IR 05000315/2022010
| ML22089A118 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/05/2022 |
| From: | Richard Skokowski Engineering Branch 3 |
| To: | Gebbie J Indiana Michigan Power Co |
| References | |
| IR 2022010 | |
| Download: ML22089A118 (8) | |
Text
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000315/2022010 AND 05000316/2022010
Dear Mr. Gebbie:
On March 14, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant 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.
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, Richard A. Skokowski, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 05000315 and 05000316 License Nos. DPR-58 and DPR-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000315 and 05000316
License Numbers:
Report Numbers:
05000315/2022010 and 05000316/2022010
Enterprise Identifier:
I-2022-010-0032
Licensee:
Indiana Michigan Power Company
Facility:
Donald C. Cook Nuclear Plant
Location:
Bridgman, MI
Inspection Dates:
January 10, 2022 to January 28, 2022
Inspectors:
B. Daley, Senior Reactor Inspector
K. Fay, Reactor Inspector (Observer)
A. Shaikh, Senior Reactor Inspector
Approved By:
Richard A. Skokowski, Chief
Engineering Branch 3
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 Donald C. Cook Nuclear 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).
- (1) Centrifugal Charging Pumps (2)2-QRV-251, Charging Flow Control Valve, 2-QMO-451 and 2-QMO-452, VCT Isolation Valves
- (3) East and West Diesel Driven Fire Pumps
- (4) Electric Motor Driven Fire Pump
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 Fire Protection Program contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.
- (1) NFPA 805 Monitoring Program (FPMP)
Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)
The inspectors reviewed the following changes to the plant's NFPA 805 program:
- (1) FPCE-2019-0031, Removal of Fire Hoses from the Power Block
- (2) FPCE-2020-0007, Lowering of the Refueling Water Storage Tank (RWST) Level Requirement
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On March 14, 2022, the inspectors presented the triennial fire protection inspection results to Joel P. Gebbie, Senior VP and Chief Nuclear Officer and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-E-N-PROT-
BKR-007
Unit 2 600V Switchgear Setting Breakers 21A6, 21C9,
21D9, 21D14
2-E-N-PROT-
RLY-001
4kV Electrical Protection Coordination Study
2-E-N-PROT-
TOL-MOV-001,
F
Cutler Hammer C300 TOL Relay Heater Trip Curves
Calculations
Report No.
R2527-001-001
Fire Protection Water Main Loop and Fire Pump Set Point
Adequacy Determination
Corrective Action
Documents
AR 2019-9101
Observation from 2019 Fire Protection Triennial
09/26/2019
AR 2020-0770
2-E-N-PROT-RLY-001 Coordination Wording
Enhancement
01/26/2022
Corrective Action
Documents
Resulting from
Inspection
AR 2022-0854
Fire Protection Triennial Potential Violation on EEE
01/31/2022
OP-2-12001
Main Auxiliary One-Line Diagram Bus "A" and "B"
Engineered Safety System (Train B)
OP-2-12002
Main Auxiliary One-Line Diagram Bus "C" and "D"
Engineered Safety System (Train A)
OP-2-12010
MCC Aux One-Line 600V Bus 21A, 21B Engineered
Safety System (Train B)
OP-2-12012
MCC Aux One-Line 600V Bus 21A, 21B Engineered
Safety System (Train B)
Drawings
OP-2-12031
MCC Aux One-Line 600V Bus 21C, 21D Engineered
Safety System (Train A)
2-E-N-DCP-
MOV-680A
Motor Operated Valves 2-QMO-451 & 452 Motors
Electrical Study
FPCE-2019-0031
Removal of Fire Hoses from the Power Block
01/28/2020
FPCE-2020-0007
Lowering of the RWST Level Requirement
07/08/2020
71111.21N.05
Engineering
Changes
ICP-01279
Add Thermal Overload Setpoint Information to the Plant
Setpoint Document (PSPD) for the GL 89-10 MOVs and
Other Equipment
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Jensen Hughes Review of DC Cook Fire Protection
Response to FPTI-08
01/28/2022
Fire Safety Analysis
10-0059
NFPA 805 Monitoring Program
Miscellaneous
R-1900-0024-001
Nuclear Safety Capability Assessment
2-IHP-4030-
066-002
Fire Pump Performance and Starting Sequence Tests
and 3
Procedures
FPMP
NFPA 805 Monitoring Program Analysis
West Diesel Fire Pump PP-145W Diesel Inspect, Replace
Parts as Needed
01/13/2020
Three Year Fire Protection Water System Unobstructed
Flow Test
11/06/2019
Three Year Fire Protection Water System Unobstructed
Flow Test
11/06/2019
Three Year Fire Protection Water System Unobstructed
Flow Test
11/06/2019
East Diesel Driven Fire Pump PP-145E, Re-install Diesel
Engine
07/21/2020
Work Orders
Replace Degraded Downstream Piping of Electric Fire
Pump 12-PP-144
10/11/2021