IR 05000456/2021003
| ML21299A077 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/26/2021 |
| From: | Hironori Peterson Region 3 Branch 3 |
| To: | Rhoades D Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2021003 | |
| Download: ML21299A077 (24) | |
Text
SUBJECT:
BRAIDWOOD STATION - INTEGRATED INSPECTION REPORT 05000456/2021003 AND 05000457/2021003
Dear Mr. Rhoades:
On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station. On October 13, 2021, the NRC inspectors discussed the results of this inspection with Mr. J. Keenan, the Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Hironori Peterson, Chief Branch 3 Division of Reactor Projects Docket Nos. 05000456 and 05000457 License Nos. NPF-72 and NPF-77
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000456 and 05000457
License Numbers:
Report Numbers:
05000456/2021003 and 05000457/2021003
Enterprise Identifier:
I-2021-003-0059
Licensee:
Exelon Generation Company, LLC
Facility:
Braidwood Station
Location:
Braceville, IL
Inspection Dates:
July 01, 2021 to September 30, 2021
Inspectors:
B. Bartlett, Senior Operations Engineer
G. Edwards, Health Physicist
D. Kimble, Senior Resident Inspector
J. Nance, Operations Engineer
N. Shah, Project Engineer
P. Smagacz, Resident Inspector
Approved By:
Hironori Peterson, Chief
Branch 3
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at 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. On September 16, 2021, the unit reached the end of the fuel cycle and power coast down operations commenced in preparation for a planned refuel outage. The unit continued to reduce power in accordance with the licensees approved reactivity management plan, and was operating at approximately 91 percent power at the end of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on-site as local COVID-19 conditions permitted.
As part of their on-site activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial physical alignment verifications of the following systems/trains:
(1)1A Residual Heat Removal (RH) Train during 1B RH Train maintenance during the week ending July 24, 2021.
(2)1B Safety Injection (SI) Train during 1A SI Train maintenance during the week ending August 28, 2021.
(3)2A Station Air Compressor during replacement of the Unit 0 Station Air Compressor replacement during the week ending September 4, 2021.
(4)2A Auxiliary Feedwater (AF) Train during 2B AF Train maintenance during the week ending September 11, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting physical inspections and reviews to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Units 1 and 2 Auxiliary Building, 346' Elevation, General Area, during the week ending August 7, 2021.
- (2) Units 1 and 2 Auxiliary Building, 330' Elevation, 1A and 2A Essential Service Water (SX) Pump Room, during the week ending August 7, 2021.
- (3) Units 1 and 2 Auxiliary Building, 330' Elevation, 1B and 2B SX Pump Room, during the week ending August 7, 2021.
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (2 Samples)
The inspectors evaluated internal flooding mitigation protection features in the following plant areas:
- (1) Unit 1 Auxiliary Building, 330', 346', and 364' Elevations, during the week ending August 7, 2021.
- (2) Unit 2 Auxiliary Building, 330', 346', and 364' Elevations, during the week ending August 7, 2021.
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam and biennial written examination administered from August 9, 2021 through September 17, 2021.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered between August 9, 2021 and September 17, 2021.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.
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 control room:
- (1) Various activities involving on-watch operations crews. These activities included, but were not limited to:
End-of-cycle reactivity maneuvers leading into Unit 2 coast down operations for the A2R22 refuel outage during the week ending September 18, 2021.
4,160 Vac electric plant maneuvers in support of emergency diesel generator testing during the week ending September 18, 2021.
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 graded scenario involving a crew of licensed operators was observed in facility's simulator on September 7, 2021.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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 and performance history review of the Direct Current (DC)
Batteries and Distribution System during the weeks ending August 21 through August 28, 2021.
- (2) Maintenance effectiveness and performance history review of nuclear instrumentation during the week ending August 28, 2021.
- (3) Maintenance effectiveness and performance history review of Overpower Delta Temperature (OPDT) components during the weeks ending September 4 through September 30, 2021.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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 activities and risk associated with emergent troubleshooting and repairs to the 1A Emergency Diesel Generator (EDG), as documented in Issue Report (IR) 4437474 during the week ending July 31, 2021.
- (2) Evaluation of the work activities and risk associated with planned maintenance on the 1B SI Recirculation Isolation Valve, 1SI8920, in conjunction with emergent work on 1HD026A, the 12A Feedwater Heater Normal Level Control Valve, during the week ending September 18, 2021.
- (3) Evaluation of the work activities and risk associated with several concurrent planned work activities, including acceptance testing for the 1A Station Air Compressor, 1A EDG monthly operability testing, 1A RH Train operability testing, and 2A Containment Spray Train operability testing during the week ending September 30, 2021.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples 1 Partial)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Evaluation of the availability of the 2B Start Up Feedwater Pump due to low oil pressure, as documented in IR 4428965 during the weeks ending July 10 through August 14, 2021.
- (2) Evaluation of the operability of the 2B RH system due to boric acid leakage on the 2FIS-0611 Recirculation Valve Controller, as documented in IR 4436953 during the weeks ending July 31 through August 14, 2021.
- (3) Evaluation of the operability of the 1A EDG after a failure to start during a monthly surveillance, as documented in IR 4437474 during the weeks ending August 7 through September 18, 2021.
- (4) Evaluation of the operability of the 2A EDG following identification of a sheared bolt associated with the 4L cylinder air manifold, as documented in IR 4443522 during the weeks ending September 4 through September 25, 2021.
(5)
(Partial)
Continued evaluation of the operability of the source range nuclear instruments with their high flux trips bypassed during reactor startup, as documented in IR 4418688 during the weeks ending July 1 through September 25, 2021.
- (6) Review of Unit 1 Core Exit Thermocouple (CETC) operability following several issues, as documented in IRs 4419609, 4420610, and 4423740 during the weeks ending September 25 through September 30, 2021.
- (7) Review of the 0B Auxiliary Building Nonaccessible Area (NAC) Exhaust Filter Plenum Ventilation Train operability following identification of testing equipment being left installed since May 2021, as documented in IR 4447805 during the weeks ending July 10 through September 30, 2021.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Testing of the 1SI8920 Mini-Flow Recirculation Valve after maintenance, as set forth in Work Order (WO) 4904903 during the week ending September 18, 2021.
- (2) Comprehensive functional and operational acceptance testing of the 1A Station Air Compressor following replacement and installation, as documented in station procedure SPP-21-002 during the weeks ending September 25 through September 30, 2021.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)2BwOSR 3.8.1.2-1, Technical Specification operability surveillance for the 2A EDG, during the weeks ending August 7 through August 14, 2021.
- (2) BwIP 2500-070, calibration of the 2B Steam Generator main steam atmospheric relief valve control loop, during the week ending August 14, 2021.
Inservice Testing (IP Section 03.01) (1 Sample)
(1)2BwOSR 5.5.8.RH, inservice testing for the 2B RH Train, during the weeks ending August 14 through August 21, 2021.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
Eval No. 20-71 Emergency Action Levels for Braidwood Station, EP-AA-1001, Addendum 3 This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
The inspectors evaluated the following select emergency preparedness (EP) drill:
- (1) Observation and evaluation of the station's Emergency Response Organization during the performance of a full-scale site-wide EP drill on August 2, 2021.
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated the following EP drill/training evolution:
- (1) Review of the implementation of the site's emergency plan by a crew of licensed operators during an evaluated emergency scenario in the facility's simulator on September 7,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Calibration and Testing Program (IP Section 03.02) (6 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Thermo Fisher RO20 SN#0013941
- (2) Eberline Model 3 SN#0017854
- (3) Ludlum 177 SN#0025821
- (4) Thermo Fisher RO20 SN#0018388
- (5) Eberline Model 3 SN#0014351
- (6) Ludlum 3030P SN#0015022
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
& Transportation
Radioactive Material Storage (IP Section 03.01)
- (1) Inspectors evaluated the licensees performance in controlling, labeling, and securing radioactive materials. This included the radioactive waste storage portion of the facility.
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
- (1) Inspectors walked down accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality.
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
- (1) The inspectors evaluated the licensees characterization and classification of radioactive waste. This included the resin waste streams at the facility.
- (2) The inspectors evaluated the licensees characterization and classification of radioactive waste. This included the dry activated waste (DAW) stream at the facility.
Shipment Preparation (IP Section 03.04) (1 Sample)
- (1) The inspectors observed that a shipment containing radioactive material is prepared according to requirements. The shipment identification number was RWS21-015 for seven B-25 Boxes of Condensate Polish Resin shipped on August 17, 2021.
Shipping Records (IP Section 03.05) (3 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) Shipment RWS21-001 UN3321 LSA-II; Resin Liner P0695283-14 in Cask 14-215.
- (3) Shipment RWS20-018 UN2916 Type (B) Package; Resin Liner PO 692200-4.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors reviewed and verified selected portions of the licensee's performance indicator submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) Unit 1 (July 1, 2020 through June 30, 2021)
- (2) Unit 2 (July 1, 2020 through June 30, 2021)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2020 through June 30, 2021)
- (2) Unit 2 (July 1, 2020 through June 30, 2021)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (July 1, 2020 through June 30, 2021)
- (2) Unit 2 (July 1, 2020 through June 30, 2021)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors conducted in-depth reviews of the licensees implementation of the CAP related to the following issues:
- (1) Review and assessment of the corrective actions for the spent fuel dry cask storage (DCS) system forced helium drying errors, as documented in IR 4364058 during the weeks ending August 7 through August 14, 2021.
- (2) Review and assessment of the corrective actions for the 1/2CC202B wrong unit valve operation, as documented in IR 4434922 during the weeks ending July 17 through September 30,
INSPECTION RESULTS
Observation: Forced Helium Drying Skid Issue During Dry Cask Processing 71152 The inspectors performed a detailed review of IR 4364058, Forced Helium Drying Skid Issue. Specifically, on August 19, 2020, a reactor services crew connected hoses incorrectly in preparation for Multi-Purpose Cannister (MPC) blowdown, resulting in an increased risk of the cask being over-pressurized due to bulk water boiling inside the cask. The inspectors chose this issue for an in-depth review of the licensee's actions within their corrective action program (CAP) due to the potential of cask failure and damage to the integrity of the fuel stored within the cask. Consequently, for this detailed Problem Identification and Resolution inspection sample, the inspectors focused on assessment of the licensee's corrective actions taken to address this condition.
The licensees evaluation concluded that the direct cause was the failure by the fuel handlers to verify that the correct hoses were properly attached to the MPC prior to starting work.
Contributing to this were inappropriate actions taken by supervision overseeing the work activities, in part, due to a culture of not reinforcing expectations for using human performance tools during previous work activities and workers not effectively challenging supervision when faced with potential issues.
Corrective actions included, but were not limited to, revising procedures to use color coded hoses to ensure correct connections and requiring that supervisors sign off on specific, key steps to ensure proper system setup. Additionally, coaching/training was provided to ensure fuel handling supervision understood the expectations for performing work observations and in how to identify and correct key behaviors. Further, fuel handling management verified the efficacy of these actions by holding monthly meetings to evaluate the observations performed and proffer feedback on their effectiveness.
The inspectors review did not identify any issues of note with the corrective actions taken; however, their effectiveness could not be confirmed as the licensee had not performed any cask handling activities since implementation.
No findings or violations of NRC requirements were identified by the inspectors in the course of this review.
Observation: 1/2CC202B Wrong Unit Error 71152 The inspectors performed a detailed review of IR 4434922, Level 4 Configuration Control - Received Unexpected Alarm 1-2-E3. The issue involved the mistaken operation of 1CC202B, Motor-Operated Valve (MOV) 1B SX to CC Makeup Downstream Isolation, during what was planned to have been a post-maintenance stroke test of 2CC202B, MOV 2B SX to CC Makeup Downstream Isolation, on July 14, 2021. The inspectors determined that the mistaken operation of 1CC202B instead of the planned and briefed 2CC202B had constituted a violation of the requirements of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings. However, because the SX to Component Cooling (CC)emergency makeup line on each unit is protected from the effects of inadvertent valve operation by the use of two MOVs in series, the mistaken operation of the 1CC202B valve instead of the intended 2CC202B valve did not result in any adverse consequences.
Subsequently, the inspectors concluded that the violation had not adversely impacted the Reactor Safety Mitigating Systems Cornerstone objective and, therefore, constituted a violation of minor significance that was not subject to formal actions per Section 2.3.1 of the NRC Enforcement Policy.
The inspectors chose this issue for an in-depth review of the licensees actions within their CAP because of the inherent risk associated with wrong unit/wrong component operational errors. Consequently, for this detailed Problem Identification and Resolution inspection sample, the inspectors focused on assessment of the licensees corrective actions taken both for this specific error, as well as those targeted at the more generic issue of preventing wrong unit/wrong component operational errors.
The inspectors did not identify any issues with the licensees CAP actions taken. Actions targeting the more generic issue of wrong unit/wrong component operational errors were focused on reinforcing existing human performance tool use and appreciation by the workforce. Actions targeting this specific event included painting the control panels for the MOV hand switches involved in this event with the appropriate unit-specific color scheme - yellow for Unit 1 and green for Unit 2. At the time of the event, all of the control panels involved, all of which are located in the same physical area of the station, were painted with a non-distinct color.
No findings or violations of NRC requirements of more than minor safety significance were identified by the inspectors in the course of this review.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 13, 2021, the inspectors presented the integrated inspection results to Mr. J. Keenan, Site Vice President, and other members of the licensee staff.
On July 15, 2021, the inspectors presented the radiation protection inspection results to Mr. J. Keenan, Site Vice President, and other members of the licensee staff.
On August 20, 2021, the inspectors presented the radiation protection inspection results to Mr. J. Keenan, Site Vice President, and other members of the licensee staff.
On August 20, 2021, the inspectors presented the biennial requalification inspection results inspection results to Mr. J. Keenan, Site Vice President, and other members of the licensee staff.
On October 1, 2021, the inspectors presented the EPlan and EAL Change Inspection Exit inspection results to Mr. D. Moore, Senior Manager, Emergency Preparedness, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
29000
SA SAC (2SA02C) Oil Temperature High
06/12/2021
4436087
1RH8729A Lock Issues
07/20/2021
4436735
2SA02C Oil Temperature High
07/23/2021
4437788
2SA02C Margin Improvement Initiative
07/29/2021
4443172
2SA01C FNL I/S Temperature is High
08/28/2021
Corrective Action
Documents
BwOP RH-M1
Operating Mechanical Lineup Unit 1 1A RH Train
BwOP AF-E2
Electrical Lineup Unit 2 Operating
BwOP AF-M2
Operating Mechanical Lineup, Auxiliary Feedwater, Unit 2
BwOP RH-E1
Electrical Lineup Unit 1 Operating
BwOP SA-E2
Electrical Lineup Unit 2 Station Air System Operating
BwOP SA-M2
Operating Mechanical Lineup Unit 2
BwOP SI-E1
Electrical Lineup Unit 1 Operating
Procedures
BwOP SI-M1
Operating Mechanical Lineup Unit 1
Pre-Fire Plan No.
101
Fire Zone 11.2-0; Auxiliary Building 346' Elevation,
Auxiliary Building General Area South
Pre-Fire Plan No.
Fire Zone 11.1A-0; Auxiliary Building 330' Elevation, Unit 1
Auxiliary Building Basement (1A/2A SX)
Pre-Fire Plan No.
Fire Zone 11.1B-0; Auxiliary Building 330' Elevation, Unit 2
Auxiliary Building Basement (1B/2B SX)
Pre-Fire Plan No.
Fire Zone 11.2-0; Auxiliary Building 346' Elevation,
Auxiliary Building General Area Center
Fire Plans
Pre-Fire Plan No.
Fire Zone 11.2-0; Auxiliary Building 346' Elevation,
Auxiliary Building General Area North
BwAP 1110-1
Fire Protection Program System Requirements
BwAP 1110-3
Plant Barrier Impairment Program
BwOP PBI-1
Plant Barrier Impairment Program Pre-Evaluated Barrier
Matrix
Plant Barrier Control Program
High-Risk Fire Area Identification
Procedures
ER-BR-600-1069
Site List of High-Risk Fire Areas Braidwood Unit 1 and
Unit 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Pre-Fire Plan Manual
Control of Transient Combustible Material
Operations On-Line Fire Risk Management
Auxiliary Building Flood Level Calculation
Confirmation of Safe Shutdown Capability After Auxiliary
Building Flooding
Calculations
Auxiliary Building Flood Level Calculations
4355236
The Plug for the 0TR19P (Lime Sludge West Lagoon Sump
Pump) is Damaged and Needs to be Replaced
08/07/2020
4366140
Unexpected Alarm 1-1-A2 Containment Drain Leak
Detection Flow High
08/29/2020
4391353
0TR19P WWT West Lime Sludge Lagoon #2 Sump Pump is
Degraded
2/20/2020
4405498
SD-191 Discrepancy During Watertight Door Surveillance
03/01/2021
4418893
WO 01785089-09 Stud Missing for Re-Installation of Flood
Seal
04/25/2021
22795
Procedural Guidance for Setting Cable Vault Sump Pumps
05/11/2021
27580
IAM for Sump Pump 0CP05P WO 5157026-01
06/04/2021
28760
Received the Unit 1 SX Sump Level High High Alarm
06/11/2021
Corrective Action
Documents
4438648
Door Operator Loose on Unit 2 SX Pump Room
08/03/2021
BB-PRA-012
Byron and Braidwood Probabilistic Risk Assessment,
Internal Flood Evaluation Summary Notebook
Miscellaneous
Guidelines for Performing Verification Walkdowns of Plant
Flood Protection Features
0BwOA PRI-8
Auxiliary Building Flooding Unit 0
Procedures
Structures Monitoring
1860257
1DSFO06/08 Outage Flood Seals Surveillance
03/03/2017
1915060
2DSFSO06/08 Outage Flood Seals Surveillance
10/18/2017
4838070
Remove/Replace Flood Seal Covers
1DSFSO07 & 09 Auxiliary Feedwater Tunnel Outage
03/25/2020
Work Orders
5079981
Watertight Door Inspection
03/18/2021
4340246
4.0 Critique for Recent and Ramps
05/012020
Corrective Action
Documents
4398670
4.0 Critique U0 CC Heat Exchanger Side Drain Down
01/28/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4418688
Level 3 Configuration Control SRNI's Required Function
Bypassed
04/24/2021
4430586
4.0 Critique U1 Reactor Trip Due to Generator Load Reject
06/21/2021
Corrective Action
Documents
Resulting from
Inspection
4441641
NRC Identified Unattended Exam Material
08/19/2021
Fire Plans
Simulator Post
Event Testing
03/05/2020
Simulator Post
Event Testing
1A MFP Start
11/06/2019
Simulator Post
Event Testing
2CC130 Issues / Drop 7 failure
07/23/2021
Simulator Post
Event Testing
2CV131 - Securing Letdown Evolution
07/14/2021
Simulator Post
Event Testing
Unit 2A MFP Start 12/7/2020
2/10/2021
ATT 10 PWR Moderator Temperature Coefficient of
Reactivity, Cycle 23 Compare to Plant Startup Data
04/29/2021
ATT 10 PWR Moderator Temperature Coefficient of
Reactivity Cycle 23 New Core Test
04/27/2021
ATT 11 PWR Rod Worth Coefficient of Reactivity Cycle 23
New Core Test
04/27/2021
ATT 12 PWR Boron Coefficient of Reactivity Cycle 23,
New Core Test
04/27/2021
ATT 13 PWR Xenon Worths Cycle 23, New Core Test
04/27/2021
ATT 16 PWR Approach to Criticality Using Boric Acid
Cycle 23, Comparison to Plant Data
04/29/2021
ATT 16 PWR Approach to Criticality Using Boric Acid
Cycle 23, New Core Test
04/27/2021
ATT 17 PWR Approach to Criticality Using Rods Cycle 23,
New Core Test
04/27/2021
Miscellaneous
TQ-BR-0115
Transient 10, Slow Primary Depressurization Due to Open
PORV w/o Charging Pumps
03/22/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
TQ-BR-302-0103
Braidwood Steady State Testing 100% and 75%
03/05/2020
TQ-BR-302-0103
FW/CV Letdown System Tuning 49%
03/05/2020
TQ-BR-302-0106
Transient Test - 1, Manual Reactor Trip
03/22/2021
TQ-BR-302-0107
Transient Test 2, Simultaneous Trip of All Main Feedwater
Pumps
03/22/2021
TQ-BR-302-0108
Transient Test 3, Simultaneous Closure of All Main Steam
Isolation Valves
03/22/2021
TQ-BR-302-0109
Transient Test 4, Simultaneous Trip of All Reactor Coolant
Pumps
03/22/2021
TQ-BR-302-0110
Transient Test 5, Trip of Any Single Reactor Coolant Pump
03/22/2021
TQ-BR-302-0111
Transient Test 6, Turbine Trip
<P-8
03/22/2021
TQ-BR-302-0112
Transient 7, Maximum Ramp Rate (100% to 75% to 100%)
03/22/2021
TQ-BR-302-0113
03/22/2021
TQ-BR-302-0114
Transient 9, Maximum Size Main Steam Line Rupture
03/22/2021
TQ-BR-302-0116
Maximum Design Load Reject
03/22/2021
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
Self-Assessments
Differences Between Braidwood Simulator and Braidwood
Unit 1
SRB 21-2
Work Orders
Open Service Work Requests
08/16/2021
OP-AA-101-111-
1001
Operations Standards and Expectations
Operator Fundamentals
OP-AA-101-113-
1006
4.0 Crew Critique Guidelines
Watch-Standing Practices
Procedures
OP-AA-103-102-
1001
Strategies for Successful Transient Mitigation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operation of Plant Equipment
Communications
Operating Narrative Logs and Records
Reactivity Management
1451512
Unit 2 Core Exit Thermocouple Nozzle 77 Connections
Swapped Affecting Indications
2/12/2012
4370362
Recurring Equipment Reliability Issue Unit 1 D
Incore Detector
09/18/2020
4393580
Hairline Cracks in Tops of Battery Cells (1DC02E)
01/03/2021
4402276
Battery 211 Terminal Voltage High Out of Admin Limit
2/14/2021
4402279
Battery 112 Quarterly Temp Deviation High Out of Admin
Limit
2/14/2021
4403966
1D Incore Detector Issues
2/22/2021
4411770
Failed Post-Maintenance Test 1D Incore
03/26/2021
4413950
Battery 211 Has Cap Broken on Cell 56
04/04/2021
4418835
1BwOS TRM 3.3.H.1 Failed Symmetric Core Exit
Thermocouple Temperature Limits
04/25/2021
4419609
Unit 1 Core Exit Thermocouple Nozzle 74 Connections
Swapped Affecting Indications
04/28/2021
21778
Unexpected Alarms 1-10-A5 and 1-114-A1 for OPDT
05/05/2021
23740
Unit 1 Core Exit Thermocouples Exceed Allowed Maximum
Deviation
05/15/2021
25470
DC111 Cracked Battery Cells
05/25/2021
4436872
Pilot Cell for Battery 112 Specific Gravity Found Low
07/25/2021
4439676
Summary of Findings from Braidwood Unit 1 Source Range
Nuclear Instrument Cable Testing
08/09/2021
4440617
Unexpected BwAR 1-10-C3 Poer Range Flux Rate Trip Alert
for N41
08/13/2021
4440747
Battery 111 Average Cell Temp High
08/15/2021
Corrective Action
Documents
4441987
Unexpected Alarms 1-10-A5 and 1-14-A1 for 1C OPDT
08/22/2021
Operability
Evaluations
Maintenance Rule 18-10 Scoping
Procedures
Maintenance Rule Functions Safety Significant
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Classification
Maintenance Rule Implementation per NEI 18-10
Maintenance Rule 18-10 Failure Definitions
Maintenance Rule 18-10 Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
4446169
Unexpected MRC Alarm; 12A HTR LO
09/14/2021
Corrective Action
Documents
4446232
1HD054A Continuous Operation Evaluation Required
09/14/2021
Miscellaneous
1SI8920 Work Window Protected Equipment List
09/13/2021
Risk Management
On-Line Risk Management
Conduct of Troubleshooting
Protected Equipment Program
Procedures
On-Line Risk Management and Assessment
213984
A2R15LL: S/U FW PP Press Switch Isolation Leak-By
05/10/2011
20432
2PS-FW282A Isolation Valve Leaks-By
04/02/2005
4419609
Unit 1 Core Exit Thermocouple Nozzle 74 - Connections
Swapped Affecting Indications
04/28/2021
20610
B Train Core Exit Thermocouples Not Communicating with
Plant Process Computer
05/01/2021
23740
Unit 1 Core Exit Thermocouples Exceed Allowed Maximum
Deviation
05/15/2021
28965
U-2 Startup Feedwater Pump Oil Pressure Low
06/12/2021
4436953
2FIS-0611 is Weeping Boric Acid
07/26/2021
4437474
1SX169A Failed to Open on Slow Local Start of 1A DG
07/28/2021
4443522
2A DG Bolt on 4L Cylinder Sheared During Scheduled Run
08/30/2021
Corrective Action
Documents
4447805
0B Non-Accessible Plenum Delay
09/21/2021
BwOP FW-24
Filling and Venting an Isolated Feedwater Pump
Risk Management Documentation
OP-AA-106-101-
1006
Operational Decision-Making Process
Adverse Condition Monitoring and Contingency Planning
Procedures
Operability Determinations (CM-1)
Procedures
1BwOSR
Group A IST Requirements for 1B Safety Injection Pump
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5.5.8.SI-10B
(1SI01PB)
1BwOSR
5.5.8.SI-1B
Train B Safety Injection System Valve Stroke Surveillance
1BwOSR
5.5.8.SI-2B
Train B Safety Injection System Isolation Valve Indication
Surveillance
SPP-21-002
Modification Test of 1SA01CA Station Air Compressor
4762173
1SI8920 Motor Operated Valve Diagnostic Test
09/14/2021
5092650
Electrical Replacement of U0 SAC EC 630879
10/06/2021
Work Orders
5175731
IST for 1SI8919A/B/8922B/8926 ASME Surveillance
Requirements for 1SI01PM
09/14/2021
Corrective Action
Documents
4438884
2A DG Lower Lube Oil Cooler Oil Leak When Running
08/04/2021
Miscellaneous
Calibration of Steam Generator 2B Main Steam Atmospheric
Relief Valve Control Loop Test Report Package
2P-MS042 BwIP 2500-070
2BwOSR 3.8.1.2-
Unit Two 2A Diesel Generator Operability Surveillance
2BwOSR
5.5.8.RH-5B
Group A IST Requirements for Residual Heat Removal
Pump 2RH01PB
Procedures
BwIP 2500-070
Calibration of Steam Generator Main Steam Atmospheric
Relief Valve Control Loop
Work Orders
4718820
2P-MS042 S/G 2B Steam Outlet Pressure Loop
08/23/2021
Miscellaneous
Eval No. 20-71
Emergency Action Levels for Braidwood Station,
EP-AA-1001, Addendum 3
09/08/2020
Standardized Radiological Emergency Plan
Procedures
Radiological Emergency Plan Annex for Braidwood Station
Procedures
Controls for Radiation Protection Instrumentation
1st and 2nd Quarter REMP Samples to Document in
20 AREOR
07/30/2020
BD-22
01/26/2021
Corrective Action
Documents
3rd and 4th Quarter REMP Samples to Document in
20 AREOR
01/28/2021
Miscellaneous
Braidwood Station Unit 1 and 2 Annual Radiological
Environmental Operating Report 2019
05/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Meteorological Tower Inspection Report
06/2019
Meteorological Tower Inspection Report
06/2020
Braidwood Nuclear Power Station Annual Radioactive
Effluent Release Report (ARERR) 2020
05/2021
Braidwood Station Unit 1 and 2 Annual Radiological
Environmental Operating Report 2020
05/2021
0B RW Demin Inlet Pressure High Out of Band
08/21/2020
0PL01J, Liquid RW Control Panel, Alarm Check
Unsatisfactory
10/07/2020
Corrective Action
Documents
Lesson Learned: Dose Received During RW Resin Liner
Survey
2/18/2021
Miscellaneous
CFR 61 Analysis for Primary Resin Filters
04/16/2021
Procedures
Radioactive Material/Waste Shipments
RWS20-015
UN3321 LSA-II; 14 DAW Legacy Waste in Cask 14-210
08/27/2020
RWS20-018
UN2916 Type (B) Package; Resin Liner PO 692200-4
11/12/2020
RWS21-001
UN3321 LSA-II; Resin Liner P0695283-14 in Cask 14-215
01/12/2021
Shipping Records
RWS21-015
UN2910 Limited Quantity of Material; Seven B-25 Boxes of
CP Resin
08/17/2021
NRC Performance Indicator Data; Mitigating
Systems Mitigating System Performance Index for Heat
Removal Systems
07/01/2020 -
06/30/2021
NRC Performance Indicator Data; Mitigating
Systems Mitigating System Performance Index for
Residual Heat Removal Systems
07/01/2020 -
06/30/2021
Miscellaneous
NRC Performance Indicator Data; Mitigating
Systems Mitigating System Performance Index for
Cooling Water Systems
07/01/2020 -
06/30/2021
Collecting and Reporting of NRC Performance Indicator Data
71151
Procedures
Mitigating System Performance Index Data Acquisition and
Reporting
4364058
Forced Helium Drying Skid Issue
08/19/2021
Corrective Action
Documents
4433954
It Was Identified That Corrective Action 04364058-22 Had
Been Extended Twice, In Reviewing the CA Template, the
Extensions and Their Approvals Were Not Documented
07/08/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4434922
Level 4 Configuration Control - Received Unexpected Alarm
1-2-Ec
07/14/2021
Drawings
M-66, Sheet 3A
Diagram of Component Cooling Water, Units 1 and 2
AW
Miscellaneous
Gap Analysis for Braidwood DCS Human Performance Error
08/18/2020
2BwOSR
5.5.8.CC-3
Common Train Component Cooling Isolation Valve Stroke
Surveillance
Quality Assurance Topical Report (QATR)
OU-MW-671-300
MPC Processing Forced Helium Dehydration (FHD) for
PWRS (ISFSI)
Issue Identification and Screening Process
Corrective Action Program (CAP) Procedure
Root Cause Analysis Manual
Corrective Action Program Evaluation Manual
Procedures
Effectiveness Review Manual
2