IR 05000266/2025002
| ML25218A273 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/11/2025 |
| From: | Sanchez-Santiago E NRC/RGN-III/DORS/RPB2 |
| To: | Edmonds T Point Beach |
| References | |
| IR 2025002 | |
| Download: ML25218A273 (1) | |
Text
SUBJECT:
POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2025002 AND 05000301/2025002
Dear Thad Edmonds:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On July 17, 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, Elba Sanchez Santiago, Chief Reactor Projects Branch 2 Division of Operating Reactor Safety Docket Nos. 05000266 and 05000301 License Nos. DPR-24 and DPR-27
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000266 and 05000301
License Numbers:
Report Numbers:
05000266/2025002 and 05000301/2025002
Enterprise Identifier:
I-2025-002-0049
Licensee:
NextEra Energy Point Beach, LLC
Facility:
Point Beach Nuclear Plant
Location:
Two Rivers, WI
Inspection Dates:
April 01, 2025, to June 30, 2025
Inspectors:
R. Farmer, Health Physicist
E. Magnuson, Reactor Inspector
J. Masse, Resident Inspector
V. Myers, Senior Health Physicist
C. Padilla, Reactor Inspector
M. Stafford, Senior Resident Inspector
Approved By:
Elba Sanchez Santiago, Chief
Reactor Projects Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Point Beach Nuclear 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.
PLANT STATUS
Unit 1 began the inspection period shut down for a refueling outage. On April 9, 2025, Unit 1 was restarted. On April 10, 2025, the unit was synchronized to the grid, and on April 13, 2025, the unit achieved full power. The unit remained at or near full power throughout the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power and remained at or near full power throughout 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
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 heat for the following systems:
A/C switchyard and control house on June 10, 2025.
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 prior to the arrival of severe thunderstorms on June 23, 2025.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)125 volt direct current (VDC) system on May 29, 2025
- (2) Unit 1 containment spray system on June 11, 2025
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 auxiliary feedwater pump system on April 17, 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 Zones 516 and 520:
Unit 1 containment 46' and 66' elevations on April 4, 2025
- (2) Fire Zones 505 and 511:
Unit 1 containment 8' and 21' elevations on April 7, 2025
- (3) Fire Zones 775, 776, and 777:
diesel generator G04 areas, 26' elevation on May 7, 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 14, 2025.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (2 Samples)
- (1) The inspectors evaluated internal flooding mitigation protections in manholes 1 and 66a.
- (2) The inspectors evaluated internal flooding mitigation protections in the vital switchgear room and the D05 station battery room.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 1 component cooling water heat exchangers, HX-012 A and B
===71111.08P - Inservice Inspection Activities (PWR) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities in Unit 1 during refueling outage
==1R42 from March 23, 2025, to April 4, 2025.
==
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic Examination
- Reactor Coolant System Piping Welds, RC-10-PZR-1001-005,006,007, Cat. R-A, Item R1.11
- Reactor Coolant System Piping Welds, RC-03-PS-1001-08,09,10,11, Cat. R-A, Item R1.2 Surface Examination
- Dye Penetrant (PT) Exam of SI-2501R-5-SI10-IWA Welded Pipe Attachment, Cat. B-K, Item B10.20 Visual Examination
- RPV Bottom Head Visual Exam of Bottom Mounted Instrument Penetrations and Bare Metal Surface, Code Case N-722 Exam, Item B15.80
- VT-3 of SI-601R-2-R195 Welded Pipe Sleeve Guide, Cat. F-A, Item F1.20B
- VT-3 of SI-2501R-5-SI-10 Welded Sliding Support, Cat. F-A, Item F1.10B Welding Activities
Base Metal Repair of Component Cooling Water HX-12C Flange Surface (WO 40849148-18)o Replacement of Reactor Coolant Pump Seal Bypass Line (WO 40605130-05)
PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
- (1) Bare Metal Visual of Unit 1 Reactor Pressure Vessel Top Head PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
- (1) Boric Acid Evaluations
- BAS 25-021-E 1SI-878D
- BAS 25-028-E 1CV-206C
- BAS 25-035-E 1P-1A
- BAS 25-053-E CETNAs
- AR 2512016 - Boric Acid Leakage onto CETNAs Walkdowns
- Performed on March 24, 2025
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 the Unit 1 approach to criticality following refueling outage 42 on April 9, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated license operator requalification training in the simulator on April 30, 2025.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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) Elevated risk due to emergency diesel generator G-01 and G-04 failures on April 21, 2025
- (2) Elevated risk during 4.16KV Undervoltage Matrix Relays 31-Day Surveillance Test on June 10, 2025
- (3) Elevated risk during 125 VDC station battery replacement on June 25, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Operability of main steam safety relief valve following identification of piping inlet flange damage
- (2) Operability determination in response to substance found on reactor vessel head and reactor vessel flange
- (3) Operability determination in response to water found in containment core holes
- (4) Operability determination in response to ground found on 125 VDC Battery
- (5) Operability of emergency diesel generator, G-01, left air bank
- (6) Operability of emergency diesel generator, G-04, following identification of frequency issues
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Change to component cooling water surge tank relief valve maintenance plan
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Unit 1 refueling outage 42 activities from April 1, 2025, to April 16, 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) (3 Samples)
- (1) Pressure test for new valves added to an existing containment penetration, on April 17, 2025
- (2) IT 300D Train B, main feedwater isolation valve testing after replacement of valve actuator on April 23, 2025
- (3) Turbine-driven auxiliary feedwater pump following 10-year maintenance overhaul on April 28, 2025
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) ORT 3B, safety injection with loss of AC test on April 15, 2025
- (2) IT 05, train B containment spray pump surveillance on May 28, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Mechanical penetration CPP-41 local leak rate test, April 2, 2025
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) Point Beach second quarter pre-exercise emergency preparedness drill on May 6,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
- (1) Workers and equipment leaving the Unit 1 containment
- (2) Workers and equipment leaving the radiologically controlled area
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensees control of radiological hazards for the following radiological work:
- (1) Removal of a liquid radioactive waste line valve
- (2) Removal of tri-nuke filters from the reactor cavity
- (3) Reactor vessel reassembly activities 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 (HRAs)and very high radiation areas (VHRAs):
- (1) Temporary HRA and locked high radiation area (LHRA) controls for fuel movement
- (2) Demineralizer cubicles LHRAs
- (3) Tri-nuke removal HRA controls 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.
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (3 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
- (1) Units 1 and 2 Drumming Area Vents
- (2) Liquid Radwaste disposal system
- (3) Unit 1 service water effluent monitor and associated piping
Sampling and Analysis (IP Section 03.02) (4 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
- (1) Recirculation and sampling of monitoring tank A
- (2) Unit 2 steam generator blowdown filter outlet sampling
- (3) Wastewater effluent grab and composite sampling
- (4) Unit 1 service water overboard sampling
Dose Calculations (IP Section 03.03) (3 Samples)
The inspectors evaluated the following dose calculations:
- (1) Auxiliary building vent stack continuous release, October 2024
- (2) Gaseous waste 31-day dose projection for third quarter 2024
- (3) Liquid waste 31-day dose projection for third quarter 2024
Abnormal Discharges (IP Section 03.04) (2 Samples)
The inspectors evaluated the following abnormal discharges:
- (1) Gaseous discharge from leak in waste gas system, July 2023
- (2) Gaseous discharge from hole cut in the roof of the primary auxiliary building, July
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (April 1, 2024, through March 31, 2025)
- (2) Unit 2 (April 1, 2024, through March 31, 2025)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (April 1, 2024, through March 31, 2025)
- (2) Unit 2 (April 1, 2024, through March 31, 2025)
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in past operability reviews that might be indicative of a more significant safety issue.
INSPECTION RESULTS
Very Low Safety Significance Issue Resolution Process: Qualification Review of Radiation Protection Manager 71124.06 This issue is a current licensing basis question and inspection effort is being discontinued in accordance with the Very Low Safety Significance Issue Resolution (VLSSIR) process.
No further evaluation is required.
Description:
Technical Specification 5.3.1 states: Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, as supplemented by Regulatory Guide 1.8, Revision 1, September 1975, for comparable positions, except for positions not related to this review.
Technical Specification 5.3.3 states: In the event the position of Health Physicist is vacated and the proposed replacement does not meet all the qualifications of Technical Specification (TS) 5.3.1, but is determined to be otherwise well qualified, the concurrence of NRC shall be sought in approving the qualification of that individual.
The inspectors noted that ANSI 18.1-1971 included a defined standard for the qualification for the Radiation Protection Professional. The NRC endorsed these standards for all positions except for Radiation Protection Supervisor or Manager. The NRC determined that more specialized expertise beyond qualifications presented in ANSI N18.1-1971 was needed. Regulatory Guide 1.8-September 1975 was developed by the NRC to address these shortcomings and described the experience and background necessary to provide sound judgement for safe and successful operation of the plant. Some of these qualities covered in the document included:
- The Radiation Protection Manager (RPM) should be an experienced professional in applied radiation protection at nuclear facilities dealing with radiation protection problems and programs similar to those at nuclear power stations;
- The RPM should be familiar with the design features and operations of nuclear power stations that affect the potential for exposures of personnel to radiation; and
- The RPM should have the technical competence to establish Radiation Protection Programs and the supervisory capability to direct the work of professionals and technicians, required to implement the radiation protection programs.
Additionally, Regulatory Guide 1.8-September 1975 prescribed these experiences to ensure the qualities were present:
- The RPM should have a bachelors degree or the equivalent in a science or engineering subject, including some formal training in radiation protection;
- The RPM should have at least 5 years of professional experience in applied radiation protection; and
- At least 3 years of this professional experience should be in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations, preferably in an actual nuclear power station.
Although not part of the licensing basis, the inspectors reviewed the Health Physics Positions (HPPOS) Database (NUREG/CR-5569, Rev. 1, 1994), which is a compilation of NRC staff positions on a wide range of topics involving radiation protection (health physics). The HPPOS Database was developed by the NRC to help ensure uniformity in inspections, enforcement, and licensing actions and, although they are not typically defined in licensing basis documents, they constitute the NRCs understanding of the applicable requirements and policies and therefore they are especially pertinent to oversight.
The inspectors noted that the topic of professional experience for the RPM was previously addressed and documented in HPPOS-018, HPPOS-020, and HPPOS-172. HPPOS-018 concluded that technician experience was not equivalent to professional experience.
HPPOS-020 concluded that the attributes of a good RPM are considered to be gained almost exclusively by specialized on-the-job, practical and supervisory experience rather than through the broad generalized academic training received by a person with a bachelors degree. Furthermore, HPPOS-172 described that individuals whose radiation protection experience is limited to narrow specialty positions with small support staff should not be expected to meet the requirements for the broad spectrum and scope of operating activities and the worker safety implications associated with positions that have first line foreman/supervisors reporting to them. Therefore, while the professional experience, as described in Regulatory Guide 1.8-September 1975 is not explicitly defined, the staffs positions, as discussed in the HPPOS, indicate that
- (1) professional experience cannot be met by technician-level experience alone,
- (2) the applicable experience must be sufficiently broad (i.e., not limited to narrow specialty positions) and
- (3) that the experience is in applied radiation protection, preferably at a nuclear power station such that the candidate has the supervisory capability to direct the work of professionals and technicians, required to implement the Radiation Protection Programs.
In reviewing the qualifications of the incumbent RPM, the inspectors reviewed the individuals Employee Qualification Record--completed as required by station procedure NP 1.1.18, and identified the applied radiation protection experience that was credited in the record was fulfilled with 7 years as an Engineering Laboratory Technician (ELT) in the U.S. Navy and include a listing of specific activities performed by the incumbent RPM as an ELT.
The inspectors assessed these activities performed by an ELT were tasks typically performed by radiation protection technicians at operating nuclear power stations. However, these activities do not appear to demonstrate the professional experience required of the RPM position as described above. The inspectors determined that, consistent with HPPOS-018, the 7 years of technician-level applied radiation protection experience provided in the Employee Qualification Record may not alone be used to satisfy the 5 years of professional experience in applied radiation protection specified for the RPM position in Regulatory Guide 1.8-September 1975.
The licensee provided another document titled Regulatory Position Paper - Point Beach Nuclear Radiation Protection Manager Qualifications. This document provided significant details associated with the individuals work experience in the 14 years since leaving the Navy. The inspectors identified that while most of this work experience since leaving the Navy was outside of the radiation protection organization, the experiences did include some aspects that might satisfy the staff positions regarding professional experience described above.
Subsequently, the inspectors determined considerable staff effort would be required to resolve this issue to finality. For example, it may be necessary to interpret terms like professional experience, technician experience, equivalent experience, preferable experience, or technical competence used in Technical Specification 5.3.1 and ANSI N18.1-1971, as supplemented by Regulatory Guide 1.8, Revision 1, September 1975, in light of the combination of the individuals Navy and post Navy experience. Additionally, the staff would have to resolve questions of applicability of these new, more detailed definitions to the licensing basis of the facility.
Licensing Basis: Technical Specification 5.3.1 states: Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, as supplemented by Regulatory Guide 1.8, Revision 1, September 1975, for comparable positions, except for positions not related to this review.
Regulatory Guide 1.8-September 1975 states that:
- The RPM should have at least 5 years of professional experience in applied radiation protection; and
- At least 3 years of this professional experience should be in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations, preferably in an actual nuclear power station.
Significance: Technical Specification 5.3.3 provides the licensee flexibility for cases when the proposed replacement does not meet all the qualifications of Technical Specification 5.3.1, but is determined to be otherwise well qualified, the concurrence of NRC shall be sought in approving the qualification of that individual. The inspectors discussed the details provided in the Regulatory Position Paper - Point Beach Nuclear Radiation Protection Manager Qualifications document with a Technical Reviewer from the Nuclear Reactor Regulation (NRR) program office. The staff preliminarily determined that based on the detailed description of the individuals experience including their 14-year tenure of employment with the licensee there was reasonable basis that the NRC may concur with a request to make this individual the RPM under Technical Specification 5.3.3.
For the purposes of the VLSSIR process, the issue of concern was screened through IMC 0609, Appendix C and D and determined it would likely be Green had a performance deficiency been identified.
Technical Assistance Request: The inspectors did not enter either the Task Interface Agreement or Technical Assistance Request process. However, the inspectors contacted the cognizant branch in the Office of NRR as expressed in the description above.
Corrective Action Reference: Not required Observation: Semi Annual Trend on Past Operability 71152S The inspectors completed a review of 22 condition reports initiated over the past 2 years that referenced past operability reviews. The inspectors provided several observations during this review. Three of these observations pertained to minor errors in the licensees implementation of their past operability process and corrective action program:
- The inspectors identified two instances where the licensee failed to properly document the closure of a past operability review request. This is contrary to step 4.5.2 of licensee procedure EN-AA-203-1001, Operability Determinations.
- The inspectors identified one example where the licensee failed to initiate a new condition report to address past operability when the original condition report had already been screened and new information became available. This is contrary to step 4.1.5 of licensee procedure PI-AA-104-1000, Condition Reporting.
- The inspectors identified two occasions where the licensee changed or deleted portions of operability determinations once new information became available instead of appending the new information. This is contrary to steps 4.3.3 and 4.3.7 of licensee procedure PI-AA-104-1000, Condition Reporting.
In addition, one condition report the inspectors reviewed had a past operability review completed but did not address the effect that the deficiency had on the ability of the component to complete its safety function. This is related to a pressurizer safety lifting above its setpoint. The licensee called for and completed a past operability review. Section 7.C of EN-AA-203-1001-F03, Past Operability/Functionality Review (POR) Form, directed, Discuss why the degraded or nonconforming condition did or did not prevent the SSC [structure, system, or component] from performing its required function(s). (Include any known information that supports the specific evaluation, any adverse impact about the condition, any TS violation, or related analysis). To address this, the licensee discussed how the condition was not reportable as opposed to discussing the impact that the valve lifting above its setpoint would have on the reactor coolant system, technical specifications, and/or the safety limits. Section 7.C was not intended to address the reportability of this deficient condition but rather what impact it had on the system.
Once this impact was determined, the licensee could then evaluate if the issue was or was not reportable.
Another condition report pertained to one of the safety related containment accident fans.
The licensee found that a discharge damper for a non-safety containment cooling fan was not capable of fully closing, thereby challenging the operability of one of the containment accident fans. In this instance, the licensee did not perform a past operability review, citing historical equipment performance. The evidence presented was that the fan had previously passed all its surveillance tests. However, these tests did not measure the total flow rate or monitor the position of the discharge damper. Without firm evidence to support past operability the licensee should have performed a past operability review. This is contrary to step 4.5.1 of licensee procedure EN-AA-203-1001, Operability Determinations.
All these examples represent minor performance deficiencies associated with the licensees past operability review process. This review was focused on the licensees implementation of past operability. The inspectors previously reviewed the technical aspects of these issues in past inspection reports and did not identify any performance deficiencies. These observations have been captured in the licensees corrective action program for disposition.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 17, 2025, the inspectors presented the integrated inspection results to Thad Edmonds and other members of the licensee staff.
- On April 3, 2025, the inspectors presented the radiation protection inspection results to Rick Welty, Radiation Protection Section Supervisor, and other members of the licensee staff.
- On April 4, 2025, the inspectors presented the Inservice inspection results to Michael Durbin, Site Vice President and other members of the licensee staff.
- On July 14, 2025, the inspectors presented the radiation protection inspection results to Kim Locke, Principal Engineering Analyst - Licensing, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
2518070
NRC Identified Items during Yard Walkdown
06/23/2025
Severe Weather Conditions
Procedures
Seasonal Readiness
2513778
CL 13E Part 1 - Auxiliary Feedwater Valve Lineup
Turbine-Driven Unit 1
04/18/2025
2513779
CL 13E Part 2 - Auxiliary Feedwater Valve Lineup
Motor Driven
04/18/2025
2513780
M-217 - Auxiliary Feedwater System
04/18/2025
2513781
M-2217 - Auxiliary Feedwater System
04/18/2025
2513782
NRC Comments Following U1 AFW Walkdown
04/18/2025
Corrective Action
Documents
Resulting from
Inspection
2513834
Steam Leak from Packing on Valve
04/20/2025
110E017, Sheet 3
P&ID Safety Injection System
E-6, Sheet 1
25V DC Dist. System
M-201 Sheet 1
P&ID Main & Reheat Steam System
M-207 Sheet 1A
M-217 Sheet 1
P&ID Auxiliary Feedwater System
107
M-217 Sheet 2
P&ID Auxiliary Feedwater System
Drawings
M-217 Sheet 3
P&ID Auxiliary Feedwater System
MDB 3.2.12 D01
DC Distribution
MDB 3.2.12 D11
DC Distribution
Miscellaneous
MDB 3.2.12 D16
DC Distribution
CL 13E Part 1
Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 1
CL 13E Part 2
Auxiliary Feedwater Valve Lineup Motor Driven
Procedures
CL 7A
Safety Injection System Checklist Mode 1, 2, 3, and 4
(with Both ECCS Trains Aligned for Injection) Unit 1
Corrective Action
Documents
2513372
Crew F Fire Brigade Communications
04/14/2025
PFP-0-PAN-
NNSR
Pre-Fire Plan Protected Area North (Inside the Fence)
Fire Plans
PFP-1-CONT-
Pre-Fire Plan Unit 1 Containment Building/Facade
Miscellaneous
FFPDB
Appendix F of the Fire Protection Design Document, Fire
Safety Analysis, A71 - Combined DG Building, Train B Areas
NP 1.9.14
Fire Protection Plan
Procedures
PC 74
Guideline for the Conduct and Evaluation of Fire Brigade
Drills
2014-0007
Allowable Flood Levels
Calculations
2014-02058
Internal Flooding Effects
Corrective Action
Documents
2514745
Z-066A Manhole Found with High Water Level
05/05/2025
Drawings
PBE-816
Cable Vault Locations
Procedures
NP 8.4.17
PBNP Flooding Program
Work Orders
40984462
Yearly (Spring) Electrical Manhole Sump Inspections
Corrective Action
Documents
2511525
PBN 2025 Thermal Performance Testing HX-012A/B
03/26/2025
Miscellaneous
Report D-12091
Component Cooling Water (CCW) Heat Exchanger Thermal
Performance Test
Procedures
OI 152
Unit 1 Component Cooling System Heat Exchanger Data
Collection
WE-100091
Piping System Qualification Report
0E
Calculations
WE-100091
Piping System Qualification Report
2469009
Dry, White/Brown Boric Acid Found in Unit 1 Fuel Transfer
Tube
10/08/2023
2469557
NRC Identified - Potential Leak Chase Caulk Degradation
10/13/2023
2469663
Unit 1 A RCP Welded Attachment Liquid Penetrant
Indications
10/15/2023
2469673
Indications Found on RPV Stud and Washer
10/15/2023
2469871
Liquid Penetrant Exam Found on CCW Piping
10/17/2023
2470057
NRC Identified: Containment Moisture Barrier Degradation
10/19/2023
2470253
Indications on Spare RPV Stud
10/21/2023
2470313
Dry Light Boric Acid Streaking on CETNAs
10/22/2023
Corrective Action
Documents
2470714
Indications on Spare RPV Studs
10/26/2023
2471725
ISI Inspection Potential Violation 10 CFR 50.55
11/06/2023
2471727
ISI Inspection Potential Violation App B Criterion V
11/06/2023
2490484
Dry Boric Acid Leak on 1HX-3A in Contact with Bolting
07/11/2024
2498841
Missed Section XI R/R Form and Capacity Question
10/21/2024
2510978
Active Boric Acid Leak on 1SI-878D
03/20/2025
2511157
Active Boric Acid Indication on 1P-1A
03/22/2025
2511161
1CV-206C, Dried Boric Acid Indication Upstream of Valve
03/22/2025
2511163
1FM-3 Seal Table Fitting Boric Acid Indication
03/23/2025
2511180
1SC-955 Boric Acid Indication from Bonnet Fitting
03/23/2025
2511234
1CV-206C Boric Acid Found on Flange Just Below Valve
03/24/2025
25120216
Dry Boric Acid Residue on CETNAs 34, 35, and 37
03/31/2025
2511548
ER-AP-116-1000-F01 - Boric Acid Leak Screening
03/26/2025
Corrective Action
Documents
Resulting from
Inspection
2511578
Reduced Thread Engagement Anchor for Support
SI-2501R-5-R194
03/27/2025
Drawings
P-336 Sheet 6B
Pipe Hanger/Support Detail SI-2510R-5-R194
Engineering
Changes
300538
Analysis of Thread Anchor Engagement at Support
SI-2501R-5-R194
03/27/2025
LTR-SDA-20-
079-P
Point Beach Unit 1 Reactor Coolant Pump Flaw Assessment
for As-Found Indications during Fall 2023 Refueling Outage
Engineering
Evaluations
WEP-RV000-TM-
CD-000001
Point Beach Unit 1 O-ring Groove Foreign Material
Evaluation and Justification
2010VT-239
Visual Examination of RCP-A-Weld-B
03/21/2010
PB1-PT-25-001
Liquid Penetrant Examination of SI-2501R-5-SI10-IWA
04/02/2025
PB1-UT-25-003
Ultrasonic Examination of RC-03-PS-1001-08
03/31/2025
PB1-UT-25-005
Ultrasonic Examination of RC-03-PS-1001-09
03/31/2025
PB1-UT-25-007
Ultrasonic Examination of RC-03-PS-1001-10
03/31/2025
PB1-UT-25-009
Ultrasonic Examination of RC-03-PS-1001-11
03/31/2025
PB1-UT-25-011
Ultrasonic Examination of RC-10-PZR-1001-07
03/31/2025
PB1-UT-25-012
Ultrasonic Examination of RC-10-PZR-1001-05
03/31/2025
PB1-UT-25-013
Ultrasonic Examination of RC-10-PZR-1001-06
03/31/2025
PB1-VT-25-002
Bare Metal Visual Examination of Bottom Mounted
Instrumentation Nozzles
03/25/2025
PB1-VT-25-011
Visual Examination (VT-3) of SI-601R-R195
04/01/2025
NDE Reports
PB1-VT-25-012
Visual Examination (VT-3) of SI-2501R-5-SI-10
04/01/2025
PB1-VT-25-029
Bare Metal Visual Examination of RPV Closure Head
04/02/2025
DG-M10
Pipe Support Guidelines
DG-M18
Fastener Design Guideline
Boric Acid Corrosion Control Program
ER-AP-116-1000-
10000
Boric Acid Corrosion Control Program Implementation
FP-PE-B31-
ASME Welding Procedure Specification
FP-PE-VIII-P1P1-
GTSM-042
ASME Welding Procedure Specification
FP-PE-WLD-02
General Welding Specification
NDE-173
PDI Generic Procedure for the Ultrasonic Examination of
Austenitic Piping Welds
NDE-451
Visible Dye Penetrant Examination Temperature
Applications 40F TO 125F
NDE-750
Visual Examination (VT-1) of Nuclear Power Plant
Components
Procedures
NDE-754
Visual Examination (VT-3) of Nuclear Power Plant
Components
Procedures
NDE-757
Visual Examination (VE) ASME Class 1 Components
Fabricated with Alloy 600/82/182 Materials
40605130-05
1P-001A / CONTG CorrectvFlange Misalignment EC298474
2/22/2023
40849148-18
HX-012C Contingency to Weld Repair Heat Exchanger
2/07/2023
Work Orders
40953371-01
U1 Cont Floor / U1 Examine Containment Floor Joints
10/22/2023
Miscellaneous
21C CPE
Scenario 2
As-Found
Reactor Startup
Procedures
Conduct of Operations
2513870
G-04 Emergency Diesel Generator Frequency Found
Out of Spec
04/20/2025
Corrective Action
Documents
2513889
G-01 Left Bank Air Start
04/21/2025
Miscellaneous
Work Activity Risk Management Plans for
-(1)2 ICP 02.013 4.16KV Undervoltage Matrix Relays
31-Day Surveillance Test (TADOT)
-D-305 Battery Replacement and D-09 Charger
Maintenance-Battery Realignment to Support
Maintenance Activities
2ICP 02.13
4.16KV Undervoltage Matrix Relays Surveillance Test
NP 10.3.7
On-Line Safety Assessment
OI 168
Emergency Diesel Generator Operability
OI 35A
Standby Emergency Power Alignment
Procedures
Work Activity Risk Management
2511582
1MS-2005, MSSV Inlet Piping Side Flange Damage
03/27/2025
2511801
Substance Found on Outer O-Ring Seating Groove
03/28/2025
2511850
Substance Found on Reactor Vessel
03/29/2025
2511930
Water Found Inside Core Hole CH-07 during Exam
03/30/2025
2513278
Negative Ground DC Side of D-07 Batt Charger
04/12/2025
2513321
1POS-02606 Water Damage Caused Ground Fault on D-07
04/13/2025
2513870
G-04 Emergency Diesel Generator Frequency Found out of
Spec
04/20/2025
Corrective Action
Documents
2513889
G-01 Left Bank Air Start
04/21/2025
Drawings
M-201 Sheet 1
P&ID Main & Reheat Steam System
Engineering
Evaluations
Assessment of U1R42 As-Left Unit 1 Containment Liner
Plate EL 8-ft.
25-054-E
Boric Acid Indication Evaluation
04/01/2025
PB 271
Specification for Steam Generator Safety Valve
2/08/1994
RR 2025-011
Repair/Replacement Form - Piping EB-01-SP Inlet to
03/27/2025
Miscellaneous
WEP-RV000-TM-
CD-000001
Point Beach Unit 1 O-ring Groove Foreign Material
Evaluation and Justification
RMP 9096-1
Reactor Vessel Head Removal and Installation Using Biach
Tensioning System
Procedures
MI 32.1
Flange and Closure Bolting
40931573-02
1R-1/Mech. Removal-Installation of RV Head
04/10/2025
40932143-07
U1 - Exam of Core Drilled Holes on El. 8' Containment
04/05/2025
41013039-01
1MS-02005 / Repair Piping Side Flange
03/31/2025
Work Orders
41016058-01
G-04; Troubleshoot and Repair
04/25/2025
Corrective Action
Documents
Resulting from
Inspection
2518624
PMC-25-000359 CC Surge Tank RV
07/01/2025
Miscellaneous
PMC-25-000359
Change 1CC-779 From the Outage to Online
03/14/2025
Procedures
MA-AA-204-
1000-10001
Preventive Maintenance Change Request (PMCR)
Corrective Action
Documents
Resulting from
Inspection
2512698
NRC Unit 1 Containment Closeout Walkdown Concerns
Apr 6, 2025
04/06/2025
OI 51
Spent Fuel Pool/Transfer Canal Doors
Conduct of Operations
Plant Status Control Management
Procedures
RP 1A
Preparation for Refueling
109
2511235
1A52-83 Breaker Closure Time Not Recorded during ORT3B
03/24/2025
2511243
ORT 3B Step 5.4.13 (W-86)
03/24/2025
2512532
Valve Not Stroking Open
04/04/2025
2512812
1CS-3125 B MFIV Could Not be Opened
04/08/2025
2512935
1CS-3125 Opening Times
04/09/2025
Corrective Action
Documents
2513344
Spurious 1C-03 1D 4-5 A or B MFIV Trouble Alarms
04/14/2025
IST Program Document
Miscellaneous
IT 05 Train B
Train B Containment Spray Pump and Valves Unit 1
IT 08A
Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve
Test (Quarterly)
IT 300D Train B
Main Feedwater Isolation Valve Test Train B Unit 1
ORT 3B
Safety Injection Actuation with Loss of Engineered
Safeguards AC (Train B) Unit 1
ORT 58
Containment Test Connection Unit 1
Procedures
ORT 75
Mechanical Penetration Leak Test Unit 1
40687906-01
1CS-03125-O, Replace MFIV Operator Elastomers
04/08/2025
40687906-02
1CS-03125-O, Ops PMT/RTS Cycle per IT 300-D Train B
04/16/2025
40860071-01
ORT 3B, SI/Loss of AC (Train B) U1 (IPTE)
04/07/2025
40931678-02
1-62/P53A2 - Verify Relay Function during ORT 3C
04/05/2025
Work Orders
41001405-09
1CPP-41 Operation Pre ORT 75 Unit 1
03/29/2025
Work Orders
41001405-12
1CPP-41/Operation PMT (ORT 75 Unit 1 and ORT 58)
04/05/2025
2514970
25 NRC Pre-Ex: Communication Equipment Proficiency
05/08/2025
2514977
25 NRC Pre-Ex: Green Bay EOF Entryway
05/08/2025
Corrective Action
Documents
2515005
25 NRC Pre-Ex: Simulation Changed Post Validation
05/08/2025
25 Pre-Exercise Master Sequence of Events Listing for
the 2nd Quarter Emergency Preparedness Drill
Miscellaneous
2Q25 EP Drill Combined Facility Critique Powerpoint
05/07/2025
2512185
HRA Postings
04/01/2025
Corrective Action
Documents
2512208
Personnel Uptake
04/02/2025
25-408
Work Area Air Sample for WL-1698
03/31/2025
25-409
General Area Air Sample for WL-1698
03/31/2025
PBPROD-M-
250401-15
Tri-Nuke filter transfer
04/01/2025
PBPROD-M-
250401-16
Tri-Nuke filter storage location
04/01/2025
PBPROD-M-
250401-24
Reactor Cavity during Head Set
04/01/2025
PBPROD-M-
250401-8
Surveys for work on valve WL-1698
03/31/2025
Radiation
Surveys
PBPROD-M-
250402
Reactor Cavity Decon
04/02/2025
25-1015
Cavity Activities
25-1016
Reactor Vessel Head - Removal/Reinstall
Radiation Work
Permits (RWPs)
25-1052
Unit 1 Outage - Alpha Level 3 Areas
2436978
Alert received on RE-218 Waste Disposal System Liquid
Monitor
09/16/2022
2441697
RMS High Alarm and Trip Setpoint Found Conservatively
Low
11/12/2022
2465121
Flawed 2016 50.59 AD Allowed ODCM/TS 5.6.2 Disconnect
08/22/2023
2465123
Records of ODCM Revisions Lack Key Elements
08/22/2023
2467108
RE-218 Failed Source Check Prior To Discharge
09/17/2023
2468596
NA Finding - PBN ODCM Revision Practices Inconsistent
W/ TS
10/04/2023
2479373
Monitor Tanks Above Admit Limit due to U2 Fuel Defect
2/16/2024
Corrective Action
Documents
2491194
Monitor Tank Discharges Challenged by RE-218 Capability
07/23/2024
2508585
New RMS Iodine Cartridges Unable to Be Analyzed
2/21/2025
2509718
PB - Failure to update ODM with Changing Conditions
03/06/2025
2513883
Charcoal Filters for PAB Hole in Roof Were Never Counted
04/21/2025
23-00008LB
Permit for Liquid Batch Release From Monitor
Tank B (B-MT)
2/07/2023
23-00081GB
Permit for Abnormal Gaseous Release from Gas Decay
Tank C
07/12/2023
Miscellaneous
24-00034LB
Permit for Liquid Batch Release from Monitor Tank A (A-MT)
10/17/2024
24-00045GC
Permit for Continuous Gaseous Release from Auxiliary
Building Vent Stack
11/15/2024
24-00075GC
Permit for Abnormal Gaseous Release from Primary
Auxiliary Building (PAB) Hole in the Roof
04/05/2025
25-00041LB
Monitoring Tank A Discharge Permit
05/07/2025
23 Annual Monitoring Report
04/26/2024
24 Annual Monitoring Report
04/30/2025
Data Sheet 6, RMS Assessment Worksheet, for Discharge
24-00034LB
10/14/2024
PBF-7072
ODCM Change Documentation
08/28/2024
Miscellaneous
SCR 2024-047
Screening for ODCM Revision
CAMP 032
Preparation of Batch Liquid and Gaseous Effluent Permits
Using RADEAS Software
CAMP 401
Radioactive Standards and Sample Placement for
Multichannel Analyzer Calibration and Quantification
CAMP 701
Secondary System and Water Treatment Plant Sample
Points
HPIP 3.52.1
Radiological Sampling for Release Accountability
Offsite Dose Calculation Manual
Offsite Dose Calculation Manual
Offsite Dose Calculation Manual
Procedures
OI 140C
Standard Radioactive Batch Liquid Release-Monitor Tanks
1_2023-07-
11_002
Gamma Isotopic Results for release permit 23-00081GB
07/11/2023
25-574
Airborne Radioactivity Survey - DAVS Isokinetic
05/06/2025
Radiation
Surveys
3_2024-10-
14_015
Gamma Isotopic for First Sample for Discharge 24-00034LB
10/14/2024
3_2024-10-
14_016
Gamma Isotopic for Second Sample for Discharge
24-0034LB
10/14/2024
3_2024-10-
15_002
Gamma isotopic for in progress sample for discharge
24-00034LB
10/15/2024
4_2023-07-
10_006
Gamma Isotopic Results for Release Permit 24-00075GC
07/10/2024
71151
Procedures
OI 55
Primary Leak Rate Calculation
2451761
2RC-00435 SN XX05950175 PZR Safety Failed As-Found
Testing
03/21/2023
2457774
D-504-7 Breaker was Over High Tol. Limit
05/16/2023
2465050
M&TE - MCTC-005 (Engineering Review Needed)
08/21/2023
2469217
While Performing 1ICP 04.025 Found Out of Tolerances
10/10/2023
2469618
Breaker Cubicle Left Side Rail Racking Indicator Tabs Bent
10/14/2023
2471588
1CC-751 Relief Valve Failed Its As-Found Test
11/03/2023
2486793
SW-001A2-A Second Blade Disconnected from Damper
Shaft
05/21/2024
Corrective Action
Documents
2501382
2SI-887 Failed As-Found Test
11/12/2024
2510100
EN-AA-203-1001 - Operability Determinations
03/11/2025
2510102
CR 2469618 Completed w/o ENG Review of Past
Operability
03/11/2025
2519608
PBN SRI POR Trend Review Process Concerns
07/16/2025
Corrective Action
Documents
Resulting from
Inspection
2519609
Minor Performance Deficiencies on Documenting PORs
in CAP
07/16/2025
Procedures
Condition Reporting
46