IR 05000266/2024004
| ML25017A226 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/21/2025 |
| From: | Travis Iskierka-Boggs NRC/RGN-III/DORS/RPB2 |
| To: | Durbin M Point Beach |
| References | |
| IR 2024004 | |
| Download: ML25017A226 (1) | |
Text
SUBJECT:
POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2024004 AND 05000301/2024004
Dear Michael Durbin:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On January 14, 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, Travis D. Iskierka-Boggs, Acting Branch 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:
05000266/2024004 and 05000301/2024004
Enterprise Identifier:
I-2024-004-0063
Licensee:
NextEra Energy Point Beach, LLC
Facility:
Point Beach Nuclear Plant
Location:
Two Rivers, WI
Inspection Dates:
October 01, 2024 to December 31, 2024
Inspectors:
J. Kutlesa, Senior Emergency Preparedness Inspector
J. Masse, Resident Inspector
V. Myers, Senior Health Physicist
A. Shaikh, Senior Reactor Inspector
M. Stafford, Senior Resident Inspector
Approved By:
Travis D. Iskierka-Boggs, Acting Branch 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 at rated thermal power and remained at or near full power throughout the remainder of the inspection period.
Unit 2 began the inspection period in a coast down for a refueling outage, at approximately 89 percent power. On October 12, 2024, operators shutdown Unit 2 from approximately 82 percent power for the scheduled refueling outage. On October 31, 2024, operators restarted Unit 2. On November 1, 2024, operators synchronized the unit to the grid, and on November 5, 2024, the unit achieved full power. The unit 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 seasonal cold temperatures for the following systems and components:
main feedwater isolation valves, service water, battery inverters, and emergency diesel generator fuel oil transfer system on November 19, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 turbine driven auxiliary feedwater pump on November 7, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 spent fuel pool cooling system on October 21, 2024.
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 608 and 611 on October 20, 2024
- (2) Fire zones 615 and 618 on October 24, 2024
- (3) Fire zone 516 on October 25, 2024
===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 2 during refueling outage U2R40 from October 21-25, 2024.
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)
- Liquid Penetrant Examination of Welded Attachment SI-151R-3-2H1-IWA
- Ultrasonic Examination of Pipe to Elbow Weld on AC-10-SI-2001-16
- Visual Examination of Rigid Support 29-PRB
- Bare Metal Visual Examination of RPV Bottom Mounted Instrumentation Penetrations
- Welding Repair on 2AF-198B 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 Examination of RPV Upper Head Closure Surfaces 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)
- BAS 23-088-E for 2SI-V-26 Boric Acid Leak
- BAS24-009 for 2CV-262C Boric Acid Leak
- BAS24-029 for 2CV-290 Boric Acid Leak
- BAS 24-039-E for 2SI-829C Boric Acid Leak
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during the Unit 2 shutdown on October 12, 2024.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 power ascension activities on October 31, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated crew performance during the biennial operational exam on October 1, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Diesel fire pump charger failure on November 4, 2024
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 reactor protection and safeguards system logic testing on October 3, 2024
- (2) Elevated risk due to lowered reactor coolant system inventory during the Unit 2 refueling outage on October 14, 2023
- (3) Elevated risk for the infrequently performed ORT 3A, Safety Injection Actuation with Loss of Engineered Safeguards, on October 14, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Operability of the turbine driven auxiliary feedwater pump following identification of scaffold interference on October 23, 2024
- (2) Operability of 2HX-15B, accident recirculation fan motor cooling coil, following identification of a tube leak on October 29, 2024
- (3) Operability of 2AF-4000, turbine driven auxiliary feedwater pump discharge to steam generator B inlet isolation valve after over thrust condition on November 6, 2024
- (4) Operability of 2SI-867B, safety injection to reactor coolant loop B cold leg check valve, following elevated leak rates during testing on November 7, 2024
- (5) Operability of G-01, emergency diesel generator after relays found to be out of tolerance on November 15, 2024
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage U2R40 activities from October 3, 2024, to November 15, 2024.
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) (5 Samples)
(1)2ICP 4.24 calibration of source range detector 2N-31 after replacement on October 24, 2024
- (2) Leakage testing on 2RC-431B, pressurizer spray line control valve following removal of bellows leak detection line on November 13, 2024
- (3) Leakage testing of 2MS-2018A, main steam non-return check valve following valve disc replacement on December 18, 2024
- (4) Containment accident recirculation fan tests following maintenance and replacement on December 19, 2024
- (5) Control room emergency filtration system breaker and system testing following repair on December 23, 2024
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) ORT 3A, Safety Injection Actuation with Loss of Engineered Safeguards AC, on October 22, 2024 (2)1RMP 9056-1, calibration of relays on 4160V bus 1A-05 on November 27, 2024
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) ORT 31, Nitrogen Supply to the Pressurizer Relief Tank, leakage testing, on October 22, 2024
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the following maintenance and testing of the alert and notification system:
- The inspectors reviewed the FEMA-approved Design Report and assessed the adequacy of Manitowoc and Kewaunee Counties Wisconsin performance of the test and maintenance activities associated with the approved Integrated Public Alert and Warning System (IPAWS) alert and notification system.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Preparedness Organization.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
- EP 1.0, Point Beach Nuclear Plant Emergency Plan, Rev 33
- EPIP 1.2.1, Emergency Action Levels and Technical Basis, Rev 28
- EP-AA-100-1007-F02, RMS Functional Assessment for New System, Rev 2 This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program.
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)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Workers exiting the radiologically controlled area
- (2) Workers and material leaving Unit 2 containment
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) Reactor vessel disassembly
- (2) Fuel sipping activities
- (3) Lower cavity activities
- (4) B reactor coolant pump seal replacement High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
- (1) Unit 2 demineralizer cubicles
- (2) Fuel movement boundaries Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Reactor head laydown area
- (2) Reactor vent
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS09: Residual Heat Removal Systems (IP Section 02.08)===
- (1) Unit 1 (July 1, 2023 through September 30, 2024)
- (2) Unit 2 (July 1, 2023 through September 30, 2024)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2023 through September 30, 2024)
- (2) Unit 2 (October 1, 2023 through September 30, 2024)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 (July 1, 2023 through September 30, 2024)
- (2) Unit 2 (July 1, 2023 through September 30, 2024)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) July 1, 2023 through September 30, 2024 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) July 1, 2023 through September 30, 2024
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) August 1, 2023 through July 31, 2024 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) August 1, 2023 through July 31, 2024 EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) August 1, 2023 through July 31, 2024
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) Human Performance Trends
INSPECTION RESULTS
Observation: Semiannual Trend Review 71152S The inspectors noted a trend in the human performance error rate at the station. The data shows an uptick in the 2024 error rate compared to that of 2023. However, the error rate for 2024 was comparable to previous years. In 2024, the licensee initiated 6637 Action Requests (AR). Of these, 144 were human performance related. This results in a ratio of 2.17 percent human performance ARs compared to the total. In 2023 this value was 2.07 percent. As a reference, the highest percentage in the last 5 years was 2020, at 2.68 percent. The licensee performed a trend assessment to look specifically at clearance related issues, which saw an increase leading up to and during the refueling outage. The corrective actions of this assessment were to reinforce questioning attitude amongst the maintenance and operations departments and to provide practice scenarios to these departments. The inspectors did not identify any findings or violations during their review that have not already been addressed.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 28, 2024, the inspectors presented the Inservice Inspection (ISI) Exit Meeting inspection results to Michael Durbin, Site Vice President, and other members of the licensee staff.
- On November 8, 2024, the inspectors presented the radiation protection inspection results to Michael Durbin, Site Vice President, and other members of the licensee staff.
- On December 20, 2024, the inspectors presented the emergency action level and emergency plan changes inspection results to D. Smith, Emergency Preparedness Manager, and other members of the licensee staff.
- On January 14, 2025, the inspectors presented the integrated inspection results to Michael Durbin, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2502033
0-PT-FP-004 - Annual Fire Pump Cap Test CR2502037
NRCID
11/19/2024
Corrective Action
Documents
Resulting from
Inspection
2502037
NRC Identified Concerns
11/19/2024
Miscellaneous
PBNP Winter Readiness 2024-25 Letter
11/15/2024
Seasonal Readiness
PC 49 Part 3
Auxiliary Building Ventilation
PC 49 Part 4
Auxiliary Building Miscellaneous and Facades
Procedures
PC 49 Part 5
Cold Weather Checklist: Outside Areas and Miscellaneous
2500465
Pink Boric Acid Noted on Packing of 2SF-820B by NRC
Resident
11/03/2024
2500467
SF-16 Has Dry Boric Acid on the Downstream Cap
11/03/2024
2500470
SF-793B Has a Flange and Unlabeled Valve Connected to it
11/03/2024
2500824
SF Valves Have Labels that do not Match Names in CL-5C
11/06/2024
2500826
CL 5C - Spent Fuel Pool Cooling and Refueling Water
Circulating Pump Normal Operation Valve Lineup
11/06/2024
Corrective Action
Documents
Resulting from
Inspection
2501047
CL 13E Part 1 Unit 2 - Auxiliary Feedwater Valve Lineup
Turbine-Driven Unit 2
11/08/2024
110E018, Sheet 4
P&ID Auxiliary Cooling System
Drawings
M-217 Sheet 2
P&ID Auxiliary Feedwater System
CL 13E Part 1
Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 2
Procedures
CL 5C
Spent Fuel Pool Cooling and Refueling Water Circulating
Pump Normal Operation Valve Lineup
Corrective Action
Documents
2496803
Smoke Detectors in U1 Containment Simultaneously
Alarmed
10/02/2024
PFP-1-CONT-
Pre-Fire Plan Unit 1 Containment Building/Facade
Fire Plans
PFP-2-CONT-
Pre-Fire Plan Unit 2 Containment Building/Facade
EPIP 1.2.1
Emergency Action Levels and Technical Basis
Procedures
NP 1.9.14
Fire Protection Plan
Corrective Action
2CV-290 Boric Acid Build-Up on Valve Stem and Packing
06/23/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Gland
BAS 23-088-E
2SI-V-26 Boric Acid Leak
04/11/2023
BAS24-009
2CV-262C Boric Acid Leak
01/22/2024
BAS24-029
2CV-290 Boric Acid Leak
04/20/2024
Engineering
Evaluations
BAS24-039
2SI-829C Boric Acid Leak
06/25/2024
PB2-UT-24-001
Liquid Penetrant Examination of Welded Attachment
SI-151R-3-2H1-IWA
10/17/2024
PB2-UT-24-005
Ultrasonic Examination of Pipe to Elbow Weld on
AC-10-SI-2001-16
10/21/2024
PB2-VT-24-017
Visual Examination of Boric Acid (BMV) of Bottom Mounted
Instrumentation Penetrations
10/17/2024
PB2-VT-24-025
Visual Examination of Boric Acid (BMV) of RPV Head
Surfaces
10/21/2024
NDE Reports
PB2-VT-24-028
Visual Examination of Pipe Hanger, Support or Restraint
10/21/2024
Operability
Evaluations
WEPM-RV010-
TM-LO-000001
Point Beach Unit 1 and 2 Reactor Vessel Clevis Insert Wear
Prediction Component Assessment
AC-10-SI-2001-
UT Calibration/Examination
10/21/2024
FP-PE-WLD-02
General Welding Specification
NDE-109_012
Manual Ultrasonic Examination Using Longitudinal-Wave
Straight-Beam Techniques
NDE-173_020
PDI Generic Procedure for The Ultrasonic Examination of
Austenitic Piping Welds
Procedures
NDE-754-024
Visual Examination (VT-3) of Nuclear Power Plant
Components
Work Orders
40802726-08
03/28/2023
Miscellaneous
SEG PBN LOC
000 010E
NRC Annual Operating Exam
EPIP 1.1
Course of Actions
Startup to Power Operation Unit 2
Conduct of Operations
RESP 4.1
BOL Physics Tests
Procedures
Conduct of Simulator Training and Evaluation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2500395
D-600 Diesel Fire Pump Battery Voltage Low on Logs
11/03/2024
2500486
D-600 P-35B Diesel Fire Pump Starting Battery
11/03/2024
Corrective Action
Documents
2500553
P-35B Fire Pump Charger #2 Failure Alarm
11/04/2024
Maintenance Rule Program Administration
Procedures
NP 1.9.14
Fire Protection Plan
2496956
Procedural Data Lost While Using DWP on iPad (High Risk)
10/03/2024
Corrective Action
Documents
2499416
WO 40992806 CL-1E Containment Closure Activities
Concerns
10/25/2024
Corrective Action
Documents
Resulting from
Inspection
2500873
CL 1E Unit 2 - Containment Closure Checklist Unit 2
11/07/2024
U2R40 Shutdown Safety Letter
10/11/2024
PBF-1562
PBNP Shutdown Safety Assessment and Fire Inspection
Checklist
10/14/2024
Miscellaneous
PBNP Shutdown
Safety
Assessment and
Fire Inspection
Checklist
Time Stamped: 1838
10/13/2024
1ICP 02.003A
Reactor Protection System Logic Train A Surveillance Test
1ICP 02.005A
Engineered Safety Features System Logic Train A Actuation
Logic Test
CL 1E
Containment Closure Checklist Unit 2
NP 10.3.6
Shutdown Safety Review and Safety Assessment
OP 4D Part 1
Draining The Reactor Coolant System
100
OP 4E Unit 2
Reactor Coolant System Lowered Inventory Requirements
Unit 2
Procedures
Conduct of Infrequently Performed Tests or Evolutions
40960056-01
1ICP 2.5A - Safeguards Logic Test - Train A
10/03/2024
40960071-01
1ICP 2.3A - Reactor Protection Logic Test - Train A
10/03/2024
Work Orders
40992806-01
2CPP-59, U2C Pipe Penetration (Spare) - Implement EC 300037
10/24/2024
Calculations
2002-0003
Service Water System Design Basis
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
98-0020
Containment Recirculation Fan Motor Cooler SW Flow vs.
Temperature Requirements for Normal and Accident Modes
of Operation
2400855
G-01 Relay Maintenance Results
08/11/2021
2493045
Relays Tested on EDG G-01 per RMP 9043-18 Were Fount
out OOT
08/16/2024
2496283
Scaffold Impacting 2AF-4006 Travel
09/25/2024
2498269
2AF-4000-O Overthrust Condition
10/16/2024
2498569
2HX-15B Tube Leak Identified
10/18/2024
Corrective Action
Documents
2499818
2SI-867B Leakage Fails Under Normal TS-31 Test
Conditions
10/29/2024
110E035 Sheet 1
P&ID Safety Injection System
M-2207 Sheet 2
P&ID Service Water System
Drawings
M-2215 Sheet 1
P&ID Heating and Ventilation
Engineering
Evaluations
300123
2AF-4000 Overthrust Weak Link Review
11/04/2024
Miscellaneous
IST Background
Doc App A
PBNP Inservice Testing Background Valve Data Sheet
CMP 2.2.9
MOV Overthrust/Overtorque Review Guidance
Scaffold Installation, Modification, and Removal Requests
RMP 9043-18
Emergency Diesel Generator G-01 3 Year Relay
Maintenance
Procedures
TS 31
High and Low Head Safety Injection Check Valve Leakage
Test Unit 2
40819765-03
G-01; Control Relay Calibration per RMP 9043-18
08/16/2024
40860214-05
2AF-4026/Build Scaffold
09/25/2024
40860221-01
AF-04000-O: U2 MOV Actuator Diagnostics & Inspections
10/25/2024
40860221-04
2AF-4000-O, Overhaul Operator, MOV Overthrust Condition
10/25/2024
40860221-09
2AF-4000-O, Complete Operator Inspections Per ETR
300123
10/25/2024
Work Orders
40883994-01
TS-31, U2 High/Low Head SI Check Lkg Test (CSD)
10/29/2024
Corrective Action
2498267
Sheaves in Transfer System Showed Some Signs of Wear
10/16/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Clearance
125V SAF-4067 Maint
Clearance
MS MS-2082-O Stem Lube
Miscellaneous
Clearance
TU Turbine Site Craft Tagout
2RMP 9096-1
Reactor Vessel Head Removal and Installation using Biach
Tensioning System
Foreign Material Exclusion Procedure
NP 10.3.6
Shutdown Safety Review and Safety Assessment
OI 105
RCS Heatup/Cooldown Plotting
Reactor Startup
OP 3C Unit 2
Hot Standby to Cold Shutdown Unit 2
Clearance and Tagging
RP-1A
Preparation for Refueling
109
Procedures
RP-1D
Filling and Draining the Unit 2 Refueling Cavity and Unit 2
Cavity Purification
2497821
2N-31 Source Range Detector Not Indicating
10/12/2024
2497976
2B52-40C Did Not Close When in Test Position
10/13/2024
2498012
2B52-40C Failed to Trip During ORT 3A
10/13/2024
2498029
ORT 3A U2 G02 Data Channels 5-14 Not Recorded
10/14/2024
2498569
2HX-15B Tube Leak Identified
10/18/2024
2498972
2N-31 Source Range Spiking
10/22/2024
2503684
Unexpected Start of W-14B
2/13/2024
Corrective Action
Documents
2503718
2B52-328H W-13B1 CR Recirc Fan Breaker Thermal
Overload Trip
2/14/2024
2503890
IST Program Document - Inservice Testing Program
Document
2/16/2024
Corrective Action
Documents
Resulting from
Inspection
2504190
MI 32.5 - Installation, Adjustment, or Replacement of
Live-Loaded Valve Packing
2/19/2024
541F445
Drawings
Model D-100-160-2 1/2 Operator 3-1500 lb USA Std Valve
Assembly
Engineering
Changes
299177
Pressurizer Spray Valve Bellows Telltale Line Removal
10/17/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2ICP 04.024
NIS Source Range Channels Calibration and CHAR Testing
of Source and Intermediate Range Channels
2ICP 10.015-1A
Replacement of Source/Intermediate Range NIS Detector
Assembly 2N-31/2N-35
2RMP 9306-2
Main Steam Non-Return Check Valve
Inspection/Maintenance with Cover Removed (Unit 2)
IT 315
Main Steam Line Isolation Valves (Cold Shutdown) Unit 2
Maintenance Testing
MI 32.5
Installation, Adjustment, or Replacement of Live-Loaded
NP 7.2.5
Repair/Replacement Program
NP 7.4.3
Post-Maintenance NDE Requirements for Power Piping
ORT 31
Nitrogen Supply to the Pressurizer Relief Tank Unit 2
ORT 3A
Safety Injection Actuation with Loss of Engineered
Safeguards AC (Train A) Unit 2
Procedures
RMP 9106
Pressurizer Spray Line Control Valve Maintenance
1RMP 9056-1
Calibration and Testing of Safety Related Protective
Relays A-05
40826730-05
11/22/2024
40860467-01
2HX-015A/Motor Cooling Coil Insp/Cleaning (GL 89-13)
2/10/2024
40860567-01
2HX-015B/Motor Cooling Coil Insp/Cleaning (GL 89-13)
11/20/2024
40873850-02
2MS-02018A / Operations PMT (IT-315)
10/30/2024
40873850-11
2MS-02018A / Operations PMT (No Leaks)
11/06/2024
40879131-01
1A-05, Calibrate Tech Spec Relays
11/21/2024
40884248-03
2ICP 4.24 - Install Instrument Fuses and Calibrate SR N-31
10/17/2024
40956046-01
2RC-00431B / Open Inspect and Repair
10/31/2024
40956046-15
2RC-00431B / Remove Leak Det Line per EC 299177
10/20/2024
40994357-02
2N-31 Det: Replace SR/IR Detector Assy ( 2N31 / N35 )
10/16/2024
Work Orders
41001227
2B52-328H W-13B1 CR Recirc Fan Breaker Thermal Ove
2/17/2024
Miscellaneous
Point Beach Nuclear Plant, and the Manitowoc County,
Kewaunee County, and The State Of Wisconsin Design
Report, and Alert And Notification System Plan
01/15/2021
Procedures
EP 1.0
Point Beach Nuclear Plant Emergency Plan
Rev 33
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
N/A
ERO Staff Training Records: 25 Records
Various
Corrective Action
Documents
CR 02465214
Reduction in Effectiveness Identified in EC
08/23/2023
Miscellaneous
EP-AA-100-1007-
F02
RMS Functional Assessment for New System
Rev 2
EP 1.0
Point Beach Nuclear Plant Emergency Plan
Rev 33
Procedures
EPIP 1.2.1
Emergency Action Levels and Technical Basis
Rev 28
Calculations
KLD TR - 1377
Point Beach Nuclear Plant 2023 Population Update Analysis
09/11/2023
Miscellaneous
JNA 23-004
Fleet Nuclear Assurance Report - Emergency Preparedness
07/20/2023
Fuel Defect 2R40 Outage Preparation
Miscellaneous
23-01
Standing Order: Increased Unit 2 Monitoring Due to
Elevated Activity
06/26/2023
HP 2.17
Very High Radiation Area Personnel Access
HP 2.5
Radiation Work Permit
NISP-RP-005
Access Controls for High Radiation Areas
Procedures
ALARA Implementing Procedure
24-2015
Air Sample After Head Lift
10/17/2024
24-896
Air Sample for Initial Breach from Pressurizer
10/14/2024
24-938
Air Sample Total Results for Head Lift
10/17/2024
PBPROD-M-
241015-18
Lower Cavity Blind Flange and Strainer Removal
10/15/2024
PBPROD-M-
241015-2
Upper Cavity Post Centa Door Breach
10/15/2024
PBPROD-M-
241015-20
Lower Cavity Tri-Nuke Install
10/15/2024
PBPROD-M-
241015-3
Upper Cavity Breaching RVLIS and Rx Head Vent
10/15/2024
PBPROD-M-
241016-14
B RCP Lower Platform
10/16/2024
Radiation
Surveys
PBRPOD-M-
241015-42
Lower Cavity Gripper Inspection
10/15/2024
24-2015
Cavity Activities
Radiation Work
Permits (RWPs)
24-2016
Reactor Vessel Head - Remove/Reinstall
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
24-2050
Fuel Sipping Modification Activities
Corrective Action
Documents
Resulting from
Inspection
2502607
NRC Identified: MSPI and MRule UA Key Word Gap
2/02/2024
N/A
EP01 Drill and Exercise Performance (DEP)
01/01/2023-
2/31/2023
N/A
EP02 Emergency Response Organization Participation
(ERO)
01/01/2023-
2/31/2023
71151
Miscellaneous
PBN-BFJR-18-
054
MSPI Basis Document for PBNP
2476287
Wrong Component Event
01/10/2024
2477419
Core Drill Activity Started in Wrong Location
01/24/2024
2477499
Test Equipment not Removed Prior to Flow Block
Restoration
01/25/2024
2478119
Field Work Performed Prior to Approval of FCR
2/01/2024
2485694
24 NRC ARD Inspection - Incorrect G-501 Voltage
Documented
05/06/2024
2486377
24 NRC ARD - Missing Signature in WO Record
05/15/2024
2487439
Procedure Attachment not Filled Out as Required
05/30/2024
2492451
Exempt Source 2448-98 not Found in Designated Locked
Location
08/08/2024
2493277
Item Left in U1 Containment
08/19/2024
2494961
Wrong Red Lock Recorded During Performance of TS-81
09/09/2024
2495592
Inspection not Performed Under Correct WOs for Clearance
09/17/2024
2496029
Danger Tag Hung on Incorrect Component
09/23/2024
2496152
Escalation - PB Trend in Clearance and Tagging Issues
09/24/2024
2496236
Information Tag on Wrong Component
09/25/2024
2496383
Hourly Fire Rounds Missed
09/26/2024
2497738
Discharge Permit Missing Some Data
10/11/2024
2498313
Work Started Prior to Signing on to Correct Clearance
10/16/2024
Corrective Action
Documents
2498757
HU Investigation for Tagged Component
10/20/2024