IR 05000483/2025002
| ML26042A378 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/12/2026 |
| From: | Ami Agrawal NRC/RGN-IV/DORS/PBB |
| To: | Karenina Scott Union Electric Co |
| Bloodgood M | |
| Shared Package | |
| ML26042A380 | List: |
| References | |
| IR 2025002 | |
| Download: ML26042A378 (0) | |
Text
February 12, 2026
SUBJECT:
CALLAWAY PLANT - INTEGRATED INSPECTION REPORT 05000483/2025002 (REVISED)
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 were initially documented in NRC Inspection Report 05000483/2025002, issued on August 11, 2025, (Agencywide Documents Access and Management System [ADAMS] Accession No. ML25216A278). The enclosed inspection report has been revised to include the completion of a partial sample associated with Inspection Procedure 71111.20, Refueling and Other Outage Activities, as certain outage activities extended beyond the original inspection period. The original report noted that one full sample was completed during the inspection period.
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 Signed by Agrawal, Ami on 02/12/26 Docket No. 05000483 License No. NPF-30
Enclosure:
As stated
Inspection Report
Docket Number:
05000483
License Number:
Report Number:
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
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.
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
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
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 for 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 for this outage.
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) (Partial Sample)
- (1) The inspectors evaluated refueling outage 27 activities beginning March 28, 2025, and continuing beyond the end of the quarter. The inspectors completed all procedural requirements except Section 03.01.d.1, Heatup and Startup.
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.
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)
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 (2)corrective actions regarding inadvertent discharge of safety injections 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 Part 21 notification P21-03302021 in which similar issues were previously experienced. The Part 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.
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.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
PORV/RHR COMS Alignment Verification
Procedures
OTN-EN-00001
Containment Spray System
Fire Plans
Fire Preplan Manual
Miscellaneous
Fire Safety Analysis Calculation KC-156, Fire Area TB-1
Corrective Action
Documents
Condition Reports
2501956
Corrective Action
Documents
Condition Reports
2202004, 202306096, 202306121, 202306156,
2306300, 202306492, 202306740, 202306747,
2306960, 202306976, 202306995, 202307006,
2307056, 202307085, 202307107, 202307124,
2307134, 202307188, 202307197, 202307212,
2307247, 202307317, 202307374, 202307421,
2307519, 202307524, 202307537, 202307605,
2307608, 202307610, 202307664, 202307688,
2307707, 202307708, 202307749, 202307858,
2307908, 202307945, 202307963, 202308035,
2308042, 202308046, 202308182, 202308192,
2308345, 202308347, 202308370, 202308527,
2308621, 202308766, 202309069, 202309088,
2309089, 202309197, 202309221, 202309248,
2309249, 202400535, 202400690, 202401125,
2401171, 202401172, 202401320, 202401455,
2401559, 202401647, 202401736, 202401794,
2401977, 202401984, 202401988, 202402021,
2402065, 202402276, 202402347, 202402498,
2402501, 202402555, 202402675, 202402715,
2403110, 202403201, 202403225, 202403264,
2403391, 202403614, 202403687, 202403706,
2403708, 202403760, 202403961, 202404134,
2404262, 202404545, 202404947, 202405149,
2405159, 202405178, 202405187, 202405273,
2405377, 202405769, 202405824, 202405951,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2406120, 202406196, 202406204, 202406233,
2406299, 202406370, 202406412, 202406417,
2406578, 202406609, 202406634, 202406660,
2406681, 202406748, 202406794, 202406822,
2406924, 202407291, 202407318, 202407493,
2407593, 202407635, 202500081, 202500087,
2500095, 202500121, 202500413, 202500465,
2500970, 202501742
Miscellaneous
- 9343293
Callaway 1R25 Degradation Assessment - April 2022
Miscellaneous
- 9350895
Callaway Unit 1 SG Condition Monitoring for Cycles 22, 23,
and 25 and Final Operational Assessment for Cycles 26,
27, 28, 29 and 30
Miscellaneous
CW0404-05
Callaway Energy Center ISI Program Plan Fifth Inspection
Interval
Miscellaneous
CW0404-06
Callaway Energy Center ISI Selection Document Fifth
Inspection Interval
Miscellaneous
CW0404-07
Callaway Energy Center Risk-Informed Inservice Inspection
Supplemental Report Fifth Inspection Interval
Miscellaneous
EPID L-2024-LLR-
0084
Callaway Plant, Unit 1 - Verbal Authorization of Relief
Requests IWE-01 and IWE-02
03/04/2025
Miscellaneous
RFR 2230232
Steam Generator Integrity Assessment Refuel 26
09/28/2023
Miscellaneous
Technical Report
EP-2014-0001-03-
Ameren Missouri - Callaway Energy Center Erosion
Susceptibility Evaluation (ESE) Update Issued February 13,
2015
Miscellaneous
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)
Procedures
APA-ZZ-00661
Administration Of Welding
Procedures
APA-ZZ-00662
ASME Section XI Repair/Replacement Program
Procedures
EDP-ZZ-01004-
R025
BACCP Program Procedure
Procedures
LMT-08-PDI-UT-1
Ultrasonic Examination of Ferritic Piping Welds
Procedures
LMT-08-PDI-UT-2
Ultrasonic Examination of Austenitic Piping Welds
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
LMT-08-PDI-UT-3
Ultrasonic Through Wall Sizing in Piping Welds
Procedures
LMT-08-PDI-UT-5
Straight Beam Ultrasonic Examination of Bolts and Studs
07.20.2016-Final
Procedures
LMT-08-UT-004
Ultrasonic Examination of Vessel Welds and Adjacent Base
Metal > 2.0 in Thickness
Procedures
LMT-08-UT-118
Ultrasonic Examination Technique for Thermal Fatigue
Cracking/Crazing (MRP-146 & MRP-192)
Procedures
LMT-08-UT-119
Conventional Ultrasonic Instrument Linearity
Procedures
MDP-ZZ-LM001-
R022
Fluid Leak Management Program
Procedures
QCP-ZZ-05040
Visual Examination to ASME VT-1
Procedures
QCP-ZZ-05041
Visual Examination to ASME VT-2
Procedures
QCP-ZZ-05042
Visual Examination to ASME VT-3
Procedures
QCP-ZZ-05048-
R015
BA Walkdown for RCS Pressure Boundary QC
Procedures
QCP-ZZ-05049-
R007
RPV Head Bare Metal Examination
Miscellaneous
KC-43, Code
Compliance
Evaluation NFPA-
805
Performance Based Standard for Fire Protection for Light
Water Reactor Electrical Generating Plants
Procedures
APA-ZZ-00703
Fire Protection Operability Criteria and Surveillance
Requirements
Procedures
EDP-ZZ-01101
Fire Protection Monitoring Program
Corrective Action
Documents
Condition Reports
2503067
Procedures
APA-ZZ-00315
Risk Management Actions
Procedures
APA-ZZ-00315,
Appendix E
Configuration Risk Management Program - Shutdown
Procedures
Train A Diesel Generator and Sequencer Testing
Procedures
OTO-NB-00002
Loss of Power to NB02
Work Orders
Jobs
2504386
Corrective Action
Documents
Condition Reports
2501697, 202501742, 202501920, 202502036,
2502067, 202502095, 202502392
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
M-22AL-1
Piping and Instrumentation Diagram Auxiliary Feedwater
System
Miscellaneous
Pressure Boundary Breach Evaluation Form
04/07/2025
Procedures
OTG-ZZ-00007
Refueling Preparation, Performance, and Recovery
Miscellaneous
Modification
Package
25-0008
Procedures
APA-ZZ-00322,
Appendix E
Post-Maintenance Test Program
Procedures
Test Procedure for Automated Measurement of Drop Times
of Control and Shutdown Rods in Westinghouse PSRS with
DRPI Power-On
Procedures
Main Feedwater Isolation Valve Inservice Test
Procedures
Turbine Driven Auxiliary Feedwater Pump Inservice Test -
Group B
Procedures
Turbine Driven Auxiliary Feedwater Pump and Check Valve
Inservice Test
Procedures
Auxiliary Feedwater Pump Discharge Check Valve Closure
Test
Procedures
Train A Auxiliary Feedwater Valve Inservice Test
Procedures
Containment Isolation Valve Leak Rate Test
Procedures
OTN-ZZ-00004
Operation of the Leak Rate Monitor (LRM)
Procedures
QCP-ZZ-05041
Visual Examination to ASME VT-2
Work Orders
Jobs
25001164, 22005060, 23512006, 23511787, 23511732,
23511628, 25001164, 23512826, 23512006
Procedures
EIP-ZZ-00101
Classification of Emergencies
Procedures
EIP-ZZ-00101,
Addendum 2
Emergency Action Level Technical Bases
Corrective Action
Documents
Condition Reports
2404415, 202404483, 202404709, 202405036,
2405062, 202405388, 202405710, 202405866,
2406202, 202406303, 202406497, 202406990,
2407007, 202500523, 202500524, 202500712,
2500740, 202501136
Procedures
APA-ZZ-00801
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
APA-ZZ-01000,
Appendix A
Control of Radioactive Material
Procedures
HDP-ZZ-01500
Radiological Postings
Procedures
HTP-ZZ-02004
Control of Radioactive Sources
Procedures
HTP-ZZ-06028
Radiological Controls for Pools that Contain or Store Spent
Fuel
Radiation
Surveys
CA-M-20250406-
Characterization Survey of C RCP
Radiation
Surveys
CA-M-20250407-
Characterization Survey - Container 30031212
Radiation Work
Permits
23004769
Disassemble, Inspect, Clean, and Reassemble Check Valve
EP8956C
Radiation Work
Permits (RWPs)
R27DRCPCOORD
D Reactor Coolant Pump Internals Replacement
Oversite/Coordination Activities
Radiation Work
Permits (RWPs)
R27DRCPINT
All Prep Work for the Removal and Installation Associated
with D Reactor Coolant Pump Internals
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.
Radiation Work
Permits (RWPs)
R27DRCPINTRP
Radiation Protection Coverage for D Reactor Coolant Pump
Internals Replacement. All Work Associated with D Reactor
Coolant Pump Internals.
Radiation Work
Permits (RWPs)
R27FUEL
Offload Reactor, Perform FOSAR, Perform Reactor Reload,
Core Mapping, Insert Shuffle, Pool Mapping, B5B Moves,
and Miscellaneous Support Activities
Calibration
Records
Air Quality Analysis Report for Bauer UNIII/25H-E3, SN
2386
03/27/2025
Calibration
Records
Job 24001284
Calibration Certificate of Temporary HEPA Unit
ID# VAC-4111-HP
04/09/2024
Calibration
Records
Job 24002990
Calibration Certificate of Control Room Emergency Air
Supply Tank ID# MAC-0025-HP
09/05/2024
Calibration
Records
Job 25001058
Calibration Certificate of Temporary HEPA Unit
ID# VAC-4116-HP
03/19/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Reports
2202309, 202202390, 202204037, 202205472,
2205959, 202206137, 202206687, 202206945,
2207201, 202207499, 202207688, 202207869,
2208007, 202208386, 202300634, 202300883,
2302393, 202303626, 202400594, 202401265,
2402782, 202404323, 202405551, 202407056
Drawings
HTP-ZZ-08501-
DTI-AIR TEST
Testing of Breathing Air
Miscellaneous
Certification ID
C020875
Scott Technical Support: SCBA Certified Technician II,
Maintenance and Overhaul - Jeff Eldringhoff
01/24/2025
Procedures
FGK01A Charcoal Test Canister Removal and Lab Testing
Procedures
FGK01B Charcoal Test Canister Removal and Lab Testing
Procedures
FUB7001 Charcoal Test Canister Removal and Lab Testing
Procedures
FUB7001 In-Place Bypass Leakage Test
Procedures
ETP-ZZ-03004
In-Place Bypass Leakage Testing of Adsorber Stage
Procedures
ETP-ZZ-03005
In-Place Bypass Leakage Testing of HEPA Filters
Procedures
HTP-ZZ-08203-
DTI-
REGULATORS
Testing Scott Regulators and Respirators Using the
Biosystems Posichek 3 USB Tester
Procedures
HTP-ZZ-08502-
DTI-MAC-CAL
Scott Mobile Air Cart Calibration
Procedures
HTP-ZZ-08503-
DTI-
UNIIICompressor
Operation of Bauer Unicus III, 25 CFM Breathing Air
Compressor and Breathing Air Cascade System
Work Orders
Job 22509842-500
FGK01B Charcoal Test Canister Removal and Lab Testing
2/13/2024
Work Orders
Job 23506576-500
FGK01A Charcoal Test Canister Removal and Lab Testing
10/15/2024
Work Orders
Job 22507436-500
In-Place Bypass Leakage Testing of Adsorber Stage and In-
Place Bypass Leakage Testing of HEPA Filters for FGK01B
2/07/2023
Work Orders
Job 22510055-500
In-Place Bypass Leakage Testing of Adsorber Stage and In-
Place Bypass Leakage Testing of HEPA Filters for FGK01A
2/18/2023
Work Orders
Job 23500086-500
Radioiodine Penetration / Efficiency Test Report for TSC
Filter Unit FUB7001
05/22/2024
Work Orders
Job 23506199-500
Charcoal Adsorber In-Place Leak Test Report and HEPA
Filter Leak Test Report for TSC Filtering Unit FUB7001
2/16/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
Job 25000432
Posi3 USB Test Results of Regulator APR-0057-HP
2/07/2025
Work Orders
Job 25000433
Posi3 USB Test Results of Regulator APR-0067-HP
2/07/2025
Work Orders
Respiratory
Protection Monthly
Inspections
2507157, 22508202, 22509545, 22511985, 22512620,
2513609, 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
24 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
25
Corrective Action
Documents
Condition Reports
2005276, 202307958, 202308226, 202308929,
2400480, 202406120, 202406164
Procedures
APA-ZZ-00662
ASME Section XI Repair/Replacement Program
Procedures
EDP-ZZ-01007
Mechanical Snubber Program
Work Orders
Jobs
23004837
Corrective Action
Documents
Condition Reports
2501903, 202501946, 202501957, 202501963
Corrective Action
Documents
Condition Reports
2502701