IR 05000266/2021004
| ML22021B296 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/28/2022 |
| From: | Adorno N Reactor Projects Region 3 Branch 4 |
| To: | Strope M Point Beach |
| References | |
| EA-18-030 IR 2021004 | |
| Download: ML22021B296 (18) | |
Text
SUBJECT:
POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2021004 AND 05000301/2021004 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Mr. Strope:
On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On January 11, 2022, the NRC inspectors discussed the results of this inspection with Mr. M. Holzmann, Operations Site Director, 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, Néstor J. Féliz Adorno, 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:
05000266/2021004 and 05000301/2021004
Enterprise Identifier:
I-2021-004-0109
Licensee:
NextEra Energy Point Beach, LLC
Facility:
Point Beach Nuclear Plant
Location:
Two Rivers, WI
Inspection Dates:
October 01, 2021 to December 31, 2021
Inspectors:
T. Hartman, Senior Resident Inspector
J. Cassidy, Senior Health Physicist
V. Petrella, Resident Inspector
R. Ruiz, Project Engineer
E. Sanchez Santiago, Senior Reactor Inspector
A. Shaikh, Senior Reactor Inspector
Approved By:
Néstor J. Féliz Adorno, 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
Type Issue Number Title Report Section Status Enforcement Discretion EA-18-030 Unanalyzed Condition for Tornado Generated Missiles 71111.15 Closed
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 82 percent rated thermal power in coastdown for the upcoming refueling outage. On October 9, 2021, the unit was shut down for refueling outage U2R38. On November 2, 2021, Unit 2 was restarted. On November 4, 2021, the unit was synchronized to the grid, and on November 8, 2021, it achieved full power. The unit remained at or near full power throughout the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection, unless otherwise noted. Currently approved IPs, with their attached revision histories, are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met, consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, 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:
Unit 1 and Unit 2 façade freeze protection on December 2, 2021
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 train A containment spray system on November 2, 2021
- (2) Unit 2 train B containment spray system on November 2, 2021
- (3) G-03 air start system, cooling system, and fuel oil system on November 9, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the spent fuel cooling system on October 20, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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 zone 608 on October 19, 2021
- (2) Fire zone 611 on October 19, 2021
- (3) Fire zone 615 on October 19, 2021
- (4) Fire zone 618 on October 19, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) G-03 and G-04 emergency diesel generator building
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) EC 295078, Revise Pressure Drop Per Stroke of Power Operated Relieve Valve (PORVS)
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) PC 29, Gas Turbine and Auxiliary Diesel Load Test, after replacement of the bearing and combination generator control module on October 1, 2021
- (2) IT 536, LRPM Program Test of Containment Sump B Suction Line Mode 5, 6, or Defueled Unit 2, after maintenance on 2SI-850B on October 21, 2021
- (3) IT 245, Safety Injection Accumulator Valves (Cold Shutdown) Unit 2, after maintenance on 2SI-841B on October 22, 2021 (4)2ICP 04.029-1, Analog Rod Position Indication Outage Calibration, after the instillation of the rod position indication into the Unit 2 control room on October 26, 2021
- (5) ORT 6, Containment Spray Sequence Test Unit 2, after the replacement of the 2-62/YIC-926B-T relay on October 27, 2021
- (6) IT 09A, Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly)
Unit 2, after maintenance on the overspeed trip mechanism on November 17, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage U2R38 activities from October 8-November 8, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) ORT 3A, Safety Injection Actuation with Loss of Engineered Safeguards AC (Train A)
Unit 2, on October 11, 2021
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) IT 535B, Leakage Reduction and Preventive Maintenance Program Seat Leakage Test of the train B RHR System (refueling) Unit 2, on October 6, 2021
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) ORT 60, train B Spray System CIV Leakage Test Unit 2, on October 14, 2021
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. 2341157, June 10, 2020
PCR No. 2351096, September 10, 2020
PCR No. 2369239, November 20, 2020 This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) A tabletop exercise with drill and exercise performance evaluation on December 14,
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 instructions to workers including radiation work permits used to access high radiation areas and labeling of radioactive material in containers.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Licensee surveys of potentially contaminated material leaving the radiologically controlled area (RCA)
- (2) Workers exiting the RCA at Unit 1 during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities. The inspectors also reviewed the following radiological work packages for high radiation areas or areas with airborne radioactivity:
- (1) Radiation Work Permit (RWP) 21-2016, Remove/Reinstall Reactor Vessel (RV) Head
Replacement
- (3) RWP 21-2057, Steam Generator Eddy Current Testing, Tube Sheet Cleaning High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Unit 2 reactor head storage area
- (2) Unit 2 reactor cavity 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.
71124.02 - Occupational ALARA Planning and Controls
Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (2 Samples)
The inspectors reviewed as low as reasonably achievable (ALARA) practices and radiological work controls for the following activities:
- (1) RWP 21-2016, Remove/Reinstall RV Head
- (2) RWP 21-2057, Steam Generator Eddy Current Testing, Tube Sheet Cleaning
Radiation Worker Performance (IP Section 03.04) (1 Sample)
The inspectors observed the following activities:
- (1) Unit 2 seal table activities
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) HEPA ventilation at Unit 2 seal table
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicator submittals listed below:
MS09: Residual Heat Removal Systems (IP Section 02.08)===
- (1) Unit 1 (October 01, 2020-September 30, 2021)
- (2) Unit 2 (October 01, 2020-September 30, 2021)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 01, 2020-September 30, 2021)
- (2) Unit 2 (October 01, 2020-September 30, 2021)
71152 - Problem Identification and Resolution (PI&R)
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends from June 01-November 30, 2021, that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Through wall leak on Unit 2 component cooling water piping
INSPECTION RESULTS
Enforcement Discretion Unanalyzed Condition for Tornado Generated Missiles EA-18-030 71111.15
Description:
On June 10, 2015, the NRC issued Regulatory Issue Summary (RIS) 2015-06, Tornado Missile Protection, (ML15020A419) and Enforcement Guidance Memorandum (EGM) 15-002, Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance (ML15111A269). The EGM was revised on February 7, 2017 (ML16355A286). The RIS focused on the requirements regarding tornado-generated missile protection and required compliance with the facility-specific licensing basis. The EGM provided guidance to allow the NRC staff to exercise enforcement discretion when an operating power plant licensee did not comply with the current licensing basis for tornado-generated missile protection.
On March 1, 2018, the licensee documented several identified non-conformances related to tornado missile protection in their corrective action program (AR02252240). In addition, the licensee discussed their intent to request to use the enforcement discretion afforded by EGM 15-002 and discussed the actions required to comply with the provisions in the EGM.
The inspectors documented the exercise of enforcement discretion in NRC Integrated Inspection Report 05000266/2018001; 05000301/2018001 (ML18128A229). Enforcement Action (EA) number EA-18-030 was assigned to administratively track the use of enforcement discretion until final corrective actions were implemented.
As discussed in EGM 15-002, the granting of enforcement discretion was scheduled to expire three years after the EGMs June 2015 issuance. On April 26, 2018, the licensee requested the NRC to extend the enforcement discretion provided by EGM 15-002 to June 2020 based upon the implementation of compensatory measures consistent with the NRC-approved regulatory guidance (ML18116A306). The NRC approved the enforcement discretion extension request by letter dated May 21, 2018 (ML18135A305).
Corrective Actions: On February 6, 2020 (ML20037A007), the licensee submitted a license amendment request to revise their licensing bases regarding protection from tornado-generated missiles. Specifically, the licensee proposed revising Updated Final Safety Analysis Report (UFSAR) Section 1.3.1, Overall Plant Requirements General Design Criteria 1-5, and Section 1.3.12, References, to describe the historical plant design for safe shutdown equipment located external to seismic class I structures and related tornado missile protection information.
On February 23, 2021, the NRC issued License Amendment No. 268 to Renewed Facility Operating License DPR-24, Amendment No. 270 to Renewed Facility Operating License DPR-27 and its associated safety evaluation report (ML20363A176). Based on its evaluation, the NRC staff approved the licensees amendment request to revise the UFSAR for Point Beach Nuclear Plant, Units 1 and 2, as proposed. The NRCs approval was based upon the licensee demonstrating the nonconforming conditions were not likely to adversely affect the ability of SSCs important to safety to withstand the potential effects of extreme winds and missiles associated with such winds on plant SSCs important to safety. Further, the NRC staff determined the licensee had demonstrated SSCs important to safety will be capable of performing their safety functions during and following a tornado. As a result, the nonconforming conditions discussed in the license amendment request to not affect the NRC staffs finding of reasonable assurance that SSCs important to safety will be capable of performing their safety functions during and following a tornado.
Corrective Action References: AR2252240; Tornado Missile Protection
Enforcement:
Based on the licensees corrective actions described above, no additional violations were identified, the enforcement discretion afforded by EGM 15-002 is no longer required, and EA-18-030 is considered closed.
Observation: Semi Annual Trend Review 71152 The inspectors reviewed action requests entered into the corrective action program for the following:
complete, accurate, and timely documentation of the issue identified in the corrective action program
evaluation and timely disposition of operability and reportability issues
consideration of extent of condition and cause, generic implications, common cause, and previous occurrences
classification and prioritization of the problems resolution, commensurate with the safety significance
identification of corrective actions that are appropriately focused to correct the problem
completion of corrective actions in a timely manner, commensurate with the safety significance of the issue
identification of negative trends associated with human or equipment performance that can potentially impact nuclear safety
operating experience is adequately evaluated for applicability, and applicable lessons learned are communicated to appropriate organizations, and implemented The inspectors completed the review and did not note any significant trends that weren't already identified and addressed by the licensee.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 25, 2021, the inspectors presented the Inservice inspection results to Mr. M. Strope, Site Vice President, and other members of the licensee staff.
On November 10, 2021, the inspectors presented the Closure of Enforcement Discretion EA-18-030 inspection results to Mr. E. Schultz, Licensing Manager, and other members of the licensee staff.
On December 8, 2021, the inspectors presented the radiation protection inspection results to Mr. D. Peterson, Chemistry/Radiation Protection Manager, and other members of the licensee staff.
On December 8, 2021, the inspectors presented the emergency plan and emergency action level changes review inspection results to M. E. Schultz, Licensing Manager, and other members of the licensee staff.
On January 11, 2022, the inspectors presented the integrated inspection results to Mr. M. Holzmann, Operations Site Director, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Seasonal Readiness WO and WR Report (Spreadsheet)
10/20/2021
Miscellaneous
PBNP Seasonal Readiness - Winter 2021-2022 Memo
09/27/2021
M-227 Sh.1 Shows DG-306A Valve in Wrong Position
11/16/2021
Corrective Action
Documents
Resulting from
Inspection
PCR 02408198
CL 5C - Spent Fuel Pool Cooling and Refueling Water Circ
10/20/2021
110E018 Sh. 4
P&ID Auxiliary Cooling System
110E035 Sh. 3
P&ID Safety Injection System
M-209 Sh. 14
P&ID Starting & Service Air System Diesel Generator Building
M-219 Sh. 3
P&ID Fuel Oil System Diesel Generator Building
Drawings
M-227 Sh. 1
P&ID Glycol Cooling System Diesel Generator Building
Miscellaneous
CL 5C
Spent Fuel Pool Cooling and Refueling Water Circulating
Pump Normal Operation Valve Lineup
Procedures
CL 7A Unit 2
Safety Injection System Checklist Unit 2 Modes 1, 2, and 3
PFP-2-CONT-FAC - Pre-Fire Plan Unit 2 Containment Building
11/02/2021
PBC-218 - FP Turb/Aux Bldgs & Cont 66 ft EL
11/02/2021
PBC-218 - FP Turb/Aux Bldgs & Cont 44 ft EL
11/15/2021
PBC-218 - Fire Barrier Locations Turb/Aux/Cont 44 ft
11/15/2021
PBC-218 - Fire Barrier Locations Turb/Aux/Cont 66 ft
11/15/2021
PBC-218 - FP Turb/Aux Bldgs & Cont 66 ft EL
11/15/2021
Corrective Action
Documents
Resulting from
Inspection
NRC FP Observation
2/16/2021
PBC-218 Sheet
Fire Barrier Locations for Turbine Building, Aux Building &
Containment Elev. 44'-0"
Drawings
PBC-218 Sheet 4
Fire Protection for Turbine Building, Aux Building &
Containment Elev. 44'-0"
Fire Plans
PFP-2-CONT-
Pre-Fire Plan Unit 2 Containment Building/Facade
Calculations
2014-04473
Internal Flooding Assessment of Emergency Diesel Generator
Building
Corrective Action
Documents
Resulting from
Drain in Mechanical Equipment Room Outside G-04
Switchgear
10/21/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Drawings
E-121202
Diesel Generator Building Concrete Plan at EL 28'-0"
Work Orders
2HX-015B1-B8 GL 89-13 Clean Heat Exchanger as Req
08/26/2021
ACTIVE (WET) Boric Acid Leak From 2SI-848H During
2-PT-SI-1
03/14/2020
Boric Acid Found on Seal Package and Pump Coupling
03/20/2020
2FI-115 Active BA Leak - Repeat From 2Q21 BALCM
Walkdown
08/16/2021
Corrective Action
Documents
2SI-878E Inactive Boric Acid Leak in Contact With Bolting
09/08/2021
Corrective Action
Documents
Resulting from
Inspection
NRC ISI Inspection Concern
10/12/2021
Engineering
Changes
21-0095
CFR 50.59 Screening for Test Procedure 594-002
10/12/2021
21-01-414
Ultrasonic Examination on RC-34-MRCL-AI-05
10/22/2021
Liquid Penetrant Examination on RHR-B-LEG-1 Thru 4 IWA
10/19/2021
Ultrasonic Examination on RC-10-SI-2001-18
10/17/2021
NDE Reports
Visual Examination on RCP-A-Support
10/18/2021
594-AELR-002
Acoustic Emission Inspection of Head Lifting Rig and Internals
Lifting Rig
FP-PE-WLD-02
General Welding Specification
MRS-GEN-1116
Pegasys Operating Procedure for ECT
Procedures
NDE-754
Visual Examination (VT-3) of Nuclear Power Plant
Components
Work Orders20-010
Repair/Replacement Plan on 2LT-934, Piping 2"-SI-902R
Miscellaneous
PBN LOC 21F
2E
SM Read/STA Eval
OP 3A Unit 2
Power Operation to Hot Standby Unit 2
Reactor Shutdown
Procedures
OP 3C Unit 2
Hot Standby to Cold Shutdown Unit 2
EC 13923; Evaluate the Need to Provide Training on this EC
05/06/2009
Corrective Action
Documents
Aux Feed Check Valve Workplan Needs Updating
03/11/2010
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Valve Removed During U2R30 is Missing and Thought
Discarded
05/22/2013
Revise Insp Frequencies for Unit AF System Check Valves TS
03/14/2016
2AF-100 Check Valve Leaking By
11/20/2017
2AF-100 Failed Seat Leakage Test (U2 Prep)
09/27/2018
Rebuilt Valve 2AF-100 Failed Pressure Test (Shop Work)
10/02/2018
07/31/2021
1OS-2-MOV Failed to go Shut
07/31/2021
U1 Crossover Steam Dump Relay 63X/SVA Found Bad
08/02/2021
PBM-241
P&ID Turbine Crossover Steam Dump
Drawings
PD99532
Nozzle Check Valve 3 in. Class 600 DRV-Z
Miscellaneous
Point Beach Nuclear Plant - Units 1 and 2 Inservice Testing
Program Table - AF
280814-01
PB2-AF-00100, NDE IAW LR TR 519 Visual Exams
10/26/2006
00358375-01
Remove Valve from PPG System/Perform Inspection for
10/28/2009
244928-01
2AF-00100/Rebuild Spare Check Valve (Shop Work)
09/26/2013
Work Orders
40572958-07
2AF-100 Check Valve Leaking By
10/02/2018
PBNP Shutdown Safety Assessment and Fire Inspection
Checklist for U2R38 on October 13, 2021 at 1300
10/13/2021
Miscellaneous
PBNP Shutdown Safety Assessment and Fire Inspection
Checklist for Unit 2 R38 on October 15, 2021 at 0945
10/15/2021
Calculations
2005-0054
Control Building Gothic Temperature Calculation
HX-66A AFW RM Cooler Has Leaking Coils on Both Ends
05/19/2021
Through Wall Leak Upstream of 1AF-281A
08/24/2021
2HS-2501R-15 Remove, Test and Rebuild Snubber
10/13/2021
Missing Saddle Identified on Feedwater Piping Support
10/19/2021
TS-4A, Discovered Overspeed Trip Oil Pressure Out of Range
11/03/2021
Corrective Action
Documents
Unit 2 RPI For Rod H-12 Spiking Low
11/16/2021
NRC Question Requiring Additional Investigation
08/30/2021
Corrective Action
Documents
Resulting from
Inspection
ECA-0.0 (P) - Reviews in Progress
09/20/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M-2213 Sheet 1
Drawings
M-2213 Sheet 2
P&ID Lube Oil System Oil, Turb, Lubrication & Control
Engineering
Changes
Aux FW Small Bore Weld Buildup
05/21/2021
EPRI TR-113890
Vibration Fatigue Testing of Socket Welds
2/16/1999
Miscellaneous
NEX-35080
Exelon Power Labs Failure Analysis of a Socket Weld from
Aux FW System
09/17/2021
Point Beach Nuclear Plant Abnormal Operating Procedure
Temporary Ventilation for Vital Areas
ECA-0.0 Unit 1
Point Beach Nuclear Plant Emergency Contingency Action
Loss of All AC Power
Procedures
EOP-0 Unit 1
Point Beach Nuclear Plant Emergency Operating Procedure
Reactor Trip or Safety Injection
Calculations
P-89-012
Required Tank Pressure for LTOP N2 Supply
8809-17 Sheet 2
Elementary Diagram Rod Position System
Drawings
HT-WPBNRP-001
Elementary Diagram NARPI System Control Bank A
0000295078
Revise Pressure Drop Per Stroke of PORVS
000
Engineering
Changes
SCR 2020-0068
Replace Rod Position Indication (RPI)
40720934-11
U2 RPI -- Terminate Cable 2Y4285A in 2C120A
10/20/2021
Work Orders
U2 RPI -- Install New Rod Position Recorders in 2C04
10/23/2021
IT 536 - LRPM Program Test of Containment Sump B Suction
Lin
10/21/2021
IT-536 Missing Sign-Off in Record Copy of WO 4072685801
10/26/2021
Corrective Action
Documents
Resulting from
Inspection
NRC Identified Changes to IT 536
10/27/2021
Procedures
IT 245
Safety Injection Accumulator Valves (Cold Shutdown) Unit 2
2SI-00841B-O / OPS PMT / RTS
10/19/2021
2SI-850A-O / OPS PMT-RTS (IT 45 Train A and/or IT 536)
10/22/2021
U2 RPI - RPIR Installation PMT
10/27/2021
ORT 6, CS Sequence
10/27/2021
11/17/2021
2ICP 4.29-1 - RPI Indicator Calibration and System Checks
10/26/2021
IT-536, U2 Cont Sump B Suction Line Leak Test (RFSD)
10/22/2021
Work Orders
2-62/YIC-926B-T, Perform Relay Replacement
10/18/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-62/YIC-926B-T, OPS PMT / RTS Task
10/27/2021
2SI-00850B: Operation PMT / RTS
10/22/2021
G-05/Replace Speed Input Module
08/13/2021
F-190, OPS PMT/RTS
10/01/2021
Corrective Action
Documents
Resulting from
Inspection
NRC Walkdown Items Found in Containment
10/31/2021
Miscellaneous
Unit 2 Primary System Cool Down Plot
10/09/2021
CL 20
Post Outage Containment Closeout Inspection Unit 2
Procedures
CL 4C Unit 2
Low Temperature Overpressure Protection Unit 2
ORT 3A
Safety Injection Actuation with Loss of Engineered Safeguards
AC (Train A) Unit 2
Procedures
ORT 60
Train B Spray System CIV Leakage Test Unit 2
Work Orders
IT-535B, LRPM Test of Train B HHSI and RHR Systems
10/08/2021
PCR No.
2351096
CFR 50.54(q) Screening Form
09/10/2020
PCR No. 2341157
CFR 50.54(q) Screening Form
06/10/2020
Miscellaneous
PCR No. 2369239
CFR 50.54(q) Screening Form
11/20/2020
Miscellaneous
HP-100-01251
Site Alpha Characterization Update
01/28/2021
Procedures
Remote Monitoring
21-2016
Remove/Reinstall RV Head
21-2018
Seal Table Activities
21-2053
Unit 2 Narrow Range RTD Replacement
Radiation Work
Permits (RWPs)
21-2057
S/G Eddy Current Testing, Tube Sheet Cleaning
21-2016
Remove/Reinstall RV Head
21-2018
Seal Table Activities
ALARA Plans
21-2057
S/G Eddy Current Testing, Tube Sheet Cleaning
Corrective Action
Documents
Respirator Training Issue
10/12/2021
MSPI Margin Reports; Units 1 and 2
10/01/2020-
09/30/2021
71151
Miscellaneous
MSPI Derivation Reports; Residual Heat Removal, Cooling
10/01/2020-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Water; Units 1 and 2
09/30/2021
Corrective Action
Documents
Potential Through Wall Leak on CCW Identified
03/02/2021