IR 05000269/2018001

From kanterella
Jump to navigation Jump to search
NRC Integrated Inspection Report 05000269/2018001, 05000270/2018001, and 05000287/2018001
ML18123A311
Person / Time
Site: Oconee  Duke energy icon.png
Issue date: 05/03/2018
From: Frank Ehrhardt
NRC/RGN-II/DRP/RPB1
To: Burchfield J
Duke Energy Corp
References
IR 2018001
Download: ML18123A311 (15)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION May 3, 2018

SUBJECT:

OCONEE NUCLEAR STATION - NRC INTEGRATED INSPECTION REPORT 05000269/2018001, 050000270/2018001, AND 05000287/2018001

Dear Mr. Burchfield:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Oconee Nuclear Station Units 1, 2 and 3. On April 12, 2018, 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 Jannette Worosilo Acting for/

Frank Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55

Enclosure:

IR 05000269/2018001, 05000270/2018001, and 05000287/2018001

Inspection Report

Docket Numbers: 50-269, 50-270, 50-287 License Numbers: DPR-38, DPR-47, DPR-55 Report Numbers: 05000269/2018001, 05000270/2018001, and 05000287/2018001 Enterprise Identifier: I-2018-001-0060 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station, Units 1, 2, and 3 Location: Seneca, SC Inspection Dates: January 1, 2018 to March 31, 2018 Inspectors: E. Crowe, Senior Resident Inspector N. Childs, Resident Inspector J. Parent, Resident 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 licensee performance by conducting a quarterly baseline inspection at Oconee Nuclear Station Units 1, 2, and 3 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. No findings were identified during this inspection period.

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.

Unit 3 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 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

71111.01 - Adverse Weather Protection Seasonal Extreme Weather

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures.

Impending Severe Weather (1 Sample)

The inspectors evaluated readiness for impending adverse weather conditions for freezing rain and extreme cold from January 2, 2018, through January 7, 2018.

71111.04 - Equipment Alignment Partial Walkdown

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

(1) Unit 1, 2, and 3 emergency feedwater system, auxiliary service water system, and low pressure service water system alignment during planned protected service water primary and booster pump tests on February 2, 2018
(2) Unit 1, 2, and 3 4160kV safety related electrical distribution systems, standby feeder buses, Lee combustion turbine alignment during planned maintenance to transformer CT-4 on February 6, 2018
(3) Unit 1, 2, and 3 13.8kV safety related electrical distribution system (underground path)alignment during planned maintenance on Keowee Unit 2 on February 13, 2018
(4) Unit 1, 2, and 3 safety-related electrical distribution system alignment and Keowee Hydro Unit-1 during annual maintenance outage of standby shutdown facility (SSF) on February 20-23, 2018
(5) Unit 1, 2, and 3 control room ventilation alignment during troubleshooting of B chiller failure to run on March 11, 2018

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the primary instrument air system on March 26, 2018.

71111.05AQ - Fire Protection Annual/Quarterly Quarterly Inspection

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

(1) Fire Zone 29 - Unit 3 turbine building 4160V switchgear on January 12, 2018
(2) Fire Zone 33 - Unit 2 turbine building 4160V switchgear on January 12, 2018
(3) Fire Zone KHS-001 - Keowee hydro station on February 8, 2018
(4) Fire Zone 53 - Unit 1 & Unit 2 low pressure injection/reactor building spray pump room on February 14, 2018
(5) Fire Zone 57 - Unit 1 purification and deborating demineralizers on February 14, 2018

Annual Inspection (1 Sample)

The inspectors evaluated fire brigade performance on January 12, 2018.

71111.06 - Flood Protection Measures Cables

The inspectors evaluated cable submergence protection in CT5 trench on March 15, 2018.

71111.07 - Heat Sink Performance Heat Sink

The inspectors evaluated the SSF diesel generator jacket water heat exchangers (A and B)performance in January 2018

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

The inspectors observed and evaluated an in-progress annual requalification operating test on

===March 7, 2018.

Operator Performance (1 Sample)===

The inspectors observed and evaluated a Unit 1 power reduction in support of performing a turbine valve movement test on March 23, 2018.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Units 1, 2, and 3 air handling unit flow limiting valve (0LPSW-846) catastrophic failure due to a water hammer event

71111.13 - Maintenance Risk Assessments and Emergent Work Control

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

(1) Yellow risk changed to green risk condition on Units 1, 2, and 3 during planned testing of the protected service water primary and booster pumps on February 1, 2018
(2) Green risk condition on Units 1, 2, and 3 during planned maintenance on transformer CT-4 on February 6, 2018
(3) Yellow risk condition on Unit 1 during emergent issue (water in lubricating oil) of turbine driven emergency feedwater pump on February 13, 2018
(4) Yellow risk condition on Units 1, 2, and 3 during annual maintenance outage of SSF on February 20 - 23, 2018
(5) Projected Yellow risk on Unit 3 during planned SSF monthly outage along with planned replacement of PCB-33 (autobank tie to 230kV yellow bus) and 3A LPI pump preventive maintenance on March 20, 2018

71111.15 - Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Unit 1, SSF reactor coolant makeup pump tripped during performance test on January 3, 2018
(2) Unit 1, turbine driven emergency feedwater pump turbine inboard seal cavity full of water on February 13, 2018
(3) Units 1, 2, and 3 low pressure service water (LPSW) valves LPSW 1111 and 1116 condition monitoring requirements not met on February 19, 2018
(4) Unit 3 low pressure injection piping variable load spring support out of tolerance on February 21, 2018
(5) Units 1, 2, and 3 SSF air handling unit (0-42) oil differential pressure higher than normal on February 22, 2018
(6) Units 1, 2, and 3 SSF diesel generator overspeed test failures on February 23, 2018
(7) Unit 2, main feeder bus normal feeder electrical breaker N2-1 charging spring motor continuously operating on March 6, 2018
(8) Unit 3, reactor protection system Channel C watchdog timer failure in central processing unit 3311 on March 7, 2018

71111.19 - Post Maintenance Testing

The inspectors evaluated the following post-maintenance tests:

(1) PT/0/A/0610/022, Degraded Grid and Switchyard Isolation Test on January 10, 2018
(2) PT/1/A/0600/012, Turbine Driven Emergency Feedwater Pump Test following draining of oil with high water content on February 14, 2018
(3) PT/2/A/0150/057, RB Pressure Switches and Associated Transmitters Leak Rate Test following replacement of 2BS-PT-0230 on February 15, 2018
(4) PT/2/A/0150/057, RB Pressure Switches and Associated Transmitters Leak Rate Test following replacement of 2BS-PT-0231 on February 16, 2018
(5) OP/0/A/1600/009 SSF Auxiliary Service Water System Test following annual maintenance on February 24, 2018
(6) PT/0/A/0600/021, Standby Shutdown Facility Diesel-Generator Operation following annual maintenance on February 24, 2018
(7) PT/2/A/0152/035, 2PSW-22 and 2PSW-24 Valve Stroke Test following 2PSW-22 actuator replacement on March 14, 2018
(8) OP/0/A/1600/010, SSF Diesel-Generator Operational Test following troubleshooting and relay replacements on March 23, 2018

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

(1) IP/0/A/3000/003 KB1, Keowee Hydro Station Battery 1 Service Test and Annual Surveillance, conducted on January 10, 2018
(2) PT/2/A/0600/012, Turbine Driven Emergency Feedwater Pump Test, conducted on January 31, 2018
(3) PT/0/A/0500/001, Protected Service Primary and Booster Pump Test, conducted on February 1, 2018
(4) PT/3/A/0202/011, High Pressure Injection Pump Test, conducted on February 7, 2018
(5) IP/0/A/4980/081 E, ABB Type 81 Relay Test, performed on Keowee Unit 2 relay K2ELK-RL-81X2, conducted on February 13, 2018
(6) IP/0/A/4980/081 E, ABB Type 81 Relay Test, performed on Keowee Unit 2 relay K2ELK-RL-81Y2, conducted on February 13, 2018

In-service (1 Sample)

(1) PT/1/A/0204/007, Reactor Building Spray Pump Test, conducted on January 16, 2018

Reactor Coolant System Leak Detection (1 Sample)

(1) PT/1/A/0600/010, Reactor Coolant Leakage (Unit 1), on January 18, 2018

71114.06 - Drill Evaluation Drill/Training Evolution

The inspectors evaluated an emergency preparedness drill which involved an increase in radiological levels in the central alarm station and a Unit 2 trip which was caused by a loss of 125 VDC power, all resulting in a site area emergency being declared on January 19,

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification The inspectors verified licensee performance indicator submittals listed below for the period from March 2017 through March 2018.

(1) Unplanned Scrams per 7000 Critical Hours
(2) Unplanned Power Changes per 7000 Critical Hours
(3) Unplanned Scrams with Complications

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 April 12, 2018, the inspector presented the inspection results to Mr. J. Ed Burchfield, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.01: Adverse Weather Protection

Nuclear Condition Report

2169114; 02174700

Procedures

OP/0/A/1104/037, Plant Heating, Rev. 004

OP/0/A/1104/041, Auxiliary Building Ventilation, Rev. 041

OP/0/A/1106/041, Turbine Building Ventilation, Rev. 007

OP/0/A/1600/002, Standby Shutdown Facility Heating, Ventilation and Air Conditioning System

Operation (HVAC), Rev. 037

OP/0/B/1104/050, Weather Related Activities, Rev. 005

OP/1/A/1104/051, ESV System, Rev. 028

OP/2/A/1104/051, ESV System, Rev. 040

OP/3/A/1104/051, ESV System, Rev. 028

PT/0/A/0110/017, Cold Weather Protection, Rev. 013

RP/0/A/1000/035, Severe Weather Preparations, Rev. 003

Work Orders/Requests

20091981; 20157474

71111.04: Equipment Alignment

Documents

AD-OP-ALL-0201, Protected Equipment, Rev. 3

OSS-0254.00-00-1021, Design Basis Specification for the Control Room Ventilation System

Oconee Nuclear Site Technical Specifications, amended August 13, 2014

Oconee Nuclear Site Technical Specifications Bases, updated June 3, 2011

OC-SSS-IA-14, Compressed Air Composite, dated April 15, 2009

Drawings

O-0705, Rev. 104

O-1705, Rev. 87

O-2705, Rev. 87

OFD-166J-1.2, Rev 15

OFD-116J-1.5, Rev. 24

OFD-116J-1.6, Rev 20

OFD-121D-1.1, Rev. 38

OFD-121D-2.1, Rev. 39

OFD-121D-3.1, Rev. 46

OFD-124A-1.2, Rev 55

OFD-124B-1.1, Rev. 67

OFD-124B-2.1, Rev. 76

OFD-124B-3.1, Rev. 61

OFD-133A-2.5, Rev. 58

OFD-137B-1.1, Rev. 26

OFD-137B-1.2, Rev. 27

OFD-144A-1.1, Rev. 16

OFD-144A-1.2, Rev. 15

OFD-144A-1.3, Rev. 10

OFD-144A-1.4, Rev. 10

Enclosure

Nuclear Condition Report

2114841; 02119628; 02137156; 02138440; 02139231; 02149244; 02162787

Procedures

MP/0/A/3007/054 A, Chillers - A and B - York - Codepak - Preventive Maintenance (QA-5),

Rev. 034

OP/0/A/1106/019, Keowee Hydro at Oconee, Rev. 104

OP/A/1106/027, Instrument Air System, Rev. 120

PT/0/A/0500/001, Protected Service Water Primary and Booster Pump Test, Rev. 003

PT/0/A/0620/009, Keowee Hydro Operation, Rev. 052

Work Orders/Requests

20085997; 20095495; 20104045; 20104322; 20112663; 20118654; 20126636; 20182563;

20185924; 20192286; 20208815; 20220075

71111.05AQ: Fire Protection

Documents

Oconee Nuclear Station Fire Brigade Drill, Drill # 2 Main Power Battery - 1A

Nuclear Condition Report

2174700; 02176943

Other

O-FS-0-OC-9000-003, Pre-Fire Plan for Keowee Hydro Station, Rev. 1

O-FS-1-AB-9758-001, Pre-Fire Plan for Unit 1 & 2 Auxiliary Building Elevation 758, Rev. 002

O-FS-1-AB-9783-001, Pre-Fire Plan for Unit 1 Auxiliary Building Elevation 783, Rev. 002

O-FS-2-TB-9796-001, Pre-Fire Plan for Unit 2 Turbine Building Elevation 796, Rev. 001

O-FS-3-TB-9796-001, Pre-Fire Plan for Unit 3 Turbine Building Elevation 796, Rev. 001

Procedures

AD-HU-ALL-0003, Conduct of Pre-Job Brief and Post-Job Critiques, Rev. 5

AD-OP-ALL-0207, Fire Brigade and Hazmat Team Administrative Controls, Rev. 0

AD-RP-ALL-6002, Inspections of Self-Contained Breathing Apparatus (SCBA) and Associated

Equipment, Rev. 0

PT/0/A/0250/025, HPSW Pump and Fire Protection Flow Test, Rev. 065

PT/0/B/2000/050, Fire Drill - Performance and Evaluation, Rev. 002

RP/0/A/1000/001, Emergency Classification, Rev. 006

71111.06: Internal Flood Protection

Nuclear Condition Report

01857433; 02122484

Procedures

TE-MN-ALL-0002, Foreign Material Exclusion Level and Controls Screening, Rev. 1

Work Orders/Requests

234895

Enclosure

71111.07: Heat Sink Performance

Calculations

OSC-3767, Diesel Jacket Water Heat Exchanger and Diesel Lube Oil Cooler Tube Plugging

Evaluation, Rev. 5

Nuclear Condition Report

01852472; 01853633; 01906254; 02174289

Other

2017 SSF Diesel and Support Systems Health Reports

DJWHX-000A Eddy Current Inspection Report - INAGE0715, dated July 14, 2015

DJWHX-000B Eddy Current Inspection Report - INAGE0715, dated July 14, 2015

Maintenance Rule Function Scoping Document for function DJW.3, Provide jacket cooling for

the SSF diesel generator, printed February 12, 2018

Maintenance Rule Function Scoping Document for function SSF+.1, Provides an independent

emergency source of electrical power, printed February 12, 2018

OSS-0254.00-00-1008, Design Basis Specification for the Standby Shutdown Facility Diesel

Support System, Rev. 48

Procedures

AD-EG-ALL-1210, Maintenance Rule Program, Rev. 1

Work Orders/Requests

210310; 02151607; 02151608

71111.11: Licensed Operator Requalification

Documents

ASE-4B, Active Simulator Exam, Rev. 01

Procedures

PT/1/A/0290/003, Turbine Valve Movement, Rev. 015

Work Orders/Requests

220083

71111.12: Maintenance Effectiveness

Documents

ONS LPSW 846 Metallurgy File #5773, Nuclear Generation Metallurgy Evaluation of

catastrophic failure of 0LPSW-846

LPSW System Health Report

Nuclear Condition Report

2163493

Work Orders/Requests

WR 20089356

71111.13: Risk Assessments

Documents

AD-EG-ALL-1004, Conduct of Probabilistic Risk Analysis Engineering, Rev. 2

AD-NF-ALL-0501, Electronic Risk Assessment Tool (ERAT), Rev. 1

Enclosure

AD-NF-NGO-0502, Probabilistic Assessment (PRA) Model Technical Adequacy, Rev. 2

Oconee Projected ERAT Risk Profile - 18W5, February 1, 2018

Oconee Projected ERAT Risk Profile - 18W12, March 20, 2018

Nuclear Condition Report

2192623; 02192755

Procedures

MP/0/A/3009/017 A, Visual Inspection and Electrical Motor Tests Using Baker Equipment, Rev.

2

PT/0/A/0500/001, Protected Service Water Primary and Booster Pump Test, Rev. 003

Work Orders/Requests

20182563; 20188353; 20208815

71111.15: Operability Evaluations

Documents

OSS-0254.00-00-1008, Design Basis Specification for the Standby Shutdown Facility Diesel

Support System, Rev 048

OSS-0254.00-00-1009, Design Basis Specification for the Standby Shutdown Facility HVAC

System, Rev 023

OSS-0254.00-00-1028, Design Basis Specification for the Low Pressure Injection and Core

Flood System, Rev 054

OSS-0254.00-00-1039, Design Basis Specification for the Low Pressure Service Water System,

Rev 49

OSS-0254.00-00-2014, Design Basis Specification for the 4160/600/120V SSF Essential AC

Power System, Rev 015

Drawings

OEE-151-39, Elementary Diagram Reactor Coolant Makeup Pump MT

R. Controls, Rev. 8

OEE-151-39A, Elementary Diagram Reactor Coolant Make-up Pump MT

R. Controls, Rev. 13

Nuclear Condition Report

01839593; 02089372; 02174814; 02184118; 02184186; 02186273; 02186649; 02185787;

2186961; 02187007; 02187046; 02189331; 02189530

Procedures

PT/1/A/0400/007, SSF RC Makeup Pump Test, Rev. 069

Work Orders/Requests

20057206; 20057256; 20094672; 20222643

71111.19: Post-Maintenance Testing

Documents

OSS-0254.00-00-1008, Design Basis Specification for the Standby Shutdown Facility Diesel

Support System, Rev 048

OSS-0254.00-00-1009, Design Basis Specification for the Standby Shutdown Facility HVAC

System, Rev 023

OSS-0254.00-00-2014, Design Basis Specification for the 4160/600/120V SSF Essential AC

Power System, Rev 015

Enclosure

Drawings

OP-OC-EL-EPD-2, Electrical Distribution, Rev. 2

Nuclear Condition Report

01780746; 02175226; 02176057; 02184401; 02186649; 02186961; 02187007; 02187046

Other

EC 101176

Procedures

IP/0/A/0100/001, Controlling Procedure for Troubleshooting and Corrective Maintenance, Rev

OP/0/A/1600/009, SSF Auxiliary Service Water System, Rev 037

OP/0/A/1600/010, Operation of the SSF Diesel-Generator, Rev 094

PT/0/A/0400/011, SSF Diesel Generator Test, Rev 015

PT/0/A0400/012, Diesel Air System Check Valve Test, Rev 012

PT/0/A/0600/020, Standby Shutdown Facility Instrument Surveillance, Rev 024

PT/0/A/0600/021, Standby Shutdown Facility Diesel-Generator Operation, Rev 016

PT/0/A/0600/023, Standby Shutdown Facility Oil Inventory, Rev 007

PT/0/A/0610/022, Degraded Grid and Switchyard Isolation Test, Rev. 039

PT/2/A/0150/057, RB Pressure Switches and Associated Transmitters Leak Rate Test, Rev.

015

PT/2/A/0152/035, 2PSDW-22 and 2PSW-24 Valve Stroke Test, Rev 6

Work Orders/Requests

20070988; 20101110; 20104802; 20104803; 20126932

71111.22: Surveillance Testing

Nuclear Condition Report

2178024; 02185270

Other

OP/0/B/1106/033, Primary System Leak Identification, completed February 21, 2018

PT/1/A/0600/010, Reactor Coolant Leakage (Unit 1), completed January 18, 2018

Procedures

IP/0/A/3000/003 BK1, Keowee Hydro Station Battery 1 Service Test and Annual Surveillance,

Rev 004

IP/0/A/3000/026, Battery Cell Connection Resistance Test, Rev 044

IP/0/A/4980/081 E, ABB Type 81 Relay Test, Rev. 015

PT/0/A/0500/001, Protected Service Water Primary and Booster Pump Test, Rev. 003

PT/0/A/0620/009, Keowee Hydro Operation, Rev. 052

PT/1/A/0204/007, Reactor Building Spray Pump Test, Rev. 104

PT/2/A/0600/012, Turbine Driven Emergency Feedwater Pump Test, Rev. 095

PT/3/A/0202/011, High Pressure Injection Pump Test, Rev 091

Work Orders/Requests

20185924-01; 20185924-02; 20220075-03

Enclosure

71114.06: Drill Evaluation

Documents

AD-EP-ALL-0105, Activation and Operation of the Technical Support Center, Rev. 1

AD-EP-ALL-0106, Activation and Operation of the Operations Support Center, Rev. 1

AD-EP-ALL-0803, Evaluation and Critique of Drills and Exercises, Rev. 3

AD-EP-ONS-0105, ONS Site Specific TSC Support, Rev. 000

AD-EP-ONS-0106, ONS Site Specific OSC Support, Rev. 000

Other

FAD-ON-EP-EAL-EALMatrix, Oconee Nuclear Station Wallchart, Rev. 000

Oconee Nuclear Station Drill 18-01, dated January 19, 2018

Procedures

AP/2/A/1700/014, Loss of Normal HPI Makeup and/or RCP Seal Injection, Rev. 014

AP/2/A/1700/023, Loss of ICS Power, Rev. 023

PT/0/A/2000/008, Procedure to Verify the Availability of Supplies and Equipment in the

Emergency Response Facilities, Rev. 000

RP/0/A/1000/001, Emergency Classification, Rev. 006

RP/0/A/1000/009, Procedure for Site Assembly, Rev. 003

RP/0/A/1000/015 A, Offsite Communications for the Control Room, Rev. 009

71151: Performance Identification Verification

Documents

Unit 1 station logs covering period of March, 2017 through March, 2018

Unit 2 station logs covering period of March, 2017 through March, 2018

Unit 3 station logs covering period of March, 2017 through March, 2018

Enclosure

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

May 3, 2018

Mr.

J. Ed Burchfield, Jr.

Site Vice President

Duke Energy Corporation

Oconee Nuclear Station

7800 Rochester Highway

Seneca, SC 29672

SUBJECT: OCONEE NUCLEAR STATION - NRC INTEGRATED INSPECTION REPORT

05000269/2018001, 050000270/2018001, AND 05000287/2018001

Dear Mr. Burchfield:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection

at your Oconee Nuclear Station Units 1, 2 and 3. On April 12, 2018, 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 Jannette Worosilo Acting for/

Frank Ehrhardt, Chief

Reactor Projects Branch 1

Division of Reactor Projects

Docket Nos.: 50-269, 50-270, 50-287

License Nos.: DPR-38, DPR-47, DPR-55

Enclosure:

IR 05000269/2018001, 05000270/2018001,

and 05000287/2018001

cc: Distribution via ListServ

ML18123A311

OFFICE RII:DRP RII:DRP RII:DRP RII:DRP RII:DRP RII:DRP

NAME ECrowe NChilds JParent MToth JWorosilo FEhrhardt

DATE 5/3/2018 4/27/2018 5/3/2018 4/27/2018 4/26/2018 4/27/2018

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Numbers: 50-269, 50-270, 50-287

License Numbers: DPR-38, DPR-47, DPR-55

Report Numbers: 05000269/2018001, 05000270/2018001, and 05000287/2018001

Enterprise Identifier: I-2018-001-0060

Licensee: Duke Energy Carolinas, LLC

Facility: Oconee Nuclear Station, Units 1, 2, and 3

Location: Seneca, SC

Inspection Dates: January 1, 2018 to March 31, 2018

Inspectors:

E. Crowe, Senior Resident Inspector
N. Childs, Resident Inspector
J. Parent, Resident Inspector

Approved By:

F. Ehrhardt, Chief

Reactor Projects Branch 1

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensee performance by

conducting a quarterly baseline inspection at Oconee Nuclear Station Units 1, 2, and 3 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. No findings were

identified during this inspection period.

Enclosure

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.

Unit 3 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 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

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather (1 Sample)

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the

onset of seasonal cold temperatures.

Impending Severe Weather (1 Sample)

The inspectors evaluated readiness for impending adverse weather conditions for freezing

rain and extreme cold from January 2, 2018, through January 7, 2018.

71111.04 - Equipment Alignment

Partial Walkdown (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following

systems/trains:

(1) Unit 1, 2, and 3 emergency feedwater system, auxiliary service water system, and low

pressure service water system alignment during planned protected service water primary

and booster pump tests on February 2, 2018

(2) Unit 1, 2, and 3 4160kV safety related electrical distribution systems, standby feeder

buses, Lee combustion turbine alignment during planned maintenance to transformer

CT-4 on February 6, 2018

Enclosure

(3) Unit 1, 2, and 3 13.8kV safety related electrical distribution system (underground path)

alignment during planned maintenance on Keowee Unit 2 on February 13, 2018

(4) Unit 1, 2, and 3 safety-related electrical distribution system alignment and Keowee

Hydro Unit-1 during annual maintenance outage of standby shutdown facility (SSF) on

February 20-23, 2018

(5) Unit 1, 2, and 3 control room ventilation alignment during troubleshooting of B chiller

failure to run on March 11, 2018

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the primary

instrument air system on March 26, 2018.

71111.05AQ - Fire Protection Annual/Quarterly

Quarterly Inspection (5 Samples)

The inspectors evaluated fire protection program implementation in the following selected

areas:

(1) Fire Zone 29 - Unit 3 turbine building 4160V switchgear on January 12, 2018

(2) Fire Zone 33 - Unit 2 turbine building 4160V switchgear on January 12, 2018

(3) Fire Zone KHS-001 - Keowee hydro station on February 8, 2018

(4) Fire Zone 53 - Unit 1 & Unit 2 low pressure injection/reactor building spray pump room

on February 14, 2018

(5) Fire Zone 57 - Unit 1 purification and deborating demineralizers on February 14, 2018

Annual Inspection (1 Sample)

The inspectors evaluated fire brigade performance on January 12, 2018.

71111.06 - Flood Protection Measures

Cables (1 Sample)

The inspectors evaluated cable submergence protection in CT5 trench on March 15, 2018.

71111.07 - Heat Sink Performance

Heat Sink (1 Sample)

The inspectors evaluated the SSF diesel generator jacket water heat exchangers (A and B)

performance in January 2018

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance

Operator Requalification (1 Sample)

The inspectors observed and evaluated an in-progress annual requalification operating test on

March 7, 2018.

Enclosure

Operator Performance (1 Sample)

The inspectors observed and evaluated a Unit 1 power reduction in support of performing a

turbine valve movement test on March 23, 2018.

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness (1 Sample)

The inspectors evaluated the effectiveness of routine maintenance activities associated

with the following equipment and/or safety significant functions:

(1) Units 1, 2, and 3 air handling unit flow limiting valve (0LPSW-846) catastrophic failure

due to a water hammer event

71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples)

The inspectors evaluated the risk assessments for the following planned and emergent

work activities:

(1) Yellow risk changed to green risk condition on Units 1, 2, and 3 during planned testing of

the protected service water primary and booster pumps on February 1, 2018

(2) Green risk condition on Units 1, 2, and 3 during planned maintenance on transformer

CT-4 on February 6, 2018

(3) Yellow risk condition on Unit 1 during emergent issue (water in lubricating oil) of turbine

driven emergency feedwater pump on February 13, 2018

(4) Yellow risk condition on Units 1, 2, and 3 during annual maintenance outage of SSF on

February 20 - 23, 2018

(5) Projected Yellow risk on Unit 3 during planned SSF monthly outage along with planned

replacement of PCB-33 (autobank tie to 230kV yellow bus) and 3A LPI pump preventive

maintenance on March 20, 2018

71111.15 - Operability Determinations and Functionality Assessments (8 Samples)

The inspectors evaluated the following operability determinations and functionality

assessments:

(1) Unit 1, SSF reactor coolant makeup pump tripped during performance test on January 3,

2018

(2) Unit 1, turbine driven emergency feedwater pump turbine inboard seal cavity full of water

on February 13, 2018

(3) Units 1, 2, and 3 low pressure service water (LPSW) valves LPSW 1111 and 1116

condition monitoring requirements not met on February 19, 2018

(4) Unit 3 low pressure injection piping variable load spring support out of tolerance on

February 21, 2018

(5) Units 1, 2, and 3 SSF air handling unit (0-42) oil differential pressure higher than normal

on February 22, 2018

Enclosure

(6) Units 1, 2, and 3 SSF diesel generator overspeed test failures on February 23, 2018

(7) Unit 2, main feeder bus normal feeder electrical breaker N2-1 charging spring motor

continuously operating on March 6, 2018

(8) Unit 3, reactor protection system Channel C watchdog timer failure in central processing

unit 3311 on March 7, 2018

71111.19 - Post Maintenance Testing (8 Samples)

The inspectors evaluated the following post-maintenance tests:

(1) PT/0/A/0610/022, Degraded Grid and Switchyard Isolation Test on January 10, 2018

(2) PT/1/A/0600/012, Turbine Driven Emergency Feedwater Pump Test following draining

of oil with high water content on February 14, 2018

(3) PT/2/A/0150/057, RB Pressure Switches and Associated Transmitters Leak Rate Test

following replacement of 2BS-PT-0230 on February 15, 2018

(4) PT/2/A/0150/057, RB Pressure Switches and Associated Transmitters Leak Rate Test

following replacement of 2BS-PT-0231 on February 16, 2018

(5) OP/0/A/1600/009 SSF Auxiliary Service Water System Test following annual

maintenance on February 24, 2018

(6) PT/0/A/0600/021, Standby Shutdown Facility Diesel-Generator Operation following

annual maintenance on February 24, 2018

(7) PT/2/A/0152/035, 2PSW-22 and 2PSW-24 Valve Stroke Test following 2PSW-22

actuator replacement on March 14, 2018

(8) OP/0/A/1600/010, SSF Diesel-Generator Operational Test following troubleshooting

and relay replacements on March 23, 2018

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine (6 Samples)

(1) IP/0/A/3000/003 KB1, Keowee Hydro Station Battery 1 Service Test and Annual

Surveillance, conducted on January 10, 2018

(2) PT/2/A/0600/012, Turbine Driven Emergency Feedwater Pump Test, conducted on

January 31, 2018

(3) PT/0/A/0500/001, Protected Service Primary and Booster Pump Test, conducted on

February 1, 2018

(4) PT/3/A/0202/011, High Pressure Injection Pump Test, conducted on February 7, 2018

(5) IP/0/A/4980/081 E, ABB Type 81 Relay Test, performed on Keowee Unit 2 relay

K2ELK-RL-81X2, conducted on February 13, 2018

(6) IP/0/A/4980/081 E, ABB Type 81 Relay Test, performed on Keowee Unit 2 relay

K2ELK-RL-81Y2, conducted on February 13, 2018

In-service (1 Sample)

(1) PT/1/A/0204/007, Reactor Building Spray Pump Test, conducted on January 16, 2018

Reactor Coolant System Leak Detection (1 Sample)

(1) PT/1/A/0600/010, Reactor Coolant Leakage (Unit 1), on January 18, 2018

Enclosure

71114.06 - Drill Evaluation

Drill/Training Evolution (1 Sample)

The inspectors evaluated an emergency preparedness drill which involved an increase in

radiological levels in the central alarm station and a Unit 2 trip which was caused by a loss

of 125 VDC power, all resulting in a site area emergency being declared on January 19,

2018.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification

The inspectors verified licensee performance indicator submittals listed below for the period

from March 2017 through March 2018. (9 Samples)

(1) Unplanned Scrams per 7000 Critical Hours

(2) Unplanned Power Changes per 7000 Critical Hours

(3) Unplanned Scrams with Complications

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 April 12, 2018, the inspector presented the inspection results to Mr.
J. Ed Burchfield, and

other members of the licensee staff.

Enclosure

DOCUMENTS REVIEWED

71111.01: Adverse Weather Protection

Nuclear Condition Report

2169114; 02174700

Procedures

OP/0/A/1104/037, Plant Heating, Rev. 004

OP/0/A/1104/041, Auxiliary Building Ventilation, Rev. 041

OP/0/A/1106/041, Turbine Building Ventilation, Rev. 007

OP/0/A/1600/002, Standby Shutdown Facility Heating, Ventilation and Air Conditioning System

Operation (HVAC), Rev. 037

OP/0/B/1104/050, Weather Related Activities, Rev. 005

OP/1/A/1104/051, ESV System, Rev. 028

OP/2/A/1104/051, ESV System, Rev. 040

OP/3/A/1104/051, ESV System, Rev. 028

PT/0/A/0110/017, Cold Weather Protection, Rev. 013

RP/0/A/1000/035, Severe Weather Preparations, Rev. 003

Work Orders/Requests

20091981; 20157474

71111.04: Equipment Alignment

Documents

AD-OP-ALL-0201, Protected Equipment, Rev. 3

OSS-0254.00-00-1021, Design Basis Specification for the Control Room Ventilation System

Oconee Nuclear Site Technical Specifications, amended August 13, 2014

Oconee Nuclear Site Technical Specifications Bases, updated June 3, 2011

OC-SSS-IA-14, Compressed Air Composite, dated April 15, 2009

Drawings

O-0705, Rev. 104

O-1705, Rev. 87

O-2705, Rev. 87

OFD-166J-1.2, Rev 15

OFD-116J-1.5, Rev. 24

OFD-116J-1.6, Rev 20

OFD-121D-1.1, Rev. 38

OFD-121D-2.1, Rev. 39

OFD-121D-3.1, Rev. 46

OFD-124A-1.2, Rev 55

OFD-124B-1.1, Rev. 67

OFD-124B-2.1, Rev. 76

OFD-124B-3.1, Rev. 61

OFD-133A-2.5, Rev. 58

OFD-137B-1.1, Rev. 26

OFD-137B-1.2, Rev. 27

OFD-144A-1.1, Rev. 16

OFD-144A-1.2, Rev. 15

OFD-144A-1.3, Rev. 10

OFD-144A-1.4, Rev. 10

Enclosure

Nuclear Condition Report

2114841; 02119628; 02137156; 02138440; 02139231; 02149244; 02162787

Procedures

MP/0/A/3007/054 A, Chillers - A and B - York - Codepak - Preventive Maintenance (QA-5),

Rev. 034

OP/0/A/1106/019, Keowee Hydro at Oconee, Rev. 104

OP/A/1106/027, Instrument Air System, Rev. 120

PT/0/A/0500/001, Protected Service Water Primary and Booster Pump Test, Rev. 003

PT/0/A/0620/009, Keowee Hydro Operation, Rev. 052

Work Orders/Requests

20085997; 20095495; 20104045; 20104322; 20112663; 20118654; 20126636; 20182563;

20185924; 20192286; 20208815; 20220075

71111.05AQ: Fire Protection

Documents

Oconee Nuclear Station Fire Brigade Drill, Drill # 2 Main Power Battery - 1A

Nuclear Condition Report

2174700; 02176943

Other

O-FS-0-OC-9000-003, Pre-Fire Plan for Keowee Hydro Station, Rev. 1

O-FS-1-AB-9758-001, Pre-Fire Plan for Unit 1 & 2 Auxiliary Building Elevation 758, Rev. 002

O-FS-1-AB-9783-001, Pre-Fire Plan for Unit 1 Auxiliary Building Elevation 783, Rev. 002

O-FS-2-TB-9796-001, Pre-Fire Plan for Unit 2 Turbine Building Elevation 796, Rev. 001

O-FS-3-TB-9796-001, Pre-Fire Plan for Unit 3 Turbine Building Elevation 796, Rev. 001

Procedures

AD-HU-ALL-0003, Conduct of Pre-Job Brief and Post-Job Critiques, Rev. 5

AD-OP-ALL-0207, Fire Brigade and Hazmat Team Administrative Controls, Rev. 0

AD-RP-ALL-6002, Inspections of Self-Contained Breathing Apparatus (SCBA) and Associated

Equipment, Rev. 0

PT/0/A/0250/025, HPSW Pump and Fire Protection Flow Test, Rev. 065

PT/0/B/2000/050, Fire Drill - Performance and Evaluation, Rev. 002

RP/0/A/1000/001, Emergency Classification, Rev. 006

71111.06: Internal Flood Protection

Nuclear Condition Report

01857433; 02122484

Procedures

TE-MN-ALL-0002, Foreign Material Exclusion Level and Controls Screening, Rev. 1

Work Orders/Requests

234895

Enclosure

71111.07: Heat Sink Performance

Calculations

OSC-3767, Diesel Jacket Water Heat Exchanger and Diesel Lube Oil Cooler Tube Plugging

Evaluation, Rev. 5

Nuclear Condition Report

01852472; 01853633; 01906254; 02174289

Other

2017 SSF Diesel and Support Systems Health Reports

DJWHX-000A Eddy Current Inspection Report - INAGE0715, dated July 14, 2015

DJWHX-000B Eddy Current Inspection Report - INAGE0715, dated July 14, 2015

Maintenance Rule Function Scoping Document for function DJW.3, Provide jacket cooling for

the SSF diesel generator, printed February 12, 2018

Maintenance Rule Function Scoping Document for function SSF+.1, Provides an independent

emergency source of electrical power, printed February 12, 2018

OSS-0254.00-00-1008, Design Basis Specification for the Standby Shutdown Facility Diesel

Support System, Rev. 48

Procedures

AD-EG-ALL-1210, Maintenance Rule Program, Rev. 1

Work Orders/Requests

210310; 02151607; 02151608

71111.11: Licensed Operator Requalification

Documents

ASE-4B, Active Simulator Exam, Rev. 01

Procedures

PT/1/A/0290/003, Turbine Valve Movement, Rev. 015

Work Orders/Requests

220083

71111.12: Maintenance Effectiveness

Documents

ONS LPSW 846 Metallurgy File #5773, Nuclear Generation Metallurgy Evaluation of

catastrophic failure of 0LPSW-846

LPSW System Health Report

Nuclear Condition Report

2163493

Work Orders/Requests

WR 20089356

71111.13: Risk Assessments

Documents

AD-EG-ALL-1004, Conduct of Probabilistic Risk Analysis Engineering, Rev. 2

AD-NF-ALL-0501, Electronic Risk Assessment Tool (ERAT), Rev. 1

Enclosure

AD-NF-NGO-0502, Probabilistic Assessment (PRA) Model Technical Adequacy, Rev. 2

Oconee Projected ERAT Risk Profile - 18W5, February 1, 2018

Oconee Projected ERAT Risk Profile - 18W12, March 20, 2018

Nuclear Condition Report

2192623; 02192755

Procedures

MP/0/A/3009/017 A, Visual Inspection and Electrical Motor Tests Using Baker Equipment, Rev.

2

PT/0/A/0500/001, Protected Service Water Primary and Booster Pump Test, Rev. 003

Work Orders/Requests

20182563; 20188353; 20208815

71111.15: Operability Evaluations

Documents

OSS-0254.00-00-1008, Design Basis Specification for the Standby Shutdown Facility Diesel

Support System, Rev 048

OSS-0254.00-00-1009, Design Basis Specification for the Standby Shutdown Facility HVAC

System, Rev 023

OSS-0254.00-00-1028, Design Basis Specification for the Low Pressure Injection and Core

Flood System, Rev 054

OSS-0254.00-00-1039, Design Basis Specification for the Low Pressure Service Water System,

Rev 49

OSS-0254.00-00-2014, Design Basis Specification for the 4160/600/120V SSF Essential AC

Power System, Rev 015

Drawings

OEE-151-39, Elementary Diagram Reactor Coolant Makeup Pump MT

R. Controls, Rev. 8

OEE-151-39A, Elementary Diagram Reactor Coolant Make-up Pump MT

R. Controls, Rev. 13

Nuclear Condition Report

01839593; 02089372; 02174814; 02184118; 02184186; 02186273; 02186649; 02185787;

2186961; 02187007; 02187046; 02189331; 02189530

Procedures

PT/1/A/0400/007, SSF RC Makeup Pump Test, Rev. 069

Work Orders/Requests

20057206; 20057256; 20094672; 20222643

71111.19: Post-Maintenance Testing

Documents

OSS-0254.00-00-1008, Design Basis Specification for the Standby Shutdown Facility Diesel

Support System, Rev 048

OSS-0254.00-00-1009, Design Basis Specification for the Standby Shutdown Facility HVAC

System, Rev 023

OSS-0254.00-00-2014, Design Basis Specification for the 4160/600/120V SSF Essential AC

Power System, Rev 015

Enclosure

Drawings

OP-OC-EL-EPD-2, Electrical Distribution, Rev. 2

Nuclear Condition Report

01780746; 02175226; 02176057; 02184401; 02186649; 02186961; 02187007; 02187046

Other

EC 101176

Procedures

IP/0/A/0100/001, Controlling Procedure for Troubleshooting and Corrective Maintenance, Rev

OP/0/A/1600/009, SSF Auxiliary Service Water System, Rev 037

OP/0/A/1600/010, Operation of the SSF Diesel-Generator, Rev 094

PT/0/A/0400/011, SSF Diesel Generator Test, Rev 015

PT/0/A0400/012, Diesel Air System Check Valve Test, Rev 012

PT/0/A/0600/020, Standby Shutdown Facility Instrument Surveillance, Rev 024

PT/0/A/0600/021, Standby Shutdown Facility Diesel-Generator Operation, Rev 016

PT/0/A/0600/023, Standby Shutdown Facility Oil Inventory, Rev 007

PT/0/A/0610/022, Degraded Grid and Switchyard Isolation Test, Rev. 039

PT/2/A/0150/057, RB Pressure Switches and Associated Transmitters Leak Rate Test, Rev.

015

PT/2/A/0152/035, 2PSDW-22 and 2PSW-24 Valve Stroke Test, Rev 6

Work Orders/Requests

20070988; 20101110; 20104802; 20104803; 20126932

71111.22: Surveillance Testing

Nuclear Condition Report

2178024; 02185270

Other

OP/0/B/1106/033, Primary System Leak Identification, completed February 21, 2018

PT/1/A/0600/010, Reactor Coolant Leakage (Unit 1), completed January 18, 2018

Procedures

IP/0/A/3000/003 BK1, Keowee Hydro Station Battery 1 Service Test and Annual Surveillance,

Rev 004

IP/0/A/3000/026, Battery Cell Connection Resistance Test, Rev 044

IP/0/A/4980/081 E, ABB Type 81 Relay Test, Rev. 015

PT/0/A/0500/001, Protected Service Water Primary and Booster Pump Test, Rev. 003

PT/0/A/0620/009, Keowee Hydro Operation, Rev. 052

PT/1/A/0204/007, Reactor Building Spray Pump Test, Rev. 104

PT/2/A/0600/012, Turbine Driven Emergency Feedwater Pump Test, Rev. 095

PT/3/A/0202/011, High Pressure Injection Pump Test, Rev 091

Work Orders/Requests

20185924-01; 20185924-02; 20220075-03

Enclosure

71114.06: Drill Evaluation

Documents

AD-EP-ALL-0105, Activation and Operation of the Technical Support Center, Rev. 1

AD-EP-ALL-0106, Activation and Operation of the Operations Support Center, Rev. 1

AD-EP-ALL-0803, Evaluation and Critique of Drills and Exercises, Rev. 3

AD-EP-ONS-0105, ONS Site Specific TSC Support, Rev. 000

AD-EP-ONS-0106, ONS Site Specific OSC Support, Rev. 000

Other

FAD-ON-EP-EAL-EALMatrix, Oconee Nuclear Station Wallchart, Rev. 000

Oconee Nuclear Station Drill 18-01, dated January 19, 2018

Procedures

AP/2/A/1700/014, Loss of Normal HPI Makeup and/or RCP Seal Injection, Rev. 014

AP/2/A/1700/023, Loss of ICS Power, Rev. 023

PT/0/A/2000/008, Procedure to Verify the Availability of Supplies and Equipment in the

Emergency Response Facilities, Rev. 000

RP/0/A/1000/001, Emergency Classification, Rev. 006

RP/0/A/1000/009, Procedure for Site Assembly, Rev. 003

RP/0/A/1000/015 A, Offsite Communications for the Control Room, Rev. 009

71151: Performance Identification Verification

Documents

Unit 1 station logs covering period of March, 2017 through March, 2018

Unit 2 station logs covering period of March, 2017 through March, 2018

Unit 3 station logs covering period of March, 2017 through March, 2018

Enclosure