03-16-2016 | On January 23, 2016, at approximately 1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br />, with Units 1 and 2 operating at 100 .
percent power Mode 1, the North Anna 34.5kv Bus 3, offsite power feed to the "C" Reserve Station Service Transformer, was lost due to the opening of the L102 breaker. This resulted in the loss of power to the Unit 1H and Unit 2J emergency buses and the automatic start of the 1H and 2J emergency diesel generators (EDG). The Unit 1H
- emergency bus off-site power was restored and the 1H EDG was secured and returned to automatic. The 2J EDG continued to carry the 2J bus until repairs to L102 were completed
- and the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limiting action for Unit 2 was exited at 1706 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.49133e-4 months <br /> on 1/24/16. .The direct cause for-the opening of the L102 breaker was an internal switch contact failure.due to moisture. At 1948 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.41214e-4 months <br /> on January 23, 2016, an 8-hour Non-Emergency Report was made to the NRC in accordance with 10 CFR 50.72(b)(3)(iv)(A) as a condition that resulted in valid actuation of Engineered Safety Features (ESF). Units 1 and 2 continued to operate safely during the event. The health and safety of the public were not affected by this event.
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LER-2016-001, 1 OF 3 |
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Category:Letter
MONTHYEARML24283A0392024-10-0909 October 2024 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.D ML24281A1372024-10-0707 October 2024 ISFSI - Submittal of Cask Registration for Spent Fuel Storage 05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative Rate2024-09-24024 September 2024 Automatic Reactor Trip Due to Prni High Negative Rate IR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter ML24243A0872024-09-20020 September 2024 Response to EPA Comments Regarding the Final Site Specific Supplement to the Generic Eist for License Renewal North Anna Power Station, Units 1 and 2 IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) 05000339/LER-2024-001-01, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24206A0062024-08-0808 August 2024 Notice of Availability of the Final Environmental Impact Statement for the North Anna Nuclear Power Station Unit Numbers 1 and 2 Subsequent License Renewal (Docket Numbers: 50-338 and 50-339) ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24241A0692024-08-0606 August 2024 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant ML24206A0902024-07-24024 July 2024 Owners Activity Report ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24082A2742024-03-22022 March 2024 Request for Approval of Alternative Request N1-I5-NDE-007 to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24086A4682024-03-21021 March 2024 Summary of Facility Changes, Tests and Experiments ML24005A0042024-03-18018 March 2024 Issuance of Amendment Nos. 296 and 279, Regarding Revised Emergency Plan for Relocation of the Technical Support Center 2024-09-24
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative Rate2024-09-24024 September 2024 Automatic Reactor Trip Due to Prni High Negative Rate 05000339/LER-2024-001-01, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 05000339/LER-2016-0012016-09-21021 September 2016 Technical Specification Required Shutdown Due to Reactor Coolant System Leak, LER 16-001-00 for North Anna Power Station, Unit 2 Regarding Technical Specification Required Shutdown Due to Reactor Coolant System Leak 05000338/LER-2016-0032016-06-16016 June 2016 1 OF 3, LER 16-003-00 for North Anna, Unit 1, Regarding Engineered Safety Feature Actuation Due to Loss of Power to "A" Reserve Station Service Transformer 05000338/LER-2016-0022016-05-0505 May 2016 , Chemical Addition System Outside of Technical Specification Due to Excessive Unseating Thrust on MOVs, LER 16-002-00 for North Anna, Unit 1, Regarding Chemical Addition System Outside of Technical Specification Due to Excessive Unseating Thrust on MOVs 05000338/LER-2016-0012016-03-16016 March 2016 1 OF 3, LER 16-001-00 for North Anna, Units 1 and 2, Regarding Emergency Diesel Generators Automatic Start Due to Loss of Power to "C" Reserve Station Service Transformer ML0229604192002-10-11011 October 2002 Ventilation Radiation Monitor System Special Report 2024-09-24
[Table view] |
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by intemet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
1.0 DESCRIPTION OF THE EVENT On January 23, 2016,
- at approximately 1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br />, Switchyard breaker L102 (EIIS System — EA, Component — BKR), supply to 34.5kV bus #3, tripped open from the' Sulfur Hexafluoride (SF6) gas pressure switch. This resulted in the loss of "C" Reserve Station Service Transformer (RSST) (EIIS System — EA, Component — XFMR) which supplies "F" transfer and 2G intake structure 4160VAC buses (EIIS System — EB, circulating water, pumps to continue to run being supplied by Unit 1. The "F" transfer bus supplies the 1H and 2J emergency buses (EIIS System — EK, Component — BU).
Their associated Emergency Diesel Generators (EDG) (EIIS System —EK, Component — DG) started and loaded to recover those buses. The 1H bus.was swapped to its alternate supply from 1B station service and the 1H EDG was shutdown and returned to auto standby. Limiting actions on Unit 1 were cleared at that time. The 2J EDG continued to carry the 2J bus. At 1948 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.41214e-4 months <br /> on January 23, 2016, an 8-hour Non- Emergency Report was made to the NRC in accordance with 10 CFR 50.72(b)(3)(iv)(A) .as a condition that resulted in valid actuation of ESF.
As a result of the event, the Unit 2 Moisture Separator Reheater (MSR) flow control valves (FCVs) (EIIS System — SB, Component — FCV) went closed and reactor power reduced to approximately 96 percent. In addition, the Unit 1 "B" Charging pump (EIIS System — CB, Component — P) auto-started due to the under-voltage condition on the 1H bus. The pump was secured and returned to auto at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> on January 23, 2016. The MSR FCVs were reopened at 0332 hours0.00384 days <br />0.0922 hours <br />5.489418e-4 weeks <br />1.26326e-4 months <br /> on January 24, 2016. At 1528 hours0.0177 days <br />0.424 hours <br />0.00253 weeks <br />5.81404e-4 months <br /> on January 24, 2016, the "C" RSST was energized and normal power restored to the 2J Emergency bus. The 2J EDG was secured at 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br />. Repairs to breaker L102 were completed and the Unit 2 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limiting action was exited at 1706 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.49133e-4 months <br /> on January 24, 2016.
2.0 SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS Units 1 and 2 continued to operate, as designed, following the loss of offsite power. No significant safety consequences resulted from this event because the 1H and 2J EDGs powered the emergency busses, as designed. Offsite power sources were restored in a timely manner and the associated EDGs were secured and returned to automatic. The health and safety of the public were not affected by this event.
3.0 CAUSE The direct cause for the opening of the L102 breaker was an internal switch contact.
failure due to moisture. Snow/moisture intrusion inside the cabinet likely shorted across the electrical terminals for the SF6 gas pressure switch (63G) and caused the 63X relay to pick up, which tripped and locked out the breaker.
The SF6 pressure switch vendor was unable to find anything wrong with the calibration of the switch. Subject matter experts (SME) within the company along with the breaker manufacturer were also unable to find anything physically wrong, with the switch.
4.0 IMMEDIATE CORRECTIVE ACTION(S) The L102 SF6 gas pressure switch was replaced and the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limiting action for Unit 2 was exited.
5.0 ADDITIONAL CORRECTIVE ACTIONS In accordance with the manufacturer's and Dominion SME recommendations, all 34.5KV breakers in the North Anna switchyard have had weather sealant applied to prevent moisture intrusion (rain/snow) where air gaps were noted to be around the conduit access plate and the mechanism access plate .at the bottom of the breaker cabinet which .are the most likely intrusion areas. Additionally the L102 and .L202 breakers had weather sealant applied to the area where the breaker cabinet top meets the breaker cabinet side walls along the front and two sides.
6.0 ACTIONS TO PREVENT RECURRENCE The preventive maintenance procedure is being revised to include an additional check for snow and moisture intrusion paths into cabinets and seal as appropriate for the breakers in question. Monitoring of all the 34.5KV breakers for moisture intrusion will occur to determine if additional actions to seal the breakers are required for the remaining. nine (9) breakers. Inspections of the sealant will also be performed to ensure it remains intact. The monitoring period will be for approximately one year to allow the breakers to be exposed to all seasonal conditions.
7.0 SIMILAR EVENTS None 8.0 ADDITIONAL INFORMATION Component: 63G pressure switch Manufacturer Solon Model 6TC Bulb type
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05000339/LER-2016-001 | Technical Specification Required Shutdown Due to Reactor Coolant System Leak LER 16-001-00 for North Anna Power Station, Unit 2 Regarding Technical Specification Required Shutdown Due to Reactor Coolant System Leak | | 05000338/LER-2016-001 | 1 OF 3 LER 16-001-00 for North Anna, Units 1 and 2, Regarding Emergency Diesel Generators Automatic Start Due to Loss of Power to "C" Reserve Station Service Transformer | | 05000338/LER-2016-002 | , Chemical Addition System Outside of Technical Specification Due to Excessive Unseating Thrust on MOVs LER 16-002-00 for North Anna, Unit 1, Regarding Chemical Addition System Outside of Technical Specification Due to Excessive Unseating Thrust on MOVs | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000338/LER-2016-003 | 1 OF 3 LER 16-003-00 for North Anna, Unit 1, Regarding Engineered Safety Feature Actuation Due to Loss of Power to "A" Reserve Station Service Transformer | |
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