IR 05000454/2023001
| 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
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, 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:
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
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Byron Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000454,05000455/
2021011-01 Main Steam Tunnel and Safety Valve Room Use of ACI 349-85 Appendix C Provisions 71111.21M Closed LER 05000454/2021-001-00 LER 2021-001-00 for Byron Station, Unit 1 Pressurizer Safety Valves As-Found Lift Pressure Outside of Tech Spec Limit 71153 Closed LER 05000454/2021-001-01 LER 2021-001-01 for Byron Station, Unit 1, Pressurizer Safety Valves As-Found Lift Pressure Outside of Tech Spec Limit 71153 Closed LER 05000455/2022-001-00 LER 2022-001-00 for 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.
71153 Closed
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.
REACTOR SAFETY
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 439113439113 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) (6 Samples)
(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,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (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 349-85 Appendix C Provisions URI 05000454,05000455/2021011-01 71111.21M
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Leak from U-0 CC HX SX Inlet Pipe
03/18/2023
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
Drawings
M-42 Sheet 4
Diagram of Essential Service Water
01/22/1998
BOP CC-E1
Unit 1 Component Cooling System Electrical Lineup
BOP CC-E2
Unit 2 Component Cooling System Electrical Lineup
BOP CC-M1
Unit 1 Component Cooling System Valve Lineup
Procedures
BOP CC-M2
Unit 2 Component Cooling System Valve Lineup
Corrective Action
Documents
Resulting from
Inspection
NRC Identified Lack of Housekeeping Signs
01/06/2023
11.4-0 North
Aux Building 383' Elevation General Area - North
11.4-0 South
Aux Building 383' Elevation General Area - South
11.4-0 West
Aux Building 383' Elevation General Area - West
PFP FHB 401-0
FZ 12.1-0
Pre-Fire Plan Fuel Handling Building 401-0 Elevation FZ
2.1-0 Plan #176
Fire Plans
PFP FHB 426-0
FZ 12.1-0
Pre-Fire Plan Fuel Handling Building 426-0 Elevation FZ
2.1-0 Plan #176
Miscellaneous
FPR Chapter 2.3
Fire Area Analysis
Amendment
Corrective Action
Documents
Water Intrusion into U1 AF Tunnel
03/02/2023
Drawings
S-1055
1A Auxiliary Feedwater Tunnel Cover (1DSFO06)
10/13/2008
BAP 1100-3
Plant Barrier Impairment (PBI) Program
Procedures
BAP 1100-3A3
Pre-Evaluated Plant Barrier Matrix
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Plant Barrier Control Program
Standing Water in 1FC04F Vault
2/18/2020
NRC ID Repair/Replacement Plan #04930998-01 Deficiency
09/16/2021
1RC01004V Missing Travel Stop with Chain
09/18/2021
RXS Recovered String-like FM from U1 Reactor Core Plate
09/19/2021
SI03008C - O-Ring Found on Component Body
09/19/2021
1CV8147 Boric Acid
03/15/2022
Active Leak Identified in 1FC02F Vault
04/13/2022
1CV008A Boric Acid Buildup on Upstream Flange
05/24/2022
Repeated 1FC02F Leakage - Long Tern Solution Required
08/31/2022
Repeated 1FC04F Leakage-Long Term Solution Required
08/31/2022
Inactive Boric Acid Leak Beneath 1FC02F
03/02/2023
B1R25 BACC MODE 3 Walkdown Results
03/06/2023
b1R25 ISI - Relevant Condition Identified on 1SI01019X
Strut
03/11/2023
Relevant Condition Identified on 1SI01019X Strut
03/10/2023
FME Found Unit 1 RX Upper Internals During Guide Card
Exam
03/12/2023
Foreign Material found in Guide Tube H10
03/12/2023
Corrective Action
Documents
B1R25 - Suspected Boric Acid Residues from Conoseal
Removal
03/12/2023
Corrective Action
Documents
Resulting from
Inspection
NRC ID: Minor PD Identified During the ISI Inspection
03/19/2023
10055C14
Pressurizer Safety/Relief Nozzle SWOL Design
06/11/2006
Drawings
M1SI01019X
HANGER as Built Drawing
F
VT-3 of 1SI05DA-6/1SI01019X
03/20/2014
1RC01R Reactor Top Head BMV
09/15/2018
B1R24 BMV
B1R24 Reactor Top Head BMV Report
09/19/2021
MT of 1SX06BB-16/C01A
03/13/2023
PT of 1SX06BB-16/C01A
03/13/2023
NDE Reports
UT of 1FW03DC-16/C20.01
03/11/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
UT of 1SI09AD-10/C08
03/14/2023
UT of 1RC35AA-6/J05
03/12/2023
1RC01R Reactor Top Head BMV
03/14/2023
VT-3 of 1SI05DA-6/1SI01019X
03/10/2023
VT-3 of 1SI05DA-6/1SI01019X
03/16/2023
UT of Weld Overlay on 1RY03AA-6/J018
03/13/2023
UT of Weld Overlay on 1RY-01-S PN-04-F4S
03/13/2023
Boric Acid Corrosion Control (BACC) Inspection Locations,
Implementation and Inspection Guidelines
Boric Acid Corrosion Control (BACC) Program Identification,
Screening and Evaluation
Magnetic Particle (MT) Examination
VT-1 Visual Examination
VT-3 Visual Examination of Component Supports,
Attachments and Interiors of Reactor Vessels
Ultrasonic Examination in Accordance with ASME Section V,
Article 4
Code Acceptance & Recording Criteria for Nondestructive
(NDE) Examination
Boric Acid Corrosion Control (BACC) Program
Bare Metal Visual Examination for Nickel Alloy Materials
PDI-UT-1
PDI Generic Procedure for the Ultrasonic Examination of
Ferritic Pipe Welds
G
PDI-UT-2
PDI Generic Procedure for the Ultrasonic Examination of
Austenitic Pipe Welds
I
PDI-UT-8
PDI Generic Procedure for the Ultrasonic Examination of
Weld Overlaid Similar and Dissimilar Metal Welds
I
WPS 1-1-GTSM-
Welding Procedure Specification
Procedures
WPS 8-8-GTSM
Welding Procedure Specification
05192287
CM-1SXE5A-3" Replace Pipe with Stainless Steel EC 631322
09/16/2021
Work Orders
1SX2167A COULD NOT BE MANIPULATED
10/03/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
LEAK ON AF PUMPS RECIRC RETURN TO SX PIPING
06/15/2021
1BGP 100-4
Power Descension
Procedures
1BGP 100-5
Plant Shutdown and Cooldown
WEC NSAL-20-1 RVH CRDM Penetration Thermal Sleeve
Failure
2/21/2020
Westinghouse Justification to Postpone NSAL-20-1
Inspections
2/27/2020
Corrective Action
Documents
B1R24 CRDM Thermal Sleeve Metrology and VT-1 Exam
Results
09/19/2021
Engineering
Changes
B1R24 CRDM Thermal Sleeve Metrology Evaluation
09/25/2021
2-9336720-000
Framatome Inc. Metrology Services Information Record:
Byron 1 CRDM Thermal Sleeve As-Found Dimensional
Report 2021 [PROPRIETARY]
09/17/2021
LTR-RIDA-20-32
Byron Unit 1 CRDM Thermal Sleeve Cracking Inspection
Deferral [PROPRIETARY]
2/27/2020
NSAL-20-1
Reactor Vessel Head Control Rod Drive Mechanism
Penetration Thermal Sleeve Cross-Sectional Failure
09/23/2021
Miscellaneous
PWROG-16003-P
Evaluation of Potential Thermal Sleeve Flange Wear
08/01/2017
5093408
Reactor Head Metrology Required in B1R24
08/03/2021
Work Orders
5137678
VT-1 of Thermal Sleeves (Unit 1)
08/03/2021
FME Found Unit 1 RX Upper Internals During Guide Card
Exam
03/12/2023
Foreign Material Found in Guide Tube H10
03/12/2023
Corrective Action
Documents
1FW009A Hydraulic Pressure Low
03/22/2023
38539
Reservoir Assembly Hydraulic Reservoir
M00
38559
Reservoir Assembly Hydraulic Operator
M00
210
Feedwater Isolation Valve 16X10X16 900 LB. Carbon Steel
M00
Drawings
M-152
Pneumatic-Hydraulic Diagram for Feedwater Isolation
Valves 1 & 2FW009
M05
638661
FME Lost Parts Evaluation for N-5 & H-10 Guide Cards
638693
Lost Parts Evaluation for the 1D RCP #1 Seal Faceplate
Engineering
Evaluations
50.59 Screening for Lost Parts Evaluation for the 1D RCP #1
Seal Faceplate
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
50.59 Evaluation for the Lost Parts Evaluation for FM
Discovered During Guide Card Inspections at Guide Tubes
N5 and H10
Emergent RICT Record for 1FW009A Maintenance and
03/27/2023
Miscellaneous
B1R25 Shutdown Safety and Contingency Plans
01/26/2023
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
to A Unit
Engineering Technical Evaluations
Lost Parts Evaluations
Risk Management Support of RICT
001
MA-BY-716-008-
1008
Reactor Services Refuel Floor FME Plan
Protected Equipment Program
Risk Informed Completion Time
Outage Risk Management
004
Shutdown Safety Management Program
Shutdown Safety Plan Independent Review
New Fuel Receipt and Inspection for Byron, Braidwood, and
Ginna
Procedures
Operation of the New Fuel Elevator for Byron and Braidwood
Work Orders
266937
RXS New Fuel Receipt and Inspection for U-1 Outage
01/31/2023
Flooding Analysis for the Auxiliary Building 364' Floor
Elevation
2A
Calculations
NED-M-MSD-014
Byron Ultimate Heat Sink Cooling Tower Basin Makeup
Calculation
009A
SX Leak By 0SX007
03/09/2018
Corrective Action
Documents
04/09/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Unexpected Alarm RVLIS Sensor Uncovered
2/07/2022
Minor Cracking on the Cell Covers for Batt. 111, 112 & 212
03/01/2022
Minor Cracking on the Cell Covers for Batt. 112
03/02/2022
Battery 111 Addition Cells Covers with Cracks
03/09/2022
Unit 2: B Train RVLIS Sensor #3 Alarm
08/01/2022
Division 111 & 112 Additional Battery Cover Cracks
09/29/2022
SX Water Leaking from Weepholes 1A DG JW Cooler
1DG01KA-X2
2/24/2022
Unexpected Alarm U2 RVLIS
01/06/2023
01/25/2023
1BOSR CC-7 Surveillance Failed and PMT Failure
03/05/2023
Leak from U-0 CC HX SX Inlet Pipe
03/18/2023
Evaluation of Impact of Leaks for Various Fixed Volume
Systems on the Emergency Diesel Generators (EDGs)
000
Engineering
Changes
Minimum Wall Evaluation of Lines 0SX02D-30," 0SX02C-30"
and 1SXH1C-6" in Support of CC N-513-4 Evaluation
Reference IR 4228044
000
Miscellaneous
Generic Jacket Water Leakage Evaluation for Emergency
Diesel Generators
06/02/2000
NDE Reports
23-UT-046
UT Erosion/Corrosion Examination of 0SX02D-30"
03/19/2023
Operability
Evaluations
OPS Assessment
99-011
Supporting Operability Documentation for 1A Diesel
Generator Jacket Water Leak
04/05/1999
1BOSR CC-7
Unit One Component Cooling from Primary Sample Cooler
Panel Return Line Check Valves 1CC091B and 1CC092B
Test
2BOL 3.3
LOCAR Post Accident Monitoring (PAM) Instrumentation
Tech Spec LCO # 3.3.3
2BOSR 3.3.1-1
Unit Two Accident Monitoring Instrumentation Monthly
Channel Checks
BAR 2-9-D6
Rx Vessel Lvl Msrment Sys Sensor Uncovered
BOP RC-12
Placing RVLIS/HJTC/CETC in Service
Procedures
BOP RC-12T1
Table 1 RVLIS Error Codes Train A and B
Work Orders
5016218
1BOSR CC-7 Surveillance Failed Leak Rate Test
03/05/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5177731
Perform 1 BOSR CC-7
03/06/2023
Drawings
M-197-3
Reactor Containment Penetration Sleeve Scheduled for
Byron Unit 1
S
Guidance for Temporarily Disconnecting Pipe; Equipment
Anchors, Cutting Pip, and or Disconnection of Flanges
Engineering
Changes
Evaluation of Proceduralized TCCP: BMP 3300-28
Procedures
BMP 3300-28
Installation and Removal of Temporary Containment
Penetration Covers
20978
LLRT For P-74 - Spare
03/20/2023
Work Orders
28280
Containment Temporary Penetration PC074M
03/21/2023
Miscellaneous
BY-MODE-034
TS 3.0.4.b Evaluation - Mode Change with Technical
Specification Equipment Out of Service
1BGP 100-2
Plant Startup
1BGP 100-2A1
Reactor Startup
1BGP 100-3
Power Ascension
107
1BGP 100-3T2
Mode 2 to 1 Checklist
OP-AA-106-101-
1006
Operational Decision Making (ODM) Process
Refuel Outage Management
Outage Scope Control
Procedures
Shutdown Safety Management Program Byron/Braidwood
Annex
Calculations
5.6.1-BYR96-233
Evaluation of Main Steam and Aux-Feedwater Tunnels for
Revised Accident Pressures and Temperatures Associated
with Replacement Steam Generators.
Byron NRC DBAI - Unresolved Issue (URI)
04/16/2021
Corrective Action
Documents
NRC URI: MS Tun & SV Rm Use ACI 349-85 App C
Provisions
05/18/2021
CFR 50.59
Safety Evaluation
UFSAR Revision 1 Final Draft
2/07/1989
Miscellaneous
Safety-Related Concrete Structures for Nuclear Power
Plants (Other than Reactor Vessels and Containments)
Calculations
BYR97-193
Battery Duty Cycle and Sizing for Byron Diesel Driven
Auxiliary Feedwater Pumps and Byron Diesel Driven SX
3A
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M/U Pumps
2B AF PP Gear Changer Aux Oil Pump Cycling
01/12/2023
WO: 1151716-01 1SI8814 Tripper Fingers Not Engaging
03/13/2023
Issue During DG Sequence Testing
03/16/2023
Corrective Action
Documents
1B Aux FW Pump Gear Box Lube Oil Pump Cycling
03/22/2023
Drawings
934D209
Swing Check Valve 10C88
Justification for Not Performing 1FW009A Valve Stroke
Testing After Limited Actuator Reservoir Maintenance per
Work Package 05348724 Exiting B1R25
000
Engineering
Changes
ALT DTL - FW009 Anti-Rotation Bars and Hole for Limit
Switch Plate
000
Engineering
Evaluations
CQD-043914-SR
Calculation for Minimum Flow Velocity for Swing Check
Valves
07/06/1989
1BOSR 0.5-
2.FW.1
Unit One Main Feedwater System Containment Isolation
Valves Full Stroke and Position Indication Test
1BOSR 0.5-
2.SI.2-2.1
Unit One 1SI8802A, 1SI8806, 1SI8809A, 1SI8835, 1SI8840,
1CV8804A, 1SI8811A and 1SI8923A Stroke Test and
Position Indication Test
1BOSR 0.5-
2.SI.3-1
Unit One 1SI8821A, 1SI8812A, 1SI8924, 1SI8807A/B, and
1SI8814 Position Indication Test
1BOSR
0.5.2.SI.1-1
Unit One SI8821A, 1SI8812A, 1SI8924, 1SI8807A/B and
1SI8814 Exercise Test
1BOSR
5.5.8.CV.5-1c
Unit One Comprehensive Inservice Testing (IST)
Requirements for Centrifugal Charging Pump 1CV01PA
1BOSR 6.1.1-8
Unit One Primary Containment Type C Local Leakage Rate
Tests and IST Tests of Primary Sampling System
1BOSR 8.1.11-1
Unit One 1A Diesel Generator Sequencer Test
1BOSR Z.7.a.1
Unit One Auxiliary Feedwater Diesel Engine Starting
Sequence and Overspeed Trip Test
1BVSR 7.1.1-1
Unit 1 Main Steam Safety Valves Operability Test
2BOSR
5.5.8.SI.5-2a
Unit Two Group A Inservice Testing (IST) Requirements for
Safety Injection Pump 2SI01PB
Procedures
2BOSR 7.5.4-2
Unit Two Diesel Driven Auxiliary Feedwater Pump Monthly
Surveillance
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
BMP 3100-5
Limitorque Operator SMB/SMC Removal and Installation
BMP 3112-1
Feedwater Isolation Valve Hydraulic Actuator Maintenance
BMP 3112-2
Main Feedwater Isolation Valve Actuator Filling and
Charging
BMP 3114-21
Main Steam Safety Valve Testing Using Setpoint Verification
Device
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
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
Power)
03/01/2023
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
Motor Drive Auxiliary Feedwater Pump
03/03/2023
5188412
1A Diesel Generator Sequencer Test
03/15/2023
5188424
(NEIL)-1AP01PB Comprehensive IST Requirements for the
Diesel Drive Auxiliary Feedwater Pump
03/03/2023
237710
Diesel Driven Auxiliary Feed Pump Inspection Per BMP
203-1
03/22/2023
5302386
(NEIL) - 2SI01PB Group A IST Requirements for Safety
Injection
01/19/2023
24617-01
2BOSR 7.5.4-2, 2B AF PP Run
01/03/2023
Work Orders
5348724
1FW009A Hydraulic Pressure Low
03/27/2023
BY-1-23-00503
ALARA Plan for RWP BY-1-23-00503, AUX (task 1) and
Containment Insulation (tasks 2).
BY-1-23-00609
ALARA Plan for RWP BY-1-23-00609, Containment Sump
Inspection and Cleaning.
ALARA Plans
BY-1-23-00614
ALARA Plan for RWP BY-1-23-00614, Reactor Head and
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Activities.
Corrective Action
Documents
Resulting from
Inspection
NRC ID: AMS-4 Air Sampler Running with No Digital Display
03/14/2023
Alpha Area Level Assessment for Unit One
04/13/2022
Miscellaneous
Alpha Area Level Assessment for Unit Two
04/15/2021
Procedures
Determination of Alpha Levels and Monitoring
Radiation
Surveys
23-188760
Radiological Survey Map of the Containment Floor Drain
Sump at Elevation 377' in the Containment Building of Unit
One, Map Number 432
03/11/2023
BY-1-23-00503
Auxiliary Building (task 1) and Containment (task 2)
Insulation Radiation Work Permit
BY-1-23-00609
Containment Sump Inspection and Cleaning Radiation Work
Permit
Radiation Work
Permits (RWPs)
BY-1-23-00616
Reactor Coolant Pump Maintenance Activities Radiation
Work Permit
NRC Performance Indicator Data: Initiating Events -
Unit/Reactor Shutdown Occurrences
01/01/2022 -
2/31/2022
NRC Performance Indicator Data: Initiating Events -
Unplanned Power Changes per 7000 Critical Hours
01/01/2022 -
2/31/2022
71151
Miscellaneous
Review of Unit 1 and Unit 2 Plant Process Computer Data
for the Calendar Year 2022
01/01/2022 -
2/31-2022
1RY8010B Failed As-Found Testing at Vendor
09/19/2021
1RY8010A Failed As-Found Testing at Vendor
10/01/2021
U2 Reactor Head Indication - B2R23
04/22/2022
U2 Reactor Head Indication at Penetration-75
04/23/2022
1RY8010C Failed As-Found Testing at Vendor
10/01/2021
Corrective Action
Documents
Investigation into Byron Pressurizer Safety Valves Failed
03/31/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
As-Found Lift Test during B1R24
Engineering
Evaluations
635206
Byron Unit 1 Evaluation of Pressurizer Safety Out of
Tolerance Impact on Safety Analyses
0