ML25216A278
| ML25216A278 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/11/2025 |
| From: | Ami Agrawal NRC/RGN-IV/DORS |
| To: | Karenina Scott Union Electric Co |
| References | |
| EPID I-2025-002-0007 IR 2025002 | |
| Download: ML25216A278 (1) | |
Text
August 11, 2025 Kent Scott, Senior Vice President and Chief Nuclear Officer Union Electric Company 8315 County Road 459 Steedman, MO 65251
SUBJECT:
CALLAWAY PLANT - INTEGRATED INSPECTION REPORT 05000483/2025002
Dear Kent Scott:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Callaway Plant. On July 15, 2025, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
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 IV; the Director, Office of Enforcement; and the NRC Resident Inspector at the Callaway Plant.
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 IV; and the NRC Resident Inspector at the Callaway Plant.
K. Scott 2
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, Ami N. Agrawal, Chief Reactor Projects Branch B Division of Operating Reactor Safety Docket No. 05000483 License No. NPF-30
Enclosure:
As stated cc w/encl: Distribution via LISTSERV Signed by Agrawal, Ami on 08/11/25
SUNSI Review By: CMH
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE SRI:DORS/PBB RI:DORS/PBB C:DORS/PBB NAME SSchwind NBrown AAgrawal SIGNATUR E
/RA/
/RA/
/RA/
DATE 08/07/25 08/06/25 08/11/25
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000483 License Number:
NPF-30 Report Number:
05000483/2025002 Enterprise Identifier:
I-2025-002-0007 Licensee:
Union Electric Company Facility:
Callaway Plant Location:
Steedman MO Inspection Dates:
April 1 to June 30, 2025 Inspectors:
B. Baca, Health Physicist N. Brown, Resident Inspector J. Drake, Senior Reactor Inspector S. Schwind, Senior Resident Inspector E. Simpson, Nuclear Systems Scientist Approved By:
Ami N. Agrawal, Chief Reactor Projects Branch B Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Callaway Plant, 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 Failure to Perform an Adequate Part 21 Review Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000483/2025002-01 Open/Closed
[P.5] -
Operating Experience 71152A The inspectors reviewed a self-revealed Green finding and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, for the licensees failure to promptly identify and correct a condition adverse to quality. Specifically, the licensee failed to recognize the applicability of a 10 CFR Part 21 report regarding possible mechanical binding of full reversing starter mechanical interlocks in 2021. Subsequently, five safety-related motor-operated valves failed due to this issue.
Additional Tracking Items None.
3 PLANT STATUS The plant was shut down for refueling outage 27 for the entire quarter.
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) (1 Sample)
The inspectors evaluated system configurations during a partial walkdown of the following system:
(1) cold overpressure mitigation system during mode 5 operations on May 3, 2025 Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated system configurations during a complete walkdown of containment spray train B on May 5, 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) reactor building fire area RB-1 on April 3, 2025 (2) control building fire areas C-1, C-5, C-6, C-7, C-8 elevation 1974'-0" on April 3, 2025 (3) fire area TB-1 on May 19, 2025
4 71111.07A - Heat Exchanger/Sink Performance Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1) component cooling water train A heat exchanger on April 5, 2025 71111.08P - Inservice Inspection Activities (PWR)
The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities during refueling outage 27 from March 31 to April 8, 2025.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01) (1 Sample)
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
(1)
Ultrasonic Examination 1.
pressurizer, safety 2BB02S001J, pipe to flange 2.
pressurizer, safety 2BB02S006J, pipe to flange 3.
pressurizer, safety 2BB02S007J, pipe to flange 4.
steam generator D, EBB01 D-RSG-SC001, bottom head to tube sheet 5.
steam generator B, EBB01 B-RSG-SC001, bottom head to tube sheet 6.
steam generator B, EBB01 B-RSG-SC003, tube sheet to shell 7.
steam generator B, EBB01 B-RSG-SC008, upper to shell 8.
essential service water train A pump discharge pipe to flange Visual 1 Examination 1.
containment liner, SUMPLF07DRWIT instrument tunnel sump base metal repair of liner Visual 2 Examination 1.
safety injection, penetration 87 to cold leg check valve 2.
safety injection, penetration 48 to cold leg check valve 3.
safety injection, penetration 49 to cold leg check valve Magnetic particle examination 1.
containment liner, SUMPLF07DRWIT, instrument tunnel sump base metal repair of liner 2.
essential service water train A pump discharge flange 3.
essential service water train A pump spool piece, welds FW-03, FW-04, and FW-05 Welding Activities 1.
weld process, shielded metal arc weld
5 a.
essential service water train A pump spool piece, welds FW-03, FW-04, and FW-05 b.
essential service water train A pump discharge flange, weld FW 07 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)
The inspectors verified that no vessel upper head penetration inspection was required this outage.
PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
(1)
Boric acid evaluations and screenings:
1.
202306651 2.
202306653 3.
202306659 4.
202306840 5.
202306893 6.
202306945 7.
202307001 8.
202307332 9.
202307476
- 10. 202307628
- 11. 202307631
- 12. 202307736
- 13. 202307782
- 14. 202307946
- 15. 202307950
- 16. 202308035
- 17. 202308107
- 18. 202308167
- 19. 202308182
- 20. 202400927
- 21. 202401126
- 22. 202401128
- 23. 202401130
- 24. 202401250 PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04)
The inspectors verified that no ASME code steam generator tube integrity inspection was required this outage.
6 71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
(1) fire water system on June 13, 2025 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 during the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1) engineered safety features train A actuation system testing on April 18, 2025 (2) risk management actions during yellow risk window for spent fuel pool cooling on April 9, 2025 (3) risk assessment regarding mode ascension prior to completion of maintenance on the incore tunnel sump level indication system on May 3, 2025 (4) risk management actions while backfeeding power through the main transformers on April 23, 2025 (5) risk management actions for reactor vessel lower internals lift on May 16, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1) erratic indication on gammametrics source range channel N60, on April 1, 2025 (2) potential reactor coolant system boundary leakage on March 31, 2025 (3) turbine-driven auxiliary feedwater pump discharge to steam generator B valve ALHV0009 on April 7, 2025 (4) control room emergency ventilation system operability during a breach in the control room envelope on April 8, 2025 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated refueling outage 27 activities beginning March 28, 2025, and continuing beyond the end of the quarter.
7 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) (7 Samples)
(1) breaker NB01BF03 replacement on April 4, 2025 (2) post-maintenance testing following flaw repairs on essential service water train A piping on April 18, 2025 (3) valve ALHV0031 following rebuild on April 24, 2025 (4) turbine-driven auxiliary feedwater pump testing following replacement of the trip and throttle valve on May 5, 2025 (5) load shed and emergency load sequencer test of breakers NG01BJF5 and NG02BJF5 after replacement on May 2, 2025 (6) rod drop testing following replacement of control rod drive mechanism thermal sleeves on May 8, 2025 (7) turbine-driven auxiliary feedwater pump testing following maintenance on the trip and throttle valve on May 6, 2025 Surveillance Testing (IP Section 03.01) (3 Samples)
(1) auxiliary feedwater pump discharge check valve closure test on May 5, 2025 (2) main feedwater isolation valve inservice test on May 5, 2025 (3) turbine-driven auxiliary feedwater pump testing on May 5, 2025 Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1) component cooling water isolation valves EGHV0130 and EGHV0131 on April 15, 2025 71114.06 - Drill Evaluation Required Emergency Preparedness Drill (1 Sample)
(1) emergency preparedness exercise on June 12, 2025 RADIATION SAFETY 71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
8 Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1) observed radiological surveys of potentially contaminated packages/equipment that were being delivered from offsite locations for incorporation into its radiological control program (2) walked down the storage locations for several nonexempt radioactive sources listed in the licensee's non-exempt source inventory (3) evaluated the licensee's physical and programmatic controls for highly activated and contaminated non-fuel materials stored within the spent fuel pool Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1) direct observation of locked high radiation area (LHRA) work activities and job coverage in support of reactor coolant pump removal and movement into a shipping cask under radiation work permit (RWP) R27DRCPINTLIFT, revision 0 (2) direct observation of work activities and job coverage in support of fuel assembly inspection activity and the replacement of a control assembly into an unirradiated fuel bundle under RWP R27FUEL, revision 0 (3) walkdown of satellite radiologically controlled areas to assess storage and security of outage related to posted radioactive materials areas and stored contaminated items High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas (VHRAs):
(1) containment instrument in-core tunnel - VHRA (2) waste holdup tank room, radwaste room 7122 - LHRA (3) entrance to stock system/decant tank room, radwaste room 7213 - LHRA 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) (2 Samples)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
(1) control room emergency ventilation system (FGK01B)
(2) technical support center filtered ventilation system (FUB7001)
9 Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
(1) reactor coolant pump D impeller work, radiation work permit R27DRCPINT, Revision 0, supported by high efficiency particulate air units VAC-4116-HP, test due date March 19, 2027, and VAC-4117-HP, test due date May 8, 2025 (2) reactor head LHRA supported by high efficiency particulate air unit VAC-4111-HP, test due date March 4, 2027 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.
OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicator submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
(1)
April 2024 to March 2025 MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
(1)
April 2024 to March 2025 OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
April 1, 2024, to December 31, 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)
April 1, 2024, to December 31, 2024 71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (3 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1) non-compliance with ASME Code Section XI during job 20003148.496 on February 5, 2025
10 (2) corrective actions regarding inadvertent discharge of safety injection on April 5, 2025 (3) corrective actions regarding a Part 21 notification on faulty full voltage reversing starters used in motor-operated valve motor control centers on April 23, 2025 71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective action program to identify instances of debris found in fuel assemblies on April 8, 2025.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-Up (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated follow-up on the loss of backfeed during shutdown cooling operations and the licensees response on April 23, 2025.
INSPECTION RESULTS Failure to Perform an Adequate Part 21 Review Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000483/2025002-01 Open/Closed
[P.5] -
Operating Experience 71152A The inspectors reviewed a self-revealed Green finding and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, for the licensees failure to promptly identify and correct a condition adverse to quality. Specifically, the licensee failed to recognize the applicability of a 10 CFR Part 21 report regarding possible mechanical binding of full reversing starter mechanical interlocks in 2021. Subsequently, five safety-related motor-operated valves failed due to this issue.
==
Description:==
On April 29, 2021, Paragon made a report in accordance with 10 CFR Part 21 about mechanical interlocks binding on two different starters and contactors. The licensee wrote a condition report on May 19, 2021, assessing applicability and incorrectly determined that the affected starters did not affect the Callaway Plant.
On November 18, 2021, component cooling water from containment outer isolation valve EGHV0059 providing cooling flow to the reactor coolant pumps failed to open. The starter was not functioning properly and prevented the valve from opening. The licensee determined the failure cause was binding of the starter, congruent with the identified failures of Paragon starters reported in the Part 21. The licensee identified the failed starter, and 21 additional, size 1 starters, as well as 2 size 2 starters that had the same part numbers as the Part 21 identified faulty starters. Previously the licensee stated in a condition report that Callaway Energy Center does not use the type of starters (DC Control Coils) discussed in the Part 21 (Revision 2), because all units at Callaway have AC control power.
On November 7, 2023, the residual heat removal train B minimum flow valve EJFCV0611 failed to open during stroke time testing. The licensee removed the starter and shipped it to Paragon for analysis, as documented in condition report (CR) 202403500. Paragons response concluded in part, the date codes and material are within the range under Paragon
11 Part 21 notification P21-03302021 in which similar issues were previously experienced.
ThePart 21 notification indicates the issues in question were from units fabricated between Sept. 2014 to Sept. 2018. The returned units are from Jan. 2018, and the interlock rockers are the same material from this revision of interlock. In CR 202403690 the licensees recommendation was to replace each starter during the next available work window via the normal work management processes.
Three additional Paragon starters had binding issues resulting in the failure of BNHV0003 containment spray (CS) train B pump suction, EMHV8807A residual heat removal train A heat exchanger to safety injection pumps suction isolation, and ENHV0006 CS train A pump discharge valves. These failures prompted the licensee to reassess the applicability of the Paragon reported Part 21. Failure of CS train A pump discharge valve ENHV0006 to open degraded the safety function of the system.
In May 2025 the licensee concluded their initial assessment was erroneous and Part 21 did apply to Callaway.
Corrective Actions: The licensee identified and removed the mechanical interlock on the Part 21 nonconforming starters, as well as identified and removed the mechanical interlock on all starters with the part number identified in Part 21, regardless of the affected date range.
Corrective Action References: Condition Reports 202102874, 202308366; 202502573; and 202503012 Performance Assessment:
Performance Deficiency: The inspectors determined that the failure to identify and correct a condition adverse to quality associated with failing starters identified in a Part 21 report was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Structures, Systems, Components and Barrier Performance attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the performance deficiency resulted in the inoperability of containment spray train A subsystems.
Significance: The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process for Findings At-Power.
The inspectors used exhibit 3, Barrier Integrity Screening Questions, to determine that the finding was of very low safety significance (Green) because the finding: (1) did not represent an actual open pathway in the physical integrity of reactor containment, failure of containment isolation system, failure of containment pressure control equipment, failure of containment heat removal components, or failure of the plants severe accident mitigation features; and (2) did not involve an actual reduction in function of hydrogen igniters in the reactor containment.
Cross-Cutting Aspect: P.5 - Operating Experience: The organization systematically and effectively collects, evaluates, and implements relevant internal and external operating experience in a timely manner.
12 Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion XVI, requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.
Contrary to the above, between April 29, 2021, and May 1, 2025, the licensee failed to establish measures to ensure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances were promptly identified and corrected. Specifically, the licensee failed to identify safety-related starters with date codes that were identified in the Part 21 report by Paragon. As a result, five of the relays experienced mechanical binding and failed to open the associated valves, rendering the safety functions of the containment spray system degraded.
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 that no proprietary information was retained or documented in this report.
On April 8, 2025, the inspectors presented the inservice inspection results to R. Ryterski, Manager, Nuclear Strategic Initiative, and other members of the licensee staff.
On April 11, 2025, the inspectors presented the occupational radiation safety inspection results to K. Scott, then Nuclear Site Vice President and other members of the licensee staff.
On July 15, 2025, the inspectors presented the integrated inspection, inspection results to K. Scott, Senior Vice President and Chief Nuclear Officer and other members of the licensee staff.
13 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71111.04 Procedures OSP-BB-00003 PORV/RHR COMS Alignment Verification 15 71111.04 Procedures OTN-EN-00001 Containment Spray System 26 71111.05 Fire Plans Fire Preplan Manual 43 71111.05 Miscellaneous Fire Safety Analysis Calculation KC-156, Fire Area TB-1 2
71111.07A Corrective Action Documents Condition Reports 202501956 71111.08P Corrective Action Documents Condition Reports 202202004, 202306096, 202306121, 202306156, 202306300, 202306492, 202306740, 202306747, 202306960, 202306976, 202306995, 202307006, 202307056, 202307085, 202307107, 202307124, 202307134, 202307188, 202307197, 202307212, 202307247, 202307317, 202307374, 202307421, 202307519, 202307524, 202307537, 202307605, 202307608, 202307610, 202307664, 202307688, 202307707, 202307708, 202307749, 202307858, 202307908, 202307945, 202307963, 202308035, 202308042, 202308046, 202308182, 202308192, 202308345, 202308347, 202308370, 202308527, 202308621, 202308766, 202309069, 202309088, 202309089, 202309197, 202309221, 202309248, 202309249, 202400535, 202400690, 202401125, 202401171, 202401172, 202401320, 202401455, 202401559, 202401647, 202401736, 202401794, 202401977, 202401984, 202401988, 202402021, 202402065, 202402276, 202402347, 202402498, 202402501, 202402555, 202402675, 202402715, 202403110, 202403201, 202403225, 202403264, 202403391, 202403614, 202403687, 202403706, 202403708, 202403760, 202403961, 202404134, 202404262, 202404545, 202404947, 202405149, 202405159, 202405178, 202405187, 202405273, 202405377, 202405769, 202405824, 202405951,
14 Inspection Procedure Type Designation Description or Title Revision or Date 202406120, 202406196, 202406204, 202406233, 202406299, 202406370, 202406412, 202406417, 202406578, 202406609, 202406634, 202406660, 202406681, 202406748, 202406794, 202406822, 202406924, 202407291, 202407318, 202407493, 202407593, 202407635, 202500081, 202500087, 202500095, 202500121, 202500413, 202500465, 202500970, 202501742 71111.08P Miscellaneous 51 - 9343293 Callaway 1R25 Degradation Assessment - April 2022 0
71111.08P Miscellaneous 51 - 9350895 Callaway Unit 1 SG Condition Monitoring for Cycles 22, 23, 24 and 25 and Final Operational Assessment for Cycles 26, 27, 28, 29 and 30 0
71111.08P Miscellaneous CW0404-05 Callaway Energy Center ISI Program Plan Fifth Inspection Interval 0
71111.08P Miscellaneous CW0404-06 Callaway Energy Center ISI Selection Document Fifth Inspection Interval 0
71111.08P Miscellaneous CW0404-07 Callaway Energy Center Risk-Informed Inservice Inspection Supplemental Report Fifth Inspection Interval 0
71111.08P Miscellaneous EPID L-2024-LLR-0084 Callaway Plant, Unit 1 - Verbal Authorization of Relief Requests IWE-01 and IWE-02 03/04/2025 71111.08P Miscellaneous RFR 2230232 Steam Generator Integrity Assessment Refuel 26 09/28/2023 71111.08P Miscellaneous Technical Report EP-2014-0001 TR Ameren Missouri - Callaway Energy Center Erosion Susceptibility Evaluation (ESE) Update Issued February 13, 2015 0
71111.08P Miscellaneous ULNRC-06915 Callaway Plant Unit 1 Union Electric Co. Renewed Facility Operating License NPF-30 Proposed Change to Technical Specifications to Allow H-08 Control Rod to be Removed for Cycle 28 (LDCN 25-0005) 0 71111.08P Procedures APA-ZZ-00661 Administration Of Welding 22 71111.08P Procedures APA-ZZ-00662 ASME Section XI Repair/Replacement Program 28 71111.08P Procedures EDP-ZZ-01004-R025 BACCP Program Procedure 25 71111.08P Procedures LMT-08-PDI-UT-1 Ultrasonic Examination of Ferritic Piping Welds 0
71111.08P Procedures LMT-08-PDI-UT-2 Ultrasonic Examination of Austenitic Piping Welds 0
15 Inspection Procedure Type Designation Description or Title Revision or Date 71111.08P Procedures LMT-08-PDI-UT-3 Ultrasonic Through Wall Sizing in Piping Welds 0
71111.08P Procedures LMT-08-PDI-UT-5 Straight Beam Ultrasonic Examination of Bolts and Studs 07.20.2016-Final 0
71111.08P Procedures LMT-08-UT-004 Ultrasonic Examination of Vessel Welds and Adjacent Base Metal > 2.0 in Thickness 1
71111.08P Procedures LMT-08-UT-118 Ultrasonic Examination Technique for Thermal Fatigue Cracking/Crazing (MRP-146 & MRP-192) 1 71111.08P Procedures LMT-08-UT-119 Conventional Ultrasonic Instrument Linearity 1
71111.08P Procedures MDP-ZZ-LM001-R022 Fluid Leak Management Program 22 71111.08P Procedures QCP-ZZ-05040 Visual Examination to ASME VT-1 27 71111.08P Procedures QCP-ZZ-05041 Visual Examination to ASME VT-2 32 71111.08P Procedures QCP-ZZ-05042 Visual Examination to ASME VT-3 24 71111.08P Procedures QCP-ZZ-05048-R015 BA Walkdown for RCS Pressure Boundary QC 15 71111.08P Procedures QCP-ZZ-05049-R007 RPV Head Bare Metal Examination 7
71111.12 Miscellaneous KC-43, Code Compliance Evaluation NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electrical Generating Plants 2
71111.12 Procedures APA-ZZ-00703 Fire Protection Operability Criteria and Surveillance Requirements 35 71111.12 Procedures EDP-ZZ-01101 Fire Protection Monitoring Program 4
71111.13 Corrective Action Documents Condition Reports 202503067 71111.13 Procedures APA-ZZ-00315 Risk Management Actions 7
71111.13 Procedures APA-ZZ-00315, Appendix E Configuration Risk Management Program - Shutdown 2
71111.13 Procedures OSP-SA-2143A Train A Diesel Generator and Sequencer Testing 35 71111.13 Procedures OTO-NB-00002 Loss of Power to NB02 37 71111.13 Work Orders Jobs 22504386 71111.15 Corrective Action Documents Condition Reports 202501697, 202501742, 202501920, 202502036, 202502067, 202502095, 202502392
16 Inspection Procedure Type Designation Description or Title Revision or Date 71111.15 Drawings M-22AL-1 Piping and Instrumentation Diagram Auxiliary Feedwater System 51 71111.15 Miscellaneous Pressure Boundary Breach Evaluation Form 04/07/2025 71111.20 Procedures OTG-ZZ-00007 Refueling Preparation, Performance, and Recovery 46 71111.24 Miscellaneous Modification Package 25-0008 71111.24 Procedures APA-ZZ-00322, Appendix E Post-Maintenance Test Program 21 71111.24 Procedures ESP-ZZ-00032 Test Procedure for Automated Measurement of Drop Times of Control and Shutdown Rods in Westinghouse PSRS with DRPI Power-On 5
71111.24 Procedures OSP-AE-V02HS Main Feedwater Isolation Valve Inservice Test 43 71111.24 Procedures OSP-AL-P0002 Turbine Driven Auxiliary Feedwater Pump Inservice Test -
Group B 83 71111.24 Procedures OSP-AL-PV005 Turbine Driven Auxiliary Feedwater Pump and Check Valve Inservice Test 30 71111.24 Procedures OSP-AL-V0003 Auxiliary Feedwater Pump Discharge Check Valve Closure Test 18 71111.24 Procedures OSP-AL-V001A Train A Auxiliary Feedwater Valve Inservice Test 64 71111.24 Procedures OSP-ZZ-LL075 Containment Isolation Valve Leak Rate Test 19 71111.24 Procedures OTN-ZZ-00004 Operation of the Leak Rate Monitor (LRM) 12 71111.24 Procedures QCP-ZZ-05041 Visual Examination to ASME VT-2 32 71111.24 Work Orders Jobs 25001164, 22005060, 23512006, 23511787, 23511732, 23511628, 25001164, 23512826, 23512006 71114.06 Procedures EIP-ZZ-00101 Classification of Emergencies 57 71114.06 Procedures EIP-ZZ-00101, Addendum 2 Emergency Action Level Technical Bases 22 71124.01 Corrective Action Documents Condition Reports 202404415, 202404483, 202404709, 202405036, 202405062, 202405388, 202405710, 202405866, 202406202, 202406303, 202406497, 202406990, 202407007, 202500523, 202500524, 202500712, 202500740, 202501136 71124.01 Procedures APA-ZZ-00801 Foreign Material Exclusion 62
17 Inspection Procedure Type Designation Description or Title Revision or Date 71124.01 Procedures APA-ZZ-01000, Appendix A Control of Radioactive Material 25 71124.01 Procedures HDP-ZZ-01500 Radiological Postings 54 71124.01 Procedures HTP-ZZ-02004 Control of Radioactive Sources 46 71124.01 Procedures HTP-ZZ-06028 Radiological Controls for Pools that Contain or Store Spent Fuel 10 71124.01 Radiation Surveys CA-M-20250406-20 Characterization Survey of C RCP 71124.01 Radiation Surveys CA-M-20250407-13 Characterization Survey - Container 30031212 71124.01 Radiation Work Permits 23004769 Disassemble, Inspect, Clean, and Reassemble Check Valve EP8956C 1
71124.01 Radiation Work Permits (RWPs)
R27DRCPCOORD D Reactor Coolant Pump Internals Replacement Oversite/Coordination Activities 1
71124.01 Radiation Work Permits (RWPs)
R27DRCPINT All Prep Work for the Removal and Installation Associated with D Reactor Coolant Pump Internals 2
71124.01 Radiation Work Permits (RWPs)
R27DRCPINTLIFT Lift D Reactor Coolant Pump Internals from Housing and Place in Shipping Container. Install/Remove Temporary FME Cover. Install FME Shield Plug in Pump Casing. Clean Flange for Machining.
2 71124.01 Radiation Work Permits (RWPs)
R27DRCPINTRP Radiation Protection Coverage for D Reactor Coolant Pump Internals Replacement. All Work Associated with D Reactor Coolant Pump Internals.
0 71124.01 Radiation Work Permits (RWPs)
R27FUEL Offload Reactor, Perform FOSAR, Perform Reactor Reload, Core Mapping, Insert Shuffle, Pool Mapping, B5B Moves, and Miscellaneous Support Activities 0
71124.03 Calibration Records Air Quality Analysis Report for Bauer UNIII/25H-E3, SN 102386 03/27/2025 71124.03 Calibration Records Job 24001284 Calibration Certificate of Temporary HEPA Unit ID# VAC-4111-HP 04/09/2024 71124.03 Calibration Records Job 24002990 Calibration Certificate of Control Room Emergency Air Supply Tank ID# MAC-0025-HP 09/05/2024 71124.03 Calibration Records Job 25001058 Calibration Certificate of Temporary HEPA Unit ID# VAC-4116-HP 03/19/2025
18 Inspection Procedure Type Designation Description or Title Revision or Date 71124.03 Corrective Action Documents Condition Reports 202202309, 202202390, 202204037, 202205472, 202205959, 202206137, 202206687, 202206945, 202207201, 202207499, 202207688, 202207869, 202208007, 202208386, 202300634, 202300883, 202302393, 202303626, 202400594, 202401265, 202402782, 202404323, 202405551, 202407056 71124.03 Drawings HTP-ZZ-08501-DTI-AIR TEST Testing of Breathing Air 5
71124.03 Miscellaneous Certification ID C020875 Scott Technical Support: SCBA Certified Technician II, Maintenance and Overhaul - Jeff Eldringhoff 01/24/2025 71124.03 Procedures ESP-GK-03001 FGK01A Charcoal Test Canister Removal and Lab Testing 20 71124.03 Procedures ESP-GK-03002 FGK01B Charcoal Test Canister Removal and Lab Testing 21 71124.03 Procedures ESP-UB-03001 FUB7001 Charcoal Test Canister Removal and Lab Testing 18 71124.03 Procedures ESP-UB-03012 FUB7001 In-Place Bypass Leakage Test 5
71124.03 Procedures ETP-ZZ-03004 In-Place Bypass Leakage Testing of Adsorber Stage 12 71124.03 Procedures ETP-ZZ-03005 In-Place Bypass Leakage Testing of HEPA Filters 10 71124.03 Procedures HTP-ZZ-08203-DTI-REGULATORS Testing Scott Regulators and Respirators Using the Biosystems Posichek 3 USB Tester 11 71124.03 Procedures HTP-ZZ-08502-DTI-MAC-CAL Scott Mobile Air Cart Calibration 4
71124.03 Procedures HTP-ZZ-08503-DTI-UNIIICompressor Operation of Bauer Unicus III, 25 CFM Breathing Air Compressor and Breathing Air Cascade System 7
71124.03 Work Orders Job 22509842-500 FGK01B Charcoal Test Canister Removal and Lab Testing 02/13/2024 71124.03 Work Orders Job 23506576-500 FGK01A Charcoal Test Canister Removal and Lab Testing 10/15/2024 71124.03 Work Orders Job 22507436-500 In-Place Bypass Leakage Testing of Adsorber Stage and In-Place Bypass Leakage Testing of HEPA Filters for FGK01B 12/07/2023 71124.03 Work Orders Job 22510055-500 In-Place Bypass Leakage Testing of Adsorber Stage and In-Place Bypass Leakage Testing of HEPA Filters for FGK01A 12/18/2023 71124.03 Work Orders Job 23500086-500 Radioiodine Penetration / Efficiency Test Report for TSC Filter Unit FUB7001 05/22/2024 71124.03 Work Orders Job 23506199-500 Charcoal Adsorber In-Place Leak Test Report and HEPA Filter Leak Test Report for TSC Filtering Unit FUB7001 12/16/2024
19 Inspection Procedure Type Designation Description or Title Revision or Date 71124.03 Work Orders Job 25000432 Posi3 USB Test Results of Regulator APR-0057-HP 02/07/2025 71124.03 Work Orders Job 25000433 Posi3 USB Test Results of Regulator APR-0067-HP 02/07/2025 71124.03 Work Orders Respiratory Protection Monthly Inspections 22507157, 22508202, 22509545, 22511985, 22512620, 22513609, 23500069, 23502647, 23503603, 23504846, 23506439, 23508039, 23509135, 23509623, 23512047, 23513194, 23514297, 24500708, 24501913, 24502596, 24503986, 24505243, 24506364, 24507852, 24508437, 24509667, 24511131, 24512424, 25500070 71151 Miscellaneous Heat Removal System Performance Indicator Data for April 2024 through March 2025 71151 Miscellaneous Safety System Functional Failure Performance Indicator Data for April 2024 through March 2025 71151 Miscellaneous PM0911004 Dose Assessment from Liquid Effluents (Quarterly):
January - December 2024 and January - March 2025 71151 Miscellaneous PM0911009 Dose Assessment from Noble Gases (Quarterly): January -
December 2024 and January - March 2025 71151 Miscellaneous PM0911010 Dose Assessment from Radioiodines and Particulates (Quarterly): January - December 2024 and January - March 2025 71152A Corrective Action Documents Condition Reports 202005276, 202307958, 202308226, 202308929, 202400480, 202406120, 202406164 71152A Procedures APA-ZZ-00662 ASME Section XI Repair/Replacement Program 28 71152A Procedures EDP-ZZ-01007 Mechanical Snubber Program 34 71152A Work Orders Jobs 23004837 71152S Corrective Action Documents Condition Reports 202501903, 202501946, 202501957, 202501963 71153 Corrective Action Documents Condition Reports 202502701