ML25218A046
| ML25218A046 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/06/2025 |
| From: | Dariusz Szwarc NRC/RGN-III/DORS/RPB3 |
| To: | Hafen S Northern States Power Company, Minnesota |
| References | |
| IR 2025002 | |
| Download: ML25218A046 (1) | |
Text
Shawn Hafen Site Vice President Monticello Nuclear Generating Plant Northern States Power Company, Minnesota 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000263/2025002
Dear Shawn Hafen:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Monticello Nuclear Generating Plant. On July 16, 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.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Dariusz Szwarc, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket No. 05000263 License No. DPR-22
Enclosure:
As stated cc: Distribution via LISTSERV August 6, 2025 Signed by Szwarc, Dariusz on 08/06/25
Letter to Shawn Hafen from Dariusz Szwarc dated August 6, 2025.
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000263/2025002 DISTRIBUTION:
Tim Steadham RidsNrrDorlLpl3 RidsNrrPMMonticello RidsNrrDroIrib Resource Jack Giessner Mohammed Shuaibi Diana Betancourt-Roldan John Pelchat Jared Heck Jennifer Dalzell R3-DORS ADAMS Accession Number: ML25218A046
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE RIII NAME DSzwarc:anm DATE 08/06/2025 OFFICIAL RECORD COPY
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000263 License Number:
DPR-22 Report Number:
05000263/2025002 Enterprise Identifier:
I-2025-002-0058 Licensee:
Northern States Power Company, Minnesota Facility:
Monticello Nuclear Generating Plant Location:
Monticello, MN Inspection Dates:
April 01, 2025, to June 30, 2025 Inspectors:
Z. Fleming, Project Engineer T. Hartman, Senior Resident Inspector C. Norton, Senior Resident Inspector S. Orth, Senior Health Physicist E. Rosario, Trans & Storage Safety Inspector Approved By:
Dariusz Szwarc, Chief Reactor Projects Branch 3 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 Monticello Nuclear Generating 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 No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
3 PLANT STATUS The unit began the inspection period at full achievable power as they were coasting down toward the refueling outage. The following power changes were performed during the inspection period:
On April 2, 2025, the licensee reduced power to approximately 83 percent power for a routine rod pattern adjustment. Power was subsequently restored to full achievable power the same day.
On April 3, 2025, the licensee reduced power to approximately 85 percent to clean the main condenser tubes. On April 4, 2025, the licensee increased power to full achievable power.
On April 9, 2025, the licensee reduced power to approximately 76 percent for a routine rod pattern adjustment. Power was subsequently restored to full achievable power the same day.
On April 18, 2025, the licensee shutdown the unit and began refueling outage 32.
Following completion of the refueling outage, the reactor was restarted and taken to critical on May 24, 2025. The unit reached full power operation on May 27, 2025.
On June 1, 2025, the licensee commenced a shutdown to replace the C safety relief valve. The licensee restarted the reactor and reached approximately 30 percent power on June 4, 2025. The licensee held power steady at around 30 percent until June 9, 2025, when they increased power to 100 percent.
The unit remained at or near 100 percent 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 onsite 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 71111.01 - Adverse Weather Protection Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of summer temperatures for emergency diesel generators (EDGs) and safety-related bus 15
4 Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the adequacy of the overall preparations to protect risk significant systems from impending severe weather including lightning and tornado watch on May 15, 2025 71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
Division 2 control room ventilation/emergency filtration train (CRV/EFT) system on April 8, 2025 (2)
Division 1 EDG starting air system on May 15, 2025 (3)
Reactor core isolation cooling (RCIC) system on May 20, 2025 (4)
Control rod drive hydraulic control units, banks 1 and 4 on May 21, 2025 Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated system configurations during a complete walkdown of the standby liquid control system on May 20, 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)
Fire Zone (FZ) 17, turbine building north cable corridor 941' on April 2, 2025 (2)
FZ 16, corridor, turbine building east & west (elevations 911' and 931'),
on April 3, 2025 (3)
FZ 9, control room on April 4, 2025 (4)
FZ 2B, east hydraulic control unit (HCU) area on April 7, 2025 (5)
FZ 19C, feedwater pipe chase on April 9, 2025 Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on April 6, 2025 71111.06 - Flood Protection Measures Flooding Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated internal flooding mitigation protections outside the lower 4kV room
5 71111.07A - Heat Exchanger/Sink Performance Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1)
Main condenser during dredging of service water intake bay on April 07, 2025 71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01) (1 Sample)
The inspectors evaluated boiling-water reactor nondestructive testing, flaw evaluation, and welding activities by reviewing the following examinations from April 21, 2025, to May 22, 2025:
(1) 1.
Visual examinations of reactor recirculation (RR) seismic support and restraint for component identifications (IDs): H6, H10, and H11 2.
Visual examinations of main steam (MS) valve internal surfaces and bolts for component IDs: V4 and B8 3.
Visual examinations of the reactor vessel internals associated with the InVessel Visual Inspections (IVVI) 4.
Relevant indication to BWRVIP18 Rev. 2A accepted for continued service on pipe to junction box weld of core spray piping component ID: CSP-P3a 5.
Ultrasonic examination of the RR pipe-topipe weld component IDs:
W23 LS U and W30 LS U 71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(1 Sample)
(1)
The inspectors observed and evaluated licensed operator performance in the control room during control rod pattern adjustment on April 2, 2025 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated just in time training (JITT) for reactor startup and reactor vessel pressure test in the simulator on April 15, 2025 71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)
Drywell structure walkdown during refueling outage on April 24, 2025
6 (2)
Licensee actions after failure to schedule monthly division 2 diesel generator surveillance test outside the division 1 emergency bus maintenance window on April 29, 2025 (3)
Removal of load test cart for Y81 inverter replacement on May 05, 2025 Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
(1)
Work Order 7001285290075, Replacing safety-related 200 Amp fuse with 150 Amp fuse on April 30, 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 for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1)
Secondary containment reactor building equipment hatch operation on April 03, 2025 (2)
Failure of Division 2 control room ventilation recirculation fan damper to modulate on April 08, 2025 (3)
Torus instrument air isolation valve exercise on April 08, 2025 (4)
Control rod drive (CRD) changeout on May 03, 2025 (5)
Planning and risk management of manually backseating high pressure core injection (HPCI) inboard isolation valve (MO2034) on May 20, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
(1) 501000096997, VD9175B not functioning properly (2) 501000096788, Recirculation inboard sample valve failed diagnostic test (3) 501000099278, Alternate N2 relief valve leaking 71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1)
For over 90 days, HPCI pressure gauge PI23117 not reading properly and is compensated by a temporary flow meter for the purpose of ensuring the line is full of water
7 (2)
Placement of a jumper to temporally allow opening the RR system out board sample valve while a Group 1 Isolation signal is inserted Severe Accident Management Guidelines Update (IP Section 03.03) (1 Sample)
(1)
The inspectors verified the site Severe Accident Management Guidelines were updated in accordance with the BWR generic sever accident technical guidelines and validated in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, Revision 1.
71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)
(1)
The inspectors evaluated refueling outage activities for RFO32 from April 18, 2025, to May 23, 2025.
(2)
The inspectors evaluated forced outage FO3301 to replace the C safety relief valve from June 1, 2025, to June 3, 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) (17 Samples)
(1)
Work Order (WO) 7001360850070, A reactor protection system (RPS)
MG set after installation of temporary power supply modification on April 1, 2025 (2)
WO 7001285290095, Load test after Y81 inverter replacement on May 04, 2025 (3)
WO 7000409790020, EDG 11 governor after replacement on May 4, 2025 (4)
WO 7001140080020, Emergency service water pump 11, following preventive maintenance on May 4, 2025 (5)
WO 7000725210050, Stack gas dilution fan inlet damper, following preventive maintenance on May 5, 2025 (6)
WO 70012072220040, RCIC steam line inboard isolation valve, MO2075, following preventive maintenance on May 5, 2025 (7)
WO 7000409790020, EDG 11 governor after second replacement on May 06, 2025 (8)
WO 7000770560140, EDG 11 voltage regulator after replacement on May 06, 2025 (9)
WO 7001418960030, Recirc sample line inboard isolation valve, MO2790, following preventive maintenance on May 08, 2025 (10)
WO 7001134250020 PMT of core spray pump 11 discharge check valve after maintenance on May 9, 2025 (11)
WOs 700090273005, 700135316100, and 700113996040 Stroke timing division 1 LPCI inboard injection valve for partial PMT following maintenance on May 9, 2025 (12)
Various WOs, Final PMTs of control rod drives following maintenance that included drive replacements and HCU hydraulic control unit maintenance on May 13, 2025.
(13)
WO 7001224820070, Control rod drive timing test after CRD replacements on May 13, 2025 (14)
WO 7001380240110, Inboard main steam isolation valve local leak rate testing on May 13, 2025
8 (15)
WO 7001208290040, HPCI outboard isolation local leak rate testing after maintenance on May 14, 2025 (16)
WO 7001207010020, Outboard main steam isolation valve (MSIV) 11 after maintenance on May 14, 2025 (17)
WO 7001207530030, Drywell personnel airlock interlock test after interlock restoration on May 23, 2025 Surveillance Testing (IP Section 03.01) (4 Samples)
(1) 0003, Drywell high pressure scram and group 2, 3, & SCTMT isolation test and calibration on April 14, 2025 (2) 013702-06, Primary containment double-gasketed seals local leak rate testing (LLRT) on April 28, 2025 (3) 013727, Transversing incore probe (TIP) system isolation valves pressure and LLRT on April 28, 2025 (4)
OSP-RHR0564, LPCI swing bus test on May 7, 2025 Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1) 0214, Drywell-tosuppression chamber vacuum breaker cycle pressure and leakage test, on May 23, 2025 Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
(1)
Outboard main steam isolation valves A and B LLRT on April 19, 2025 Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
(1)
WO 7001205450035, Portable fire pump operation on April 29, 2025 71114.06 - Drill Evaluation Required Emergency Preparedness Drill (1 Sample)
(1)
Hostile action based drill on June 17, 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, identifies the concentrations and quantities of radioactive materials, and assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
9 Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)
Workers exiting the radiologically controlled area (RCA)
(2)
Workers exiting the drywell access point Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensees control of radiological hazards for the following radiological work:
(1) 1R32 - Torus - diving - inspect/clean (RWP 255119) and associated as low as reasonably achievable (ALARA) plan (2) 1R32 - Reactor water cleanup (RWCU) E201C heat exchanger (HX) repair (RWP 255121) and associated ALARA plan (3) 1R32 - RWCU - Replace drain pipes & RC valve (RWP 255126) and associated ALARA plan (4) 1R32 - Drywell (DW) CRD changeout (RWP 255509) and associated ALARA plan 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:
(1)
Reactor building 935' TIP cubicle (Door 60)
(2)
Reactor building 935' drywell access area (3)
Material stored within the spent fuel pool (control of suspension lines)
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 - InPlant Airborne Radioactivity Control and Mitigation Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
(1)
Reactor building 1027' reactor head stand (2)
Reactor building 962' reactor water cleanup area Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
(1)
The inspectors evaluated the licensees use of respiratory protection devices.
10 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures Sample (IP Section 02.04) (1 Sample)
(1)
April 01, 2024, through March 31, 2025 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
(1)
May 01, 2024, through March 31, 2025 BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
(1)
April 01, 2024, through March 31, 2025 OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
May 01, 2024, through March 31, 2025 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
(1)
May 01, 2024, through March 31, 2025 71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
Licensee failure to promptly identify portions of the reactor pressure vessel (RPV) exceeded the limiting cooldown rate specified in the Pressure Temperature Limits Report (2)
The licensees inability to manually open rollup doors of FLEX buildings
11 INSPECTION RESULTS Observation: Corrective Actions to Address Procedural Deficiencies in Monitoring Reactor Pressure Vessel Cooldown Rates 71152A On February 28, 2024, following a reactor scram accompanied by a trip of the recirculation pumps, the licensee did not promptly identify that the reactor vessel (RPV) bottom exceeded the limiting cooldown rate specified in the pressure temperature limits report. As a result, the licensee did not complete the required technical specification action to determine if the reactor coolant system was acceptable for continued operation prior to starting the reactor and progressing to Mode 1. A non-cited violation for this issue was documented in Inspection Report 2024002. The inspectors selected this sample to follow up on the licensees corrective actions in response to the issue.
The licensee subsequently determined that procedure 0118, Reactor Vessel Temperature Monitoring, utilized a computer program that monitored only RPV belt line temperature during cool down but did not account for the RPV temperature stratification that occurs without recirculation. Corrective actions included modifying procedure 0118 to monitor temperatures for the entire RPV and display the point with the highest cool down rate.
On April 19, 2025, the inspectors observed the licensee cool down the RPV for RFO 32 utilizing the revised 0118. The cool down rate for all points on the RPV was monitored and the point with the highest cooldown rate prominently displayed. The inspectors identified no issues of concern associated with the licensees corrective actions.
Observation: Corrective Actions to Address Inability to Manually Open FLEX Building Doors 71152A On November 17, 2021, the licensee identified that the rope used to manually open the rollup doors of the FLEX building was missing. During loss of offsite power or station blackout, the inability to quickly open the rollup doors manually could hinder the ability to use the FLEX equipment as designed. The inspectors selected this issue as a sample based on the importance of the FLEX equipment and the strategies that could potentially be impacted by the identified issue.
Corrective actions included replacing the rope used to manually open the doors, as well as modifying OSP-FIR1489, B.5.B/FLEX Equipment Inventory, to include verification of the ability to manually open the rollup doors.
On April 29, 2025, the inspectors observed an inventory of FLEX equipment and verified the presence of the rope and the use of the updated inventory sheet. The inspectors identified no issues of concern and assessed that the corrective actions were adequate.
12 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On July 16, 2025, the inspectors presented the integrated inspection results to S. Hafen, Site Vice President, and other members of the licensee staff.
On April 24, 2025, the inspectors presented the radiation protection inspection results to S. Hafen, Site Vice President, and other members of the licensee staff.
On May 22, 2025, the inspectors presented the inservice inspection activities for Monticello M1R32 outage inspection results to S. Hafen, Site Vice President, and other members of the licensee staff.
13 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Miscellaneous OWI01.01 Operations Group Organization and Responsibility Assignments 54 602000034760 1444, Pre and Post Severe Weather Inspection Checklist 24 7001349890010 1150, Summer Checklist 91 71111.01 Procedures A.6 Act of Nature 64 Corrective Action Documents Resulting from Inspection 501000099079 RCIC Barometric Cond Insulation Damage 05/20/2025 NH170037 Main Control Room CRV/EFT System 84 Drawings NX92164 Monticello Nuclear Generating Plant Air Starting System E
215407 Standby Liquid Control System Prestart Valve Checklist 14 215413 RCIC System Prestart Valve Checklist 32 71111.04 Procedures 215437 Control Rod Drive System Prestart Valve and Hydraulic Control Unit Checklist 7
STRATEGY A.302-B Fire Zone 2B, East HCU Area 15 STRATEGY A.309 Fire Zone 9, Control Room 11 STRATEGY A.316 Fire Zone 16, Corridor, Turbine Building East & West (Elevations 911' and 931')
20 STRATEGY A.317 Fire Zone 17, Turbine Building North Cable Corridor 941' 7
STRATEGY A.319-C Fire Zone 19C, F.W. Pipe Chase 8
Fire Plans STRATEGY A.343 Fire Zone 43, Compressed Air Building 5
71111.05 Miscellaneous A.343 Fire Brigade Drill Guide, 17 Compressor B Cooling Pump Motor Fire, Drill Guide 43.01 04/06/2025 71111.06 Procedures Ops Man B.09.0605 G.15. Operation of the HELB Flood Barrier Lower 4kV 63
14 Inspection Procedure Type Designation Description or Title Revision or Date Engineering Changes EC 6030000001641 DBD-S.04 Intake Structure 7
4125PM East Service Water Bay Inspection/Dredging 26 71111.07A Procedures 4126PM West Service Water Bay Inspection/Dredging 27 501000097684 Light Particulate Inside Reactor Vessel 04/23/2025 501000097737 Bent Lift Tab on Jet Pump 15 WD1 04/25/2025 501000097771 Welded Attachment Drawing Discrepancy 04/25/2025 501000097842 RFO32 IVVI Indication: Core Spray P3a 04/25/2025 Corrective Action Documents 501000097996 RFO32 IVVI Indication: TGGB 04/29/2025 Drawings PEI01.02.04 Recirculation Loop A ISI Isometric Drawings (Figure 5.2) 4 MN25UT-003 Ultrasonic Examination of RR Pipe-toPipe Component ID:
W23 LS U 04/24/2025 MN25UT-004 Ultrasonic Examination of RR Pipe-toPipe Component ID:
W30 LS U 04/24/2025 MN25VT-013 Visual Examination (VT3) of RR Clevis, Lugs, and Constant-Support Component ID: H6 04/25/2025 MN25VT-014 Visual Examination (VT3) of RR Sway Brace Component ID: H11 04/25/2025 MN25VT-015 Visual Examination (VT3) of RR Double Spring and Lugs Support Component ID: H10 04/25/2025 MN25VT-016 Visual Examination (VT1) of MS Valve Bolts Component ID:
B8 04/26/2025 MN25VT-017 Visual Examination (VT3) of MS Valve Internal Surfaces Component ID: V4 04/26/2025 NDE Reports MN25VT-028 Visual Examination (VT1) of New MS Valve Bolts Component ID: B8 05/01/2025 FPPE-NDE402 Ultrasonic Examination of Austenitic Pipe Welds 8
PDI-UT2 Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds J
71111.08G Procedures PEI02.05.05 Vessel Examination of Monticello Reactor Vessel Interior 7
71111.11Q Miscellaneous SEG MTLOR-JIT20250025 Startup JITT 1
15 Inspection Procedure Type Designation Description or Title Revision or Date SEG MTLOR-JIT20250115 Reactor Vessel Pressure Test 0
2300 Reactivity Adjustment 28A Procedures C.205 Power Operation 84C Engineering Evaluations MT2025EDG06 Stride to Extend the Emergency Diesel Generator (EDG)
Monthly Test Frequency 04/30/2025 3487 Drywell Entry Checklist 15 Procedures FPOP-SFCP01 Surveillance Frequency Control Program 5
Radiation Work Permits (RWPs) 255500 1R32 - DW GENERAL ACTIVITIES 04/24/2025 7001285290075 Replace 200A Fuse With 150A Fuse 04/30/2025 71111.12 Work Orders 7001285290095 Y81 Inverter Replacement 3
501000096997 VD9175B Not Functioning Properly 04/07/2025 Corrective Action Documents 501000098321 Incorrect information on 2270 05/04/2025 NH170037 Main Control Room CRV/EFT Systems 84 Drawings NH170037 Main Control Room CRV/EFT System 80 Miscellaneous Operating Instruction Placard for Railroad Doors in Reactor Building 04/03/2025 025517-IA1 Instrument Air System Valve Exercise 44 2270 Critical Safety System Checklist 24 3487 Drywell Entry Checklist 15 602000038003 9309, Changeout Selected CRDs - Maintenance 46 9007 Procedure for Moving Fuel Into, Out of, and Within the Core 56 FPIH-SAF01 Heat and Cold Stress Control Guidelines 8
Procedures Ops Man D.205 Reactor and Core Components Handling Equipment 38 71111.13 Work Orders 7001401230040 HPCI Steam Line Isolation Inboard, Manually Backseat Valve for 900# Inspection 0
501000087225 MO 2012 Failed to Cycle as Expected 06/28/2024 501000094127 MO 2012 Past Operability 04/03/2025 501000096788 Recirculation Inboard Sample Valve Failed Diagnostic Test 04/02/2025 501000096997 VD9175B Not Functioning Properly 04/07/2025 71111.15 Corrective Action Documents 501000099278 Alt N2 Relief Valve Leaking 05/26/2025
16 Inspection Procedure Type Designation Description or Title Revision or Date Corrective Action Documents Resulting from Inspection 501000099416 Calculation Error in AN2 Leak Analysis 05/29/2025 501000093404 HPCI Pressurizing Station Low Pressure 12/17/2024 Corrective Action Documents 501000096952 104701 50.59 Review Required 04/04/2025 Drawings NH36250 P&ID (Water Side) High Pressure Coolant Injection System 87 71111.18 Procedures 8154, page 90 Installation of Electrical Jumpers/Block to Allow Stroking of MOVs 20 025520-IIC1 Reactor Coolant Pressure Boundary Leakage Test 56 2167 Plant Startup 112 2204 Plant Shutdown 84 2270 Critical Safety System Checklist 24 9267 Tension RPV Studs 38 Procedures 9292 Clean Reactor Pressure Vessel Head Flange And replace ORings 16 71111.20 Self-Assessments 602000022178 QF1123, Shutdown Safety Assessment Contingency Planning Form 3
Corrective Action Documents 501000098076 FLEX Equipment Missing 04/30/2025 Corrective Action Documents Resulting from Inspection 501000098031 Inconsistent Guidance in 0137 Procedure 04/29/2025 Drawings NX783467-7 Reactor Protection System 80 Engineering Evaluations 602000027874 QF0957, IST Evaluation / 96 Hour Evaluation / Rebaseline 05/08/2025 0003 Drywell, High Pressure Scram and Group 2, 3, & SCMT Isolation Test and Calibration Procedure 37 0074 Control Rod Drive Exercise 73 0075 Control Rod Drive Coupling Test 20 71111.24 Procedures 013702-06 X35A, X35B, X35C, X35D & X35E Primary Containment Double-Gasketed Seals Local Leak Rate Test 0
17 Inspection Procedure Type Designation Description or Title Revision or Date 013707A Reactor Steam Supply Valves Leak Rate Testing 46 013727 TIP System Isolation Valves Pressure and Local Leak Rate Test 29 0214 Drywell-toSuppression Chamber Vacuum Breaker Cycle Pressure and Leakage Test 30 025503-IA11 Core Spray Loop A Quarterly Pump and valve Tests 69 025507-IA2 Main Steam Isolation Valve Functional Checks Test 46 1022 CRD-Withdrawal Stall Flow Test 21 1054 Control Rod Drive Normal Drive Timing Test 27 1427 CRD-Insert Stall Flow Test 11 417103-PM Off Gas Dilution Fan Damper Position 4
602000010244 456102-OCD, Uninterruptible Power Supply Inverter (Y81) 14 9019 Changeout Selected CRDs - Operations 35 9051 Changeout Selected CRDs-Operations 8
B.08.0805 11 Emergency Diesel Generator Start Up 64 B.09.1205 Reactor Protection Power Supplies 35 ESP-MST013707E Reactor Steam Supply Valve Line Leak Rate Test 0
G4A 11 RPS MG Set 480 VAC Supply 1
NSP-MSC0137F LLRT-LRM-Makeup Flow Method (Graftel 96237) 0 NSP-MSC0137G LLRT-LRM-Makeup Flow Method (Graftel EV) 0 OSP-RHR0564 LPCI Swing Bus Test 6
7000409790020 11 Emergency Diesel Generator Governor PMT 0
7000725210050 Stack Gas Dilution Fan Inlet Damper, VD8000J29 Post-Maintenance Test 0
7000770560140 11 EDG Voltage Regulator Replacement 5
7001140080020 11 Emergency Service Water Pump Discharge Check Valve PMT 2
7001205450035 Use P505 Portable Fire Pump to Pressurize Fire Header 04/27/2025 7001207010020 11 OTBD MSIV 0
70012072220040 RCIC Steam Line Inboard Isolation, MO 2075 0
Work Orders 7001207530030 0447, Primary Containment Personnel Airlock Interlock Test 9
18 Inspection Procedure Type Designation Description or Title Revision or Date 7001208290040 HPCI Steam Line Isolation Outboard 1
7001224820070 Master PMT for CRD 05/13/2025 7001285290095 Y81 Inverter Replacement 3
700135316 PMT RHR DIV 1 LPCI INJ INBBD 1
7001360850070 Monticello Nuclear Generating Plant PMT/RTS Instructions 0
700138018 Repack AO280D 05/13/2025 7001380240110 Disassemble and Reassemble AO280A 05/03/2025 7001418960030 RECIRC SX LINE INBD ISOL 0
71114.06 Miscellaneous 6/17/25 HAB Drill Controller Guide Full Scale Practice Drill 0
RWP 255119 Torus Dive and Filter Transfer Activities 0
RWP 255121 RWCU HX E201C Repair 0
RWP 255126 RWCU HX Drain Line & RC Valve Replacements 0
ALARA Plans RWP 255509 Control Rod Drives Changeout 0
501000090824 Elevated Dose Rates for Upcoming Work 10/07/2024 501000096909 Adverse Trend in RP Performance 04/04/2025 Corrective Action Documents 501000097618 Trend in Radworker Performance 04/23/2025 501000097641 Three ARGOS Exit Gates Locks 04/23/2025 Corrective Action Documents Resulting from Inspection 501000097946 Dose Measurement Set Points Higher 04/29/2025 Procedures FPRP-SEN02 Radiological Work Planning and Controls 14 255119 1R32 - Torus - Diving - Inspect/Clean 00 255121 1R32 - RWCU E201C HX Repair 00 255126 1R32 - RWCU - Replace Drain Pipes & RC Valve 00 Radiation Work Permits (RWPs) 255509 1R32 - DW CRD Changeout 00 71124.01 Work Orders 700152706 TBNWS Rad Mon High Alarm 03/23/2025 Reactor Chemistry Results 12/03/2024 Reactor Chemistry Results 03/11/2025 Reactor Chemistry Results 03/19/2025 71151 Miscellaneous Monticello Nuclear Generating Plant - 2024 Annual Dose Summary 04/01/2025
19 Inspection Procedure Type Designation Description or Title Revision or Date Monticello Nuclear Generating Plant - 2025 Annual Dose Summary 04/01/2025 Electronic Dosimeter Transaction Log (>100 mrem Entries) 04/21/2025 QF0445 Safety System Functional Failures (April 01, 2024, through March 31, 2025) 18 QF0445 RCS Leakage (April 01, 2024, through March 31, 2025) 18 Corrective Action Documents 501000058393 FLEX Building Equipment 11/17/2021 Miscellaneous 602000036059 OSP-FIR1489, B.5.B/FLEX Equipment Inventory 37 71152A Procedures 0118 Reactor Vessel Temperature Monitoring 25