IR 05000282/2025002
| ML25223A204 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/13/2025 |
| From: | Dariusz Szwarc NRC/RGN-III/DORS/RPB3 |
| To: | Paulhardt W Northern States Power Company, Minnesota |
| References | |
| IR 2025002 | |
| Download: ML25223A204 (1) | |
Text
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000282/2025002 AND 05000306/2025002
Dear Werner K. Paulhardt Jr.:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant and discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Prairie Island Nuclear Generating Plant.
August 13, 2025
W. Paulhardt Jr.
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 Nos. 05000282 and 05000306 License Nos. DPR-42 and DPR-60
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000282 and 05000306
License Numbers:
Report Numbers:
05000282/2025002 and 05000306/2025002
Enterprise Identifier:
I-2025-002-0059
Licensee:
Northern States Power Company
Facility:
Prairie Island Nuclear Generating Plant
Location:
Welch, MN
Inspection Dates:
April 01, 2025, to June 30, 2025
Inspectors:
J. Bell, Branch Chief
B. Bergeon, Senior Operations Engineer
R. Farmer, Health Physicist
T. Henning, Senior Operations Engineer
M. Learn, Team Leader
K. Pusateri, Resident Inspector
D. Tesar, Senior Resident Inspector
T. Wingfield, Operations Engineer
Approved By:
Dariusz Szwarc, Chief
Reactor Projects Branch 3
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Prairie Island 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
Failure to Implement Structures Monitoring License Renewal Commitments as Described in the USAR.
Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000306/2025002-01 Open/Closed None 71111.15 The inspectors identified a Green finding and associated non-cited violation (NCV) of the Prairie Island Unit 2 Operating License Condition 2.C.(8)(b). Specifically, the licensee failed to implement the requirements of structures monitoring program inspections prior to October 29, 2014, to ensure that diesel equipment and vibration isolation elements for diesel equipment were inspected against established acceptance criteria to prevent the loss of intended function, as described in the License Renewal updated safety analysis report (USAR) supplement.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 entered the inspection period at, and remained at, full-rated thermal power until April 13, 2025. Unit 1 was reduced to approximately 40 percent power for condenser tube cleaning from April 13 through April 19, 2025. On April 19, 2025, Unit 1 was returned to full-rated thermal power and remained at or near full-rated thermal power for the remainder of the inspection period except for brief power reductions to perform surveillance testing, or flexible power operations.
Unit 2 entered the inspection period at full-rated thermal power and remained at or near full-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
71111.01 - Adverse Weather Protection
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 (AB-2), level 4 storm on April 28, 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)121 motor driven cooling water pump while aligned to B cooling water header on April 9, 2025 (2)12 diesel-driven cooling water pump while aligned to A cooling water header on April 9, 2025
- (3) Unit 2 control rod drive power system on May 16, 2025 (4)121 spent fuel pool (SFP) pump walkdown while 122 SFP pump out of service (OOS)for maintenance on May 27, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Detection Zone (FDZ) 31, 121 control room chiller room, auxiliary building, elevation 755' on April 22, 2025
- (2) FDZ 35, during continuous fire watch on May 1, 2025
- (3) FDZ 11, Fire Area 81, elevated risk due to 12 component cooling (CC) pump OOS maintenance on June 18, 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 observation of crew five fire drill - fire in 2 GT transformer on June 2, 2025.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) 122 SFP heat exchanger eddy current test on May 19, 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 exam administered from May 5, 2025, to June 13, 2025, and the biennial written examinations administered from May 5, 2025, to June 13, 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 from May 5, 2025 to June 6, 2025.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test administered from May 5, 2025, to June 6, 2025.
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.
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) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 downpower for condenser waterbox cleaning on April 14, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated FLEX power operations in the control room on May 12, 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) Joint maintenance on emergency diesel generator expansion joints on May 19, 2025
- (2) Inservice testing (IST) of cooling water valves during repairs on MV-32028 on June 25, 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)22 diesel-driven cooling water pump restoration steps and sequence on April 2, 2025
- (2) Cable bundle support issue for Yellow channel reactor protection system on April 3, 2025 (3)21 safeguards exhaust ventilation fan risk management on April 23, 2025 (4)122 SFP heat exchanger CC leak during disassembly on May 20, 2025
- (5) Unit 2 non-urgent rod control failure on May 19, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples, 2 Partials)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Prompt operability for 121 control room air handler degraded boot on April 23, 2025
- (2) Immediate operability of battery room SSCs with rising temperatures on May 2, 2025
- (3) Prompt operability determination for CAP 501000098987, 25PIR-PI D5 ENG 1 Coolant Leak, on May 23, 2025
- (4) Flux probe stuck inserted into core on May 28, 2025
(Partial)
D6 operability for through-wall leak on April 1, 2025 (7)
(Partial)
Operability of void in 1RH-21 pipe and potential gas intrusion from reactor coolant system in Mode 1 (QIM 501000099808) on June 11, 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) (7 Samples)
(1)121 control room air handler PMT; Work Order (WO) 700153909, revision 0, on April 21, 2025
- (2) D5 EDG PMT per WO 700154998 created 5/22/2025, on May 22, 2025
- (3) WO 700149207, SP 1106A 12 Diesel CL Pmp Monthly - PMT Run, on May 5, 2025
- (4) PE 3002-5-22, 22 DD [diesel-driven] CLG WTR Pump 10 Year Relay Replacement, revision 5, on April 4, 2025
- (5) Diesel-driven fire pump charger replacement PMT on May 21, 2025
- (6) PMT on 122 spent fuel pool heat exchanger on June 12, 2025
- (7) WO 700145993, Train A CTMT FCU [fan cooling unit] CL [cooling water] QTR, on June 11, 2025
Surveillance Testing (IP Section 03.01) (3 Samples)
- (1) SP 2251, Caustic Addition Valve Quarterly Test, revision 19, on April 10, 2025
- (2) SP 2307, D6 Diesel Generator 6 Month Fast Start Test, revision 59, on April 30, 2025
- (3) SP 2089A, Train A RHR Pump and Suction Valve from the RWST Quarterly Test, revision 40, on May 15, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) WO 700143234, SP 1155A CC Sys Qtr Test Trn A - Comprehensive IST Test, on May 5, 2025
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
- (1) TP 1877B, 122 Diesel Generator 300KW 3 Year Test and Inspection, on May 2,
RADIATION SAFETY
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative (GPI) program to identify incomplete or discontinued program elements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling,
Storage, & Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
(1)area 19 satellite radiologically controlled area (2)containers in the rad waste storage building barrel yard
Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
(1)aerated drains treatment system (2)spent resin tank (SRT) and associated resin sluice piping
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste: (1)baffle bolt and clevis bolt maintenance filters (2)primary bead resin
Shipment Preparation (IP Section 03.04) (1 Sample)
- (1) The inspectors observed the preparation of radioactive shipment 25-021 of an oil and grease chemistry sample on June 5, 2025.
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
(1)24-068, 2 Sealands of dry active waste (DAW) with friable asbestos, LSA-I (2)24-071, 5 containers of Westinghouse outage equipment, SCO-II (3)25-006, resin liner 179, LSA-II (4)25-012, 2 Sealands of DAW, LSA-II
INSPECTION RESULTS
Failure to Implement Structures Monitoring License Renewal Commitments as Described in the USAR.
Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000306/2025002-01 Open/Closed None 71111.15 The inspectors identified a Green finding and associated non-cited violation (NCV) of the Prairie Island Unit 2 Operating License Condition 2.C.(8)(b). Specifically, the licensee failed to implement the requirements of structures monitoring program inspections prior to October 29, 2014, to ensure that diesel equipment and vibration isolation elements for diesel equipment were inspected against established acceptance criteria to prevent the loss of intended function, as described in the License Renewal updated safety analysis report (USAR) supplement.
Description:
Condition 2.C.(8)(b) of Renewed Facility Operating License for Prairie Island Nuclear Generating Plant, Units 1 and 2, dated October 16, 2009, and supplemented on April 15, 2011, and the licensees USAR supplement submitted pursuant to 10 CFR 54.21(d) describe certain aging management programs (AMPs) and activities to be completed before the period of extended operation. The license condition required these activities to be completed no later than October 29, 2014.
One of these AMPs is the structures monitoring program, with enhancements that added inspections for diesel equipment, including its vibration isolation elements, evaluated against established acceptance criteria. This AMP is described in License Renewal USAR Supplement Appendix L, Section L.2.38, Structures Monitoring Program. This section states in part: The Structures Monitoring Program is a condition monitoring program that manages aging effects in structures, supports and structural components, including bolting, within the scope of License Renewal. The program performs periodic visual inspections to monitor the condition of structures, supports and components, including bolting, against established acceptance criteria to ensure that degradation is identified, evaluated, and, when necessary, corrected such that there is no loss of intended function.
On February 24, 2025, during a routine surveillance test on the Unit 2 D6 emergency diesel generator (EDG), a through-wall leak was discovered on the high temperature (HT) cooling water piping. On April 4, 2025, an operability evaluation of the D6 EDG determined in part that the failure mechanism was vibration-induced wear [] that developed slowly after approximately 35 years of operation. This through-wall leak resulted in the D6 EDG being removed from service and unavailable to perform its safety function, during implementation of the repairs.
During their review, the inspectors were unable to identify any record of planned maintenance activities which accomplished the required inspections. In addition, aging management inspection walkdowns, which are performed every 2 years, were generic in nature and did not have specific established acceptance criteria for the diesel equipment, nor the vibration isolation elements for diesel equipment. The inspectors concluded that the License Renewal requirement that components within the scope of the program, diesel equipment and the vibration isolation elements for diesel equipment, be inspected and evaluated against established acceptance criteria to ensure that degradation is identified, evaluated, and when necessary, corrected such that there is no loss of intended function, were not met.
Corrective Actions: The licensee has corrected the through-wall leak caused by the long-term vibration-induced wear and performed extent of condition walkdowns of the other D5 and D6 EDG engines. In addition, a CAP was initiated to address the acceptance criteria.
Corrective Action References:
501000095507, Through Wall Coolant Leak 501000096290, D6 Coolant Leak POD did not Address Loop 501000101168, D6 HT Coolant Pipe - Acceptance Criteria
Performance Assessment:
Performance Deficiency: The licensees failure to implement aging management program requirements as described by Section L.2.38 of License Renewal USAR Supplement Appendix L (a.k.a., the Structure Monitoring AMP) prior to October 29,2014, was contrary to Operating License Condition 2.C.(8)(b), and was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor (MTM) because it was associated with the Procedure Quality attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the failure to incorporate established acceptance criteria into the AMP failed to ensure the identification, evaluation, and correction of the long-term vibration-induced wear of the D6 EDG cooling water piping, resulting in a through-wall leak, and the D6 EDG being taken out of service for repairs rendering it unavailable and unable to perform its intended safety function.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
The Inspectors determined that the answer to all six
- (6) screening questions of Exhibit 2 - Mitigating Systems Screening Questions, Section A Mitigating SSCs and PRA Functionality (except Reactivity Control Systems) were answered No, based upon the conclusion that the D6 EDG would fulfill its 24-hour PRA mission time, resulting in the issue screening to Green.
Cross-Cutting Aspect: None
Enforcement:
Violation: Condition 2.C.(8)(b) of Renewed Facility Operating License for Prairie Island Nuclear Generating Plant, Units 1 and 2, dated October 16, 2009, and supplemented on April 15, 2011, states, The License Renewal USAR Supplement describes certain programs to be implemented and activities to be completed prior to the Period of Extended Operation (PEO). Additionally, it states, The licensee shall implement those new programs and enhancements to existing programs no later than October 29, 2014. Appendix L of the USAR (a.k.a., the License Renewal USAR Supplement), Section L.2.38, Structures Monitoring Program AMP, specifies in part that The program performs periodic visual inspections to monitor the condition of structures, supports and components, including bolting, against established acceptance criteria to ensure that degradation is identified, evaluated, and, when necessary, corrected such that there is no loss of intended function.
Commitment Number 30 from USAR Appendix L, Table L.5, License Renewal Commitments, state in part that, The following structures, components, and component supports will be added to the scope of the inspections: [...] diesel equipment, [] and [...]
vibration isolation elements for diesel equipment.
Contrary to the above, the licensee failed to implement the Structures Monitoring AMP, as described in the License Renewal UFSAR Supplement, prior to October 29, 2014.
Specifically, the licensee did not incorporate into their AMP established acceptance criteria to ensure that degradation was identified, evaluated, and corrected to prevent loss of function for diesel equipment or vibration isolation elements for diesel equipment. Ultimately, this allowed long-term vibration-induced degradation to go uncorrected, culminating in a through-wall leak in the HT cooling water piping on the D6 EDG. The degradation, which developed over approximately 35 years of operation, ultimately rendered the D6 EDG inoperable and unavailable from February 26, 2025, through February 27, 2025.
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 June 30, 2025, the inspectors presented the integrated inspection results to Werner Paulhardt, Site Vice President, and other members of the licensee staff.
- On May 23, 2025, the inspectors presented the biennial requalification program inspection results to Werner Paulhardt, Site Vice President, and other members of the licensee staff.
- On June 6, 2025, the inspectors presented the radiation protection inspection results to Werner Paulhardt, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
AB-2
Severe Weather
Procedures
1C20.7
D1/D2 Diesel Generators
Procedures
C1.1.35-3
Cooling Water System
Procedures
C16-1
Spent Fuel Pool Cooling Checklist
Fire Plans
FDZ 11
Bus Rms 15 & 16 Unit 1 715'
Fire Plans
FDZ 31
21 & 122 Control Room Chiller Aux Bldg 755'
Fire Plans
FDZ 35
& 22 Battery Rooms
Drawings
XH-106-86
Isometric Spent Fuel Cooling Unit 1
Corrective Action
Documents
501000075003
Equipment Position Not Identified
07/02/2023
Corrective Action
Documents
501000077842
Loss of CT-11 Due to 1H4 Trip
10/17/2023
Corrective Action
Documents
501000077958
Unit 1 Reactor Trip
10/19/2023
Corrective Action
Documents
501000079970
2/12/2023
Corrective Action
Documents
501000082457
PU&A When Performing 2C1.2-M2
03/04/2024
Corrective Action
Documents
501000083200
SP 1106B Reperformed
03/22/2024
Corrective Action
Documents
501000084597
SP 1159 Completed Unsat
04/27/2024
Corrective Action
Documents
501000084692
IST Inoperable CL Return Valves
04/28/2024
Corrective Action
Documents
501000087599
1R-37 OOS Impacts to TS 3.7.12
07/11/2024
Corrective Action
Documents
501000095753
SBT Data Not Sent to Records
03/03/2025
Corrective Action
Documents
501000095767
Exam Security (STA U/I)
03/04/2025
Corrective Action
Documents
501000095849
Missing 396 Missing from File
03/06/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
501000095852
Operator LOR Training Not Completed
03/05/2025
Miscellaneous
1C1.2-BOP
Unit 1 Balance of Plant Systems Startup
10/27/2022
Miscellaneous
1C1.2-M1
Unit 1 Startup to Mode 1
10/27/2022
Miscellaneous
1C1.2-M2
Unit 1 Startup to Mode 2
10/27/2022
Miscellaneous
1C1.4
Unit 1 Power Operation
10/29/2022
Miscellaneous
1Q2023 SUPP
TP 1850
Crew Watchstanding Logs (1Q2023)
09/22/2023
Miscellaneous
1Q2023 TP 1850
Crew Watchstander Verification
09/22/2023
Miscellaneous
25 Biennial
Sample Plan
Exam Cross Check
03/31/2025
Miscellaneous
25 LOR
Operational
Sample Plan
Exam Cross Check
05/01/2025
Miscellaneous
2403
Scenario Based Testing LOR Week 1 Crew 6 Group 1
Validation
04/19/2024
Miscellaneous
2404S
Scenario Based Testing ILT Validation 2024-04
07/19/2024
Miscellaneous
Miscellaneous
Miscellaneous
Miscellaneous
Miscellaneous
Miscellaneous
Miscellaneous
Miscellaneous
Miscellaneous
Miscellaneous
Miscellaneous
Miscellaneous
3Q2023 SUPP
TP 1850
Crew Watchstanding Logs (3Q2023)
03/23/2024
Miscellaneous
3Q2023 TP 1850
Crew Watchstander Verification
03/23/2024
Miscellaneous
501000095767
Evaluation of STA Exam Security Event
Miscellaneous
Appendix C1B
Appendix - Reactor Startup Simulator testing
10/19/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Appendix D30
Post Refueling Startup Testing
10/20/2022
Miscellaneous
Appendix D32
Temperature Coefficient Measurement at Hot Zero Power
10/22/2022
Miscellaneous
Appendix D51
Temperature Coefficient Measurement at Power
10/22/2022
Miscellaneous
N-01
Core Performance Testing Unit 1 Cycle 33
07/12/2023
Miscellaneous
PI-LOR-NRC-
2501S
Simulator Exercise Guide
Miscellaneous
PI-LOR-NRC-
2502S
Simulator Exercise Guide
Miscellaneous
PI-LOR-NRC-
2504S
Simulator Exercise Guide
Miscellaneous
PI-LOR-NRC-
2506S
Simulator Exercise Guide
Miscellaneous
RR-01
Simulator Repeatability (Cycle 33)
05/03/2024
Miscellaneous
Simulator Real Time Measurement (Cycle 33)
07/01/2024
Miscellaneous
S-01
Steady State Tests (Cycle 33)
03/17/2023
Miscellaneous
SRC 2024-02
Simulator Review Committee 2024-02
09/16/2024
Miscellaneous
RHR System Trouble Alarm
04/12/2023
Miscellaneous
Ovation Reset/Snap Conflicts Causing Crashes
2/07/2024
Miscellaneous
5PS20 Power Supply Failure 24 VDC
09/05/2023
Miscellaneous
CNTMT & RCS Pressure Post LOCA
07/18/2024
Miscellaneous
Unexpected Simulator Critical Alarm
05/13/2025
Miscellaneous
T-03
Simultaneous Closure of All Main Steam Isolation Valves
(Cycle 33)
03/18/2024
Miscellaneous
T-05
Trip of Any Single Reactor Coolant Pump (Cycle 33)
03/18/2024
Miscellaneous
T-09
Maximum Size Unisolable Main Steam Line Rupture
(Cycle 33)
05/26/2023
Miscellaneous
T-10
Slow Primary System Depressurization to Saturated
Condition with Pressurizer Relief or Safety Valve Stuck
Open (Inhibit Activation of High Pressure ECCS) (Cycle 33)
07/02/2024
Miscellaneous
T-11
Maximum Design Load Rejection (Cycle 33)
07/02/2024
Miscellaneous
Week 3 Crew 2
RO Biennial
Written Exam
Written Exam
04/28/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Week 3 Crew 2
SRO Biennial
Written Exam
Written Exam
04/28/2025
Procedures
FL-LOR
Fleet Licensed Operator Requalification Training Program
Description
Procedures
FP-T-SAT-40
Implementation Phase
Procedures
FP-T-SAT-71
Exam Security
Procedures
FP-T-SAT-73
Licensed Operator Requalification Program Examinations
Procedures
FP-T-SAT-74
NRC Operator License Application & Renewal Requirements
Procedures
FP-T-SAT-75
Job Performance Measure & Simulator Exercise Guide
Development
Procedures
FP-T-SAT-80
Simulator Configuration Management
Procedures
FP-T-SAT-81
Simulator Testing and Documentation
Self-Assessments QF0406
03/07/2025
Procedures
1C1.4
Unit 1 Power Operation
Engineering
Evaluations
2000024617
Steam from 12 RHR Pit After PMP Start
2/05/2024
Miscellaneous
1067-0121-RPT-
001
RHR Pump Seal Failure Evaluation
Procedures
FP-WM-MMP-01
Minor Maintenance Process
Procedures
FP-WM-WOE-01
Work Order Execution Process
Procedures
FP-WM-WOI-01
Work Identification, Screening, Validation, and Cancellation
Procedures
1C5
Control Rod and Rod Position Indication Systems
Procedures
C35
Cooling Water
100
Procedures
FP-E-SE-03
CFR 50.59 and 72.48 Processes
Corrective Action
Documents
501000098156
Battery Room Temp above C18.1 Limit
05/01/2025
Engineering
Evaluations
2000017241
Request Number 417; Provide Copies of the Monthly
Inspections that have been done on the AFW Inlet with
the Leak
06/18/2025
Engineering
Evaluations
2000017241
Request No.: 414; HT Cooling Water Pipe Characteristics
05/08/2025
Engineering
Evaluations
2000017241
Request No.: 416; For the Recently Performed Analysis on
21 SFP HX Describe the Analysis that was Completed to
06/18/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Leave the Probe in the Heat Exchanger
Engineering
Evaluations
2000017425
MCC 1MA2 High Temp; CAP: 501000100300
Engineering
Evaluations
2000017425
CAP 501000095507; POD 500000334155; Due to Leak on
the D6 Engine 1 High Temperature Cooling Water Pipe
Engineering
Evaluations
2000017425
Prompt Operability Determination, CAP 501000095507,
POD 500000334155, Rev. 1; Leak on the D6 Engine 1
High Temperature Cooling Water Pipe
04/04/2025
Miscellaneous
608000001293
Auxiliary Building High Temperature HELB Evaluation
(130F/150F)
06/25/2025
Miscellaneous
Summary No.: 2-
MIC-2147
UT Examination; Procedure: FP-PE-NDE-425; Work Scope:
2R34 MIC; Report No.: 2R34-MIC-001;
WO: 700148314-0060
Miscellaneous
Wartsila
Technical Bulletin
Cracks on Cylinder Heads, Engine Type UD30/33/45,
Issue 2
2/28/2014
Procedures
FP-E-SE-05
Strategic Engineering Walkdowns
Procedures
H10.1
ASME Inservice Testing Program
Procedures
SP 1468.1
Unit 1 GL-08-01 Inspections for Mode 1,3, and 4
Drawings
NE-40014 V
Sheet 3 SK-
601000002794-
Diesel Fire Pump
Procedures
FP-WM-PLA-01
Work Order Planning Process
Procedures
FP-WM-PMT-01
Post-Maintenance Testing
Procedures
SP 2251
Caustic Addition Valve Quarterly Test
Work Orders
03/30/2025
Work Orders
SP 1155A CC SYS QTR TEST TRN A
05/07/2025
Work Orders
SP 1106A 12 DIESEL CL PMP MNTHLY
05/16/2025
Work Orders
Replace 122 DDFP A Battery Charger
05/21/2025
Corrective Action
Documents
501000095652
REMP TLDs Irradiated in Transit
2/24/2025
Corrective Action
Documents
Resulting from
501000099647
Dose Tracking not Performed Per Procedure
06/05/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Corrective Action
Documents
Resulting from
Inspection
501000099648
Septic System Question
06/05/2025
Miscellaneous
FP-R-LIC-21
Records of Spills or Other Unusual Occurrences
01/15/2020
Miscellaneous
L-PI-21-023
20 Annual Radiological Environmental Monitoring
Program Report
05/14/2024
Miscellaneous
L-Pl-22-023
21 Annual Radiological Environmental Monitoring
Program Report
05/10/2022
Miscellaneous
L-Pl-23-011
22 Annual Radiological Environmental Monitoring
Program Report
05/08/2023
Miscellaneous
L-Pl-24-020
23 Annual Radiological Environmental Monitoring
Program Report
05/09/2024
Miscellaneous
L-Pl-25-014
24 Annual Radiological Environmental Monitoring
Program Report
05/10/2025
Miscellaneous
RPC REMP
LAND USE
CENSUS
24 Land Use Census at Prairie Island
10/12/2024
Procedures
FP-CY-GWPP-01
Fleet Groundwater Protection Program
Procedures
H4
Offsite Dose Calculation Manual (ODCM)
Corrective Action
Documents
501000076498
RAM Sources not in Designated Location
09/01/2023
Corrective Action
Documents
501000085925
Radman Showing Non-Existent Radioisotope
05/28/2024
Corrective Action
Documents
501000092508
NOS: RW Shipment Document Deficiencies
11/20/2024
Corrective Action
Documents
501000092592
Physical Security Precautions of RAM
11/21/2024
Corrective Action
Documents
501000092613
Qual of Rad Mat Ship Supervisor Designee
11/21/2024
Corrective Action
Documents
501000094094
FP-RP-RW-02 Has Misleading Information
01/15/2025
Corrective Action
501000094439
Increased Barrel Yard Area Dose Rates
01/27/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
Resulting from
Inspection
501000099592
NRC RAD Ram Tag Illegible
06/04/2025
Corrective Action
Documents
Resulting from
Inspection
501000099600
NRC RAD Backlog of Rad Waste
06/04/2025
Corrective Action
Documents
Resulting from
Inspection
501000099611
NRC RAD Multiple DOP Testing Stickers
06/04/2025
Miscellaneous
Fuel Integrity Radiochemistry Review, 1st Quarter 2025
Original
Miscellaneous
QF1281
Sample Characterization Loading Form - Baffle Bolt and
Clevis Bolt Maintenance Filters
01/07/2025
Miscellaneous
QF1281
Sample Characterization Loading Form - Primary Bead
Resin
11/09/2024
Miscellaneous
QF1281
Sample Characterization Loading Form - Liner 179
11/09/2024
Procedures
B21B
Liquid Waste System
Procedures
D59
Process Control Program for Processing/Dewatering of
Radioactive Waste from Liquid Systems
Procedures
FP-RP-CRS-01
Control, Inventory and Leak Testing of Radioactive Sources
Procedures
FP-RP-RW-02
Radioactive Shipping Procedure
Procedures
FP-RP-RW-04
Creating Radioactive Material Packages for Transportation
Offsite
Procedures
FP-RP-RW-06
Create Radioactive Packages Using Radman
Procedures
RPIP 1320
Monitoring of Rad Waste in Interim Storage
Procedures
RPIP 1330
Satellite RCA Process
Self-Assessments QF0406
Snapshot Assessment of Receipt, Storage, and Shipment
of Radioactive Materials
2/21/2025
Shipping Records24-068
Sealands DAW, Contains Friable Asbestos
2/03/2024
Shipping Records24-071
Westinghouse Outage Equipment
2/09/2024
Shipping Records25-006
Liner 179
2/11/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Shipping Records25-012
Sealands DAW
04/08/2025
Work Orders
RADIOACTIVE SRCE INVENTORY / LEAK CK
07/22/2024
Work Orders
RPIP 5001 D5/D6 FO STORAGE TK INSP
07/16/2024