IR 05000461/2025003
| ML25356A361 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/29/2025 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Mudrick C Constellation Energy Generation |
| References | |
| IR 2025001, IR 2025003 | |
| Download: ML25356A361 (0) | |
Text
SUBJECT:
CLINTON POWER STATION - INTEGRATED INSPECTION REPORT 05000461/2025003; AND 07201046/2025001
Dear Christopher H. Mudrick:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Clinton Power Station. On November 18, 2025, the NRC inspectors discussed the results of this inspection with A. Sterio, Acting 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, third 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, fourth quarter integrated inspection reports, which will be issued 45 days after the fourth quarter ends on December 31, 2025.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. 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 Clinton Power Station.
December 29, 2025 If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Clinton Power 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, Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety Docket Nos. 05000461 and 07201046 License No. NPF-62 Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Ruiz, Robert on 12/29/25
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Clinton Power 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
High Suppression Pool Water Level due to Incorrect Installation of Fuel Pool Cooling and Cleanup Valve Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000461/2025003-01 Open/Closed
[H.11] -
Challenge the Unknown 71152A A Green Finding and associated non-cited violation (NCV) of Technical Specifications Section 5.4, Procedures, was self-revealed when the site entered emergency operating procedure (EOP)-6, Primary Containment Control, due to high suppression pool water level.
Specifically, the licensee did not follow the instructions of the work order and installed the fuel pool cooling and clean up valve 1FC034B actuator incorrectly. This resulted in an unexpected transfer of water from the fuel pool cooling and cleanup surge tanks to the suppression pool, raising suppression pool water level above the Technical Specification Suppression Pool Water Level limit.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at or near 100 percent power. On July 12, 2025, power was lowered to 75 percent power to perform a routine rod pattern adjustment and surveillances.
Power was then raised to 100 percent on July 13, 2025. On July 17, 2025, power was lowered to 92 percent to perform a routine rod pattern adjustment. Power was raised to 100 percent on July18, 2025. On September 8, 2025, the unit was shut down for a planned refueling outage, C1R22, and remained shut down until the end of the inspection period on September 30, 2025.
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)generator stator water cooling system on July 8, 2025 (2)division III starting air and lubricating oil systems on July 10, 2025 Complete Walkdown Sample (IP Section 03.02) (1 Partial)
(1)
(Partial)
The inspectors evaluated system configurations during a complete walkdown of the reactor core isolation cooling (RCIC) system beginning on September 20, 2025.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)fire area CB-1e; 737' diesel generator building Unit 2 storage area on July 9, 2025 (2)fire area F-1; 737' fuel building grade level on August 4, 2025 (3)fire area A-1 (b,d,e); auxiliary building 737' cable supports on September 5, 2025
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill at the diesel generator building unit 2 storage area sling storage room on July 9, 2025.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding and mitigation protections in the control building and diesel generator buildings.
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01) (1 Sample)
The inspectors evaluated boiling water reactor non-destructive testing and previously completed welds by reviewing the following items from September 8-12, 2025:
(1)
1. Visual Examination (VT-3) of residual heat remover rigid support 1RH09021R
2. Volumetric UT on residual heat remover piping weld 1-RH-37-4-4
3. ASME Code Class 2 weld review for suppression pool minimum flow bypass
valve 1E22F012 replacement on work order 4784365
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during a planned downpower to 75 percent to perform end of cycle rod adjustments on July 12, 2025.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during a planned downpower to 50 percent in preparation for the refueling outage on September 7, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification simulator training on July 29, 2025.
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)
'0' service air compressor, 0SA01C rebuild and replacement per work order (WO) 04877693 on July 22, 2025 (2)division I shutdown service water (SX) system completed on September 6, 2025 (3)division II residual heat removal (RH) system completed on September 8, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples 2 Partials)
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) The inspectors evaluated the thoroughness of work completion, work management, and risk associated to the anticipated transient without scram (ATWS) reactor pressure B21-N401A channel functional per WO 5529102 on July 9, 2025.
- (2) The inspectors evaluated the thoroughness of work completion, work management, and risk associated to the '0' service air compressor (0SA01C) risk screening and mitigation plan for clearance order CO 01-SA-0SA01C-005 on July 16, 2025.
(3)
(Partial)
The inspectors evaluated the thoroughness of work completion, work management, and risk associated to the containment fire protection header containment isolation valves (1FP050 and 1FP092) leakage repair and testing under WO 05725664 beginning on September 12, 2025.
(4)
(Partial)
The inspectors evaluated the thoroughness of work completion, work management, and risk associated to the reactor water cleanup (RT) drain line containment isolation valve to radwaste (1WX020) repair under WO 05615967 beginning on September 13, 2025.
- (5) The inspectors evaluated the thoroughness of work completion, work management, and risk associated to the reactor core isolation cooling exhaust vacuum breaker valve (1E51F077) local leak rate testing limits evaluation completed on September 28, 2025.
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)fission product monitor gaseous channel failed upscale and declared inoperable as documented per Action Request (AR) 04881076 on July 15, 2025 (2)division I battery modified performance test per 9382.16 as documented per AR 04881403 and division III modified performance test per 9382.18 as documented per AR 04881566 on July 16, 2025 (3)degradation of 1SX14AA 3-inch line shutdown service water supply to standby gas treatment charcoal bed deluge as documented per AR 4883319 on July 24, 2025 (4)fuel building inner truck bay door seal damaged when new fuel trailer contacted it as documented per AR 4887474 on July 31, 2025
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1)temporary modification sample reviewing the implementation of aquadams in the control building and radwaste building for water inventory control measures completed on September 27, 2025
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial) The inspectors evaluated refueling outage 1CR22 activities beginning on September 8, 2025.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (1 Sample)
(1)fission product monitor gaseous channel, 1E31-K612 testing following replacement of high voltage power supply per WO 05693259 on July 21, 2025 Surveillance Testing (IP Section 03.01) (3 Samples 1 Partial)
(1)main control room tracer gas test on control room ventilation trains A and B per 9070.06 per WO 5322081 on July 8, 2025 (2)diesel generator 1A monthly operability run per 9080.01 and WO 05689013 on July 10, 2025 (3)diesel driven fire pump A (0FP01PA) functionality test per 9071.01A, following replacement of the batteries per WO 05378323-03 on July 14, 2025 (4)
(Partial)division I diesel generator integrated testing under WO 05449881 beginning on September 25, 2025 Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Partial)
(1)
(Partial)main steam line containment isolation local leak rate testing beginning on September 12, 2025, under WO 5161467
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels, identifies the concentrations and quantities of radioactive materials, and assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)licensee surveys of workers and potentially contaminated material leaving the radiologically controlled area (RCA) at the main access point during a refueling outage (2)licensee surveys of workers and potentially contaminated material leaving the RCA at the service building access point during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensees control of radiological hazards for the following radiological work:
(1)control rod drive exchange (2)drytube replacement (3)drywell and non-drywell local leak rate testing
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
(1)drywell equipment hatch (2)fuel building equipment drain tank room Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.03 - 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)standby gas treatment system (SGTS)
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) 737' turbine building 4A heater bay - high efficiency particulate air (HEPA) system
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
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) dose assessment for intake (inhalation) from work in the drywell on February 1, 2023
Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situations:
- (1) declared pregnant worker dose assessment performed in 2024
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 Sample)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
- (1) Unit 1 (July 25, 2024, through June 30, 2025)
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) Unit 1 (October 1, 2024, through June 30, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
(July 11, 2024, through June 30, 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)
(July 11, 2024, through June 30, 2025)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)
(Partial)reactor core isolation cooling turbine trip valve, overthrust event, and low pressure suction trip review beginning on September 20, 2025 (2)inadvertent filling of suppression pool and EOP-6 entry due to the fuel pool cooling and cleanup valve isolation valve (1FC034B) actuator installation completed on September 29, 2025
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 Sample)
- (1) The inspectors evaluated the licensees activities related to long-term operation and monitoring of their independent spent fuel storage installation (ISFSI). The inspectors were onsite on July 29 and July 30, 2025. During the onsite walkdown, the inspector toured the ISFSI and evaluated the material and radiological conditions of the ISFSI pad and storage system. The inspectors verified that radiological conditions on the ISFSI pad were as expected during the walkdown.
Since the last inspection, the inspectors evaluated corrective action documents and changes performed in accordance with 10 CFR 72.48, Changes, Tests, and Experiments. The inspectors also reviewed procedures and interviewed operations staff regarding daily checks on the loaded casks.
INSPECTION RESULTS
High Suppression Pool Water Level due to Incorrect Installation of Fuel Pool Cooling and Cleanup Valve Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000461/2025003-01 Open/Closed
[H.11] -
Challenge the Unknown 71152A A Green Finding and associated non-cited violation (NCV) of Technical Specifications Section 5.4, Procedures, was self-revealed when the site entered emergency operating procedure (EOP)-6, Primary Containment Control, due to high suppression pool water level.
Specifically, the licensee did not follow the instructions of the work order and installed the fuel pool cooling and clean up valve 1FC034B actuator incorrectly. This resulted in an unexpected transfer of water from the fuel pool cooling and cleanup surge tanks to the suppression pool, raising suppression pool water level above the Technical Specification Suppression Pool Water Level limit.
Description:
On August 20, 2025, as part of planned maintenance on the fuel pool cooling and cleanup demineralizer system, the licensee replaced valve 1FC034B. On August 21, 2025, while performing procedure 3317.01 Section 8.1.1.10 to place the fuel pool cooling and cleanup demineralizer system back into service, a high suppression pool water level alarm was received by the main control room (MCR). As a result of the high suppression water level, the licensee entered EOP-6, Primary Containment Control, and a technical specification 2-hour shutdown Limiting Condition for Operation (LCO). Operators in the MCR responded promptly and restored level to the normal band. The condition lasted 14 minutes. Subsequently, the licensee conducted an investigation which revealed the actuator/valve handle on the 1FC034B was incorrectly installed leading to the valve inadvertently being left open when the valve handle was placed in the closed position.
The NRC became aware of the EOP-6 entry on August 21, 2025, and became aware of the incorrect valve installation on September 4, 2025, after troubleshooting was completed by the site. The licensee documented the issue in their corrective action program as IR 04892300.
Work Order (WO) 05713260-01 Step 5 required the replacement valve to be installed, in the same direction of flow and position as the original valve. The incorrect installation of the valve which resulted in the valve being left in an open position, created a flow path from the fuel pool cooling demineralizer system to the suppression pool when restoring, venting, and filling the fuel pool cooling and cleanup demineralizer system. This flow path allowed for the unexpected rise of approximately 2 inches in suppression pool water level with a maximum level slightly above 19 ft and 5 inches, the suppression pool Technical Specification Limit.
Corrective Actions: In response to the high suppression pool water level entry, the site conducted troubleshooting, determined the cause of high suppression pool water level to be the incorrect installation of the 1FC034B, installed the valve actuator in the correct position, and performed a work group evaluation (WGE) to further learnings.
Corrective Action References: IR 04895391 and IR 04892300
Performance Assessment:
Performance Deficiency: The licensees failure to follow WO 5713260-01 Step 5 which required the newly replaced 1FC034B to be installed in the same direction of flow and position as the original valve was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more-than-minor because it was associated with the Configuration Control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the suppression pool exceeded technical specification high suppression pool water level limit due to the incorrect installation and lineup of the 1FC034B that could have potentially challenged initial conditions of the sites safety analysis in Mode 1, adversely impacted the sites suppression pool high level design limit, and required entry into a 2-hour shutdown LCO action statement. Example 5.b in IMC 0612 Appendix E Example of Minor Issues supports the more-than-minor determination.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
Specifically, all the questions in IMC 0609 Appendix A, The Significance Determination Process (SDP) For Findings At-Power, Exhibit 2, Mitigating Systems Screening Questions, and Exhibit 3, Barrier Integrity Screening Questions, were answered No which screened the degraded condition to Green, very low safety significance.
Cross-Cutting Aspect: H.11 - Challenge the Unknown: Individuals stop when faced with uncertain conditions. Risks are evaluated and managed before proceeding. Specifically, the site did not challenge or verify assumptions regarding the valve position/alignment and the subsequent potential risk of impacting suppression pool water level due to the valve replacement.
Enforcement:
Violation: Technical Specifications Section 5.4.1 requires that, in part, Written procedures shall be established, implemented, and maintained covering the following activities: a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978.
Regulatory Guide 1.33, Revision 2, Appendix A, February 1978 Section 9a, Procedures for Performing Maintenance requires that, in part, maintenance that can affect the performance of safety related equipment should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.
The licensee established work order (WO) 5713260-01 to install valve 1FC034B. Step 5 stated install the 1FC034B valve, into the system in the same direction of flow and position as the original valve.
Contrary to the above on August 20, 2025, the licensee failed to implement Step 5 of WO 5713260-01. Specifically, the licensee failed to install 1FC034B in same position as the original valve in, leading to the unexpected high suppression water level and entry into EOP-6.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 4, 2025, the inspectors presented the ISFSI program review inspection results to N. Plumey, Site Vice President, and other members of the licensee staff.
- On September 12, 2025, the inspectors presented the inservice inspection results to N. Plumey, Site Vice President, and other members of the licensee staff.
- On September 19, 2025, the inspectors presented the radiation protection inspection results to N. Plumey, Site Vice President, and other members of the licensee staff.
- On November 18, 2025, the inspectors presented the integrated inspection results to A. Sterio, Acting Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04706295
ISFSI -HI-STORM Efflorescence
10/01/2023
04720546
DCS - 2023 4th Quarter Inspection
11/30/2023
04794066
DCS - 2024 Annual Inspection
08/15/2024
04874667
NDE not Conducted FB Crane Hook for 3 Years
06/19/2025
04876405
NOS ID: ISFSI Haul Path with Edge or Joint Degradation
06/26/2025
04876406
NOS ID: Gaps Found on the Lower Screens of HI-Storms
06/26/2025
Corrective Action
Documents
04876967
Steel Plate on ISFSI Haul Path Need Evaluation
06/27/2025
Corrective Action
Documents
Resulting from
Inspection
04887392
NRC ID HI-STORM 100-0108 Gap in Upper Vent Greater
than 1/4"
07/31/2025
2.48-CL-2024-S-
001
Dry Cask Storage/ISFSI Inspection Surveillance Program
NOSA-CPS-25-
Independent Spent Fuel Storage Installation Audit Report
07/15/2025
Miscellaneous
Att 1
General Dry Cask Storage Walkdown
Constellation 72.48 Review Process
Procedures
Dry Cask Storage/ ISFSI Inspection Surveillance Program
22-179100
Misc-ISFSI Pad
2/02/2022
22-179110
ISFSI Pad Radiation Survey Locations
10/13/2022
22-179782
Misc-ISFSI Pad Radiation Survey Locations
10/20/2022
23-196777
ISFSI Pad-PA Fence (Routine)
06/25/2023
24-19986
ISFSI Pad-Grid (Routine)
06/28/2024
Radiation
Surveys
25-240468
ISFSI Pad (Routine)
05/04/2025
Self-Assessments 04831309
Clinton ISFSI Pre-NRC Inspection Readiness Assessment
07/28/2025
297107
ISFSI-DCS Eng Performance Annual Inspection of ISFSI
08/30/2023
60855
Work Orders
05406171
ISFSI-DCS Eng Performance Annual Inspection of ISFSI
08/20/2024
Corrective Action
Documents
04899521
1E51C002E RCIC Turb Trip As Found Wiring Incorrect
09/21/2025
Corrective Action
04879779
NRC Question on Stator Leakage Monitoring System
07/08/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
(SLMS)
M05 1079-
001/002
P&ID Reactor Core Isolation Cooling (RCIC)(RI)
AJ
M05-10077-001
P&ID Standby Liquid Control (SLC)
Drawings
M05-9035 sheet 3
P&ID - Div III Diesel Generator Lube Oil EMD 16-645-
E4/2200KW 1DG01KC
H
3110.01
Generator Stator Cooling (GC)
3110.01E001
Generator Stator Cooling Electrical Lineup
7a
3110.01V001
Generator Stator Cooling Valve Lineup
11d
3506.01
Diesel Generator and Support Systems (DG)
3506.01E001
Diesel Generator and Support Systems Electrical Lineup
18d
3506.01P006
Placing Division 3 Diesel Generator 1C in Standby
Procedures
3506.01V001
Diesel Generator and Support Systems Valve Lineup
13A
1893.04M110
737 Auxiliary General Access Area Prefire Plan
6b
1893.04M410
737' Fuel Building Grade Level
4c
Fire Plans
1893.04M513
737' Diesel Generator Building Unit 2 Storage Area
6a
25-17
Fire Drill Scenario 737' DG Rigging/Sling Room Fire
06/24/2025
Miscellaneous
Permit ID 1657
Transient Combustible Permit Fuel Building
Elevation 737'-0"
07/31/2025
1019.05
Transient Equipment/Materials
Procedures
Control of Transient Combustible Material
Miscellaneous
23/02
NRC Operating Experience Smart Sample (OpESS)
01/09/2024
CL-PRA-005.12
SX System Notebook
CL-PRA-005.27
CC System Notebook
CL-PRA-012, Vol.
of 2
Internal Flood Notebook: Evaluation Summary
Procedures
CL-PRA-012, Vol.
of 2
Internal Flood Notebook: Walkdown
04808007
Small Leak Found on Division I SX Piping Near 1SX349A
10/09/2024
04809307
Report Additional SX Inspections per Code Case
10/14/2024
Corrective Action
Documents
04812222
Low UT Reading Obtained on 1SX25A-4
10/25/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04883319
Report Degradation on 1SX14AA Line
07/18/2025
04890796
Report Low UT Reading on 1SX06AA20
08/15/2025
Engineering
Changes
Wall Thinning Evaluation of 1SX06AA-20" IAW N513-5
08/21/2025
Miscellaneous
209.05F001
Clinton Power Station Procedure Qualification Record
NDE Reports
Ultrasound Examination on 1-RH-37-4-4
09/21/2023
VT-3 Visual Examination of Component Supports,
Attachments and Interiors of Reactor Vessels
Procedures
WPS 1-1-GTSM-
ASME Welding Procedure Specification Record
Work Orders
1E22F012 Valve Seat has Degraded Condition
09/24/2023
3005.01
Unit Power Changes
3103.01
3304.01
Control Rod Hydraulic and Control
3304.02
Rod Control and Information System
23d
4007.02
Inadvertent Rod Movement
014
4301.01
16D
4401.04
EOP-14, Cold Shutdown RPV Control
4402.04
EOP-64, Containment and Radioactivity Release Control
CPS 3006.01
Unit Shutdown
Procedures
EOP-14 and 64
Clinton Power Station Licensed Operator Training Simulator
Exercise Guide
04832418
Unexpected 5065-5A RHR B/C WLP TRIP
01/26/2025
Corrective Action
Documents
04894026
1E12-F046B Min Flow Check Open not able to be verified
08/28/2025
Work Orders
5619890
Troubleshoot Breaker for 1E12-C003
01/26/2025
04896175
As Left LLRT for 9861.02D015 1E51F077
09/09/2025
04897507
1FP050 and 1FP092 LLRT Results per 9861.02D045
09/12/2025
04897584
1WX020 As-Found Leakage Outside Admin Limit
09/13/2025
04898450
9861.02D059 1VR006A/B LLRT Above Admin Limit
09/17/2025
Corrective Action
Documents
04899315
9861.02D045, FP to CNMT, 1FP092 Above
Evaluation Limit
09/20/2025
Corrective Action
04880008,
PCRA Enhancements for CPS 9534.02A/E, and CPS
07/09/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
04880022
9534.02B/F
E02-1RR99 sheet
514
Reactor Recirc System (RR) Anticipated Transient Without
H
E03-1RR04JA
sheet 2
Internal-External Wiring Diagram Anticipated Transient
Without Scram (ATWS) System 1 Control Panel (1RR04JA)
E
E03-1RR04JA
sheet 3
Internal-External Wiring Diagram Anticipated Transient
Without Scram (ATWS) System 1 Control Panel (1RR04JA)
G
M05-1079-001
P&ID Reactor Core Isolation Cooling (RCIC) (RI)
AJ
Drawings
M05-1089
Radwaste Sludge Process (WX)
CL-PRA-005.07
Reactor Core Isolation Cooling System Notebook
Engineering
Evaluations
Appendix J Evaluation Form: 1E51-F077
09/09/2025
9534.02A
ATWS Reactor Pressure B21-N401A Channel Functional
Maintenance Rule (a)(1) AND (a)(2) Requirements
Integrated Risk Management
Procedures
OP-AA-107-F-01
Risk Screening/Mitigation Plan
0561596713
1WX020 failed to open - BWRT overflowing to RF
Work Orders
4787766-01,
4877693-01,
5119992-01,
4787766-04,
4877693-04
Various Work Orders with Risk Screening/Mitigation Plans
For The '0' Service Air Compressor Rebuild Activity
07/16/2025
Calculations
19-D-49
Class 1E 125V DC System Analysis
Rev 0 D
Corrective Action
Documents
4887474
New Fuel Trailer Contacted Inner Truck Bay Door
07/31/2025
Engineering
Changes
645074
Through Wall Flaw Evaluation of Piping 1SX14AA in
Accordance With Code Case N-513-5
Engineering
Evaluations
ECR 468320
FBRA Inner Door Leak Impact to Secondary Containment,
Revision to ECR 468303
08/06/2025
Miscellaneous
Clinton Technical Specifications
07/15/2025
5067.04
Alarm Panel 5067 Annunciators - Row 4
9382.16
Division I 125VDC Battery Modified Performance Test
Procedures
9382.18
Division III 125VDC Battery Modified Performance Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
1944747
Door 1SD-30 is Missing Small Portion of Seal
08/06/2025
Engineering
Changes
Temporary Placement of Water Bladders (Aqudams) in 702'
Radwaste, 702' and 719' Control Building
04900136
MSIV Stem Assemblies Need Rebuilt prior to C1R23
09/23/2025
04900157
Secondary Containment Bypass Leakage Above TS Limit
09/24/2025
04900293
C1R22 LL: Suppression Pool Level Suspect Readings
09/24/2025
04900403
C1R22 1E51F076 Overthrust
09/24/2025
Corrective Action
Documents
04900454
Leak in Drywell from 1B21F051D
09/25/2025
Miscellaneous
C1R22 SSMP
C1R22 Shutdown Safety Management Program
3005.01F001
Unit Power Changes Power Increase Flowchart
3005.01F002
Unit Power Changes Power Decrease Flowchart
3005.01F003
Secondary Thermal Power Validation
0b
CPS 3006.01
Unit Shutdown
Procedures
3006.01F001
Unit Shutdown Flowchart
0a
04009845
PSU: C1R17 MSIV LLRT Tech Spec 3.6.1.3 Limit Exceeded
05/12/2017
04896157
MSIV LLRT 9861.04 Acceptance Criteria not Met
09/09/2025
04897000
MSIV LLRT Leakage Determination
09/12/2025
04900160
9861.04 MSIV LLRT Final Results
09/24/2025
Corrective Action
Documents
Risk Assessment:
CPS-1-2025-0329
Simple Issue Risk Assessment: C1R22 MSIV Decision and
Impact
Miscellaneous
01501872
Control Room Envelope Inleakage Testing at Clinton Power
Station 2025
07/07/2025
05449881
9080.21R20 OP *DG1A Integrated Test (Except Section 8.5)
(Blank)
10/22/25
9070.06
Main Control Room Tracer Gas Test
9071.01A
Diesel Driven Fire Pump A Functionality Test
9080.01
Diesel Generator 1A Operability Manual and Quick Start
Operability
9080.21
Diesel Generator 1A - ECCS Integrated
Procedures
9443.08
Leak Detection System Drywell Gas (E31-K612) Radiation
Monitor Calibration
38g
ALARA Plans
513-2
C1R22 Outage DW UV CRDM Pull (17 CDRMs)
08/14/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-2
C1R22 RFF Dry Tube Activities
07/25/2025
Worker Received Unexpected Dose Alarm
08/08/2025
Corrective Action
Documents
Liquid Scintillation Counter 3 - Broken C14 Source
09/16/2025
24-113
TEDE ALARA Evaluation Screening Worksheet - C1R22 FF
Activities (No Cavity Access) High Energy Work
09/05/2024
Miscellaneous
24-52
TEDE ALARA Evaluation Screening Worksheet - C1R22 DW
Undervessel Prep and Restore Activities/CRD Exchange
03/22/2024
Electron Capture Isotope Control
Controls for Very High Radiation Areas
Procedures
RP-AA-503-F-1
Unconditional Release Instructions using the Tool and
Equipment Monitor (TEM) for Personal Items Used in The
RCA and in a Contaminated Area
25-245837
Containment 781' RT HX Room B (C6-04)
08/07/2025
25-247959
Aux Building 762' RHR Heat Exchanger B (After Dose
Rate Alarm)
09/08/2025
GM Frisker Electron Capture Efficiency Determination -
Survey #2025-245837
08/08/2025
Radiation
Surveys
Alpha Area Level Assessment
10/03/2023
CL-1-25-00513
Radiation Work
Permits (RWPs)
CL-1-25-00902
CFF Drytube replacement
Self-Assessments AR 04795566
Pre-NRC 71124.01 Radiological Hazard and Exposure
Controls
07/08/2025
Quarterly Service Air and Self Contained Breathing
Apparatus (Breathing Air Grade D Test) (Performed
01/16/25, 04/23/25, and 07/07/25)
Various
N-CL-RP-JT-
EM32171
Performance Training and Evaluation: Inspect Respiratory
Protection Equipment
Miscellaneous
RP-CL-825-01
2, Respiratory Inspection Data Sheet
(dated 5/12/25, 6/13/25, and 7/17/25)
Controlled Negative Pressure (CNP) Fit Testing
Procedures
RP-CL-825-101
CPS Maintenance and Care of Respiratory Protection
Equipment
Miscellaneous
100518-0
NVLAP Voluntary Laboratory Accreditation Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(01/01/2025 through 12/31/2125)
NCS-19-002
Removing SRD/DLR Bias
1, Sample Personnel Exposure Investigation
(dated 12/31/2023, 08/04/2022, and 01/28/2025)
1, Trending for Shifts in Scaling Factors
(Dated 04/11/23 through 07/08/2025)
Calculations
CY-AA-130-3010-
F-03
Dose Equivalent Iodine Determination
Various
Occupational Exposure Control Effectiveness Performance
Indicator Data
Various
NRR Performance Indicators (PIs) SharePoint Site
07/22/2025
Operations Narrative Logs
07/22/2025
Miscellaneous
Regulatory Assessment Performance Indicator Guideline
CPS 9911.51R20
Liquid Radioactive Effluent Surveillance - Monthly
Various
71151
Work Orders
CPS 9911.59R20
Gaseous Radioactive Effluent Surveillance - Monthly
Various
04892300
EOP 6 Entered for High Suppression Pool Level
08/21/2025
04900403
C1R22 1E51F076 Overthrust
09/24/2025
04900701
C1R22: Incorrect Wiring on MOV 1E51-F076
09/25/2025
1E51F076: RCIC Steam Supply LLRT Higher than Admin
Limit
Perform Thrust Verification and MOV Clean and Inspect of
1E51F076
09/22/2025
C1R22 1E51F076 Overthrust
09/25/2025
Corrective Action
Documents
Work Group
Evaluation: IR 4892300
Work Group Evaluation: EOP 6 Entered for High
Suppression Pool Level
0