem Unit 1 and Unit 2 on 10/1 - 12/28/02, Heat Sink Performance, Fire Protection, Emergent Work, Refueling and Outage, and Temporary Modifications | Boric Acid High Radiation Area Non-Destructive Examination Offsite Dose Calculation Manual Fire Barrier Stroke time Fire impairment Nondestructive Examination Temporary Modification VT-2 Locked High Radiation Area Aging Management Significance Determination Process Operability Determination Fire Protection Program Fire Watch Operability Assessment |
| IR 05000272/2002010 | 31 March 2003 | IR 05000272-02-010, IR 05000311-02-010, Salem Generating Station - Preliminary White Finding | Significance Determination Process Preliminary White Finding |
| IR 05000272/2002011 | 6 January 2003 | IR 05000272-02-011, 05000311-02-011, 05000354-02-008; on 11/18/02-11/21/02, Salem/Hope Creek Generating Stations. Temporary Instruction 2515/148, Inspection of Nuclear Reactor .Safeguards Interim Cpmpensatory Measures. | |
| IR 05000272/2003002 | 27 March 2003 | IR 05000272-03-002 and IR 05000311-03-002, on 02/10-14 and 24-28/03, Salem Unit 1 and Unit 2, Fire Protection | |
| IR 05000272/2003003 | 13 May 2003 | IR 05000272-03-003, IR 05000311-03-003, on 12/30/02 - 3/29/03, for Public Service Electric Gas Nuclear LLC, Salem Units 1 and 2, Adverse Weather Protection, Equipment Alignment, Non-routine Plant Evolutions, Post Maintenance Testing | Boric Acid High Radiation Area Fire Barrier Past operability Temporary Modification Locked High Radiation Area Significance Determination Process Operability Determination Fuel cladding Fire Protection Program Downpower |
| IR 05000272/2003004 | 12 May 2003 | IR 05000272-03-004 & 05000311-03-004; 3/10 - 3/14 and 3/24 - 3/28/03; Salem Units 1 and 2; Biennial Baseline Inspection of the Identification and Resolution of Problems; Problem Identification and Resolution | Probabilistic Risk Assessment Temporary Modification Condition Adverse to Quality Significance Determination Process Operability Determination Biofouling |
| IR 05000272/2003005 | 12 August 2003 | IR 05000272-03-005, IR 05000311-03-005, on 03/30/03 - 06/28/03; Public Service Electric Gas Nuclear LLC, Salem Units 1 & 2; Maintenance Implementation, Personnel Performance During Non-routine Plant Evolutions, Post Maintenance Testing, Sur | Safe Shutdown Packing leak Fire Barrier Stroke time Past operability Operator Manual Action Temporary Modification Significance Determination Process Operability Determination Fire Protection Program Operability Assessment |
| IR 05000272/2003006 | 15 October 2003 | IR 05000272-03-006; 05000311-03-006; 06/02/2003 - 08/06/2003; Salem Nuclear Power Station, Unit 1 and Unit 2; Special Inspection of Leak in Unit 1 Spent Fuel Storage Pool | Boric Acid Offsite Dose Calculation Manual Condition Adverse to Quality Significance Determination Process Through Wall Leak Through-Wall Leakage |
| IR 05000272/2003007 | 10 November 2003 | IR 05000272-03-007 & 05000311-03-007, on 06/29/2003 - 09/27/2003; Public Service Electric Gas Nuclear LLC, Salem Unit 1 and Unit 2; Maintenance Effectiveness | Safe Shutdown Boric Acid High winds High Radiation Area Fire Barrier Stroke time Contraband Internal Flooding Probabilistic Risk Assessment Temporary Modification Locked High Radiation Area Significance Determination Process Operability Determination Biofouling Operability Assessment |
| IR 05000272/2003008 | 30 January 2004 | IR 05000272-03-008, 05000311-03-008; 08/18/2003 - 11/07/2003: Salem Generating Station, Units 1 and 2; Special Inspection; Problem Identification and Resolution | Safe Shutdown Probabilistic Risk Assessment Condition Adverse to Quality Significance Determination Process Large early release frequency Operability Determination |
| IR 05000272/2003009 | 12 February 2004 | IR 05000272-03-009 and 05000311-03-009, on 09/28/2003 Through 12/31/2003, for Salem Nuclear Generating Units 1 and 2; Inservice Inspection (ISI) Activities, Maintenance Effectiveness, Maintenance Risk Assessments & Emergent Work Control | Safe Shutdown Boric Acid High Radiation Area Fire Barrier Water Inventory Control Internal Flooding Probabilistic Risk Assessment Temporary Modification Locked High Radiation Area Condition Adverse to Quality Significance Determination Process Foreign Material Exclusion Process Control Program Large early release frequency Operability Determination Maintenance Rule Program Biofouling Pressure Boundary Leakage Scaffolding Power change Downpower Operability Assessment Siren |
| IR 05000272/2003010 | 30 January 2004 | IR 05000272-03-010, IR 05000311-03-010; on 10/20/03 - 10/24/03; for Salem Generating Station, Units 1 and 2; Supplemental Inspection | Non-Destructive Examination |
| IR 05000272/2004002 | 13 May 2004 | IR 05000272-04-002, IR 05000311-04-002, on 01/01/2004 - 03/31/2004, Public Service Electric Gas Nuclear LLC, Salem Units 1 and 2; Maintenance Implementation, Post Maintenance Testing, and Event Followup | High Radiation Area Stroke time Hydrostatic Temporary Modification Locked High Radiation Area Significance Determination Process Large early release frequency Operability Determination Maintenance Rule Program Biofouling Downpower Operability Assessment |
| IR 05000272/2004003 | 11 August 2004 | IR 05000272-04-003, IR 05000311-04-003, on 04/01/2004 - 06/30/2004; Public Service Electric Gas Nuclear LLC, Salem Units 1 and 2; Heat Sink Performance, Maintenance Rule, Post Maintenance Testing, Surveillance Testing, Pi&R, and Event Follo | Boric Acid Packing leak High Radiation Area Fire Barrier Water Inventory Control Internal Flooding Probabilistic Risk Assessment Temporary Modification Locked High Radiation Area Aging Management Significance Determination Process Foreign Material Exclusion Large early release frequency Operability Determination Maintenance Rule Program Fuel cladding Pressure Boundary Leakage Downpower Operability Assessment |
| IR 05000272/2004006 | 23 April 2004 | IR 05000272-04-006 and IR 05000311-04-006, on 02/23/04 - 03/12/04, Salem Nuclear Generating Station, Units 1 and 2; Safety System Design and Performance Capability | |
| IR 05000272/2004007 | 8 July 2004 | IR 05000272-04-007, IR 05000311-04-007 and IR 05000354-04-007, on 2/9/04 - 6/24/04; Salem / Hope Creek Generating Stations; IP 71111.11B Licensed Operator Requalification Program Inspection | Significance Determination Process |
| IR 05000272/2004008 | 7 April 2004 | IR 05000272-04-008, IR 05000311-04-008, IR 05000354-04-006, on 03/16/2004 - 03/18/2004 for Salem and Hope Creek Generating Stations; Emergency Preparedness Exercise Report | |
| IR 05000272/2004009 | 21 May 2004 | IR 05000272-04-009, 05000311-04-009, and 05000354-04-008, on 04/05-04/09/2004; Salem/Hope Creek Nuclear Generating Stations | |
| IR 05000272/2005005 | 31 January 2006 | IR 05000272-05-005, 05000311-05-005; 10/01/2005 - 12/31/2005; Salem Nuclear Generating Station Units 1 and 2; Equipment Alignment, Maintenance Effectiveness, Maintenance Risk Assessments and Emergency Work Control, Refueling and Other Outag | Boric Acid High winds Packing leak High Radiation Area Stroke time Time to boil Internal Flooding Past operability Probabilistic Risk Assessment Nondestructive Examination Temporary Modification VT-2 Significance Determination Process Foreign Material Exclusion Process Control Program Large early release frequency Operability Determination Safeguards Contingency Plan Code Reconciliation Liquid penetrant Dissimilar Metal Weld Substantial potential for overexposure Substantial potential for an overexposure Unidentified leakage Overexposure |
| IR 05000272/2005007 | 2 May 2005 | IR 05000272-05-007, IR 05000311-05-007, IR 05000354-05-006, on 02/28/2005 - 03/18/2005, Salem Units 1 and 2 and Hope Creek; Biennial Baseline Inspection of the Identification and Resolution of Problems; Problem Identification and Resolution | Boric Acid Probabilistic Risk Assessment Temporary Modification Condition Adverse to Quality Significance Determination Process Design basis earthquake Foreign Material Exclusion Process Control Program Large early release frequency Operability Determination Fire Protection Program Operability Assessment |
| IR 05000272/2005012 | 26 January 2006 | IR 05000354-05-007, 05000272-05-012, 05000311-05-012; 11/28/2005 - 12/16/2005; Hope Creek Nuclear Generating Station; Salem Nuclear Generating Station; Biennial Baseline Inspection of the Identification and Resolution of Problems | Stroke time Temporary Modification Condition Adverse to Quality Significance Determination Process Operability Determination |