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 Mr. Bryan Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 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: NPF-39 and NPF-85 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 Enclosure
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 Type Designation Description or Title Revision or
Procedure Date
37060 Calculations 1-09-059 Pipe Stress Analysis 12
Corrective Action 3984984
Documents 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 4172733-40, 41
Documents 4317285
Resulting from 4319388
Inspection 4321736
21932
Engineering Engineering A Spray Pond Spray Network Piping Replacement Flange 2
Changes Change 629220 Addition and Strut Modification
PMC-18-114354 Change Drywell HVAC Fan Motor Rebuild Frequency (EQ) 02/27/2019
and Condition Based (Non EQ)
PMC-18-115736 Standby Liquid Control Pump Relief Valve Frequency 09/10/2019
Extension
PMC-19-116197 Alternative Treatment Maintenance Strategy for Core Spray 12/03/2019
RISC-3 Check Valve Inspection Preventive Maintenance
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 01/03/2020
Alternate Treatment
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 10/07/2019
Generator Fuel Oil Storage Transfer, and Diesel Generator
Heating, Ventilation and Air Conditioning RISC-3
Components
Engineering LG-5060-012-003 10 CFR 50.59 System Categorization Document-Residual 1
Evaluations Heat Removal Service Water System
LG-5069-011-003 10 CFR 50.69 System Categorization Document-Emergency 1
Service Water System
LG-5069-020- 10 CFR 50.69 System Categorization Document-Diesel 1
081-092-003 Generator
LG-5069-051-003 10 CFR 50.69 System Categorization Document-Residual 1
Heat Removal System
LG-5069-052-19- 10 CFR 50.69 Immediate Review of the Core Spray System 02/05/2019
IM-01
LG-5069-055- 10 CFR 50.69 System Categorization Document-HPCI 1
056-003 System
LG-MISC-035 NRC 10 CFR 50.69 Inspection Support for Limerick 0
Generating Station
N-00E-117-00010 10 CFR 50.69 Success Path Components Lists for Limerick 0
Generating Station Units 1 and 2
Miscellaneous Exelon letter to
- U.S. NRC, Limerick Generating Station, Units 06/28/2017
and 2, 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 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 01/19/2018
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
Exelon letter to
- U.S. NRC, Limerick Generating Station, Units 04/23/2018
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
Exelon letter to
- U.S. NRC, Limerick Generating Station, Units 07/27/2018
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
U.S. NRC Issuance of Amendments Nos. 230 and 193 to 07/31/2018
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
Entergy Response to Request to NRC Request for Additional 08/06/2007
Information Regarding Alternative ANO2-R&R-004 Revision
LG-5060-055- Integrated Decision Making Panel Meeting Minutes for
056-19-04 06/25/2019
LG-5069-078- 50.69 Integrated Decision-Making Panel Meeting Minutes for
090-19-012 05/04/2019
LG-5069-078- 50.69 Integrated Decision Making Panel Meeting Minutes for
090-19-012, 05/04/2019
Regulatory Guide An Approach for Determining the Technical Adequacy of 2
1.200 Probabilistic Risk Assessment Results for Risk-Informed
Activities
Shift Order 19- License Amendment Implementing 10 CFR 50.69
001
Miscellaneous Shift Order-19- 10 CFR 50.69 Supplement-Issue Report Screening
050
Procedures ER-AA-569 10 CFR 50.69 Program 3
ER-AA-569-1001 10 CFR 50.69 Active Component Risk Significance Insights 3
ER-AA-569-1002 10 CFR 50.69 Passive Component Categorization 2
ER-AA-569-1003 10 CFR 50.69 Risk Informed Categorization for Structures, 5
Systems, and Components
ER-AA-569-1003- 10 CFR 50.69 System Categorization Document 5
F-01
ER-AA-569-1004 10 CFR 50.69 Alternative Treatment Implementation Process 3
ER-AA-569-1005 Integrated Decision-Making Panel for Risk Informed SSC 5
Categorization Duties and Responsibilities
ER-AA-569-1006 Requirements for Immediate, Interim, and Periodic 2
Performance Monitoring Reviews
ER-AA-569-1007 Job Familiarization of 50.69 Project Team and Site Personnel 4
LS-AA-1110 Exelon Reportabilty Reference Manual 29
T-300 FLEX Pump Setup at Spray Pond 3
Self-Assessments IR 4276932 Limerick February 2020 50.69 NRC Inspection Self- 11/18/2019
Assessment
NOSA-LM-19-05 Engineering Design Control Audit Report 08/07/2019
Report 032362- PRA Focused-Scope Peer Review and Finding Level Fact 0
RPT-10 and Observation Independent Assessment
7