IR 05000454/2021003
| ML21301A216 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/29/2021 |
| From: | Hironori Peterson Region 3 Branch 3 |
| To: | Rhoades D Exelon Generation Co |
| References | |
| EA-21-143 IR 2021003 | |
| Download: ML21301A216 (28) | |
Text
SUBJECT:
BYRON STATION - INTEGRATED INSPECTION REPORT 05000454/2021003 AND 05000455/2021003 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Mr. Rhoades:
On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Byron Station. On October 12, 2021, the NRC inspectors discussed the results of this inspection with Mr. J. Kowalski, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, 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:
05000454/2021003 and 05000455/2021003
Enterprise Identifier:
I-2021-003-0064
Licensee:
Exelon Generation Company, LLC
Facility:
Byron Station
Location:
Byron, IL
Inspection Dates:
July 01, 2021 to September 30, 2021
Inspectors:
S. Bell, Health Physicist
D. Betancourt-Roldan, Senior Resident Inspector
J. Bozga, Senior Reactor Inspector
J. Cassidy, Senior Health Physicist
A. Demeter, Reactor Engineer
V. Meghani, Reactor Inspector
N. Shah, Acting Senior Resident Inspector
J. Vera, Acting Senior Resident Inspector
J. Weigandt, 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000454,05000455/2021011-03 Main Steam Safety Valve Room Structural Acceptance Criteria 71111.21M Closed EDG EA-21-143 Failure to Comply with 10 CFR Part 37 71124.08 Closed
PLANT STATUS
Unit 1 began the inspection period operating at full power. Apart from minor reductions in power to support scheduled testing activities, load changes requested by the transmission dispatcher, and coast down in preparation for a planned refueling outage, the unit remained at or near full power. On September 13, 2021, the unit began a refueling outage. The unit went critical again on September 30, 2021. The unit was returned to full power on October 6, 2021.
Unit 2 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.
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 on-site activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP
===71152, Problem Identification and Resolution, 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01)===
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
'B' Train Residual Heat Removal (RH) while 1A RH was out of service as set forth in Work Order (WO) 4965525 on July 31, 2021 (2)
'B' Train Containment Spray (CS) system prior to testing on 'A' Train as set forth in WO 5164582 on September 4, 2021
- (3) RH system during reduced inventory on September 14, 2021
- (4) Emergency Diesel Generator (EDG) during reduced inventory or when reloading fuel on September 23 and 24, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Spent Fuel Pool (SFP) during core offload on September 13, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (10 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 (FZs) 11.1A-0, 11.1B-0: Units 1 and 2 Essential Service Water (SW)
Pump Rooms during the week of July 24, 2021
- (2) FZs 11.2-0 W, 11.2-0 SW, 11.2-0 S, 11.2-0 N: Auxiliary Building, general areas, elevation 346' and 364' during the week of July 25, 2021
- (3) FZs 9.1-1, 9.2-1, 9.3-1, 9.4-1: Auxiliary Building 1A and 1B EDG and Day Tank Rooms, elevation 401' -0" during the week ending August 21, 2021
- (4) FZ 8.6-0: Turbine Building, elevation 451' during hot work on September 16, 2021
- (5) FZ 11.4A-1: 1B Auxiliary Feedwater (AF) during hot work on September 17, 2021
- (6) SFP area during refueling during the week ending September 18, 2021
- (7) Unit 1 Containment Outer Missile Barrier during the week of September 19, 2021
- (8) Unit 1 Containment Inner Missile Barrier during the week of September 19, 2021
- (9) FZ 11.4-0 N: Auxiliary Building, general area, elevation 383', on September 29, 2021
- (10) FZ 5.6-1: Unit 1, Auxiliary Building Division 11, Miscellaneous Electrical Equipment and Battery Room, elevation 451', on September 29, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Units 1 and 2 SW pump rooms and Auxiliary Building general areas, elevation 346' and 364' during the week ending July 24, 2021
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk significant piping system boundaries, and containment boundary were appropriately monitored for degradation and repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from September 13, 2021 to September 24, 2021:
03.01.a - Nondestructive Examination and Welding Activities.
Ultrasonic (UT) examination of Reactor Pressure Vessel (RPV) closure studs, 1RC-01-R/S19-S36
UT examination of auxiliary feedwater pipe to tee weld 1AF02DA-4/C04
UT examination of reactor coolant system pipe to elbow weld 1RC05AB-6/J02
UT examination of reactor coolant system elbow to pipe weld 1RC05AB-6/J03
UT examination of reactor coolant system pipe to elbow weld 1RC05AB-6/J04
UT examination of reactor coolant system pipe to elbow weld 1RC04AB-12/J03
UT examination of reactor coolant system elbow to pipe weld 1RC04AB-12/J04
UT examination of reactor coolant system pipe to elbow weld 1RC04AB-12/J05
Visual Examination (VT-3) of main steam system pipe support 1MS07AA-28/1MS01205X
Pressure boundary field weld of 1SXB7A (Work Order 4892348)03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
Bare Metal Visual (BMV) examination of the RPV upper head penetrations
Liquid Penetrant (PT) examination of embedded flaw repair on the reactor vessel head, Control Rod Drive (CRD) Nozzle 31 and 43 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
Boric Acid Leakage Evaluation on Component ID 1RC8037B (Issue Report 04326596)
Boric Acid Leakage Evaluation on Component ID 1CV8548A (Issue Report 04323827)
Boric Acid Leakage Evaluation on Component ID 1SI8878C (Issue Report 04324941)
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) Various activities involving on-watch operations crews. These activities included, but were not limited to:
Backshift in Control Room on August 21, 2021
Down power from 40 percent to 10 percent for shutdown on September 12, 2021
Reactor start up and low power physics testing on September 30, 2021
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated Licensed Operator Requalification Training in the simulator on August 3, 2021
- (2) The inspectors observed and evaluated Licensed Operator Requalification Training in the simulator on August 10, 2021.
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) Maintenance effectiveness and performance history review of fuel cooling on September 17, 2021
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) Maintenance effectiveness and performance history review of Commercial Grade Dedications and Periodic Evaluations on July 22, 2021
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) Low Pressure Turbine Rotor Lift during the week ending September 11, 2021
- (2) Emergent new fuel inspection on September 13, 2021
- (3) Risk during offloading and at reduced inventory on September 17, 2021
- (4) Unit 2 risk management while connected electrically to Unit 1 on September 17, 2021
- (5) Flex configuration during reduced inventory on September 17, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)2CV178 needs to be in auto as documented in Issue Report (IR) 04421309 on July 1, 2021
- (2) Evaluation of the operability of 0XR-EM013; Seismic Recorder error, "Error Light Blinking Once Every One Second," as documented in IR 4433017 on July 11, 2021
- (3) Operability of the 1A EDG as documented in IR 4436890, "Oil Temp," and IR 4437469, Cylinder 2L Air Leak," on July 31, 2021
- (4) Evaluation of the functionality of the 0A Fire Pump with the recirculation valve failed shut on August 8, 2021
- (5) Evaluation of the 0B Diesel Driven Fire Pump degraded performance on September 1, 2021
- (6) Evaluation of 1SXA9A; Low UT as documented in IR 4446351 on September 24, 2021
- (7) Evaluation of 1SI8806B; Motor Actuator Separation as documented in IR 4446576 on September 24, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering Change (EC) 631322; 15XE5A-3' SX piping replacement with stainless steel on August 17, 2021
- (2) EC 632047; Unit 1 Pressure and Temperature Limits Report Revision - Implement changes to Low-Temperature Overpressure Protection (LTOP) Settings on September 24, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (12 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
(1)1B EDG following outage maintenance as documented in IR 4438077 on July 17, 2021 (2)0B SX makeup pump on August 14, 2021 (3)1SI8813; Motor Operated Valve (MOV) stroke as set forth in WO 4704699, 1RH8702A as set forth in WO 5020478-03, and 1MS01A Main Steam Isolation Valve as set forth in WO 5024053 on September 20, 2021 (4)1BOSR 8.1.11-2; 1B EDG Sequencer Test as set forth in WO 5020736 on September 21, 2021 (5)1SX01PB; Unit 1 B SX Pump following coupling work as set forth in WO 1893885 on September 20, 2021 (6)1CV01PB; B Charging Pump as set forth in WOs 5020399, 5020589, 5020679,
===5020680, and 5020830 on September 21, 2021
- (7) Hi-Pot Test as set forth in WO 1874339-04 on September 20, 2021
- (8) Local Leak-Rate Testing of Emergency Airlock and 1RF055 Relief Valve testing on September 24, 2021
- (9) Unit 1 Containment Floor Drain Sumps Narrow Range Level Loops Calibration on September 24, 2021
- (10) Reactor Containment Fan Cooler on September 28, 2021 (11)1B AF Pump on September 30, 2021
- (12) Low Physics Testing on September 30, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01)===
- (1) The inspectors evaluated Unit 1 refueling outage B1R24 activities from September 17 to October 1, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)0BOSR 7.9.6-2; SW Makeup Pump 0B Monthly Operability Surveillance as set forth in WO 5163096 on July 17, 2021
- (2) Comprehensive testing of the 0B SX Makeup Pump during the week ending August 14, 2021 (3)1A EDG Monthly Start on August 31, 2021 (4)2A CV pump ASME testing on September 1, 2021 (5)1BOSR 5.5.8.SX.5-1C as set forth in WO 5162416 on September 5, 2021
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Nuclear Electric Insurance Limited (NEIL) 5151715; 2RH01PB Group A Inservice Test (IST) Requirements for RH Pump during the week ending July 24, 2021
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Local leak-rate test of 1RY8033 and 1RY8047 on September 17, 2021
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) HL130M; Low Head Flex Pump as set forth in WO 5076731, test aborted as documented in IR 4434915 on July 11, 2021 and 0BOSR FX-A1, High Head Flex Pumps 0FX02PB and 02PC as set forth in WOs 5083762 and 5083761 July 17 through July 31, 2021
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes:
Eval No. 20-72 Emergency Action Levels for Byron Station, EP-AA-1002, Addendum 3
Eval No. 20-81 Byron Station Radiological Emergency Plan This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) DEP Evaluated Scenario on August 3,
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)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) The inspectors reviewed the following:
Radiation Work Packages
BY-1-21-00613; Reactor Head Disassembly
BY-1-21-00616; Reactor Coolant Pump (RCP) Maintenance Activities
BY-1-21-00647; Control Rod Drive Mechanism (CRDM) Inspection - Prep and PT Electronic Alarming Dosimeter Alarms
Dose Rate Alarm 09/14/2021 19:06
Dose Rate Alarm 08/11/2021 09:53
Dose Rate Alarm 09/21/2020 18:30
Dose Rate Alarm 07/09/2020 18:09 Labeling of Containers
Five 20' Sealand Containers
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) Observed workers exiting the radiologically controlled area (RCA) at Auxiliary Building 401' during the Unit 1 refueling outage
- (2) Observed workers exiting the RCA at Contractors Access Facility during the Unit 1 refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) Observed activities associated with Radiological Work Package BY-1-21-00613 "Reactor Head Disassembly Reassembly"
- (2) Observed activities associated with Radiological Work Package BY-1-21-00614 "Reactor Head Lifts"
- (3) Observed activities associated with Radiological Work Package BY-1-21-00647 "Reactor Head Penetration 31/43 Preparation and Penetrant Testing"
- (4) Observed activities associated with Radiological Work Package BY-1-21-00616 "Reactor Coolant Pump Maintenance Activities" 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) Radwaste Building 609' Liner and Dry Active Waste Storage Facilities
- (2) Radwaste Building 609' Liquid Radwaste Processing Area
- (3) Unit 1 Containment 377' Inside the 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
71124.02 - Occupational ALARA Planning and Controls
Radiological Work Planning (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensees radiological work planning. The inspectors reviewed the following activities:
- (1) RWP BY 1-21-00616; Reactor Coolant Pump Maintenance Activities
- (2) RWP BY 2-20-00505; Auxiliary Building/Containment Scaffold
- (3) RWP BY-1-20-00613; Reactor Head Dis-Assembly/Re-Assembly Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (3 Samples)
The inspectors evaluated dose estimates, exposure tracking, and the associated radiological outcome evaluation.
- (1) RWP BY 2-20-00505; Auxiliary Building/Containment Scaffold
- (2) RWP BY-1-20-00613; Reactor Head Dis-Assembly/Re-Assembly
- (3) RWP BY 1-20-00616; Reactor Coolant Pump Maintenance Activities
Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (4 Samples)
The inspectors reviewed as low as reasonably achievable practices and radiological work controls. The inspectors reviewed the following activities:
- (1) RWP BY-1-21-00616; Reactor Coolant Pump Maintenance Activities and Associated ALARA Plans
- (4) RWP BY-1-21-00647; Reactor Head Penetration 31/43 Preparation and Penetrant Testing and Associated ALARA Plans
Radiation Worker Performance (IP Section 03.04) (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician performance during:
- (1) Reactor Dis-Assembly
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (2 Samples)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
(1)0A Control Room (VC)
(2)0A and OB Fuel Handling Building (FHB)
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) HEPA filtration units associated with the reactor head stand in Unit 1 Containment
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
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
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
& Transportation
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
- (1) Inspectors walked down accessible portions of the solid radioactive waste systems located on the 609' of the Radwaste Building. The inspectors evaluated system configuration and functionality.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) Unit 1 (July 1, 2020-June 30, 2021)
- (2) Unit 2 (July 1, 2020-June 30, 2021)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2020-June 30, 2021)
- (2) Unit 2 (July 1, 2020-June 30, 2021)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (July 1, 2020-June 30, 2021)
- (2) Unit 2 (July 1, 2020-June 30, 2021)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) Potential Adverse Trend in Work Package Completion
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)0B SX Makeup Pump on August 19, 2021
INSPECTION RESULTS
URI Main Steam Safety Valve Room Structural Acceptance Criteria URI 05000454,05000455/2021011-03 71111.21M
Description:
Calculation No. 5.6.3, "Safety Valve Room Analysis and Design", Revision 5, evaluated the valve room concrete wall and slab sections for load combinations including compartment pressurization due to a main steam line break. In parts of the calculation, an acceptance limit of Fy (yield strength = 60 ksi) was used for checking adequacy of the reinforcing steel, while in other parts of the same calculation as well as in other similar calculations, a more restrictive limit of 0.9Fy (= 54 ksi) was used. The URI was opened due to a concern whether the use of Fy limit provided adequate margin consistent with the design basis. For the URI closure, inspectors reviewed the licensee response to the questions and independently reviewed the applicable parts of the UFSAR as well as the design code.
UFSAR Section 3.8.4, Other Seismic Category I Structures, is applicable to the Safety Valve Room structural design. Section 3.8.4.5.1 which describes the Structural Acceptance Criteria for reinforced concrete design states, in part, that the stresses and strains of various structural components are based on the ultimate strength design provisions in ACI-318 and that the margin of safety is contained in the capacity reduction factor (denoted by Greek letter "phi") specified in the code. It also states that the Byron/Braidwood Stations comply with portions of ACI-349 which are based on ACI 318. ACI-318 editions listed under Table 3.8-2 are 71, 77, and 83. A review of the calculation showed that the moment capacities of concrete sections were checked based on factored loads using the principles and method described in the ACI 318 code and the required margin was provided by increasing the factored loads to account for the capacity reduction factor (phi = 0.9). Methodologies described in the ACI-318 and the ACI-349 require use of steel yield strength combined with a limiting concrete strain of
.003 for determination of the concrete section moment capacity.
Application of another 0.9 factor to Fy was therefore redundant but conservative. It was not included in the original calculations but was used in some instances during updates of certain sections. It was also noted that a
.9 Fy limit is specified in the UFSAR for design of
containment and internal structures and that may have caused the inconsistency. Based on the above discussion, it is concluded that the use of Fy as limiting steel stress in the subject calculation is consistent with the design basis and therefore this URI is closed without identification of any finding or violation.
Enforcement Discretion Enforcement Action EA-21-143: Failure to Comply with 10 CFR Part 37 71124.08
Description:
On April 27, 2016, the licensee was issued NRC Inspection Report Nos. 05000454/2016406 and 05000455/2016406, which documented a licensee identified violation of 10 CFR Part 37, Physical Protection of Category 1 and Category 2, Quantities of Radioactive Material at Facilities with a 10 CFR Part 73, Physical Protection Program. The violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM)14-001, "Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52."
Subsequently, the inspectors re-evaluated this activity and found that while a violation of regulatory requirements continues to exist, the conditions remain within the criteria for enforcement discretion established within EGM 14-001.
Corrective Actions: As specified in EGM 14-001, the application of discretion is authorized until the underlying technical issue is dispositioned through rulemaking or other regulatory action. Additional corrective actions are not required.
Corrective Action References: Not Applicable.
Enforcement:
Violation: On April 27, 2016 a violation of 10 CFR Part 37 was documented in Byron Inspection Report Nos. 05000454/2016406 and 05000455/2016406. The inspectors determined that the previously identified violation remains.
Basis for Discretion: This violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM) 14-001, "Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52."
Observation: Thermal Sleeves 71152 The inspectors performed a detailed review of IR 4447364; B1R24 CRDM Thermal Sleeve Metrology and VT-1 Exam 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 CRDM 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 Fall Unit 1 2021 outage versus the NSAL-20-1 lowering criteria. In addition, the licensee performed an evaluation of the thermal sleeve at penetration 30 and 34 which lowered beyond the NSAL-20-1 lowering criteria. VT-1 visual examinations were performed on Penetrations 30, 34, 37, and 35 in accordance with NSAL-20-1 criteria. No recordable or relevant indications (i.e., cracking) were identified.
Also, the licensee performed an evaluation of the wear before complete flange separation occurs for Penetrations 30 and 34 and the PWROG-16003-P, Revision 2 acceptance criteria was met. The inspectors reviewed the evaluations and consulted with technical staff from the Office of Nuclear Reactor Regulation (NRR). No findings or violations were identified.
Observation: Vulnerability in post-maintenance testing related to the 0B Essential Service Water Makeup Pump 71152 On August 12, 2021, the NRC observed 0B Essential Service Water Makeup Pump testing. The pump was declared inoperable for testing at 1124; TS 3.7.9 Action Condition F was entered for 0BOSR 7.9.6-2, Essential Service Water Makeup Pump 0B Monthly Operability Surveillance and 0BOSR 5.5.8.SX.5-2c, Unit 0 Comprehensive IST Requirements for Essential Service Water Makeup Pump 0B. During the comprehensive, final part of the test, gearbox oil temperature indication was steadily increasing. The field operators reported the condition to the control room. The rising indication was then closely monitored as the test was completed. The indication came within 8 degrees of its limit. The tests were annotated as "Complete Sat," and Condition F was exited at 1303.
Due to crediting a safety related test with an uncertain temperature indication, the inspectors reviewed the licensees recent CAP products related to 0TE-SX178B, Essential Service Water Makeup Pump Gear Oil RTD. Instrument problems were documented in 4259629 and 4339213, from 2019 and 2020 respectively. Subsequently, the element was replaced in 2019, but the old RTD was tested and found to work normally. The issue from 2020 was closed to a work request. Following the August test, the licensee initiated 4440377 and prompted an existing work order, 5002723 to effect repair. Workers found and cleaned a high resistance connection for 0TE-SX178B. Additionally, they replaced the failed open 0TE-SX177B Essential Service Water Makeup Pump Water RTD. Post-maintenance testing was only an instrument calibration.
In the observed test, the faulty gearbox oil temperature readings were taken in support a GL 89-13 commitment. The related CAP review suggests that a timelier resolution of this problem could have resulted had the licensee perform a more comprehensive investigation and assessment of the 2019 and 2020 issues. There were no findings or violations of NRC requirements identified in the course of this review.
Observation: Potential Adverse Trend in Work Package Completion 71152 The inspectors performed a semi-annual review of the licensee's corrective action program over six months for adverse trends in work package completion.
-
4413082 NRC ID: Improper Work Order Closure 3/31/2021 (8 ACITs)
-
4413530 NRC ID: Incorrect Megger Calculations, 4/1/2021 (2 MREQs)
-
4423176 Three taped joints not repaired during SAT 242-2 Outage, 5/12/2021 (2 ACITs, HURB, & ANLY)
-
4428225 Fabricated Clamp not Inspected, 6/8/2021 (ACIT, HURB, & ANLY)
-
4430638 NRC ID: Sign offs missing in 1 AF-018 Loop Cal Package, 6/21/2021 (6 ACITs, HURB, & PCRA)
-
4438077 NRC 1D: 1B EDG Flex Coupling PM Credited Incorrectly, 7/30/2021 (3 ACITs)
The licensee has identified a related trend and entered it into their CAP as 4431360, Trend Identified in Maintenance Work Package Closure Gaps. The inspectors determined the licensee appropriately followed their corrective action process and did not identify any significant trends that might indicate the existence of a more significant safety concern. While none of these issues individually rose to the level of being documented as a finding, taken in aggregate the inspectors found that they could suggest a generic level of distraction within the licensee's workforce as it relates to quality checks of work package completion.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 12, 2021, the inspectors presented the integrated inspection results to Mr. J. Kowalski, Site Vice President, and other members of the licensee staff.
On August 23, 2021, the inspectors presented the URI Closure - 05000454, 05000455/ 2021011-03 inspection results to Mr. J. Kowalski, Site Vice President, and other members of the licensee staff.
On September 24, 2021, the inspectors presented the Byron Unit 1 ISI inspection results to Mr. J. Kowalski, Site Vice President, and other members of the licensee staff.
On September 30, 2021, the inspectors presented the radiation protection baseline inspection results to Ms. L. Zurawski, Regulatory Assurance Manager, and other members of the licensee staff.
On October 1, 2021, the inspectors presented the EPlan and EAL Change Inspection Exit inspection results to Mr. D. Moore, Senior Manager, Emergency Preparedness, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
BOP CS-E1B
Containment Spray System Train "B" Electrical Lineup
BOP CS-M1B
Containment Spray System Train "B" Valve Lineup
BOP RH-M1B
Train "B" Residual Heat Removal System Valve Lineup
BOP-FC-E1
Fuel Pool Cooling System Electrical Lineup
2/06/1985
BOP-FC-M1
Fuel Pool Cooling System Valve Lineup
05/21/2001
Procedures
BOP-FC-T2
Fuel Cooling System One Line Diagram
11.2-0 N
Pre-Fire Plan Auxiliary Building 346-0 Elevation
General Area North FZ 11.2-0 North, Plan #102
11.2-0 NW
Pre-Fire Plan Auxiliary Building 346-0 Elevation
General Area Northwest FZ 11.2-0 Northwest,
Pre-Fire Plan #98
11.2-0 S
Pre-Fire Plan Auxiliary Building 346-0 Elevation
General Area South FZ 11.2-0 South, Plan #99
11.2-0 SW
Pre-Fire Plan Auxiliary Building 346-0 Elevation
General Area Southwest FZ 11.2-0 Southwest, Plan #100
11.2-0 W
Pre-Fire Plan Auxiliary Building 346-0 Elevation
General Area West FZ 11.2-0 West, Plan #101
PFP AB1 383-0
FZ 11.4A-1
Aux. Bldg. 383-0 Elev. Unit 1 1b Aux. Diesel Feedwater
Pump and Day Tank Room
PFP CNMT1 377-
FZ 1.1-1
Pre-Fire Plan Containment Building Unit 1 377-0 Elevation
Missile Shield Area FZ 1.1-1
PFP CNMT1 377-
FZ 1.2-1
Pre-Fire Plan Containment Building Unit 1 377-0 Elevation
Annular Area FZ 1.2-1
PFP CNMT1 401-
FZ 1.1-1
Pre-Fire Plan Containment Building Unit 1 401-0 Elevation
Missile Shield Area FZ 1.1-1
PFP CNMT1 401-
FZ 1.2-1
Pre-Fire Plan Containment Building Unit 1 401-0 Elevation
Annular Area FZ 1.2-1
PFP CNMT1 426-
FZ 1.3-1
Pre-Fire Plan Containment Building Unit 1 426-0 Elevation
Upper Area FZ 1.3-1
PFP FZ 11.1A-0
Aux. Bldg. 330'-0" Elev. Unit 1 Essential Service Water
Pump Rm
Fire Plans
PFP FZ 11.1B-0
Aux. Bldg. 330'-0" Elev. Unit 2 Essential Service Water
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Pump Rm
FPR Ch. 2.3.11
Fire Area Analysis for Auxiliary Building Basement
Miscellaneous
FPR Fig. 2.3-16
Essential Service Water Pump Room
Work Orders
04838070-14
Flood Seal Covers 1DSFS007+09 AF Tunnel Outage
Inspection
03/25/2020
4437794
NRC Questions on Flooding Design Basis
07/29/2021
Corrective Action
Documents
Resulting from
Inspection
4438035
Additional NRC Questions on Flooding Design Basis
07/30/2021
Confirmation of Safe Shutdown Capability After Auxiliary
Building Flooding
2/17/2014
Auxiliary Building Flood Level Calculations
07/17/1997
BB-PRA-012
Byron and Braidwood Probabilistic Risk Assessment:
Internal Flood Evaluation Summary Notebook
November
2019
Engineering
Evaluations
BB-PRA-014
Byron/Braidwood Probabilistic Risk Analysis Quantification
Notebook
BB019A
Procedures
0BOA PRI-8
Auxiliary Building Flooding, Unit 0
01860257-01
1DSFS006/08 Outage Flood Seals Surveillance
03/03/2017
01915060-01
2DSFSO 06/08 Outage Flood Seals Surveillance
10/08/2017
Work Orders
05079981-01
Watertight Door Inspection
03/18/2021
Corrective Action
Documents
4397488
Previous IWL Sample Sizes Not IAW ASME IWL Code
Requirements
01/22/2021
4446714
NRC ID Repair/Replacement Plan #04930998-01 Deficiency
09/16/2021
Corrective Action
Documents
Resulting from
Inspection
4447959
B1R24-NRC Information Request
09/22/2021
Miscellaneous
50.59 Screening
BRW-S-2006-18 /
Revision of UFSAR Section 3.6.2. 1.2.1.2.2 e
(ATI 429821-01)
Liquid Penetrant (PT) Examination
VT-3 Visual Examination of Components, Supports,
Attachments and Interiors of Reactor Vessels
Ultrasonic Examination of Ferritic Piping Welds
Procedures
Ultrasonic Examination of Stud and Bolts
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Bare Metal Visual Examination for Nickel Alloy Materials
PDI-UT-1
Generic Procedure for Ultrasonic Examination of Ferritic Pipe
G
PDI-UT-5
Generic Procedure for the Straight Beam Ultrasonic
Examination of Bolts and Studs
G
4892348
Generate WO to Repair Flaw in 1SXB7A
10/28/2019
Work Orders
4930998
1SD002A High Flow on SLT
09/30/2019
04373331
Evidence of Water in 2FC04F Vault
09/30/2020
04406737
Dual Core Offload Will Not Meet B.5.b Dispersal Guidelines
03/05/2021
4390608
Spent Fuel Pool System Health Review
2/16/2020
4391128
Active Leak Identified in 2FC04F Vault
2/18/2020
4391132
Standing Water in 0FC01F Vault
2/18/2020
4403670
Unit 2 Spent Fuel Pool Filter DP High
2/20/2021
4406587
NRC ID: Boric Acid Buildup on 0PI-FC006
03/04/2021
4415802
2PI-0630 Reading Erratic
04/12/2021
21152
Inactive Boric Acid Leak at Pipe Cap on 1FC024
04/29/2021
27038
Rising D/P on 1FC04F
06/02/2021
Corrective Action
Documents
4437370
1FC8764A Spraying Water
07/27/2021
00055783
PE Evaluation Safety Basis for Commercial Grade
Dedication of Pall 0.45 Micron Filter Cartridge CAT
ID 0000678367-2
213407
PE Evaluation Safety Basis Commercial Grade Dedication
and Item Equivalency Evaluation for Secondary Fuel Filter
for Auxiliary Fuel Pump Diesel
245708
PE Evaluation Safety Basis and Commercial Grade
Dedication for Ultra Low Sulfur Diesel Fuel Oil Winter Blend
of 25% Grade 1 and 75% Grade 2
Engineering
Evaluations
258274
PE Evaluation Extend CID 1451775-1 to 1AF026A and
1AF026B and Item Equivalency Evaluation for the 2" Check
Valve Cat ID 0001451775-1
Quality Receipt Inspection Package 273564 Fuel Diesel
Blend of 75% Grade 2 and 25% Grade 1
2/22/2021
Miscellaneous
Quality Receipt Inspection Package 263072 Element Filter
Secondary
2/30/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Quality Receipt Inspection Package 269107 Filter Cartridge
EPR Rubber O-Ring 0.45-Micron for Seal
07/09/2020
Procedures
Procurement Engineering Support Activities
05041922-19
Install Reactor Vessel Head per BMP 3118-7
09/20/2021
Work Orders
05187937-04
1SI8856A IST Relief Valve Test
09/20/2021
Shutdown Reactor Coolant System Makeup, Unit 1
BOP RC-4
Reactor Coolant System Drain
Contingency Plan #2--Flex Strategy During Short Top of
Active Fuel Periods for B1R24
07/26/2021
Procedures
New Fuel Receipt and Inspection for Byron, Braidwood, and
Ginna
2644403
0B Diesel Driven Fire Pump Performance
03/23/2016
256789
0B Fire Pump Failed Flow and Pressure Test
06/13/2019
4436890
07/25/2021
4437469
1A DG Cylinder 2L Air Leak
07/28/2021
4443810
0B Diesel Driven Fire Pump Declining Performance Trend
08/30/2021
4446351
Low Ultrasonic Test Reading on Pre-Freeze for 1SXA9A
09/14/2021
Corrective Action
Documents
4446576
1SI8806 Motor Operated Valve Motor Separating from
Actuator
09/15/2021
Engineering
Evaluations
Minimum Wall Evaluation for Freeze on 1SXA9A-6"
09/15/2021
Work Orders
4935003-02
Fire Protection Pump Flow and Pressure Test
07/29/2020
4401524
Implementation of PTLR License Amendment Request and
2/10/2021
Corrective Action
Documents
27059
EC 632047, Activities Related to Unit 1 Pressure and
Temperature Limits Report Revision
06/02/2021
Engineering
Changes
2047
Unit 1 Pressure and Temperature Limits Report (PTLR)
Revision-Implement Changes to LTOPS Setpoints,
Heatup/Cooldown Curves, and Documentation Due to
PTLR Revision
09/03/2021
4330492
Gauge Pegged High
03/29/2020
4342341
1FI-SX042 1B SX Cub Clr Outlet Flow Ind Inaccurate
05/10/2020
Corrective Action
Documents
4373750
1B SX Pump Cube Cooler Flow indication
10/01/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4384810
Flowmeter Requires Repair for Scheduled Surveillance
11/16/2020
Corrective Action
Documents
Resulting from
Inspection
4438077
NRC ID: 1B EDG Flex Coupling PM Credited Incorrectly
07/30/2021
1BOSR
5.5.8.AF.5-2b
Unit One Group B In-Service Testing (IST) Requirements for
Diesel Driven Auxiliary Feedwater Pump 1AF01PB
1BOSR
5.5.8.SX.5-2c
Unit One Comprehensive In-Service Testing (IST)
Requirements for the Essential Service Water (SX) Pump
1SX01PB And Unit 1 SX Pumps Discharge Check Valves
1BOSR 6.2.1-4
Unit 1 Primary Containment Type B Local Leakage Rate
Test of Emergency Personnel Airlock
1BOSR 7.5.4-2
Unit One Diesel Driven Auxiliary Feedwater Pump Monthly
Surveillance
1BOSR 8.1.11-2
Unit One 1B Diesel Generator Sequencer Test
1BOSR Z.7.a.1
Unit One Auxiliary Feedwater Diesel Engine Starting
Sequence and Overspeed Trip Test
BISR 3.3.2-201
Surveillance Calibration of Containment Water and
Containment Floor Drain Sump Water Level Loops
Post-Maintenance Testing
High Potential Testing
Procedures
MA-BY-725-515
Preventive Maintenance of Non-Segregated Bus Duct
05020425-02
1RF055 IST Relief Valve Test (Pre/Post LLRT)
09/21/2021
05022334
Calibrate 1LT-PC003 Transmitter and Perform
Environmental Qualification Requirements
09/21/2021
1874339-04
LR - EM: 1AP07E-K Electrical Testing of Non-Segregated
Bus
09/20/2021
1893885
Replace Coupling and Align as Required 1SX01PB
09/20/2021
4704699-03
OPS PMT - Stroke Valve 1SI8813
09/20/2021
4942174
Replace Victaulic / Flexible Couplings in DG Jacket Water
06/16/2021
4980773-07
MM Replace 1B DG Exhaust Manifold
01/28/2020
20399-02
OP PMT: Verify Proper Cubicle Cooler Operation
09/21/2021
20402-03
OPS - Perform PIT/STT 1SI8813 (1BOSR 0.5-2.SI.5)
09/20/2021
Work Orders
20478-03
OPS PMT - PIT/Stroke of 1RH8702A
09/19/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20589-03
OPS PMT - Check for Leaks on 1B CV Pump
09/21/2021
20679-02
09/21/2021
20680-02
OP PMT - Visual on Gear Oil Pins and Oil Leaks
09/21/2021
20736
U1 DG Seq Staggered Test Tracking Updated by 163081
and 163082
09/21/2021
20830
4KV Relay Routine Calibration (1B CV Pump)
09/21/2021
22332-01
Calibrate 1LT-PC002 Transmitter and Perform
Environmental Qualification Requirements
09/21/2021
24100-03
09/30/2021
24502
OP 1BOSR 6.6.2-1, U-1 RCFC Surveillance
09/28/2021
24511
Low Power Physics Testing Program Using the W ADRC
09/30/2021
5148010
1BOSR 6.6.2-1, U-1 RCFC Surveillance
09/28/2021
5165336-01
LR-OPS 1BOSR 5.5.8.AF.5-2B - 1B AF Group B Test
09/30/2021
5180895
(NEIL)- 1B AF Pump Surveillance
09/30/2021
4445997
Close Light for 1A MSIV Did Not Lite During STT
09/13/2021
4447690
As Found 1SX311B Plugged With Silt
09/21/2021
4448311
1MS001A Failed Initial STT
09/24/2021
4448437
Unexpected Alarm CNMT Leak Det. Flow High
09/24/2021
4448722
1A MSIV AOP IA Regulator and N2 Pre-Charge
(Both Trains)
09/26/2021
4448767
1FP010 Did Not Open for STT
09/27/2021
4448819
Failed Logic Testing During SSPS
09/27/2021
Corrective Action
Documents
4449021
1A MSIV Showing Dual
09/28/2021
4448004
Tags Plus Not Used
09/22/2021
Corrective Action
Documents
Resulting from
Inspection
4448702
Issues Identified on B1R24 Containment Closeout NRC
Walkdown
09/26/2021
Miscellaneous
B1R24 Shutdown Safety Process Overview
1BGP 100-2A1
Reactor Startup
1BGP 100-5
Plant Shutdown and Cooldown
1BGP 100-6
Refueling Outage
1BOSR 7.2.1-1
Unit One Main Steam Isolation Valve Operability Test
Procedures
1BOSR 7.2.1-
MSIV Acceptance Criteria Data Sheet
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1.BY01
1BOSR Z.5.b.1-1
Unit One Containment Loose Debris Inspection
1BOSR Z.5.b.1-
1T1
Unit One Containment Loose Debris Inspection Data Sheet
BOP RC-9
Filling an Isolated Reactor Coolant Loop, the Pressurizer,
and Drawing a Pressurizer Bubble
BOP RH-9
Pump Down of The Refueling Cavity to the RWST
NF-BY-510
Low Power Physics Test Program
Shutdown Safety Management Program
Byron and Braidwood Refuel Outage Execution Guide
24053-16
MSIV Hot Operability Testing
09/30/2021
25520
Train B SSPS Surveillance
09/27/2021
Work Orders
5190837
1FP010 Did Not Open for STT
09/28/2021
4389841
1A Diesel Generator Tachometer Reading High
2/12/2020
4419373
1A Diesel Generator Jacket Water Lower Cooler Leaking
04/27/2021
Corrective Action
Documents
4436890
1A Diesel Generator Lube Oil Temperature Low
07/25/2021
4434915
Low Head Flex Pump (0MVHL130M-1) Rust Particles in
Coolant
07/14/2021
Corrective Action
Documents
Resulting from
Inspection
4444404
NRC Question About 1A Diesel Generator Upper Lube Oil
Cooler
09/01/2021
0BOSR 7.9.6-2
Essential Service Water Makeup Pump 0B Monthly
Operability Surveillance
0BOSR FX-A1
Flex Pump Annual Flow Surveillance
1BOSR
5.5.8.SX.5-1C
Unit One Comprehensive In-Service Testing (IST)
Requirements for the Essential Service Water (SX) Pump
1SX01PA and Unit 1 SX Pumps Discharge Check Valves
Procedures
1BOSR 6.1.1-11
Primary Containment Local Leak-Rate Tests
5076731
Annual Flex Pump #1 Flow Testing
07/08/2021
5083761
Component Operational Inspection of High Head Flex Pump
07/21/2021
5083762
Component Operational Inspection of High Head Flex Pump
07/21/2021
Work Orders
5162415-1
OPS 2BOSR 5.5.8.CV.5-1A-2A Charging Pump Group A
Test
09/01/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5162416
1BOSR 5.5.8.SX.5-1C 1A SX Comprehensive
09/02/2021
5163096
LR-SX Makeup Pump 0B Operability
07/15/2021
5164599
OPS 0BOSR 5.5.8.SX.5-2C 0B SX Comprehensive
08/12/2021
5171381
LR-0BOSR 7.9.6-2, SX Makeup Pump 0B Monthly
Operability
08/12/2021
5175655-01
1A Diesel Generator Operability and Semi-Annual
Surveillance
08/31/2021
Eval No. 20-72
Emergency Action Levels for Byron Station, EP-AA-1002,
Addendum 3
08/21/2020
Miscellaneous
Eval No. 20-81
Byron Station Radiological Emergency Plan
09/17/2020
RP Tech Received Dose Rate Alarm Responding to RW Spill
07/10/2020
Corrective Action
Documents
Dose Rate Alarm
09/21/2020
Corrective Action
Documents
Resulting from
Inspection
Planned Dose Rate Alarm Documentation Could Not Be
Found
09/17/2021
Miscellaneous
21 Bioassay Program Annual Review at Byron Nuclear
Power Station
03/22/2021
Dosimetry Issue, Usage and Control
Procedures
Determination of Alpha Levels and Monitoring
21-105125
Reactor Coolant Pump C
09/15/2021
21-105127
Reactor Coolant Pump A
09/15/2021
21-105147
Reactor Coolant Pump D
09/15/2021
21-105149
Reactor Coolant Pump B
09/15/2021
Radiation
Surveys
21-105227
Reactor Head for CRDM PT Inspection
09/16/2021
BY-1-20-00505
ALARA Plans, Work in Progress Reviews and Post Job
Evaluation
Various
BY-1-21-00613
Reactor Head Dis-Assembly/ Re-Assembly Radiation Work
Permit and Associated ALARA Plans
BY-1-21-00616
RCP Maintenance Activities - Radiation Work Permit and
Associated ALARA Plans
BY-1-21-00647
CRDM Maintenance -Prep and PT Radiation Work Permit
and Associated ALARA Plans
ALARA Plans
BY-2-20-00505
ALARA Plans and Work in Progress Reviews
Various
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Shielding Extension CC-AA-401
06/11/2020
Corrective Action
Documents
Adverse Dose Trend for Axion/ATF Project
11/20/2020
B2R22 Radiation Protection Refueling Outage Report Fall
20
Undated
SAC #21-013
Station ALARA Committee Agenda - B1R24 - Valves/RXS
07/23/2021
SAC #21-015
Station ALARA Committee (SAC) Agenda -2021 B1R24
Scaffolds
07/27/2021
Miscellaneous
SAC#21-013
Station ALARA Committee Meeting Minutes
07/26/2021
SCBA Monthly Inspections to be Performed with Surrogate
Mask
04/02/2020
SCBA Compressor Cascade Bottle Qualification Discrepancy
06/02/2020
Corrective Action
Documents
SCBA Compressor Out of Service
06/02/2021
Dayshift SRO and RO Respirator Qualifications Including
SCBA for On-Shift Crew September 13, 2021
Various
Unit 1 Alpha Area Level Assessment
06/29/2020
Grade D Service/SCBA Air Analysis
09/01/2021
Third Quarter Respirator and SCBA Inspection Records
Various
Miscellaneous
BY-1-21-00647
TEDE ALARA Evaluation Screening Worksheet for Under
Reactor Head Inspections
09/09/2021
RP-BY-825-1003
Operation, Inspection and Use of the MSA Firehawk M7 Air
Mask Self-Contained Breathing Apparatus (SCBA)
Procedures
RP-BY-825-8703
Operation of the Mako Air Compressor (BAM06H)
04843651-01
OA Control Room Makeup System Charcoal Adsorber Bank
Operability
05/27/2020
Work Orders
04843652-01
Control Room 0A Makeup System HEPA Filter Test - DOP
05/27/2020
Byron Station 10 CFR 37 Security Plan
2/19/2019
CFR 37 Security Plan Training Records for Radiation
Protection Personnel
Various
Training Records for Security Part 37
Various
Miscellaneous
SY-AA-150-101-
F-44
Part 37 Refresher/Security Training
2/27/2019
Corrective Action
Documents
259629
0B SX Makeup Secured Due to Rapidly Rising Gear Box Oil
Temp
06/26/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
27728
Thermal Sleeve at Pen-34 Lowered Beyond Specific Eval
Value
03/18/2020
4339213
0B SX MU Pump Gear Oil Temp Indication/Sensor Possibly
Broke
04/28/2020
4354388
0A SX Make Up Pump Indication Failed
07/02/2020
4440377
0B SX Makeup Pump Gear Box Temperature Indication
08/12/2021
4447364
B1R24 CRDM Thermal Sleeve Metrology a VT and-1 Exam
Results
09/19/2021
631064
B1R23 CRDM Thermal Sleeve Metrology Evaluation
Engineering
Changes
635099
B1R24 CRDM Thermal Sleeve Metrology Evaluation
2-9336720-000
Byron 1 CROM Thermal Sleeve As-Found Dimensional
Report 2021
09/18/2021
Miscellaneous
PWROG-16003-P
Evaluation of Potential Thermal Sleeve Flange Wear
NDE Reports
Byron 1R24 Thermal Sleeve ID Visual Examination
09/19/2021
Work Orders
5002723
Makeup Pump 0B Diesel Temperature Loop 0SX-180B
08/20/2021