IR 05000254/2020010
| ML20329A436 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities |
| Issue date: | 11/24/2020 |
| From: | Reimer K NRC/RGN-III/DRP/B1 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2020010 | |
| Download: ML20329A436 (20) | |
Text
November 24, 2020
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000254/2020010 AND 05000265/2020010
Dear Mr. Hanson:
On October 23, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Quad Cities Nuclear Power Station and discussed the results of this inspection with Mr. K. Ohr, 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/
Kenneth R. Riemer, Chief Branch 1 Division of Reactor Projects
Docket Nos. 05000254 and 05000265 License Nos. DPR-29 and DPR-30
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000254 and 05000265
License Numbers:
Report Numbers:
05000254/2020010 and 05000265/2020010
Enterprise Identifier: I-2020-010-0034
Licensee:
Exelon Generation Company, LLC
Facility:
Quad Cities Nuclear Power Station
Location:
Cordova, IL
Inspection Dates:
October 05, 2020 to October 23, 2020
Inspectors:
V. Petrella, Reactor Inspector
C. Mathews, Illinois Emergency Management Agency
C. Phillips, Project Engineer
A. Shaikh, Senior Reactor Inspector
D. Tesar, Resident Inspector
Approved By:
Kenneth R. Riemer, Chief
Branch 1
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 Quad Cities Nuclear Power 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.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week and during that time conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities, and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.
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 CAP's effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted a 5-year review of the Unit 1 turbine building closed cooling water (TBCCW) system.
- 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.
INSPECTION RESULTS
Assessment 71152B Assessment of the Corrective Action Program
Based on the samples reviewed, the team determined that your staff's performance in each of these areas adequately supported nuclear safety.
Effectiveness of Problem Identification
Overall, the licensee was generally effective at identifying issues at a low threshold and was properly entering them into the CAP as required by station procedures. The inspectors determined issues were normally identified and captured in a complete and accurate manner in the CAP. The inspectors determined the licensee was effective at identifying negative trends that could potentially impact nuclear safety. The inspectors walked down portions of the Unit 1 TBCCW system, the Unit 1 control rod drive system, and the main control room.
The inspectors did, however, identify issues in the area of problem identification. The inspectors concluded that the CAP was not always used to its full potential. In addition, maintenance discrepancy tags were not always removed from the field for work that had been accomplished or cancelled. Maintenance discrepancy tags that are still hanging for work that has been completed or cancelled can interfere with the entry of items into the CAP.
The licensee's CAP audit completed in 2019 identified a small number of equipment and housekeeping deficiencies
- (10) that were not entered into the CAP, and 33 percent of the deficiency tags reviewed (5 of 15) were found to be completed or cancelled. Maintenance department management determined that there was a process for removing tags, and no further actions were necessary. The operations department management spoke with non-licensed equipment operators and asked them to review deficiency tags periodically, as time allowed.
The maintenance audit completed in March 2020 identified a small number
- (4) of CAQs items that had not been entered into the CAP. In response, the station generated a performance improvement action plan (PIAP) to provide site-wide communication and face-to-face reinforcement of CAP usage. The PIAP was completed on April 30, 2020. The effectiveness review (EFR) of the PIAP was completed in June 2020. The Safety Culture Monitoring Panel and End-of-Day Senior Leadership Team reviews determined that the efforts regarding the PIAP for issues not being entered into the CAP were effective. This was a determination based on what the site was seeing with regards to CAP documents being initiated and the efforts that had been put forth to address this trend. The maintenance audit identified that 27 percent of the deficiency tags reviewed (8 of 30) were from completed or cancelled work.
The actions associated with the deficiency tags from that audit were to issue a site-wide communication regarding proper removal of orphaned deficiency tags. This communication was to be sent out four times before the outage in April 2020 and once a month after the outage for an overall timeframe of three months. The action was marked as completed before the three months even started, and subsequently the site-wide communication was sent out only once prior to the outage.
The inspectors had identified about 15 items that had not been entered into the CAP without prompting from the resident inspectors over the last two years. The majority of these items were identified before the corrective actions were taken in April.
Effectiveness of Prioritization and Evaluation of Issues
The inspectors determined the licensee was effective at prioritizing and evaluating issues.
Most issues were evaluated appropriately in accordance with station procedures and addressed at levels commensurate with their safety significance. Root, potential, and contributing causes were identified for issues as required. The proper level of consideration was taken for extent of cause and condition, generic implications, and evaluation of previous occurrences. The inspectors determined the Management Review Committee meetings and the Station Ownership Committee meetings were thorough and maintained a high standard for evaluation quality. Members of the two committees were prepared and engaged. The committee members discussed selected issues in sufficient detail and challenged each other regarding proposed conclusions and recommendations.
The inspectors also completed an in-depth review of issue reports and work orders for a 5-year time period for the Unit 1 TBCCW system.
Effectiveness of Corrective Actions
The inspectors concluded the licensee was generally effective in developing corrective actions that were appropriately focused to correct the identified problem and to address the root and contributing causes for significant conditions adverse to quality to preclude repetition. The licensee completed these corrective actions in a timely manner and in accordance with procedural requirements commensurate with the safety significance of the issue. For NRC-identified issues, the inspectors determined the licensee assigned actions were effective and timely.
Assessment 71152B Operating Experience and Self-Assessments and Audits Observations
Based on the samples reviewed, the team determined that licensee performance in the use of operating experience, self-assessments, and audits adequately supported nuclear safety.
Use of Operating Experience
Overall, the inspectors concluded operating experience was adequately evaluated for applicability and appropriate actions were implemented in an effective and timely manner to address lessons learned as needed. Relevant industry operating experience was disseminated across the various departments and was used at the station for activities such as pre-job briefs and daily meetings. The inspectors also verified the use of operating experience in formal CAP products such as root cause evaluations and apparent cause evaluations was appropriate and adequately considered.
Self-Assessments and Audits
Based on the results of the inspection, the inspectors determined the licensee was effective at performing self-assessments and audits to identify issues and enhancement opportunities at an appropriate low level, properly evaluated those issues, and resolved them commensurate with their safety significance. The self-assessments and audits reviewed were accurate and thorough. The inspectors concluded these audits and self-assessments were completed by personnel knowledgeable in the subject area. Issues identified were entered into the CAP as required by procedures. The inspectors also determined that findings from the CAP self-assessment were generally consistent with the inspectors assessment.
Assessment 71152B Assessment of Safety Conscious Work Environment
The inspectors found no evidence of challenges to the licensees safety-conscious work environment. Licensee personnel appeared willing to raise nuclear safety concerns through at least one of several means available.
The inspectors held scheduled interviews with eight individuals from various departments and experience levels to assess their willingness to raise nuclear safety issues. Information obtained during the interviews indicated an environment was established where licensee personnel felt free to raise nuclear safety issues without fear of retaliation. Licensee personnel were aware of and generally familiar with the CAP and other processes, including the Employee Concern Program and the NRCs allegation process, through which concerns could be raised. In addition, a review of the types of issues in the Employee Concern Program indicated licensee staff were appropriately using the CAP to identify issues. The inspectors did not observe and were not provided any examples where there was retaliation for the raising of nuclear safety issues. Documents provided to the inspectors regarding surveys and monitoring of the safety culture and safety conscious work environment generally supported the conclusions from the interviews.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 23, 2020, the inspectors presented the biennial problem identification and resolution inspection results to Mr. K. Ohr, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ALARA Plans
QC-02-19-0807
TB BLDG Moisture Separator/Steam Reheater Activities
(Q2R25)
Corrective Action
Documents
IRSF BLDG has Leaking Water Shields
03/07/2011
AR 1312050-01
Reoccurring AT to Refill IRSF Water Shields
01/11/2012
NOS ID: Long Term Storage for Lead Blankets
04/15/2013
Clean Water Act 316(B) Final Rules Delayed to Nov. 4, 2013
06/27/2013
TBCCW HX Outlet Temperature Low on Rounds
10/29/2015
1B TBCCW Heat Exchanger North Cover Leak
04/28/2016
NRC ID'd: MO 2-2399-40 Overthrust Event Human
Performance
06/13/2016
TI 1-3840-3 On 912-1 is Reading 5 Degrees Higher Than
Local
07/23/2016
Document the Power Labs Failure Analysis Report of the
Failed Servo and Lockup Solenoid Valves
08/06/2019
Unit 1 RCIC Failed Surveillance
05/10/2017
1A EHC TBCCW TCV Slow to Respond
04/27/2017
Unit 1 HPCI did Not Trip during QCOS 2300-05
11/07/2017
SA: NRC RP Occupational ALARA Planning and Controls
01/26/2018
Self-Assessment: Operator Fundamentals
01/29/2018
Self-Assessment: Configuration Control Program
01/29/2018
Cover Missing from TI 1-3841-36H
01/18/2018
EO ID: Hydrolase or Block Floor Drain that is Causing
Contamination
03/13/2018
Improper Control of Safeguards Information
03/09/2018
2A RFP Vent Fan Discharge Damper Closed on Fan Start
04/06/2018
Assignment #87 Station OPEX Review of IRIS 467286 from
Monticello for Applicability
01/31/2020
Assignment #88 Station OPEX Review of IRIS 451474 from
Peach Bottom for Applicability
2/12/2020
Unit 1 MSV #1 did Not Initiate 10 Percent Close RPS Signal
06/09/2018
Air Leak on U1 TBCCW Expansion Tank LCV PRV
07/10/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
U2 EDG Elevated Temps During Monthly Load Test
07/16/2018
AR 4161195-99
Performance Analysis
2/20/2020
Need Update to PM WO SFP Level
08/24/2018
Rear Sight Aperture Missing
08/30/2018
PAF Enter 1 Turnstile Releases with no Badge Usage
09/07/2018
MO-1-1001-7C May Not Open During Mode 3 LOCA
09/11/2018
Performance of Contact Verifications on Output Breaker 7-8
with Output Breaker 6-7 Open Caused Unit SCRAM Due to
Turbine-Generator Load Reject
11/01/2018
Emergency Light Battery Pack Low Conductance
10/04/2018
CRD Exercises in Q1F66 Found New CRDM to be Repaired
10/04/2018
Assignment #13 Perform Level 3 OPEX Evaluation
01/31/2019
REC Assignment Not Created for Strength from SRPT
4099106-04
10/26/2018
Incorrect Assignment Types and Event Codes Used in DEF
ARS
10/26/2018
Tamper Seal Tape Missing on SBO DCS Applications Panel
10/29/2018
PORC Minutes Not Submitted Within 30 Days
11/14/2018
PORC Action Item Documentation of Approval Deficiency
11/14/2018
RRP Seal MGMT ER-AA-3006 Implementation Deficiencies
11/20/2018
Review of QDC FRV Lockups Trend
2/10/2018
EO ID: 3 DPM Leak on TBCCW to 1A IAC SOL. Bypass
Valve
2/12/2018
Expired Capacitors in Inventory
2/29/2018
EP - Siren Failures (QC08, QC18, QC26, QC31)
01/07/2019
AVB-4 Leaking Fluid
01/09/2019
AVB 4 Leaking Fluid - Vegetable Oil
01/09/2019
SA ID - Vendor Audit Records Missing from EDMS
01/10/2019
1A RHR Pump in IST Alert Range
01/23/2019
Active Vehicle Barrier #4 Leaking Fluid
2/04/2019
Unit 1 HPCI Failed to Roll During QCOS 2300-27 Due to
Blown Fuse
03/08/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EO ID: Standby 1A TBCCW Discharge PI Indicates High
2/22/2019
Humidity in the TSC is High
03/04/2019
Long Term Storage Area >90 Days for Temp Shielding
Equipment
03/06/2019
Long Term Storage Area >90 Days for Temp Shielding
Equipment
03/06/2019
IMD Requires New Test Equipment
03/12/2019
Assignment #15 Perform OPEX Review of NRC IN 2019-01
05/10/2019
Q1R25 - Higher than Expected Radiological Conditions
03/18/2019
Q1R25 IVVI CS Piping 3P4D Weld New Indication
03/24/2019
Long Term Storage Area for Lead Blankets
03/28/2019
04/19/2019
Error Found in Quarterly ODCM Permit for 3rd Qtr 2018
04/02/2019
Manual Action 50.59/Calculation Different from EC
04/23/2020
NOS ID: TSC HVAC Mod was Not Assessed by EP
04/18/2019
NOS ID - PA Speaker Testing Not Completed in 2018
04/18/2019
2-1301-20 HPCI CCST Suction Check Valve Leaks
By/Hangs Up
04/30/2019
Follow Up to IR 4235745
04/30/2019
EO ID: Leak on SS Mesh Hose to 1C RFP Outboard Seal
Cooling
05/07/2019
EDMS Record Turned Over with Incorrect Title
05/21/2019
EO ID'D 1A TBCCW Pump Disch PI is Vibrating Excessively
05/22/2019
1A TBCCW Oil Leak
05/22/2019
Unit 1 HPCI did Not Trip Locally During QCOS 2300-13
06/05/2019
NRC IN 2019-02: EDG Excitation System Diode Failures
06/12/2019
Diesel Fuel Self-Assessment Deficiency
06/25/2019
FAC OE - 2018 Indian Point HP FWH Leak (INPO ICES
- 444436)
06/27/2019
EP-Loss of Off-Site Communication
07/08/2019
HPCI Not Disabled for Fire Areas TB-III And TB-I
07/24/2019
PAF Enter 1 Turnstile will Not Release
08/06/2019
Pre-Access Facility Entry Turnstile Number 1 Failed Test
08/07/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PJR QC-01-19-0054DW Inboard MSIV Overhaul
09/24/2019
TRNG - Self-Assessment Gaps in NISP-TR-01 Form
Completion
09/30/2019
Emergency Lighting Needs Added to Aux Electric Room
10/07/2019
Unable to Perform PMT AO 0-4199-315, CR HVAC AFU Fire
10/11/2019
4.0 Critique U1 Downpower
10/21/2019
Water Found in Control Room HVAC Air Filtration Unit
10/27/2019
Results of 2019 Self-Assessment Check-In Critical CTRL
Docs
10/30/2019
Unable to Drain via 1-3999-240B
10/30/2019
Operation Training Issue Matrix Update
10/30/2019
Perform Update to ODCM at Next Major Revision
11/07/2019
Configuration Control Self-Assessment Deficiency
11/13/2019
SRPT Def - Issues with Actions Under IR 4168791
11/14/2019
SRPT Def: REC Not Created for Strength in SRPT
4197601-04
11/14/2019
SRPT Def: EFR Assignments Not Created under RCR
4177502-05
11/14/2019
SRPT Def: Issues with ECAP 4187243
11/14/2019
SRPT Def: Issues with ECAP 4217557-04
11/19/2019
ALARA FASA Deficiency #1 - Post Job Review Not
Completed
11/20/2019
ALARA FASA Deficiency #2 - WIP Admin Errors
11/20/2019
SPRT Def: Issues with CAPE 4248635-12
11/21/2019
1B TBCCW HX Requires Additional Maintenance
11/25/2019
Plant Emergency Siren Breaker Trip During Surv
11/29/2019
Cyber Security Lessons Learned - SFAQ 17-04
2/04/2019
Cyber - System Assessment Requires Revision
2/04/2019
Missing Signature on IT-AA-101-1502-F-01 for Log QDC-
001-19
2/04/2019
Missing Initial and Date on DTE Inventory PM Packages
2/04/2019
Missing Pages in EDMS Scans of Cyber Incident Forms
2/04/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Cyber - Required Recurring Task Periods Exceeded
2/04/2019
Incorrect Document Number in EDMS
2/04/2019
Cyber - SA 04204131 Deficiency 1
2/04/2019
Cyber - SA 04204131 Deficiency 2
2/04/2019
Cyber - SA 04204131 Deficiency 3
2/04/2019
Cyber - SA 04204131 Deficiency 4
2/04/2019
Cyber - SA 04204131 Deficiency 5
2/04/2019
Trigger IR - Chemistry 3 Month Decline
2/06/2019
SA ID: Objective Evidence Report Quality Deficiencies
2/17/2019
SA ID: Objective Evidence Reports Require Clarification
2/17/2019
1A TBCCW HX Requires Additional Maintenance
2/17/2019
EO-ID 1C RFP Outbd Seal Cooling Jacket Leak
01/08/2020
Preparation for NRC Problem Identification and Resolution
(PI&R) Inspection
Inadequate Progress in Resolving Site Obsolescence Issues
01/27/2020
19-003 SA Deficiency-FLS Peer Group
2/06/2020
EP-Siren Failure (QC26, QC40)
2/17/2020
Explosive Detector #2 Shows Detector Flow Warning
2/19/2020
HPCI ECAP 4217557 Corrective Action Implementation Error 02/26/2020
Assignment #3 Station OPEX Review of IRIS 469506 From
Cook for Applicability
04/24/2020
Assignment #26 Station OPEX Review of IRIS 474860 from
Columbia for Applicability
07/10/2020
Assignment #31 Station OPEX Review of IRIS 479210 from
Davis-Besse for Applicability
08/03/2020
Unit 0 250 Battery Charger Resistor Replacements
2/27/2020
03/05/2020
Viking Boxes 11 and 12 Failed Test
03/17/2020
NSMART Array Battery Failures
03/19/2020
FME 480V Breaker N015 Lockwasher Issue
03/27/2020
ERV 2-0203-3D Relief Valve did Not Actuate
03/30/2020
Elevated Dose Rates on Both U2 Core Spray Lines DW 640'
04/02/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Emergency Light Pack 76H Trickle Charger Light is Out
04/07/2020
Corrective Action
Documents
Unit 2 Refuel Bridge Main Hoist Load Cell Abnormal
Indication
04/08/2020
B Control Room HVAC RCU Feed Breaker Tripped
05/21/2020
QC-02-20-00906 Cavity Decon Post-Job Review
04/15/2020
Unable to Rack in 2A RHRSW Pump Breaker
05/22/2020
250V DC Essential Battery Undervoltage
05/26/2020
U1 DGCW Piping Inspection
05/27/2020
Facilities Maintenance Backlog of Security Work Requests
06/04/2020
U2 HPCI Check Valve Response During QCOS 2300-11
06/04/2020
U1 HPCI Service Water Strainer High D/P
06/08/2020
2D Corrosion on U2 250VDC Safety Batteries
06/11/2020
ECCS Keep Fill Check Valve Stuck Closed
06/11/2020
2B RBCCW Pump Shaft Seal Leaking Oil
06/13/2020
MO 1-3301-C Found with Extruding Gasket
06/17/2020
EMD Group 1 Fire Seal Discrepancies
06/18/2020
U2 TBCCW Temperature Irregularities
06/19/2020
Greater than 25 Percent of ILT 20-1 Candidates Screen as
At-Risk
06/19/2020
U1 1-5802 Oil Analysis Indicates out of Spec Oil Samples
06/23/2020
Unit 2 QCIS 1600-10-QAI Lessons Learned
06/23/2020
Hydrogen Leak Detected in 2252-7 Cabinet
06/25/2020
06/26/2020
Disch Press Gage Reading Higher than Suct Press
07/01/2020
PI&R CAP Invest Issues Identified During Self-Assessment
07/20/2020
Gap Under India 2 Gate does Not Meet Security
Requirements
07/21/2020
Security OPEX - Failure of OC Canister Seal
07/22/2020
DEP was Not Counted in the Month Completed
07/23/2020
DEP Opportunity Not Counted in the Month it was Performed
07/23/2020
Q1R26 - Torus Vapor Phase Recommended Coating Repairs 07/23/2020
ERO Participation Credit Given in Error
07/23/2020
EP Historical Demonstration Criteria Failure
08/04/2020
EP Containment Hydrogen from Simulator Not Accurate in
08/11/2020
NCV 20-002, CLSR PKG - Failed 3D ERV Event
08/31/2020
AR 44344520
NCV 20-001, CLSR PKG - CREVs AFU PMT Not Performed
Event
05/20/2020
CA 4187243-28
Implement Revision to QCOS 6500-09 and QCOS 6500-10
to Math TIC #3490, to Open the Knife Switches Prior to
Relays Testing
2/14/2019
CAPE 04117193
Improper Control of Safeguards Information
03/20/2018
CAPE 4330737-
ERV 2-0203-3D did Not Actuate
04/24/2020
CAPE 5328207
LPCI Swing Bus (MCC 28/29-5) did Not Transfer QCOS
6700-02
04/30/2020
ECAP 4163086-
U1 MSV 1 RPS Limit Switch did Not Initiate 10 Percent RPS
Close Signal
09/20/2018
ECAP 4187243-
Undervoltage Trip of Bus 13-1 During QCOS 6500-09
11/29/2018
ECAP 4254019-
Pump Failed to Start During QCOS 1000-04
06/03/2019
ECAPE 3990038
MSIVs 1-0203-1B, 1-0203-1D, 1-0203-2C and 1-0203-2D
Closure Times Exceeded the Maximum Technical
Specification Limit of 5 Seconds
04/11/2019
ECAPE 4116642
MSIVs 2-0203-1A and 2-0203-1C Closure Times Exceeded
the Maximum Technical Specification Limit of 5 Seconds
04/11/2019
ECAPE 4266776
HPCI Not Disabled for Fire Areas TB-III and TB-I
09/05/2019
EFR 14
Effectiveness Review for CR 4116642
05/21/2020
EFR 3291738-17
Effectiveness Review for Actions to Address the Failure to
05/21/2020
PIAP AP-2020-22
Issues Not Being Entered Into CAP
06/25/2020
RCR 4160631
Unit 1 Resin Intrusion Event
09/21/2018
RCR 4274286
Water Intrusion on the "A" Isolated Phase Bus Duct Near the
Unit Auxiliary Transformer Caused
10/04/2019
RCR 4335396
Quad Cities Unit 2 Trip Due to Cut Wire in Generator
Protection Circuit
05/29/2020
Corrective Action
Documents
Resulting from
Inspection
NRC PI&R ID'd: Action Created with the Wrong Reference
10/07/2020
NRC PI&R ID'd: MA-AA-716-026 Requirements Not
Followed
10/11/2020
NRC PI&R ID's WO Cancellation Notes Require More Detail
10/19/2020
NRC PI&R ID'd: TBCCW System Walkdown Results
10/19/2020
NRC PI&R ID'd: Typo Identified in Self-Assessment
4097431-04
10/21/2020
NRC PI&R ID'd: 1B TBCCW HX Inspection Frequency
Incorrect
10/21/2020
NRC PI&R ID'd: ELP 45F Labeling Enhancement
10/21/2020
NRC PI&R ID: CAP Not Used to Full Potential
10/21/2020
NRC PI&R ID: MREQ 4323765-02 Closure Issues
10/22/2020
IEMA ID: Trends on Remediation Well
10/23/2020
Miscellaneous
Heat Exchanger Inspection Report for 1A TBCCW
2/27/2016
Heat Exchanger Inspection Report for 1B TBCCW
11/22/2019
Heat Exchanger Inspection Report for 1A TBCCW
2/17/2019
CFAM Monthly Performance Summary - OR-PI
March 2019
CFAM Monthly Performance Summary - OR-PI
March 2020
CFAM Monthly Performance Summary - OR-PI
May 2020
CFAM Monthly Performance Summary - OR-PI
June 2019
CFAM Monthly Performance Summary - OR-PI
September
2019
CFAM Monthly Performance Summary - OR-PI
December
2018
NOSA-QDC-19-
Corrective Action Program Audit Report
NOSA-QDC-19-
Radiation Protection Audit Report
NOSA-QDC-20-
Chemistry Audit Report
Procedures
Station Housekeeping/Material Condition Program
15, 17, 18
Hot Spot Tracking
Self-Assessments AR 04096589
Pre-2018 NRC Emergency Preparedness Graded Exercise
Baseline Inspection
08/16/2018
Foreign Material Exclusion Self-Assessment
2/12/2019
IP 71130-04 Equipment Performance, Testing/Maintenance
and IP 71151 Performance Indicator
05/08/2020
Review of Power Reactor Target Sets
07/06/2020
Engineering Design Control Audit Report
07/24/2019
Engineering Programs Audit Report
06/24/2020
NOSA-QDC-18-
Security Programs Audit Report
01/30/2018
NOSA-QDC-18-
Emergency Preparedness Audit Report
04/25/2018
NOSA-QDC-19-
Security Programs Audit Report
2/06/2019
NOSA-QDC-19-
Emergency Preparedness Audit Report
04/24/2019
NOSA-QDC-20-
Maintenance Functional Area Audit Report
03/11/2020
NOSA-QDC-20-
Security Programs Audit Report
2/05/2020
NOSA-QDC-20-
Emergency Preparedness Audit Report
04/22/2020
4097382-04
Radwaste and Radioactive Material Handling, Storage, and
Transportation
10/05/2018
4097431-04
NRC RP Occupational ALARA Planning and Controls
4118048-04
Post-Accident Gaseous Effluent Monitoring (NUREG 0737)
2/18/2018
4197601-04
NRC RP Exposure Controls, Airborne Inspections
05/02/2019
4198147-13-03
Radiation Protection Dosimetry
01/03/2020
4198941-13-03
Radiation Protection Instrumentation
11/14/2019
4199090-13-03
2019 ALARA (Site Review)
11/20/2019
207564-04
NRC RP - Rad Monitoring Instrumentation Inspection
07/16/2019
207574-04
NRC RP - Solid Waste Processing, Handling, Storage, and
Transportation Inspection
10/22/2019
SRPT 4082073-
Condensate Chemistry
01/04/2019
SRPT 4096570-
Self-Assessment and Benchmark Compliance
SRPT 4098275-
Operator Fundamentals
10/31/2018
SRPT 4184143-
Diesel Fuel Oil
07/02/2019
SRPT 4184154-
Lab Safety - Hygiene
2/19/2019
SRPT 4205175-
Clearance and Tagging
2/27/2019
SRPT 4206027-
Radioactive Effluents Control Program/Radiological
Environmental Monitoring Program/Radiation Monitoring
(RECP/REMP)
06/04/2019
SRPT 4228697-
Off-Year NRC PI&R Assessment of the Corrective Action
Program
SRPT 4259948-
Project Legacy - CY Mid-Project Update
09/10/2019
SRPT 4337229-
Chemistry Supervisory Oversight
06/24/2020
Work Orders
Op Work Instructions to Stroke 0-4199-315, Fire WTR to
Charcoal Filts AO
(LR) TBCCW System Walkdown By System Engineer
11/16/2015
(LR) TBCCW System Walkdown By System Engineer
09/22/2016
(LR) U1 TBCCW System Walkdown
07/18/2017
HPCI CCCST Suction CK VLV Disassemble & Inspect
04/06/2020
(LR) U1 TBCCW System Walkdown
03/16/2018
T/S and Repair Trip of Bus 13-1
03/21/2019
(LR) TBCCW System Walkdown
11/01/2019
(LR) TBCCW System Walkdown
06/23/2020