IR 05000254/2019002

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Integrated Inspection Report 05000254/2019002 and 05000265/2019002
ML19214A115
Person / Time
Site: Quad Cities  Constellation icon.png
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

uly 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: DPR-29 and DPR-30 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 Enclosure

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/ LER 2017-002-01 for Quad 71153 Closed 2017-002-01 Cities Nuclear Power Station,

Unit 1, Four Main Steam Isolation Valves (MSIVs)

Closure Times Exceeded LER 05000254,05000265/ LER 2018-001-01 for Quad 71153 Closed 2018-001-01 Cities Nuclear Power Station,

Unit 2, Two Main Steam Isolation Valves (MSIVs)

Closure Times Exceeded LER 05000254,05000265/ LER 2019-001-00 for Quad 71153 Closed 2019-001-00 Cities, Unit 1, HPCI System Inoperable Due to Blown Fuse in the Motor Speed Changer Circuit

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) 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)

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)

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.)

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) 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)

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)

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)

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)

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)

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) 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) 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) 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)

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
  • 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
  • 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

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) 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) 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 Type Designation Description or Title or Date

Procedure

71111.01 Corrective Action IR 4238374 U1 Main Transformer Leaking Oil 04/11/2019

Documents IR 4244757 1A ASD Temporary Cooling Needed for Summer Readiness 04/30/2019

IR 4244760 1B ASD Temporary Cooling Needed for Summer Readiness 04/30/2019

IR 4244763 2A ASD Temporary Cooling Needed for Summer Readiness 04/30/2019

IR 4244768 2B ASD Temporary Cooling Needed for Summer Readiness 04/30/2019

Miscellaneous Advanced Nuclear Dispatch, Number: 229 02/26/2016

Nuclear Load Following Congestion Relief Program; 11/18/2014

Number: 219

Risk Issue ODM: U2 Main 0

Number: QDC-2-

2019-0124

SPOG: 1-3-C Station 4 Quad Cities Units 1 and 2 Special Protection 13

System

Procedures OP-AA-102-102 General Area Checks and Operator Field Rounds 16

OP-AA-108-107 Switchyard Control 4

OP-AA-108-107- Station Response to Grid Capacity Conditions 7

1001

OP-AA-108-107- Interface Procedure Between BGE/ComEd/PECO and 11

1002 Exelon Generation (Nuclear/Power) for Transmission

Operations

QCOA 0010-16 Flood Emergency Procedure 29

QCOA 6100-03 Loss of Offsite Power 42

WC-AA-107 Seasonal Readiness 21

WC-QC-8003- Quad Cities Station Units 1 and 2 , Nuclear Plant Interface 4

1008 Requirements (NPIRs)

Work Orders Contingency Seasonal Readiness Work Orders

71111.04 Procedures AD-AA-101-F-10 Unit 1 Core Spray System Preparation for Standby 1

Operation

QCOP 1400-09 Unit 2 Core Spray System Preparation for Standby 5

Operation

QCOP 6600-04 Diesel Generator 1/2 Preparation for Standby Operation 34

QOM 2-1400-08 Core Spray System Fuse and Breaker Checklist 5

Inspection Type Designation Description or Title or Date

Procedure

QOM 2-1400-09 2A Core Spray Valve Checklist 8

QOM 2-1400-10 2B Core Spray Valve Checklist 6

QOM-1-1400-10 Unit 1B Core Spray Valve Checklist 8

71111.04S QCOP 6600-04 Diesel Generator 1/2 Preparation for Standby Operation 34

QCOP 6600-24 Unit 2 Diesel Generator Preparation for Standby Operation 3

QOM 0-6600-01 Unit 0 Diesel Generator Valve Checklist 17

QOM 2-6600-01 Unit 2 Diesel Generator Checklist 25

71111.05Q Corrective Action CR 4251296 Missed QCAP 1500-01 Actions 05/23/2019

Documents IR 4232291 FAS Device 32-24 and 52-11 Alarm 03/23/2019

IR 4251296 Missed QCAP 1500-01 Actions 05/23/2019

Drawings Drawing F-264 Fire Suppression System RHR Service Water Pumps Area G H

Control Rod Drive Feed Pumps Area J

Engineering EC 623395 Temporary Supplemental Cooling to the ASD Cabinets 0

Changes EC 623395 CC-AA-209; Approved Fire Protection Program 0

Configuration Change Impact Review

Fire Plans Fire Zone 8.2.8.E Unit 1 TB 639-0 Elev. Main Turbine Floor (Outside Shield June 2010

Wall)

FZ 11.1.1 A, B, Unit 1 TB 547-0 Elev. RHR Service Water Pumps March 2012

and C

FZ 11.1.1.B Unit 1 RHR Service Water Pump Room 23

FZ 11.1.1.C Unit 1 RHR Service Water Pump Room 23

Procedures ER-AA-425-1001 Surveillance Test Interval (STI) Evaluation Form 1

QCAP 1500-01 Administrative Requirements for Fire Protection 39

QCMM 5700-04 Installation and Removal of ASD Temporary Cooling Units 0

QCOA 4100-11 TRX(I) Supervisory (Trouble) Devices Monitoring Local 34

System Panels

71111.12 Corrective Action IR 4121737 Unexpected Trip of GCB 3-4 In 345kV Switchyard 04/01/2018

Documents IR 4234556 QDC Readiness to Replace/Address a Failed 4kV/480V 03/30/2019

XFMR

IR 4247012 Create WO to Document Risk Assessment for 345 kV 05/07/2019

Switching

IR 4247090 MRule A1DE Required for SY9700-01, 345kV Switchyard 05/07/2019

IR 4250438 Issue in IR 4233332 Requires MRFF Processing 05/20/2019

Inspection Type Designation Description or Title or Date

Procedure

71111.13 Miscellaneous Tagout: 02-IA- 02/11/2019

240FIX-001

Procedures OP-AA-109-103 Tag-Out Requester Checklist; WO 04768967-01 01/14/2019

WC-AA-104-F-01 Risk Screening/Mitigation Plan; MM Repair Instrument Air 01/14/2019

Leak on Solder Joint WO 04768967-01

71111.15 Corrective Action IR 4236078 EDG to ESS Bus Ducts in EQ Harsh Zones 04/03/2019

Documents IR 4238910 RV 1-1402-28A Set-Point Test Exceeded 10-Year Test 04/12/2019

Frequency

IR 4242536 Unexpected Speed Hold on B ASD 04/23/2019

IR 4258635 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- ATWS Recirc Pump Trip System ECCS INIT-FW, RCIC, T

6577F HPCI and Turb Trips Div I and Div II - Part 6

Engineering EC 440244 Review Use of Materials in Non-Seg Bus Routed from EDGS

Changes to Dash Busses through EQ Harsh Zones

ECR 441826 Engineering Evaluate Acceptability of Filters for the Control 06/20/2019

Room HVAC Charcoal Absorber Installed Backwards

Miscellaneous Consolidated Safety Relief Valve Sizing and Selection 08/07/2013

Report for Core Spray Pump Discharge Over Fire Protection

ASME OM Code- Code for Operation and Maintenance of Nuclear Power

2004 Plants

Procedures QCAN 901(2)-4 Recirculation Adjustable Speed Drive B Speed Hold 12

C-5

QCOA 0202-08 Reactor Recirculation Control System Trouble 17

QCOA 0202-08 Attachment D; RRCS/ASD Event List 17

QCOS 0202-19 Online Testing of Unit 1 Division I ATWS Recirculation Pump 10

Trip and Alternate Rod Insertion Logic

QCOS 0202-20 Online Testing of Unit 1 Division II ATWS Recirculation 12

Pump Trip and Alternate Rod Insertion Logic

UFSAR 7.8 Anticipated Transient Without Scram Mitigation System 13

Work Orders WO 1817554 Flushing Cores Spray Lines into Reactor (IST) 03/27/2017

71111.18 Miscellaneous FWAA 4227272- NC-19-004-Y, Yellow NER for Fitzpatrick Loss of Instr Air

66-08

Inspection Type Designation Description or Title or Date

Procedure

Procedures DOA 4700-01 Instrument Air System Failure 53

OP-AA-101-111 Roles and Responsibilities of On-Shift Personnel 12

OP-AA-101-111- Operations Standards and Expectations 22

1001

OP-QC-103-102- Quad Cities Strategies for Successful Transient Mitigation 25

1002

71111.19 Corrective Action IR 4230579 PSU Leakage Identified on the 0203-1D Inboard MSIV 03/18/2019

Documents IR 4235323 1D RHR Pump Tripped During QCOS 1000-06 04/01/2019

Miscellaneous Inservice Testing Valve EPN: 0-5741-319A-AO; CR HVAC-B Train RCU HX

Bases Document RHRSW Supply Isolation

Inservice Testing Valve EPN: 0-5741-319B-AO; CR HVAC-B Train RCU HX

Bases Document Serv Wtr Supply Isolation

Procedures QCOS 0250-04 MSIV Closure Timing (PMT for MSIV Outage Maintenance) 28

QCOS 0250-12 MSIV Closure Scram Sensor Channel Outage Functional 2

Test

QCOS 1000-06 RHR Pump/Loop Operability Test 61

QCOS 5750-04 Quarterly Testing of Control Room HVAC System Valves 38

and Dampers

Work Orders WO 4832132 CRD Scram Timing in Hot Condition (IST) 04/07/2019

WO 4877341 Control Room HVAC System Check Vlv Test (IST) 04/08/2019

WO 4911981 RHR C Pump Flow Rate (IST) 04/01/2019

WO 4911983 RHR D Pump Flow Rate (IST) 04/02/2019

71111.20 Corrective Action IR 4230600 PSU Q1R25 As Found MSIV 1B LLRT Exceeds TS Limit 03/18/2019

Documents <34

IR 4231752 PSU Q1R25: Failed Relay 03/21/2019

IR 4231753 Found Bad Relay for HPCI Circuit 03/21/2019

IR 4231897 Fatigue Assessment IR 03/21/2019

IR 4232031 Rapid Trending Identified Negative Trend in FME 03/22/2019

IR 4232329 Foreign Material Event - Unit 1 Reactor Vessel 03/23/2019

IR 4232493 WHR Fatigue Assessment 03/24/2019

IR 4232916 Incorrect Valve Tag Removed 03/25/2019

IR 4236198 Unable to Perform DW Spray Header Air Flow Test 04/04/2019

IR 4236574 MSIV-1-0203-1A As-Left Thrust Readings Less Than As- 04/05/2019

Inspection Type Designation Description or Title or Date

Procedure

Found

Drawings Diagram 4E- Relaying and Metering Diagram Generator and Main Power 1

1331A Transformer 1

Drawing 4E-1331 Relaying and Metering Diagram Generator and Main BB

Transformer 1

Drawing 4E-1338 Schematic Diagram Generator and Transformer Tripping AY

Relays Primary System

Miscellaneous Haul/Deployment Paths 01/03/2019

Shutdown Safety Modification Activities for Q1R25 01/09/2019

Log #01

Shutdown Safety Q1R25 Shutdown Safety FLEX Considerations 01/09/2019

Log #02

Shutdown Safety List of High Risk Activities and First Time Activities for 01/09/2019

Log #03 Q1R25

Shutdown Safety Communication Plan for Q1R25 01/09/2019

Log #04

Shutdown Safety List of System Health Review for Q1R25 01/16/2019

Log #05

Procedures MA-AA-736-620 Application of Freeze Seal Using RIDGID SuperFreeze 1

SF-2500

NF-AB-715 Critical Prediction Checklist 13

NF-AB-720-F-1 Control Rod Sequence Review and Approval Sheet for Unit 1

Cycle 26

OU-AA-103 Shutdown Safety System Health Review 20

QCGP 1-1 Normal Unit 1 Startup 115

QCOP 1000-24 Draining Reactor Cavity and Vessel to the Torus 23

QCOS 0201-02 Primary System Boundary Thermal Limitations 31

QCOS 0201-02 Reactor Thermal Limitations Surveillance Data Sheet 31

Work Orders WO 4628169 Core Verification 03/31/2019

71111.22 Corrective Action IR 4232248 PSU Q1R25 FW CV 1-0220-62A Exceeded Required Action 03/23/2019

Documents Limit

IR 4232654 Q1R25 LLRT 1-2001-3 Leakage Could Not Be Quantified 03/25/2019

IR 4235847 Q1R25 RPV Class 1 & Class 2 System Leakage Test 04/03/2019

Results

Inspection Type Designation Description or Title or Date

Procedure

Procedures ER-AA-425 Implementation of the Technical Specification Surveillance 2

Frequency Control Program

QCOS 1000-31 1A Loop LPCI and Containment Cooling Modes of RHR 29

Non-Outage Logic Test

QCOS 6600-50 Unit One Division II Emergency Core Cooling System 43

Simulated Automatic Actuation and Diesel Generators

Auto-Start Surveillance

STI Change Review the Frequency of Technical Specification (TS) 0

Request Number Surveillance Requirements (SR) for the HPCI/RCIC Low

QC-18-008 Pressure Flow Rate and RCIC Automatic Initiation Testing

from 24 Months to 48 Months

Work Orders WO 1659536 Part 21 Issue on 1-1201-2 03/30/2019

WO 4620642 MM Part 21 Action Item for MOV 1-1201-5 in Q1R25 04/01/2019

WO 4690630 Core Flow Calibration 04/09/2019

WO 4907182 RX WTR Cleanup Valve Timing Test (IST) 04/07/2019

71124.06 Calculations Permit Number Liquid Release Permit Report - River Discharge Tank 05/04/2018

2018005

Permit Number Gaseous Release Permit Report - Main Chimney Noble Gas 06/03/2019

2019191 Unit 1+2

Permit Number Gaseous Release Permit Report - Reactor Vent Noble Gas 06/03/2019

2019193 Unit 1

Permit Number Gaseous Release Permit Report 06/04/2019

2019199

Permit Number Gaseous Release Permit Report 06/04/2019

2019201

Permit Number Gaseous Release Permit Report - Reactor Vent Iodine and 06/04/2019

2019203 Particulate Unit 2

Release Report Liquid Release Permit Report - Discharge Bay 05/01/2019

2019004

Miscellaneous CY-QC-170-301 Offsite Dose Calculation Manual Quad Cities Station Units 1 13

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 12

Inspection Type Designation Description or Title or Date

Procedure

CY-QC-110-606 Main Chimney Gaseous & Particulate Sampling 20

CY-QC-120-735 Main Chimney & Reactor Building Vent Noble Gas Release 9

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 10/11/2017

Absorber

04635819-01 Main Chimney Noble Gas Monitor Calibration 03/06/2019

04670696 Service Water Monitor Calibration 12/20/2018

0467582-01 Radwaste Effluent Monitor Calibration 01/04/2019

04876363-01 Reactor Building Vent/Fuel Pool Rad Monitor 02/20/2019

Calibration/Functional Test

71124.07 Corrective Action 04120126 Water Found in Radwaste Piping Vault 03/28/2018

Documents 04136730 REMP 2018 1st Quarter Missing/Anomalies Samples 05/11/2018

202852 REMP Air Sampler Station Found Without Power 12/07/2018

249167 1st Quarter 2019 Missed REMP Samples 05/15/2019

Miscellaneous Quad Cities Nuclear Power Station, Units 1 and 2 Annual 05/10/2019

Radiological Environmental Operation Report

Meteorological Monitoring Program at the Quad Cities 03/21/2019

Nuclear Generating Station January 2019

Meteorological Monitoring Program at the Quad Cities 04/25/2019

Nuclear Generating Station February 2019

Procedures EIML-SPM-1 Sampling Procedures Manual Environmental Incorporated 16

Midwest Laboratory

EN-AA-407 Response to Inadvertent Releases of Licensed Materials to 10

Groundwater, Surface Water, Soil or Engineered Structures

EN-AA-408 Radiological Groundwater Protection Program 0

EN-AA-408-4000 Radiological Groundwater Protection Program 9

Implementation

EN-QC-408-4160 Quad Cities Station Radioactive Groundwater Protective 2

Program Reference Material

71151 Miscellaneous CY-QC-120-720 Actual Dose Data and Supporting Information Package 10/31/2018

through

03/31/2019

Inspection Type Designation Description or Title or Date

Procedure

Procedures CY-QC-120-720 Plant Effluent Dose Calculations 7

71152 Corrective Action IR 3990038 MSIVs 1-0203-1B, 1-0203-1D, 1-0203-2C and 1-0203-2D 03/27/2017

Documents Closure Times Exceeded the Maximum Technical

Specification Limit of <5 Seconds

IR 4116642 MSIVs 2-0203-1A and 2-0203-1C Closure Times Exceeded 03/19/2018

the Maximum Technical Specification Limit of <5 Seconds

IR 4230672 EO ID: 1C RHRSW HP O/B Seal Leaking 03/18/2019

IR 4231463 HPCI Motor Speed Changer Cycling Off of High Speed Stop 03/21/2019

IR 4232959 Bus 19 Main Feed Breaker Failed to Trip During Crosstie 03/26/2019

IR 4233634 Paint Flaking from Refuel Floor Ceiling (FME) 03/27/2019

IR 4234060 Evaluation of Paint Chips that Fell from RB Overhead 03/28/2019

IR 4235733 Rising Trend on PI 2-0262-17D 2B Recirc Pump OB Seal 04/02/2019

Press

IR 4237779 MCR Alarm Not Received on 902-56 Panel 04/09/2019

IR 4238831 1C RHRSW High Pressure Pump OB Seal Leak During Run 04/12/2019

IR 4245286 VT3 of Support M-994D-22 During Q1R26 05/01/2019

IR 4251168 Logic Test Discrepancies and Improvements QCOS 1000-31 05/23/2019

IR 4251706 The U2 A Drywell Rad Monitor (2-2419A) Failed Downscale 05/24/2019

IR 4252249 OOT, RIS 1-2419-A, Trend Code B3 05/28/2019

IR 4258115 U2 A Drywell Radiation Monitor, 2-2419A, Failed 06/19/2019

Downscale

IR 4259369 MRule A1DE Required for CM2400-02, Unit 2 DW Rad 06/25/2019

Monitor

Drawings Drawing M-37 Diagram of RHR Service Water Piping BI

Procedures QCIS 2400-04 Unit 2 Division I Drywell Radiation Monitor Calibration and 8

Functional Test

Work Orders WO 4924935 The Unit 2 A Drywell Rad Monitor Failed Downscale 05/28/2019

71153 Corrective Action ECAPE 4217557 U1 HPCI Failed to Roll During QCOS 2300-27 03/08/2019

Documents

20