IR 05000266/2021002
| ML21208A420 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/29/2021 |
| From: | Nestor Feliz-Adorno Reactor Projects Region 3 Branch 4 |
| To: | Strope M Point Beach |
| References | |
| IR 2021001, IR 2021002 | |
| Download: ML21208A420 (31) | |
Text
SUBJECT:
POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2021002, 05000301/2021002, AND 07200005/2021001
Dear Mr. Strope:
On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On July 12, 2021, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
Two findings of very low safety significance (Green) are documented in this report. Two of these findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs), consistent with Section 2.3.2 of the Enforcement Policy.
A licensee-identified violation, which was determined to be of very low safety significance, is documented in this report. We are treating this violation as a non-cited violation (NCV)
consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations, or the significance or severity of the violations documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Point Beach Nuclear Plant.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, Region III, and the NRC Resident Inspector at Point Beach Nuclear Plant.
July 29, 2021 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; 05000301; and 07200005 License Nos. DPR-24, DPR-27
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000266, 05000301, 07200005
License Numbers:
Report Numbers:
05000266/2021002,05000301/2021002, 07200005/2021001
Enterprise Identifier:
I-2021-002-0098 and I-2021-001-0159
Licensee:
Nextera Energy Point Beach, LLC
Facility:
Point Beach Nuclear Plant
Location:
Two Rivers, WI
Inspection Dates:
March 01, 2021 to June 30, 2021
Inspectors:
J. Cassidy, Senior Health Physicist
J. Dalzell, Reactor Inspector
R. Edwards, Senior Health Physicist
T. Hartman, Senior Resident Inspector
V. Petrella, Resident Inspector
R. Ruiz, Project Engineer
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. A licensee-identified non-cited violation is documented in report section: 7115
List of Findings and Violations
SCBA Regulator Testing and Maintenance Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000266,05000301/2021002-01 Open/Closed
[H.3] - Change Management 71124.03 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of 10 CFR 20.1703(c)(4)(vii) for the licensee failure to maintain a respiratory protection program that includes written procedures regarding storage, issuance, maintenance, repair, testing, and quality assurance of respiratory protection equipment. Although the licensees procedure indicated that the testing schedule was consistent with the vendors manual, the procedural required testing periodicity was twice that specified by the vendor. Consequently, the licensees procedure failed to ensure the maintenance and testing of components used in situations with highest radiological risk and that could also be used in atmospheres that are Immediately Dangerous to Life and Health.
Breathing Air Quality Testing and Analysis Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000266,05000301/2021002-02 Open/Closed
[H.13] -
Consistent Process 71124.03 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of 10 CFR 20.1703(c)(4)(v) when the licensee failed to implement written procedures regarding breathing air quality as part of the respiratory protection program. Specifically, licensee procedures required Air Quality Testing be performed quarterly (per OSHA 1910.134 and NRC Regulatory Guide 8.15); however, the licensee performed the testing at an annual frequency. Consequently, the reduced frequency challenged the licensees ability to provide adequate protection to the workers wearing self-contained breathing apparatuses.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On April 20, 2021, reactor power was reduced to approximately 55 percent for turbine stop valve testing and condenser waterbox cleaning. On April 21, 2021, the unit was returned to 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 and remained at or near full power throughout the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved Ips, with their attached revision histories, are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met, consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors 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 and regional 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, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all, or a 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 some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
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 extreme high temperatures on June 3, 2021.
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated flood protection barriers, mitigation plans, procedures, and equipment for consistency with the licensees design requirements and risk analysis assumptions for coping with external flooding on June 24, 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 1 train B containment spray system on May 27, 2021
- (2) Unit 1 motor-driven auxiliary feedwater pump on May 27, 2021
- (3) Unit 1 train A safety injection system on June 29, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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 304N, 304S, and 305 on April 6, 2021 (2)fire zones 162, 163, 164, 165, and 166 on April 23, 2021 (3)fire zone 238 on April 23, 2021 (4)fire zone 237 on April 23, 2021 (5)fire zone 240 on April 23, 2021
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on May 29, 2021.
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 main control room during safety injection system testing on April 8, 2021, and during the Unit 1 down power from 100 percent power to 55 percent power on April 20, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator simulator exam on May 24, 2021.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)leading edge flow meter inputs to reactor thermal output indication: failures on February 7, February 28, March 9, March 19, March 21, and March 28, 2021
- (2) G-05 gas turbine exceeds reliability performance criteria
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)elevated risk for the Unit 1 train B safeguards logic testing on April 15, 2021 (2)elevated risk for the Unit 1 train B reactor protection logic testing on April 15, 2021 (3)elevated risk for the Unit 2 blue inverter (2DY-02) maintenance and inspection on May 3, 2021 (4)last minute rescheduling of maintenance activities due to conservative grid operations on June 28-29, 2021
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)pipe hanger found moved on Unit 1 component cooling water system (2)elevated temperature on Unit 2 turbine-driven auxiliary feedwater pump inboard packing gland
- (3) Prompt Operability Determination, 2386499-01, CCW Piping Analysis Not Updated for Removed Pipe Penetration
- (4) ASME Code Case N-513-4 evaluation of pin hole leak in the 6" CCW piping adjacent to valve 2CC-753.
(5)increased frequency of adding nitrogen to the power-operated relief valve accumulator
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)0-SOP-IA-006, K-2B Instrument Air Compressor Recovery from Maintenance, after maintenance on K-002B Instrument Air Compressor on April 9, 2021
- (2) PC 29, Gas Turbine and Auxiliary Diesel Load Test, after maintenance on G-05 Emergency Diesel Generator on April 5, 2021 (3)1RMP 9056-2, Calibration and Testing of Safety Related Protective Relays A-06 after replacement of 1-62-1/A-06 and 1-62-2/A-06 relays on April 29, 2021 (4)2RMP 9036-6, 2DY-02 Blue Channel Instrument Bus Static Inverter Maintenance Procedure after maintenance on the 2DY-02 Blue Channel Instrument Bus Static Inverter on May 4, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) IT 45 Train B, Safety Injection Valves Train B Unit 2, on April 8, 2021
- (2) TS 81, Emergency Diesel Generator G-01 Monthly, on April 18, 2021
- (3) IT 08A, Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly)
Unit 1, on April 19, 2021
- (4) TS 83, Emergency Diesel Generator G-03 Monthly, on June 2, 2021
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) IT 07D/E/F, P-32D/E/F Service Water Pumps Comprehensive Test, on May 12, 2021
FLEX Testing (IP Section 03.02) (1 Sample)
(1)0-SOP-FLEX-003, Flex Portable Diesel Low Pressure Pump Operation Z-2003A & Z-2003B, on June 2, 2021
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) A full-scale emergency preparedness site drill conducted on April 28,
RADIATION SAFETY
71124.02 - Occupational ALARA Planning and Controls
Radiological Work Planning (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensees radiological work planning for the following work activities.
- (1) Remove/Reinstall Reactor Vessel (RV) Head under Radiation Work Permit (RWP)20-1016
- (2) Reactor Coolant System (RCS) Leak Repair under Radiation Work Permit (RWP)20-1062
- (3) Scaffolding Containment Outage Activities under Radiation Work Permit (RWP)20-1025
- (4) Scaffolding Containment Outage Activities under Radiation Work Permit (RWP)20-2025 Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (4 Samples)
The inspectors evaluated dose estimates and exposure tracking for the following work activities.
- (1) Remove/Reinstall RV Head under Radiation Work Permit (RWP) 20-1016
- (3) Scaffolding Containment Outage Activities under Radiation Work Permit (RWP)20-1025
- (4) Scaffolding Containment Outage Activities under Radiation Work Permit (RWP)20-2025
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (1 Sample)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Control Room Ventilation System - Common Unit
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose.
Internal Dosimetry (IP Section 03.03) (1 Sample)
The inspectors evaluated the internal dosimetry program implementation.
- (1) The inspectors reviewed the Whole Body Counts associated with a contamination event on October 9, 2020.
Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situation:
- (1) Licensees implementation of requirements to manage radiation protection of shallow dose equivalent for AR 02330629.
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (8 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) GM Tube-Based Ratemeter and Area Monitor - MGP AMP-200 7717-004 ready for use
- (2) GM Tube-Based Ratemeter and Area Monitor - MGP AMP-100 479291 ready for use
- (3) Ion Chamber Survey Meter - Ludlum 9-3 330694 ready for use
- (4) Ion Chamber Survey Meter - Eberline RO20 472966 330694 ready for use
- (5) Extendable Survey Meter - Mirion Telepole 330482 ready for issue
- (6) Personnel Contamination Monitor - ARGOS 0712-047 at auxiliary building exit
- (7) Tool and Equipment Monitor - Mirion Cronos-4 1511-198 at auxiliary building exit
- (8) Portal Monitor - Mirion GEM-5 0712-118 at auxiliary building exit
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 03.04)===
- (1) Unit 1 (May 1, 2020 through April 30, 2021)
- (2) Unit 2 (May 1, 2020 through April 30, 2021)
BI02: RCS Leak Rate Sample (IP Section 03.11) (2 Samples)
- (1) Unit 1 (May 1, 2020 through April 30, 2021)
- (2) Unit 2 (May 1, 2020 through April 30, 2021)
71152 - Problem Identification and Resolution
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) National Fire Protection Association Standard (NFPA) 805 fire protection program implementation deficiencies
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60854 - Preoperational Testing of an ISFSI The inspectors reviewed documents, interviewed plant personnel, and performed in-field observations to assess the licensees preoperational testing of an ISFSI. The inspectors performed an independent assessment that the licensee had adequately demonstrated its readiness to safely perform ISFSI loading and unloading operations. Specifically, the inspectors evaluated the following:
- (1) The licensee performed preoperational dry run activities. The inspectors evaluated following activities:
The inspectors observed welding dry run activities on April 12-14, 2021. Specifically, the inspectors observed closure welding of a canister and non-destructive examination of the welds.
The inspectors observed processing dry run activities on April 26-28, 2021. Specifically, the inspectors observed canister reflood evolution, bulk water removal and blowdown, vacuum drying operations, and helium backfill.
The inspectors observed MPC insertion and HI-STORM transport dry run activities on May 10-12, 2021. Specifically, the inspectors observed insertion and removal of a MPC into a HI-STORM FW, transport of HI-STORM FW to the ISFSI Pad and placement of the cask on the ISFSI Pad.
The inspectors observed fuel loading dry run activities on May 24-17, 2021. Specifically, the inspector observed movement of the HI-TRAC between the decontamination pit and the spent fuel pool, fuel moves, and MPC lid placement and removal.
- (2) Fuel Selection
The inspectors reviewed cask fuel selection packages to verify that the licensee was loading fuel in accordance with TS 2.1, Fuel to be Stored in the HI-STORM FW MPC Storage System.
60855 - Operation of an ISFSI The inspectors evaluated the licensees independent spent fuel storage installation cask loadings on June 1-5, 2021. Specifically, the inspectors observed the following activities:
movement of the HI-TRAC from the decontamination pit to the spent fuel pool
spent fuel loading and verification activities
placement of the damaged fuel canister lids and MPC lid
movement of the HI-TRAC from the spent fuel pool to the decontamination pit
canister welding and non-destructive weld evaluations
drying evolutions
transfer of the MPC from the HI-TRAC to the HI-STORM FW The inspectors performed walkdowns of the ISFSI pad, including independent radiation surveys, and walkdowns of the ISFSI haul path and vertical cask transporter (VCT).
The inspectors evaluated the following:
selected corrective action program action requests
selected 72.48 screenings and evaluations 60856 - Review of 10 CFR 72.212(b) Evaluations The inspectors evaluated the licensees compliance with the requirements of 10 CFR 72.212 and 10 CFR 72.48, as well the licensees revised engineering documentation and calculations associated with the HI-STORM FW CoC 072-1032, Revision 6. Prior to use of a dry cask storage system, the licensee is required to perform written evaluations in accordance with 10 CFR 72.212(b)(5)(i) to establish that the terms, conditions, and specifications of a CoC or an amended CoC have been met. Specifically, the inspectors performed an in-office review of the following from March 1-May 30, 2021:
10 CFR 72.212 Evaluation Report for the HI-STORM FW CoC 072-1032, Revision 6 and associated calculations
EC 294818, HI-STORM FW Cask System Licensing and Operation and supporting engineering changes and referenced calculations
HI-TRAC Lifting Yoke Assembly
Vertical Cask Transporter Seismic Stability Analysis
Auxiliary Building and Crane Structural Analysis
Stack-up and MPC Transfer Seismic Analysis
ISFSI Pad Structural Capacity Qualification
INSPECTION RESULTS
SCBA Regulator Testing and Maintenance Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000266,05000301/2021002-01 Open/Closed
[H.3] - Change Management 71124.03 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of 10 CFR 20.1703(c)(4)(vii) for the licensee failure to maintain a respiratory protection program that includes written procedures regarding storage, issuance, maintenance, repair, testing, and quality assurance of respiratory protection equipment. Although the licensees procedure indicated that the testing schedule was consistent with the vendors manual, the procedural required testing periodicity was twice that specified by the vendor. Consequently, the licensees procedure failed to ensure the maintenance and testing of components used in situations with highest radiological risk and that could also be used in atmospheres that are Immediately Dangerous to Life and Health.
Description:
The licensee replaced the Self-Contained Breathing Apparatus (SCBA) units at the site with the SCOTT Air-Pak X3 Model 4.5 in October 2019 to limit intake of radioactive material. The licensee reviewed/revised procedure NP 4.2.32 Respiratory Protection Program to support the equipment change.
The inspectors identified that the procedure contained a testing frequency that was inconsistent with the frequency provided by the vendor. The current revision of procedure NP 4.2.32 Respiratory Protection Program (Revision 21) Attachment A SCBA Equipment Information indicates that Functional Flow Testing will be performed every two years (per SCOTT Air-Pak X3 Model 4.5 Operating and Maintenance Instructions) <emphasis added>.
However, the inspectors reviewed the Operating & Maintenance for the SCOTT Air-Pak X3 Pro & Air-Pak X3 Snap-Change Model 2.2/4.5/5.5 Rev F 2/18 and found "Periodic Testing - SCOTT recommends that this respirator be inspected and tested by a SCOTT Authorized Service Center using SCOTT Authorized Test Equipment at least once a year
<emphasis added>. Heavy use and/or severe service conditions may require more frequent inspection and testing. This recommendation is in addition to all other cleaning and maintenance procedures."
The licensee did not have an evaluation or technical basis on this issue and could not demonstrate that extending the frequency of required maintenance and testing did not degrade performance of components used in situations with highest radiological risk and could also be used in atmospheres that are Immediately Dangerous to Life and Health.
Consequently, all of the units missed the testing maintenance that should have been performed in October 2020 had the units been tested at the frequency of at least once a year.
Corrective Actions: The licensee rescheduled the vendor maintenance of the SCBA regulators to June 15 to 17, 2021. Additionally, Radiation Protection and the Fire Protection Coordinator were evaluating the issue to determine actions needed.
Corrective Action References: AR02391216
Performance Assessment:
Performance Deficiency: The licensee failed to maintain written procedures regarding maintenance, repair, testing, of respiratory protection equipment as required by 10 CFR 20.1703(c)(4)(vii). Although the licensees procedure (NP 4.2.32 Respiratory Protection Program) indicated that the testing schedule was consistent with the vendors manual, the procedural required testing periodicity was twice that specified by the vendor.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Plant Facilities/Equipment and Instrumentation attribute of the Occupational Radiation Safety cornerstone and adversely affected the cornerstone objective to ensure the adequate protection of the worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation.
Specifically, licensee procedures were not revised to incorporate the vendor testing instructions (required by the procedure) when new SCBAs were implemented by the licensee.
Additionally, the licensee did not perform an evaluation of the extended periodicity to demonstrate it would not result in an actual personnel safety concern.
Significance: The inspectors assessed the significance of the finding using Appendix C, Occupational Radiation Safety SDP. The inspectors assessed the significance of the finding using Appendix C, Occupational Radiation Safety SDP. The inspectors determined that the finding was of very low safety significance (i.e., Green) because:
- (1) it did not involve as-low-as reasonably achievable planning or work controls,
- (2) there was no overexposure,
- (3) there was no substantial potential for an overexposure, and
- (4) the ability to assess dose was not compromised.
Cross-Cutting Aspect: H.3 - Change Management: Leaders use a systematic process for evaluating and implementing change so that nuclear safety remains the overriding priority.
Specifically, the process used to implement the new SCBAs did not update the maintenance and testing procedure with the vendors instructions for the new SCBAs.
Enforcement:
Violation: 10 CFR 20.1703(c)(4)(vii) states The licensee shall implement and maintain a respiratory protection program that includes written procedures regarding storage, issuance, maintenance, repair, testing, and quality assurance of respiratory protection equipment.
Procedure NP 4.2.32 Respiratory Protection Program, Revision 21, Attachment A SCBA Equipment Information states functional flow testing will be performed every two years (per SCOTT Air-Pak X3 Model 4.5 Operating and Maintenance Instructions).
SCOTT Air-Pak X3 Model 4.5 Operating and Maintenance Instructions (Rev F 2/18)states Periodic Testing - SCOTT recommends that this respirator be inspected and tested (including functional flow testing) by a SCOTT Authorized Service Center using SCOTT Authorized Test Equipment at least once a year.
Contrary to the above, as of October 2019, the licensee failed to maintain a respiratory protection program that includes written procedures regarding storage, issuance, maintenance, repair, testing, and quality assurance of respiratory protection equipment.
Specifically, procedure NP 4.2.32, Attachment A specifies functional flow testing for its SCBAs every two years and per the vendors instructions; however, the vendors instructions specify the testing at least once per year.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Breathing Air Quality Testing and Analysis Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000266,05000301/2021002-02 Open/Closed
[H.13] -
Consistent Process 71124.03 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of 10 CFR 20.1703(c)(4)(v) when the licensee failed to implement written procedures regarding breathing air quality as part of the respiratory protection program. Specifically, licensee procedures required Air Quality Testing be performed quarterly (per OSHA 1910.134 and NRC Regulatory Guide 8.15); however, the licensee performed the testing at an annual frequency. Consequently, the reduced frequency challenged the licensees ability to provide adequate protection to the workers wearing self-contained breathing apparatuses.
Description:
Procedure NP 4.2.32 Respiratory Protection Program Revision 21 Attachment A SCBA Equipment Information requires Air Quality Testing will be performed quarterly (per OSHA 1910.134 and NRC Regulatory Guide 8.15). Additionally, the licensee developed a Technical Basis Document, HP-100-013020 SCBA Air Quality Requirements dated February 2, 2020.
This assessment was performed in support of the decision to contract the filling of SCBA cylinders to an offsite vendor and abandon the equipment used to perform onsite filling of SCBA cylinders. The assessment concluded that Point Beach Nuclear Plant shall request the offsite vendor to provide air quality test records a minimum of four times per year.
The licensee started using a contracted vendor to refill SCBA cylinders in May 2019. The records of breathing air quality analysis provided by licensee indicated that the testing and analysis was only performed once per year. Additionally, this testing was performed in February or March when the relative humidity is lower than other times of the year.
Consequently, the results for the required dew point measurement of the compressed air may not be representative for the entire year.
Corrective Actions: Radiation Protection and the Fire Protection Coordinator were evaluating the issue to determine actions needed.
Corrective Action References: AR02391216
Performance Assessment:
Performance Deficiency: The licensee failed to implement written procedures for the frequency of testing breathing air quality as required by 10 CFR 20.1703(c)(4)(v). Although A of Licensee procedure NP 4.2.32 Respiratory Protection Program required Air Quality Testing be performed quarterly (per OSHA 1910.134 and NRC Regulatory Guide 8.15), the inspectors identified that the licensee was performing the testing on an annual frequency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Plant Facilities/Equipment and Instrumentation attribute of the Occupational Radiation Safety cornerstone and adversely affected the cornerstone objective to ensure the adequate protection of the worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation.
Specifically, the licensee determined that breathing air quality must be tested and analyzed on a quarterly basis to maintain certification but did not implement this requirement when a vendor was selected to refill the SCBA bottles. The reduced frequency challenged the licensees ability to provide adequate protection to the workers wearing self-contained breathing apparatuses.
Significance: The inspectors assessed the significance of the finding using Appendix C, Occupational Radiation Safety SDP. The inspectors determined that the finding was of very low safety significance (i.e., Green) because:
- (1) it did not involve as-low-as reasonably achievable planning or work controls,
- (2) there was no overexposure,
- (3) there was no substantial potential for an overexposure, and
- (4) the ability to assess dose was not compromised.
Cross-Cutting Aspect: H.13 - Consistent Process: Individuals use a consistent, systematic approach to make decisions. Risk insights are incorporated as appropriate. Specifically, the process used to have an off-site vendor to fill SCBA bottles did not systematically implement the results from the licensee developed Technical Basis Document, HP-100-013020 SCBA Air Quality Requirements
Enforcement:
Violation: 10 CFR 20.1703(c)(4)(v) states The licensee shall implement and maintain a respiratory protection program that includes written procedures regarding breathing air quality.
Licensee procedure NP 4.2.32 Respiratory Protection Program Revision 21, in part, implements the respiratory protection program. Attachment A SCBA Equipment Information of this procedure required Air Quality Testing be performed quarterly (per OSHA 1910.134 and NRC Regulatory Guide 8.15).
Contrary to the above, since May 2019, the licensee failed to implement a respiratory protection program that includes written procedures regarding breathing air quality.
Specifically, the licensee failed to implement procedure NP 4.2.32 requirements for quarterly testing of air quality for air used in SCBAs. The licensee had only performed the testing in February 20, 2019, March 2020, and February 2021.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Licensee-Identified Non-Cited Violation 71152 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Point Beach License Condition 4.F requires, in part, that the licensee implement and maintain in effect all provisions of the approved Fire Protection Program that complies with 10 CFR 50.48(a) and 10 CFR 50.48(c), NFPA [National Fire Protection Association]
Standard NFPA 805, as approved in the Safety Evaluation Report (SER) dated September 8, 2016. Section 2.4.3.3 of NFPA 805 states, in part, that the PSA [Probabilistic Safety Assessment] approach, methods, and data shall be appropriate for the nature and scope of the change being evaluated, be based on the as-built and as-operated and maintained plant, and reflect the operating experience at the plant.
Contrary to the above, from February 14, 2017, to May 23, 2020, the licensee failed to implement and maintain in effect all provisions of the approved Fire Protection Program that complies with 10 CFR 50.48(a) and 10 CFR 50.48(c) because the PSA approach, methods, and data were not based on the as-built and as-operated and maintained plant. Specifically, the supporting calculations for the fire PSA were not based on the as-built service water system because they did not account for the potential of spurious operation of service water valves. As a result, the licensee did not account for the potential spurious valve operation impact on service water flow during NFPA 805 fire events.
Significance/Severity: Green. The inspectors screened this finding in accordance with Inspection Manual Chapter (IMC) 0609, Significance Determination Process, Attachment 4, Initial Characterization of Findings. The finding was associated Fire Protection and affected the ability to reach and maintain safe shutdown conditions in the event of a fire and was therefore reviewed using IMC 0609, Appendix F, Attachment 1, Fire Protection Significance Determination Process Worksheet. The finding was screened as a finding of very low safety significance (Green) in accordance with Step 1.4.7, Post-fire Safe Shutdown, Question 1.4.7-C which asked, Does the fire finding adversely affect the ability to reach and maintain hot shutdown/hot standby or safe and stable condition using the credited safe shutdown success path? The licensee revised calculations and determined that post-fire safe shutdown was not affected because the service water system would remain operational with two service water pumps following spurious operation of four valves.
Corrective Action References: AR 02331854 Observation: Review of Selected Fire Protection Issues 71152 Since the plant's transition to 10 CFR 50.48(c) [National Fire Protection Association (NFPA)
Standard 805] in February 2017, the licensee has identified a number of issues associated with the fire protection program. The inspectors selected three of these issues and performed an in-depth review of the associated Action Requests (ARs) and corrective actions to ensure that the licensee implemented corrective actions commensurate with the significance of the identified issues.
AR 02286581, "NFPA 805 Documentation Incorrect" - The licensee identified incorrect statements in PRA [Probabilistic Risk Assessment] 8.1, Fire PRA Boundary Definition and Partitioning Notebook regarding fire compartment 122GRP. The licensee determined that multiple openings and non-fire rated doors existed in a barrier for which PRA 8.1 documented that Barrier wall and floor/ceiling segments qualify as fire rated construction and No unprotected combustible pathways to adjacent compartments existed. As part of the corrective actions and extent of condition the licensee performed walkdowns of other non-three hour rated barriers between fire compartments and identified numerous other discrepancies between PRA 8.1 and conditions in the field.
AR 02331840, "NFPA 805 Action Not Contained in Procedure" - The Nuclear Safety Capability Assessment (NSCA) credited closing blowdown isolation valves 1MS-5958 and 1MS-5959 by isolating instrument air using valves 1IA-3047 and 1IA-3048 in Fire Area A08 remotely from the control room. However, Emergency Operating Procedure EOP-2 directed operators to verify valves 1MS-5958 and 1MS-5959 were shut and, if not, to locally close them. As part of the corrective action to address this issue, the licensee revised NSCA Section 7.2.3.3 to credit EOP-2.
AR 02331854, "NFPA 805 Spurious Operation of Service Water Valves Not Considered" - The licensee identified that the NSCA and Fire PRA rely on the service water system to support several systems to ensure safe and stable shutdown. The licensee initially concluded that three (out of six) service water pumps would be required to support system operation. As a result of spurious operation of service water (SW) valves SW-2890, SW-2891, SW-2869, and SW-2870, there were several fire conditions where only two service water pumps would be available. The spurious operation of these valves was not considered in calculations 2012-006 and 2018-0016. The licensee reevaluated the operation of the service water system with only two SW pumps following the spurious operation of the identified valves and concluded that the SW system would deliver the required amount of water flow. The licensee subsequently revised calculations 2012-006 and 2018-0016 to demonstrate this.
The inspectors spoke with plant personnel regarding these three ARs in order to understand the issues, the appropriateness of the corrective actions, and the ultimate resolution. The inspectors reviewed the changes that were made to the relevant PRA documents, NSCA, and calculations, and performed walkdowns where necessary.
During the course of the review the inspectors concluded that the likely cause of these issues not being discovered and resolved during the transition to NFPA 805 was that the individuals and work groups involved in the transition to NFPA 805 did not effectively communicate and coordinate their activities. Based on the samples reviewed, once those concerns were identified, the licensee performed a detailed review of the NFPA 805 program and took corrective actions to disposition the issues. The inspectors reviewed a sample of these corrective actions, as documented above, and concluded that they were reasonable and appropriate. The inspectors determined that two of the issues evaluated by the licensee (AR 02286581 and AR 02331840) had associated minor violations that were identified by the licensee and were dispositioned in accordance with the NRC's policies. A License-Identified Violation related to AR 02331854 is documented in this report.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 12, 2021, the inspectors presented the integrated inspection results to Mr. M.
Strope, Site Vice President, and other members of the licensee staff.
On May 28, 2021, the inspectors presented the Independent Spent Fuel Storage Installation Pre-Operational Inspection results to Mr. M. Strope, Site Vice President, and other members of the licensee staff.
On June 10, 2021, the inspectors presented the Independent Spent Fuel Storage Installation Loading Inspection results to Mr. B. Woyak, Safety Assurance and Learning Site Director, and other members of the licensee staff.
On June 24, 2021, the inspectors presented the Radiation Protection inspection results to Mr. M. Holzmann, Operations Director, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ALARA Plans
ALARA Package
No. R001
Dry Cask Storage ALARA Plan
VCT Load Testing Documentation Package
05/15/2014
HI-STORM FW Lift Bracket Documentation Package
03/10/2021
HI-TRAC VW Lift Yoke Documentation Package
03/30/2021
MPC FW Lift Cleat Assembly Documentation Package
03/01/2021
HI-TRAC VW Lift Yoke Load Test
09/30/2020
HI-TRAC VW Lift Yoke/Lift Lugs Load Test
2/04/2021
Certificate of Compliance No. 1032, Amendment No. 3
06/13/2011
Miscellaneous
HI-2200093
Loading Plan and Fuel Compatibility Report for Point Beach
and 4
GQP 9.6
Visual Examination of Welds
HPP-2951-300
MPC Sealing, Drying, and Backfilling
HPP-2951-500
8.5: HI-PORT Frequent Use Inspection Checklist
HPP-2951-600
MPC Unloading
MSLT-MPC-
Holtec
Helium Mass Spectrometer Leak Test Procedure
03/14/2018
NDE-401
Visible Dye Penetrant Examination Expanded Temperature
Applications
NP 8.4.7
Control of Safe Load Path and Rigging Manual
PBF-9240
Large Overhead Crane Daily Inspections
Independent Spent Fuel Storage Installation / Dry Fuel
Storage Project Management
RDW 19.11
ISFSI Daily Surveillance
Procedures
RDW 19.12
ISFSI Thermal Surveillance
Self-Assessments RPT# PBN
19-005
Independent Spent Fuel Storage Installation
06/08/2019
60854
Work Orders
WO 40698177 04
PAB Crane Mechanical Inspection and Maintenance
01/08/2021
ISFSI LIC DOC Site Disposition Gap
05/08/2019
ISFSI Aging Management Program Ownership
05/09/2019
AMP-Required ISFSI Related Inspection are Not On-Track
05/09/2019
60855
Corrective Action
Documents
NA Finding: PBN ISFSI Station Ownership
05/22/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Repairs for 2017 VSC Annual Inspection
07/29/2019
Repairs for 2018 Annual VSC Inspection
07/29/2019
Repairs for 2019 Annual VSC Inspection
08/12/2019
ISFSI MPC Minimum Wall Thickness Verification
09/23/2020
Dry Run Work Delay Observation
05/27/2021
PAB Crane Locked Up While Performing HPP-2951-200
06/01/2021
FM On Top of DD45 Discovered During Cask Map
06/02/2021
HPP-29510-300 MPC Sealing, Drying and Backfilling
06/04/2021
Air Sample Greater Than Expected from the Vacuum Drying
06/10/2021
CFR 50.59
Screen
20-0067
EC 291715: Z-17 SFP Crane Upgrades
Engineering
Changes
CFR 72.48
Screen
2019-0091
VSC-INSP-05 Lead Cask Inspection
08/15/2019
CFR 72.212 Evaluation Report for HI-SOTRM FW
Inspection of Rigging Components
03/31/2021
CFR 72.48
Screen NUH-
AMP-01
NUHOMS Aging Management Program
06/27/2019
CFR 72.48
Screen NUH-
INSP-06
High Burnup Fuel Aging Management Plan
06/27/2019
Miscellaneous
NPM 2017-0106
Demonstration of NDE-401, "Visible Dye Penetrant
Examination Expanded Temperature Applications"
09/15/2017
MSLT-MPC-
Holtec
Helium Leak Test Report for Multipurpose Canister
06/05/2021
NDE Reports
Report No.
917882-200
Liquid Penetrant Examination Results - Lid to Shell Weld
06/03/2021
Radiological Surveys Performed at ISFSI Used to
Demonstrate Compliance with 10 CFR 72.104
05/03/2021
Periodic Radiological Surveys Performed at the ISFSI
05/03/2021
Radiation
Surveys
Survey PBPROD-
06/05/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M-20210606-6
Survey PBPROD-
M-20210607-5
MPC 200 HI-STORM Loaded for Transport
06/07/2021
Survey PBPROD-
M-20210609-9
MPC 200 ISFSI Pad Boundary Survey
06/09/2021
HI-2188505
Effect of Cask Spacing on Thermal Performance of HI-
STORM FW System at Point Beach
and 5
HI-2188506
Point Beach Time Histories
HI-2188517
Point Beach SFP Top Floor Level Time Histories
HI-2188657
Point Beach Haul Path Underground Utility Evaluation
HI-2188752
Cask Handling Weights at Point Beach Nuclear Plant
HI-2188838
Seismic Analysis of Cask Loading Area
HI-2188848
Stability Analysis of HI-TRAC VW on Cask Decontamination
Area During Seismic Event
and 5
HI-2200094
Thermal Evaluation of HI-TRAC VW in Decontamination
Area
2, 3, and 5
HI-2200202
Point Beach Site Boundary Dose Rates Calculations for
HI-STORM FW System
HI-2200204
HI-STORM FW and HI-TRAC VW CoC Dose Rate
Calculations for Point Beach
HI-2200225
Seismic Analysis of Spent Fuel Rack Storage Assembly for
Point Beach
HI-2200436
Seismic Stability Analysis of HI-STORM/HI-TRAC Stack
During MPC Transfer Operations
HI-2200438
Evaluation of Transporter Fire Effects on HI-STORM FW and
HI-TRAC VW at Point Beach
HI-2200572
Structural Analysis of the Truck Bay Floor Slab During
Stack-Up Loading
HI-2200631
Evaluation of Plant Hazards at Point Beach Nuclear Plant
HI-2200744
Seismic Analysis of the Hi-STORM on Hauling Transporter
and 3
HI-2200849
VCT Seismic Stability at Point Beach Nuclear Plant (PBNP)
and 5
Calculations
HI-2201043
Structural Evaluation of HI-STORM FW XL Mating Device
60856
Corrective Action
Documents
21 ISFSI Inspection Question 1, Calculation Revision
Misalignment
03/04/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
21 ISFSI Inspection Question 2, Clarify HI-2188505
03/04/2021
CFR 50.59
Screen 2020-
0085
HI-STORM FW Cask System Licensing and Operations
Document Change Request Form
Cask Decontamination Platform Modification
Holtec ISFSI Expansion - Temperature Monitoring System
HI-STORM FW Cask System Licensing and Operation
ECO-5018-118
Limits of Storage Overpack Steel
Holtec 10 CFR 2.48 Evaluation
No.: 1472
ECO-5018-118
Holtec 10 CFR 2.48 Evaluation
No.: 1518
Transition of Spent Fuel Storage for Point Beach Nuclear
Plant
Engineering
Changes
Holtec 10 CFR 2.48 Evaluation
No.: 1529
Foreign Materials
RRTI 2951-001
PBNP Non-Mechanistic Tipover
RRTI 2951-002
PBNP ISFSI Pad Structural Assessment
RRTI 2951-005
RRTI 2951-006
Blast Pressure Wave
RRTI 2951-007
Spent Fuel Water Displacement When the HI-TRAC is
Placed Inside the Pool
RRTI 2951-008
Ancillary Equipment Combustibles
Engineering
Evaluations
RRTI 2951-010
Transformers Along Haul Path
Miscellaneous
10CFR50.54(q)(2) - Maintaining the Emergency Plan
Evaluation Form
Radiation
Surveys
ATI Report No.:
8006-100-1422-A
1st Quarter, 2021, TLDs
05/19/2021
Miscellaneous
PBF-2124a
Mean Converted Lake Level Calculation
Severe Weather Conditions
Procedures
NP 2.1.5
Electrical Communications, Switchyard Access and Work
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Planning
NP 8.4.17
PBNP Flooding Program
PBNP-MISO-
NUC-001
Nuclear Plant Operating Agreement for Point Beach Nuclear
Plant
110E017 Sheet 1
P&ID Safety Injection System, Unit 1
110E017 Sheet 2
P&ID Safety Injection System, Unit 1
110E017 Sheet 3
P&ID Safety Injection System, Unit 1
M 217 Sheet 3
P&ID Auxiliary Feedwater System, Unit 1
Drawings
M-217 Sheet 1
P&ID Auxiliary Feedwater System, Units 1 & 2
2
CL 13E Part 2
Auxiliary Feedwater Valve Lineup Motor Driven
Miscellaneous
CL 7A
Safety Injection System Checklist Mode 1,2,3 Unit 1
PFP-0-PAB 8 - Pre-Fire Plan Primary Auxiliary (In Drawing)
04/23/2021
Corrective Action
Documents
Resulting from
Inspection
NRC RI Questions
04/23/2021
Pre-Fire Plan Control Building Elev 8 ft, 26 ft, 44 ft and 66 ft
PFP-0-PAB 26
Pre-Fire Plan Unit 1 & Unit 2 Auxiliary Building 26 FT
PFP-0-PAB 46
Pre-Fire Plan Unit 1 & Unit 2 Auxiliary Building 46 ft
Fire Plans
PFP-0-PAB-8
Primary Auxiliary Building Elevations 8' and Below
Hourly Fire Round Performance Sheet-PAB
04/23/2021
Fire Round Performance Sheet - Turbine Hall and
Miscellaneous Areas
04/06/2021
Miscellaneous
Fire Round Performance Sheet - PAB
04/23/2021
Perform Maintenance on the SCBA
03/27/2021
Perform Maintenance on the SCBA
04/24/2021
Work Orders
Perform Maintenance on the SCBA
05/22/2021
Miscellaneous
PBN LOC 21C
001E
NRC Annual Simulator Exam
IT 45 Train B
Safety Injection Valves Train B Unit 2
Procedures
OP 2D Unit 1
Power Operation Maneuvering - Unit 1
Unit 2 - Received PPCS Priority Alarm for RTO
2/07/2021
Unit 2 Invalid LEFM RTO Inputs Causing TLCO Entry
2/28/2021
Corrective Action
Documents
Spike Down on LEFM
03/09/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Unexpected PPCS Alarms Due To F-3110, LEFM FW Flow
Spike
03/19/2021
Unit 1 RTO Shifted to Venturi
03/21/2021
PBNP LEFM FIP Action - Revise CTC Software Version
03/26/2021
Trend: LEFM Flow Low Spike Causing False Power
Indication
04/06/2021
Miscellaneous
EVAL-PB-GT-
2402
G-05 Gas Turbine Exceeded Reliability (FF) Criteria
05/28/2021
Corrective Action
Documents
Resulting from
Inspection
2392117
NRC Identified Incorrect PDC Noted in Look Ahead
05/03/2021
High Risk Plan for 2DY-02, 125V DC / 120V AC Inverter
Maintain and Inspect
05/04/2021
PBNP Shutdown Safety Assessment and Fire Inspection
Checklist
06/28/2021
PBNP Shutdown Safety Assessment and Fire Inspection
Checklist
06/29/2021
T-0 Execution Schedule by Early Start
06/28/2021
T-0 Execution Schedule by Early Start
06/29/2021
T-0 Execution Schedule by Early Start
06/30/2021
Risk Plan for 1ICP 2.5B -- Safeguards Logic Test - Train B
04/15/2021
Miscellaneous
Risk Plan for 1ICP 2.3B -- Reactor Protection Logic
Test - Train B
04/15/2021
Procedures
NP 10.3.7
On-Line Safety Assessment
1ICP 2.3B - RP Logic Test - Train B
04/15/2021
Work Orders
1ICP 2.5B - SG Logic Test - Train B
04/15/2021
Potential Thru Wall Leak on CCW Identified
03/02/2021
PPG AC 0152N-11 Unit 2 NDE Periodic Monitoring
03/05/2021
CCW Piping Analysis not Updated for Removed Pipe
03/10/2021
NRC Identified Pipe Hanger Moved from Original Location
04/06/2021
Corrective Action
Documents
2P-29 (TDAFP) Elevated Temp on Pump Inbd Packing
Gland
04/08/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Increased Frequency of Nitrogen Addition to PORV
06/06/2021
Corrective Action
Documents
Resulting from
Inspection
Code Case Required Inspection of U2 CCW Pipe Not
Performed
06/10/2021
295970
Nonplanar Flaw Evaluation in CCW Piping Adjacent to
Engineering
Changes
296054
Piping Analysis of CCW Return Piping for Removed
Penetration to Support POD 02386499-01
Operability
Evaluations
AR 2386499-01
CCW Piping Analysis Not Updated for Removed Pipe
03/24/2021
Work Orders
2PPG AC 0152N-11/Unit 2 NDE Periodic Monitoring
03/24/2021
1-62-2/A-06 Relay Replacement
04/29/2021
1A-06 Calibrate 1A-06 Tech Spec Relays
05/03/2021
K-002B-18 Month Compressor Maintenance
04/09/2021
K-002B-18 Month Compressor Maintenance
04/09/2021
2DY-02 - Maintain and Inspect Inverter
05/04/2021
1-62-1/A-06 Relay Replacement
04/29/2021
Work Orders
G-05/Abnormal Indications on G-05 HMI
04/05/2021
Corrective Action
Documents
Resulting from
Inspection
Criteria Specified in 0-SOP-FLEX-003 Not Direct Correlation
06/24/2021
IT 07D
P-32D Service Water Pump (Quarterly)
IT 07E
P-32E Service Water Pump (Quarterly)
IT 07F
P-32F Service Water Pump (Quarterly)
Procedures
TS 83
Emergency Diesel Generator G-03 Monthly
IT-07D, P-32D Service Water Pump Comprehensive Test
05/22/2019
IT 45 Train B, Unit 2 Safety Injection VLVS
04/08/2021
IT-08A, 1P-29 AFP Cold Start Test/VLVS
04/19/2021
TS-81, G-01 Emergency Diesel Generator Operability
04/18/2021
Work Orders
IT-07D, P-32D Service Water Pump Comprehensive Test
05/12/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
IT-07E, P-32E Service Water Pump Comprehensive Test
05/12/2021
IT-07F, P-32F Service Water Pump Comprehensive Test
05/12/2021
0-SOP-FLEX-003 / Z-2003A and B Annual Full Flow Tests
06/02/2021
Drill Scenario
04/28/2021
Nuclear Accident Reporting Form
04/28/2021
NPM # 2019-
0035
1Q19 EP Drill Report
03/21/2019
NPM # 2019-
0102
4Q19 EP Drill Report
11/04/2019
Miscellaneous
NPM # 2021-
0048
2Q21 EP Drill Report
05/25/2021
20-1016
Remove/Reinstall RV Head
Various
20-1025
Scaffolding Containment Outage Activities
Various
ALARA Plans
20-1062
RCS Leak Repair
Various
N/A
Point Beach U1R39 Radiation Protection Post Outage
Report
Miscellaneous
N/A
Point Beach U2R37 Radiation Protection Post Outage
Report
Procedures
NISP-RP-010
Radiological Job Coverage
20-1016
Remove/Reinstall RV Head
20-1025
Scaffolding Containment Outage Activities
Radiation Work
Permits (RWPs)
20-1062
RCS Leak Repair
Corrective Action
Documents
AR 2294511-66
Evaluate New Fit Testing Method for Possible
Implementation
N/A
Corrective Action
Documents
Resulting from
Inspection
SCBA Discrepancies Identified
04/26/2021
Procedures
PC 75 Part 1
Monthly and Turnaround Maintenance for The Scott 4.5
Self-Contained Breathing Apparatus
AR 2329355-04
L1A/L2A/RWT: AR02381669, Level 1 NRC IP 71124.03 and
71124.04 Inspection Assessment
01/22/2021
Self-Assessments
AR 2337124-03
Annual RP Program Review
03/10/2020
Work Orders
WO 40523755 01
18-Month Filter Testing
10/08/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
WO 40625100 01
18-Month Filter Testing
04/15/2020
Corrective Action
Documents
Individual Handled a Source Without Dosimetry
11/19/2019
HP-100-091219
R0
Plant Source Term and Impact on RP Program
09/12/2019
ID No.
JDG01UAW
Whole Body Count Evaluation
10/12/2020
Miscellaneous
NVLAP Lab
Code: 100555-0
Certificate of Accreditation to ISO.IEC 17025:2017
06/30/2021
HPIP 1.12
Bioassay Requirements
HPIP 1.57.1
Evaluation of Whole Body Count Results
HPIP 1.65
Personnel Neutron Exposure Monitoring
HPIP 1.66
Dosimetry Placement for Extremity and Multiple Whole Body
Locations and Extremity Dose Determination
NP 4.2.15
Fetal Protection Policy Implementation
NP 4.2.27
Personnel Exposure Monitoring Device Minimum
Requirements and General Use
Procedures
Personnel Monitoring Program
Self-Assessments AR 2329342-04
L1A/L2A/RWT: 02369603, Level 1 NRC Baseline RP
Inspection Assessment
09/25/2020
Environmental Samples Below Minimum Volume
09/11/2019
Isotope Half-life Study to Determine Unidentified Peak
2/21/2020
2nd Quarter Facade Well Sample Required LLD Not Met
09/14/2020
Corrective Action
Documents
August GW Samples Could Not be Obtained
09/16/2020
2016 AMR Liquid Dose Update
06/22/2021
GWPP Enhancement for Warehouse 7 SSC
06/23/2021
Corrective Action
Documents
Resulting from
Inspection
REMP Air Station Housing Units Review
06/24/2021
Updated Site Conceptual Model
01/01/2017
ACIT 0337720-01
Evaluate REMP Samples for Potential Reduction
Not Provided
2019 Annual Monitoring Report
04/27/2020
20 Annual Monitoring Report
04/29/2021
Miscellaneous
Offsite Dose Calculation Manual
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Report Number
2019-001
Chesapeake
Nuclear Services
Point Beach Nuclear Power Plant Meteorological and
Atmospheric Dispersion Report
07/19/2019
HPIP 3.58.1
Radiological Environmental Sampling
NP 3.4.7
Groundwater Protection Program (GWPP)
Procedures
NP 3.4.9
Groundwater Protection Plan Technical Basis
Self-Assessments NEI 07-07 Peer
Assessment
Report
NEI Ground Water Protection Initiative
2/15/2017
Supplement
Meteorological Tower Inspection Reports
06/30/2016
WO 40689482 02
ICP 6.3-2 -- Meteorological System Calibration
08/25/2020
Work Orders
WO 40727734 01
ICP 7.30 - Inspection of Meteorological Sites
06/10/2021
Performance Indicators; Units 1 and 2; Reactor Coolant
System Leakage
04/01/2020 -
03/31/2021
Miscellaneous
Performance Indicators; Units 1 and 2; Safety System
Functional Failures
04/30/2020 -
03/31/2021
LI-AA-100-10003
NRC Performance Indicator
71151
Procedures
NP 5.2.16
NRC Performance Indicators
2012-0006
Service Water Flow during NFPA 805 Fire Events
2018-0016
Service Water Flow during NFPA 805 Fire Events
FPTE 2016-003
PBN Nuclear Safety Capability Assessment (NSCA)
Calculations
PRA 8.1
Fire PRA Plant Boundary Definition and Partitioning
Notebook
NFPA 805 Documentation Incorrect
10/18/2018
NFPA 805 Action Not Contained in Procedure
10/17/2019
Corrective Action
Documents
NFPA 805 Spurious Operation of Service Water Valves Not
Considered
10/17/2019
Corrective Action
Documents
Resulting from
Inspection
NRC Identified Small Gap in Barrier Between FZ 245 and
FZ 322
06/10/2021
Procedures
EOP-2 UNIT 1
Faulted Steam Generator Isolation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OM 3.27
Control of Fire Protection and NFPA 805 Equipment
77