|
---|
Category:Letter type:NL
MONTHYEARNL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0213, Inservice Inspection Program Owner'S Activity Report for Outage 1R312023-03-21021 March 2023 Inservice Inspection Program Owner'S Activity Report for Outage 1R31 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-23-0011, Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only2023-01-0505 January 2023 Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, NL-22-0887, Cycle 32 Core Operating Limits Report2022-11-21021 November 2022 Cycle 32 Core Operating Limits Report NL-22-0884, Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-1012022-11-17017 November 2022 Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-101 NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0756, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02022-09-30030 September 2022 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis NL-22-0608, Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers2022-08-17017 August 2022 Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers NL-22-0552, Inservice Inspection Program Owner'S Activity Report for Outage 2R282022-07-28028 July 2022 Inservice Inspection Program Owner'S Activity Report for Outage 2R28 NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value NL-22-0361, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak.2022-06-20020 June 2022 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak. NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0388, Cycle 29 Core Operating Limits Report2022-05-31031 May 2022 Cycle 29 Core Operating Limits Report NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0340, Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical2022-05-10010 May 2022 Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations 2024-01-11
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000364/LER-2017-0052018-01-11011 January 2018 Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector, LER 17-005-00 for Joseph M. Farley Nuclear Plant, Unit 2, Regarding Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector 05000364/LER-2017-0042017-12-22022 December 2017 I OF 3, LER 17-004-00 for Joseph M. Farley Nuclear Plant, Unit 2 Regarding Turbine-Driven Auxiliary Feedwater Pump Steam Admission Valve Air Leak Resulted in a Condition Prohibited by Technical Specifications 05000364/LER-2017-0032017-12-20020 December 2017 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits, LER 17-003-00 for Joseph M. Farley, Unit 2, Regarding Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000364/LER-2017-0022017-12-19019 December 2017 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits, LER 17-002-00 for Joseph M. Farley, Unit 2, Regarding Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000364/LER-2017-0012017-08-21021 August 2017 2B Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak without Makeup Capability, LER 17-001-00 for Farley, Unit 2, Regarding 28 Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak without Makeup Capability 05000348/LER-2016-0072017-06-0707 June 2017 Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters, LER 16-007-01 for Joseph M. Farley, Unit 1, Regarding Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters 05000348/LER-2016-0092017-02-0202 February 2017 Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications, LER 16-009-00 for Joseph M. Farley Nuclear Plant, Units 1 and 2 Regarding Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications 05000348/LER-2016-0082017-01-23023 January 2017 Manual Reactor Trip Due to Generator Voltage Swings, LER 16-008-00 for Farley, Unit 1, Regarding Manual Reactor Trip Due to Generator Voltage Swings 05000348/LER-2016-0052016-12-28028 December 2016 Toxic Gas Event, LER 16-005-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Toxic Gas Event 05000348/LER-2016-0042016-12-19019 December 2016 Unapproved Environmental Qualification Material Caused Inoperability of One Containment Cooling Train, LER 16-004-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Unapproved Environmental Qualification Material Caused lnoperability of One Containment Cooling Train 05000348/LER-2016-0062016-12-19019 December 2016 Manual Reactor Trip due to Loss of Speed Control on 1A Steam Generator Feed Pump, LER 16-006-00 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Manual Reactor Trip due to Loss of Speed Control on 1A Steam Generator Feed Pump 05000348/LER-2016-0032016-12-12012 December 2016 Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band, LER 16-003-00 for Farley, Unit 1, Regarding Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band 05000348/LER-2016-0022016-11-30030 November 2016 Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve, LER 16-002-00 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve 05000348/LER-2016-0012016-06-0909 June 2016 Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications, LER 16-001-00 for Farley, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications 05000364/LER-2015-0012016-01-13013 January 2016 Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications due ,to a Design Issue, LER 15-001-01 for Farley, Unit 2, Regarding Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications Due to a Design Issue NL-13-1525, Special Report 13-001-00 for Joseph M. Farley, Unit 2, Regarding Nonfunctional Radiation Monitor R-60B2013-07-26026 July 2013 Special Report 13-001-00 for Joseph M. Farley, Unit 2, Regarding Nonfunctional Radiation Monitor R-60B NL-11-2445, LER 11-S01-00 for Joseph M. Farley, Unit 1 Regarding Loss of Power to Security Systems2012-01-0909 January 2012 LER 11-S01-00 for Joseph M. Farley, Unit 1 Regarding Loss of Power to Security Systems NL-08-0756, Special Report 2008-002-00, Inoperable Radiation Monitor R-60B2008-05-0909 May 2008 Special Report 2008-002-00, Inoperable Radiation Monitor R-60B NL-08-0659, Special Report 2008-001-00, Inoperable Radiation Monitor R-29B2008-04-25025 April 2008 Special Report 2008-001-00, Inoperable Radiation Monitor R-29B NL-05-2234, Special Report No. 2005-001-00 for Joseph M. Farley Nuclear Plant - Unit 1 Re Inoperable Radiation Monitor R-60B2005-12-0606 December 2005 Special Report No. 2005-001-00 for Joseph M. Farley Nuclear Plant - Unit 1 Re Inoperable Radiation Monitor R-60B 2018-01-11
[Table view] |
Text
Thomas A. Lynch Southern Nuclear Vice President* Farley Operating Company. Inc.
Farley Nuclear Plant Post Office Drawer 470 Ashford. Alabama 36312 Tel 334814A511 Fax 334.814.4728 SOUTHERN ' \ .
COMPANY January 9, 2012 Docket Nos.: 50-348 NL-11-2445 50-364 U. S. Nuclear Regulatory Commission AnN: Document Control Desk Washington. D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Licensee Event Report 2011-S01-00 Loss of Power to Security Systems Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 73.71 Section (d) and 10 CFR 73 Appendix G Section I(c), Southern Nuclear Operating Company (SNC) is submitting the enclosed Licensee Event Report. This letter contains no NRC commitments. If you have any questions, please contact Doug McKinney at (205) 992-5982.
Sincerely.
1~
T. A. Lynch Vice President - Farley TAlIWDO
Enclosure:
Units 1 and 2 Licensee Event Report 2011-S01-00
U. S. Nuclear Regulatory Commission NL-11-2445 Page 2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Chief Nuclear Officer Ms. P. M. Marino, Vice President - Engineering Mr. B. L. Ivey, Vice President - Regulatory Affairs RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant - Units 1 and 2 Licensee Event Report 2011-S01-00 Loss of Power to Security Systems Enclosure Units 1 and 2 Licensee Event Report 2011-S01-00
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150*0104 EXPIRES: 10131/2013 (10-2010)
Es1ima1ed burden per response 10 comply w~h 1his manda10ry collec1ion request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorpora1ed into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIAIPrivacy Sectio~.5 F53), U.S. Nuclear Regulatory LICENSEE EVENT REPORT (LER) Commission, Washington, DC 20 0001. or by internet e-mail to infoeolleets.resource 0 nrc'Bov, and to the Desk Officer, Office of Information and Regulatory Affairs, NE B-10202, (3150-0104), Office of Man8Q9ment and Budget, Washington, DC 20503. If a means used to impose an rnformation collection does no1 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 2. DOCKET NUMBER 13. PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000348 1 OF 3
- 4. TITLE Loss of Power to Security Systems
- 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR SEQUENTIAL REV YEAR MONTH DAY YEAR NUMBER NO. Farley Nuclear Plant, Unit 2 05000364 FACILITY NAME DOCKET NUMBER 11 15 2011 2011 - S01 - 00 01 09 2012
- 9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check al/ that apply) o 20.2201(b) o 20.2203(a)(3)(i) o 5O.73(a)(2)(i)(C) o 5O.73(a)(2)(vii) 1 o 20.2201(d) o 20.2203(a)(3)(ii) o 5O.73(a)(2)(ii)(A) o 5O.73(a)(2)(viii)(A) o 20.2203(a)(1) o 20.2203(a)(4) o 5O.73(a)(2)(ii)(8) o 5O.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) o 5O.36(c)(1 )(i)(A) o 5O.73(a)(2)(iii) o 5O.73(a)(2)(ix)(A)
- 10. POWER LEVEL o 20.2203(a)(2)(ii) o 5O.36(c)(1 )(ii)(A) o 5O.73(a)(2)(iv)(A) o 5O.73(a)(2)(x) o 20.2203(a)(2)(iii) o 5O.36(c)(2) o 50.73(a)(2)(v)(A) o 73.71 (a)(4) o 20.2203(a)(2)(iv) o 5O.46(a)(3)(ii) o 50.73(a)(2)(v)(B) o 73.71 (a)(5) 100 o 20.2203(a)(2)(v) o 50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) 181 OTHER o 20.2203(a)(2)(vi) o 50.73(a)(2)(i)(8) o 5O.73(a)(2)(v)(D) Specify in Abstract below or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME rELEPHONE NUMBER (Include Area Code)
J.M, Farley Nuclear Plant, W. D. Oldfield - Principal Licensing Engineer 334814-4765
- 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT MANU- REPORTABLE MANU* REPORTABLE CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT FACTURER TO EPIX FACTURER TO EPIX B EE IS 8569 N 14, SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR SUBMISSION o YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 181 NO DATE ABSTRACT (Limit to 1400 spaces, I.e., approximately 15 single-spaced typewrillen Jines)
On November 15, 2011 at approximately 06:05, with Unit 1 at 100 percent and Unit 2 at 88 percent power, all security equipment lost power including card readers, microwaves, and cameras. The security uninterruptable power supply (UPS) did not operate to keep the security equipment functional. Security compensatory measures were established within approximately ten minutes and remained in effect until the power was restored to all security equipment. There was never any indication of undetected access, evidence of tampering, or on-going security threat. Power was restored to all security equipment through the operation of a UPS manual bypass switch. All loads were systematically restored and successfully tested before compensatory measures were relaxed on November 15, 2011 at 18:00.
A one-hour non emergency report was made on November 15, 2011 at 07:03 in accordance with 10 CFR 73 Appendix G Section I(c) for a failure of a safeguard system that could allow undetected access to the protected area or vital areas. The vendor supported troubleshooting revealed that the security UPS failed due to three faulty microswitches in the blown fuse alarm circuitry. These microswitches were replaced and the system was removed from manual bypass to normal operation on November 18, 2011 at approximately 15:00.
NRC FORM 366 (10*2010)
NRC FORM 366A LICENSEE EVENT REPORT (LER) u.s. NUCLEAR REGULATORY COMMISSION (10-2010)
CONTINUATION SHEET
- 1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE YEAR SEQUENTIAL IREVISION NUMBER NUMBER Joseph M. Farley Nuclear Plant, Unit 1 05000348 I 2 of 3 2011 - 801 - 00 NARRATIVE Westinghouse -- Pressurized Water Reactor Energy Industry Identification Codes are identified in the text as [XX]
Description of Event On November 15, 2011 at approximately 06:05, with Unit 1 at 100 percent and Unit 2 at 88 percent power, all security equipment lost power including card readers, microwaves, and cameras. There was no significant plant equipment out of service that had an impact on this event. The security uninterruptable power supply (UPS) (EE] did not operate to keep the security equipment functional.
Security compensatory measures were established within approximately ten minutes and remained in effect until the power was restored to all security equipment. There was never any indication of undetected access, evidence of tampering, or on-going security threat. Power was restored to all security equipment through the operation of an UPS manual bypass switch. All loads were systematically restored and successfully tested before compensatory measures were relaxed on November 15, 2011 at 18:00.
A one-hour non emergency report was made on November 15, 2011 at 07:03 in accordance with 10 CFR 73 Appendix G Section I(c) for a failure of a safeguard system that could allow undetected access to the protected area or vital areas. The vendor supported troubleshooting revealed that the security UPS failed due to three faulty microswitches in the blown fuse alarm circuitry. The faulty 4 amp at 250 volt microswitches (type MAl and part number 540-9197) were manufactured by Bussmann. These microswitches were replaced and the system was removed from manual bypass to normal operation on November 18, 2011 at approximately 15:00.
Cause of Event The normal alignment of the UPS inverter is "Normal Operation." When the inverter senses an internal fault it automatically switches to static bypass or the alternate power source from a dedicated security diesel. On November 15, 2011, the inverter sensed blown fuses due to three faulty microswitches and attempted to swap to static bypass. However, due to an alarm that came in the previous week (frequency out-of-tolerance) on November 10, 2011 , static bypass to the security diesel was unavailable. Therefore, when the inverter sensed blown fuses and attempted to swap to bypass, the bypass was unavailable and the inverter shutdown, resulting in a total loss of security power.
The Security UPS had only been in operation for approximately four months. The vendor indicated that this was not a common equipment fault with this brand of UPS. Therefore, the equipment faults could not have been prevented. However, the event could have been prevented had it been recognized that an immediate response to the alarm received the previous week on November 10, 2011 was needed. As a result, the causal analysis identified weaknesses in system monitoring and knowledge gaps in system operation as contributing causes.
NRC FORM 366A (W-2010)
NRC FORM 366A (10 -2010)
LICENSEE EVENT REPORT (LER) u.s. NUCLEAR REGULATORY COMMISSION I~______~~~~~____ C_O_N~T_IN~U~A~T~IO~N~S_HE_E_T~~~~~__~__~~~~
- 1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGE YEAR SEQUENTIAL IREVISION NUMBER NUMBER Joseph M. Farley Nuclear Plant, Unit 1 05000348 I 3 of 3 2011 - 801 - 00 NARRATIVE Safety Assessment Although security systems experienced a loss of power, compensatory measures were established within approximately ten minutes. These compensatory measures were maintained until security system power was restored, loads reestablished, and systems tested. Additional security force officers from other Southern Nuclear (SNC) plants were brought in as added assurance in establishing compensatory measures in the event power was subsequently lost during troubleshooting and/or power transfer operations. A determination was made that no security threat ever existed . Therefore, no risk to plant equipment or operation was identified. Accordingly, there was no safety significance associated with this event, as there we re no releases of radioactive materials, no personnel injuries, and no undetected or unauthorized entries made into the protected area or other vital areas. There were no safety system functional failures as a result of this event. This event had no adverse effect on the safety and health of the public.
Corrective Action The three faulty microswitches were replaced and the system was removed from manual bypass to normal operation.
Causal analysis was initiated and additional corrective actions were identified. These actions related to the new security UPS involve improving equipment monitoring, enhancing operating procedures. and training on system operation will be tracked to closure in the corrective action program.
Additional Information Similar Events:
None NRC FORM 36M (1 (}'20 I 0)