IR 05000277/2021010
| ML21200A176 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/20/2021 |
| From: | Glenn Dentel Division of Operating Reactors |
| To: | Rhoades D Exelon Generation Co LLC, Exelon Nuclear |
| Dentel G | |
| References | |
| IR 2021010 | |
| Download: ML21200A176 (8) | |
Text
July 20, 2021
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000277/2021010 AND 05000278/2021010
Dear Mr. Rhoades:
On June 24, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Peach Bottom Atomic Power Station, Units 2 and 3 and discussed the results of this inspection with Mr. David Henry, 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 Nos. 05000277 and 05000278 License Nos. DPR-44 and DPR-56
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000277 and 05000278
License Numbers:
Report Numbers:
05000277/2021010 and 05000278/2021010
Enterprise Identifier: I-2021-010-0015
Licensee:
Exelon Generation Company, LLC
Facility:
Peach Bottom Atomic Power Station, Units 2 and 3
Location:
Delta, PA 17314
Inspection Dates:
June 7, 2021 to June 24, 2021
Inspectors:
C. Bickett, Senior Reactor Inspector
D. Kern, Senior Reactor Inspector
J. Lilliendahl, Senior Emergency Response Coord
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 triennial fire protection inspection at Peach Bottom Atomic Power Station, Units 2 and 3, 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.
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 (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site.
However, all the inspection activities were performed onsite. The inspections documented below met the objectives and requirements for completion of the IP.
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) Fire Protection Water Supply System
- (2) Automatic Suppression Systems
- (3) Residual Heat Removal (RHR) system
- (4) High Pressure Coolant Injection (HPCI) system
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 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 Combustible Material
- (2) Fire Protection System Impairment Control
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.
- (1) EC 627869 - Implement Fire Hose Removal Strategy
- (2) EC 623631 - Fire Safety Shutdown Improvements following 2017 Functional Areas Self-Assessment
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On June 24, 2021, the inspectors presented the triennial fire protection inspection results to Mr. David Henry, 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
2673479
04115309
04125405
04127608
04153095
230804
Corrective Action
Documents
Resulting from
Inspection
04418605
04428400
04428402
04428589
04428649
04428822
04430609
Drawings
M-1-S-65, Sht. 17 Unit 2 Residual Heat Removal System Electrical
Schematic
101
M-1-S-65, Sht. 20 Unit 2 Residual Heat Removal System Electrical
Schematic
101
Engineering
Changes
FSSD Program Improvements following FASA 2017
07/13/2018
86-10 Evaluation Supporting Removal of Fire Hose at
Interior Hose Stations at Peach Bottom Atomic Power
Station
Replacement of MO-2-10-089A/B/C/D for HPSW Pressure
Reduction
Implement Fire Hose Removal Strategy Need to Create
WO to Drive Planning
HPCI/RCIC Pump Low Suction Pressure Trip Elimination
Miscellaneous
NE-00296
Specification for Post-Fire Safe Shutdown Program
Requirements at Peach Bottom Atomic Power Station
PEA-05738
Failure Analysis of Fire Protection Piping IR 04133867
and 04190107
11/01/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PEA-57860
Evaluation of Fire Valve for Selective Leaching /Corrosion
- Fire Water System East Main Header South Division
Shutoff PIV-D-2
2/30/2014
PEA-71643
Selective Leaching Evaluation of One Fire Valve and One
Piping Tee
05/26/2017
Procedures
Fire Protection System Impairment Control
Control of Transient Combustible Material
OP-PB-102-106
Operator Response Time Program at Peach Bottom
Alternative Shut Down
23