IR 05000254/2024004
| ML25041A148 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  (DPR-029, DPR-030) |
| Issue date: | 02/10/2025 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| EPID I-2024-004-0065 IR 2024004 | |
| Download: ML25041A148 (1) | |
Text
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000254/2024004 AND 05000265/2024004
Dear David Rhoades:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Quad Cities Nuclear Power Station. On January 28, 2025, the NRC inspectors discussed the results of this inspection with Doug Hild, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety 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:
05000254/2024004 and 05000265/2024004
Enterprise Identifier:
I-2024-004-0065
Licensee:
Constellation Nuclear
Facility:
Quad Cities Nuclear Power Station
Location:
Cordova, IL
Inspection Dates:
October 01, 2024, to December 31, 2024
Inspectors:
J. Benjamin, Senior Resident Inspector
Z. Coffman, Resident Inspector
J. Corujo-Sandin, Senior Reactor Inspector
C. Hunt, Senior Resident Inspector
J. Kutlesa, Senior Emergency Preparedness Inspector
T. Okamoto, Resident Inspector
M. Siddiqui, Reactor Inspector
Approved By:
Robert Ruiz, Chief
Reactor Projects Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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
Type Issue Number Title Report Section Status LER 05000265,07200053/
2024-001-00 LER 2024-001-00 for Quad Cities Nuclear Power Station, Unit 2, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing 71153 Closed
PLANT STATUS
Unit 1 The unit began the inspection period at full-rated thermal power. On December 29, 2024, the unit began its end-of-cycle coastdown period in preparation for refueling outage Q1R28, and remained in that condition for the rest of the inspection period, with the exception of short-term power reductions for control rod sequence exchanges, testing, and as requested by the transmission system operator.
Unit 2 The unit began the inspection period at full-rated thermal power. On September 26, 2024, the unit experienced an unplanned reduction in power to approximately 40 percent due to a failure of the 2B adjustable speed drive. The unit returned to full-rated thermal power on September 28, 2024, where it remained at full-rated thermal power, with the exception of short-term power reductions for control rod sequence exchanges, travelling screen maintenance, testing, and as requested by the transmission system operator.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather with expected temperatures below freezing for multiple days on November 26, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1/2 emergency diesel generator (EDG) during Unit 1 EDG work window on October 7, 2024
- (2) Unit 2 residual heat removal (RHR) loop 2A during planned work window on RHR loop 2B on November 21, 2024
- (3) Safe shutdown makeup pump on November 22, 2024
- (4) Unit 1 station blackout (SBO) diesel generator during planned work on the Unit 2 SBO on November 13, 2024
- (5) Unit 2 batteries and battery charger on November 7, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 reactor core isolation cooling system on November 18, 2024.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (11 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Zone 8.2.6.E, Unit 2, elevation 595', reactor feed pump room on October 11, 2024
- (2) Fire Zone 11.1.4, Unit 2, elevation 544', high pressure coolant injection room on October 25, 2024
- (3) Fire Zone 7.1, 6.1.A/B, Unit 1, elevation 628'-6" and 615'-6", 250 V battery and charger rooms on October 31, 2024
- (4) Fire Zone 8.2.1.B, Unit 2, elevation 547', condensate pump room on November 7, 2024
- (5) Fire Zone 9.2, Unit 2 diesel generator room on November 8, 2024
- (6) Fire Zone 5.0, Unit 2, turbine building, elevation 595'-0", safe shutdown pump room on November 25, 2024
- (7) Fire Zone 8.2.7.A, Unit 1 turbine building, elevation 615'-6", hydrogen seal oil area and motor control centers on November 27, 2024
- (8) Fire Zone 8.2.1.A, Unit 1 turbine building, elevation 547', condensate pump room on November 27, 2024
- (9) Fire Zone 8.2.8.E, Unit 1 turbine building, elevation 639', main turbine floor (outside shield wall) on December 2, 2024
- (10) Fire Zone 1.1.1.4, Unit 1 reactor building, elevation 647'-6", third floor on December 26, 2024
- (11) Fire Zone 8.2.2.A, Unit 2 turbine building, elevation 572'-6", control rod drive pumps on December 27, 2024
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered from October 7, 2024, to November 15, 2024.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification training on October 22, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Process radiation monitoring system on November 4, 2024
- (2) Safe shutdown makeup pump system on November 21, 2024
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Work Orders (WOs) 5268197, 5268200, 5399937, and 5157234
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Work management risk for work week 10/07/2024, on October 7, 2024
- (2) Work management risk for work week 10/21/2024, on October 21, 2024
- (3) Work management risk for work week 11/04/2024, on November 4, 2024
- (4) Work management risk for work week 12/16/2024, on December 12, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (2) AR 4808624, WO 5413653, 1B RHRSW [residual heat removal service water] RM CLR HDR PIPING REPLCMNT (1-5745-B)
- (3) Review of EDG underfrequency time delay relays 0-6601-181X and 1-6601-181X following Part 21 notification (ML24128A237), pending relay replacements, completed the week ending November 9, 2024
- (4) AR 4800548, On the 2-2202-70A Panel, the PS2A ON Light Was Out, completed the week ending November 9, 2024
- (5) AR 4817851, Plant Public Address System Not Functional
- (6) AR 4820139, U2 HPCI [high pressure coolant injection] C/S for 2301-36 Operated Intermittently
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Update to local intense precipitation barriers associated with the station external flooding response on October 30, 2024
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (3 Samples)
- (1) Post-maintenance testing (PMT) associated with the Unit 1 emergency diesel generator following a planned work window on October 10, 2024
- (2) PMT associated with the Unit 1 250 Vdc battery cell 76 replacement work window on October 27, 2024
- (3) PMT associated with the Unit 1 emergency diesel generator following an Agastat time delay relay replacement on November 4, 2024
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
- EP-AA-1006, Constellation Radiological Emergency Plan Annex for Quad Cities Station, Revision 42
- EP-AA-1006, Addendum 1, Quad Cities Station On-Shift Staffing Technical Basis, Revision 3
- EP-AA-1006, Addendum 2, Quad Cities Evacuation Time Estimates, Revision 2
- EP-AA-120-1001, QDC Emergency Plan Revised for IPAWS Implementation, Evaluation No. 23-38 This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Simulator-based licensed operator requalification training on October 29,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS09: Residual Heat Removal Systems (IP Section 02.08)===
- (1) Unit 1 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
===71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (2 Partials)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
(Partial)
1. 10-minute mission time for the HPCI system
(2) (Partial)
operated valve factors 71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)===
- (1) The inspectors reviewed the licensees control room narrative logs to identify potential trends in log keeping practices that might be indicative of a more significant safety issue on November 13, 2024.
71153 - Follow-Up 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) 05000265/2024-001-00, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing (Agencywide Document Access and Management System [ADAMS] Accession No. ML24131A015.) The inspectors determined that the cause of the condition described in the LER did not result in an issue of concern as the reactor was in Mode 5 with all rods inserted at the time of the reactor protection system actuation; therefore, no rod movement occurred. No performance deficiency nor violation of NRC requirements was identified. This LER is closed.
INSPECTION RESULTS
Minor Violation 71152S Failure to Maintain Control Room Narrative Logs Minor Violation: Technical Specification Section 5.4.1.a, Procedures, requires, in part, that written procedures shall be established, implemented, and maintained, covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, dated February 1978. Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation), Appendix A, Section 1, addresses Administrative Procedures, and Section 1.h, addresses Log Entries, Record Retention, and Review Procedures.
The licensee established OP-AA-111-101, Operating Narrative Logs and Records, Revision 19, to address log entry requirements in the control room narrative log. Section 4.1, General Requirements for Operations Records, Step 4.1.1, states, MAINTAIN records at a level of detail that will allow reconstruction of shift activities by oncoming personnel that do not have the benefit of a face-to-face discussion of the shift Section 4.3, Narrative Logs, Step 4.3.2, contains examples of information to be recorded in operations logs as applicable. Step 4.3.2.17, Receipt of unexpected alarms, is an example of information to be recorded.
Contrary to the above, from January 1, 2024 through December 1, 2024, the licensee failed to implement OP-AA-111-101, Step 4.1.1, to maintain records at a level of detail that will allow reconstruction of shift activities by oncoming personnel that do not have the benefit of a face-to-face discussion of the shift. Specifically, the licensee failed to record the receipt of 15 unexpected alarms per OP-AA-111-101, Step 4.3.2.17, over the time period reviewed by the inspectors. The inspectors determined that although operators responded to the alarms as required, and documented the receipt of the alarms in the corrective action program, the failure to maintain the control room narrative logs in accordance with OP-AA-111-101 was a performance deficiency and a violation of licensee Technical Specification (TS) 5.4.1.
The licensee documented the inspectors observations in the corrective action program under AR 4822796, NRC ID: Logging of Unexpected Alarms.
Screening: The inspectors determined the performance deficiency was minor. Specifically, the failure to record the receipt of the individual unexpected alarms was not viewed as a precursor to a significant event, did not have the potential to lead to a more significant safety issue, and did not adversely affect a cornerstone objective.
Enforcement:
This failure to comply with TS 5.4.1 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Observation: Control Room Narrative Logs Observation 71152S The final NRC Safety Culture Policy Statement (SCPS) that was published on June 14, 2011, provides the NRCs expectation that individuals and organizations performing regulated activities establish and maintain a healthy safety culture that recognizes the safety and security significance of their activities and the nature and complexity of their organizations and functions. Because safety and security are the primary pillars of the NRCs regulatory mission, consideration of both safety and security issues, commensurate with their significance, is an underlying principle of the SCPS. NUREG-2165, Safety Culture Common Language, lists the traits, attributes, and examples of a healthy nuclear safety culture.
Following a minor violation for the failure to maintain the control room narrative logs documented in NRC Integrated Inspection Report 05000254/2024003; 05000265/2024003, the inspectors performed a semiannual trend analysis of the licensees control room narrative logs for the past four quarters against the requirements of OP-AA-111-101, Operating Narrative Logs and Records, Revision 19, to identify any potential trends that might indicate the existence of a more significant safety issue. Control room narrative logs are a quality record, the treatment of which is addressed in licensee topical report NO-AA-10, Quality Assurance Topical Report (QATR), Revision 98, Section 17, Quality Assurance Records.
In general, the site has requirements for the generation, collection, and maintenance of records necessary to provide evidence of quality in operations, such as the control room narrative log, and those records are to be legible, accurate, and complete.
The licensee established OP-AA-111-101, Operating Narrative Logs and Records, Revision 19, to address log entry requirements in the control room narrative log. In addition to a general requirement for records to be written at a level of detail which allows the reconstruction of shift activities by oncoming personnel without the benefit of a face-to-face turnover, OP-AA-111-101 also provides specific examples of items to be recorded, such as unexpected alarms and status changes of safety-related and other major plant equipment.
During their review, the inspectors identified 15 additional examples of unexpected alarms associated with safety-related or safety significant systems that were not recorded as required per OP-AA-111-101. The alarms were documented in the licensee corrective action program.
The inspectors also noted that the licensee identified two instances where the failure to maintain the control room narrative log in accordance with OP-AA-111-101 was a contributing cause in issues of concern, summarized below:
1. Following an issue documented in AR 4777894, Unable to Locate QCOS 6900-02
Surveillance, dated May 31, 2024, the licensee identified the failure to maintain control room narrative logs as a contributing factor to missing a TS surveillance requirement associated with the Unit 1 250 Vdc safety-related battery following the replacement of battery cells 41-80. Specifically, status changes to safety-related equipment were not documented for the cell replacement. Additionally, log entries were not maintained at a level of detail that would allow reconstruction of shift activities by oncoming personnel that did not have the benefit of a face-to-face discussion of the shift. Consequently, QCOS 6900-02, Station Safety Related Battery Quarterly Surveillance, Revision 46, was not performed in the required 7-day period following the recharge of the replacement battery cells per Technical Specification Surveillance Requirement 3.8.6.2. Upon discovery, the licensee entered Technical Specification Surveillance Requirement 3.0.3 which required the surveillance to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The licensee subsequently successfully completed QCOS 6900-02 within the allowed 24-hour time frame.
2. Following an issue documented in AR 4808751, Unit 2 SJAE Lineup Following
Summer Configuration, dated October 11, 2024, the licensee identified that the failure to log the status of major plant equipment was a contributing factor concerning the Unit 2 steam jet air ejector system being found in an unexpected lineup following summer operation.
Actions taken by the licensee to address these gaps in log keeping behaviors include additional training for licensed operators on log keeping requirements, the addition of two operations standing orders related to the tracking of TS equipment during maintenance and requiring a senior reactor operator peer check on the control room narrative log, and benchmarking log keeping practices at other sites in the fleet. Additionally, the site performed a performance analysis under AR 4777894 which determined that a lapse in operations standards exhibited by licensed operators was the driving factor for why existing procedural guidance for log keeping was not being followed.
Based on the examples reviewed, and a review of the safety culture traits described in NUREG-2165, the inspectors determined that the site exhibited negative performance in the area of PA.2, Job Ownership, where individuals understand and demonstrate personal responsibility for the behaviors and work practices that support nuclear safety. To date, actions taken by the site have not been successful in addressing this adverse trend in safety culture behavior. Regarding the alarms not documented in the control room log identified by the inspectors, the inspectors determined that although operators responded to the alarms as required, and documented the receipt of the alarms in the corrective action program, the failure to maintain the control room narrative logs in accordance with OP-AA-111-101 was a performance deficiency and a minor violation of licensee Technical Specification (TS) 5.4.1 which is documented in the Inspection Results section of this inspection report.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 28, 2025, the inspectors presented the integrated inspection results to Doug Hild, Site Vice President, and other members of the licensee staff.
- On December 16, 2024, the inspectors presented the emergency action level and emergency plan changes inspection results to Fred Muhly, Emergency Preparedness Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Severe Weather Preparation and Response
20-1
SBO Electrical Distribution
M-81, Sheet 1
Diagram of Residual Heat Removal Piping
01/16/1998
M-81, Sheet 2
Diagram of Residual Heat Removal RHR Piping
07/27/1999
M-81, Sheet 3
Diagram of Residual Heat Removal RHR Piping
01/10/2013
Drawings
M-89
Diagram of Reactor Core Isolation Cooling RCIC Piping
08/15/2003
Inservice Testing
QCOP 1000-50
Unit 2 RHR System Preparation for Standby Operation
QCOP 1300-01
RCIC System Preparation for Standby Operation
QCOP 2900-01
Safe Shutdown Makeup Pump System Preparation for
Standby Operation
QCOP 6600-04
Diesel Generator 1/2 Preparation for Standby Operation
QCOP 6600-12
Diesel Generator Air Start System Pressure Verification
QCOP 6620-07
SBO DG Preparation for Normal Start
QCOS 1300-05
RCIC Pump Operability Test
QCOS 2900-01
Safe Shutdown Makeup Pump Flow Rate Test
QCOS 2900-03
Safe Shutdown Makeup System Power Operated Valve Test
QCOS 2900-05
SSMP Local Breaker Control Test
QCOS 2900-09
Cycling of Fire Water Valves to Safe Shutdown Makeup
Pump
QCOS 6620-01
QOM 2-1000-04
Unit 2 RHR Valve Checklist (South RHR Room)
QOM 2-1300-02
UNIT 2 RCIC VALVE CHECKLIST
Procedures
QOM 2-1300-04
Unit 2 RCIC Fuse Checklist
Program Diagnostic Test MOV RCIC PMP Downstream
Torus Suction Valve
05/23/2013
Program Diagnostic Test MOV RCIC System Upstream
Discharge Valve
11/27/2013
MM Program Grease Inspection and Stem Lube
MOV 2-1301-48
03/09/2022
Work Orders
MM Lube MO 2-1361-62 Valve Stem
2/08/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Install Quick Stem Sensor (QSS) on MOV 2-1301-22 RCIC
PMP CCST Suction Valve
04/19/2006
Calculations
FL-15045
Calculation On CARDOX Room Fill
10/02/1968
Detection and Suppression Turbine Building Main Floor
05/02/2003
M-27, Sheet 2
Diagram of Fire Protection Piping
09/10/1999
M-27, Sheet 2
Diagram of Fire Protection Piping, Unit 1
09/10/1999
Drawings
M-27, Sheet 4
Diagram of Fire Protection Piping
04/18/1998
Engineering
Changes
Implement Fire Hose Removal Strategy
FZ 1.1.1.4
Unit 1 RB 647'-6" Elev. Third Floor
08/2022
FZ 11.1.4
UNIT 2 RB 544'-0" ELEV. HPCI Pump Room
08/2022
FZ 6.1.A
UNIT 1 TB 615'-6" ELEV. A BATTERY CHARGER ROOM
U-1
08/2022
FZ 6.1.B
UNIT 1 TB 615'-6" ELEV. B BATTERY CHARGER ROOM
U-1
08/2022
FZ 7.1
UNIT 1 TB 628'-6" ELEV. 250V BATTERY ROOM
08/2022
FZ 8.2.1.A
Unit 1 TB 547' Elev Condensate Pump Room
08/2022
FZ 8.2.1.B
UNIT 2 TB 547'-0" ELEV. CONDENSATE PUMP ROOM
08/2022
FZ 8.2.2.A
Unit 2 TB 572'-6" Elev. CRD Pumps
08/2022
FZ 8.2.6.E
UNIT 2 TB 595-0 ELEV. REACTOR FEED PUMPS
08/2022
FZ 8.2.7.A
Unit 1 TB 615'-6" Elev Hydrogen Seal Oil area and MCCs
09/2022
FZ 8.2.8.E
Unit 1 TB 639'-0" Elev. Main Turbine Floor (Outside Shield
Wall)
08/2022
Fire Plans
FZ 9.2
Unit 2 Diesel Generator Room
Miscellaneous
FSI-6503
Fire System Impairment Permit for Alarm in U1 H2 Seal Oil
11/26/2024
Fire Damper Visual Inspection
08/20/2021
Standby Diesel Generator Cardox Fire Protection
Functional Test
2/14/2022
Fire Damper Visual Inspection
11/03/2023
Inspect Cardox System
03/11/2024
Standby Diesel Generator Cardox Fire Protection Functional
Test
04/29/2024
Work Orders
Replace Group B Fire Hoses
05/30/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Exam Security Clock Reset
10/22/2024
Breaker for SSMP Room Cooler Found Tripped
2/03/2012
2016 MRule Program and Expert Panel Items
03/04/2016
Superheat Data Collection Identified Circuit #1 as UNSAT
08/31/2016
Ckt 1 of SSMP Room Cooler Has No Refrigerant
05/19/2023
RIS 1-1705-16A Erratic Causing RB Vent Trip and SBGT
Start
06/29/2023
1-1705-16B FP Rad Monitor Spiked High
2/26/2024
OSP APS As-Found - ECCS Thin Wall 2-1/2" Pipe
03/21/2024
Corrective Action
Documents
Received 901-3 G16 Fuel Pool Channel A Hi Radiation
07/21/2024
Engineering
Evaluations
50.59 Screen QC-
S-2021-0001
U1 and U2 Install 10 second Time Delay Relay to Reactor
Building Ventilation and Fuel Pool Radiation Monitoring
Circuit
Miscellaneous
Health Group
Issues/Action
Plan
RIS 1-1705-16A Erratic Causing RB Vent Trip and SBGT
Start Maintenance Rule a(1) Plan
06/26/2024
Maintenance Rule 18-10 Scoping
Procedures
Nuclear Oversight Independent Inspection Plant
SSMP Thermal Expansion Valves Replacement/Superheat
Data Collection
2/29/2016
Work Orders
MM EWP SSMP TXVs Superheat Data Collection
05/28/2020
Unit 1 125 VDC Battery Cell 53 Low Specific Gravity
10/21/2024
RV 1-1299-80 Lifted and Leaking While Restoring U1
10/22/2024
PCV 1-8799-20 Unable to Maintain DW Pressure
10/23/2024
Leak in U2 Battery Room Ceiling
11/04/2024
U2 Condenser Pit Low Level Alarm
11/06/2024
Unexpected C-15 Alarm on 902-7 for Traveling Screen D/P
2/14/2024
Corrective Action
Documents
Operations 4.0 Critique for Fish Intrusion Event
2/14/2024
Unit 1 EDG 1-6601-40C Relay Connections Hot
2/18/2023
Corrective Action
Documents
Quad Cities Received Letter from TE Connectivity Outlining
Issues with E7000 Series Relays
05/07/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
On the 2-2202-70A Panel, the PS2A ON Light Was Out
09/10/2024
U1 EDG 1-6601-40C Relay Connection Still Hot
10/14/2024
Plant Public Address System Not Functional
11/15/2024
U2 HPCI C/S for 2301-36 Operates Intermittently
11/27/2024
Wiring Diagram Standby Diesel Generator 1 Excitation
Cabinet 2251-12
10/31/1994
ATWS Recirc Pump Trip System ECCS Init FW, RCIC,
HPCI, and Turbine Trips
P
Drawings
ATWS Recirc Pump Trip System
F
Evaluate Elevated Temperature on Right Connection of Unit
EDG Field Overcurrent Relay
ASME Code Reconciliation for Use of Higher Allowable
Stresses
2/11/2019
Engineering
Changes
ECR 406537
RHRSW Cubicle Cooler Min Wall Information Applicability of
10/03/2024
ASME B31.1
Power Piping
2004
Constellation
Power Labs Test
Project QDC-
46437
Relay Stock Code 0001453626 Test Results
05/09/2023
Miscellaneous
TE Connectivity
Part 21
TE Connectivity-Part 21 Transfer of Information
04/23/2024
ER-AA-5400-
1001
Raw Water Piping Integrity Management Guide
Procedures
QCAN 902-5 H-2
ATWS Channel A/B Trouble
Work Orders
1B RHRSW PMP AREA CLR CLN/INSP
10/19/2023
Corrective Action
Documents
APS LIP Barrier MOD As-Found Documentation
10/11/2024
Update to LIP Barriers to Assist the Station External
Flooding Response
Engineering
Changes
Update to LIP Barriers to Assist the Station External
Flooding Response
Corrective Action
Follow-Up to IR 4800106 U2 250VDC Battery Issues
09/17/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
U1 250V Battery Pilot Cell Voltage
09/18/2024
Additional Troubleshooting Need for U1 EDG FOTP
(1-5203)
10/07/2024
Documents
Expansion Tank Sight Glass Leak
10/10/2024
Miscellaneous
TE Connectivity - Part 21 Transfer of Information
04/23/2024
Operability
Evaluations
Evaluate Impact of Agastat E7000 TDR Part 21 Installed in
U0 EDG 0-6601-181X and U1 EDG 1-6601-181X
Applications
Procedures
TIC 3851
De-Energizing 250 Vdc Turbine Building MCC 1 for
Replacement of Unit 1 250 Vdc Battery
0a
MM U-1 EDG 18 YEAR INSPECTION 1-6601
10/11/2024
OP DIESEL GENERATOR TIMED START
10/11/2024
REPLACE U1 EDG UNDER FREQUENCY TDR 1-6601-
181X
11/04/2024
OP U1 DG MONTHLY LOAD TEST (IST) - QCOS 6600-41
10/11/2024
QCOS 6900-02, U1 250 VDC BATTERY QUARTERLY
(PERFORM WITHIN 7D)
10/27/2024
Work Orders
(LR) DIESEL GENERATOR LOAD TEST (IST)
11/04/2024
Addendum 1
Quad Cities Station On-Shift Staffing Technical Basis
Addendum 2
Quad Cities Evacuation Time Estimates
Calculations
QDC Emergency Plan Revised for IPAWS Implementation
23-38
Procedures
Constellation Radiological Emergency Plan Annex for Quad
Cities Station
QCA 101
Procedures
QGA 200
PRIMARY CONTAINMENT CONTROL
Corrective Action
Documents
Leak Noted on 1C RHRSW HP Pump Seal
08/20/2024
71151
Corrective Action
Documents
Resulting from
Inspection
NRC ID: Identification of MSPI Discrepancy for U2 RHRSW
11/21/2024
Corrective Action
Unable to Locate QCOS 6900-02 Surveillance
05/31/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Unit 2 SJAE Lineup Following Summer Configuration
10/11/2024
Documents
Potential Trend on Log Keeping in Operations
10/15/2024
Corrective Action
Documents
Resulting from
Inspection
NRC ID: Logging of Unexpected Alarms
2/10/2024
Corrective Action
Documents
SCRAM Signal Received During QCOS 0300-30
03/28/2024
Procedures
QCOS 0300-30
Scram Discharge Volume Vent and Drain Valve Seat
Leakage Test AO 1(2)-0302-21A/B/C/D and AO 1(2)-0302-
2A/B/C/D
3