08-08-2016 | On June 15, 2016, at 05:15 Eastern Daylight Time, Unit 2 was in Mode 1 (i.e., Run mode) at 100 percent of rated thermal power. At that time, Operations personnel were preparing to run the Residual Heat Removal Service Water ( RHRSW) system in the spppression pool cooling mode. While performing the valve lineup, an alarm was received on low RHRSW suction pressure. Two instrument valves connected to the "B" and "D" RHRSW pump suctions were found closed. This resulted in the pump start logic being unable to sense RHRSW pump suction pressure, which prevented the pumps from being able to start. With the pumps unable to start, the associated RHRSW division was inoperable. It is most likely that the valves were mispositioned during a previous operation of the "B" RHRSW division. The event resulted from procedures which did not adequately control the position of the instrument valves. Corrective actions for this event included repositioning the valves to their correct configuration and revising applicable procedures. |
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Category:Letter
MONTHYEARIR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20243012023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 ML23212B2682023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 Integrated Inspection Report 05000324 2023001 and 05000325 2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000324/20224032022-11-10010 November 2022 Cyber Security Inspection Report 05000324/2022403 and 05000325/2022403 ML22307A1762022-11-0707 November 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) IR 05000324/20220032022-11-0707 November 2022 Integrated Inspection Report 05000324/2022003 and 05000325/2022003 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000324/20220052022-08-24024 August 2022 Updated Inspection Plan for Brunswick Steam Electric Plant (Report 05000324/2022005 and 05000325/2022005) ML22230D0692022-08-22022 August 2022 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident IR 05000324/20220022022-08-0505 August 2022 Integrated Inspection Report 05000324/2022002 and 05000325/2022002 IR 05000324/20220102022-06-27027 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000324 2022010 and 05000325 2022010 ML22028A1742022-05-12012 May 2022 Issuance of Amendment Nos. 309 and 337 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-580, Revision 1 IR 05000324/20220012022-05-10010 May 2022 Integrated Inspection Report 05000324/2022001 and 05000325/2022001 ML22119A1352022-05-0909 May 2022 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000325/2022403; 05000324/2022403 ML22082A2682022-05-0202 May 2022 Issuance of Amendment Nos. 308 and 336 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22102A0502022-04-11011 April 2022 301 Corporate Notification Letter IR 05000324/20224012022-03-16016 March 2022 Security Baseline Inspection Report 05000324/2022401 and 05000325/2022401 ML22054A2152022-03-0808 March 2022 Correction to Amendments to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications IR 05000324/20210062022-03-0202 March 2022 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 (Reports No. 05000324/2021006 and 05000325/2021006) IR 05000324/20210042022-02-14014 February 2022 Integrated Inspection Report 05000324/2021004 and 05000325/2021004 ML22035A1262022-02-0909 February 2022 Withdrawal of Exemption Request from the Requirements of 10 CFR Part 50, Appendix E, Section IV.F.2.d (EPID L-2021-LLE-0055 (COVID-19)) ML21354A5032022-01-24024 January 2022 Requested Exemption from 10 CFR 50, Appendix E, Section IV.F.2.D Not Required (EPID L-2021-LLE-0055 (COVID-19)) ML22018A1842022-01-18018 January 2022 Notification of Brunswick Steam Electric Plant, Units 1 & 2 - Design Bases Assurance Inspection - U.S. Nuclear Regulatory Inspection Report 05000324/2022010 and 05000325/2022010 ML21348A7192021-12-21021 December 2021 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times 2023-09-25
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000324/LER-2017-0032017-08-0303 August 2017 1 OF 4, LER 17-003-00 for Brunswick, Unit 2, Regarding Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable, 05000325/LER-2017-0032017-08-0202 August 2017 Control Room Air Conditioning and Emergency Ventilation Systems Rendered Inoperable, LER 17-003-00 for Brunswick, Unit 1, Regarding Control Room Air Conditioning and Emergency Ventilation Systems Rendered Inoperable 05000324/LER-2017-0022017-06-12012 June 2017 Plant Mode Change with Primary Containment Inoperable, LER 17-002-00 for Brunswick, Unit 1, Regarding Foreign Material in Switch Results in Unplanned Automatic Start of Emergency Diesel Generators 05000324/LER-2017-0012017-05-18018 May 2017 Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3, LER 17-001-00 for Brunswick, Unit 2, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 05000324/LER-2016-0012016-08-0808 August 2016 Mispositioned Valves Result in Residual Heat Removal Service Water System Inoperability, LER 16-001-00 for Brunswick Steam Electric Plant, Unit 2, Regarding Mispositioned Valves Result in Residual Heat Removal Service Water System lnoperability 05000325/LER-2016-0032016-05-0202 May 2016 Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3, LER 16-003-00 for Brunswick Steam Electric Plant, Unit 1 Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 05000324/LER-2016-0022016-05-0202 May 2016 High Pressure Coolant Injection System Inoperable due to Failed Relay Coil, LER 16-002-00 for Brunswick Steam Electric Plant (BSEP), Units 1 and 2, Regarding Emergency Diesel Generator 3 Inoperable Due to Failure to Auto-Start 05000325/LER-2016-0012016-04-0606 April 2016 Electriqal Bus Fault Results in Lockout of Startup Auxiliary Transformer and Loss of Offsite Power, LER 16-001-00 for Brunswick, Unit 1, Regarding Electrical Bus Fault Results in Lockout of Startup Auxiliary Transformer and Loss of Offsite Power BSEP 15-0088, Special Report, Technical Specification 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report2015-10-22022 October 2015 Special Report, Technical Specification 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report ML1019404522008-06-0303 June 2008 10CFR50.75g File: AR00237296 Overflowed CST ML1019404542008-05-13013 May 2008 10CFR50.75g File: AR00272173 Thru Wall Leak in Cw Intake Pipe Was Found to Contain Tritium in the Groundwater Leaking Into the Pipe ML1019404562008-04-28028 April 2008 10CFR50.75g File: AR00242461 Routine Environmental Soil/Water Sampling Has Identified Low Levels of Tritium . BSEP 03-0023, LER 2002-02-00 from Brunswick, Unit 2 Regarding Remote Shutdown Panel Power Supply Inventer Design Deficiency2003-02-14014 February 2003 LER 2002-02-00 from Brunswick, Unit 2 Regarding Remote Shutdown Panel Power Supply Inventer Design Deficiency 2017-08-03
[Table view] |
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 e-mail to 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.
Brunswick Steam Electric Plant (BSEP) 001 05000-324 2016 - 000 Energy Industry Identification System (EllS) codes are identified in the text as [XX].
Background
Initial Conditions On June 15, 2016, at 05:15 Eastern Daylight Time (EDT), Unit 2 was in Mode 1 (i.e., Run mode) at 100 percent of rated thermal power. No out-of-service equipment contributed to, or affected the course of, this event.
Reportability Criteria This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) because Unit 2 was operated in a condition prohibited by the Technical Specifications (TS). Specifically, one division of the Residual Heat Removal (RHR) [BO] Service Water (RHRSW) [BI] system was found to be inoperable. The duration of the inoperability was based on the last successful operation of the RHRSW system, or June 4, 2016, at 14:41 EDT. TS Limiting Condition for Operation (LCO) 3.7.1 Condition B says that with one RHRSW subsystem inoperable for reasons other than Condition A (i.e., one pump inoperable), the system must be restored within 7 days or be in Mode 3 (i.e. shut down) within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The plant was operated until June 15, 2016, at 05:45 EDT in this condition (i.e., 10 days, 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, 4 minutes).
Therefore, the plant was operated in a condition prohibited by the TS.
Event Description
On June 15, 2016, at 05:15 EDT, Unit 2 was in Mode 1 (i.e., Run mode) at 100 percent of rated thermal power. Operations personnel were preparing to start the RHRSW system in the suppression pool cooling mode. While opening Nuclear Service Water (NSW) system [BI] valves to supply RHRSW, operators received an annunciator for RHRSW pump suction pressure being low. Personnel then identified two RHRSW instrument valves which were closed and should have been open. The associated instrument lines feed pressure instruments for the suction of the "B" and "D" RHRSW pumps. With the valves closed, suction pressure from NSW could not be sensed, and the RHRSW pumps could not start. Both instrument valves were immediately opened. This restored the affected RHRSW subsystem to operable status at 05:45 EDT on June 15, 2016.
Event Causes It is most likely that the instrument valve mispositioning occurred during a previous operation of the "B" division of RHRSW on April 6, 2016. Investigators found no evidence of tampering. The RHRSW suction valves were opened on June 4, 2016, at 14:41 EDT, and the low pressure annunciator did not alarm. The absence of the low pressure alarm confirms the "B" and "D" RHRSW pumps could have started.
Therefore, the duration of inoperability is conservatively assumed to have begun on June 4, 2016, at 14:41 EDT.
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 e-mail to 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. I The apparent cause of this event is that procedures lacked sufficient control of the positions of the subject instrument valves. Procedures allowed operators to select which valves to manipulate under certain conditions, creating the possibility that valves might be left in the incorrect position during system restoration.
Safety Assessment The purpose of the RHRSW system is to provide a heat sink for the RHR system. It normally receives suction from the NSW system supply header and moves cooling water through the RHR heat exchangers.
The RHR heat exchangers receive flow from the RHR system. In the suppression pool cooling mode, RHR water is circulated from the suppression pool to the heat exchangers where RHRSW flow cools it.
In this event, one of two RHRSW subsystems was inoperable for a period greater than the allowable seven days. The unaffected division of RHRSW was always operable during this time. Consequently, the safety function of the RHRSW system was maintained.
Based on this analysis, this event had no adverse impact on the health and safety of the public.
Corrective Actions
Any changes to the corrective actions and schedules noted below will be made in accordance with the site's corrective action program.
- The affected instrument valves were placed in the correct position, and the RHRSW system was made operable. This action is complete.
- Procedures governing use of the affected instrument valves will be revised to specifically designate as-left positions, and valve positions will be independently verified. This action will be completed by September 16, 2016.
Previous Similar Events
A review of LERs and the site's corrective action program for the past three years did not identify any previous similar occurrences in which mispositioned components rendered a safety system inoperable.
Commitments This report contains no regulatory commitments.
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05000325/LER-2016-001 | Electriqal Bus Fault Results in Lockout of Startup Auxiliary Transformer and Loss of Offsite Power LER 16-001-00 for Brunswick, Unit 1, Regarding Electrical Bus Fault Results in Lockout of Startup Auxiliary Transformer and Loss of Offsite Power | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000324/LER-2016-001 | Mispositioned Valves Result in Residual Heat Removal Service Water System Inoperability LER 16-001-00 for Brunswick Steam Electric Plant, Unit 2, Regarding Mispositioned Valves Result in Residual Heat Removal Service Water System lnoperability | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000325/LER-2016-002 | Emergency Diesel Generator 3 Inoperable Due to Failure to Auto-Start | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000324/LER-2016-002 | High Pressure Coolant Injection System Inoperable due to Failed Relay Coil LER 16-002-00 for Brunswick Steam Electric Plant (BSEP), Units 1 and 2, Regarding Emergency Diesel Generator 3 Inoperable Due to Failure to Auto-Start | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000325/LER-2016-003 | Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 LER 16-003-00 for Brunswick Steam Electric Plant, Unit 1 Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000325/LER-2016-004 | Tornado Missile Vulnerability Results in Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000325/LER-2016-005 | Drywell High Range Radiation Monitors Inoperable due to Thermally Induced Current Phenomenon | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000325/LER-2016-006 | Control Room Air Conditioning Units Inoperable due to Corroded Supports | 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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