IR 05000456/2020010
| ML20086G679 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/25/2020 |
| From: | Hironori Peterson NRC/RGN-III |
| To: | Bryan Hanson Exelon Generation Co |
| References | |
| IR 2020010 | |
| Download: ML20086G679 (22) | |
Text
March 25, 2020
SUBJECT:
BRAIDWOOD GENERATING STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000456/2020010 AND 05000457/2020010
Dear Mr. Hanson:
On February 28, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Braidwood Generating Station and discussed the results of this inspection with Ms. M. Marchionda-Palmer, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
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,
/RA/
Hironori Peterson, Chief Branch 3 Division of Reactor Projects
Docket Nos. 50-456 and 50-457 License Nos. NPF-72 and NPF-77
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000456 and 05000457
License Numbers:
Report Numbers:
05000456/2020010 and 05000457/2020010
Enterprise Identifier: I-2020-010-0033
Licensee:
Exelon Generation Company, LLC
Facility:
Braidwood Generating Station
Location:
Braceville, IL
Inspection Dates:
February 03, 2020 to February 28, 2020
Inspectors:
L. Cender, Health Physicist
G. Hausman, Senior Reactor Inspector
N. Shah, Project Engineer
P. Smagacz, Resident Inspector
J. Weigandt, Reactor Engineer
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 a biennial problem identification and resolution inspection at Braidwood Generating Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000456/2019-001-00 LER 2019-001-00 for Braidwood Station, Unit 1,
Unit Trip on Low Steam Generator Level Due to Failure of a Controller on a Feedwater Regulating Valve 71153 Closed
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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
- (1) The inspectors performed a biennial assessment of the licensees corrective action program (CAP), use of operating experience, self-assessments and audits, and safety conscious work environment.
- Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted a 5-year review of the Units 1 and 2 125 Vdc systems.
- Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.
- Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) Licensee Event Report (LER) 05000456/2019-001-00, "Unit Trip on Low Steam Generator Level Due to Failure of a Controller on a Feedwater Regulating Valve,"
(ADAMS Accession No. ML19324D929). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.
INSPECTION RESULTS
Assessment 71152B Review of Corrective Action Program:
Based on the samples reviewed, the team determined that the licensees' performance in each of these areas adequately supported nuclear safety.
Effectiveness of Problem Identification:
Overall, the station was effective at identifying issues at a low threshold and properly entering them into the CAP as required by station procedures. The team determined that the station was effective at identifying negative trends that could potentially impact nuclear safety. The team interviewed personnel, reviewed documents, walked down portions of the plant, and assessed licensee problem identification.
One item of note, while observing surveillance testing, the NRC resident inspectors noted that the flow gauge for the 2B residual heat removal pump was not responding properly. The licensee staff did not capture this issue in the CAP, in part, due to the belief that this was a low-level concern. However, after prompting by the inspectors, the licensee recognized that this gauge also controls the position of the downstream flow valve, which could impact pump operability. Although the licensee later verified the pump was operable, the initial lack of sensitivity potentially resulted in a more significant issue being missed. The licensee documented this issue as AR 4322053
Effectiveness of Prioritization and Evaluation of Issues:
ln-depth reviews of a risk-informed sampling of Action Request (ARs), work orders (WOs),and cause evaluations were completed, including a 5-year time period for the 125 Vdc. The team determined that the licensee had established a low threshold for entering issues into the CAP, that the issues were generally being appropriately prioritized and evaluated for resolution, and that the corrective actions (CAs) were implemented to mitigate the risk of issues occurring that could affect overall system operability and/or reliability.
The inspectors noted that the licensee had identified potential degradation of the feedwater check valves (AR 4291137), as a contributing cause to a Unit 1 reactor trip documented in AR 4281429. As part of the trip evaluation, the licensee decided to continue operating with the valves in the degraded condition; however, the inspectors noted that there was no assigned action to assess and document the risk impact of this decision. The inspectors noted that while the licensee had done some risk assessment and had proposed actions to address the issue, these actions were not subject to the normal station management review/challenge process, since they were not tied to a formal CAP action. The inspectors subsequently concluded that the licensees justification for continued operation was reasonable and did not identify any open safety concern. However, the licensees decision to not assign a formal CAP action and therefore bypass the normal management review process was documented as AR 4322046.
The inspectors also noted that while issue evaluations were generally sound, there were several examples where additional research was needed to understand the technical basis, primarily due to a lack of clear documentation. This theme had previously been identified in earlier licensee self-assessments and CAP audits and continued to be a concern.
The licensee documented this observation as AR 4322045.
Effectiveness of Corrective Actions:
The team concluded that the licensee was generally effective in developing CAs that were appropriately focused to correct the identified problem and to address the root and contributing causes for significant issues in order to preclude repetition. The licensee generally completed CAs in a timely manner and in accordance with procedural requirements commensurate with the safety significance of the issue. For NRC identified issues, the team determined that the licensee generally assigned CAs that were effective and timely.
During a walk down of the Unit 1 feedwater system, the inspectors identified an open deficiency tag on the Unit 1 Main Feedwater Regulating Valve Control Panel Display (panel 1PL1001). This panel was not safety-related. Specifically, the display was not receiving data or displaying valve position. The inspectors noted that the issue was identified in July 2019 under AR 4263048. In this AR, the licensee had noted that this panel was needed for an Adverse Condition Monitoring Plan. Subsequently, AR 4294972 was initiated in November 2019, as the display had not been repaired. After checking the CAP database and querying the licensee, the inspectors determined that both ARs were closed to a work order, which was then closed with no action taken. Subsequently, the inspectors determined that this display was not needed for indications or trending, but was used as a back-up indication by the control room. The licensee documented the failure to fix this issue as AR 4321854.
No violations or findings were identified.
Assessment 71152B 5-year Review of Units 1 and 2 125V DC Systems:
The inspectors performed an expanded 5-year review of the Units 1 and 2 125 Vdc system; specifically, by performing system walk-downs and evaluating condition reports, engineering changes, and work orders. The inspectors also interviewed the system engineer responsible for this system. Overall, the inspectors determined that the licensee was effectively managing issues associated with this system.
Since 2014, the licensee has observed intermittent grounds on both the Units 1 and 2 DC bus systems (i.e., buses 111, 112, 211 and 212). These grounds were primarily attributed to equipment issues (bus 111) and potential water intrusion due to wet weather (buses 112, 211 and 212). These grounds were documented in the CAP and the NRC resident inspectors had been reviewing them through the baseline inspection program. Because of the intermittent and/or short-lived nature of the grounds, the location of the grounds was difficult to discern.
The inspectors identified no operability or other immediate safety concerns with these grounds and concluded that the licensee had taken proactive actions to find and correct the cause of the grounds.
No violations or findings were identified.
Assessment 71152B Operating Experience, Self-Assessment and Audits:
The inspectors reviewed operating experience (OpE) captured in the CAP and sampled OpE from NRC, industry, vendors, and third-party groups. Overall, for the samples selected, the licensee was generally performing the appropriate assessments for station applicability.
Through interviews and observations at selected station meetings, the inspectors also concluded that OpE was being appropriately used in daily plant activities.
The inspectors determined that the licensee was adequately performing self-assessments and audits in accordance with licensee procedures and implementing corrective actions as needed. Of note, the inspectors observed that the overall conclusions of the licensees self-assessment and Nuclear Oversight audit of the CAP program done prior to this NRC inspection, was consistent with the inspectors observations.
No violations or findings were identified.
Assessment 71152B Review of Safety Conscious Work Environment:
The inspectors observed various station meetings, including those in which new CAP items were reviewed, and interviewed a representative cross-section of station personnel, both individually and small groups. Additionally, the inspectors interviewed the Employee Concerns Program (ECP) Coordinator, reviewed recent case logs and case files and inquired about the program during interviews with station personnel.
During interviews, several licensee staff stated a lack of confidence in the licensee's ability to correct low level issues. This was primarily based on issues taking a significant time to resolve and/or being closed without any apparent action being taken. This perception caused some interviewees to state that they likely wouldn't continue to document these concerns in the CAP. The inspectors determined that much of this was due to the lack of clear feedback on what actions were being taken to address the issue and understanding of what certain CAP actions (such as "closed to trend") actually meant. The inspectors also determined that the interviewees would not hesitate to raise a concern if they believed that plant or worker safety was potentially involved. This concern was discussed with the licensee, who documented it as AR 4322027.
Overall, inspectors found no evidence of challenges to the licensee's safety conscious work environment (SCWE). Licensee's employees were willing to raise nuclear safety concerns through at least one of several means available. Workers expressed favorable opinions of the ECP during interviews, and those that had utilized it had no concerns regarding the overall outcome. The inspectors noted that the licensee had generally addressed potential SCWE issues in the ECP and identified no significant trends with documented issues within the last two-years.
No violations or findings were identified.
Observation: LER closeout observation 71152B Review of Root Cause of Unit 1 Trip on Low Steam Generator Level:
The inspectors performed a detailed review of LER 2019-01-00, Unit 1 Trip on Low Steam Generator Level Due to Failure of a Controller on a Feedwater Regulating Valve. A root cause evaluation for this issue was performed under AR 4281429. As part of this evaluation, the licensee reviewed a previous root cause evaluation for a 2018 Unit 1 reactor trip, also caused by a feedwater controller malfunction, documented in AR 4144070. Although the feedwater system is non-safety related, it is a system important to plant risk.
Based on the results of the 2018 evaluation, the licensee revised the 2019 evaluation to include additional information regarding performance issues with the feedwater check valves.
Specifically, these valves would occasionally not fully open (AR 4165777), resulting in partial flow restrictions in the feedwater system. Although the licensee had taken corrective action, this issue remained a concern and was a contributor in the 2019 Unit 1 reactor trip.
In the 2019 evaluation, the licensee elected to continue operating with these valves in a degraded condition; however, there was no formal CAP action initiated to assess the potential operational risk of this decision. The inspectors noted that the licensee had opened an Adverse Condition Monitoring Plan (ACMP) to monitor the check valve performance and had developed a white paper to evaluate the operational risk and offer several recommendations to improve operating reliability. However, because these actions were not formally tied back to AR 4281429, they were not subject to management review through the normal CAP screening processes or other means. Therefore, these documents did not constitute a formal decision and/or risk assessment to justify continued operation with the degraded check valves.
After reviewing the white paper, ACMP and discussing the issue with plant engineers, the inspector concluded the licensee could reasonably justify continued operation with the degraded check valves. Additionally, inspectors noted this issue was being tracked in the U1 system health report and the Plant Health Committee approved replacement of the existing valves with a new style of valve. These actions were being tracked in the CAP under AR 4291137.
The inspectors concluded that although the licensee had not taken a formal CAP action to justify continued operation with the degraded Unit 1 feedwater check valves, the implemented controls were appropriate to manage the risk until the issue was corrected. Therefore, no violations or findings were identified. The licensee documented the failure to assign a formal action in AR
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On February 28, 2020, the inspectors presented the biennial problem identification and resolution inspection results to Ms. M. Marchionda-Palmer, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2448240
Westinghouse NSAL-15-1. FQ(Z) Tech Spec Surveillance
2/05/2015
2567071
OSP-A-CT--Exciter Stator Phase Banding Is Loosening
10/07/2015
2589930
Root Cause Report: Severe Corrosion and Degraded
Coating Observed on Line 0SXH2AA-6
2/29/2015
2589930
Heavy General Corrosion on 0SXH2AA 6" in 0SX165A Pit
11/19/2015
270540
DC System Trend IR (January 2014 - July 2019)
08/08/2019
3993342
Request Formal OPEX Review for ICES 407278
04/03/2017
4066205
Braidwood Station OPEX Level 3 Review - NRC IN 2017-06
10/24/2017
4071655
Preparation for NRC Problem Identification and Resolution
Inspection
06/01/2018
4074647
Ops Effectiveness Review of ATV Actions Self-Assessment
11/14/2017
4081071
Level 3 OPEX Review Needed--Unusual Event Hydrogen
Leak
2/05/2017
4083304
DC System Short Circuit Calculation Update
2/12/2017
4086455
Green NCV - Errors in Analysis of Record for MS Line HELB
2/21/2017
4107379
Security 24 HR Loggable SY-AA-103-500 Procedure Not
Followed
2/23/2018
4110095
PI&R Deficiency (OBJ 2H): Shift Review Bypassed
03/01/2018
4110095
PI&R Deficiency: Shift Review Bypassed
03/01/2018
4110536
PI&R Deficiency Inappropriate NCAP IR
03/02/2018
4115813
Failed Gasket of 2B AF PP Gearbox Oil Cooler
03/16/2018
23789
PI&R Deficiency: Aging Management Program
04/06/2018
24952
RCS Pressure Transient During 7300 TCP Mod
04/10/2018
26942
Level 2 C&T Event--Work Stopped on 1PA08J and 1PA09J
04/15/2018
28714
OSP-A Loss of ESF Bus 141 During 1A EDG Sequencer
Testing
04/19/2018
29240
OSP-X 1RC01R NDE Results for 1RV-03-002 Reactor Head
06/19/2020
4131031
EC 620239 Poorly Written Lacks Operational Experience
04/26/2018
4132550
Root Cause Report: Unit 1 A1R20 Turbine Trip
06/22/2018
4143493
PI&R Deficiency: Untimely IR Generation Review
06/01/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4143518
PI&R Deficiency: Corrective Action Investigations
06/01/2018
4144070
U1 Manual Rx Trip
06/04/2018
4144695
Unit 1 DG-1 Maintenance Rule a(1) Determination
06/06/2018
4145161
Trend--THU Behaviors
06/07/2018
4146837
LORT TSA Failure (Isolate WS Flooding)
06/13/2018
4147583
1PI-AF105 Inlet Pressure Reads Lower Than Outlet Gauge
06/15/2018
4149089
BYR OPEX: U2 DEHC Drop 2 in Failure Mode
06/21/2018
4154913
NER NC-18-015 Yellow Adverse Trend in Fleet Fuel
Performance
07/10/2018
4156368
Potential Inventory Loss for Ultimate Heat Sink
07/17/2018
4158520
NRC ID'D - Support on 1B DG Lube OIl - Not Fret Protected
07/24/2018
4158523
NRC ID'D - 5 Missing Shroud Bolts - Top of 1B DG
07/24/2018
4160763
PI&R: UFSAR Revision Not Tracked Properly
08/01/2018
4167984
2Q18 Green NCV--Inadequate Maintenance Work
Instructions
08/28/2018
4167985
2Q18 Green Finding--Work Instruction Error Caused RCS
Issue
08/28/2018
4182698
OSP-X 2B SI Pump Recirculation Flow Anomaly
10/11/2018
4182783
OSP-A 2B SI Pump Recirculation Line Restriction
10/12/2018
4183593
Inspection Results of 2B SI Pump Recirculation Line FME
10/15/2018
4186040
NRC ID During Mode 4 Containment Walk Down
10/21/2018
4188177
FME Identified in K-14 RCCA Assembly
10/26/2018
4190621
NRC Green LIV - Security Inspection
11/01/2018
4190742
Digital FRV Controlling with Integral Function
11/01/2018
4193552
Notification Part 21 Framatome RFM Manipulator Gripper
11/09/2018
4197712
OPS Focus, Monitoring Plant Conditions Closely
11/26/2018
4198029
Foreign Material Exclusion (FME) - Declining Trend
2/22/2019
203982
2B SI Pump Low Recirculation Flow Rate
03/21/2019
210285
Source of FME ins 2B SI System
01/11/2019
216119
Level 3 OPEX Review Requested
01/31/2019
217023
DBAI: HELB Manual Actions
2/10/2014
217133
DBAI: Global Effects of Missile Impact on RWST Hatch
Cover
2/04/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
217715
Self-Assessment: Ops Mid-Cycle with OJT/TPE/Inst/SMEs
2/06/2019
217716
Self-Assessment: Ops 71111.11
2/06/2019
217944
Level 3 OPEX Review--ICES 449343
04/24/2019
22716
Loose Conduit Nut on 1B AF Pump
2/22/2019
24262
DG Temperature Switch - Part 21 Evaluation
2/27/2019
29548
Potential Part 21 Applicability on Battery Charger 111
10/17/2019
232818
FME: 2TO5337A Inspection Revealed FM
08/10/2019
233266
Two DEP Failures of an Evaluated Simulator Scenario
03/26/2019
235177
FME: Metal Tag Cable Created I/A Leak on 1LC-ES086
04/01/2019
236442
NOS ID RCR 4145161 Contained Descripencies: CA Not
Classified
04/04/2019
254840
2BWOA RCP-2 Entry
06/06/2019
256355
Self Assessment FME
06/12/2019
261661
One ILT SRO-I Preliminary Denied License By NRC
07/03/2019
263659
Scaffold Tie Off to Structure Broke--Div 12 ESF Room
07/12/2019
265036
DC Bus 212 Ground (2DC06E - 125 Vdc ESF - Distribution
Center Bus 212)
07/18/2019
265545
Unexpected Annunciator 1-21-D6. DC Bus 111 Ground
(1DC05E 125 Vdc ESF Dist. Cent 111 Assembly)
07/19/2019
266244
Perform OPEX Review of 2019 INPO FME AFIs
09/24/2019
267116
DC Bus 212 Ground (2DC06E - 125 Vdc ESF Dist. Cent 212
Assembly)
07/26/2019
268875
Station Vulnerability Issue Due to Ginna OPEX 458342
08/01/2019
268944
NOS ID 2018 Bioassay Prgm Periodic Measuremt Not
Performed
08/01/2019
269225
Efficiency Impact Seen With Lake Softening
07/25/2019
269360
DC Bus 212 Ground (2DC06E - 125 Vdc ESF Dist. Cent 212
Assembly)
08/03/2019
270275
+96 Vdc Ground on DC 111
08/07/2019
270893
2TO5337A Inspection Revealed FM
08/10/2019
272759
Pilot Cell 19 at 91F (>90F Admin Limit) 2DC01E (2DC01E -
ESF Battery 211 Assembly)
08/18/2019
272834
DC 112 Specific Gravity Deviation High (1DC02E - ESF
08/18/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Battery 112 Assembly)
273460
OP-AA-105-102, Att 1 Not Complete for First Qtr 2019
08/20/2019
273637
Crew Learning for LORT Scenario
08/22/2019
277166
DC Bus 211 Ground (2DC05E - 125 Vdc ESF Dist. Center
Bus 211 Assembly)
09/06/2019
277356
Unexpected Alarm 1-21-E8 125 Vdc Batt Charger 111
Trouble
09/06/2019
278172
Part 21 Closure Actions Inadequate
10/10/2019
278351
09/11/2019
278530
Proactive Inspection to Prevent Grounds 1AP01E (1AP01E -
Unit Aux. Power Transformer 141-1)
09/11/2019
278534
Proactive Inspection to Prevent Grounds 2AP70E (2AP70E -
Unit Aux. Power Transformer 241-2)
09/11/2019
278536
Proactive Inspection to Prevent Grounds 1AP02E (1AP02E -
Transformer, System Aux Trans 142-1)
09/11/2019
278539
Proactive Inspection to Prevent Grounds 1AP71E (1AP71E -
System Aux Transformer 142-2)
09/11/2019
278540
Proactive Inspection to Prevent Grounds 2AP02E (2AP02E -
System Aux. Power Transformer 242-1)
09/11/2019
278544
Proactive Inspection to Prevent Grounds 2AP71E (2AP71E -
System Aux. Power Transformer 242-2)
09/11/2019
278548
Proactive Inspection to Prevent Grounds 1SY01E (1SY01E -
SAT 142-1 E.O. Disc Switch)
09/11/2019
278549
Proactive Inspection to Prevent Grounds 1SY02E (1SY02E -
SAT 142-2 E.O. Disc Switch)
09/11/2019
278551
Proactive Inspection to Prevent Grounds 2SY01E (2SY01E -
SAT 242-1 E.O. Disc Switch)
09/11/2019
278557
Proactive Inspection to Prevent Grounds 1FP01EA
(1FP01EA - Outside FP Alarm Horn for Transformer Area)
09/11/2019
278558
Proactive Inspection to Prevent Grounds 1FP01EB
(1FP01EB - Inside FP Alarm Horn for Transformer Area)
09/11/2019
278559
Proactive Inspection to Prevent Grounds 2FP01EA
(2FP01EA - Alarm Horn Outdoor Transformer Area)
09/11/2019
278561
Proactive Inspection to Prevent Grounds 2FP01EB
09/11/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(2FP01EB - Alarm Horn Outdoor Transformer Area)
281258
1ER-DC05E Positive Ground Pushed Is > Rounds Maximum
(1ER DC05E DC Bus 111 Ground Voltage Recorder)
09/22/2019
282020
DC ESF Bus 112 Ground Alarm Received (1DC06E - 125
Vdc ESF Dist. Cent 112 Assembly)
09/25/2019
282409
NOS ID'D: 1 of 10 LORT JPM Score Sheets was Incomplete
09/26/2019
283427
FME: Foreign Material Found During Disassembly of
1PS124A
09/30/2019
283868
20 Pre-NRC Problem Identification and Resolution
Inspection
01/17/2020
285090
1B AF Pump Flow Lower Than Acceptable Flow
10/04/2019
285470
2-OSP-F Unexpected Alarm DC 112 Ground
10/06/2019
285532
-122 Vdc 112 Ground
10/07/2019
286018
2 DC Ground
10/08/2019
286217
05-OSP-X Received Unexpected ALM 1-21-E8, 111 Battery
Charger Trouble (1DC03C Battery Charger 111)
10/09/2019
287611
FME - Metal Shavings Found in ES Piping
10/14/2019
288186
10-OSP-R T/S Multiple Spurious Alarms on DC 111 Charger
(1DC03E 125 Vdc Battery Charger 111)
10/16/2019
288445
11-OSP-R Intermittent DC Bus 112 Ground (1DC06E - 125
Vdc ESF Dist. Cent 112)
10/16/2019
289894
Unexpected Alarm 1-22-D6 DC Bus 112 Ground
10/21/2019
295309
1ER-DC05E Reads > 75 V (1ER-DC05E - DC Bus 111
Ground Voltage Recorder)
11/07/2019
298533
DC Bus 212 Ground Detector Is Degraded (2ER-DC06E -
DC Bus 212 Ground Voltage Recorder)
11/19/2019
298558
25 Vdc Battery Charger 111 Alarm Received After Ground
Check (1ER-DC05E DC Bus 111 Ground Voltage
Recorder)
11/20/2019
298558
25 Vdc Battery Charger 111 Alarm Received After Ground
Check
11/20/2019
4300007
DC 112 Ground During FP RTS (1FP02J - Fire Protection
Cabinet 1FP02J)
11/26/2019
4301635
Clearance & Tagging Annual Audit Deficiency - Ops
2/04/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4302464
Unexpected Alarms 1-21-D6 and 1-21-E8 (1DC05E 125
Vdc ESF Dist. Cent 111 Assembly)
2/09/2019
4302464
Unexpected Alarms 1-21-D6 and 1-21-E8
2/09/2019
4304503
Erratic Negative Ground Volt Reading When Depressed DC
2
2/17/2019
4304938
Level 3 Config Control: Zero d/p Indicated on 0PDI-VC058
2/19/2019
4308125
Battery 212 Charger Circuit Card Issue (2DC04E - 125 Vdc
Battery Charger 212 Assembly)
01/05/2020
4308795
Unexpected Annunciator: 1-21-E8 (1DC03E 125 Vdc
Battery Charger 111)
01/08/2020
Corrective Action
Documents
Resulting from
Inspection
21466
NRC ID: Issue With Rigging Restraint
2/25/2020
21854
NRC ID'd Deficiency on 1PL100J With No Open WR/WO
2/27/2020
Drawings
20E-1-4030DC05
Schematic Diagram, 125 Vdc ESF Distribution Center, Bus
111, Part 1, 1DC05E
X
20E-1-4030DC06
Schematic Diagram, 125 Vdc ESF Distribution Center, Bus
111, Part 2, 1DC05E
P
AC-7
AC One Line Diagram, January 6, 2015 (For Training Use
Only)
DC-1
25 Vdc System (For Training Use Only)
DC-2
250 Vdc System (For Training Use Only)
Engineering
Changes
25953
Evaluate Impact on Safety Analyses due to As-Found ECCS
Flow Rates
10/20/2018
BR-19-002
Surveillance Test Interval (STI) Evaluation: Revise The 125
Vdc ESF Battery Bank and Charger Operability Weekly
Surveillance Frequency from Once per 7-days to Once per
31-days
BRW-15-006
Surveillance Test Interval (STI) Evaluation: Change the STI
for Service Test (SR 3.8.4.3) to an 18-month Staggered Test
Basis
Engineering
Evaluations
2541232-46-01
ICES 318417, Sequoyah Unit 1 Trip Due to Loss of Vital
Inverter Power Board
05/19/2016
2683598-83
ICES 323906, Prairie Island Diesel Driven Fire Pump Failed
09/22/2016
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
to Start
28714
Multiple Losses of ESF Bus 141 during 1A Diesel Generator
Sequence Testing in A1R20
06/08/2018
4190742
Feedwater Regulating Valve Oscillations During Power
Ascension
01/17/2019
4192903
2018 Equipment Reliability Evaluation
2/10/2018
ATI 02541232-46-
ICES 318417, Sequoyah Unit 1 Trip Due to Loss of Vital
Inverter Power Board
05/19/2016
ATI 02683598-83
ICES 323906, Prairie Island Diesel Driven Fire Pump Failed
to Start
09/22/2016
ATI 03969265-82
ICES 407851, Palo Verde Unit 2 Inverter Failed to Transfer
to Emergency Power
No Date
Given
ATI 03993342-02
ICES 407278, Catawba Battery System Cell Failure
04/04/2017
ATI 04008241-33
ICES 408139, Fermi Unit 2 Uninterruptible Power Supply
Inverter Failed to Start
No Date
Given
ATI 04048975-28
ICES 420726, Fermi Unit 2 Balance of Plant Battery Charger
Failed to Charge
09/27/2017
ATI 04048975-96
ICES 426149, Byron Unit 2 Battery Charger Input Breaker
Tripped Open
No Date
Given
ATI 04066205-02
NRC IN 2017-06: Battery and Battery Charger Short-Circuit
Current Contributions to a Fault on the Direct Current
Distribution System
2/13/2017
ATI 04242973-53
IRIS 460461, Quad Cities Unit 1 24/48 Vdc Charger Tripped
10/30/2019
Miscellaneous
2018 ECP Logs
2019 ECP Logs
2019 ECP Files
Plant Health Committee Agenda
2/24/2020
Braidwood Management Review Committee Agenda
2/11/2020;
2/13/2020;
2/24/2020
Station Ownership Committee Package
2/10/2020;
2/12/2020;
2/13/2020;
2/24/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Station Trend Report
November
2019
Station Trend Report
December
2019
--
Final Safety Evaluation for PWROG Topical Report WCAP-
17661, Rev. 1, "Improved RAOC and CAOC FQ Surveillance
Technical Specifications,"
2018 ECP Files
Standard
IEEE Recommended Practice for Maintenance, Testing, and
Replacement of Vented Lead-Acid Batteries for Stationary
Applications
1995
NUREG-0800, Standard Review Plan, 8.3.2 D-C Power-
Systems
IN 2013-05; Battery Expected Life and Its Potential Impact on
Surveillance Requirements
03/19/2013
Att 20
Performance Analysis 04281548-06
10/30/2019
Exelon Nuclear Policy: Nuclear Safety Culture
2/05/2015
PORC Meeting:
18-025
PORC Topic: Surveillance Test Interval (STI) BRW-15-006 -
Change the STI for Service Test (SR 3.8.4.3) To An 18-
Month Staggered Test Basis
09/20/2018
STS428.TG
NRC Inspection Manual, Part 9900: Technical Guidance,
Standard Technical Specifications, Section 4.2.8.X.X.
Surveillance Requirements - 125 Volt Battery Bank
10/01/1979
Operability
Evaluations18-001
2B SI Pump Low Recirc Flow Rate
Procedures
1BwHSR 3.8.4.2-
111
Unit One 125 Volt ESF Battery Charger 111 Capacity Test
1BwHSR 3.8.4.2-
2
Unit One 125 Volt ESF Battery Charger 112 Capacity Test
1BwHSR 3.8.4.3-
111
Unit One 125 Volt ESF Battery Bank 111 Service Test
1BwHSR 3.8.4.3-
2
Unit One 125 Volt ESF Battery Bank 112 Service Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1BwHSR 3.8.6.6-
111
Unit One 125 V ESF Battery Bank 111 Modified Performance
Test
1BwHSR 3.8.6.6-
2
Unit One 125 V ESF Battery Bank 112 Modified Performance
Test
1BwOSR 3.8.6.1-
Unit One 125 Vdc ESF Battery Bank and Charger 111
Operability Surveillance
1BwOSR 3.8.6.1-
Unit One 125 Vdc ESF Battery Bank and Charger 112
Operability Surveillance
1BwOSR 3.8.6.5-
Unit One 125 Vdc ESF Battery Bank 111 Operability
Surveillance
1BwOSR 3.8.6.5-
Unit One 125 Vdc ESF Battery Bank 112 Operability
Surveillance
2BwHSR 3.8.4.2-
211
Unit Two 125 Volt ESF Battery Charger 211 Capacity Test
2BwHSR 3.8.4.2-
2
Unit Two 125 Volt ESF Battery Charger 212 Capacity Test
2BwHSR 3.8.4.3-
211
Unit Two 125 Volt ESF Battery Bank 211 Service Test
2BwHSR 3.8.4.3-
2
Unit Two 125 Volt ESF Battery Bank 212 Service Test
2BwHSR 3.8.6.6-
211
Unit Two 125 V ESF Battery Bank 211 Modified Performance
Test
2BwHSR 3.8.6.6-
2
Unit Two 125 V ESF Battery Bank 212 Modified Performance
Test
2BwOSR 3.8.6.1-
Unit Two 125 Vdc ESF Battery Bank and Charger 211
Operability Surveillance
2BwOSR 3.8.6.1-
Unit Two 125 Vdc ESF Battery Bank and Charger 212
Operability Surveillance
2BwOSR 3.8.6.5-
Unit Two 125 Vdc ESF Battery Bank 211 Operability
Surveillance
2BwOSR 3.8.6.5-
Unit Two 125 Vdc ESF Battery Bank 212 Operability
Surveillance
Nuclear Risk Management Process
Procedures
BwHS TRM
25 Volt Battery Bank Surveillance
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
3.8.C.4
BwHS TRM
3.8.C.4S1
25 Volt ESF Battery Bank and Rack Surveillance Data
Sheet for Battery 111
BwHS TRM
3.8.C.4S2
25 Volt ESF Battery Bank and Rack Surveillance Data
Sheet for Battery 112
BwHS TRM
3.8.C.4S3
25 Volt ESF Battery Bank and Rack Surveillance Data
Sheet for Battery 211
BwHS TRM
3.8.C.4S4
25 Volt ESF Battery Bank and Rack Surveillance Data
Sheet for Battery 212
BwOP DC-5-111
25 Vdc ESF Battery 111 Equalization
BwOP DC-5-112
25 Vdc ESF Battery 112 Equalization
BwOP DC-5-211
25 Vdc ESF Battery 211 Equalization
BwOP DC-5-212
25 Vdc ESF Battery 212 Equalization
Plant Health Committee
Maintenance Rule 18-10 - Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
NRC Problem Identification and Resolution Inspection
Procedure
01/01/2015
Station Rework Reduction Program
Station Battery Testing Strategies
Nuclear Oversight Audit Templates
Performance Monitoring and Analysis Manual
Performance Gap Resolution
Operating Experience Program
Processing of Level 1 and Level 2 OPEX Evaluations
Processing of Level 2 OPEX Evaluations
Processing of Level 3 OPEX Evaluations
Issue Identification and Screening Process
Corrective Action Program Procedure
Corrective Action Program Evaluation Manual
Self-Assessments
Braidwood Station Maintenance Rule Periodic a(3)
Assessment
December 1,
2017 to
January 19,
2019
4074648
Simulator Management Compliance (per TQ-AA-306)
11/14/2017
NOS Objective Evidence Report Maintenance Functional
Area Audit - Battery Maintenance and Testing (AR 2608396-
17)
2/03/2016
NOSA-BRW-16-
Braidwood Station Maintenance Audit Report 01/19/2016 to
01/29/2016 (AR2608396)
2/03/2016
NOSA-BRW-16-
Braidwood Station Engineering Programs and Station
Blackout Audit Report 03/28/2016 to 04/08/2016
04/13/2016
NOSA-BRW-18-
Braidwood Station Maintenance Functional Area Audit
Report 02/19/2018 to 03/2/2018 (AR4090567)
03/08/2018
NOSA-BRW-18-
Braidwood Station Emergency Preparedness Audit Report
03/26/2018 to 04/06/2018 (AR4113152)
04/11/2018
NOSA-BRW-18-
Braidwood Station In-service Inspection, In-service Testing,
and Appendix J Audit Report 08/20/2018 to 08/31/2018
09/07/2018
NOSA-BRW-19-
Braidwood Station Corrective Action Program Audit Report
03/25/2019 to 04/05/2019 (AR4224677)
04/10/2019
NOSA-BRW-19-
Braidwood Station Radiation Protection Audit Report
07/22/2019 to 08/02/2019 (AR4254882)
08/07/2019
PI-AA-126-1001-
F-01
2018 Employee Concerns Program Performance and
Effectiveness Review
PIIM 2019-0242
2019-0242 System and Component Monitoring
06/07/2019
Corrective Action
Documents
4144070
Unit 1 Manual Reactor Trip Due to Lowering Steam
Generator Level - Root Cause Investigation Report
2/12/2020
4165777
1FW079B Check Valve Further Closed than 1FW079A, C, &
D
08/20/2018
25240
Review of Byron IR 4185973 FW Reg Valv Travel
Transducers
03/01/2019
251835
1PL100J Windows Operating System Crashed
05/26/2019
263048
1PL100J Screen Illegible
07/10/2019
281429
Unit 1 Reactor Trip on 1FW520 Valve Closure
289400
15-OSP-R U1&2 FRV Positioner ByP Reg Handwheel
10/20/2019
291137
1FW530 Full Open Following Power Ascension
10/25/2018
294972
1PL100J Screen is Fuzzy
11/06/2019
296357
A1R21LL - Valve Team Lessons Learned
11/11/2019
4303483
Troubleshooter Requested for FW Performance Hardening
2/12/2019
699328
1FW079B Check Valve Further Closed than Expected
11/14/2007
2428
Modify 1FW520 LOOP to Allow Living with FW Line
Restriction
11/21/2007
Engineering
Evaluations
-
Braidwood Unit 1 Feedwater Line C Hydraulic Resistance
Imbalance RELAP5 Study
October
2019
Miscellaneous
Adverse
Condition
Monitoring and
Contingency Plan
U1 Feedwater Regulating Valve (FRV) Position
10/25/2019
Adverse
Condition
Monitoring and
Contingency Plan
U2 Feedwater Regulating Valve DVC Health
10/29/2019
Procedures
ROOT CAUSE ANALYSIS MANUAL
Work Orders
29232
1FW079B Check Valve Further Closed than 1FW079A,
C, & D
2/01/2019
4989927
Troubleshooter Requested for FW Performance Hardening
2/15/2019