IR 05000266/2023004

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Integrated Inspection Report 05000266/2023004 and 05000301/2023004
ML24032A056
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 02/01/2024
From: Billy Dickson
NRC/RGN-III/DORS/RPB2
To: Durbin M
Point Beach
References
IR 2023004
Preceding documents:
Download: ML24032A056 (1)
v • d • e


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: DPR-24 and DPR-27

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

Enclosure

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 Report Aspect Section Barrier Integrity Green [H.7] - 71111.08P NCV 05000266/2023004-01 Documentation Open/Closed 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 Report Aspect Section Barrier Integrity Green [H.12] - Avoid 71111.08P NCV 05000266/2023004-02 Complacency Open/Closed 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 Potential Failure to Correct 71152A Open 23004-03 an

NRC Identified

Violation

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)===

Main article: IP 71111.08

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1) Ultrasonic Examination

Dye Penetrant Examination

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

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

Corrective Action Documents

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

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)===

Main article: IP 71151
(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)===

Main article: IP 71152

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)

Main article: IP 71152
(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 Report Aspect Section Barrier Integrity Green [H.7] - 71111.08P NCV 05000266/2023004-01 Documentation Open/Closed 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 Report Aspect Section Barrier Integrity Green [H.12] - Avoid 71111.08P NCV 05000266/2023004-02 Complacency Open/Closed 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 Potential Failure to Correct an NRC Identified Violation 71152A (Open) URI 05000266,05000301/2023004-03

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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 02467591 Loss of Input from ISFSI 09/21/2023

Documents

Procedures AOP-21 PPCS Malfunction 21

OI-111 PPCS ISFSI Thermal Performance Monitoring Alarm 13

Response

OP-AA-102-1002 Seasonal Readiness 43

Work Orders 40850481-01 PC-49.3 - Cold Weather Preparation for PAB 09/29/2023

40850482-01 PC-49.4 - Cold Weather Preparation for PAB and Facades 09/29/2023

71111.04 Corrective Action 02470239 2MS-2082 Equipment Label 10/21/2023

Documents

Resulting from

Inspection

Drawings 110E017, Sheet 1 Safety Injection System 61

110E018, Sheet 1 Auxiliary Coolant System 71

ISI-2282 Isometric - Auxiliary Feedwater to Steam Generator B 0

ISI-2338 Isometric - Aux. Feedwater Pump 2P-29 3

M-217 Auxiliary Feedwater System 107

P-241 Emergency Feedwater from DB-3 into CTMT Penetration P-5 8

Procedures CL 13 E Part 1 Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 2 32

CL 7A Safety Injection System Checklist Mode 1, 2, 3 Unit 1 41

71111.05 Calculations 2014-0007 Allowable Flood Levels 5

Corrective Action 02469972 Cart Partially in a Flood Exclusion Zone 10/18/2023

Documents

Resulting from

Inspection

Fire Plans PFP-1-CONT-Pre-Fire Plan Unit 1 Containment Building/Facade 2

FAC

Procedures NP 8.4.17 PBNP Flooding Program 37

OM 3.27 Control of Fire Protection and NFPA 805 Equipment 83

71111.08P Corrective Action AR 02423369 Foreign Material Found on FA 1D19 03/31/2022

Documents AR 02423501 Piping Support Gap Dimensions Exceed Allowable Total 04/01/2022

AR 02423534 Foreign Material Discovered on Lower Core Plate 04/02/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

AR 02423607 Dry Boric Acid Residue on CETNAS 35 and 37 04/03/2022

AR 02423957 Foreign Material in Primary Side of Steam Generator 04/06/2022

AR 02424003 Indication Found on CTMT Liner Plate at Dome Truss #8 04/07/2022

AR 02424004 Horizontal Gouge Found on the Liner Plate at Dome Truss #2 04/07/2022

AR 02424005 Liner Plate - Working DT# 2 and #8 Removing the Required 04/07/2022

AR 02424259 Foreign Material from U1 Manipulator Bridge 04/09/2022

AR 02424354 Recordable Indications on U1 Containment Moisture Barrier 04/10/2022

AR 02469663 Unit 1 A RCP Welded Attachment Liquid Penetrant Indications 10/15/2023

AR 02469871 Liquid Penetrant Exam Indication Found on CCW Piping 10/17/2023

Corrective Action AR 02469557 NRC Identified - Potential Leak Chase Caulk Degradation 10/13/2023

Documents AR 02470057 NRC Identified: Containment Moisture Barrier Degradation 10/19/2023

Resulting from AR 02470059 NRC Identified 10/19/2023

Inspection AR 02470185 NRC Identified - Boric Acid Screening/Evaluation Deficiencies10/20/2023

AR 02471725 ISI Inspection Potential Violation 10 CFR 50.55 11/06/2023

AR 02471727 ISI Inspection Potential Violation App B Criterion V 11/06/2023

Engineering EC 298500 Revise DWG. and Calc for Support EB-9-FW-H4 for As-Built 05/26/2023

Changes Config

Engineering BAS22-059 Boric Acid Leak Screening R-1 Cetnas 35 and 37 04/04/2022

Evaluations 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-Point Beach Unit 1 Reactor Coolant Pump Flaw Assessment Rev. 0

P for As-Found Linear Indications During Fall 2020 Refueling

Outage

LTR-SDA-20-079-Point Beach Unit 1 Reactor Coolant Pump Flaw Assessment Rev. 1

P for As-Found Linear Indications During Fall 2020 Refueling

Outage

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 Type Designation Description or Title Revision or

Procedure 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

20U1Ven-004 PT of RCP-A-2-IWA 10/17/2020

PB1-IWEV-22-VT-3 of Moisture Barrier Section A1-A2 04/13/2022

109

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

Procedures ER-AP-116-1000 Boric Acid Corrosion Control Program Rev. 8

FP-PE-B31-Welding Procedure Specification Rev. 4

P1P8-GTSM-013

NDE-173 PDI Generic Procedure for the Ultrasonic Examination of Rev. 19

Austenitic Piping Welds

NDE-451 Visible Dye Penetrant Examination Temperature Applications Rev. 33

40F to 125F

NDE-451 Visible Dye Penetrant Examination Temperature Applications Rev. 32

40F to 125F

NDE-754 Visual Examination (VT-3) of Nuclear Power Plant Rev. 24

Components

NDE-757 Visual Examination (VE) ASME Class 1 Components Rev. 12

Fabricated with Alloy 600/82/182 Materials

NDE-760 VT-1, VT-3 & General Visual Examination of IWE Boundary Rev. 11

Components

WPS 8-MN-Welding Procedure Specification Rev. 7

GTAW

Work Orders WO 40278323 HB-19 Piping Replacement 09/01/2022

WO 40753055 Repair of Degraded Expansion Joints 04/12/2022

WO 40767857 CCW Piping Replacement 03/25/2021

71111.11A Miscellaneous Point Beach 2023 Compilation of Licensed Operator NRC Requalification Testing 12/04/2023

Inspection Type Designation Description or Title Revision or

Procedure Date

Licensed Results for 2023

Operator Annual

Operating Test

Results

71111.11Q Corrective Action 02468823 Emergency Power Supply Light Lit on U2 Turb EH Control 10/06/2023

Documents

Miscellaneous PBN LOC 21B Simulator Exercise Guide Scenario #4 0

004S

Work Orders 40952180 Emergency Power Supply Light Lit on U2 Turb EH Con 10/07/2023

71111.12 Corrective Action 02371361 1CV-1296 Failed Primary Boundary Leak Test 10/12/2020

Documents 02442792 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

2471207 1NI-40A WR Log Power Channel Failed Low 10/31/2023

Miscellaneous 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-Diesel Generator Maintenance Rule Function Scoping

SYS01 Document

PBN-C-125V-125 V DC Maintenance Rule Function Scoping Document

SYS01

Procedures ER-AA-100-2002 Maintenance Rule Program Administration 39

MA-AA-100-1028 Certification of Quality Control Inspection Personnel 0

NP 11.1.14 Inspection Planning 13

NP 11.1.15 Quality Control Inspections 8

PI-AA-104-1000 Condition Reporting 39

Work Orders 40760699-01 2LT-961 - Replace Sump B Level Transmitter 03/16/2023

40760699-02 2LT-961 - Bench Check Level Transmitter 12/12/2022

40774713-01 62/P-038A, P-038A Replace Agastat Relay per FBN 02364452 06/16/2023

Inspection Type Designation Description or Title Revision or

Procedure 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, 08/03/2023

K1

40836158-12 G-04, Replace Local-Remote Protective Relays 08/04/2023

40836491-01 G-04 - Replace Alarm Panel Capacitor 08/01/2023

71111.13 Corrective Action 02468875 N-31 SRNI Failed to Energize Following U1 S/D 10/07/2023

Documents 02468947 N-40 NI Fission Channel Has Periods of Spiking 10/07/2023

2469317 Transfer Tube Gate Valve Not Fully Shut 10/11/2023

2469615 Retest N-31/N-35 Detector Insulation Resistances in U1R41 10/14/2023

Drawings 110E018, Sheet 4 Auxiliary Cooling System 53

21595-21 Fuel Transfer Tube 2

21766-1 Fuel Transfer Arrangement 8

883D195, Sheet Nuclear Instrument Trip Signals 7

Miscellaneous PBNP Shutdown Safety Assessment and Fire Inspection 10/13/2023

Checklist for 10/13/2023 at 0045

PRF-1562 PBNP Shutdown Safety Assessment and Fire Inspection 10/21/2023

Checklist, Days

Procedures CL 1E Unit 1 Containment Closure Checklist Unit 1 32

NP 10.3.5 Risk Monitoring and Risk Management 3

NP 10.3.6 Shutdown Safety Review and Safety Assessment 37

OP 3B Reactor Shutdown 50

Work Orders 40821751 IN-31 DET: Replace SR/IR Detector Assy (IN31/N35) 10/10/2023

40830737 1ICP 4.24 - NI Source Range Ch. Insp, Mnt & Cal 10/10/2023

71111.15 Corrective Action 02398724 Sprinkler Deflector Below 1HX-22C MSR 07/16/2021

Documents 02463522 Repeat: Sprinkler Deflector Below 07/31/2023

1HX-22C MSR/2HX-22C MSR

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

2470289 Relief Valve Previously Installed Incorrectly 10/22/2023

Drawings 499B466, Sh 303 1B-03 480V Undervoltage Scheme 23

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous ACMP for the 1A-06/2A-06 SWGR Room Temp. 09/30/2023

Procedures MA-AA-203-1000 Maintenance Testing 20

NP 11.1.14 Inspection Planning 13

RMP 9377-1 Relief, Safety, and Safety Relief Valve Installation and 27

Removal

71111.18 Drawings 684J741, Sheet 3 Chemical and Volume Control 18

Engineering 298474 Replace 1P-1A RCP Seal Housing, Re-Route Bypass Piping 5

Changes

Procedures DG-M02 Westinghouse Piping Class Summary 16

EN-AA-205-1104 Standard Design Process 1

Work Orders 40605130 1P-1A/Install New RCP Seal Housing 10/26/2023

40830572 PB1, Unit 1 as Left RCS Pressure Test 11/02/2023

71111.20 Corrective Action 02471207 1NI-40A WR Log Power Channel Failed Low 10/31/2023

Documents

Corrective Action 02470968 NRC Containment Walkdown 10/28/2023

Documents

Resulting from

Inspection

Miscellaneous PBF-2058 Fire Protection/NFPA 805 Fire Surveillance 10/07/2023

Tagout 1 SI SI-866A-O 01 10/12/2023

Tagout 1 SI SI-878A-O 01 10/12/2023

Procedures AD-AA-101-1004 Work Hour Controls 24

FP-MA-ES-01 Electrical Safety 27

MA-AA-101-1000 Foreign Material Exclusion Procedure 30

OP 1B Reactor Startup 83

OP 1C Startup to Power Operation 50

OP 3C Hot Standby to Cold Shutdown 24

OP-AA-100-1007 Conduct of Fuel Handling Activities 3

OP-AA-101-1000 Clearance and Tagging 35

RESP 4.1 BOL Physics Tests 32

SY-AA-100-1011 Fatigue Management 10

71111.24 Corrective Action 02462392 2HX-12D As-Found Coating Inspection 2023 07/14/2023

Documents 02469560 1CV-1296, ORT 46 Results Unsat 10/13/2023

Inspection Type Designation Description or Title Revision or

Procedure Date

2469864 1ICP 05.021 - Pressurizer Level Control System Calibration 10/17/2023

2470715 IT 01A - High Head Safety Injection Pumps and Valves 10/26/2023

(Cold S)

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

Corrective Action 02462782 The PMT for 2HX-12D Was Questioned due to Vague 07/19/2023

Documents Guidance

Resulting from 02470696 Review OP-AA-100-1000 Guidance 10/25/2023

Inspection 02471803 NRC Identified M&TE Documented WO Record Copy Was 11/07/2023

Incorrect

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 12/15/2023

Repack

2475914 Valve Drawings May Not Reflect Installed Packing 01/04/2024

Drawings 684J741, Sheet 2 Chemical & Volume Control 84

684J741, Sheet 3 Chemical & Volume Control 18

88904 Forged Bolted Bonnet Primary Nuclear Motor Operated Gate 9

Valve for: ASA 1500 lb. - 10"

M-207, Sheet 4 Service Water System 31

Miscellaneous Supplement for WO 40830718-01 11/02/2023

Procedures IT 03D RHR Valve Exercise Test for Operation or Shutdown Unit 1 16

IT 08A Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve 93

Test (Quarterly)

IT 210 SI Valves (Cold Shutdown) 25

MA-100-1015 Valve Packing 8

Inspection Type Designation Description or Title Revision or

Procedure Date

MA-AA-100-1021 Motor Operated Valve Stem Lube and Actuator Gearbox 3

Grease Inspection

MA-AA-203-1000 Maintenance Testing 20

OI 55 Primary Leak Rate Calculation 35

ORT 46 Auxiliary Charging Line Unit 1 24

RMP 9106 Pressurizer Spray Line Control Valve Maintenance 22

RMP 9376-2 Limitorque MOV Testing for Gate and Globe Valves 30

TS 33 Containment Accident Recirculation Fan-Cooler Units Unit 143

Work Orders 40656662-01 1RH-00701 / Repack Valve 10/29/2023

40656662-02 1RH-00701 / Operations PMT 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 10/26/2023

Shutdown)

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 10/11/2023

Inspection

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

40856546-01 0-PT-FP-003 Electric Motor-Driven Fire Pump Functional Test10/13/2023

71114.04 Miscellaneous 10 CFR 50.54(q) Qualification Records (Spreadsheet) 05/05/2023

NUC EPR 2001 10 CFR 50.54(Q) Qualification Guide 0

Inspection Type Designation Description or Title Revision or

Procedure Date

PCR 02399684 50.54(Q) Screening for LAR 296 01/06/2023

Procedures EP 8.0 Maintaining Emergency Preparedness 58

EP 8.0 Maintaining Emergency Preparedness 59

71124.01 Corrective Action AR 02469336 RCP Draining Water on the 10 Foot Platform

Documents AR 02469531 Two Lapel Air Samplers Faulted

AR 02469579 RP Technician Received Dose Alarm

Corrective Action AR 02470037 Very High Radiation Area Barrier Questioned 10/19/2023

Documents

Resulting from

Inspection

Procedures HPIP 1.66 Dosimetry Placement for Extremity and Multiple Whole Body 21

Locations and Extremity Dose Determination

RP-AA-102-1000 Alpha Monitoring 8

RP-AA-103-1002 High Radiation Area Controls 13

Radiation Surveys PBPROD-M-1CV-1296 & 1CV-1426 Removal

231014-23

PBPROD-M-1RH-709B Cleaning and Gasket Replacement

231015-11

PBPROD-M-Breach and Posting Change for 1RH-709B

231015-6

PBPROD-M-1RH-709B-Lapping

231016-23

PBPROD-M-RCP Lower, A Side O Ring Removal and Shielding Install

231016-8

PBPROD-M-RCP Lower, A Side Impeller Removal

231016-9

Radiation Work 23-1021 RCP Seal Replacement 01

Permits (RWPs) 23-1032 Containment Valve Maintenance Activities 00

23-1034 PAB Valve Maintenance Activities 01

23-1069 A RCP Impeller Work 00

71124.03 Miscellaneous Crew A SCBA The Self-Contained Breathing Apparatus Qualifications of 10/13/2023

Qualification Crew A

Status

Procedures HPIP 3.52 Airborne Radioactivity Surveys 51

Inspection Type Designation Description or Title Revision or

Procedure Date

NP 4.2.32 Respiratory Protection Program 23

Work Orders Work Order PC-75.1 Perform Maintenance on the SCBA 09/27/2023

Package

40856649-01

71124.04 Corrective Action AR 02470095 Dose Assessment Process Enhancements 10/19/2023

Documents

Resulting from

Inspection

Miscellaneous Personnel Contamination Event Dose Assessment 02/24/2023

Procedures HPIP 1.60 Calculating Shallow and Deep Dose Rates due to Skin 17

Contamination

NISP-RP-006 Portable Personnel Contamination Monitoring 1

71151 Procedures 2ICP 02.003A Reactor Protection System Logic Train A Surveillance Test 15

PBN-BFJR-18-MSPI Basis Document for PBNP 29

054

Work Orders 40827293-01 2P-11B-M, MCE Analyze Motor 08/10/2023

71152A Corrective Action 02430785 SAT Analysis Work Order Documentation (NRC Identified) 06/27/2022

Documents 02430785 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

2474248 Alarm on Fireworks, Leak Now Affecting Electronics of FS 12/11/2023

Corrective Action 02472083 PMC In Screening for Extended Amount of Time 11/10/2023

Documents 02472083 PMC In Screening for Extended Amount of Time 11/10/2023

Resulting from 02473217 CA Untimely due to Inappropriate Closure to PMCR 11/28/2023

Inspection 02473415 PMT WO Task Not Closed 11/30/2023

Drawings M-208 Sheet 4 P&ID Fire Protec./Sprinkler Sys. Point Beach N.P. Unit 1 28

Miscellaneous RSI 4973 The Effect of Vacuum Breaker Maintenance Practices and 0

Nitrogen Cover Gas Elimination on Spray Additive Tank

Sodium Hydroxide and Concentration Measurements at Point

Beach

Procedures MA-AA-204-1000- Preventive Maintenance Change Request (PMCR) 16

10001

PI-AA-104-1000 Condition Reporting 39

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 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

40957465-02 1C-042, Operations PMT/RTS 11/29/2023

71152S Corrective Action 02449867 Relief Valve Lifted and will not Reseat 03/02/2023

Documents 02452187 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

2471749 1LO-3609 Relief Valve Failed Its As-Found Test 11/06/2023

Inspection Type Designation Description or Title Revision or

Procedure Date

2471993 1LO-243 Relief Valve Failed Its As-Found Test 11/09/2023

28

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