IR 05000266/2020001

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Integrated Inspection Report 05000266/2020001 and 05000301/2020001
ML20134J119
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 05/13/2020
From: Richard Skokowski
NRC/RGN-III
To: Craven R
Point Beach
References
IR 2020001
Preceding documents:
Download: ML20134J119 (21)
v • d • e


Text

May 13, 2020

SUBJECT:

POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2020001 AND 05000301/2020001

Dear Mr. Craven:

On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On April 8, 2020, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Richard A. Skokowski, Chief Branch 4 Division of Reactor Projects 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: 05000266/2020001 and 05000301/2020001 Enterprise Identifier: I-2020-001-0051 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant Location: Two Rivers, WI Inspection Dates: January 01, 2020 to March 31, 2020 Inspectors: K. Barclay, Resident Inspector J. Cassidy, Senior Health Physicist G. Edwards, Health Physicist T. Hartman, Senior Resident Inspector J. Neurauter, Senior Reactor Inspector Approved By: Richard A. Skokowski, Chief Branch 4 Division of Reactor Projects 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

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period at rated thermal power and remained at or near full power throughout the remainder of the inspection period.

Unit 2 began the inspection period at rated thermal power. On February 28, 2020, the unit began coastdown for the upcoming refueling outage. On March 14, 2020, the unit was taken offline for planned refueling outage U2R37. The unit remained offline for the remainder of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/readingrm/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. From January 1 - March 19, 2020, the inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week and during that time conducted plant status activities as described in IMC 2515, Appendix D; and observed risk significant activities when warranted. In addition, resident and regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In the cases where it was determined the objectives and requirements could not be performed remotely, management elected to postpone and reschedule the inspection to a later date.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

External Flooding Sample (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) G-01 emergency diesel generator (EDG) on January 31, 2020
(2) 1P-29 turbine-driven auxiliary feedwater pump on February 12-13, 2020

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Fire Zones 770, 771, 772, and 773, associated with the G-03 emergency diesel generator and the 1AO6 switchgear on February 6, 2020
(2) Fire Zones 775, 776, and 777, associated with the G-04 emergency diesel generator and the 2AO6 switchgear on February 6, 2020
(3) Fire Zones 552 and 553, associated with the service water pumphouse on February 7, 2020

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

Main article: IP 71111.08
(1) The inspectors verified the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and repairs and replacements were appropriately fabricated, examined and accepted by reviewing documentation of the following activities from March 23, 2020 to March 31, 2020:

03.01.a - Nondestructive Examination and Welding Activities.

  • Visual Examination (VT-3/General Visual-IWE) of Containment, ASME Category E-A, Component Liner Plates, Elevation 46 Feet, 0 Degrees to 60 Degrees
  • Visual examination (VT-3) of chemical and volume control system rigid pipe support, ASME Category F-A, Component 42-10-PHA
  • Component cooling water pump 2P-11A replacement, weld sample including:

W-7-2a, W-7-5, W-7-6, W-7-8, W-7-10, W-8-2, W-8-4, W-8-6, W-8-8, W-8-10, W-D-1, and W-S-1 (Work Order 40104738-45 and Work Order 40104738-45, Supplement 1)03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

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 2 reactor and plant shutdown on March 14, 2020.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed a crew performance evaluation practice (CPE) scenario in the simulator on January 27, 2019.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) RE-235 control room noble gas monitor and the failure to shift control room ventilation to recirculation mode on November 3, 2019

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) G-03 EDG maintenance work window from January 27-31, 2020
(2) G-02 EDG maintenance work window from February 10-11, 2020
(3) 2P-15B safety injection pump maintenance on March 3, 2020
(4) W-85 battery charger and inverter room fan maintenance on March 5, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 1 turbine-driven auxiliary feedwater accumulator check valve leaks excessively
(2) G-05 gas turbine battery cell temperatures below minimum
(3) FLEX mode 5/6 makeup pumps did not receive all required testing
(4) multiple issues identified during emergency diesel generator G-04 endurance run
(5) Unit 2 manipulator crane slack cable set incorrectly

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:

(1) G-05 gas turbine generator testing on January 16, 2020
(2) G-03 emergency diesel generator testing on January 31, 2020
(3) D-09 battery charger on February 25-26, 2020
(4) 2P-10B residual heat removal pump on March 4, 2020

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1) (Partial)

The inspectors evaluated refueling outage U2R37 activities from March 13 to March 31, 2020.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

Main article: IP 71111.22
(1) ORT 3B, Safety Injection Actuation with Loss of Engineered Safeguards AC (Train B)

Unit 2, on March 17, 2020

(2) 1 RMP 9071-1, A-05 4160/480 Degraded and Loss of Voltage, on February 19, 2020

Inservice Testing (IP Section 03.01) (1 Sample)

(1) IT 03 Train B, Low Head Safety Injection Pumps and Valves, Train B Unit 1, on

March 25, 2020 RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) detailed review of the calculated Unit 1 RCS unidentified leakage values during the week ending February 29,

RADIATION SAFETY

71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,

and Transportation Shipping Records (IP Section 02.05) (1 Partial)

The inspectors evaluated the following non-excepted package shipment records:

(1) (Partial)

The inspectors initiated review of shipment record 19-037.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

Main article: IP 71151
(1) Unit 1 January 1 - December 31, 2020
(2) Unit 2 January 1 - December 31, 2020 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)

(2 Samples)

(1) Unit 1 January 1 - December 31, 2020
(2) Unit 2 January 1 - December 31, 2020

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 January 1 - December 31, 2020
(2) Unit 2 January 1 - December 31, 2020

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) control room recirculation fan flow switch troubleshooting
(2) unplanned reactor coolant system level drop

INSPECTION RESULTS

Observation: Wrong Component Worked On While Troubleshooting Control 71152 Room Recirculation Fan Flow Switch On January 24, 2020, while troubleshooting the start circuit for W-13B1, control room recirculation fan, a maintenance technician performed work on an incorrect component. The licensee was testing control room ventilation flow switches, which are part of the W-13B1 start circuit, when the error occurred.

The licensee intended to work on FS-4133B, W-13 B1/B2 control room recirculation fan low flow discharge flow switch, but inadvertently worked on FS-4133C, W-13B2 control room recirculation fan flow switch. The maintenance technician made the error because he proceeded to work on a component without an official label. Specifically, FS-4133C did not have an official label and was incorrectly marked FS-4133B with a handwritten note. The error was identified when the licensee didn't get the expected system response during testing. The entire system was already removed from service for troubleshooting and no additional loss of system function occurred.

The licensee entered the issue into the corrective action program as AR 2342555 and initially designated it as a condition report (CR). The inspectors review found that the licensee changed the CR to a routine work task (RWT), and its content focused on the lack of proper labeling without mention of working on the wrong component or any human performance problems.

The inspectors challenged the licensee about the designation of the AR and the limited information that was provided about the error. The licensee acknowledged that a human performance issue had occurred, and that the AR should have been coded as a CR. The station took a maintenance crew clock reset, communicated the event to the crafts, and the discussed the proper response when they find an unlabeled component.

Because the components aren't covered under 10 CFR 50, Appendix B, no violations of NRC requirements were identified.

Observation: Unplanned Reactor Coolant System Level Drop 71152 On March 19, 2020, the licensee identified an approximate 2 gallons per minute leak on the diaphragm of 2CV-399, the Unit 2 C charging pump suction valve. The reactor was shutdown at the time of the leak with the reactor vessel head disassembly in progress and the reactor was in lowered inventory with a time to core boil of 20 minutes. In-progress outage activities, which also had the potential to reduce water level, masked the leak indication as the control room operators assumed the lowering level was related to the planned activities.

The licensee was preparing to add water to account for planned losses when they determined that the loss rate was larger than expected. The licensee used the charging system to restore reactor vessel level and located the leak on 2CV-399 approximately thirty minutes later. Once the leak was isolated, the operators then reduced charging flow (input) to match the new letdown flow (output). Overall, the leakage lasted for approximately 1.5 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before water level was restored.

Total reactor coolant system inventory loss was estimated at about 300 gallons. The lowest reactor vessel level recorded was approximately 66. percent, which was below the licensees target value of 70 percent, but above 55 percent, which is the Reduced Inventory milestone as defined in Generic Letter 88-17, Loss of Decay Heat Removal. At the time of the leak, the licensee had at least one safety injection pump available to inject to the core if needed.

The licensee documented the issue in their corrective action program as AR 2349012. No violations of NRC requirements were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On April 8, 2020, the inspectors presented the integrated inspection results to Mr. R. Craven, Site Director and other members of the licensee staff.
  • On March 31, 2020, the inspectors presented the Unit 2 Inservice Inspection (ISI)inspection results to Mr. R. Craven, Site Director, and other members of the licensee staff.
  • On April 14, 2020, the inspectors presented the radiation protection inspection activities associated with radioactive waste shipment 19-037 inspection results to Ms. J. Walters, Radiation Protection Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action AR 02308488 Crane Pad Placed In Drainage Path to Lake 04/02/2019

Documents

Miscellaneous PBF-2124a Point Beach Nuclear Plant Mean Converted Lake Level 3

Calculation

Procedures AOP-13C Severe Weather Conditions 49

NP 8.4.17 PBNP Flooding Program 32

RMP 9422 Circulating Water Pumphouse and Turbine Hall Barrier 2

Placement

Work Orders WO 40648717 Z-1108 / Inspect Flood Barrier for Door 2 12/02/2019

WO 40657505 PC 6 Part 9 Operations Flood Equipment Inventory 02/17/2020

71111.04 Corrective Action AR 02344613 PM to Inspect Safety Related (SR) Steam Traps not Coded 02/13/2020

Documents SR

Resulting from AR 02345013 1(2)AF-4002 Recirculation Valve Air Hose SR 02/18/2020

Inspection Documentation

AR 02345017 WR: Replace 1AF-04002-O Air Supply Hose 02/18/2020

AR 02345019 WR: Replace 2AF-04002-O Air Supply Hose 02/18/2020

AR 02347299 CR 02344613 Reopened for Rescreening 03/05/2020

AR 02347722 Drawing Error On M-209 Sh. 12 Diesel Air Drawing 03/09/2020

Drawings M-201 Sh. 1 P&ID Main & Reheat Steam System 62

M-209 Sh. 12 P&ID Emergency Diesel Air Starting System 23

M-217 Sh. 1 P&ID Auxiliary Feedwater System 104

M-217 Sh. 2 P&ID Auxiliary Feedwater System 38

M-219 Sh. 1 P&ID Fuel Oil System 51

M-219 Sh. 2 P&ID Fuel Oil System Diesel Generator Building 16

Miscellaneous Modification 92- IST Testability of 2AF-4002 (2P-29 Mini-Recirc) 11/23/1992

2

Procedures CL 10D Fuel Oil Systems 24

CL 11A G-01 G-01 Diesel Generator Checklist 28

CL 13E Part 1 Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 1 52

Work Orders WO 40573336 1P-29 - Inspect and Repair Steam Traps 04/14/2020

71111.05 Corrective Action AR 02343857 HR-73 Hose Has Cracking in Outer Rubber Sheath 02/06/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents AR 02343992 Hose Reels In CWPH Have Cracking In Fire Hose Rubber 02/07/2020

Resulting from Jacket

Inspection AR 02343993 Wheeled Ansul Fire Extinguisher Out of PFP-0-PAN 02/07/2020

Location

Fire Plans PFP-0-PAN Pre-Fire Plan Protected Area North 1

Miscellaneous Door Card Reader Logs; Doors - 18, 27, 28, 321, 324, 600, 02/05-

601, 602 06/2020

FPTE 2016-043 PBNP Detailed Fire Modeling Report - Fire Compartment 1

773GRP - G-03 Switchgear Room - Diesel Generator

Building

FPTE 2016-044 PBNP Detailed Fire Modeling Report - Fire Compartment 1

777GRP - G-04 Diesel Room - Diesel Generator Building

FPTE 2106-045 PBNP Detailed Fire Modeling Report - Fire Compartment 1

777GRP - G-04 Switchgear Room - Diesel Generator

Building

PBF-2058A Fire Round Performance Sheet - PAB - Four Hour and 02/05-

(Completed) Hourly 06/2020

PBF-2058B Fire Round Performance Sheet-Turbine Hall and 02/05-

(Completed) Mscellaneous Areas - Four Hour and Hourly 06/2020

Procedures OM 3.27 Control of Fire Protection and NFPA 805 Equipment 71

71111.08P Corrective Action 02284227 During 2-PT-RH-1, Found Packing Leak on 2CV-133 10/06/2018

Documents 02284241 Boric Acid Found on 2SC-955 10/07/2018

284703 2HX-21B Broken Partition Plate Bolts 10/09/2018

285553 Foreign Material Found on Lower Core Plate in Location G-9 10/12/2018

286960 Unable to Determine Acceptance of Constant Support 10/20/2018

Settings

287835 Active Packing Boric Acid Leak on 2SI-878C 10/25/2018

2337609 Dry, White, Light Boric Acid on 2SI-897A 12/06/2019

2341751 2SI-897B, 1Q20 Walkdowns Identified Wet Boric Acid on 01/20/2020

Packing

2348547 Replace / Remake Swagelok Fitting 03/15/2020

2348554 2LY-427, Lower Bellows Tubing Connection, Boric Acid 03/15/2020

2348559 2RC-581, Downstream Tubing Fitting, Boric Acid Indication 03/15/2020

2348563 2SC-955, Valve Yoke Boric Acid Corrosion 03/16/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

2348815 Inactive Boric Acid Leak from 2CV-302B 03/17/2020

Corrective Action 02350634 NRC Unit 2 Inservice Inspection (ISI) Inspection - Liquid 03/31/2020

Documents Penetrant/Magnetic Particle Examination (PT/MT) in Lieu of

Resulting from Radiographic Examination (RT) in Repair/Replacement Plan

Inspection 2018-002

2350663 Boric Acid Indications Not Identified / Recorded 03/31/2020

Engineering EC 273506 Unit 2 Component Coolant Pump Replacement - Upgrades 17

Changes for Reliability

Miscellaneous BAE 18-068-E Boric Acid Evaluation: 2SC-955 Valve Packing Leak 10/07/2018

BAE 18-087-E Boric Acid Evaluation: 2SI-878C Valve Packing Leak 10/25/2018

BAE 20-004-E Boric Acid Evaluation: 2SI-897B Valve Packing Leak 01/20/2020

BAE 20-056-E Boric Acid Evaluation: 2SC-955 Valve Packing Gland 03/17/2020

Leakage

BAE 20-064-E Boric Acid Evaluation: 2CV-302B Cap Fitting Leak 03/18/2020

BAS18-072 Boric Acid Screening: 2CV-133 Valve Packing Leak 10/08/2018

BAS19-127 Boric Acid Screening: 2SI-897A Valve Packing Gland or 12/06/2019

Packing Gland Follower Leak

BAS20-052 Boric Acid Screening: 2CV-V-1 Leakage Downstream of 03/15/2020

Swagelok Fitting

BAS20-053 Boric Acid Screening: 2LT-427 Lower Bellows Tube Leak 03/15/2020

BAS20-055 Boric Acid Screening: 2RC-581 Downstream Swagelok 03/15/2020

Fitting Leak

RR 2018-002 Repair / Replacement Activity: Valve 2AF-106 Replacement 5

and Support DB-3-2D2

RR 2018-013 Repair / Replacement Activity: Unit 2 Component Cooling 2

Water Pump 2P-011A Replacement

WPS FP-PE-B31- Welding Procedure Specification: P1 Carbon Steel to P1 6

P1P1-GTSM-001 Carbon Steel

NDE Reports 2020U2MT-001 Magnetic Particle Examination of Feedwater Nozzle to 03/25/2020

Steam Generator Shell Weld, Component SG-A-6R1

20U2UT-034 UT Calibration/Examination: Ultrasonic Examination of Pipe 03/24/2020

Elbow-to-Elbow Weld, Component RC-03-CH-2001-24

20U2VT-005 Visual Examination of Pipe Hanger, Support or Restraint 03/23/2020

(VT-3), Rigid Support, Component 42-10-PHA

Inspection Type Designation Description or Title Revision or

Procedure Date

20U2VT-029 Visual Examination of IWE Surfaces (VT-3), Containment 03/23/2020

Liner Plates, Component 46 Foot Elevation, 0 Degrees to 60

Degrees

WO 40104738-08 Replace Pump 2P-011A Per EC 273506: Hydrostatic Test of 10/03/2018

Pump Suction, Pump Discharge and New Cross Connect

WO 40104738-25 Replace Pump 2P-011A Per EC 273506: Weld 12/05/2018

Nondestructive Examination Records

WO 40104738-28 Replace Pump 2P-011A Per EC 273506: Hydrostatic Test of 10/17/2018

New Component Cooling Water Pump 2P-011A and Piping

WO 40575118-03 Valve 2AF-106 Replacement: Weld Non-Destructive 12/06/2018

Examination Records

WO 40575118-11 Valve 2AF-106 Replacement: Radiography Examination 12/06/2018

Records, Field Welds

WO 40575118-19 Valve 2AF-106 Replacement: Pipe Support Welds - Non- 12/06/2018

Destructive Examination Records

Procedures NDE-173 PDI Generic Procedure for the Ultrasonic Examination of 18

Austenitic Piping Welds

NDE-350 Magnetic Particle Examination, Alternating Current (AC) 34

Yoke

NDE-753 Visual Examination (VT-2), Leakage Detection of Nuclear 19

Power Plant Components

NDE-754 Visual Examination of Nuclear Power Plant Components 21

NDE-760 VT-1, VT-3 & General Visual Examination of IWE Boundary 10

Components

PDI-UT-2 Generic Procedure for the Ultrasonic Examination of H

Austenitic Piping Welds

WP-1 Welding Procedure for Carbon Steels, Group P-1 to P-1, 8

GTAW-SMAW

Work Orders 40104738-08 Replace Pump 2P-011A Per EC 273506: Hydrostatic Test of 10/03/2018

Pump Suction, Pump Discharge and New Cross Connect

40104738-25 Replace Pump 2P-011A Per EC 273506: Weld 12/05/2018

Nondestructive Examination Records

40104738-28 Replace Pump 2P-011A Per EC 273506: Hydrostatic Test of 10/17/2018

New Component Cooling Water Pump 2P-011A and Piping

Inspection Type Designation Description or Title Revision or

Procedure Date

40104738-45 Replace Pump 2P-011A Per EC 273506: Weld 12/05/2018

Documentation Task

40104738-45, Replace Pump 2P-011A Per EC 273506: Weld 12/11/2018

Supplement S01 Documentation Task

40575118-03 Valve 2AF-106 Replacement: Weld Non-Destructive 12/06/2018

Examination Records

40575118-08 Valve 2AF-106 Replacement: Weld Documents; Groove and 10/29/2018

Fillet Weld Data; Weld Maps

40575118-11 Valve 2AF-106 Replacement: Radiography Examination 12/06/2018

Records, Field Welds

40575118-19 Valve 2AF-106 Replacement: Pipe Support Welds - Non- 12/06/2018

Destructive Examination Records

40635279-02 Perform Magnetic Particle Examination (MT) on Feedwater 03/25/2020

to Steam Generator Weld SG-A-6R1 in Accordance with

NDE-350

40635279-06 Perform Visual Examination (VT-3) of Piping Support 42-10- 03/24/2020

PHA in Accordance with NDE-754

40635279-15 Perform Ultrasonic Examination (UT) of Piping Weld RC-03- 03/24/2020

CH-2001-24 in Accordance with NDE-173

40635478-02 VT-3/General Visual-IWE of Containment Liner Plates, 03/24/2020

Elevation 46 Feet, 0 Degrees to 60 Degrees

71111.11Q Miscellaneous PBN LOC 20A CPE Practice 0

005S

Procedures OP 3A Unit 2 Power Operation to Hot Standby Unit 2 20

OP 3B Reactor Shutdown 47

OP 3C Unit 2 Hot Standby to Cold Shutdown Unit 2 17

ORT 4 Unit 2 Main Turbine Mechanical Overspeed Trip Device Unit 2 35

71111.12 Corrective Action AR 01904709 RM-DAM-06, RE-235 Will Not Process High Alarm Trip 09/17/2013

Documents Function

AR 02334093 RE-235 High Alarm Did Not Cause CREFS Shift to Mode 5 11/03/2019

AR 02344559 Update MR Functions Affected By Transition to NFPA 805 02/13/2020

AR 02344594 MR Functions Still Reference Appendix R 02/13/2020

Corrective Action AR 02342376 Proactively Replace Relays For Dam 6 Channel 9 01/24/2020

Documents AR 02350077 NRC Identified: MR Evaluation Documentation Discrepancy 03/26/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Resulting from

Inspection

Drawings 499B466 Sh. Schematic Diagram H & V Auxiliaries 20

1514

499B466 Sh. Elementary Wiring Diagram Control Room Charcoal Filter 9

540A Fan W-14A

499B466 Sh. Elementary Wiring Diagram Control Room Recirculation Fan 5

543A W-13B1

499B466 Sh. Elementary Wiring Diagram Control Room Recirculation Fan 10

543B W-13B2

E-94 Sh. 105 Radiation Monitoring System Ext. Connection Diagram DAM 4

Cabinet C256

E-98 Sh. 41 Radiation Monitoring System Ext. Connection Diagram 7

Monitors

ESK-12-42 RE-234/235 DAM 6 - 7/8/9 Control Room I2/Gas Monitor 9

ESK-4-01 RMS DAM 1-8 Cabinet Arrangement 2

EW-11F Radiation Monitoring System Internal Wiring Diagram DAM 3

Cabinet C256

M-144 Sh. 2 Heating and Ventilation Temperature Control P&ID 24

Temperature Control

Miscellaneous DBD-31 Design Basis Document: Control Room HVAC and 10

Habitability

Station Log Station Log 11/03/2019

Vendor Manual Eberline Vendor Manual: PNG/AP/Noble Gas & ING-Iodine / 7

Control #21 Noble Gas Air Monitor

71111.13 Corrective Action AR 02346040 High Risk Management Plan Not Complete For HX-12B 02/25/2020

Documents Work

Corrective Action AR 02344176 Notified Door 483 Handle Stuck In Unlatch Position 02/10/2020

Documents AR 02347384 Inadequate Danger Tape Usage During Lift 03/05/2020

Resulting from

Inspection

Miscellaneous Point Beach Station Unit 1 and 2 01/27-

Daily Status Report 31/2020

Station Log 01/27/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

PBN Unit 1 and 2 03/05/2020

Current Risk Summary Report

PBN Unit 1 and 2 03/03/2020

Current Risk Summary Report

PBN Unit 1 and 2 02/09-

Current Risk Summary Report 10/2020

PBN Unit 1 and 2 01/26-

Current Risk Summary Report 31/2020

Procedures MA-AA-212-1000 Rigging and Material Handling 20

NP 10.3.7 On-Line Safety Assessment 43

71111.15 Calculations 2001-0056 TDAFW Mini Recirc Valve (1/2AF-4002) Instrument Air 07/21/2011

Accumulator Sizing

2002-0002 Nitrogen Backup System for SSG Pump Discharge Valves 08/19/2015

(AF-4012/4019) and Minimum Recirculation Valves (AF-

4007/4014)

Corrective Action AR 02331777 Z-2009 A/B/C Mid-Year Performance Test not Performed 10/16/2019

Documents AR 02341001 1P-29 Accumulator Check Valve Excessive Leakage 01/13/2020

AR 02341282 D-501 Battery Cell Temperatures 01/15/2020

AR 02341632 D-501 Pilot Cell Temperature Low 01/18/2020

AR 02346664 G-04 G2A Vibration Data 03/01/2020

AR 02346671 Alerts Received During G-04 Endurance Run 03/01/2020

AR 02347606 W-184C Small EDG Room Fan Failed to Start in Auto 03/02/2020

AR 02349258 Incorrect Setpoint for U2 Manipulator 02/20/2020

Miscellaneous Station Log for 10/16/2019 Swing Shift through 10/17/2019 10/17/2019

Day Shift

Procedures 1-PT-AF-3 1P-29 Turbine-Driven AFW Pump Backup Air System 10

Pressure Decay Test (Refueling) Unit 1

71111.19 Calculations 2003-0046 Battery Charger Sizing and Current Limit Set Points 8

Corrective Action AR 02340591 PMT/RTS Deficiencies in Completed WO 40104553 AND EC 01/09/2020

Documents 273505

AR 02341346 MTN - QA Records Quality and Accuracy Issue 01/16/2020

AR 02341348 Maintenance Quality and Accuracy of QA Records 01/16/2020

AR 02341475 G-501 Did Not Remain Running 01/16/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

AR 02341475 G-501 Did Not Remain Running 01/16/2020

AR 02341883 Replace G-501 Low Lube Oil Pressure Switch 01/21/2020

AR 02343473 Adverse Trend in RTS/PMT Implementation 02/04/2020

Work Orders WO 40548526 ICP-13.7B-1 G-03 Diesel Instrumentation 01/31/2020

WO 40620568 G-03, 3-Year Electrical Maintenance Items 01/31/2020

WO 40626350 D-305 / D-09, Battery & Charger Maint and Surveillance 02/27/2020

Tests

WO 40626350 D-305 / D-09, Battery & Charger Maint and Surveillance 02/27/2020

WO 40656395 Load Test G-05, G-501 01/16/2020

WO 40658762 2P-10B Sample and Change Oil 03/05/2020

WO 40660229 D-09 Battery Charger Capacitor Replacement 02/26/2020

WO 40663880 IT 04 Train B 03/04/2020

WO 40689857 01 KC-09590 - G-05 Gas Turbine PLC Logic Changes (EC 01/16/2020

293759)

WO 40691038 G-03 3Y PM Mechanical Maintenance 01/31/2020

71111.20 Corrective Action AR 02348372 Unit 2 Entered AOP 25 Turbine Trip without Reactor Trip 03/14/2020

Documents AR 02348373 Unit 2 Turbine Overspeed Trip Prior to ORT 4 Data 03/14/2020

Collection

Miscellaneous U2R37 Outage Safety Review Supporting Documentation 0

PBNP Shutdown Safety Assessment and Fire Inspection 03/14-

Checklists 31/2020

Procedures 2RMP 9096-1 Reactor Vessel Head Removal and Installation Using Biach 21

Tensioning System

NP 8.4.7 Control of Safe Load Path and Rigging 14

SLP 2 Safe Load Path and Rigging Manual; Items Lifted By 33

Containment Polar Crane Unit 2

Work Orders WO 40635368 2ICP 4.4-6 - LTOP Transmitters Outage Cal 03/23/2020

WO 40711845 2ICP 2.16-2 - OP Mitigation Sys LTOP REQ'D < 392 DEG F 03/28/2020

71111.22 Corrective Action AR 02348709 2MS-2084 Did Not Actuate Correctly during ORT 3B 03/17/2020

Documents AR 02348781 B Train EDGs Frequency Response was not Bounded by 03/17/2020

Calc

AR 02348812 ORT 3B Recorders not Started Prior to Countdown 03/17/2020

Miscellaneous Unit 1 Leak Rates Spreadsheet 02/29/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures IT 03 Train B Low Head Safety Injection Pumps and Valves Train B Unit 1 9

OI 55 Primary Leak Rate Calculation 32

ORT 3B Safety Injection Actuation with Loss of Engineered 47

Safeguards AC (Train B) Unit 2

Work Orders WO 40661799 U1A UV, Test U1 Train A Undervoltage and Degraded 02/19/2020

71124.08 Corrective Action AR 02346786 Gaps in Category 2 Radwaste Shipment Documentation 03/02/2020

Documents Identified during Nuclear Assurance PBN 20-003, Radiation

Protection Audit

Miscellaneous N/A RP-AA-108-1002-F010 LSA/SCO Emergency Response 03/11/2020

Information Comparison to Emergency Response Guide 163

N/A Point Beach Shipment 19-037 Evaluation 03/17/2020

Procedures RP-AA-108-1002 Shipment of Radioactive Material 13

RP-AA-108-1003 Radioactive Materials Surveys for Shipment 8

RP-AA-108-1004 Packaging Materials for Shipment 4

Shipping Records19-037 UN 3321, Radioactive Material, Low Specific Activity (LSA- 05/30/2019

II), 7; Primary Resin

71151 Miscellaneous Performance Indicators; Units 1 and 2; Unplanned Power 01/01/2019 -

Changes Per 7000 Critical Hours 12/31/2019

Performance Indicators; Units 1 and 2; Unplanned Scrams 01/01/2019 -

with Complications 12/31/2019

Point Beach PI Reporting Data; Units 1 and 2; Unplanned 01/01/2019 -

Power Changes Per 7,000 Critical Hours 12/31/2019

Point Beach PI Reporting Data; Units 1 and 2; Unplanned 01/01/2019 -

Scrams Per 7,000 Critical Hours 12/31/2019

Point Beach PI Reporting Data; Units 1 and 2; Unplanned 01/01/2019 -

Scrams with Complications Per 7,000 Critical Hours 12/31/2019

Performance Indicators; Units 1 and 2; Unplanned Scrams 01/01/2019 -

Per 7000 Critical Hours 12/31/2019

71152 Corrective Action AR 02342555 W-13B1 Troubleshooting 01/27/2020

Documents AR 02349012 2CV-399 Diaphragm Leakage 03/19/2020

Corrective Action AR 02342244 NRC Identified Door-171 Not Closing Freely 01/23/2020

Documents AR 02346559 Cart With Temp Power Transformer Is Bowed 02/28/2020

Resulting from AR 02347045 Fire Barrier Penetration Degrading 03/03/2020

Inspection

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous Trend of Reactor Vessel Water Level 03/18-

19/2020

Station Logs - Night Shift 03/19/2020

Procedures NP 8.5.1 Equipment Identification and Labeling Procedure 17

Work Orders WO 40702379 W-13B1 Failed to Auto Start 01/23/2020

19

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