IR 05000352/2020010
| ML20073H282 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/11/2020 |
| From: | Glenn Dentel Engineering Region 1 Branch 2 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Dentel G | |
| References | |
| IR 2020010 | |
| Download: ML20073H282 (9) | |
Text
March 11, 2020
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - TITLE 10 OF THE CODE OF FEDERAL REGULATIONS 50.69 RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS, AND COMPONENTS INSPECTION REPORT 05000352/2020010 AND 05000353/2020010
Dear Mr. Hanson:
On February 27, 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,
/RA/
Glenn T. Dentel, Chief Engineering Branch 2 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:
05000352/2020010 and 05000353/2020010
Enterprise Identifier: I-2020-010-0008
Licensee:
Exelon Generation Company, LLC
Facility:
Limerick Generating Station, Units 1 and 2
Location:
Sanatoga, PA 19464
Inspection Dates:
February 10, 2020 to February 27, 2020
Inspectors:
E. DiPaolo, Senior Reactor Inspector (Team Lead)
F. Arner, Senior Reactor Analyst
S. Haney, Resident Inspector
A. Patel, Senior Reactor Inspector
Approved By:
Glenn T. Dentel, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Title 10 of the Code of Federal Regulations (10 CFR) 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components 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 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.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===37060 - 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components Inspection
10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components Inspection===
- (1) The inspectors reviewed the licensees program and procedures associated with 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, license amendment described in the plant safety evaluation and Updated Final Safety Analysis Report, and documented in the staffs Safety Evaluation Report (ADAMS Accession No. ML18165A162). The inspectors reviewed the licensees 10 CFR 50.69 categorization process and alternate treatment requirements completed on the following systems:
- Emergency Service Water
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 27, 2020, the inspectors presented the 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components 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
37060
Calculations
1-09-059
Pipe Stress Analysis
Corrective Action
Documents
3984984
4159984
214649
214654
24273
231629
232738
244378
244380
244440
250921
255997
256574
259201
267276
268323
271437
276932
287925
288001
288385
298778
299068
4312075
Corrective Action
Documents
Resulting from
Inspection
4172733-40, 41
4317285
4319388
21736
21932
Engineering
Changes
Engineering
Change 629220
A Spray Pond Spray Network Piping Replacement Flange
Addition and Strut Modification
PMC-18-114354
Change Drywell HVAC Fan Motor Rebuild Frequency (EQ)
and Condition Based (Non EQ)
2/27/2019
PMC-18-115736
Standby Liquid Control Pump Relief Valve Frequency
Extension
09/10/2019
PMC-19-116197
Alternative Treatment Maintenance Strategy for Core Spray
RISC-3 Check Valve Inspection Preventive Maintenance
2/03/2019
PMC-19-116869
RISC-3 Electric O-ring EEQ for System 57
10/09/2019
PMC-19-117859
RISC-3 System 052 (Core Spray) Motor Operated Valves
Alternate Treatment
01/03/2020
PMC-19-117911
Alternative Treatment for Core Spray RISC-3 Components
09/06/2019
PMC-19-119782
Alternate Treatment for System 20 Diesel Generator, Diesel
Generator Fuel Oil Storage Transfer, and Diesel Generator
Heating, Ventilation and Air Conditioning RISC-3
Components
10/07/2019
Engineering
Evaluations
LG-5060-012-003
CFR 50.59 System Categorization Document-Residual
Heat Removal Service Water System
LG-5069-011-003
CFR 50.69 System Categorization Document-Emergency
Service Water System
LG-5069-020-
081-092-003
CFR 50.69 System Categorization Document-Diesel
Generator
LG-5069-051-003
CFR 50.69 System Categorization Document-Residual
Heat Removal System
LG-5069-052-19-
IM-01
CFR 50.69 Immediate Review of the Core Spray System
2/05/2019
LG-5069-055-
056-003
CFR 50.69 System Categorization Document-HPCI
System
LG-MISC-035
NRC 10 CFR 50.69 Inspection Support for Limerick
Generating Station
N-00E-117-00010
CFR 50.69 Success Path Components Lists for Limerick
Generating Station Units 1 and 2
Miscellaneous
Exelon letter to
- U.S. NRC, Limerick Generating Station, Units
and 2, Application to Adopt 10 CFR 50.69, Risk-Informed
Categorization and Treatment of Structures, Systems, and
Components for Nuclear Power Plants
06/28/2017
Exelon letter to
- U.S. NRC, Limerick Generating Station, Units
08/14/2017
and 2, Supplement to Application to Adopt 10 CFR 50.69,
Risk-Informed Categorization and Treatment of Structures,
Systems, and Components for Nuclear Power Plants
Exelon letter to
- U.S. NRC, Limerick Generating Station, Units
and 2, Response to Request for Additional Information,
Application to Adopt 10 CFR 50.69, Risk-Informed
Categorization and Treatment of Structures, Systems, and
Components for Nuclear Power Plants
01/19/2018
Exelon letter to
- U.S. NRC, Limerick Generating Station, Units
and 2, Response to Request for Additional Information,
Application to Adopt 10 CFR 50.69, Risk-Informed
Categorization and Treatment of Structures, Systems, and
Components for Nuclear Power Plants
04/23/2018
Exelon letter to
- U.S. NRC, Limerick Generating Station, Units
and 2, Supplement to Application to Adopt 10 CFR 50.69,
Risk-Informed Categorization and Treatment of Structures,
Systems, and Components for Nuclear Power Plants
07/27/2018
U.S. NRC Issuance of Amendments Nos. 230 and 193 to
Adopt Title 10 of the Code of Federal Regulations Section
50.69, Risk-Informed Categorization and Treatment of
Structures, Systems and Components for Nuclear Power
Reactor
07/31/2018
Entergy Response to Request to NRC Request for Additional
Information Regarding Alternative ANO2-R&R-004 Revision
08/06/2007
LG-5060-055-
056-19-04
Integrated Decision Making Panel Meeting Minutes for
06/25/2019
LG-5069-078-
090-19-012
50.69 Integrated Decision-Making Panel Meeting Minutes for
05/04/2019
LG-5069-078-
090-19-012,
50.69 Integrated Decision Making Panel Meeting Minutes for
05/04/2019
An Approach for Determining the Technical Adequacy of
Probabilistic Risk Assessment Results for Risk-Informed
Activities
Shift Order 19-
001
License Amendment Implementing 10 CFR 50.69
Miscellaneous
Shift Order-19-
050
CFR 50.69 Supplement-Issue Report Screening
Procedures
CFR 50.69 Program
CFR 50.69 Active Component Risk Significance Insights
CFR 50.69 Passive Component Categorization
CFR 50.69 Risk Informed Categorization for Structures,
Systems, and Components
ER-AA-569-1003-
F-01
CFR 50.69 System Categorization Document
CFR 50.69 Alternative Treatment Implementation Process
Integrated Decision-Making Panel for Risk Informed SSC
Categorization Duties and Responsibilities
Requirements for Immediate, Interim, and Periodic
Performance Monitoring Reviews
Job Familiarization of 50.69 Project Team and Site Personnel
Exelon Reportabilty Reference Manual
T-300
FLEX Pump Setup at Spray Pond
Self-Assessments
Limerick February 2020 50.69 NRC Inspection Self-
Assessment
11/18/2019
NOSA-LM-19-05
Engineering Design Control Audit Report
08/07/2019
Report 032362-
RPT-10
PRA Focused-Scope Peer Review and Finding Level Fact
and Observation Independent Assessment
0