06-19-2015 | Salem Unit 1 exceeded its Technical Specification (TS) allowed outage time for one channel of Overtemperature Delta-T ( OT Delta-T) due to inadequate post-maintenance testing following replacement of a Power Range Nuclear Instrument (PR NI) upper detector cun-ent meter.
Corrective actions include an extent of condition review of other PR NI system post-maintenance testing and review of the post- maintenance testing procedure to identify deficiencies.
This report is made in accordance with 10 CFR 50.73 (a)(2)(iXB), "Any operation or condition which was prohibited by the plant's Technical Specifications... |
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0001, or by Internet e-mail to Infocollects.Resourceranrc.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.
2. DOCKET 6. LERNUMBER 1. FACILITY NAME a PAGE
PLANT AND SYSTEM IDENTIFICATION
Westinghouse - Pressurized Water Reactor {PWR/4} Protection System, Meter {JC/MTR} Energy Industry Identification System (EllS) codes and component function identifier codes appear as {SS/CCC}.
IDENTIFICATION OF OCCURRENCE
Event Date: April 21, 2015 Discovery Date: April 22, 2015
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 that contributed to this event.
DESCRIPTION OF OCCURRENCE
On April 21, 2015, at 1001, Salem Instrument and Controls (I&C) replaced the upper detector current meter on PR NI Channel 1N44 {JC/MTR}. The post-maintenance test and operations retest was completed at 1500 and the channel was declared operable.
On April 22, 2015 at 1337, operations personnel identified that the Axial Flux Recorder indication had made a step change from -1.8 percent to -3.0 percent indication but remained within acceptance limits, following replacement of the PR NI 1N44 upper detector current meter on April 21, 2015.
On April 23, 2015 at 0108, operations entered TS 3.3.1.1, Actions 2 and 6 for current adjustment of the 1N44 PR NI. l&C noted the as-found voltage at the input to the isolator that feeds the AFD recorder, the OT Delta-T channel, and the Delta Flux indicator was below the expected value. This would have caused the output of the isolator to be out of its acceptable range. The PR NI 1N44 channel detector adjustment was completed satisfactorily and the channel was declared operable at 0435.
Subsequent engineering analysis determined that the overall effect of the as-found voltage offset indicated that Channel 4 OT Delta-T had been inoperable since replacement of the upper detector current meter on April 21, 2015.
Channel 4 of OT Delta-T was determined to have been inoperable for approximately 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br />, exceeding its TS 3.3.1.1, Action 2 and 6 allowed outage time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to place the channel in a tripped condition. A review determined there were no other NI PR channels taken out of service during the time of this event.
This report is made in accordance with 10 CFR 50.73 (a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications...
CAUSE OF EVENT
The cause of Channel 4 OT Delta-T inoperability was due to replacement of the PR NI Channel 1N44 upper detector current meter. The post-maintenance test and operations retesting done was not adequate to ensure the systems associated with PR NI Channel 1N44 were restored to operability. The inadequate post-maintenance and retesting activities were the result of a work planner knowledge deficiency.
SAFETY CONSEQUENCES AND IMPLICATIONS
The safety significance of this event is minimal. 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. Existing plant conditions during this event did not challenge the OT Delta-T trip setpoint and the remaining three channels of OT Delta-T remained operable and capable of generating an OT Delta-T trip signal for all appropriate plant conditions.
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 LERs for the previous three years identified one similar event:
Delta-T Inoperable, dated March 19, 2015, describes a Salem Unit 2 event in which inoperability of Channel 4 of OT Delta-T was caused by a failed voltage isolator from PR NI Channel 2N44.
CORRECTIVE ACTIONS
1. An extent of condition review was performed on both Salem unit 1 and 2 to determine if other PR NI system post-maintenance testing would be similarly compromised. One corrective maintenance activity was found on PR NI 1N42 and was corrected to include the additional guidance needed in the post-maintenance testing and retesting.
2. The post-maintenance testing procedure will be reviewed to identify possible deficiencies for post- maintenance test planning.
3. The Planning Curriculum Review Committee will determine if formal training on this event will be required.
4. Operations will create a crew learning plan to ensure operations understands all downstream NI modules which could be affected by PR NI maintenance activities to ensure that post-maintenance retesting activities clearly address the impact of the maintenance performed.
5. Results of the work group evaluation completed for this event was communicated to work planners.
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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