IR 05000373/2024004
| ML25041A288 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/10/2025 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| IR 2024004 | |
| Download: ML25041A288 (1) | |
Text
SUBJECT:
LASALLE COUNTY STATION - INTEGRATED INSPECTION REPORT 05000373/2024004 AND 05000374/2024004
Dear David Rhoades:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at LaSalle County Station. On January 8, 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 NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be Severity Level IV is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at LaSalle County Station.
February 10, 2025 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:
05000373/2024004 and 05000374/2024004
Enterprise Identifier:
I-2024-004-0060
Licensee:
Constellation Nuclear
Facility:
LaSalle County Station
Location:
Marseilles, IL
Inspection Dates:
October 01, 2024, to December 31, 2024
Inspectors:
M. Abuhamdan, Reactor Inspector
J. Benjamin, Senior Resident Inspector
J. Cassidy, Senior Health Physicist
A. Guieb, Project Engineer
T. Hooker, Health Physicist
J. Kutlesa, Senior Emergency Preparedness Inspector
E. Magnuson, Reactor Inspector
J. Meszaros, Resident Inspector
J. Nance, Operations Engineer
J. Park, Reactor Inspector
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. A licensee-identified non-cited violation is documented in report section: 7115
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 05000373,05000374/
2023-002-01 LER 2023-002-01, LaSalle County Station, Units 1 and 2,
Air Circuit Breaker (ACB)
Mechanically Operated Contacts (MOC) Switch Failed to Actuate 71153 Closed LER 05000373/2024-001-00 LER 2024-001-00, LaSalle County Station, Unit 1, Core Operating Limits Report Thermal Limits Exceeded 71153 Closed LER 05000373/2024-003-00 LER 2024-003-00, LaSalle County Station, Unit 1,
Technical Specification (TS)
Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded 71153 Closed LER 05000373/2024-003-01 LER 2024-003-01, LaSalle County Station, Unit 1,
Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded 71153 Closed LER 05000373/2024-002-00 LER 2024-002-00, LaSalle County Station, Unit 1,
Reactor Protection System Half Scram due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On November 22, 2024, the unit was down powered to approximately 60 percent power for power suppression testing and to make a control rod pattern adjustment. The unit was restored to full power on November 25, 2024, and remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power. On November 15, 2024, the unit was down powered to approximately 75 percent power for control rod scram time testing and to make a control rod pattern adjustment. The unit was restored to full power on November 16, 2024. On December 13, 2024, the unit was down powered to approximately 80 percent power for a control rod pattern adjustment. It was restored to full power on December 14, 2024. The unit remained at or near 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
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) Station cold weather preparations
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
(1)2A emergency diesel generator following work window and restoration to operability on October 10, 2024
- (2) Unit 2 reactor core isolation cooling (RCIC) following troubleshooting window and restoration to operability on October 18, 2024
- (3) Unit 1 RCIC system with Unit 1B emergency diesel generator inoperable due to a diesel fuel leak on October 21, 2024
- (4) Unit 1B standby liquid control after quarterly pump run surveillance on November 26, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)
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 2H4, reactor building, elevation 694'-6," Unit 1 RCIC and low-pressure core spray pump cubicle week October 7, 2025
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) 2A residual heat removal (RHR) heat exchanger and performance testing
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) Simulator training scenario titled Cold Weather Preps
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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)2A reactor water cleanup pump auto trip, per Work Order (WO) 5580104
- (2) Unit 2 RCIC flow control issues
- (3) Unit 2 local power range monitor failure trend caused by reverse engineered cards as documented in Action Request (AR) 4781907
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Unit 2 B/C RHR water leg pump rebuild and installation on November 13, 2024, given previous ball-bearing commercial grade dedication issue documented in AR 4786379
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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) Unit 2 elevated risk due to 2A emergency diesel generator work window on October 8, 2024
- (2) Unit 2 elevated risk due to Unit 2 RCIC inoperable for troubleshooting on October 17, 2024
- (3) Unit 2 elevated risk due to outside earth core bore activities the week of October 21, 2024
- (4) Unit 1 elevated risk due to 1A emergency diesel generator out of service for maintenance on October 28, 2024
- (5) Unit 2 elevated risk due to planned 2A RHR system work window on November 11, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) AR 4805729, 0 Emergency Diesel Generator Circulating Oil Pump Abnormal Noise
- (2) AR 4809723, 2B Residual Heat Removal Service Water Pump Leak
- (3) AR 4810060, LaSalle Susceptibility to GNF-3 LTP Threading Burrs
- (4) AR 4813563, A-VC Delayed Compressor Start
- (5) AR 4817902, Entered LOA-RD-201 for Potential Stuck Control Rod
- (6) AR 4825553, High Servo Error on RR Subloop 1A1
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) PMT associated with the 2A emergency diesel generator work window October 7, 2024
- (2) PMT associated with the replacement of air circuit breaker 2423 mechanically operated contact switch on October 7, 2024, per WO 4736142
- (4) PMT associated with the B diesel fire pump controller under WO 54113390
- (5) PMT associated with the 0B auxiliary electrical equipment room (VE) compressor low suction pressure under WO 4851648
- (7) PMT associated with the Unit 1B emergency diesel generator after a diesel fuel leak occurred during the October 21, 2024, endurance run
- (8) PMT associated with the Unit 1A emergency diesel generator cooling water pump after a planned work window on October 29, 2024
- (9) PMT associated with the B control room/auxiliary electrical equipment room ventilation system train after a planned work window on November 15, 2024
- (10) PMT associated with the 2A emergency diesel generator cooling water strainer high d/p alarm, per WO 5574165 on November 1, 2024
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) Unit 1 division 1 RHR service water pump run and system flush on November 4, 2024
- (2) Unit 1 RCIC cold quick start per LOS-RI-Q5 on November 14, 2024
- (3) Common diesel driven A fire pump operational check on November 7, 2024
- (4) Unit 1 2B emergency diesel generator surveillance test LOS-DG-3 idle start on November 18, 2024
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1 primary containment isolation valve operability test and in-service inspection (ISI) performed under WO 5550556, attachment 1A valves
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
- EP-AA-1005, Radiological Emergency Plan Annex for LaSalle Station, Revision 42
- EP-AA-1005, Addendum 1, LaSalle Station On-Shift Staffing Technical Basis, Revision 3
- EP-AA-1005, Addendum 2, LaSalle Evacuation Time Estimates, Revision 2
- EP-AA-120-1001, LAS Emergency Plan Revised for IPAWS Implementation, Evaluation No. 23-36 This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Winter readiness in the simulator with evaluation of drill and exercise performance indicators on November 14,
RADIATION SAFETY
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (1 Sample)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Unit 2 control room envelope ventilation system
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.
Internal Dosimetry (IP Section 03.03) (1 Sample)
The inspectors evaluated the following internal dose assessments:
- (1) EID 018931 06/13/2023
Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
- (1) Declared pregnant worker
- (2) Effective dose equivalent for external (EDEX) radiation exposures
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (8 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Frisker used at the radiologically controlled exit
- (2) Whole body monitors used at the chemistry lab and auxiliary building 768' elevation
- (3) Chemistry lab radiation counting instrumentation
- (4) Whole body counters in the dosimetry room
- (5) Portal monitors at the main access facility exit
- (6) Portable ion chambers stored ready for use in the calibration facility
- (7) Irradiators stored and secured in the plant
- (8) Area radiation monitors and continuous air monitors staged in the plant
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Eberline AMS 4, SN #0013597
- (2) Ludlum Model 3, SN #0016630
- (3) Gamma Products Inc HPGe Detector, Cave A
- (4) PerkinElmer Tri-Carb 4910TR, C
- (5) ThermoScientific PM-12, SN #12008
- (6) Canberra FastScan
- (7) ThermoScientific RadEye PX, SN #0025283
- (8) MGP AMP-200, SN #0016004
- (9) MGP AMP-100, SN #077575
- (10) MGP Telepole, SN #0023597
- (11) Ludlum Model 3002, SN #0029014
- (12) Eberline RO20, SN #0015813
- (13) RADeCO H-810, SN #228 Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 2, service water effluent radiation monitor, 2D18-1009
- (2) Unit 2, standby gas treatment system, 0PLD1J
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 (September 1, 2023, through September 30, 2024)
- (2) Unit 2 (September 1, 2023, through September 20, 2024)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) September 1, 2023, through September 30, 2024 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) September 1, 2023, through September 30, 2024
===71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (1 Sample 1 Partial)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) The inspectors evaluated corrective actions implemented in response to a Unit 1B emergency diesel generator fuel oil leak documented in AR 1041521, given an additional fuel oil leak on October 21, 2024.
(2)
(Partial)
The inspectors evaluated the overall problem identification and resolution aspects of a relatively long-standing issue regarding the Unit 2 RCIC system response in manual control mode. The review of this sample was still ongoing at the end of this inspection period and was therefore treated as a partial sample.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)===
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in initial corrective action identification, screening, and resolution prioritization that might be indicative of a more significant safety issue.
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) Licensee Event Reports (LERs) 05000373/2024-003-00 and
===05000373/2024-003-01, LaSalle County Station, Unit 1, Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded (Agencywide Document Access and Management System [ADAMS]
Accession Nos. ML24158A051 [2024-003-00] and ML24213A022 [2024-003-01].)
The inspection conclusions associated with this LER are documented in this report under Inspection Results Section. This LER is closed.
- (2) LER 05000373/2024-002-00 for LaSalle County Station Unit 1, Reactor Protection System Half Scram due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip (ADAMS Accession No. ML24138A030.) The inspectors reviewed the LER and determined that the cause of the condition described in the LER was not reasonably within the licensees 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.
- (3) LER 05000373/2024-001-00 for LaSalle County Station, Unit 1, Core Operating Limits Report Thermal Limits Exceeded (ADAMS Accession No. ML24117A127.)
The inspection conclusions associated with this LER are documented in this report under Inspection Results Section. This LER is closed.
- (4) LER 05000373(374)/2023-002-01, LaSalle County Station, Units 1 & 2, Supplement to Air Circuit Breaker (ACB) Mechanically Operated Contacts (MOC) Switch Failed to Actuate (ADAMs Accession No. ML24283A102.) The inspectors reviewed the updated LER submittal, which includes administrative changes only. The previous LER submittal was reviewed in NRC Integrated Inspection Report 05000373/2024003 and 05000374/2024003. This LER is closed.
Personnel Performance (IP Section 03.03)===
- (1) The inspectors observed the Unit 2 control rod pattern adjustment on December 13, 2024, and evaluated the execution of the activity within established procedures.
- (2) The inspectors observed the Unit 1 control rod power suppression testing on November 23, 2024, and evaluated execution of the activity within established plant procedures.
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: LaSalle Unit 1 Technical Specifications (TSs) 3.2.2 requires, in part, that all minimum critical power ratios (MCPR) to be greater than or equal to the MCPR operating limits specified in the core operating limit report. TS 3.2.2 Condition A applies to any MCPR not within the limits and requires the MCPR(s) to be restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Contrary to the above, the licensee exceeded the completion time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore the MCPR operating limit after not being met during the previous operating cycle (March 18, 2022, through February 19, 2024).
Significance/Severity: Severity Level IV. Traditional Enforcement is being used to disposition this violation with no associated reactor oversight process performance deficiency, per NRC Enforcement Manual revision dated December 26, 2023, Section 3.10. The inspectors determined the severity of the violation using Section 6 of the NRC Enforcement Policy and determined this issue was a Severity Level IV because it most represented the examples in Section 6.1.d.
Corrective Action References: AR 4752108 Minor Violation 71153 LERs 05000/373/2024-003-00 and 2024-003-01, LaSalle County Station, Unit 1, Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded Minor Violation: The inspectors reviewed the LER and identified a minor violation of NRC requirements as described in the LER. LaSalle Unit 1 TS Surveillance Requirement (SR) 3.6.1.3.9 requires the removal and testing of the explosive squib from each shear isolation valve of the traversing in-core probe (TIP) system. The TS bases for SR 3.6.1.3.9 states that the controls that limit shelf life and operating life of the explosive charge be followed. The 5-year expiration date was exceeded for the three identified TIP shear valves, therefore the licensee determined that TS SR 3.6.1.3.9 bases was not met. This licensee declared the three TIP shear valves inoperable. The station exceeded the completion time for TS LCO 3.6.1.3, Primary Containment Isolation Valve, and therefore the licensee reported this condition as a condition prohibited by the TSs.
Screening: The inspectors determined the performance deficiency was minor. The inspectors determined that this violation was minor. The expired squib cartridges were subsequently removed and tested successfully demonstrating that the expired squib cartridges were still capable of performing their function.
Enforcement:
This failure to comply with LaSalle Unit 1 TS SR 3.6.1.3.9 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 8, 2025, the inspectors presented the integrated inspection results to John VanFleet, Site Vice President, and other members of the licensee staff.
- On October 25, 2024, the inspectors presented the radiation protection inspection results to John VanFleet, Site Vice President, and other members of the licensee staff.
- On December 16, 2024, the inspectors presented the EAL, and emergency plan change inspection results to Ronald Vanderhyden Jr., Emergency Preparedness Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OP-AA-108-111-
1001
Severe Weather and Natural Disaster Guidelines
Procedures
Severe Weather Preparation and Response
M-101, Sheet 1
P&ID Reactor Core Isolation Coolant (R.C.I.C)
BH
M-101, Sheet 2
P & ID Reactor Core Isolation Coolant System (R.C.I.C)
AT
Drawings
M-99
P & ID Standby Liquid Control System
LOP-SC-02
Standby Operation of the Standby Liquid Control System
LOS-DG-M2
2A EDG Operability Test
111
LOS-RI-Q
LOS-RI-R4
RCIC System Startup and Valve IST
111
Procedures
LOS-SC-Q1
SBLC Pump Operability/Inservice Test and Explosive Valve
Continuity Check
Fire Plans
FZ 2H4
Pre-fire plan FZ 2H4 694-6 Elevation, Unit 1 RCIC and
Low-pressure Core Spray Pump Cubicle
Engineering
Changes
Evaluation of 2A RHR Heat Exchanger Thermal
Performance Data Using Alternate EPRI Methodology
01/06/2023
Engineering
Changes
Evaluation of 2A RHR Heat Exchanger Thermal
Performance Data Using Alternate EPRI Method
03/23/2021
3E12-B001A RHR HX Heat XFER Test per LTS-200-17
01/07/2019
LRA 2E12-B001A RHR HX XFER Test per LTS-200-17
01/04/2023
Work Orders
LRA 2E12-B001A RHR HX XFER Test per LTS-200-17
01/04/2023
Miscellaneous
LaSalle Training
Plan Cold
Weather Preps
Simulator Based Cold Weather Scenarios 1-3
2A RWCU Pump Failed to Start
03/03/2023
Received MCR Alarm 2H13-P602 A306 RT Outlet Cond
08/25/2023
LOS RI-Q5 Attachment 2A Completed with Portions UNSAT
09/22/2023
2A RWCU Pump Auto-Tripped
05/21/2024
U2 RX Water Recirculation Loop B Flow Issues at 2PL14J
05/28/2024
Unit 2 RCIC Pump Flow Controller Not Working in Manual
05/30/2024
Corrective Action
Documents
RM-U2 LPRM 24-17D Bypassed Due Being Downscale
06/20/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Unit 2 LPRM Inoperability Trend
06/27/2024
Evaluate RM Frequency for 2G33-F033
07/12/2024
2G33-Z001-08A Failed to Cycle During 2A RT f/D Backwash
07/13/2024
Unit 2 RCIC Identified Issues, Troubleshooting Results
10/18/2024
Miscellaneous
169788
Quality Receipt Inspection Package of Ball Bearings
01/24/2012
Maintenance Rule Implementation Per NEI 18-10
Procedures
Maintenance Rule - (a)(1) and (a)(2) Requirements
MMD Rebuild the HPCS Water Leg Pump
08/20/2016
Work Orders
MM Repair/Replace the 2E12-C003 Water Leg Pump
11/14/2024
Procedures
On-Line Risk Management
0DG01K-C (0 DG Circ Oil Pump Noise
11/05/2024
A-VC Delayed Compressor Start
10/30/2024
Corrective Action
Documents
High Servo Error on RR Subloop 1A1
2/23/2024
LOP-VC-01
Control Room HVAC Operation
Procedures
OP-LA-102-106
LaSalle Station Operator Response Time Program
3-5 DPS Leak From 1E51-C005 When Running
03/24/2017
B VC Filter Train Inlet Temp Indicator Pegged Upscale High
11/15/2023
1CM022A Failed to Indicate Fully Closed
05/10/2024
1F012 Close Time at Max Acceptable Value
09/25/2024
U2 RCIC Governor Valve Indicating Closed When Throttled
10/17/2024
Unit 2 RCIC Identified Issues, Troubleshooting Results
10/18/2024
Small Steam Leak on the 1E51-F045
11/14/2024
Corrective Action
Documents
Small Steam Leak on the 1E51-F045
11/14/2024
4160V Switchgear 242Y (2AP06E) Diesel Generator 2A
Feed ACB 2423 System DG Part 1
Y
Drawings
M-87, Sheet 3
P&ID Core Standby Cooling System Equipment Cooling
Water System
T
Replace MOC Switch(s) That Have Used Contacts
10/09/2024
U2 RCIC System Biennial Comprehensive IST Pump Test
10/18/2024
OP LOS-DG-SR6 1A DG Flow Balance Test, Div II
10/29/2024
OP LOS-VC-A1 VC EMU Train Att B
11/15/2024
Work Orders
OP PMT After RCIC Governor Valve Inspect/Repair
10/17/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
LRA_LOS-RI-Q5 U1 RCIC Cold-Quick Start Att 1A
11/15/2024
OP LOS-RI-Q6 U2 RCIC Quarterly Att 2A
10/18/2024
LRA OP LOS-DG-M3 U1 HPCS DG Surv Att 1B-Idle
10/22/2024
LRA Flush U1 Div 1 RHR Service Water
11/04/2024
OP PMT New B VE Compressor Operates Properly
11/15/2024
LRA LOS-DG-M3 2B DG Idle Start
11/18/2024
Addendum 1
LaSalle Station On-Shift Staffing Technical Basis
Calculations
LAS Emergency Plan Revised for IPAWS Implementation,
Evaluation No. 23-36
23-36
Procedures
Radiological Emergency Plan Annex for LaSalle Station
Miscellaneous
S-24-6-2
LORT Dynamic Simulator Scenario Guide Winter Readiness
with DEP
LAP-300-45
Ventilation Filter Testing Program
06/21/2017
ATTACHMENT 1
Respiratory Inspection and Certification Log
05/09/2024
Miscellaneous
SRRS ID: 2B.117
RP-LA-826 Pneumatic/Air Systems Quality Surveillance
2nd Quarter 2024
05/01/2024
ER-LA-390
Control Room Envelope Habitability Program
LOS-VC-SR1
Control Room and Auxiliary Electric Equipment Room HVAC
Pressurization Surveillance
LOS-VC-SR2
Control Room Envelope In-Leakage Test Using Tracer Gas
LOS-VC-SR3
Control Room Emergency Make-Up Train HEPA Filter and
Charcoal Filter In-Place Leak Tests
LOS-VC-SR4
VC/VE Recirculation Filter Test
Controlled Negative Pressure (CNP) Fit Testing
Procedures
RP-LA-826
Pneumatic / Air System Quality Surveillance
Work Orders
Control Room Emergency Makeup Train Charcoal Filter
Leak Test
05/07/2021
ED and TLD Data Comparison and Trending
Alpha Scorecard
10/07/2024
EID #E088111
Declaration of Pregnancy
various
Miscellaneous
EID 018931
RP-AA-220 Attachment 2
03/02/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Internal Investigation Form
LAS-24-001
24 Bioassay Program Annual Review at LaSalle Nuclear
Power Station
Personnel
Exposure
Investigation #24-
2
SLR/SRD Discrepancy INPO 05-008
03/19/2024
ATTACHMENT 2
Waste Stream LLD Verification
01/11/2024
Bioassay Program
Procedures
Methods for Estimating Internal Exposure from In-Vivo and
In-Vitro Bioassay Data
0011487876
Ludlum RADEYEPX/NRD Certificate of Calibration
2/21/2023
0011492021
Ludlum Model 3002 Certificate of Calibration
11/01/2023
0011493223
Ludlum Model 3030P Certificate of Calibration
01/31/2024
0011498458
MGP AMP-100 Certificate of Calibration
2/11/2024
0011503964
Eberline RO20 Certificate of Calibration
2/06/2024
0011504144
MGP Telepole WR Certificate of Calibration
2/06/2024
0011532147
Eberline RO20AA
07/08/2024
0011540882
Ludlum Model 3 Certificate of Calibration
05/30/2024
0011565521
Eberline AMS-4 Certificate of Calibration
09/16/2024
CY-LA-130-310
Post Calibration Geometry Check Worksheet
05/02/2024
Air Sampler Calibration Data Sheet
08/12/2024
RADeCO H-810 Calibration Data Sheet
07/28/2024
PM-12 Calibration Data Sheet
08/08/2023
SAM-12 Calibration Data Sheet
2/27/2023
Calibration
Records
ARGOS-5 Calibration Data Sheet
2/19/2023
Corrective Action
Unable to Access ARM for Source Check
11/21/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Unable to Complete Weekly Surveillance of 1PL75J
2/01/2023
RP-LA-716ARM Source Check Completed Past Crit Date
2/27/2024
Documents
OOT Not Completed in Timely Manner
09/24/2024
Corrective Action
Documents
Resulting from
Inspection
NRC Identified Out of Spec Value in IMD Data Table
10/25/2024
Operation of the Whole-Body Counter (WBC) Using
Apex-InVivo
Calibration of Hi-Vol Air Samplers
Operation and Calibration of the PM-12 Gamma Portal
Monitor
Operation and Calibration of the AMP-50/100/200
RP-LA-710
Source Response Testing and Calibration of the General
Atomic ARM (Reboiler Steam Outlet and HRSS Room)
RP-LA-713
Determination of Liquid PRM HI Alarm Setpoints
RP-LA-716
Area Radiation Monitor (A.R.M.) Source Checks
Procedures
RP-LA-720
Station Vent Stack and Standby Gas Treatment Stack Wide
Range Gas Monitor Effluent Release Rate Alarm Setpoints
22 Radiation Instrumentation Self-Assessment
2/27/2022
Exelon Power Labs Self-Assessment
08/11/2022
Self-Assessments
NCS-23-001
Annual Review of Process of Performing Weekly
Performance Source Checks for Portable Radiation Survey
Instruments
03/31/2023
Unit 02 Service Water Effluent Radiation Monitor Calibration
01/03/2023
06/19/2023
Post Acc Div II CNMT Gross Gamma Rad Mon
11/28/2023
Fuel Pool Exhaust Radiation Monitor Calibration
04/25/2024
Work Orders
U2 DW Gross Gamma PPC Point Spurious Alarm
05/08/2024
PPC Point D483 Shows RCIC CY Suction Vlv 1E51-F010
Not Open
10/13/2023
Unexpected Alarm for 2A DG Cooling Water Strainer D/P Hi
10/26/2023
71151
Corrective Action
Documents
U2 D RHR WS Pump Seal Leak When Running
11/16/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MSPI Reporting Review by NRC
11/16/2023
U1 RCIC Governor Valve Indicating Closed When Throttled
2/11/2023
MCR Unexpected Alarms 2PM01J-A109, 2PM01J-A201
250VDC UV
03/04/2024
1E51-F019 Breaker Tripped during RCIC Run
03/09/2024
Unit 2 Div 2 RHRWS Pumps in Alert Range
04/10/2024
NOS ID: Oil Weeping From 1A EDG Cooling Water Pump
08/28/2024
Unknown Cause in Change in the IST Dp for 2C & 2D
RHRWS pps
01/08/2025
Corrective Action
Documents
Resulting from
Inspection
NRC IDed: CSCS MSPI Reporting in May-2024
01/15/2025
Miscellaneous
LS-MSPI-001
LaSalle County Nuclear Generating Station Mitigating
System Performance Index (MSPI) Basis Document
Monthly Data Elements for NRC ROP Indicator -
Occupational Exposure Control Effectiveness
Various
Monthly Data Elements for NRC ROP Indicator - Reactor
Coolant System (RCS) Specific Activity
Various
Monthly Data Elements for NRC ROP
Indicator -RETS/ODCM Radiological Effluent Occurrences
Various
Procedures
Mitigating System Performance Index
Data Acquisition & Reporting
Work Orders
2B RHR WS Biennial Comprehensive IST Pump Test
05/14/2024
1B DG Fuel Line Leak
03/11/2010
NRC Questions on 1B EDG Fuel Line IR 1041521
07/28/2010
Corrective Action
Documents
Diesel Fuel Leak on U1 HPCS DG During 24hr Run
10/21/2024
Engineering
Evaluations
ECR 396464
NRC Questions on 1B EDG Fuel Line IR 1041521
07/25/2011
Miscellaneous
LAS-89656
Evaluation of a Leaking Fuel Oil Line Connection from the
1B EDG at LaSalle Station
04/13/2010
Work Orders
MM Replace EDG Fuel Lines
10/02/2013
05000373,
05000374/2023-
2-01
LaSalle County Station, Units 1 & 2, Supplement to Air
Circuit Breaker (ACB) Mechanically Operated Contacts
(MOC) Switch Failed to Actuate
10/09/2024
ReMA L1C21-
10PST
Reactivity Maneuver Approval (ReMA) Plan L1C21-10PST
for November 2024 Power Suppression Test
11/21/2024
Miscellaneous
ReMA Plan 2025
December Control
Rod Exchange
Reactivity Maneuver Approval (ReMA) Plan L1C21-10PST
for November 2024 Power Suppression Test
1