|
---|
Category:Letter
MONTHYEARIR 05000482/20240142024-12-17017 December 2024 Comprehensive Engineering Team Inspection Report 05000482/2024014 ML24352A0322024-12-17017 December 2024 Notification of Post Approval Site Inspection for License Renewal and Request for Information 05000482/LER-2024-002-01, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-12-11011 December 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve IR 05000482/20244022024-12-0505 December 2024 Security Baseline Inspection Report 05000482/2024402 ML24337A0132024-12-0202 December 2024 Cycle 27 Core Operating Limits Report, Revision 1 ML24306A2192024-11-0101 November 2024 Results of the Steam Generator Tube Inservice Inspection During the 26th Refueling Outage to Reflect TSTF-577 Reporting Requirements IR 05000482/20240032024-11-0101 November 2024 Integrated Inspection Report 05000482/2024003 IR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000482/LER-2024-002-01, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-12-11011 December 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2022-001, Low Steam Generator Level Due to Main Feedwater Valve Failure Caused Reactor Trip2022-09-14014 September 2022 Low Steam Generator Level Due to Main Feedwater Valve Failure Caused Reactor Trip 05000482/LER-2021-004, Low Steam Generator Level Due to Main Feedwater Valve Failure Caused Automatic Reactor Trip2021-10-18018 October 2021 Low Steam Generator Level Due to Main Feedwater Valve Failure Caused Automatic Reactor Trip 05000482/LER-2021-003, Re Automatic Reactor Trip Due to Low Steam Generator Level2021-07-12012 July 2021 Re Automatic Reactor Trip Due to Low Steam Generator Level 05000482/LER-2021-001-01, Re Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications2021-03-17017 March 2021 Re Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications 05000482/LER-2021-001, Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications2021-02-15015 February 2021 Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications 05000482/LER-2020-001-01, Plant Shutdown Due to Inoperable Containment Purge Isolation Valves2020-07-0606 July 2020 Plant Shutdown Due to Inoperable Containment Purge Isolation Valves 05000482/LER-2019-002, Emergency Diesel Generator Inoperable Due to Temperature Control Valve Failure2019-10-14014 October 2019 Emergency Diesel Generator Inoperable Due to Temperature Control Valve Failure 05000482/LER-2019-001, Re Valid Actuation of One of the Emergency Diesel Generators2019-07-18018 July 2019 Re Valid Actuation of One of the Emergency Diesel Generators 05000482/LER-2018-002, Modification Activities Affected Control Room Envelope Boundary Causing a Condition Prohibited by Technical Specifications2019-02-27027 February 2019 Modification Activities Affected Control Room Envelope Boundary Causing a Condition Prohibited by Technical Specifications 05000482/LER-2018-001, Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications2018-10-0404 October 2018 Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications 05000482/LER-2017-0032017-11-0202 November 2017 ARV and MSSV Tornado Missile Vulnerabilities Result in Unanalyzed Condition, LER 17-003-00 for Wolf Creek Generating Station Regarding ARV and MSSV Tornado Missile Vulnerabilities Result in Unanalyzed Condition 05000482/LER-2017-0012017-05-17017 May 2017 Condition Prohibited by Technical Specifications Due to One Train of Component Cooling Water Inoperable, LER 17-001-00 for Wolf Creek Regarding Condition Prohibited by Technical Specifications Due to One Train of Component Cooling Water Inoperable 05000482/LER-2016-0022017-01-16016 January 2017 Loss of Switchyard Bus Results in Emergency Diesel Generator Actuation, LER 16-002-00 for Wolf Creek Generating Station Regarding Loss of Switchyard Bus Results in Emergency Diesel Generator Actuation 2024-07-02
[Table view] |
text
Robert J. Bayer Plant Manager U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 July 18, 2019 WO 19-0027
Subject:
Docket No. 50-482:
Licensee Event Report 2019-001-00, "Loss of Startup Transformer Results in Emergency Diesel Generator Actuation" To Whom It May Concern:
The enclosed Licensee Event Report (LER) 2019-001-00 is being submitted pursuant to 10 CFR 50.73(a)(2)(iv)(A) regarding a valid actuation of one of the emergency diesel generators at Wolf Creek Generating Station.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4015, or Ron Benham at (620) 364-4204.
RJB/rlt
Enclosure:
LER 2019-001-00 cc:
S. A. Morris (NRC), w/e N. O'Keefe (NRC), w/e B. K. Singal (NRC), w/e Senior Resident Inspector (NRC), w/e Sincerely, Robert J. Bayer P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
3.Page Wolf Creek Generating Station 05000 482 1
OF 3
- 4. Title Loss of Startup Transformer Results in Emergency Diesel Generator Actuation
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved I
Sequential I Rev Facility Name Docket Number Month Day Year Year Number No.
Month Day Year 05000 Facility Name Docket Number 05 24 2019 2019 -
001 -
00 07 18 2019 05000
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply)
D 20.2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.2201(d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B) 1 D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. Power Level D 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
D 50. 73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5)
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1) 100 D 20.2203(a)(2)(v)
D 50. 73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
J'.. /.ti};:.;:}... *
.. **. D 50.73(a)(2)(i)(C)
D Other (Specify in Abstract below or in "Hot collar testing" was performed on the transformer bushings to determine if they needed to be replaced. The results indicated that the bushings were acceptable for continued service. Continuity checks were also performed with satisfactory results.
BASIS FOR REPORTABILITY This event is being reported in accordance with 10 CFR 50.73(a)(2)(iv)(A) as an event or condition that resulted in manual or automatic actuation of any of the systems listed in paragraph (a)(2)(iv)(B) of 10 CFR 50.73. For the event that occurred on May 24, 2019, loss of power to the NB002 bus resulted in an undervoltage condition and subsequent automatic actuation of the "B" emergency diesel generator. In addition, an auxiliary feedwater actuation signal was generated which resulted in the starting of the "B" motor driven auxiliary feedwater pump.
CAUSE
The most probable cause of the startup transformer failure is that the presence of bird activity caused an initial short, either phase to phase, or phase to ground. This initial fault caused the loss of one phase. This caused an increased potential on the other two phases. The increased potential requires the presence of an even larger air gap to keep arcing from occurring. In addition, immediately following the initial fault, there was plasma material remaining in the air. These caused further faults which resulted in the loss of all three phases of the startup transformer.
CORRECTIVE ACTIONS
All of the rodent covers were re-installed taking care to limit the size as much as possible on any openings. Additional corrective actions currently being considered include installing auto foggers in the transformer yard and switchyard to try to reduce the presence of birds around the transformers, and obtaining customized rodent/bird covers that would prevent smaller animals or birds from entering the bushing lug areas.
SAFETY SIGNIFICANCE
The "B" EDG, as well as its associated load sequencer, responded as required. During the time the startup transformer was inoperable, the "B" EDG continued to supply power to the NB002 bus. In addition, the offsite source serving the NB001 bus didn't experience any interruptions. Therefore both trains of Class 1 E power were operable during this event.
Since all safety related equipment operated as designed, the safety significance of this event was low.
OPERATING EXPERIENCE/PREVIOUS EVENTS A review of Wolf Creek LERs for the past three years identified one other occurrence of a loss of one source of offsite power which resulted in an emergency diesel generator actuation (LER 2016-002-00). However, this event was caused by human error related to incorrect wiring terminations being made during maintenance, rather than the presence of wildlife. Page 3
of 3
|
---|
|
|
| | Reporting criterion |
---|
05000482/LER-2019-001, Re Valid Actuation of One of the Emergency Diesel Generators | Re Valid Actuation of One of the Emergency Diesel Generators | 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)(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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000482/LER-2019-002, Emergency Diesel Generator Inoperable Due to Temperature Control Valve Failure | Emergency Diesel Generator Inoperable Due to Temperature Control Valve Failure | 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), 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) |
|