IR 05000282/2019012

Triennial Fire Protection Inspection Report 05000282/2019012 and 05000306/2019012 (DRS-A.Dahbur)

ML19239A415
Person / Time
Site:	Prairie Island
Issue date:	08/27/2019
From:	Robert Daley Engineering Branch 3
To:	Sharp S Northern States Power Company, Minnesota
References
IR 2019012
Download: ML19239A415 (8)

Text

ust 27, 2019

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000282/2019012 AND 05000306/2019012

Dear Mr. Sharp:

On July 25, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant and discussed the results of this inspection with Ms. Dominique Wilson, Director of Site Performance Operation Support, 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/

Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 05000282 and 05000306 License Nos. DPR-42 and DPR-60

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000282 and 05000306 License Numbers: DPR-42 and DPR-60 Report Numbers: 05000282/2019012 and 05000306/2019012 Enterprise Identifier: I-2019-012-0020 Licensee: Xcel Energy Facility: Prairie Island Nuclear Generating Plant Location: Welch, Minnesota Inspection Dates: June 24, 2019 to July 25, 2019 Inspectors: A. Dahbur, Senior Reactor Inspector M. Domke, Reactor Inspector D. Szwarc, Senior Reactor Inspector Approved By: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure

SUMMARY

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

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

Additional Tracking Items None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.05XT - Fire Protection - NFPA 805 Fire Protection Inspection Requirements (IP Section 02.01a)

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

(1) 18 Unit 2 Relay and Cable Spreading Room;

(2) 32 "B" Train Hot Shutdown Panel; and

(3) 59 Auxiliary Building Mezzanine Level.

Analyzed Circuits:

• CV-31084, Steam Generator Power Operated Relief Valve; and

• X-HIAW 48-22, 12 Diesel Cooling Water Pump.

B.5.b Inspection Activities (IP Section 02.03) (2 Samples)

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

(1) Attachment H - Containment Flooding; and

(2) Attachment K - Recovery of D1/D2 Cooling.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On July 25, 2019, the inspectors presented the triennial fire protection inspection results to Ms. Dominique Wilson, Director of Site Performance Operation Support, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05XT Calculations P2117-2400-03- Calculation for NFPA 805 Safe Shutdown Analysis - Decay 0

Heat Removal

Corrective Action 01515933 Missing Fire Barrier Between FA 15 And FA 59 03/16/2016

Documents 1536541 Unacceptable Thinning Found During Planned MIC 10/03/2016

Inspection

500001538543 Issues While Performing SP 1197 10/19/2016

501000016344 Sprinkler Heads Need Cleaning 08/30/2018

501000016839 PENF 19 Concrete Needs Repair 09/13/2018

501000020789 NOS ID: Seal Inspection Justification 12/07/2018

501000028647 B5b Cell Phones Not Tested 06/18/2019

Corrective Action 501000028783 CAP Closed to Lower Severity Level CAP 06/20/2019

Documents 501000028976 EDMG Cell Phones 06/26/2019

Resulting from 501000029050 EDMG-1 And PINGP 1385 Not At Gate House 06/27/2019

Inspection 501000029210 B.5.b Enhancement 06/28/2019

501000029213 Duplicate Calculations Issued 07/02/2019

501000029319 Incorrect Reference In Engineering Change 07/08/2019

501000029377 F5 Appendix D Unit 1/Unit 2 Error 07/0/2019

501000029377 F5 Appendix D U1/U2 Error 07/09/2019

501000029388 PRA Notebook Editorial Error 07/10/2019

501000029467 Error in Compensatory Measure Evaluation 07/12/2019

501000029680 Fire PRA Model Credit For Incipient Detectors 07/17/2019

Drawings 97FP02-2 (97FP02) AFW Pump Room Fire Protection Piping System 0

WPS-10

NE-40009 Sheet 12 Diesel Cooling Water Pump 78

NE-40009 Sheet 12 Diesel Cooling Water Pump 77

NF-40022-1 Circuit Diagram - 4KV And 480 Safeguard Buses Unit 1 81

NF-40322-3 Logic Diagram - Main Steam System Unit 1 76

Engineering 21572 NFPA 805 - PINGP Station Fire Damper -NFPA 805 02/12/2015

Changes Transition Activity -LAR L-PI-12-089, Attachment S, Table S-

Inspection Type Designation Description or Title Revision or

Procedure Date

2, Item 16

23914 NFPA 805 - Incipient Detection Project, LAR L-PI-14-045, 1

Table S-2, Item 5, 8

EC 25100 NFPA 805 - Unit 1 And 2 Auxiliary Feedwater Pump Room 12/02/2016

Separation

EC 25124 NFPA 805 12 And 22 DDCLP Modification 0

Engineering FPCE 18-008 Change Evaluation For H77.3 07/19/2018

Evaluations FPCE 18-010 Camera To Monitor 22 RCP Motor Lower Oil Reservoir Level 0

FPCE 18-013 Clearance Order For Pinhole Leak On Pipe 6-FP-18 2

FPEE 12-010 Access Control (FA15) To Auxiliary Building Mezzanine Level 1

Unit 1 (FA59)

FPEE-12-006 Fire Area 85 Boundaries And F5 Appendix K Barriers 3

FPEE-14-003 Explosion Analysis For Compressed Gas Cylinders 12/18/2014

FPEE-17-002 NFPA 805 LAR S-2 Compensatory Measures 0

FPRA-PI-CF Circuit Failure Mode Likelihood Analysis Notebook 04/13/2018

FPRA-PI-MCA Multi-Compartment Analysis Notebook 04/13/2018

FPRA-PI-MSO Fire Multiple Spurious Operation Notebook 04/13/2019

FPRA-PI-RRA Relay Room Analysis Notebook 5.3

V.SMN.15.007 Relay Room Incipient Detection Modification Sensitivity 03/10/2015

Miscellaneous FL-BSE-100-003L Introduction to Nuclear Security 0

PINGP 1385 Emergency Response Organization Activation 19

V.SMN.19.006 PINGP [Prairie Island Nuclear Generating Plant] NFPA 0

[National Fire Protection Association] 805 Monitoring

Program Risk Target Values

Operability F5 APP B Control Room Evacuation (Fire) 65

Evaluations

Procedures EDMG-2 Guideline for Damage Mitigation Strategies 12

F5 Appendix A Detection Zones and Fire Areas 41

F5 APPENDIX D Impact of Fire Outside Control/Relay Room 42

F5 Appendix D Impact of Fire Outside Control/Relay Room 41

F5 Appendix F Fire Hazards Analysis 36

F5 Appendix K Fire Protection Systems Functional Requirements 29

FP-PE-PRA-02 PRA Guideline for Model Maintenance and Update 16

Inspection Type Designation Description or Title Revision or

Procedure Date

H77 Fire Protection Program 2

H77.1 Fire Protection Program NFPA 805 Chapter 3 Compliance 2

Summary (NEI 04-02 Table B-1)

H77.2 Fire Protection Program NSCA Methodology Compliance 0

(NEI 04-02 Table B-2)

H77.3 Fire Area Assessments 0

Work Orders 700010880 SP 1192 Safeguards Electrical And Mechanical Penetrations 10/15/2018

Surveillance Inspection

700025089 SP 1197 Annual Header/Drains Flush Fire Protection System 06/18/2018

700028970 SP 1275 18 Month Safe Shutdown Fire Barrier Inspection 08/01/2018

700030214 SP 1196 Fire Protection Safety Related Sprinkler System 08/30/2018

Test

700032679 TP 1423 Portable Diesel Fire Pump Test 09/17/2018

700041404 SP 1197 Annual Header/Drains Flush Fire Protection System 07/13/2018

6