IR 05000454/2025003
| ML25346A020 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/12/2025 |
| From: | Dariusz Szwarc NRC/RGN-III/DORS/RPB3 |
| To: | Mudrick C Constellation Energy Generation |
| References | |
| IR 2025003 | |
| Download: ML25346A020 (0) | |
Text
SUBJECT:
BYRON STATION - INTEGRATED INSPECTION REPORT 05000454/2025003 AND 05000455/2025003
Dear Christopher H. Mudrick:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Byron Station. On December 10, 2025, the NRC inspectors discussed the results of this inspection with Harris Welt, 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.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance 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.
December 12, 2025 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 Byron Station.
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, Dariusz Szwarc, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket Nos. 05000454 and 05000455 License Nos. NPF-37 and NPF-66
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000454 and 05000455
License Numbers:
Report Numbers:
05000454/2025003 and 05000455/2025003
Enterprise Identifier:
I-2025-003-0057
Licensee:
Constellation Nuclear
Facility:
Byron Station
Location:
Byron, IL
Inspection Dates:
July 01, 2025, to September 30, 2025
Inspectors:
N. Bolling, Resident Inspector
T. Hooker, Health Physicist
M. Learn, Team Leader
T. Ospino, Resident Inspector
C. Padilla, Senior Resident Inspector
Approved By:
Dariusz Szwarc, Chief
Reactor Projects Branch 3
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Byron 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: 71111.1
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power and remained at or near full power throughout the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power and remained at or near full power throughout 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)partial walkdown of the 1A emergency diesel generator (EDG) on July 9, 2025 (2)partial walkdown of the 1A auxiliary feedwater train prior to other train work on July 17, 2025
71111.05 - Fire Protection
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
(1)observation and evaluation of the stations fire brigade during an announced fire drill on July 15, 2025
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)observation of various activities involving on-watch operations crews in the main control room during the week ending September 5, 2025
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)observation of the performance of a complex casualty graded scenario by a crew of licensed plant operators in the facilitys simulator on August 12, 2025
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples 1 Partial)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)
(Partial) maintenance effectiveness review of the 0A essential service water makeup pump (2)review of work practices and challenges generated during the work window associated to the Unit 2B safety injection unplanned maintenance on the week ending July 11, 2025 (3)review of work practices related to the EDG control air system and the maintenance and operability implications for the week ending August 22, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 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)review and evaluation of the risk associated with dry cask storage activities, as documented in various work orders (2)risk assessment of the week of September 2, 2025, due to multiple opposite train planned work
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
(1)evaluation of the operability of 1B EDG starting air system, as documented in various action requests (ARs)
(2)evaluation of the operability of 1A EDG after control air loss, as documented in AR 4884396 (3)evaluation of the operability of 2A main steam isolation valve (MSIV) upon discovery of a non-safety-related gauge installed on the safety-related train, as documented in AR 4889796 (4)evaluation of the functionality of four non-safety-related diaphragms installed on the 2A auxiliary feedwater train which is safety related, as documented in various ARs
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) (4 Samples)
(1)functional and operational testing of the 2B safety injection train test after failed air test of the 2B SI pump cubicle cooler, as documented in Work Order (WO) 5677654 (2)functional and operational testing of 1B EDG following replacement of 1DG5212B turning gear interlock valve, as documented in WO 5681243 (3)functional and operational testing of DC 211 battery following cell replacement, as documented in WO 5678488 (4)functional and operational testing of 0A SX makeup pump following fuel line repairs, as documented in WO 5535776
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) BOP IC-3, Moveable Incore Detectors Flux Mapping Procedure, on July 23, 2025 (2)2BOSR 7.5.4-2, Unit Two Diesel Driven Auxiliary Feedwater Pump Monthly Surveillance, on August 5, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)1BOSR 5.5.8.CS.5-2c, Unit One Comprehensive Inservice Testing (IST) Requirements for Containment Spray Pump 1CS01PB, as documented in WO 5647834
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
(1)emergency preparedness drill on July 24, 2025
Additional Drill and/or Training Evolution
The inspectors evaluated:
(1)emergency preparedness drill before evaluated NRC drill on September 17,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (1 Sample)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 2, essential service water process monitor, 2PR03J
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)auxiliary building ventilation system, including Unit 1 auxiliary building ventilation effluent monitor (1RE-PR028) and the Unit 2 auxiliary building vent effluent monitor (2RE-PR028)
(2)liquid effluent discharge system, including the effluent release tanks, and radwaste release tank monitor (0RE-PR01J)
(3)gaseous radwaste system, including gaseous decay tanks, sampling station, and radiological waste control room
Sampling and Analysis (IP Section 03.02) (3 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
(1)gaseous effluents released from the Unit 2 auxiliary building vents (2)liquid effluents released from the liquid effluent discharge system (3)gaseous effluents released from the gaseous decay tanks
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
(1)permit number L-20250507-465-B; Liquid Release Tank 0WX01T; May 5, 2025 (2)permit number G-20250331-2224-B; Unit 2 Containment Purge; April 14, 2025
Abnormal Discharges (IP Section 03.04) (1 Sample)
The inspectors evaluated the following abnormal discharges:
- (1) 2023 gaseous abnormal release
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:
MS08: Heat Removal Systems (IP Section 02.07)===
- (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)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
- (2) Unit 2 (July 1, 2024, through June 30, 2025)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 (February 1, 2024, through August 31, 2025)
- (2) Unit 2 (February 1, 2024, through August 31, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) May 1, 2024, through August 31, 2025 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) April 1, 2024, through August 31, 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) The inspectors reviewed the implementation and tracking of the essential service water fouling monitoring program (BVP 800-30) and extent-of-condition exams.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
(1)non-safety-related equipment installed as safety-related parts on safety-related trains
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.15 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: 10 CFR 50, Appendix B, Criterion VIII, Identification and Control of Materials, Parts, and Components, requires, in part, that identification and control measures shall be designed to prevent the use of incorrect or defective material, parts, and components.
Contrary to above, the licensee failed to establish measures for the identification and control of materials, parts, and components. Specifically, the licensee failed to ensure Procurement Classification 1 (QL-1), Safety Related, components were selected for replacement in safety-related components, as required by step 4.1 of site procedure SM-AA-300-1002, Revision 11, Bill of Material Development and Right Parts Selection for Maintenance, when a non-safety-related (NSR) gauge and four NSR diaphragms were installed in safety-related systems and constitutes a performance deficiency. The NSR gauge was installed on the pressure sensing line of the 2A main steam isolation valve accumulator on April 27, 2021, discovered on August 12, 2025, and replaced on September 5, 2025. The four NSR diaphragms were installed in the 2AF005A through 2AF005D auxiliary feedwater flow control valves on April 18, 2025, discovered on August 27, 2025, and replaced on October 29, 2025.
Significance/Severity: Green. The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined the finding was of very low safety significance (Green)because they answered Yes to question 1 in Exhibit 2, Mitigating Systems Screening Questions.
Corrective Action References:
AR 4889796, NSR Pressure Gauge Installed in SR Application AR 4893579, NSR Diaphragm Installed in 2AF005A AR 4893583, NSR Diaphragm Installed in 2AF005B AR 4893585, NRS Diaphragm Installed in 2AF005C AR 4893586, NSR Diaphragm Installed in 2AF005D Observation: Non-Safety-Related Equipment Installed as Safety-Related Parts on Safety-Related Trains 71152S The inspectors conducted a review of plant issues, with a focus on entries in the licensees corrective action program over recent months. This review identified a potential negative trend involving the installation of non-safety-related (NSR) components in safety-related (SR)applications.
1. NSR Pressure Gauge Installed in SR Application (AR 4889796)
A non-safety-related, Quality Level 4, pressure gauge (Part 2PI-MS251A) was installed on the safety-related 2A main steam isolation valve (MSIV) train under Work Order (WO)4569070 on April 27, 2021. This gauge, which serves as the accumulator tank pressure indicator, remained in place for over 4 years without detection when the error was discovered on August 12, 2025. Although a past operability determination was performed, which determined there was no reason to suspect the pressure boundary would fail during a design basis event, the gauge was isolated immediately and subsequently replaced with a safety-related pressure gauge on September 5, 2025.
2. NSR Diaphragms Installed in SR Auxiliary Feedwater Flow Control Valves
(ARs 4893585, 493583, 493585, 493586)
During the most recent Unit 2 outage, four NSR, Quality Level 4 diaphragms, were installed in place of SR, qualified diaphragms in the 2A auxiliary feedwater system flow control valves (2AF005A-D), under WOs 5411043, 5411042, 5411041, and 5411040, respectively.
The installation followed procedure MA-BY-MM-4-AF005, Revision 7, 1/2AF005A Through H Valve Repair. This issue was identified not through routine checks but as a result of a question raised by Braidwood Nuclear Plant regarding preventive maintenance frequency.
A functionality evaluation (EC 645425) was conducted, which noted that the NSR diaphragms had undergone a parts quality initiative (PQI) inspection prior to use. Although no operability concerns were identified, the licensee replaced the diaphragms with Quality Level 1 components on October 29, 2025.
In both cases, the licensee failed to meet the requirements of SM-AA-300-1002, Revision 11, Bill of Material Development and Right Parts Selection for Maintenance. Step 4.1.4 states, in part, Only Safety Related item/components (Cat ID Quality Level 1 or 2) are permissible for use, in Configuration Level 1 (Safety-Related Equipment). These oversights represent lapses in human performance which could have led to more significant consequences.
Upon discovery, the licensee did perform extent-of-condition searches and took action to replace the affected parts. The licensee also expanded the scope by including evaluation of ARs generated as a result of a potential for incorrect parts to be installed in generation of a Trend IR, AR 4901934, in order to evaluate their parts selection process performance.
The licensee identified opportunities to improve training and the parts selections. However, it is also important to stress the importance of acquiring parts that meet the design and manufacturing requirements under a quality assurance program complying with 10 CFR 50, Appendix B and their role in ensuring the continued reliability of structures, systems, and components important to the safe shutdown of the plant.
The screening and significance determinations for the installation of these NSR components are discussed in the licensee-identified non-cited violation attached to this report.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On December 10, 2025, the inspectors presented the integrated inspection results to Harris Welt, Site Vice President, and other members of the licensee staff.
- On September 11, 2025, the inspectors presented the radiation protection inspection results to Harris Welt, Site Vice President, and other members of the licensee staff.
- On September 30, 2025, the inspectors presented the radiation protection inspection results to Jason Reed, Manager of RP Programs, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
NRC ID DG M/E Lineups Need to be Revised
07/09/2025
BOP AF-E1A
Auxiliary Feedwater Train A Electrical Lineup
BOP AF-M1A
Auxiliary Feedwater System Train 'A' Valve Lineup
BOP DG-E1A
Diesel Generator Train A Electrical Lineup
Procedures
BOP DG-M1A
Train A Diesel Generator System Valve Lineup
Miscellaneous
Fire Drill Scenario
- 25-03
Barrel Storage Building
07/15/2025
HU-AA-1211-F-
Pre-Job Briefing Checklist
Roles and Responsibilities of On-Shift Personal
OP-AA-101-111-
1001
Operation Standards and Expectations
Procedures
Conduct of Simulator Training and Evaluation
05/25/2025
2VA04SB Welds Repairs Required
07/08/2025
Delay to LCO Window Due to Additional Welds Needed
07/08/2025
2B SI Lower Cooler Failed Pressure Test During
Maintenance
07/10/2025
Active SX Leak from 2VA04SB Lower Cooler
07/10/2025
Need Contingency Weld Package for Future SI Cooler Work
07/10/2025
Foreign Material Causes Loss of Control Air - 1A EDG
07/17/2025
1A DG Output Breaker Opened during Monthly Surveillance
07/22/2025
1A DG Inoperability Due to Control Air Loss
07/22/2025
1PI-DG124 Reading Low Turbo Lube Oil Pressure
07/22/2025
1A DG Non-Essential Control Air Reg Failure
07/25/2025
Corrective Action
Documents
AR 1A DG Starting Air Systems Have Crosstalk
08/05/2025
Drawings
M-152, Sheet 15
MFRs Supplement Diagram of Diesel Generator Control
Diagram Shutdown System
2/05/1998
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M-152, Sheet 20
Control Diagram Starting System and Alarms
2/06/2013
Failure Analysis
Failure Analysis of Valve, Check, Body Material Aluminum,
Size 1/4 X 1
07/17/2023
Miscellaneous
Maintenance Plan
(Excel file)
2B Safety Injection (2SI01PB) 48hrs of 7d LCO
Work Orders
1A DG Output Breaker Opened During Monthly Surveillance
07/23/2025
Miscellaneous
Major Activities
for Week
Week: 2536BA A-Train
09/02/2025
BFP FH-69
Hi-Trac Movement Within the Fuel Building
Procedures
Spent Fuel Loading Campaign Management
Work Orders
25 Dry Cask Storage Campaign
1B DG Starting Air Receiver Pressure did not Change
on Start
11/07/2025
1B DG Starting Air Receiver Pressure Uneven Change
on Start
03/07/2025
1B DG Starting Air Receiver Pressure Uneven Change
on Start
05/07/2021
1B DG Starting Receiver Degraded Trend
06/11/2025
1B DG Starting Air Receiver Pressure Uneven SAT Outage
03/09/2025
1A DG Output Breaker Opened during Monthly Surveillance
07/22/2025
1A DG Inoperability Due to Control Air Loss
07/22/2025
1PI-DG124 Reading Low Turbo Lube Oil Pressure
07/22/2025
NSR Pressure Gauge Installed in SR Application
08/12/2025
NSR Diaphragm Installed in 2AF005A
08/27/2025
NSR Diaphragm Installed in 2AF005B
08/27/2025
NSR Diaphragm Installed in 2AF005C
2/27/2025
Corrective Action
Documents
NSR Diaphragm Installed in 2AF005D
08/27/2025
M-152, Sheet
Number 15
MFRs Supplement Diagram of Diesel Generator Control
Diagram Shutdown System
2/05/1998
Drawings
M-152, Sheet
Number 20
Control Diagram Starting Systems and Alarms
2/06/2013
Engineering
Changes
Replace MSIV N2 Pressure Gauge with Safety Related
04/05/2005
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2AF005A-D Functionality Evaluation for NSR Actuator
09/04/2025
CES SO-0351
MO-7176
Report of Witness Tests of KSV-20-T Engine-Generator Set
11/30/1979
CES-0420-100
Report of Witness Tests KSV-20T Engine-Generator Set
09/20/1984
Logs
Byron Logs 22-23 July
07/22/2025
Miscellaneous
09/17/2025
EWP IM Perform Calibration of 2PI-MS251A
04/27/2021
Rebuild Actuator/Replace Elastomers 2AF005D
04/18/2025
Rebuild Actuator/Replace Elastomers 2AF005B
04/18/2025
Rebuild Actuator/Replace Elastomers 2AF005C
04/18/2025
Work Orders
Rebuild Actuator/Replace Elastomers 2AF005A
04/18/2025
EC 398675 (EDG Frequency and Voltage Variation)
08/09/2019
Post-B2R25 Incore Blocked Thimbles
05/07/2025
2B AF PP is Leaking a Decent Amount of Exhaust to the
Room
06/12/2025
2B SI Lower Cooler Failed Pressure Test During
Maintenance
07/10/2025
Minor Active Leak on Lower Cooler of 2VA04SB
07/11/2025
Corrective Action
Documents
Incore Blocked Thimble #15
07/23/2025
0BOSR 7.9.6-1
Essential Service Water Makeup Pump 0A Monthly
Operability Surveillance
1BOSR
5.5.8.CS.5-2c
Unit One Comprehensive Inservice Testing (IST)
Requirements for Containment Spray Pump 1CS01PB
2BOSR
5.5.8.SI.5-2A
Unit Two Group A Inservice Testing (IST) Requirements for
Safety Injection Pump 2SI01PB
2BOSR 7.5.4-2
Unit Two Auxiliary Feedwater Pump Monthly Surveillance
Procedures
BOP IC-3
Moveable Incore Detectors Flux Mapping Procedure
Essential Service Water Makeup Pump Support 0BVSR
Z.7.A.6-1
09/23/2025
OPS Perform 1BOSR 5.5.8.CS.5-2C 1B CS Pump
Comprehensive
07/17/2025
Work Orders
(NEIL)-2SI01PB Group A IST Requirements for Safety
07/11/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Injection Pump
DC 211 Battery Voltage Low (Cell 44)
09/12/2025
1B DG Staring Air Receiver Pressure Uneven Change on
Start
09/12/2025
(NEIL) - 2B Diesel Driven AF Pump Monthly Surveillance
08/05/2025
Byron 2025
Integrated Drill
Byron 2025 Integrated Drill Binder #3
07/24/2025
Miscellaneous
Byron 2025 Pre-
Exercise
Byron 2025 Pre-exercise Binder #31
09/17/2025
Miscellaneous
2PR03J Calibration Source Tracking
09/30/2025
22 Annual Radioactive Effluent Release Report
04/27/2023
24 Annual Radioactive Effluent Release Report
04/28/2025
Software Quality Assurance for OpenEMS Byron Nuclear
Power Plant
23 Annual Radioactive Effluent Release Report
04/25/2024
21 Annual Radioactive Effluent Release Report
04/02/2022
L-20250507-465-
B
Liquid Permit Release Information
05/07/2025
2C.111
Gaseous Pre-Release Permit Report, Gaseous Release
Permit Report, RP-BY-90-0-0H3 Bubbler, Supporting
Documentation and BCP 400-TCNMT/Continuous
03/31/2025
CY-BY-110-600-1
Chemistry Sample Points - Turbine Building
G-20250822-
29-B
Gas Permit Release Information
08/22/2025
L-20250505-463-
B
Liquid Permit Release Information
05/05/2025
Miscellaneous
L-20250822-488-
B
Liquid Permit Release Information
08/22/2025
Radioactive Effluent and Monitoring Programs
Potentially Contaminated Systems Controls Program
Determination of Carbon-14 in Gaseous Effluents
CY-BY-170-301
Offsite Dose Calculation Manual for Byron Station Units 1
and 2
Procedures
Y-AA-170-1100
Quality Assurance for Radiological Monitoring Programs
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Self-Assessments 04893178
25 RETS/REMP 71124.06 & 71124.07
09/05/2025
Calibration
Records
CY-BY-130-8000
CY-BY-130-8001 Attachment 3 Compositor Performance
Check Sheet, CY-BY-130-8000 Attachment 2
NPDES/Compositor Performance Check Sheet 06/4/2025 -
6/07/2025
06/11/2025
NOS ID: Correct ODCM for Two Offsite Dosimeters
04/07/2023
No Flow into CWBD Steel Pot for ODCM Sampling
09/29/2023
Third Party Lab Issues with RETS/REMP Reports
07/17/2025
Corrective Action
Documents
CGS Vendor Labs Unable to Meet Ni-63 Specs. on Byron
Fish
07/29/2025
BYRON 2023-
22
22 Annual Radiological Environmental Operating Report
(AREOR)
05/04/2023
BYRON 2024-
28
23 Annual Radiological Environmental Operating Report
(AREOR)
05/09/2024
Miscellaneous
BYRON 2025-
29
24 Annual Radiological Environmental Operating Report
(AREOR)
05/12/2025
0BCSR 12.A.1-7
Radiological Environmental Monitoring, Milk Ingestion -
Monthly
0BCSR 12.B.1-1
Radiological Environmental Monitoring, Land Use Census -
Annual
Radiological Environmental Monitoring Program
CY-BY-170-301
Offsite Dose Calculation Manual for Byron Station Units 1
and 2
CY-BY-408-416-
Radiological Groundwater Protection Program Sampling
Response to Inadvertent Releases of Licensed Materials to
Groundwater, Surface Water, Soil or Engineered Structures
Radiological Groundwater Protection Program
Radiological Groundwater Protection Program
Implementation
Procedures
EN-BY-408-4160
RGPP Reference Material for Byron Generating Station
71151
Miscellaneous
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for Cooling Water
Systems
07/01/2024-
06/30/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for Residual Heat
Removal Systems
07/01/2024-
06/30/2025
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for Heat Removal
Systems
07/01/2024-
06/30/2025
Monthly Data Elements for NRC ROP Indicator -
Occupational Exposure Control Effectiveness
various
Monthly Data Elements for NRC ROP Indicator -
RETS/ODCM Radiological Effluent Occurrences
various
Corrective Action
Documents
0SX98AB - B2R23 UT Inspection Results
04/27/2022
Corrective Action
Documents
Resulting from
Inspection
NRC ID: NRC Document Request Not Provided in a Timely
Manner
07/15/2025
Engineering
Evaluations
B2R23 Minimum Wall Thickness Evaluation for Raw Water
Program
BVP 800-30
Essential Service Water Fouling Monitoring Program
(GL 89-13 Program Basis Document)
Procedures
ER-AA-5400-
1001
Raw Water Piping Integrity Management Guide
NSR Pressure Gauge Installed in SR Application
08/12/2025
NSR Diaphragm Installed in 2AF005A
08/27/2025
NSR Diaphragm Installed in 2AF005B
08/27/2025
NSR Diaphragm Installed in 2AF005C
08/27/2025
NSR Diaphragm Installed in 2AF005D
08/27/2025
Corrective Action
Documents
Trend IR: Cases Where the Wrong Parts Were Installed
09/30/2025
Engineering
Changes
2AF005A-D Functionality Evaluation for NSR Actuator
09/05/2025