IR 05000266/2020001
| ML20134J119 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/13/2020 |
| From: | Richard Skokowski NRC/RGN-III |
| To: | Craven R Point Beach |
| References | |
| IR 2020001 | |
| Preceding documents: |
|
| Download: ML20134J119 (21) | |
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:
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
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)
- (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.
- Ultrasonic examination (UT) of reactor coolant system elbow-to-elbow pipe weld, ASME Category R-A, Component RC-03-CH-2001-24
- Magnetic particle examination (MT) of reactor coolant system, feedwater nozzle to steam generator weld, ASME Category C-B, Component SG-A-6R1
- 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
- Auxiliary feedwater system check valve 2AF-106 replacement, welds W-1, W-2, W-3b, W-4, W-5, W-8, W-9, and W-12 (Work Order 40575118-08)
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.
- Boric acid evaluations (BAEs): BAE 18-068-E, 2SC-955 Valve Packing Leak; BAE 18-087-E, 2SI-878C Valve Packing Leak; BAE 20-004-E, 2SI-897B Valve Packing Leak; BAE 20-056-E, 2SC-955 Valve Packing Gland Leakage; and BAE 20-064-E, 2CV-302B Cap Fitting Leak
- Boric acid corrective action records (ARs): AR 02284227, 2CV-133 Valve Packing Leak; AR 02337609, 2CV-133 Valve Packing Leak; AR 02348547, 2CV-V-1 Leakage Downstream of Swagelok Fitting; AR 02348554, 2LT-427 Lower Bellows Tube Leak; and AR 02348559, 2RC-581 Downstream Swagelok Fitting Leak
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (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)
- (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)===
- (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 Room Recirculation Fan Flow Switch 71152 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Crane Pad Placed In Drainage Path to Lake
04/02/2019
Miscellaneous
PBF-2124a
Point Beach Nuclear Plant Mean Converted Lake Level
Calculation
Procedures
Severe Weather Conditions
NP 8.4.17
PBNP Flooding Program
RMP 9422
Circulating Water Pumphouse and Turbine Hall Barrier
Placement
Work Orders
Z-1108 / Inspect Flood Barrier for Door 2
2/02/2019
PC 6 Part 9 Operations Flood Equipment Inventory
2/17/2020
Corrective Action
Documents
Resulting from
Inspection
PM to Inspect Safety Related (SR) Steam Traps not Coded
SR
2/13/2020
1(2)AF-4002 Recirculation Valve Air Hose SR
Documentation
2/18/2020
WR: Replace 1AF-04002-O Air Supply Hose
2/18/2020
WR: Replace 2AF-04002-O Air Supply Hose
2/18/2020
CR 02344613 Reopened for Rescreening
03/05/2020
Drawing Error On M-209 Sh. 12 Diesel Air Drawing
03/09/2020
Drawings
M-201 Sh. 1
P&ID Main & Reheat Steam System
M-209 Sh. 12
P&ID Emergency Diesel Air Starting System
M-217 Sh. 1
P&ID Auxiliary Feedwater System
104
M-217 Sh. 2
P&ID Auxiliary Feedwater System
M-219 Sh. 1
P&ID Fuel Oil System
M-219 Sh. 2
P&ID Fuel Oil System Diesel Generator Building
Miscellaneous
Modification 92-
2
IST Testability of 2AF-4002 (2P-29 Mini-Recirc)
11/23/1992
Procedures
CL 10D
Fuel Oil Systems
CL 11A G-01
G-01 Diesel Generator Checklist
CL 13E Part 1
Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 1
Work Orders
1P-29 - Inspect and Repair Steam Traps
04/14/2020
Corrective Action
HR-73 Hose Has Cracking in Outer Rubber Sheath
2/06/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
Hose Reels In CWPH Have Cracking In Fire Hose Rubber
Jacket
2/07/2020
Wheeled Ansul Fire Extinguisher Out of PFP-0-PAN
Location
2/07/2020
Fire Plans
Pre-Fire Plan Protected Area North
Miscellaneous
Door Card Reader Logs; Doors - 18, 27, 28, 321, 324, 600,
601, 602
2/05-
06/2020
FPTE 2016-043
PBNP Detailed Fire Modeling Report - Fire Compartment
773GRP - G-03 Switchgear Room - Diesel Generator
Building
FPTE 2016-044
PBNP Detailed Fire Modeling Report - Fire Compartment
777GRP - G-04 Diesel Room - Diesel Generator Building
FPTE 2106-045
PBNP Detailed Fire Modeling Report - Fire Compartment
777GRP - G-04 Switchgear Room - Diesel Generator
Building
PBF-2058A
(Completed)
Fire Round Performance Sheet - PAB - Four Hour and
Hourly
2/05-
06/2020
PBF-2058B
(Completed)
Fire Round Performance Sheet-Turbine Hall and
Mscellaneous Areas - Four Hour and Hourly
2/05-
06/2020
Procedures
OM 3.27
Control of Fire Protection and NFPA 805 Equipment
Corrective Action
Documents
284227
During 2-PT-RH-1, Found Packing Leak on 2CV-133
10/06/2018
284241
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
Settings
10/20/2018
287835
Active Packing Boric Acid Leak on 2SI-878C
10/25/2018
2337609
Dry, White, Light Boric Acid on 2SI-897A
2/06/2019
2341751
2SI-897B, 1Q20 Walkdowns Identified Wet Boric Acid on
Packing
01/20/2020
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
Procedure
Type
Designation
Description or Title
Revision or
Date
2348815
Inactive Boric Acid Leak from 2CV-302B
03/17/2020
Corrective Action
Documents
Resulting from
Inspection
2350634
NRC Unit 2 Inservice Inspection (ISI) Inspection - Liquid
Penetrant/Magnetic Particle Examination (PT/MT) in Lieu of
Radiographic Examination (RT) in Repair/Replacement Plan
2018-002
03/31/2020
2350663
Boric Acid Indications Not Identified / Recorded
03/31/2020
Engineering
Changes
Unit 2 Component Coolant Pump Replacement - Upgrades
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
Leakage
03/17/2020
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
Packing Gland Follower Leak
2/06/2019
BAS20-052
Boric Acid Screening: 2CV-V-1 Leakage Downstream of
Swagelok Fitting
03/15/2020
BAS20-053
Boric Acid Screening: 2LT-427 Lower Bellows Tube Leak
03/15/2020
BAS20-055
Boric Acid Screening: 2RC-581 Downstream Swagelok
Fitting Leak
03/15/2020
RR 2018-002
Repair / Replacement Activity: Valve 2AF-106 Replacement
and Support DB-3-2D2
RR 2018-013
Repair / Replacement Activity: Unit 2 Component Cooling
Water Pump 2P-011A Replacement
WPS FP-PE-B31-
Welding Procedure Specification: P1 Carbon Steel to P1
Carbon Steel
NDE Reports
Magnetic Particle Examination of Feedwater Nozzle to
Steam Generator Shell Weld, Component SG-A-6R1
03/25/2020
UT Calibration/Examination: Ultrasonic Examination of Pipe
Elbow-to-Elbow Weld, Component RC-03-CH-2001-24
03/24/2020
Visual Examination of Pipe Hanger, Support or Restraint
(VT-3), Rigid Support, Component 42-10-PHA
03/23/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Visual Examination of IWE Surfaces (VT-3), Containment
Liner Plates, Component 46 Foot Elevation, 0 Degrees to 60
Degrees
03/23/2020
Replace Pump 2P-011A Per EC 273506: Hydrostatic Test of
Pump Suction, Pump Discharge and New Cross Connect
10/03/2018
Replace Pump 2P-011A Per EC 273506: Weld
Nondestructive Examination Records
2/05/2018
Replace Pump 2P-011A Per EC 273506: Hydrostatic Test of
New Component Cooling Water Pump 2P-011A and Piping
10/17/2018
Valve 2AF-106 Replacement: Weld Non-Destructive
Examination Records
2/06/2018
Valve 2AF-106 Replacement: Radiography Examination
Records, Field Welds
2/06/2018
Valve 2AF-106 Replacement: Pipe Support Welds - Non-
Destructive Examination Records
2/06/2018
Procedures
NDE-173
PDI Generic Procedure for the Ultrasonic Examination of
Austenitic Piping Welds
NDE-350
Magnetic Particle Examination, Alternating Current (AC)
NDE-753
Visual Examination (VT-2), Leakage Detection of Nuclear
Power Plant Components
NDE-754
Visual Examination of Nuclear Power Plant Components
NDE-760
VT-1, VT-3 & General Visual Examination of IWE Boundary
Components
PDI-UT-2
Generic Procedure for the Ultrasonic Examination of
Austenitic Piping Welds
H
WP-1
Welding Procedure for Carbon Steels, Group P-1 to P-1,
GTAW-SMAW
Work Orders
40104738-08
Replace Pump 2P-011A Per EC 273506: Hydrostatic Test of
Pump Suction, Pump Discharge and New Cross Connect
10/03/2018
40104738-25
Replace Pump 2P-011A Per EC 273506: Weld
Nondestructive Examination Records
2/05/2018
40104738-28
Replace Pump 2P-011A Per EC 273506: Hydrostatic Test of
New Component Cooling Water Pump 2P-011A and Piping
10/17/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40104738-45
Replace Pump 2P-011A Per EC 273506: Weld
Documentation Task
2/05/2018
40104738-45,
Supplement S01
Replace Pump 2P-011A Per EC 273506: Weld
Documentation Task
2/11/2018
40575118-03
Valve 2AF-106 Replacement: Weld Non-Destructive
Examination Records
2/06/2018
40575118-08
Valve 2AF-106 Replacement: Weld Documents; Groove and
10/29/2018
40575118-11
Valve 2AF-106 Replacement: Radiography Examination
Records, Field Welds
2/06/2018
40575118-19
Valve 2AF-106 Replacement: Pipe Support Welds - Non-
Destructive Examination Records
2/06/2018
40635279-02
Perform Magnetic Particle Examination (MT) on Feedwater
to Steam Generator Weld SG-A-6R1 in Accordance with
NDE-350
03/25/2020
40635279-06
Perform Visual Examination (VT-3) of Piping Support 42-10-
PHA in Accordance with NDE-754
03/24/2020
40635279-15
Perform Ultrasonic Examination (UT) of Piping Weld RC-03-
CH-2001-24 in Accordance with NDE-173
03/24/2020
40635478-02
VT-3/General Visual-IWE of Containment Liner Plates,
Elevation 46 Feet, 0 Degrees to 60 Degrees
03/24/2020
71111.11Q Miscellaneous
PBN LOC 20A
005S
CPE Practice
Procedures
OP 3A Unit 2
Power Operation to Hot Standby Unit 2
Reactor Shutdown
OP 3C Unit 2
Hot Standby to Cold Shutdown Unit 2
ORT 4 Unit 2
Main Turbine Mechanical Overspeed Trip Device Unit 2
Corrective Action
Documents
RM-DAM-06, RE-235 Will Not Process High Alarm Trip
Function
09/17/2013
RE-235 High Alarm Did Not Cause CREFS Shift to Mode 5
11/03/2019
Update MR Functions Affected By Transition to NFPA 805
2/13/2020
MR Functions Still Reference Appendix R
2/13/2020
Corrective Action
Documents
Proactively Replace Relays For Dam 6 Channel 9
01/24/2020
NRC Identified: MR Evaluation Documentation Discrepancy
03/26/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Drawings
499B466 Sh.
1514
Schematic Diagram H & V Auxiliaries
499B466 Sh.
540A
Elementary Wiring Diagram Control Room Charcoal Filter
Fan W-14A
499B466 Sh.
543A
Elementary Wiring Diagram Control Room Recirculation Fan
W-13B1
499B466 Sh.
543B
Elementary Wiring Diagram Control Room Recirculation Fan
W-13B2
E-94 Sh. 105
Radiation Monitoring System Ext. Connection Diagram DAM
Cabinet C256
E-98 Sh. 41
Radiation Monitoring System Ext. Connection Diagram
Monitors
RE-234/235 DAM 6 - 7/8/9 Control Room I2/Gas Monitor
RMS DAM 1-8 Cabinet Arrangement
EW-11F
Radiation Monitoring System Internal Wiring Diagram DAM
Cabinet C256
M-144 Sh. 2
Heating and Ventilation Temperature Control P&ID
Temperature Control
Miscellaneous
Design Basis Document: Control Room HVAC and
Habitability
Station Log
Station Log
11/03/2019
Vendor Manual
Control #21
Eberline Vendor Manual: PNG/AP/Noble Gas & ING-Iodine /
Noble Gas Air Monitor
Corrective Action
Documents
High Risk Management Plan Not Complete For HX-12B
Work
2/25/2020
Corrective Action
Documents
Resulting from
Inspection
Notified Door 483 Handle Stuck In Unlatch Position
2/10/2020
Inadequate Danger Tape Usage During Lift
03/05/2020
Miscellaneous
Point Beach Station Unit 1 and 2
Daily Status Report
01/27-
31/2020
Station Log
01/27/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PBN Unit 1 and 2
Current Risk Summary Report
03/05/2020
PBN Unit 1 and 2
Current Risk Summary Report
03/03/2020
PBN Unit 1 and 2
Current Risk Summary Report
2/09-
10/2020
PBN Unit 1 and 2
Current Risk Summary Report
01/26-
31/2020
Procedures
Rigging and Material Handling
NP 10.3.7
On-Line Safety Assessment
Calculations
2001-0056
TDAFW Mini Recirc Valve (1/2AF-4002) Instrument Air
Accumulator Sizing
07/21/2011
2002-0002
Nitrogen Backup System for SSG Pump Discharge Valves
(AF-4012/4019) and Minimum Recirculation Valves (AF-
4007/4014)
08/19/2015
Corrective Action
Documents
Z-2009 A/B/C Mid-Year Performance Test not Performed
10/16/2019
1P-29 Accumulator Check Valve Excessive Leakage
01/13/2020
D-501 Battery Cell Temperatures
01/15/2020
D-501 Pilot Cell Temperature Low
01/18/2020
G-04 G2A Vibration Data
03/01/2020
Alerts Received During G-04 Endurance Run
03/01/2020
W-184C Small EDG Room Fan Failed to Start in Auto
03/02/2020
Incorrect Setpoint for U2 Manipulator
2/20/2020
Miscellaneous
Station Log for 10/16/2019 Swing Shift through 10/17/2019
Day Shift
10/17/2019
Procedures
1-PT-AF-3
1P-29 Turbine-Driven AFW Pump Backup Air System
Pressure Decay Test (Refueling) Unit 1
Calculations
2003-0046
Battery Charger Sizing and Current Limit Set Points
Corrective Action
Documents
PMT/RTS Deficiencies in Completed WO 40104553 AND EC 273505
01/09/2020
MTN - QA Records Quality and Accuracy Issue
01/16/2020
Maintenance Quality and Accuracy of QA Records
01/16/2020
G-501 Did Not Remain Running
01/16/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
G-501 Did Not Remain Running
01/16/2020
Replace G-501 Low Lube Oil Pressure Switch
01/21/2020
Adverse Trend in RTS/PMT Implementation
2/04/2020
Work Orders
ICP-13.7B-1 G-03 Diesel Instrumentation
01/31/2020
G-03, 3-Year Electrical Maintenance Items
01/31/2020
D-305 / D-09, Battery & Charger Maint and Surveillance
Tests
2/27/2020
D-305 / D-09, Battery & Charger Maint and Surveillance
2/27/2020
Load Test G-05, G-501
01/16/2020
2P-10B Sample and Change Oil
03/05/2020
D-09 Battery Charger Capacitor Replacement
2/26/2020
IT 04 Train B
03/04/2020
WO 40689857 01
KC-09590 - G-05 Gas Turbine PLC Logic Changes (EC 293759)
01/16/2020
G-03 3Y PM Mechanical Maintenance
01/31/2020
Corrective Action
Documents
Unit 2 Entered AOP 25 Turbine Trip without Reactor Trip
03/14/2020
Unit 2 Turbine Overspeed Trip Prior to ORT 4 Data
Collection
03/14/2020
Miscellaneous
U2R37 Outage Safety Review Supporting Documentation
PBNP Shutdown Safety Assessment and Fire Inspection
Checklists
03/14-
31/2020
Procedures
2RMP 9096-1
Reactor Vessel Head Removal and Installation Using Biach
Tensioning System
NP 8.4.7
Control of Safe Load Path and Rigging
SLP 2
Safe Load Path and Rigging Manual; Items Lifted By
Containment Polar Crane Unit 2
Work Orders
2ICP 4.4-6 - LTOP Transmitters Outage Cal
03/23/2020
2ICP 2.16-2 - OP Mitigation Sys LTOP REQ'D < 392 DEG F
03/28/2020
Corrective Action
Documents
2MS-2084 Did Not Actuate Correctly during ORT 3B
03/17/2020
B Train EDGs Frequency Response was not Bounded by
Calc
03/17/2020
ORT 3B Recorders not Started Prior to Countdown
03/17/2020
Miscellaneous
Unit 1 Leak Rates Spreadsheet
2/29/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
IT 03 Train B
Low Head Safety Injection Pumps and Valves Train B Unit 1
OI 55
Primary Leak Rate Calculation
ORT 3B
Safety Injection Actuation with Loss of Engineered
Safeguards AC (Train B) Unit 2
Work Orders
U1A UV, Test U1 Train A Undervoltage and Degraded
2/19/2020
Corrective Action
Documents
Gaps in Category 2 Radwaste Shipment Documentation
Identified during Nuclear Assurance PBN 20-003, Radiation
Protection Audit
03/02/2020
Miscellaneous
N/A
RP-AA-108-1002-F010 LSA/SCO Emergency Response
Information Comparison to Emergency Response Guide 163
03/11/2020
N/A
Point Beach Shipment 19-037 Evaluation
03/17/2020
Procedures
Shipment of Radioactive Material
Radioactive Materials Surveys for Shipment
Packaging Materials for Shipment
Shipping Records19-037
UN 3321, Radioactive Material, Low Specific Activity (LSA-
II), 7; Primary Resin
05/30/2019
71151
Miscellaneous
Performance Indicators; Units 1 and 2; Unplanned Power
Changes Per 7000 Critical Hours
01/01/2019 -
2/31/2019
Performance Indicators; Units 1 and 2; Unplanned Scrams
with Complications
01/01/2019 -
2/31/2019
Point Beach PI Reporting Data; Units 1 and 2; Unplanned
Power Changes Per 7,000 Critical Hours
01/01/2019 -
2/31/2019
Point Beach PI Reporting Data; Units 1 and 2; Unplanned
Scrams Per 7,000 Critical Hours
01/01/2019 -
2/31/2019
Point Beach PI Reporting Data; Units 1 and 2; Unplanned
Scrams with Complications Per 7,000 Critical Hours
01/01/2019 -
2/31/2019
Performance Indicators; Units 1 and 2; Unplanned Scrams
Per 7000 Critical Hours
01/01/2019 -
2/31/2019
Corrective Action
Documents
W-13B1 Troubleshooting
01/27/2020
03/19/2020
Corrective Action
Documents
Resulting from
Inspection
NRC Identified Door-171 Not Closing Freely
01/23/2020
Cart With Temp Power Transformer Is Bowed
2/28/2020
Fire Barrier Penetration Degrading
03/03/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Work Orders
W-13B1 Failed to Auto Start
01/23/2020