IR 05000373/2025001
| 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
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
Inspection Report
Docket Numbers:
05000373 and 05000374
License Numbers:
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
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
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
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)
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
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 (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)
=
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
- (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.
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.
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)===
- (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
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
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.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
LAP-100-44
Inclement Weather Guidance
LOA-TORN-001
High Winds - Tornado
OP-AA-108-111-
1001
Severe Weather and Natural Disaster Guidelines
Procedures
Severe Weather Preparation and Response
NRC Question Related to FC ADHR WS Flow
2/20/2025
Corrective Action
Documents
Resulting from
Inspection
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
M-144, Sheet 2
P & ID Fuel Pool Cooling Filter & Demineralizing System
Y
Drawings
M-99
P & ID Standby Liquid Control System
Engineering
Changes
L2R20 ADHR Evaluation
000
LOP-FC-03
Fuel Pool Cooling System Startup, Operation, Shutdown,
Level Changes, and Flushing
LOP-RH-07
Shutdown Cooling System Startup, Shutdown, Operation
and Transfer
LOP-SC-01M
Standby Liquid Control System Mechanical Checklist
Procedures
LOP-VC-01
Control Room HVAC Operation
PFP RX BLDG
673-3, Fire Zone
211
Pre-Fire Plan Unit 1 General Area
PFP RX BLDG
673-3, Fire Zone
2
Pre-Fire Plan Unit 2 HPCS Cubicle
Fire Plans
PFP RX BLDG
673-3, Fire Zone
3E
Pre-Fire Plan Unit 2 General Area and RWCU Pump
Cubicles
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
PFP RX BLDG
694-6 Elevation,
Fire Zone 2H3
Pre-Fire Plan Unit 1 RHR Heat Exchanger B Cubicle
PFP RX BLDG
694-6, Fire Zone
2H2
Pre-Fire Plan Unit 1 HPCS Cubicle
PFP RX BLDG
740-0, Fire Zone
2F
Pre-Fire Plan Unit 1 General Area and CRD Repair Room
PFP RX BLDG
786-6, Fire Zone
3D
Pre-Fire Plan Unit 2 Reactor Building General Area
PFP RX BLDG
843-6, Fire Zone
FA1
Pre-Fire Plan Elevation U1 and U2 Refuel Floor Area
004
High Risk Fire Area Identification
MA-AA-716-008-
1008
Reactor Services Refuel Floor FME Plan
Fire Prevention for Hot Work
Control of Transient Combustible Material
Procedures
OP-LA-201-012-
001
LaSalle On-Line Fire Risk Management
UT PA Exam Results for 2RR28B-3" Weld 1
2/26/2023
L2R19 VT-3 IWF Class 1 Support Indication Reactor Water
Cleanup
2/26/2023
UT PA Exam Results for 2RH03CB-12" Weld 1
2/27/2023
IR 04557459 Written with the Wrong Component Listed
2/27/2023
UT PA Exam Results for 2RH03CB-12" Weld 2
2/27/2023
UT PA Exam Results for 2RT01B-6" Weld 17
2/28/2023
2/28/2023
Corrective Action
Documents
UT PA Exam Results for 2RR28B-3" Weld 1R
03/01/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
UT PA Exam Results for 2RR28B-3" Weld 1 Repair 2
03/02/2023
Internal Corrosion in 2A RHR Pump Seal Cooler Outlet Pipe
2/05/2023
Engineering
Changes
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
Magnetic Particle Examination
2/18/2025
1RH-2001-21A Ultrasonic Examination Report
2/20/2025
1FW-2001-20A Safe End to Nozzle Examination Report
2/20/2025
1FW-2002-20A Safe End to Nozzle Examination Report
2/18/2025
Visual Examination of Pipe Hanger, Support or Restraint
(VT-3)
2/11/2025
Visual Examination of Pipe Hanger, Support or Restraint
(VT-3)
2/11/2025
Visual Examination of Pipe Hanger, Support or Restraint
(VT-3)
2/12/2025
Visual Examination of Welds (VT-1)
2/12/2025
Visual Examination of Pipe Hanger, Support or Restraint
(VT-3)
2/18/2025
NDE Reports
Visual Examination of Pipe Hanger, Support or Restraint
(VT-3)
2/18/2025
VT-1 Visual Examination
VT-3 Visual Examination of Component Supports,
Attachments and Interiors of Reactor Vessels
Procedures
GEH-PDI-UT-1
PDI Generic Procedure for the Ultrasonic Examination of
Ferritic Welds
2.1
Work Orders
Unit 2 Bottom Head Drain Reroute (EC636268) Task 19
03/03/2023
ReMA Plan
- L2C20-02
L2C20 Standing Shutdown ReMA
03/17/2023
Miscellaneous
Sequence ID:
SAr9.1
L2C20 December 2024 Shutdown Sequence
2/18/2024
LGP-2-1
Normal Unit Shutdown
133
LGP-3-2
Reactor Scram
Procedures
OP-LA-101-111-
1002
LaSalle Operations Philosophy Handbook
Engineering
Changes
Ability of 1B Diesel Generator to Have Performed Required
Function with Fuel Oil Leak
Maintenance Rule Implementation Per NEI 18-10
Procedures
Maintenance Rule - (a)(1) and (a)(2) Requirements
1B SBLC Pump Discharge Check Valve Chattering
03/12/2025
1B SBLC Pump Run Indicated Low Flow
03/13/2025
Corrective Action
Documents
Leak on 1B SBLC Plungers Packing
03/14/2025
Risk Management
Integrated Risk Management
Procedures
On-Line Risk Management and Assessment
Unit 2 Div 2 RHRWS Pumps in Alert Range
04/10/2024
Unknown Cause in Change in the IST Dp for 2C & 2D
RHRWS pps
01/08/2025
CRD 18-35 Scram Time Exceeded 90% TS limit
2/26/2025
L2R20 LL - CRD 22-31 Scram Time Exceeded TS Limit
2/26/2025
CRD 26-31-Scram Time Within 90% of TS Limits
2/26/2025
CRD 50-19 Scram Time Exceeded 90% TS Limit
2/26/2025
CRD 58-27 Scram Time Exceeded 90% TS Limit
2/26/2025
CRD 38-43 Scram Time Within 90% of TS Limits
2/26/2025
CRD 30-55 Scram Time Exceeded 90% TS Limit
2/26/2025
Corrective Action
Documents
1B SBLC Pump Discharge Check Valve Chattering
03/12/2025
Engineering
Changes
EC EVAL 643386
Backseating Evaluation for Valve 1E51-F008
Procedures
Limitorque Motor-Operated and Chainwheel Operated Valve
Operations
EM Perform EQ Inspection and Votes Test 1E51-F008
2/27/2024
2B RHR WS Biennial Comprehensive IST Pump Test
04/10/2024
Work Orders
Scram Time Rods per LOS-RD_SR12 & Flush Rods at 00 or
2/28/2025
IM -EWP-LIS-RH-207 U2 RHR B Service Water Flow Ind
Cal
04/12/2024
Work Orders
2B RHR WS Biennial Comprehensive IST Pump Test
05/14/2024
Remove Bonnet Vent Valves on Unit 2 RR Discharge
Isolation Valves (2B33-F067A/F067B)
04/23/2019
Shutdown Cooling Trip Bypass Keylock Switches
Unit 2 - Adding a Time Delay to Load Reject Circuit
Engineering
Changes
DFP 'B' Engine Replacement
Work Orders
Remove Bonnet Vent Valves on 2B33-F067A
2/21/2023
Drywell Closeout Upper Elevation Walkdown with NRC
2/26/2025
NRC Question Related to FC ADHR WS Flow
2/20/2025
Corrective Action
Documents
Drywell Closeout 740 Elevation Walkdown with NRC
2/27/2025
Shutdown Reactivity Maneuver Plan
03/17/2023
Miscellaneous
PORC 25-02
L2R20 Shutdown Safety Plan
1B SBLC Pump Discharge Check Valve Chattering
03/12/2025
1B SBLC Pump Run Indicated Low Flow
03/14/2025
Corrective Action
Documents
Leak on 1B SBLC Plungers Packing
03/14/2025
Drawings
M-92
P&ID Primary Containment Vent & Purge
LOS-DG-201
Diesel Generator, 0DG01K, Start and Load Acceptance
Surveillance
LOS-DG-R0
Diesel Generator 0DG01K Twenty-Four Hour Run
Surveillance
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
OP LOP-NB-R2 Reactor Vessel Leakage Test
2/27/2025
Reactor Vessel Leakage Test
2/27/2025
U2 Core Verification (BOC Startup)
2/23/2025
2/18/2025
2/24/2025
Unit 2 Div 1 DC Restoration PMT JBR
2/18/2025
Scram Time Rods per LOS-RD-SR12 & Flush Rods at 00 or
2/28/2025
LLRT 2VQ034, 35, 36, 38
2/17/2025
Work Orders
PC VQ Valves LLRT 2VQ029/30/42
2/17/2025
OP LOS-MS-R7 U2 Main Steam Safety Relief Valve
Operability Test
2/24/2025
OP LOS-RP-SA3 U2 Rx Manual Scram Func Att 2A
2/09/2025
OP LOS-RP-SA3 U2 Rx Manual Scram Func Att 2B
2/09/2025
Unit 2 Div 2 DC Restoration PMT JBR
2/22/2025
LOS-RD-SR4 Rod Movement Log
2/25/2025
2E12-F025A Perform 'As Found' LLRT LTS-100-15
2/23/2025
OP LOS-SC-Q1 1A SBLC Pump Quarterly Att 1A
03/14/2025
OP LOS-SC-Q1 1B SBLC Pump Quarterly Att 1B
03/14/2025
2E12-F050A Failed LLRT
2/24/2025
Corrective Action
Documents
Resulting from
Inspection
NRC ID: E-Plan IPAWS Testing Records not Available
2/25/2025
Miscellaneous
N/A
PNS System Maintenance Reports
January
23 through
December
24
Procedures
Contracted Siren Maintenance Oversight
001
Miscellaneous
N/A
ERO Personnel Qualifications
Various
Exelon Nuclear Standardized Radiological Emergency Plan
Procedures
ERO Training and Qualification
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
24 Letters of Agreement: Seneca Fire Dept.; LaSalle
County Sheriff; Marseilles Area Ambulance Service;
Marseilles Fire Protection District; Seneca Ambulance
Service; Morris Hospital
Various
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
Gas Leak in the Unit 1 Hydrogen Analyzer Room
03/27/2024
Corrective Action
Documents
Radwaste Impacts Due to CCW (2TBCCW) Sent to Floor
Drains
08/27/2024
RP Knowledge and Skills, Self-Assessment Findings
10/20/2024
Dose Outside Performance Criteria for August SAC
10/22/2024
NOS ID: Rad Boundaries/Signage did not Follow Procedure
11/08/2024
NOS ID: Radiological Surveys Were Missing Required Data
11/08/2024
NOS ID: Alpha Eval Incorrectly Tracked
11/08/2024
Unit 1 Hydrogen Analyzer Room High Radioactive Gas
Content
11/08/2024
Unit 1 OG Pretreat Room Radioactive Leak
2/13/2024
Technician "Gassed Up" After U1 Pre Treat Sampling
2/16/2024
Rad Risk Assess. Approvals Not Documented for High-Risk
Job
2/19/2024
Radiological Risk Management
Administration of the Radiation Work Permit Program
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
25-233152
4-valve Room Prior to 2G33-F393A Insulation Removal
2/05/2025
Radiation
Surveys
25-233666
RT Pump Room Prior to Piping End Prep
2/12/2025
L-02-25-0642
L2R20 RB High Risk Valves-2G33-F393-394 Cut Out and
Replacement
LA-02-25-00518
L2R20 DW ISI, FAC, LROT Inspection Activities
LA-02-25-00901
L2R20 RFF Reactor Disassembly and Reassembly Activities
LA-2-25-00304
RWCU System Maintenance
Radiation Work
Permits (RWPs)
LA-2-25-00304
L2R20 RB RXB High Risk Valves-2G33-F393A
04716436
24 In Field Work Controls
10/10/2024
04716437
24 - Radworker Performance
10/28/2024
Self-Assessments
04716440-08-02
24 Rad Pro Knowledge and Skills
10/31/2024
Procedures
Dosimetry Issue, Usage, and Control
71151
Miscellaneous
Monthly Data Elements for NRC ROP Indicator - Emergency
Response Organization Drill Participation
January
23 through
December
24
Monthly Data Elements for NRC ROP Indicator - Alert and
Notification System (ANS) Reliability
January
23 through
December
24
71151
Miscellaneous
Monthly Data Elements for NRC ROP Indicator - Emergency
Response Facility and Equipment Readiness (ERFER)
January
25 through
February
25
Calculations
Curtiss Wright Seismic Report NUS-A056QA for Controller
Module Model CON2000-701-03/N
RCIC Controller Not Stable During RCIC Low Press Run
03/17/2022
U2 RCIC Broke
06/01/2023
Unit RCIC Work Window 4.0 Critique
06/14/2023
U2 RCIC Critique (DUP)
06/14/2023
U2 RCIC Pump Flow Controller Not Working in Manual
09/21/2023
U2 RCIC INPO Nuclear Safety Concern
09/10/2024
U2 RCIC INPO Nuclear Safety Concern Follow On
09/10/2024
Unit 2 RCIC Identified Issues, Troubleshooting Results
10/18/2024
Corrective Action
Documents
U2 RCIC Flow Controller Improperly Calibrated
10/24/2024
Engineering
Changes
Curtiss Wright Seismic Report NUS-A056QA for Controller
Module Model Con2000-701-03/N
3002010628
Nuclear Maintenance Applications Center: Terry Turbine
Maintenance Guide, RCIC Application
10/01/2017
Miscellaneous
LS-MSPI-001
LaSalle MSPI Basis Document
Writers Guide for Procedures and T&RM
AD-LA-1000
LaSalle Procedure Writers Guide
Setpoint Change Control
Equipment Reliability Process Description
Preventive Maintenance Program
System Performance Monitoring and Analysis
LIS-RI-202
Unit 2 RCIC Pump Discharge Flow Indication Calibration
LIS-RI-215
Unit 2 RCIC Control System Calibration
LMP-RI-02
Reactor Core Isolation Cooling Turbine Maintenance
Procedures
LOP-RI-06
Controlled Start of the Reactor Core Isolation Cooling
System in the CST Test Mode
LOS RI-Q3
Reactor Core Isolation Colling (RCIC) System Pump
Operability and Valve Inservice Tests in Conditions 1,2, and
Maintenance Planning
Procedures
MA-AA-716-010-
20
Writer's Guide for Maintenance Work Order Instructions
RCIC Pump Discharge Flow IND
04/30/2020
RCIC Control Sys
11/02/2021
U2 RCIC Replace the EGM Module and RGSC
11/27/2023
RCIC Pump Discharge Flow IND
09/30/2022
LRA Turbine Inspection/Rebuild
2/25/2023
U2 RCIC S/P Check Valves TST LOS-RI-R4, ATT 1A/LOS-
RI-Q3
03/10/2023
RCIC Control Sys
06/11/2023
RCIC Controller Not Stable During RCIC Low Press Run
2/11/2023
U1 RCIC S/P Check Valve TST LOS-RI-R4, ATT 1A/LOS-
RI-Q3 ATT
03/09/2024
RCIC Pump Discharge Flow IND
05/31/2023
RCIC Pump Flow Controller not Working in Manual
06/08/2023
U2 RCIC Broke
06/05/2023
U2 RCIC Troubleshooting/Repair
11/29/2023
LOS-RI-01 U2 RCIC Valves ATT 2A
05/01/2024
Work Orders
LOS-RI-Q1 U2 RCIC Valves ATT 2A
07/31/2024
Loss of Unit 1 SAT Due to OCB 1-13 Tripped on Diff Current
04/20/2024
Loss of Division 1 Gross Gamma
04/20/2024
Loss of 'A' MSL Rad Monitor
04/20/2024
Loss of 1B CW Pump
04/20/2024
VR No Air Flow Supply Isolation Damper Closed Alarm
04/20/2024
Corrective Action
Documents
VR Isolation Dampers Shut on Loss of the SAT
04/20/2024