IR 05000369/2020004
| ML21026A254 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/26/2021 |
| From: | Tobin T NRC/RGN-II/DRP/RPB1 |
| To: | Teresa Ray Duke Energy Carolinas |
| References | |
| IR 2020002, IR 2020004 | |
| Download: ML21026A254 (21) | |
Text
January 26, 2021
SUBJECT:
MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2020004, 05000370/2020004, AND 07200038/2020002
Dear Mr. Ray:
On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On January 14, 2021, 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/
Margaret C. Tobin, Acting Chief Reactor Projects Branch 1 Division of Reactor Projects
Docket Nos. 05000369, 05000370, and 07200038 License Nos. NPF-17 and NPF-9
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000369, 05000370, and 07200038
License Numbers:
Report Numbers:
05000369/2020004, 05000370/2020004, and 07200038/2020002
Enterprise Identifier: I-2020-004-0047; I-2020-002-0073
Licensee:
Duke Energy Carolinas, LLC
Facility:
McGuire Nuclear Station
Location:
Huntersville, North Carolina
Inspection Dates:
September 01, 2020 to December 31, 2020
Inspectors:
A. Hutto, Senior Resident Inspector
A. Butcavage, Reactor Inspector
R. Cureton, Resident Inspector
B. Griman, Project Engineer
B. Kellner, Senior Health Physicist
S. Sandal, Senior Risk Analyst
Approved By:
Margaret C. Tobin, Acting Chief
Reactor Projects Branch 1
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at McGuire Nuclear Station, 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.
PLANT STATUS
Unit 1 began the inspection period shutdown for a scheduled refueling outage. The unit was placed on line October 20, 2020 and was returned to 100 percent rated thermal power (RTP) on October 24, 2020. The unit operated at or near 100 percent RTP for the remainder of the inspection period.
Unit 2 operated at or near 100 percent RTP for the entire inspection period.
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 Disease 2019 (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions 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
71111.01 - Adverse Weather Protection
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)1A train of spent fuel pool cooling system (KF), on October 6, 2020 (2)1B train of auxiliary feedwater (CA) system, on November 12, 2020 (3)2A diesel generator (EDG), on December 17, 2020
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the 2B nuclear service water system on November 9, 2020.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Unit 1 and 2 vital battery area, on October 11, 2020
- (2) Turbine building basement instrument air compressor area, on December 21, 2020
- (3) Unit 1 auxiliary building 750' ETA switchgear area, on December 28, 2020
- (4) Unit 2 auxiliary building 733' ETB switchgear area, on December 30, 2020
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an announced live burn training on November 19, 2020.
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (2 Samples)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 1 and 2 diesel generator rooms, on October 19, 2020
- (2) Unit 1and 2 auxiliary building 695 level and component cooling pump areas, on November 3, 2020
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined, and accepted by reviewing the following activities from 9/21/20 to 10/16/20:
03.01.a - Nondestructive Examination and Welding Activities.
- Ultrasonic Examination (UT) of ASME Class 1, Component ID. 1RPV1-446A, Closure Head Meridional Weld, Rpt. No.VE-20-003 (10 Year ISI Sample Review)
- UT, ASME Class 1, Component ID. 1RPV1-446A Reactor Vessel Closure Head Meridional Weld, Rpt. No. VE-20-005 (10 Year ISI Sample Review)
- Enhanced Visual Examination (EVT-1) of Reactor Vessel Core Barrel Upper Flange Weld (MRP-227 Primary Component Sample Review)
- VT-2 of ASME Class 1 Reactor Lower Head Penetrations IAW N722-1 BMI Penetrations, plus Lower Head Surface, and Nozzle Connections
- Work Order (WO) 20424739, Pre-Fab Welds, ASME Class 2, Valve 1-NI-IV-5010 Replacement
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities
- VT -2 of ASME Class 1, Reactor Upper Closure Head IAW N729-4, Penetration Numbers 15, 25, 32, 62, and 75 (Video Review)
- WO 2036630, PM 1NC-RX-59, Perform Lower Canopy Seal Weld Leak Check Inspection (Reviewed)
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
The inspectors evaluated the licensees boric acid corrosion control program performance, through field walk-downs inside containment and review of the boric acid program corrective actions and evaluations of reported leakage as listed in the documents reviewed section. This review included corrective actions planned to address refueling cavity seal leakage presented in CR-1557752.
03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
- No Sg EC Scheduled. Reviewed MNS 1E9C27, Skip Year Justification (Reviewed)
OE Sample: AR -02342522, Evaluation of IG-20-1, CRDM Latch Assembly Stationary Gripper Wear
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) On July 21, 2020, the licensee completed the comprehensive biennial requalification written examinations and the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), Requalification Requirements, of the NRCs Operators Licenses. During the week of December 14, 2020, the inspectors performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, Licensed Operator Requalification Program. These results were compared to the thresholds established in Section 3.02, Requalification Examination Results, of IP 71111.11.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 refueling outage, on October 15, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator refresher training dual unit exercise on November 3, 2020. The training scenario included a Unit 1 steam generator tube leak and rupture concurrent with a Unit 2 loss of the 2A busline and generator runback.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Nuclear Condition Report (NCR) 2354739, Investigate/repair overload on 1WL-39A, on October 25, 2020
- (2) NCR 2349944, 1VB-50 failed penetration test due to excessive leakage, on December 10, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Equipment protection plan for the EVCB vital battery out of service for maintenance and testing, on December 7, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) NCR 2349944, Penetration 1VB-50 failed leak test due to excessive leakage, on October 8, 2020
- (2) NCR 2353723, MSD 585 evaluation for material remaining in lower containment through mode 4, on October 11, 2020
- (3) NCR 2356006, 2D reactor coolant loop flow Channel 1 reading 111 percent, on November 3, 2020
- (5) NCR 2360561, PT/0/A/4150/041," RCCA Bank Reposition," could not be completed due to operator aid computer alarm, on December 8, 2020
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering change (EC) 417467, Permanently bypass containment iodine detector 2EMF40
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) PT/1/A/4200/008 B, "NC Pressure Isolation Valve Leak Test," Enclosure 13.5, "Valve Leak Rate Test for 1NI-60," following 1NI-60 valve repair, on October 19, 2020
- (2) PT/1/A/4400/105, "RCCA Drop Timing Using DRPI System," following M1R27 component shuffle and core reload, on October 19, 2020
- (3) PT/0/A/4150/029, "Initial Approach to Criticality and Zero Power Physics Testing,"
following M1R27 core reload, on October 20, 2020
- (4) PT/1/A/4350/002 A, "Diesel Generator 1A Operability Test," following 1A diesel generator preventive maintenance (PM) on October 27, 2020
- (5) PT/1/A/4502/002 A, "WL Train A Valve Stroke Timing - Quarterly," following actuator replacement for 1WL-39A, on November 13, 2020
- (6) PT/1/A/4401/014 B, "Train B KC/ND HX Valve Stroke Timing - Quarterly," following valve PMs on 1KC-81B, on December 10, 20020
- (7) IP/0/A/3061/012, "Charging Site Lead-Acid Batteries," Enclosure 11.2, "Post Equalize Cell Readings," following performance test and equalize charge of vital battery EVCB, on December 14, 2020
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage M1R27 activities from October 1, 2020 to October 21, 2020.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) PT/1/A/4350/002 A, "1A Diesel Generator Operability Test," on November 24, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) PT/2/A/4252/001 A, "2A CA Pump Performance Test," on December 29, 2020
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) PT/1/A/4200/001 C, "Isolation Valve Leak Rate Test," on October 08, 2020
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the emergency preparedness drill conducted on October 28, 2020. The drill involved a steam generator tube rupture, followed by a failed open main steam relief valve, and loose parts induced fuel failure.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated radiological protection-related instructions to plant workers.
Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) Observed licensee surveys of potentially contaminated material being removed through the Unit 1 equipment hatch during a refueling outage.
- (2) Observed surveys to release material from the RCA during the Unit 1 refueling outage.
- (3) Observed workers exiting the RCA during a Unit 1 refueling outage.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (2) Rx head lift and move to the head stand - RWP #1728
- (3) Rx core barrel lift and placement in the stand in the deep of the cavity - RWP #1384
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Unit 1 incore thimble main access hatch (Grave Danger)
- (2) Unit 1 incore thimble secondary access hatch (Grave Danger)
- (3) Unit 1 transfer tube access hatch (Grave Danger)
- (4) Unit 1 Lower Containment personnel hatch (High Radiation Area)
- (5) Unit 1 Containment fuel transfer tube temporary fencing (LHRA)
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1 (October 1, 2019 through September 30, 2020)
- (2) Unit 2 (October 1, 2019 through September 30, 2020)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (October 1, 2019 through September 30, 2020)
- (2) Unit 2 (October 1, 2019 through September 30, 2020)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 1, 2019 through June 30, 2020
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in human performance that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) NCR 2334437, Internal flood barrier service life
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
2515/194 - Inspection of the Licensees Implementation of Industry Initiative Associated With the Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012-01)
Revision 0 of this TI was previously inspected, and closed, in Inspection Report 2019011 (ADAMS ML19330D480). However, a subsequent revision to the NEI Voluntary Initiative (Revision 3) provided plants the option of to leave the open phase protection (OPP) system in monitoring mode only in lieu of activating the automatic trip circuitry, provided it was supported by a risk evaluation. Revision 1 (and later Revision 2) of this TI was issued to provide inspection guidance for the new option.
The inspectors reviewed licensee analyses and procedures that demonstrated operator manual actions would successfully mitigate the impact of an open phase condition (OPC). The analyses were reviewed remotely, and the procedures were reviewed and walked down on site.
The inspectors completed Section 03.01c of TI 2515/194, Revision 2.
The inspectors verified that modeling used for the OPC reflected the as-designed and as-built plant, assumptions made by the licensee were reasonable, and licensee procedures were adequate to successfully respond to an OPC. The inspectors also verified that human reliability analysis and recovery evaluations were done in accordance with NEI and voluntary initiative guidance.
60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants
- (1) The inspectors evaluated the licensees activities related to long-term operation and monitoring of their independent spent fuel storage installation.
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 1, 2020, the inspectors presented the radiation safety inspection results to T. Ray, Site Vice President, and other members of the licensee staff.
- On January 14, 2021, the inspectors presented the integrated inspection results to Tom Ray and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2515/194
Calculations
MCC-1535.00-00-
250
McGuire Nuclear Station PRA Analysis of Implementation
Options for Open Phase Condition Protection
Procedures
EP/1/A/5000/E-0
Reactor Trip or Safety Injection
EP/1/A/5000/ES-
0.1
Reactor Trip Response
OP/1/A/6100/010
L
Annunciator Response for Panel 1AD-11
Procedures
AD-WC-ALL-0230 Seasonal Readiness
AP/0/A/5500/044
Plant Flooding
PT/0/B/4700/038
Cold Weather Protection
PT/0/B/4700/070
On Demand Freeze Protection Verification Checklist
Corrective Action
Documents
ADJUST 2RN-25B VI ACCUMULATOR TANK PRESSURE
November
28, 2019
2RNST0002: STRAINER HAS A PACKING LEAK
GREATER THAN ALLOWED
December
21, 2019
2RNFS5780: 2B ND Pump Motor AHU RN Flow Low
March 26,
20
Drawings
MCFD-2574-
01.01
Flow Diagram of Nuclear Service Water System (RN)
Procedures
OP/2/A/6350/002
A
Diesel Generator
117
Work Orders
20368730
2RN-43A REPLACE CLUTCH RING ASSEMBLY
June 25,
20
20388176
PM 2RNLP5010, RN PUMP STRAINER 2B PRESSURE
March 10,
20
Drawings
MSFD-13
Vital Battery Room
Fire Plans
CSD-MNS-PFP-
AB-0733-001
Aux Bldg Elevation 733 Pre-Fire Plan
CSD-MNS-PFP-
AB-0750-001
Aux Bldg Elevation 750 Pre-Fire Plan
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
AD-EG-ALL-1520
Transient Combustible Control
Procedures
AP/0/A/5500/044
Plant Flooding
Corrective Action
Documents
Action Request -
2342522
IG-20-1, CRDM Latch Assembly Stationary Gripper Wear
Operating Experience Evaluation
8/5/20
AR #01985576
Self-Assessment, Boric Acid Corrosion Control Program -
Implementation Procedure Effectiveness
7/25/16
Leakage identified during a VT-2 for Class A & B Walk-down
3/16/19
ISI Owner Proficiency, Program Health Report Indicator
Decline
2/03/20
Boric Acid Evaluation
2/28/20
M1R27 Scope Change - Thermal Fatigue Examinations
9/15/20
Recommendations from the Operating Experience, Dropped
Rod Event in 2019
9/16/20
ISI Visual Examination of 1-RPV-HEAD-PEN
10/1/20
Boric Acid Corrosion Control Evaluation
10/7/20
ISI Visual Examination Limitation of 1-RPV-HEAD-Pen
10/3/20
AR SUBJECT: G-ENG-SA-15-01-Augmented Inservice
Inspection - Focused SA
7/8/15
Evaluation of 1-KF-VA-0014 Excessive Boron at Pipe
Cap/Nipple Connection
2/21/20
M1R27 Mode 3 Walkdown (Shutdown)
9/19/20
Drawings
MCM-1201.01-
0148.001
Reactor Nozzle Details
10/1/1999
MCM-1225.01-
25.001
As Built Location of Weld Seams on Reactor Closure Head
8/1/1977
Engineering
Evaluations
MNS 1E9C27
Skip Cycle
Assessment Final
McGuire Unit 1 Steam Generator, M1R27 Skipped
Inspection Cycle Outage Review
Miscellaneous
AD-NE-ALL-1101,
Rev.5, Att. 6
Visual Acuity Record for Company ID No. 472208
8/25/20
AD-NE-ALL-1101, Documentation of ASME Section XI, Appendix VII Annual
8/18/20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Rev.5, Att. 8
Training and 10 CFR 50.55a Hands on Practice, Candidate
ID 472208
Candidate ID No.
288663
NDE Examiner Written Certification Review, Direct and
Remote VT-2 (with BACC)
9/9/20
Certificate of
Personnel
Qualification ID
No.: C2319
Visual Examination VT 1 and VT-3, Qualification Certification
8/11/20
Certificate of
Personnel
Qualification ID
No.: L6868
Qualification Certification as VT Instructor and VT-1, 2 & 3
Examiner
8/11/20
Certificate of
Personnel
Qualification ID
No.: L6868
Visual Acuity Examination Certification
1/8/20
NRC Safety
Evaluation for
Relief Request
09-MN-003
Safety Evaluation by the Office of Nuclear Reactor
Regulation of Third 10-Year Interval Inservice Inspection
Relief Request No. 09-MN-003, Duke Energy Carolinas LLC,
McGuire Nuclear Station Unit 1, Docket No. 50-369
6/28/10
PDI Program
Qualification for
Candidate #1025
Performance Demonstration Initiative Program, Manual
Ultrasonic Examination Qualification Record for PDI-UT-12,
Rev. "D", Add. 0, Candidates #1025
7/9/14
PDI Program
Qualification for
Candidate #1037
Performance Demonstration Initiative Program, Manual
Ultrasonic Examination Qualification Record for PDI-UT-12,
Rev. "E", Add. 0, Candidates #1037
8/30/19
Relief Request
09-MN-003
McGuire 1, Relief Request For Extension of Reactor Vessel
Inservice Inspection Date to 2020 +/- 1Year
6/28/10
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Visual Sections Ill
& XI, Ultrasonic
Sections Ill & XI,
Appendix VIII,
PDI PDQS No.
23, with Special
Qualifications for
MRP-227/228
Endorsement and
VT-2 of Reactor
Heads
Certificate of Personnel Qualification, Candidate ID No.:
L6868
8/11/20
Visual VT-1 & 3
Section XI, with
MRP-227 and
Endorsement
Certificate of Personnel Qualification, Candidate ID No.:
C2319
8/11/20
Welder ID D7468
Record of Welder Performance Qualification Test, ASME
Section IX, Groove Welds, GTAW Process, Manual, P-1 thru
P15F, P34 and all P3X, WPS No. GTSM0101-01, Rev. 4
11/25/08
NDE Reports
A 51-9222850-
000
Relief Request 09-MN-003, Verification of Oconee Unit-3, 10
Year Reactor ISI Inspection Completion in 2014, in
exchange for Extension of McGuire Unit-1,10 Year Reactor
Vessel ISI Inspection, "Oconee Nuclear Station, Unit-3
EOC27 Reactor Vessel UT Examination Report
7/24/14
Certificate of
Vision
Examination ID
No. C2319
Certification of Visual Acuity
1/20/20
NDE Examiner
VT-2 Direct and Remote (with BACC)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Written Practice
Certification
Review, ID No.
288663
PT/ LA/4200/044
Containment Structural Integrity Inspection
4/25/19
VE-20-003
Ultrasonic Examination (UT) of ASME Class 1, Component
I
- D. 1RPV1-446A, Reactor Vessel Closure Head Meridional
9/24/20
VE-20-004
Ultrasonic Examination (UT) of ASME Class 1, Component
I
- D. 1RPV1-446B, Reactor vessel Closure Head Meridional
9/24/20
VT-20-079
Inconel Transition Weld to Stainless Steel Tube
9/28/20
VT-20-098
ASME Class 1, RPV Closure Head Outer Surface, Visual
Inspection (VT-2)
10/3/20
Procedures
54-ISl-370-007
Remote Underwater Visual Examination of PWR Reactor
Pressure Vessel
Internals in Accordance with MRP 227 & 228
2/8/18
AD-EG-PWR-
1611
Boric Acid Corrosion Control Program Implementation
Program
AD-MN-ALL-0006
FLUID LEAK MANAGEMENT
AD-PI-ALL-0400
Operating Experience Program
NDE-NE-ALL-
212
Utilization of PDI-UT-12 Procedure for Manual Phased Array
Ultrasonic Examination of Reactor Pressure Vessel Welds
NDE-NE-ALL-
202
Visual Examination of PWR Reactor Pressure Vessel Upper
Head Penetrations
NDE-NE-ALL-
203
Visual Examination of PWR Reactor Pressure Vessel
Bottom Mounted Instrument Penetrations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PD-EG-PWR-
1611
BORIC ACID CORROSION CONTROL PROGRAM
PDI-UT-12
Procedure for Manual Phased Array Ultrasonic Examination
of Reactor Pressure Vessel Welds
E
SM 0-A-8140-001 Welding Of QA And Non-QA Piping, Valves And
Components, Valve ID No. 1-NI-IV-5010
9/30/20
TE-MN-PWR-
0006
INSPECTION, ASSESSMENT, AND CLEANUP OF BORIC
ACID ON PLANT MATERIALS
Work Orders
Weld Document Instruction, Weld ID 201037, Replace
Isolation Valve, 1-NI-IV-5010
9/26/20
71111.11Q Procedures
AD-OP-ALL-1000
Conduct of Operations
Miscellaneous
Duke Equipment Reliability Maintenance Rule Database
Procedures
AD-EG-ALL-1204
Single Point Vulnerability Identification, Elimination and
Mitigation
AD-EG-ALL-1206
Equipment Reliability Classification
AD-EG-ALL-1209
System, Component, and Program Health Reports and
Notebooks
AD-EG-ALL-1210
AD-EG-ALL-1211
System Performance Monitoring and Trending
Procedures
AD-OP-ALL-0201
Protected Equipment
Procedures
AD-EG-ALL-1211
System Performance Monitoring and Trending
AD-OP-ALL-0102
Operability Decision Making
AD-OP-ALL-0105
Operability Determinations and Functionality Assessment
Engineering
Evaluations
Permanently Bypass Containment Iodine Detector 2EMF40
Procedures
AD-EG-ALL-1155
Post Modification Testing
Procedures
OP/1/A/6100/003
Controlling Procedure for Unit Operation
PT/0/A/4150/028
Initial Criticality and Zero Power Physics Testing
PT/1/A/4600/003
F
Containment Cleanliness and ECCS Operability Inspection
Procedures
AD-EG-ALL-1202
Preventive Maintenance and Surveillance Testing
Administration
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AD-EG-ALL-1720
In-service Testing (IST) Program Implementation
AD-WC-ALL-0250 Work Implementation and Completion
PT/1/A/4200/001
C
Isolation Valve Leak Rate Test
130
PT/2/A/4252/001
A
2A CA Pump Performance Test
097
Corrective Action
Documents
Nuclear Condition
Report
266623, 02291246, 02339071, 02342263, 02345554, and
2345729
Various
Miscellaneous
Radioactive Air Sample Log Results, 10/1/2019 through
9/28/2020
9/28/20
RP# 604962
Intake Assessment - Ingestion [DRAFT]
9/27/20
TEDE-ALARA
Evaluation
Worksheet
RWP # 1840, Task 6 [Unit 1 Cavity, deep end decon]
9/28/20
Procedures
AD-PI-ALL-0100
Corrective Action Program
AD-RP-ALL-0003
Radiological Air Sampling
AD-RP-ALL-0005
Access Controls for High and Locked High Radiation Areas
AD-RP-ALL-0007
Control of Radioactive Material
AD-RP-ALL-0010
Radiological Job Coverage
AD-RP-ALL-2008
Remote Monitoring
AD-RP-ALL-2014
Work in Alpha Environments
AD-RP-ALL-2017
Access Controls to Very High Radiation Areas and
Supplemental Access Controls for HRA and LHRA
AD-RP-ALL-2019
TEDE-ALARA Evaluations and DAC-Hour Tracking
RPMP 7-1
Radiological Key Control
RPMP 7-11
Contamination Controls
RPMP 7-15
Supplemental Guidelines for Establishing High, Locked High
and Very High Radiation Areas
Radiation
Surveys
MNS-M-
200922-21
Unit 1 Blind flange removal [transfer canal]
9/22/20
MNS-M-
200924-7
Unit 1 Post Rx Head move
9/24/20
MNS-M-
200927-12
Unit 1 Core Barrel removal and move to stand in lower cavity 9/27/20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MNS-M-
200928-13
Unit 1 Core Barrel removal and move to stand in lower cavity 9/27/20
MNS-M-
200928-14
Unit 1 Core Barrel removal and move to stand in lower cavity
Radiation Work
Permits (RWPs)
RWP # 1040
U-1 Rx Bldg: 10 year ISI Reactor Vessel and Core Barrel
RWP # 1384
Unit 1 Rx Bldg: Remove and Replace Core Barrel
RWP # 1728
Unit 1 Rx Bldg: R & R Rx head, vessel flange cleaning and
cleaning and replace Rx head O-rings
RWP # 1730
Unit 1 Rx Bldg: Remove and Replace "A" NCP Seals
RWP # 1902
Unit 1 Rx Bldg/Aux Bldg: Misc Surveillance (management,
safety tours, etc.)
Shipping Records Shipment ID 20-4-
086
McGuire Incoming Radioactive Material Shipment
Documentation [including equipment radiation surveys] used
in basis for Intake Assessment
9/15/20
71151
Corrective Action
Documents
Nuclear Condition
Report 02270402,
293248, and
2348855
Various
Miscellaneous
Electronic Dosimeter (ED) Dose / Dose Rate Alarm Logs -
10/01/2019 through 09/29/2020
Various
Procedures
AD-LS-ALL-0004
NRC Performance Indicators and Monthly Operating Report
AD-PI-ALL-0100
Corrective Action Program
AD-PI-ALL-0100
Corrective Action Program
AD-PI-ALL-0700
Performance Indicators
Procedures
AD-LS-ALL-0006
Notification/Reportability Evaluation
AD-PI-ALL-0100
Corrective Action Program
AD-PI-ALL-0105
Effectiveness Reviews