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: NPF-72 and NPF-77 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 Enclosure
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 71153 Closed Braidwood Station, Unit 1,
Unit Trip on Low Steam Generator Level Due to Failure of a Controller on a Feedwater Regulating Valve
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 Type Designation Description or Title Revision or
Procedure Date
71152B Corrective Action 2448240 Westinghouse NSAL-15-1 . FQ(Z) Tech Spec Surveillance 02/05/2015
Documents 2567071 OSP-A-CT--Exciter Stator Phase Banding Is Loosening 10/07/2015
2589930 Root Cause Report: Severe Corrosion and Degraded 12/29/2015
Coating Observed on Line 0SXH2AA-6
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 06/01/2018
Inspection
4074647 Ops Effectiveness Review of ATV Actions Self-Assessment 11/14/2017
4081071 Level 3 OPEX Review Needed--Unusual Event Hydrogen 12/05/2017
Leak
4083304 DC System Short Circuit Calculation Update 12/12/2017
4086455 Green NCV - Errors in Analysis of Record for MS Line HELB 12/21/2017
4107379 Security 24 HR Loggable SY-AA-103-500 Procedure Not 02/23/2018
Followed
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 04/19/2018
Testing
29240 OSP-X 1RC01R NDE Results for 1RV-03-002 Reactor Head 06/19/2020
Weld
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 Type Designation Description or Title Revision or
Procedure 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 07/10/2018
Performance
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 08/28/2018
Instructions
4167985 2Q18 Green Finding--Work Instruction Error Caused RCS 08/28/2018
Issue
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 02/22/2019
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 12/10/2014
217133 DBAI: Global Effects of Missile Impact on RWST Hatch 02/04/2019
Cover
Inspection Type Designation Description or Title Revision or
Procedure Date
217715 Self-Assessment: Ops Mid-Cycle with OJT/TPE/Inst/SMEs 02/06/2019
217716 Self-Assessment: Ops 71111.11 02/06/2019
217944 Level 3 OPEX Review--ICES 449343 04/24/2019
22716 Loose Conduit Nut on 1B AF Pump 02/22/2019
24262 DG Temperature Switch - Part 21 Evaluation 02/27/2019
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 04/04/2019
Classified
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 07/18/2019
Center Bus 212)
265545 Unexpected Annunciator 1-21-D6. DC Bus 111 Ground 07/19/2019
(1DC05E 125 Vdc ESF Dist. Cent 111 Assembly)
266244 Perform OPEX Review of 2019 INPO FME AFIs 09/24/2019
267116 DC Bus 212 Ground (2DC06E - 125 Vdc ESF Dist. Cent 212 07/26/2019
Assembly)
268875 Station Vulnerability Issue Due to Ginna OPEX 458342 08/01/2019
268944 NOS ID 2018 Bioassay Prgm Periodic Measuremt Not 08/01/2019
Performed
269225 Efficiency Impact Seen With Lake Softening 07/25/2019
269360 DC Bus 212 Ground (2DC06E - 125 Vdc ESF Dist. Cent 212 08/03/2019
Assembly)
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 - 08/18/2019
ESF Battery 211 Assembly)
272834 DC 112 Specific Gravity Deviation High (1DC02E - ESF 08/18/2019
Inspection Type Designation Description or Title Revision or
Procedure 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 09/06/2019
Bus 211 Assembly)
277356 Unexpected Alarm 1-21-E8 125 Vdc Batt Charger 111 09/06/2019
Trouble
278172 Part 21 Closure Actions Inadequate 10/10/2019
278351 60 DPM JW Leak 1B EDG--1DG01KB 09/11/2019
278530 Proactive Inspection to Prevent Grounds 1AP01E (1AP01E - 09/11/2019
Unit Aux. Power Transformer 141-1)
278534 Proactive Inspection to Prevent Grounds 2AP70E (2AP70E - 09/11/2019
Unit Aux. Power Transformer 241-2)
278536 Proactive Inspection to Prevent Grounds 1AP02E (1AP02E - 09/11/2019
Transformer, System Aux Trans 142-1)
278539 Proactive Inspection to Prevent Grounds 1AP71E (1AP71E - 09/11/2019
System Aux Transformer 142-2)
278540 Proactive Inspection to Prevent Grounds 2AP02E (2AP02E - 09/11/2019
System Aux. Power Transformer 242-1)
278544 Proactive Inspection to Prevent Grounds 2AP71E (2AP71E - 09/11/2019
System Aux. Power Transformer 242-2)
278548 Proactive Inspection to Prevent Grounds 1SY01E (1SY01E - 09/11/2019
SAT 142-1 E.O. Disc Switch)
278549 Proactive Inspection to Prevent Grounds 1SY02E (1SY02E - 09/11/2019
SAT 142-2 E.O. Disc Switch)
278551 Proactive Inspection to Prevent Grounds 2SY01E (2SY01E - 09/11/2019
SAT 242-1 E.O. Disc Switch)
278557 Proactive Inspection to Prevent Grounds 1FP01EA 09/11/2019
(1FP01EA - Outside FP Alarm Horn for Transformer Area)
278558 Proactive Inspection to Prevent Grounds 1FP01EB 09/11/2019
(1FP01EB - Inside FP Alarm Horn for Transformer Area)
278559 Proactive Inspection to Prevent Grounds 2FP01EA 09/11/2019
(2FP01EA - Alarm Horn Outdoor Transformer Area)
278561 Proactive Inspection to Prevent Grounds 2FP01EB 09/11/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
(2FP01EB - Alarm Horn Outdoor Transformer Area)
281258 1ER-DC05E Positive Ground Pushed Is > Rounds Maximum 09/22/2019
(1ER DC05E DC Bus 111 Ground Voltage Recorder)
282020 DC ESF Bus 112 Ground Alarm Received (1DC06E - 125 09/25/2019
Vdc ESF Dist. Cent 112 Assembly)
282409 NOS ID'D: 1 of 10 LORT JPM Score Sheets was Incomplete 09/26/2019
283427 FME: Foreign Material Found During Disassembly of 09/30/2019
1PS124A
283868 2020 Pre-NRC Problem Identification and Resolution 01/17/2020
Inspection
285090 1B AF Pump Flow Lower Than Acceptable Flow 10/04/2019
285470 02-OSP-F Unexpected Alarm DC 112 Ground 10/06/2019
285532 -122 Vdc 112 Ground 10/07/2019
286018 212 DC Ground 10/08/2019
286217 05-OSP-X Received Unexpected ALM 1-21-E8, 111 Battery 10/09/2019
Charger Trouble (1DC03C Battery Charger 111)
287611 FME - Metal Shavings Found in ES Piping 10/14/2019
288186 10-OSP-R T/S Multiple Spurious Alarms on DC 111 Charger 10/16/2019
(1DC03E 125 Vdc Battery Charger 111)
288445 11-OSP-R Intermittent DC Bus 112 Ground (1DC06E - 125 10/16/2019
Vdc ESF Dist. Cent 112)
289894 Unexpected Alarm 1-22-D6 DC Bus 112 Ground 10/21/2019
295309 1ER-DC05E Reads > 75 V (1ER-DC05E - DC Bus 111 11/07/2019
Ground Voltage Recorder)
298533 DC Bus 212 Ground Detector Is Degraded (2ER-DC06E - 11/19/2019
DC Bus 212 Ground Voltage Recorder)
298558 125 Vdc Battery Charger 111 Alarm Received After Ground 11/20/2019
Check (1ER-DC05E DC Bus 111 Ground Voltage
Recorder)
298558 125 Vdc Battery Charger 111 Alarm Received After Ground 11/20/2019
Check
4300007 DC 112 Ground During FP RTS (1FP02J - Fire Protection 11/26/2019
Cabinet 1FP02J)
4301635 Clearance & Tagging Annual Audit Deficiency - Ops 12/04/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
4302464 Unexpected Alarms 1-21-D6 and 1-21-E8 (1DC05E 125 12/09/2019
Vdc ESF Dist. Cent 111 Assembly)
4302464 Unexpected Alarms 1-21-D6 and 1-21-E8 12/09/2019
4304503 Erratic Negative Ground Volt Reading When Depressed DC 12/17/2019
2
4304938 Level 3 Config Control: Zero d/p Indicated on 0PDI-VC058 12/19/2019
4308125 Battery 212 Charger Circuit Card Issue (2DC04E - 125 Vdc 01/05/2020
Battery Charger 212 Assembly)
4308795 Unexpected Annunciator: 1-21-E8 (1DC03E 125 Vdc 01/08/2020
Battery Charger 111)
Corrective Action 4321466 NRC ID: Issue With Rigging Restraint 02/25/2020
Documents 4321854 NRC ID'd Deficiency on 1PL100J With No Open WR/WO 02/27/2020
Resulting from
Inspection
Drawings 20E-1-4030DC05 Schematic Diagram, 125 Vdc ESF Distribution Center, Bus X
111, Part 1, 1DC05E
20E-1-4030DC06 Schematic Diagram, 125 Vdc ESF Distribution Center, Bus P
111, Part 2, 1DC05E
AC-7 AC One Line Diagram, January 6, 2015 (For Training Use 8
Only)
DC-1 125 Vdc System (For Training Use Only) 9
DC-2 250 Vdc System (For Training Use Only) 3
Engineering 625953 Evaluate Impact on Safety Analyses due to As-Found ECCS 10/20/2018
Changes Flow Rates
BR-19-002 Surveillance Test Interval (STI) Evaluation: Revise The 125 0
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 2
for Service Test (SR 3.8.4.3) to an 18-month Staggered Test
Basis
Engineering 2541232-46-01 ICES 318417, Sequoyah Unit 1 Trip Due to Loss of Vital 05/19/2016
Evaluations Inverter Power Board
2683598-83 ICES 323906, Prairie Island Diesel Driven Fire Pump Failed 09/22/2016
Inspection Type Designation Description or Title Revision or
Procedure Date
to Start
28714 Multiple Losses of ESF Bus 141 during 1A Diesel Generator 06/08/2018
Sequence Testing in A1R20
4190742 Feedwater Regulating Valve Oscillations During Power 01/17/2019
Ascension
4192903 2018 Equipment Reliability Evaluation 12/10/2018
ATI 02541232-46- ICES 318417, Sequoyah Unit 1 Trip Due to Loss of Vital 05/19/2016
Inverter Power Board
ATI 02683598-83 ICES 323906, Prairie Island Diesel Driven Fire Pump Failed 09/22/2016
to Start
ATI 03969265-82 ICES 407851, Palo Verde Unit 2 Inverter Failed to Transfer No Date
to Emergency Power 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 No Date
Inverter Failed to Start Given
ATI 04048975-28 ICES 420726, Fermi Unit 2 Balance of Plant Battery Charger 09/27/2017
Failed to Charge
ATI 04048975-96 ICES 426149, Byron Unit 2 Battery Charger Input Breaker No Date
Tripped Open Given
ATI 04066205-02 NRC IN 2017-06: Battery and Battery Charger Short-Circuit 12/13/2017
Current Contributions to a Fault on the Direct Current
Distribution System
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 02/24/2020
Braidwood Management Review Committee Agenda 02/11/2020;
2/13/2020;
2/24/2020
Station Ownership Committee Package 02/10/2020;
2/12/2020;
2/13/2020;
2/24/2020
Inspection Type Designation Description or Title Revision or
Procedure 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
IEEE-450 IEEE Recommended Practice for Maintenance, Testing, and 1995
Standard Replacement of Vented Lead-Acid Batteries for Stationary
Applications
ML052350494 NUREG-0800, Standard Review Plan, 8.3.2 D-C Power- 2
Systems
ML122130601 IN 2013-05; Battery Expected Life and Its Potential Impact on 03/19/2013
Surveillance Requirements
PI-AA-125-1006, Performance Analysis 04281548-06 10/30/2019
Att 20
PI-AA-3 Exelon Nuclear Policy: Nuclear Safety Culture 02/05/2015
PORC Meeting: PORC Topic: Surveillance Test Interval (STI) BRW-15-006 - 09/20/2018
18-025 Change the STI for Service Test (SR 3.8.4.3) To An 18-
Month Staggered Test Basis
STS428.TG NRC Inspection Manual, Part 9900: Technical Guidance, 10/01/1979
Standard Technical Specifications, Section 4.2.8.X.X.
Surveillance Requirements - 125 Volt Battery Bank
Operability 18-001 2B SI Pump Low Recirc Flow Rate 1
Evaluations
Procedures 1BwHSR 3.8.4.2- Unit One 125 Volt ESF Battery Charger 111 Capacity Test 4
111
1BwHSR 3.8.4.2- Unit One 125 Volt ESF Battery Charger 112 Capacity Test 1
2
1BwHSR 3.8.4.3- Unit One 125 Volt ESF Battery Bank 111 Service Test 1
111
1BwHSR 3.8.4.3- Unit One 125 Volt ESF Battery Bank 112 Service Test 1
2
Inspection Type Designation Description or Title Revision or
Procedure Date
1BwHSR 3.8.6.6- Unit One 125 V ESF Battery Bank 111 Modified Performance 4
111 Test
1BwHSR 3.8.6.6- Unit One 125 V ESF Battery Bank 112 Modified Performance 4
2 Test
1BwOSR 3.8.6.1- Unit One 125 Vdc ESF Battery Bank and Charger 111 18
Operability Surveillance
1BwOSR 3.8.6.1- Unit One 125 Vdc ESF Battery Bank and Charger 112 20
Operability Surveillance
1BwOSR 3.8.6.5- Unit One 125 Vdc ESF Battery Bank 111 Operability 15
Surveillance
1BwOSR 3.8.6.5- Unit One 125 Vdc ESF Battery Bank 112 Operability 16
Surveillance
2BwHSR 3.8.4.2- Unit Two 125 Volt ESF Battery Charger 211 Capacity Test 4
211
2BwHSR 3.8.4.2- Unit Two 125 Volt ESF Battery Charger 212 Capacity Test 1
2
2BwHSR 3.8.4.3- Unit Two 125 Volt ESF Battery Bank 211 Service Test 1
211
2BwHSR 3.8.4.3- Unit Two 125 Volt ESF Battery Bank 212 Service Test 1
2
2BwHSR 3.8.6.6- Unit Two 125 V ESF Battery Bank 211 Modified Performance 4
211 Test
2BwHSR 3.8.6.6- Unit Two 125 V ESF Battery Bank 212 Modified Performance 4
2 Test
2BwOSR 3.8.6.1- Unit Two 125 Vdc ESF Battery Bank and Charger 211 18
Operability Surveillance
2BwOSR 3.8.6.1- Unit Two 125 Vdc ESF Battery Bank and Charger 212 18
Operability Surveillance
2BwOSR 3.8.6.5- Unit Two 125 Vdc ESF Battery Bank 211 Operability 15
Surveillance
2BwOSR 3.8.6.5- Unit Two 125 Vdc ESF Battery Bank 212 Operability 15
Surveillance
AD-AA-3000 Nuclear Risk Management Process 4
71152B Procedures BwHS TRM 125 Volt Battery Bank Surveillance 8
Inspection Type Designation Description or Title Revision or
Procedure Date
3.8.C.4
BwHS TRM 125 Volt ESF Battery Bank and Rack Surveillance Data 3
3.8.C.4S1 Sheet for Battery 111
BwHS TRM 125 Volt ESF Battery Bank and Rack Surveillance Data 3
3.8.C.4S2 Sheet for Battery 112
BwHS TRM 125 Volt ESF Battery Bank and Rack Surveillance Data 4
3.8.C.4S3 Sheet for Battery 211
BwHS TRM 125 Volt ESF Battery Bank and Rack Surveillance Data 3
3.8.C.4S4 Sheet for Battery 212
BwOP DC-5-111 125 Vdc ESF Battery 111 Equalization 9
BwOP DC-5-112 125 Vdc ESF Battery 112 Equalization 9
BwOP DC-5-211 125 Vdc ESF Battery 211 Equalization 8
BwOP DC-5-212 125 Vdc ESF Battery 212 Equalization 8
ER-AA-2001 Plant Health Committee 25
ER-AA-320-1004 Maintenance Rule 18-10 - Performance Monitoring and 1
Dispositioning Between (a)(1) and (a)(2)
IP 71152 NRC Problem Identification and Resolution Inspection 01/01/2015
Procedure
MA-AA-716-017 Station Rework Reduction Program 8
MA-AA-721-1001 Station Battery Testing Strategies 2
NO-AA-210-1002 Nuclear Oversight Audit Templates 10
PI-AA-101-1001 Performance Monitoring and Analysis Manual 3
PI-AA-101-1003 Performance Gap Resolution 0
PI-AA-115 Operating Experience Program 5
PI-AA-115-1001 Processing of Level 1 and Level 2 OPEX Evaluations 3
PI-AA-115-1002 Processing of Level 2 OPEX Evaluations 3
PI-AA-115-1003 Processing of Level 3 OPEX Evaluations 5
PI-AA-120 Issue Identification and Screening Process 9
PI-AA-125 Corrective Action Program Procedure 7
PI-AA-125-1003 Corrective Action Program Evaluation Manual 5
71152B Self-Assessments Braidwood Station Maintenance Rule Periodic a(3) December 1,
Assessment 2017 to
January 19,
2019
4074648 Simulator Management Compliance (per TQ-AA-306) 11/14/2017
M1C-4 NOS Objective Evidence Report Maintenance Functional 02/03/2016
Area Audit - Battery Maintenance and Testing (AR 2608396-
17)
NOSA-BRW-16- Braidwood Station Maintenance Audit Report 01/19/2016 to 02/03/2016
01/29/2016 (AR2608396)
NOSA-BRW-16- Braidwood Station Engineering Programs and Station 04/13/2016
Blackout Audit Report 03/28/2016 to 04/08/2016
(AR2637791)
NOSA-BRW-18- Braidwood Station Maintenance Functional Area Audit 03/08/2018
Report 02/19/2018 to 03/2/2018 (AR4090567)
NOSA-BRW-18- Braidwood Station Emergency Preparedness Audit Report 04/11/2018
03/26/2018 to 04/06/2018 (AR4113152)
NOSA-BRW-18- Braidwood Station In-service Inspection, In-service Testing, 09/07/2018
and Appendix J Audit Report 08/20/2018 to 08/31/2018
(AR4161245)
NOSA-BRW-19- Braidwood Station Corrective Action Program Audit Report 04/10/2019
03/25/2019 to 04/05/2019 (AR4224677)
NOSA-BRW-19- Braidwood Station Radiation Protection Audit Report 08/07/2019
07/22/2019 to 08/02/2019 (AR4254882)
PI-AA-126-1001- 2018 Employee Concerns Program Performance and 2
F-01 Effectiveness Review
PIIM 2019-0242 2019-0242 System and Component Monitoring 06/07/2019
71153 Corrective Action 4144070 Unit 1 Manual Reactor Trip Due to Lowering Steam 02/12/2020
Documents Generator Level - Root Cause Investigation Report
4165777 1FW079B Check Valve Further Closed than 1FW079A, C, & 08/20/2018
D
25240 Review of Byron IR 4185973 FW Reg Valv Travel 03/01/2019
Transducers
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 12/12/2019
699328 1FW079B Check Valve Further Closed than Expected 11/14/2007
2428 Modify 1FW520 LOOP to Allow Living with FW Line 11/21/2007
Restriction
Engineering - Braidwood Unit 1 Feedwater Line C Hydraulic Resistance October
Evaluations Imbalance RELAP5 Study 2019
Miscellaneous Adverse U1 Feedwater Regulating Valve (FRV) Position 10/25/2019
Condition
Monitoring and
Contingency Plan
Adverse U2 Feedwater Regulating Valve DVC Health 10/29/2019
Condition
Monitoring and
Contingency Plan
Procedures PI-AA-125-1001 ROOT CAUSE ANALYSIS MANUAL 5
Work Orders 4829232 1FW079B Check Valve Further Closed than 1FW079A, 12/01/2019
C, & D
4989927 Troubleshooter Requested for FW Performance Hardening 12/15/2019
19