IR 05000369/2020003
| ML20309A659 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/04/2020 |
| From: | Jared Nadel NRC/RGN-II/DRP/RPB1 |
| To: | Teresa Ray Duke Energy Carolinas |
| References | |
| IR 2020001, IR 2020003 | |
| Download: ML20309A659 (19) | |
Text
November 4, 2020
SUBJECT:
MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2020003, 05000370/2020003, AND 07200038/2020001
Dear Mr. Ray:
On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On October 28, 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.
One Severity Level IV violation without an associated finding is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)
consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at McGuire Nuclear Station. 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/
Jared H. Nadel, 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:
05000369/2020003, 05000370/2020003 and 07200038/2020001
Enterprise Identifier: I-2020-003-0053; 1-2020-001-0106
Licensee:
Duke Energy Carolinas, LLC
Facility:
McGuire Nuclear Station
Location:
Huntersville, North Carolina
Inspection Dates:
July 01, 2020 to September 30, 2020
Inspectors:
A. Hutto, Senior Resident Inspector
R. Cureton, Resident Inspector
C. Fontana, Emergency Preparedness Inspector
B. Griman, Resident Inspector
B. Kellner, Senior Health Physicist
S. Sanchez, Senior Emergency Preparedness Insp
J. Walker, Emergency Response Inspector
Approved By:
Jared H. Nadel, 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
Failure to Adequately Document the Basis for a Change to the Emergency Action Level Wallchart Cornerstone Significance Cross-Cutting Aspect Report Section Not Applicable NCV 05000370,05000369/2020003-01 Open/Closed Not Applicable 71114.04 The inspectors identified a SL-IV NCV of Title 10 of the Code of Federal Regulations (CFR),
Part 50.54(q)(3), for changes made to the McGuire Nuclear Station Radiological Emergency Plan (E-Plan), and associated emergency action level (EAL) wallchart, that failed to demonstrate the changes would not reduce the effectiveness (RIE) of the E-Plan. Specifically, the licensee did not provide an adequate analysis for the inspectors to determine that the removal of clarifying information was not a RIE of the EAL wallchart.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000369,05000370/2020
-001-00 LER 2020-001-00 for McGuire Nuclear Station, Unit 1,
Condition prohibited by Technical Specification 3.4.15,
Leakage Detection Instrumentation 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at or near 100 percent rated thermal power (RTP). On September 18, 2020 the unit was shutdown for a scheduled refueling outage and ended the inspection period in Mode 5.
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 (COVID-19), resident and regional 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, increasing the amount of time on site as local COVID-19 conditions permitted. As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; 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 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
71111.04 - 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)2B diesel generator, on July 22, 2020 (2)1B containment spray system, on August 25, 2020 (3)1A train spent fuel pool cooing system, on September 28, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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 2 Aux Bldg. 733' elevation, on September 10, 2020
- (2) Unit 1 Aux Bldg. 716' elevation, on September 17, 2020
- (3) Unit 1/2 control room area, on September 22, 2020
- (4) Unit 1/2 control room ventilation area, on September 24, 2020
- (5) Unit 1/2 Aux Bldg. 695 elevation, on September 28, 2020
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 reactor shutdown and plant cooldown, on September 19, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated active simulator exam ASE-21, involving a loss of vacuum manual trip and a loss of coolant safety injection, on August 4, 2020.
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) 02327032, 1A decay heat removal pump (ND) lower oil sight glass leaking, on September 16, 2020
- (2) NCR 2335556, 2A diesel generator failed starting air solenoid test, on September 24, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
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 1B diesel generator maintenance, on July 6, 2020
- (2) Equipment protection plan for Unit 1 "A" train component cooling water system preventive maintenance (PM), on July 27, 2020
- (3) Equipment protection plan for 2B diesel generator maintenance, on August 4, 2020
- (4) Equipment protection plan for 1A diesel generator maintenance, on August 25, 2020
- (5) Independent Review Team outage risk assessment for Unit 1 refueling outage M1R27, on September 17, 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 2337068, 1EQADE0001: 1A emergency diesel generator (EDG) cylinder 4L fuel pump leak, on July 6, 2020
- (2) NCR 2339629, 2B diesel generator roof hatch leak on diesel/components, on July 16, 2020
- (3) NCR 2341632, Oil leakage from Unit 1 turbine driven auxiliary feedwater pump overspeed trip lever, on July 30, 2020
- (4) NCR 2341827, Minor oil leak on 1A diesel generator governor servo booster, on August 6, 2020
- (5) NCR 2349994, Nuclear instrument 1N32 count rate drifting up, on September 30, 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 permanent modification:
- (1) Engineering Change (EC) 418000, Containment floor and equipment sump RCS leakage detection operator aid computer updates
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) PT/1/A/4350/002 B, Diesel Generator 1B Operability Test following PMs, on July 13, 2020
- (2) PT/2/A/4350/002 A, Diesel Generator 2A Operability Test following PMs, on July 22, 2020
- (3) PT/1/A/4350/002 A, Diesel Generator 1A Operability Test following PMs, on September 2, 2020
- (4) Work Order 20405452 Task 4, 1B decay heat removal pump functional run following oil change, on September 8, 2020
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated refueling outage M1R27 activities from September 19, 2020 to September 30, 2020.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) PT/1/A/4206/002 A, "NI Train A Valve Stroke Timing - Quarterly," on July 23, 2020
- (2) PT/1/A/4350/036 A, "Diesel Generator 1A 24 Hour Run," on August 27, 2020
- (3) PT/2/A/4204/010, "2A ND Pump Air Handling Unit Performance Test," on September 29, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) PT/2/A/4252/001, "#2 TD CA Pump Performance Test," on July 28, 2020
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) Flex 500 kw diesel generator testing, on September 21, 2020
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of September 14, 2020.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Response Organization during the week of September 14, 2020.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of September 14, 2020. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of September 14, 2020.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the emergency preparedness drill conducted on July 22, 2020. The drill involved a turbine trip with a failure of the reactor to trip, followed by large break reactor coolant system leak and subsequent increase in containment radiation levels.
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Active simulator exam ASE-21 demonstrating drill and exercise performance measures, on August 18,
RADIATION SAFETY
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (3 Samples)
The inspectors evaluated the configuration and accessible portions of the following permanently installed ventilation systems:
- (1) Auxiliary Building Filtered Exhaust System (ABFVES)
- (2) Unit 1 Containment Purge and Ventilation System
- (3) Unit 2 Containment Purge and Ventilation System
Temporary Ventilation Systems (IP Section 03.02) (3 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
(1)1000 CFM HEPA ventilation unit installed on the Kelly Decon Booth - ID # MNS-1000-1, DOP Test date 9/11/2018
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose.
Internal Dosimetry (IP Section 03.03) (2 Samples)
The inspectors evaluated the following internal dose assessments for actual internal exposures:
- (1) Apex-InVivo Analysis Report, Worker ID 500380, Investigative whole body count due to exit monitor alarm, 04/06/2020
- (2) No internal dose evaluations due to actual internal exposures were available for review for the period evaluated.
Special Dosimetric Situations (IP Section 03.04) (4 Samples)
The inspectors evaluated the following special dosimetric situations:
- (1) Dose assessment for four declared pregnant workers from October 2018 through August 2020.
- (2) Unusual Dosimetry Occurrence (UDO) 20-06, Lost Electronic Dosimeter (ED) and Dosimeter of Legal Record (DLR).
- (3) Unusual Dosimetry Occurrence (UDO) 20-07, Lost Dosimeter of Legal Record (DLR).
- (4) Unusual Dosimetry Occurrence (UDO) 20-14, Dosimeter of Legal Record (DLR) worn after medical procedure involving radionuclide injection.
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (14 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Unit 1 Main Vent Stack Effluent Radiation Monitor, 1-EMF-036 (Low range)
- (2) Unit 1 Containment Purge Effluent Radiation Monitor, 1-EMF-038/039/040 (Particulate, gaseous, and Iodine)
- (3) Unit 2 Containment Purge Effluent Radiation Monitor, 2-EMF-038/039/040 (Particulate, gaseous, and Iodine)
- (4) Liquid Effluent Radiation Monitor, 0-EMF-049
- (5) Waste Gas Effluent Radiation Monitor, 0-EMF-050
- (6) Ludlum Model 177 count rate meter with pancake probe (frisker), ENRAD ID# 07147, Cal due date 7/24/2020
- (7) Ludlum Model 177 count rate meter with pancake probe (frisker), ENRAD ID# 12877, Cal due date 2/10/2021
- (8) Ludlum Model 177 count rate meter with side window GM detector (hotdog probe),
ENRAD ID# 02505, Cal due date 2/10/2021
- (9) Ludlum Model 9-3 ion chamber, ENRAD ID# 7249, Cal due date 2/6/2021
- (10) Ludlum Model 9-3 ion chamber, ENRAD ID# 12036, Cal due date 2/3/2021
- (11) Canberra Model ARGOS-5AB contamination monitor, ENRAD ID# 08002
- (12) Canberra Model ARGOS-5PB contamination monitor, ENRAD ID# 07901
- (13) Mirion Telepole telescoping GM dose rate instrument, ENRAD ID# 02116, Cal due date 6/2/2021
- (14) Canberra Model GEM-5 portal monitor, ENRAD ID#
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (IP Section 02.12)===
- (1) EP01: Drill & Exercise Performance for the period July 1, 2019, through June 30, 2020.
EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)
- (1) EP02: Emergency Response Organization Drill Participation for the period July 1, 2019, through June 30, 2020.
EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)
- (1) EP03: Alert & Notification System Reliability for the period July 1, 2019, through June 30, 2020.
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2019 - June 30, 2020)
- (2) Unit 2 (July 1, 2019 - June 30, 2020)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2019 - June 30, 2020)
- (2) Unit 2 (July 1, 2019 - June 30, 2020)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (July 1, 2019 - June 30, 2020)
- (2) Unit 2 (July 1, 2019 - June 30, 2020)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) October 2019 to June 2020
71152 - Problem Identification and Resolution
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:
71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000369/370/2020-001-00, Condition Prohibited by Technical Specification 3.4.15, Reactor Coolant System (RCS) Leakage Detection Instrumentation (ADAMS Accession No. ML20293A357). The inspection conclusions associated with this LER are documented in this report under Inspection Results.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
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
The inspectors evaluated the following change reviews:
- AR 2296586, 72.48 screen, "Pad 9 Design for ISFSI Phase IV"
- AR 2297342, 72.48 screen, "Deletion of MP/0/A/7700/119"
INSPECTION RESULTS
Failure to Adequately Document the Basis for a Change to the Emergency Action Level Wallchart Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000370,05000369/2020003-01 Open/Closed Not Applicable 71114.04 The inspectors identified a SL-IV NCV of Title 10 of the Code of Federal Regulations (CFR),
Part 50.54(q)(3), for changes made to the McGuire Nuclear Station Radiological Emergency Plan (E-Plan), and associated emergency action level (EAL) wallchart, that failed to demonstrate the changes would not reduce the effectiveness (RIE) of the E-Plan. Specifically, the licensee did not provide an adequate analysis for the inspectors to determine that the removal of clarifying information was not a RIE of the EAL wallchart.
Description:
While performing a detailed review of a change to the EAL wallchart, the inspectors noted that a deletion of No Mode for mode applicability for the HS 6.1 EAL on the wallchart used for classification purposes during a radiological emergency could be considered a RIE. The inspectors found in the 10CFR50.54(q) change documentation, that the licensee categorized these changes as editorial in nature. By categorizing the changes as editorial, an analysis to determine whether the changes were a RIE was not conducted. The inspectors determined that these changes were more than editorial and therefore required an analysis be performed because the removal of specific or clarifying information could delay the ERO in the performance of their duties. An adequate analysis was not provided either when the No Mode was introduced into HS 6.1 on the wallchart mode applicability in December 2019 (causing a misalignment with the EAL technical bases document), or when it was removed in March 2020 to return the wallchart and the technical bases to alignment.
Corrective Actions: The licensee entered the issue into the corrective action program on September 17, 2020.
Corrective Action References: Nuclear Condition Report 02349151
Performance Assessment:
The licensees failure to provide an analysis demonstrating that changes to the EAL wallchart was not a RIE was determined to impede the NRCs ability to perform its regulatory function and is dispositioned using the Traditional Enforcement process.
Enforcement:
Severity: This finding is a violation of NRC requirements because it had the potential for impacting the NRCs ability to perform its regulatory function. Therefore, traditional enforcement is applicable, in accordance with Inspection Manual Chapter 0611 and 0612, Appendix B, Figure 2. This finding is determined to be a SL-IV violation in accordance with Section 6.6.d.1 of the Enforcement Policy because it involves the licensees ability to meet or implement a regulatory requirement not related to assessment or notification such that the effectiveness of the emergency plan is reduced.
Violation:
Title 10 of the Code of Federal Regulations, Part 50.54(q)(3) states, in part, that a licensee may make changes to its emergency plan without NRC approval only if the licensee performs and retains an analysis demonstrating that the changes do not reduce the effectiveness of the plan and the plan, as changed, continues to meet the requirements in Appendix E to this part. Contrary to the above, from December 16, 2019, to March 23, 2020, the licensee failed to perform an analysis demonstrating that changes to their E-Plan, and EAL wallchart, did not reduce the effectiveness of the Plan. Specifically, the licensee did not provide an analysis to determine whether the addition and removal of specific clarifying information was not a RIE of the approved McGuire E-Plan and associated EAL wallchart.
Enforcement Action: This violation is being treated as an non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: TS 3.4.15, RCS Leakage Detection Instrumentation, requires that the containment floor and equipment (CFAE) sump level monitors detect a one gallon per minute sump input within one hour after RCS leakage has reached the sumps. Contrary to the above, from April 15, 1994 until June 29, 2020, the licensee relied on a non-conservative assumption in their CFAE alarm setpoint calculation that prevented the CFAE sumps from detecting a one gallon per minute input within one hour.
Significance/Severity: Green. The inoperability of the CFAE sump monitors was determined to be of very low safety significance (Green), as the finding is associated with the barrier integrity cornerstone and screens as green per Manual Chapter 0609 Appendix A, Exhibit 3, as the finding does not involve potential non-compliance with regulatory requirements for protection of the reactor pressure vessel against fracture.
Corrective Action References: NCR 2337223, Non-conservative alarm setpoint for the CFAE sump level.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 11, 2020, the inspectors presented the occupational radiation safety inspection results to E. Pigott, Plant Manager and other members of the licensee staff.
- On September 18, 2020, the inspectors presented the emergency preparedness program inspection results to Mr. T. Ray and other members of the licensee staff.
- On October 28, 2020, 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
60855.1
Miscellaneous
2.48 screen, "Pad 9 Design for ISFSI Phase IV"
2.48 screen, "Deletion of MP/0/A/7700/119"
Drawings
MCFD-1563-01.00
"Flow Diagram of Containment Spray System"
MCFD-1570-01.00
"Flow Diagram of Spent Fuel Cooling System"
Procedures
OP/2/A/6350/002
"Diesel Generator"
Drawings
MFSD-024
"Control Room"
Fire Plans
CSD-MNS-PFP-AB-
0716-001
Units 1 & 2 Auxiliary Building Elevation : 716
CSD-MNS-PFP-AB-
0733-001
Units 1 & 2 Auxiliary Building Elevation : 733
Miscellaneous
MCS-1465.00-00-
0008
Design Basis for Fire Protection
Procedures
AD-EG-ALL-1520
Transient Combustible Control
FS/0/9000/001
"Fire Strategy #1 (Aux 695)"
Corrective Action
Documents
1A ND Pump lower oil sight glass leaking
04/25/2020
NCR 2335556
2A diesel generator failed starting air solenoid test
Procedures
AD-EG-ALL-1209
System, Component and Program Health Reports and
Programs
AD-EG-ALL-1210
Procedures
AD-OP-ALL-0201
Protected Equipment
AD-OP-ALL-0204
Plant Status Control
AD-WC-ALL-0204
On-line Risk Management Process
Procedures
AD-EG-ALL-1211
System Performance Monitoring and Trending
AD-OP-ALL-0102
Operability Decision Making
AD-OP-ALL-0105
Engineering
Changes
Containment floor and equipment sump RCS leakage
detection operator aid computer updates
Procedures
AD-EG-ALL-1155
Post Modification Testing
PT/1/A/4350/002 A
Diesel Generator 1A Operability Test
116
Miscellaneous
M1R27
McGuire M1R27 Refueling Outage Schedule
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
AD-WC-ALL-0430
Outage Risk Review
Procedures
AD-EG-ALL-1202
Preventive Maintenance and Surveillance Testing
Administration
AD-EG-ALL-1720
In-service Testing (IST) Program Implementation
PT/2/A/4204/010
2A ND Pump Air Handling Unit Performance Test
019
Procedures
McGuire Emergency Plan, Rev. 20.1
CSD-EP-MNS-0101-
EAL Technical Bases Document, Rev. 031
RP/0/A/5700/000
Classifications of Emergencies, Rev. 031
Calibration
Records
ENRAD ID # 04182
SCBA Flow Test, Regulator Serial Number WAA339176
01/21/2020
ENRAD ID # 04196
SCBA Flow Test, Regulator Serial Number WAA339120
01/11/2019
ENRAD ID# 04196
SCBA Flow Test, Regulator Serial Number WAA339120
01/20/2020
ENRAD ID# 04200
SCBA Flow Test, Regulator Serial Number WAA339087
2/07/2019
S/N 8030093102
PortaCount 2 Fit Test
03/30/2020
Corrective Action
Documents
07/14/2020
Miscellaneous
Plant Breathing Air (VB), Grade D Breathing Air Analysis
10/28/2019
Plant Breathing Air (VB), Grade D Breathing Air Analysis
01/27/2020
Air Sample Analysis Tracking Log - October 1, 2018
through July 30, 2020
AD-RP-ALL-6002,
"Unit
Inspection Sheet"
SCBA and Respirator Facepiece inspections for November
and December 2019
Various
S/N 25427 (Bauer
H19-V)
SCBA Air Compressor, Grade D Breathing Air Analysis
05/01/2019
S/N 25427 (Bauer
H19-V)
SCBA Air Compressor, Grade D Breathing Air Analysis
01/27/2020
Procedures
AD-RP-ALL-6000
Respiratory Protective Equipment Approval and Issue
AD-RP-ALL-6001
Quantitative Fit Testing
AD-RP-ALL-6002
Inspections of Self-Contained Breathing Apparatus (SCBA)
and Associated Equipment
AD-RP-ALL-6005
Powered Air-Purifying Respirators
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Self-
Assessments
2018 Respiratory Protection Self Assessment
Undated
Corrective Action
Documents
NCR 02237659, 02267375, 02269850, 02291246, and
2301072
Various
Miscellaneous
Unusual Dosimetry Occurrence Log, January 2018 through
August 2020
2019 (M1 R26) Alpha Characterization
3/03/2020
McGuire Nuclear Station General Site Area and
Independent Spent Fuel Storage Installation (ISFSI)
Perimeter Thermo-Luminescent Dosimeter (TLD)
Monitoring Results -3rd quarter 2018 through 4th quarter
2019
Various
2018, 2019, and 2020 National Voluntary Laboratory
Accreditation Program (NVLAP) Certificate of Accreditation
to ISO/IEC 17025:2005, LAB CODE: 100505-0
Various
Personal Contamination Event Logs, October 2018
through July 2020
08/03/2020
DAW 3/1/20
Nuclide Distribution Report [Dry Active Waste (DAW)
Characterization (Part 61 Analysis)]
2/27/2020
Dosimetry Technical
Report: 15-01
MNS MAGNASTOR ISFSI Neutron Energy Evaluation
04/23/2015
MNSPM1
Whole Body Counter (WBC) background, source check,
Quality Control (QC), and Quality Assurance (QA) Trend
reports for the period 4/1/2020 through 4/15/2020
Self-
Assessments
Self-Assessment
Number: 02158064
2019 Dosimetry Lab Internal Audit
08/07/2019
Corrective Action
Documents
Resulting from
Inspection
Station Sciences Survey Instruments Out of Calibration
08/04/2020
71151
Miscellaneous
McGuire Nuclear Station Units 1 and 2, 2019 Annual
Radioactive Effluent Release Report (ARERR)
04/28/2020
June 2020 Liquid
and Gas Dose
08/04/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Summary Report
(Includes month,
quarter, year to date
effluent releases
and doses for
January through
June 2020)
Procedures
AD-LS-ALL-0004
NRC Performance Indicators and Monthly Operating
Report
AD-PI-ALL-0100
Corrective Action Program
Procedures
AD-LS-ALL-0006
Notification/Reportability Evaluation
AD-PI-ALL-0100
Corrective Action Program
AD-PI-ALL-0104
Prompt Investigation Response Team
AD-PI-ALL-0105
Effectiveness Reviews
Corrective Action
Documents
NCR 2337223
Non-conservative alarm setpoint for the CFAE sump level
Engineering
Changes
Containment floor and equipment sump RCS leakage
detection operator aid computer updates
Miscellaneous
LER
05000369/370/2020-
001-00
Condition Prohibited by Technical Specification 3.4.15,
Reactor Coolant System (RCS) Leakage Detection
Instrumentation