IR 05000354/2025012

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Fire Protection Team Inspection Report 05000354/2025012
ML25037A009
Person / Time
Site: Hope Creek 
Issue date: 02/06/2025
From: Glenn Dentel
Division of Operating Reactors
To: Mcfeaters C
Public Service Enterprise Group
References
IR 2025012
Download: ML25037A009 (1)


Text

February 6, 2025

SUBJECT:

HOPE CREEK GENERATING STATION - FIRE PROTECTION TEAM INSPECTION REPORT 05000354/2025012

Dear Charles McFeaters:

On January 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Hope Creek Generating Station and discussed the results of this inspection with Robert McLaughlin, Nuclear Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety

Docket No. 05000354 License No. NPF-57

Enclosure:

As stated

Inspection Report

Docket Number:

05000354

License Number:

NPF-57

Report Number:

05000354/2025012

Enterprise Identifier: I-2025-012-0005

Licensee:

PSEG Nuclear, LLC - N09

Facility:

Hope Creek Generating Station

Location:

Hancocks Bridge, NJ

Inspection Dates:

January 13, 2025 to January 30, 2025

Inspectors:

L. Cline, Senior Reactor Inspector

E. Miller, Senior Reactor Inspector

J. Tifft, Senior Reactor Inspector

Approved By:

Glenn T. Dentel, Chief

Engineering Branch 2

Division of Operating Reactor Safety

SUMMARY

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

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

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

REACTOR SAFETY

===71111.21N.05 - Fire Protection Team Inspection (FPTI)

Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)===

The inspectors verified that components and/or systems will function as required to support the credited functions stated for each sample. Additional inspection considerations are located in the fire hazards analysis or safe shutdown analysis (SSA).

(1) Fire Detection System
(2) Fire Barrier System
(3) Reactor Core Isolation Cooling System
(4) Emergency Diesel Generator 'A'

Fire Protection Program Administrative Controls (IP Section 03.02) (2 Samples)

The inspectors verified that the selected control or process is implemented in accordance with the licensees current licensing basis. If applicable, ensure that the licensees Fire Protection Program (FPP) contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.

(1) Control of Transient Combustibles
(2) Fire Brigade Training, Drills, and Qualification

Fire Protection Program Changes/Modifications (IP Section 03.03) (1 Sample)

The inspectors verified the following:

a. Changes to the approved FPP do not constitute an adverse effect on the ability to safely shutdown.

b. The adequacy of the design modification, if applicable.

c. Assumptions and performance capability stated in the SSA have not been degraded through changes or modifications.

d. The FPP documents, such as the Updated Final Safety Analysis Report, fire protection report, fire hazards analysis, and SSA were updated consistent with the FPP or design change.

e. Post-fire safe shutdown operating procedures, such as abnormal operating procedures, affected by the modification were updated.

(1) Time Critical Actions Revalidation

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On January 30, 2025, the inspectors presented the fire protection team inspection results to Robert McLaughlin, Nuclear Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21N.05 Corrective Action

Documents

20880344

20898243

20899016

20941160

20981379

20946992

20967574

20971380

20972669

20980170

20898424

Corrective Action

Documents

Resulting from

Inspection

20983334

20985279

20985414

20985602

20985610

20985611

20985613

20985616

20985639

20985927

20986162

20986168

20986183

20986184

20986528

20986531

20986541

20986591

Drawings

E-1521-1 Sheet 2 Raceway Plan Reactor Building Area 14 Plan Elevation

54'-0"

Revision 24

E-1522-1 Sheet 1 Raceway Plan Reactor Building Area 14 Plan Elevation

Revision 26

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

77'-0"

E-1523-1 Sheet 1 Raceway Plan Reactor Building Area 14 Plan Elevation

2'-0"

Revision 30

E-1531-1 Sheet 2 Raceway Plan Reactor Building Area 13 Plan Elevation

54'-0"

Revision 28

E-1631-1 Sheet 2 Raceway Plan Reactor Building Area 22 Plan Elevation

54'-0"

Revision 25

E-1683-1

Raceway Plan Aux. Building D/G Area 28 plan at

Elevation 102'

Revision 34

E-1685-1

Raceway Plan Aux Building D/G Area 28 plan at Elevation

130'

Revision 29

Engineering

Evaluations

HC.ER-PS.FP-

0001-A5

Combustible Loading Calculation Methodology and Fire

Hazard Analysis for Turbine and Radwaste Building

Revision 0

VTD 430049

Volume 002

EPU TR T0611 - Appendix R/Fire Protection

11/16/2005

Miscellaneous

AC1G0601P

AP1G0636B

Cable Pull Cards 'A' Emergency Diesel Generator

01/16/2025

AC1G0601P

AP1G0636B

Cable Reports for 'A' Emergency Diesel Generator

01/16/2025

BL1Q0310A

BL1Q0310E

BP1Q0310B

BP1Q0310C

BP1Q0310D

Cable Pull Cards RCIC Feedwater Isolation Valve F013

01/13/2025

BL1Q0310A

BL1Q0310E

BP1Q0310B

BP1Q0310C

BP1Q0310D

Cable Reports RCIC Feedwater Isolation Valve F013

01/13/2025

HC.ER-PS.FP-

0001-A3

Hope Creek Fire Protection Report - Safe Shutdown

Analysis

Revision 0

NOSA-HPC-23-

Limited Scope Fire Protection Audit Report

05/31/2023

NUREG-1852

Demonstrating the Feasibility and Reliability of Operator

October

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Manual Actions in Response to Fire

2007

Order 80131728-

0070

Operations Time Validation Sheet - TCA-3 and TCA-4

11/27/2025

Order 80131728-

0090

Operations Response Time Validation Sheet - TCA-6

10/18/2024

Order 80131728-

0130

Operations Response Time Validation Sheet - TCA-12

01/27/2025

Updated Final

Safety Analysis

Report

Revision 26

Procedures

FP-AA-005

Fire Protection Surveillance and Periodic Test Program

Revision 8

FP-AA-011

Control of Transient Combustible Material

Revision 9

FP-AA-014

Fire Protection Training Program

Revision 7

HC.FP-ST-QK-

29(F)

Class 1 Fire Detection Functional Test

Revision 19

HC.FP-SV.ZZ-

26(F)

Flood and Fire Barrier Penetration Seal Inspection

Revision 9

HC.FP-SV.ZZ-

0056(F)

Fire Barrier Inspection

Revision 8

HC.FP-SV.ZZ-

0078(F)

Drywall Fire Barrier Inspection

Revision 6

OP-AA-102-106

Operator Response Time Program

Revision 2

OP-HC-102-106

Hope Creek Master List of Timed Actions

Revision 7

OP-HC-102-106-

F1

Master List of Timed Actions

Revision 2

OP-HC-108-101

Key Control - Hope Creek

Revision 3

SY-AA-101-120

Control of Security Locks, Keys, Cores and Combination

Locks

Revision 15

Work Orders

251906

229301