IR 05000461/2020010
| ML21071A077 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 03/11/2021 |
| From: | Richard Skokowski Division of Reactor Safety III |
| To: | Rhoades D Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2020010 | |
| Download: ML21071A077 (9) | |
Text
March 11, 2021
SUBJECT:
CLINTON POWER STATION - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000461/2020010
Dear Mr. Rhoades:
On February 11, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Clinton Power Station and discussed the results of this inspection with Mr. G. Olson, Maintenance Director 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,
/RA/
Richard A. Skokowski, Chief Engineering Branch 3 Division of Reactor Safety
Docket No. 05000461 License No. NPF-62
Enclosure:
As stated
Inspection Report
Docket Number:
05000461
License Number:
Report Number:
Enterprise Identifier: I-2020-010-0058
Licensee:
Exelon Generation Company, LLC
Facility:
Clinton Power Station
Location:
Clinton, IL
Inspection Dates:
September 21, 2020 to February 11, 2021
Inspectors:
K. Barclay, Reactor Inspector
J. Beavers, Senior Resident Inspector
A. Dahbur, Senior Reactor Inspector (Lead)
B. Daley, Senior Reactor Inspector
D. Sargis, Resident Inspector
D. Szwarc, Senior Reactor Analyst
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 Clinton Power 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, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the Coronavirus Disease (COVID-19), regional inspectors were directed to begin telework. During this time regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. In some cases, portions of an IP were completed remotely and on-site.
The inspection documented below was determined that the objectives and requirements stated in the IP could be completed remotely.
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 the following systems credited in the approved fire protection program could perform their licensing basis function:
- (1) Safe Shutdown Method 2 which credited Automatic Depressurization System (ADS),
Low Pressure Core Injection (LPCI) and Residual Heat Removal (RHR) "B" Pump for suppression pool cooling
- (2) Suppression System in Emergency Diesel Generator (EDG) Room (CO2)
- (3) Suppression System in Auxiliary Building (Sprinklers System)
Fire Protection Program Administrative Controls (IP Section 03.02) (1 Sample)
The inspectors verified that the following fire protection program administrative controls were implemented in accordance with the current licensing basis:
- (1) Control of Transient Combustible Material
Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)
The inspectors reviewed the following changes to ensure that they did not constitute an adverse effect on the ability to safely shutdown post-fire and to verify that fire protection program documents and procedures affected by the changes were updated.
- (1) Generic Letter 86-10 Evaluation for MSO Scenario 2-NEW-6 RCIC [Reactor Core Isolation Cooling], HPCS [High Pressure Core Spray] or RHR Operating with No Flowpath (EC-389773)
- (2) Generic Letter 86-10 Evaluation for Loss of Breaker Control (EC-383787)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On February 11, 2021, the inspectors presented the triennial fire protection inspection results to Mr. G. Olson, Maintenance Director and other members of the licensee staff.
- On October 9, 2020, the inspectors presented the Interim Exit Meeting inspection results to Mr. T. Chalmers, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.05 Calculations
19-AI-78
Evaluate Circuits Routed Through Various Fire Areas to
Determine If an Appendix R Fire in That Area Could
Cause Loss of Offsite Power
19-AI-81
CPS Appendix R Safe Shutdown Component Circuit
Analysis87-802
Hydraulic Calculations for Fire Protection Water Supply
System Fire Flow Testing
Corrective Action
Documents
04162045
EOID: 0FP01PA, Fire Pump A, Failed to Start for
Operability
08/06/2018
1668436
9071.04C002 Failed Acceptance Criteria
06/05/2014
4171931
Leak on A Fire Pump 1FP013
09/11/2018
4353266
Analyze Data Per 9071.02, Section 8.5 for 0FP01PB8.5
Analyzing Recorded Data 8.5.1
07/15/2020
Corrective Action
Documents
Resulting from
Inspection
Revise and Correct UFSAR Appendix E Cable Tray
Drawings
10/02/2020
Revise and Correct Drawing E28-1001-05A-EI
10/08/2020
Drawings
CE-CLT6-51.0
Sheet 001
One-Line Single Line Diagram
A
E02-1RH99
Residual Heat Removal Sys (RH) Shutdown Clg. Suction
Valves 1E12-F006A & 1E12-F006B
N
E02-1RH99
Residual Heat Removal Sys (RH) RHR B to Feedwater
Keep Fill Valve 1E12-F496
M
E02-1RH99
Schematic Diagram Residual Heat Removal System (RH)
Residual Heat Removal Pump 1B
H
E02-1RH99,
Sheet 503
RHR Suction Valve 1E12-F006B
N
E03-1RH00
Internal - External Wiring Diagram Residual Heat Removal
System (RH) Motor Operated Valves Limit Switches
S
E29-1001-01A-EI
Diesel Generator and HVAC Building Ground Floor Plan
El. 737'-0" Area 1
AH
E29-1001-04A-EI
Electrical Installation Diesel Generator and HVAC Building
Y
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Ground Floor Plan El. 737'-0" Area 4
M05-1075
Sheet 1
P&ID Residual Heat Removal (RH)
AZ
M05-1075
Sheet 2
P&ID Residual Heat Removal (RH)
M05-1075
Sheet 3
P&ID Residual Heat Removal (RH)
AI
M05-1075
Sheet 4
P&ID Residual Heat Removal (RH)
AG
Engineering
Changes
GL86-10 Evaluation in Support of Revision to CPS
1893.06, for Min Acceptable Voltage for the Fire
Protection Diesel Engine
MSO Scenario 7D - Loss of Breaker Control / Initiating
Loss of Bus Coordination and GL 86-10-2011-09001 Fire
Protection Evaluation / Qualitative Fire Modeling for Fire
Zone F-1A
MSO Scenario 2l - Spurious RHR Min Flow Closure with
Spurious Pump Start
MSO Scenario 2-new-6 - RCIC, HPCS, or RHR Operating
with No Flowpath Historical GL-86-10-2012-10-001
Engineering
Evaluations
EPU-T0611
Extended Power Uprate Task T0611 Appendix R Fire
Protection
Miscellaneous
SSD Cables Routing for a Component: 1E12-C002B RHR
Pump 1-B A-3A
10/06/2020
SSD Cables Routing for a Component: 1E12-C002C RHR
Pump 1-C A-3B
10/06/2020
XTP-FP/CO-14
Diesel Generator Carbon Dioxide Fire Protection System
Test
03/08/1986
Procedures
4401.01 EOP-1
RPV Control
CPS 1893.06
Fire Protection Maintenance and Testing Program
CPS 3312.01
47d
3312.01H001
LPCI Initiation and Shutdown Hard Card
CPS 3312.02
Alternate Shutdown Cooling (A-SDC) Methods
9e
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CPS 3312.03
RHR - Shutdown Cooling (SDC) & Fuel Pool Cooling and
Assist (FPC&A)
11f
4003.01C006
4003.01C007
RSP - DIV 1 Suppression Pool Cooling Operation
0a
4003.01C008
RSP - DIV 1 Shutdown Cooling Operation
1c
4003.01H001
MCR - "A" CRO Hard Card
4003.01H002
MCR - "B" CRO Hard Card
0a
4003.01H003
RSP - Hard Card 'A'
0c
CPS 4411.03
Injection/Flooding Sources
10d
CPS 4411.04
Throttling ECCS Flow
5d
Control of Transient Combustible Material
Work Orders
21410
9601.10A20 Visual Inspection Spray/Sprinkler System
(C00l)
08/21/2018
1858700
9071.09, FP CO2 System Auto Actuation (DIV I DG)
Detector Functional
03/19/2020
4987766
9071.19A20 OP Fire Protection Valve Lineup
(Safety-Related C00l)
07/03/2020