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Category:Licensee Event Report (LER)
MONTHYEAR05000325/LER-2024-002, Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization2024-04-10010 April 2024 Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization 05000325/LER-2024-001, Primary Containment Penetration Local Leak Rate Testing Failure2024-04-10010 April 2024 Primary Containment Penetration Local Leak Rate Testing Failure 05000324/LER-2023-001, Two Main Steam Line Safety Relief Valves Inoperable2023-07-17017 July 2023 Two Main Steam Line Safety Relief Valves Inoperable 05000325/LER-2023-001, Loss of Redundant Power Supply Operation Causes Turbine Trip and Subsequent Reactor Scram2023-06-15015 June 2023 Loss of Redundant Power Supply Operation Causes Turbine Trip and Subsequent Reactor Scram 05000325/LER-2022-001, High Pressure Coolant Injection (HPCI) Inoperable2022-09-12012 September 2022 High Pressure Coolant Injection (HPCI) Inoperable 05000325/LER-2021-001, Automatic Specified System Actuation Due to Loss of Power to Emergency Bus E32022-01-20020 January 2022 Automatic Specified System Actuation Due to Loss of Power to Emergency Bus E3 05000324/LER-2020-005, (Bsep), Unit 1 Re Condition Prohibited by Technical Specifications Due to Ventilation Charcoal Sample Lab Results2021-01-21021 January 2021 (Bsep), Unit 1 Re Condition Prohibited by Technical Specifications Due to Ventilation Charcoal Sample Lab Results 05000325/LER-2020-002-01, Technical Specification Required Shutdown Due to Unidentified Leakage2020-11-17017 November 2020 Technical Specification Required Shutdown Due to Unidentified Leakage 05000325/LER-2020-004, (Bsep), Unit 1, Setpoint Drift in Main Steam Line Safety Relief Valves Results in Three Valves Inoperable2020-09-29029 September 2020 (Bsep), Unit 1, Setpoint Drift in Main Steam Line Safety Relief Valves Results in Three Valves Inoperable 05000325/LER-2020-003, Automatic Specified System Actuations Due to Loss of Offsite Power2020-09-21021 September 2020 Automatic Specified System Actuations Due to Loss of Offsite Power 05000325/LER-2020-001, Manual Reactor Scram During Startup Due to All Bypass Valves Fully Opening2020-05-20020 May 2020 Manual Reactor Scram During Startup Due to All Bypass Valves Fully Opening 05000324/LER-2019-003, High Pressure Coolant Injection (HPCI) Inoperable2019-07-31031 July 2019 High Pressure Coolant Injection (HPCI) Inoperable RA-19-0263, False High Reactor Water Level Results in Automatic Specified System Actuations2019-06-19019 June 2019 False High Reactor Water Level Results in Automatic Specified System Actuations 05000324/LER-2019-002, Manual Reactor Protection System Actuation and Specified System Actuation2019-05-28028 May 2019 Manual Reactor Protection System Actuation and Specified System Actuation 05000324/LER-2019-001, Automatic Actuation of the Primary Containment Isolation System2019-04-30030 April 2019 Automatic Actuation of the Primary Containment Isolation System 05000325/LER-2018-003, Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Two Valves Inoperable2018-08-0909 August 2018 Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Two Valves Inoperable 05000325/LER-2018-002, Automatic Reactor Trip During Stator Coolant System Realignment2018-06-0505 June 2018 Automatic Reactor Trip During Stator Coolant System Realignment 05000325/LER-2018-001, Implementation of Enforcement Guidance Memorandum (Egm) 11-003, Revision 32018-05-0707 May 2018 Implementation of Enforcement Guidance Memorandum (Egm) 11-003, Revision 3 05000324/LER-1917-004, Regarding Emergency Diesel Generator and Primary Containment Isolation System Actuations2017-11-15015 November 2017 Regarding Emergency Diesel Generator and Primary Containment Isolation System Actuations 05000324/LER-1917-003, Regarding Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable,2017-08-0303 August 2017 Regarding Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Three Valves Inoperable, 05000325/LER-1917-003, Regarding Control Room Air Conditioning and Emergency Ventilation Systems Rendered Inoperable2017-08-0202 August 2017 Regarding Control Room Air Conditioning and Emergency Ventilation Systems Rendered Inoperable 05000324/LER-1916-006-01, Regarding Control Room Air Conditioning Units Inoperable Due to Corroded Supports2017-05-0303 May 2017 Regarding Control Room Air Conditioning Units Inoperable Due to Corroded Supports 05000324/LER-2017-001, Regarding Speed and Frequency Oscillations Result in Inoperable Emergency Diesel Generator2017-03-22022 March 2017 Regarding Speed and Frequency Oscillations Result in Inoperable Emergency Diesel Generator 05000324/LER-2016-005, Regarding Drywell High Range Radiation Monitors Inoperable Due to Thermally Induced Current Phenomenon2016-12-0505 December 2016 Regarding Drywell High Range Radiation Monitors Inoperable Due to Thermally Induced Current Phenomenon 05000324/LER-2016-004, Regarding Tornado Missile Vulnerability Results in Condition Prohibited by Technical Specifications2016-09-0606 September 2016 Regarding Tornado Missile Vulnerability Results in Condition Prohibited by Technical Specifications 05000324/LER-2016-002-01, For Brunswick Steam Electric Plant Unit 1 Regarding Emergency Diesel Generator 3 Inoperable Due to Failure to Auto-Start2016-08-0808 August 2016 For Brunswick Steam Electric Plant Unit 1 Regarding Emergency Diesel Generator 3 Inoperable Due to Failure to Auto-Start 05000324/LER-2016-001, Regarding Mispositioned Valves Result in Residual Heat Removal Service Water System Lnoperability2016-08-0808 August 2016 Regarding Mispositioned Valves Result in Residual Heat Removal Service Water System Lnoperability 05000325/LER-2016-003, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 32016-05-0202 May 2016 Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 05000325/LER-2016-001, Regarding Electrical Bus Fault Results in Lockout of Startup Auxiliary Transformer and Loss of Offsite Power2016-04-0606 April 2016 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 05000324/LER-2015-003, Regarding Oil Leak Renders Residual Heat Removal Service Water System Pump Inoperable2015-06-0808 June 2015 Regarding Oil Leak Renders Residual Heat Removal Service Water System Pump Inoperable 05000324/LER-2015-002, Regarding Emergency Diesel Generator Loss of Safety Function2015-05-20020 May 2015 Regarding Emergency Diesel Generator Loss of Safety Function 05000324/LER-2015-001, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 22015-04-24024 April 2015 Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 2 05000325/LER-2015-001, (Bsep), Unit 1, Regarding High Pressure Coolant Injection (HPCI) System Inoperable Due to Auxiliary Oil Pump Failure2015-04-10010 April 2015 (Bsep), Unit 1, Regarding High Pressure Coolant Injection (HPCI) System Inoperable Due to Auxiliary Oil Pump Failure 05000325/LER-2014-005, Regarding Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Two Valves Inoperable2014-07-21021 July 2014 Regarding Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Two Valves Inoperable 05000324/LER-2014-002, Regarding Secondary Containment Loss of Safety Function Due to Opening in Reactor Building Roof Drain Piping2014-06-19019 June 2014 Regarding Secondary Containment Loss of Safety Function Due to Opening in Reactor Building Roof Drain Piping 05000324/LER-2014-004, Regarding Fire Related Unanalyzed Condition That Could Impact Equipment Credited in Safe Shutdown Analysis2014-05-16016 May 2014 Regarding Fire Related Unanalyzed Condition That Could Impact Equipment Credited in Safe Shutdown Analysis 05000325/LER-2014-003, Regarding Secondary Containment Loss of Safety Function Due to Airlock Door Interlock Design2014-05-0909 May 2014 Regarding Secondary Containment Loss of Safety Function Due to Airlock Door Interlock Design 05000325/LER-2014-002, Regarding Secondary Containment Isolation Dampers Inoperable During Operations with Potential to Drain the Reactor Vessel2014-05-0505 May 2014 Regarding Secondary Containment Isolation Dampers Inoperable During Operations with Potential to Drain the Reactor Vessel 05000324/LER-2014-001, Regarding Secondary Containment Loss of Safety Function Due to Airlock Door Interlock Design2014-05-0202 May 2014 Regarding Secondary Containment Loss of Safety Function Due to Airlock Door Interlock Design 05000325/LER-2014-001, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 22014-05-0101 May 2014 Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 2 05000324/LER-2013-002, From Brunswick Steam Electric Plant, Unit 1, Fire Related Unanalyzed Condition That Could Impact Equipment Credited in Safe Shutdown Analysis2013-09-27027 September 2013 From Brunswick Steam Electric Plant, Unit 1, Fire Related Unanalyzed Condition That Could Impact Equipment Credited in Safe Shutdown Analysis 05000324/LER-2013-004, Regarding Operation Prohibited by Technical Specifications - Recirculation Loop Flow Mismatch2013-08-19019 August 2013 Regarding Operation Prohibited by Technical Specifications - Recirculation Loop Flow Mismatch 05000324/LER-2013-001, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 12013-05-0606 May 2013 Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 1 05000324/LER-2012-007-01, Regarding Loss of Control Room Emergency Ventilation2013-04-11011 April 2013 Regarding Loss of Control Room Emergency Ventilation 05000324/LER-2012-007, (Bsep), Unit 1, Loss of Control Room Emergency Ventilation2013-02-12012 February 2013 (Bsep), Unit 1, Loss of Control Room Emergency Ventilation 05000324/LER-2011-001-02, Regarding Condition Prohibited by Technical Specifications Due to RWCU Instrumentation Inoperable2013-01-20020 January 2013 Regarding Condition Prohibited by Technical Specifications Due to RWCU Instrumentation Inoperable 05000325/LER-2012-006, (Bsep), Unit 1, Operation Prohibited by Technical Specifications Due to Operation with a Potential for Draining the Reactor Vessel (OPDRV)2012-11-19019 November 2012 (Bsep), Unit 1, Operation Prohibited by Technical Specifications Due to Operation with a Potential for Draining the Reactor Vessel (OPDRV) 05000324/LER-2012-005, Regarding Local Control Capability of Emergency Diesel Generator No. 2 Not Available2012-10-29029 October 2012 Regarding Local Control Capability of Emergency Diesel Generator No. 2 Not Available 05000325/LER-2012-004, Regarding High Pressure Coolant Injection (HPCI) Inoperable Due to Erratic Governor Operation2012-06-29029 June 2012 Regarding High Pressure Coolant Injection (HPCI) Inoperable Due to Erratic Governor Operation 2024-04-10
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LER-2003-001, Reactor Feed Pump Trip Results in Specified System Actuations |
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3252003001R00 - NRC Website |
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gi CP&L A Progress Energy Company March 13, 2003 SERIAL: BSEP 03-0014 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET NO. 50-325/LICENSE NO. DPR-71 LICENSEE EVENT REPORT 1-03-001 Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Progress Energy Carolinas, Inc. submits the enclosed Licensee Event Report. This report fulfills the requirement for a written report within sixty (60) days of a reportable occurrence.
Please refer any questions regarding this submittal to Mr. Edward T. O'Neil, Manager - Support Services, at (910) 457-3512.
Sincerely, W. G. Noll Plant General Manager Brunswick Steam Electric Plant CRE/cre Enclosure: Licensee Event Report Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461 15~6De9)
Document Control Desk BSEP 03-0014 l Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-051
Abstract
On January 12, 2003, at approximately 1552 hours0.018 days <br />0.431 hours <br />0.00257 weeks <br />5.90536e-4 months <br />, decreasing reactor coolant level, due to a reactor feedwater pump turbine (RFPT) trip, resulted in the actuation of the reactor protection system (RPS), as well as Group 2 and Group 6 primary containment isolation valve closures. After the plant trip, the four emergency diesel generators (EDGs) started due to an invalid signal generated by switchyard equipment. In addition, the Reactor Core Isolation Cooling system was manually operated to maintain coolant level in the reactor vessel.
At the time of the event, Unit 1 was initially operating at 94 percent of rated thermal power.
The cause of the RPS and subsequent equipment actuations was attributed to the decrease in reactor vessel level caused by a RFPT 1B trip which was the result of insufficient lube oil pressure margin on the RFPT 1B bearing header during a Main Oil Pump (MOP) trip. With proper margin, the standby MOP would have been able to maintain bearing header oil pressure, thereby avoiding RFPT trip and the event. The cause of the automatic start of the EDGs is the failure of a Power Circuit Breaker (PCB) to open on its initial trip signal, which resulted in the invalid automatic EDG start signal. The safety significance of this occurrence is considered minimal.
RFPT 1B is being operated with both MOPs in operation until further investigation can be performed to resolve the rapid oil pressure decrease noted when an MOP is tripped in single MOP operation. The PCB was tested to ensure proper operation and returned to service.
NRC FORM 366 (7-2001)
(If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (if more space is required, use additional copies of NRC Form 366A) (17)
COMMITMENTS
Those actions committed to by Progress Energy Carolinas, Inc. (PEC) in this document are identified below.
Any other actions discussed in this submittal represent intended or planned actions by PEC. They are described for the NRC's information and are not regulatory commitments. Please notify the Manager -
Support Services at BSEP of any questions regarding this document or any associated regulatory
commitments
During the next Unit 1 refuel outage (i.e., B115Rl), further investigation of the RFPT lB lubricating oil system will be conducted to determine the resolution of the issue associated with the rapid bearing header pressure decrease noted when a MOP trips in single MOP operation.
- By May 22, 2003, a multi-disciplined team will provide recommendations to improve the operation and reliability of the RFPT lubricating oil system. The recommendations will be implemented as appropriate.
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05000324/LER-2003-001, For Brunswick Unit 2 Main Steam Line Drain Isolation Valve Local Leak Rate Test Failures | For Brunswick Unit 2 Main Steam Line Drain Isolation Valve Local Leak Rate Test Failures | | 05000325/LER-2003-001, Reactor Feed Pump Trip Results in Specified System Actuations | Reactor Feed Pump Trip Results in Specified System Actuations | | 05000325/LER-2003-002 | Oscillation Power Range Monitor (OPRM) Inoperability Due To Inadequate Confirmation Count Performance | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000324/LER-2003-002, Oscillation Power Range Monitor (OPRM) Inoperability Due to Inadequate Confirmation Count Performance | Oscillation Power Range Monitor (OPRM) Inoperability Due to Inadequate Confirmation Count Performance | | 05000324/LER-2003-003, Re Unit 2 Scram During Startup Due to Electro Hydraulic Control System Malfunction | Re Unit 2 Scram During Startup Due to Electro Hydraulic Control System Malfunction | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) | 05000271/LER-2003-004, Hearing - Entergy Exhibit 13, LER 2003-004-00, Brunswick, Unit 2, Loss of Generator Excitation Results in Reactor Protection System and Other Specified System Actuations | Hearing - Entergy Exhibit 13, LER 2003-004-00, Brunswick, Unit 2, Loss of Generator Excitation Results in Reactor Protection System and Other Specified System Actuations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | 05000324/LER-2003-004, Regarding Loss of Generator Excitation Results in Reactor Protection System and Other Specified System Actuations | Regarding Loss of Generator Excitation Results in Reactor Protection System and Other Specified System Actuations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) |
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