IR 05000254/2021001
| ML21116A247 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/26/2021 |
| From: | Kenneth Riemer NRC/RGN-III/DRP/B1 |
| To: | Rhoades D Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2021001 | |
| Download: ML21116A247 (19) | |
Text
April 26, 2021
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000254/2021001 AND 05000265/2021001
Dear Mr. Rhoades:
On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Quad Cities Nuclear Power Station. On April 13, 2021, the NRC inspectors 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.
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:
05000254/2021001 and 05000265/2021001
Enterprise Identifier: I-2021-001-0049
Licensee:
Exelon Generation Company, LLC
Facility:
Quad Cities Nuclear Power Station
Location:
Cordova, IL
Inspection Dates:
January 01, 2021 to March 31, 2021
Inspectors:
J. Cassidy, Senior Health Physicist
C. Hunt, Senior Resident Inspector
C. Mathews, Illinois Emergency Management Agency
J. Park, Reactor Inspector
D. Tesar, Senior 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, 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.
PLANT STATUS
UNIT 1 The unit began the inspection period at full-rated thermal power. On February 8, 2021, the unit began its end-of-cycle coastdown period. On March 15, 2021, the unit shut down for Refueling Outage (RO) Q1R26. On March 30, 2021, the unit was restarted, and power ascension was ongoing through the end of the inspection period. For all other periods, the unit was at full-rated thermal power 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, where it remained for the entire inspection period, with the exception of short-term power reductions for control rod sequence exchanges, 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 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 Disease 2019 (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; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; 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 portions 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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated on February 3, 2021, the adequacy of site preparations for impending severe cold weather predicted for February 4 to 11, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 reactor core isolation cooling during high pressure coolant injection work window on March 2, 2021
- (2) Unit 1/2 emergency diesel generator (EDG) during Unit 1 EDG unavailability on March 16, 2021
- (3) Unit 1 EDG following a diesel generator cooling water modification on March 17, 2021
- (4) Unit 1B low pressure core injection system walkdown on March 24, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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 11.1.3, Unit 1 reactor building, elevation 554'-0", high pressure coolant injection (HPCI) & HPCI access tunnel and Fire Zone 11.1.4, Unit 2 reactor building, elevation 544'-0", HPCI pump room on January 21, 2021
- (2) Fire Zone 8.2.6.A, Unit 1 turbine building, elevation 595'-0", 4kV switchgear & Unit 1 trackway on February 19, 2021
- (3) Fire Zone 11.3.4, Unit 2 reactor building, elevation 544'-0", northeast corner room - 2A residual heat removal room on February 25, 2021
- (4) Fire Zone 1.1.1.3, Unit 1 reactor building, elevation 623'-0", mezzanine level on March 22, 2021
- (5) Fire Zone 8.2.2A, Unit 2 turbine building, elevation 572'-6", control rod drive pumps on March 23, 2021
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined, and accepted by reviewing the documentation of the following activities from March 22 to March 26, 2021:
03.01.a - Nondestructive Examination and Welding Activities.
1. volumetric exam (ultrasonic testing (UT)) of Component ID 30C-S25, Category
R-A, Item R1.20-4
2. volumetric exam (UT) of Component ID 1008B-5, Category R-A, Item R1.11-2
3. surface exam (magnetic particle examination (MT)) of Component ID
1025-W-211A, Category C-C, Item C3.20
4. surface exam (MT) of Component ID RPV-THHF, Category B-A, Item B1.40
5. pressure boundary welds 1, 2, 5, and 10 fabricated during replacement of
1-1001-65B HP residual heat removal service water pump discharge elbow under Work Order 5010715
The above UT and MT exam records were selected from the previous outage in Spring 2019 (Q1R25), since there were neither the inservice inspection exams nor the aging management related exams scoped in during this outage (Spring 2021, Q1R26). It is also noted that there were no volumetric or surface exam records with relevant indications from the previous outage that had been accepted for continued service, and hence were not available for the inspector's review.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (3 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 load drop for end-of-cycle rod pattern adjustments and hydraulic control unit L-12 SCRAM outlet adjustment on January 16, 2021.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 shutdown/cooldown for RO Q1R26 on March 15, 2021.
- (3) The inspectors observed and evaluated licensed operator performance in the control room during the Unit 1 reactor startup and heat up on March 30, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator requalification training simulator as-left scenario on February 4, 2021.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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) E-2 certification meeting and risk management for work week January 24, 2021
- (2) E-2 certification meeting and risk management for work week March 1, 2021
- (3) E-2 certification meeting and risk management for work week March 8, 2021 (4)impact of emergent issue during Unit 1 Q1R26 RO on Unit 2 online risk on March 17, 2021 (5)trip of reserve auxiliary transformer T-12 during RO Q1R26 on March 19, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Issue Report 4389284, "Time Delay Unit 10A-K45B As-Found Out of Spec"
- (2) Issue Report 633276, "Op Eval 2B CREVs [control room emergency ventilation]
Freon Leak"
- (3) Issue Report 4396776, "Expanded Scope WO [work order] 4708066-01 1A RHR
[residual heat removal] Room Cooler Inspection"
- (4) Issue Report 4403127, "EO ID Bus 13-1 to 23-1 Tie Breaker Lockout Relay Found Tripped"
- (5) Operability Evaluation 633936, "Evaluate Impacts of FWCV [feedwater control valve]
1-0220-62A Lost Parts during Q1R26"
- (6) Operability Evaluation 633948, "1-0220-1 Maintenance Steam Line Drain Header Stop Valve"
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (4 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Work Order 4688647-21, "Temporary Configuration Change for Work Order
===4688647-21 per Engineering Change 332661," on March 11, 2021
- (2) Engineering Change 626221, "Unit 1 HPCI SV-8 and SV-12 Replacement," on March 22, 2021
- (3) Engineering Change 407242, "U-1 Install 5 Isolation Valves in Safety Related Service Water Piping on Each ECCS [emergency core cooling system] Room Cooler Supply Piping," on March 15, 2021
- (4) Engineering Change 625679, "1A and 1B ASD [adjustable speed drive] Upgrade Modification," on March 18, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01)===
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) QCOS 6600-06, "Diesel Generator Cooling Water Pump Flow Rate Test," following Work Order 5095941 on February 1, 2021 (2)post-maintenance test for Bus 18 to Bus 19 cross-connect breaker on March 17, 2021 (3)post-maintenance test for 1/2 EDG maintenance on March 19, 2021
- (5) QCOS 1000-04, "'B' RHR Service Water Operability," ('B' loop residual heat removal service water) on March 26, 2021
- (6) QCOS 1300-01, "Periodic RCIC [reactor core isolation cooling] Pump Operability Test," on March 31, 2021
- (7) QCOS 2300-01, "Periodic HPCI Pump Operability Test," on March 31, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated Unit 1 RO Q1R26 activities from March 15, 2021, to the end of the quarter on March 31, 2021. Inspection activities related to the Q1R26 outage continued into the next inspection period.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 1 EDG monthly load run on January 11, 2021
- (2) Work Order 05095941-01, "Backflush DG [diesel generator] HX [heat exchanger]
2-6661 'A' & 'B' Cooling Water Annubar FI 2-3941-26," on February 1, 2021
- (3) QOS 6500-01, "4 kV Bus 13-1 Undervoltage Functional Test," on March 25, 2021
- (4) QCOS 201-08, "Reactor Coolant System Pressure Test," on March 28, 2021
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) QCOS 1000-06, "RHR Pump/Loop Operability Test," Revision 64, on January 25, 2021
- (2) QCOS 1100-07, "Standby Liquid Control Pump Flow Rate Test," Revision 41, on February 1, 2021
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) QCOS 0100-42, "Containment Penetration Expansion Bellows Local Leak Rate Test," and QCOS 1400-19, "Core Spray Pressure Isolation Valve Seat Leakage Test," on March 19, 2021
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) The inspectors observed activities related to the technical support center during an emergency preparedness drill on February 2, 2021.
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
(1)technical support center and control room activities during an emergency preparedness drill on February 23,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas and labeling of radioactive material in containers.
Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
(1)observed licensee surveys of potentially contaminated material leaving the radiological controlled area (RCA)
(2)observed workers exiting the RCA at Unit 1 during a refueling outage (3)observed work area staging for inspection/repairs of the 'B' contaminated condensate storage tank
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities with high radiological risk or airborne radioactivity
(1)observed activities associated with Radiological Work Package QC-01-21-00513, "Drywell Control Rod Drive (CRD) Exchange" (2)observed activities associated with Radiological Work Package QC-01-21-00901, "Reactor Disassembly/Reassembly" (3)observed activities associated with Radiological Work Package QC-00-21-00229, "Inspection/Repair on Contaminated Condensate Storage Tanks" High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas:
- (1) Unit 1 reactor cavity
- (2) Unit 1 drywell
- (3) Unit 2 steam tunnel
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.02 - Occupational ALARA Planning and Controls
Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (3 Samples)
The inspectors reviewed as low as reasonably achievable practices and radiological work controls and reviewed the following activities:
(1)observed activities associated with Radiological Work Package QC-01-21-00513, "Drywell Control Rod Drive (CRD) Exchange" (2)observed activities associated with Radiological Work Package QC-01-21-00901, "Reactor Disassembly/Reassembly" (3)observed activities associated with Radiological Work Package QC-00-21-00229, "Inspection/Repair on Contaminated Condensate Storage Tanks"
Radiation Worker Performance (IP Section 03.04) (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician performance during:
(1)reactor disassembly/reassembly
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
(1)temporary HEPA filtration units on the Unit 1 refuel floor
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
71124.05 - Radiation Monitoring Instrumentation
Calibration and Testing Program (IP Section 03.02) (10 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Canberra ACCUSCAN II
- (2) Unit 1 Division II Drywell Radiation Monitor 1-2419-B
- (3) Ludlum Model 3030P Serial Number 264768
- (4) MGP Model Amp 200 Serial Number 7711-055
- (5) MGP Model Telepole Serial Number 6696-101
- (6) Eberline Model AMS4 Serial Number 107/107
- (7) RADeCO Model H-809 High Volume Air Sampler Serial Number 052
- (8) NE Technology Model IPM9 Serial Number I348
- (9) Thermo Scientific Model SAM-12 Serial Number 12205
- (10) Ludlum Model 177 Serial Number 339058
Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 1 steam jet air ejector effluent monitor
- (2) Unit 1 service water effluent monitor
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 03.01)===
- (1) Unit 1 (01/01/2020 - 12/31/2020)
- (2) Unit 2 (01/01/2020 - 12/31/2020)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 03.02) (2 Samples)
- (1) Unit 1 (01/01/2020 - 12/31/2020)
- (2) Unit 2 (01/01/2020 - 12/31/2020)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 03.03) (2 Samples)
- (1) Unit 1 (01/01/2020 - 12/31/2020)
- (2) Unit 2 (01/01/2020 - 12/31/2020)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 13, 2021, the inspectors presented the integrated inspection results to Mr. K. Ohr, Site Vice President, and other members of the licensee staff.
- On February 11, 2021, the inspectors presented the radiation protection inspection results to Mr. M. Humphrey, Organizational Effectiveness & Regulatory Director, and other members of the licensee staff.
- On March 19, 2021, the inspectors presented the radiation protection inspection results to Mr. K. Ohr, Site Vice President, and other members of the licensee staff.
- On March 26, 2021, the inspectors presented the inservice inspection results to Mr. B. Wake, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
OP-AA-108-111-
1001
Severe Weather and Natural Disaster Guidelines
QCOP 0010-02
Required Cold Weather Routines
Corrective Action
Documents
EO ID: Steam Leak on RCIC Drain Pot LS Drain Valve
04/10/2019
Procedures
QCOP 6600-04
Diesel Generator 1/2 Preparation for Standby Operation
QCOS 1300-11
RCIC Valve Position Verification
Fire Plans
FZ 1.1.1.3
Unit 1 RB 623'-0" Elev. Mezzanine Level
07/2012
FZ 11.3.4
Unit 2 RB 544'-0" Elevation NE Corner Room - 2A RHR
Room
07/2009
FZ 8.2.2.A
Unit 2 TB 572'-6" Elevation CRD Pumps
10/2013
FZ 8.2.6.A
Unit 1 TB 595'-0" TB 595'-0" Elev. 4KV Switchgear & U-1
Trackway
03/2018
71111.08G Corrective Action
Documents
Foreign Material Lost in RPV
03/23/2019
Q1R25 FW Check Valve 1-0220-62A VT-3 Exam As-Found
Condition
03/28/2019
OLL 1-0220-62A Bonnet Bolting Missed Surface Exam
03/30/2019
PSU Q1R25 VT-1 of Bolting for Valve 1-1301-41 Bypassed
04/01/2019
Required Exam for 1-8799-214 Not Performed in Q1R25
04/02/2019
Q1R25 Trend IR - Required Bolting Exams Not Performed
04/15/2019
VT3 of Support M-994D-22 During Q1R26
05/01/2019
Q1R25 MSIV 1-0203-1B Bonnet Nut Installed W/O MT & VT-
Exam
06/12/2019
B CCST Tank NDE Results
03/22/2021
Engineering
Changes
Evaluation of Foreign Material Lost from GEH Core Spray
Inspection Tool in Unit 1 Reactor Vessel in Q1R25
04/09/2019
Evaluation of the Waiver of R-4411 MT/VT-1 Exam
Requirements for a Class I Bonnet Nut on 1-0203-1B MSIV
(Q1R25)
Miscellaneous18-115
ASME Section XI Repair/Replacement Plan
06/20/2019
20-003
ASME Section XI Repair/Replacement Plan
08/24/2020
Procedure Qualification Record (PQR)
04/19/2001
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
209.05F001
NDE Reports
20-MT-006
Magnetic Particle Examination Data Sheet
2/28/2020
20-MT-008
Magnetic Particle Examination Data Sheet
2/28/2020
20-PT-013
Liquid Penetrant Examination Data Sheet
2/28/2020
20-PT-014
Liquid Penetrant Examination Data Sheet
2/28/2020
20-VT-001
VT-1 Visual Examination NDE Report
2/28/2020
Magnetic Particle Examination
03/24/2019
Magnetic Particle Examination
03/26/2019
Magnetic Particle Examination
03/26/2019
UT Calibration/Examination
03/24/2019
UT Calibration/Examination
03/23/2019
Procedures
Preheat, Interpass Temperature and Postweld Heat
Treatment of Welds
Eddy Current Surface Examinations
Liquid Penetrant (PT) Examination
Magnetic Particle (MT) Examination
and 9
Ultrasonic (UT) Measurement of Material Thickness and
Interfering Conditions
VT-3 Visual Examination of Component Supports,
Attachments, and Interiors of Reactor Vessels
GEH-PDI-UT-1
PDI Generic Procedure for the Ultrasonic Examination of
Ferritic Welds
PDI-UT-1
Table 1
PDI-UT-1
Table 2
03/10/2020
WPS 1-1-GTSM-
ASME Welding Procedure Specification Record
Work Orders
CRD 34-23 Drive Mechanism Leakage
04/18/2019
MM 1B RHRSW Discharge Piping Leak
03/03/2020
Corrective Action
Documents
PRA Review Question, HRE Guidance for SW Strainers
09/05/2019
Temporary Structure Placed on FLEX Haul Path
03/05/2021
Trip of Reserve Aux Transformer T-12 During Q1R26
03/19/2021
Procedures
OP-QC-107-1001
Quad Cities Risk Management Guidelines
QCOS 0050-02
Flex Haul Path Inspection
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Time Delay Unit 10A-K45B As Found Out of Spec
2/09/2021
Expanded Scope w/o 4708066-01, 1A RHR Room Cooler
Inspection
01/19/2021
4.0 Critique 1A RHR Room Cooler Inspection
01/20/2021
EOC for IR 4396776 - 1A RHR Room Cooler HX Inspection
01/19/2021
EO ID Bus 13-1 to 23-1 Tie Breaker Lockout Fly Found
Tripped
2/18/2021
Engineering
Changes
Op Eval EC 'B' CREVS Freon Leak
Evaluate Impacts of FW CV 1-0220-62A Lost Parts During
Q1R26
000
1-0220-1 Main Steam Line Drain Header Stop Valve
000
Work Orders
1A RHR Corner Room Cooler
01/19/2021
Corrective Action
Documents
APS - Handle of Valve Installed Contacts a 3/4" Line
03/19/2021
Liquid Penetrant Inspection Indications on New Rigid
Support
03/26/2021
Q1R26 Pin Hole Leak on DGCW Line Downstream of
1-399-885
03/26/2021
Engineering
Changes
Temporary Support for the Diesel Generator Cooling Water
(DGCW) System While the Reactor Feed Pump Motors are
Being Moved
U-1 Install 5 Isolation Valves in SR Service Water Piping on
Each ECCS Room Cooler Supply Piping
Unit 1 HPCI SV-8 and SV-12 Replacement
Procedures
Temporary Configuration Changes
QCOP 0202-51
ASD Testing in Open Loop Test Mode
Corrective Action
Documents
U2 EDGCWP Initial Test Conditions Not Established
2/01/2021
IR 504920
Aborted QCOS 6600-06 for U1 EDG
06/29/2006
Procedures
QCOP 6600-05
Shared Unit Diesel Generator Start Up
QCOS 1000-04
RHR Service Water Pump Operability Test
QCOS 1000-06
RHR Pump/Loop Operability Test
QCOS 1300-01
Periodic RCIC Pump Operability Test
QCOS 2300-01
Periodic HPCI Pump Operability Test
QCOS 6600-06
Diesel Generator Cooling Water Pump Flow Rate Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
Q1R26 Decay Heat and Related Calculations
Miscellaneous
Safety Evaluation
Report
06/27/1983
Technical
Evaluation Report
06/27/1983
Procedures
Control of Heavy Loads Program
MA-QC-756-600
Reactor Disassembly
OU-QC-104
Shutdown Safety Management Program Quad Cities Annex
QCMM 5800-04
Reactor Building Overhead Crane Reactor Cavity
Maintenance Support Tools Transport
QCMM 5800-05
Reactor Building Overhead Crane Utilization
QCOP 1000-44
Alternate Decay Heat Removal
Procedures
QCOP 0100-01
Local Leak Rate Test Make-up Flow Rate Method
QCOS 0100-42
Containment Penetration Expansion Bellows Local Leak
Rate Test
Work Orders
OP As Found Seat Leakage Test MO 1-1402-25A
03/17/2021
QOS 6500-01, 4 KV Undervoltage Functional Test
OP Perform Testable Double Ply Bellows (LLRT)
03/23/2021
QCOS 1000-6 'A' RHR Pump Flow Rate Group A Test (IST)
QCOS 1100-7 'A' SBLC Pump Flow Rate Group B Test
Backflush DG HX 2-6661 A&B Cooling Water Annubar FE
2-3941-42
2/01/2021
QCOS 6600-41 U1 DG Monthly Load Test
01/10/2021
Corrective Action
Documents
1st Quarter ERO Drill Performance
03/22/2021
ALARA Plans
QC-00-21-00229
Inspection / Repair on CCST Tanks
03/15/2021
QC-01-21-00513
DW Control Rod Drive (CRD) Exchange
QC-01-21-00901
FF RX Disassembly/Reassembly Activities
Corrective Action
Documents
Resulting from
Inspection
RWP's Lack Info
03/17/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
NISP-RP-010
Radiological Job Coverage
Radiological Risk Management
Radiation Work
Permits (RWPs)
QC-01-21-00513
DW Control Rod Drive (CRD) Exchange
QC-01-21-00901
FF RX Disassembly/Reassembly Activities
Procedures
Administration of the Radiation Work Permit Program
Miscellaneous
QC-01-21-00513
TEDE-ALARA Evaluation Screening Worksheet
01/21/2021
QC-01-21-00901
TEDE-ALARA Evaluation Screening Worksheet
03/08/2021
Procedures
NISP-RP-008
Use and Control of HEPA Filtration and Vacuum Equipment
Calibration
Records
Calibration of the ACCUSCAN II WBC System at the Quad
Cities Nuclear Generating Station
07/21/2020
26942
00162776-01. TS, DI
- V. II, Drywell Radiation Monitor
Cal/Func Test, WS124031M
2/10/2019
Certificate
0011217699
MGP Amp200 Serial Number 7711-055
03/10/2020
Certificate
0011225896
Ludlum Model 177 Serial Number 339058
2/25/2020
Certificate
0011238650
Certificate of Calibration Ludlum 3030P Serial Number
264768
06/05/2020
Certificate
0011242092
Certificate of Calibration RAD-PRO 5 Serial Number
20110702019
05/19/2020
Certificate
0011244672
Eberline Model AMS4 Serial Number 107/107
05/15/2020
Certificate
0011244710
MGP Telepole Serial Number 6696-101
05/29/2020
RADeCO Serial
Number 052
RADeCO Model H-809 High Volume Air Sampler
05/12/2020
IPM Calibration Data Sheet Monitor I348
03/14/2021
SAM-12 Calibration Data Sheet Serial Number 12205
2/10/2020
Unit 1 Steam Jet Air Ejector Off-GAs Logarithmic Radiation
Monitor Calibration and Functional Test
08/18/2020
Service Water Monitor Calibration
01/13/2021
Corrective Action
Certificate
Ludlum 3/43-92 Serial Number 282993/PR314732
07/16/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
- 0011237071
MCR Received 902-3 G-16, Fuel Pool Channel A Hi
Radiation
07/04/2020
Drywell CAM Detector Sensitive to Light
10/05/2020
Unit 2 Reactor Building Stack Monitor Low Sample Flow
10/07/2020
Follow up to IR 4374922
10/07/2020
Quarterly Lists of QC Results and Plots
2/18/2020
Conservative Setpoint Used for Radwaste Effluent Monitor
01/13/2021
Miscellaneous
Quality Control Charts for ACCUSCAN II Second Quarter
20
2/16/2020
CY-QC-130-404
Unit 1 Steam Jet Air Ejector Setpoint Calculation
2/22/2020
QDC-19-003
Unconditional Release Detection Thresholds and Dose
Consequences
Procedures
Controls for Radiation Protection Instrumentation
Operation and Calibration of IPM Whole Body Frisking
Monitor
Calibration of H-Vol Air Samplers
Operation and Calibration of the Model SAM-12 Small
Articles Monitor
Self-Assessments IR 4201130
Exelon Power Labs RP Instruments (EPL)
2/31/2019
71151
Miscellaneous
Quad Cities 1 Quarterly Performance Indicators
Quad Cities 2 Quarterly Performance Indicators
QC Unit 1 Power History Report
QC Unit 2 Power History Report