IR 05000261/2023010
| ML23324A450 | |
| Person / Time | |
|---|---|
| Site: | Robinson  (DPR-023) |
| 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:
Report Number:
Enterprise Identifier:
I-2023-010-0054
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
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
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
Procedure
Type
Designation
Description or Title
Revision or
Date
RNP-M/MECH-
20
Appendix R Reactor Cooldown Evaluation
RNP-M/MECH-
1661
Component Cooling Water System
Calculations
RNP-M/MECH-
1712
Robinson Nuclear Plant Appendix R Mechanical Basis
Corrective Action
Documents
111308
Time Transient Conditions for Appendix R
11/19/2003
2491920
Update RNP-E-8.050 to Clarify Accessing CC-716A & B
10/25/2023
Corrective Action
Documents
Resulting from
Inspection
NCR 2490754
23 RNP, NRC FPTI - Cart Not Properly Restrained
10/17/2023
B-190628
Control Wiring Diagram
B-190628
Control Wiring Diagram
B-190628 Sheet
218
Control Wiring Diagram
B-190628 Sheet
231
Control Wiring Diagram
B-190628 Sheet
2
Control Wiring Diagram
G-190626 Sheet 4
Main and 4160 Volt One Line Diagram
SC-013
Component Cooling Water
SD-013
Component Cooling Water System (For Training Use
Only)
Drawings
SD-021
Chemical and Volume Control System (For Training
Use)
AD-OP-ALL-0205
Time Critical Actions/Time Sensitive Actions
OMM-043
Walk-Through Validation Checklist for DSP-002
10/12/2018
OMM-043
Walk-Through Validation Checklist for DSP-002
10/13/2018
71111.21N.05
Engineering
Evaluations
RNP-E-8.050
Fire Safe Shutdown Transient Analysis and Timeline
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Evaluation
RNP-E/ELEC-1216
The Fire Safety Shutdown Analysis for H.B. Robinson
Nuclear Plant
RNP-E/ELEC-1217
Non-Power Operations Analysis for H.B. Robinson
Nuclear Plant
DBD/R87038/SD13
Component Cooling Water System
DBD/R87038/SD16
Sys DBD - Electrical Power Distribution System
DBD/R87038/SD21
Chemical & Volume Control System
DBD/R87038/SD62
Sys DBD - Cable and Raceway System
IP-JPM-133
Check CCW Flow to the RHR Pump Seal Cooler IAW
DSP-008
10/25/2023
Miscellaneous
Completed Performance of Actions of the Auxiliary
Building Operator IAW DSP-002
2/21/2019
AD-OP-RNP-0205
Completed Operator Time Critical Action for JPM IP-128
2/17/2021
DSP-001
Alternate Shutdown Diagnostic
DSP-002
Shutdown With a Fire in The Control Room/ Hagan
Room
DSP-018
Shutdown From The Control Room With a Fire in The
Auxiliary Building Lower Hallway
DSP-020
Shutdown From The Control Room With a Fire in The
Emergency Switchgear Room
Fire Protection Systems Minimum Equipment and
Compensatory Actions
OST-020
Shiftly Surveillances
10/24/2023
OST-114-2
Completed Pump 'B' Operability Testing During Cold
Shutdown
08/19/2015
OST-407-2
Completed Surveillance For Verification of Component
Response to Blackout Sequence Train B
2/14/2022
OST-639
Completed September Fire Equipment Monthly
Inventory
09/14/2023
OST-639
October Fire Equipment Monthly Inventory
10/31/2023
Procedures
OST-942
Completed Surveillance for CCW to Safety Related
Equipment Valve Position Verification
09/19/2023
7