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Category:Letter
MONTHYEARIR 05000324/20240032024-11-13013 November 2024 Integrated Inspection Report 05000324/2024003 and 05000325/2024003 IR 05000324/20253012024-10-17017 October 2024 Notification of Licensed Operator Initial Examination 05000325/2025301 and 05000324/2025301 IR 05000324/20244012024-10-15015 October 2024 Security Baseline Inspection Report 05000324/2024401 and 05000325/2024401 ML24297A6262024-10-11011 October 2024 PCA Letter to NRC Brunswick Potential Tropical Storm Eight IR 05000324/20240102024-09-10010 September 2024 Focused Engineering Inspection Commercial Grade Dedication Report 05000324-2024010 and 05000325-2024010 ML24218A0862024-09-0909 September 2024 NRC to NMFS, Designation of Duke Energy Progress LLC as the Non-Federal Representative for Brunswick Steam Electric Plant, Units 1 and 2 ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24242A0322024-08-29029 August 2024 Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 29, 10 CFR 54.37 Update, Technical Requirements Manuals, Technical Specification Bases, 10 CFR 50.59 and 10 CFR 72.48 Evaluation Summaries, and Commitment Change IR 05000324/20240052024-08-23023 August 2024 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2024005 and 05000325/2024005) IR 05000324/20240022024-08-0505 August 2024 Integrated Inspection Report 05000324/2024002 and 05000325/2024002 and 07200006/2024001 ML24206A1062024-07-30030 July 2024 2024 Brunswick Requal Inspection Corporate Notification Letter ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000324/20244202024-07-0202 July 2024 – Security Baseline Inspection Report 05000324/2024420 and 05000325/2024420 ML24108A0702024-06-0505 June 2024 – Issuance of License Amendments to Revise the 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach IR 05000324/20244022024-05-17017 May 2024 Plan Material Control and Accounting Program Inspection Report 05000324/2024402 and 05000325/2024402 - Cover Letter IR 05000324/20240012024-05-0909 May 2024 Integrated Inspection Report 05000324/2024001 and 05000325/2024001 05000325/LER-2024-001, Primary Containment Penetration Local Leak Rate Testing Failure2024-04-10010 April 2024 Primary Containment Penetration Local Leak Rate Testing Failure 05000325/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 IR 05000324/20243012024-04-0303 April 2024 NRC Operator License Examination Report 05000325/2024301 and 05000324/2024301 ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML24026A0982024-03-0101 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0057 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000324/20230062024-02-28028 February 2024 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 – NRC Inspection Reports 05000324/2023006 and 05000325/2023006 IR 05000324/20244032024-02-14014 February 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perm Inspection 05000325/2024403; 05000324/2024403 ML24032A1392024-02-12012 February 2024 Correction of Errors within Authorized Alternative Request RA-22-0308 IR 05000324/20230042024-02-0606 February 2024 Integrated Inspection Report 05000324/2023004 and 05000325/2023004 ML24036A0962024-02-0202 February 2024 Operator Licensing Examination Approval 050003242024301 and 050003252024301 IR 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 ML23212B2682023-07-25025 July 2023 – Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 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 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 2024-09-09
[Table view] 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
[Table view] |
LER-2011-001, For Brunswick, Unit 1, Regarding Loss of Control Room Emergency Ventilation |
Event date: |
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Report date: |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(x)
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)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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3252011001R00 - NRC Website |
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text
Progress Energy June 2.2011 SERIAL: BSEP 11-0058 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit No. 1 Renewed Facility Operating License No. DPR-71 Docket Nos. 50-325 Licensee Event Report 1-2011-001 Ladies and Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Carolina Power
& Light Company, now doing business as Progress Energy Carolinas, Inc., submits the enclosed Licensee Event Report (LER). 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. Lee Grzeck, Acting Supervisor -
Licensing/Regulatory Programs, at (910) 457-2487.
Sincerely, Joseph M. Frisco, Jr.
Plant General Manager Brunswick Steam Electric Plant LJG/ljg
Enclosure:
Licensee Event Report Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461
ýe' 09-
Document Control Desk BSEP 11-0058 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Ave. N.E., Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Brunswick Steam Electric Plant (BSEP), Unit 1 05000325 1 of4
- 4. TITLE Loss of Control Room Emergency Ventilation
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIALu REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO.
MN FACILITY NAME DOCKET NUMBER 04 07 2011 2011 - 001 - 00 06 02 2011
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[E 20.2201(b)
[I 20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii)
[1 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
F1 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[] 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
[I 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A) 0l 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
[: 50.36(c)(2)
[I 50.73(a)(2)(v)(A)
[l 73.71(a)(4) 100 El 20.2203(a)(2)(iv)
E] 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5)
El 20.2203(a)(2)(v)
[: 50.73(a)(2)(i)(A)
[I 50.73(a)(2)(v)(C)
C] OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B) 2 50.73(a)(2)(v)(D)
Specify in Abstract below or I_
I in The breaker, including the solid state trip unit, was removed and sent to Progress Energy's Crystal River plant breaker shop for testing, to the extent possible, and analysis. There was no evidence of a fault, and the trip unit was found to be operating within specifications during secondary current injection. No problems occurred during actual trip testing that would cause a spurious trip. The solid state trip unit was then sent to Progress Energy's Harris Environmental and Energy (HE&E) Center.. No problems were noted in the visual examination, including checks of the solder connections and inspection of the transistors for corrosion.
Discreet component checks were performed on all diodes and transistors with no failures noted. The trip unit was then sent to ABB (i.e., the original equipment manufacturer) for additional testing. The trip unit passed the secondary current injection test and the silicon control rectifier (SCR) leakage was verified to be acceptable. ABB confirmed that there have been no design changes in the trip units between 1992 and 2010. ABB could not find any problem with the trip unit. No spurious trips occurred during any of this testing and no problems related to a spurious trip were found.
Based on the evidence and analysis performed in this investigation, the spurious trip of the E-7 main breaker is attributed to a malfunction of the new solid state trip unit. However, this malfunction could not be duplicated during testing and no specific root cause could be determined.
The BSEP breaker in question is an ABB K-3000S model; which is widely used throughout the industry.
A review of external Operating Experience (OE) identified other spurious trips of this model breaker. The cause of a number of these breaker trips was attributed to the trip unit, however, testing and analysis could not ultimately identify a problem with the trip unit. Thus, spurious trips with an unknown cause attributed to the trip unit have been known to occur. The typical industry corrective action for solid state trip unit failures with undetermined causes is replacement of the individual unit.
The BSEP breaker (i.e., with its original trip unit) which had been removed from E-7 during B220R1 was reinstalled on April 8, 2011, and the substation reenergized. No subsequent problems occurred with the breaker.
Event Cause
The direct cause of the E-7 breaker trip event was a spurious actuation of the solid state trip unit. No problems could be found in the post-event testing or during repeat of the loss of offsite power/loss of coolant accident (LOOP/LOCA) test. Therefore, the root cause of this event could not be determined.
Safety Assessment
The safety significance of this event is considered minimal. The condition existed for approximately one hour and 51 minutes, and plant staff took immediate action to return the equipment to service.
Corrective Actions
The following corrective actions will be taken.
" The E-7 breaker was replaced and the substation reenergized. This action is complete.
" The tripped breaker that was removed will be refurbished, which will include replacement of the trip unit, prior to reuse. This action is currently scheduled to be completed by October 20, 2011.
Previous Similar Events
A review of LERs and corrective action program nuclear condition reports (NCRs) for the past three years identified the following similar previous occurrence.
NCR 350664, dated August 16, 2009, identified a similar failure where the feeder breaker to lighting panel IA tripped and no problem could be found. The breaker was reinstalled and has not had an additional trip. The trip unit was later replaced on May 11, 2010. The old trip unit was inspected and corrosion was observed on transistors. This event could not have reasonably been expected to prevent the condition reported in this LER. (Note that for the E-7 breaker trip identified in this LER, the new solid state trip unit that was installed on the refurbished breaker was part of an extent of condition action in response to the transistor corrosion issue identified in NCR 350664).
LER 1-2009-001, dated March 22, 2009, reports a loss of control room emergency ventilation (CREV) and air conditioning systems. The direct cause of the loss of control air to the control room ventilation system was blockage of air flow through the Control Building instrument air dryer, due to freezing of condensate within the cooling coil. This event could not have reasonably been expected to prevent the condition reported in this LER.
LER 1-2008-004, dated August 18, 2008, reports two CREV subsystems inoperable due to failure to isolate. The select cause of this event was determined to be failure to identify appropriate Preventive Maintenance (PM) routes for the CREV system components. The corrective action was to develop PM tasks for the Control Building ventilation system dampers, actuators, limit switches, and relays. This event could not have reasonably been expected to prevent the condition reported in this LER.
Commitments
No regulatory commitments are contained in this report.
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05000324/LER-2011-001-02, Regarding Condition Prohibited by Technical Specifications Due to RWCU Instrumentation Inoperable | Regarding Condition Prohibited by Technical Specifications Due to RWCU Instrumentation Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000324/LER-2011-001-01, (Bsep), Unit 2, Regarding Condition Prohibited by Technical Specifications Due to RWCU Instrumentation Inoperable | (Bsep), Unit 2, Regarding Condition Prohibited by Technical Specifications Due to RWCU Instrumentation Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000324/LER-2011-001, For Brunswick, Unit 2, Regarding Condition Prohibited by Technical Specifications Due to RWCU Instrumentation Inoperable | For Brunswick, Unit 2, Regarding Condition Prohibited by Technical Specifications Due to RWCU Instrumentation Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000325/LER-2011-001, For Brunswick, Unit 1, Regarding Loss of Control Room Emergency Ventilation | For Brunswick, Unit 1, Regarding Loss of Control Room Emergency Ventilation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000325/LER-2011-002 | Fire Related Unanalyzed Condition that could Impact Equipment Credited in Safe Shutdown Analysis | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000324/LER-2011-002, For Brunswick, Unit 2, Regarding Unanalyzed Condition Due to Reactor Pressure Vessel (RPV) Head Detensioned During Startup | For Brunswick, Unit 2, Regarding Unanalyzed Condition Due to Reactor Pressure Vessel (RPV) Head Detensioned During Startup | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000325/LER-2011-003 | Loss of Control Room Air Conditioning and Emergency Ventilation | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000324/LER-2011-003, Regarding Loss of Control Room Air Conditioning and Emergency Ventilation | Regarding Loss of Control Room Air Conditioning and Emergency Ventilation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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