01-29-2016 | On October 28, 2015, Salem Unit 1 was in Mode 1 operating at 100 percent power and Unit 2 was in Mode 6 with fuel movement in progress. The Salem Unit 1 Control Room Emergency Air Conditioning System (CREACS) train was in single train filtration mode supplying air to the common Control Room due to outage activities on Unit 2.
At 0628, the Salem Unit 1 CREACS train was declared inoperable due to failure of its charcoal filter surveillance test, resulting in both units CREACS trains being inoperable. Unit 1 entered Technical Specification (TS) 3.0.3, and Unit 2 suspended fuel movement to comply with TS 3.7.6, Action c.
At 0950, the Unit 2 CREACS train was returned to service and aligned to single train filtration mode supplying air to the common Control Room. Unit 1 exited TS 3.0.3, meeting the requirement of TS 3.7.6.1, Action a., to restore a single train of CREACS to operable.
This event was caused by less than adequate procedure guidance and ownership of the surveillance activity by the maintenance shop responsible for performing the work. The direct cause of the TS entry was the filter failure due to aging.
This event is reportable under 10 CFR 50.73(a)(2)(i)(B), as a condition prohibited by the plant's TS, and 10 CFR 50.73(a)(2Xv)(D), as a condition that could have prevented the fulfillment of a safety function. |
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Category:Letter
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[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000272/LER-2024-001, Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger2024-05-0909 May 2024 Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger 05000311/LER-1922-001, Invalid Safety Injection and Valid Reactor Trip Due to Inaccurate Steam Generator Pressure Indications2023-02-21021 February 2023 Invalid Safety Injection and Valid Reactor Trip Due to Inaccurate Steam Generator Pressure Indications 05000272/LER-2017-0012018-01-0808 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 05000311/LER-2016-0022017-09-0707 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-2015-0022017-09-0707 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 05000311/LER-2017-0012017-06-13013 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 05000272/LER-2015-0022016-11-16016 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 05000311/LER-2016-0062016-10-31031 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 05000311/LER-2016-0052016-08-29029 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 05000272/LER-2016-0012016-07-0505 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 05000311/LER-2016-0032016-04-14014 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-2016-0012016-03-21021 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 05000272/LER-2015-0072016-01-29029 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 05000311/LER-2015-0032016-01-22022 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 LR-N14-0128, Special Report 311/14-04-00, Pursuant to the Requirements of Technical Specification (TS) 3.4.10.3, Action D, for Overpressure Protection System Used to Mitigate an RCS Pressure Transient2014-05-13013 May 2014 Special Report 311/14-04-00, Pursuant to the Requirements of Technical Specification (TS) 3.4.10.3, Action D, for Overpressure Protection System Used to Mitigate an RCS Pressure Transient ML1015505772010-04-0808 April 2010 Event Notification for Salem on Storm Drain System Tested Positive for Tritium ML1034404492010-04-0505 April 2010 Document: Apparent Cause Evaluation Template Document: from Robert Montgomery LR-N05-0419, LER 05-04-00 for Salem Generating Station, Unit 2 Regarding Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves2005-08-15015 August 2005 LER 05-04-00 for Salem Generating Station, Unit 2 Regarding Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves ML0435704542004-12-13013 December 2004 Special Report 311/04-010 for Salem Unit 2 Regarding the 2R45 Detector Being Inoperable on 12/01/2004 ML19030A6261980-03-0303 March 1980 Licensee Event Report Inoperability of Air Particulate Detector Pump ML19031B0801978-09-18018 September 1978 Submit Licensee Event Report for Reportable Occurrence 78-56/03L ML19031B5101978-08-24024 August 1978 LER 1978 for Reportable Occurrence 78-43/03L on Quadrant Power Tilt Ratio Greater than 1.02 ML19031B0381978-08-24024 August 1978 LER 1978-042-03 for Salem Unit 1 Excessive Trip Setpoint During Functional Test on No. 13 S/G Steam Flow Channel 1 ML19031B5091978-08-24024 August 1978 LER 1978 for Reportable Occurrence 78-45/03L on 100 Ft. Elevation Personnel Airlock Inoperable ML19031B0361978-08-24024 August 1978 LER 1978-044-03 for Salem Unit 1 Inoperability of No. 11 S/G Feedwater Flow Channel 2 ML19031A8951978-08-14014 August 1978 LER 1978-041-03 for Salem Unit 1 Excessive Quadrant Power Tilt Ratio During Power Escalation ML19031B0391978-08-0303 August 1978 LER 1978-040-03 for Salem Unit 1 Inoperability of Makeup Valve from Demineralized Water Plant ML19031B5121978-08-0202 August 1978 Licensee Event Report 1978 for Reportable Occurrence 78-39/03L Re No. 13 Containment Fan Foil Unit Inoperable ML19031B5111978-08-0202 August 1978 Licensee Event Report 1978 for Reportable Occurrence 78-38/03L Re No. 11 Steam Generator Flow Channel II Inoperable ML19031B1651978-07-20020 July 1978 LER 1978-035-03 for Salem Unit 1 Loss of Power to No. 2 Station Power Transformer ML19031B5131978-07-20020 July 1978 Licensee Event Report 1978 for Reportable Occurrence 78-36/03L Re Vital Bus Under Voltage Relay Setting Outside Technical Specification Limit ML19031C0301978-07-20020 July 1978 07/20/1978 Letter Reportable Occurrence on Non-Radwaste Sampling for Suspended Solids ML19031B1671978-07-12012 July 1978 LER 1978-026-03 for Salem Unit 1 Failure of Motor Operated Valve ML19031C0311978-07-12012 July 1978 07/12/1978 Letter Reportable Occurrence on Missed Surveillance of Monthly Functional Test of Steam Generator Blowdown Radiation Monitoring Channels ML19031B0401978-07-12012 July 1978 LER 1978-033-03 for Salem Unit 1 No. 11 Steam Generator Steam Flow Channel II ML19031B5151978-07-10010 July 1978 Licensee Event Report 1978 for Reportable Occurrence 78-30/03L Re Control Bank and Shutdown Rod Misalignment ML19031B0411978-06-30030 June 1978 LER 1978-027-03 for Salem Unit 1 Malfunctioning Exterior Door of Containment Entry Air Lock ML19031B5171978-06-30030 June 1978 No. 1 - Licensee Event Report 1978 for Reportable Occurrence 78-28/03L Re Inoperable 100 Ft. Elevation Air Lock Interior Door ML19031C0321978-06-28028 June 1978 06/28/1978 Letter Reportable Occurrence on Non-Radwaste Sampling for Suspended Solids Analysis ML19031A8191978-06-21021 June 1978 LER 1978-029-01 for Salem Unit 1 Inoperability of Two Power Range Channels During Training Startups ML19031B5191978-05-15015 May 1978 LER 1978-025-03 for Salem Generating Station Unit 1 Re Missed Tech. Specification Surveillance: 4.8.2.4.1 DC and 4.8.2.2 AC Breaker Alignment and Power Availability ML19031B5201978-05-10010 May 1978 LER Supplemental Report for Reportable Occurrence 77-43/03L Re Inoperable No 12 S/G Channel 3 Due to Failed Pressure Transmitter ML19031B5211978-04-27027 April 1978 04/27/1978 Letter Reportable Occurrence on Excessive Concentration of Iodine in Milk Sample Collected at Environmental Sampling Location ML19031B0421978-04-17017 April 1978 LER 1978-021-03 for Salem Unit 1 Missed Surveillance of Fluoride Sample ML19031A8961978-04-17017 April 1978 LER 1978-022-01 for Salem Unit 1 Seismic Test Results for NEMA 12 Enclosures ML19031B5221978-04-11011 April 1978 LER 1978-080-03 for Salem Unit 1 Inoperability of 1B Diesel ML19031C0331978-04-0606 April 1978 04/06/1978 Letter Reportable Occurrence on Non-Radwaste Sampling for Suspended Solids Analysis ML19031B5231978-04-0606 April 1978 LER 1977-042-03 for Salem Unit 1 Inoperability of Channel III Pressurizer Level ML19031A8971978-04-0606 April 1978 LER 1978-018-03 for Salem Unit 1 Excessive Trip Setpoint During Functional Test on PWR Range Channel N43 ML19031A8981978-04-0505 April 1978 LER 1978-017-03 for Salem Unit 1 Tilt Ratio During Power Escalation 2024-05-09
[Table view] |
0001, or by Internet e-mail to infocdlects.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 currently valid OMB control number,1 he NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
2015 - NUMBER 007 - 001
PLANT AND SYSTEM IDENTIFICATION
Westinghouse - Pressurized Water Reactor {PWR/4} Control Room Air Conditioning System {NA/FLT} Energy Industry Identification System (EllS) codes and component function identifier codes appear as {SS/CCC}.
IDENTIFICATION OF OCCURRENCE
Event Date: October 7, 2015 Discovery Date: October 22, 2015
CONDMONS PRIOR TO OCCURRENCE
Salem Unit 1 was in operational Mode 1, operating at approximately 100 percent power. Salem Unit 2 was in Mode 6 with fuel movement in progress. The Salem Unit 1 Control Room Emergency Air Conditioning System (CREACS) {NA/FLT} train was in single train filtration mode supplying air to the common Control Room due to outage activities on the Unit 2. No additional structures, systems or components were inoperable at the time of discovery that contributed to this event.
DESCRIPTION OF OCCURRENCE
On October 7, 2015, a carbon sample was obtained from the unit 1 CREACS charcoal filtration unit for analysis in accordance with the requirements of TS Surveillance 4.7.6.1.b.3.
On October 28, 2015, at 0628, Salem operations was notified of failure of the Unit 1 charcoal filter TS surveillance test. Test results indicated a methyl iodide penetration of 3.054 percent with a TS acceptance criteria of less than 2.5 percent. The Unit 1 CREACS train was declared inoperable due to failure of its charcoal filter surveillance test, resulting in both units CREACS trains being inoperable. Unit 1 entered TS 3.0.3 because of no TS 3.7.6 Action Statement addressing the loss of both CREACS trains. Fuel movement on Unit 2 was suspended to comply with Unit 2's TS 3.7.6, Action c.
Subsequent review indicated that PSEG had received the results of the methyl iodide penetration analysis from the vendor testing laboratory on October 22, 2015, at 1843. PSEG documented the failure to take timely mitigating actions in the corrective action program.
On October 28, 2015 at 0950, the Unit 2 CREACS train was returned to service and aligned to single train filtration mode supplying air to the common Control Room. With single train filtration operation restored, Unit 1 exited TS 3.0.3, and entered TS 3.7.6.1, Action a., which requires alignment of the system to single train filtration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and restoration of the inoperable filtration train to operable status within 30 days.
The Unit 1 CREACS charcoal filter carbon was replaced, tested, and the CREACS train was returned to service on October 30, 2015 at 1442.
0001, or by Internet e-mail 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.ff a means used to impose an Information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is nor required to respond to, the information collection.
2. DOCKET 6. LER NUMBER 1. FACILITY NAME Salem Generating Station — Unit 1 05000272 a PAGE
MJMBER
MJMBER
The Event Date for this LER is considered to be October 7, 2015, when the charcoal filter sample was taken.
The Discovery Date is considered to be October 22, 2015, when PSEG was notified by the vendor of the sample results. This event is reported as a condition prohibited by TS since at the time of discovery, the filter had exceeded its TS 3.7.6.1, Action a., Allowed Outage Time (AOT) to align CREACS for single train filtration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This event is also reported as a condition that could have prevented the fulfillment of a safety function because both units CREACS trains were inoperable from the time of discovery until the Unit 2 CREACS train was returned to service and aligned to single train filtration mode supplying air to the common Control Room.
An eight-hour NRC Event Notification (EN) was required on or before 0243 on October 23, 2015, as required by 10 CFR 50.72(b)(3)(v)(D) for an event or condition that at the time of discovery could have prevented the fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident. However, the EN was not made until Operations was notified of the surveillance failure. EN 51504 was completed on October 28, 2015, at 1326. This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(D).
CAUSE OF EVENT
This event was caused by less than adequate procedure guidance and ownership of the surveillance activity by the maintenance shop responsible for performing the work. The direct cause of the TS entry was the filter failure due to aging.
SAFETY CONSEQUENCES AND IMPLICATIONS
The Salem Unit 1 and 2 CREACS is a shared system between Unit 1 and 2 supplying a common Control Room Environment (CRE). The CREACS consists of two independent, redundant trains, one from each unit, that recirculate and filter air in the CRE and a CRE boundary that limits the in-leakage of unfiltered air. Each CREACS train consists of a pre- filter, a high efficiency particulate air (HEPA) filter, an activated charcoal absorber section for removal of gaseous activity, and fans. Following receipt of a Safety Injection or High Radiation actuation signal, one 100 percent capacity fan in each units CREACS will operate in accident pressurized mode with outside air supplied from the non-accident unit air intake duct for continued CRE pressurization.
A single CREACS filtration train is capable of providing adequate removal of post-accident airborne contaminants to ensure radiation exposures in the CRE are limited to 5 REM Total Effective Dose Equivalent (TEDE) or less. The Salem Updated Final Safety Analysis Report (UFSAR) assumes the charcoal filter has a removal efficiency of 95 percent. Vendor performance of multiple analyses of the filter's charcoal methyl iodide penetration indicated that the worst case sample result indicated a greater than 95 percent efficiency. Therefore, the level of degradation of the charcoal filter would not have prevented the filler unit from performing its design safety function.
SAFETY SYSTEM FUNCTIONAL FAILURE
A review of this event determined that a Safety System Functional Failure (SSFF) as defined in Nudear Energy Institute (NEI) 99-02, Regulatory Assessment Performance Indicator Guideline, did not occur.
0001, or byinternet e-mail to Infocdiects.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 im pose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
2. DOCKET I
NARRATNE
PREVIOUS OCCURRENCES
A review of Salem Unit 1 and 2 Licensee Event Reports forthe previous three years identified no other similar events.
CORRECTIVE ACTIONS
1) The Unit 1 CREACS charcoal filter was replaced, tested, and the CREACS train was returned to service on October 30, 2015.
2) The surveillance procedure will be revised to include an administrative limit for charcoal filter replacement below the TS requirement of less than 2.5% methyl iodine penetration.
3) Other corrective actions are being tracked in the Licensee's Corrective Action Program.
COMMITMENTS
This LER contains no regulatory commitments.
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05000311/LER-2015-001 | P.O. Box 236, Hancocks Bridge, NJ 08038-0236 PSEG MAR 1 0 2015 LR-N15-0040 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LER 311/2015-001-00 Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 SUBJECT: Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable The Licensee Event Report, "Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable" is being submitted pursuant to 10 CFR 50.73 (a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications..." The attached LER contains no commitments. Should you have any questions or comments regarding the submittal, please contact David Lafleur of Salem Regulatory Assurance at 856-339-1754. Sincerely, John F. Perry Site Vice President — Salem Attachments (1) MAR 1 9 2015 10 CFR 50.73 Page 2 LR-N15-0040 CC Mr. D. Dorman, Administrator — Region 1, NRC Ms. C. Sanders, Licensing Project Manager — 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) *Send LICENSEE EVENT REPORT (LER) (See Page 2 for 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. 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-mail 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 currently valid 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 3 4. -nTLE Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable | | 05000272/LER-2015-001 | Fuel Movement in Progress With Fuel Handling Building Ventilation Inoperable | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-2015-002 | 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 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-2015-002 | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000272/LER-2015-003 | Plant Shutdown Required by Technical Specifications | | 05000311/LER-2015-003 | 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 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000272/LER-2015-004 | Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable | | 05000272/LER-2015-005 | Low Containment Spray Additive Tank Sodium Hydroxide Concentration | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000272/LER-2015-006 | Pressurizer Power Operated Relief Valves and Block Valves Do Not Meet the Requirements of 10 CFR 50 Appendix R. | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000272/LER-2015-007 | 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 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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