On 3/8/15, at 1158, the 14 Containment Fan Cooler Unit ( CFCU) was declared inoperable following a trip of its low speed breaker on thermal overload protection during a scheduled surveillance test. Unit 1 entered Technical Specification (TS) 3.6.2.3, Action "a." for inoperability of one CFCU. Troubleshooting was unable to identify and correct the cause of the low speed breaker trip within the 7 day TS allowed outage time.
Unit 1 entered Mode 3 (Hot Standby) at 1652 on 3/15/15, and Mode 5 (Cold Shutdown) at 1419 on 3/16/15.
The TS required shutdown of Salem Unit 1 was due to the 14 CFCU low speed breaker tripping on startup.
Troubleshooting identified failed motor {BK/MO} stator support welds which allowed contact between the rotor and the stator on startup. The 14 CFCU motor was replaced.
This report is made in accordance with 10 CFR 50. 73 (a)(2)(i)(A), "The completion of any nuclear plant shutdown required by the plant's Technical Specifications ... " NRG FORM366 (01-2014) |
0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Offce 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. FACILITYNAME
PLANT AND SYSTEM IDENTIFICATION
Westinghouse - Pressurized Water Reactor {PWR/4} Containment Fan Cooler Unit {BK} Containment Fan Cooler Unit Motor {BK/MO} Energy Industry Identification System (EllS) codes and component function identifier codes appear as {SS/CCC}.
IDENTIFICATION OF OCCURRENCE
Event Date: 3/15/15 Discovery Date: 3/15/15
CONDITIONS PRIOR TO OCCURRENCE
Salem Unit 1 was in operational Mode 1, operating at approximately 100 percent power. No additional structures, systems or components were inoperable at the time of discovery that contributed to this event.
DESCRIPTION OF OCCURRENCE
On 3/8/15, at 1158, the 14 Containment Fan Cooler Unit (CFCU) {BK} was declared inoperable following entered Technical Specification (TS) 3.6.2.3, Action "a." for inoperability of one CFCU. TS 3.6.2.3, Action 'a.' states that with one of the required CFCU fans inoperable, the fan must be restored to operable status within 7 days or the plant must be placed in at least Hot Standby (Mode 3) within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown (Mode 5) within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Troubleshooting of the 14 CFCU was unable to identify and correct the cause of the low speed breaker trip within the 7 day allowed outage time period. The TS allowed outage time expired on 3/15/15 at 1158 and unit shutdown was initiated at 1227. At 1329, a four hour notification was made to the NRC pursuant to the requirements of 10 CFR 50. 72(b )(2)(i) for "The initiation of any nuclear plant shutdown required by the plant's Technical Specifications." Unit 1 entered Mode 3 at 1652 on 3/15/15 and Mode 5 at 1419 on 3/16/15.
This event is reported in accordance with 10 CFR 50.73 (a)(2)(i)(A), "The completion of any nuclear plant shutdown required by the plant's Technical Specifications ... "
CAUSE OF EVENT
The TS required shutdown of Salem Unit 1 was due to the 14 CFCU low speed breeker tripping on startup. Troubleshooting and vendor analysis determined that the cause of the 14 CFCU motor {BK/MO} failure to start and run in slow speed was due to failed motor stator support welds which allowed contact between the rotor and the stator upon low speed startup.
SAFETY CONSEQUENCES AND IMPLICATIONS
This event did not result in any offsite release of radioactivity or increase of offsite dose rates, and there were no personnel injuries or damage to any other safety-related equipment.
Salem's CFCUs are credited in conjunction with the Containment Spray (CS) system to (1) provide heat removal from containment (limit containment peak pressure and temperature), and (2) minimize doses by maintaining containment atmosphere iodine in solution. The Salem design consists of five CFCUs and two CS trains per unit. Salem's design basis requires at least three CFCUs and one CS train for post-accident mitigation. As such, the inoperability of a single CFCU does not result in a loss of safety function.
SAFETY SYSTEM FUNCTIONAL FAILURE
A review of this event determined that a Safety System Functional Failure (SSFF) as defined in Nuclear Energy Institute (NEI) 99-02, Regulatory Assessment Performance Indicator Guideline, did not occur. This event did not prevent the ability of a system to fulfill its safety function to either shutdown the reactor, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident.
PREVIOUS OCCURRENCES
A review of Salem Unit 1 and 2 Licensee Event Reports for the previous three years identified no other similar events.
CORRECTIVE ACTIONS
1. The 14 CFCU motor was replaced.
2. Rotor to stator air gap measurements were verified to be within acceptable limits on all 5 CFCUs.
3. Preventative Maintenance plans for CFCUs will be changed to include rotor to stator air gap inspections.
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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