IR 05000298/2019010

Triennial Fire Protection Inspection Report 05000298/2019010

ML19150A142
Person / Time
Site:	Cooper
Issue date:	05/30/2019
From:	James Drake NRC/RGN-IV/DRS/EB-2
To:	Dent J Nebraska Public Power District (NPPD)
Drake J
References
IR 2019010
Download: ML19150A142 (14)

Text

May 30, 2019

SUBJECT:

COOPER NUCLEAR STATION - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000298/2019010

Dear Mr. Dent,

Jr.:

On May 2, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Cooper Nuclear Station and discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

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

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

James F. Drake, Acting Branch Chief Engineering Branch 2 Division of Reactor Safety

Docket No. 50-298 License No. DPR-46

Enclosure:

Inspection Report 05000298/2019010

Inspection Report

Docket Number:

05000298

License Number:

DPR-46

Report Number:

05000298/2019010

Licensee:

Nebraska Public Power District

Facility:

Cooper Nuclear Station

Location:

Brownville, Nebraska

Inspection Dates:

April 15, 2019, to May 02, 2019

Inspectors:

S. Alferink, Reactor Inspector

B. Correll, Reactor Inspector

J. Mateychick, Senior Reactor Inspector

C. Stott, Reactor Inspector

Approved By:

James F. Drake, Acting Branch Chief

Engineering Branch 2

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial fire protection inspection at Cooper Nuclear 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.

List of Findings and Violations

No findings were identified.

Additional Tracking Items

None.

INSPECTION SCOPE

This inspection was conducted using the appropriate portions of the inspection procedure (IP)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

71111.05XT - Fire Protection - NFPA 805 (Triennial) B.5.b Inspection Activities (IP Section 02.03)

The inspectors evaluated the following B.5.b Mitigating Strategy:

Fuel pool cooling using service water from the residual heat removal heat exchangers

Fire Protection Inspection Requirements (IP Section 02.01a) (5 Samples)

The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones, including analyzed electrical circuits:

(1) CB-D - Control Room, Computer Room, Cable Spreading Room, Cable Expansion Room, Auxiliary Relay Room

(2) RB-J - Switchgear Room 1F

(3) RB-K - Switchgear Room 1G

(4) RB-CF - Reactor Building 903 North Side

(5) RB-DI - Reactor Building 903 South Side

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

On May 2, 2019, the inspectors presented the triennial fire protection inspection results to Mr. J.

Dent, Jr. and other members of the licensee staff. The inspectors verified no proprietary information was retained or documented in this report.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.05XT Calculations

FPRR 2007-

003

Fire Protection Program

Regulatory Review

GE-NE-T23-

00742-01

Fire Analyses for Cooper

Nuclear Station

March

1997

GE-NE-T23-

00786-00-13

Cooper Nuclear Station

Containment Analysis Project

MDE-37-0286

Safe Shutdown Appendix R

Analyses for Cooper Nuclear

Station

February

1986

NEDC 05-008

Bulk Thermal-Hydraulic

Analyses for the Cooper SFP

with GE14 and GNF2 Fuel

Assemblies

NEDC 09-085

Task 7.14 Fire Risk

Quantification

NEDC 09-101

Detailed Fire Modeling Report

- Fire Compartment RB

NEDC 10-041

Recovery Action Feasibility

Assessment Report Review

EPM Report R1906-004-005

NEDC 10-046

Detailed Fire Modeling Report

- Fire Compartment RB-J

NEDC 10-047

Detailed Fire Modeling Report

- Fire Compartment RB-K

NEDC 10-062

EPM Report R1906-003-001

Rev. 1, NFPA 805 Radioactive

Release Review

NEDC 10-080

NFPA 805 Chapter 3

Fundamental Fire Protection

Program and Design Element

Review

NEDC 10-085

Task 8 Fire Risk Evaluation

Area CB-D

NEDC 10-090

Fire Risk Evaluation

Area RB-DI

NEDC 11-003

Non-Power Operation Modes

Transition Review of EPM

Report R1906-006-001

NEDC 11-019

Nuclear Safety Capability

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Assessment

NEDC 11-088

Fire Safety Analysis for Fire

Area CB-D

NEDC 11-094

Fire Safety Analysis for Fire

Area RB-CF EPM Report

R1906-008-RBCF

NEDC 11-095

Fire Safety Analysis for Fire

Area RB-DI EPM Report

R1906-008-RBDI

NEDC 11-098

Fire Safety Analysis for Fire

Area RB-J EPM Report

R1906-008-RBJ

NEDC 11-099

Fire Safety Analysis for Fire

Area RB-K EPM Report

R1906-008-RBK

NEDC 11-105

Fire Safety Analysis for Fire

Area TB-A EPM Report

R1906-007-TBA

NEDC 11-107

Fire Safety Analysis for Fire

Area YD

NEDC 11-148

NFPA 805 Transition

Radiological Assessments

NEDC 14-043

Fire Safety Analysis for Entire

Power Block, EPM Report

R1906-008-GEN

NEDC 14-045

Use of Fire Protection System

for Non-Fire Conditions

NEDC 86-

105B

CNS Critical AC Bus

Coordination Study

NEDC 95-062

Fuel Pool Boil off Makeup

Flow Rate Supplied by Fire

Hose from RHR HX SW Drain

NEDC 97-

044C

NPSH Margins for the RHR

and HPCI Pumps for an

Appendix R Event

Corrective

Action

Documents

2016-02899 2016-06427

2016-00713 2016-04709

2017-00223 2017-06233

2018-08638 2018-08621

Corrective

Action

2019-02295 2019-02319

2019-02323 2019-02530

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

Resulting from

Inspection

2019-02531 2019-02533

2019-02540 2019-02576

Drawings

2006 Sh. 1

Circulating and Screen Wash

and Service Water Systems

2006 Sh. 3

Circulating and Screen Wash

and Service Water Systems

2016 Sh. 1

Flow Diagram Fire Protection

Turbine Generator Building

2016 Sh. 1B

Flow Diagram Fire Protection

Control, Radwaste and

Augmented Radwaste

Buildings

2016 Sh. 1C

Flow Diagram Fire Protection

Reactor Building

2016 Sh. 2

Fire Protection System Flow

Diagram for Pumphouse and

Storage Tanks

2016 Sh. 4

Halon and Cardox System

Flow Diagram

2016 Sh. 7

Fire Protection System Site

Plan Flow Diagram

2036 Sh. 1

Reactor Building Service

Water System

A5

2040 Sh. 1

Residual Heat Removal

System

2040 Sh. 2

Residual Heat Removal

System Loop B

2043

Reactor Core Isolation

Coolant and Reactor

Feedwater Systems

2044

High Pressure Coolant

Injection and Reactor

Feedwater System

2045

Core Spray System

3002 Sh. 1

Auxiliary One Line Diagram

MCC Z, Swgr Bus 1A, 1B, 1E,

& Critical Swgr Bus 1F, 1G

3003 Sh. 2

Auxiliary One Line Diagram

Motor Control Centers A, B, F,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

& G

3006 Sh. 5

Auxiliary One Line Diagram

Starter Racks LZ and TZ

MCC's K, L, LX, RA, RX, S, T,

TX, X

3007 Sh. 6

Auxiliary One Line Diagram

Motor Control Centers E, Q,

R, RB, & Y

3058

DC One Line Diagram

791E253

Sh. 2

Automatic Blowdown System

N28

791E253

Sh. 3

Automatic Blowdown System

N12

791E261

Sh. 19

Residual Heat Removal

System

N28

791E261

Sh. 20

Residual Heat Removal

System

N16

791E261

Sh. 21

Residual Heat Removal

System

N17

791E261

Sh. 24

Residual Heat Removal

System

791E261

Sh. 4

Residual Heat Removal

System

791E261

Sh. 5

Residual Heat Removal

System

791E264

Sh. 6

RCIC System

791E266

Sh. 7

Primary Containment Isolation

System

N30

791E271

Sh. 7

HPCI System

791E271

Sh. 8

HPCI System

N20

E-501

Sh. 30D

RWCU-MOV-MO18 RWCU

Supply Outboard Isolation

Valve

N01

E501 Sh. 15H

RHR-MOV-MO16A Integrated

Control Circuit Diagram RHR

Pump A/C Min Flow Valve

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

E501 Sh. 16D

RCIC-MOV-MO15

N03

E501 Sh. 26A

SW-MOV-MO89A RHR Hx A

Service Water Outlet

N03

E501 Sh. 48A

SW-MOV-MO89B RHR Hx B

Service Water Outlet

Engineering

Changes

CED 6024460

Add Auxiliary Relays to

Condensate Pump and

Condensate Booster Pump

Breakers

08/24/2017

CED 6033800

Replacement of Startup

Station Service Transformer

10/05/2015

CED 6036741

Add Reliable SFP Level

Indication

01/28/2015

CED 6037040

Control Room Level Indication

03/27/2015

CED 6037042

Flexible Coping Strategies

(FLEX) External Connections

04/10/2015

EC 6040480

Addition of Constant Level

Lubricators to SW Booster

Pumps

08/10/2017

Engineering

Evaluations04-046

Appendix R MOV Overthrust

Evaluation

EE 09-031

Evaluation of Critical

Switchgear Rooms 1F and 1G

Fire Barrier Separation

EE 10-043

Evaluation of SSAR Changes

to Ensure Containment

Overpressure Availability

EE 10-071

CNS Acceptance of EPM

Report No: R1906-002-002,

NFPA Code Conformance

Review

EE01-006

Dispositions of NFPA Code

Compliance Deviations

EE01-007

Fire Detector Location and

Spacing

EE01-009

Review of NFPA 10, 14, & 24

Code Conformance for Power

Block Buildings

EE01-013

Disposition of NFPA Code

Compliance Deviations

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

PSA-ES098

Evaluation of Cable Types

Used at CNS for NFPA 805

Purposes

Fire Plans

CNS-FP-383

Generic Sea/Land Container,

Elevation - Various

Miscellaneous

NFPA 805 Monitoring

Program Periodic Assessment

2018

6871020P77-

A

ASTRO 25 Integrated Voice

and Data GTR 8000 Base

Radio

November

2011

CO-

161117PER

Nuclear Electric Insurance

Limited Property Loss Control

Comprehensive Evaluation

Report

November

2016

CO-

171130PER

Nuclear Electric Insurance

Limited Property Loss Control

Comprehensive Evaluation

Report

November

2017

Engineering

Report 2015-

2

NFPA 805 Fire Protection

Monitoring Program

LO 2018-0034

Fire Protection Program Self-

Assessment

01/31/2019

TMN

SKL0515159

Battery Explosion/Shutdown

from Outside the Control

Room

TRM T3.11

Technical Requirements

Manual - Fire Protection

Systems

10/17/2016

USAR

Volume X,

Section 9

Updated Safety Analysis

Report - Fire Protection

System

04/26/2018

USAR

Volume XIII,

Section 10.0

Fire Protection Program

09/14/2015

Procedures

NFPA 805 Portable Lighting

Test

0-Barrier-

Reactor

Reactor Building

0-CNS-OU-

Cooper Shutdown Safety

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

108

Management Program

0.23

CNS Fire Protection Plan

0.50.5

Outage Shutdown Safety

15.FP.307

Halon 1301 Computer Room

Fire Suppression Surveillance

Checks

15.FP.307

Halon 1301 Computer Room

Fire Suppression Surveillance

Checks

15.FP.650

Fire Locker and Hazardous

Material Response Inventory

15.FP.652

Critical Switchgear Room Duct

Wrap Visual Examination

2.2.4

Communication Systems

2.4CSCS

Inadvertent CSCS Initiation

2.4FPC

Fuel Pool Cooling Trouble

3-CNS-DC-

28

Fire Protection Program

Change Review

3-CNS-DC-

179

Fire Protection Engineering

Evaluations

3-CNS-DC-

357

NFPA 805 Monitoring

Program

3-EN-DC-115

Engineering Change Process

15C14

3-EN-DC-186

Fuse Control

0C0

3.49

Fire Protection Performance

Based Surveillance Test

Process

3.6.3

Fire Barrier Control

5.1Incident

Site Emergency Incident

5.3Alt-

Strategy

Alternate Core Cooling

Mitigating Strategies

5.3DC125

Loss of 125 VDC

5.4Fire-S/D

Fire Induced Shutdown from

Outside Control Room

5.4Post-Fire-

Control

Control Building Post-Fire

Operational Control

5.4Post-Fire-

Reactor Building Post-Fire

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Reactor

Operational Information

5.7COMMUN

Communications

6.1FP.302

Fire Detector System

Examination (Division 1)

6.ADS.202

ADS Manual Valve Circuit

Continuity from ASD-ADS

Panel

6.ASDR.301

ASD Panel Instrument Checks

6.FP.101

Fire Pump Operability Test

and 43

6.FP.102

Annual Testing of Fire Pumps

and 36

6.FP.103

Diesel Fire Pump Examination

6.FP.201

Operations Cycling of Fire

Main Valves

6.FP.202

Hose Station Valve Operability 9

6.FP.203

Fire Damper Assembly

Examination (Fire Protection

System 24 Month

Examination)

6.FP.204

Fire Door Examination

6.FP.301

Operations Power Block

Sprinkler System Testing

6.FP.302

Automatic Deluge and Pre-

Action Systems Testing

6.FP.304

Fire Detection System

Circuitry Operability

6.FP.306

Fire Detection Systems

Examination

6.FP.314

Panel 9-32 and 9-33 Incipient

Smoke Detector Testing

6.FP.604

Fire Door Full Examination

6.FP.606

Fire Barrier/Penetration Seal

Visual Examination

6.FP.608

License Required Firefighting

Equipment Examination

6.FP.610

Yard Hydrant Flow Check and

Fire Protection System Flow

Test

2, 27, and

6.HPCI.102

HPCI Test Mode Surveillance

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Operation From ASD-HPCI

Panel

6.RHR.201

RHR Motor Operated Valve

Operability Test from

ASD-RHR Panel

7.2.78.2

Pipe Penetration Seal

Installation Using Gasket

Placement

7.3.21.2

Fire Seal Installation - Internal

Conduit Using 3M Calk

7.3.21.7

3M Interam E-5A Fire Wrap

Fire Resistive Assembly

7.3.21.8

Promat-H Board Fire Barrier

Installation and Repair

TPP 201

CNS Licensed Personnel

Requalification Program

TPP 204

Non-Licensed Nuclear Plant

Operator Training Program

TTP 0206

Fire Brigade

TTP 0207

Fire Brigade Drills and

Evaluations

Self-

Assessments

2015-0031-31

NFPA 805 Monitoring

Program Periodic Assessment

2018

2/20/2018

QAD 2917-

0006

QA Audit 17-02, Fire

Protection

03/29/2017

Work Orders

28696 5028698 5057857

5058485 5070809 5077089

5085188 5102729 5118016

5118581 5125115 5125116

28988 5138324 5150832

5164653 5172539 5173795

5176537 5177517 5180034

5195504 5208766 5210075

234943 5252419 6166654

ML19150A142

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

By: JMM Yes No

Publicly Available Sensitive

OFFICE

RI:EB2

RI:EB2

RI:EB1

SRI:EB2

ABC:EB2

BC:PBC

ABC:EB2

NAME

SAlferink

BCorrell

CStott

JMateychick

JDrake

JKozal

JDrake

SIGNATURE

/RA/

/RA/

/RA/

/RA/

/RA/

/RA/

/RA/

DATE

5/22/2019

5/23/2019

5/21/2019

5/22/2019

5/22/2019

5/27/2019

5/30/2019