ML25351A235
| ML25351A235 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/18/2025 |
| From: | Ami Agrawal NRC/RGN-IV/DORS/PBB |
| To: | Karenina Scott Union Electric Co |
| References | |
| IR 2025003 | |
| Download: ML25351A235 (0) | |
Text
December 18, 2025 Kent Scott, Senior Vice President, and Chief Nuclear Officer Union Electric Company 8315 County Road 459 Steedman, MO 65077
SUBJECT:
CALLAWAY PLANT - INTEGRATED INSPECTION REPORT 05000483/2025003
Dear Kent Scott:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Callaway Plant. On September 25, 2025, the NRC inspectors discussed the results of this inspection with Erin Smith, Regulatory Affairs Engineer, 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 1, 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 inspection reports that should have been issued by November 13, 2025, to December 31, 2025. The NRC resumed the routine cycle of issuing inspection reports on November 13, 2025.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
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.
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 12/18/25
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE SRI:DORS/PBB SPE:DORS/PBB BC:DORS/PBB NAME NBrown MBloodgood AAgrawal SIGNATURE
/RA/
/RA/
/RA/
DATE 12/17/25 12/18/25 12/18/25
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000483 License Number:
NPF-30 Report Number:
05000483/2025003 Enterprise Identifier:
I-2025-003-0004 Licensee:
Union Electric Company Facility:
Callaway Plant Location:
Steedman, MO Inspection Dates:
July 1 to September 30, 2025 Inspectors:
P. Breidenbach, Operations Engineer N. Brown, Senior Resident Inspector R. Deese, Senior Reactor Analyst S. Hedger, Senior Emergency Preparedness Inspector N. Hernandez, Senior Operations Engineer D. Johnson, Senior Emergency Preparedness Specialist L. Moore, Emergency Preparedness Inspector S. Schwind, Senior Reactor Inspector C. Sigel, 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 the 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. A licensee-identified non-cited violation is documented in report section 71153.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items Type Issue Number Title Report Section Status LER 05000483/2025-002-00 LER 2025-002-00 for Callaway, Unit 1, Reactor Vessel Bottom Head (RVBH)
Bottom Mounted Instrument (BMI) Nozzle Pressure Boundary Leakage 71153 Closed LER 05000483/2025-001-00 LER 2025-001-00 for Callaway, Unit 1, Refueling Water Storage Tank Lowered Below TS 3.5.4 Limit 71153 Closed
3 PLANT STATUS The Callaway Plant began the inspection period shutdown with the plant in Mode 5. On July 5, 2025, the licensee commenced a plant startup. The main generator was synchronized to the grid on July 7 and full power operations resumed on July 10. The plant remained at rated thermal power for the remainder of the inspection period.
INSPECTION SCOPES Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light -Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY 71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1) train A control building HVAC on July 10, 2025 (2) train A 4160V class 1E electrical system on September 9, 2025 (3) train B motor-driven auxiliary feedwater on September 17, 2025 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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) control building 2016' elevation on July 3, 2025 (2) auxiliary building room 1314 on July 18, 2025 (3) auxiliary building elevation 1967'-0", fire area A-2, on August 1, 2025 (4) containment spray pump B and residual heat removal rooms, fire area A-4, on September 5, 2025 (5) emergency diesel generator A room fire area D-1 on September 9, 2025
4 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 brigade drill on August 18, 2025.
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03) (1 Sample)
(1)
The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating test and biennial written exam on September 5, 2025.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
(1)
Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on July 24, 2025.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
5 Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
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 reactor startup on July 5, 2025.
(2)
The inspectors observed and evaluated licensed operator performance in the control room during power ascension and surveillances on July 8, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
(1)
The inspectors observed and evaluated annual scenarios on August 6, 2025.
(2)
The inspectors observed and evaluated annual scenarios on August 11, 2025.
71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (2 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) snubber AB01R512145A on July 22, 2025 (2) steam generator A channel 1 wide range level transmitter found out of tolerance on July 23, 2025 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1) risk management actions during PG210 and PG109 work on July 10, 2025 (2) risk management actions during planned emergency diesel generator A outage on September 15-25, 2025
6 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1) core exit thermocouples not connected correctly on July 21, 2025 (2) power range detector SENI044 on August 7, 2025 (3) power range detector SENI044 on September 2, 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 from the beginning of the inspection period through July 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) (6 Samples)
(1) startup main feed pump on August 11, 2025 (2) spent fuel pool train A cooling pump on August 25, 2025 (3) electrohydraulic control pump A on August 28, 2025 (4) essential service water B on September 10, 2025 (5) power range nuclear instrument SEN0044 on September 12, 2025 (6) emergency diesel generator A on September 25, 2025 Surveillance Testing (IP Section 03.01) (3 Samples)
(1) centrifugal charging pump B on July 9, 2025 (2) emergency diesel generator B slow start and one hour loaded run on July 16, 2025 (3) emergency diesel generator A slow start and one hour loaded run on July 31, 2025 71114.01 - Exercise Evaluation Inspection Review (IP Section 02.01-02.11) (1 Sample)
(1)
The inspectors observed the biennial exercise and evaluated emergency plan performance on September 16, 2025. The exercise scenario involved a simulated seismic event, resulting in multiple aftershocks that caused equipment issues. Leaks in several systems occurred, along with a loss of alternating current power sources except from a single emergency diesel generator. Reactor fuel clad damage, a faulted and ruptured steam generator, and damage to the containment structure resulted in a simulated radiological release from the site.
7 71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03) (1 Sample)
(1)
The inspectors evaluated the Callaway Plant Radiological Emergency Response Plan, revision 57, that was submitted to the NRC on December 12, 2024 (ML24347A120 through ML24347A122).
Screenings and evaluations associated with the 10 CFR 50.54(q) emergency plan change process were reviewed as well. These evaluations do not constitute NRC approval.
71114.08 - Exercise Evaluation - Scenario Review Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
(1)
The inspectors reviewed the licensee's preliminary exercise scenario that was submitted to the NRC on July 16, 2025 (ML25197A790 and ML25197A791), for the exercise scheduled on September 16, 2025. The inspectors discussed the preliminary scenario comments with D. Harris, Manager, Emergency Preparedness, and other members of the emergency preparedness staff on August 6, 2025. The inspectors' review does not constitute NRC approval of the scenario.
OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
(1)
April 1, 2024, through June 30, 2025 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13)
(1 Sample)
(1)
April 1, 2024, through June 30, 2025 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14)
(1 Sample)
(1)
January 1, 2025, through June 30, 2025 71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated a loss of engineered safety features safety function and the licensees response on September 11, 2025.
8 Event Report (IP Section 03.02) (2 Samples)
The inspectors evaluated the following licensee event reports (LERs):
(1)
LER 2025-001-00, Refueling Water Storage Tank Lowered Below TS 3.5.4 Limit, ADAMS Accession Number 25182A246. The inspection conclusions associated with this LER are documented in the Inspection Results section of this report. This LER is closed.
(2)
LER 2025-002-00, Reactor Vessel Bottom Head (RVBH) Bottom Mounted Instrument (BMI) Nozzle Pressure Boundary Leakage, Adams Accession Number ML25183A213. The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct and therefore was not reasonably preventable. No performance deficiency or violation of NRC requirements was identified. This LER is closed.
INSPECTION RESULTS Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Technical Specification (TS) 3.5.4, Refueling Water Storage Tank (RWST) requires, in part, that the borated water level remain above a minimum of 394,000 gallons (93.7 percent). Contrary to TS 3.5.4, from 12:30 p.m. to 1:40 p.m. on May 4, 2025, the RWST borated water level was below the minimum level of 394,000 gallons. Specifically, in Mode 4, and using the RWST to provide makeup water to the volume control tank (VCT) while flushing the chemical and volume control system (CVCS) train B mixed bed demineralizer (FGB03B),
the RWST level reached a level of 391,596 gallons (93.1 percent) of borated water.
Significance/Severity: Green. Failure to maintain the RWST level above the required TS limit was a performance deficiency. Inspectors determined this performance deficiency was more than minor, and therefore, a finding, because it was associated with 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. Inspectors assessed the significance using IMC 0609, Attachment 4, SDP screening which refers to IMC 0609, Appendix G, Shutdown Operations Significance Determination Process, Attachment 1, Exhibit 3, for Mitigating Systems. The finding was determined to be of very low safety significance (Green) because it did not: 1. involve a deficiency affecting the design or qualification of a mitigating SSC, 2. represent a loss of system safety function, 3. represent an actual loss of safety function, 4. represent an actual loss of safety function of one or more non -TS trains of equipment during shutdown designated as risk-significant (e.g., 10 CFR 50.65), for greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 5. degrade RCS level indication and/or core exit thermal couples (CETs) when the cavity is not flooded,
- 6. involve an open, cold leg penetration without an adequate, large hot leg vent path, or
- 7. involve a seismic, flooding, or severe weather initiating event, or 8. involve issues related to fire protection, fire brigade, fire hoses, fire extinguishers, or hose stations.
Corrective Action References: Condition Report 202503105; Licensee Event Report 2025-001-00, Refueling Water Storage Tank Lowered Below TS 3.5.4 Limit, Adams Accession Number ML2512A246.
9 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On September 25, 2025, the inspectors presented the integrated inspection results to E. Smith, Regulatory Affairs Engineer, and other members of the licensee staff.
On August 6, 2025, the inspectors presented the emergency preparedness exercise scenario review inspection results to D. Harris, Manager, Emergency Preparedness and other members of the licensee staff.
On November 20, 2025, the inspectors presented the emergency preparedness exercise inspection results to T. Hart, Senior Director, Plant Operations and Plant Manager and other members of the licensee staff.
10 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date OSP-AL-00001, Checklist 1 AFE Manual and Power Operated Valve Alignment 10 OSP-NB-00001 Class 1E Electrical Source Verification 49 OSP-NB-00001, Checklist 1 Train A Electrical Source Verification Outside Control Room 20 71111.04 Procedures OTN-GK-00001, Checklist 2 Control Building HVAC Normal System Lineup 15 KC-46 Detailed Fire Modeling Report Fire Compartment: A-4 Safety-Related Pump Area, Auxiliary Building, El. 1974' 1
KC-48 Detailed Fire Modeling Report for Fire Area A-8 3
KC-82 Auxiliary Building Safety Related Pump Area 2
KC-84 Fire Safety Analysis Calculation: KC-84 Fire Area A-4 Auxiliary Building Safety-Related Pump Area 2
KC-149 Diesel Generator A, Diesel Generator Building El. 2000 3
Calculations M-FL-08 Determine Flood Levels in Control Building Rooms 3401, 3406, 3301, 3302, 3403, 3404, 3405, 3407, 3408, 3409, 3410, 3411, 3412, 313, 3414, 3415, 3416, 3605 6
Corrective Action Documents Condition Reports 202504304 2nd Quarter Announced Fire Drills Miscellaneous Fire Preplan Manual 43 APA-ZZ-00703 Fire Protection Operability Criteria and Surveillance Requirements 5
OTO-KC-00001, Addendum A-04 Auxiliary Building - 1974' - 'B' Train ECCS Pump Rooms 1
OTO-KC-00001, Addendum C-13 Control Building 2016' Access Control and Equipment A/C Units Room Number 2 3
OTO-KC-00001, Addendum C-14 Control Building 2016' Access Control and Electrical Equipment A/C Units Room 3
71111.05 Procedures OTO-KC-00001, Addendum C-15 Control Building 2016' Switchboard and Battery Rooms 2 and 4 3
11 Inspection Procedure Type Designation Description or Title Revision or Date OTO-KC-00001, Addendum C-16 Control Building 2016' Switchboard and Battery Rooms 1 and 3 3
OTO-KC-00001, Addendum C-17 Control Building 2016' Electrical Chase South 2
OTO-KC-00001, Addendum C-18 Control Building 2016' Electrical Chase North 2
OTO-KC-00001, Addendum C-19 Control Building 2016' Cable Chase A (North) 2 OTO-KC-00001, Addendum C-20 Control Building 2016' Electrical Chase South 2
71111.11A Miscellaneous IP 71111.11 Table 03.03-1 Results Table for Annual Exam 09/05/2025 Corrective Action Documents Condition Reports 202403710, 202503105, 202504727 Licensed Operator Medical Records (6 total) 2025 LOCT Biennial Written Exam #2 All Written RO and SRO Exams (6 weeks) are Stand Alone Exams. No Overlaps.
0 CTM-CRC Curriculum Review Committee (CRC) Meeting Agenda &
Minutes for 6/25/25 7
Miscellaneous Simulator Oversight Group Meeting Minutes Simulator Oversight Meeting Dated March 20, 2025 03/20/2025 71111.11B Procedures TDP-ZZ-00019 APPENDIX A Simulator Security Guidelines 52 Miscellaneous Training Plan T61.0810 8 Callaway Energy Center Simulator Differences 07/31/2025 ISF-SE-0N41A Special Fctnal-Nuc; Nuc Inst Pwr Rng N41 32 OSP-BG-V0004 Excess Letdown Values Position Indication Test 13 OTG-ZZ-00001 Plant Heatup Cold Shutdown to Hot Standby 98 OTG-ZZ-00002 Reactor Startup - IPTE 64 OTG-ZZ-00003 Plant Startup - IPTE Hot Zero Power to 30% Power - IPTE 66 OTG-ZZ-00004 Power Operation 104 71111.11Q Procedures OTS-SF-00002 Control Rod Exercising for CRUD Mitigation - IPTE 6
12 Inspection Procedure Type Designation Description or Title Revision or Date 71111.12 Corrective Action Documents Condition Reports 202501370, 202501744 Drawings 8618-X-94747 A.C. Station Service 44 Miscellaneous RICT-2025-04 Procedures APA-ZZ-00315 Risk Management Actions 19 71111.13 Work Orders Jobs 25003276, 20254820 Corrective Action Documents Condition Reports 202504510, 202504836, 202505337 Procedures ETP-BB-03138 Disassembly of the Core Exit Thermocouple Nozzle Assembly (CETNA) 30 71111.15 Work Orders Jobs 25003601 OTG-ZZ-00001 Plant Heatup Cold Shutdown to Hot Standby 98 OTG-ZZ-00002 Reactor Startup - IPTE 64 71111.20 Procedures OTG-ZZ-00003 Plant Startup Hot Zero Power to 30% Power - IPTE 66 Corrective Action Documents Condition Report 202505503 OSP-BG-P005B Centrifugal Charging Pump B Inservice Test - Group B 63 OSP-EF-P001B ESW Train B Inservice Test 91 OSP-NE-0001A Standby Diesel Generator A Periodic Tests 71 OSP-NE-0001B Standby Diesel Generator Periodic Tests 71 OSP-SA-2413B Train B Diesel Generator and Sequencer Testing 39 OTN-CH-00001 Main Turbine Control Oil System 22 OTN-CH-00001, Addendum 1 EHC Hydraulic Pump Rotation and Standby Pump Test 2
Procedures OTN-EC-00001 Fuel Pool Cooling and Cleanup System 44 71111.24 Work Orders Jobs 24503661, 25507583, 25000197, 25506195, 24509979, 24508814, 24508855, 25003276, 25502662, 20512036, 24003682 Corrective Action Documents Condition Reports 202301262, 202301431, 202302813, 202305035, 202305887, 202404610, 202407206, 202502701, 202505635, 202505636, 202505638, 202505694, 202505698 71114.01 Corrective Action Documents Condition Reports 202505920, 202505922
13 Inspection Procedure Type Designation Description or Title Revision or Date Resulting from Inspection Miscellaneous 2025 NRC IPX Graded Exercise Critique Summary, September 16-17, 2025 9/25/2025 EIP-ZZ-00102 Emergency Implementing Actions 71 EIP-ZZ-00201 Notifications 56 EIP-ZZ-00201 Addendum A Control Room Notification Flowchart 42 EIP-ZZ-00201 Addendum C EOF Notification Package 41 EIP-ZZ-00211 Field Monitoring 41 EIP-ZZ-00212 Protective Action Recommendations 33 EIP-ZZ-00240, Addendum E Health Physics Coordinator (HPC) Checklist 25, 29 EIP-ZZ-01211 Accident Dose Assessment 45 Procedures EIP-ZZ-C0010, Addendum D Dose Assessment Coordinator (DAC) Checklist 19, 22 Work Orders Jobs 23002434 EP Tracking Number: 202429 50.54(q) Screening Form, Document: RERP Revision 057, Radiological Emergency Response Plan 11/13/2024 EP Tracking Numbers:
2024026A and -B 50.54(q) Screening and Evaluation Forms; Document: KSP-ZZ-00102, Monthly Emergency Communications System Testing, Revision 022 10/8/2024 Miscellaneous ULNRC-06909 Docket Numbers 50-483; Callaway Plant Unit 1; Union Electric Co.; Renewed Facility Operating License NPF-30; Radiological Emergency Response Plan (RERP),
Revision 057 12/12/2024 71114.04 Procedures KDP-ZZ-00400 RERP Impact Evaluation and Changes 31 ULNRC-06797 Docket Number 50-483, Callaway Plant Unit 1; Union Electric Co.; Renewed Facility Operating License NPF-30; 2023 Callaway RERP Exercise 2/16/2023 71114.08 Miscellaneous ULNRC-06955 Docket Numbers 50-483, Callaway Plant Unit 1; Union Electric Co.; Renewed Facility Operating License NPF-30; 2025 Callaway RERP Exercise 7/16/2025
14 Inspection Procedure Type Designation Description or Title Revision or Date EIP-ZZ-00101 Addendum 2 Emergency Action Level Technical Bases Document 19 Procedures EIP-ZZ-00212 Protective Action Recommendations 33 Corrective Action Documents Condition Reports 202404365, 2020405725, 202405794, 202406460, 202406533, 202504535, 202504600, 202504685 Callaway Energy Center - Muster Meeting Drill Report 2Q2024, 3Q2024, 4Q2024 Callaway Participation Matrix (ERO Participation) 2Q2024, 3Q2024, 4Q2024, 1Q2025, 2Q2025 DEP Calculation Sheets 2Q2024, 3Q2024, 4Q2024, 1Q2025, 2Q2025 DEP Worksheets 2nd Quarter 2024, 3rd Quarter 2024, 4th Quarter 2024, 1st Quarter 2025, 2nd Quarter 2025 ERO Training Drill Report January 9 - February 13, 2025 ERO Training Drill Report January 4 - February 8, 2024 ERO Training Drill Report September 19 - October 24, 2024 LOCT Cycle 24-3 Drill Report Miscellaneous NRC IPX Dress Rehearsal Drill Report 71151 Procedures KDP-ZZ-02000 NRC Performance Indicator (PI) Data Collection 25 Corrective Action Documents Condition Report 202505521 Drawings E-23BG11E Charging Pump to Reactor Coolant and Miniflow Isolation Valve BGHV8110 0
71153 Procedures ODP-ZZ-00001, Shift Manager Communications 33
15 Inspection Procedure Type Designation Description or Title Revision or Date Addendum 13 OSP-BG-V001A Chemical and Volume Control Train A Valve Inservice Test 47 Work Orders Jobs 25003653