IR 05000254/2019002
| ML19214A115 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/31/2019 |
| From: | Kenneth Riemer NRC/RGN-III/DRP/B1 |
| To: | Bryan Hanson Exelon Generation Co |
| References | |
| IR 2019002 | |
| Download: ML19214A115 (22) | |
Text
July 31, 2019
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2INTEGRATED INSPECTION REPORT 05000254/2019002 AND 05000265/2019002
Dear Mr. Hanson:
On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Quad Cities Nuclear Power Station, Units 1 and 2. On July 11, 2019, the NRC inspectors discussed the results of this inspection with Mr. Ken Ohr and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
The inspectors documented a licensee-identified violation which was determined to be of very low safety significance in this report. The NRC is treating this violation as non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
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 10 CFR 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:
05000254/2019002 and 05000265/2019002
Enterprise Identifier: I-2019-002-0063
Licensee:
Exelon Generation Company, LLC
Facility:
Quad Cities Nuclear Power Station, Units 1 and 2
Location:
Cordova, IL
Inspection Dates:
April 01, 2019 to June 30, 2019
Inspectors:
J. Cassidy, Senior Health Physicist
G. Edwards, Health Physicist
R. Murray, Senior Resident Inspector
J. Park, Reactor Inspector
C. Phillips, Project Engineer
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 an integrated inspection at Quad Cities Nuclear Power Station,
Units 1 and 2 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.
Licensee-identified non-cited violations are documented in report sections: 71111.05Q.
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 05000254,05000265/
2017-002-01 LER 2017-002-01 for Quad Cities Nuclear Power Station,
Unit 1, Four Main Steam Isolation Valves (MSIVs)
Closure Times Exceeded 71153 Closed LER 05000254,05000265/
2018-001-01 LER 2018-001-01 for Quad Cities Nuclear Power Station,
Unit 2, Two Main Steam Isolation Valves (MSIVs)
Closure Times Exceeded 71153 Closed LER 05000254,05000265/
2019-001-00 LER 2019-001-00 for Quad Cities, Unit 1, HPCI System Inoperable Due to Blown Fuse in the Motor Speed Changer Circuit 71153 Closed
PLANT STATUS
Unit 1
The unit began the inspection period shut down for refueling outage Q1R25. Startup on Unit 1 was commenced on April 6, 2019, and the unit was synchronized to the grid on April 7, 2019.
The unit reached full rated thermal power on April 9, 2019, where it remained for the entire inspection period with the exception of planned power reductions for turbine testing, control rod pattern adjustments, and other short-term power reductions as requested by the transmission system operator.
Unit 2
The unit began the inspection period at full rated thermal power, where it remained for the entire inspection period, with the exception of short-term power reductions 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 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 plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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
External Flooding Sample (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated readiness to cope with external flooding for the following areas:
- Units 1 and 2 turbine building during rising Mississippi River levels on April 1, 2019
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather (summer/ hot weather) conditions prior to the onset of extreme temperatures for the following systems:
- transformer cooling, adjustable speed drive cooling, offsite power systems
Summer Readiness Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems on May 10, 2019
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1B core spray during refueling outage Q1R25 on April 1, 2019
- (2) Units 2A and 2B core spray during Unit 2 high pressure coolant injection system maintenance on April 30, 2019
- (3) Unit 1/2 emergency diesel generator during unavailable Unit 1 emergency diesel generator on May 9, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (3 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Fire zone 1.2.1; Unit 1 reactor building, elevation 544-0/666-6, drywell and drywell expansion gap on April 3, 2019
- (2) Fire zone 11.1.1 A, B, C; Unit 1 turbine building, elevation 547-0, residual heat removal service water pumps on May 27, 2019
- (3) Fire zone 8.2.8.E; Units 1 and 2 turbine building, elevation 639-0, main turbine floor (outside shield wall) on June 25, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the following areas:
- (1) Units 1 and 2 residual heat removal service water vaults on April 29, 2019
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated the Unit 1 start-up from refueling outage Q1R25 on April 6, 2019
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated training scenarios in the simulator on June 24, 2019
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
(1)345 kV system (2)4kV switchgear
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Q1R25 outage shutdown safety and Unit 2 online risk the week of April 1, 2019 (2)repair instrument air leak on containment vent valve on April 16, 2019
- (3) Unit 1B adjustable speed drive (ASD) speed hold and severe weather during week of April 23, 2019
- (4) Work week risk for weeks of May 27 and June 3, 2019
- (5) Emergent work and operational risk activity for repairs on the Unit 1B ASD cooling water leak the week of June 24, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (4 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Issue Report 4238910, RV 1-1402-28A Set-Point Test Exceeded 10-Year Test Frequency, on April 15, 2019
- (2) Issue Report 4242536, Unexpected Speed Hold on [1] B ASD, on April 23, 2019
- (3) Issue Report 4236078, EDG [emergency diesel generator] to ESS [essential service system] BUS Ducts in EQ [environmental qualification] Harsh Zones, on May 8, 2019
- (4) Issue Report 4258635, B CREVS [control room emergency ventilation system]
Rough Pre-Filters Installed Backwards, on June 20, 2019
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering Change 402298, U1 Core Spray Pipe Repairs In-Vessel, which performs structural replacement of the P4D weld at the core spray piping downcomer-to-shroud elbow on April 1, 2019
- (2) QOA 4700-06, Loss of Instrument Air, procedure number 28 on June 16, 2019
71111.19 - Post-Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance tests:
- (1) Residual heat removal pump/loop operability test following outage on April 1, 2019
- (2) QCOS 0201-08, Reactor Vessel Class 1 and Associated Class 2 System Leak Test, following refueling outage Q1R25 on April 3, 2019
- (3) QCOS 0250-12, MSIV (main steam isolation valve) Stroke Test, and QCOS 0250-04, MSIV Closure Timing Following Q1R25 Maintenance, on April 5, 2019
- (4) Scram Time Testing of Control Rods Following Outage work on April 5, 2019
- (5) Work Order 4877341 (QCOS 5750-04), Quarterly Testing of Control Room HVAC (heating, ventilation, and air conditioning) System Valves and Dampers, following B Train Control Room Emergency Ventilation Maintenance on April 12, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The Inspectors Evaluated Unit 1 Refueling Outage Q1R25 Activities that Continued into the Second Quarter (began on March 18, 2019) and Completed on April 6, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) QCOS 1200-01, RWCU (reactor water cleanup) Power Operated Valve Testing, on April 1, 2019
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Core Flow Calibration on April 9, 2019
Surveillance Tests (other) (IP Section 03.01) (2 Samples)
- (1) Division II Emergency Core Cooling System Simulated Auto Initiation With Diesel Auto Start and load on April 3, 2019
- (2) Surveillance Test Interval Change Request QC-18-008: Revised TS [Technical Specification] SR (Surveillance Requirement) for the HPCI (high pressure coolant injection]/RCIC (Reactor Core Isolation Cooling] Low Pressure Flow Rate and RCIC Automatic Initiation Testing from 24-Months to 48-Months, on May 29, 2019
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) Emergency preparedness drill on May 21,
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Calibration and Testing Program (Process & Effluent Monitors) (IP Section 02.02) (1 Sample)
The inspectors reviewed the following gaseous and liquid effluent monitor instrument calibrations and tests:
(1)
- Unit 1 Reactor Building Vent Monitor
- Main Chimney Special Particulate Iodine Noble Gas Monitor
- Unit 1 Service Water Radiation Monitor
- Radioactive Waste Liquid Effluent Monitor
Dose Calculations (IP Section 02.05) (1 Sample)
The inspectors reviewed the following to assess public dose:
- (1) The inspectors reviewed the following liquid and gaseous discharge permits to evaluate public dose calculations:
- Liquid Discharge, Permit Number 2018004
- Liquid Discharge, Permit Number 2018005
- Gaseous Discharge, Permit Number 2019199
- Gaseous Discharge, Permit Number 2019201
- Gaseous Discharge, Permit Number 2019203
The inspectors reviewed the following annual radiological effluent release reports:
- 2017 Radioactive Effluent Release Report
- 2018 Radioactive Effluent Release Report
The inspectors also reviewed the following abnormal gaseous or liquid tank discharges:
- none were available for review during this inspection
Instrumentation and Equipment (IP Section 02.04) (1 Sample)
The inspectors reviewed the following radioactive effluent discharge system surveillance test results:
(1)
- Stand-By Gas Treatment System
- Control Room Ventilation System
- Technical Support Center Ventilation System
Sampling and Analysis (IP Section 02.03) (1 Sample)
The inspectors reviewed the following:
(1)
- Main Chimney
- Unit 1 Reactor Building Vent
- Unit 2 Reactor Building Vent
Effluent discharges with inoperable monitors
- none were available for review during this inspection
Walk Downs and Observations (IP Section 02.01) (1 Sample)
The inspectors walked down the following gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design:
(1)
- Main Chimney Monitoring System
- Unit 1 Reactor Building Vent Monitoring System
- Unit 2 Reactor Building Vent Monitoring System
71124.07 - Radiological Environmental Monitoring Program
Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02) (1 Sample)
- (1) The inspectors examined the remediation efforts associated with the 2018 Radwaste Piping Vault Leak and other historical leaks at the facility.
Site Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the radiological environmental monitoring program implementation.
- (1) Walkdowns, Calibrations, and Maintenance Record Review
- Air Sampling Station Q-01
- Air Sampling Station Q-02
- Air Sampling Station Q-04
- Optically Stimulated Luminescent Dosimeter (OSLD) Monitoring Station Q-01
- OSLD Monitoring Station Q-02
- OSLD Monitoring Station Q-04
Environmental Sample Collections and Preparation Observation
- Water Sample Q-33
- Water Sample Q-34
Licensee Actions in Response to Missed Sample, Inoperable Sampler, Lost TLD or Anomalous Measurement
- Q-01 (AI) (Air Sample); 01/04/2019; No Sample, Power Outage
- Q-36 (WW) (Well Water); 01/10/2019; Sample leaked during transportation.
New Sample Completed 01/14/2019.
- Q-33 (SW) (Surface Water); 01/05/2019; No Sample, Water Frozen
Sampling Program for the Potential of Licensed Material Entering Groundwater
- Monitoring Well QC-GP-18
- Remediation Well RW-1
- Radwaste Piping Vault
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI02: RCS Leak Rate Sample (IP Section 02.11)===
- (1) Unit 1 (04/01/2018-03/31/2019)
- (2) Unit 2 (04/01/2018-03/31/2019)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
(1)10/01/2018 - 03/31/2019
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in drywell radiation monitor failures that might be indicative of a more significant safety issue on June 21, 2019.
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) LER 265/2018-001-01 Two Main Steam Isolation Valves (MSIVs) Closure Times Exceeded (ADAMS Accession: ML19115A142). The inspectors reviewed the updated LER submittal. The previous LER submittal was reviewed in Inspection Report 05000254/ 2018002; 05000265/ 2018002.
- (2) LER 254/2017-002-01, Four Main Steam Isolation Valves (MSIVs) Closure Times Exceeded (ADAMS Accession: ML19115A136). The inspectors reviewed the updated LER submittal. The previous LER submittal was reviewed in Inspection Report 05000254/2017002; 05000265/2017002.
- (3) LER 254/2019-001-00, HPCI System Inoperable Due to Blown Fuse in the Motor Speed Changer Circuit (ADAMS Accession: ML19095A380). 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 also concluded that no violation of NRC requirements occurred.
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.05Q This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Quad Cities Units 1 and 2 license condition 3.F requires the licensee to implement and maintain, in effect, all provisions of the approved fire protection program as described in the Final Safety Analysis Report and as approved through Safety Evaluation Reports dated July 27, 1979, with supplements dated November 5, 1980, and February 12, 1981; December 30, 1982; December 1, 1987 with supplement dated April 20, 1988; December 11, 1987 with supplement dated July 21, 1988; and February 25, 1991.
The Updated Final Safety Analysis Report Section 9.5.1, Fire Protection System, states Quad Cities Administrative Procedures (QCAP) define the fire protection program by assigning responsibilities, defining the organization, and providing information and procedures pertinent to fire protection. These procedures provide the Administrative Technical Requirements for fire protection and safe shutdown equipment and specify surveillance requirements for the applicable systems and equipment.
QCAP 1500-01, Administrative Requirements for Fire Protection, 39, outlines the administrative requirements for the fire protection system.
QCAP 1500-01, Procedure - Fire Detection System, section D.1.a.(d), states in part:
IF supervisory device listed in Attachment A is inoperable, THEN perform one of the following:
-Test detection system at a frequency of once per month OR
-declare system inoperable
Contrary to the above, from March 23, 2019 to May 16, 2019, the licensee failed to maintain in effect all provisions of the approved fire protection program. Specifically, on March 23, 2019, the licensee documented in Issue Report 4232291 that fire alarm system (FAS) device 32-24 was in alarm and initiated an impairment for the device. Fire alarm system device 32-24 was a supervisory device for the Unit 1 residual heat removal service water vaults and was an emergency fire protection system listed in Attachment A of QCAP 1500-01. From March 23, 2019, to May 16, 2019, the licensee failed to either declare supervisory device 32-24 inoperable or test the detection system at a frequency of once per month.
Significance: Green. The inspectors determined the issue was more than minor because the performance deficiency was associated with the Mitigating Systems cornerstone attribute of Protection Against External Factors (fire) and it adversely affect the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage).
The inspectors determined the significance of the finding could be determined using Inspection Manual Chapter (IMC) 0609, Appendix F, Fire Protection Significance Determination Process, dated May 2, 2018. The inspectors used IMC 0609, Appendix F, 1, Fire Protection Significance Determination Process Worksheet, and determined the finding needed to be assigned a fire degradation rating using IMC 0609, Appendix F, Attachment 2, Degradation Rating Guidance. The inspectors concluded the finding represented a high fire degradation rating because the finding was related to fire detection and annunciators were disabled, inaudible, or nonfunctional. Specifically, FAS device 32-24 was non-functional, and control room annunciators would not have alerted operators of a fire in the Unit 1 residual heat removal service water vaults (local alarm panel annunciation was available).
In IMC 0609, Appendix F, Attachment 1, Step 1.4.2: Fixed Fire Protection Systems, the inspectors determined that the non-functional detection system did not adversely affect the ability of the system to protect any equipment important to safe shutdown. The affected residual heat removal service water rooms were supplied with a fixed fire suppression system that were always functional. Therefore, the inspectors determined the finding was of very low safety significance (Green).
Corrective Action References: The licensee identified this issue in condition report Issue Report 4251296. The licensee corrected this concern on May 16, 2019, when FAS device 32-24 was repaired and tested.
Observation: Drywell Radiation Monitor Failures 71152 The inspectors reviewed recent failures of the 2A drywell radiation monitors as documented in IRs 4251706 and 4258115, written on May 24 and June 19, 2019, respectively. Both failures were attributed to dirty contacts in the radiation monitor chassis. After the first failure, documented under IR 4251706, the licensee was able to clean the contacts in the detector chassis and retested it satisfactorily. In the most recent failure documented in IR 4258115, the licensee documented that they had replaced the detector chassis and attributed the failure of the chassis to dirty contacts in the detector selector switch. The licensee decided to replace the entire chassis because this was the second failure of the detector within the previous month. The failed chassis was sent to Power Labs for a failure analysis under assignment number 05 (IR 4258115-05). The inspectors recommend the biennial problem identification and resolution (PI&R) team review the results of the failure analysis and any licensee generated corrective actions. In addition, the licensee discussed that all four drywell radiation monitor chassis (2 per unit) sit in the same environment; they are close to the floor in the control room and susceptible to dust intrusion. The licensee also documented in IR 4251706 that IR 4252208 assignment number 04 was created to evaluate if a preventative maintenance change frequency was warranted for the drywell radiation monitors. The inspectors recommend the biennial PI&R team review both the licensee's evaluation of IR 4252208 assignment number 04 and the performance of all of the drywell radiation monitors because they are in a similar environment. The licensee's corrective actions should address the extent of cause and condition.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On June 6, 2019, the inspectors presented the radiation protection inspection results to Mr. K. Ohr, Site Vice President, and other members of the licensee staff.
- On July 11, 2019, the inspectors presented the integrated 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
or Date
Corrective Action
Documents
U1 Main Transformer Leaking Oil
04/11/2019
1A ASD Temporary Cooling Needed for Summer Readiness
04/30/2019
1B ASD Temporary Cooling Needed for Summer Readiness
04/30/2019
2A ASD Temporary Cooling Needed for Summer Readiness
04/30/2019
2B ASD Temporary Cooling Needed for Summer Readiness
04/30/2019
Miscellaneous
Advanced Nuclear Dispatch, Number: 229
2/26/2016
Nuclear Load Following Congestion Relief Program;
Number: 219
11/18/2014
Risk Issue
Number: QDC-2-
2019-0124
ODM: U2 Main
SPOG: 1-3-C
Station 4 Quad Cities Units 1 and 2 Special Protection
System
Procedures
General Area Checks and Operator Field Rounds
Switchyard Control
OP-AA-108-107-
1001
Station Response to Grid Capacity Conditions
OP-AA-108-107-
1002
Interface Procedure Between BGE/ComEd/PECO and
Exelon Generation (Nuclear/Power) for Transmission
Operations
QCOA 0010-16
Flood Emergency Procedure
QCOA 6100-03
Seasonal Readiness
WC-QC-8003-
1008
Quad Cities Station Units 1 and 2, Nuclear Plant Interface
Requirements (NPIRs)
Work Orders
Contingency Seasonal Readiness Work Orders
Procedures
AD-AA-101-F-10
Unit 1 Core Spray System Preparation for Standby
Operation
QCOP 1400-09
Unit 2 Core Spray System Preparation for Standby
Operation
QCOP 6600-04
Diesel Generator 1/2 Preparation for Standby Operation
QOM 2-1400-08
Core Spray System Fuse and Breaker Checklist
Inspection
Procedure
Type
Designation
Description or Title
or Date
QOM 2-1400-09
2A Core Spray Valve Checklist
QOM 2-1400-10
2B Core Spray Valve Checklist
QOM-1-1400-10
Unit 1B Core Spray Valve Checklist
QCOP 6600-04
Diesel Generator 1/2 Preparation for Standby Operation
QCOP 6600-24
Unit 2 Diesel Generator Preparation for Standby Operation
QOM 0-6600-01
Unit 0 Diesel Generator Valve Checklist
QOM 2-6600-01
Unit 2 Diesel Generator Checklist
71111.05Q Corrective Action
Documents
CR 4251296
Missed QCAP 1500-01 Actions
05/23/2019
FAS Device 32-24 and 52-11 Alarm
03/23/2019
Missed QCAP 1500-01 Actions
05/23/2019
Drawings
Drawing F-264
Fire Suppression System RHR Service Water Pumps Area G
Control Rod Drive Feed Pumps Area J
H
Engineering
Changes
Temporary Supplemental Cooling to the ASD Cabinets
CC-AA-209; Approved Fire Protection Program
Configuration Change Impact Review
Fire Plans
Fire Zone 8.2.8.E
Unit 1 TB 639-0 Elev. Main Turbine Floor (Outside Shield
Wall)
June 2010
FZ 11.1.1 A, B,
and C
Unit 1 TB 547-0 Elev. RHR Service Water Pumps
March 2012
FZ 11.1.1.B
Unit 1 RHR Service Water Pump Room
FZ 11.1.1.C
Unit 1 RHR Service Water Pump Room
Procedures
Surveillance Test Interval (STI) Evaluation Form
QCAP 1500-01
Administrative Requirements for Fire Protection
QCMM 5700-04
Installation and Removal of ASD Temporary Cooling Units
QCOA 4100-11
TRX(I) Supervisory (Trouble) Devices Monitoring Local
System Panels
Corrective Action
Documents
Unexpected Trip of GCB 3-4 In 345kV Switchyard
04/01/2018
QDC Readiness to Replace/Address a Failed 4kV/480V
XFMR
03/30/2019
Create WO to Document Risk Assessment for 345 kV
Switching
05/07/2019
MRule A1DE Required for SY9700-01, 345kV Switchyard
05/07/2019
Issue in IR 4233332 Requires MRFF Processing
05/20/2019
Inspection
Procedure
Type
Designation
Description or Title
or Date
Miscellaneous
Tagout: 02-IA-
2/11/2019
Procedures
Tag-Out Requester Checklist; WO 04768967-01
01/14/2019
WC-AA-104-F-01
Risk Screening/Mitigation Plan; MM Repair Instrument Air
Leak on Solder Joint WO 04768967-01
01/14/2019
Corrective Action
Documents
EDG to ESS Bus Ducts in EQ Harsh Zones
04/03/2019
RV 1-1402-28A Set-Point Test Exceeded 10-Year Test
Frequency
04/12/2019
Unexpected Speed Hold on B ASD
04/23/2019
B CREVS Rough Pre-Filters Installed Backwards
06/21/2019
Drawings
Drawing 4E-1426
Recirculating Pump ASD 1B Input Breaker Control
J
Drawing 4E-1426
Recirculating Pump ASD 1B Input Breaker Control
E
Drawing 4E-
6577F
ATWS Recirc Pump Trip System ECCS INIT-FW, RCIC,
HPCI and Turb Trips Div I and Div II - Part 6
T
Engineering
Changes
Review Use of Materials in Non-Seg Bus Routed from EDGS
to Dash Busses through EQ Harsh Zones
ECR 441826
Engineering Evaluate Acceptability of Filters for the Control
Room HVAC Charcoal Absorber Installed Backwards
06/20/2019
Miscellaneous
Consolidated Safety Relief Valve Sizing and Selection
Report for Core Spray Pump Discharge Over Fire Protection
08/07/2013
2004
Code for Operation and Maintenance of Nuclear Power
Plants
Procedures
QCAN 901(2)-4
C-5
Recirculation Adjustable Speed Drive B Speed Hold
QCOA 0202-08
Reactor Recirculation Control System Trouble
QCOA 0202-08
D; RRCS/ASD Event List
QCOS 0202-19
Online Testing of Unit 1 Division I ATWS Recirculation Pump
Trip and Alternate Rod Insertion Logic
QCOS 0202-20
Online Testing of Unit 1 Division II ATWS Recirculation
Pump Trip and Alternate Rod Insertion Logic
UFSAR 7.8
Anticipated Transient Without Scram Mitigation System
Work Orders
Flushing Cores Spray Lines into Reactor (IST)
03/27/2017
Miscellaneous
FWAA 4227272-
66-08
NC-19-004-Y, Yellow NER for Fitzpatrick Loss of Instr Air
Inspection
Procedure
Type
Designation
Description or Title
or Date
Procedures
DOA 4700-01
Instrument Air System Failure
Roles and Responsibilities of On-Shift Personnel
OP-AA-101-111-
1001
Operations Standards and Expectations
OP-QC-103-102-
1002
Quad Cities Strategies for Successful Transient Mitigation
Corrective Action
Documents
PSU Leakage Identified on the 0203-1D Inboard MSIV
03/18/2019
1D RHR Pump Tripped During QCOS 1000-06
04/01/2019
Miscellaneous
Inservice Testing
Bases Document
Valve EPN: 0-5741-319A-AO; CR HVAC-B Train RCU HX
RHRSW Supply Isolation
Inservice Testing
Bases Document
Valve EPN: 0-5741-319B-AO; CR HVAC-B Train RCU HX
Serv Wtr Supply Isolation
Procedures
QCOS 0250-04
MSIV Closure Timing (PMT for MSIV Outage Maintenance)
QCOS 0250-12
MSIV Closure Scram Sensor Channel Outage Functional
Test
QCOS 1000-06
RHR Pump/Loop Operability Test
QCOS 5750-04
Quarterly Testing of Control Room HVAC System Valves
and Dampers
Work Orders
CRD Scram Timing in Hot Condition (IST)
04/07/2019
Control Room HVAC System Check Vlv Test (IST)
04/08/2019
04/01/2019
04/02/2019
Corrective Action
Documents
PSU Q1R25 As Found MSIV 1B LLRT Exceeds TS Limit
<34
03/18/2019
PSU Q1R25: Failed Relay
03/21/2019
Found Bad Relay for HPCI Circuit
03/21/2019
Fatigue Assessment IR
03/21/2019
Rapid Trending Identified Negative Trend in FME
03/22/2019
Foreign Material Event - Unit 1 Reactor Vessel
03/23/2019
WHR Fatigue Assessment
03/24/2019
Incorrect Valve Tag Removed
03/25/2019
Unable to Perform DW Spray Header Air Flow Test
04/04/2019
MSIV-1-0203-1A As-Left Thrust Readings Less Than As-
04/05/2019
Inspection
Procedure
Type
Designation
Description or Title
or Date
Found
Drawings
Diagram 4E-
1331A
Relaying and Metering Diagram Generator and Main Power
Transformer 1
Drawing 4E-1331 Relaying and Metering Diagram Generator and Main
Transformer 1
BB
Drawing 4E-1338
Schematic Diagram Generator and Transformer Tripping
Relays Primary System
AY
Miscellaneous
Haul/Deployment Paths
01/03/2019
Shutdown Safety
Log #01
Modification Activities for Q1R25
01/09/2019
Shutdown Safety
Log #02
Q1R25 Shutdown Safety FLEX Considerations
01/09/2019
Shutdown Safety
Log #03
List of High Risk Activities and First Time Activities for
Q1R25
01/09/2019
Shutdown Safety
Log #04
Communication Plan for Q1R25
01/09/2019
Shutdown Safety
Log #05
List of System Health Review for Q1R25
01/16/2019
Procedures
Application of Freeze Seal Using RIDGID SuperFreeze
SF-2500
Critical Prediction Checklist
NF-AB-720-F-1
Control Rod Sequence Review and Approval Sheet for Unit
Cycle 26
Shutdown Safety System Health Review
QCGP 1-1
Normal Unit 1 Startup
115
QCOP 1000-24
Draining Reactor Cavity and Vessel to the Torus
QCOS 0201-02
Primary System Boundary Thermal Limitations
QCOS 0201-02
Reactor Thermal Limitations Surveillance Data Sheet
Work Orders
Core Verification
03/31/2019
Corrective Action
Documents
PSU Q1R25 FW CV 1-0220-62A Exceeded Required Action
Limit
03/23/2019
Q1R25 LLRT 1-2001-3 Leakage Could Not Be Quantified
03/25/2019
Q1R25 RPV Class 1 & Class 2 System Leakage Test
Results
04/03/2019
Inspection
Procedure
Type
Designation
Description or Title
or Date
Procedures
Implementation of the Technical Specification Surveillance
Frequency Control Program
QCOS 1000-31
1A Loop LPCI and Containment Cooling Modes of RHR
Non-Outage Logic Test
QCOS 6600-50
Unit One Division II Emergency Core Cooling System
Simulated Automatic Actuation and Diesel Generators
Auto-Start Surveillance
STI Change
Request Number
QC-18-008
Review the Frequency of Technical Specification (TS)
Surveillance Requirements (SR) for the HPCI/RCIC Low
Pressure Flow Rate and RCIC Automatic Initiation Testing
from 24 Months to 48 Months
Work Orders
Part 21 Issue on 1-1201-2
03/30/2019
MM Part 21 Action Item for MOV 1-1201-5 in Q1R25
04/01/2019
Core Flow Calibration
04/09/2019
RX WTR Cleanup Valve Timing Test (IST)
04/07/2019
Calculations
Permit Number
2018005
Liquid Release Permit Report - River Discharge Tank
05/04/2018
Permit Number
2019191
Gaseous Release Permit Report - Main Chimney Noble Gas
Unit 1+2
06/03/2019
Permit Number
2019193
Gaseous Release Permit Report - Reactor Vent Noble Gas
Unit 1
06/03/2019
Permit Number
2019199
Gaseous Release Permit Report
06/04/2019
Permit Number
2019201
Gaseous Release Permit Report
06/04/2019
Permit Number
2019203
Gaseous Release Permit Report - Reactor Vent Iodine and
Particulate Unit 2
06/04/2019
Release Report
2019004
Liquid Release Permit Report - Discharge Bay
05/01/2019
Miscellaneous
CY-QC-170-301
Offsite Dose Calculation Manual Quad Cities Station Units 1
and 2
SVP-18-029
Radioactive Effluent Release Report for 2017
04/27/2018
SVP-19-026
Radioactive Effluent Release Report for 2018
04/30/2019
Procedures
CY-QC-110-605
Reactor Building Cent Gaseous & Particulate Sampling
Inspection
Procedure
Type
Designation
Description or Title
or Date
CY-QC-110-606
Main Chimney Gaseous & Particulate Sampling
CY-QC-120-735
Main Chimney & Reactor Building Vent Noble Gas Release
Rate
Work Orders
01836282-01
Stand-By Gas Treatment Charcoal Absorber Test
05/10/2017
01906646-01
Technical Support Center Charcoal Absorber Surveillance
09/07/2017
01918595-01
Control Room Emergency Filtration System Charcoal
Absorber
10/11/2017
04635819-01
Main Chimney Noble Gas Monitor Calibration
03/06/2019
04670696
Service Water Monitor Calibration
2/20/2018
0467582-01
Radwaste Effluent Monitor Calibration
01/04/2019
04876363-01
Reactor Building Vent/Fuel Pool Rad Monitor
Calibration/Functional Test
2/20/2019
Corrective Action
Documents
04120126
Water Found in Radwaste Piping Vault
03/28/2018
04136730
REMP 2018 1st Quarter Missing/Anomalies Samples
05/11/2018
202852
REMP Air Sampler Station Found Without Power
2/07/2018
249167
1st Quarter 2019 Missed REMP Samples
05/15/2019
Miscellaneous
Quad Cities Nuclear Power Station, Units 1 and 2 Annual
Radiological Environmental Operation Report
05/10/2019
Meteorological Monitoring Program at the Quad Cities
Nuclear Generating Station January 2019
03/21/2019
Meteorological Monitoring Program at the Quad Cities
Nuclear Generating Station February 2019
04/25/2019
Procedures
EIML-SPM-1
Sampling Procedures Manual Environmental Incorporated
Midwest Laboratory
Response to Inadvertent Releases of Licensed Materials to
Groundwater, Surface Water, Soil or Engineered Structures
Radiological Groundwater Protection Program
Radiological Groundwater Protection Program
Implementation
EN-QC-408-4160
Quad Cities Station Radioactive Groundwater Protective
Program Reference Material
71151
Miscellaneous
CY-QC-120-720
Actual Dose Data and Supporting Information Package
10/31/2018
through
03/31/2019
Inspection
Procedure
Type
Designation
Description or Title
or Date
Procedures
CY-QC-120-720
Plant Effluent Dose Calculations
Corrective Action
Documents
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
03/27/2017
MSIVs 2-0203-1A and 2-0203-1C Closure Times Exceeded
the Maximum Technical Specification Limit of <5 Seconds
03/19/2018
EO ID: 1C RHRSW HP O/B Seal Leaking
03/18/2019
HPCI Motor Speed Changer Cycling Off of High Speed Stop
03/21/2019
Bus 19 Main Feed Breaker Failed to Trip During Crosstie
03/26/2019
Paint Flaking from Refuel Floor Ceiling (FME)
03/27/2019
Evaluation of Paint Chips that Fell from RB Overhead
03/28/2019
Rising Trend on PI 2-0262-17D 2B Recirc Pump OB Seal
Press
04/02/2019
MCR Alarm Not Received on 902-56 Panel
04/09/2019
1C RHRSW High Pressure Pump OB Seal Leak During Run
04/12/2019
VT3 of Support M-994D-22 During Q1R26
05/01/2019
Logic Test Discrepancies and Improvements QCOS 1000-31
05/23/2019
The U2 A Drywell Rad Monitor (2-2419A) Failed Downscale
05/24/2019
OOT, RIS 1-2419-A, Trend Code B3
05/28/2019
U2 A Drywell Radiation Monitor, 2-2419A, Failed
Downscale
06/19/2019
MRule A1DE Required for CM2400-02, Unit 2 DW Rad
Monitor
06/25/2019
Drawings
Drawing M-37
Diagram of RHR Service Water Piping
BI
Procedures
QCIS 2400-04
Unit 2 Division I Drywell Radiation Monitor Calibration and
Functional Test
Work Orders
The Unit 2 A Drywell Rad Monitor Failed Downscale
05/28/2019
Corrective Action
Documents
ECAPE 4217557
U1 HPCI Failed to Roll During QCOS 2300-27
03/08/2019