IR 05000454/2021003

Integrated Inspection Report 05000454/2021003 and 05000455/2021003 and Exercise of Enforcement Discretion

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: NPF-37 and NPF-66

Report Numbers: 05000454/2021003 and 05000455/2021003

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

Enclosure

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, Main Steam Safety Valve 71111.21M Closed 05000455/2021011-03 Room Structural Acceptance Criteria EDG EA-21-143 Failure to Comply with 71124.08 Closed 10 CFR Part 37

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.

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,

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

(2) RWP BY-1-21-00613; Reactor Head Dis-Assembly/Re-Assembly and Associated ALARA Plans

(3) RWP BY-1-21-00614; Reactor Head Lifts 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

(2) B1R24 CRDM Thermal Sleeve Metrology and VT-1 Exam results on September 19,

INSPECTION RESULTS

URI Main Steam Safety Valve Room Structural Acceptance 71111.21M Criteria URI 05000454,05000455/2021011-03

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 Enforcement Action EA-21-143: Failure to Comply with 10 CFR 71124.08 Discretion Part 37

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 71152 Essential Service Water Makeup Pump 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 Type Designation Description or Title Revision or

Procedure Date

71111.04 Procedures BOP CS-E1B Containment Spray System Train "B" Electrical Lineup 1

BOP CS-M1B Containment Spray System Train "B" Valve Lineup 3

BOP RH-M1B Train "B" Residual Heat Removal System Valve Lineup 13

BOP-FC-E1 Fuel Pool Cooling System Electrical Lineup 02/06/1985

BOP-FC-M1 Fuel Pool Cooling System Valve Lineup 05/21/2001

BOP-FC-T2 Fuel Cooling System One Line Diagram 3

71111.05 Fire Plans PFP AB 346-0 FZ Pre-Fire Plan Auxiliary Building 346-0 Elevation 2

11.2-0 N General Area North FZ 11.2-0 North, Plan #102

PFP AB 346-0 FZ Pre-Fire Plan Auxiliary Building 346-0 Elevation 2

11.2-0 NW General Area Northwest FZ 11.2-0 Northwest,

Pre-Fire Plan #98

PFP AB 346-0 FZ Pre-Fire Plan Auxiliary Building 346-0 Elevation 2

11.2-0 S General Area South FZ 11.2-0 South, Plan #99

PFP AB 346-0 FZ Pre-Fire Plan Auxiliary Building 346-0 Elevation 2

11.2-0 SW General Area Southwest FZ 11.2-0 Southwest, Plan #100

PFP AB 346-0 FZ Pre-Fire Plan Auxiliary Building 346-0 Elevation 2

11.2-0 W General Area West FZ 11.2-0 West, Plan #101

PFP AB1 383-0 Aux. Bldg. 383-0 Elev. Unit 1 1b Aux. Diesel Feedwater 2

FZ 11.4A-1 Pump and Day Tank Room

PFP CNMT1 377-Pre-Fire Plan Containment Building Unit 1 377-0 Elevation 2

FZ 1.1-1 Missile Shield Area FZ 1.1-1

PFP CNMT1 377-Pre-Fire Plan Containment Building Unit 1 377-0 Elevation 2

FZ 1.2-1 Annular Area FZ 1.2-1

PFP CNMT1 401-Pre-Fire Plan Containment Building Unit 1 401-0 Elevation 2

FZ 1.1-1 Missile Shield Area FZ 1.1-1

PFP CNMT1 401-Pre-Fire Plan Containment Building Unit 1 401-0 Elevation 2

FZ 1.2-1 Annular Area FZ 1.2-1

PFP CNMT1 426-Pre-Fire Plan Containment Building Unit 1 426-0 Elevation 2

FZ 1.3-1 Upper Area FZ 1.3-1

PFP FZ 11.1A-0 Aux. Bldg. 330'-0" Elev. Unit 1 Essential Service Water 2

Pump Rm

PFP FZ 11.1B-0 Aux. Bldg. 330'-0" Elev. Unit 2 Essential Service Water 2

Inspection Type Designation Description or Title Revision or

Procedure Date

Pump Rm

Miscellaneous FPR Ch. 2.3.11 Fire Area Analysis for Auxiliary Building Basement 29

FPR Fig. 2.3-16 Essential Service Water Pump Room 22

Work Orders 04838070-14 Flood Seal Covers 1DSFS007+09 AF Tunnel Outage 03/25/2020

Inspection

71111.06 Corrective Action 4437794 NRC Questions on Flooding Design Basis 07/29/2021

Documents 4438035 Additional NRC Questions on Flooding Design Basis 07/30/2021

Resulting from

Inspection

Engineering 3C8-0787-001 Confirmation of Safe Shutdown Capability After Auxiliary 12/17/2014

Evaluations Building Flooding

3C8-1281-001 Auxiliary Building Flood Level Calculations 07/17/1997

BB-PRA-012 Byron and Braidwood Probabilistic Risk Assessment: November

Internal Flood Evaluation Summary Notebook 2019

BB-PRA-014 Byron/Braidwood Probabilistic Risk Analysis Quantification BB019A

Notebook

Procedures 0BOA PRI-8 Auxiliary Building Flooding, Unit 0 5

Work Orders 01860257-01 1DSFS006/08 Outage Flood Seals Surveillance 03/03/2017

01915060-01 2DSFSO 06/08 Outage Flood Seals Surveillance 10/08/2017

05079981-01 Watertight Door Inspection 03/18/2021

71111.08P Corrective Action 4397488 Previous IWL Sample Sizes Not IAW ASME IWL Code 01/22/2021

Documents Requirements

Corrective Action 4446714 NRC ID Repair/Replacement Plan #04930998-01 Deficiency 09/16/2021

Documents 4447959 B1R24-NRC Information Request 09/22/2021

Resulting from

Inspection

Miscellaneous 50.59 Screening Revision of UFSAR Section 3.6.2. 1.2.1.2.2 e 0

BRW-S-2006-18 / (ATI 429821-01)

6E-06-0116

Procedures ER-AA-335-002 Liquid Penetrant (PT) Examination 12

ER-AA-335-016 VT-3 Visual Examination of Components, Supports, 13

Attachments and Interiors of Reactor Vessels

ER-AA-335-030 Ultrasonic Examination of Ferritic Piping Welds 5

ER-AA-335-037 Ultrasonic Examination of Stud and Bolts 4

Inspection Type Designation Description or Title Revision or

Procedure Date

ER-AP-335-001 Bare Metal Visual Examination for Nickel Alloy Materials 8

PDI-UT-1 Generic Procedure for Ultrasonic Examination of Ferritic Pipe G

Welds

PDI-UT-5 Generic Procedure for the Straight Beam Ultrasonic G

Examination of Bolts and Studs

Work Orders 4892348 Generate WO to Repair Flaw in 1SXB7A 10/28/2019

4930998 1SD002A High Flow on SLT 09/30/2019

71111.12 Corrective Action 04373331 Evidence of Water in 2FC04F Vault 09/30/2020

Documents 04406737 Dual Core Offload Will Not Meet B.5.b Dispersal Guidelines 03/05/2021

4390608 Spent Fuel Pool System Health Review 12/16/2020

4391128 Active Leak Identified in 2FC04F Vault 12/18/2020

4391132 Standing Water in 0FC01F Vault 12/18/2020

4403670 Unit 2 Spent Fuel Pool Filter DP High 02/20/2021

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

4437370 1FC8764A Spraying Water 07/27/2021

Engineering 00055783 PE Evaluation Safety Basis for Commercial Grade

Evaluations 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

258274 PE Evaluation Extend CID 1451775-1 to 1AF026A and

1AF026B and Item Equivalency Evaluation for the 2" Check

Valve Cat ID 0001451775-1

Miscellaneous Quality Receipt Inspection Package 273564 Fuel Diesel 02/22/2021

Blend of 75% Grade 2 and 25% Grade 1

Quality Receipt Inspection Package 263072 Element Filter 12/30/2019

Secondary

Inspection Type Designation Description or Title Revision or

Procedure Date

Quality Receipt Inspection Package 269107 Filter Cartridge 07/09/2020

EPR Rubber O-Ring 0.45-Micron for Seal

Procedures SM-AA-300 Procurement Engineering Support Activities 9

Work Orders 05041922-19 Install Reactor Vessel Head per BMP 3118-7 09/20/2021

05187937-04 1SI8856A IST Relief Valve Test 09/20/2021

71111.13 Procedures 1BFSG-14 Shutdown Reactor Coolant System Makeup, Unit 1 1

BOP RC-4 Reactor Coolant System Drain 25

OU-AA-103, Contingency Plan #2--Flex Strategy During Short Top of 07/26/2021

Active Fuel Periods for B1R24

OU-AP-201 New Fuel Receipt and Inspection for Byron, Braidwood, and 18

Ginna

71111.15 Corrective Action 2644403 0B Diesel Driven Fire Pump Performance 03/23/2016

Documents 4256789 0B Fire Pump Failed Flow and Pressure Test 06/13/2019

4436890 1A DG Lube Oil Temp Low 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

4446576 1SI8806 Motor Operated Valve Motor Separating from 09/15/2021

Actuator

Engineering EC 645075 Minimum Wall Evaluation for Freeze on 1SXA9A-6" 09/15/2021

Evaluations

Work Orders 4935003-02 Fire Protection Pump Flow and Pressure Test 07/29/2020

71111.18 Corrective Action 4401524 Implementation of PTLR License Amendment Request and 02/10/2021

Documents Exemption Request

27059 EC 632047, Activities Related to Unit 1 Pressure and 06/02/2021

Temperature Limits Report Revision

Engineering 632047 Unit 1 Pressure and Temperature Limits Report (PTLR) 09/03/2021

Changes Revision-Implement Changes to LTOPS Setpoints,

Heatup/Cooldown Curves, and Documentation Due to

PTLR Revision

71111.19 Corrective Action 4330492 Gauge Pegged High 03/29/2020

Documents 4342341 1FI-SX042 1B SX Cub Clr Outlet Flow Ind Inaccurate 05/10/2020

4373750 1B SX Pump Cube Cooler Flow indication 10/01/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

4384810 Flowmeter Requires Repair for Scheduled Surveillance 11/16/2020

Corrective Action 4438077 NRC ID: 1B EDG Flex Coupling PM Credited Incorrectly 07/30/2021

Documents

Resulting from

Inspection

Procedures 1BOSR Unit One Group B In-Service Testing (IST) Requirements for 10

5.5.8.AF.5-2b Diesel Driven Auxiliary Feedwater Pump 1AF01PB

1BOSR Unit One Comprehensive In-Service Testing (IST) 12

5.5.8.SX.5-2c 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 19

Test of Emergency Personnel Airlock

1BOSR 7.5.4-2 Unit One Diesel Driven Auxiliary Feedwater Pump Monthly 34

Surveillance

1BOSR 8.1.11-2 Unit One 1B Diesel Generator Sequencer Test 33

1BOSR Z.7.a.1 Unit One Auxiliary Feedwater Diesel Engine Starting 6

Sequence and Overspeed Trip Test

BISR 3.3.2-201 Surveillance Calibration of Containment Water and 11

Containment Floor Drain Sump Water Level Loops

MA-AA-716-012 Post-Maintenance Testing 26

MA-AA-773-045 High Potential Testing 9

MA-BY-725-515 Preventive Maintenance of Non-Segregated Bus Duct 15

Work Orders 05020425-02 1RF055 IST Relief Valve Test (Pre/Post LLRT) 09/21/2021

05022334 Calibrate 1LT-PC003 Transmitter and Perform 09/21/2021

Environmental Qualification Requirements

1874339-04 LR - EM: 1AP07E-K Electrical Testing of Non-Segregated 09/20/2021

Bus

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

20478-03 OPS PMT - PIT/Stroke of 1RH8702A 09/19/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

20589-03 OPS PMT - Check for Leaks on 1B CV Pump 09/21/2021

20679-02 OPS PMT - Run 1B CV PP Motor 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 09/21/2021

and 163082

20830 4KV Relay Routine Calibration (1B CV Pump) 09/21/2021

22332-01 Calibrate 1LT-PC002 Transmitter and Perform 09/21/2021

Environmental Qualification Requirements

24100-03 ST - OPS Verify Adequate Oil 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

71111.20 Corrective Action 4445997 Close Light for 1A MSIV Did Not Lite During STT 09/13/2021

Documents 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 09/26/2021

(Both Trains)

4448767 1FP010 Did Not Open for STT 09/27/2021

4448819 Failed Logic Testing During SSPS 09/27/2021

4449021 1A MSIV Showing Dual 09/28/2021

Corrective Action 4448004 Tags Plus Not Used 09/22/2021

Documents 4448702 Issues Identified on B1R24 Containment Closeout NRC 09/26/2021

Resulting from Walkdown

Inspection

Miscellaneous B1R24 Shutdown Safety Process Overview

Procedures 1BGP 100-2A1 Reactor Startup 36

1BGP 100-5 Plant Shutdown and Cooldown 80

1BGP 100-6 Refueling Outage 54

1BOSR 7.2.1-1 Unit One Main Steam Isolation Valve Operability Test 17

1BOSR 7.2.1-MSIV Acceptance Criteria Data Sheet 0

Inspection Type Designation Description or Title Revision or

Procedure Date

1.BY01

1BOSR Z.5.b.1-1 Unit One Containment Loose Debris Inspection 18

1BOSR Z.5.b.1-Unit One Containment Loose Debris Inspection Data Sheet 7

1T1

BOP RC-9 Filling an Isolated Reactor Coolant Loop, the Pressurizer, 39

and Drawing a Pressurizer Bubble

BOP RH-9 Pump Down of The Refueling Cavity to the RWST 29

NF-BY-510 Low Power Physics Test Program 19

OU-AA-103 Shutdown Safety Management Program 22

OU-AP-200-1001 Byron and Braidwood Refuel Outage Execution Guide 1

Work Orders 5024053-16 MSIV Hot Operability Testing 09/30/2021

25520 Train B SSPS Surveillance 09/27/2021

5190837 1FP010 Did Not Open for STT 09/28/2021

71111.22 Corrective Action 4389841 1A Diesel Generator Tachometer Reading High 12/12/2020

Documents 4419373 1A Diesel Generator Jacket Water Lower Cooler Leaking 04/27/2021

Service Water

4436890 1A Diesel Generator Lube Oil Temperature Low 07/25/2021

Corrective Action 4434915 Low Head Flex Pump (0MVHL130M-1) Rust Particles in 07/14/2021

Documents Coolant

Resulting from 4444404 NRC Question About 1A Diesel Generator Upper Lube Oil 09/01/2021

Inspection Cooler

Procedures 0BOSR 7.9.6-2 Essential Service Water Makeup Pump 0B Monthly 42

Operability Surveillance

0BOSR FX-A1 Flex Pump Annual Flow Surveillance 9

1BOSR Unit One Comprehensive In-Service Testing (IST) 12

5.5.8.SX.5-1C Requirements for the Essential Service Water (SX) Pump

1SX01PA and Unit 1 SX Pumps Discharge Check Valves

1BOSR 6.1.1-11 Primary Containment Local Leak-Rate Tests 12

Work Orders 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

5162415-1 OPS 2BOSR 5.5.8.CV.5-1A-2A Charging Pump Group A 09/01/2021

Test

Inspection Type Designation Description or Title Revision or

Procedure 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 08/12/2021

Operability

5175655-01 1A Diesel Generator Operability and Semi-Annual 08/31/2021

Surveillance

71114.04 Miscellaneous Eval No. 20-72 Emergency Action Levels for Byron Station, EP-AA-1002, 08/21/2020

Addendum 3

Eval No. 20-81 Byron Station Radiological Emergency Plan 09/17/2020

71124.01 Corrective Action AR 04355919 RP Tech Received Dose Rate Alarm Responding to RW Spill 07/10/2020

Documents AR 04371042 Dose Rate Alarm 09/21/2020

Corrective Action AR 04447047 Planned Dose Rate Alarm Documentation Could Not Be 09/17/2021

Documents Found

Resulting from

Inspection

Miscellaneous 2021 Bioassay Program Annual Review at Byron Nuclear 03/22/2021

Power Station

Procedures RP-AA-210 Dosimetry Issue, Usage and Control 32

RP-AA-302 Determination of Alpha Levels and Monitoring 12

Radiation 2021-105125 Reactor Coolant Pump C 09/15/2021

Surveys 2021-105127 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

21-105227 Reactor Head for CRDM PT Inspection 09/16/2021

71124.02 ALARA Plans BY-1-20-00505 ALARA Plans, Work in Progress Reviews and Post Job Various

Evaluation

BY-1-21-00613 Reactor Head Dis-Assembly/ Re-Assembly Radiation Work 0

Permit and Associated ALARA Plans

BY-1-21-00616 RCP Maintenance Activities - Radiation Work Permit and 0

Associated ALARA Plans

BY-1-21-00647 CRDM Maintenance -Prep and PT Radiation Work Permit 0

and Associated ALARA Plans

BY-2-20-00505 ALARA Plans and Work in Progress Reviews Various

Inspection Type Designation Description or Title Revision or

Procedure Date

Corrective Action AR 04349656 Shielding Extension CC-AA-401 06/11/2020

Documents AR 04383433 Adverse Dose Trend for Axion/ATF Project 11/20/2020

Miscellaneous B2R22 Radiation Protection Refueling Outage Report Fall Undated

20

SAC #21-013 Station ALARA Committee Agenda - B1R24 - Valves/RXS 07/23/2021

SAC #21-015 Station ALARA Committee (SAC) Agenda -2021 B1R24 07/27/2021

Scaffolds

SAC#21-013 Station ALARA Committee Meeting Minutes 07/26/2021

71124.03 Corrective Action AR 04332211 SCBA Monthly Inspections to be Performed with Surrogate 04/02/2020

Documents Mask

AR 04347577 SCBA Compressor Cascade Bottle Qualification Discrepancy 06/02/2020

AR-04427044 SCBA Compressor Out of Service 06/02/2021

Miscellaneous Dayshift SRO and RO Respirator Qualifications Including Various

SCBA for On-Shift Crew September 13, 2021

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

BY-1-21-00647 TEDE ALARA Evaluation Screening Worksheet for Under 09/09/2021

Reactor Head Inspections

Procedures RP-BY-825-1003 Operation, Inspection and Use of the MSA Firehawk M7 Air 4

Mask Self-Contained Breathing Apparatus (SCBA)

RP-BY-825-8703 Operation of the Mako Air Compressor (BAM06H) 1

Work Orders 04843651-01 OA Control Room Makeup System Charcoal Adsorber Bank 05/27/2020

Operability

04843652-01 Control Room 0A Makeup System HEPA Filter Test - DOP 05/27/2020

71124.08 Miscellaneous Byron Station 10 CFR 37 Security Plan 12/19/2019

CFR 37 Security Plan Training Records for Radiation Various

Protection Personnel

Training Records for Security Part 37 Various

SY-AA-150-101-Part 37 Refresher/Security Training 12/27/2019

F-44

71152 Corrective Action 4259629 0B SX Makeup Secured Due to Rapidly Rising Gear Box Oil 06/26/2019

Documents Temp

Inspection Type Designation Description or Title Revision or

Procedure Date

27728 Thermal Sleeve at Pen-34 Lowered Beyond Specific Eval 03/18/2020

Value

4339213 0B SX MU Pump Gear Oil Temp Indication/Sensor Possibly 04/28/2020

Broke

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 09/19/2021

Results

Engineering 631064 B1R23 CRDM Thermal Sleeve Metrology Evaluation 0

Changes 635099 B1R24 CRDM Thermal Sleeve Metrology Evaluation 0

Miscellaneous 142-9336720-000 Byron 1 CROM Thermal Sleeve As-Found Dimensional 09/18/2021

Report 2021

PWROG-16003-P Evaluation of Potential Thermal Sleeve Flange Wear 2

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

26