IR 05000352/2020014
| ML20294A395 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/20/2020 |
| From: | Mel Gray Engineering Region 1 Branch 1 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Gray M | |
| References | |
| IR 2020014 | |
| Download: ML20294A395 (7) | |
Text
October 20, 2020
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000352/2020014 AND 05000353/2020014
Dear Mr. Hanson:
On October 1, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Limerick Generating Station, Units 1 and 2 and discussed the results of this inspection with Mr. Frank Sturniolo, Site Vice President, 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 Reactor Safety
Docket Nos. 05000352 and 05000353 License Nos. NPF-39 and NPF-85
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000352 and 05000353
License Numbers:
Report Numbers:
05000352/2020014 and 05000353/2020014
Enterprise Identifier: I-2020-014-0000
Licensee:
Exelon Generation Company, LLC
Facility:
Limerick Generating Station, Units 1 and 2
Location:
Sanatoga, PA 19464
Inspection Dates:
September 14, 2020 to October 1, 2020
Inspectors:
A. Patel, Senior Reactor Inspector (Team Leader)
J. Brand, Reactor Inspector
L. Dumont, Reactor Inspector
Approved By:
Mel Gray, Chief
Engineering Branch 1
Division of 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 Limerick Generating Station, Units 1 and 2, 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 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. The inspections documented below met the objectives and requirements for completion of the IP.
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 power-operated valves (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. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) HV-012-032A, Residual Heat Removal (RHR) Service Water Spray Nozzle Inlet Valve
- (2) HV-051-2F014A, 2A RHR Heat Exchanger Shutoff Valve
- (3) HV-051-1F068B, 1B RHR Heat Exchanger Service Water Outlet Valve
- (4) HV-055-1F003, High Pressure Coolant Injection (HPCI) Main Steam Supply Outboard Primary Containment Isolation Valve
- (5) HV-050-2F045, Reactor Core Isolation Cooling (RCIC) Steam Supply Valve
- (6) HV-055-2F004, HPCI Pump Suction from Condensate Storage Tank Valve
- (7) HV-C-051-2F048A, 2A RHR Heat Exchanger Bypass Valve
- (8) HV-011-123, Service Water Emergency Service Water (ESW) LOOP A Return Valve
- (10) FV-050-113, RCIC Governor 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 October 1, 2020, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. Frank Sturniolo, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
8031-P-104
Limerick Generating Station Units 1 & 2, MOV Design
Specification
LE-0104, DC
MCC Manual
Control Circuit
Calculation
Corrective Action
Documents
Resulting from
Inspection
4369321
4369678
4370053
4370057
4370083
4370088
4370090
4370099
Miscellaneous
55-VCS-1
Limerick Generating Station, Units 1&2, IST Program
Bases Document
Procedures
MOV Rising Stem Motor Operated Valve Thrust and
Torque Sizing and Set-Up Window Determination
Methodology
MOV Margin Analysis and Periodic Verification Test
Intervals
MOV Limitorque Actuator Capability Determination
Methodology
MA-AA-723-300-
1005
Review and Evaluation of Motor Operated Valve Test Data 3
Periodic Inspection of Limitorque Model SMB/SB/SBD-000
Through 5 Motor Operated Valves
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