IR 05000261/2023010

Fire Protection Team Inspection Report 05000261/2023010

ML23324A450
Person / Time
Site:	Robinson
Issue date:	11/28/2023
From:	Daniel Bacon NRC/RGN-II/DRS/EB2
To:	Basta L Duke Energy Progress
References
IR 2023010
Download: ML23324A450 (9)

Text

SUBJECT:

H. B. ROBINSON STEAM ELECTRIC PLANT - FIRE PROTECTION TEAM INSPECTION REPORT 05000261/2023010

Dear Laura Basta:

On November 2, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at H. B. Robinson Steam Electric Plant and discussed the results of this inspection with George Curtis 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, Daniel M. Bacon, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 05000261 License No. DPR-23

Enclosure:

As stated

Inspection Report

Docket Number: 05000261

License Number: DPR-23

Report Number: 05000261/2023010

Licensee: Duke Energy Progress, LLC

Facility: H. B. Robinson Steam Electric Plant

Location: Hartsville, SC

Inspection Dates: October 16, 2023 to November 03, 2023

Inspectors: P. Braaten, Senior Reactor Inspector E. Coffman, Reactor Inspector D. Strickland, Reactor Inspector

Approved By: Daniel M. Bacon, Chief Engineering Branch 2 Division of Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a fire protection team inspection at H. B. Robinson Steam Electric 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

===71111.21N.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 (FHA) or safe shutdown analysis (SSA).

a. Review deficiencies or open fire protection impairments for the selected system, including any temporary modifications, operator workarounds, or compensatory measures.

b. Verify that operator actions can be accomplished as assumed in the licensees FHA, or as assumed in the licensees fire probabilistic risk assessment (FPRA)analysis and SSA.

c. Review repetitive or similar maintenance work requests which could be an indicator of a design deficiency and could affect the ability of the components to perform their functions, when needed.

d. Ensure that post maintenance and/or surveillance activities are performed as scheduled.

e. Perform a walkdown inspection to identify equipment alignment discrepancies.

Inspect for deficient conditions such as corrosion, missing fasteners, cracks, and degraded insulation.

f. Ensure the selected SSCs that are subject to aging management review (AMR)pursuant to 10 CFR Part 54 are being managed for aging (e.g., loss of material, cracking, reduction of heat transfer) in accordance with appropriate aging management programs. Verify that the licensees aging management program activities (such as, Fuel Oil Analysis or Selective Leaching Aging Management Program) associated with FP equipment are being implemented.

g. If a review of operating experience issues will be completed for the selected inspection sample, verify that the licensee adequately reviewed and dispositioned the operating experience in accordance with their processes.

• Chemical and Volume Control System

• Component Cooling Water System

• Cable Spreading Room Area Wide Incipient Fire Detection System

• Fire Area 3 Pre-action Sprinkler System

Fire Protection Program Administrative Controls (IP Section 03.02) (1 Sample)

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 FPP contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.

• Transient Combustible Control Program

Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)

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, FHA, and SSA were updated consistent with the FPP or design change.

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

• EC 419000 - Auxiliary Relay Panels Replacement

• EC 63452 - Modify MOV's to Align with Dedicated Shutdown Procedures

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On November 2, 2023, the inspectors presented the fire protection team inspection results to George Curtis and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21N.05 Calculations RNP-M/MECH-Appendix R Reactor Cooldown Evaluation 5

20

RNP-M/MECH-Component Cooling Water System 1

1661

RNP-M/MECH-Robinson Nuclear Plant Appendix R Mechanical Basis 12

1712

Corrective Action 111308 Time Transient Conditions for Appendix R 11/19/2003

Documents

Corrective Action 02491920 Update RNP-E-8.050 to Clarify Accessing CC-716A & B 10/25/2023

Documents NCR 2490754 2023 RNP, NRC FPTI - Cart Not Properly Restrained 10/17/2023

Resulting from

Inspection

Drawings B-190628 Control Wiring Diagram 12

B-190628 Control Wiring Diagram 17

B-190628 Sheet Control Wiring Diagram 11

218

B-190628 Sheet Control Wiring Diagram 17

231

B-190628 Sheet Control Wiring Diagram 20

2

G-190626 Sheet 4 Main and 4160 Volt One Line Diagram 24

SC-013 Component Cooling Water 6

SD-013 Component Cooling Water System (For Training Use 6

Only)

SD-021 Chemical and Volume Control System (For Training 9

Use)

Engineering AD-OP-ALL-0205 Time Critical Actions/Time Sensitive Actions 3

Evaluations OMM-043 Walk-Through Validation Checklist for DSP-002 10/12/2018

OMM-043 Walk-Through Validation Checklist for DSP-002 10/13/2018

RNP-E-8.050 Fire Safe Shutdown Transient Analysis and Timeline 4

Inspection Type Designation Description or Title Revision or

Procedure Date

Evaluation

RNP-E/ELEC-1216 The Fire Safety Shutdown Analysis for H.B. Robinson 5

Nuclear Plant

RNP-E/ELEC-1217 Non-Power Operations Analysis for H.B. Robinson 2

Nuclear Plant

Miscellaneous DBD/R87038/SD13 Component Cooling Water System 13

DBD/R87038/SD16 Sys DBD - Electrical Power Distribution System 13

DBD/R87038/SD21 Chemical & Volume Control System 8

DBD/R87038/SD62 Sys DBD - Cable and Raceway System 6

IP-JPM-133 Check CCW Flow to the RHR Pump Seal Cooler IAW 10/25/2023

DSP-008

JPM IP-145 Completed Performance of Actions of the Auxiliary 02/21/2019

Building Operator IAW DSP-002

Procedures AD-OP-RNP-0205 Completed Operator Time Critical Action for JPM IP-12802/17/2021

DSP-001 Alternate Shutdown Diagnostic 19

DSP-002 Shutdown With a Fire in The Control Room/ Hagan 60

Room

DSP-018 Shutdown From The Control Room With a Fire in The 2

Auxiliary Building Lower Hallway

DSP-020 Shutdown From The Control Room With a Fire in The 1

Emergency Switchgear Room

FP-012 Fire Protection Systems Minimum Equipment and 36

Compensatory Actions

OST-020 Shiftly Surveillances 10/24/2023

OST-114-2 Completed Pump 'B' Operability Testing During Cold 08/19/2015

Shutdown

OST-407-2 Completed Surveillance For Verification of Component 12/14/2022

Response to Blackout Sequence Train B

OST-639 Completed September Fire Equipment Monthly 09/14/2023

Inventory

OST-639 October Fire Equipment Monthly Inventory 10/31/2023

OST-942 Completed Surveillance for CCW to Safety Related 09/19/2023

Equipment Valve Position Verification

7