IR 05000454/2023001

Integrated Inspection Report 05000454/2023001 and 05000455/2023001

ML23124A386
Person / Time
Site:	Byron
Issue date:	05/05/2023
From:	Hironori Peterson NRC/RGN-III/DORS/RPB3
To:	Rhoades D Constellation Energy Generation, Constellation Nuclear
References
IR 2023001
Download: ML23124A386 (23)

Text

May 5, 2023

SUBJECT:

BYRON STATION - INTEGRATED INSPECTION REPORT 05000454/2023001 AND 05000455/2023001

Dear David Rhoades:

On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Byron Station. On April 11, 2023, the NRC inspectors discussed the results of this inspection with A. Schuerman, Plant Manager, 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, Nguyen, April signing on behalf of Peterson, Hironori on 05/05/23 Hironori Peterson, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety 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: 05000454/2023001 and 05000455/2023001 Enterprise Identifier: I-2023-001-0055 Licensee: Constellation Energy Generation, LLC Facility: Byron Station Location: Byron, IL Inspection Dates: January 01, 2023 to March 31, 2023 Inspectors: B. Bergeon, Senior Operations Engineer J. Bozga, Senior Reactor Inspector J. Cassidy, Senior Health Physicist A. Demeter, Resident Inspector T. Hooker, Health Physicist R. Knutson, Illinois Emergency Management Agency E. Magnuson, Reactor Inspector J. Masse, Acting Resident Inspector J. Robbins, Senior Resident Inspector E. Sanchez Santiago, Senior Project Engineer Approved By: Hironori Peterson, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety 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 05000454,05000455/ Main Steam Tunnel and 71111.21M Closed 2021011-01 Safety Valve Room Use of ACI 349-85 Appendix C Provisions LER 05000454/2021-001-00 LER 2021-001-00 for Byron 71153 Closed Station, Unit 1 Pressurizer Safety Valves As-Found Lift Pressure Outside of Tech Spec Limit LER 05000454/2021-001-01 LER 2021-001-01 for Byron 71153 Closed Station, Unit 1, Pressurizer Safety Valves As-Found Lift Pressure Outside of Tech Spec Limit LER 05000455/2022-001-00 LER 2022-001-00 for Byron 71153 Closed Station, Unit 2, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking.

PLANT STATUS

Unit 1 began the inspection period operating at full power. On March 6, 2023, Unit 1 was taken offline for a planned refueling outage. On March 24, Unit 1 went critical and returned to full power on March 27. The unit remained at full power for the remainder of the inspection period.

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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Engineered safety feature switchgear 141 bus on January 25, 2023

(2) Accessible portions of 1A and 1B essential service water trains on February 7, 2023

(3) Unit 1 and 2 component cooling trains during maintenance of the common component cooling train on March 30, 2023

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 emergency diesel generators (EDGs) on March 14, 2023.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Fire Zone 12.1-0; fuel handling building, 401' and 426' elevations on January 6, 2023

(2) Fire Zone 11.3-0; auxiliary building 364' elevation general area on January 24, 2023

(3) Fire Zone 11.4-0; auxiliary building 383' elevation general area on March 28, 2023

(4) Fire Zone 11.6-0; auxiliary building 426' elevation general area on March 29, 2023

71111.06 - Flood Protection Measures

Flooding Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated flooding mitigation protections in the Unit 1 auxiliary feedwater (AF) tunnel following the discovery of water intrusion into the tunnel, as documented in Issue Report (IR) 4558592 on March 2, 2023.

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1) Ultrasonic Examination Feedwater System Weld: 1FW03DC-16/C20.01, Cat R-A/R1.11 Reactor Coolant System Weld: 1RC35AA-6/J04, Cat R-A/R1.11 Pressurizer Overlay Weld: 1RY-01-S PN-04-F4S, Augmented Inspection Dye Penetrant and Magnetic Particle Examination Dye Penetrant and Magnetic Particle Test of Service Water System Weld:

1SX06BB-16/C01A, C-C/C3.20 Welding Activities Weld Repair/Replacement of 1SX2167A 1B Auxiliary Feedwater Pump Cubicle Cooler Inlet Isolation Valve, Work Order (WO) 04631529-01 Weld Repair/Replacement of CM-1SXE5A-3," Auxiliary Feedwater Pump Recirculation to Service Water Piping, WO 05027587-01 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection

Activities (IP Section 03.02) (1 Sample)

The inspectors verified that the license conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:

(1) Bare Metal Visual of 1RC01R Reactor Top Head PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)

The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following:

(1) Boric Acid Evaluations Action Request (AR) 4492901; Active Leak Identified in 1FC02F Vault AR 4534558; 1SI077 Boric Acid Leakage - Additional Targets Identified AR 4485008; 1CV8147 Boric Acid Corrective Action Documents AR 4501643; 1CV008A Boric Acid Buildup on Upstream Flange AR 439113; Standing Water in 1FC04F Vault Walkdowns Performed on March 5, 2023 and March 9, 2023

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(1 Sample)

(1) The inspectors observed and evaluated licensed operator performance of various on-watch operations shift crews in the Control Room including, but not limited to:

shutdown and cooldown for refuel outage B1R25

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated Licensed Operator Requalification Training 23-1-1, Revision 1 on February 16, 2023.

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 review associated with the Unit 1 control rod drive system (CRDM) thermal sleeve lowering on February 8, 2023

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) Evaluation of the planned work associated with new fuel receipt and inspection in preparation for Refueling Outage B1R25, as documented in WO 5266937 on January 31, 2023

(2) Evaluation of the plant risk associated with changing shutdown safety risk during draindown in cavity level in preparation of head detensioning and removal for refuel outage B1R25 on March 7, 2023

(3) Verification of select risk mitigating actions implemented in the plant during reduced inventory conditions while the head was being removed during B1R25 on March 8, 2023

(4) Evaluation of the risk associated with the loose parts evaluation decision to leave unrecovered foreign material within the reactor coolant system, as documented in IRs 4561361 and 4561439 on March 21, 2023

(5) Evaluation of the risk associated with the emergent risk informed completion time (RICT) implementation for the 1FW009A maintenance work window, as documented in WO 5348724 on March 28, 2023

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Evaluation of the operability of Unit 2 reactor vessel level indication system following unexpected alarm on January 24, 2023

(2) Evaluation of the operability for 125 VDC batteries following identification of cracks in battery cell lids on January 24, 2023

(3) Evaluation of the operability of 1A EDG, as documented in IR 4550405 on January 31, 2023

(4) Evaluation of the operability of the component cooling system following the failure of surveillance 1BOSR CC-7 and associated post-maintenance testing on March 21, 2023

(5) Evaluation of the common component cooling heat exchanger following discovery of a pinhole leak at the service water inlet pipe, as documented in IR 4563104 on March 31, 2023

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

(1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Installation and removal of temporary containment penetration cover at penetration 74 during B1R25 on March 23, 2023

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated refueling outage B1R25 activities from March 6 through March 24, 2023.

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system

operability and/or functionality: Post-Maintenance Testing (PMT) (IP Section 03.01)

(1) 1A centrifugal charging pump, 1CV01PA, comprehensive pump run following a pump outage work window on March 16, 2023

(2) 1BOSR Z.7.a.1, 1B Diesel Driven Feedwater Pump Overspeed Trip Test, following pump inspection, as documented in WO 5237710 on March 23, 2023

(3) 1B auxiliary feedwater pump surveillance testing following maintenance, as documented in WOs 5325010-01 and 5336866-01 on March 24, 2023

(4) 1FW009A hydraulic system testing following maintenance and associated RICT implementation, as documented in WO 5348724 on March 28, 2023

(5) 1D main steam isolation valve operability test following maintenance, as documented in WO 5234361 on March 24, 2023

(6) 1SI8814 valve exercise testing following discovery of additional needed maintenance, as documented in WO 1151716 and IR 4561502 on March 29, 2023

Surveillance Testing (IP Section 03.01) (6 Samples)

(1) 2BOSR 7.5.4-2; 2B AF Pump Run, as documented in WO 05324617-01 on January 24, 2023

(2) 1BOSR 8.1.2-2; 1B EDG Operability Monthly Surveillance, as documented in WO 05335746-01 on February 23, 2023

(3) 2BOSR 8.1.2-1; 2A EDG Semiannual Run, as documented in WO 05292744-01 on February 27, 2023

(4) BMP 3114-21; Main Steam Safety Valve Testing Using Setpoint Verification Device for Unit 1 on March 1, 2023

(5) 1BOSR 8.1.11-1; 1A Diesel Generator Sequencer Test on March 16, 2023

(6) 1BOSR 5.5.8.SI.2-3; Unit One Accumulator Discharge Primary and Backup Check Valve Stroke Test on March 20, 2023

Inservice Testing (IST) (IP Section 03.01) (2 Samples)

(1) Inservice Testing of the 2B Safety Injection Pump as documented in WO 5302386 on January 19, 2023.

(2) Inservice testing of the Unit 1 motor and diesel driven auxiliary feedwater pumps, as documented in WOs 5188424 and 5188305 on March 3, 2023.

Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)

(1) 1BOSR 6.1.1-8; Primary Containment Type C Local Leak Rate Testing for Primary Sampling System Containment Isolation Valves, as documented in WOs 4617034, 4618041, and 5022294 on March 9,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (1 Sample)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Licensee surveys of potentially contaminated material leaving the radiological controlled area at the Unit 1 Containment Access Facility

Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) Reactor coolant pump maintenance activities

(2) Containment sump inspection and cleaning

(3) Containment insulation 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) Spent resin transfer pump room

(2) Unit 1 incore detector sump area

(3) Unit 1 fuel transfer tube area 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.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

(1) Unit 1 (January 1, 2022 through December 31, 2022)

(2) Unit 2 (January 1, 2022 through December 31, 2022)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)

(2 Samples)

(1) Unit 1 (January 1, 2022 through December 31, 2022)

(2) Unit 2 (January 1, 2022 through December 31, 2022)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (January 1, 2022 through December 31, 2022)

(2) Unit 2 (January 1, 2022 through December 31, 2022)

71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000454/2021-001-00 and 454-2021-001-01, "Pressurizer Safety Valves As-Found Lift Pressure Outside of Tech Spec Limit," (ADAMS Accession No. ML21322A197 and ML22243A193). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors could not substantiate that a violation of technical specifications occurred. The inspectors reviewed the previous LER submittal and the updated LER submittal. This LER is Closed.

(2) LER 05000455/2022-001-00, "Byron Station Unit 2 Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking,"

(ADAMS Accession No. ML22173A039). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is Closed.

INSPECTION RESULTS

URI Main Steam Tunnel and Safety Valve Room Use of ACI 71111.21M 349-85 Appendix C Provisions URI 05000454,05000455/2021011-01

Description:

The Unresolved Item (URI) was opened to determine whether American Concrete Institute (ACI) 349-85, "Code Requirements for Nuclear Safety Related Concrete Structures, Appendix C, Special Provisions for Impulsive and Impactive Effects," was part of the licensing basis.

Updated Final Safety Analysis Report (UFSAR) Section 3.8.4.1 described the main steam tunnel as a seismic category I structure. Section 3.8.4.1.4 of the UFSAR described the main steam safety valve room as a reinforced concrete structure which was a part of the main steam tunnel (also a reinforced concrete structure). The inspectors reviewed Calculation No. 5.6.3-BYR96-233, "Evaluation of Main Steam and Aux-Feedwater Tunnels for Revised Accident Pressures and Temperatures Associated With Replacement Steam Generators,"

Revision 1, Calculation No. 5.6.1-BYR96-234, "Evaluation of Safety Valve Rooms for Revised Accident Pressures and Temperatures Associated With Replacement Steam Generators, Revision 1, and Calculation No. 5.6.1, "Main Steam and Auxiliary Feedwater Tunnel Analysis and Design," Revision 7. These calculations used ACI 349-85, Appendix C, to analyze the main steam tunnel and main steam safety valve rooms for the applied loading due to compartment pressurization from a main steam line break. The inspectors also reviewed the associated 10 CFR 50.59 regulatory evaluation which incorporated ACI 349-85, Appendix C, into Revision 1 of the UFSAR.

The inspectors considered Regulatory Guide (RG) 1.142, "Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments),"

Revisions 0 and 1. This RG provided the regulatory guidance for licensees on application of the ACI 349 appendix containing special provisions for impulsive and impactive effects on a reinforce concrete structure for the applied loading due to compartment pressurization. The inspectors also consulted with the Office of Nuclear Reactor Regulation.

The inspectors did not identify any findings or violations. This URI is closed.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

On April 11, 2023, the inspectors presented the integrated inspection results to A. Schuerman, Plant Manager, and other members of the licensee staff.

On March 16, 2023, the inspectors presented the radiation protection inspection results to S. Leach, Senior Manager, Site Radiation Protection, and other members of the licensee staff.

On March 16, 2023, the inspectors presented the inservice inspection results to P. Murray, Engineering Programs Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Corrective Action AR 04563104 Leak from U-0 CC HX SX Inlet Pipe 03/18/2023

Documents

Drawings 6E-1-4006A Key Diagram 4160V ESF SWGR Bus 141 (1AP05E) 08/07/1995

M-42 Sheet 1A Diagram of Essential Service Water 01/22/1998

M-42 Sheet 1B Diagram of Essential Service Water 01/22/1998

M-42 Sheet 2A Diagram of Essential Service Water 01/22/1998

M-42 Sheet 2B Diagram of Essential Service Water 01/22/1998

M-42 Sheet 3 Diagram of Essential Service Water 01/22/1998

M-42 Sheet 4 Diagram of Essential Service Water 01/22/1998

Procedures BOP CC-E1 Unit 1 Component Cooling System Electrical Lineup 7

BOP CC-E2 Unit 2 Component Cooling System Electrical Lineup 5

BOP CC-M1 Unit 1 Component Cooling System Valve Lineup 29

BOP CC-M2 Unit 2 Component Cooling System Valve Lineup 24

71111.05 Corrective Action AR 04546971 NRC Identified Lack of Housekeeping Signs 01/06/2023

Documents

Resulting from

Inspection

Fire Plans 11.4-0 North Aux Building 383' Elevation General Area - North 4

11.4-0 South Aux Building 383' Elevation General Area - South 3

11.4-0 West Aux Building 383' Elevation General Area - West 3

PFP FHB 401-0 Pre-Fire Plan Fuel Handling Building 401-0 Elevation FZ 4

FZ 12.1-0 12.1-0 Plan #176

PFP FHB 426-0 Pre-Fire Plan Fuel Handling Building 426-0 Elevation FZ 3

FZ 12.1-0 12.1-0 Plan #176

Miscellaneous FPR Chapter 2.3 Fire Area Analysis Amendment

71111.06 Corrective Action AR 04558592 Water Intrusion into U1 AF Tunnel 03/02/2023

Documents

Drawings S-1055 1A Auxiliary Feedwater Tunnel Cover (1DSFO06) 10/13/2008

Procedures BAP 1100-3 Plant Barrier Impairment (PBI) Program 27

BAP 1100-3A3 Pre-Evaluated Plant Barrier Matrix 44

Inspection Type Designation Description or Title Revision or

Procedure Date

CC-AA-201 Plant Barrier Control Program 14

71111.08P Corrective Action AR 04391133 Standing Water in 1FC04F Vault 12/18/2020

Documents AR 04446714 NRC ID Repair/Replacement Plan #04930998-01 Deficiency 09/16/2021

AR 04447291 1RC01004V Missing Travel Stop with Chain 09/18/2021

AR 04447377 RXS Recovered String-like FM from U1 Reactor Core Plate 09/19/2021

AR 04447381 1 SI03008C - O-Ring Found on Component Body 09/19/2021

AR 04485008 1CV8147 Boric Acid 03/15/2022

AR 04492901 Active Leak Identified in 1FC02F Vault 04/13/2022

AR 04501643 1CV008A Boric Acid Buildup on Upstream Flange 05/24/2022

AR 04519864 Repeated 1FC02F Leakage - Long Tern Solution Required 08/31/2022

AR 04519868 Repeated 1FC04F Leakage-Long Term Solution Required 08/31/2022

AR 04558675 Inactive Boric Acid Leak Beneath 1FC02F 03/02/2023

AR 04559721 B1R25 BACC MODE 3 Walkdown Results 03/06/2023

AR 04561174 b1R25 ISI - Relevant Condition Identified on 1SI01019X 03/11/2023

Strut

AR 04561174 Relevant Condition Identified on 1SI01019X Strut 03/10/2023

AR 04561361 FME Found Unit 1 RX Upper Internals During Guide Card 03/12/2023

Exam

AR 04561439 Foreign Material found in Guide Tube H10 03/12/2023

AR 04561441 B1R25 - Suspected Boric Acid Residues from Conoseal 03/12/2023

Removal

Corrective Action AR 04563221 NRC ID: Minor PD Identified During the ISI Inspection 03/19/2023

Documents

Resulting from

Inspection

Drawings 10055C14 Pressurizer Safety/Relief Nozzle SWOL Design 06/11/2006

M1SI01019X HANGER as Built Drawing F

NDE Reports B1R19-VT-022 VT-3 of 1SI05DA-6/1SI01019X 03/20/2014

B1R22-VEN-002 1RC01R Reactor Top Head BMV 09/15/2018

B1R24 BMV B1R24 Reactor Top Head BMV Report 09/19/2021

B1R25-MT-001 MT of 1SX06BB-16/C01A 03/13/2023

B1R25-PT-001 PT of 1SX06BB-16/C01A 03/13/2023

B1R25-UT-009 UT of 1FW03DC-16/C20.01 03/11/2023

Inspection Type Designation Description or Title Revision or

Procedure Date

B1R25-UT-016 UT of 1SI09AD-10/C08 03/14/2023

B1R25-UT-020 UT of 1RC35AA-6/J05 03/12/2023

B1R25-VEN-001 1RC01R Reactor Top Head BMV 03/14/2023

B1R25-VT-040 VT-3 of 1SI05DA-6/1SI01019X 03/10/2023

B1R25-VT-061 VT-3 of 1SI05DA-6/1SI01019X 03/16/2023

B1R25-WOL-001 UT of Weld Overlay on 1RY03AA-6/J018 03/13/2023

B1R25-WOL-002 UT of Weld Overlay on 1RY-01-S PN-04-F4S 03/13/2023

Procedures AR-AP-331-1001 Boric Acid Corrosion Control (BACC) Inspection Locations, 12

Implementation and Inspection Guidelines

AR-AP-331-1002 Boric Acid Corrosion Control (BACC) Program Identification, 12

Screening and Evaluation

ER-AA-335-003 Magnetic Particle (MT) Examination 10

ER-AA-335-014 VT-1 Visual Examination 12

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

Attachments and Interiors of Reactor Vessels

ER-AA-335-049 Ultrasonic Examination in Accordance with ASME Section V, 3

Article 4

ER-AA-335-1008 Code Acceptance & Recording Criteria for Nondestructive 6

(NDE) Examination

ER-AP-331 Boric Acid Corrosion Control (BACC) Program 11

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

PDI-UT-1 PDI Generic Procedure for the Ultrasonic Examination of G

Ferritic Pipe Welds

PDI-UT-2 PDI Generic Procedure for the Ultrasonic Examination of I

Austenitic Pipe Welds

PDI-UT-8 PDI Generic Procedure for the Ultrasonic Examination of I

Weld Overlaid Similar and Dissimilar Metal Welds

WPS 1-1-GTSM- Welding Procedure Specification 5

PWHT

WPS 8-8-GTSM Welding Procedure Specification 7

Work Orders 05192287 CM-1SXE5A-3" Replace Pipe with Stainless Steel EC 09/16/2021

631322

WO 04631529-01 1SX2167A COULD NOT BE MANIPULATED 10/03/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

WO 05027587-01 LEAK ON AF PUMPS RECIRC RETURN TO SX PIPING 06/15/2021

71111.11Q Procedures 1BGP 100-4 Power Descension 70

1BGP 100-5 Plant Shutdown and Cooldown 83

71111.12 Corrective Action AR 04320104 WEC NSAL-20-1 RVH CRDM Penetration Thermal Sleeve 02/21/2020

Documents Failure

AR 04322068 Westinghouse Justification to Postpone NSAL-20-1 02/27/2020

Inspections

AR 04447364 B1R24 CRDM Thermal Sleeve Metrology and VT-1 Exam 09/19/2021

Results

Engineering EC 635099 B1R24 CRDM Thermal Sleeve Metrology Evaluation 09/25/2021

Changes

Miscellaneous 142-9336720-000 Framatome Inc. Metrology Services Information Record: 09/17/2021

Byron 1 CRDM Thermal Sleeve As-Found Dimensional

Report 2021 [PROPRIETARY]

LTR-RIDA-20-32 Byron Unit 1 CRDM Thermal Sleeve Cracking Inspection 02/27/2020

Deferral [PROPRIETARY]

NSAL-20-1 Reactor Vessel Head Control Rod Drive Mechanism 09/23/2021

Penetration Thermal Sleeve Cross-Sectional Failure

PWROG-16003-P Evaluation of Potential Thermal Sleeve Flange Wear 08/01/2017

Work Orders 5093408 Reactor Head Metrology Required in B1R24 08/03/2021

5137678 VT-1 of Thermal Sleeves (Unit 1) 08/03/2021

71111.13 Corrective Action AR 04561361 FME Found Unit 1 RX Upper Internals During Guide Card 03/12/2023

Documents Exam

AR 04561439 Foreign Material Found in Guide Tube H10 03/12/2023

AR 04563995 1FW009A Hydraulic Pressure Low 03/22/2023

Drawings 38539 Reservoir Assembly Hydraulic Reservoir M00

38559 Reservoir Assembly Hydraulic Operator M00

210 Feedwater Isolation Valve 16X10X16 900 LB. Carbon Steel M00

M-152 Pneumatic-Hydraulic Diagram for Feedwater Isolation M05

Valves 1 & 2FW009

Engineering 638661 FME Lost Parts Evaluation for N-5 & H-10 Guide Cards 0

Evaluations 638693 Lost Parts Evaluation for the 1D RCP #1 Seal Faceplate 0

6E-23-004 50.59 Screening for Lost Parts Evaluation for the 1D RCP #1 0

Seal Faceplate

Inspection Type Designation Description or Title Revision or

Procedure Date

6G-23-002 50.59 Evaluation for the Lost Parts Evaluation for FM 0

Discovered During Guide Card Inspections at Guide Tubes

N5 and H10

Miscellaneous Emergent RICT Record for 1FW009A Maintenance and 03/27/2023

PMT

B1R25 Shutdown Safety and Contingency Plans 01/26/2023

Procedures 1BEP-0 Reactor Trip or Safety Injection Unit 1 306

1BFR-H.1 Response to Loss of Secondary Heat Sink Unit 1 304

1BOA ELEC-2 Loss of Instrument Bus Unit 1 110

1BOA PRI-6 Component Cooling Malfunction Unit 1 114

1BOA PRI-7 Essential Service Water Malfunction Unit 1 110

BOP CC-10 Alignment of the U-0 CC Pump and U-0 CC Heat Exchanger 35

to A Unit

CC-AA-309-101 Engineering Technical Evaluations 16

ER-AA-2006 Lost Parts Evaluations 14

ER-AA-600-1052 Risk Management Support of RICT 001

MA-BY-716-008- Reactor Services Refuel Floor FME Plan 0

1008

OP-AA-108-117 Protected Equipment Program 7

OP-AA-108-118 Risk Informed Completion Time 2

OU-AA-101-1011 Outage Risk Management 004

OU-AA-103 Shutdown Safety Management Program 23

OU-AA-103-1001 Shutdown Safety Plan Independent Review 5

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

Ginna

OU-AP-203 Operation of the New Fuel Elevator for Byron and Braidwood 8

Work Orders 5266937 RXS New Fuel Receipt and Inspection for U-1 Outage 01/31/2023

71111.15 Calculations 3C8-1281-001 Flooding Analysis for the Auxiliary Building 364' Floor 12A

Elevation

NED-M-MSD-014 Byron Ultimate Heat Sink Cooling Tower Basin Makeup 009A

Calculation

Corrective Action AR 04228044 SX Leak By 0SX007 03/09/2018

Documents AR 04415429 1A DG JW Header Leak 04/09/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

AR 04476444 Unexpected Alarm RVLIS Sensor Uncovered 02/07/2022

AR 04481669 Minor Cracking on the Cell Covers for Batt. 111, 112 & 212 03/01/2022

AR 04481897 Minor Cracking on the Cell Covers for Batt. 112 03/02/2022

AR 04483675 Battery 111 Addition Cells Covers with Cracks 03/09/2022

AR 04514245 Unit 2: B Train RVLIS Sensor #3 Alarm 08/01/2022

AR 04525362 Division 111 & 112 Additional Battery Cover Cracks 09/29/2022

AR 04544700 SX Water Leaking from Weepholes 1A DG JW Cooler 12/24/2022

1DG01KA-X2

AR 04547076 Unexpected Alarm U2 RVLIS 01/06/2023

AR 04550405 1A DG JW Leak 01/25/2023

AR 04559414 1BOSR CC-7 Surveillance Failed and PMT Failure 03/05/2023

AR 04563104 Leak from U-0 CC HX SX Inlet Pipe 03/18/2023

Engineering EC 623441 Evaluation of Impact of Leaks for Various Fixed Volume 000

Changes Systems on the Emergency Diesel Generators (EDGs)

EC 627668 Minimum Wall Evaluation of Lines 0SX02D-30," 0SX02C-30" 000

and 1SXH1C-6" in Support of CC N-513-4 Evaluation

Reference IR 4228044

Miscellaneous BYRON-00-5043 Generic Jacket Water Leakage Evaluation for Emergency 06/02/2000

Diesel Generators

NDE Reports 2023-UT-046 UT Erosion/Corrosion Examination of 0SX02D-30" 03/19/2023

Operability OPS Assessment Supporting Operability Documentation for 1A Diesel 04/05/1999

Evaluations99-011 Generator Jacket Water Leak

Procedures 1BOSR CC-7 Unit One Component Cooling from Primary Sample Cooler 0

Panel Return Line Check Valves 1CC091B and 1CC092B

Test

2BOL 3.3 LOCAR Post Accident Monitoring (PAM) Instrumentation 5

Tech Spec LCO # 3.3.3

2BOSR 3.3.1-1 Unit Two Accident Monitoring Instrumentation Monthly 27

Channel Checks

BAR 2-9-D6 Rx Vessel Lvl Msrment Sys Sensor Uncovered 2

BOP RC-12 Placing RVLIS/HJTC/CETC in Service 5

BOP RC-12T1 Table 1 RVLIS Error Codes Train A and B 1

Work Orders 5016218 1BOSR CC-7 Surveillance Failed Leak Rate Test 03/05/2023

Inspection Type Designation Description or Title Revision or

Procedure Date

5177731 Perform 1 BOSR CC-7 03/06/2023

71111.18 Drawings M-197-3 Reactor Containment Penetration Sleeve Scheduled for S

Byron Unit 1

Engineering EC 345542 Guidance for Temporarily Disconnecting Pipe; Equipment 1

Changes Anchors, Cutting Pip, and or Disconnection of Flanges

EC 361370 Evaluation of Proceduralized TCCP: BMP 3300-28 1

Procedures BMP 3300-28 Installation and Removal of Temporary Containment 7

Penetration Covers

Work Orders 5220978 LLRT For P-74 - Spare 03/20/2023

28280 Containment Temporary Penetration PC074M 03/21/2023

71111.20 Miscellaneous BY-MODE-034 TS 3.0.4.b Evaluation - Mode Change with Technical 1

Specification Equipment Out of Service

Procedures 1BGP 100-2 Plant Startup 54

1BGP 100-2A1 Reactor Startup 38

1BGP 100-3 Power Ascension 107

1BGP 100-3T2 Mode 2 to 1 Checklist 22

OP-AA-106-101- Operational Decision Making (ODM) Process 24

1006

OU-AA-101 Refuel Outage Management 30

OU-AA-101-1007 Outage Scope Control 20

OU-AP-104 Shutdown Safety Management Program Byron/Braidwood 29

Annex

71111.21M Calculations 5.6.1-BYR96-233 Evaluation of Main Steam and Aux-Feedwater Tunnels for 1

Revised Accident Pressures and Temperatures Associated

with Replacement Steam Generators.

Corrective Action AR 04417167 Byron NRC DBAI - Unresolved Issue (URI) 04/16/2021

Documents AR 04424322 NRC URI: MS Tun & SV Rm Use ACI 349-85 App C 05/18/2021

Provisions

Miscellaneous 10 CFR 50.59 UFSAR Revision 1 Final Draft 12/07/1989

Safety Evaluation

Regulatory Guide Safety-Related Concrete Structures for Nuclear Power 1

1.142 Plants (Other than Reactor Vessels and Containments)

71111.24 Calculations BYR97-193 Battery Duty Cycle and Sizing for Byron Diesel Driven 3A

Auxiliary Feedwater Pumps and Byron Diesel Driven SX

Inspection Type Designation Description or Title Revision or

Procedure Date

M/U Pumps

Corrective Action AR 04548135 2B AF PP Gear Changer Aux Oil Pump Cycling 01/12/2023

Documents AR 04561502 WO: 1151716-01 1SI8814 Tripper Fingers Not Engaging 03/13/2023

AR 04562629 Issue During DG Sequence Testing 03/16/2023

AR 04564121 1B Aux FW Pump Gear Box Lube Oil Pump Cycling 03/22/2023

Drawings 934D209 Swing Check Valve 10C88 7

Engineering EC 638737 Justification for Not Performing 1FW009A Valve Stroke 000

Changes Testing After Limited Actuator Reservoir Maintenance per

Work Package 05348724 Exiting B1R25

EC 638741 ALT DTL - FW009 Anti-Rotation Bars and Hole for Limit 000

Switch Plate

Engineering CQD-043914-SR Calculation for Minimum Flow Velocity for Swing Check 07/06/1989

Evaluations Valves

Procedures 1BOSR 0.5- Unit One Main Feedwater System Containment Isolation 10

2.FW.1 Valves Full Stroke and Position Indication Test

1BOSR 0.5- Unit One 1SI8802A, 1SI8806, 1SI8809A, 1SI8835, 1SI8840, 23

2.SI.2-2.1 1CV8804A, 1SI8811A and 1SI8923A Stroke Test and

Position Indication Test

1BOSR 0.5- Unit One 1SI8821A, 1SI8812A, 1SI8924, 1SI8807A/B, and 10

2.SI.3-1 1SI8814 Position Indication Test

1BOSR Unit One SI8821A, 1SI8812A, 1SI8924, 1SI8807A/B and 12

0.5.2.SI.1-1 1SI8814 Exercise Test

1BOSR Unit One Comprehensive Inservice Testing (IST) 8

5.5.8.CV.5-1c Requirements for Centrifugal Charging Pump 1CV01PA

1BOSR 6.1.1-8 Unit One Primary Containment Type C Local Leakage Rate 14

Tests and IST Tests of Primary Sampling System

1BOSR 8.1.11-1 Unit One 1A Diesel Generator Sequencer Test 32

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

Sequence and Overspeed Trip Test

1BVSR 7.1.1-1 Unit 1 Main Steam Safety Valves Operability Test 12

2BOSR Unit Two Group A Inservice Testing (IST) Requirements for 4

5.5.8.SI.5-2a Safety Injection Pump 2SI01PB

2BOSR 7.5.4-2 Unit Two Diesel Driven Auxiliary Feedwater Pump Monthly 36

Surveillance

Inspection Type Designation Description or Title Revision or

Procedure Date

BMP 3100-5 Limitorque Operator SMB/SMC Removal and Installation 21

BMP 3112-1 Feedwater Isolation Valve Hydraulic Actuator Maintenance 31

BMP 3112-2 Main Feedwater Isolation Valve Actuator Filling and 19

Charging

BMP 3114-21 Main Steam Safety Valve Testing Using Setpoint Verification 2

Device

Work Orders 1151716 Replace Body to Bonnet Gasket & Repack Valve 03/14/2023

4617034 LLRT For P-70 - 1PS9354A and 1PS9354B 03/09/2023

4618041 LLRT For P-70 - 1PS9356A and 1PS9356B 03/09/2023

4818840 MM - 1CV01PA Repair Inboard & Outboard Pump Seals 03/16/2023

4997520 PM - MOV Stem Lube 03/14/2023

20435 Replace MCB Control Switch for 1AF01PB 03/22/2023

22294 LLRT For P-70 - 1PS9357A and 1PS9357B 03/09/2023

5188016 Main Steam Safety Valves Operability Test (<94% Reactor 03/01/2023

Power)

5188200 MOV PM, Actuator Inspection, Diagnostic Testing 03/14/2023

5188202 PM Inspection, In-Service Diag Test, PIT 03/14/2023

5188305 (NEIL)-1AP01PA Comprehensive IST Requirements for the 03/03/2023

Motor Drive Auxiliary Feedwater Pump

5188412 1A Diesel Generator Sequencer Test 03/15/2023

5188424 (NEIL)-1AP01PB Comprehensive IST Requirements for the 03/03/2023

Diesel Drive Auxiliary Feedwater Pump

237710 Diesel Driven Auxiliary Feed Pump Inspection Per BMP 03/22/2023

203-1

5302386 (NEIL) - 2SI01PB Group A IST Requirements for Safety 01/19/2023

Injection

24617-01 2BOSR 7.5.4-2, 2B AF PP Run 01/03/2023

5348724 1FW009A Hydraulic Pressure Low 03/27/2023

71124.01 ALARA Plans BY-1-23-00503 ALARA Plan for RWP BY-1-23-00503, AUX (task 1) and 29

Containment Insulation (tasks 2).

BY-1-23-00609 ALARA Plan for RWP BY-1-23-00609, Containment Sump 29

Inspection and Cleaning.

BY-1-23-00614 ALARA Plan for RWP BY-1-23-00614, Reactor Head and 29

Inspection Type Designation Description or Title Revision or

Procedure Date

Upper Internals Moves (task 2) and Visual Flange Inspection

and Reactor Cavity Entry (task 3).

BY-1-23-00616 ALARA Plan for RWP BY-1-23-00616 Reactor Maintenance 29

Activities.

Corrective Action AR 04561965 NRC ID: AMS-4 Air Sampler Running with No Digital Display 03/14/2023

Documents

Resulting from

Inspection

Miscellaneous RP-AA-302 Alpha Area Level Assessment for Unit One 04/13/2022

RP-AA-302 Alpha Area Level Assessment for Unit Two 04/15/2021

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

Radiation 2023-188760 Radiological Survey Map of the Containment Floor Drain 03/11/2023

Surveys Sump at Elevation 377' in the Containment Building of Unit

One, Map Number 432

Radiation Work BY-1-23-00503 Auxiliary Building (task 1) and Containment (task 2) 00

Permits (RWPs) Insulation Radiation Work Permit

BY-1-23-00609 Containment Sump Inspection and Cleaning Radiation Work 01

Permit

BY-1-23-00616 Reactor Coolant Pump Maintenance Activities Radiation 00

Work Permit

71151 Miscellaneous NRC Performance Indicator Data: Initiating Events - 01/01/2022 -

Unit/Reactor Shutdown Occurrences 12/31/2022

NRC Performance Indicator Data: Initiating Events - 01/01/2022 -

Unplanned Power Changes per 7000 Critical Hours 12/31/2022

Review of Unit 1 and Unit 2 Plant Process Computer Data 01/01/2022 -

for the Calendar Year 2022 12/31-2022

71153 Corrective Action AR 04447391 1RY8010B Failed As-Found Testing at Vendor 09/19/2021

Documents AR 04450104 1RY8010A Failed As-Found Testing at Vendor 10/01/2021

AR 04495001 U2 Reactor Head Indication - B2R23 04/22/2022

AR 04495098 U2 Reactor Head Indication at Penetration-75 04/23/2022

AR 04550108 1RY8010C Failed As-Found Testing at Vendor 10/01/2021

CAPE Investigation into Byron Pressurizer Safety Valves Failed 03/31/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

As-Found Lift Test during B1R24

Engineering 635206 Byron Unit 1 Evaluation of Pressurizer Safety Out of 0

Evaluations Tolerance Impact on Safety Analyses

21