Text

NRC Triennial Fire Protection Inspection Report Nos.. 05000369/2018011 and 05000370/2018011
	ML18183A584
Person / Time
Site:	McGuire, Mcguire
Issue date:	06/29/2018
From:	Scott Shaeffer; NRC/RGN-II/DRS/EB2
To:	Teresa Ray; Duke Energy Carolinas
References
	IR 2018011
	Download: ML18183A584 (13)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION une 29, 2018

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - NRC TRIENNIAL FIRE PROTECTION INSPECTION REPORT NOS. 05000369/2018011 AND 05000370/2018011

Dear Mr. Ray,

On May 17, 2018, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your McGuire Nuclear Station, Units 1 and 2 and 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/

Scott M. Shaeffer, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos: 50-369; 50-370 License Nos: NPF-9 and NPF-17

Enclosure:

Inspection Report 05000369/2018011 and 05000370/2018011 w/Attachment: Supplemental Information

REGION II==

Docket Nos: 50-369, 50-370 License No: NPF-9, NPF-17 Report No: 05000369/2018011 and 05000370/2018011 Enterprise Identifier: I-2018-011-0023 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station, Units 1 and 2 Location: Huntersville, NC 28078 Dates: April 30 - May 4, 2018 (Week 1)

May 14-17, 2018 (Week 2)

Inspectors: P. Braaten, Reactor Inspector J. Dymek, Reactor Inspector T. Grice, Senior Fuel Facility Inspector (Week 1 Only)

J. Montgomery, Senior Reactor Inspector (Lead Inspector)

D. Strickland, Reactor Inspector Approved by: Scott M. Shaeffer, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

The U.S. NRC continued monitoring licensees performance by conducting a triennial fire protection inspection (TFPI) 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.

List of Findings and Violations No findings were identified.

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/inspectionprocedure/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.

REACTOR SAFETY

===71111.05XT - Fire Protection - NFPA 805 (Triennial)

The inspectors evaluated the following from April 30, 2017 - May 17, 2017:

Fire Protection Inspection Requirements ===

Main article: IP 71111.05

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

(1) FA 2, Unit 1 Motor Driven CA Pump Room

(2) FA 2A , Unit 1 Turbine Driven CA Pump Room

(3) FA 9-11, Unit 1 B Train Electrical Pen Room & Switchgear Room

(4) FA 14, Aux Building Common-Elevation 733

B.5.b Inspection Activities (1 Sample)

The inspectors evaluated feasibility of the following B.5.b Mitigating Strategies:

(1) Spent Fuel Pool External Makeup

INSPECTION RESULTS

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

Description:

Inspectors identified an unresolved item (URI) associated with how the site calculated fire frequencies of electrical cabinets in the fire PRA. The site retained floor-mounted electrical cabinets characterized as well-sealed and robustly-secured as ignition sources in the fire PRA. The guidance of NUREG-6850, which the site is committed to, instructs that electrical cabinets housing voltages less than 400V, and that are characterized as well-sealed and robustly secured not be counted as ignition sources. This is because the fire PRA should only consider fires that can propagate to other combustibles and targets, and by including ignition sources that cannot propagate to other combustibles and targets, the frequency of fires in other electrical cabinets that can actually propagate could be erroneously lowered.

Inspectors noted that retaining floor-mounted cabinets characterized as well-sealed and robustly-secured appeared to not be in alignment with the sites NFPA 805 submittal, and associated SE, which each contain information specific to the question about how well-sealed robustly secured cabinets were treated in the fire PRA. The SE states, Regarding the counting of well-sealed, robustly-secured electrical cabinets having circuits less than 440V, the licensee stated in its response to PRA RAI 03.b.01 that it updated the FPRA to remove cabinets meeting this definition. The site has asserted that this statement in the SE is incorrect, and does not align with what the site submitted on the docket as a part of their NFPA 805 submittal.

Planned Closure Action(s): This issue is being characterized as a URI, pending a decision from NRR as to the interpretation of the sites submittal regarding treatment of floor-mounted well-sealed and robustly-secured cabinets, and the accuracy of the associated SER.

NRC Tracking Number: 05000369,370/2018-011-01

EXIT MEETINGS AND DEBRIEFS

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

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

On May 17, 2018, the lead inspector presented the preliminary inspection results to Mr. T. Ray and other members of the licensees staff.

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

J. Brady, Reg. Affairs

J. Campellone, Appendix R/NFPA 805 Engineer

G. Carpenter, Fire Protection Engineer

C. Chan, Fleet Risk Informed Fire Protection

E. Forster, PRA

B. Richards, Regulatory Affairs Lead

S. Rodgers, Fire Protection Engineer

B. Weaver, PRA

NRC Personnel

A. Hutto, Senior Resident Inspector

S. Shaeffer, Chief, Engineering Branch 2, DRS, Region II

LIST OF COMPONENTS REVIEWED

Component Identification Description

1NC-VA0027C A Loop Pressurizer Spray Control

1NC-VA0029C 1B NC Loop Pressurizer Spray Control

1NC-VA0272AC A Train Head Vent to PRT Isolation

1NC-VA0237AC A Train Head Vent to PRT Isolation

1SM-P5140 SG B Steam Line Pressure Channel #3

1SM-P5150 SG C Steam Line Pressure Channel #1

1SM-P5160 SG C Steam Line Pressure Channel #3

1SM-VA0001AB 1D Steam Isolation

1SM-VA0003ABC C Steam Isolation

1SM-VA0005AB B Steam Isolation

1SM-VA0007AB A Steam Isolation

1SV-VA0001AB 1D Steam PORV

1SV-VA0007ABC C Steam PORV

1SV-VA0013AB B Steam PORV

1SV-VA0019AB 1A Steam PORV

Procedures

AD-EG-ALL-1132, Preparation and Control of Design Change Engineering Changes, Rev. 10

AD-EG-ALL-1502, Fire Protection Impact Screening for Plant Design Changes, Rev. 0

AD-EG-ALL-1503, National Fire Protection Association (NFPA) 805 Monitoring, Rev. 1

IP-0-A-3090-010, Sealing Safety-Related Equipment Outside Containment and Doghouses,

Rev. 33

IP-0-A-3090-010-A, Non QA Condition 1 Electrical Enclosure Cable Entry Sealing, Rev. 5

AD-OP-ALL-1001, Conduct of Abnormal Operations, Rev. 1

OP/0/A/6100/020, Operational Guidelines Following a Fire in Auxiliary Building or Vital Area,

Rev. 031

OMP 5-8, Shift Supervisor Turnovers, Rev. 068

PT/0/A/4600/113, Operator Time Critical Task Verification, Rev. 026

MCC-1435-00-00-0022, Fire Protection Manual Action Feasibility and Reliability Demonstration,

1/25/2011

OMP 4-4, Procedure Development Process and Activities, Rev. 002

PT/1/A/4700/011, Auxiliary Plant Panels Document File Verification, Rev. 058

MCC-1435-00-00-0043, NFPA 805 TransitionNPO, Rev. 002

MCC-1435-00-00-0044, NFPA 805 TransitionNPO component Selection, Rev. 11

AD-WC-ALL-0420, Shutdown Risk Management, Rev. 3

OP/0/B/6400/002D, Flex Hale Pump (Low Pressure) Operation, Rev. 009

PT/1/A/4600/030, Cycling Time Critical Manual Valves, Rev. 14

AP/0/A/5500/45, Plant Fire, Rev. 19

APB-AP-45, Basis Document for AP/0/A/5500/045 (Plant Fire), Rev 001

AP/1/A/5500/24, Loss of Plant Control Due to Fire or Sabotage, Rev. 35

APB-AP-24, Basis Document for Loss of Plant Control Due to Fire or Sabotage, Rev. 02

PT/0/A/4600/112, Exterior/Interior Fire Equipment Inspection, Rev. 009

AD-EG-ALL-1501, Fire Protection Change Process, Rev. 1

AD-EG-ALL-1520, Transient Combustible Control, Rev. 9

AD-EG-ALL-1521, Hot Work Permits, Rev. 5

AD-EG-ALL-1522, Duties of a Fire Watch, Rev. 5

AD-EG-ALL-1531, Selection, Care and Maintenance of Fire Ensembles, Rev. 0

AD-MN-ALL-0015, Nuclear station Scaffold Erection, Tracking and Dismantling, Rev. 12

AD-TQ-ALL-0086, Fire Brigade Training, Rev. 5

PD-EG-ALL-1500, Fleet Fire Protection Program Manual, Rev. 1

NSD-316, Fire Protection Impairment and Surveillance, Rev. 18

Calculations, Evaluations, & Specifications

MCC-1205.19-00-0084, Evaluation of the Effects of IN 92-18 on Motor Operated Valves, Rev. 5

MCC-1381.05-00-0335, Unit 1/2, NFPA 805 Circuit Breaker and Fuse Coordination Study,

Rev. 21

MCC-1435.00-00-0023, NFPA 805 Transition Expert Panel Report for Addressing Potential

McGuire Multiple Spurious Operations, Rev. 4

MCC-1435.00-00-0025, Nuclear Safety Capability Assessment (NSCA) for Fire Protection Safe

Shutdown Analysis in Support of NFPA 805 Transition, Rev. 2

MCC-1435.00-00-0026, NFPA 805 Transition Existing Engineering Equivalency Evaluations,

Rev. 5

MCC-1435.00-00-0041, NFPA 805 Transition Risk-Informed Performance-Based Fire Risk

Evaluations, Rev. 4

MCS-1465.00-00-0008, Plant Design Basis Specification for Fire Protection, Rev. 23

MCC-1223.49-00-0031, Sprinkler System for Component Cooling Pumps @ Elevation 733-0,

Rev. 10

MCC-1206.47-69-1001, Auxiliary Building Flooding Analysis, Rev. 21

MCC-1435.03-00-0013, Fire Protection Code Deviations, Rev. 6

MCC-1435.03-00-0014, Generic Letter 86-10 Evaluations for Fire Protection Features, Rev. 11

MCC-1435.00-00-0026, NFPA 805 Transition Existing Engineering Equivalency Evaluations,

Rev. 5

MCC-1435.00-00-0027 Transition Licensing Action Review, Rev. 4

MCC-1435.00-00-0028, NFPA Transition-NEI 04-02, B-1 Table/Report, Rev. 8

MCC-1435.00-00-0031, NFPA 12A Code Conformance Review, Turbine-Driven Auxiliary Feed

Water Pump Room, Rev. 1

MCS 1599.RF-00-0001, Design Basis Specification for the RF/RY System, Rev.027

MCS-376.00-EFA-0001, Design Basis Specification for the EFA System, Rev. 015

MCC-1535.00-00-0101, MNS Fire PRA Partitioning and Frequency Calculation, Rev. 3

MCC-1535.00-00-0104, MNS Fire PRA Scenario Calculation, Rev. 4

MCC-1535.00-00-0106, MNS Fire PRA Summary Report Calculation, Rev. 6

MCC-1535.00-00-0169, MNS FPRA (Fire PRA) Input for Fire Risk Evaluations, Rev. 3

MCC-1435.00-00-0024, NFPA 805 Transition - NEI 04-02 B-3 Table Fire Area Transition,

Rev. 6

MCC-1435.00-00-0021, NFPA 805 Transition NEI 04-02 B-2 Table - Nuclear Safety Capability

Assessment Methodology Review, Rev. 5

MCC-1435.00-00-0045, NFPA 805 Transition Recovery Action Feasibility Study, Rev. 2

Work Orders

WO 2004576101, Inspect Fire Barriers (Walls, Ceiling & Floors), 7/7/2016

WO 2005652601, Halon 1301 System Periodic Test, 10/26/2016

WO 2007557401, Main Fire Pump A, 11/3/2016

WO 2007858201, Test Fire Zones, 12/1/2016

WO 2015602361, Inspect Fire Doors, 2/27/2017

WO 2017144601, Fire Detection System Operational Tests for Auxiliary Building Elevation

733-0 and 750-0, 2/28/2018 and 3/7/2018

PT/0/A/4250/011, Inspect Fire Doors, 10/22/2017

PT/0/A/4400/001M, Fire Protection System Flow Test, 10/18/2017

PT/0/A/4400/001T, Fire Protection System Auxiliary Building Flush, 9/8/2015

PT/0/A/4400/010B, Main Fire Pump B, 3/7/2017

PT/0/A/4400/010C, Main Fire Pump C, 12/8/2017

TP/1/A/11400/05C, Halon Test Gas Discharge for Unit 1 CA Pump, 12/11/1979 & 12/18/1979

Drawings

MC-1202-02.0A, Auxiliary Building Units 1 & 2 - Floor El. 733+0 General Arrangement Plan

Sheet 1 of 2, Rev. 50

MC-1202-03.0A, Auxiliary Building Units 1 & 2 - Floor El. 733+0 General Arrangement Plan

Sheet 2 of 2, Rev. 48

MC-1201-04.0A, Auxiliary Building Floor El 716+0 General Arrangement, Rev. 40

MC-1202-05.0A, Auxiliary Building Units 1 & 2 - Floor El 733+0 General Arrangement

Switchgear Room Plans, Rev. 55

MC-1705-01.01, One Line Diagram 125 VDC / 120 VAC Vital Instr and Control Pwr Sys,

Rev. 39

MC-1713-10.04, Connection Diagram Right Back Half Input Cabinet 1IC10, Rev. 21

MC-1716-01.01, Outline & Fabrication Details Auxiliary Shutdown Panel, Rev. 24

MC-1716-01.02, Outline & Fabrication Details Auxiliary Shutdown Panel, Rev. 10

MC-1716-02.03, Connection Diagram Standby Shutdown Facility Control Panel SSFCP,

Rev. 46

MC-1716-04.04, Connection Diagram Standby Shutdown Facility Auxiliary Relay Cabinet

ISSFARC Right Half, Rev. 22

MC-1731-01.02, Connection Diagram Reactor Coolant System Solenoid Operated Valves,

Rev. 20

MC-1759-01.01, Interconnection Diagram 125VDC Distribution Ctr. No. EVDA Units 1 Thru 3

1-EVDA-1 & 2-EVDA-1 Unit 1, Rev. 27

MC-1767-06.06, Connection Diagram Reactor Bldg. Penetrations Type G Penetrations

Penetration Nos E312, E397, Rev. 22

MCEE-150-00.29, Elementary Diagram Reactor Vessel Vent Head System Soleniod [sic] Valve

1NC272A, Rev. 8

MCEE-150-00.32-01, Elementary Diagram Reactor Vessel Vent Head System HFD Breaker

w/ KKI Power Circuit 1EVDA1-1A & 1EVDA1-1B, Rev. 3

MCEE-150-00.32, Reactor Vessel Vent Head System SSF Controls PWR Transfer & Alarm

Relays, Rev. 6

MCEE-150-00.33, Elementary Diagram Reactor Vessel Vent Head System SSF Controls for

Sol. VLV

S. 1NC272A & 273A, Rev. 4

MC-1220-12, Unit 1 Flow Diagram of Auxiliary Building Units 1&2 Floor Drain Layout, Rev. 10

MCFD-1592-01.00, Unit 1 Flow Diagram of Auxiliary Feedwater System, Rev. 9

MCFD-1592-01.01, Unit 1 Flow Diagram of Auxiliary Feedwater Systems, Rev. 34

MCFD-1553-01.00, Unit 1 Flow Diagram of Reactor Coolant System, Rev. 12

MCFD-2553-01-00, Unit 2 Flow Diagram of Reactor Coolant System, Rev. 18

MCFD-1554-01.03, Unit 1 Flow Diagram of Chemical and Volume Control System, Rev. 4

MCFD-1574-01.00, Unit 1 Flow Diagram of Nuclear Service Water System, Rev. 32

MCFD-2593-01.03, Unit 2 Flow Diagram of Main steam Main Steam Vent to Atmosphere,

Rev. 18

OP-MC-PS-NV, from McGuire Operations Training (Page 125 of 155), NV System Composite,

Rev. 58

OP-MC-PS-NC, from McGuire Operations Training (Page 109 of 137), Reactor Head Vents,

Rev. 36

MC-1201-02.0A, Auxiliary Building Unit 1 & 2, Floor Elevation 716-0, General Arrangement

Plan, Rev. 69

MC-1202-02.0A, Auxiliary Building Unit 1 & 2, Floor Elevation 733-0, General Arrangement

Plan, Rev. 50

MC-1315-05.01-005, Penetration Seal Configuration Electrical Penetration Seal Firestop Design

Detail E-9, Rev. 0

MC-1315-06.01-005, Penetration Seal Configuration Electrical Penetration Seal Firestop Design

Detail M-6, Rev. 0

MC-1315-06.01-006, Penetration Seal Configuration Electrical Penetration Seal Firestop Design

Detail M-8, Rev. 0

MC-1418, Piping Layout system RF, Plan @ Elevation 733-0, Auxiliary Building, Rev. 34

MC-1522-01.43-00, HVAC Auxiliary Building CA Pump Room Duct Layout @ Elevation 716-0

MCM-1182.00-0131.001, Doors PD1 and PD2

MCFD-1599-01.00, Flow Diagram of the Fire Protection System (RF/RY), Rev. 19

MCFD-1599-02.00, Flow Diagram of the Fire Protection System (RF/RY), Rev. 26

MCFD-1599-02.01, Flow Diagram of the Fire Protection System (RF/RY), Rev. 18

Fire Fighting Preplan Strategies

Pre-Fire Plan, Unit 1 & 2 Auxiliary Building: Fire Areas 2 & 2A, Rev. 0

Pre-Fire Plan, Unit 1 & 2 Auxiliary Building: Fire Areas 9-11, Rev. 0

Pre-Fire Plan, Unit 1 & 2 Auxiliary Building: Fire Areas 14, Rev. 0

Technical Manuals, Vendor Information

ECN 0299, Operations and Service Maintenance Manual, RSD Single Stage Pump, Rev. A

Audits & Self-Assessments

2018-MNS-FIRE-01, Nuclear Oversight Audit - McGuire Fire Protection

1940066, MNS NFPA 805 Implementation Readiness Self-Assessment

AR 2176788-05, MNS 2018 NRC TFPI Readiness Assessment

License Basis Documents

Safety Evaluation Report (SER) by the Office on Nuclear Reactor Regulation (NRR) Related to

Transition to a Risk Informed, Performance Based Fire Protection Program in Accordance with

CFR 50.48(C), 12/06/2016

Duke Energy Carolinas LLC, McGuire Nuclear Station, Transition to 10 CFR 50.48(C),

1NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Electric

Generating Plants 2001 Edition, Transition Report, September 2013

Duke Energy Carolinas LLC, McGuire Nuclear Station supplemental letters dated January 8,

2014; October 13, 2014; November 12, 2014; December 12, 2014; January 26, 2015;

February 27, 2015; March 13, 2015; July 15, 2015; August 20, 2015; September 9, 2015;

October 1, 2015; January 14, 2016; April 26, 2016; September 29, 2016; and November 21,

2016

McGuire Nuclear Station Operating License NPF-9 and NPF-17

National Fire Protection Association Standard 805, Performance Based Standard for Fire

Protection for Light Water Reactor Electric Generating Plants, 2001 Edition

IR 05000369/2018011

Text

SUBJECT:

Dear Mr. Ray,

Enclosure:

SUMMARY

INSPECTION SCOPES

REACTOR SAFETY

B.5.b Inspection Activities (1 Sample)

INSPECTION RESULTS

Description:

EXIT MEETINGS AND DEBRIEFS

SUPPLEMENTARY INFORMATION

Licensee Personnel

NRC Personnel

Navigation menu

IR 05000369/2018011

Text

SUBJECT:

Dear Mr. Ray,

Enclosure:

SUMMARY

INSPECTION SCOPES

REACTOR SAFETY

B.5.b Inspection Activities (1 Sample)

INSPECTION RESULTS

Description:

EXIT MEETINGS AND DEBRIEFS

SUPPLEMENTARY INFORMATION

Licensee Personnel

NRC Personnel

Navigation menu

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