IR 05000373/2025003
| ML25349A053 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/15/2025 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Mudrick C Constellation Energy Generation, Constellation Nuclear |
| References | |
| EA-NMSS-2023-0002, EAF-NMSS-2025-0226 IR 2025003 | |
| Download: ML25349A053 (0) | |
Text
SUBJECT:
LASALLE COUNTY STATION - INTEGRATED INSPECTION REPORT 05000373/2025003; 05000374/2025003; 07200070/2025001 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Christopher H. Mudrick:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at LaSalle County Station. On November 17, 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.
Due to the temporary cessation of government operations, which commenced on October 01, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations. However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025, 3rd quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025. The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, 4th quarter integrated inspection reports, which will be issued 45 days after the 4th quarter ends on December 31, 2025.
The NRC-identified a violation of 10 CFR 72.48 (c)(1), (c)(2), and (d)(1) and 10 CFR 72.212(b)(3) that resulted from a CoC holders failure to comply with 10 CFR 72.48 for a CoC holder-generated change to the multi-purpose canister fuel basket, known as the continuous basket shim variant. However, an Interim Enforcement Policy (IEP) issued in August 2025 is applicable to this violation. Specifically, Enforcement Policy section 9.4, Enforcement Discretion December 15, 2025 for General Licensee Adoption of Certificate of Compliance (CoC) Holder-Generated Modifications under 10 CFR Part 72.48, provides enforcement discretion to not issue an enforcement action for this violation. The licensee will be expected to comply with 10 CFR 72.212 provisions after the NRC dispositions the noncompliance for a CoC holder-generated change that affects the General Licensee.
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; 05000374; 07200070 License Nos. NPF-11 and NPF-18
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000373; 05000374; 07200070
License Numbers:
Report Numbers:
05000373/2025003; 05000374/2025003; 07200070/2025001
Enterprise Identifier:
I-2025-003-0055; I-2025-001-0134
Licensee:
Constellation Nuclear
Facility:
LaSalle County Station
Location:
Marseilles, IL
Inspection Dates:
July 01, 2025, to September 30, 2025
Inspectors:
N. Audia, Reactor Inspector
J. Benjamin, Senior Resident Inspector
J. Cassidy, Senior Health Physicist
J. Hoang, Reactor Technology Instructor
T. Hooker, Health Physicist
B. Lin, Senior Health Physicist
A. Muneeruddin, 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 URI 05000373,05000374/2023003-01 Continuous Basket Shim Design Change for HI-STORM 100 60855 Closed EDG EAF-NMSS-2025-0226 Continuous Basket Shim - General Licensee Adoption of Certificate of Compliance Holder-Generated Changes under 10 CFR 72.48 (IEP 9.4)60855 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On September 6, 2025, the unit down powered to approximately 78 percent to perform main turbine control valve testing, control rod scram time testing, and a control rod sequence exchange and was returned to full power on September 7, 2025. The unit operated at or near full power for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power. On September 27, 2025, the unit down powered to approximately 63 percent to perform main turbine control valve testing, a main control rod sequence exchange and scram time testing. The unit was restored to full power on September 28, 2025, and operated at full 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 spent fuel pool cooling on July 7, 2025
- (2) Unit 2B train service water pump with Unit 2A train service water pump out of service for maintenance on July 23, 2025
71111.05 - Fire Protection
Fire Brigade Drill Performance Sample (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated the onsite fire brigade training and crew performance during an unannounced fire drill on August 21, 2025.
- (2) The inspectors evaluated the onsite fire brigade training and crew performance during an unannounced fire drill on August 22, 2025.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated license operator requalification training: out-of-the-box evaluation on July 8, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)1A standby liquid control pump
- (2) Unit 1 SCRAM discharge volume drain valve, 1C11-F381
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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)planned elevated Unit 2 on-line risk the week of July 7, 2025, during the Unit 2A train service water system work window (2)unplanned elevated Unit 1 on-line risk on September 2, 2025, following the Common emergency diesel generator Unit 1 output breaker closure failure during testing (3)planned elevated Unit 2 on-line risk from September 2 through September 4, 2025, during Unit 2A train residual heat removal (RHR) system maintenance window
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Action Request (AR) 4879420, Reactor Core Isolation Cooling Turbine Trip Pushbutton Broke
- (2) Unit 1 emergency cooling water system operability during routine fill and vent activities
- (3) AR 4836829, 'C' Vacuum Breaker, 2PC001C, Failed Force Check
- (4) AR 4865523 and AR 4865896, NRC Identified U-1 250V Battery Discrepancies
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) (3 Samples)
- (1) Unit 1B train spent fuel pooling cooling water pump replacement, WO 5181459
- (2) Unit 2B train RHR service water pump seal replacement, WO 1927593
- (3) Unit Common emergency diesel generator Unit 1 output breaker relay replacement on October 30, 2025
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) Unit Common emergency diesel generator fuel oil transfer pump test per LOS-DG-Q1, Attachment A1 on July 2, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 2 reactor core isolation cooling water pump operability and inservice test on August 26, 2025
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
(1)diverse and flexible coping strategy hale pump A functional surveillance on July 8, 2025
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) emergency response organization full-scale exercise on August 19,
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (3 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
(1)main vent stack sample skid and radiation monitor (2)standby gas treatment sample skid and radiation monitor (3)cooling pond blowdown effluent release point
Sampling and Analysis (IP Section 03.02) (3 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
(1)particulate and iodine sampling of Unit 0 main vent stack (2)noble gas grab sample of Unit 0 main vent stack (3)cooling pond blowdown composite sampling
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
- (1) Permit Number G-20250527-1232-C
- (2) Permit Number G-20221025-925-C
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the groundwater protection initiative (GPI) program to identify incomplete or discontinued program elements.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
- (2) Unit 2 (July 1, 2024, through June 30, 2025)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
- (2) Unit 2 (July 1, 2024, through June 30, 2025)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
- (2) Unit 2 (July 1, 2024, through June 30, 2025)
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)extent-of-condition review based upon AR 4865896, Unit 1 250 VDC Battery Spacing Discrepancies
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855 - Operation of an Independent Spent Fuel Storage Installation Operation of an Independent Spent Fuel Storage Installation
- (1) The inspectors evaluated the licensee's use of the Holtec multi-purpose canister (MPC) continuous basket shim (CBS) variant during a previous independent spent fuel storage installation (ISFSI) loading.
INSPECTION RESULTS
Enforcement Discretion Enforcement Action EAF-NMSS-2025-0226: Continuous Basket Shim - General Licensee Adoption of Certificate of Compliance Holder-Generated Changes under 10 CFR 72.48 (IEP 9.4)60855
Description:
Holtec International implemented a design change to its multi-purpose canister (MPC) fuel basket, known as the continuous basket shim (CBS) variant, which altered the structural configuration from welded to bolted shims. This change resulted in a departure from the method of evaluation (MOE) described in the final safety analysis report (FSAR) used to establish the design basis for tip-over events. Holtec did not fully evaluate the cumulative impact of the MOE changes or apply them consistently with the licensing basis. As a result, the NRC issued three Severity Level IV violations to Holtec for noncompliance with 10 CFR 72.48 requirements (see U.S. Nuclear Regulatory Commission Inspection Report 07201014/2022-201, Holtec International, Agency wide Documents Access and Management System (ADAMS) Accession No. ML23145A175 and Holtec International, Inc. - Notice of Violation; The U.S. Nuclear Regulatory Commission Inspection Report No. 07201014/2022-201, ADAMS Accession No. ML24016A190).
When the licensee (also referred to as a general licensee) chooses to adopt a change the Certificate of Compliance (CoC) holder made pursuant to a CoC holders change authority under 10 CFR 72.48 (referred to herein as a CoC holder-generated change,), the General Licensee (GL) must perform a separate review using the requirements of 10 CFR 72.48(c).
Accordingly, when the licensee chooses to adopt a CoC holder-generated change, and that change results in a non-conforming cask, there is a violation of 10 CFR 72.48 and certain provisions of 10 CFR 72.212 by the licensee, in addition to a CoC holder violation of 10 CFR 72.48. The licensee failed to recognize the noncompliance with 10 CFR 72.48 requirements made by the CoC holders design change and subsequently loaded the CBS variant casks.
Corrective Actions: The licensee entered this into its corrective action program to restore compliance with the 10 CFR 72.212 provisions that require each cask to conform to the terms, conditions, and specifications of a CoC or an amended CoC listed in 10 CFR Part 72.214.
Corrective Action References:
AR 4683011, Potential NRC Concern Regarding HOLTEC DCS System, dated June 6, 2023 AR 4746833, Holtec Level IV Violations for CBS Design Change, dated February 6, 2024
Enforcement:
Significance/Severity: Consistent With the guidance in Section 1.2.6.D of the NRCs Enforcement Manual, if a violation does not fit an example in the enforcement policy violation examples, it should be assigned a severity level:
- (1) commensurate with its safety significance; and
- (2) informed by similar violations addressed in the violation examples. The violation was evaluated to be similar to a Severity Level IV violation in Enforcement Policy Section 6.1.d.2. Since this violation meets the criteria of Section 9.4, Enforcement Discretion for General Licensee Adoption of CoC Holder-Generated Changes Under 10 CFR 72.48, of the NRC Enforcement Policy (ML25224A097), and the licensee has taken actions to restore compliance, the NRC is exercising enforcement discretion by not issuing an enforcement action for this violation.
Violation: Title 10 CFR 72.48(c)(1) states, in part, a licensee may make changes in the facility or spent fuel storage cask design as described in the FSAR (as updated), without obtaining:
- (ii) a CoC amendment submitted by the certificate holder pursuant to § 72.244 if: (C) the change, test, or experiment does not meet any of the criteria in paragraph (c)(2) of this section.
Title 10 CFR 72.48(c)(2) states, in part, a GL shall request that the certificate holder obtain a CoC amendment, prior to implementing a proposed change, if the change would: (viii) result in a departure from a MOE described in the FSAR (as updated) used in establishing the design bases or in the safety analyses.
Title 10 CFR 72.48(d)(1) states, in part, that the licensee shall have a written evaluation which provides the basis for the determination that the change does not require a CoC amendment pursuant to § 72.48(c)(2).
Title 10 CFR 72.212(b)(3) states, in part, a GL must ensure that each cask used by the GL conforms to the terms, conditions, and specifications of a CoC or an amended CoC listed in
§ 72.214.
Contrary to the above, prior to December 20, 2024, the licensee failed to:
- (1) request that the certificate holder obtain a CoC amendment for a change in the cask design that resulted in a departure from an MOE described in the FSAR;
- (2) have a written evaluation providing the bases for the determination that the adopted change did not require a CoC Amendment; and
- (3) ensure that the affected casks conformed to the terms, conditions, and specifications of the applicable CoC. Specifically, the licensee failed to identify that the CBS variant design change resulted in a departure from a MOE described in the FSAR used in establishing the design bases. The licensee did not request that the certificate holder, Holtec, obtain a CoC amendment pursuant to 10 CFR 72.244. The licensee also failed to ensure that each cask conformed to the terms, conditions, and specifications of a CoC or an amended CoC listed in 10 CFR 72.214, prior to using the CBS variant design.
Basis for Discretion: The NRC exercised enforcement discretion in accordance with Section 9.4 of the Enforcement Policy, titled Enforcement Discretion for General Licensee Adoption of Certificate of Compliance Holder-Generated Changes under 10 CFR 72.48, (ML25224A097), because the licensee met the criteria within this section. Specifically, this section states that the NRC will exercise enforcement discretion and not issue an enforcement action to a GL, for a noncompliance with the requirements of paragraphs (c)(1)and
- (2) and (d)(1) of 10 CFR 72.48 and with the provisions of 10 CFR 72.212 that require GLs to ensure use of casks that conform to the terms, conditions and specifications of a CoC listed in 10 CFR 72.214, when the noncompliance results from a CoC holders failure to comply with 10 CFR 72.48 for a CoC holder-generated change. In support of the 2023 loading campaign, the licensee adopted a generic CoC holder design change (the CBS basket variant) and subsequently loaded the casks. On January 30, 2024, the NRC issued a notice of violation, identifying the noncompliance, for the generic design change associated with the CBS basket variant (ML24016A190). As a result, the licensee became noncompliant due to the CoC holders failure to comply with 10 CFR 72.48 for the CoC holder-generated change. Since this violation has been determined to be more than minor and it meets the criteria of Section 9.4 of the policy, the NRC is exercising enforcement discretion by not issuing an enforcement action for this violation.
The disposition of this violation closes URI: 05000373,05000374/2023003-01.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On November 17, 2025, the inspectors presented the integrated inspection results to John VanFleet, Site Vice President, and other members of the licensee staff.
- On August 21, 2025, the inspectors presented the radiation protection inspection results to John VanFleet, Site Vice President, and other members of the licensee staff.
- On September 29, 2025, the inspectors presented the ISFSI inspection results to John VanFleet, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Potential NRC Concern Regarding Holtec DCS System
06/06/2023
60855
Corrective Action
Documents
Holtec Level IV Violations for CBS Design Change
2/06/2024
Corrective Action
Documents
Increase Vibration Trend on 2B FC Motor (2FC01PB)
PeaKVue
01/06/2025
LOP-FC-02E
Unit 2 Fuel Pool Cooling System Electrical Checklist
LOP-FC-02M
Unit 2 Fuel Pool Cooling Mechanical Checklist
LOP-WS-02
Service Water Pump and Service Water Jockey Pump
Startup and Operation
LOP-WS-02M
Unit 2 Service Water System Mechanical Checklist
Procedures
LOP-WS-05
Service Water Strainer Operations
Work Orders
2FC01PB Increase Vibe Trend - Lubrication
01/09/2025
Delta Crew Unannounced Fire Drill
08/28/2025
Corrective Action
Documents
Romeo Crew Unannounced Fire Drill
08/21/2025
Fire Plans
FZ 4E3
Aux. Bldg. 731'-0" Elev. U1 Division 2 Essential
Switchgear Room
Miscellaneous
Fire Drill Scenario
No. 23-21
Procedures
Fire Brigade
Procedures
LOA-RD-201
Control Rod Drive Abnormal
U1 SDV Drain Valve 1C11-F381 Failed to Move During
LOS-RD-Q1
03/06/2025
1A SBLC Pump Flow in Alert Range During LOS-SC-Q1
05/19/2025
Corrective Action
Documents
1C11-F380 Low Margin to Stroke Time Warning Range
07/17/2025
Corrective Action
Documents
Resulting from
Inspection
Missing Work Package
08/06/2025
M-100
P&ID CRD Hydraulic Piping Sheet 2
Drawings
M-100
P&ID CRD Hydraulic Piping Sheet 4
N
Engineering
Changes
IST Pump Evaluation for Pump 1C41-C001A
Miscellaneous
ISSUE-2025-3570
Engage Health - 1C11-F381 Maintenance Rule
Determination
05/01/2025
Procedures
LOS-SC-Q1
SBLC Pump Operability/Inservice Test and Explosive
Valve Continuity Check
Disassemble and Inspect Check Valve
03/14/2025
Contingency Replace SBLC Flowmeter per LIP-SC-502
03/14/2025
Replace IA Regulator 1C11-F415 for 1C11-F381 Valve
03/07/2025
03/07/2025
Work Orders
IST Comprehensive Pump Test for 1C41-C001A
05/19/2025
Corrective Action
Documents
DG Output Breaker Failed to Close on Unit 1
09/02/2025
09.01.2025.18.20.41
Unit 2 'A' RHR Protected System/Pathway Checklist
09/01/2025
Miscellaneous
LAS-1937-LAS
Unit 1 '0' DG Output Breaker Support/Refute Matrix
09/02/2025
Risk Management Configuration Control
On-Line Risk Management
Procedures
Protected Equipment Program
043604(CMED)
Seismic Qual of GNB NCX-17 and NCX-27 Battery Cells
05/16/1989
Calculations
043796(CMED)
Seismic Qual of Battery Racks 1DC01E and 1&2DC14E
Due to Material Changes of Racks
05/23/1990
2PC001C, C Vacuum Breaker Failed Force Check
2/12/2025
NRC Identified U-1 250V Battery Discrepancies
05/13/2025
NRC Identified U-1 250V Battery Discrepancies
05/14/2025
Corrective Action
Documents
Missing Seismic Test Reports for 250V Batteries
06/06/2025
NRC Question - Were All SRs Met after RCIC Failure to
Trip
07/10/2025
Corrective Action
Documents
Results of U2 250V Battery EOC Walkdown
07/31/2025
Corrective Action
Documents
Resulting from
Inspection
Missing Work Package
08/06/2025
Drawings
Primary Containment & Reactor Vessel Isolation System
Part 11
Engineering
Evaluations
TE-BATT-2025-02
Evaluation of NRC-Identified Rack Issues for LaSalle
25V and 250V Batteries
Miscellaneous
J-2554
Storage Batteries and Accessories Purchase Order
08/20/1976
LOP-HP-01
Filling and Venting the High Pressure Core Spray System
LOP-LP-01
Filling and Venting, Draining the Low Pressure Core Spray
System
Procedures
LOP-RH-04
Filling, Venting, and Flushing the RHR Service Water
System
Primary Containment Vacuum Breaker PMT
2/24/2025
OP LOS-PC-Q3 D/W to S/P Vacuum Brks Test Att 2A
2/13/2024
Work Orders
MM Troubleshoot the 2PC001C Valve
2/24/2025
Calculations
NED-I-EIC-0158
Determination of Optimal RCIC Keep Filled Alarm Setpoint
and Associated TS Allowable Value
2B RHR Service Water Pump Leak
10/16/2024
05/09/2025
Corrective Action
Documents
FLEX Hale Pump A Submersible Pipe Elbow has
Damaged End
07/08/2025
M-147
BL
Drawings
M-85
P&ID Diesel Oil System
AE
Engineering
Changes
Provide M&TE Requirements for Comprehensive Pump
Tests
Miscellaneous
LOS-RI-Q3/Q5
LaSalle IST Surveillance Acceptance Criteria Manual
LOS-DG-Q1, Att. 1
DG Fuel Oil Transfer Pump Test
LOS-RI-Q5
RCIC System Pump Operability Valve Inservice Tests and
Cold Quick Start
Procedures
MA-AA-716-230-
1002
Vibration Analysis/Acceptance Guideline
Refurbish Operating Mechanism
10/13/2016
Replace 2B RHR WS Pump Inboard and Outboard Seals
09/03/2025
PMT - Perform a Functional and Leak Check for 2B RHR
WS Pump
09/04/2025
EWP EM Replace 1B FC Motor
08/11/2025
OP PMT 1FC01PB Runs Sat
08/11/2025
MS - PMT Fuel Pool Cooling 1B Pump Motor Vibes
08/11/2025
Refurbish Operating Mechanism
05/25/2025
FLEX MISC EQUIPMENT ANNUAL FUNCTIONAL
SURVEILLANCE
07/09/2025
Unit 2 'B' Train Residual Heat Removal Quarterly Pump
Run
08/11/2025
Work Orders
LRA LOS-DG-M1 0 DG Idle Start Att 0 - Idle
07/01/2025
Miscellaneous
08/19/2025 LaSalle
DEP Drill Package
DEP Drill Package 08/19/2025
CY-LA-170-301
Offsite Dose Calculation Manual
DTSQA
classification log ID:
EX0008268
OpenEMS
1.1
RA24-009
23 Annual Radioactive Effluent Release Report
04/26/2024
Miscellaneous
RA25-011
24 Annual Radioactive Effluent Release Report
04/25/2025
LCP-310-14
Sampling and Compositing Cooling Pond Makeup and
Blowdown Samples
Procedures
LCP-310-52
Wide Range Gas Monitor Normal Noble Gas, Iodine, and
Particulate Sampling
Self-
Assessments
04855562
Self Assessment: Radioactive Gaseous and Liquid
Effluent
Treatment (RETS)
05/12/2025
SVS WRGM Aux Sample Pump Loss
08/08/2023
WWTF EQ Tank not Sampled During Week of 1/15/24
01/23/2024
Fleet Gap in ANSI N13.37 Environmental Dosimetry
01/26/2024
Q1 2020 Field Dosimeter Data Readings Lower than
Expected
2/07/2024
Field Dosimeter Extent-of-Condition Review
2/12/2024
Corrective Action
Documents
REMP Control Dairy Location Permanently Unavailable
08/08/2024
Request WR/WO to Calibrate 0XI-EM007 for 375' Wind
Direction
09/24/2024
Typographical Errors in 2022 and 2023 AREOR
2/16/2025
Missed ODCM Sample Required per LOP-VQ-04/ODCM
2.4.1
Land Use Census
22
Land Use Census
23
Land Use Census
24
Monthly Report on the Meteorological Monitoring Program
at the LaSalle County Nuclear Generating Station
06/17/2025
Results of Radiochemistry Cross Check Program
07/03/2025
Results of Radiochemistry Cross Check Program
05/28/2025
RA23-029
22 Annual Radiological Environmental Operating Report
05/12/2023
RA24-011
23 Annual Radiological Environmental Operating Report
05/03/2024
Miscellaneous
RA25-012
24 Annual Radiological Environmental Operating Report
05/09/2025
Radiological Groundwater Protection Program
Radiological Groundwater Protection Program
Implementation
EN-LA-408-4160
RGPP Reference Material for LaSalle County Generating
Station
Procedures
LCP-140-1
Radioactivity Measurements and Corrective Action
Schedule
04750740
Self Assessment: Radiological Environmental Monitoring
Program (REMP)
10/15/2024
Self-
Assessments
NOSA-LAS-23-03
Chemistry, Radwaste, Effluent and Environmental
Monitoring Audit Report
04/05/2023
Miscellaneous
LS-MSPI-001
MSPI Monitoring and Margin Evaluation
71151
Procedures
Mitigating Systems Performance Index Basis Document
71151
Procedures
Mitigating System Performance Index Data Acquisition &
Reporting
NRC Identified U-1 250 V Battery Discrepancies
05/14/2025
EOC Walkdown for Unit 2 Div 3 Battery
05/20/2025
EOC Walkdown for Unit 1 Div 1 125 V Battery
05/20/2025
EOC Walkdown for Unit 1 Div 2 125 V Battery
05/20/2025
EOC Walkdown for Unit 2 Div 1 125 V Battery
05/20/2025
EOC Walkdown for Unit 2 Div 2 125 V Battery
05/20/2025
EOC Walkdown for Unit 2 250 V Battery
05/20/2025
EOC Walkdown for Unit 1 Div 3 125 V Battery
05/20/2025
Corrective Action
Documents
DG Output Breaker Failed to Close on Unit 1
09/02/2025
Preventative Maintenance Program
Equipment Classification
Procedures
LEP-DC-106
Installation of 250 Volt Batteries
Work Orders
Replace Unit 1 250VDC Battery 1DC01E
05/06/2024