IR 05000456/2023004
| ML24032A475 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 02/02/2024 |
| From: | Hironori Peterson NRC/RGN-III/DORS/RPB3 |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| IR 2023004 | |
| Download: ML24032A475 (1) | |
Text
SUBJECT:
BRAIDWOOD STATION - INTEGRATED INSPECTION REPORT 05000456/2023004 AND 05000457/2023004
Dear David Rhoades:
On December 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station. On January 17, 2024, the NRC inspectors discussed the results of this inspection with G. Gugle, 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 Reactor Projects Branch 3 Division of Operating Reactor Safety Docket Nos. 05000456 and 05000457 License Nos. NPF-72 and NPF-77
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000456 and 05000457
License Numbers:
Report Numbers:
05000456/2023004 and 05000457/2023004
Enterprise Identifier:
I-2023-004-0044
Licensee:
Constellation Energy Generation, LLC
Facility:
Braidwood Station
Location:
Braceville, IL
Inspection Dates:
October 01, 2023 to December 31, 2023
Inspectors:
K. Barclay, Senior Reactor Inspector
R. Bowen, Illinois Emergency Management Agency
J. Cassidy, Senior Health Physicist
D. Kimble, Senior Resident Inspector
J. Robbins, Senior Resident Inspector
P. Smagacz, Resident Inspector
P. Zurawski, Senior Resident Inspector
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 Braidwood 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
None.
PLANT STATUS
Unit 1 began the inspection period operating at full power. With the exception of minor reductions in power to support scheduled testing activities and load changes requested by the transmission system dispatcher, the unit remained operating at or near full power for the entire inspection period.
Unit 2 began the inspection period operating at full power. With the exception of minor reductions in power to support scheduled testing activities and load changes requested by the transmission system dispatcher, the unit remained operating 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures during the weeks ending December 2 through December 16, 2023.
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather when thunderstorms were predicted during elevated risk conditions due to 2B Auxiliary Feedwater (AF) Pump maintenance during the week ending October 14, 2023.
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)1B Safety Injection (SI) Train while protected for 1A SI Train maintenance during the week ending October 7, 2023 (2)2A AF Train while protected for 2B AF Train maintenance during the week ending October 14, 2023
- (3) Unit 1 AF after restoration from maintenance of the 1B AF Train during the week ending November 11, 2023
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)
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 11.3A-1, Auxiliary Building 364' Elevation, SI Pump 1A Room during the week ending December 2, 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)
The inspectors observed and evaluated the following licensed operator activities in the main control room:
- (1) Various activities involving on-watch operations crews. These activities included, but were not limited to:
- Observation of selected portions of the operation and loading of the 1B Emergency Diesel Generator (EDG) during the week ending November 11, 2023
- Observation of selected 4160 Vac electrical bus switching operations during the week ending November 11, 2023
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
The inspectors observed and evaluated the following licensed operator training activity:
- (1) A complex casualty evaluated scenario involving a crew of licensed operators was observed in facilitys simulator on November 7, 2023
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
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 continued monitoring and assessment of the 15X55AA piping leakage during the weeks ending November 11 through November 18, 2023
- (2) Maintenance effectiveness review associated with the main Control Room ventilation system during the week ending December 6, 2023
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, performance history, and quality reviews for the 2B AF Pump, with specific emphasis on the diesel engine following identification of unacceptable fuel oil contamination in the engine lubricating oil, as documented in Issue Report (IR) 4703982 during the weeks ending October 7 through October 21, 2023
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 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) Review and evaluation of the risk associated with an emergent Technical Specification (TS) RICT [Risk-Informed Completion Time] for the 2WO056A primary containment isolation valve, as documented in IR 4706461 during the week ending October 7, 2023
- (2) Review and evaluation of the risk associated with an emergent TS 3.7.5 RICT for the 2B AF Pump, as documented in Work Order (WO) 5402459 during the week ending October 14, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Evaluation of the operability of the Unit 1 Power Distribution Monitoring System (PDMS) following identification of anomalous core exit thermocouple readings, as documented in IR 4709877 during the week ending October 28, 2023
- (2) Evaluation of the operability of the excore power range instruments, as documented in IR 4713882 during the weeks ending October 4 through 11, 2023
- (3) Evaluation of the operability of the 2C Steam Generator (SG) Power-Operated Relief Valve (PORV) following identification of a nontypical setup on the installed amplifier module signal conditioner, as documented in IR 4717796 during the week ending November 18, 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) (2 Samples)
- (1) Functional and operational testing of the 2B AF Pump diesel engine following a significant maintenance work window, as documented in WOs 541827 and 5402459 during the weeks ending October 14 through November 4, 2023
- (2) Functional and operational testing of the 1A Containment Spray Pump after cubicle cooler maintenance, as documented in WO 5401820 during the week ending December 16, 2023
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) Semiannual fast start surveillance testing of the 2B EDG, as documented in WO 5383878 during the weeks ending October 21 through October 29, 2023
- (2) Unit 1 Train A Auxiliary Feedwater Quarterly Surveillance, as documented in WO 5408735 during the week ending December 2, 2023
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.
- EP-AA-1001 Addendum 3, Revision 7; 10 CFR 50.54(q)(3) Evaluation No. 21-72: Emergency Action Levels for Braidwood Station of January 20, 2022
- EP-AA-1000: Standardized Radiological Emergency Plan, Revision 33
- EP-AA-1001: Radiological Emergency Plan Annex for Braidwood Station, Revision 35
- EP-AA-1001: Addendum 1 Braidwood Station On-Shift Staffing Technical Basis, Revision 2
- EP-AA-1001: Addendum 3 Emergency Action Levels for Braidwood Station, Revision 7 This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated sites emergency plan by observing the following emergency response organization (ERO) activities:
- (1) The 2023 Braidwood off-year full-scale ERO exercise during the week ending October 7,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1 (October 1, 2022 through September 30, 2023)
- (2) Unit 2 (October 1, 2022 through September 30, 2023)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (October 1, 2022 through September 30, 2023)
- (2) Unit 2 (October 1, 2022 through September 30, 2023)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 1, 2022 through September 30, 2023 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) October 1, 2022 through September 30, 2023
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Review and assessment of the stations corrective actions for recurring 2C SG PORV operability issues, as documented in IRs 4702773, 4704254, 4697594, 4706721, and
===4708650, during the weeks ending October 21 through November 4, 2023
- (2) Review and assessment of the stations corrective actions associated with a pinhole leak on the 10-inch safety-related essential service water (SX) return line 1SX27DA, as documented in IR 4550413-22 during the week ending November 25, 2023 71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)===
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in the EDG Starting Air System that might be indicative of a more significant safety issue during the weeks ending November 4 through December 2, 2023.
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01) (1 Partial)
(1)
(Partial)
Review and assessment of the identification of fuel oil in the 2B AF Pump diesel engine oil system, as documented in IR 4703982 during the weeks ending October 7 through December 16,
INSPECTION RESULTS
Observation: 2MS018C: 2C Steam Generator (SG) Power-Operated Relief Valve (PORV) Operability Issues 71152A The inspectors performed a detailed review of several issue reports (IRs) related to the subject performance problem. These included, but were not limited to:
- IR 4697594, 2MS018C Abnormal Indications; 08/21/2023
- IR 4702773, 2MS018JC Abnormal Indications; 09/15/2023
- IR 4704254, 2MS018C Abnormal Indications; 09/22/2023
- IR 4706721, 2MS018C Abnormal Indications; 10/03/2023
- IR 4716007, 2MS018JC Abnormal Indications (Repeat Issue); 10/07/2023
- IR 4708650, 2MS018C Abnormal; 10/11/2023
- IR 4710584, 2MS018JC Fan Filter Replacement; 10/18/2023
- IR 4717796, 2MS018JC Amplifier Replacement; 11/15/2023
- IR 4719624, 2MS018JC Abnormal Indications (Repeat Issue); 11/26/2023 In late August 2023, the station began experiencing recurring trips of the 2C SG PORV controller, each of which rendered the 2C SG PORV inoperable and necessitated the entry into a 30-day action, leading to a unit shutdown per Technical Specification (TS) 3.7.4. Upon investigation, plant operators noted essentially the same fault indications on the controller with each instance. While the indications pointed to an overtemperature condition within the controller electronics, the condition was able to be reset by operators and rapidly cleared in each case. As the licensee worked through troubleshooting efforts, however, what began as a recurring problem once every 2 to 3 weeks eventually became a recurring issue once every few days.
In mid-October 2023, the licensee identified that the controller electronics cabinet fan filter was nearly completely blocked. Temperatures and airflow within the controller electronics cabinet following replacement of the fan filter immediately improved, and the licensee assumed that the problem had been identified and corrected after several days without another trip of the 2C SG PORV controller.
In late November 2023, the 2C SG PORV controller again tripped, with plant operators noting essentially the same fault indications on the controller as before. At this point, the licensee elected to replace the controller chassis with a new module, which appeared to finally correct the issue.
With the final return of the 2C SG PORV to service, the inspectors examined the licensees corrective actions from the previous several weeks to assess whether outstanding issues and performance problems had been addressed. Several observations by the inspectors were discussed with station management, which included but were not limited to:
- Each instance of the tripping of the 2C SG PORV controller required the station to enter a 30-day action leading to a unit shutdown per TS 3.7.4. While each controller electronics trip was, in actuality, fairly easily and readily cleared by operators via the performance of a manual reset of the controller logic per established plant procedures, each recurrence of the trip carried with it the risk that the controller might actually have failed to be able to be easily reset. Such an eventuality would have placed the station into a more emergent mode of response that potentially could have resulted in a forced unit shutdown, per plant TS. Additionally, each recurrence of the issue required plant operators to stroke test the 2C SG PORV following the resetting of its controller logic in order to positively demonstrate operability prior to exiting the TS 3.7.4 30-day required action. Considering the recurring nature of the 2C SG PORV controller trips, the inspectors questioned whether or not a more aggressive overall troubleshooting effort by the licensee should have been employed.
- The inspectors noted that the licensees identification of the nearly fully plugged controller electronics cabinet fan filter came approximately 2 months after the initial 2C SG PORV controller trip. Given the electronics trip indications pointed to, at least in part, a possible overtemperature condition within the electronics, the inspectors noted that a review of the timeliness of this identification on the part of the licensee might be warranted.
- Following the identification of the nearly completely plugged controller electronics cabinet fan filter and its replacement, the inspectors noted that the licensee quickly concluded that the issue had been corrected. While the inspectors noted that the preponderance of the evidence would seem to have validated this conclusion by the licensee, a review of this decision, with an emphasis on the length of time dedicated to obtaining overall confidence that the issue had been resolved, might also be warranted.
In the course of the inspectors review, no findings or violations of NRC requirements were identified.
Observation: 1SX27DA-10 Pinhole Leak Corrective Actions 71152A On January 25, 2023, a pinhole leak in a 90-degree elbow on the 10-inch essential service water (SX) system return line to the Braidwood cooling lake from the 1A Emergency Diesel Generator (EDG) was discovered by plant operators during a 1A EDG surveillance run. The licensee performed a formal operability evaluation and planned replacement of the affected section of the 10-inch SX line for the next scheduled 1A EDG maintenance work window.
In late September 2023, the 1DX27DA-10 affected elbow was replaced with a new 10-inch carbon steel elbow during a scheduled 1A EDG maintenance period. The removed 10-inch SX elbow was sent by the licensee to their Constellation PowerLabs facility for a detailed failure analysis, which was documented within the licensees Corrective Action Program (CAP) as IR 4550413, Action No. 22, Failure Analysis of 1SX27DA Leak Location, on November 10, 2023. The inspectors chose to perform a detailed review of this licensee analysis, as well as the licensees planned corrective actions for the underlying cause, due to the overall risk significance associated with the SX system and the additional safety significance imposed by the leak locations potential impact on the availability and reliability of the 1A EDG.
The licensees failure analysis concluded that the pinhole through the pipe elbow wall was the result of under-deposit corrosion, with tuberculation pitting. The licensees analysis further concluded that stagnate water conditions favorable for under-deposit pit formation present when the 1A EDG is in a standby condition allowed for an anaerobic (low oxygen)environment to form under the deposit layers at the metal surface and accelerate metal corrosion. No evidence of microbially induced corrosion (MIC) was detected by the licensees PowerLabs facility.
In response to this information, the licensee revisited their original corrective action that replaced the 1DX27DA-10 elbow with a new, like-for-like 10-inch carbon steel elbow, and determined the replacement of the carbon steel elbow with a stainless steel pipe elbow would be more effective at reducing the likelihood of under-deposit corrosion and through-wall penetration. Consequently, future replacements of these similar elbow sections with stainless steel components are planned and appear to be appropriate.
In the course of the inspectors review, no findings or violations of NRC requirements were identified.
Observation: Emergency Diesel Generator Non-Safety Starting Air System 71152S The inspectors performed a review of plant issues, particularly those entered into the licensees corrective action program (CAP) over the past several months. During their review, the inspectors noted that the licensee continues to experience performance issues involving the stations non-safety-related diesel generator starting air systems. Specific CAP entries reviewed by the inspectors included, but were not limited to:
- IR 4714650; 2DG01SB-B Not Working Properly
- IR 4710909; 2B DG Fast Start Time >7.5 sec
- IR 4699075; 1DG01SA-B Cycling Excessively
- IR 4696456; 2-22-C8, 2DG01SB-B O/L Tripped, 2B DG Support System
- IR 4691998; 2DG01SA-B Running Continuously
- IR 4690736; 2B DG Starting Air Compressor #1 Continuously Running
- IR 4689060; Abnormal Starting Air Indication During 2A DG Run
- IR 4683897; 2B DG #2 Air Compressor 2DG01SB-B Tripped Overloads
- IR 4681228; 2B D/G #2 Air Compressor Tripped Thermals
- IR 4538267; 1DG01SA-A, 1A DG #1 Air Compressor Running Continuously The starting air system for each diesel generator consists of two independent and redundant non-safety-related air systems for each emergency diesel generator (EDG). Although not safety-related, they are essential support equipment for the stations EDGs, which are highly risk significant. Each subsystem consists of one compressor, the associated drier assemblies, and all the associated control equipment and interconnecting piping. During normal operation, the air compressors maintain starting air header pressure in the air receiver tanks to start the EDGs and will automatically start if pressure drops too low.
The inspectors reviewed numerous IRs documenting issues with the compressors over the course of the year and the potential effects on operability of the EDGs. Each issue documented required an operability review of the EDGs and corrective maintenance to restore the compressors to a functional status. Although the issues never presented an operability concern at the time they arose, the inspectors noted that the repeat issues stressed operations and maintenance resources and had the capability if left uncorrected to affect the operability of the EDGs.
The inspectors did not identify any findings or violations of NRC requirements in the course of this review.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 17, 2024, the inspectors presented the integrated inspection results to G. Gugle, Site Vice President, and other members of the licensee staff.
- On December 20, 2023, the inspectors presented the emergency action level and emergency plan changes inspection results to D. Edwards, Emergency Preparedness Coordinator, and other members of the licensee staff.
THIRD PARTY REVIEWS As discussed in IMC 0611, Section 13.01, the inspectors completed a review of the report issued by the World Association of Nuclear Operators (WANO) for the most recent periodic plant evaluation completed at the Braidwood Station in August 2023.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4719872
Division 11 MEER Temperature Low
11/27/2023
Corrective Action
Documents
22602
2A SAC Receiver Pressure Low SER 1849 During Cold
Weather
2/10/2023
Miscellaneous
Letter from Greg Gugle, Braidwood Generating Station Site
Vice President, to Marri Marchionda-Palmer, Senior Vice
President of Nuclear Operations Constellation Nuclear,
Certification of 2023-2924 Winter Readiness
11/15/2023
0BwOA ENV-1
Adverse Weather Conditions Unit 0
26
0BwOS XFT-A1
Unit Common Freezing Temperature Equipment Protection
Surveillance
0BwOS XFT-A2a
Unit Common Station Heat Area Heaters Freezing
Temperature Equipment Protection Surveillance
0BwOS XFT-A2b
Unit Common Station Heat Area Heaters Freezing
Temperature Equipment Protection Surveillance
0BwOS XFT-A3
Unit Common Cold Weather Surveillance
0BwOS XFT-A4
Unit Common Freezing Temperature Equipment Protection
Inside Surveillance
BwOP SI-10
RWST Heating Pump and Heater Operations
General Area Checks and Operator Field Rounds
OP-AA-108-111-
1001
Severe Weather and Natural Disaster Guidelines
OP-BR-102-102-
1001
Augmented Operator Field Rounds
Procedures
Seasonal Readiness
BwOP AF-E1
Electrical Lineup - Unit One Operating
BwOP AF-E2
Electrical Lineup - Unit 2 Operating
BwOP AF-M1
Operating Mechanical Lineup Unit 1, Auxiliary Feedwater
BwOP AF-M2
Operating Mechanical Lineup Unit 2
BwOP SI-E1
Electrical Lineup - Unit 1 Operating
Procedures
BwOP SI-M1
Operating Mechanical Lineup Unit 1
Fire Plans
Pre-Fire Plan No.
118
Fire Zone 11.3A-1; Auxiliary Building 364' Elevation, Safety
Injection Pump 1A Room
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Pre-Fire Plan No.
135
Fire Zone 11.4A-0; Auxiliary Building 383' Elevation Control
Room, Refrigeration Equipment Room
BwAP 1110-1
Fire Protection System Requirements
Pre-Fire Plan Manual
Procedures
Control of Transient Combustible Material
OP-AA-101-111-
1001
Operations Standards and Expectations
Operator Fundamentals
OP-AA-101-113-
1006
4.0 Crew Critique Guidelines
Watch-Standing Practices
OP-AA-103-102-
1001
Strategies for Successful Transient Mitigation
Operation of Plant Equipment
Communications
Operating Narrative Logs and Records
Reactivity Management
Systematic Approach to Training Process Description
Operator Training Programs
Conduct of Simulator Training and Evaluation
Examination Security and Administration
Simulator Management
Procedures
TQ-BR-201-0113
Braidwood Training Department Simulator Examination
Security Actions
4348354
0VA01CC Vibration Analysis Results
06/05/2020
4388101
A Train VC Heaters Not Functioning Properly
2/04/2020
29807
0TIC-VC086 Not Maintaining MCR Temperature
10/16/2022
4548411
0VC05FB Charcoal Test Canister Depleted
01/13/2023
Corrective Action
Documents
22049
2/07/2023
Maintenance Rule FunctionsSafety Significant Classification
Maintenance Rule 18-10Scoping
Maintenance Rule 18.10Failure Definitions
Procedures
Maintenance Rule 18-10Performance Monitoring and
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Dispositioning Between (a)(1) and (a)(2)
ER-AA0320
Maintenance Rule Implementation per NEI-18-10
Corrective Action
Documents
4706461
2WO56A Open Light Indication Lost
10/02/2023
Miscellaneous
Final RICT Record for 2B Auxiliary Feedwater Pump Diesel
Engine Bearing Inspections/Replacements Maintenance
Window
10/16/2023
Risk Management
PARAGON Model Capability
On-Line Risk Management
Risk Management Support of RICT
Calculation of RMAT and RICT for Risk Informed Completion
Time Program
ER-BW-600-2001
Braidwood RICT System Guidelines
Integrated Risk Management
Protected Equipment Program
Risk Informed Completion Time
Procedures
On-Line Risk Management and Assessment
Work Orders
5404748
2WO056A Open LIght Indication Lost
10/17/2023
4709877
Unexpected Annunciators 1-10-D7 and 1-10-E7
10/16/2023
Corrective Action
Documents
4713882
Unexpected Alarm, 2-10-B4 Power Range Lower Detector
Flux Deviation High
10/31/2023
1BwOS PDMS-1a
AAR Power Distribution Monitoring System (ODMS)
1BwOS TRM
3.3.h.1
Unit One Power Distribution Monitoring System (PDMS)
Operability Weekly Surveillance
Procedures
BwOP RC-12
Placing RVLIS/HJTC/CETC in Service
4704174
Abnormalities Stroking 1AF004A (1BwOSR 5.5.8.AF-3A)
09/21/2023
4710909
2B EDG Fast Start Time >7.5 sec
10/19/2023
4719810
1AF022A Close Limit Switch Needs Replacement
11/27/2023
Corrective Action
Documents
4719814
1AF024 Indication Limit Switch Needs Adjustment
11/27/2023
1BwOSR
5.5.8.AF-3A
Group A IST Requirements for Unit One Motor Driven Auxiliary
Feedwater Pump
Procedures
1BwOSR
Comprehensive Full Flow Test for 1A Containment Spray
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5.5.8CS-3A
Pump (1CS01PA) and Check Valves 1CS003A, 1CS011A)
2BwOSR 3.8.1.2-
Unit Two 2B Diesel Generator Operability Surveillance
2BwOSR
5.5.8.AF-3B
Group A IST Requirements for Unit Two Diesel Driven
Auxiliary Feedwater Pump
5383878
2B EDG Operability Monthly
10/19/2023
5401820
OP ASME Surveillance on Unit 1 Train A Containment Spray
(1CS01PA)
2/06/2023
5401827
Unit 2 Diesel Driven Auxiliary Feedwater Pump Monthly Run
10/14/2023
5402459
Post-Maintenance Testing 2AF01PB: Perform ASME and
Verify No Leaks
10/13/2023
5404667
2B Diesel Generator Operability Semi-Annual Surveillance
10/19/2023
Work Orders
5408735
Unit 1 Motor Driven Auxiliary Feedwater Pump ASME
Quarterly Surveillance
11/27/2023
Calculations
Addendum 3
Revision: 7
Evaluation No.:
21-72
§50.54(q) Program Evaluation/Assessment Review:
Emergency Action Levels for Braidwood Station
01/20/2022
Standardized Radiological Emergency Plan
Radiological Emergency Plan Annex for Braidwood Station
Addendum 1
Braidwood Station On-Shift Staffing Technical Basis
Procedures
Addendum 3
Emergency Action Levels for Braidwood Station
Miscellaneous
23 Braidwood Off Year Exercise Scenario
10/03/2023
Standardized Radiological Emergency Plan
Radiological Emergency Plan Annex for Braidwood Station
Procedures
Addendum 3
Constellation EP-AA-1001 Addendum 3
NRC Performance Indicator Data; Barrier Integrity - RCS
Identified Leakage
10/01/2022-
09/30/2023
71151
Miscellaneous
Monthly Data Elements for NRC ROP Indicator - Reactor
Coolant System (RCS) Specific Activity
various
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Monthly Data Elements for NRC ROP Indicator - Occupational
Exposure Control Effectiveness
various
Monthly Data Elements for NRC ROP Indicator - RETS/ODCM
Radiological Effluent Occurrences
various
Collecting and Reporting of NRC Performance Indicator Data
Procedures
Monthly Data Elements for NRC Reactor Coolant System
(RCS) Leakage
4550393
Leak on Underside of Piping Just Downstream of 1SX057A
01/25/2023
4550412
Trend in SX System Leaks
01/25/2023
4551315
Scope Expansion Inspections on 1SX27DB-10'
01/30/2023
4551316
Scope Expansion Inspections on 2SX27DA-10'
01/30/2023
4551318
Scope Expansion Inspections on 1SX26AB-10"
01/30/2023
4551319
Scop Expansion Inspections on 1SX26AA-10'
01/30/2023
4555829
Review of UT [Ultrasonic Testing] Data from 2SX27DA-10'
2/20/2023
4697594
2MS018JC Abnormal Indications
08/21/2023
4702773
2MS018JC Abnormal Indications
09/15/2023
4704254
2MS018JC Abnormal Indications
09/22/2023
4706721
2MS018JC Abnormal Indications
10/03/2023
4708516
Review of 10/5/23 UT [Ultrasonic Testing] Follow Up Data
from 2SX27DA-10'
10/10/2023
4708650
2MS018JC Abnormal
2/11/2023
4710584
2MS018JC Fan Filter Replacement
10/18/2023
4716007
2MS018JC Abnormal Indications (Repeat Issue)
10/07/2023
4717796
2MS018JC Amplifier Replacement
11/15/2023
Corrective Action
Documents
4719624
2MS018JC Abnormal Indications (Repeat Issue)
11/26/2023
BwOP MS-14
Resetting of the Steam Generator Power Operated Relief
Valve
Quality Assurance Topical Report (QATR)
Issue Identification and Screening Process
Corrective Action Program (CAP) Procedure
Root Cause Analysis Manual
Corrective Action Program Evaluation Manual
Procedures
Effectiveness Review Manual 2NO-AA-10
Q
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5310334-04
Replace 2C PORV Controller PWM Chassis with New
11/30/2023
Work Orders
Action No. 22
Failure Analysis of 1SX27DA Leak Location
11/10/2023
4538267
1DG01SA-A, 1A DG #1 Air Compressor Running Continuously
11/22/2022
4681228
2B D/G #2 Air Compressor Tripped Thermals
05/29/2023
4683897
2B DG #2 Air Compressor 2DG01SB Tripped Overloads
06/10/2023
4689060
Abnormal Starting Air Indication During 2A DG Run
07/06/2023
4690736
2B DG Starting Air Compressor #1 Continuously Running
07/15/2023
4691998
2DG01SA-B Running Continuously
07/22/2023
4696456
2-22-C8 2DG01SB O/L Tripped, 2B DG Support System
08/15/2023
4699075
1DG01SA-B Cycling Excessively
08/29/2023
4710909
2B DG Afast Start Time >7.5 sec
10/19/2023
Corrective Action
Documents
4714650
2DG01SB Not Working Properly
11/02/2023
238259
1AF01PB Crankcase Oil Analysis Degrading Trend
04/10/2019
4703982
Degraded Oil in 2B Diesel-Driven Auxiliary Feedwater
(2AF01PB) Engine Crank Case
09/21/2023
4704473
2AF01PB - 5L Return Line Leaking
09/23/2023
4704480
2AF01PB - 2R Ruel Return Line Leaking
09/23/2023
4706623
Review of 2B AF Pump Oil Results
10/02/2023
4708247
Review of 2B AF Pump Oil Results
10/09/2023
4708461
2B AF Main Bearing Degraded
10/10/2023
4708525
2B AF Pump 3L Fuel Injector Leaking
10/10/2023
4708613
Inspect/Repair Fuel Leak Visually Identified Abnormality
10/10/2023
4708713
2B Auxiliary Feedwater Removed Fuel Injector on No. 3 Left
10/11/2023
4709470
1B AF Pump Extent-of-Condition Fuel Dilution Review Results
10/13/2023
Corrective Action
Documents
4709534
2AF01PB Rocker Cover Leaks
10/14/2023
Corrective Action
Documents
Resulting from
Inspection
4706606
Information in 2B AF Vendor Manual and Oil Sample
10/02/2023
Miscellaneous
Various Bureau Veritas (VEndor) Lube Oil Analysis
Management System (LOAMS) Reports for the 2B AF Diesel
Engine (2AF01PB)
03/10/2023-
2/14/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Detroit Diesel
Series 149
Engine Service
Manual
08/1997
2BwOS TRM
2.7.a.1
Unit Two Auxiliary Feedwater Diesel Prime Mover
Performance Surveillance
2BwOSR 3.7.5.4-
Unit Two Diesel Driven Auxiliary Feedwater Pump
Surveillance
BwMP 3200-014
Auxiliary Feedwater Pump Diesel Drive Unit Inspection and
Maintenance
BwOP AF-300
Sampling Auxiliary Feedwater Diesel Lube Oil (AF01PB)
BwOP AF-7
Auxiliary Feedwater Pump B (Diesel) Startup on Recirc
Predictive Maintenance Program
MA-AA-716-230-
1001
Oil Analysis Interpretation Guideline
Procedures
MA-AA-716-230-
1004
Lubricant Sampling Guideline
1865780
2AF01PB-K 12-Year Preventative Maintenance (PM) for
Auxiliary Feedwater Diesels
05/01/2023
230646
2AF01PB - Perform 18-Month Inspection
04/28/2023
5350643
Unit 2 Diesel-Driven Auxiliary Feedwater Pump ASME
Quarterly Surveillance
05/19/2023
5371917
Unit 2 Diesel-Driven Auxiliary Feedwater Pump Monthly Run
06/08/2023
5378877
Unit 2 Diesel-Driven Auxiliary Feedwater Pump Monthly Run
07/14/2023
5379233
Unit 2 Diesel-Driven Auxiliary Feedwater Pump ASME
Quarterly Surveillance
09/01/2023
5385077
Unit 2 Diesel-Driven Auxiliary Feedwater Pump Monthly Run
08/10/2023
5402459-01
Mechanical Maintenance: Change Oil in 2AF01PB Crank Case
09/22/2023
5402459-03
Mechanical Maintenance: 2AF01PB - Repair Suspected Fuel
Leak
09/22/2023
5402459-09
Mechanical Maintenance: 2AF01PB - Inspect Main Crank
Shaft Bearings
10/09/2023
Work Orders
5402959-13
Mechanical Maintenance: 2AF01PB - Inspect/Repair Fuel
Leak
10/09/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5402959-18
Operations: Perform 2AF01PB Engine Break-In Following
Maintenance
10/13/2023