IR 05000369/2019001

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Nuclear Regulatory Commission Integrated Inspection Report 05000369/2019001 and 05000370/2019001
ML19129A066
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 05/08/2019
From: Frank Ehrhardt
NRC/RGN-II/DRP/RPB1
To: Teresa Ray
Duke Energy Carolinas
References
IR 2019001
Download: ML19129A066 (12)
v • d • e


Text

{{#Wiki_filter:UNITED STATES May 8, 2019

SUBJECT:

MCGUIRE NUCLEAR STATION - NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000369/2019001 AND 05000370/2019001

Dear Mr. Ray:

On March 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your McGuire Nuclear Station Units 1 and 2. On April 10, 2019, 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.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, /RA/ Frank Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17

Enclosure:

IR 05000369/2019001 and 05000370/2019001

Inspection Report

Docket Numbers: 50-369, 50-370 License Numbers: NPF-9, NPF-17 Report Numbers: 05000369/2019001 and 05000370/2019001 Enterprise Identifier: I-2019-001-0019 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station, Units 1 and 2 Location: Huntersville, NC Inspection Dates: January 1, 2019 to March 31, 2019 Inspectors: A. Hutto, Senior Resident Inspector R. Cureton, Resident Inspector P. Braaten, Reactor Inspector S. Downey, Senior Reactor Inspector Approved By: F. Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a quarterly baseline inspection at McGuire Nuclear Station Units 1 and 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.

List of Findings and Violations No findings were identified.

Additional Tracking Items Type Issue number Title Report Section Status URI 05000369,05000370/2018011- Question about 71111.05XT Closed 01 treatment of well-sealed, robustly secured cabinets in the Fire PRA.

PLANT STATUS

Unit 1 began the inspection period at or near 100 percent rated thermal power RTP). On March 23, 2019, 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 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

71111.04 - Equipment Alignment Partial Walkdown (IP Section 02.01)

Main article: IP 71111.04

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) 1B diesel generator (DG) while the 1A DG was out of service (OOS) for maintenance, on January 22, 2019
(2) Unit 1 "B" train of component cooling water (KC) while the "A" train was OOS for valve preventive maintenance (PM), on January 30, 2018
(3) Unit 2 "A" train of nuclear service water (RN) while the 2B RN system was OOS for maintenance, on March 5, 2019
(4) Unit 1 "A" train of decay heat removal (ND) while the 1B ND pump was OOS for motor PMs, on March 11, 2019

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

Main article: IP 71111.05Q

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Unit 2 DG building on March 24, 2019
(2) Unit 2 motor generator set room on March 24, 2019
(3) Unit 2 ETA switchgear room on March 28, 2019
(4) Unit 2 ETB switchgear room on March 28, 2019

===71111.05XT - Fire Protection - NFPA 805 Fire Protection Inspection Requirements (IP Section 02.01a) (1 Partial) The inspectors reviewed existing documentation and engaged in discussions with licensee staff as well as NRC staff to close an open unresolved item (URI).

(1) Reviewed and closed URI 05000369, 370/2018-011-01: Question about treatment of well-sealed, robustly secured cabinets in the Fire PRA.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

Main article: IP 71111.11Q

The inspectors observed and evaluated licensed operator performance in the control room during the cool down to mode 4 during outage M1R26. Securing the 1B feedwater and 1D reactor coolant pumps was also observed on March 23, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) ===

Main article: IP 71111.05

The inspectors observed and evaluated MNS Drill 19-01 on February 13, 2019. The drill consisted of a loss of coolant accident, failed fuel, and other equipment failures.

71111.12 - Maintenance Effectiveness Quality Control (IP Section 02.02)

Main article: IP 71111.12

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities: Potential Part 21 issue with Eaton Relay CID 368228 received on January 2, 2019 (Nuclear Condition Report (NCR) 2254724) Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample) The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions: 2CF-28AB stroked slow during emergency safeguards features testing (NCR 2231060)

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

Main article: IP 71111.13

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Protection plan for the standby shutdown facility (SSF) diesel OOS for PM on January 14, 2019
(2) Protection plan for the 2B DG OOS for PM on January 22, 2019
(3) Complex plan review for the 2B diesel down day on February 5, 2019
(4) Protection plan for the 1B DG OOS for PM on February 26, 2019
(5) Protection plan for the SSF DG OOS for PM February 28, 2019

==71111.15 - Operability Determinations and Functionality Assessments Operability Determinations and Functionality Assessment Samples (IP Section 02.01) (5 Samples) The inspectors evaluated the following operability determinations and functionality assessments:

(1) NCR 2250842, Ultrasonic testing inspection at 1RNWEEFW130-45-SW, on January 3, 2019
(2) NCR 2250779, Unit 2 Safety injection pressure gauge reads high after venting, on January 15, 2019
(3) NCR 2254439, 2C T-Hot erratic indications, on January 29, 2019
(4) NCR 2253952, Common mode failure evaluation for 2A DG turbocharger surging, on January 29, 2019
(5) NCR 2255461, Oil leak on 1B diesel generator cylinder 2R valve lever shaft O-rings, on February 5, 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 modification: Engineering Change 415005, "Temporary Bypass of Sample Flow Around 2EMF-40" after failed leak test.

71111.19 - Post Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)

Main article: [[=

=IP 71111.15|count=5}}

The inspectors evaluated the following post maintenance tests:

(1) PT/0/A/4200/002, "Standby Shutdown Facility Operability Test," following SSF diesel PMs, on January 17, 2019
(2) PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test," following diesel down day maintenance on, January 24, 2019
(3) PT/2/A/4350/002 B, "Diesel Generator 2B Operability Test," following diesel down day maintenance on, February 7, 2019
(4) PT/1/A/4204/002 B, "ND Train B Valve Stroke Timing - Quarterly," functional test of 1ND-67B following PM, on March 14, 2019
(5) PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test," following maintenance fluid checks on, March 19, 2019

==71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Partial) The inspectors evaluated refueling outage M1R26 activities from March 21, 2019, to March 31, 2019.

==71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: 

==

In Service Testing (IST) (IP Section 03.01)==

Main article: IP 71111.20

PT/1/A/4252/001 A, "1A CA Pump Performance Test," on January 29, 2019

Surveillance Testing (IP Section 03.01) (4 Samples)

(1) PT/0/A/4200/002, "Standby Shutdown Facility Operability Test," on January 31, 2019
(2) PT/1/A/4350/036 B, 1B Diesel Generator 24 Hour Run, on February 11, 2019
(3) PT/2/A/4403/007, "RN Train 2A Flow Balance," on February 22, 2019
(4) PT/2/A/4350/025/022R, "Essential Auxiliary Power System Power Source Verification,"

on February 27, 2019

71114.06 - Drill Evaluation Emergency Preparedness (EP) Drill (IP Section 02.01)

Main article: IP 71114.06

The inspectors evaluated the EP drill conducted on February 13, 2019. The drill involved a tornado strike inside the protected area, followed by a loose parts alarm and large break loss of coolant accident.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified the licensee performance indicator submittals listed below: IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

Main article: IP 71151
(1) Unit 1 (January 1, 2018 - December 31, 2018)
(2) Unit 2 (January 1, 2018 - December 31, 2018)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1 (January 1, 2018 - December 31, 2018)
(2) Unit 2 (January 1, 2018 - December 31, 2018)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (January 1, 2018 - December 31, 2018)
(2) Unit 2 (January 1, 2018 - December 31, 2018)

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

Main article: IP 71152

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) NCR 02250380, A VC/YC chiller tripped upon starting
(2) Operating experience smart sample (OpESS) 2018/01, 10 CFR Part 21 notification of the potential existence of defects related to control rod drive mechanism (CRDM)thermal sleeves (NCR 02189388)

INSPECTION RESULTS

Minor Violation 71111.05XT Minor Violation: During the transition process to a new licensing basis under 10 CFR 50.48(c), the licensee failed to provide complete and accurate information in response to an NRC request for additional information. Specifically, the licensee did not justify the treatment of well-sealed and robustly secured cabinets in the Fire PRA.

Screening: The inspectors determined the performance deficiency was minor. The inspectors determined the issue to be a minor violation in accordance with the Enforcement Policy because it was determined to be less significant than a SL IV violation.

Enforcement:

This failure to comply with 10 CFR 50.9(a) constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

Unresolved Item Question about treatment of well-sealed, robustly secured 71111.05XT (Closed) cabinets in the Fire PRA.

05000369,05000370/2018011-01

Description:

URI 2018-011-01 was reviewed by regional inspectors and discussed with staff from Office of Nuclear Reactor Regulation. It was determined that the URI did represent a violation of requirements to provide an adequate response to the NRC during the transition phase to NFPA 805. While the licensee did provide a partial response, the concern raised in PRA RAI 19c was never fully addressed for all electrical cabinets that are below 440v and considered to be well-sealed and robustly secured. The inspectors determined that had the licensee fully responded to the concerned posed by the review team and fully evaluated the different methodology used, the NRC would have approved the methodology. Based on this, the inspectors screened the issue as a minor traditional enforcement violation because it did not meet any of the criteria for a SL IV or higher violation.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On April 10, 2019, the inspector presented the inspection results to Mr. Thomas Ray, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.04: Equipment Alignment OP/1/A/6350/002, Diesel Generator MCFD-1573-01.00, Flow Diagram of Component Cooling System MCFD-2574-01.00, Flow Diagram of Nuclear Service Water System MCFD-2574-01.01, Flow Diagram of Nuclear Service Water System MCFD-1561-01.00, Flow Diagram of Residual Heat Removal System 71111.05Q: Fire Protection MCS-1465.00-00-0008, Design Basis Specification for Fire Protection MCS-1465.00-00-0022, Appendix R Safe Shutdown Analysis MCC-1435.00-00-0059, NFPA 805 - Appendix R Safe Shutdown Deterministic Analysis AD-EG-ALL-1520, Transient Combustible Control MFSD-022, Unit 1 MG Set Room MFSD-007.008, Unit 2 2A and 2B Diesel Generator Rooms MFSD-018, 2ETA Room MFSD-012, 2ETB Room 71111.11: Licensed Operator Requalification Program and Licensed Operator Performance AD-OP-ALL-1000, Conduct of Operations NSD 509, Site Standards in Support of Operational Focus OMP 4.3, Use of Emergency and Abnormal Procedures and FLEX Support Guidelines SOMP 01-07, Control Room Oversight OP/A/2/6100/SD-20, Draining the NC System OP/A/2/6100/SO-1, Maintaining NC System Level OP/A/2/6100/SD-16, Preparing for NC System Drain RP/0/A/5700/000, Classification of Emergency 71111.12: Maintenance Effectiveness 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, Maintenance Rule Program AD-EG-ALL-1211, System Performance Monitoring and Trending Duke Equipment Reliability Maintenance Rule Database 71111.13: Maintenance Risk Assessments and Emergent Work Control NSD-213, Risk Management Process NSD-415, Operational Risk Management (Modes 1-3) per 10 CFR 50.65(a)(4) SOMP 02-02, Operations Roles in the Risk Management Process OMP 13-7, Operational Control of Protected Equipment AD-OP-ALL-0201, Protected Equipment 71111.15: Operability Determinations and Functionality Assessments AD-OP-ALL-0102, Operability Decision Making AD-OP-ALL-0105, Operability Determinations and Functionality Assessment 71111.18: Plant Modifications EC 415005, "Temporary Bypass of Sample Flow Around 2EMF-40" after failed leak test. AD-EG-ALL-1137, Engineering Change Product Selection 71111.19: Post-Maintenance Testing NSD-408, Testing AD-EG-ALL-1155, Post Modification Testing PT/0/A/4200/002, "Standby Shutdown Facility Operability Test" PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test" PT/2/A/4350/002 B, "Diesel Generator 2B Operability Test" PT/1/A/4204/002 B, "ND Train B Valve Stroke Timing - Quarterly" PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test" 71111.20: Refueling and Other Outage Activities McGuire M1R26 Refueling Outage Schedule OP/2/A/6100/SD-16, Preparing for NC System Drain OP/2/A/6100/SD-20, Draining the NC System OP/2/A/6100/SO-1, Maintaining NC System Level OP/1/A/6100/003, Controlling Procedure for Unit Operation OP/1/A/6100/SO-1, Maintaining NC System Level OP/1/A/6100/SO-10, Controlling Procedure for LTOP Operation 71111.22: Surveillance Testing AD-EG-ALL-1202, Preventive Maintenance and Surveillance Testing Administration AD-WC-ALL-0250, Work Implementation and Completion AD-EG-ALL-1720, In-service Testing (IST) Program Implementation 71114.06: Drill Evaluation RP/0/A/5700/000, Classification of Emergency RP/0/A/5700/002, Alert RP/0/A/5700/003, Site Area Emergency RP/0/A/5700/004, General Emergency RP/0/A/5800/010, NRC Immediate Notification Requirements RP/0/B/5700/029, Notification to Offsite Agencies from the Control Room 71151: Performance Indicator (PI) Verification AD-LS-ALL-0004, NRC Performance Indicators and Monthly Operating Report AD-PI-ALL-0100, Corrective Action Program 71152: Problem Identification and Resolution AD-PI-ALL-0100, Corrective Action Program AD-PI-ALL-0102, Apparent Cause Evaluation AD-PI-ALL-0103, Quick Cause Evaluation AD-PI-ALL-0104, Prompt Investigation Response Team AD-PI-ALL-0105, Effectiveness Reviews AD-LS-ALL-0006, Notification/Reportability Evaluation 10|= =IP 71111.15|count=5}}

The inspectors evaluated the following post maintenance tests:

(1) PT/0/A/4200/002, "Standby Shutdown Facility Operability Test," following SSF diesel PMs, on January 17, 2019
(2) PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test," following diesel down day maintenance on, January 24, 2019
(3) PT/2/A/4350/002 B, "Diesel Generator 2B Operability Test," following diesel down day maintenance on, February 7, 2019
(4) PT/1/A/4204/002 B, "ND Train B Valve Stroke Timing - Quarterly," functional test of 1ND-67B following PM, on March 14, 2019
(5) PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test," following maintenance fluid checks on, March 19, 2019

==71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Partial) The inspectors evaluated refueling outage M1R26 activities from March 21, 2019, to March 31, 2019.

==71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: 

==

In Service Testing (IST) (IP Section 03.01)==

Main article: IP 71111.20

PT/1/A/4252/001 A, "1A CA Pump Performance Test," on January 29, 2019

Surveillance Testing (IP Section 03.01) (4 Samples)

(1) PT/0/A/4200/002, "Standby Shutdown Facility Operability Test," on January 31, 2019
(2) PT/1/A/4350/036 B, 1B Diesel Generator 24 Hour Run, on February 11, 2019
(3) PT/2/A/4403/007, "RN Train 2A Flow Balance," on February 22, 2019
(4) PT/2/A/4350/025/022R, "Essential Auxiliary Power System Power Source Verification,"

on February 27, 2019

71114.06 - Drill Evaluation Emergency Preparedness (EP) Drill (IP Section 02.01)

Main article: IP 71114.06

The inspectors evaluated the EP drill conducted on February 13, 2019. The drill involved a tornado strike inside the protected area, followed by a loose parts alarm and large break loss of coolant accident.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified the licensee performance indicator submittals listed below: IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

Main article: IP 71151
(1) Unit 1 (January 1, 2018 - December 31, 2018)
(2) Unit 2 (January 1, 2018 - December 31, 2018)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1 (January 1, 2018 - December 31, 2018)
(2) Unit 2 (January 1, 2018 - December 31, 2018)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (January 1, 2018 - December 31, 2018)
(2) Unit 2 (January 1, 2018 - December 31, 2018)

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

Main article: IP 71152

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) NCR 02250380, A VC/YC chiller tripped upon starting
(2) Operating experience smart sample (OpESS) 2018/01, 10 CFR Part 21 notification of the potential existence of defects related to control rod drive mechanism (CRDM)thermal sleeves (NCR 02189388)

INSPECTION RESULTS

Minor Violation 71111.05XT Minor Violation: During the transition process to a new licensing basis under 10 CFR 50.48(c), the licensee failed to provide complete and accurate information in response to an NRC request for additional information. Specifically, the licensee did not justify the treatment of well-sealed and robustly secured cabinets in the Fire PRA.

Screening: The inspectors determined the performance deficiency was minor. The inspectors determined the issue to be a minor violation in accordance with the Enforcement Policy because it was determined to be less significant than a SL IV violation.

Enforcement:

This failure to comply with 10 CFR 50.9(a) constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

Unresolved Item Question about treatment of well-sealed, robustly secured 71111.05XT (Closed) cabinets in the Fire PRA.

05000369,05000370/2018011-01

Description:

URI 2018-011-01 was reviewed by regional inspectors and discussed with staff from Office of Nuclear Reactor Regulation. It was determined that the URI did represent a violation of requirements to provide an adequate response to the NRC during the transition phase to NFPA 805. While the licensee did provide a partial response, the concern raised in PRA RAI 19c was never fully addressed for all electrical cabinets that are below 440v and considered to be well-sealed and robustly secured. The inspectors determined that had the licensee fully responded to the concerned posed by the review team and fully evaluated the different methodology used, the NRC would have approved the methodology. Based on this, the inspectors screened the issue as a minor traditional enforcement violation because it did not meet any of the criteria for a SL IV or higher violation.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On April 10, 2019, the inspector presented the inspection results to Mr. Thomas Ray, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.04: Equipment Alignment OP/1/A/6350/002, Diesel Generator MCFD-1573-01.00, Flow Diagram of Component Cooling System MCFD-2574-01.00, Flow Diagram of Nuclear Service Water System MCFD-2574-01.01, Flow Diagram of Nuclear Service Water System MCFD-1561-01.00, Flow Diagram of Residual Heat Removal System 71111.05Q: Fire Protection MCS-1465.00-00-0008, Design Basis Specification for Fire Protection MCS-1465.00-00-0022, Appendix R Safe Shutdown Analysis MCC-1435.00-00-0059, NFPA 805 - Appendix R Safe Shutdown Deterministic Analysis AD-EG-ALL-1520, Transient Combustible Control MFSD-022, Unit 1 MG Set Room MFSD-007.008, Unit 2 2A and 2B Diesel Generator Rooms MFSD-018, 2ETA Room MFSD-012, 2ETB Room 71111.11: Licensed Operator Requalification Program and Licensed Operator Performance AD-OP-ALL-1000, Conduct of Operations NSD 509, Site Standards in Support of Operational Focus OMP 4.3, Use of Emergency and Abnormal Procedures and FLEX Support Guidelines SOMP 01-07, Control Room Oversight OP/A/2/6100/SD-20, Draining the NC System OP/A/2/6100/SO-1, Maintaining NC System Level OP/A/2/6100/SD-16, Preparing for NC System Drain RP/0/A/5700/000, Classification of Emergency 71111.12: Maintenance Effectiveness 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, Maintenance Rule Program AD-EG-ALL-1211, System Performance Monitoring and Trending Duke Equipment Reliability Maintenance Rule Database 71111.13: Maintenance Risk Assessments and Emergent Work Control NSD-213, Risk Management Process NSD-415, Operational Risk Management (Modes 1-3) per 10 CFR 50.65(a)(4) SOMP 02-02, Operations Roles in the Risk Management Process OMP 13-7, Operational Control of Protected Equipment AD-OP-ALL-0201, Protected Equipment 71111.15: Operability Determinations and Functionality Assessments AD-OP-ALL-0102, Operability Decision Making AD-OP-ALL-0105, Operability Determinations and Functionality Assessment 71111.18: Plant Modifications EC 415005, "Temporary Bypass of Sample Flow Around 2EMF-40" after failed leak test. AD-EG-ALL-1137, Engineering Change Product Selection 71111.19: Post-Maintenance Testing NSD-408, Testing AD-EG-ALL-1155, Post Modification Testing PT/0/A/4200/002, "Standby Shutdown Facility Operability Test" PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test" PT/2/A/4350/002 B, "Diesel Generator 2B Operability Test" PT/1/A/4204/002 B, "ND Train B Valve Stroke Timing - Quarterly" PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test" 71111.20: Refueling and Other Outage Activities McGuire M1R26 Refueling Outage Schedule OP/2/A/6100/SD-16, Preparing for NC System Drain OP/2/A/6100/SD-20, Draining the NC System OP/2/A/6100/SO-1, Maintaining NC System Level OP/1/A/6100/003, Controlling Procedure for Unit Operation OP/1/A/6100/SO-1, Maintaining NC System Level OP/1/A/6100/SO-10, Controlling Procedure for LTOP Operation 71111.22: Surveillance Testing AD-EG-ALL-1202, Preventive Maintenance and Surveillance Testing Administration AD-WC-ALL-0250, Work Implementation and Completion AD-EG-ALL-1720, In-service Testing (IST) Program Implementation 71114.06: Drill Evaluation RP/0/A/5700/000, Classification of Emergency RP/0/A/5700/002, Alert RP/0/A/5700/003, Site Area Emergency RP/0/A/5700/004, General Emergency RP/0/A/5800/010, NRC Immediate Notification Requirements RP/0/B/5700/029, Notification to Offsite Agencies from the Control Room 71151: Performance Indicator (PI) Verification AD-LS-ALL-0004, NRC Performance Indicators and Monthly Operating Report AD-PI-ALL-0100, Corrective Action Program 71152: Problem Identification and Resolution AD-PI-ALL-0100, Corrective Action Program AD-PI-ALL-0102, Apparent Cause Evaluation AD-PI-ALL-0103, Quick Cause Evaluation AD-PI-ALL-0104, Prompt Investigation Response Team AD-PI-ALL-0105, Effectiveness Reviews AD-LS-ALL-0006, Notification/Reportability Evaluation

10]]

[[IP sample::=

=IP 71111.15|count=5}}

The inspectors evaluated the following post maintenance tests:

(1) PT/0/A/4200/002, "Standby Shutdown Facility Operability Test," following SSF diesel PMs, on January 17, 2019
(2) PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test," following diesel down day maintenance on, January 24, 2019
(3) PT/2/A/4350/002 B, "Diesel Generator 2B Operability Test," following diesel down day maintenance on, February 7, 2019
(4) PT/1/A/4204/002 B, "ND Train B Valve Stroke Timing - Quarterly," functional test of 1ND-67B following PM, on March 14, 2019
(5) PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test," following maintenance fluid checks on, March 19, 2019

==71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Partial) The inspectors evaluated refueling outage M1R26 activities from March 21, 2019, to March 31, 2019.

==71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: 

==

In Service Testing (IST) (IP Section 03.01)==

Main article: IP 71111.20

PT/1/A/4252/001 A, "1A CA Pump Performance Test," on January 29, 2019

Surveillance Testing (IP Section 03.01) (4 Samples)

(1) PT/0/A/4200/002, "Standby Shutdown Facility Operability Test," on January 31, 2019
(2) PT/1/A/4350/036 B, 1B Diesel Generator 24 Hour Run, on February 11, 2019
(3) PT/2/A/4403/007, "RN Train 2A Flow Balance," on February 22, 2019
(4) PT/2/A/4350/025/022R, "Essential Auxiliary Power System Power Source Verification,"

on February 27, 2019

71114.06 - Drill Evaluation Emergency Preparedness (EP) Drill (IP Section 02.01)

Main article: IP 71114.06

The inspectors evaluated the EP drill conducted on February 13, 2019. The drill involved a tornado strike inside the protected area, followed by a loose parts alarm and large break loss of coolant accident.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified the licensee performance indicator submittals listed below: IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

Main article: IP 71151
(1) Unit 1 (January 1, 2018 - December 31, 2018)
(2) Unit 2 (January 1, 2018 - December 31, 2018)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1 (January 1, 2018 - December 31, 2018)
(2) Unit 2 (January 1, 2018 - December 31, 2018)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (January 1, 2018 - December 31, 2018)
(2) Unit 2 (January 1, 2018 - December 31, 2018)

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

Main article: IP 71152

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) NCR 02250380, A VC/YC chiller tripped upon starting
(2) Operating experience smart sample (OpESS) 2018/01, 10 CFR Part 21 notification of the potential existence of defects related to control rod drive mechanism (CRDM)thermal sleeves (NCR 02189388)

INSPECTION RESULTS

Minor Violation 71111.05XT Minor Violation: During the transition process to a new licensing basis under 10 CFR 50.48(c), the licensee failed to provide complete and accurate information in response to an NRC request for additional information. Specifically, the licensee did not justify the treatment of well-sealed and robustly secured cabinets in the Fire PRA.

Screening: The inspectors determined the performance deficiency was minor. The inspectors determined the issue to be a minor violation in accordance with the Enforcement Policy because it was determined to be less significant than a SL IV violation.

Enforcement:

This failure to comply with 10 CFR 50.9(a) constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

Unresolved Item Question about treatment of well-sealed, robustly secured 71111.05XT (Closed) cabinets in the Fire PRA.

05000369,05000370/2018011-01

Description:

URI 2018-011-01 was reviewed by regional inspectors and discussed with staff from Office of Nuclear Reactor Regulation. It was determined that the URI did represent a violation of requirements to provide an adequate response to the NRC during the transition phase to NFPA 805. While the licensee did provide a partial response, the concern raised in PRA RAI 19c was never fully addressed for all electrical cabinets that are below 440v and considered to be well-sealed and robustly secured. The inspectors determined that had the licensee fully responded to the concerned posed by the review team and fully evaluated the different methodology used, the NRC would have approved the methodology. Based on this, the inspectors screened the issue as a minor traditional enforcement violation because it did not meet any of the criteria for a SL IV or higher violation.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On April 10, 2019, the inspector presented the inspection results to Mr. Thomas Ray, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.04: Equipment Alignment OP/1/A/6350/002, Diesel Generator MCFD-1573-01.00, Flow Diagram of Component Cooling System MCFD-2574-01.00, Flow Diagram of Nuclear Service Water System MCFD-2574-01.01, Flow Diagram of Nuclear Service Water System MCFD-1561-01.00, Flow Diagram of Residual Heat Removal System 71111.05Q: Fire Protection MCS-1465.00-00-0008, Design Basis Specification for Fire Protection MCS-1465.00-00-0022, Appendix R Safe Shutdown Analysis MCC-1435.00-00-0059, NFPA 805 - Appendix R Safe Shutdown Deterministic Analysis AD-EG-ALL-1520, Transient Combustible Control MFSD-022, Unit 1 MG Set Room MFSD-007.008, Unit 2 2A and 2B Diesel Generator Rooms MFSD-018, 2ETA Room MFSD-012, 2ETB Room 71111.11: Licensed Operator Requalification Program and Licensed Operator Performance AD-OP-ALL-1000, Conduct of Operations NSD 509, Site Standards in Support of Operational Focus OMP 4.3, Use of Emergency and Abnormal Procedures and FLEX Support Guidelines SOMP 01-07, Control Room Oversight OP/A/2/6100/SD-20, Draining the NC System OP/A/2/6100/SO-1, Maintaining NC System Level OP/A/2/6100/SD-16, Preparing for NC System Drain RP/0/A/5700/000, Classification of Emergency 71111.12: Maintenance Effectiveness 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, Maintenance Rule Program AD-EG-ALL-1211, System Performance Monitoring and Trending Duke Equipment Reliability Maintenance Rule Database 71111.13: Maintenance Risk Assessments and Emergent Work Control NSD-213, Risk Management Process NSD-415, Operational Risk Management (Modes 1-3) per 10 CFR 50.65(a)(4) SOMP 02-02, Operations Roles in the Risk Management Process OMP 13-7, Operational Control of Protected Equipment AD-OP-ALL-0201, Protected Equipment 71111.15: Operability Determinations and Functionality Assessments AD-OP-ALL-0102, Operability Decision Making AD-OP-ALL-0105, Operability Determinations and Functionality Assessment 71111.18: Plant Modifications EC 415005, "Temporary Bypass of Sample Flow Around 2EMF-40" after failed leak test. AD-EG-ALL-1137, Engineering Change Product Selection 71111.19: Post-Maintenance Testing NSD-408, Testing AD-EG-ALL-1155, Post Modification Testing PT/0/A/4200/002, "Standby Shutdown Facility Operability Test" PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test" PT/2/A/4350/002 B, "Diesel Generator 2B Operability Test" PT/1/A/4204/002 B, "ND Train B Valve Stroke Timing - Quarterly" PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test" 71111.20: Refueling and Other Outage Activities McGuire M1R26 Refueling Outage Schedule OP/2/A/6100/SD-16, Preparing for NC System Drain OP/2/A/6100/SD-20, Draining the NC System OP/2/A/6100/SO-1, Maintaining NC System Level OP/1/A/6100/003, Controlling Procedure for Unit Operation OP/1/A/6100/SO-1, Maintaining NC System Level OP/1/A/6100/SO-10, Controlling Procedure for LTOP Operation 71111.22: Surveillance Testing AD-EG-ALL-1202, Preventive Maintenance and Surveillance Testing Administration AD-WC-ALL-0250, Work Implementation and Completion AD-EG-ALL-1720, In-service Testing (IST) Program Implementation 71114.06: Drill Evaluation RP/0/A/5700/000, Classification of Emergency RP/0/A/5700/002, Alert RP/0/A/5700/003, Site Area Emergency RP/0/A/5700/004, General Emergency RP/0/A/5800/010, NRC Immediate Notification Requirements RP/0/B/5700/029, Notification to Offsite Agencies from the Control Room 71151: Performance Indicator (PI) Verification AD-LS-ALL-0004, NRC Performance Indicators and Monthly Operating Report AD-PI-ALL-0100, Corrective Action Program 71152: Problem Identification and Resolution AD-PI-ALL-0100, Corrective Action Program AD-PI-ALL-0102, Apparent Cause Evaluation AD-PI-ALL-0103, Quick Cause Evaluation AD-PI-ALL-0104, Prompt Investigation Response Team AD-PI-ALL-0105, Effectiveness Reviews AD-LS-ALL-0006, Notification/Reportability Evaluation 10| ]]

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