IR 05000266/2023004
| ML24032A056 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/01/2024 |
| From: | Billy Dickson NRC/RGN-III/DORS/RPB2 |
| To: | Durbin M Point Beach |
| References | |
| IR 2023004 | |
| Download: ML24032A056 (1) | |
Text
SUBJECT:
POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2023004 AND 05000301/2023004
Dear Michael Durbin:
On December 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On January 8, 2024, 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.
Two findings of very low safety significance (Green) are documented in this report. Two of these findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or the significance or severity of the violations 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 Point Beach Nuclear Plant.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Point Beach Nuclear Plant.
February 1, 2024 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, Billy C. Dickson, 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:
05000266/2023004 and 05000301/2023004
Enterprise Identifier:
I-2023-004-0055
Licensee:
NextEra Energy Point Beach, LLC
Facility:
Point Beach Nuclear Plant
Location:
Two Rivers, WI
Inspection Dates:
October 01, 2023 to December 31, 2023
Inspectors:
G. Hansen, Sr. Emergency Preparedness Inspector
T. Hooker, Health Physicist
E. Magnuson, Reactor Inspector
J. Masse, Resident Inspector
V. Myers, Senior Health Physicist
V. Petrella, Resident Inspector
E. Sanchez Santiago, Senior Project Engineer
M. Stafford, Senior Resident Inspector
Approved By:
Billy C. Dickson, 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
Failure to Demonstrate Acceptability for Continued Service for Indications Detected in a Reactor Coolant Pump Welded Support Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000266/2023004-01 Open/Closed
[H.7] -
Documentation 71111.08P The inspectors identified a finding of very low safety significance (Green) and an associated non-cited violation (NCV) of 10 CFR 50.55a(g)(4) for the failure to evaluate and accept for service a relevant indication in accordance with ASME Section XI requirements. Specifically, the licensee failed to evaluate and accept for continued service a relevant indication found during a regularly scheduled exam of reactor coolant pump (RCP) welded support RCP-A-1-IWA.
Failure to Establish Acceptance Criteria for ASME Section XI Successive Exam of a Welded Support Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000266/2023004-02 Open/Closed
[H.12] - Avoid Complacency 71111.08P The inspectors identified a finding of very low safety significance (Green) and an associated non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the failure to establish appropriate quantitative or qualitative acceptance criteria when performing an ASME Section XI successive exam on RCP welded support RCP-A-1-IWA. Specifically, the licensee did not establish acceptance criteria to determine if the evaluation of the actual indication growth during successive examinations against the predicted growth was satisfactorily accomplished.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000266,05000301/20 23004-03 Potential Failure to Correct an
NRC Identified
Violation 71152A Open
PLANT STATUS
Unit 1 began the inspection period in a coast down for a refueling outage, at approximately 93 percent power. On October 7, 2023, operators shutdown Unit 1 from approximately 90 percent power for the scheduled refueling outage. On October 31, 2023, operators restarted Unit 1. On November 1, 2023, operators synchronized the unit to the grid, and on November 4, 2023, 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 seasonal cold temperatures for the following systems:
Instrument power white and yellow inverters; D-105 and D-106 batteries; Independent Spent Fuel Storage Installation (ISFSI) temperature monitoring indication on December 22, 2023.
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 system on October 24, 2023
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 residual heat removal system on December 20, 2023.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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 505, 511, 516, and 520 on October 18, 2023
- (2) Fire zone 524 on October 18, 2023
===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.
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 Weld: RC-10-AC-1001-03, Cat. R-A/R1.11
- Reactor Coolant System Weld: RC-10-AC-1001-04, Cat. R-A/R1.11
- Reactor Coolant System Weld: RC-10-AC-1001-04, Cat. AUG/MRP-146 Dye Penetrant Examination
- Reactor Coolant Pump Welded Attachment: RCP-A-1-IWA, B-K/B10.30 Visual Examination
- VT-3 of Welded Spring Support: SI-2501R-2-SI-1, F-A/F1.10C
- VT-3 of Containment Moisture Barrier: G1-G2-J4, E-A/E1.30 Welding Activities
- Weld Repair/Replacement of HB-19 Service Water to Engineered Safeguards Piping Work Order (WO) 040278323-16
- Installation of RTD Bypass Manifolds WO 40678285-31,32
- Weld Repair/Replacement of CCW Piping WO 40767857 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the license conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
(1)
- Bare metal visual of Unit 1 reactor 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
- BAS22-059 R1 CETNAS 35 and 37 Corrective Action Documents
- AR 02423607 - Dry Boric Acid Residue on CETNAS 35 and 37 Walkdowns
- Performed on October 7, 2023
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 on August 14, 2023-November 22, 2023.
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 shutdown and cooldown on October 6 and October 7, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator simulator training on November 13, 2023.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 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)125V direct current electrical system
- (2) Containment isolation valves and primary containment integrity
- (3) Source range instruments
- (4) Diesel generator fuel oil system
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSCs remain capable of performing their intended function:
(1)
- Unit 2 containment sump B level transmitter
- P-38A minimum recirculation control time delay relay
- G-04 emergency diesel generator protective relays
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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) Unit 1 source range instrument failure during refueling outage on October 7, 2023
- (2) Unit 1 containment key safety function with boundary valve not fully closed on October 11, 2023
- (3) Unit 1 elevated risk due to the G-05, Gas Turbine Generator, going out of service on October 13, 2023
- (4) Unit 1 yellow risk during core re-load on October 21, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Operability determination for fire sprinklers on October 10, 2023
- (2) Operability of service water pumps following 480V bus ground on October 16, 2023
- (3) Operability determination for the diesel generator building air handling unit, HX-269, not cooling on October 17, 2023
- (4) Operability determination for the nitrogen relief valve for the Unit 1 pressurizer power operated relief valve on December 19, 2023
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) Permanent modification to the 1P-1A reactor coolant pump seal leak-off line
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage U1R41 activities from October 6, 2023, to November 9, 2023.
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) (8 Samples)
- (1) Post maintenance test after maintenance on the 2HX-12D, Unit 2 Component Cooling Water Heat Exchanger, on July 19, 2023
- (2) Post maintenance test after the calibration of 2-274/A05, 2A-05 bus degraded voltage relay, on August 16, 2023
- (3) Post maintenance test of the auxiliary feed pump discharge valve following stem and actuator lubrication, on October 11, 2023
- (4) Post maintenance test after the pressurizer level control system calibration on October 16, 2023
- (5) Post maintenance test after relay replacement on the 1-62/A01, bus time delay relay, on November 7, 2023
- (6) Post maintenance test after the calibration of the condensate storage tank level instruments using ICP 06.099, Condensate Storage Tank Level Instruments, on November 9, 2023
- (7) Post maintenance test after contactors and thermal overload relay testing on the 1MS-02082, 1P-29, auxiliary feedwater turbine-driven pump, overspeed trip starter, on November 16, 2023
- (8) Post maintenance test after packing replacement on the 1RH-701, reactor coolant system to P10-A/B residual heat removal pump suction header, motor operated valve on December 14, 2023
Surveillance Testing (IP Section 03.01) (5 Samples)
- (1) IT 210, safety injection valve testing during cold shutdown, on October 19, 2023
- (2) TS 33, containment accident recirculation fan-cooler units, on October 27, 2023
- (3) IT 01A, High Head Safety Injection Pumps and Valves (Cold Shutdown) Unit 1, on November 15, 2023 (4)0-PT-FP-003, Electrical Motor-Driven Fire Pump Functional Test, on October 13, 2023
- (5) IT 08A, Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly)
Unit 1, on November 27, 2023
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) IT 05 Train A, Train A Containment Spray Pump and Valves Unit 1, on August 23, 2023
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) ORT 46, Auxiliary Charging Line Unit 1, on October 13, 2023
Reactor Coolant System Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Unexpected rise in Unit 2 unidentified leak rate on November 14, 2023
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.
- PCR No. 02399684, dated January 6, 2023 This evaluation does not constitute NRC approval.
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) (3 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Surveys of potentially contaminated material leaving the radiologically controlled area
- (2) Workers exiting the radiologically controlled area
- (3) Workers exiting the protected area
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 coolant pump impeller replacement
- (2) Residual heat removal system valve work
- (3) Reactor coolant pump seal replacement
- (4) Chemical volume control valve work in containment High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
- (1) Unit 1 demineralizer valve gallery
- (2) Unit 1 residual heat removal cubicle
- (3) Unit 1 containment keyway entrance
- (4) Unit 1 transfer tube 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
Permanent Ventilation Systems (IP Section 03.01) (1 Sample)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Primary auxiliary building ventilation system
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.
Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situations:
- (1) Shallow dose equivalent assessment from a discrete radioactive particle
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) Unit 1 (July 1, 2022 through September 30, 2023)
- (2) Unit 2 (July 1, 2022 through September 30, 2023)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2022 through September 30, 2023)
- (2) Unit 2 (October 1, 2022 through September 30, 2023)
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Review of one bank of the Unit 1 E pressurizer heaters group not cycling
- (2) Review of the leaking FS-3764, G-01 diesel generator sprinkler flow switch
- (3) Review of NRC identified non-cited violation pertaining to sodium hydroxide concentrations in the spray additive tank
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in relief valve as-found testing failures that might be indicative of a more significant safety issue. The inspectors observed that there was an increase in corrective action documents related to relief valves of approximately 15 percent compared to previous years. However, the inspectors did not identify any adverse trends that could lead to a more significant safety concern. All of these relief valve testing failures were handled appropriately by the licensee and a majority of these were associated with non-safety related valves.
INSPECTION RESULTS
Failure to Demonstrate Acceptability for Continued Service for Indications Detected in a Reactor Coolant Pump Welded Support Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000266/2023004-01 Open/Closed
[H.7] -
Documentation 71111.08P The inspectors identified a finding of very low safety significance (Green) and an associated non-cited violation (NCV) of 10 CFR 50.55a(g)(4) for the failure to evaluate and accept for service a relevant indication in accordance with ASME Section XI requirements. Specifically, the licensee failed to evaluate and accept for continued service a relevant indication found during a regularly scheduled exam of reactor coolant pump (RCP) welded support RCP-A-1-IWA.
Description:
In October 2020, the licensee performed an ASME code required liquid penetrant (PT) exam on RCP welded support RCP-A-1-IWA and identified two relevant linear indications in the area of the weld between the RCP casing and the welded attachment. Due to the general location, and a previous history of surface cracks created by casting shrinkage, the licensee dispositioned both linear indications as casting defects from original construction.
The licensee then contracted with Westinghouse to perform an analytical evaluation and accepted both linear indications for continued service. In Westinghouse evaluation LTR-SDA-20-079-P, Rev. 0, both linear indications were evaluated as casting defects in the casing of the RCP. The fracture evaluation cited historical fracture analysis of similar casting shrinkage defects in the pump casing and thermal aging and embrittlement of the pump casing, to determine maximum permissible flaw sizes for defects found in the pump casing.
The most limiting case accepted a 25 percent through wall flaw in the pump casing, with an aspect ratio of 6:1, for the remaining operating life of the plant. While the depth of both flaws discovered in 2020 was unable to be determined due to material limitations of cast pump casing, historical analysis of similar flaws showed that the flaws were likely to be no deeper than 0.24 inches if they were casting defects. The flaw evaluation determined that both indications were acceptable for continued service using the previous analyses to bound the indications discovered in the field.
In October 2023, during a successive exam performed on the two indications found in 2020, licensee personnel documented the location of linear indication #2 from the 2020 exam as in the centerline of the weld between the pump casing and the welded attachment. Review of previous exam reports for RCP-A-1-IWA from 2010 showed that both linear indications found in 2020 had not been present during the exam performed in 2010.
The inspectors determined that the original flaw evaluation contained in LTR-SDA-20-079-P, Rev. 0 did not evaluate indication #2 for continued service. Specifically, ASME Subsection IWB-3142.4 titled, Acceptance by Analytical Evaluation, states A component containing relevant conditions is acceptable for continued service if an analytical evaluation demonstrates the components acceptability. The original evaluation used fracture mechanics for casting induced service defects to bound the maximum flaw size and historical data from previously detected casting flaws to bound the likely maximum depth of both indications. While this approach may be bounding for the indication contained entirely in the pump casing, it was not appropriate for a service induced flaw in the support weld.
Westinghouse analysis LTR-SDA-20-079-P, Rev. 1 used the standard ASME Section XI, Subsection IWB-3600 flaw analysis methods to predict the future growth of the flaw.
Furthermore, while the original evaluation was for the remaining life of the plant, the revised evaluation was only valid for two operating cycles, when the weld is scheduled to be reexamined and the results used to justify acceptability for the remaining life of the plant.
Corrective Actions: The licensee entered the issue into the corrective action program and reevaluated indication #2 in Westinghouse analysis LTR-SDA-20-079-P, Rev. 1, and accepted both indications for continued service. While the licensee determined the original evaluation remained applicable for indication #1 for the life of the plant, the new evaluation for indication #2 used a different analysis method and also limited the applicability of the analytical evaluation for two operating cycles. Specifically, the new analysis used the flaw evaluation methods of IWB-3600, because the original methodology did not bound flaws identified in the weld material. Continued successive exams of both indications are planned to be performed in accordance with IWB-2420 to verify that the predicted flaw growth for both indications remains bounding.
Corrective Action References: AR 02471725 - ISI Inspection Potential Violation 10 CFR 50.55
Performance Assessment:
Performance Deficiency: The licensees failure to demonstrate the acceptability for continued service of a relevant indication found in a weld of support RCP-A-1-IWA was contrary to ASME Section XI, Subsection IWB-3142.4, and was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the failure to demonstrate the acceptability of a service induced defect that was allowed to remain in service in an ASME Class 1 support would have the potential to challenge the structural integrity of the support and its associated safety barrier.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
Specifically, the inspectors utilized IMC 0609, Appendix A, Exhibit 1, Initiating Events Screening Questions. The inspectors determined the finding was of very low safety significance (Green) because it did not result in an RCS leak or likely affect other systems used to mitigate a loss of coolant accident.
Cross-Cutting Aspect: H.7 - Documentation: The organization creates and maintains complete, accurate and up-to-date documentation. Specifically, the original PT exam report did not adequately describe the location of the two indications. It provided a general schematic photograph and two close-up photographs of the indications. As a result, the licensee did not accurately establish the location of indication #2 in the weld between the support and the pump casing and did not evaluate it correctly for continued service. The inspectors noted similar issues with the additional exam performed on welded support RCP-A-2-IWA, where rounded indications were located only with photographs, rather than quantitative measurements of the location.
Enforcement:
Violation: 10 CFR 50.55a(g)(4) requires, in part, that components (including supports) that are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements set forth in Section XI of editions and addenda of the ASME BPV Code. ASME Section XI (2007 edition), Subsection IWB-3142.4 states A component containing relevant conditions is acceptable for continued service if an evaluation demonstrates the components acceptability.
The evaluation and acceptance criteria shall be specified by the Owner.
Contrary to the above, from October 20, 2020, until October 26, 2023, the licensee failed meet the requirements set forth in Section XI of editions and addenda of the ASME BPV Code of a component classified as ASME Code Class 1. Specifically, the licensee did not demonstrate the acceptability for continued service of a relevant indication found in a weld of support RCP-A-1-IWA because they evaluated it as a casting defect in the pump casing of the RCP, when it was a service induced defect in the weld of the support.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Failure to Establish Acceptance Criteria for ASME Section XI Successive Exam of a Welded Support Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000266/2023004-02 Open/Closed
[H.12] - Avoid Complacency 71111.08P The inspectors identified a finding of very low safety significance (Green) and an associated non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the failure to establish appropriate quantitative or qualitative acceptance criteria when performing an ASME Section XI successive exam on RCP welded support RCP-A-1-IWA. Specifically, the licensee did not establish acceptance criteria to determine if the evaluation of the actual indication growth during successive examinations against the predicted growth was satisfactorily accomplished.
Description:
In October 2020, while performing an ASME Section XI liquid penetrant (PT) exam on reactor coolant pump (RCP) welded support RCP-A-1-IWA, the licensee discovered two linear indications exceeding the acceptance criteria of ASME Section XI Table IWB-3410-1. ASME Section XI provides two options for addressing flaws or relevant conditions that exceed the IWB-3410-1 acceptance criteria: repair/replacement activity or analytical evaluation. The licensee accepted the flaws for continued service via Westinghouse analysis LTR-SDA-20-079-P, Rev. 0.
According to ASME Section XI IWB-2420, components with flaws or relevant conditions accepted for service through analytical evaluation must be reexamined for the subsequent three inspection periods. During each successive inspection, the growth of the flaw or relevant condition must be compared with the predicted flaw growth from the analytical evaluation. If the flaw growth remains within the acceptance criteria predicted by the analytical evaluation, the component continues to be inspected for the remaining periods. If the flaw growth exceeds the predicted growth, IWB-2420(d) requires reexamination of the entire component and examination of additional components in accordance with IWB-2430.
In October 2023, the licensee performed the first successive PT exam on RCP-A-1-IWA.
They observed both indications had grown in length by an amount they judged to be small. In AR 02469663, the licensee evaluated the linear indications as essentially unchanged from the previous exam. However, the inspectors noted the licensee did not include growth acceptance criteria in the successive PT exam instructions.
This was noteworthy because indications are detected with PT exams via bleedout, and the size and shape of the bleedout are influenced by the exam itself, in addition to the associated flaw. Consequently, the measurement of the indication does not directly correlate to the flaw measurement. The lack of acceptance criteria for determining growth evaluation created an unclear standard for dispositioning linear indications during successive exams.
Furthermore, as per IWB-2420(d), additional actions are required if the flaws growth exceeds that of the analytical evaluation. However, there was no clear standard for determining if those actions were necessary.
Corrective Actions: The licensee entered the issue into their corrective action program, established growth acceptance criteria for both indications via Westinghouse Analysis LTR-SDA-20-079-P, Rev. 1, and confirmed both indications met the acceptance criteria.
Corrective Action References: AR 02471727 - ISI Inspection Potential Violation App B Criterion V ISI
Performance Assessment:
Performance Deficiency: The licensees failure to establish acceptance criteria for the successive PT exam of RCP-A-1-IWA was contrary to 10 CFR 50 Appendix B, Criterion V, and was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the failure to establish acceptance criteria for the successive exam of RCP support RCP-A-1-IWA would have the potential to allow growth of a service induced flaw to continue beyond the bounds of the flaw growth predicted by the analytical evaluation.
Such flaw growth would have the potential to challenge the structural integrity of the support and its associated safety barrier.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
Specifically, the inspectors utilized IMC 0609, Appendix A, Exhibit 1, Initiating Events Screening Questions, and determined the finding was of very low safety significance (Green)because it did not result in an RCS leak or likely affect other systems used to mitigate a loss of coolant accident.
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, due to the licensees position on the identified flaw being acceptable for continued service for the life of the plant, they did not plan for the possibility of a different outcome during the successive examinations. They also did not apply error reduction techniques of ensuring they had all the information necessary to perform the exam to completion, which included verification any identified flaw growth would not require additional exam expansions or evaluations.
Enforcement:
Violation: Title 10 CFR 50 Appendix B, Criterion V, Instructions, Procedures, and Drawings requires, in part, that instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
Contrary to the above, since approximately October 2020, the licensee failed to establish appropriate quantitative or qualitative acceptance criteria in instructions for determining that important activities have been satisfactorily accomplished. Specifically, the licensee accepted two indications found on RCP welded support RCP-A-1-IWA through analytical evaluation, involving successive ASME Section XI examinations to evaluate actual indication growth against the predicted growth. However, in their successive examination instructions, contained in WO 40748764-01, the licensee did not establish acceptance criteria to determine if the evaluation of the actual indication growth during successive examinations against the predicted growth was satisfactorily accomplished.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Unresolved Item (Open)
Potential Failure to Correct an NRC Identified Violation URI 05000266,05000301/2023004-03 71152A
Description:
In July 2022, the NRC issued a non-cited violation of 10 CFR 50, Appendix B, Criterion V, for the licensees failure to prescribe an appropriate instruction or procedure with the appropriate acceptance criteria for determining the technical specification required concentration of sodium hydroxide in the spray additive tank. Specifically, the licensee failed to include instrument uncertainty when calculating the sodium hydroxide concentration. The licensees corrective action for this violation was to submit a change to the preventative maintenance (PM) model work order, which calculated this concentration.
In 2023, when reviewing the PM work order instructions, the inspectors identified that the procedures were the same as in 2022, ignoring instrument uncertainty. The licensee uses the Asset Information Center (AIC) program to perform PM changes. Inspectors found that the licensee had failed to correctly enter the PM into AIC by leaving the required asset change table empty. This failure caused the PM change to linger in AIC, and the licensee never updated the PM model work order.
Inspectors found no requirements to check the status of PM changes in AIC, and further questioning showed several other PM changes missing similar information. While these other examples were administrative, the oldest change that remained in AIC dates back to 2020.
The licensee performed this work order twice with the incorrect instructions for each unit between July 2022 and October 2023. The results of these tests were within the narrower band, which considered instrument uncertainty.
Planned Closure Actions: Because the inspectors did not gather all of the required information until close to the end of the quarter a URI is being issued. The inspectors need to work with regional experts from the Enforcement & Investigation Coordination Staff team to determine if this violates NRC requirements.
Licensee Actions: Once the licensee became aware of the problem, they updated the asset change table and made assignments to progress the change through the AIC system. The PM model work order has been updated.
Corrective Action References: AR 02472083 - PMC in Screening for Extended Amount of Time and AR 02473217 - CA Untimely due to Inappropriate Closure to PMCR
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 8, 2024, the inspectors presented the integrated inspection results to Michael Durbin, Site Vice President, and other members of the licensee staff.
- On October 20, 2023, the inspectors presented the radiation protection inspection results to Michael Durbin, Site Vice President, and other members of the licensee staff.
- On November 3, 2023, the inspectors presented the In-service inspection results to Seth Johnson, Site Maintenance Director, and other members of the licensee staff.
- On November 30, 2023, the inspectors presented the Emergency Action Level and Emergency Plan change review inspection results to Eric Schultz, Regulatory Affairs Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2467591
Loss of Input from ISFSI
09/21/2023
PPCS Malfunction
OI-111
PPCS ISFSI Thermal Performance Monitoring Alarm
Response
Procedures
Seasonal Readiness
40850481-01
PC-49.3 - Cold Weather Preparation for PAB
09/29/2023
Work Orders
40850482-01
PC-49.4 - Cold Weather Preparation for PAB and Facades
09/29/2023
Corrective Action
Documents
Resulting from
Inspection
2470239
2MS-2082 Equipment Label
10/21/2023
110E017, Sheet 1
Safety Injection System
110E018, Sheet 1
Auxiliary Coolant System
ISI-2282
Isometric - Auxiliary Feedwater to Steam Generator B
ISI-2338
Isometric - Aux. Feedwater Pump 2P-29
M-217
Auxiliary Feedwater System
107
Drawings
P-241
Emergency Feedwater from DB-3 into CTMT Penetration P-5
CL 13 E Part 1
Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 2
Procedures
CL 7A
Safety Injection System Checklist Mode 1, 2, 3 Unit 1
Calculations
2014-0007
Allowable Flood Levels
Corrective Action
Documents
Resulting from
Inspection
2469972
Cart Partially in a Flood Exclusion Zone
10/18/2023
Fire Plans
PFP-1-CONT-
Pre-Fire Plan Unit 1 Containment Building/Facade
NP 8.4.17
PBNP Flooding Program
Procedures
OM 3.27
Control of Fire Protection and NFPA 805 Equipment
Foreign Material Found on FA 1D19
03/31/2022
Piping Support Gap Dimensions Exceed Allowable Total
04/01/2022
Corrective Action
Documents
Foreign Material Discovered on Lower Core Plate
04/02/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Dry Boric Acid Residue on CETNAS 35 and 37
04/03/2022
Foreign Material in Primary Side of Steam Generator
04/06/2022
Indication Found on CTMT Liner Plate at Dome Truss #8
04/07/2022
Horizontal Gouge Found on the Liner Plate at Dome Truss #2
04/07/2022
Liner Plate - Working DT# 2 and #8 Removing the Required
04/07/2022
Foreign Material from U1 Manipulator Bridge
04/09/2022
Recordable Indications on U1 Containment Moisture Barrier
04/10/2022
Unit 1 A RCP Welded Attachment Liquid Penetrant Indications
10/15/2023
Liquid Penetrant Exam Indication Found on CCW Piping
10/17/2023
NRC Identified - Potential Leak Chase Caulk Degradation
10/13/2023
NRC Identified: Containment Moisture Barrier Degradation
10/19/2023
NRC Identified
10/19/2023
NRC Identified - Boric Acid Screening/Evaluation Deficiencies
10/20/2023
ISI Inspection Potential Violation 10 CFR 50.55
11/06/2023
Corrective Action
Documents
Resulting from
Inspection
ISI Inspection Potential Violation App B Criterion V
11/06/2023
Engineering
Changes
Revise DWG. and Calc for Support EB-9-FW-H4 for As-Built
Config
05/26/2023
BAS22-059
Boric Acid Leak Screening R-1 Cetnas 35 and 37
04/04/2022
BAS23-013
Boric Acid Leak Screening 2SI-829B
01/27/2023
BAS23-123
Boric Acid Leak Screening 1SI-835A
10/09/2023
BAS23-124
Boric Acid Leak Screening 1SI-878B
10/09/2023
BAS23-125
Boric Acid Leak Screening 1RH-720
10/09/2023
BAS23-128
Boric Acid Leak Screening 1CV-270A
10/10/2023
BAS23-130
Boric Acid Leak Screening 1SC-950
10/10/2023
BAS23-135
Boric Acid Leak Screening 1P-1A
10/17/2023
LTR-SDA-20-079-
P
Point Beach Unit 1 Reactor Coolant Pump Flaw Assessment
for As-Found Linear Indications During Fall 2020 Refueling
Outage
Rev. 0
LTR-SDA-20-079-
P
Point Beach Unit 1 Reactor Coolant Pump Flaw Assessment
for As-Found Linear Indications During Fall 2020 Refueling
Outage
Rev. 1
Engineering
Evaluations
NPC-47876
Report of Unit 1 Reactor Coolant Pump A Flaw Evaluations
05/01/1989
NDE Reports
2010PT-004
PT of RCP-A-1-IWA
03/18/2010
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2010VT-033
VT-3 of EB-9-FW-H4
03/10/2010
20U1 Ven-005
PT of RCP-A-1-IWA
10/15/2020
PT of RCP-A-2-IWA
10/17/2020
PB1-IWEV-22-
109
VT-3 of Moisture Barrier Section A1-A2
04/13/2022
PB1-PT-23-003
PT of RCP-A-1-IWA
10/16/2023
PB1-UT-23-015
UT of RC-10-AC-1001-03
10/13/2023
PB1-UT-23-016
UT of RC-10-AC-1001-04
10/13/2023
PB1-UT-23-017
MRP-146 UT of RC-10-AC-1001-04
10/13/2023
PB1-UT-23-029
UT of RC-10-AC-1001-03
10/13/2023
PB1-VT-22-012
VT-3 of EB-9-FW-H4
04/08/2022
PB1-VT-23-030
VT-3 of SI-2501R-2-SI-1
10/16/2023
Boric Acid Corrosion Control Program
Rev. 8
FP-PE-B31-
Welding Procedure Specification
Rev. 4
NDE-173
PDI Generic Procedure for the Ultrasonic Examination of
Austenitic Piping Welds
Rev. 19
NDE-451
Visible Dye Penetrant Examination Temperature Applications
40F to 125F
Rev. 33
NDE-451
Visible Dye Penetrant Examination Temperature Applications
40F to 125F
Rev. 32
NDE-754
Visual Examination (VT-3) of Nuclear Power Plant
Components
Rev. 24
NDE-757
Visual Examination (VE) ASME Class 1 Components
Fabricated with Alloy 600/82/182 Materials
Rev. 12
NDE-760
VT-1, VT-3 & General Visual Examination of IWE Boundary
Components
Rev. 11
Procedures
WPS 8-MN-
Welding Procedure Specification
Rev. 7
HB-19 Piping Replacement
09/01/2022
Repair of Degraded Expansion Joints
04/12/2022
Work Orders
CCW Piping Replacement
03/25/2021
Miscellaneous
Point Beach 2023
Compilation of Licensed Operator NRC Requalification Testing 12/04/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Licensed
Operator Annual
Operating Test
Results
Results for 2023
Corrective Action
Documents
2468823
Emergency Power Supply Light Lit on U2 Turb EH Control
10/06/2023
Miscellaneous
PBN LOC 21B
004S
Simulator Exercise Guide Scenario #4
Work Orders
40952180
Emergency Power Supply Light Lit on U2 Turb EH Con
10/07/2023
2371361
1CV-1296 Failed Primary Boundary Leak Test
10/12/2020
2442792
Received Unexpected C02E 1-10 G-04 Diesel Trip or Lockout
11/30/2022
2463453
G-04 EDG Fuel Oil Pump
07/30/2023
2466593
G-02-42/FTC2 G-02 FO Pump #2 Relay Failed
09/10/2023
2468875
N-31 SRNI Failed to Energize Following U1 S/D
10/07/2023
2468947
N-40 NI Fission Channel Has Periods of Spiking
10/07/2023
2469615
Retest N-31/N-35 Detector Insulation Resistances in U1R41
10/14/2023
Corrective Action
Documents
2471207
1NI-40A WR Log Power Channel Failed Low
10/31/2023
PBN-1-CI-SYS01
Primary Containment Integrity Maintenance Rule Function
Scoping Document
PBN-1-NI-SYS01
Nuclear Instrumentation Maintenance Rule Function Scoping
Document
PBN-2-DG-
SYS01
Diesel Generator Maintenance Rule Function Scoping
Document
Miscellaneous
PBN-C-125V-
SYS01
25 V DC Maintenance Rule Function Scoping Document
Maintenance Rule Program Administration
Certification of Quality Control Inspection Personnel
NP 11.1.14
Inspection Planning
NP 11.1.15
Quality Control Inspections
Procedures
Condition Reporting
40760699-01
2LT-961 - Replace Sump B Level Transmitter
03/16/2023
40760699-02
2LT-961 - Bench Check Level Transmitter
2/12/2022
Work Orders
40774713-01
2/P-038A, P-038A Replace Agastat Relay per FBN 02364452
06/16/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40836158-08
G-04, Replace BTR and SDRX2 Protective Relays
08/03/2023
40836158-10
G-04, Replace CTL/Protective Contactors FF, FFP1, BPMC,
K1
08/03/2023
40836158-12
G-04, Replace Local-Remote Protective Relays
08/04/2023
40836491-01
G-04 - Replace Alarm Panel Capacitor
08/01/2023
2468875
N-31 SRNI Failed to Energize Following U1 S/D
10/07/2023
2468947
N-40 NI Fission Channel Has Periods of Spiking
10/07/2023
2469317
Transfer Tube Gate Valve Not Fully Shut
10/11/2023
Corrective Action
Documents
2469615
Retest N-31/N-35 Detector Insulation Resistances in U1R41
10/14/2023
110E018, Sheet 4
Auxiliary Cooling System
21595-21
Fuel Transfer Tube
21766-1
Fuel Transfer Arrangement
Drawings
883D195, Sheet
Nuclear Instrument Trip Signals
PBNP Shutdown Safety Assessment and Fire Inspection
Checklist for 10/13/2023 at 0045
10/13/2023
Miscellaneous
PRF-1562
PBNP Shutdown Safety Assessment and Fire Inspection
Checklist, Days
10/21/2023
CL 1E Unit 1
Containment Closure Checklist Unit 1
NP 10.3.5
Risk Monitoring and Risk Management
NP 10.3.6
Shutdown Safety Review and Safety Assessment
Procedures
Reactor Shutdown
40821751
IN-31 DET: Replace SR/IR Detector Assy (IN31/N35)
10/10/2023
Work Orders
40830737
1ICP 4.24 - NI Source Range Ch. Insp, Mnt & Cal
10/10/2023
2398724
Sprinkler Deflector Below 1HX-22C MSR
07/16/2021
2463522
Repeat: Sprinkler Deflector Below
07/31/2023
2463555
WR Needed to Move Guard on Sprinkler
08/01/2023
2468196
HX-269 Not Cooling
09/29/2023
2468250
Review 1(2)A06 ACMP for an Operator Challenge
09/30/2023
2469640
1B-03 Ground Fault Upon Re-energization
10/15/2023
Corrective Action
Documents
2470289
Relief Valve Previously Installed Incorrectly
10/22/2023
Drawings
499B466, Sh 303
1B-03 480V Undervoltage Scheme
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
ACMP for the 1A-06/2A-06 SWGR Room Temp.
09/30/2023
Maintenance Testing
NP 11.1.14
Inspection Planning
Procedures
RMP 9377-1
Relief, Safety, and Safety Relief Valve Installation and
Removal
Drawings
684J741, Sheet 3
Chemical and Volume Control
Engineering
Changes
298474
Replace 1P-1A RCP Seal Housing, Re-Route Bypass Piping
DG-M02
Westinghouse Piping Class Summary
Procedures
Standard Design Process
40605130
1P-1A/Install New RCP Seal Housing
10/26/2023
Work Orders
40830572
PB1, Unit 1 as Left RCS Pressure Test
11/02/2023
Corrective Action
Documents
2471207
1NI-40A WR Log Power Channel Failed Low
10/31/2023
Corrective Action
Documents
Resulting from
Inspection
2470968
NRC Containment Walkdown
10/28/2023
PBF-2058
Fire Protection/NFPA 805 Fire Surveillance
10/07/2023
Tagout
SI SI-866A-O 01
10/12/2023
Miscellaneous
Tagout
SI SI-878A-O 01
10/12/2023
Work Hour Controls
FP-MA-ES-01
Electrical Safety
Foreign Material Exclusion Procedure
Reactor Startup
Startup to Power Operation
Hot Standby to Cold Shutdown
Conduct of Fuel Handling Activities
Clearance and Tagging
RESP 4.1
BOL Physics Tests
Procedures
Fatigue Management
2462392
2HX-12D As-Found Coating Inspection 2023
07/14/2023
Corrective Action
Documents
2469560
1CV-1296, ORT 46 Results Unsat
10/13/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2469864
1ICP 05.021 - Pressurizer Level Control System Calibration
10/17/2023
2470715
IT 01A - High Head Safety Injection Pumps and Valves
(Cold S)
10/26/2023
2471287
2RE-211, Cont. Air Part. Rad Mon. Step Change & Increasing
10/31/2023
2471375
OI 55 Primary Leak Rate
11/01/2023
2471401
OI 55 Primary Leak Rate
11/01/2023
2471407
U2 Increase Unidentified RCS Leakage
11/01/2023
2471421
Operator Challenge Determination
11/01/2023
2471423
Various Boric Acid Buildup Found During U2 Cont Entry
11/01/2023
2471750
2RC-431B PZR Spray Valve Steam Leak
11/06/2023
2462782
The PMT for 2HX-12D Was Questioned due to Vague
Guidance
07/19/2023
2470696
Review OP-AA-100-1000 Guidance
10/25/2023
2471803
NRC Identified M&TE Documented WO Record Copy Was
Incorrect
11/07/2023
2471808
Timely Writing of AR for NRC Identified Issue Not Written
11/07/2023
2471925
ICP 06.099 - Condensate Storage Tank Level Instruments
11/08/2023
2473108
Record Supplement Required for WO 40856397-01
11/27/2023
2473127
IST Sign-Off in IT 08A Not Completed Correctly
11/27/2023
2474630
NRC Identified Work Package Closeout Gap for 1RH-701
Repack
2/15/2023
Corrective Action
Documents
Resulting from
Inspection
2475914
Valve Drawings May Not Reflect Installed Packing
01/04/2024
684J741, Sheet 2
Chemical & Volume Control
684J741, Sheet 3
Chemical & Volume Control
88904
Forged Bolted Bonnet Primary Nuclear Motor Operated Gate
Valve for: ASA 1500 lb. - 10"
Drawings
M-207, Sheet 4
Service Water System
Miscellaneous
Supplement for WO 40830718-01
11/02/2023
IT 03D
RHR Valve Exercise Test for Operation or Shutdown Unit 1
IT 08A
Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve
Test (Quarterly)
IT 210
SI Valves (Cold Shutdown)
Procedures
MA-100-1015
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Motor Operated Valve Stem Lube and Actuator Gearbox
Grease Inspection
Maintenance Testing
OI 55
Primary Leak Rate Calculation
ORT 46
Auxiliary Charging Line Unit 1
RMP 9106
Pressurizer Spray Line Control Valve Maintenance
RMP 9376-2
Limitorque MOV Testing for Gate and Globe Valves
TS 33
Containment Accident Recirculation Fan-Cooler Units Unit 1
40656662-01
1RH-00701 / Repack Valve
10/29/2023
40656662-02
11/08/2023
40656662-03
1RH-00701-O / Perform MOV Actuator Check-out
10/21/2023
40747600
Replace 1CV-01296 During Next Outage
10/13/2023
40811889-01
2A-05, Calibrate Tech Spec Relays
08/16/2023
40811889-11
2-274/A05 Perform Calibration of Degraded Voltage Relay
08/16/2023
40821613-01
1-62/A01 - Calibrate New Replacement Relay
10/02/2023
40821613-02
1-62/A01 - Replace Relay
10/22/2023
40830354-01
1SMS-02082 - Contactor & Thermal Overload Testing
10/16/2023
40830354-03
1MS-2082 - Return to Service
11/08/2023
40830508-01
IT-01A, High Head Safety Injection Pumps/Valves (Cold
Shutdown)
10/26/2023
40830685-01
1-62/A01 - Calib & Test UV Bus Stripping Time Delay Relay
10/25/2023
40830718-01
1ICP 5.21 - Pressurizer Level Control System Calibration
10/19/2023
40830934
AF-4001-0: U1 MOV Stem Lube/Actuator Gearbox Grease
Inspection
10/11/2023
40834570-01
2HX-012D GL 89-13 Open/Inspect/Clean/Close HX
09/15/2023
40834570-02
2HX-012D Operations PMT/RTS
09/15/2023
40834570-21
2HX-012D Contingency Perform Section XI System Leak Test
09/15/2023
40856193-01
ICP 6.99 - Condensate Storage Tanks Level Inst Cal
11/06/2023
40856397-01
IT-08A, 1P-29 AFP Cold Start Test/Valves
11/01/2023
40856421-01
IT-05 Train A
10/02/2023
Work Orders
40856546-01
0-PT-FP-003 Electric Motor-Driven Fire Pump Functional Test
10/13/2023
CFR 50.54(q) Qualification Records (Spreadsheet)
05/05/2023
Miscellaneous
NUC EPR 2001
CFR 50.54(Q) Qualification Guide
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PCR 02399684
50.54(Q) Screening for LAR 296
01/06/2023
EP 8.0
Maintaining Emergency Preparedness
Procedures
EP 8.0
Maintaining Emergency Preparedness
RCP Draining Water on the 10 Foot Platform
Two Lapel Air Samplers Faulted
Corrective Action
Documents
RP Technician Received Dose Alarm
Corrective Action
Documents
Resulting from
Inspection
Very High Radiation Area Barrier Questioned
10/19/2023
HPIP 1.66
Dosimetry Placement for Extremity and Multiple Whole Body
Locations and Extremity Dose Determination
Alpha Monitoring
Procedures
High Radiation Area Controls
PBPROD-M-
231014-23
PBPROD-M-
231015-11
1RH-709B Cleaning and Gasket Replacement
PBPROD-M-
231015-6
Breach and Posting Change for 1RH-709B
PBPROD-M-
231016-23
PBPROD-M-
231016-8
RCP Lower, A Side O Ring Removal and Shielding Install
Radiation Surveys
PBPROD-M-
231016-9
RCP Lower, A Side Impeller Removal
23-1021
RCP Seal Replacement
23-1032
Containment Valve Maintenance Activities
23-1034
PAB Valve Maintenance Activities
Radiation Work
Permits (RWPs)
23-1069
A RCP Impeller Work
Miscellaneous
Crew A SCBA
Qualification
Status
The Self-Contained Breathing Apparatus Qualifications of
Crew A
10/13/2023
Procedures
HPIP 3.52
Airborne Radioactivity Surveys
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NP 4.2.32
Respiratory Protection Program
Work Orders
Work Order
Package
40856649-01
PC-75.1 Perform Maintenance on the SCBA
09/27/2023
Corrective Action
Documents
Resulting from
Inspection
Dose Assessment Process Enhancements
10/19/2023
Miscellaneous
Personnel Contamination Event Dose Assessment
2/24/2023
HPIP 1.60
Calculating Shallow and Deep Dose Rates due to Skin
Contamination
Procedures
NISP-RP-006
Portable Personnel Contamination Monitoring
2ICP 02.003A
Reactor Protection System Logic Train A Surveillance Test
Procedures
PBN-BFJR-18-
054
MSPI Basis Document for PBNP
71151
Work Orders
40827293-01
2P-11B-M, MCE Analyze Motor
08/10/2023
2430785
SAT Analysis Work Order Documentation (NRC Identified)
06/27/2022
2430785
SAT Analysis Work Order Documentation (NRC Identified)
06/27/2022
2472729
SW Leak on FS-3764, G-01 DG Sprinkler Flow Switch
11/19/2023
2472966
One Bank of the E PZR Heater Group Not Cycling
11/23/2023
2473217
CA Untimely due to Inappropriate Closure to PMCR
11/28/2023
Corrective Action
Documents
2474248
Alarm on Fireworks, Leak Now Affecting Electronics of FS
2/11/2023
2472083
PMC In Screening for Extended Amount of Time
11/10/2023
2472083
PMC In Screening for Extended Amount of Time
11/10/2023
2473217
CA Untimely due to Inappropriate Closure to PMCR
11/28/2023
Corrective Action
Documents
Resulting from
Inspection
2473415
11/30/2023
Drawings
M-208 Sheet 4
P&ID Fire Protec./Sprinkler Sys. Point Beach N.P. Unit 1
Miscellaneous
RSI 4973
The Effect of Vacuum Breaker Maintenance Practices and
Nitrogen Cover Gas Elimination on Spray Additive Tank
Sodium Hydroxide and Concentration Measurements at Point
Beach
MA-AA-204-1000-
10001
Preventive Maintenance Change Request (PMCR)
Procedures
Condition Reporting
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40819818-01
SAT NAOH SR 3.06.07.3
01/11/2023
40819820-01
SAT NAOH SR 3.06.07.3
01/11/2023
40847898-01
SAT NAOH SR 3.06.07.3
07/13/2023
40847905-01
SAT NAOH SR 3.06.07.3
07/13/2023
40957465-01
1T-1E, One Bank of the E PZR Heater Group Not Cycling
11/24/2023
Work Orders
40957465-02
1C-042, Operations PMT/RTS
11/29/2023
2449867
Relief Valve Lifted and will not Reseat
03/02/2023
2452187
2SI-887 Relief Valve Seal Broken
03/24/2023
2453733
2CS-2108 Relief Valve Failed As-Found Testing
04/07/2023
2454105
2AF-4079B Fail Its As-Found Test after Removal
04/11/2023
2454747
2SW-2963 Relief Valve Failed Its As-Found Test
04/17/2023
2454756
2SW-2959 Relief Valve Failed Its As-Found Test
04/17/2023
2454780
2SW-2885 Relief Valve Failed Its As-Found Test
04/17/2023
2455025
2LO-258 Relief Valve Failed Its As-Found Test
04/19/2023
2455031
2CV-257 Relief Valve Failed Its As-Found Test
04/19/2023
2456037
2AF-4079B Relief Valve Failed Its As-Found Test
04/28/2023
2457217
0SW-04440 Relief Valve Failed Its As-Found Test
05/09/2023
2457544
WL-1330B Relief Valve Failed Its As-Found Test
05/12/2023
2457671
WL-1130A Relief Valve Failed Its As-Found Test
05/15/2023
2457689
SW-4438 Relief Valve Failed Its As-Found Test
05/15/2023
2457796
MRC Cognitive Trend Relief Valves Failing As-Found Testing
05/16/2023
2459247
SW Piping Blockage on SW-2801 Relief Valve Inlet Piping
2462368
2CC-00721D Relief Valve Failed Its As-Found Test
07/14/2023
2462378
2SW-0293 Relief Valve Failed Its As-Found Test
07/14/2023
2463835
DA-6372B Relief Valve Failed Its As-Found Test
08/04/2023
2471083
1SW-0431 Relief Valve Failed Its As-Found Test
10/30/2023
2471355
1CC-747D Relief Valve Failed Its As-Found Test
11/01/2023
2471418
1FD-2412 Relief Valve Failed Its As-Found Test
11/01/2023
2471419
1FD-2410 Relief Valve Information
11/01/2023
2471530
1AF-4079B Relief Valve Failed Its As-Found Test
11/02/2023
2471541
1CS-2187 Relief Valve Failed Its As-Found Test
11/03/2023
2471588
1CC-751 Relief Valve Failed Its As-Found Test
11/03/2023
Corrective Action
Documents
2471749
1LO-3609 Relief Valve Failed Its As-Found Test
11/06/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2471993
1LO-243 Relief Valve Failed Its As-Found Test
11/09/2023