IR 05000333/2021011
| ML21146A093 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/03/2021 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Rhoades D Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2021011 | |
| Download: ML21146A093 (7) | |
Text
June 3, 2021
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000333/2021011
Dear Mr. Rhoades:
On May 20, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at James A. FitzPatrick Nuclear Power Plant and discussed the results of this inspection with Mr. Timothy Peter, 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, X
/RA/
Signed by: Melvin K. Gray
Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket No. 05000333 License No. DPR-59
Enclosure:
As stated
Inspection Report
Docket Number:
05000333
License Number:
Report Number:
Enterprise Identifier: I-2021-011-0005
Licensee:
Exelon Nuclear
Facility:
James A. FitzPatrick Nuclear Power Plant
Location:
Oswego, NY
Inspection Dates:
May 03, 2021 to May 20, 2021
Inspectors:
A. Patel, Senior Reactor Inspector
L. Dumont, Reactor Inspector
J. Schoppy, Senior Reactor Inspector
Approved By:
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at James A. FitzPatrick Nuclear Power 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.
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), regional inspectors were directed to begin telework. Regional based inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. For the inspection documented below portions of the IP were completed remotely as well as on site and all the objectives and requirements for completion of the IP were met.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)
The inspectors:
a. Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.
b. Determined whether the sampled POVs are capable of performing their design-basis functions.
c. Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.
d. Evaluate maintenance activities including a walkdown of the sampled POVs (if accessible).
(1)10MOV-17, Residual Heat Removal Shutdown Cooling Outboard Isolation Valve (2)10MOV-34A, Residual Heat Removal 'A' Torus Cooling Valve Supply (3)10MOV-66B, Residual Heat Removal Heat Exchanger 'B' Bypass Valve (4)10MOV-89A, Residual Heat Removal Heat Exchanger 'A' Service Water Outlet Isolation Valve (5)12MOV-15, Reactor Water Cleanup Supply Inboard Isolation Valve (6)13MOV-21, Reactor Core Isolation Cooling Pump Discharge to Reactor Inboard Valve (7)23MOV-15, High Pressure Coolant Injection Steam Supply Inboard Isolation Valve (8)46MOV-101A, Emergency Service Water Loop 'A' Supply Header Isolation Valve (9)23AOV-42, High Pressure Coolant Injection Turbine Steam Supply Upstream Drain Isolation Valve (10)29AOV-80A, Main Steam Line 'A' Inboard Isolation Valve (11)11EV-14B, Standby Liquid Control 'B' Double Squib Activated Shear Explosive Valve
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 20, 2021, the inspectors presented the design basis assurance inspection (programs) results to Mr. Timothy Peter, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
9663-JAF-CALC-
0001
MOV Thermal Overload Sizing
Revision 2
JAF-CALC-
ELEC-02609
The 125VDC Station Battery 'A' Sizing & Voltage Drop
Revision 3
Corrective Action
Documents
Resulting from
Inspection
21060
21382
21465
21640
21742
21743
21748
21836
21932
21938
22026
22264
22842
24138
24144
24366
24369
24515
24614
Engineering
Evaluations
IST-2010-005
POV Stroke Time Acceptance Criteria IST Technical
Position Paper
Revision 6
MOV Program Risk Ranking Input
Revision 2
Procedures
Motor-Operated Valve Program Engineering Procedure
Revision 8
Air Operated Valve Program Implementing Procedure
Revision 6