IR 05000397/2018007

NRC Triennial Fire Protection Baseline Inspection Report (NRC Inspection Report 05000397/2018007)

ML18129A382
Person / Time
Site:	Columbia
Issue date:	05/09/2018
From:	James Drake NRC/RGN-IV/DRS/EB-2
To:	Sawatzke B Energy Northwest
Drake J
References
IR 2018007
Preceding documents:	ML18012A711 (12 January 2018)
Download: ML18129A382 (14)

Text

May 9, 2018

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

Enclosure U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number:

05000397

License Number:

NPF-21

Report Number:

05000397/2018007

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

Number

Title

Revision or

Date

FP-02-07-02

Hydraulic Analysis of Fire Water Supply System

FPF 2.11

Emergency Lighting Monthly Inspections and

Appendix R Lamp Positioning

ME-02-02-23

Post-Fire Safe Shutdown Flooding Analysis -

Radwaste Building

MSE-EJJ-10-01

Expert Panel Identification and Review of Multiple

Spurious Operation Scenarios

April 23, 2010

NE-02-85-19

Post-Fire Safe Shutdown Analysis

NE-02-94-35

System Impact on Post-Fire Safe Shutdown

TM-2160

B.5.b Implementation

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

Number

Title

Revision

2-217A-28

Cable Chase - Zone 2 System 66 (Preaction)

2-217A-29

Cable Chase - Zone 2 System 66 (Preaction)

2-217A-30

Cable Chase - Zone 2 System 66 (Preaction)

2-217A-31

Cable Chase - Zone 2 System 66 (Preaction)

A529

Reactor Building Stair No. A5

A530

Reactor Building Stair No. A6

Drawings

Number

Title

Revision

C 896

FP-TK-110 Water Storage Tank Plan Sections and

Details

D00292, Sheet 36

Fire Detection and Alarm System Installation Diagram

- Radioactive Waste and Control Building El 467

FM892-8

Sprinkler and Hose Station Plans EL 467-0

and 471-0 and Miscellaneous Floors

FM-892-12

Access-Egress for Post-Fire Safe Shutdown Activities

FM-892-13

Access-Egress for Post-Fire Safe Shutdown Activities

FM-892-14

Access-Egress for Post-Fire Safe Shutdown Activities

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)

Building H&V System DG2 Room Normal Supply

Fan DMA-FN-22

EWD-88E-020A

Electrical Wiring Diagram Diesel Generator

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

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

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

EWD-9E-019

Electrical Wiring Diagram Residual Heat Removal

System Motor Operated Valve (MOV)

RHR-V-4B (E12-F004B)

PFSS-2

Appendix R Post-Fire Safe Shutdown (PFSS)

Division 2 Boundaries of Line Diagram

EWD-9E-097

Electrical Wiring Diagram Residual Heat Removal

System Miscellaneous Relay Circuits (Division 2)

Drawings

Number

Title

Revision

E948-1A

Appendix R Post-Fire Safe Shutdown Protected

Raceways Whittaker Cable Support Diagram

E948-2A

Appendix R Post-Fire Safe Shutdown Protected

Raceways Reactor Building Elevations 501-0 and

2-0

E948-3

Appendix R Post-Fire Safe Shutdown Protected

Raceways Radwaste Building - Elevations 467-0 and

25-0

EWD-9E-004

Electrical Wiring Diagram Residual Heat Removal

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

EWD-9E-099

Electrical Wiring Diagram Residual Heat Removal

System Miscellaneous Relay Circuits (Division 2)

EWD-9E-100

Electrical Wiring Diagram Residual Heat Removal

System Miscellaneous Relay Circuits (Division 2)

E502-2

Main One Line Diagram

EWD-9E-003

Electrical Wiring Diagram Residual Heat Removal

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

EWD-7E-020

Electrical Wiring Diagram High Pressure Core Spray

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

EWD-7E-023

Electrical Wiring Diagram High Pressure Core Spray

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

EWD-7E-022

Electrical Wiring Diagram High Pressure Core

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

Breaker HPCS-CB-P1

EWD-7E-003

Electrical Wiring Diagram High Pressure Core

Spray System Standby Water Leg Pump HPCS-P-3

(E22-C003)

EWD-7E-018

Electrical Wiring Diagram High Pressure Core Spray

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

M520

Flow Diagram High Pressure Core Spray (HPCS)

System and Low Pressure Core Spray Systems

Reactor Building

104

Drawings

Number

Title

Revision

EWD-7E-017

Electrical Wiring Diagram High Pressure Core Spray

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

EWD-58E-022

Electrical Wiring Diagram Standby Service Water

System MOV SW-V-12B

EWD-58E-021

Electrical Wiring Diagram Standby Service Water

System, MOV-SW-V-12B

EWD-58E-004

Electrical Wiring Diagram Standby Service Water

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

EWD-58E-004B

Electrical Wiring Diagram Standby Service Water

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

M524-2

Flow Diagram Standby Service Water System

Reactor, Radwaste, DG Buildings and Yard

20

EWD-9E-022

Electrical Wiring Diagram Residual Heat Removal

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

EWD-58E-014

Electrical Wiring Diagram Standby Service Water

System MOV SW-V-2B

EWD-58E-015

Electrical Wiring Diagram Standby Service Water

System MOV SW-V-2B

E542-22D

Connection Wiring Diagram Supervisory

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

Half

E542-22E

Connection Wiring Diagram, Supervisory

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

EWD-58E-004

Electrical Wiring Diagram Standby Service Water

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

EWD-58E-004B

Electrical Wiring Diagram Standby Service Water

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

PFSS-2

Appendix R Post-Fire Safe Shutdown (PFSS)

Division 2 Boundaries One Line Diagram

EWD-9E-006

Electrical Wiring Diagram Residual Heat Removal

Drawings

Number

Title

Revision

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

EWD-6E-008

Electrical Wiring Diagram Reactor Core Isolation

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

EWD-6E-008A

Electrical Wiring Diagram Reactor Core Isolation

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

6E013

Reactor Core Isolation Cooling System Miscellaneous

Relay Circuits Sheet 4

EWD-9E-057

Electrical Wiring Diagram Residual Heat Removal

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

EWD-9E-123

Electrical Wiring Diagram Residual Heat Removal

System Annunciator

EWD-9E-004A

Electrical Wiring Diagram Residual Heat Removal

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

EWD-9E-004

Electrical Wiring Diagram Residual Heat Removal

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

EWD-41-003

Electrical Wiring Diagram Reactor Water Cleanup

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

RWCU-TS-20

EWD-46E-252C

Electrical Wiring Diagram AC Electrical Distribution

System Power Panel E-PP-8AF Circuit Details

EWD-9E-019

Electrical Wiring Diagram Residual Heat Removal

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

EWD-58E-047

Electrical Wiring Diagram Standby Service Water

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

EWD-1E-038

Electrical Wiring Diagram Nuclear Boiler System

Automatic Depressurization Safety Relief

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

EWD-1E-038A

Electrical Wiring Diagram Nuclear Boiler System

Automatic Depressurization Safety Relief

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

Drawings

Number

Title

Revision

H-4649-D

Sections - 20 x 10 Type A Head - 3 Stage

H-4650-D

Fire Pump - Vertical Turbine Model EBA

M515-1

Flow Diagram - Fire Protection System

110

M515-2

Flow Diagram - Fire Protection System Details

M515-4

Flow Diagram - Fire Protection System General

Services Building and Turbine Generator Building

M515-5

Flow Diagram - Fire Protection System Reactor

Building, Diesel Generator Building, and Radwaste

Building

M573-2

Flow Diagram - Potable Water Cold and Fire

Protection Systems Pump houses

M585

General Arrangement Plans and Sections Circulating

Water Pump House

M827

Heating Ventilation and Air Conditioning - Sections

and Details Radwaste and Control Building

M932-1

Fire Main Ring Header

Modification

Number

Title

Revision

16302-1

Disabled HPCS-V-10 and HPCS-V11 in Place

Procedures

Number

Title

Revision

ABN-EDMG

Extensive Damage Mitigation Guidelines (EDMG)

20/002

ABN-CR-EVAC

Control Room Evacuation and Remote Cooldown

ABN-FIRE

Fire

ABN-RHR-SDC-

ALT

Residual Heat Removal Alternate Shutdown Cooling

015

ABN-TSG-008

Initiation of Drywell or Wetwell Spray Through the

Residual Heat Removal System

006

Procedures

Number

Title

Revision

ABN-TSG-010

Spent Fuel Pool Makeup Through the Residual Heat

Removal System Via Fire Water or Condensate

Transfer

006

OI-18

Equipment Operator Rounds

014/001

PFP-RB-471

Reactor 471 Pre-fire Plans

PFP-RW-467

Radwaste (RW) 467 Pre-fire Plans

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

Control

015/002

PPM 1.3.10C

Control of Transient Combustibles

20/001

PPM 1.3.85

On-Line Fire Risk Management

005/001

PPM 15.1.12

Fire Main Header Flush and Hydrant Inspection

PPM 15.1.29

B.5.b Pumper Truck and Monitor Nozzle Operability

PPM 15.2.2

Function and Sensitivity Check of Ionization Detectors 18

PPM 15.2.5

Zone 66 Ionization Detector Visual Inspections,

Function and Sensitivity Tests

PPM 15.2.25

Manual Pull Stations - CFT

PPM 15.2.33

Power Generation Control Complex Halon Initiator

Replacement

PPM 15.2.36

Power Generation Control Complex Halon System

U679 Through U894 - Sensitivity Check, Actuation

Test and CFT

PPM 15.2.39

Emergency Lighting 8-Hour EBU and Essential

Fluorescent Lighting

003/003

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

Procedures

Number

Title

Revision

PPM 15.3.5

Fire Damper Operational Inspection

PPM 15.3.6

Control Room Halon Pressure Check, Weight Check,

Flow Test, and Power Generation Control Complex

Barrier Inspection

PPM 15.3.9

Fire Pump Drive Inspection/Maintenance of

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

PPM 15.3.10

Fire Pump Drive Inspection/Maintenance of

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

PPM 15.3.17

Fire Door Operability - Semiannual, Annual, Biennial

PPM 15.4.2

Fire Main Hydraulic Data Acquisition

PPM 15.4.6

Essential Fire Rated Penetration Seal, and Essential

Fire and Flood Barrier Operability Inspection

PPM 15.4.8

Fire Protection System Annual Functional Test

SWP-FPP-01

Nuclear Fire Protection Program (FPP)

Vendor Documents

Number

Title

Date

CVI 02,02,01,

Sheet 99

NEDO-10466-A, Power Generation Control Complex

Design Criteria and Safety Evaluation

February

1979

CVI 29,00,36

Johnston Vertical Deep well Pumps - Installation,

Operation, and Maintenance Manual

June 23, 1993

Work Orders

2013384-01

2013384-01

2013384-01

2013384-01

2013384-01

2013384-01

2013398-01

2035208-01

2057483-01

2066673-01

2066673-17

2066673-32

2066673-45

2066678-01

2066678-04

2066678-05

2076515-01

2078563-01

2083090-09

2083772-01

2084026-01

2084026-01

2088624-01

2094033-01

2094034-01

2094035-01

2094036-01

2094037-01

2100740-01

2100771-01

2100855-01

2102264-01

2104060-01

2108154-01

2109260-21

2109260-22

2116464-01

2119050-01

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

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

Number

Title

Revision or

Date

FP-02-07-02

Hydraulic Analysis of Fire Water Supply System

FPF 2.11

Emergency Lighting Monthly Inspections and

Appendix R Lamp Positioning

ME-02-02-23

Post-Fire Safe Shutdown Flooding Analysis -

Radwaste Building

MSE-EJJ-10-01

Expert Panel Identification and Review of Multiple

Spurious Operation Scenarios

April 23, 2010

NE-02-85-19

Post-Fire Safe Shutdown Analysis

NE-02-94-35

System Impact on Post-Fire Safe Shutdown

TM-2160

B.5.b Implementation

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

Number

Title

Revision

2-217A-28

Cable Chase - Zone 2 System 66 (Preaction)

2-217A-29

Cable Chase - Zone 2 System 66 (Preaction)

2-217A-30

Cable Chase - Zone 2 System 66 (Preaction)

2-217A-31

Cable Chase - Zone 2 System 66 (Preaction)

A529

Reactor Building Stair No. A5

A530

Reactor Building Stair No. A6

Drawings

Number

Title

Revision

C 896

FP-TK-110 Water Storage Tank Plan Sections and

Details

D00292, Sheet 36

Fire Detection and Alarm System Installation Diagram

- Radioactive Waste and Control Building El 467

FM892-8

Sprinkler and Hose Station Plans EL 467-0

and 471-0 and Miscellaneous Floors

FM-892-12

Access-Egress for Post-Fire Safe Shutdown Activities

FM-892-13

Access-Egress for Post-Fire Safe Shutdown Activities

FM-892-14

Access-Egress for Post-Fire Safe Shutdown Activities

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)

Building H&V System DG2 Room Normal Supply

Fan DMA-FN-22

EWD-88E-020A

Electrical Wiring Diagram Diesel Generator

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

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

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

EWD-9E-019

Electrical Wiring Diagram Residual Heat Removal

System Motor Operated Valve (MOV)

RHR-V-4B (E12-F004B)

PFSS-2

Appendix R Post-Fire Safe Shutdown (PFSS)

Division 2 Boundaries of Line Diagram

EWD-9E-097

Electrical Wiring Diagram Residual Heat Removal

System Miscellaneous Relay Circuits (Division 2)

Drawings

Number

Title

Revision

E948-1A

Appendix R Post-Fire Safe Shutdown Protected

Raceways Whittaker Cable Support Diagram

E948-2A

Appendix R Post-Fire Safe Shutdown Protected

Raceways Reactor Building Elevations 501-0 and

2-0

E948-3

Appendix R Post-Fire Safe Shutdown Protected

Raceways Radwaste Building - Elevations 467-0 and

25-0

EWD-9E-004

Electrical Wiring Diagram Residual Heat Removal

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

EWD-9E-099

Electrical Wiring Diagram Residual Heat Removal

System Miscellaneous Relay Circuits (Division 2)

EWD-9E-100

Electrical Wiring Diagram Residual Heat Removal

System Miscellaneous Relay Circuits (Division 2)

E502-2

Main One Line Diagram

EWD-9E-003

Electrical Wiring Diagram Residual Heat Removal

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

EWD-7E-020

Electrical Wiring Diagram High Pressure Core Spray

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

EWD-7E-023

Electrical Wiring Diagram High Pressure Core Spray

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

EWD-7E-022

Electrical Wiring Diagram High Pressure Core

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

Breaker HPCS-CB-P1

EWD-7E-003

Electrical Wiring Diagram High Pressure Core

Spray System Standby Water Leg Pump HPCS-P-3

(E22-C003)

EWD-7E-018

Electrical Wiring Diagram High Pressure Core Spray

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

M520

Flow Diagram High Pressure Core Spray (HPCS)

System and Low Pressure Core Spray Systems

Reactor Building

104

Drawings

Number

Title

Revision

EWD-7E-017

Electrical Wiring Diagram High Pressure Core Spray

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

EWD-58E-022

Electrical Wiring Diagram Standby Service Water

System MOV SW-V-12B

EWD-58E-021

Electrical Wiring Diagram Standby Service Water

System, MOV-SW-V-12B

EWD-58E-004

Electrical Wiring Diagram Standby Service Water

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

EWD-58E-004B

Electrical Wiring Diagram Standby Service Water

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

M524-2

Flow Diagram Standby Service Water System

Reactor, Radwaste, DG Buildings and Yard

20

EWD-9E-022

Electrical Wiring Diagram Residual Heat Removal

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

EWD-58E-014

Electrical Wiring Diagram Standby Service Water

System MOV SW-V-2B

EWD-58E-015

Electrical Wiring Diagram Standby Service Water

System MOV SW-V-2B

E542-22D

Connection Wiring Diagram Supervisory

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

Half

E542-22E

Connection Wiring Diagram, Supervisory

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

EWD-58E-004

Electrical Wiring Diagram Standby Service Water

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

EWD-58E-004B

Electrical Wiring Diagram Standby Service Water

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

PFSS-2

Appendix R Post-Fire Safe Shutdown (PFSS)

Division 2 Boundaries One Line Diagram

EWD-9E-006

Electrical Wiring Diagram Residual Heat Removal

Drawings

Number

Title

Revision

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

EWD-6E-008

Electrical Wiring Diagram Reactor Core Isolation

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

EWD-6E-008A

Electrical Wiring Diagram Reactor Core Isolation

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

6E013

Reactor Core Isolation Cooling System Miscellaneous

Relay Circuits Sheet 4

EWD-9E-057

Electrical Wiring Diagram Residual Heat Removal

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

EWD-9E-123

Electrical Wiring Diagram Residual Heat Removal

System Annunciator

EWD-9E-004A

Electrical Wiring Diagram Residual Heat Removal

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

EWD-9E-004

Electrical Wiring Diagram Residual Heat Removal

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

EWD-41-003

Electrical Wiring Diagram Reactor Water Cleanup

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

RWCU-TS-20

EWD-46E-252C

Electrical Wiring Diagram AC Electrical Distribution

System Power Panel E-PP-8AF Circuit Details

EWD-9E-019

Electrical Wiring Diagram Residual Heat Removal

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

EWD-58E-047

Electrical Wiring Diagram Standby Service Water

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

EWD-1E-038

Electrical Wiring Diagram Nuclear Boiler System

Automatic Depressurization Safety Relief

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

EWD-1E-038A

Electrical Wiring Diagram Nuclear Boiler System

Automatic Depressurization Safety Relief

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

Drawings

Number

Title

Revision

H-4649-D

Sections - 20 x 10 Type A Head - 3 Stage

H-4650-D

Fire Pump - Vertical Turbine Model EBA

M515-1

Flow Diagram - Fire Protection System

110

M515-2

Flow Diagram - Fire Protection System Details

M515-4

Flow Diagram - Fire Protection System General

Services Building and Turbine Generator Building

M515-5

Flow Diagram - Fire Protection System Reactor

Building, Diesel Generator Building, and Radwaste

Building

M573-2

Flow Diagram - Potable Water Cold and Fire

Protection Systems Pump houses

M585

General Arrangement Plans and Sections Circulating

Water Pump House

M827

Heating Ventilation and Air Conditioning - Sections

and Details Radwaste and Control Building

M932-1

Fire Main Ring Header

Modification

Number

Title

Revision

16302-1

Disabled HPCS-V-10 and HPCS-V11 in Place

Procedures

Number

Title

Revision

ABN-EDMG

Extensive Damage Mitigation Guidelines (EDMG)

20/002

ABN-CR-EVAC

Control Room Evacuation and Remote Cooldown

ABN-FIRE

Fire

ABN-RHR-SDC-

ALT

Residual Heat Removal Alternate Shutdown Cooling

015

ABN-TSG-008

Initiation of Drywell or Wetwell Spray Through the

Residual Heat Removal System

006

Procedures

Number

Title

Revision

ABN-TSG-010

Spent Fuel Pool Makeup Through the Residual Heat

Removal System Via Fire Water or Condensate

Transfer

006

OI-18

Equipment Operator Rounds

014/001

PFP-RB-471

Reactor 471 Pre-fire Plans

PFP-RW-467

Radwaste (RW) 467 Pre-fire Plans

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

Control

015/002

PPM 1.3.10C

Control of Transient Combustibles

20/001

PPM 1.3.85

On-Line Fire Risk Management

005/001

PPM 15.1.12

Fire Main Header Flush and Hydrant Inspection

PPM 15.1.29

B.5.b Pumper Truck and Monitor Nozzle Operability

PPM 15.2.2

Function and Sensitivity Check of Ionization Detectors 18

PPM 15.2.5

Zone 66 Ionization Detector Visual Inspections,

Function and Sensitivity Tests

PPM 15.2.25

Manual Pull Stations - CFT

PPM 15.2.33

Power Generation Control Complex Halon Initiator

Replacement

PPM 15.2.36

Power Generation Control Complex Halon System

U679 Through U894 - Sensitivity Check, Actuation

Test and CFT

PPM 15.2.39

Emergency Lighting 8-Hour EBU and Essential

Fluorescent Lighting

003/003

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

Procedures

Number

Title

Revision

PPM 15.3.5

Fire Damper Operational Inspection

PPM 15.3.6

Control Room Halon Pressure Check, Weight Check,

Flow Test, and Power Generation Control Complex

Barrier Inspection

PPM 15.3.9

Fire Pump Drive Inspection/Maintenance of

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

PPM 15.3.10

Fire Pump Drive Inspection/Maintenance of

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

PPM 15.3.17

Fire Door Operability - Semiannual, Annual, Biennial

PPM 15.4.2

Fire Main Hydraulic Data Acquisition

PPM 15.4.6

Essential Fire Rated Penetration Seal, and Essential

Fire and Flood Barrier Operability Inspection

PPM 15.4.8

Fire Protection System Annual Functional Test

SWP-FPP-01

Nuclear Fire Protection Program (FPP)

Vendor Documents

Number

Title

Date

CVI 02,02,01,

Sheet 99

NEDO-10466-A, Power Generation Control Complex

Design Criteria and Safety Evaluation

February

1979

CVI 29,00,36

Johnston Vertical Deep well Pumps - Installation,

Operation, and Maintenance Manual

June 23, 1993

Work Orders

2013384-01

2013384-01

2013384-01

2013384-01

2013384-01

2013384-01

2013398-01

2035208-01

2057483-01

2066673-01

2066673-17

2066673-32

2066673-45

2066678-01

2066678-04

2066678-05

2076515-01

2078563-01

2083090-09

2083772-01

2084026-01

2084026-01

2088624-01

2094033-01

2094034-01

2094035-01

2094036-01

2094037-01

2100740-01

2100771-01

2100855-01

2102264-01

2104060-01

2108154-01

2109260-21

2109260-22

2116464-01

2119050-01

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