IR 05000369/2019004
| ML20029D145 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 01/29/2020 |
| From: | Frank Ehrhardt Division Reactor Projects II |
| To: | Teresa Ray Duke Energy Carolinas |
| References | |
| IR 2019004 | |
| Download: ML20029D145 (12) | |
Text
January 29, 2020
SUBJECT:
MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2019004 AND 05000370/2019004
Dear Mr. Ray:
On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On January 16, 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/
Frank J. Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects
Docket Nos. 05000369 and 05000370 License Nos. NPF-9 and NPF-17
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000369 and 05000370
License Numbers:
Report Numbers:
05000369/2019004 and 05000370/2019004
Enterprise Identifier: I-2019-004-0021
Licensee:
Duke Energy Carolinas, LLC
Facility:
McGuire Nuclear Station
Location:
Huntersville, North Carolina
Inspection Dates:
October 01, 2019 to December 31, 2019
Inspectors:
G. Hutto, Senior Resident Inspector
B. Griman, Acting Resident Inspector
M. Meeks, Senior Operations Engineer
M. Schwieg, Reactor Inspector
Approved By:
Frank J. Ehrhardt, 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 operated at or near 100 percent rated thermal power (RTP) for the entire 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 performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
External Flooding Sample (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated readiness to cope with external flooding for the following areas:
- Unit 1 and 2 yard storm drains
- Auxiliary building roof flood mitigation features
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Diesel generator 1A on October 8, 2019 (2)
"B" train of control room chilled water on November 5, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the 1A train of the nuclear service water (RN) system on December 19, 2019.
71111.05A - Fire Protection (Annual)
Annual Inspection (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated fire brigade performance on December 6, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (3 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Auxiliary building elevation 716' safety injection system (NI) pump rooms on October 9, 2019
- (2) Service building elevation 739' instrument air compressor area on December 15, 2019
- (3) Control room area on December 31, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 1 and 2 component cooling water pump areas and the auxiliary building sump, on December 11, 2019
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) Annual Review of Licensee Requalification Examination Results: On November 15, 2019, the licensee completed 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 2, 2019, 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 the large volume 1A accumulator feed and bleed on October 5, 2019, and entry into AP-36, "Control Room High Temperature," on November 4, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated Active Simulator Exam (ASE-32), which involved a rod control malfunction, a main steam line break, and the reactor failing to trip on October 30, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Nuclear Condition Report (NCR) 2291880, "A" control room chilled water system (YC)chiller tripped
- (2) NCR 2292639, Investigate/repair oil leak at standby shutdown facility (SSF) diesel oil filter 0ADFL0010 housing
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Unit 1 equipment protection plan for the B train control room chilled water pump out of service (OOS) on October 1, 2019
- (2) Elevated risk during Yellow Grid condition on October 3, 2019
- (3) Unit 2 equipment protection plan for the 2A diesel generator OOS on October 23, 2019
- (4) Unit 1 equipment protection plan for the 1B safety injection pump OOS on December 11, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (4 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) NCR 2295184, Abnormal radio-isotopic activity in Unit 2 component cooling system, on October 9, 2019
- (2) NCR 2297083, MAGNASTOR ultrasonic examination during fabrication prior to normalizing heat treatment, on October 15, 2019
- (3) NCR 2298259, Cutler Hammer relay environmental qualification qualified life not established in the equipment data base, on October 23, 2019
- (4) NCR 2305715, Harris operating experience testing SA-1 differential relays applies to McGuire Nuclear Station, on December 12, 2019
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 95873), Replace All Three 125 VDC Standby Shutdown Facility Battery Chargers, on December 17, 2019
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) PT/1/A/4350/002 B, Diesel Generator 1B Operability Test, after oil sample on October 8, 2019
- (2) PT/2/A/4403/003 A, RN Train A Valve Stroke Time Testing - Shutdown, after valve preventive maintenance (PMs) on 2RN-16A, on October 22, 2019
- (3) PT/2/A/4350/002 A, Diesel Generator 2A Operability Test, after diesel down-day maintenance on October 24, 2019
- (4) PT/2/A/4200/020 A, Airlock Operability Test, after Unit 2 upper airlock seal inspection, on November 14, 2019
- (5) PT/1/A/4206/001 B, 1B Safety Injection Pump Operability Test, after pump coupling PMs, on December 12, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) PT/2/A/4350/002, Diesel Generator 2B Operability Test, on November 7, 2019
- (2) PT/2/A/4350/006, LD Train A Valve Stroke Timing - Quarterly, on December 18, 2019
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) 2B NI pump performance test on October 7, 2019
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) McGuire Drill 19-07 which involved a loss of off-site power and subsequent loss of all AC power, on November 13,
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, 2018-September 30, 2019)
- (2) Unit 2 (October 1, 2018-September 30, 2019)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (October 1, 2018-September 30, 2019)
- (2) Unit 2 (October 1, 2018-September 30, 2019)
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 the area of equipment reliability that might be indicative of a more significant safety issue.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 16, 2020, the inspectors presented the integrated inspection results to Tom Ray and other members of the licensee staff.
THIRD PARTY REVIEWS
Inspectors reviewed the World Association of Nuclear Operators reports that were issued during the inspection period.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
MCC-1100.00-00-
0002
McGuire Probable Maximum Precipitation Flood Analysis
Drawings
MC-1022-01.00
Grading Plan, Plant Area
Miscellaneous
MCS-1465.00-00-
0012
Design Basis Specification for Flooding from External
Sources
71111.04Q Drawings
MCFD-1618-
01.00
Flow Diagram of Control Room Chilled Water System
Rev. 9
Procedures
OP/1/A/6350/002
Diesel Generator
Corrective Action
Documents
NCR 2279804
1RNP5220 (1A DG HX RN Flow) Indication is Erratic
NCR 2292418
Minor RN Leak on the Outlet of the A YC Chiller
Drawings
MCFD-1574-
01.00
Flow Diagram of Nuclear Service Water System
Rev. 33
MCFD-1574-
01.01
Flow Diagram of Nuclear Service Water System
Rev. 37
Miscellaneous
MCS-1574.RN-
00-0001
Design Basis Document Nuclear Service Water System
Rev. 26
Work Orders
1-RN-ST-0001 Leakage Identified on the strainer
Miscellaneous
MCS-1465.00-00-
0008
Design Basis Specification for Fire Protection
Procedures
AD-OP-ALL-0207
Fire Brigade Administrative Procedures
71111.05Q Drawings
CSD-MNS-PFP-
SRV-0739-001
Units 1 and 2 Service Building Elevation 739
Rev. 0
MFSD-004
AUX 716
Rev. 0
MFSD-024
Control Room
Rev. 1
Procedures
AD-EG-All-1520
Transient Combustible Control
Calculations
MCC-1206.47-69-
100
Auxiliary Building Flooding Analysis
Miscellaneous
MCS-1154.00-
0004
Design Basis Specification for Auxiliary Building Structures
Procedures
AP/0/A/5500/044
Plant Flooding
71111.11Q Drawings
MCFC-1362-
2.00
Flow Diagram of Safety Injection System (NI)
Rev. 8
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MCFD-1372-
01.01
Flow Diagram of Nuclear Sampling System (NM)
Rev. 8
MCFD-1562-
2.01
Flow Diagram of Safety Injection System (NI)
Rev. 7
MCFD-
1562.03.01
Flow Diagram of Safety Injection System (NI)
Rev. 15
MFCD-1562-
03.00
Flow Diagram of Safety Injection System (NI)
Rev. 18
Procedures
OP/1/A/6200/009
Accumulator Operation
Rev. 116
Procedures
AD-EG-ALL-1209
System, Component and Program Health Reports and
Programs
AD-EG-ALL-1210
Maintenance Rule Proram
AD-EG-ALL-1211
System Performance Monitoring and Trending
Procedures
AD-OP-ALL-0201
Protected Equipment
AD-OP-ALL-0204
Plant Status Control
AD-WC-ALL-0240 On-line Risk Management Process
Procedures
AD-OP-ALL-0102
Operability Decision Making
AD-OP-ALL-0105
Operability Determinations and Functionality Assessment
Engineering
Changes
Replace All Three 125 VDC SSF Battery Chargers Mod
Procedures
AD-EG-ALL-1132
Preparation and Control of Design Change Engineering
Changes
AD-EG-ALL-1137
Engineering Change Product Selection
Procedures
AD-WC-ALL-0250 Work Implementation and Completion
PT/0/A/4350/030
Nordberg Diesel Engine 6 yr Periodic Maintenance
Rev. 27
PT/1/A/4206/001
B
1B Safety Injection Pump Operability Test
PT/1/A/4350/002
B
Diesel Generator 1B Operability Test
Rev. 113
PT/2/A/4200/020
A
Airlock Operability Test
PT/2/A/4350/002
A
Diesel Generator 2A Operability Test
PT/2/A/4403/003
RN Train A Valve Stroke Time Testing - Shutdown
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
A
Procedures
AD-EG-ALL-1202
Preventive Maintenance and Surveillance Testing
Administration
AD-EG-ALL-1720
In-service Testing (IST) Program Implementation
PT/2/A/4206/001
B
2B NI Pump Performance Test
Rev. 51
Work Orders
20341401
10/07/2019
Procedures
AD-EP-ALL-0101
Emergency Classification
AD-EP-ALL-0105
Activation and Operation of the Technical Support Center
AD-EP-ALL-0109
Offsite Protective Action Recommendations
AD-EP-ALL-0111
Control Room Activation of the ERO
71151
Procedures
AD-LS-ALL-0004
NRC Performance Indicators and Monthly Operating Report
Corrective Action
Documents
NCR 2300082
Rotorck Clutch Ring Part 21 Engineering Evaluation
Procedures
AD-PI-ALL-0100
Corrective Action Program