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Category:Letter
MONTHYEARIR 05000298/20240032024-11-0505 November 2024 Integrated Inspection Report 05000298/2024003 ML24250A2052024-10-0808 October 2024 Issuance of Amendment No. 278 Regarding Revision to Technical Specification Table 3.3.2.1-1 and Transfer of Minimum Critical Power Ratio Values to Core Operating Limit Report ML24227A0822024-09-0303 September 2024 Summary of Regulatory Audit in Support of License Amendment Request to Modify the High Pressure Coolant Injection Low Flow Value IR 05000298/20240052024-08-22022 August 2024 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2024005) IR 05000298/20240022024-07-25025 July 2024 Integrated Inspection Report 05000298/2024002 ML24183A1722024-07-17017 July 2024 Issuance of Amendment No. 277 to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML24197A1462024-07-15015 July 2024 NRC Region IV Ltr to Cooper Nuclear Station Re FEMA Level 1 Finding ML24134A1782024-07-0303 July 2024 Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33 ML24197A0682024-06-24024 June 2024 FEMA Ltr to Missouri State Emergency Management Agency - Level 1 Finding, 24 June 2024 ML24192A0112024-06-13013 June 2024 2024-06-Post Exam Comments 05000298/LER-2023-002-01, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2024-06-0606 June 2024 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications IR 05000298/20244012024-06-0404 June 2024 Security Baseline Inspection Report 05000298/2024401 ML24151A1082024-05-30030 May 2024 NRC Initial Operator Licensing Examination Approval 05000298/2024301 ML24137A0942024-05-17017 May 2024 Regulatory Audit Plan in Support of License Amendment Request to Modify Allowable Value Regarding Technical Specification for High Pressure Coolant Injection Pump Discharge Low Flow 05000298/LER-2024-005, High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical2024-05-13013 May 2024 High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical. 05000298/LER-2024-004, Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications2024-05-0909 May 2024 Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications IR 05000298/20240012024-05-0303 May 2024 Integrated Inspection Report 05000298/2024001 ML24129A0952024-04-25025 April 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000298/20240102024-04-24024 April 2024 Comprehensive Engineering Team Inspection Report 05000298/2024010 05000298/LER-2024-003, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications2024-04-22022 April 2024 High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) ML24093A2282024-04-0202 April 2024 Notice of Enforcement Discretion for Cooper Nuclear Station IR 05000298/20240902024-04-0101 April 2024 – Notice of Violation, NRC Inspection Report 05000298/2024090 05000298/LER-2024-001, Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications2024-03-0404 March 2024 Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications 05000298/LER-2024-002, Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump2024-03-0404 March 2024 Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump IR 05000298/20230062024-02-28028 February 2024 Annual Assessment Letter for Cooper Nuclear Station - Report 05000298/2023006 IR 05000298/20230042024-02-12012 February 2024 Integrated Inspection Report 05000298/2023004 ML24033A3092024-02-12012 February 2024 Summary of Regulatory Audit Regarding the Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20230122024-02-12012 February 2024 NRC Inspection Report 05000298/2023012 ML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements 05000298/LER-2023-002, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2023-12-20020 December 2023 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23311A1122023-11-0909 November 2023 Project Manager Assignment IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20243012023-09-0101 September 2023 Notification of NRC Initial Operator Licensing Examination 05000298/2024301 IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 05000298/LER-2022-002-01, Manual Core Spray Injection to Restore Skimmer Surge Tank Level2023-06-29029 June 2023 Manual Core Spray Injection to Restore Skimmer Surge Tank Level ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 05000298/LER-2022-004-01, 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open2023-05-11011 May 2023 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open 05000298/LER-2023-001, Valve Test Failures Result in Condition Prohibited by Technical Specifications2023-05-0808 May 2023 Valve Test Failures Result in Condition Prohibited by Technical Specifications IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report 2024-09-03
[Table view] Category:Deficiency Report (per 10CFR50.55e and Part 21)
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- MPR ASSOCIATES INC, ENGINEERS January 9, 2013 RPT-0315-0062-2109 Revision 0 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Interim Report in Accordance with 10 CFR Part 21
Dear Sir or Madam:
MPR Associates (MPR) is investigating the failure of a replacement emergency diesel generator excitation system that MPR supplied to Cooper Nuclear Station. The root cause investigation is still in-process and will not be completed within 60 days of discovery as defined by 10 CFR Part 21.
The attached 10 CFR Part 21 Interim Report provides the information known at this time. An updated report will be provided once the root cause investigation is completed.
If you have any questions, please contact the undersigned.
Sincerely, Paul S. Damerell Principal Officer Attachment 320 KING STREET ALEXANDRIA, VA 22314-3230 703-519-0200 FAX: 703-519-0224 hftp://www.mpr.com
ASSOCIATES INC.
ENGINEERS Attachment to MPR Letter dated January 9, 2013 RT-0315-0062-2109 Revision 0 10 CFR Part 21 Interim Report on Replacement EDG Excitation System Failure at Cooper Nuclear Station Listed below is the information as known at the time of this interim report. Updated information will be provided once thie root cz;use investigation "s completed. The root cause investigation is scheduled for completion by March 29, 2013.
- 1. Reporting Individual Paul Damerell, Principal Officer MPR Associates, Inc.
320 King Street Alexandria, VA 22314
- 2. Identification of the Basic Compo~en-. that Failed The basic component is a Basler Electric SBSR emergency diesel generator (EDG) excitation system that was supplied as a replacement system to Cooper Nuclear Station (CNS).
The replacement system included design changes relative to the original CNS excitation system, which is also a Basler Electric SBSR design. The design changes included larger magnetic components, which were intended to allow for continuous operation of the new exciter at the EDG overload rating.
- 3. Identification of the Supplier The excitation system was supplied by MPR Associates (headquarters in Alexandria, VA).
Basler Electric (headquarters in Highland, IL) designed and fabricated the system under a commercial grade program certified to ISO 9001:2008. MPR Associates dedicated the commercial grade item for nuclear use under the MPR Nuclear QA Program, which complies with 10 CFR 50 Appendix B (Reference 1) and ASME NQA-l (Reference 2).
. I
- 4. Nature of the Failure CNS installed the replacement excitation system in the Division 1 EDG system during refueling outage RE27. Prior ta declaring the EDG operable, CNS manually terminated an EDG maintenance run due to erratic EDG reactive power indication, which was followed by a sudden drop of EDG reactive load and an indication of negative reactive power.
Several rounds of troubleshooting and surveillance testing were performed unsuccessfully. The surveillance testing resulted in faults to ground and overheating and failure of components in the excitation system. Some of the failed equipment included the automatic voltage regulator (AVR), manual voltage control autotransformer (T60), rectifier power diode failure indication resistors and light-emitting diodes (LEDs), insulation on the control windings of two saturable transformers, and elements of the data acquisition equipment used to record data during the testing.
The root cause of the failure has not yet been determined. However, on-s.te troubleshooting efforts at CNS by MPR and Basler Electric identi-fed unexpecteG high voltages across the direct current (DC) control winding of the saturable transformers. These voltages are likely the cause of the failures experienced in-situ at CNS.
Follow-up tests at Basler Electric on a similar replacement systenr, designed for the Hatch Plant (but not yet installed in the plant) also identified higher than expected voltages across the DC control windings of the saturable transformers. MPR and Basler Electric recommended postponement of the Hatch Plant installation until the impact of this condition (i.e., the higher than expected voltages) is evaluated. Note that the test.ing on '-Mp Hatch replacement system to date did not result in failure of the system or abnormal functic- of components external to the saturable transformers.
- 5. Date of the Failure Testing of the replacement excitation system began on October 27, 2012. The maintenance run resulting in erratic EDG reactive power indication was performed on October 30, 2012. CNS, MPR, and Basler Electric discontinued troubleshooting efforts for the replacement excitation system on November 9, 2012.
The replacement system was removed, and the original B.l,;e.r Electric SBSR excitation system was re-installed. CNS declared the re-installed system operable on November 14, 2012.
MPR formally documented the issue in the MPR corrective action program on November 13, 2012.
- 6. Number and Location of the Affected 3asic Components Based on the information known to date, this 10 CFR Part 21 Interim Report affects the following SBSR type excitation systems that were dedicated and supplied by MPR.
Nuclear P!ant Date Equipment Provided Items Supplied Cooper Nuclear 2012 1 system (failed during installation)
Hatch 2012 5 systems (not yet installed)
- 7. Corrective Action Plan MPR is performing a failure analysis and root cause investigation to determine the extent of the condition, corrective actions, and actions to prevent recurrence. The root cause investigation is scheduled for completion by March 29, 2013.
- 8. Advice Given to Purchasers or Licensees There are numerous Basler Electric SBSR type excitation systems in service at multiple plants throughout the nuclear industry. In addition to CNS and Hatch, MPR has dedicated and supplied SBSR excitation systems to the Beaver Valley, Davis-Besse, and Robinson plants. Each system supplied is custom designed for the generator that it is slated to control. Basler Electric SBSR excitation systems have demonstrated reliable service for many years.
The replacement SBSR excitation system supplied to CNS was not identical to the original system. Specifically, there were design differences in some of the components, including larger transformers, which were intended to allow for continuous operation of the new exciter at the EDG overload rating. Although it was not foreseen (and not revealed by factory acceptance testing), it seems that the design changes in the replacement system led to its maloperation and failure when it was init-.ally installed at CNS. This faulty operation and failure were readily observed as part of normal EDG surveillance testing. Upon re-installation, the original SBSR excitation system functioned properly. Hence, it appears that:
" Differences between the replacement system and original system lead to the problem, and
" The problem is readily detectable in nermal surveillance testing.
For these reasons, SBSR excitation systems ius-'alled at plaxts that have shown reliable operation during surveillance testing are in a satisfactory state and co=adition. LPR has no evidence that the mechanism or conditions that led to the failure at CNS will lead to failures at other installations. Therefore, plants with SBSR excitation systems installed should continue to use them and conduct normal surveillance testing.
- 9. References
- 1. 10 CFR 50 Appen'iix 3, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.
- 2. ASME NQA-1, Quality Assurince Requirements for L;Oer Facility Applications, 2008 Edition with 2009 Addenda.
QA Approval: " , ) Date: January 9, 2013 Michael K. Dunkelberger, QA Manager Final Approval: Date: Tanuary 9, 2013 Paul S. Damerell, Principai di3fice