IR 05000397/2019011
| ML19268A201 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| 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) | |
Text
September 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:
Report Number:
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
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)
=
- (1) Residual Heat Removal Motor and Pump 2A
- Residual heat removal system health report
- 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
- Calculations for the number of required nitrogen bottles for system operability, capacity of the automatic depressurization system accumulators, and the time delays for valve closures
- 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
- Design bases documents, updated final safety analysis report, technical specifications and bases to assure licensing bases match component capabilities Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)
(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
- Design bases documents, updated final safety analysis report, technical specifications and bases to assure licensing bases match component capabilities
(2)
(Partial)
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.
- Activation of the remote shutdown panel completed within 10 minutes
- Isolation and de-energization of electrical bus SM-8 within 10 minutes
- Trip reactor protection system breakers within 10 minutes
- Venting primary containment without AC or DC 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
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculations
CE-02-87-29
Seismic Requirements for Scaffolding
CMR 15837
Update E/I-02-16-02 Due to Replacement of
RHR-M-P/2A
E/I-02-16-02
Standby AC Power ESF Load Group Transient Analysis
E/I-02-91-03
Calculation for Division 1, 2, and 3 Diesel Generators
Loading
E/I-02-92-01
Fuse Coordination Study for DC Power Systems
E/I-02-92-09
AC Short Circuit Current Analysis for 6.9kV, 4.16kV, and
480V Systems
E/I-02-92-17
Medium Voltage Electrical Distribution System Phase
Overcurrent Relay Settings
E/I-02-94-02
Direct Current Voltage Drop
2.05.01
Battery Sizing, Voltage Drop, and Charger Studies for Div. 1
and 2 Systems
4.14.02
SSW System (Spray Ponds)
5.17.19
Calculation for RHR Pressure Drop Calculation Modes A.1,
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
Supply N2 for Operating the ADS MSRVs Subsequent to a
Small Break LOCA
CMR-12870
Calculation Modification Record - Move Non-1E Loads from
Safety-Related Inverter E-PP-8AA, E/I-02-90-01
04/18/2014
E/I-02-95-01
Overcurrent Protective Device Settings and Coordination
Calculation for 480 Volt Distribution Systems
ME-02-00-14
CEP System Air Operated Valve (AOV) Functional and
MEDP Calculation
ME-02-02-02
Reactor Building Flooding Analysis
ME-02-02-08
Thermal Analysis of SW-P-1A and 1B at Shutoff Head
Conditions
ME-02-02-12
Seismic and Weak Link Analyses of AOVs CEP-V-3A and
4A
ME-02-85-79
SSW Spray Pond Temperature Transient w/o Sprays
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ME-02-91-88
Verification of 3 Min. Time Delay for CIV-V-39A/B Closure
ME-02-92-29
Number of Nitrogen Bottles Required for CIA System
Operability
ME-02-92-41
Calculation for Ultimate Heat Sink Analysis
ME-02-92-43
Room Temperature Calculation for DG Building, Reactor
Building, Radwaste Building, and Service Water
ME-02-95-11
Calculation of 42 Gallon Accumulator Capacity to Perform
the ADS Function with a Loss of the Safety-Related CIA
Supply
ME-02-95-25
Evaluation of Standby Service Water Capability
ME-02-97-08
Evaluate Ability of Service Water System to Provide
Adequate Cooling to the Diesel Generators While Operating
in a RPV/Containment Flooding Configuration
NE-02-92-38
IPE PRA: Equipment Survivability Evaluation
Corrective Action
Documents
Action Requests
(ARs)
00387202, 00387555, 00387577, 00387700, 00394958,
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
Operated Valve Component Level
Corrective Action
Documents
Resulting from
Inspection
Action Requests
(ARs)
00397740, 00397778, 00398257, 00398262, 00397701,
00397702, 00397705, 00397755, 00397777, 00397813,
00397828, 00397881, 00397899, 00397963, 00398055,
00398058, 00398173, 00398174, 00398176, 00398177,
00398243, 00398296, 00398297, 00398300, 00398324,
0039827
Drawings
E502-2
Main One Line
E505-1
DC One Line Diagram
109
M521-1
115
2B22-03, 2
Nuclear Boiler System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2B22-04, 54
Valve Actuators, Safety-Related, Pneumatically Operated,
General Requirements
2B22-08, 7
Self Actuated Nozzle Type Safety Valves with Air Cylinder
Actuated Pneumatically Operated Auxiliary Lifting Gear and
Parts List
09/08/2016
E504-1
Vital One Line Diagram
E535
Motor Control System Sheet No. 54F
E775-3
Main Control Room
PGCC Duct Layout
Sections and Details
E775-5
Main Control Room
PGCC Lateral and Transitional
Duct Layout
(Lower Floor Section)
EWD-46E-207A
Electrical Wiring Diagram
AC Electrical Distribution System
Inverters E-IN-2A and E-IN-2B
EWD-46E-211
Electrical Wiring Diagram
AC Electrical Distribution System
UPS TDAS/PDIS Computer
Power Panel E-PP-US/PT
EWD-46E-248
Electrical Wiring Diagram
AC Distribution System
Main Control Room
UPS Power Panel E-PP-8AA
EWD-46E-266
AC Electrical Distribution System
Reactor Building
Power Panel E-PP-3DAC
EWD-46E-317
Electrical Wiring Diagram
AC Electrical Distribution System
Radwaste Building
Power Panel E-PP-8A
EWD-58E-014
Standby Service Water System MOV SW-V-2B
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M520
High-Pressure Core Spray and Low-Pressure Core Spray
Flow Diagrams
103
M524-1
Standby Service Water System
135
M524-2
Standby Service Water System
M556
Containment Instrument Air System
Sketch 1
Sketch 1 Conduit Rework of E-PP-8AA and E-PP-US/5
Panesl
NA
Engineering
Changes
Move Non-1E Loads from Safety-Related Inverter
E-PP-8AA (Div 2)
Appendix R Modification for RHR-V-4B
Installation of Parallel Conductors on the Control Circuits of
E-CB-DG/7
Steam Tunnel Fan Alternate AC Source for
RRA-FN-21 and -9
Miscellaneous
Photographs of Electrical Splices Categorized as Class 1
System Health Report - AC (Instruments)
Surveillance Test Interval Evaluation Form
Schultz Motor Installation and Maintenance Manual
Load Testplan for 900HP Residual Heat Removal Pump
Motor
PDC 14635
Replace RHR Pump Motor P-2A
PO 339717
Flowserve RHR Pump Replacement
06/26/2015
PO 342467
Schulz RHR Pump Motor Replacement
2/31/2014
Specification
15606
Motor, Induction, Medium Voltage, Residual Heat Removal,
Safety-Related
Specification
15606
Specification for Motor, Induction, Medium Voltage, Residual
Heat Removal
STI-367211
LOP LOCA Testing STI Evaluation
04/15/2019
System Health
Report, AC/DC
System Health Report AC/DC (Instrument), Quarter 2, 2019
Quarter 2,
2019
System Health
Report, RHR
System Health Report RHR, Quarter 1, 2019
Quarter 1,
2019
280-RLCU00117-
Test Report SSW Pump Serial Number 731-S-0013
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Cable Schedule Information for Cable 2P8AA-0060
NA
Raceway Schedule Information
NA
675-00-7
Solatron - Line Voltage Regulator Operating and Service
Manual
2-00-15
Solidate Controls, Inc.
15kVA Inverter/Static Switch
84VC0150-03 84W0020-06 (Proprietary)
Operating Experience - Part 21 - Potential Defect Issued by
Ametek/Solidstate Controls
11/06/2017
Operating Experience - Part 21 Notification from AMETEK
Solid-State Controls for AC Voltage Sense Board
P/N 80-9210842
07/30/2018
Operating Experience - Part 21 ABB Motors
03/05/2019
Operating Experience - Evaluate EPRI Switchyard
Monitoring Technologies for Nuclear Power Plants for
Applicability to Columbia
03/07/2019
CVI/OMM 23-00-
Standby Service Water Vertical Pumps
CVI/OMM 818-
00-6
O&M Manual for the C&S Tricentric Stop Valve
DBD 305
Compressed Air Systems
DBD 307
Main Steam System
SD000156
Containment Instrument Air
SD000194
Uninterruptible Power Supply System
SD000198
TR-112175
EPRI Capacitor Application and Maintenance Guide
08/1999
Procedures
1.3.47
Fuse Replacement Control
10.2.53
DES-2-1
Plant Design Changes
ENG-DES-50
Interface to Standard Design Process
IP-ENG-001
Standard Design Process
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SWP-LIC-02
Licensing Basis Impact Determination
SWP-TST-02
Post-Maintenance Testing
1.5.19
Surveillance Frequency Control Program Procedure
1.5.20
Surveillance Frequency Control Program Procedure
10.24.28
SW-PS-1B Calibration
10.25.1
Inspections and Cleaning Division 1, E-IN-3A and E-IN-3B;
and Division 2, E-IN-2A and E-IN-2B; Inverters
10.25.19
Termination and Splicing Instruction
5.5.5
RHR/SW Crosstie Lineup
5.6.2
Station Blackout (SBO) and Extended Loss of AC Power
ELAP Attachements
ABN-CIA
Containment Instrument Air System Failure
ABN-CONT-
VENT
Containment Vent Without AC and DC Power Available
ABN-CR-EVAC
Control Room Evacuation and Remote Cooldown
ABN-FLOODING
Flooding
AOVPP-01
Air Operated Valve Program Plan
EOP 5.1.1
RPV Control
EOP 5.1.4
Emergency Wetwell Venting
EOP 5.5.2
RHR/SW Crosstie Lineup
EOP 5.5.20
Emergency Wetwell Venting with High Hydrogen and
Oxygen Concentration
EOP 5.5.21
Emergency Drywell Venting with High Hydrogen and
Oxygen Concentration
Spray Pond B Level - CC
LBD-IST-4
Inservice Testing Program Plan
MSP-MS/IST-
R101
MSRV Manual Actuation and Accessories Operability-
IN-SITU
OI-69
Time Critical Operator Actions
OSP-CIA/IST-
Q702
CIA Valve Operability - Shutdown
OSP-RHR/IST-
Q702
RHR Loop A Operability Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Loop B Valve Position Verification
SW Spray Pond Average Sediment Depth Measurement
QSP-SW/IST-
Q702
Standby Service Water Loop B Operability
SOP-CIA-OPS
Containment Instrument Air System Operation
SOP-SW-FILL
Standby Service Water System Fill
SOP-SW-
SHUTDOWN
Standby Service Water System Shutdown
SOP-SW-SPRAY
Standby Service Water Spray Header Operations
SOP-SW-START
Standby Service Water System Start
SQI-10-3
Receiving Inspection
SYS-4-24
Age Management of Electrolytic Capacitors
TM-2136
Air Operated Valve (AOV) Expert Categorization
TSP-SW-ISI-
G802
SW Loop B System Leakage Test
Self-Assessments AR-SA 387497
NRC Design Bases Assurance Pre-Inspection Readiness
Work Orders
Work Orders
(WOs)
2062267, 02062289, 02112270, 02117077, 02111626,
2113945, 02111983, 01179141, 01179142, 02062267,
2109842, 02050251, 02111620, 02070990, 02088765,
2088766, 02107343, 0203367254, 0203367277,
2070990003, 027098920, 02042529, 02047965,
2073657, 02114537-01