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=Text=
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{{#Wiki_filter:/RA/
{{#Wiki_filter:==SUBJECT:==
COLUMBIA GENERATING STATION - NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REPORT (NRC INSPECTION REPORT 05000397/2018007)


***
==Dear Mr. Sawatzke:==
On April 26, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Columbia Generating Station and discussed the results of this inspection with Mr. Alex Javorik, Vice President of Engineering, and other members of your staff. The results of this inspection are documented in the enclosed report.


/RA/ /RA-E/ /RA/ /RA/ /RA/ /RA/ 05/03/18 05/04/18 05/07/18 05/03/18 05/09/18 05/09/18
The NRC inspectors did not identify any finding or violation of more than minor significance.


/RA/  
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/
James F. Drake, Acting Chief Engineering Branch 2 Division of Reactor Safety Docket: 50-397 License: NPF-21 Enclosure:
Inspection Report 05000397/2018007


/RA/ /RA-E/ /RA/ /RA/ /RA/ /RA/ 05/03/18 05/04/18 05/07/18 05/03/18 05/09/18 05/09/18
U.S. NUCLEAR REGULATORY COMMISSION
 
==Inspection Report==
Docket Number: 05000397 License Number: NPF-21 Report Number: 05000397/2018007 Enterprise Identifier: I-2018-007-0002 Licensee: Energy Northwest Facility: Columbia Generating Station Location: Richland, Washington Inspection Dates: April 9, 2018, to April 26, 2018 Inspectors: J. Mateychick, Senior Reactor Inspector (Team Lead)
B. Correll, Reactor Inspector S. Makor, Reactor Inspector G. Pick, Senior Reactor Inspector Approved By: J. Drake, Chief Engineering Branch 2 Division of Reactor Safety Enclosure
 
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a Triennial Fire Protection Baseline 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. NRC and self-revealed findings, violations, and additional items are summarized in the table below.
 
List of Findings and Violations The NRC inspectors did not identify any finding or violation of more than minor significance.
 
=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==
71111.05T - Fire Protection (Triennial)
The inspectors evaluated the design, operational status, and material condition of the licensees fire protection program, including assumptions made in plant and area specific fire protection analyses, by verifying that the licensees program includes:
: (1) Adequate controls for combustibles and ignition sources inside the plant;
: (2) Adequate fire detection and suppression capability;
: (3) Passive fire protection features in good material condition;
: (4) Adequate compensatory measures for out-of-service, degraded or inoperable fire protection equipment, systems, or features;
: (5) Adequate protection to ensure the post-fire capability to safely shutdown the plant, including implementation of NRC/industry fire-induced circuit failure analysis guidance;
: (6) Feasible and reliable manual actions when appropriate to achieve safe shutdown; and
: (7) Adequate review and documentation of fire protection program changes.
 
Fire Protection Inspection Requirements (Four Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
Fire Area        Description R-1D              Reactor Building Northwest 471 Elevation RC-3              Cable Chase RC-4              Division 1 Electrical Equipment Room RC-14            Division 1 Switchgear Room The inspectors reviewed and evaluated the following fire protection inspection requirements:
: (1) Fire brigade drill performance
: (2) Protection of safe shutdown capabilities
: (3) Passive fire protection
: (4) Active fire protection
: (5) Protection from damage from fire suppression activities
: (6) Alternative shutdown capability
: (7) Circuit analysis
: (8) Communications
: (9) Emergency lighting (Fixed and Portable 8 hour units)
: (10) Cold shutdown repairs
: (11) Compensatory measures a. Compensatory measures for degraded fire protection components b. Compensatory measures for components necessary to achieve safe and stable conditions
: (12) Review and documentation of fire protection plan changes
: (13) Control of transient combustibles and ignition sources
: (14) Sample of fire protection corrective action documents B.5.b Inspection Activities (One Sample)
The inspectors evaluated feasibility of the B.5.b mitigating strategies by determining the following:
* Procedures are being maintained and adequate
* Equipment is properly staged and is being maintained and tested
* Station personnel are knowledgeable and can implement the procedures The inspectors evaluated feasibility of the following B.5.b Mitigating Strategies:
ABN-TSG-008          Initiation of Drywell or Wetwell Spray Through the Residual Heat Removal System ABN-TSG-010          Spent Fuel Pool Makeup Through the Residual Heat Removal System Via Fire Water or Condensate Transfer
 
==INSPECTION RESULTS==
The NRC inspectors did not identify any finding or violation of more than minor significance.
 
==EXIT MEETINGS AND DEBRIEFS==
The inspectors verified no proprietary information was retained or documented in this report.
 
On April 26, 2018, the inspectors presented the fire protection inspection results to Mr. A. Javorik, Vice President of Engineering, and other members of the licensee staff.
 
=DOCUMENTS REVIEWED=
 
Cable Routing Data Components
Residual Heat Removal System, Standby Service Water System
(RHR-P-2B, RHR-V-6B, RHR-FCV-64B, RHR-V-4B, SW-P-1B, RHR-V-3B, SW-V-12B)
Calculations            Title                                                  Revision or
Number                                                                          Date
FP-02-07-02            Hydraulic Analysis of Fire Water Supply System          2
FPF 2.11                Emergency Lighting Monthly Inspections and              2
Appendix R Lamp Positioning
ME-02-02-23            Post-Fire Safe Shutdown Flooding Analysis -            1
Radwaste Building
MSE-EJJ-10-01          Expert Panel Identification and Review of Multiple      April 23, 2010
Spurious Operation Scenarios
NE-02-85-19            Post-Fire Safe Shutdown Analysis                        12
NE-02-94-35            System Impact on Post-Fire Safe Shutdown                6
TM-2160                B.5.b Implementation                                    5
Action Requests (AR-)
378859*      379297*      379315*    378806*      378968*  379317*      379319*    378940*
378989      379316*      379320*    335821        374802    377838      378937*    340250
377836      378917*      379403*    379349*      378917*
*Issued as a result of inspection activities.
Drawings                Title                                                  Revision
Number
2-217A-28              Cable Chase - Zone 2 System 66 (Preaction)              10
2-217A-29              Cable Chase - Zone 2 System 66 (Preaction)              5
2-217A-30              Cable Chase - Zone 2 System 66 (Preaction)              7
2-217A-31              Cable Chase - Zone 2 System 66 (Preaction)              6
A529                    Reactor Building Stair No. A5                          6
A530                    Reactor Building Stair No. A6                          6
Drawings        Title                                                Revision
Number
C 896            FP-TK-110 Water Storage Tank Plan Sections and      3
Details
D00292, Sheet 36 Fire Detection and Alarm System Installation Diagram 0
                - Radioactive Waste and Control Building El 467
FM892-8          Sprinkler and Hose Station Plans EL 467-0          5
and 471-0 and Miscellaneous Floors
FM-892-12        Access-Egress for Post-Fire Safe Shutdown Activities 12
FM-892-13        Access-Egress for Post-Fire Safe Shutdown Activities 10
FM-892-14        Access-Egress for Post-Fire Safe Shutdown Activities 6
M521-1          Flow Diagram Residual Heat Removal Loop A          115
M521-2          Flow Diagram Residual Heat Removal Loop B          115
EWD-88-E-007    Electrical Wiring Diagram Diesel Generator (DG)      10
Building H&V System DG2 Room Normal Supply
Fan DMA-FN-22
EWD-88E-020A    Electrical Wiring Diagram Diesel Generator          11
Building H&V System DG2 Room Normal Air
Dampers DMA-AD-22/1 and DMA-AD-22/2
EWD-88E-029A    Electrical Wiring Diagram Diesel Generator          2
Building H&V System DG2 Room Air Handling
Unit DMA-AH-22 Outlet Heater DMA-EHC-22
EWD-88E-034      Electrical Wiring Diagram Diesel Generator Building  2
H&V System Annunciator DMA-ANN-PNL/DGHV2
EWD-9E-019      Electrical Wiring Diagram Residual Heat Removal      25
System Motor Operated Valve (MOV)
RHR-V-4B (E12-F004B)
PFSS-2          Appendix R Post-Fire Safe Shutdown (PFSS)            16
Division 2 Boundaries of Line Diagram
EWD-9E-097      Electrical Wiring Diagram Residual Heat Removal      13
System Miscellaneous Relay Circuits (Division 2)
Drawings  Title                                              Revision
Number
E948-1A    Appendix R Post-Fire Safe Shutdown Protected        0
Raceways Whittaker Cable Support Diagram
E948-2A    Appendix R Post-Fire Safe Shutdown Protected        8
Raceways Reactor Building Elevations 501-0 and
2-0
E948-3    Appendix R Post-Fire Safe Shutdown Protected        13
Raceways Radwaste Building - Elevations 467-0 and
25-0
EWD-9E-004 Electrical Wiring Diagram Residual Heat Removal    19
System Pump RHR-P-2B Breaker RHR-CB-P2B
EWD-9E-099 Electrical Wiring Diagram Residual Heat Removal    10
System Miscellaneous Relay Circuits (Division 2)
EWD-9E-100 Electrical Wiring Diagram Residual Heat Removal    8
System Miscellaneous Relay Circuits (Division 2)
E502-2    Main One Line Diagram                              63
EWD-9E-003 Electrical Wiring Diagram Residual Heat Removal    22
System Pump RHR-P-2B (E12-C002B)
EWD-7E-020 Electrical Wiring Diagram High Pressure Core Spray  16
System MOV HPCS-V-15 (E22-F015)
EWD-7E-023 Electrical Wiring Diagram High Pressure Core Spray  22
System Pump HPCS-P-1 (E-22-C001)
EWD-7E-022 Electrical Wiring Diagram High Pressure Core        21
Spray System Pump HPCS-P-1 (E22-C001)
Breaker HPCS-CB-P1
EWD-7E-003 Electrical Wiring Diagram High Pressure Core        7
Spray System Standby Water Leg Pump HPCS-P-3
          (E22-C003)
EWD-7E-018 Electrical Wiring Diagram High Pressure Core Spray  17
System MOV HPCS-V-11 (E22-F011)
M520      Flow Diagram High Pressure Core Spray (HPCS)        104
System and Low Pressure Core Spray Systems
Reactor Building
Drawings    Title                                              Revision
Number
EWD-7E-017  Electrical Wiring Diagram High Pressure Core Spray 15
System MOV HPCS-V-10 (E22-F0101)
EWD-58E-022  Electrical Wiring Diagram Standby Service Water    21
System MOV SW-V-12B
EWD-58E-021  Electrical Wiring Diagram Standby Service Water    24
System, MOV-SW-V-12B
EWD-58E-004  Electrical Wiring Diagram Standby Service Water    27
System SW-P-1B Breaker SW-CB-P1B
EWD-58E-004B Electrical Wiring Diagram Standby Service Water    3
System SW-P-1B Breaker SW-CB-P1B
M524-2      Flow Diagram Standby Service Water System          120
Reactor, Radwaste, DG Buildings and Yard
EWD-9E-022  Electrical Wiring Diagram Residual Heat Removal    21
System MOV RHR-V-6B (E12-F006B)
EWD-58E-014  Electrical Wiring Diagram Standby Service Water    19
System MOV SW-V-2B
EWD-58E-015  Electrical Wiring Diagram Standby Service Water    22
System MOV SW-V-2B
E542-22D    Connection Wiring Diagram Supervisory              2
Panel E-CP-C2 (Division 2) Rear Sub-Panel Lower
Half
E542-22E    Connection Wiring Diagram, Supervisory            5
Panel E-CP-CS2 (Division 2) Right Sub-Panel
EWD-58E-004  Electrical Wiring Diagram Standby Service Water    27
System W-P-1B Breaker SW-CB-P1B
EWD-58E-004B Electrical Wiring Diagram Standby Service Water    3
System SW-P-1B Breaker SW-CB-P1B
PFSS-2      Appendix R Post-Fire Safe Shutdown (PFSS)          16
Division 2 Boundaries One Line Diagram
EWD-9E-006  Electrical Wiring Diagram Residual Heat Removal    14
Drawings    Title                                                Revision
Number
System Pump RHR-P-2C Breaker RHR-CB-P2C
EWD-6E-008  Electrical Wiring Diagram Reactor Core Isolation    23
Cooling System MOV RCIC-V-45 (E51-F045)
EWD-6E-008A  Electrical Wiring Diagram Reactor Core Isolation    5
Cooling System MOV RCIC-V-45 (E51-F045)
6E013        Reactor Core Isolation Cooling System Miscellaneous  21
Relay Circuits Sheet 4
EWD-9E-057  Electrical Wiring Diagram Residual Heat Removal      20
System MOV RHR-FCV-64B (E12-F064B)
EWD-9E-123  Electrical Wiring Diagram Residual Heat Removal      3
System Annunciator
EWD-9E-004A  Electrical Wiring Diagram Residual Heat Removal      1
System Pump RHR-P-2B Breaker RHR-CB-P2B
EWD-9E-004  Electrical Wiring Diagram Residual Heat Removal      19
System Pump RHR-P-2B Breaker RHR-CB-P2B
EWD-41-003  Electrical Wiring Diagram Reactor Water Cleanup      0
System RWCU-FT-37, RWCU-PT-5, and
RWCU-TS-20
EWD-46E-252C Electrical Wiring Diagram AC Electrical Distribution 4
System Power Panel E-PP-8AF Circuit Details
EWD-9E-019  Electrical Wiring Diagram Residual Heat Removal      25
System MOV-RHR-V-4B (E12-F004B)
EWD-58E-047  Electrical Wiring Diagram Standby Service Water      22
System MOV RHR-V-68B (E12-F068B)
EWD-1E-038  Electrical Wiring Diagram Nuclear Boiler System      21
Automatic Depressurization Safety Relief
Valve MS-RV-3D (B22-F013V)
EWD-1E-038A  Electrical Wiring Diagram Nuclear Boiler System      4
Automatic Depressurization Safety Relief
Valve M-RV-3D (B22-F013V)
Drawings    Title                                              Revision
Number
H-4649-D    Sections - 20 x 10 Type A Head - 3 Stage
H-4650-D    Fire Pump - Vertical Turbine Model EBA              2
M515-1      Flow Diagram - Fire Protection System              110
M515-2      Flow Diagram - Fire Protection System Details      18
M515-4      Flow Diagram - Fire Protection System General      2
Services Building and Turbine Generator Building
M515-5      Flow Diagram - Fire Protection System Reactor      6
Building, Diesel Generator Building, and Radwaste
Building
M573-2      Flow Diagram - Potable Water Cold and Fire          8
Protection Systems Pump houses
M585        General Arrangement Plans and Sections Circulating  27
Water Pump House
M827        Heating Ventilation and Air Conditioning - Sections 41
and Details Radwaste and Control Building
M932-1      Fire Main Ring Header                              6
Modification Title                                              Revision
Number
16302-1      Disabled HPCS-V-10 and HPCS-V11 in Place            12
Procedures  Title                                              Revision
Number
ABN-EDMG    Extensive Damage Mitigation Guidelines (EDMG)      020/002
ABN-CR-EVAC  Control Room Evacuation and Remote Cooldown        37
ABN-FIRE    Fire                                                40
ABN-RHR-SDC- Residual Heat Removal Alternate Shutdown Cooling    015
ALT
ABN-TSG-008  Initiation of Drywell or Wetwell Spray Through the  006
Residual Heat Removal System
Procedures
Title                                                  Revision
Number
ABN-TSG-010 Spent Fuel Pool Makeup Through the Residual Heat      006
Removal System Via Fire Water or Condensate
Transfer
OI-18      Equipment Operator Rounds                              014/001
PFP-RB-471  Reactor 471 Pre-fire Plans                            5
PFP-RW-467  Radwaste (RW) 467 Pre-fire Plans                      5
PPM 1.3.10  Plant Fire Protection Program Implementation          034/002
PPM 1.3.10A Control of Ignition Sources                            017/001
PPM 1.3.10B Active Fire System Operability and Impairment          015/002
Control
PPM 1.3.10C Control of Transient Combustibles                      020/001
PPM 1.3.85  On-Line Fire Risk Management                          005/001
PPM 15.1.12 Fire Main Header Flush and Hydrant Inspection          19
PPM 15.1.29 B.5.b Pumper Truck and Monitor Nozzle Operability      10
PPM 15.2.2  Function and Sensitivity Check of Ionization Detectors 18
PPM 15.2.5  Zone 66 Ionization Detector Visual Inspections,        8
Function and Sensitivity Tests
PPM 15.2.25 Manual Pull Stations - CFT                            9
PPM 15.2.33 Power Generation Control Complex Halon Initiator      5
Replacement
PPM 15.2.36 Power Generation Control Complex Halon System          10
U679 Through U894 - Sensitivity Check, Actuation
Test and CFT
PPM 15.2.39 Emergency Lighting 8-Hour EBU and Essential            003/003
Fluorescent Lighting
PPM 15.2.40 Emergency Lighting 8-Hour EBU Discharge - Annual      007/002
PPM 15.2.41 Annual Surveillance of 8-Hour Portable Lanterns        005/003
PPM 15.3.2  Hose Station Inspection and Change out                13
Procedures
Title                                                Revision
Number
PPM 15.3.5        Fire Damper Operational Inspection                    15
PPM 15.3.6        Control Room Halon Pressure Check, Weight Check,      9
Flow Test, and Power Generation Control Complex
Barrier Inspection
PPM 15.3.9        Fire Pump Drive Inspection/Maintenance of            17
FP-ENG-1 (FP-P-1)
PPM 15.3.10      Fire Pump Drive Inspection/Maintenance of            20
FP-ENG-110 (FP-P-110)
PPM 15.3.17      Fire Door Operability - Semiannual, Annual, Biennial  9
PPM 15.4.2        Fire Main Hydraulic Data Acquisition                  13
PPM 15.4.6        Essential Fire Rated Penetration Seal, and Essential  10
Fire and Flood Barrier Operability Inspection
PPM 15.4.8        Fire Protection System Annual Functional Test        21
SWP-FPP-01        Nuclear Fire Protection Program (FPP)                8
Vendor Documents  Title                                                Date
Number
CVI 02,02,01,    NEDO-10466-A, Power Generation Control Complex        February
Sheet 99          Design Criteria and Safety Evaluation                1979
CVI 29,00,36      Johnston Vertical Deep well Pumps - Installation,    June 23, 1993
Operation, and Maintenance Manual
Work Orders
2013384-01    02013384-01        02013384-01        02013384-01    02013384-01
2013384-01    02013398-01        02035208-01        02057483-01    02066673-01
2066673-17    02066673-32        02066673-45        02066678-01    02066678-04
2066678-05    02076515-01        02078563-01        02083090-09    02083772-01
2084026-01    02084026-01        02088624-01        02094033-01    02094034-01
2094035-01    02094036-01        02094037-01        02100740-01    02100771-01
2100855-01    02102264-01        02104060-01        02108154-01    02109260-21
2109260-22    02116464-01        02119050-01
 
ML18129A382
SUNSI Review: ADAMS:        Non-Publicly Available  Non-Sensitive    Keyword: NRC-002
By: JMM        Yes  No    Publicly Available      Sensitive
OFFICE        RI:EB2      RI:EB2          SRI:EB2    SRI:EB2        BC:DRP/A      ABC:DRS/EB2
NAME          BCorrell    SMakor          GPick      JMateychick    MHaire        JDrake
SIGNATURE          /RA/      /RA-E/          /RA/      /RA/          /RA/            /RA/
DATE            05/03/18    05/04/18        05/07/18  05/03/18      05/09/18        05/09/18
 
May 9, 2018
Mr. Brad Sawatzke
Chief Executive Officer
Energy Northwest
MD 1023, P.O. Box 968
Richland, WA 99352
SUBJECT:          COLUMBIA GENERATING STATION - NRC TRIENNIAL FIRE
PROTECTION BASELINE INSPECTION REPORT (NRC INSPECTION
REPORT 05000397/2018007)
Dear Mr. Sawatzke:
On April 26, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at
the Columbia Generating Station and discussed the results of this inspection with Mr. Alex
Javorik, Vice President of Engineering, 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/
James
: [[contact::F. Drake]], Acting Chief
Engineering Branch 2
Division of Reactor Safety
Docket: 50-397
License: NPF-21
Enclosure:
Inspection Report 05000397/2018007
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:        05000397
License Number:        NPF-21
Report Number:        05000397/2018007
Enterprise Identifier: I-2018-007-0002
Licensee:              Energy Northwest
Facility:              Columbia Generating Station
Location:              Richland, Washington
Inspection Dates:      April 9, 2018, to April 26, 2018
Inspectors:           
: [[contact::J. Mateychick]], Senior Reactor Inspector (Team Lead)
: [[contact::B. Correll]], Reactor Inspector
: [[contact::S. Makor]], Reactor Inspector
: [[contact::G. Pick]], Senior Reactor Inspector
Approved By:         
: [[contact::J. Drake]], Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees
performance by conducting a Triennial Fire Protection Baseline 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. NRC and self-revealed findings, violations, and additional items are
summarized in the table below.
List of Findings and Violations
The NRC inspectors did not identify any finding or violation of more than minor significance.
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
71111.05T - Fire Protection (Triennial)
The inspectors evaluated the design, operational status, and material condition of the
licensees fire protection program, including assumptions made in plant and area specific
fire protection analyses, by verifying that the licensees program includes:
    (1) Adequate controls for combustibles and ignition sources inside the plant;
    (2) Adequate fire detection and suppression capability;
    (3) Passive fire protection features in good material condition;
    (4) Adequate compensatory measures for out-of-service, degraded or inoperable fire
protection equipment, systems, or features;
    (5) Adequate protection to ensure the post-fire capability to safely shutdown the plant,
including implementation of NRC/industry fire-induced circuit failure analysis guidance;
    (6) Feasible and reliable manual actions when appropriate to achieve safe shutdown; and
    (7) Adequate review and documentation of fire protection program changes.
Fire Protection Inspection Requirements (Four Samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
Fire Area        Description
R-1D              Reactor Building Northwest 471 Elevation
RC-3              Cable Chase
RC-4              Division 1 Electrical Equipment Room
RC-14            Division 1 Switchgear Room
The inspectors reviewed and evaluated the following fire protection inspection requirements:
    (1) Fire brigade drill performance
    (2) Protection of safe shutdown capabilities
    (3) Passive fire protection
    (4) Active fire protection
    (5) Protection from damage from fire suppression activities
    (6) Alternative shutdown capability
    (7) Circuit analysis
    (8) Communications
    (9) Emergency lighting (Fixed and Portable 8 hour units)
    (10) Cold shutdown repairs
    (11) Compensatory measures
a. Compensatory measures for degraded fire protection components
b. Compensatory measures for components necessary to achieve safe and stable
conditions
    (12) Review and documentation of fire protection plan changes
    (13) Control of transient combustibles and ignition sources
    (14) Sample of fire protection corrective action documents
B.5.b Inspection Activities (One Sample)
The inspectors evaluated feasibility of the B.5.b mitigating strategies by determining the
following:
          *  Procedures are being maintained and adequate
          *  Equipment is properly staged and is being maintained and tested
          *  Station personnel are knowledgeable and can implement the procedures
The inspectors evaluated feasibility of the following B.5.b Mitigating Strategies:
ABN-TSG-008          Initiation of Drywell or Wetwell Spray Through the Residual Heat
Removal System
ABN-TSG-010          Spent Fuel Pool Makeup Through the Residual Heat Removal System
Via Fire Water or Condensate Transfer
INSPECTION RESULTS
The NRC inspectors did not identify any finding or violation of more than minor significance.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 26, 2018, the inspectors presented the fire protection inspection results to
Mr.
: [[contact::A. Javorik]], Vice President of Engineering, and other members of the licensee staff.
DOCUMENTS REVIEWED
Cable Routing Data Components
Residual Heat Removal System, Standby Service Water System
(RHR-P-2B, RHR-V-6B, RHR-FCV-64B, RHR-V-4B, SW-P-1B, RHR-V-3B, SW-V-12B)
Calculations            Title                                                  Revision or
Number                                                                          Date
FP-02-07-02            Hydraulic Analysis of Fire Water Supply System          2
FPF 2.11                Emergency Lighting Monthly Inspections and              2
Appendix R Lamp Positioning
ME-02-02-23            Post-Fire Safe Shutdown Flooding Analysis -            1
Radwaste Building
MSE-EJJ-10-01          Expert Panel Identification and Review of Multiple      April 23, 2010
Spurious Operation Scenarios
NE-02-85-19            Post-Fire Safe Shutdown Analysis                        12
NE-02-94-35            System Impact on Post-Fire Safe Shutdown                6
TM-2160                B.5.b Implementation                                    5
Action Requests (AR-)
378859*      379297*      379315*    378806*      378968*  379317*      379319*    378940*
378989      379316*      379320*    335821        374802    377838      378937*    340250
377836      378917*      379403*    379349*      378917*
*Issued as a result of inspection activities.
Drawings                Title                                                  Revision
Number
2-217A-28              Cable Chase - Zone 2 System 66 (Preaction)              10
2-217A-29              Cable Chase - Zone 2 System 66 (Preaction)              5
2-217A-30              Cable Chase - Zone 2 System 66 (Preaction)              7
2-217A-31              Cable Chase - Zone 2 System 66 (Preaction)              6
A529                    Reactor Building Stair No. A5                          6
A530                    Reactor Building Stair No. A6                          6
Drawings        Title                                                Revision
Number
C 896            FP-TK-110 Water Storage Tank Plan Sections and      3
Details
D00292, Sheet 36 Fire Detection and Alarm System Installation Diagram 0
                - Radioactive Waste and Control Building El 467
FM892-8          Sprinkler and Hose Station Plans EL 467-0          5
and 471-0 and Miscellaneous Floors
FM-892-12        Access-Egress for Post-Fire Safe Shutdown Activities 12
FM-892-13        Access-Egress for Post-Fire Safe Shutdown Activities 10
FM-892-14        Access-Egress for Post-Fire Safe Shutdown Activities 6
M521-1          Flow Diagram Residual Heat Removal Loop A          115
M521-2          Flow Diagram Residual Heat Removal Loop B          115
EWD-88-E-007    Electrical Wiring Diagram Diesel Generator (DG)      10
Building H&V System DG2 Room Normal Supply
Fan DMA-FN-22
EWD-88E-020A    Electrical Wiring Diagram Diesel Generator          11
Building H&V System DG2 Room Normal Air
Dampers DMA-AD-22/1 and DMA-AD-22/2
EWD-88E-029A    Electrical Wiring Diagram Diesel Generator          2
Building H&V System DG2 Room Air Handling
Unit DMA-AH-22 Outlet Heater DMA-EHC-22
EWD-88E-034      Electrical Wiring Diagram Diesel Generator Building  2
H&V System Annunciator DMA-ANN-PNL/DGHV2
EWD-9E-019      Electrical Wiring Diagram Residual Heat Removal      25
System Motor Operated Valve (MOV)
RHR-V-4B (E12-F004B)
PFSS-2          Appendix R Post-Fire Safe Shutdown (PFSS)            16
Division 2 Boundaries of Line Diagram
EWD-9E-097      Electrical Wiring Diagram Residual Heat Removal      13
System Miscellaneous Relay Circuits (Division 2)
Drawings  Title                                              Revision
Number
E948-1A    Appendix R Post-Fire Safe Shutdown Protected        0
Raceways Whittaker Cable Support Diagram
E948-2A    Appendix R Post-Fire Safe Shutdown Protected        8
Raceways Reactor Building Elevations 501-0 and
2-0
E948-3    Appendix R Post-Fire Safe Shutdown Protected        13
Raceways Radwaste Building - Elevations 467-0 and
25-0
EWD-9E-004 Electrical Wiring Diagram Residual Heat Removal    19
System Pump RHR-P-2B Breaker RHR-CB-P2B
EWD-9E-099 Electrical Wiring Diagram Residual Heat Removal    10
System Miscellaneous Relay Circuits (Division 2)
EWD-9E-100 Electrical Wiring Diagram Residual Heat Removal    8
System Miscellaneous Relay Circuits (Division 2)
E502-2    Main One Line Diagram                              63
EWD-9E-003 Electrical Wiring Diagram Residual Heat Removal    22
System Pump RHR-P-2B (E12-C002B)
EWD-7E-020 Electrical Wiring Diagram High Pressure Core Spray  16
System MOV HPCS-V-15 (E22-F015)
EWD-7E-023 Electrical Wiring Diagram High Pressure Core Spray  22
System Pump HPCS-P-1 (E-22-C001)
EWD-7E-022 Electrical Wiring Diagram High Pressure Core        21
Spray System Pump HPCS-P-1 (E22-C001)
Breaker HPCS-CB-P1
EWD-7E-003 Electrical Wiring Diagram High Pressure Core        7
Spray System Standby Water Leg Pump HPCS-P-3
          (E22-C003)
EWD-7E-018 Electrical Wiring Diagram High Pressure Core Spray  17
System MOV HPCS-V-11 (E22-F011)
M520      Flow Diagram High Pressure Core Spray (HPCS)        104
System and Low Pressure Core Spray Systems
Reactor Building
Drawings    Title                                              Revision
Number
EWD-7E-017  Electrical Wiring Diagram High Pressure Core Spray 15
System MOV HPCS-V-10 (E22-F0101)
EWD-58E-022  Electrical Wiring Diagram Standby Service Water    21
System MOV SW-V-12B
EWD-58E-021  Electrical Wiring Diagram Standby Service Water    24
System, MOV-SW-V-12B
EWD-58E-004  Electrical Wiring Diagram Standby Service Water    27
System SW-P-1B Breaker SW-CB-P1B
EWD-58E-004B Electrical Wiring Diagram Standby Service Water    3
System SW-P-1B Breaker SW-CB-P1B
M524-2      Flow Diagram Standby Service Water System          120
Reactor, Radwaste, DG Buildings and Yard
EWD-9E-022  Electrical Wiring Diagram Residual Heat Removal    21
System MOV RHR-V-6B (E12-F006B)
EWD-58E-014  Electrical Wiring Diagram Standby Service Water    19
System MOV SW-V-2B
EWD-58E-015  Electrical Wiring Diagram Standby Service Water    22
System MOV SW-V-2B
E542-22D    Connection Wiring Diagram Supervisory              2
Panel E-CP-C2 (Division 2) Rear Sub-Panel Lower
Half
E542-22E    Connection Wiring Diagram, Supervisory            5
Panel E-CP-CS2 (Division 2) Right Sub-Panel
EWD-58E-004  Electrical Wiring Diagram Standby Service Water    27
System W-P-1B Breaker SW-CB-P1B
EWD-58E-004B Electrical Wiring Diagram Standby Service Water    3
System SW-P-1B Breaker SW-CB-P1B
PFSS-2      Appendix R Post-Fire Safe Shutdown (PFSS)          16
Division 2 Boundaries One Line Diagram
EWD-9E-006  Electrical Wiring Diagram Residual Heat Removal    14
Drawings    Title                                                Revision
Number
System Pump RHR-P-2C Breaker RHR-CB-P2C
EWD-6E-008  Electrical Wiring Diagram Reactor Core Isolation    23
Cooling System MOV RCIC-V-45 (E51-F045)
EWD-6E-008A  Electrical Wiring Diagram Reactor Core Isolation    5
Cooling System MOV RCIC-V-45 (E51-F045)
6E013        Reactor Core Isolation Cooling System Miscellaneous  21
Relay Circuits Sheet 4
EWD-9E-057  Electrical Wiring Diagram Residual Heat Removal      20
System MOV RHR-FCV-64B (E12-F064B)
EWD-9E-123  Electrical Wiring Diagram Residual Heat Removal      3
System Annunciator
EWD-9E-004A  Electrical Wiring Diagram Residual Heat Removal      1
System Pump RHR-P-2B Breaker RHR-CB-P2B
EWD-9E-004  Electrical Wiring Diagram Residual Heat Removal      19
System Pump RHR-P-2B Breaker RHR-CB-P2B
EWD-41-003  Electrical Wiring Diagram Reactor Water Cleanup      0
System RWCU-FT-37, RWCU-PT-5, and
RWCU-TS-20
EWD-46E-252C Electrical Wiring Diagram AC Electrical Distribution 4
System Power Panel E-PP-8AF Circuit Details
EWD-9E-019  Electrical Wiring Diagram Residual Heat Removal      25
System MOV-RHR-V-4B (E12-F004B)
EWD-58E-047  Electrical Wiring Diagram Standby Service Water      22
System MOV RHR-V-68B (E12-F068B)
EWD-1E-038  Electrical Wiring Diagram Nuclear Boiler System      21
Automatic Depressurization Safety Relief
Valve MS-RV-3D (B22-F013V)
EWD-1E-038A  Electrical Wiring Diagram Nuclear Boiler System      4
Automatic Depressurization Safety Relief
Valve M-RV-3D (B22-F013V)
Drawings    Title                                              Revision
Number
H-4649-D    Sections - 20 x 10 Type A Head - 3 Stage
H-4650-D    Fire Pump - Vertical Turbine Model EBA              2
M515-1      Flow Diagram - Fire Protection System              110
M515-2      Flow Diagram - Fire Protection System Details      18
M515-4      Flow Diagram - Fire Protection System General      2
Services Building and Turbine Generator Building
M515-5      Flow Diagram - Fire Protection System Reactor      6
Building, Diesel Generator Building, and Radwaste
Building
M573-2      Flow Diagram - Potable Water Cold and Fire          8
Protection Systems Pump houses
M585        General Arrangement Plans and Sections Circulating  27
Water Pump House
M827        Heating Ventilation and Air Conditioning - Sections 41
and Details Radwaste and Control Building
M932-1      Fire Main Ring Header                              6
Modification Title                                              Revision
Number
16302-1      Disabled HPCS-V-10 and HPCS-V11 in Place            12
Procedures  Title                                              Revision
Number
ABN-EDMG    Extensive Damage Mitigation Guidelines (EDMG)      020/002
ABN-CR-EVAC  Control Room Evacuation and Remote Cooldown        37
ABN-FIRE    Fire                                                40
ABN-RHR-SDC- Residual Heat Removal Alternate Shutdown Cooling    015
ALT
ABN-TSG-008  Initiation of Drywell or Wetwell Spray Through the  006
Residual Heat Removal System
Procedures
Title                                                  Revision
Number
ABN-TSG-010 Spent Fuel Pool Makeup Through the Residual Heat      006
Removal System Via Fire Water or Condensate
Transfer
OI-18      Equipment Operator Rounds                              014/001
PFP-RB-471  Reactor 471 Pre-fire Plans                            5
PFP-RW-467  Radwaste (RW) 467 Pre-fire Plans                      5
PPM 1.3.10  Plant Fire Protection Program Implementation          034/002
PPM 1.3.10A Control of Ignition Sources                            017/001
PPM 1.3.10B Active Fire System Operability and Impairment          015/002
Control
PPM 1.3.10C Control of Transient Combustibles                      020/001
PPM 1.3.85  On-Line Fire Risk Management                          005/001
PPM 15.1.12 Fire Main Header Flush and Hydrant Inspection          19
PPM 15.1.29 B.5.b Pumper Truck and Monitor Nozzle Operability      10
PPM 15.2.2  Function and Sensitivity Check of Ionization Detectors 18
PPM 15.2.5  Zone 66 Ionization Detector Visual Inspections,        8
Function and Sensitivity Tests
PPM 15.2.25 Manual Pull Stations - CFT                            9
PPM 15.2.33 Power Generation Control Complex Halon Initiator      5
Replacement
PPM 15.2.36 Power Generation Control Complex Halon System          10
U679 Through U894 - Sensitivity Check, Actuation
Test and CFT
PPM 15.2.39 Emergency Lighting 8-Hour EBU and Essential            003/003
Fluorescent Lighting
PPM 15.2.40 Emergency Lighting 8-Hour EBU Discharge - Annual      007/002
PPM 15.2.41 Annual Surveillance of 8-Hour Portable Lanterns        005/003
PPM 15.3.2  Hose Station Inspection and Change out                13
Procedures
Title                                                Revision
Number
PPM 15.3.5        Fire Damper Operational Inspection                    15
PPM 15.3.6        Control Room Halon Pressure Check, Weight Check,      9
Flow Test, and Power Generation Control Complex
Barrier Inspection
PPM 15.3.9        Fire Pump Drive Inspection/Maintenance of            17
FP-ENG-1 (FP-P-1)
PPM 15.3.10      Fire Pump Drive Inspection/Maintenance of            20
FP-ENG-110 (FP-P-110)
PPM 15.3.17      Fire Door Operability - Semiannual, Annual, Biennial  9
PPM 15.4.2        Fire Main Hydraulic Data Acquisition                  13
PPM 15.4.6        Essential Fire Rated Penetration Seal, and Essential  10
Fire and Flood Barrier Operability Inspection
PPM 15.4.8        Fire Protection System Annual Functional Test        21
SWP-FPP-01        Nuclear Fire Protection Program (FPP)                8
Vendor Documents  Title                                                Date
Number
CVI 02,02,01,    NEDO-10466-A, Power Generation Control Complex        February
Sheet 99          Design Criteria and Safety Evaluation                1979
CVI 29,00,36      Johnston Vertical Deep well Pumps - Installation,    June 23, 1993
Operation, and Maintenance Manual
Work Orders
2013384-01    02013384-01        02013384-01        02013384-01    02013384-01
2013384-01    02013398-01        02035208-01        02057483-01    02066673-01
2066673-17    02066673-32        02066673-45        02066678-01    02066678-04
2066678-05    02076515-01        02078563-01        02083090-09    02083772-01
2084026-01    02084026-01        02088624-01        02094033-01    02094034-01
2094035-01    02094036-01        02094037-01        02100740-01    02100771-01
2100855-01    02102264-01        02104060-01        02108154-01    02109260-21
2109260-22    02116464-01        02119050-01
 
ML18129A382
SUNSI Review: ADAMS:        Non-Publicly Available  Non-Sensitive    Keyword: NRC-002
By: JMM        Yes  No    Publicly Available      Sensitive
OFFICE        RI:EB2      RI:EB2          SRI:EB2    SRI:EB2        BC:DRP/A      ABC:DRS/EB2
NAME          BCorrell    SMakor          GPick      JMateychick    MHaire        JDrake
SIGNATURE          /RA/       /RA-E/           /RA/       /RA/           /RA/           /RA/
DATE            05/03/18   05/04/18       05/07/18   05/03/18       05/09/18       05/09/18
}}
}}

Latest revision as of 04:31, 21 October 2019

NRC Triennial Fire Protection Baseline Inspection Report (NRC Inspection Report 05000397/2018007)
ML18129A382
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 05/09/2018
From: James Drake
NRC/RGN-IV/DRS/EB-2
To: Sawatzke B
Energy Northwest
Drake J
References
IR 2018007
Download: ML18129A382 (14)
v • d • e


Text

SUBJECT:

COLUMBIA GENERATING STATION - NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REPORT (NRC INSPECTION REPORT 05000397/2018007)

Dear Mr. Sawatzke:

On April 26, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Columbia Generating Station and discussed the results of this inspection with Mr. Alex Javorik, Vice President of Engineering, 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/

James F. Drake, Acting Chief Engineering Branch 2 Division of Reactor Safety Docket: 50-397 License: NPF-21 Enclosure:

Inspection Report 05000397/2018007

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number: 05000397 License Number: NPF-21 Report Number: 05000397/2018007 Enterprise Identifier: I-2018-007-0002 Licensee: Energy Northwest Facility: Columbia Generating Station Location: Richland, Washington Inspection Dates: April 9, 2018, to April 26, 2018 Inspectors: J. Mateychick, Senior Reactor Inspector (Team Lead)

B. Correll, Reactor Inspector S. Makor, Reactor Inspector G. Pick, Senior Reactor Inspector Approved By: J. Drake, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a Triennial Fire Protection Baseline 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. NRC and self-revealed findings, violations, and additional items are summarized in the table below.

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

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

71111.05T - Fire Protection (Triennial)

The inspectors evaluated the design, operational status, and material condition of the licensees fire protection program, including assumptions made in plant and area specific fire protection analyses, by verifying that the licensees program includes:

(1) Adequate controls for combustibles and ignition sources inside the plant;
(2) Adequate fire detection and suppression capability;
(3) Passive fire protection features in good material condition;
(4) Adequate compensatory measures for out-of-service, degraded or inoperable fire protection equipment, systems, or features;
(5) Adequate protection to ensure the post-fire capability to safely shutdown the plant, including implementation of NRC/industry fire-induced circuit failure analysis guidance;
(6) Feasible and reliable manual actions when appropriate to achieve safe shutdown; and
(7) Adequate review and documentation of fire protection program changes.

Fire Protection Inspection Requirements (Four Samples)

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

Fire Area Description R-1D Reactor Building Northwest 471 Elevation RC-3 Cable Chase RC-4 Division 1 Electrical Equipment Room RC-14 Division 1 Switchgear Room The inspectors reviewed and evaluated the following fire protection inspection requirements:

(1) Fire brigade drill performance
(2) Protection of safe shutdown capabilities
(3) Passive fire protection
(4) Active fire protection
(5) Protection from damage from fire suppression activities
(6) Alternative shutdown capability
(7) Circuit analysis
(8) Communications
(9) Emergency lighting (Fixed and Portable 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> units)
(10) Cold shutdown repairs
(11) Compensatory measures a. Compensatory measures for degraded fire protection components b. Compensatory measures for components necessary to achieve safe and stable conditions
(12) Review and documentation of fire protection plan changes
(13) Control of transient combustibles and ignition sources
(14) Sample of fire protection corrective action documents B.5.b Inspection Activities (One Sample)

The inspectors evaluated feasibility of the B.5.b mitigating strategies by determining the following:

  • Procedures are being maintained and adequate
  • Equipment is properly staged and is being maintained and tested
  • Station personnel are knowledgeable and can implement the procedures The inspectors evaluated feasibility of the following B.5.b Mitigating Strategies:

ABN-TSG-008 Initiation of Drywell or Wetwell Spray Through the Residual Heat Removal System ABN-TSG-010 Spent Fuel Pool Makeup Through the Residual Heat Removal System Via Fire Water or Condensate Transfer

INSPECTION RESULTS

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

EXIT MEETINGS AND DEBRIEFS

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

On April 26, 2018, the inspectors presented the fire protection inspection results to Mr. A. Javorik, Vice President of Engineering, and other members of the licensee staff.

DOCUMENTS REVIEWED

Cable Routing Data Components

Residual Heat Removal System, Standby Service Water System

(RHR-P-2B, RHR-V-6B, RHR-FCV-64B, RHR-V-4B, SW-P-1B, RHR-V-3B, SW-V-12B)

Calculations Title Revision or

Number Date

FP-02-07-02 Hydraulic Analysis of Fire Water Supply System 2

FPF 2.11 Emergency Lighting Monthly Inspections and 2

Appendix R Lamp Positioning

ME-02-02-23 Post-Fire Safe Shutdown Flooding Analysis - 1

Radwaste Building

MSE-EJJ-10-01 Expert Panel Identification and Review of Multiple April 23, 2010

Spurious Operation Scenarios

NE-02-85-19 Post-Fire Safe Shutdown Analysis 12

NE-02-94-35 System Impact on Post-Fire Safe Shutdown 6

TM-2160 B.5.b Implementation 5

Action Requests (AR-)

378859* 379297* 379315* 378806* 378968* 379317* 379319* 378940*

378989 379316* 379320* 335821 374802 377838 378937* 340250

377836 378917* 379403* 379349* 378917*

  • Issued as a result of inspection activities.

Drawings Title Revision

Number

2-217A-28 Cable Chase - Zone 2 System 66 (Preaction) 10

2-217A-29 Cable Chase - Zone 2 System 66 (Preaction) 5

2-217A-30 Cable Chase - Zone 2 System 66 (Preaction) 7

2-217A-31 Cable Chase - Zone 2 System 66 (Preaction) 6

A529 Reactor Building Stair No. A5 6

A530 Reactor Building Stair No. A6 6

Drawings Title Revision

Number

C 896 FP-TK-110 Water Storage Tank Plan Sections and 3

Details

D00292, Sheet 36 Fire Detection and Alarm System Installation Diagram 0

- Radioactive Waste and Control Building El 467

FM892-8 Sprinkler and Hose Station Plans EL 467-0 5

and 471-0 and Miscellaneous Floors

FM-892-12 Access-Egress for Post-Fire Safe Shutdown Activities 12

FM-892-13 Access-Egress for Post-Fire Safe Shutdown Activities 10

FM-892-14 Access-Egress for Post-Fire Safe Shutdown Activities 6

M521-1 Flow Diagram Residual Heat Removal Loop A 115

M521-2 Flow Diagram Residual Heat Removal Loop B 115

EWD-88-E-007 Electrical Wiring Diagram Diesel Generator (DG) 10

Building H&V System DG2 Room Normal Supply

Fan DMA-FN-22

EWD-88E-020A Electrical Wiring Diagram Diesel Generator 11

Building H&V System DG2 Room Normal Air

Dampers DMA-AD-22/1 and DMA-AD-22/2

EWD-88E-029A Electrical Wiring Diagram Diesel Generator 2

Building H&V System DG2 Room Air Handling

Unit DMA-AH-22 Outlet Heater DMA-EHC-22

EWD-88E-034 Electrical Wiring Diagram Diesel Generator Building 2

H&V System Annunciator DMA-ANN-PNL/DGHV2

EWD-9E-019 Electrical Wiring Diagram Residual Heat Removal 25

System Motor Operated Valve (MOV)

RHR-V-4B (E12-F004B)

PFSS-2 Appendix R Post-Fire Safe Shutdown (PFSS) 16

Division 2 Boundaries of Line Diagram

EWD-9E-097 Electrical Wiring Diagram Residual Heat Removal 13

System Miscellaneous Relay Circuits (Division 2)

Drawings Title Revision

Number

E948-1A Appendix R Post-Fire Safe Shutdown Protected 0

Raceways Whittaker Cable Support Diagram

E948-2A Appendix R Post-Fire Safe Shutdown Protected 8

Raceways Reactor Building Elevations 501-0 and

2-0

E948-3 Appendix R Post-Fire Safe Shutdown Protected 13

Raceways Radwaste Building - Elevations 467-0 and

25-0

EWD-9E-004 Electrical Wiring Diagram Residual Heat Removal 19

System Pump RHR-P-2B Breaker RHR-CB-P2B

EWD-9E-099 Electrical Wiring Diagram Residual Heat Removal 10

System Miscellaneous Relay Circuits (Division 2)

EWD-9E-100 Electrical Wiring Diagram Residual Heat Removal 8

System Miscellaneous Relay Circuits (Division 2)

E502-2 Main One Line Diagram 63

EWD-9E-003 Electrical Wiring Diagram Residual Heat Removal 22

System Pump RHR-P-2B (E12-C002B)

EWD-7E-020 Electrical Wiring Diagram High Pressure Core Spray 16

System MOV HPCS-V-15 (E22-F015)

EWD-7E-023 Electrical Wiring Diagram High Pressure Core Spray 22

System Pump HPCS-P-1 (E-22-C001)

EWD-7E-022 Electrical Wiring Diagram High Pressure Core 21

Spray System Pump HPCS-P-1 (E22-C001)

Breaker HPCS-CB-P1

EWD-7E-003 Electrical Wiring Diagram High Pressure Core 7

Spray System Standby Water Leg Pump HPCS-P-3

(E22-C003)

EWD-7E-018 Electrical Wiring Diagram High Pressure Core Spray 17

System MOV HPCS-V-11 (E22-F011)

M520 Flow Diagram High Pressure Core Spray (HPCS) 104

System and Low Pressure Core Spray Systems

Reactor Building

Drawings Title Revision

Number

EWD-7E-017 Electrical Wiring Diagram High Pressure Core Spray 15

System MOV HPCS-V-10 (E22-F0101)

EWD-58E-022 Electrical Wiring Diagram Standby Service Water 21

System MOV SW-V-12B

EWD-58E-021 Electrical Wiring Diagram Standby Service Water 24

System, MOV-SW-V-12B

EWD-58E-004 Electrical Wiring Diagram Standby Service Water 27

System SW-P-1B Breaker SW-CB-P1B

EWD-58E-004B Electrical Wiring Diagram Standby Service Water 3

System SW-P-1B Breaker SW-CB-P1B

M524-2 Flow Diagram Standby Service Water System 120

Reactor, Radwaste, DG Buildings and Yard

EWD-9E-022 Electrical Wiring Diagram Residual Heat Removal 21

System MOV RHR-V-6B (E12-F006B)

EWD-58E-014 Electrical Wiring Diagram Standby Service Water 19

System MOV SW-V-2B

EWD-58E-015 Electrical Wiring Diagram Standby Service Water 22

System MOV SW-V-2B

E542-22D Connection Wiring Diagram Supervisory 2

Panel E-CP-C2 (Division 2) Rear Sub-Panel Lower

Half

E542-22E Connection Wiring Diagram, Supervisory 5

Panel E-CP-CS2 (Division 2) Right Sub-Panel

EWD-58E-004 Electrical Wiring Diagram Standby Service Water 27

System W-P-1B Breaker SW-CB-P1B

EWD-58E-004B Electrical Wiring Diagram Standby Service Water 3

System SW-P-1B Breaker SW-CB-P1B

PFSS-2 Appendix R Post-Fire Safe Shutdown (PFSS) 16

Division 2 Boundaries One Line Diagram

EWD-9E-006 Electrical Wiring Diagram Residual Heat Removal 14

Drawings Title Revision

Number

System Pump RHR-P-2C Breaker RHR-CB-P2C

EWD-6E-008 Electrical Wiring Diagram Reactor Core Isolation 23

Cooling System MOV RCIC-V-45 (E51-F045)

EWD-6E-008A Electrical Wiring Diagram Reactor Core Isolation 5

Cooling System MOV RCIC-V-45 (E51-F045)

6E013 Reactor Core Isolation Cooling System Miscellaneous 21

Relay Circuits Sheet 4

EWD-9E-057 Electrical Wiring Diagram Residual Heat Removal 20

System MOV RHR-FCV-64B (E12-F064B)

EWD-9E-123 Electrical Wiring Diagram Residual Heat Removal 3

System Annunciator

EWD-9E-004A Electrical Wiring Diagram Residual Heat Removal 1

System Pump RHR-P-2B Breaker RHR-CB-P2B

EWD-9E-004 Electrical Wiring Diagram Residual Heat Removal 19

System Pump RHR-P-2B Breaker RHR-CB-P2B

EWD-41-003 Electrical Wiring Diagram Reactor Water Cleanup 0

System RWCU-FT-37, RWCU-PT-5, and

RWCU-TS-20

EWD-46E-252C Electrical Wiring Diagram AC Electrical Distribution 4

System Power Panel E-PP-8AF Circuit Details

EWD-9E-019 Electrical Wiring Diagram Residual Heat Removal 25

System MOV-RHR-V-4B (E12-F004B)

EWD-58E-047 Electrical Wiring Diagram Standby Service Water 22

System MOV RHR-V-68B (E12-F068B)

EWD-1E-038 Electrical Wiring Diagram Nuclear Boiler System 21

Automatic Depressurization Safety Relief

Valve MS-RV-3D (B22-F013V)

EWD-1E-038A Electrical Wiring Diagram Nuclear Boiler System 4

Automatic Depressurization Safety Relief

Valve M-RV-3D (B22-F013V)

Drawings Title Revision

Number

H-4649-D Sections - 20 x 10 Type A Head - 3 Stage

H-4650-D Fire Pump - Vertical Turbine Model EBA 2

M515-1 Flow Diagram - Fire Protection System 110

M515-2 Flow Diagram - Fire Protection System Details 18

M515-4 Flow Diagram - Fire Protection System General 2

Services Building and Turbine Generator Building

M515-5 Flow Diagram - Fire Protection System Reactor 6

Building, Diesel Generator Building, and Radwaste

Building

M573-2 Flow Diagram - Potable Water Cold and Fire 8

Protection Systems Pump houses

M585 General Arrangement Plans and Sections Circulating 27

Water Pump House

M827 Heating Ventilation and Air Conditioning - Sections 41

and Details Radwaste and Control Building

M932-1 Fire Main Ring Header 6

Modification Title Revision

Number

16302-1 Disabled HPCS-V-10 and HPCS-V11 in Place 12

Procedures Title Revision

Number

ABN-EDMG Extensive Damage Mitigation Guidelines (EDMG) 020/002

ABN-CR-EVAC Control Room Evacuation and Remote Cooldown 37

ABN-FIRE Fire 40

ABN-RHR-SDC- Residual Heat Removal Alternate Shutdown Cooling 015

ALT

ABN-TSG-008 Initiation of Drywell or Wetwell Spray Through the 006

Residual Heat Removal System

Procedures

Title Revision

Number

ABN-TSG-010 Spent Fuel Pool Makeup Through the Residual Heat 006

Removal System Via Fire Water or Condensate

Transfer

OI-18 Equipment Operator Rounds 014/001

PFP-RB-471 Reactor 471 Pre-fire Plans 5

PFP-RW-467 Radwaste (RW) 467 Pre-fire Plans 5

PPM 1.3.10 Plant Fire Protection Program Implementation 034/002

PPM 1.3.10A Control of Ignition Sources 017/001

PPM 1.3.10B Active Fire System Operability and Impairment 015/002

Control

PPM 1.3.10C Control of Transient Combustibles 020/001

PPM 1.3.85 On-Line Fire Risk Management 005/001

PPM 15.1.12 Fire Main Header Flush and Hydrant Inspection 19

PPM 15.1.29 B.5.b Pumper Truck and Monitor Nozzle Operability 10

PPM 15.2.2 Function and Sensitivity Check of Ionization Detectors 18

PPM 15.2.5 Zone 66 Ionization Detector Visual Inspections, 8

Function and Sensitivity Tests

PPM 15.2.25 Manual Pull Stations - CFT 9

PPM 15.2.33 Power Generation Control Complex Halon Initiator 5

Replacement

PPM 15.2.36 Power Generation Control Complex Halon System 10

U679 Through U894 - Sensitivity Check, Actuation

Test and CFT

PPM 15.2.39 Emergency Lighting 8-Hour EBU and Essential 003/003

Fluorescent Lighting

PPM 15.2.40 Emergency Lighting 8-Hour EBU Discharge - Annual 007/002

PPM 15.2.41 Annual Surveillance of 8-Hour Portable Lanterns 005/003

PPM 15.3.2 Hose Station Inspection and Change out 13

Procedures

Title Revision

Number

PPM 15.3.5 Fire Damper Operational Inspection 15

PPM 15.3.6 Control Room Halon Pressure Check, Weight Check, 9

Flow Test, and Power Generation Control Complex

Barrier Inspection

PPM 15.3.9 Fire Pump Drive Inspection/Maintenance of 17

FP-ENG-1 (FP-P-1)

PPM 15.3.10 Fire Pump Drive Inspection/Maintenance of 20

FP-ENG-110 (FP-P-110)

PPM 15.3.17 Fire Door Operability - Semiannual, Annual, Biennial 9

PPM 15.4.2 Fire Main Hydraulic Data Acquisition 13

PPM 15.4.6 Essential Fire Rated Penetration Seal, and Essential 10

Fire and Flood Barrier Operability Inspection

PPM 15.4.8 Fire Protection System Annual Functional Test 21

SWP-FPP-01 Nuclear Fire Protection Program (FPP) 8

Vendor Documents Title Date

Number

CVI 02,02,01, NEDO-10466-A, Power Generation Control Complex February

Sheet 99 Design Criteria and Safety Evaluation 1979

CVI 29,00,36 Johnston Vertical Deep well Pumps - Installation, June 23, 1993

Operation, and Maintenance Manual

Work Orders

2013384-01 02013384-01 02013384-01 02013384-01 02013384-01

2013384-01 02013398-01 02035208-01 02057483-01 02066673-01

2066673-17 02066673-32 02066673-45 02066678-01 02066678-04

2066678-05 02076515-01 02078563-01 02083090-09 02083772-01

2084026-01 02084026-01 02088624-01 02094033-01 02094034-01

2094035-01 02094036-01 02094037-01 02100740-01 02100771-01

2100855-01 02102264-01 02104060-01 02108154-01 02109260-21

2109260-22 02116464-01 02119050-01

ML18129A382

SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword: NRC-002

By: JMM Yes No Publicly Available Sensitive

OFFICE RI:EB2 RI:EB2 SRI:EB2 SRI:EB2 BC:DRP/A ABC:DRS/EB2

NAME BCorrell SMakor GPick JMateychick MHaire JDrake

SIGNATURE /RA/ /RA-E/ /RA/ /RA/ /RA/ /RA/

DATE 05/03/18 05/04/18 05/07/18 05/03/18 05/09/18 05/09/18

May 9, 2018

Mr. Brad Sawatzke

Chief Executive Officer

Energy Northwest

MD 1023, P.O. Box 968

Richland, WA 99352

SUBJECT: COLUMBIA GENERATING STATION - NRC TRIENNIAL FIRE

PROTECTION BASELINE INSPECTION REPORT (NRC INSPECTION

REPORT 05000397/2018007)

Dear Mr. Sawatzke:

On April 26, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at

the Columbia Generating Station and discussed the results of this inspection with Mr. Alex

Javorik, Vice President of Engineering, 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/

James

F. Drake, Acting Chief

Engineering Branch 2

Division of Reactor Safety

Docket: 50-397

License: NPF-21

Enclosure:

Inspection Report 05000397/2018007

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number: 05000397

License Number: NPF-21

Report Number: 05000397/2018007

Enterprise Identifier: I-2018-007-0002

Licensee: Energy Northwest

Facility: Columbia Generating Station

Location: Richland, Washington

Inspection Dates: April 9, 2018, to April 26, 2018

Inspectors:

J. Mateychick, Senior Reactor Inspector (Team Lead)
B. Correll, Reactor Inspector
S. Makor, Reactor Inspector
G. Pick, Senior Reactor Inspector

Approved By:

J. Drake, Chief

Engineering Branch 2

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees

performance by conducting a Triennial Fire Protection Baseline 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. NRC and self-revealed findings, violations, and additional items are

summarized in the table below.

List of Findings and Violations

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

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

71111.05T - Fire Protection (Triennial)

The inspectors evaluated the design, operational status, and material condition of the

licensees fire protection program, including assumptions made in plant and area specific

fire protection analyses, by verifying that the licensees program includes:

(1) Adequate controls for combustibles and ignition sources inside the plant;

(2) Adequate fire detection and suppression capability;

(3) Passive fire protection features in good material condition;

(4) Adequate compensatory measures for out-of-service, degraded or inoperable fire

protection equipment, systems, or features;

(5) Adequate protection to ensure the post-fire capability to safely shutdown the plant,

including implementation of NRC/industry fire-induced circuit failure analysis guidance;

(6) Feasible and reliable manual actions when appropriate to achieve safe shutdown; and

(7) Adequate review and documentation of fire protection program changes.

Fire Protection Inspection Requirements (Four Samples)

The inspectors evaluated fire protection program implementation in the following selected

areas:

Fire Area Description

R-1D Reactor Building Northwest 471 Elevation

RC-3 Cable Chase

RC-4 Division 1 Electrical Equipment Room

RC-14 Division 1 Switchgear Room

The inspectors reviewed and evaluated the following fire protection inspection requirements:

(1) Fire brigade drill performance

(2) Protection of safe shutdown capabilities

(3) Passive fire protection

(4) Active fire protection

(5) Protection from damage from fire suppression activities

(6) Alternative shutdown capability

(7) Circuit analysis

(8) Communications

(9) Emergency lighting (Fixed and Portable 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> units)

(10) Cold shutdown repairs

(11) Compensatory measures

a. Compensatory measures for degraded fire protection components

b. Compensatory measures for components necessary to achieve safe and stable

conditions

(12) Review and documentation of fire protection plan changes

(13) Control of transient combustibles and ignition sources

(14) Sample of fire protection corrective action documents

B.5.b Inspection Activities (One Sample)

The inspectors evaluated feasibility of the B.5.b mitigating strategies by determining the

following:

  • Procedures are being maintained and adequate
  • Equipment is properly staged and is being maintained and tested
  • Station personnel are knowledgeable and can implement the procedures

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

ABN-TSG-008 Initiation of Drywell or Wetwell Spray Through the Residual Heat

Removal System

ABN-TSG-010 Spent Fuel Pool Makeup Through the Residual Heat Removal System

Via Fire Water or Condensate Transfer

INSPECTION RESULTS

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

EXIT MEETINGS AND DEBRIEFS

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

On April 26, 2018, the inspectors presented the fire protection inspection results to

Mr.

A. Javorik, Vice President of Engineering, and other members of the licensee staff.

DOCUMENTS REVIEWED

Cable Routing Data Components

Residual Heat Removal System, Standby Service Water System

(RHR-P-2B, RHR-V-6B, RHR-FCV-64B, RHR-V-4B, SW-P-1B, RHR-V-3B, SW-V-12B)

Calculations Title Revision or

Number Date

FP-02-07-02 Hydraulic Analysis of Fire Water Supply System 2

FPF 2.11 Emergency Lighting Monthly Inspections and 2

Appendix R Lamp Positioning

ME-02-02-23 Post-Fire Safe Shutdown Flooding Analysis - 1

Radwaste Building

MSE-EJJ-10-01 Expert Panel Identification and Review of Multiple April 23, 2010

Spurious Operation Scenarios

NE-02-85-19 Post-Fire Safe Shutdown Analysis 12

NE-02-94-35 System Impact on Post-Fire Safe Shutdown 6

TM-2160 B.5.b Implementation 5

Action Requests (AR-)

378859* 379297* 379315* 378806* 378968* 379317* 379319* 378940*

378989 379316* 379320* 335821 374802 377838 378937* 340250

377836 378917* 379403* 379349* 378917*

  • Issued as a result of inspection activities.

Drawings Title Revision

Number

2-217A-28 Cable Chase - Zone 2 System 66 (Preaction) 10

2-217A-29 Cable Chase - Zone 2 System 66 (Preaction) 5

2-217A-30 Cable Chase - Zone 2 System 66 (Preaction) 7

2-217A-31 Cable Chase - Zone 2 System 66 (Preaction) 6

A529 Reactor Building Stair No. A5 6

A530 Reactor Building Stair No. A6 6

Drawings Title Revision

Number

C 896 FP-TK-110 Water Storage Tank Plan Sections and 3

Details

D00292, Sheet 36 Fire Detection and Alarm System Installation Diagram 0

- Radioactive Waste and Control Building El 467

FM892-8 Sprinkler and Hose Station Plans EL 467-0 5

and 471-0 and Miscellaneous Floors

FM-892-12 Access-Egress for Post-Fire Safe Shutdown Activities 12

FM-892-13 Access-Egress for Post-Fire Safe Shutdown Activities 10

FM-892-14 Access-Egress for Post-Fire Safe Shutdown Activities 6

M521-1 Flow Diagram Residual Heat Removal Loop A 115

M521-2 Flow Diagram Residual Heat Removal Loop B 115

EWD-88-E-007 Electrical Wiring Diagram Diesel Generator (DG) 10

Building H&V System DG2 Room Normal Supply

Fan DMA-FN-22

EWD-88E-020A Electrical Wiring Diagram Diesel Generator 11

Building H&V System DG2 Room Normal Air

Dampers DMA-AD-22/1 and DMA-AD-22/2

EWD-88E-029A Electrical Wiring Diagram Diesel Generator 2

Building H&V System DG2 Room Air Handling

Unit DMA-AH-22 Outlet Heater DMA-EHC-22

EWD-88E-034 Electrical Wiring Diagram Diesel Generator Building 2

H&V System Annunciator DMA-ANN-PNL/DGHV2

EWD-9E-019 Electrical Wiring Diagram Residual Heat Removal 25

System Motor Operated Valve (MOV)

RHR-V-4B (E12-F004B)

PFSS-2 Appendix R Post-Fire Safe Shutdown (PFSS) 16

Division 2 Boundaries of Line Diagram

EWD-9E-097 Electrical Wiring Diagram Residual Heat Removal 13

System Miscellaneous Relay Circuits (Division 2)

Drawings Title Revision

Number

E948-1A Appendix R Post-Fire Safe Shutdown Protected 0

Raceways Whittaker Cable Support Diagram

E948-2A Appendix R Post-Fire Safe Shutdown Protected 8

Raceways Reactor Building Elevations 501-0 and

2-0

E948-3 Appendix R Post-Fire Safe Shutdown Protected 13

Raceways Radwaste Building - Elevations 467-0 and

25-0

EWD-9E-004 Electrical Wiring Diagram Residual Heat Removal 19

System Pump RHR-P-2B Breaker RHR-CB-P2B

EWD-9E-099 Electrical Wiring Diagram Residual Heat Removal 10

System Miscellaneous Relay Circuits (Division 2)

EWD-9E-100 Electrical Wiring Diagram Residual Heat Removal 8

System Miscellaneous Relay Circuits (Division 2)

E502-2 Main One Line Diagram 63

EWD-9E-003 Electrical Wiring Diagram Residual Heat Removal 22

System Pump RHR-P-2B (E12-C002B)

EWD-7E-020 Electrical Wiring Diagram High Pressure Core Spray 16

System MOV HPCS-V-15 (E22-F015)

EWD-7E-023 Electrical Wiring Diagram High Pressure Core Spray 22

System Pump HPCS-P-1 (E-22-C001)

EWD-7E-022 Electrical Wiring Diagram High Pressure Core 21

Spray System Pump HPCS-P-1 (E22-C001)

Breaker HPCS-CB-P1

EWD-7E-003 Electrical Wiring Diagram High Pressure Core 7

Spray System Standby Water Leg Pump HPCS-P-3

(E22-C003)

EWD-7E-018 Electrical Wiring Diagram High Pressure Core Spray 17

System MOV HPCS-V-11 (E22-F011)

M520 Flow Diagram High Pressure Core Spray (HPCS) 104

System and Low Pressure Core Spray Systems

Reactor Building

Drawings Title Revision

Number

EWD-7E-017 Electrical Wiring Diagram High Pressure Core Spray 15

System MOV HPCS-V-10 (E22-F0101)

EWD-58E-022 Electrical Wiring Diagram Standby Service Water 21

System MOV SW-V-12B

EWD-58E-021 Electrical Wiring Diagram Standby Service Water 24

System, MOV-SW-V-12B

EWD-58E-004 Electrical Wiring Diagram Standby Service Water 27

System SW-P-1B Breaker SW-CB-P1B

EWD-58E-004B Electrical Wiring Diagram Standby Service Water 3

System SW-P-1B Breaker SW-CB-P1B

M524-2 Flow Diagram Standby Service Water System 120

Reactor, Radwaste, DG Buildings and Yard

EWD-9E-022 Electrical Wiring Diagram Residual Heat Removal 21

System MOV RHR-V-6B (E12-F006B)

EWD-58E-014 Electrical Wiring Diagram Standby Service Water 19

System MOV SW-V-2B

EWD-58E-015 Electrical Wiring Diagram Standby Service Water 22

System MOV SW-V-2B

E542-22D Connection Wiring Diagram Supervisory 2

Panel E-CP-C2 (Division 2) Rear Sub-Panel Lower

Half

E542-22E Connection Wiring Diagram, Supervisory 5

Panel E-CP-CS2 (Division 2) Right Sub-Panel

EWD-58E-004 Electrical Wiring Diagram Standby Service Water 27

System W-P-1B Breaker SW-CB-P1B

EWD-58E-004B Electrical Wiring Diagram Standby Service Water 3

System SW-P-1B Breaker SW-CB-P1B

PFSS-2 Appendix R Post-Fire Safe Shutdown (PFSS) 16

Division 2 Boundaries One Line Diagram

EWD-9E-006 Electrical Wiring Diagram Residual Heat Removal 14

Drawings Title Revision

Number

System Pump RHR-P-2C Breaker RHR-CB-P2C

EWD-6E-008 Electrical Wiring Diagram Reactor Core Isolation 23

Cooling System MOV RCIC-V-45 (E51-F045)

EWD-6E-008A Electrical Wiring Diagram Reactor Core Isolation 5

Cooling System MOV RCIC-V-45 (E51-F045)

6E013 Reactor Core Isolation Cooling System Miscellaneous 21

Relay Circuits Sheet 4

EWD-9E-057 Electrical Wiring Diagram Residual Heat Removal 20

System MOV RHR-FCV-64B (E12-F064B)

EWD-9E-123 Electrical Wiring Diagram Residual Heat Removal 3

System Annunciator

EWD-9E-004A Electrical Wiring Diagram Residual Heat Removal 1

System Pump RHR-P-2B Breaker RHR-CB-P2B

EWD-9E-004 Electrical Wiring Diagram Residual Heat Removal 19

System Pump RHR-P-2B Breaker RHR-CB-P2B

EWD-41-003 Electrical Wiring Diagram Reactor Water Cleanup 0

System RWCU-FT-37, RWCU-PT-5, and

RWCU-TS-20

EWD-46E-252C Electrical Wiring Diagram AC Electrical Distribution 4

System Power Panel E-PP-8AF Circuit Details

EWD-9E-019 Electrical Wiring Diagram Residual Heat Removal 25

System MOV-RHR-V-4B (E12-F004B)

EWD-58E-047 Electrical Wiring Diagram Standby Service Water 22

System MOV RHR-V-68B (E12-F068B)

EWD-1E-038 Electrical Wiring Diagram Nuclear Boiler System 21

Automatic Depressurization Safety Relief

Valve MS-RV-3D (B22-F013V)

EWD-1E-038A Electrical Wiring Diagram Nuclear Boiler System 4

Automatic Depressurization Safety Relief

Valve M-RV-3D (B22-F013V)

Drawings Title Revision

Number

H-4649-D Sections - 20 x 10 Type A Head - 3 Stage

H-4650-D Fire Pump - Vertical Turbine Model EBA 2

M515-1 Flow Diagram - Fire Protection System 110

M515-2 Flow Diagram - Fire Protection System Details 18

M515-4 Flow Diagram - Fire Protection System General 2

Services Building and Turbine Generator Building

M515-5 Flow Diagram - Fire Protection System Reactor 6

Building, Diesel Generator Building, and Radwaste

Building

M573-2 Flow Diagram - Potable Water Cold and Fire 8

Protection Systems Pump houses

M585 General Arrangement Plans and Sections Circulating 27

Water Pump House

M827 Heating Ventilation and Air Conditioning - Sections 41

and Details Radwaste and Control Building

M932-1 Fire Main Ring Header 6

Modification Title Revision

Number

16302-1 Disabled HPCS-V-10 and HPCS-V11 in Place 12

Procedures Title Revision

Number

ABN-EDMG Extensive Damage Mitigation Guidelines (EDMG) 020/002

ABN-CR-EVAC Control Room Evacuation and Remote Cooldown 37

ABN-FIRE Fire 40

ABN-RHR-SDC- Residual Heat Removal Alternate Shutdown Cooling 015

ALT

ABN-TSG-008 Initiation of Drywell or Wetwell Spray Through the 006

Residual Heat Removal System

Procedures

Title Revision

Number

ABN-TSG-010 Spent Fuel Pool Makeup Through the Residual Heat 006

Removal System Via Fire Water or Condensate

Transfer

OI-18 Equipment Operator Rounds 014/001

PFP-RB-471 Reactor 471 Pre-fire Plans 5

PFP-RW-467 Radwaste (RW) 467 Pre-fire Plans 5

PPM 1.3.10 Plant Fire Protection Program Implementation 034/002

PPM 1.3.10A Control of Ignition Sources 017/001

PPM 1.3.10B Active Fire System Operability and Impairment 015/002

Control

PPM 1.3.10C Control of Transient Combustibles 020/001

PPM 1.3.85 On-Line Fire Risk Management 005/001

PPM 15.1.12 Fire Main Header Flush and Hydrant Inspection 19

PPM 15.1.29 B.5.b Pumper Truck and Monitor Nozzle Operability 10

PPM 15.2.2 Function and Sensitivity Check of Ionization Detectors 18

PPM 15.2.5 Zone 66 Ionization Detector Visual Inspections, 8

Function and Sensitivity Tests

PPM 15.2.25 Manual Pull Stations - CFT 9

PPM 15.2.33 Power Generation Control Complex Halon Initiator 5

Replacement

PPM 15.2.36 Power Generation Control Complex Halon System 10

U679 Through U894 - Sensitivity Check, Actuation

Test and CFT

PPM 15.2.39 Emergency Lighting 8-Hour EBU and Essential 003/003

Fluorescent Lighting

PPM 15.2.40 Emergency Lighting 8-Hour EBU Discharge - Annual 007/002

PPM 15.2.41 Annual Surveillance of 8-Hour Portable Lanterns 005/003

PPM 15.3.2 Hose Station Inspection and Change out 13

Procedures

Title Revision

Number

PPM 15.3.5 Fire Damper Operational Inspection 15

PPM 15.3.6 Control Room Halon Pressure Check, Weight Check, 9

Flow Test, and Power Generation Control Complex

Barrier Inspection

PPM 15.3.9 Fire Pump Drive Inspection/Maintenance of 17

FP-ENG-1 (FP-P-1)

PPM 15.3.10 Fire Pump Drive Inspection/Maintenance of 20

FP-ENG-110 (FP-P-110)

PPM 15.3.17 Fire Door Operability - Semiannual, Annual, Biennial 9

PPM 15.4.2 Fire Main Hydraulic Data Acquisition 13

PPM 15.4.6 Essential Fire Rated Penetration Seal, and Essential 10

Fire and Flood Barrier Operability Inspection

PPM 15.4.8 Fire Protection System Annual Functional Test 21

SWP-FPP-01 Nuclear Fire Protection Program (FPP) 8

Vendor Documents Title Date

Number

CVI 02,02,01, NEDO-10466-A, Power Generation Control Complex February

Sheet 99 Design Criteria and Safety Evaluation 1979

CVI 29,00,36 Johnston Vertical Deep well Pumps - Installation, June 23, 1993

Operation, and Maintenance Manual

Work Orders

2013384-01 02013384-01 02013384-01 02013384-01 02013384-01

2013384-01 02013398-01 02035208-01 02057483-01 02066673-01

2066673-17 02066673-32 02066673-45 02066678-01 02066678-04

2066678-05 02076515-01 02078563-01 02083090-09 02083772-01

2084026-01 02084026-01 02088624-01 02094033-01 02094034-01

2094035-01 02094036-01 02094037-01 02100740-01 02100771-01

2100855-01 02102264-01 02104060-01 02108154-01 02109260-21

2109260-22 02116464-01 02119050-01

ML18129A382

SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword: NRC-002

By: JMM Yes No Publicly Available Sensitive

OFFICE RI:EB2 RI:EB2 SRI:EB2 SRI:EB2 BC:DRP/A ABC:DRS/EB2

NAME BCorrell SMakor GPick JMateychick MHaire JDrake

SIGNATURE /RA/ /RA-E/ /RA/ /RA/ /RA/ /RA/

DATE 05/03/18 05/04/18 05/07/18 05/03/18 05/09/18 05/09/18

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