ML25128A115
| ML25128A115 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/08/2025 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| IR 2025001 | |
| Download: ML25128A115 (1) | |
Text
David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer (CNO)
Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION - INTEGRATED INSPECTION REPORT 05000373/2025001 AND 05000374/2025001
Dear David Rhoades:
On March 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at LaSalle County Station. On April 9, 2025, the NRC inspectors discussed the results of this inspection with John VanFleet, 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, Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety Docket Nos. 05000373 and 05000374 License Nos. NPF-11 and NPF-18
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV May 8, 2025 Signed by Ruiz, Robert on 05/08/25
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE RIII RIII NAME NShah:gmp RRuiz DATE 05/08/2025 05/08/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000373 and 05000374 License Numbers:
NPF-11 and NPF-18 Report Numbers:
05000373/2025001 and 05000374/2025001 Enterprise Identifier:
I-2025-001-0065 Licensee:
Constellation Nuclear Facility:
LaSalle County Station Location:
Marseilles, IL Inspection Dates:
January 01, 2025, to March 31, 2025 Inspectors:
J. Benjamin, Senior Resident Inspector M. Domke, Senior Reactor Inspector R. Farmer, Health Physicist T. Hooker, Health Physicist J. Kutlesa, Senior Emergency Preparedness Inspector T. McGowan, Emergency Preparedness Inspector J. Meszaros, Resident Inspector P. Smagacz, Acting Senior Resident Inspector R. Zuffa, Illinois Emergency Management Agency Approved By:
Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at LaSalle County Station, 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 Type Issue Number Title Report Section Status LER 05000373/2024-004-00 LER 2024-004-00 for LaSalle County Station, Unit 1, Emergency Diesel Generator Auto-Start and Load due to Loss of Station Auxiliary Transformer 71153 Closed
3 PLANT STATUS Unit 1 operated at rated thermal power for the entire inspection period.
Unit 2 began the inspection period at rated thermal power. On February 9, 2025, the unit coasted down to approximately 91 percent power and commenced refueling outage (RFO)
L2R20. On March 1, 2025, the unit started up and reached rated thermal power on March 4, 2025. The unit remained at rated thermal power for the remainder of the inspection period.
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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.
REACTOR SAFETY 71111.01 - Adverse Weather Protection Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending high winds and severe thunderstorms on March 14, 2025.
71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1) fuel pool cooling while protected for alternate decay heat removal during RFO L2R20 division 1 and 2 residual heat removal (RHR) maintenance on February 20, 2025 (2) train 'A' and 'B' RHR service water while protected for shutdown cooling during RFO L2R20 on February 11, 2025 (3)
Unit 1A train standby liquid control system with Unit 1B train standby liquid control system inoperable due to a failed check valve on March 12, 2025 (4)
Common 'B' train main control room ventilation system when 'A' train main control room ventilation train was out of service for planned maintenance on March 24, 2025
4 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (9 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)
Fire Zone (FZ) 312, reactor building, elevation 673'-4", Unit 2 high pressure core spray cubicle on January 8, 2025 (2)
FZ 314, reactor building, elevation 673'-4", Unit 2 low pressure core spray and reactor coolant isolation cooling system cubicle on January 8, 2025 (3)
FZ 2H2, reactor building, elevation 694'-6", Unit 1 high pressure core spray cubicle on January 8, 2025 (4)
FZ 211, reactor building, elevation 673'-4", Unit 1 general area on January 10, 2025 (5)
FZ 2F, reactor building, elevation 740'-0", Unit 1 general area and control rod drive repair room on January 10, 2025 (6)
FZ FA1 (North), elevation 843'-6", Unit 2 refuel floor on February 12, 2025 (7)
FZ 3D, reactor building, elevation 786'-0", Unit 2 general area on February 23, 2025 (8)
FZ 3E, reactor building, elevation 761'-0", Unit 2 general area on February 23, 2025 (9)
FZ 2H3, reactor building, elevation 694'-6", Unit 1 RHR heat exchanger 'B' cubicle on February 12, 2025 71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01) (1 Sample)
The inspector evaluated boiling water reactor non-destructive testing by reviewing the following examinations from February 10, 2025 to February 21, 2025:
(1) 1.
Volumetric, phased array nondestructive examination of American Society of Mechanical Engineers (ASME) R1.11-2 category B dissimilar metal Feedwater safe end to nozzle weld 1FW-2001-20A on containment drywell elevation 796' 2.
Volumetric, phased array nondestructive examination of ASME R1.11-2 category B dissimilar metal Feedwater safe end to nozzle weld 1FW-2002-20A on containment drywell elevation 796' 3.
Volumetic convential ultrasonic nondestructive examination of ASME R-A/R1.16-2 stainless steel weld IRH-2001-21A on containment drywell elevation 740' 4.
Visual VT-3 examination on seismic component MS04-2876X on containment drywell elevation 740' 5.
Visual VT-1 examination on lug component MS04-2876X (IWA) on containment drywell elevation 740' 6.
Pressure boundary ASME class 1 weld review for bottom head drain replacement work order number 05237886 task 19 specifically replacement welds 1R3, 4A, 17R1, 18R1
5 71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(1 Sample)
(1)
The inspectors observed and evaluated licensed operator performance in the control room during shutdown operations for RFO L2R20 on February 9, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated simulator-based training on January 22, 2025.
71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1) evaluation of the Unit 1B train emergency diesel generator fuel oil leak that occurred on October 21, 2024 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1) elevated risk during grid cold weather alert on January 7, 2025 (2)
Unit 1 risk evaluation due to emergent work associated with the standby liquid control system during the week ending March 15, 2025 (3) elevated risk during control room ventilation 'A' train work window week of March 24, 2025 (4) elevated risk during Unit Common 'B' train emergency diesel generator 24-hour run surveillance test on March 31, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1) operability of the reactor core isolation cooling system after mechanical backseating of the outboard steam isolation valve on January 17, 2025
6 (2) operability of Unit 2 division 2 RHR service water pumps given inservice test results falling in alert range and no increased testing frequency established, as documented in Action Request (AR) 4828295 (3)
AR 4831047, UMCRA-1H13-P601-A501, 1B DG Engine Trouble Alarm Received Unexpectedly (4) control rod operability after scram time testing on February 26, 2025, given scram times documented in ARs 4840680, 4840783, 4840671, 4840797, 4840717, 4840682, and 4840751 (5) operability of Unit 1A train standby liquid control due to observed chattering of 'B' check valve and reduced flow during surveillance as documented in AR 4844688 on March 12, 2025 71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(4 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1)
Engineering Change (EC) 640788, Diesel Fire Pump 'B' Engine Replacement, during the week ending February 8, 2025 (2)
EC 625078, Remove Bonnet Vent Valves on Unit 2 Reactor Recirculation Discharge Isolation Valves, during the week ending March 14, 2025 (3)
EC 631743, Shutdown Cooling Trip Bypass Keylock, during the weeks ending March 8 through March 15, 2025 (4)
EC 640577, Unit 2 - Adding a Time Delay to Load Reject Circuit, during the week ending March 15, 2025 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated Unit 2 RFO L2R20 from February 10 through March 1, 2025.
71111.24 - Testing and Maintenance of Equipment Important to Risk The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (10 Samples 1 Partial)
(1)
(Partial)
Unit Common 'B' diesel fire pump after upgrade during the week of February 3, 2025 (2)
Unit 2 division 1 125 Vdc battery testing after electrical maintenance during RFO L2R20 on February 18, 2025 (3) performance of LOS-MS-R7 after safety relief valve replacement during RFO L2R20 on February 20 and 21, 2025 (4) performance of reactor vessel leakage test per LOS-NB-R2 after RFO L2R20 on February 26, 2025
7 (5)
Unit 2 division 2 125 Vdc battery testing after electrical maintenance during RFO L2R20 on February 22, 2025 (6)
Unit 2B train residual heat removal pump run after RFO L2R20 work window on February 20, 2025 (7)
Unit 2C train residual heat removal pump run after RFO L2R20 work window on February 18, 2025 (8)
WO 5625872, "2E12-F050A Failed LLRT [local leak rate test]," on February 24, 2025 (9) verification of core loading after refueling on February 22, 2025 (10)
Unit 2A train residual heat removal pump discharge relief valve on February 23, 2025 (11)
Unit 1 standby liquid control 'A' and 'B' trains pump runs after emergent work on the
'B' check valve and system rotameter replacement on March 14, 2025 Surveillance Testing (IP Section 03.01) (3 Samples)
(1)
LOS-RP-SA3, Unit 2, reactor manual scram functional test, instrument channels A and B on February 9, 2025 (2)
LOS-DG-201, Unit common emergency diesel generator start and load acceptance surveillance, February 14, 2025 (3)
LOS-DG-R0, Unit common emergency diesel generator 24-hour surveillance test on March 31, 2025 Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
LOS-RH-Q1 Unit 2C train residual heat removal pump attachment 2 on January 6, 2025 Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1) primary containment vent and purge outlet valves on February 17, 2025 71114.02 - Alert and Notification System Testing Inspection Review (IP Section 02.01-02.04) (1 Sample)
(1)
The inspectors evaluated the following maintenance and testing of the alert and notification system:
annual siren inspection and maintenance records for the period of February 2023 - February 2025 71114.03 - Emergency Response Organization Staffing and Augmentation System Inspection Review (IP Section 02.01-02.02) (1 Sample)
(1)
The inspectors evaluated the readiness of the emergency preparedness organization.
71114.05 - Maintenance of Emergency Preparedness Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
(1)
The inspectors evaluated the maintenance of the emergency preparedness program.
8 RADIATION SAFETY 71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1) licensee surveys of potentially contaminated workers and material leaving the radiologically controlled area (RCA) at the north service building exit (2) licensee surveys of potentially contaminated workers and material leaving the RCA at the main RCA exit Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1) removal of insulation from valve 2G33-F393A (2) inner pipe preparation within a glove bag on 2A RT pump (3) ultrasonic testing of 2RA001A piping elbow (4) addition of shielding on pipes connected to valve 2G33-F393A High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
(1)
Unit 2 694 elevation shutdown cooling line raceway (2)
Unit 2 B/C residual heat removal suction pump room (3)
Unit 2 reactor water cleanup pump room Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
(1)
The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
9 71124.04 - Occupational Dose Assessment Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situations:
(1) use of finger rings for measurement of extremity dose for removal of insulation on valve 2G33-F393A OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) (2 Samples)
(1)
Unit 1 (January 1 through December 31, 2024)
(2)
Unit 2 (January 1 through December 31, 2024)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)
(2 Samples)
(1)
Unit 1 (January 1 through December 31, 2024)
(2)
Unit 2 (January 1 through December 31, 2024)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
(1)
Unit 1 (January 1 through December 31, 2024)
(2)
Unit 2 (January 1 through December 31, 2024)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
(1)
January 2023 through December 2024 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13)
(1 Sample)
(1)
January 2023 through December 2024 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14)
(1 Sample)
(1)
January 2025 through February 2025
10 71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
(1)
LER 05000373/2024-004-00, Emergency Diesel Generator Auto-Start and Load due to Loss of Station Auxiliary Transformer (Agencywide Documents Access and Management System [ADAMS] Accession No. ML24171A003). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct and therefore was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified. This LER is closed.
INSPECTION RESULTS No findings were identified.
EXIT MEETINGS AND DEBRIEFS The inspectors verified that no proprietary information was retained or documented in this report.
On April 9, 2025, the inspectors presented the integrated inspection results to John VanFleet, Site Vice President, and other members of the licensee staff.
On February 14, 2025, the inspectors presented the radiation protection inspection results to John VanFleet, Site Vice President, and other members of the licensee staff.
On February 21, 2025, the inspectors presented the inservice inspection results to John Van Fleet, Site Vice President, and other members of the licensee staff.
On February 28, 2025, the inspectors presented the emergency preparedness inspection results to Deb McBreen, Operations Director, and other members of the licensee staff.
THIRD PARTY REVIEWS Inspectors reviewed Institute on Nuclear Power Operations reports that were issued during the inspection period.
11 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date LAP-100-44 Inclement Weather Guidance 4
LOA-TORN-001 High Winds - Tornado 30 OP-AA-108-111-1001 Severe Weather and Natural Disaster Guidelines 30 71111.01 Procedures SY-AA-101-146 Severe Weather Preparation and Response 4
AR 4839094 NRC Question Related to FC ADHR WS Flow 02/20/2025 Corrective Action Documents Resulting from Inspection AR 4848380 NRC Follow up to Question Related to FC ADHR WS Flow 03/24/2025 M-134, Sheet 1 P & ID CSCS Equipment Cooling Water System BH M-134, Sheet 2 P & ID Core Standby Cooling System Equipment Cooling Water System AT M-144, Sheet 1 P & ID Fuel Pool Cooling Filter & Demineralizing System AS M-144, Sheet 2 P & ID Fuel Pool Cooling Filter & Demineralizing System Y
Drawings M-99 P & ID Standby Liquid Control System AD Engineering Changes EC 643002 L2R20 ADHR Evaluation 000 LOP-FC-03 Fuel Pool Cooling System Startup, Operation, Shutdown, Level Changes, and Flushing 62 LOP-RH-07 Shutdown Cooling System Startup, Shutdown, Operation and Transfer 88 LOP-SC-01M Standby Liquid Control System Mechanical Checklist 13 71111.04 Procedures LOP-VC-01 Control Room HVAC Operation 57 PFP RX BLDG 673-3, Fire Zone 211 Pre-Fire Plan Unit 1 General Area 3
PFP RX BLDG 673-3, Fire Zone 312 Pre-Fire Plan Unit 2 HPCS Cubicle 2
71111.05 Fire Plans PFP RX BLDG 673-3, Fire Zone 3E Pre-Fire Plan Unit 2 General Area and RWCU Pump Cubicles 2
12 Inspection Procedure Type Designation Description or Title Revision or Date PFP RX BLDG 673-4, Fire Zone 314 Pre-Fire Plan Unit 2 LPCS/RCIC Pump Room 2
PFP RX BLDG 694-6 Elevation, Fire Zone 2H3 Pre-Fire Plan Unit 1 RHR Heat Exchanger B Cubicle 2
PFP RX BLDG 694-6, Fire Zone 2H2 Pre-Fire Plan Unit 1 HPCS Cubicle 2
PFP RX BLDG 740-0, Fire Zone 2F Pre-Fire Plan Unit 1 General Area and CRD Repair Room 2
PFP RX BLDG 786-6, Fire Zone 3D Pre-Fire Plan Unit 2 Reactor Building General Area 2
PFP RX BLDG 843-6, Fire Zone FA1 Pre-Fire Plan Elevation U1 and U2 Refuel Floor Area 004 ER-AA-600-1069 High Risk Fire Area Identification 4
MA-AA-716-008-1008 Reactor Services Refuel Floor FME Plan 22 OP-AA-201-004 Fire Prevention for Hot Work 19 OP-AA-201-009 Control of Transient Combustible Material 30 Procedures OP-LA-201-012-001 LaSalle On-Line Fire Risk Management 6
AR 4557455 UT PA Exam Results for 2RR28B-3" Weld 1 02/26/2023 AR 4557459 L2R19 VT-3 IWF Class 1 Support Indication Reactor Water Cleanup 02/26/2023 AR 4557639 UT PA Exam Results for 2RH03CB-12" Weld 1 02/27/2023 AR 4557711 IR 04557459 Written with the Wrong Component Listed 02/27/2023 AR 4557817 UT PA Exam Results for 2RH03CB-12" Weld 2 02/27/2023 AR 4557912 UT PA Exam Results for 2RT01B-6" Weld 17 02/28/2023 AR 4558003 UTPA for 2RT01B-6" Weld 18 02/28/2023 71111.08G Corrective Action Documents AR 4558217 UT PA Exam Results for 2RR28B-3" Weld 1R 03/01/2023
13 Inspection Procedure Type Designation Description or Title Revision or Date AR 4558634 UT PA Exam Results for 2RR28B-3" Weld 1 Repair 2 03/02/2023 AR 4721674 Internal Corrosion in 2A RHR Pump Seal Cooler Outlet Pipe 12/05/2023 Engineering Changes EC 636268 Unit 2 Bottom Head Drain Reroute 03/16/2023 Engineering Evaluations DDR 2690 Deviation Disposition Request for minimum corrosion allowance for carbon steel forgings 11/04/2022 L2R20-MT-002 Magnetic Particle Examination 02/18/2025 L2R20-UT-008 1RH-2001-21A Ultrasonic Examination Report 02/20/2025 L2R20-VEN-001 1FW-2001-20A Safe End to Nozzle Examination Report 02/20/2025 L2R20-VEN-002 1FW-2002-20A Safe End to Nozzle Examination Report 02/18/2025 L2R20-VT-001 Visual Examination of Pipe Hanger, Support or Restraint (VT-3) 02/11/2025 L2R20-VT-002 Visual Examination of Pipe Hanger, Support or Restraint (VT-3) 02/11/2025 L2R20-VT-005 Visual Examination of Pipe Hanger, Support or Restraint (VT-3) 02/12/2025 L2R20-VT-006 Visual Examination of Welds (VT-1) 02/12/2025 L2R20-VT-022 Visual Examination of Pipe Hanger, Support or Restraint (VT-3) 02/18/2025 NDE Reports L2R20-VT-023 Visual Examination of Pipe Hanger, Support or Restraint (VT-3) 02/18/2025 ER-AA-335-014 VT-1 Visual Examination 12 ER-AA-335-016 VT-3 Visual Examination of Component Supports, Attachments and Interiors of Reactor Vessels 14 Procedures GEH-PDI-UT-1 PDI Generic Procedure for the Ultrasonic Examination of Ferritic Welds 12.1 Work Orders WO 5237886-19 Unit 2 Bottom Head Drain Reroute (EC636268) Task 19 03/03/2023 ReMA Plan
- L2C20-02 L2C20 Standing Shutdown ReMA 03/17/2023 71111.11Q Miscellaneous Sequence ID:
SAr9.1 L2C20 December 2024 Shutdown Sequence 12/18/2024
14 LGP-2-1 Normal Unit Shutdown 133 LGP-3-2 Reactor Scram 83 71111.11Q Procedures OP-LA-101-111-1002 LaSalle Operations Philosophy Handbook 96 Engineering Changes EC 642941 Ability of 1B Diesel Generator to Have Performed Required Function with Fuel Oil Leak 0
ER-AA-320 Maintenance Rule Implementation Per NEI 18-10 00 71111.12 Procedures ER-AA-320-1004 Maintenance Rule - (a)(1) and (a)(2) Requirements 03 AR 4844688 1B SBLC Pump Discharge Check Valve Chattering 03/12/2025 AR 4845280 1B SBLC Pump Run Indicated Low Flow 03/13/2025 Corrective Action Documents AR 4845342 Leak on 1B SBLC Plungers Packing 03/14/2025 ER-AA-600 Risk Management 7
OP-AA-107 Integrated Risk Management 8
71111.13 Procedures WC-AA-101-1006 On-Line Risk Management and Assessment 5
AR 4764916 Unit 2 Div 2 RHRWS Pumps in Alert Range 04/10/2024 AR 4828295 Unknown Cause in Change in the IST Dp for 2C & 2D RHRWS pps 01/08/2025 AR 4840671 CRD 18-35 Scram Time Exceeded 90% TS limit 02/26/2025 AR 4840680 L2R20 LL - CRD 22-31 Scram Time Exceeded TS Limit 02/26/2025 AR 4840682 CRD 26 Scram Time Within 90% of TS Limits 02/26/2025 AR 4840717 CRD 50-19 Scram Time Exceeded 90% TS Limit 02/26/2025 AR 4840751 CRD 58-27 Scram Time Exceeded 90% TS Limit 02/26/2025 AR 4840783 CRD 38-43 Scram Time Within 90% of TS Limits 02/26/2025 AR 4840797 CRD 30-55 Scram Time Exceeded 90% TS Limit 02/26/2025 Corrective Action Documents AR 4844688 1B SBLC Pump Discharge Check Valve Chattering 03/12/2025 71111.15 Engineering Changes EC EVAL 643386 Backseating Evaluation for Valve 1E51-F008 1
Procedures OP-AA-103-105 Limitorque Motor-Operated and Chainwheel Operated Valve Operations 7
WO 4758055 EM Perform EQ Inspection and Votes Test 1E51-F008 02/27/2024 WO 5214768 2B RHR WS Biennial Comprehensive IST Pump Test 04/10/2024 71111.15 Work Orders WO 5355489 Scram Time Rods per LOS-RD_SR12 & Flush Rods at 00 or 48 02/28/2025
15 WO 5527728 IM -EWP-LIS-RH-207 U2 RHR B Service Water Flow Ind Cal 04/12/2024 71111.15 Work Orders WO 5527960 2B RHR WS Biennial Comprehensive IST Pump Test 05/14/2024 EC 625078 Remove Bonnet Vent Valves on Unit 2 RR Discharge Isolation Valves (2B33-F067A/F067B) 04/23/2019 EC 631743 Shutdown Cooling Trip Bypass Keylock Switches 1
EC 640577 Unit 2 - Adding a Time Delay to Load Reject Circuit 1
Engineering Changes EC 640788 DFP 'B' Engine Replacement 0
71111.18 Work Orders WO 4816800 Remove Bonnet Vent Valves on 2B33-F067A 02/21/2023 AR 4840816 Drywell Closeout Upper Elevation Walkdown with NRC 02/26/2025 WO 4839094 NRC Question Related to FC ADHR WS Flow 02/20/2025 Corrective Action Documents WO 4842502 Drywell Closeout 740 Elevation Walkdown with NRC 02/27/2025 L2C20-02 Shutdown Reactivity Maneuver Plan 03/17/2023 71111.20 Miscellaneous PORC 25-02 L2R20 Shutdown Safety Plan 0
AR 4844688 1B SBLC Pump Discharge Check Valve Chattering 03/12/2025 AR 4845280 1B SBLC Pump Run Indicated Low Flow 03/14/2025 Corrective Action Documents AR 4845342 Leak on 1B SBLC Plungers Packing 03/14/2025 Drawings M-92 P&ID Primary Containment Vent & Purge AU LOS-DG-201 0 Diesel Generator, 0DG01K, Start and Load Acceptance Surveillance 21 LOS-DG-R0 0 Diesel Generator 0DG01K Twenty-Four Hour Run Surveillance 39 Procedures LTS-900-6 RHR Shutdown Cooling Return Pressure Isolation Valve Water Leak Test 1(2)E12-F050A/B, 1(2)E12-F053A/B, and 1(2)E12-F099A/B 26 WO 5344917 OP LOP-NB-R2 Reactor Vessel Leakage Test 02/27/2025 WO 5344917 Reactor Vessel Leakage Test 02/27/2025 WO 5344926 U2 Core Verification (BOC Startup) 02/23/2025 WO 5344968 2C RHR PMTs 02/18/2025 WO 5344969 2B RHR PMTs 02/24/2025 WO 5344994 Unit 2 Div 1 DC Restoration PMT JBR 02/18/2025 WO 5355489 Scram Time Rods per LOS-RD-SR12 & Flush Rods at 00 or 48 02/28/2025 WO 5393175 LLRT 2VQ034, 35, 36, 38 02/17/2025 71111.24 Work Orders WO 5393180 PC VQ Valves LLRT 2VQ029/30/42 02/17/2025
16 WO 5393242 OP LOS-MS-R7 U2 Main Steam Safety Relief Valve Operability Test 02/24/2025 WO 5529697 OP LOS-RP-SA3 U2 Rx Manual Scram Func Att 2A 02/09/2025 WO 5530430 OP LOS-RP-SA3 U2 Rx Manual Scram Func Att 2B 02/09/2025 WO 5554037 Unit 2 Div 2 DC Restoration PMT JBR 02/22/2025 WO 5557889 LOS-RD-SR4 Rod Movement Log 02/25/2025 WO 5566272 2E12-F025A Perform 'As Found' LLRT LTS-100-15 02/23/2025 WO 5601138 OP LOS-SC-Q1 1A SBLC Pump Quarterly Att 1A 03/14/2025 WO 5602167 OP LOS-SC-Q1 1B SBLC Pump Quarterly Att 1B 03/14/2025 WO 5625872 2E12-F050A Failed LLRT 02/24/2025 Corrective Action Documents Resulting from Inspection AR 4841181 NRC ID: E-Plan IPAWS Testing Records not Available 02/25/2025 Miscellaneous N/A PNS System Maintenance Reports January 2023 through December 2024 71114.02 Procedures EP-MW-121-1006 Contracted Siren Maintenance Oversight 001 Miscellaneous N/A 20 ERO Personnel Qualifications Various EP-AA-1000 Exelon Nuclear Standardized Radiological Emergency Plan 33 71114.03 Procedures TQ-AA-113 ERO Training and Qualification 39 EP-AA-120-F-06 Evacuation Time Estimate Review Checklist 05/05/2024 KLD TR - 1408 LaSalle County Generating Station 2024 Population Update Analysis 06/13/2024 N/A 2024 Letters of Agreement: Seneca Fire Dept.; LaSalle County Sheriff; Marseilles Area Ambulance Service; Marseilles Fire Protection District; Seneca Ambulance Service; Morris Hospital Various 71114.05 Miscellaneous N/A EP Inventories 2023 & 2024 Various LA-02-25-00518 L2R20 DW ISI, FAC, LROT Inspection Activities 01/31/2025 LA-02-25-00901 L2R20 RFF Reactor Disassembly and Reassembly Activities 01/29/2025 ALARA Plans LA-2-25-00304 2A RT Pump Project 01/27/2025 AR 4761497 Gas Leak in the Unit 1 Hydrogen Analyzer Room 03/27/2024 71124.01 Corrective Action Documents AR 4797099 Radwaste Impacts Due to CCW (2TBCCW) Sent to Floor Drains 08/27/2024
17 AR 4810702 RP Knowledge and Skills, Self-Assessment Findings 10/20/2024 AR 4811146 Dose Outside Performance Criteria for August SAC 10/22/2024 AR 4816117 NOS ID: Rad Boundaries/Signage did not Follow Procedure 11/08/2024 AR 4816122 NOS ID: Radiological Surveys Were Missing Required Data 11/08/2024 AR 4816155 NOS ID: Alpha Eval Incorrectly Tracked 11/08/2024 AR 4816170 Unit 1 Hydrogen Analyzer Room High Radioactive Gas Content 11/08/2024 AR 4823593 Unit 1 OG Pretreat Room Radioactive Leak 12/13/2024 AR 4824042 Technician "Gassed Up" After U1 Pre Treat Sampling 12/16/2024 AR 4824995 Rad Risk Assess. Approvals Not Documented for High-Risk Job 12/19/2024 RP-AA-401-1002 Radiological Risk Management 17 RP-AA-403 Administration of the Radiation Work Permit Program 15 Procedures RP-AA-503-F-01 Unconditional Release Instructions Using the Tool and Equipment Monitor (TEM) for Personal Items Used in the Radiologically Controlled Area (RCA) and in a Contaminated Area 7
2025-233152 4-valve Room Prior to 2G33-F393A Insulation Removal 02/05/2025 Radiation Surveys 2025-233666 RT Pump Room Prior to Piping End Prep 02/12/2025 L-02-25-0642 L2R20 RB High Risk Valves-2G33-F393-394 Cut Out and Replacement 1
LA-02-25-00518 L2R20 DW ISI, FAC, LROT Inspection Activities 00 LA-02-25-00901 L2R20 RFF Reactor Disassembly and Reassembly Activities 00 LA-2-25-00304 RWCU System Maintenance 00 Radiation Work Permits (RWPs)
LA-2-25-00304 L2R20 RB RXB High Risk Valves-2G33-F393A 1
04716436 2024 In Field Work Controls 10/10/2024 04716437 2024 - Radworker Performance 10/28/2024 Self-Assessments 04716440-08-02 2024 Rad Pro Knowledge and Skills 10/31/2024 71124.04 Procedures RP-AA-210 Dosimetry Issue, Usage, and Control 34 71151 Miscellaneous LS-AA-2110 Monthly Data Elements for NRC ROP Indicator - Emergency Response Organization Drill Participation January 2023 through December 2024
18 LS-AA-2130 Monthly Data Elements for NRC ROP Indicator - Alert and Notification System (ANS) Reliability January 2023 through December 2024 71151 Miscellaneous LS-AA-2135 Monthly Data Elements for NRC ROP Indicator - Emergency Response Facility and Equipment Readiness (ERFER)
January 2025 through February 2025 Calculations L-004330 (EC 630084)
Curtiss Wright Seismic Report NUS-A056QA for Controller Module Model CON2000-701-03/N 0
AR 4485554 RCIC Controller Not Stable During RCIC Low Press Run 03/17/2022 AR 4681919 U2 RCIC Broke 06/01/2023 AR 4684795 Unit RCIC Work Window 4.0 Critique 06/14/2023 AR 4684797 U2 RCIC Critique (DUP) 06/14/2023 AR 4704146 U2 RCIC Pump Flow Controller Not Working in Manual 09/21/2023 AR 4800683 U2 RCIC INPO Nuclear Safety Concern 09/10/2024 AR 4800685 U2 RCIC INPO Nuclear Safety Concern Follow On 09/10/2024 AR 4810348 Unit 2 RCIC Identified Issues, Troubleshooting Results 10/18/2024 Corrective Action Documents AR 4811828 U2 RCIC Flow Controller Improperly Calibrated 10/24/2024 Engineering Changes EC 630084 Curtiss Wright Seismic Report NUS-A056QA for Controller Module Model Con2000-701-03/N 0
3002010628 Nuclear Maintenance Applications Center: Terry Turbine Maintenance Guide, RCIC Application 10/01/2017 Miscellaneous LS-MSPI-001 LaSalle MSPI Basis Document 20 AD-AA-101-1002 Writers Guide for Procedures and T&RM 18 AD-LA-1000 LaSalle Procedure Writers Guide 3
CC-AA-103-2001 Setpoint Change Control 5
ER-AA-10 Equipment Reliability Process Description 9
ER-AA-200 Preventive Maintenance Program 7
ER-AA-2003 System Performance Monitoring and Analysis 18 LIS-RI-202 Unit 2 RCIC Pump Discharge Flow Indication Calibration 16 LIS-RI-215 Unit 2 RCIC Control System Calibration 21 LMP-RI-02 Reactor Core Isolation Cooling Turbine Maintenance 26 71152A Procedures LOP-RI-06 Controlled Start of the Reactor Core Isolation Cooling System in the CST Test Mode 31
19 LOS RI-Q3 Reactor Core Isolation Colling (RCIC) System Pump Operability and Valve Inservice Tests in Conditions 1,2, and 3
60 MA-AA-716-010 Maintenance Planning 35 Procedures MA-AA-716-010-1020 Writer's Guide for Maintenance Work Order Instructions 2
WO 4704314 RCIC Pump Discharge Flow IND 04/30/2020 WO 4932662 RCIC Control Sys 11/02/2021 WO 4980430 U2 RCIC Replace the EGM Module and RGSC 11/27/2023 WO 5030345 RCIC Pump Discharge Flow IND 09/30/2022 WO 5103995 LRA Turbine Inspection/Rebuild 02/25/2023 WO 5145550 U2 RCIC S/P Check Valves TST LOS-RI-R4, ATT 1A/LOS-RI-Q3 03/10/2023 WO 5204910 RCIC Control Sys 06/11/2023 WO 5240282 RCIC Controller Not Stable During RCIC Low Press Run 12/11/2023 WO 5241758 U1 RCIC S/P Check Valve TST LOS-RI-R4, ATT 1A/LOS-RI-Q3 ATT 03/09/2024 WO 5300925 RCIC Pump Discharge Flow IND 05/31/2023 WO 5343171 RCIC Pump Flow Controller not Working in Manual 06/08/2023 WO 5371708 U2 RCIC Broke 06/05/2023 WO 5403690 U2 RCIC Troubleshooting/Repair 11/29/2023 WO 5482486 LOS-RI-01 U2 RCIC Valves ATT 2A 05/01/2024 71152A Work Orders WO 5538711 LOS-RI-Q1 U2 RCIC Valves ATT 2A 07/31/2024 AR 4767915 Loss of Unit 1 SAT Due to OCB 1-13 Tripped on Diff Current 04/20/2024 AR 4767916 Loss of Division 1 Gross Gamma 04/20/2024 AR 4767918 Loss of 'A' MSL Rad Monitor 04/20/2024 AR 4767919 Loss of 1B CW Pump 04/20/2024 AR 4767921 VR No Air Flow Supply Isolation Damper Closed Alarm 04/20/2024 71153 Corrective Action Documents AR 4767922 VR Isolation Dampers Shut on Loss of the SAT 04/20/2024