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Category:Inspection Report
MONTHYEARIR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 IR 05000369/20220032022-10-27027 October 2022 Integrated Inspection Report 05000369/2022003 and 05000370/2022003 IR 05000369/20220112022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000369/2022011 and 05000370/2022011 IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 IR 05000369/20220052022-08-29029 August 2022 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 NRC Inspection Report 05000369/2022005 and 05000370/2022005 IR 05000369/20220022022-07-26026 July 2022 Integrated Inspection Report 05000369/2022002 and 05000370/2022002 IR 05000369/20224012022-05-12012 May 2022 Cyber Security Inspection Report 05000369/2022401 and 05000370/2022401 IR 05000369/20220012022-04-23023 April 2022 Integrated Inspection Report 05000369/2022001 and 05000370/2022001 RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System IR 05000369/20224022022-03-24024 March 2022 Security Baseline Inspection Report 05000369/2022402 and 05000370/2022402 IR 05000369/20210062022-03-0202 March 2022 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 (Report 05000369/2021006 and 05000370/2021006) IR 05000369/20220102022-02-16016 February 2022 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000369/2022010 and 05000370/2022010 IR 05000369/20210042022-01-26026 January 2022 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2021004 and 05000370/2021004 ML21342A3862021-12-0707 December 2021 William B. McGuire Nuclear Plant - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection (NRC Inspection Report 05000369/2022401 and 05000370/2022401) IR 05000369/20210032021-10-28028 October 2021 Integrated Inspection Report 05000369/2021003 and 05000370/2021003 IR 05000369/20210052021-08-23023 August 2021 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000369/2021005 and 05000370/2021005) IR 05000369/20210022021-08-0303 August 2021 Integrated Inspection Report 05000369/2021002 and 05000370/2021002 IR 05000369/20214012021-07-30030 July 2021 Security Baseline Inspection Report 05000369/2021401 and 05000370/2021401 IR 05000369/20210112021-05-20020 May 2021 Triennial Fire Protection Inspection Report 05000369/2021011 and 05000370/2021011 IR 05000369/20214022021-05-20020 May 2021 Security Baseline Target Set Inspection Report 05000369/2021402 and 05000370/2021402 IR 05000369/20210012021-04-30030 April 2021 Integrated Inspection Report 05000369/2021001 and 05000370/2021001 IR 07200038/20210012021-04-30030 April 2021 Construction of an Independent Spent Fuel Storage Installation Report 07200038/2021001 IR 05000369/20210102021-03-17017 March 2021 Design Basis Assurance Inspection Teams Inspection Report 05000369 2021010 and 05000370/2021010 IR 05000369/20200062021-03-0303 March 2021 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2020006 and 05000370/2020006 IR 05000369/20203022021-02-26026 February 2021 Reissue - William B. McGuire, NRC Retake Written Examination Report 05000369/2020302 and 05000370/2020302 IR 05000369/20200042021-01-26026 January 2021 Integrated Inspection Report 05000369/2020004, 05000370/2020004, and 07200038/2020002 IR 05000369/20204012020-12-17017 December 2020 Material Control and Accounting Program Inspection Report 05000369/2020401 and 05000370/2020401 (OUO Removed) IR 05000369/20204022020-11-19019 November 2020 William B. Mcguire Nuclear Station, Units 1 and 2 Security Baseline Inspection Report 05000369/2020402 and 05000370/2020402 IR 05000369/20200032020-11-0404 November 2020 Integrated Inspection Report 05000369/2020003, 05000370/2020003, and 07200038/2020001 IR 05000369/20200102020-10-27027 October 2020 Design Basis Assurance Inspection Report 05000369/2020010 and 05000370/2020010 IR 05000369/20200112020-09-18018 September 2020 Biennial Problem Identification and Resolution Inspection Report 05000369/2020011 and 05000370/2020011 IR 05000369/20200052020-08-17017 August 2020 Updated Inspection Plan for Mcguire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2020005 and 05000370/2020005) IR 05000369/20200122020-07-31031 July 2020 NRC Post-Approval Site Inspection for License Renewal, Inspection Report 05000369/2020012 and 05000370/2020012 IR 05000369/20200022020-07-29029 July 2020 Integrated Inspection Report 05000369/2020002 and 05000370/2020002 IR 05000369/20200012020-04-28028 April 2020 Integrated Inspection Report 05000369/2020001 and 05000370/2020001 IR 05000369/20203012020-04-24024 April 2020 William B. McGuire Nuclear Station NRC Examination Report 05000369/2020301 and 05000370/2020301 2024-01-31
[Table view] Category:Letter
MONTHYEARIR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 ML22340A6662022-12-0808 December 2022 Summary of November 30, 2022, Public Meeting with Duke Energy Carolinas, LLC for McGuire Nuclear Station, Units 1 & 2 Proposed LAR to Adopt TSTF-505, Rev. 2 and 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000369/20220032022-10-27027 October 2022 Integrated Inspection Report 05000369/2022003 and 05000370/2022003 IR 05000369/20220112022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000369/2022011 and 05000370/2022011 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 ML22230B6132022-09-0101 September 2022 Review of the Draft Environmental Assessment and Finding of No Significant Impact for Brunswick Steam Electric Plant and McGuire Nuclear Station Independent Spent Fuel Storage Installations Decommissioning Funding Plans IR 05000369/20220052022-08-29029 August 2022 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 NRC Inspection Report 05000369/2022005 and 05000370/2022005 IR 05000369/20220022022-07-26026 July 2022 Integrated Inspection Report 05000369/2022002 and 05000370/2022002 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3112022-05-16016 May 2022 Letter Issuing Exemption to McGuire IR 05000369/20224012022-05-12012 May 2022 Cyber Security Inspection Report 05000369/2022401 and 05000370/2022401 2024-01-31
[Table view] |
Inspection Report - McGuire - 2020010 |
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Text
October 27, 2020
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 & 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000369/2020010 AND 05000370/2020010
Dear Mr. Ray:
On September 14, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station, Units 1 & 2. On October 5, 2020, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000369 and 05000370 License Nos. NPF-17 and NPF-9
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000369 and 05000370 License Numbers: NPF-9 and NPF-17 Report Numbers: 05000369/2020010 and 05000370/2020010 Enterprise Identifier: I-2020-010-0041 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station, Units 1 & 2 Location: Huntersville, NC Inspection Dates: June 22, 2020 to September 14, 2020 Inspectors: P. Braxton, Reactor Inspector N. Morgan, Reactor Inspector G. Ottenberg, Senior Reactor Inspector Approved By: James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at McGuire Nuclear Station, Units 1 & 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)
Main article: IP 71111.21
The inspectors:
a. Evaluated whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.
b. Evaluated whether the sampled POVs are capable of performing their design-basis functions.
c. Evaluated whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.
d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) 1NI-10B, Unit 1 NV Pumps to NC Cold Legs
- (2) 2KC-56A, 2A ND Heat Exchanger KC Inlet Isolation
- (3) 2NI-184B, 2B ND Pump Suction from Containment Sump
- (4) 1SA-49AB, 1B Steam Generator SM Supply to Unit 1 Turbine Driven CA
- (5) 1CA-54AC, Unit 1 Turbine Driven CA Pump Discharge to 1B Steam Generator
- (6) 1SASV-0490, 0491, 0492, SOVs associated with 1SA-49AB, 1B Steam Generator SM Supply to Unit 1 Turbine Driven CA
- (7) 2NC-31B, Unit 2 Pressurizer Power Operated Relief Valve Block Valve
- (8) 2NC-32B, Unit 2 Pressurizer Power Operated Relief Valve
- (9) 1NS-1B, Unit 1 Containment Sump Block Valve
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 5, 2020, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. Tom Ray, Site Vice President and other members of the licensee staff.
- On July 9, 2020, the inspectors presented the pre-walkdown completion inspection results to Mr. Tom Ray, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.21N.02 Calculations Maximum MCC-1223.13-00-0015 Rev. 9
Expected DPs of
NS EMO Valves,
Reference NC
GL89-10
MCC 1205.19-00- GL 89-10 Verification for MOV Grou12 K Borg Warner 3" Rev. 9
0035 1528 Lb. Class Gate Valve
MCC 1205.19-00- GL 89-10 Verification for MOV Group N, Aloyco Flex Rev. 8
0040 Wedge 8", 12", 14" Gate Valve
MCC 1223.03-00- NC AOV Max. and Mm. Line pressures for Valves 2NC- Rev. 1
0050 56B, 1/2 NC-3213, 34A, and 36B
MCC-1205.06-00- AOV Capability Evaluation for 1 (2)NC0032, 0034, 0036 Rev. 5
0015
MCC-1205.06-00- AOV Capability Evaluation for 1(2) SA0048 & SA0049 Rev. 5
23
MCC-1205.19-00- Electric Motor Operator Sizing Guidelines Per GL89-10 Revs. 50
0003 for Gate Valves and 52
MCC-1205.19-00- GL89-10 BUTTERFLY VALVE ELECTRIC MOTOR Rev. 29
0012 OPERATOR SIZING GUIDELINES PER
MCC-1205.19-00- GL 89-10 Design Verification for 16" Class 150 Henry Rev. 4
25 Pratt Electric Motor Operated Butterfly Valves (Group F)
MCC-1205.19-00- GL 89-10 Verification for MOV Group L Walworth 18" 300 Rev. 5
0036 lb. Gate Valve
MCC-1205.19-00- GL 89-10 Verification for MOV Group T, BWIP 4" Flex Rev. 3
0064 Wedge 1500lb Gate Valve
MCC-1223.03-00- Data Sheets for EMO Valves per GL 89-10, NC System Rev. 5
28
MCC-1223.12-00- Maximum Expected Delta P's of NI EMO Valves Rev. 12
0017
MCC-1223.23-00- Design Parameters for KC System GL 89-10 EMO Valves Rev. 10
0009
MCC-1223.42-00- Documentation of CA Valve Design Basis and GL 89-10 Rev. 16
Inspection Type Designation Description or Title Revision or
Procedure Date
26 Response
MCC-1223.43-02- Air Operated Valve ( AOV) Design Basis for the SA Rev. 0
004 System
MCC-1381.05-00- U1, 6.9KV, 4.16KV & 600V Auxiliary Power Systems Rev. 6
258 Safety-Related Voltage Analysis
MCC-1552.08-00- FWST Level Setpoints (PIP 0-M97-0045) Rev. 11
0118
MCM 1205.06- Air Operated Valve (AOV) Test Data Sheets For Unit 1 & Rev. 17
0510.001 2
MCM-1205.00- Design, Seismic and Weak Link Analysis Rev. 1
273
Corrective Action NCR 2075393 M2R24 Deferral of NA2 Actuator Replacements dated
Documents 11/02/2016
NCR 2113546 EC Suspensions due to Feb 2016 budget summit results dated
04/02/2017
NCR 2266948 Editorial Chg for MCC-1205.19-00-0003 Act Model No dated
1NI0010B 04/05/2019
NCR 2284057 2KCVA0056 ACTUATOR OIL LEAK dated
07/29/2019
Corrective Action NCR 2337190 During 2020 NRC DBAI-POV Inspection Records dated
Documents Deficiency 06/29/2020
Resulting from NCR 2337753 2020 DBAI NRC POV inspection-GL 89-10 program dated
Inspection documentation 07/01/2020
NCR 2338289 2020 NRC DBAI POV inspection-UFSAR 6.3.2.11 dated
discussion 07/07/2020
NCR 2338677 2020 NRC DBAI POV inspection-2KC0056A torque value dated
used 07/09/2020
Drawings MCEE-0147- Auxiliary Feedwater System Selector Station Control Rev. 2
2.00 Circuit
MCEE-0147- Unit 1 Feedwater System AFWPT Isolation Valve Rev. 3
25.00 1CA0054A
MCEE-0242- Elementary Diagram Component Cooling System ND HX Rev. 3
00.09 2A Auto Supply Valve 2KC0056A
Inspection Type Designation Description or Title Revision or
Procedure Date
MCEE-151-00.06 ELEMENTARY DIAGRAM BIT DISCHARGE ISOLATION Rev. 10
VALVE 1NI10B
MCEE-159-00.04 E/D NS PMP 1B SUCT FROM C ONTAIN SUMP BLOCK Rev. 10
1NS1B
MCEE-250-00.02 Reactor Coolant (NC) Pressurized Power Operated Rev. 14
Safety Relief Valve 2NC32B
MCEE-250-00.05 Pzr. No. 2 Power Operated Safety Relief Isolation Vlv. Rev. 10
2NC31B
MCEE-251-00.65 E/D SAFETY INJ SYS (NI) CONTAINMENT SUMP LINE Rev. 11
2B ISOL 2NI184B
MCFD-1592- Flow Diagram of Auxiliary Feedwater System (CA) Rev. 9
01.00
MCFD-1593- Flow Diagram of Main Steam Supply to Auxiliary Rev. 12
01.02 Equipment System ( SA) Turbine Exhaust System ( TE)
MCID 1499- Instrumentation Detail Steam to Auxiliary FWPT Rev. 4
SA.02
MCM 1205.00- 12" EMO GATE VALVE ITEM 4D-011 Rev. 1
0045.001
MCM 1205.00- Valve Assembly, Gate - 3 Inch, 1528 lb., CRES, with Rev. F
0478.001 Motor Oper., Sched. 160
MCM 1205.09- dated
0009.001 10/28/1975
MCM 1205.09- dated
25.001 05/16/2001
MCM 1210.04- Valve Solenoid 3 Way ( AC or DC) Rev. 00G
0365.001
MCM-1205.00- 18" 300 LB MO GATE VALVE ITEM NO.0 4D-005, 04D- Rev. 8
20.001 250 & 04D-257
MCM-1205.00- 4"-1500 Weld Ends Stainless Steel Flex Wedge Gate Rev. F
266.001 Valve with Rotork 40NA1E-57 Actuator, Smart Stem,
Leakoff, Vent, Hardfaced Disc Guides and Disc Slots
MCM-1205.02- MOTOR OPERATED BUTTERFLY VALVES, KC Rev. 10
0140.001 SYSTEM
MCM1205.37- 1SA-49AB Valve Drawing Rev. 7
Inspection Type Designation Description or Title Revision or
Procedure Date
28.001
MCTC-1562- McGuire Nuclear Station, Units 1 & 2 Design Criteria, Rev. 6
NI.V001-01 Operability Requirements and Compensatory Measures,
Testing and Acceptance Criteria Isolation Valves 1/2NI-
9A, -10B
Engineering Static Test Analysis of 1NI0010 dated
Evaluations 03/03/2020
Static Test Analysis for 2KC0056 dated
10/01/2015
Static Test Analysis of 2NI0184 dated
04/11/2017
MCC-1205.19-00- GL 95-07 Pressure Locking and Thermal Binding Rev. 9
0052 Evaluation
MCC-1205.19-00- JOG Classification of McGuire's GL 96-05 MOV Rev. 4
0082 Population
MCM-1205.00- Dynamic Test Program For McGuire Nuclear Station 4" dated
274-002 Flex Wedge Motor Operated Gate Valve 01/13/2000
Miscellaneous McGuire Nuclear Station Fourth Ten-Year Interval Rev. 28
Inservice Testing Program
DC - 18.01 Motor-Operated Valve (MOV) Control and Position Rev. 6
Indication
DPC-1205.19-00- Evaluation of Operator Test Bench Accuracy Rev. 0
0012
DPM-1205.00- NRC Generic Letter 96-05 Program Plan Rev. 1
0009
DPS-1205.00-00- Nuclear Safety Related Carbon and Stainless Steel Rev. 4
0002 Forged and Cast Electric Motor Operated Gate Valves
DPS-1205.19-00- Guideline for Performing Motor Operated Valve Reviews Revs. 4 and
0002 and Calculations 7
EPRI Evaluation Guide for Valve Thrust and Torque dated
3002008055 Requirements 01/24/2018
EPRI TR-104884 Technical Repair Guide for Rotork Valve Actuators "NA" dated
Range Models December
1995
Inspection Type Designation Description or Title Revision or
Procedure Date
MCC 1205.19-00- GL 89-10 Verification for MOV Group s, Atwood & Morrill Rev. 1
0060 4 inch parallel Slide 1500 lb Gate Valve
MCC-1205.19-00- McGuire NRC Generic Letter 89-10 Valve List Rev. 7
0011
MCM 1205.19- Electric Motor Operator GL89-10 Set-up Information Rev. 74
0039.001
MCM 1210.04- Qualification Test Report on V70900-65 Rev. 2
250.001
MCM 1210.04- Operation and Maintenance Manual Solenoid Valve, Rev. D
0336.001 Nuclear Service 3-Way Universal Valcor Model V70900-
65-24
MCM-1205.19- Electric Motor Operator GL 89-10 Set-up Information Rev. 74
0039.001
MCS-1205.37-00- Auxiliary Feedwater Pump Turbine Isolation Valve Rev. 1
0002 Actuators for the Auxiliary Steam Supply (SA) System
MCS-1553.NC- Design Basis Specification for the NC System Rev. 36
00-0001
MCS-1562.NI-00- Design Basis Specification for the NI System Rev. 31
0001
MCS-1563.NS- Design Basis Specification for the NS System Rev. 35
00-0001
MCS-1573.KC- DESIGN BASIS SPECIFICATION FOR THE KC SYSTEM Rev. 28
00-0001
MCS-1593.SA- Design Basis Specification for the SA and TE Systems Rev. 10
00-0001
Procedures AD-EG-ALL-1117 DESIGN ANALYSES AND CALCULATIONS Rev. 7
AD-EG-ALL-1202 PREVENTIVE MAINTENANCE AND SURVEILLANCE Rev. 9
TESTING ADMINISTRATION
AD-EG-ALL-1432 Air Operated Valve Design Basis Review Rev. 1
NC Valve Stroke PT/2/A/4151/005 Rev. 19
Timing Test Using
Air
PD-EG-ALL-1430 Air Operated Valve Program Rev. 2
PT/1/A/4200/009 ENGINEERED SAFETY FEATURES ACTUATION Rev. 18
Inspection Type Designation Description or Title Revision or
Procedure Date
B PERIODIC TEST TRAIN B completed
04/18/2019
PT/1/A/4208/003 NS Train B Valve Stroke Timing - Shutdown Rev. 18
E
PT/2/A/4151/002 NC TRAIN B VALVE STROKE TIMING- QUARTERLY Rev. 30
B
PT/2/A/4151/003 NC Train B Valve Stroke Timing Using Accumulator Rev. 30
B Pressure - Shutdown
PT/2/A/4200/009 Engineered Safety Features Actuation Periodic Test Train Rev. 102
A A completed
06/21/2017
PT/2/A/4200/022 ND SUCTION SWAPOVER TIMING TEST Rev. 36
completed
09/26/2018
PT/2/A/4401/014 Train A KC/ND HX Valve Stroke Timing - Quarterly Rev. 15
A completed
05/29/2020
PT/2/A/4401/014 Train A KC/ND HX Valve Stroke Timing - Quarterly Rev. 15
A completed
2/29/2020
PT/l/A/4206/003 NI Train B Valve Stroke Timing - Shutdown Rev. 33
B completed
04/05/2019
Work Orders 20121091,
20121091-13,
206564,
206564-01,
289635-01,
2037280-07,
20362793-0,
20327584-01,
258365,
20128174,
257961,
Inspection Type Designation Description or Title Revision or
Procedure Date
20362057-01,
293591-01,
2188436-01,
2102350,
211520,
20025918,
20128582,
277050,
295224
11