IR 05000397/2019011

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Design Basis Assurance Inspection (Teams) Inspection Report 05000397/2019011
ML19268A201
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 09/25/2019
From: Vincent Gaddy
Region 4 Engineering Branch 1
To: Sawatzke B
Energy Northwest
Gaddy V
References
IR 2019011
Download: ML19268A201 (15)
v • d • e


Text

ber 25, 2019

SUBJECT:

COLUMBIA GENERATING STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000397/2019011

Dear Mr. Sawatzke:

On August 22, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station. On August 22, 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 findings or violations 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/

Vincent G. Gaddy, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-397 License No. NPF-21

Enclosure:

Inspection Report 05000397/2019011

Inspection Report

Docket Number: 05000397 License Number: NPF-21 Report Number: 05000397/2019011 Enterprise Identifier: I-2019-011-0010 Licensee: Energy Northwest Facility: Columbia Generating Station Location: Richland, WA Inspection Dates: August 05, 2019, to August 22, 2019 Inspectors: W. Sifre, Senior Reactor Inspector J. Braisted, Reactor Inspector S. Graves, Senior Reactor Inspector M. Hayes, Operations Engineer Contractors: S. Gardner R. Waters Approved By: Vincent G. Gaddy, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Columbia Generating Station in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations No findings or violations of more than minor significance were identified.

Additional Tracking Items None

INSPECTION SCOPES

===Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.

Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

===71111.21M - Design Bases Assurance Inspection (Teams)

The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)

=

Main article: IP 71111.21
(1) Residual Heat Removal Motor and Pump 2A
  • Calculations for reactor building flooding and system pressure drop
  • Corrective action program reports to verify the monitoring of potential degradation
  • Design bases and inservice testing bases documents
  • Calculations for relay protection and cable sizing
  • Diesel loading calculation to verify capability of on-site power to supply pump motor within technical specifications requirements
(2) Containment Instrument Air System
  • Corrective action program reports to verify the monitoring of potential degradation
  • Work orders for completed technical specification surveillances and inservice testing of system valves
  • Procedures for abnormal system operation and performing inservice testing of system valves
  • Design bases and inservice testing bases documents and the system description
  • System one-line diagrams
(3) 125 Volt DC Division 3 High Pressure Core Spray Electrical Distribution Panel
  • Component maintenance history and corrective action program reports to verify the monitoring of potential degradation
  • Vendor manual to compare site practices with vendor recommendations
  • Fuse Control Program and logs to ensure configuration control
  • Calculations for protection and cable sizing with focus on fuse coordination
(4) Standby Service Water Pump SW-P-1B
  • Material condition and configuration (i.e., visual inspection during a walkdown)
  • Consistency between station documentation (e.g., procedures) and vendor specifications
  • Room heat-up calculations
  • Component maintenance history, system health reports, testing results, and corrective action program reports to verify the monitoring of potential degradation
  • Calculations for design of component, net positive suction head for the pump, submergence, hydraulic piping analyses, including runout conditions, Ultimate Heat Sink capacity and capabilities to verify these components can support accident mitigation requirements

(1 Sample 1 Partial)

(1) Containment Exhaust Purge Valves CEP-V-3A/4A
  • Material condition and configuration (i.e., visual inspection during a walkdown)
  • Consistency between station documentation (e.g., procedures) and vendor specifications
  • Component maintenance history and corrective action program reports
  • Component maintenance history and testing results to verify the monitoring of potential degradation
  • Calculations for air-operated valve torque and thrust, valve weak-link analysis, and maximum operating differential pressures, line pressures, temperature, and flow

Evaluation of Operator Procedures and Actions Related to Components and Permanent Modifications From August 5, 2019, to August 22, 2019, the inspectors observed the following operator actions associated with selected components and modifications.

Control room operator actions resulting from an evacuation of the control room.

  • Isolation and de-energization of electrical bus SM-8 within 10 minutes
  • Reducing DC load during extended loss of AC power Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)===
(1) Engineering Change (EC) 13576, "Installation of Parallel Conductors on the Control

===Circuits of E-CB-DG/7," Revision 2

(2) Engineering Change (EC) 14786, "Steam Tunnel Fan Alternate AC Source for RRA-FN-21 and -9," Revision 3
(3) Engineering Change (EC) 14635, Replace Residual Heat Removal Pump and Motor P-2A, Revision 1
(4) Engineering Change (EC) 16302, Abandon High Pressure Core Spray Valves V-10 and V-11 in place, Revision 0
(5) Engineering Change (EC) 12788, "Move Non-1E Loads from Safety-Related Inverter E-PP-8AA," Revision 0
(6) Engineering Change (EC) 13176, "Appendix R Modification for Residual Heat Removal Valve V-4B," Revision 0 Review of Operating Experience Issues (IP Section 02.06) (4 Samples)===
(1) NRC Information Notice 2017-06, Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the Direct Current Distribution
(2) NRC Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations
(3) AR 00390708 - Part 21 - Asea Brown Bovary Motors
(4) AR 00392900 - Part 21 - "Ametek/SCI AC Voltage Sensing Board"

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

On August 22, 2019, the inspectors presented the design basis assurance inspection (teams)inspection results to Mr. B. Sawatzke, Chief Executive Officer, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations CE-02-87-29 Seismic Requirements for Scaffolding 1

CMR 15837 Update E/I-02-16-02 Due to Replacement of 0

RHR-M-P/2A

E/I-02-16-02 Standby AC Power ESF Load Group Transient Analysis 3

E/I-02-91-03 Calculation for Division 1, 2, and 3 Diesel Generators 21

Loading

E/I-02-92-01 Fuse Coordination Study for DC Power Systems 2

E/I-02-92-09 AC Short Circuit Current Analysis for 6.9kV, 4.16kV, and 5

480V Systems

E/I-02-92-17 Medium Voltage Electrical Distribution System Phase 3

Overcurrent Relay Settings

E/I-02-94-02 Direct Current Voltage Drop 1

2.05.01 Battery Sizing, Voltage Drop, and Charger Studies for Div. 1 14

and 2 Systems

4.14.02 SSW System (Spray Ponds) 0

5.17.19 Calculation for RHR Pressure Drop Calculation Modes A.1, 4

A.2, B, C.1, C.2, C.3, C.4, D, E, F, G, and S

5.46.05 Amount of Time that the CIA Safety-Related Headers will 4

Supply N2 for Operating the ADS MSRVs Subsequent to a

Small Break LOCA

CMR-12870 Calculation Modification Record - Move Non-1E Loads from 04/18/2014

Safety-Related Inverter E-PP- 8AA, E/I-02-90-01

E/I-02-95-01 Overcurrent Protective Device Settings and Coordination 6

Calculation for 480 Volt Distribution Systems

ME-02-00-14 CEP System Air Operated Valve (AOV) Functional and 0

MEDP Calculation

ME-02-02-02 Reactor Building Flooding Analysis 4

ME-02-02-08 Thermal Analysis of SW-P-1A and 1B at Shutoff Head 0

Conditions

ME-02-02-12 Seismic and Weak Link Analyses of AOVs CEP-V-3A and 0

4A

ME-02-85-79 SSW Spray Pond Temperature Transient w/o Sprays 3

Inspection Type Designation Description or Title Revision or

Procedure Date

ME-02-91-88 Verification of 3 Min. Time Delay for CIV-V-39A/B Closure 0

ME-02-92-29 Number of Nitrogen Bottles Required for CIA System 0

Operability

ME-02-92-41 Calculation for Ultimate Heat Sink Analysis 7

ME-02-92-43 Room Temperature Calculation for DG Building, Reactor 13

Building, Radwaste Building, and Service Water

ME-02-95-11 Calculation of 42 Gallon Accumulator Capacity to Perform 0

the ADS Function with a Loss of the Safety-Related CIA

Supply

ME-02-95-25 Evaluation of Standby Service Water Capability 2

ME-02-97-08 Evaluate Ability of Service Water System to Provide 2

Adequate Cooling to the Diesel Generators While Operating

in a RPV/Containment Flooding Configuration

NE-02-92-38 IPE PRA: Equipment Survivability Evaluation 0

Corrective Action Action Requests 00387202, 00387555, 00387577, 00387700, 00394958,

Documents (ARs) 00390870, 00348180, 00387494, 00382583, 00369398,

292559, 00183326, 00363476, 00352792, 00397881,

291162, 00292559, 00335546, 00372061, 00387700,

00391184, 00032871, 00344031, 00361359

ME-02-01-25 Calculation for Inboard Scram Discharge Volume Vent Air 1

Operated Valve Component Level

Corrective Action Action Requests 00397740, 00397778, 00398257, 00398262, 00397701,

Documents (ARs) 00397702, 00397705, 00397755, 00397777, 00397813,

Resulting from 00397828, 00397881, 00397899, 00397963, 00398055,

Inspection 00398058, 00398173, 00398174, 00398176, 00398177,

00398243, 00398296, 00398297, 00398300, 00398324,

0039827

Drawings E502-2 Main One Line 64

E505-1 DC One Line Diagram 109

M521-1 Residual Heat Removal 115

2B22-03, 2 Nuclear Boiler System 21

Inspection Type Designation Description or Title Revision or

Procedure Date

2B22-04, 54 Valve Actuators, Safety-Related, Pneumatically Operated, 0

General Requirements

2B22-08, 7 Self Actuated Nozzle Type Safety Valves with Air Cylinder 09/08/2016

Actuated Pneumatically Operated Auxiliary Lifting Gear and

Parts List

E504-1 Vital One Line Diagram 6

E535 Motor Control System Sheet No. 54F 18

E775-3 Main Control Room 34

PGCC Duct Layout

Sections and Details

E775-5 Main Control Room 34

PGCC Lateral and Transitional

Duct Layout

(Lower Floor Section)

EWD-46E-207A Electrical Wiring Diagram 4

AC Electrical Distribution System

Inverters E-IN-2A and E-IN-2B

EWD-46E-211 Electrical Wiring Diagram 19

AC Electrical Distribution System

UPS TDAS/PDIS Computer

Power Panel E-PP-US/PT

EWD-46E-248 Electrical Wiring Diagram 45

AC Distribution System

Main Control Room

UPS Power Panel E-PP-8AA

EWD-46E-266 AC Electrical Distribution System 7

Reactor Building

Power Panel E-PP-3DAC

EWD-46E-317 Electrical Wiring Diagram 11

AC Electrical Distribution System

Radwaste Building

Power Panel E-PP-8A

EWD-58E-014 Standby Service Water System MOV SW-V-2B 19

Inspection Type Designation Description or Title Revision or

Procedure Date

M520 High-Pressure Core Spray and Low-Pressure Core Spray 103

Flow Diagrams

M524-1 Standby Service Water System 135

M524-2 Standby Service Water System 19

M556 Containment Instrument Air System 53

Sketch 1 Sketch 1 Conduit Rework of E-PP-8AA and E-PP-US/5 NA

Panesl

Engineering EC 12788 Move Non-1E Loads from Safety-Related Inverter 3

Changes E-PP-8AA (Div 2)

EC 13176 Appendix R Modification for RHR-V-4B

EC 13576 Installation of Parallel Conductors on the Control Circuits of 2

E-CB-DG/7

EC 14786 Steam Tunnel Fan Alternate AC Source for 3

RRA-FN-21 and -9

Miscellaneous Photographs of Electrical Splices Categorized as Class 1

System Health Report - AC (Instruments)

Surveillance Test Interval Evaluation Form

CVI 02E12-08-18 Schultz Motor Installation and Maintenance Manual 0

CVI 02E12-08-20 Load Testplan for 900HP Residual Heat Removal Pump 0

Motor

PDC 14635 Replace RHR Pump Motor P-2A 1

PO 339717 Flowserve RHR Pump Replacement 06/26/2015

PO 342467 Schulz RHR Pump Motor Replacement 12/31/2014

Specification Motor, Induction, Medium Voltage, Residual Heat Removal, 2

15606 Safety-Related

Specification Specification for Motor, Induction, Medium Voltage, Residual 2

15606 Heat Removal

STI-367211 LOP LOCA Testing STI Evaluation 04/15/2019

System Health System Health Report AC/DC (Instrument), Quarter 2, 2019 Quarter 2,

Report, AC/DC 2019

System Health System Health Report RHR, Quarter 1, 2019 Quarter 1,

Report, RHR 2019

280-RLCU00117- Test Report SSW Pump Serial Number 731-S-0013 0

Inspection Type Designation Description or Title Revision or

Procedure Date

2P8AA-0060 Cable Schedule Information for Cable 2P8AA-0060 NA

2PAA-0060-001 Raceway Schedule Information NA

675-00-7 Solatron - Line Voltage Regulator Operating and Service 3

Manual

2-00-15 Solidate Controls, Inc. 7

15kVA Inverter/Static Switch

84VC0150-03 84W0020-06 (Proprietary)

AR 00373514 Operating Experience - Part 21 - Potential Defect Issued by 11/06/2017

Ametek/Solidstate Controls

AR 00382900 Operating Experience - Part 21 Notification from AMETEK 07/30/2018

Solid-State Controls for AC Voltage Sense Board

P/N 80-9210842

AR 00390708 Operating Experience - Part 21 ABB Motors 03/05/2019

AR 00390797 Operating Experience - Evaluate EPRI Switchyard 03/07/2019

Monitoring Technologies for Nuclear Power Plants for

Applicability to Columbia

CVI/OMM 23-00- Standby Service Water Vertical Pumps 4

CVI/OMM 818- O&M Manual for the C&S Tricentric Stop Valve 2

00-6

DBD 305 Compressed Air Systems 8

DBD 307 Main Steam System 8

SD000156 Containment Instrument Air 11

SD000194 Uninterruptible Power Supply System 14

SD000198 Residual Heat Removal 17

TR-112175 EPRI Capacitor Application and Maintenance Guide 08/1999

Procedures 1.3.47 Fuse Replacement Control 12

10.2.53 Scaffolding 46

DES-2-1 Plant Design Changes 57

ENG-DES-50 Interface to Standard Design Process 2

IP-ENG-001 Standard Design Process 0

Inspection Type Designation Description or Title Revision or

Procedure Date

SWP-LIC-02 Licensing Basis Impact Determination 15

SWP-TST-02 Post-Maintenance Testing 2

1.5.19 Surveillance Frequency Control Program Procedure 1

1.5.20 Surveillance Frequency Control Program Procedure 1

10.24.28 SW-PS-1B Calibration 11

10.25.1 Inspections and Cleaning Division 1, E-IN-3A and E-IN-3B; 25

and Division 2, E-IN-2A and E-IN-2B; Inverters

10.25.19 Termination and Splicing Instruction 26

5.5.5 RHR/SW Crosstie Lineup 12

5.6.2 Station Blackout (SBO) and Extended Loss of AC Power 13

ELAP Attachements

ABN-CIA Containment Instrument Air System Failure 7

ABN-CONT- Containment Vent Without AC and DC Power Available 4

VENT

ABN-CR-EVAC Control Room Evacuation and Remote Cooldown 40

ABN-FLOODING Flooding 20

AOVPP-01 Air Operated Valve Program Plan 1

EOP 5.1.1 RPV Control 22

EOP 5.1.4 Emergency Wetwell Venting 5

EOP 5.5.2 RHR/SW Crosstie Lineup 12

EOP 5.5.20 Emergency Wetwell Venting with High Hydrogen and 7

Oxygen Concentration

EOP 5.5.21 Emergency Drywell Venting with High Hydrogen and 7

Oxygen Concentration

ISP-SW-X303 Spray Pond B Level - CC 5

LBD-IST-4 Inservice Testing Program Plan 1

MSP-MS/IST- MSRV Manual Actuation and Accessories Operability- 5

R101 IN-SITU

OI-69 Time Critical Operator Actions 12

OSP-CIA/IST- CIA Valve Operability - Shutdown 5

Q702

OSP-RHR/IST- RHR Loop A Operability Test 52

Q702

Inspection Type Designation Description or Title Revision or

Procedure Date

OSP-SW-M102 Loop B Valve Position Verification 41

OSP-SW-Q101 SW Spray Pond Average Sediment Depth Measurement 11

QSP-SW/IST- Standby Service Water Loop B Operability 34

Q702

SOP-CIA-OPS Containment Instrument Air System Operation 4

SOP-SW-FILL Standby Service Water System Fill 7

SOP-SW- Standby Service Water System Shutdown 2

SHUTDOWN

SOP-SW-SPRAY Standby Service Water Spray Header Operations 0

SOP-SW-START Standby Service Water System Start 8

SQI-10-3 Receiving Inspection 31

SYS-4-24 Age Management of Electrolytic Capacitors 1

TM-2136 Air Operated Valve (AOV) Expert Categorization 1

TSP-SW-ISI- SW Loop B System Leakage Test 4

G802

Self-Assessments AR-SA 387497 NRC Design Bases Assurance Pre-Inspection Readiness 1

Work Orders Work Orders 02062267, 02062289, 02112270, 02117077, 02111626,

(WOs) 02113945, 02111983, 01179141, 01179142, 02062267,

2109842, 02050251, 02111620, 02070990, 02088765,

2088766, 02107343, 0203367254, 0203367277,

2070990003, 027098920, 02042529, 02047965,

2073657, 02114537-01

13

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