IR 05000454/2022002
| ML22217A063 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/08/2022 |
| From: | Hironori Peterson Region 3 Branch 3 |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2022002 | |
| Download: ML22217A063 (33) | |
Text
SUBJECT:
BYRON STATION - INTEGRATED INSPECTION REPORT 05000454/2022002 AND 05000455/2022002
Dear Mr. Rhoades:
On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Byron Station. On July 14, 2022, the NRC inspectors discussed the results of this inspection with Mr. H. Welt, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. 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 violation or the significance or severity of the violation 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 Byron Station.
August 8, 2022 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, Hironori Peterson, Chief Branch 3 Division of Reactor Projects Docket Nos. 05000454 and 05000455 License Nos. NPF-37 and NPF-66
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000454 and 05000455
License Numbers:
Report Numbers:
05000454/2022002 and 05000455/2022002
Enterprise Identifier:
I-2022-002-0045
Licensee:
Constellation Energy Generation, LLC
Facility:
Byron Station
Location:
Byron, IL
Inspection Dates:
April 1, 2022 to June 30, 2022
Inspectors:
D. Betancourt-Roldan, Senior Resident Inspector
J. Bozga, Senior Reactor Inspector
J. Cassidy, Senior Health Physicist
M. Gangewere, Reactor Inspector
D. Kimble, Senior Resident Inspector, Braidwood Station
E. Sanchez Santiago, Project Engineer
A. Shaikh, Senior Reactor Inspector
M. Siddiqui, Reactor Inspector
P. Smagacz, Resident Inspector, Braidwood Station
C. Thompson, Illinois Emergency Management Agency
J. Weigandt, Acting Senior Resident Inspector
Approved By:
Hironori Peterson, Chief
Branch 3
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Byron Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
Failure to Have Appropriate Work Instructions Leads to Inoperability of the Unit 1 Diesel Driven Auxiliary Feedwater Pump Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000454/2022002-01 Open/Closed None (NPP)71111.15 A finding of very low safety significance (Green) and associated non-cited violation (NCV) of Title 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, Drawings," was self-revealed for the licensee's failure to have work instructions appropriate for the circumstances when replacing the 1B auxiliary feedwater (AF) pump jacket water braided hoses, an activity affecting quality. Specifically, Work Order (WO) 1888896, "Diesel Driven Auxiliary Feedwater Pump Inspection per BMP 3203-1," and WO 4633348. Replace Hoses that were not Replaced During B1R21 During B1R22, did not provide appropriate instructions on the number of flex hoses that needed to be fabricated and replaced. This ultimately led to a hose in the 1B AF pump not being replaced as specified in the WOs and subsequently failing due to age related degradation, which caused the 1B AF pump to be declared inoperable until the hose was replaced.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period operating at full power. Apart from minor reductions in power to support scheduled testing activities or small load changes requested by the transmission dispatcher, the unit remained at or near full power for the entire inspection period.
Unit 2 began the inspection period operating at approximately 90 percent power, in coast down for the planned refueling outage. On April 18, 2022, the unit began a refueling outage. The unit went critical again on May 11, 2022, and returned to full power on May 15, 2022. The unit has remained at or near full power.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems on June 10, 2022.
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)2B Residual Heat Removal (RH) Train aligned for shutdown cooling on April 22, 2022.
- (2) Spent Fuel Pool cooling while the core was offloaded on April 27, 2022
- (3) Component Cooling Water (CC) System following several alignment changes on June 6, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 Containment Spray (CS) System on April 26, 2022.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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 (FZ) 12.1-0; Fuel Handling Building, 401' -0" Elevation and 426' -0" Elevation on April 27, 2022
- (2) FZ 1.3-2; Unit 2 Containment 426' -0" containment upper area on April 28, 2022
- (3) Inner Missile Barrier Containment on April 28, 2022
- (4) Turbine Deck on May 2, 2022
- (5) FZs 11/5A-1, 11.5B-1, and 11.6-1; Unit 1 Auxiliary Building on June 10, 2022
- (6) Auxiliary Building 426' Elevation, Division 11 and 12 ESF Switchgear rooms on June 28, 2022
71111.07T - Heat Exchanger/Sink Performance Heat Exchanger (Service Water Cooled) (IP Section 03.02)
The inspectors evaluated heat exchanger performance on the following:
- (1) Motor Driven Auxiliary Feedwater Pump Oil Cooler (2AF01AA)
- (2) CC Water Heat Exchanger (1CC01A)
Ultimate Heat Sink (IP Section 03.04) (1 Sample)
The inspectors evaluated the ultimate heat sink performance on the following:
- (1) The ultimate heat sink, specifically Sections 03.04.b and 03.04.d were completed.
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors reviewed the licensee degradation monitoring and repair/replacement activities of the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk significant piping system boundaries, and containment boundary. Specifically, the inspectors reviewed the following activities from April 18 to May 3, 2022:
03.01.a - Nondestructive Examination and Welding Activities.
Remote inservice ultrasonic examination of reactor vessel nozzle to safe end, nozzle to pipe, and safe end to pipe welds
Liquid penetrant examination of residual heat removal system component 2RH-02-AA/RHES-01 (support skirt weld)
Ultrasonic examination (UT-1) of feedwater (FW) system, component ID 2FW03DA-16/C23, pipe-elbow weld Ultrasonic examination (UT-1) of FW system, component ID 2FW03DA-16/C24, elbow-pipe weld
Ultrasonic examination (UT-1) of FW system, component ID 2FW03DA-16/C25, pipe-elbow weld
Ultrasonic examination (UT-1) of FW system, component ID 2FW03DD-16/C17, elbow-pipe weld
Ultrasonic examination (UT-1) of FW system, component ID 2FW03DD-16/C18, pipe-elbow weld
AR 04376383; Rejectable NDE Indication on 2FW009C Final Plug Weld
AR 04376507; Rejectable NDE Indication on 2FW009C FW-5
Pressure boundary excavation and field weld (four locations) of 2VA03SA (WO 1950332)03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
ASME Code Case N-729 ultrasonic examination of all head penetrations including leak path assessment
ASME Code Case N-729 bare metal visual examination of upper head surface
Reactor vessel upper head penetration # 75 flaw acceptance and operability review
Bare metal visual (BMV) examination of the RPV upper head penetrations 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
Boric Acid Leakage Evaluation on Component ID 2CV8401B (Issue Report 4377597)
Boric Acid Leakage Evaluation on Component ID 2FE-0136 (Issue Report 4463896)
Boric Acid Leakage Evaluation on Component ID 2FC04F (Issue Report 4328082)
Boric Acid Leakage Evaluation on Component ID 2FC02F (Issue Report 4391135)03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
Steam generators A, B, C, and D, eddy current (ET) examination
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 2 downpower in preparation for refueling outage on April 17, 2022, and Unit 2 reactor vessel drain down for head set and loop fill on May 3, 2022.
- (2) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 2 reactor startup and power ascension on May 11, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the performance of licensed plant operators in the simulator on June 14, 2022.
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) Unit 1 'A' CS system on April 8, 2022
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Unit 1 'B' CS system, as documented in WOs 138757, 5110561, 5110562, and 1807588 on January 20, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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) Technical Specification (TS) 3.0.4.b Evaluation; mode change with TS equipment out of service.
- (2) Evaluation of the emergent work associated with 1CV131 Letdown Control Valve malfunction, as documented in Issue Report (IR) 4494392 on April 20, 2022.
- (3) Evaluation of the risk management associated with shutdown cooling and Reactor Coolant System (RCS) drain down per 2BGP 100-6, Refueling Outage, Revision 56, on April 20, 2022.
- (4) Risk management during the week of May 2, 2022.
- (5) D6 Control Cabinet Power Supply trouble for 1PA34J power supply Train B failure, as documented in IR 4501672 on May 25, 2022.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Evaluation of the operability of the 1A Emergency Diesel Generator (EDG) following identification of a low governor oil, as documented in IR 4490346 on April 5, 2022.
- (2) Evaluation of the operability of the 1B AF pump following identification of a hose leak, as documented in IR 4492979 on April 14, 2022.
- (3) Evaluation of the operability of the Unit 2 N-32 Source Range Nuclear Instrument, following observation of anomalous indications, as documented in IRs 4495778 and
===4494520, during the week ending May 7, 2022.
- (4) Evaluation of the operability of the 2B EDG following identification of degraded equipment, as documented in IRs 4500831, 4500836, and 4500843, on May 20, 2022.
- (5) Foreign Material Exclusion evaluation of material lost in SG, as documented in IR 4496744.
- (6) Evaluation of the operability for Penetration 75 indication, as documented in IR 4495098.
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
=
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering Change (EC): 629149; 480V Substation Breaker Setting Change
- (2) EC 627889: 25A-3" Pipe Replacement
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Functional and operational testing of the 2A Chemical and Volume Control pump following rotating element replacement, as documented in WO 4749380, on May 2, 2022.
- (2) Functional and operational testing of the 2PS9356B following repairs, as documented in WO 5089242 on May 10, 2022.
- (3) Functional and operational testing of the 2B AF pump following maintenance, as documented in multiple WOs on May 13, 2022.
- (4) Functional and operational testing of the 1D Reactor Coolant Pump Seal following replacement, as documented in WO 5256214 on May 10, 2022.
- (5) Functional and operational testing of post-refueling physics testing, as documented in WO 5091520 on May 16, 2022.
- (6) Functional and operational testing of the Pressure Relief Tank Rupture Discs following replacement, as documented in WOs 5091495 and 5091498, on June 3, 2022.
- (7) Functional and operational testing of the 2AF178 2B AF Suction Motor Operated Valve following troubleshooting and maintenance, as documented in WO 5089590 on June 3, 2022.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage B2R23 activities from April 18 to May 10, 2022.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (4 Samples)
- (1) Main Steam Safety Valve Trevi-Testing, as documented in WOs 5085883, 4723440,
===4724302, 4724303, 4724304, 4724305, 4724306, and 5206756 on April 12 and April 21, 2022.
(2)2B AF testing, as documented in WO 5085881 on April 13, 2021.
(3)1A EDG monthly testing, as documented in W 5248909 on May 6, 2022.
(4)2BOSR 5.5.8CV6-3; Missed Surveillance and Post-Maintenance Deferral, as documented in IR 4497553 on May 5, 2022.
Inservice Testing (IP Section 03.01)===
(1)2B EDG Endurance Run and Hot Restart Test, as documented in WO 4848734 on May 19, 2022.
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
(1)2BOSR 6.1.1-21; Leak Rate Test of 2WO006A, as documented in WO 5091371-01 on April 28,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (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 and workers exiting the Radiologically Controlled Area at 401' Main Control Point during a refueling outage.
- (2) Licensee surveys of potentially contaminated material leaving the Radiologically Controlled Area and workers exiting the Radiologically Controlled Area at Unit 2 Contractor Access Facility during a refueling outage.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Manual Movement of Reactor Thimble from the Unit 2 Seal Table
- (2) Steam Generator Eddy Current
- (3) Reactor Vessel Head Penetration 75 (Preparation and Mock-up)
- (4) Unit 2 Steam Generator Manway/Diaphragm Removal High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Unit 2 Incore Sump
- (2) Unit 2 Steam Generator Manway Access
- (3) Unit 2 377' Containment Inside Missile Barrier Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Temporary High Efficiency Particulate Air (HEPA) Ventilation under the Unit 2 Reactor Head
- (2) Temporary High Efficiency Particulate Air (HEPA) Ventilation used for Steam Generator work
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
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 02.04)===
- (1) Unit 1 (April 1, 2021 - March 31, 2022)
- (2) Unit 2 (April 1, 2021 - March 31, 2022)
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 (April 1, 2021 - March 31, 2022)
- (2) Unit 2 (April 1, 2021 - March 31, 2022)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (April 1, 2021 - March 31, 2022)
- (2) Unit 2 (April 1, 2021 - March 31, 2022)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 October 1, 2021 through May 31, 2022
- (2) Unit 2 October 1, 2021 through May 31, 2022 OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 1, 2021 through May 31, 2022 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) October 1, 2021 through May 31, 2022
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) The inspectors performed a detailed review of IR 4496332; B2R23 CRDM Thermal Sleeve Metrology Results.
- (2) The inspectors reviewed post-maintenance testing (PMT) IR 4474490, Incomplete PMT for MCB Hand Switch Replacement. As a result, the inspectors reviewed additional PMT work orders and IRs.
- (3) Inconsistent Use of Test Instrument Selection Criteria when Testing CS Additive Tank Vacuum Relief.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends fuses and fuse holders that might be indicative of a more significant safety issue.
INSPECTION RESULTS
Failure to Have Appropriate Work Instructions Leads to Inoperability of the Unit 1 Diesel Driven Auxiliary Feedwater Pump Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000454/2022002-01 Open/Closed None (NPP)71111.15 A finding of very low safety significance (Green) and associated non-cited violation (NCV) of Title 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, Drawings," was self-revealed for the licensee's failure to have work instructions appropriate for the circumstances when replacing the 1B auxiliary feedwater (AF) pump jacket water braided hoses, an activity affecting quality. Specifically, Work Order (WO) 1888896, "Diesel Driven Auxiliary Feedwater Pump Inspection per BMP 3203-1," and WO 4633348. Replace Hoses that were not Replaced During B1R21 During B1R22, did not provide appropriate instructions on the number of flex hoses that needed to be fabricated and replaced. This ultimately led to a hose in the 1B AF pump not being replaced as specified in the WOs and subsequently failing due to age related degradation, which caused the 1B AF pump to be declared inoperable until the hose was replaced.
Description:
On April 14, 2022, the 1B AF diesel driven pump was started to perform its scheduled monthly surveillance. Approximately 21 minutes into the run, local operators reported a jacket water leak and proceeded to secure the pump. Following evaluation of the leak by the operators and maintenance, the station determined that the leak was not able to be temporarily repaired and that it affected the operability of the pump. The licensee proceeded to enter Condition A of Technical Specifications (TS) 3.7.5, Auxiliary Feedwater System, which is a 72-hr action statement. The leaking hose was replaced, and the pump was returned to service after a successful post-maintenance run during night shift on April 14, 2022.
The affected hose was sent to Power Labs for failure analysis, where it was determined that the cause of the failure was age related degradation. The hose manufacturing stamp indicated it was manufactured in 2005, which meant the hose was 17 years old at the point when the failure occurred. In accordance with the stations preventive maintenance documents (PMID 103868-36 and 112168-36), the flexible hoses need to be replaced at a 12-year frequency. To meet the preventive maintenance the hoses for the 1B AF pump were scheduled to be replaced in 2017 and 2018 under WOs 1888896 and 4633348 (2018). The 2B AF pump hoses were replaced in 2018 under WO 1894388, Replace Flexible Hoses.
However, the WOs associated with the 1B AF pump did not provide appropriate instructions on the number of flex hoses that needed to be fabricated and replaced. This ultimately led to a hose in the 1B AF pump not being replaced, as was the purpose of the WOs, and subsequently failing due to age related degradation on April 14, 2022.
Corrective Actions: The affected jacket water braided hose was replaced and the 1B AF pump was returned to operable status on April 14, 2022. The licensee also plans to replace all flexible hoses on the 1B and 2B AF pumps as well as 0A and 0B essential service water diesel driven pumps with appropriate documentation to verify each flexible hose has been replaced with a new part.
Corrective Action References: AR 4492979
Performance Assessment:
Performance Deficiency: The inspectors determined that the licensee's failure to have work instructions appropriate for the circumstances to replace the 1B AF jacket water braided hoses, an activity affecting quality, was contrary to Title 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, Drawings," and was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, not having appropriate work instructions led to a flexible hose not being replaced in accordance with the purpose of the WOs. That hose developed a leak due to age related degradation that affected the reliability and availability of the equipment.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors screened this finding against the Mitigating Systems screening questions in Exhibit 2 and answered "NO" to all six screening questions. Therefore, the finding screened to very low safety significance (Green).
Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Violation: Title 10 CFR 50 Appendix B, Part V, "Instructions, Procedures, Drawings," states, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Contrary to the above, on March 23, 2017, and September 25, 2018, technicians replaced flexible hoses on the 1B AF pump using WOs 1888896 and 4633348, an activity affecting quality, without appropriate work instructions for the work. Specifically, the WOs did not specify how many hoses needed to be replaced or how to install them. This ultimately led to one of the flexible hoses developing a leak due to age related degradation and affected the availability of the 1B AF pump, a safety related component.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Observation: Post-Maintenance Testing Inconsistencies with 1SX01PB and 2AF017B 71152A Based on post-maintenance testing (PMT) issue report (IR) 4474490, from January 28th, 2022, inspectors reviewed PMT WOs and IRs to assess the corrective action program (CAP) performance attributes of completeness, accuracy, evaluation, and corrective actions.
On March 22nd, 2022, following a work window, PMT, and comprehensive testing of 1SX01PB, Unit 1 B Essential Service Water pump, NRC inspectors performed a PMT inspection of 1SX01PB. The inspectors identified that the pump was running with a lower-than-normal oil level. The oil sump level was at the bottom of the sight glass.
Inspectors reviewed the associated WOs and noted that the associated PMT checks of oil level were already recorded as having been completed satisfactory. Operations staff was informed of the low oil condition and that the PMT oil level checks had been recorded as finished. Two gallons of oil were subsequently added to the running pump, and the issue was documented in the CAP as IR 4486869, NRC ID: 1B SX Pp oil low in sight glass after work window.
During another PMT review, inspectors noted inconsistencies with WO 5089590 2AF017B, Unit 2 B Auxiliary Feed Essential Service Water isolation motor operated valve. Inspectors found that task 4 (sway strut support removal and reinstallation) was completed, but its required engineering PMT, task 17, had not been completed. Inspectors also found that task 15, operations PMT, was closed to WO 04974921-01, which was completed in the previous year, May 11, 2021. Task 15 was the required PMT for completed work tasks 14, 19, and 20 (diagnostic testing, contactor replacement, and control relay and breaker handle replacement). The inspectors brought their concern to operations and maintenance management. The site documented the inspectors concerns in the CAP as IR 4501960, NRC Identified-Incorrect 2AF017B PMT closure and 4508013, NRC ID - PMT process not followed. Following discussions with different levels of management at the site, the inspectors were provided information that demonstrated that although a formal PMT was not performed, different tasks in the WO included portions that met the intent of the PMT.
Breakdowns in following PMT process procedures can result in incomplete or inaccurate PMT. Without proper PMT, a latent problem could prevent systems, structures, or components from operating as expected when needed to perform their safety function.
Consequently, PMT is especially important for the Auxiliary Feedwater system, which is not normally operated outside of testing. Inspectors reviewed the licensees procedure MA-AA-716-012, Post-Maintenance Testing (Rev. 27), in part, and saw the following steps:
4.2.4. stated, in part Post-Maintenance Testing shall be performed following any corrective and some preventive maintenance activities on plant equipment that may have impacted the equipments ability to perform its intended function. These activities may include:
-
1. Maintenance that affects the integrity or operation of a fluid or gas system or
components within those systems...
-
3. Maintenance that affects / disturbs electrical connections, control circuitry or
electronic components."
4.2.7. stated If it becomes necessary to deliberately deviate from established PMT, then the group responsible for performing the PMT shall OBTAIN and DOCUMENT justification for the deviation., and
4.3.3. stated If the scope of the work expands beyond the original maintenance task, then that task / Work Package shall be revised and reviewed for possible changes to Post-Maintenance Testing.
The inspector considered that the failure to follow MA-AA-716-012 was a performance deficiency and violation of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, Drawings. The performance deficiency was determined to be of minor significance.
Although a formal PMT was not performed, other actions in the same work order accomplished the intent of the PMT prior to returning the equipment to service.
The review of the January PMT-related IR and subsequent related issues suggest there are opportunities to better use the CAP for evaluation of IRs and for more timely corrective actions to optimize development, execution, and oversight of subsequent PMT. There were no findings as a result of this review, and the observation was shared with the site, who is addressing this item as part of their planned corrective actions.
No findings or violations of NRC requirements of more than minor safety significance were identified in the course of this review.
Observation: Test Instrument Selection Criteria Not Being Used for Testing Containment Spray Additive Tank Vacuum Relief Valves 71152A Inspectors evaluated the CAP to assess completeness, timeliness, and evaluation of an identified problem.
Based on some past challenges related to measurement and test equipment (M&TE), a maintenance effectiveness inspection was performed for Unit 1 Containment Spray (CS)vacuum breaker relief valve tests (WO 5110561 & 5110562). The testing is required by ASME OM code. In the event of a CS actuation, the safety related vacuum breaker relief valves open as vents for the spray additive tank to allow sodium hydroxide (NaOH) to be adducted from the tank into the discharge of the CS pumps. The safety function provides for a design flow of 55 gallons per minute of NaOH into containment to obtain pH = 7 in the containment sump. Accordingly, if the vacuum breaker relief valves dont properly open, design flow may not be obtained.
In April, inspectors noted issues of concern related to the documentation of the test instrument used, force gauge serial no. 2906994. The work orders were performed in 2022, but the recorded calibration due date was February 22, 2021. Additionally, the force gauge that was used to check ounces of force to move the valve stem open was calibrated for a range above the test setpoint. Specifically, the recorded setpoints measured were between 1.32 oz to 3.32 oz (.0825 lbf to
.277 lbf), while the calibrations recorded test range of 16 oz to
144 oz (1 lbf to 9 lbf). According to the work package instructions, Engineering Change Request (ECR) 163345, and ECR 167093, the acceptance criteria for unseating force is less than or equal to 7 oz (.4375 lbf).
On April 11th, 2022, inspectors discussed their concerns with Byron staff and questioned whether the calibration due date and instrument used were correct. The concern would be that an out of calibration instrument or incorrect instrument may provide invalid test results.
Staff clarified that the listed calibration due date was mistakenly entered as the calibration date and noted that calibration was not overdue. To address the concern of the test force setpoint being below the calibration range, the licensee entered the condition into the CAP as IR 4500840, NRC identified issue with vacuum breaker testing, on May 19th, 2022, and conducted a post-test calibration check of the force gauge at 7 oz. The satisfactory post-test calibration check, certification no. 11394822, was provided to the NRC and demonstrated that test acceptance criteria was met.
Inspectors further checked if the work package included adequate instruction for proper test equipment selection. The instructions used by technicians appeared as a single step that stated, in part:
7.2.1. Using a calibrated force gauge, selected for oz., APPLY force linearly and directly up the stem of the valve However, the work order also included BMP 3100-9 IST Bench Testing Safety/Relief Valves, Rev. 23, a Reference Use procedure, which did not appear to be used. The BMP listed more specific test instrument selection instructions as follows:
F.2.c.3) Pressure gauges (all tests), with range appropriate to valve being tested and to type of test using following criteria:
1. Gauge must be calibrated.
2. Gauge must be specific to test medium.
3. Range of gauge should be approximately two times max. test pressure, BUT NOT
less than 1 1/2 times OR greater than four times test pressure.
4. Gauge used to determine set pressure MUST have, as a minimum, tolerance of
plus 1% AND minus 1% of the relief/safety valve set pressure.
Inspectors noted that evaluation of the above criteria of BMP 3100-9, provided adequate instructions for test equipment selection. A historical review indicated that the issue of concern has been recurring for both units for beyond ten years. The station appeared to be using a similar gauge during this time, so the satisfactory calibration check at 7 oz demonstrated assurance of historical operability.
The inspectors determined that the failure to assure that adequate test instrumentation was available and used to test safety related equipment was a performance deficiency and contrary to 10 CFR 50, Appendix B, Criterion XI. Per Inspection Manual Chapter 0612, Appendix B and example 5.d in Appendix E, the team determined that this performance deficiency was minor, because the licensee was able to show reasonable assurance that acceptance criteria was met.
Corrective actions planned by the licensee include measures to obtain the correct tools for future vacuum breaker tests. Inspectors briefed management on the use of CAP for performing comprehensive and timely documentation of longstanding test deficiencies.
No findings or violations of NRC requirements of more than minor safety significance were identified in the course of this review.
Observation: Thermal Sleeves 71152A The inspectors performed a detailed review of IR 4496332; B2R23 CRDM Thermal Sleeve Metrology Results.
The sample selected was associated with a 10 CFR Part 21 notification to the NRC (Westinghouse LTR-NRC-19-79, dated December 12, 2019; ADAMS Accession No. ML19346H873) and additional information on the 10 CFR Part 21 in Nuclear Safety Advisory Letter (NSAL) NSAL-20-1, Reactor Vessel Head Control Rod Drive Mechanism Penetration Thermal Sleeve Cross-Sectional Failure, dated February 14, 2020 (ADAMS Accession No. ML20063J583). The specific issue was associated with mechanical fatigue and fracture that leads to flange separation of thermal sleeves in the control rod drive mechanism penetration tubes which could have a safety consequence that was not previously considered. In addition, the sample was associated with NSAL-18-1, Thermal Sleeve Flange Wear Leads to Stuck Control Rod, July 9, 2018 (ADAMS Accession No. ML18198A275). The specific issue was associated with thermal sleeve flange wear that leads to complete flange separation of the thermal sleeves which may prevent control rod insertion. PWROG-16003-P, Evaluation of Potential Thermal Sleeve Flange Wear, Revision 2 provides acceptance criteria for evaluation of thermal sleeve flange wear associated with NSAL 18-1.
The licensee performed an evaluation of the actual thermal sleeve wear measurements taken at thermal sleeve penetrations during the spring Unit 2 2022 outage, and the NSAL-20-1 acceptance criteria was met. In addition, the PWROG-16003-P, Revision 2 acceptance criteria was met.
No findings or violations were identified Observation: Trend in Fuse Deficiencies 71152S The inspectors performed a semiannual review of the licensee's CAP for adverse trends. An abnormally high number of fuse problems had been identified in the second quarter of 2022.
The 18 issue reports (IRs) with month and day are as follows:
- 4493936, Fuse holder broken during fuse removal, 4/18
- 4493879, Fuse holder broken during fuse removal, 4/18
- 4493880, Control power fuse holder broken during fuse removal, 4/18
- 4494379, 2AP96E-B3 fuse holder broken, 4/20
- 4494380, 2AP96E-B4 fuse holder broken, 4/20
- 4494377, 2AP96E-E4 fuse holder broken, 4/20
- 4494375, 2AP96E-C4 fuse block broken, 4/20
- 4494336, Fuse holder broken during fuse removal, 4/20 4494301, Bus 257 AB Phase fuse open, 4/20 4494275, Fuse holder installed upside down, 4/20
- 4494589, Broken fuse holder, 4/21
- 4494659, MCC Fuse holder broken, 4/21
- 4494993, Fuse holder detached from panel 2AP60E-F2-FU, 4/22
- 4495221, Control Power Fuse Detached from panel 2AP60E-F1-FU, 4/24 4496383, 2AF017B Blown Fuse in MCC Bucket 232X3-CUB A5, 4/28 4496204, Fuses not installed and no EPN label present, 4/28 4498267, Bad fuse for 2AP60E-E3-FU (control power), 5/07 4498895, 2B FW Pump Fuse 12 N/P Blown, 5/10
- The licensee also identified a related trend, documenting 12 of the 18 deficiencies in their CAP as 4502316, Potential Trend identified in broken fuse holders, 5/27.
After reviewing the reports, the inspectors did not identify a performance deficiency. The inspectors determined the licensee appropriately followed the corrective action process and did not identify existence of a more safety significant concern.
No findings or violations of NRC requirements of more than minor safety significance were identified in the course of this review.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 14, 2022, the inspectors presented the integrated inspection results to Mr. H. Welt, Site Vice President, and other members of the licensee staff.
On April 29, 2022, the inspectors presented the radiation protection inspection results to Mr. S. Leach, Radiation Protection Manager, and other members of the licensee staff.
On May 4, 2022, the inspectors presented the inservice inspection results to Mr. J. Kowalski, Site Vice President, and other members of the licensee staff.
On June 23, 2022, the inspectors presented the triennial heat sink inspection results to Mr. H. Welt, Site Vice President, and other members of the licensee staff.
On June 24, 2022, the inspectors presented the radiation protection inspection results to Mr. H. Welt, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4504518
NRC ID: Piping Support Missing from 2A DG Fuel Supply Line
06/08/2022
Corrective Action
Documents
Resulting from
Inspection
4504519
NRC ID: 231X Broken Cover Glass for Relay
06/08/2022
Drawings
KSV-31-3
Fuel Transfer Pump
C
0BOSR XHT-A1
High Temperature Equipment Protection
Procedures
BOP 199-XHT-1
Hot/Extreme Weather Operations
Corrective Action
Documents
Resulting from
Inspection
4499160
NRC Identified: Breaker Open Light not Lit
05/11/2022
M-129 Sheet 1A
Diagram of Containment Spray Unit 2
M-129 Sheet 1B
Diagram of Containment Spray Unit 2
M-129 Sheet 1C
Diagram of Containment Spray Unit 2
AH
M-136 Sheet 4
Diagram of Safety Injection Unit 2
AZ
M-63-1A
Diagram of Fuel Pool Cooling and Clean-Up
BI
M-63-1B
Diagram of Fuel Pool Cooling and Clean-Up
M-63-1C
Diagram of Fuel Pool Cooling and Clean-Up
AY
Drawings
M-66, Sheet 3B
Diagram of Component Cooling Critical Control Room Drawing
Miscellaneous
Fuel Pool Cooling One Line Diagram
BOP CC-1
Component Cooling Water System Startup
BOP CC-10
Alignment of the U-0 CC Pump and U-0 CC Hx to a Unit
BOP CC-M2
Component Cooling System Valve Lineup
BOP CS-E2
Containment Spray System Electrical Lineup (Unit 2)
BOP CS-M2
Containment Spray System Valve Lineup
Fuel Pool Cooling System Electrical Lineup
Fuel Pool Cooling and Cleanup System Valve Lineup
Procedures
BOP RH-M2B
Train "B" Residual Heat Removal System Valve Lineup
Drawings
FP-7,
Fire Barrier Location Plan Elev 426-0
F
Fire Plans
FZ 1.3-2
Containment 426' 0" Elevation Unit 2, Containment Upper
Area
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FZ 12.1-0
Fuel Handling Building 426'-0" Elevation
FZ 12.1-0
Fuel Handling Building 401'-0" Elevation
PFP AB1 414 FZ
11.5A-1 11.5B-1
Pre-Fire Plan Auxiliary Building Unit 1 414-0 Elevation
Electrical Penetration Area FZ 11.5A-1, 11.5B-1 PLAN #152
PFP AB1 426-0
FZ 11.6-1
Pre-Fire Plan Auxiliary Building Unit 1 426-0 Elevation
Division 12 Electrical Penetration Area FZ 11.6-1
PFP AB1 426-0
FZ 5.1-1
Pre-Fire Plan Auxiliary Building Unit 1 426-0 Elevation
Division 12 ESF Switchgear Room FZ 5.1-1 Plan #41
PFP AB1 426-0
FZ 5.2-1
Pre-Fire Plan Auxiliary Building Unit 1 426-0 Elevation
Division 11 ESF Switchgear Room FZ 5.2-1 Plan #43
BYR97-034
Byron Essential Service Water Cooling Tower Basin Minimum
Volume Versus Level and Minimum Usable Volume
Calculation
Calculations
CC-MP-01
Verification of CC System Overpressure Protection
2/01/1988
4162710
SX Piping Leaks Trend IR
01/08/2019
26273
1A SX Pump Oil Leak Outboard Pump
04/12/2020
26982
1A SX Pump Vent Valve Broken
04/15/2020
4449689
Oil Leak on 1AF01PB Filter Housing
09/30/2021
Corrective Action
Documents
4505718
NRC ID: Inactive Oil Leak on 1A AF Pump
06/15/2022
4505244
NRC ID: Ops Surveillance missing "N/A" on open bullet steps.
06/13/2022
4505468
NRC ID - Incorrect Date & Test ID on 2AF017B Report
06/14/2022
4505468
NRC ID: Incorrect Date and Test ID on 2AF017B
06/14/2022
4505517
NRC ID: Insulation Not Fully Secured
06/14/2022
4505533
NRC ID: Small Pools of Oil Underneath 1AF01PB
06/14/2022
4505717
NRC ID: Inactive Oil Leak on 2A AF Pump
06/15/2022
4505756
NRC ID: Procedure Usage on WO 4785428 (HX Inspection
Report)
06/15/2022
4505757
NRC ID: Review 1/2BOSR 6.6.2-1 for Procedure Change
06/15/2022
4505978
NRC ID: Gaps in Work Package Documentation
06/16/2022
4506114
NRC ID: Gaps in Inspection Form Documentation
06/17/2022
4506137
A Potential Trend in WO and Surveillance Paperwork
Closeouts
06/17/2022
Corrective Action
Documents
Resulting from
Inspection
4506178
NRC ID: Incorrect Data on WO 4785428 (HX Inspection
06/17/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Report)
Drawings
M-126
Diagram of Essential Service Water Sections D-F 6-8
04/04/2000
339308
Acceptance Criteria for As-found Heat Exchanger Tube
Blockage
401538
Anode Removal of Stainless-Steel Coolers
09/02/2015
Engineering
Changes
634142
Through Wall Leak on Line 1SX68AB-1 1/2"
2-14-233.410
0B Intake Bay - South Side of RSH River Screen House
Inspection
08/20/2019
AH-CC-654
Exchanger Specification Sheet Component Cooling HX
2/19/1974
N-1661
Heat Transfer Division American-Standard Power & Controls
Group: Heat Exchanger Specification Sheet
09/08/1977
Miscellaneous
Sargent & Lundy
Heat Exchanger
Data Sheets,
attached to
1/17/90 S&L letter
S.C. Mehta to F.
Lentine
1/2AF01AA Heat Exchanger Data Sheet
01/17/1990
Ultrasonic Thickness Calibration Sheet
06/01/2020
Operability
Evaluations
1BOA PRI-7
Essential Service Water Malfunction Unit 1
110
0BOSR
5.5.8SX.5-1c
Unit Zero Comprehensive Inservice Testing (IST)
Requirements for Essential Service Water Makeup Pump 0A
1BOSR
5.5.8.SX.5-1c
Unit One Comprehensive Inservice Testing (OST)
Requirements for the Essential Service Water (SX) Pump
1SX01PA and Unit 1 SX Pumps Discharge Check Valves
2BOA PRI-7
Essential Service Water Malfunction Unit 2
111
2BOSR
5.5.8.SX.5-1c
Unit Two Comprehensive Inservice Testing (IST)
Requirements for the Essential Service Water (SX) Pump
2SX01PA and Unit 2 SX Pumps Discharge Check Valves
BVP 800-30
Essential Service Water Fouling Monitoring Program
(GL 89-13 Program Basis Document)
Procedures
Maintenance Specification: Application Selection, Evaluation
and Control of Temporary Leak Repairs
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Closed Cooling Water Chemistry
CY-AA-120-4110-
F-02
Byron Raw Water Treatment and Control
CY-AP-120-1000-
F-02
Byron Primary Strategic Water Chemistry Plan
CY-AP-2000-F-02
Byron Secondary Strategic Water Chemistry
Heat Exchanger Electromagnetic Testing Methodology
GL 89-13 Program Implementing Procedure
GL 89-13 Program Implementation Instructional Guide
Service Water Heat Exchanger Inspection Guide
7, 9, 11
GL 89-13 Program Performance Indicators
ER-BY-450
Byron Structures Monitoring Program
Torquing and Tightening of Bolted Connections
Shipping Records
4949137
LR-Support Diver Inspection/Cleaning of RSH North 0A Intake
Sed PM
10/02/2019
1480642-01
Perform 2A Mtr Drv AF PP Oil Clr Eddy Current Testing
09/16/2013
1653824-01
Perform Guided Wave Inspection of 2SX67AA-1.5 During
B2R18
06/17/2014
1838239
LR-OTI Auxiliary Feedwater System Inspection
04/10/2019
1897106-02
Dive Inspection of 0B RSH Intake Bay per ER-AA-450
09/16/2020
1908363-01, 04,
LR U2 Ultrasonic Thickness Examination of Selected Service
Water
05/10/2016
4767804
EWP IM Perform Calibration of Loop 0SX-065
09/20/2019
4785428-03
LR-U2 Motor Driven AF Pump - Clean and Inspect Lube Oil
Cooler
11/08/2018
4856571
LR-Support Diver Inspection/Cleaning SXCT South 0B Basin
06/24/2020
4864027
LR-Support Diver Inspection/Cleaning SXCT North 0A Basin
05/29/2020
4876057
LR-Support Eddy Current Testing Concurrent with GL 89-13
08/26/2020
487741
EWP IM Perform Calibration of 0SX-064
06/04/2020
4889682
0SX02PA Comprehensive IST Req for SX Makeup Pump
05/30/2019
24503
LR-Support Diver Inspection/Cleaning RSH South IB Intake
Sed PM ID
08/20/2019
Work Orders
24816
LR-RSH Center Bay Diver Inspection
05/21/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4932711
0SX02PA Comprehensive IST Req for SX Makeup Pump
08/01/2019
4950925
0SX02PA Comprehensive IST Req for SX Makeup Pump
10/03/2019
4964642
EWP IM Perform Calibration of Loop 0SX-065
05/11/2021
29921
Reactor Containment Fan Cooler Surveillance
06/24/2020
5041533-03
LR-U2 Motor Driven AF Pump - Clean and Inspect Lube Oil
Cooler
11/02/2021
505039
EWP IM Perform Calibration of 0SX-064
10/28/2021
256027-01
LR-2A AF Pump SX Suction Line Flushing Surveillance
06/01/2022
Calculations
51-9131378-006
Technical Justification for Detection of Leak Path Indications in
RPV Upper Head Penetrations
006
04376383
Rejectable NDE Indication on 2FW009C Final Plug Weld
10/13/2020
04376507
Rejectable NDE Indication on 2FW009C FW-5
10/14/2020
04495098
U2 Reactor Head Indication at Pen-75
04/23/2022
04496413
FME - Foreign Object Found in 2C SG Secondary Side
04/29/2022
04496417
FME - Foreign Object Found in 2A SG Secondary Side
04/29/2022
04496418
FME - Foreign Object Found in 2D SG Secondary Side
04/29/2022
044964210
FME - Foreign Object Found in 2B SG Secondary Side
04/29/2022
04496744
FME - Floating Tie Wrap lost in SG B (2RC01BB)
4/30/2022
28082
Active Leak Identified in 2FC04F Vault
03/20/2020
4377597
WO 5084887 Failed PMT - 2CV8401B External Leakage
10/19/2020
4391135
Standing Water in 2FC02F
2/18/2020
Corrective Action
Documents
4463896
2FE-0136 Inactive, Non-Minor Boric Acid Leakage from
Bolting
11/30/2021
Corrective Action
Documents
Resulting from
Inspection
4494383
NRC ID: WO#1950332-01 Missing Work Package Instructions
04/20/2022
Engineering
Evaluations
Operability Evaluation Reactor Head Penetration 75
Rev 0
2RC01R Reactor Top Head BMV
04/28/2022
BR23-PT-001
Liquid Penetrant Examination of Component
2RH-02-AA/RHES-01 (Support Skirt)
04/24/2022
NDE Reports
BR23-UT-012
Ultrasonic Examination of Component 2AF02DA-4/C04
04/20/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
BR23-UT-013
Ultrasonic Examination of Component 2AF02DA-4/C03
04/20/2022
BR23-UT-014
Ultrasonic Examination of Component 2AF02EA-4/C01
04/20/2022
BR23-UT-015
Ultrasonic Examination of Component 2AF02DE-4/C06
04/20/2022
BR23-UT-016
Ultrasonic Examination of Component 2AF02EA-4/C03
04/20/2022
BR23-UT-017
Ultrasonic Examination of Component 2AF02EA-4/C02
04/20/2022
BR23-UT-018
Ultrasonic Examination of Component 2AF02EA-4/C04
04/20/2022
BR23-UT-019
Ultrasonic Examination of Component 2AF02EA-4/C05
04/20/2022
54-ISI-604
Automated Ultrasonic Examination of Open Tube RPV Closure
Head Penetrations
Liquid Penetrant (PT) Examination
Visual Examination of ASME IWE Class MC and Metallic
Liners of Class CC Components,
Ultrasonic (UT) Examination of Ferritic Piping Welds
Bare Metal Visual Examination for Nickel Alloy Materials
Byron/Braidwood Unit 2: Steam Generator Eddy Current
Activities
MRS-2.4.2 GEN-
Eddy Current Inspection of Pre-Service and In-Service
Heat Exchanger Tubing
Procedures
WDI-STD-1165
Remote Inservice Inspection of Reactor Vessel Nozzle to Safe
End, Nozzle to Pipe and Safe End to Pipe Welds Using the
Athena Phased Array System
Work Orders
1950332
Repair Channel Head Based on Inspection Results
05/21/2021
2BGP 100-2A1
Reactor Startup
Procedures
BOP RC-4
Reactor Coolant System Drain
293785
Certificate of Calibration
2/22/2021
Calibration
Records
11363988
Certificate of Calibration
2/08/2022
Corrective Action
Documents
04484018
1CS01PA - Elevated Vibration
05/13/2022
Corrective Action
Documents
Resulting from
Inspection
4500840
NRC Identified Issue with Vacuum Breaker Testing
05/19/2022
Procedures
Maintenance Rule Implementation per NEI 18-10
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4418373
1AF-012 TRP Update
04/22/2021
4494392
1CV131 Failed to Respond
04/20/2022
Corrective Action
Documents
4501672
1PA34J Power Supply Trouble Card C12-335
05/24/2022
Corrective Action
Documents
Resulting from
Inspection
4502395
Response to NRC Question on 1AF-012 Test Report Status
05/27/2022
Drawings
6E-1-4031AF02
Loop Schematic Diagram Aux. Feedwater Steam
Gen. 1A Flow Control System ESF-12 Pnl. 1PA34J
O
Miscellaneous
Shutdown Safety Equipment Status Checklist - MODE 6 399',
Vented
1BOA PRI-15
CVCS Abnormalities Unit 1
2BGP 100-6
Refueling Outage
BAR 1-4-D6
Cont Cab Pwr Sup Trouble
BAR 1-8-A5
Ltdwn HX Outlt Flow High
BHC 1-LD
Letdown Malfunction
000
BOP CV-15
Excess Letdown Operations
Procedures
TRP 1AF-012
Auxiliary Feedwater to Steam Generator 1A Flow Control
Loop (AF) (Train B)
5145422
1FI-AF012A/B Reading 7.5 GPM in MCR & RSP, should
be 0 GPM
10/28/2021
Work Orders
262089
1PA34J Power Supply Trouble Card C12-335
05/24/2022
04492979
Jacket Water Leak on 1B Auxiliary Water Pump
04/14/2022
04496008
Extent of Condition for 2B Auxiliary Feedwater Pump
04/27/2022
4490436
1A EDG Mechanical Governor Oil Level Adjustment
04/05/2022
4494520
Unexpected Rise in Source Range Counts - N32
04/21/2022
4495098
U2 Reactor Head Indication at Pen-75
04/23/2022
4495778
2NY-NR8039 Showing Abnormal Reading
04/26/2022
4496744
FME - Floating Tie Wrap lost in SG B (2RC01BB)
04/30/2022
4500836
2B DG Brg Temp Hi Trip Press Sw 2PS-DG105B OOT
05/19/2022
4500836
2B DG Brg Temp Hi Trip Press Sw 2PS-DG105B OOT
05/19/2022
Corrective Action
Documents
4500843
2B DG Crankcase Oil Level Low in Band
05/19/2022
NDE Reports
INR-B2R23-UT-
Penetration 75, Reportable Indication Notification Report
04/22/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1BOSR 8.1.2-1
Unit One 1A Diesel Generator Operability Surveillance
BAP 370-1
Station Lubrication Program
Inservice Testing (IST) Program Corporate Technical Positions
Control of Lubricants Program
Procedures
OP-BY-101-0002
Byron Operations Expectations Philosophy Handbook
1888896
Diesel Driven Auxiliary Feedwater Pump Inspection per
BMP 3203-1
03/23/2017
1894388
Replace Flexible Hoses
10/12/2017
Work Orders
4633348
Replace Hoses that were not Replaced During B1R21
During B1R22
09/25/2018
2SXE5A-3" SX Pipe Replacement with Stainless-Steel
Engineering
Changes
480 Volt Substation Breaker Setting Change
4495080
2PS9356B Failed LLRT at 56.4 SCFH @ 40 PSIG Test
Pressure
04/23/2022
4495217
2RY16AB - PRT Rupture Disc as Found
04/24/2022
4495218
2RY16AA - PRT Rupture Disc as Found
04/24/2022
4495500
Failed PMT-2PS9356B Failed PMT STT
04/25/2022
4495518
B2R23 2PS9356B Failed as Left LLRT
04/25/2022
4497789
Dual Indication on 2PS9356B with Valve in Closed Position
05/05/2022
Corrective Action
Documents
4497834
Entered 2BOA RCP-1, Reactor Coolant Pump Seal Failure
Unit 2
05/05/2022
4497746
NRC Concern with Troubleshooting Activity
05/04/2022
4498278
Discretionary Near Miss/Working at Height/2B AF Pump Room
05/07/2022
Corrective Action
Documents
Resulting from
Inspection
4501960
NRC Identified - Incorrect 2AF017B PMT Closure.
05/25/2022
Engineering
Evaluations
ECR 454558
Request Engineering to Evaluate Proper Torque Valve for
Rupture Discs.
05/03/2022
Miscellaneous
UFSAR 5.4.11
Pressurizer Relief Discharge System
Procedures
Preventive Maintenance Program
4498740
2AF024 Not Indicating Open During 2BOSR 0.5-3.AF.3-2
05/10/2022
4698389
Rebuild Actuator, Regulators/Replace Elastomers
05/10/2022
Work Orders
4699260
PM Inspection, In-Service Diag. Test, PIT
05/03/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4749380
OPS Perform 2BOSR 5.C.2-1 CV System Flow Balance
05/02/2022
4910712
Replace Time Delay Relay 2AF01J-K4
05/11/2022
4955752
Replace AF PP/Gearbox Lube Oil System Relief Valve
05/11/2022
4955906
Replace AF PP/Gearbox Lube Oil System Relief Valve
05/11/2022
4965733
EOC Inspection on 2AF01PB
05/11/2022
5008479
Replacement of the Synchro Start Speed Pickup
05/11/2022
5089242
2PS9356B Doesn't Stroke Fully Open Following Maintenance
05/06/2022
5089590
2AF017B - Minor Degradation Identified During Diagnostic
Testing
05/11/2022
5091168
2AP05EQ Relay #AF1AX for 2AF01PA
05/01/2022
5091392
2AF01J Relay #K2 for Bus 2AF01PB
05/09/2022
5091394
2AF01J Relay #K4 for Bus 2AF01PB
05/11/2022
5091452
Calibrate K11 TDR
05/11/2022
5091479
2AF053A IST Relief Valve Test
05/10/2022
5091489
Inspect Coupling 2AF01PA-L
05/01/2022
5091495
EWP MM 2RY16AB Replace and Test Rupture
05/01/2022
5091498
EWP MM 2RY16AA Replace and Test Rupture Disk
05/01/2022
5091520-01
OP RE - NF-BY-510, Low Power Physics Testing Program
05/11/2022
5091560
2SX174 IST Maintenance DIS/INSP
05/11/2022
5091593
2AF001A IST Disassembly and Inspection
05/07/2022
5092341
2AF014B IST Disassembly and Inspection
05/07/2022
5093954
LR-2AF02A - HX Inspection per Generic Letter 89-13
05/11/2022
5168425
Diesel Driven AF PP Insp to Support 2BVSR Z.7.A.1
05/11/2022
237933
Request Inspect/Replace L2X Relay - 2B AF Pump
05/11/2022
256214-02
256214-17
MS - PMT Check/Monitor Vibration Levels
257808
2AF015B Leaking by When Valve Shut
05/11/2022
04498444
Unexpected 2A Auxiliary Feedwater Pump Start
05/08/2022
04498497
2B Auxiliary Feedwater Pump Oil Leak
05/09/2022
4497253
Fatigue Assessment/Waiver
05/02/2022
4498320
2D RCP No. 1 Seal Degradation
05/07/2022
4498888
U2 Rod Drive Group 1AC Rods Not Moving
05/10/2022
Corrective Action
Documents
4498901
U2 Rod Drive Power Cabinet SCDE Rods Not Moving
05/10/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4499196
Unplanned entry into 2BOA ROD-2
05/11/2022
4499220
U2 Turbine Trip After Syncing
05/12/2022
4494234
Oil leak - 2SI8808B
04/19/2022
Corrective Action
Documents
Resulting from
Inspection
4494283
Unit-2 Cnmt Oil Leakage on Charcoal Filtration Housing.
04/20/2022
Miscellaneous
B2R23 Shutdown Safety Process Overview
2BOSR Z,5.b.1-1
Unit Two Containment Loose Debris Inspection
Equipment Classification
Operations Standards and Expectations
Shutdown Safety Management Program Byron/Braidwood
Annex
Administrative Controls During Fuel Handling Activities for
Byron and Braidwood
Fuel Movement in the Spent Fuel Pool for Byron and
Braidwood
Fuel Movement in Containment for Byron and Braidwood
Procedures
PWR Fuel and Core Component Handling Practices
04492638
2MS016D Lifted in Unacceptable Range During Testing
04/12/2022
Corrective Action
Documents
04497533
2BOSR 5.5.8.CV.6-3 Cannot be Performed as Scheduled
05/04/2022
B2R23 MSSV Trevi-Testing Plan
04/12/2022
Miscellaneous
PMC-22-135071
Change Frequency of 1/2CV8368 Check Valves
05/12/2022
23440
2MS013A IST Set Point Verification
04/13/2022
24302
2MS014A IST Set Point Verification
04/13/2022
24303
2MS014D IST Set Point Verification
04/13/2022
24304
2MS016A IST Set Point Verification
04/13/2022
24305
2MS016D IST SET Point Verification
04/13/2022
24306
2MS017B IST Set Point Verification
04/13/2022
4848734
2B Diesel Generator 24 Hr Endurance Run and Hot Restart
05/19/2022
5085881-01
OPS - 2BOSR 5.5.8.AF.5-2C Comprehensive IST
Requirements 2AF01PB
04/14/2022
5085883
Main Steam Safety Valves Operability Test (<94% RX PWR)
04/13/2022
Work Orders
5091371
LLRT for P-6 and P-10 - 2WO006A/B, 2WO007A/B
05/05/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5091371-01
As Found LLRT for P-6 and P-10 - 2WO006A/B, 2WO007A/B
04/28/2022
206756
2MS017D IST Trevi-Test
04/13/2022
5848909
(NEIL)-LR-1A Diesel Generator Operability Surveillance
05/06/2022
Corrective Action
Documents
B2R23 Lessons Learned - Loop Drain
04/22/2022
Corrective Action
Documents
Resulting from
Inspection
NRC ID: EC Stickers not added to S/G HEPA Units
04/28/2022
Alpha Area Level Assessment
04/15/2021
Miscellaneous
Alpha Area Level Assessment
04/13/2022
NISP-RP-004
Radiological Posting and Labeling
Electron Capture Isotope Control
Procedures
Determination of Alpha Levels and Monitoring
Radiation Surveys RP-AA-460
Controls for High and Locked High Radiation Areas
BY-0-22-00705
S/G Eddy Current Testing and Tube Repairs
BY-2-22-00654
Seal Table Activities
BY-2-22-00683
Thimble Tube Removal / Replacement
BY-2-22-00710
Task
S/G Diaphragms
Radiation Work
Permits (RWPs)
BY-2-22-00710
Task 1
S/G Manways
Annual Radiological Environmental Operating Report
Byron Generating Station Units 1 and 2
04/30/2022
Monthly Report on the Meteorological Monitoring Program at
the Byron Nuclear Generating Station
2/04/2020
Monthly Report on the Meteorological Monitoring Program at
the Byron Nuclear Generating Station
05/04/2020
Annual Report on the Meteorological Monitoring Program at
the Byron Nuclear Generating Station 2019
03/23/2020
Annual Site Survey - Exelon Meteorological Monitoring Sites
08/28/2020
Miscellaneous
Teledyne Brown Engineering Environmental Services Quality
2/04/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Assurance Report
Radiologic Groundwater Protection Program Results for 2019
01/21/2020
21 Annual RGPP Monitoring Report Summary of Results
and Conclusions
Byron Generating Station
2/11/2021
20 Annual RGPP Monitoring Report Summary of Results
and Conclusions
Byron Generating Station
2/17/2021
Teledyne Brown Engineering Environmental Services Quality
Assurance Report
2/22/2021
11102547 Report
Hydrogeologic Investigation Report
01/31/2020
Environmental Dosimetry - Performance Specifications,
Testing, and Analysis
Procedures
CY-BY-170-301
Offsite Dose Calculation Manual for Byron Station Units 1
and 2
Self-Assessments
NUPIC Audit
Number 24879
Supplier Audit Report for ATI Environmental, Inc.
Northbrook, IL
2/18/2020
1Q22 BYR U1
Mitigating Systems Performance Indicators
06/18/2022
Monthly Data Elements for NRC ROP Indicator - Reactor
Coolant System (RCS) Specific Activity
10/01/2021 -
05/31/2022
Monthly Data Elements for NRC ROP Indicator - Occupational
Exposure Control Effectiveness
10/01/2021 -
05/31/2022
Miscellaneous
Monthly Data Elements for NRC ROP Indicator - RETS/ODCM
Radiological Effluent Occurrences
10/01/2021 -
05/31/2022
Mitigating Systems Performance Index (MSPI) Monitoring and
Margin Evaluation
Mitigating System Performance Index Data Acquisition and
Reporting
71151
Procedures
Mitigating System Performance Index Data Acquisition &
Reporting
4474490
Incomplete PMT for MCB Hand Switch Replacement
01/28/2022
Corrective Action
Documents
4496332
B2R23 CRDM Thermal Sleeve Metrology Results
04/28/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4486869
NRC ID: 1B SX Pp Oil Low in Sight Glass After Work Window
03/23/2022
4490884
Security Equipment Security Door Anti Pick Plate Loose.
04/06/2022
4508013
NRC ID - PMT Process Not Followed
06/29/2022
Corrective Action
Documents
Resulting from
Inspection
4508013
NRC ID - PMT Process Not Followed
06/28/2022
Document No.
2-9348016-000
Byron 2 CRDM Thermal Sleeve As-Found Dimensional
Report 2022
04/25/2022
Miscellaneous
UFSAR 06.5z
A
Iodine Removal Effectiveness Evaluation of Containment
Spray System
Corrective Action
Documents
4502316
Potential Trend Identified in Broken Fuse Holders
05/27/2022