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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-2002-001, Oscillation Power Range Monitor (OPRM) Inoperability Due to Non-Conservative Setpoint |
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3252002001R00 - NRC Website |
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16V'a' CP&L A Progress Energy Cormany JAN 2 0 2003 SERIAL: BSEP 03-0011 U. S. Nuclear Regulatory Commission AiTTN: Document Control Desk Washington, DC 20555-0001 10 CFR 50.73 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET NO. 50-325/LICENSE NO. DPR-71 LICENSEE EVENT REPORT 1-2002-001 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, Z),2 W. G Noll Plant General Manager Brunswick Steam Electric Plant MAT/mat
Enclosure:
Licensee Event Report 1-2002-001 Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461 1 t5,2) "-)-
Document Control Desk BSEP 03-0011 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II A'TN: 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: Mr. Theodore A. Easlick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Ms. Brenda L. Mozafari (Mail Stop OWEN 8G9) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Mr. Leonard N. Olshan (Mail Stop OWFN 8H12) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Mr. Allen G Howe (Mail Stop OWEN 8G9) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. JoA. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-051
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Abstract
On November 22, 2002, GE Nuclear Energy (GE) identified a reportable condition in accordance with 10 CFR 21.21(d) (i.e., SC02-21, "Stability Option III: OPRM Tmin Specification"). SC02-21 states that the Stability Option III period based detection algorithm (PBDA) range for minimum period of detection (i.e.,
Tmin) values specified in Licensing Topical Report NEDO-31960-A, "BWR Owner's Group Long-Term Stability Solutions Licensing Methodology (Supplement 1)," was non-conservative and recommended that the Oscillation Power Range Monitor (OPRM) be considered inoperable if the Tmin value is set greater than 1.2 seconds. Stability Option HI is installed on Unit 1 and the Tmin value was set at 1.4 seconds. Therefore, at 1328 Eastern Standard Time (EST) on November 22, 2002, all OPRM channels were declared inoperable in accordance with Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," and an alternate method to detect and suppress thermal hydraulic instability oscillations was placed into effect as directed by Condition I of TS 3.3.1.1. Subsequently, the Tmin value was changed to 1.2 seconds and all OPRM channels were declared operable at 0917 EST on November 27, 2002. The safety significance of this occurrence is considered minimal.
The apparent cause of the event is an incomplete analysis, performed by GE, when establishing oscillation period ranges to be used for the PBDA.
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 NRC Form 366A) (17) these conditions, SC02-21 states that the failure of automatic detection at these conditions is not expected to result in fuel failures but may lead to violation of the TS MCPR Safety Limit.
In addition, although considered inoperable with Tmin set greater than 1.2 seconds, the OPRM Upscale trip function was fully operational and would have continued to protect the plant from thermal-hydraulic instabilities throughout the operating range. If such protection was not provided, operators are trained to recognize instabilities and to take appropriate actions should an instability occur.
PREVIOUS SIMILAR EVENTS
A review of reportable events for the past three years has not identified any previous similar events.
COMMITMENTS
No commitments are being established in this report.