IR 05000456/2022002
| ML22206A235 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/26/2022 |
| From: | Hironori Peterson Region 3 Branch 3 |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2022002 | |
| Download: ML22206A235 (24) | |
Text
SUBJECT:
BRAIDWOOD STATION - INTEGRATED INSPECTION REPORT 05000456/2022002; 05000457/2022002; AND 07200073/2022001
Dear Mr. Rhoades:
On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station. On July 15, 2022, the NRC inspectors discussed the results of this inspection with Mr. 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 Branch 3 Division of Reactor Projects Docket Nos. 05000456; 05000457; and 07200073 License Nos. NPF-72 and NPF-77
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000456; 05000457; and 07200073
License Numbers:
Report Numbers:
05000456/2022002; 05000457/2022002; and 07200073/2022001
Enterprise Identifier:
I-2022-002-0044 and I-2022-001-0100
Licensee:
Constellation Energy Generation, LLC
Facility:
Braidwood Station
Location:
Braceville, IL
Inspection Dates:
April 01, 2022 to June 30, 2022
Inspectors:
R. Bowen, Illinois Emergency Management Agency
A. Demeter, Acting Resident Inspector
G. Edwards, Health Physicist
D. Kimble, Senior Resident Inspector
J. Masse, Reactor 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 and Unit 2 began the inspection period operating at full power. With the exception of short duration reductions in power to support scheduled testing activities and load changes requested by the transmission system dispatcher, both units 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 the station's offsite and alternate alternating current (AC)power systems for summer readiness and the onset of hot weather during the weeks ending May 21 through June 4, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial physical alignment verifications of the following systems/trains:
- (1) The 1B Emergency Diesel Generator (EDG) during 1A EDG maintenance during the week ending April 16, 2022
- (2) The 2B Residual Heat Removal (RH) Train during 2A RH Train maintenance during the week ending May 5, 2022
- (3) Unit 1 and Unit 2, Division 1, direct current (DC) power while protected during an extended Unit 1 Station Auxiliary Transformer (SAT) maintenance window during the week ending May 14, 2022
- (4) Unit 1 EDGs while protected during an extended Unit 1 SAT maintenance window during the week ending May 14,2022
- (5) The 2B Auxiliary Feedwater (AF) Train while protected during an extended Unit 1 SAT maintenance window during the week ending May 14, 2022
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:
Unit 1 power maneuvering in response to the system transmission dispatcher, during the week ending April 30, 2022.
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 June 11, 2022.
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 leakage from the Unit 1 Charging and Letdown Regenerative Heat Exchanger Return to the Reactor Coolant System (RCS) Manual Isolation Valve (1CV-8321A) during the weeks ending April 23 through June 25, 2022.
- (2) Maintenance effectiveness review associated with EDG local annunciator panel power supplies during the week ending April 23, 2022.
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 emergent work associated with the 2B EDG annunciator panel, as documented in Issue Report (IR) 4490289 during the week ending April 9, 2022.
- (2) Evaluation of the planned work associated with 1A EDG, as documented in Work Order (WO) 4901183 during the week ending April 16, 2022.
- (3) Evaluation of the emergency activities associated with a leak from a welded joint on the Unit 0 Component Cooling (CC) Heat Exchanger Essential Service Water (SX)
Outlet, as documented in IR 4494801 and WO 5252064 during the weeks ending April 23 through April 30, 2022.
- (4) Evaluation of the emergent activities associated with the loss of local alarm annunciators for the 2A EDG, as documented in IR 4493589 and 5249849 during the week ending April 23, 2022.
- (5) Evaluation of the work associated with the Unit 1 SAT maintenance window utilizing a planned Technical Specification Risk-Informed Completion Time (TS RICT), as documented in multiple WOs during the week ending May 14, 2022.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 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 the 1B EDG following identification of a crack in the jacket water cooling manifold, as documented in IR 4492197 during the week ending April 16, 2022.
- (2) Evaluation of the functionality of the Unit 2 Rod Drive System following identification of a degraded power supply, as documented in IR 4471553 during the week ending May 28, 2022.
- (3) Evaluation of the operability of the Unit 0 CC Heat Exchanger following identification of a leak through a welded joint on the SX outlet of the heat exchanger, as documented in IR 4494801 during the week ending June 4, 2022.
- (4) Evaluation of the operability of the 0B Control Room Chiller (VC) following identification of a degraded chiller oil level, as documented in IR 4505042 during the weeks ending June 25 through June 30, 2022.
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 configuration change on Unit 2:
- (1) A temporary plant modification per Engineering Change (EC) 635793: Install Temporary Power Supply in 2RD033, during the weeks ending May 21 through May 28, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and functionality:
- (1) Non-destructive testing on the SX side of the Unit 0 CC Heat Exchanger following analysis and evaluation of a leak through a welded joint, as documented in WO 5253243 during the week ending May 21, 2022
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities:
Surveillance Tests (other) (IP Section 03.01)
- (1) BwISR 3.3.1.6-004: Quarterly Excore Power Range N44 Axial Flux/7300 Delta Flux Penalty Calibration, as documented in WO 5242877 during the weeks ending June 11 through June 18, 2022
FLEX Testing (IP Section 03.02) (1 Sample)
(1)0BwOS FX-12: FLEX Pump Full Flow Test Surveillance, as documented in WOs 5011598 and 5013180 during the weeks ending June 18 through June 25, 2022
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)
The inspectors evaluated site's emergency plan by observing the following emergency response organization (ERO) activities:
- (1) A site-wide emergency preparedness drill that resulted in a simulated General Emergency event classification on May 18, 2022
- (2) A site-wide emergency preparedness drill that resulted in a simulated General Emergency event classification on June 1,
RADIATION SAFETY
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (1 Sample)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Fuel Handling Building ventilation systems
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry
Internal Dosimetry (IP Section 03.03) (2 Samples)
The inspectors evaluated the following internal dose assessments:
- (1) Internal dose assessment conducted for an individual reporting onsite that had previously reported having an intake at another facility conducted on October 20, 2021
- (2) Internal dose assessment conducted for an individual who was hanging shielding during a valve repair on February 9, 2021
Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
- (1) Dose assessment for a declared pregnant worker in 2021
- (2) Dose assessment for a declared pregnant worker in 2022
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (5 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Area Radiation Monitors in auxiliary building
- (2) Area Radiation Monitors in the fuel handling building
- (3) Friskers used at the exit to the auxiliary building
- (4) Portable ion chambers stored ready for use and/or during use at the Radiation Protection checkpoint at the auxiliary building entrance
- (5) Portable ion chambers stored ready for use and/or during use in the Radiation Protection instrument room in the auxiliary building
Calibration and Testing Program (IP Section 03.02) (10 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Thermo Scientific PM12; SN #12084
- (2) Bicron RSO-50E; SN #C613F
- (3) Thermo Scientific SAM12; SN #235A
- (4) Mirion Telepole II; SN #0019520
- (5) Mirion Argos 5; SN #1011-279
- (6) Ludlum Model 30; SN #26144
- (7) Ludlum Model 12-4; SN #336338
- (8) Thermo Scientific PM12; SN #12060
- (9) Thermo Scientific PM12; SN #12082
- (10) Mirion RDS-31; SN #2B.106 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Auxiliary building ventilation stack effluent stack monitor, 1PRJ28
- (2) Station blowdown line liquid effluent radiation monitor, 0R-PR010
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors reviewed and verified selected portions of the licensee's performance indicator submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (April 1, 2021 - March 31, 2022)
- (2) Unit 2 (April 1, 2021 - March 31, 2022)
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 (April 1, 2021 - March 31, 2022)
- (2) Unit 2 (April 1, 2021 - March 31, 2022)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (April 1, 2021 - March 31, 2022)
- (2) Unit 2 (April 1, 2021 - March 31, 2022)
71152A - Annual Follow-Up Problem Identification and Resolution Annual Follow-Up of Selected Issues (Section 03.03)
The inspectors conducted an in-depth review of the licensees implementation of the corrective action program (CAP) related to the following issue:
- (1) Review and assessment of the station's corrective actions from a Unit 2 configuration control event where a pressure test signal was applied to the incorrect instrument loop, as documented in IR 4474052 during the weeks ending April 2 through June 30, 2022.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors conducted a semiannual review of the licensees CAP for potential adverse trends that might be indicative of a more significant safety concern during the weeks ending June 4 through June 30, 2022. A specific trend related to Reactor Vessel Level Indication System (RVLIS) issues is documented in the Results Section of this report.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855 - Operation of an ISFSI Operation of an ISFSI
- (1) The inspectors assessed the licensees Independent Spent Fuel Storage Installation (ISFSI) cask loading activities from May 16 through May 20, 2022. Specifically, the inspectors observed the following activities during the loading of multi-purpose canister (MPC) No. 676:
- heavy lift of the loaded transfer cask (HI-TRAC) from the spent fuel pool to the cask processing area
- closure welding and non-destructive evaluations
- canister processing including blowdown and forced helium dehydration
- stack-up and download of the MPC from the HI-TRAC into the storage cask (HI-STORM)
- radiological field surveys
The inspectors performed walkdowns of the ISFSI pad, including walkdowns of the ISFSI haul path.
The inspectors evaluated the following:
- spent fuel selected for loading into dry cask storage during this loading campaign
- selected corrective action program documents
- selected 72.48 screenings and evaluations
INSPECTION RESULTS
Observation: Test Signal Inadvertently Applied to the Incorrect Instrument Loop 71152A The inspectors performed a detailed review of IR 4474052, Level 3 Configuration Control:
Incorrect Connection of Test Equipment. The issue involved Instrument Maintenance Department (IMD) calibration procedure BwIP 2P-0120, Calibration of Charging Header Pressure Loop 2P-0120 (CV), which was performed under Work Order (WO) 5063738, 2P-0120 Charging Header Pressure Loop. On January 26, 2022, IMD technicians performing this calibration activity were prompted to change out their test signal equipment partway through the procedure due to a low battery indication. Despite the use of robust barriers within the applicable 2PA06J instrumentation cabinet intended to prevent such an error, the IMD technicians connected the replacement test signal equipment to test connection points associated with the Unit 2 Volume Control Tank (VCT) pressure instrument loop, vice the intended 2P-0120 Charging Header Pressure instrument loop. When the test signal was subsequently applied, Unit 2 operators in the main control room were forced to respond to invalid VCT pressure indications and took steps to stabilize VCT pressure.
The inspectors chose this issue for an in-depth review of the licensees actions within their corrective action program (CAP) because of the inherent risk associated with wrong unit /
wrong component manipulations. While in this particular case the wrong component error did not result in any significant adverse impact to the applicable unit, such an error could have resulted in a significant plant transient or unintended automatic equipment actuation.
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 addressing potential wrong unit / wrong component errors.
The inspectors determined that the erroneous connection of the IMD test signal equipment to test connection points associated with the Unit 2 VCT pressure instrument loop, vice the intended 2P-0120 Charging Header Pressure instrument loop on January 26, 2022, had constituted a violation of the requirements of TS 5.4.1(a), which requires that written procedures be established, implemented, and maintained for the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. In this case, Section 8.a of Regulatory Guide 1.33, Revision 2, Appendix A, February 1978, contains the requirement for procedures associated with instrument calibrations, and licensee procedure BwIP 2P-0120, Calibration of Charging Header Pressure Loop 2P-0120 (CV),
Revision 1, is an applicable procedure. Section 4.1, Test Setup, of this procedure directs that the IMD test equipment is to be connected to Terminals TBF-7 and TBF-8 in Cabinet 2PA06J to facilitate calibration of the Charging Header Pressure Loop 2P-0120. Contrary to these instructions, the IMD test signal equipment was connected to Terminals TBF-1 and TBF-2 in Cabinet 2PA06J. However, because there were no safety consequences associated with this event, the inspectors concluded that the error had not adversely affected the Initiating Events Cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. As a result, the issue was determined to be a violation of minor significance that was not subject to formal actions per Section 2.3.1 of the NRC Enforcement Policy.
The inspectors did not identify any issues with the licensees CAP actions taken. The licensees formal CAP evaluation revealed that human performance failures had occurred at multiple times during the calibration. Subsequent interviews performed with station supervisors and technicians revealed that multiple interpretations of standards and expectations existed with respect to the use of several human performance tools. Multiple corrective actions targeting this aspect of the event were implemented by the licensee; these included the reinforcement of standards and expectations by plant management with shop superintendents regarding the use of human performance tools, peer-to-peer coaching, and supervisory oversight in the field.
No findings or violations of NRC requirements of more than minor safety significance were identified by the inspectors in the course of this review.
Observation: Trend in Reactor Vessel Level Indication System (RVLIS) Issues 71152S The inspectors performed a review of plant issues, particularly those entered into the licensees CAP over the past several months. During their review, the inspectors noted an adverse trend involving the performance of the Reactor Vessel Level Indication System (RVLIS). The majority of issues were on Unit 1, but the inspectors noted that the trend was not exclusive to only that unit. Specific CAP entries reviewed by the inspectors included, but were not limited to:
- IR 4442055; 1-9-D6 - Unexpected Main Control Room Alarm - RVLIS Sensor Uncovered.
- IR 4442887; 1-9-D6 - Unexpected Main Control Room Alarm - RVLIS Sensor Uncovered.
- IR 4450389; Unexpected Main Control Room Alarm - RVLIS Sensor/Core Exit Thermocouple (CETC) Failure.
- IR 4472056; Alarm 2-9-D6 - RVLIS Level Sensor 7B Erratic.
- IR 4482013; 1-9-D6, RVLIS Sensor Uncovered, Sensor 6A (Plenum 27%).
- IR 4488602; Unexpected Alarm on Unit One A-Train RVLIS.
- IR 4508584; Unexpected Alarm 1-9-D6, RVLIS Sensor Uncovered, Sensor 3A.
The Reactor Vessel Level Indication System is described in Appendix E, Requirements Resulting from the Three Mile Island 2 Accident, of the stations Updated Final Safety Analysis Report (UFSAR) as part of a system of instrumentation used to detect inadequate core cooling (ICC) during significant accident scenarios. Operability requirements for RVLIS in operational Modes 1, 2, and 3 are set forth in Section 3.3.3 of the stations Technical Specifications (TS). The Bases for TS 3.3.3 states, in part:
The Reactor Vessel Water Level Monitoring System provides a direct measurement of the liquid level above the fuel. Two channels are required OPERABLE (Train A and Train B). Each channel consists of eight sensors on a probe. For a channel to be considered OPERABLE one of the two sensors in the "head" region and three of the six sensors in the "plenum" region shall be OPERABLE. The level indicated by the OPERABLE sensors represents the amount of liquid mass that is in the reactor vessel above the core. Operability of each sensor may be determined by reviewing the error codes displayed on the control room indicator.
In the cases reviewed, the inspectors noted that the issues typically involved brief or spurious abnormal readings from a single RVLIS sensor, which was insufficient by itself to render the applicable RVLIS channel inoperable. The inspectors also noted, however, that the continuing presence and frequency of these abnormal readings was, at best, becoming a nuisance for control room operators and, at worst, a chronic issue that could eventually challenge RVLIS TS operability.
The inspectors further noted that the licensee was placing an appropriate level of emphasis on this issue; at the conclusion of the inspection period the licensee generated IR 4508208; Potential Trend in Unit 1/Unit 2 RVLIS Issues, within the stations CAP to drive additional engineering reviews into this issue.
The inspectors did not identify any findings or violations of NRC requirements in the course of their review.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 15, 2022, the inspectors presented the integrated inspection results to Mr. G. Gugle, Site Vice President, and other members of the licensee staff.
On April 1, 2022, the inspectors presented the radiation protection inspection results to Mr. J. Petty, Plant Manager, and other members of the licensee staff.
On May 20, 2022, the inspectors presented the ISFSI Cask Loading inspection results to Mr. G. Gugle, Site Vice President, and other members of the licensee staff.
On June 10, 2022, the inspectors presented the radiation protection inspection results to Mr. G. Gugle, Site Vice President, 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 final report issued by the Institute of Nuclear Power Operations (INPO) for the most recent periodic plant performance evaluation of Braidwood Station, which was performed during July 2021 and had a formal exit on September 13, 2021.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ALARA Plans
BW-00-22-00325
Dry Cask Storage and Support Activities
BRW-14-0070-N
Braidwood Cask Model Update for 2014 ISFSI Campaign
Calculations
BRW-21-0027-N
Braidwood Cask Model Update for 2022 ISFSI Campaign
00157367
Entry Into 1BwOA PRI-4 Due to High RCS Activity on
1PR06J
05/05/2003
244340
Abnormal Noise Emanating from the FHB Crane
04/29/2019
265230
DCS - Indication Found During MPC Delivery Inspection
07/18/2019
270528
MPC 531 Lid Has Minor Indications (Acceptable)
08/08/2019
274522
2019 Braidwood DCS Campaign Lessons Learned
08/26/2019
04323080
03/02/2020
04329064
PCRA to Update BwFP FH-20 FHB Crane Temp
Requirement
03/24/2020
04375525
NOS Finding: M&TE Not Entered for ISFSI Campaign WOs
10/09/2020
Corrective Action
Documents
04486579
OI Benchmark: Industry Use of Admin Controls for Cask
Ops
03/22/2022
05/16/2022
2.48-203
Procedure OU-MW-671-300
7B
2.48-204
Holtec RRTI-2788-002
2.48-205
EC 628051/Analysis No. BRW-09-0028 and Analysis No.
BRW-09-0029
0, 2, 1A
2.48-206
Holtec Notice HN-01
2.48-208
ECR 443383, ISFSI Grillage Polyethylene Bars
2.48-212
Holtec FCR 27881002
2.48-223
EC 629492/Analysis No. BRW-09-0028 and Analysis No.
BRW-09-0029
0, 2A, 1B
2.48-224
BWNPS 10 CFR 72.212 Evaluation Report
06-01
2.48-226
2.48-227
2.48-228
2.48-229
BWNPS 10 CFR 72.212 Evaluation Report
06-02
60855
Miscellaneous
2.48-31
Review of PCI/CES and LTS Procedures
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
BRW-21-0026-N
Braidwood Fuel Selection Package and Alternative List for
22 ISFSI Campaign
DIT-BRW-2010-
0104
Braidwood Fuel Characterization
2/14/2010
DOC-1023-677
MPC 32 to Braidwood Generating Station
21-175
MPC Lift Spider Assembly
2/07/2021
Report No.
914743-676-01
Lid to Shell
05/17/2022
Report No.
914743-676-02
Lid to Shell / SN 676
05/17/2022
Report No.
914743-676-03
Lid to Shell / SN 676
05/18/2022
NDE Reports
Report No.
914743-676-04
Lid to Shell / SN 676
05/18/2022
BwFP FH-69
HI-TRAC Movement Within the Fuel Building
BwFP FH-83
Spent Fuel Cask Contingency Procedures
OU-MW-671-300
Forced Helium Dehydration (FHD) for PWRs (ISFSI)
Procedures
PC-CNSTR-OP-
EXE-H-01
Closure Welding of Holtec Multi-Purpose Canisters at Exelon
Facilities
Revision 22
Self-Assessments NOSA-BRW-20-
Independent Spent Fuel Storage Installation Audit Report
10/14/2020
00676183 01
WH-Perform In-Mast Sipping of All Fuel Assemblies
10/18/2004
04673912 01
Fuel BLDG Overhead Crane Lubrication
04/29/2019
05063024
0HC03G INSP of FHB Overhead Crane
06/03/2021
05063029
LR-Yearly Inspection
06/18/2021
05121105 05
ISFSI RX ENG Inventory MPC After Fuel Load
05/17/2022
05123909
MPC Lift Cleat Inspection
2/07/2021
05123918
HI STORM Lift Bracket Inspection
2/07/2021
05123919
Inspect MPC Spider Lift
2/07/2021
05138020
HI-TRAC Trunnion Inspect
2/11/2022
Work Orders
05138021
Lift Yoke Inspection
2/11/2022
Miscellaneous
Letter from Mr. Greg Gugle to Ms. Marri Marchionda-Palmer,
Certification of 2022 Summer Readiness
05/13/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0BwOA ENV-1
Adverse Weather Conditions Unit 0
24
CC-BR-118-1001
Site Implementation of Diverse and Flexible Coping
Strategies (FLEX) and Spent Fuel Pool Instrumentation
Program
General Area Checks and Operator Field Rounds
OP-AA-108-107-
1001
Station Response to Grid Capacity Conditions
OP-AA-108-111-
1001
Severe Weather and Natural Disaster Guidelines
OP-BR-102-102-
1001
Augmented Operator Field Rounds
Procedures
Seasonal Readiness
4407811
Date Wrong for 1ER-DC05E/Evaluate for Y2K Compliancy
03/10/2021
Corrective Action
Documents
4452755
1ER-DC05E Positive Ground Pushed is High Out of Band
10/13/2021
BwOP AF-E2
Electrical Lineup Unit 2 Operating
BwOP AF-M2
Operating Mechanical Lineup, Auxiliary Feedwater, Unit 2
BwOP DC-E2
Electrical Lineup Unit 1 Operating-125V DC Division
BwOP DG-E1
Electrical Lineup Unit 1 1A Diesel Generator
BwOP DG-M1
Operating Mechanical Lineup Unit 1 1A D/G
BwOP DG-M2
Operating Mechanical Lineup Unit 1 1B D/G
BwOP RH-E2
Electrical Lineup Unit 2 Operating
BwOP RH-E2
Electrical Lineup Unit 2 Operating
Procedures
BwOP RH-M4
Operating Mechanical Lineup Unit 2 2B Train
Miscellaneous
Braidwood Station Licensed Operator Requalification
Simulator Scenario Guide, Cycle 22-3 OBE
OP-AA-101-111-
1001
Operations Standards and Expectations
Operator Fundamentals
OP-AA-101-113-
1006
4.0 Crew Critique Guidelines
OP-AA-103-1-2-
1001
Strategies for Successful Transient Mitigation
Procedures
Watch-Standing Practices
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operation of Equipment
Communications
OP-AA-108-107-
1002
Interface Procedure Between BGE/COMED/PECO and
Exelon Generation (Nuclear/Power) for Transmission
Operations
Operating Narrative Logs and Records
Reactivity Management
Systematic Approach to Training Process Description
Operator Training Programs
Conduct of Simulator Training and Evaluation
Simulator Management
TQ-BR-201-0113
Braidwood Training Department Simulator Examination
Security Actions
4482320
Boron Accumulation at 1CV8321A
03/03/2022
4490289
2PL08J Annunciator Panel Has No Power
04/05/2022
4492850
1CV8321A Steam Leak
04/13/2022
4493891
Work Request for 1B EDG Annunciator Power Supply
04/18/2022
Corrective Action
Documents
4493892
Work Request for 1A EDG Annunciator Power Supply
04/18/2022
Drawings
M-64, Sheet 5
Diagram of Chemical and Volume Control and Boron
Thermal Regeneration Unit 1
BI
Maintenance Rule Functions Safety Significant
Classification
Maintenance Rule Implementation per NEI 18-10
Maintenance Rule 18-10 Scoping
Maintenance Rule 18-10 Failure Definitions
Procedures
Maintenance Rule 18-10 Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
Work Orders
4901183
Year Inspection
06/03/2022
4493589
Unexpected Annunciators: 2-21-C8 & 2-21-D8
04/16/2022
4494966
Scope Expansion of 0SX02D-30"
04/22/2022
4494967
Scope Expansion Inspection of 1SX02B-30"
04/22/2022
4494969
Scope Expansion Inspection of 1SX03A-30"
04/22/2022
Corrective Action
Documents
4494970
Scope Expansion Inspection of 2SX02B-30"
04/22/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Adverse Condition Monitoring and Contingency Plan
(ACMP): SX Leak on Unit 0 CC Heat Exchanger (0SX03A)
Miscellaneous
Final RICT Record for Unit 1 Station Auxiliary Transformer
(SAT) 142-1 and 142-2 Work Window
05/15/2022
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
Conduct of Troubleshooting
Integrated Risk Management
Protected Equipment Program
Risk Informed Completion Time
Procedures
On-Line Risk Management and Assessment
4901183
Year Inspection
06/03/2022
249849-01
Troubleshoot Annunciator Panel
04/18/2022
253243-01
Ultrasonic Thickness Exam on Line 0SX02D-30" - 0CC01A
Heat Exchanger Inlet Nozzle
05/17/2022
253244-01
Ultrasonic Thickness Exam on Line 1SX02B-30" - 0CC1A
Heat Exchanger Inlet Nozzle
05/04/2022
Work Orders
253245-02
Ultrasonic Thickness Exam on 1SX03A-30" - 1CC01A Heat
Exchanger Outlet Nozzle
05/04/2022
4471553
Reflash of U2 Rod Control Non-Urgent Failure Alarm
01/13/2022
4492197
1B DG Repair Crack in Manifold
04/11/2022
4494801
SX Piping Leakage at Outlet of U-O CC Hx
04/22/2022
Corrective Action
Documents
4505042
0B VC Chiller Oil Additions
06/11/2022
635793
Install Temporary Power Supply in 2RD03J
636541
Engineering to Evaluate Seal Weld for Cracked 1B DG
Engineering
Changes
636627
Configuration Control Processing of Design Analysis
051853, Revision 005M, for Evaluation of the Structural
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Integrity of Line 0SX03A-30" per Code Case N-513-4,
Considering the Through Wall Leakage Identified
636646
Operability Evaluation 22-001: Pinhole Leak on a Weld on
Line 0SX03A-30"
636646
Operability Evaluation 22-001: Pinhole Leak on a Weld on
Line 0SX03A-30"
Miscellaneous
BRW-2-2021-
0304
ODM: Unit 2 Rod Drive Non-Urgent Failure
Engineering Technical Evaluations
Risk Management Documentation
OP-AA-106-101-
1006
Operational Decision-Making Process
Adverse Condition Monitoring and Contingency Planning
Procedures
Operability Determinations (CM-1)
Work Orders
214697
IM 2RD03J Fab & Install Temp PS in Parallel with PS1, PS2
05/25/2022
4467108
Unexpected Annunciator 2-10-D6: Rod Control Non-Urgent
Failure
2/16/2021
4468189
Reflash of Unit 2 Rod Control Non-Urgent Failure Alarm
2-10-D6
2/24/2021
Corrective Action
Documents
4471553
Reflash of Unit 2 Rod Control Non-Urgent Failure Alarm
01/13/2022
Engineering
Changes
635793
Install Temporary Power Supply in 2RD03J
Temporary Configuration Changes
29-30
Procedures
IP-ENG-001
Standard Design Process (EB-17-06)
Work Orders
253243-01
Ultrasonic Thickness Exam on Line 0SX02D-30" - 0CC01A
Heat Exchanger Inlet Nozzle
05/17/2022
Procedures
Ultrasonic (UT) Measurement of Material Thickness and
Interfering Conditions
4502482
0FX03PA Battery Voltage Low - Failed Acceptance Criteria
05/28/2022
4502483
0FX03PB Battery Voltage Low - Failed Acceptance Criteria
05/282022
4502484
0FX01PA Battery Voltage Low - Failed Acceptance Criteria
05/28/2022
Corrective Action
Documents
4502485
0FX01PB and 0FX01PC Battery Voltages Low but Still in
Band
05/28/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4504183
OOT and Blown Control Power Fuse on 2N-NR8041
06/07/2022
4504563
Cleared Controller Fuse for 2N-NR8042
06/09/2022
4505840
0FX03PA Voltage Low
06/16/2022
4505992
0A Medium Head Flex Pump Won't Stay Running
06/16/2022
4505994
0A High Head Flex Test Connection Bad Fitting
06/16/2022
4506515
0FX03PB Developed Leak from Diesel Oil Filter When
Started
06/20/2022
4507359
0FX03PB Low Head Flex Pump Flow
06/24/2022
4507621
0FX03PB Fuel Oil Leak
06/26/2022
4507623
B High Head Flex Pump Did Not Meet Test Parameters
06/26/2022
4508035
0B High Head Flex Pump High Oil Temp
06/28/2022
0BwOS FX-12
FLEX Pump Full Flow Test Surveillance
BwISR 3.3.1.6-
004
Quarterly Excore Power Range N44 Axial Flux
Difference/7300 Delta Flux Penalty Calibration
OP-BR-FX-1003
High Head FLEX Pump Operating Guideline
OP-BR-FX-1004
Medium Head FLEX Pump Operating Guideline
Procedures
OP-BR-FX-1005
Low Head FLEX Pump Operating Guideline
5011598
0FX01PA (A Train Medium Head FLEX Pump) Performance
Test
06/20/2022
Work Orders
5013180
0FX03PA (A Train Low Head FLEX Pump) Performance
Test
06/16/2022
4504645
Braidwood 2022 Performance Indicator Drill Critique and
Learnings Operations Support Center
06/09/2022
4504679
Braidwood 2022 Performance Indicator Drill Learnings
Technical Support Center 1 of 2
06/09/2022
4504684
Braidwood 2022 Performance Indicator Drill Learnings
Technical Support Center 2 of 2
06/09/2022
Corrective Action
Documents
4504733
Braidwood 2022 Performance Indicator Drill Learnings
Main Control Room / Simulator
06/09/2022
Standardized Radiological Emergency Plan
Radiological Emergency Plan Annex for Braidwood Station
Procedures
Addendum 1
Braidwood Station On-Shift Staffing Technical Basis
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Addendum 3
Emergency Action Levels for Braidwood Station
0EA01C SCBA Air Compressor PM's Needed Air
Replacement
07/21/2021
Corrective Action
Documents
SCBA Compressor Out of Service
04/05/2022
Trace Analytics SCBA Grade D Quality Air Report
05/05/2022
Miscellaneous
Air One Equipment SCBA Hydrostatic Testing Results
01/25/2022
Controlled Negative Pressure (CNP) Fit Testing
Operation of Air Samplers
Procedures
Maintenance, Care, and Inspection of Respiratory Protective
Equipment
Calibration
Records
Calibration of the Accuscan II WBC System at the Exelon
Generating Station
2/23/2022
Dose Assessment for a Declared Pregnant Worker.
2/01/2022
Dose Assessment for a Declared Pregnant Worker.
2/20/2021
Miscellaneous
Braidwood Dry Activated Waste Part 61 Analysis
20
Internal Dose Control Program Description
Procedures
Operation and Calibration of the PM-12 Gamma Portal
Monitor
Serial Number
0019520
Mirion Telepole II
07/27/2021
Serial Number
1011-279
Argos 5 Monitor
03/17/2022
Serial Number
2060
Thermo Scientific PM12
03/22/2022
Serial Number
2082
Thermo Scientific PM12
2/03/2021
Serial Number
2084
Thermo Scientific PM12 Unit 1 Containment Access Facility
03/23/2022
Serial Number
235A
Thermo Scientific SAM12
03/17/2022
Calibration
Records
Serial Number
Ludlum Model 30
2/25/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
26144
Serial Number
2B.106
Mirion RDS-31
09/21/2021
Serial Number
336338
Ludlum Model 12-4
2/25/2021
Serial Number
C613F
Bicron RSO-50E
03/14/2022
Low Flow and Pump (2PR30PB) Turning Off on 2PR3DJ
07/24/2021
Unexpected Alarm: 0AR68J High Alarm
09/05/2021
Corrective Action
Documents
U1 CAF PM12 12010 Needs Battery Replaced
03/23/2022
04956514
1PR28J Calibration of Effluent Gaseous Rad Monitor Plant
Ventilation Monitor
01/27/2021
Work Orders
04999329-01
Calibration Liquid Effluent Radiation Monitor Station
Blowdown Line
09/01/2021
NRC Performance Indicator Data; Mitigating Systems
Safety System Functional Failures
04/01/2021 -
03/31/2022
NRC Performance Indicator Data; Mitigating Systems
Mitigating System Performance Index for Emergency AC
Power
04/01/2021 -
03/31/2022
Miscellaneous
NRC Performance Indicator Data; Mitigating Systems
Mitigating Systems Performance Index for High Pressure
Injection
04/01/2021 -
03/31/2022
Collecting and Reporting of NRC Performance Indicator
Data
Monthly Data Elements for NRC Safety System Functional
Failures
71151
Procedures
Mitigating System Performance Index Data Acquisition and
Reporting
4474052
Level 3 Configuration Control: Incorrect Connection of Test
Equipment
01/26/2022
4475596
4.0 Critique - Volume Control Tank Pressure Abnormal
Indication
2/02/2022
Corrective Action
Documents
4475837
Maintenance Department For-Cause Management Review
Meeting Results
2/03/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
BwAR 2-9-B2
Volume Control Tak (VCT) Pressure High/Low
BwIP 2P-0120
Calibration of Charging Header Pressure Loop 2P-0120 (CV)
BwOP RP-11A18
2PA06J Panel Appendix
Quality Assurance Topical Report (QATR)
Issue Identification and Screening Process
Root Cause Analysis Manual
Corrective Action Program Evaluation Manual
Procedures
Effectiveness Review Manual
Work Orders
5063738
2P-0120 Charging Header Pressure Loop
01/26/2022
4442055
1-9-D6 - Unexpected Main Control Room Alarm -RVLIS
Sensor Uncovered
08/23/2021
4442887
1-9-D6 - Unexpected Main Control Room Alarm - RVLIS
Sensor Uncovered
08/26/2021
4450389
Unexpected Main Control Room Alarm - Reactor Vessel
Level Indication System (RVLIS) Sensor/Core Exit
Thermocouple (CETC) Failure
10/03/2021
4472056
Alarm 2-9-D6 - RVLIS Level Sensor 7B Erratic
01/15/2022
4482013
1-9-D6, RVLIS Sensor Uncovered Sensor 6A (Plenum 27%)
03/02/2022
4488602
Unexpected Alarm on Unit One-A RVLIS
03/30/2022
4508208
Potential Trend in Unit 1/Unit 2 RVLIS Issues
06/29/2022
Corrective Action
Documents
4508584
Unexpected Alarm 1-9-D6, RVLIS Sensor Uncovered
Sensor 3A
06/30/2022