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Category:Letter
MONTHYEARML24302A2402024-10-28028 October 2024 CFR 21 Report 1-BY-BC-1-LV Battery Charger IR 05000338/20240032024-10-28028 October 2024 – Integrated Inspection Report 05000338-2024003 and 05000339-2024003 ML24302A2342024-10-23023 October 2024 Request for Project Number Related to Dominion Energy Services New Nuclear Program at North Anna Power Station ML24283A0392024-10-0909 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 ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc 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) ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma 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 05000338/LER-2024-001, Automatic Reactor Trip Due to PRNI High Negative Rate2024-07-25025 July 2024 Automatic Reactor Trip Due to PRNI High Negative Rate 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 05000339/LER-2024-001, Loss of Generator Field for 2J EDG During 2-PT-82.282024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 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 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 05000338/LER-2024-001, Automatic Reactor Trip Due to PRNI High Negative Rate2024-07-25025 July 2024 Automatic Reactor Trip Due to PRNI High Negative Rate ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 05000339/LER-2024-001, Loss of Generator Field for 2J EDG During 2-PT-82.282024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 05000339/LER-2023-001, Reactor Coolant Pressure Boundary Leak Due to Poor Weld Workmanship2023-11-30030 November 2023 Reactor Coolant Pressure Boundary Leak Due to Poor Weld Workmanship 05000338/LER-2022-001-01, Automatic Reactor Trip During Control Rod Operability Testing2022-09-0606 September 2022 Automatic Reactor Trip During Control Rod Operability Testing 05000338/LER-2022-001, Automatic Reactor Trip During Control Rod Operability Testing2022-06-0707 June 2022 Automatic Reactor Trip During Control Rod Operability Testing 05000338/LER-2021-002, Unanalyzed Condition Due to App R Concerns with Cable Separation2021-09-17017 September 2021 Unanalyzed Condition Due to App R Concerns with Cable Separation 05000338/LER-2021-001, Manual Reactor Trip on Degrading Condenser Vacuum Due to Piping Failure2021-07-0101 July 2021 Manual Reactor Trip on Degrading Condenser Vacuum Due to Piping Failure 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] |
LER-2024-001, Loss of Generator Field for 2J Eog During 2-PT-82.28 |
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10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 10CFR50.73 Vir:ginia Electric and Power Company North Anna Power Station 1022 Haley Drive Mineral, Virginia 23117 August 20, 2024 Attention: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Dear Sir or Madam:
Serial No.:
24-210A NAPS:
RAP Docket Nos.: 50-339 License Nos.: NPF-7 Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to North Anna Power Station Unit 2.
Report No. 50-339/2024-001-01 This report has been reviewed by the Facility Safety Review Committee and will be forwarded to the Management Safety Review Committee for its review.
Sincerely,
/4~ adtr--
Lisa Hilbert Site Vice President North Anna Power Station Enclosure Commitments contained in this letter: None cc:
United States Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station
Abstract
On April 18, 2024, at 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> with Unit 2 in Mode 1, 100% power, during the performance of 2-PT-82.28,
,, 2J Diesel Generator Test (Simulated Loss of Off-Site Power)" the electrical generator failed to flash the field which resulted in a no voltage condition. The engine operated at rated speed of 900 RPM/ 60 Hz with a local room annunciator " Loss of Field Flash" locked in alarm. The 2J EOG was subsequently shut down and placed in quarantine in support of failure investigation.
Investigation into the issue identified the voltage regulator control system K1 M relay was found in the closed position. This condition would result in a loss of field flash or prevention of field flash of the electrical generator and subsequently no generator voltage output. This event is reportable per 10 CFR 50.73(a)(2)(i)(B) as a Condition Prohibited by Technical Specifications.
l The direct cause of this event is foreign material within the K1 M preventing proper operation. The health and safety of the public were not affected by this event. ---
. 1.0 Description of Event
- 2. DOCKET NUMBER
- 3. LER NUMBER I
00339 NUMBER NO.
I YEAR SEQUENTIAL REV J~~~ ~ 1 001 1 ~ ~
On April 18, 2024, at 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> with Unit 2 in Mode 1, 100% power, during the performance of 2-PT-82.28, " 2J Diesel Generator Test (Simulated Loss of Off-Site Power)" the electrical generator (El IS System EK, Component GEl\\l) failed to
!flash the field which resulted in a no voltage condition. The engine operated at rated speed of 900 RPM/ 60 Hz with a local room annunciator" Loss of Field Flash" locked in alarm. The 2J Emergency Diesel Generator (EOG) (EIIS System EK, Component DG) was subsequently shut down and placed in quarantine in support of failure investigation. Investigation into the issue identified the voltage regulator control system Ki M relay was found in the closed position. This condition would result in a loss of field flash or prevention of field flash of the electrical generator and subsequently no generator voltage output. This event is reportable per 10 CFR 50. 73(a)(2)(i)(B) as a Condition Prohibited by Technical Specifications. During the fault exposure period for the 2J EOG, the 2H EOG was inoperable on two occasions for a total of 4.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. However, the 2H EOG was still available to perform its design function during those periods of time.
NOTE: The K1 relay (EIIS Component 53) is comprised of two separate components, Ki R is the generator field flash relay which is mechanically connected (clipped on) to the K1 M portion which is the electrical coil and field shutdown portion. The K1 R provides the latching mechanism which holds the K1 M in the " picked up" position when coil power is removed from K1 M. Both components together are referred to as K1.
2.0 Significant Safety Consequences and Implications No significant safety consequences resulted from this event. The health and safety of the public were not affected by this event.
3.0 Cause of the Event The direct cause of this event is foreign material within the K1 M preventing proper operation. There are two postulated causes for FM entry into the relay. The first scenario would be the potential for a small piece of plastic wrapping material to have been introduced during the wrapping and boxing / packaging process by the relay vendor. In the second scenario, it is postulated that during the unpackaging of the K1 Rand K1 M relay components, a small piece of clear plastic FM either tore off during unpackaging or a small piece entered the relay. The K1 relay was installed 2 years ago. As described above, the K1 relay is comprised of two separate components and K1 R is designed to slide on top of the K1 M relay clipping into place.
, It appears that the foreign material, which resembles a piece of clear plastic, was inside the relay since its installation. While he source of the foreign material cannot be definitively proven, as it is possible for the FM to have entered the relay during che manufacture process, packaging, unwrapping, or site assembly. The material would have been in a location internal of he relay not visible to site electrical maintenance performing site assembly and installation. Over the past two years, the K1 R relay has functioned as intended with total of 24 successful tests. However, during testing on April 18th, 2024, the presence of the plastic foreign material caused it to bind, preventing the contacts from changing state as designed. This
' malfunction resulted in the EOG failing to produce any output voltage because of the absence of flashing the field.
4.0 Immediate Corrective Action I
- 2. DOCKET NUMBER
- 3. LER NUMBER 00339 I YEAR SEQUENTIAL REV I\\IUI\\/IBER NO.
~ ~
Upon removal of the foreign material, the relay was mechanically cycled noting no abnormal conditions or binding. The K'I relay was then functionally tested (electrically energized and deenergized) by engineering noting proper operation with no abnormal conditions confirming the foreign material was the cause for relay failure.
I 5.0 Additional Corrective Actions Work orders were created to inspect the K1 relays for ail EDGs for foreign material and to functionally test each K1 r*elay.
These work orders have been completed and no foreign material was found in the other K1 relays.
16.0 Actions to Prevent Recurrence t
Revise 0-EPM-0702-04 " Inspection of EOG ' K' Relays and Contacts" to inspect the interior of the relay to identify any
- oreign materials or unusual particles that do not belong. Use a light source to illuminate the interior for enhanced visibility.
Utilize a can of compressed air and position the nozzle at a safe distance to avoid damage to relay components. Apply 1short bursts of air to dislodge and remove any potential debris. In addition to the above steps include an Independent Verification (IV) step to verify the absence of foreign materials inside the relay.
7.0 Similar Events No similar events have been noted at North Anna.
8.0 Additional Information The health and safety of the public were not affected by this event. Page 3
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