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| issue date = 02/13/2019
| issue date = 02/13/2019
| title = Evaluations of Changes, Tests, and Experiments Inspection Report 05000254/2019010 and 05000265/2019010 (DRS-A.Shaikh)
| title = Evaluations of Changes, Tests, and Experiments Inspection Report 05000254/2019010 and 05000265/2019010 (DRS-A.Shaikh)
| author name = Daley R C
| author name = Daley R
| author affiliation = NRC/RGN-III
| author affiliation = NRC/RGN-III
| addressee name = Hanson B C
| addressee name = Hanson B
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000254, 05000265
| docket = 05000254, 05000265
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION Region III 2443 Warrenville Road, Suite 210 Lisle, IL 60532
{{#Wiki_filter:UNITED STATES ary 13, 2019
-4352 February 13, 2019 Mr. Bryan Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville , IL 60555 SUBJECT: QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS INSPECTION REPORT 05000254/2019010 AND 05000265/2019010
 
==SUBJECT:==
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS INSPECTION REPORT 05000254/2019010 AND 05000265/2019010


==Dear Mr. Hanson:==
==Dear Mr. Hanson:==
On January 18, 2019
On January 18, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Quad Cities Nuclear Power Station, Units 1 and 2, and discussed the results of this inspection with Mr. Hal Dodd and other members of your staff. The results of this inspection are documented in the enclosed report.
, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Quad Cities Nuclear Power Station, Units 1 and 2 , and discussed the results of this inspection with Mr. Hal Dodd and other members of your staff.
 
The NRC inspectors did not identify any finding or violation of more-than-minor significance.


The results of this inspection are documented in the enclosed report. The NRC inspectors did not identify any finding or violation of more
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.
-than-minor significance
. 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,
Sincerely,
/RA/ Robert C. Daley, Chief Engineering Branch 3 Docket No s.: 05000254 and 05000265 License No s.: DPR-29 and DPR
/RA/
-30 Enclosure:
Robert C. Daley, Chief Engineering Branch 3 Docket Nos.: 05000254 and 05000265 License Nos.: DPR-29 and DPR-30
I R 05000254/2019010
; 05000265/2019010 cc: Distribution via LISTSERV


ML 19045A 423 OFFICE RIII RIII NAME AShaikh:cl RDaley SIGNATURE DATE 02/11/19 02/13/19 Enclosure U.S. NUCLEAR REGULATORY COMMISSION
===Enclosure:===
IR 05000254/2019010; 05000265/2019010


==Inspection Report==
==Inspection Report==
Docket Number(s):
Docket Number(s): 05000254 and 05000265 License Number(s): DPR-29 and DPR-30 Report Number(s): 05000254/2019010 and 05000265/2019010 Enterprise Identifier: I-2019-010-0035 Licensee: Exelon Generation Company, LLC Facility: Quad Cities Nuclear Power Station, Units 1 and 2 Location: Cordova, IL Inspection Dates: January 14, 2019 to January 18, 2019 Inspectors: M. Domke, Reactor Inspector I. Hafeez, Reactor Inspector A. Shaikh, Senior Reactor Inspector Approved By: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure
05000254 and 05000265 License Number(s):
DPR-29 and DPR
-30 Report Number(s):
05000254/2019010 and 05000265/2019010 Enterprise Identifier:
I-2019-010-0035 Licensee: Exelon Generation Company, LLC Facility: Quad Cities Nuclear Power Station, Units 1 and 2 Location: Cordova, IL Inspection Dates:
January 14, 2019 to January 18, 2019 Inspectors:
M. Domke, Reactor Inspector I. Hafeez, Reactor Inspector A. Shaikh , Senior Reactor Inspector Approved By:
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety
 
2


=SUMMARY=
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensee's performance by conducting a Evaluations of Changes, Tests, and Experiments inspection at Quad Cities Nuclear Power Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Evaluations of Changes, Tests, and Experiments 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.
, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.


No findings or violations were identified.
No findings or violations were identified.


3 TABLE OF CONTENTS
TABLE OF CONTENTS


=INSPECTION SCOPES=
=INSPECTION SCOPES=
................................
................................................................
.............


==REACTOR SAFETY==
==REACTOR SAFETY==
................................
...............................................................................................................
................................................................
...............


==INSPECTION RESULTS==
==INSPECTION RESULTS==
................................
...........................................................................................................
................................................................
...........


==EXIT MEETINGS AND DEBRIEFS==
==EXIT MEETINGS AND DEBRIEFS==
................................
............................................................................................ 5
............................................................
5  


=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=
 
  ........................................................................................................ 5
  ................................................................................................
........ 5
INSPECTION SCOPES
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
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
-rm/doc-collections/insp
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
-manual/inspection
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
-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
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
-Water Reactor Inspection Program - Operations Phase.
complete when the IP requirements most appropriate to the inspection activity were met
"  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.
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.
REACTOR SAFETY
REACTOR SAFETY
71111.17T  
71111.17T - Evaluations of Changes, Tests, and Experiments
- Evaluations of Changes, Tests, and Experiments
2.01 Sample Selection (29 Samples)
2.01 Sample Selection (29 Sample s) The inspectors evaluated the following:
The inspectors evaluated the following:
  (1) QC-S-2016-0028; TSI  
      (1)   QC-S-2016-0028; TSI -Bypass Unit 1 Turbine Rotor Expansion
-Bypass Unit 1 Turbine Rotor Expansion
      (2)   QC-E-2017-001; Updated QDC Dose Calculations to Increase the Core Average
  (2) QC-E-2017-001; Updated QDC Dose Calculations to Increase the Core Average Exposure (CAVEX) Limit
Exposure (CAVEX) Limit
  (3) QC-S-2016-0043; Install Jumper Around Unit 1 Non
      (3)   QC-S-2016-0043; Install Jumper Around Unit 1 Non-Essential 250VDC Battery Cell 45
-Essential 250VDC Battery Cell 45
      (4)   QC-S-2016-0031; Return 2-4601 Service Air Compressor to Original Design and
  (4) QC-S-2016-0031; Return 2
Incorporate Vendor (NEAC) Recommended Upgrades
-4601 Service Air Compressor to Original Design and Incorporate Vendor (NEAC) Recommended Upgrades
      (5)   QC-S-2016-0036; Unit 1 Containment Coatings Condition and Deferral of Inspection
  (5) QC-S-2016-0036; Unit 1 Containment Coatings Condition and Deferral of Inspection
      (6)   QC-S-2017-0025; RHR Pump/Loop Operability Test
  (6) QC-S-2017-0025; RHR Pump/Loop Operability Test
      (7)   QC-S-2017-0026; Removing the Actuator from the 1-5772-32A Damper and Gagging
  (7) QC-S-2017-0026; Removing the Actuator from the 1
the Damper in the Open or Closed Position
-5772-32A Damper and Gagging the Damper in the Open or Closed Position
      (8)   QC-S-2017-0029; Update Procedures and Calculation QDC-1000-M-0131 for Unit 0
  (8) QC-S-2017-0029; Update Procedures and Calculation QDC-1000-M-0131 for Unit 0 DGCW Upper Flow Limit
DGCW Upper Flow Limit
  (9) QC-S-2017-0053; Return 1
      (9)   QC-S-2017-0053; Return 1-3999-56 to Normal Open Position by Installing a Disc Lifting
-3999-56 to Normal Open Position by Installing a Disc Lifting Gag to Mitigate Stem
Gag to Mitigate Stem-Disc Separation Problem
-Disc Separation Problem
      (10)   QC-S-2017-0079; Replace SBLC Tank Heater Controller TIC 1(2)-1154
  (10) QC-S-2017-0079; Replace SBLC Tank Heater Controller TIC 1(2)-1154 (11) QC-S-2018-0038; Diesel Generator Cooling Water Pump Flow Rate Test
      (11)   QC-S-2018-0038; Diesel Generator Cooling Water Pump Flow Rate Test
  (12) QC-S-2017-0002; 345KV Switchyard Line L0401 System 1 Relay Protection Upgrade
      (12)   QC-S-2017-0002; 345KV Switchyard Line L0401 System 1 Relay Protection Upgrade
  (13) QC-S-2017-0007; Temp Power For HRSS Valves 1
      (13)   QC-S-2017-0007; Temp Power For HRSS Valves 1-8941-727/728/729/701 During
-8941-727/728/729/701 During Q1R24 (14) QC-S-2017-0008; Provide Temp Power Feed To U1 TB Lighting During Q1R24 When Bus 15 is OOS
Q1R24
  (15) QC-S-2017-0010; Reactor Recirc Pump Motor Lube Oil Level Indication
      (14)   QC-S-2017-0008; Provide Temp Power Feed To U1 TB Lighting During Q1R24 When
-Unit 1 (16) QC-S-2017-0011; Provide Temp Power For EDG Equipment Associated with Bus 15 OOS (17) QC-S-2017-0014; 345KV Bus Tie (BT) 3
Bus 15 is OOS
-4 Gas Circuit Breaker (GCB) Replacement
      (15)   QC-S-2017-0010; Reactor Recirc Pump Motor Lube Oil Level Indication-Unit 1
  (18) QC-S-2017-0022; Perform Field Mod of HU
      (16)   QC-S-2017-0011; Provide Temp Power For EDG Equipment Associated with Bus 15
-1 for 2nd Harmonic Restraint From 15% to 7.5% (19) QC-S-2017-0022; Operation of Transformer Severon Monitors for
OOS
Maintenance
      (17)   QC-S-2017-0014; 345KV Bus Tie (BT) 3-4 Gas Circuit Breaker (GCB) Replacement
  (20) QC-S-2017-0033; Temporarily Isolate Turbine Bearing #* Deluge Detector to Remove Ground Fault Alarm
      (18)   QC-S-2017-0022; Perform Field Mod of HU-1 for 2nd Harmonic Restraint From 15% to
  (21) QC-S-2017-0059; Reactor Recirc Pump Motor Lube Oil Level Indication
7.5%
-Unit 2
      (19)   QC-S-2017-0022; Operation of Transformer Severon Monitors for Maintenance
(22) QC-S-2018-0015; 345KV Switchyard Line L0404 MOD
      (20)   QC-S-2017-0033; Temporarily Isolate Turbine Bearing #* Deluge Detector to Remove
and Stability Scheme Upgrade
Ground Fault Alarm
  (23) QC-E-2017-002; Perform 50.59 Evaluation of UFSAR Change in Accordance with Recommendation of
      (21)   QC-S-2017-0059; Reactor Recirc Pump Motor Lube Oil Level Indication-Unit 2
IR 01418982
      (22) QC-S-2018-0015; 345KV Switchyard Line L0404 MOD and Stability Scheme Upgrade
  (24) QC-S-2016-0029; H2 Area Leak Detectors Set Point Change
      (23) QC-E-2017-002; Perform 50.59 Evaluation of UFSAR Change in Accordance with
  (25) QC-S-2016-0030; Structural Analysis of the Quad Cities Low Profile Transporter
Recommendation of IR 01418982
  (26) QC-S-2017-0089; Lifting Devices for the 2B Core Spray Motor Replacement
      (24) QC-S-2016-0029; H2 Area Leak Detectors Set Point Change
  (27) QC-S--2017-0078; Perform Field MODs of HU
      (25) QC-S-2016-0030; Structural Analysis of the Quad Cities Low Profile Transporter
-1 Relays for 2nd Harmonic Restraint From 15% to 7.5%
      (26) QC-S-2017-0089; Lifting Devices for the 2B Core Spray Motor Replacement
  (28) QC-S-2016-0042; Revise Outdated UFSAR Description of Reactor Building Penetration Seal Material  
      (27) QC-S--2017-0078; Perform Field MODs of HU-1 Relays for 2nd Harmonic Restraint
  (29) QC-S-2018-0046;Technical Support Center (TSC) HVAC Upgrade
From 15% to 7.5%
      (28) QC-S-2016-0042; Revise Outdated UFSAR Description of Reactor Building Penetration
Seal Material
      (29) QC-S-2018-0046;Technical Support Center (TSC) HVAC Upgrade
INSPECTION RESULTS
INSPECTION RESULTS
No findings of significance were identified.
No findings of significance were identified.
EXIT MEETINGS AND DEBRIE
EXIT MEETINGS AND DEBRIEFS
FS  The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
The inspectors confirmed that proprietary information was controlled to protect from public
On January 18, 2019, the inspector presented the Evaluations of Changes, Tests, and Experiments
disclosure.
inspection results to Mr. Hal Dodd and other members of the licensee staff.
    *  On January 18, 2019, the inspector presented the Evaluations of Changes, Tests, and
Experiments inspection results to Mr. Hal Dodd and other members of the licensee staff.
DOCUMENTS REVIEWED
DOCUMENTS REVIEWED
QC-S-2016-0028; TSI  
    *  QC-S-2016-0028; TSI -Bypass Unit 1 Turbine Rotor Expansion; Revision 0
-Bypass Unit 1 Turbine Rotor Expansion; Revision 0
    *  QC-S-2016-0031; Return 2-4601 Service Air Compressor to Original Design and
QC-S-2016-0031; Return 2
Incorporate Vendor (NEAC) Recommended Upgrades; Revision 0
-4601 Service Air Compressor to Original Design and Incorporate Vendor (NEAC) Recommended Upgrades; Revision
    *  QC-S-2016-0036; Unit 1 Containment Coatings Condition and Deferral of Inspection;
QC-S-2016-0036; Unit 1 Containment Coatings Condition and Deferral of Inspection; Revision 0
Revision 0
QC-S-2017-0025; RHR Pump/Loop Operability Test; Revision 0
    *  QC-S-2017-0025; RHR Pump/Loop Operability Test; Revision 0
QC-S-2017-0026; Removing the Actuator from the 1
    *  QC-S-2017-0026; Removing the Actuator from the 1-5772-32A Damper and Gagging
-5772-32A Damper and Gagging the Damper in the Open or
the Damper in the Open or Closed Position; Revision 0
Closed Position; Revision 0
    *  QC-S-2017-0029; Update Procedures and Calculation QDC-1000-M-0131 for Unit 0
QC-S-2017-0029; Update Procedures and Calculation QDC
DGCW Upper Flow Limit; Revision 0
-1000-M-0131 for Unit 0 DGCW Upper Flow Limit; Revision 0
    *  QC-S-2017-0053; Return 1-3999-56 to Normal Open Position by Installing a Disc Lifting
QC-S-2017-0053; Return 1
Gag to Mitigate Stem-Disc Separation Problem; Revision 0
-3999-56 to Normal Open Position by Installing a Disc Lifting Gag to Mitigate Stem
    *  QC-S-2017-0079; Replace SBLC Tank Heater Controller TIC 1(2)-1154; Revision 0
-Disc Separation Problem; Revision 0
    *  QC-S-2018-0038; Diesel Generator Cooling Water Pump Flow Rate Test; Revision 0
QC-S-2017-0079; Replace SBLC Tank Heater Controller TIC 1(2)
    *  ECR 428527; Provide Input to Procedure Change on QCOS 1000-06; 04/11/2017
-1154; Revision 0
    *  ECR 48466; Develop Suction Head Pressure/Cavitation Limit for QCOS 1000-06;
QC-S-2018-0038; Diesel Generator Cooling Water Pump Flow Rate Test; Revision 0
2/25/1998
ECR 428527; Provide Input to Procedure Change on QCOS 1000
    *  ECR 436259; Document the Basis for Moving the QCOS 6600-06 DGWP NPSH Limit;
-06; 04/11/201
07/31/2018
ECR 48466; Develop Suction Head Pressure/Cavitation Limit for QCOS 1000
    *  EC 404993; Updated QDC Dose Calculations to Increase the Core Average Exposure
-06; 02/25/1998
        (CAVEX) Limit
ECR 436259; Document the Basis for Moving the QCOS 6600
    *  EC 619709; Return 1-3999-56 Valve to Normal Open Position by Installing a Disc Lifting
-06 DGWP NPSH Limit; 07/31/2018
Gag to Mitigate Stem Disc Separation Problem; 08/02/2017
EC 404993; Updated QDC Dose Calculations to Increase the Core Average Exposure  
* EC 406699; Unit 1 Containment Coatings Condition and Deferral of Inspection;
(CAVEX) Limit
10/06/2016
EC 619709; Return 1
* ER-AA-330-008; Exelon Safety-Related (Service Level I) Protective Coatings;
-3999-56 Valve to Normal Open Position by Installing a Disc Lifting Gag to Mitigate Stem Disc Separation Problem; 08/02/2017
Revision 12
 
* ER-QC-330-1000; Primary Containment and Coatings Inspection; Revision 7
EC 406699; Unit 1 Containment Coatings Condition and Deferral of Inspection; 10/06/2016
* QDC-1000-M-0131; NPSH Availability vs. Requirements for DGCW and RHRSW
ER-AA-330-008; Exelon Safety
Pumps; Revision 4
-Related (Service Level I) Protective Coatings; Revision 12 ER-QC-330-1000; Primary Containment and Coatings Inspection; Revision 7
* CWE097.0200.40; Base Suppression Pool Level Required for Proper Operation of the
QDC-1000-M-0131; NPSH Availability vs. Requirements for DGCW and RHRSW Pumps; Revision 4
RHR/LPCI and Core Spray Pumps During Plant Cold Shutdown and Refueling
CWE097.0200.40; Base Suppression Pool Level Required for Proper Operation of the RHR/LPCI and Core Spray Pumps During Plant Cold Shutdown and Refueling Conditions; Revision 0
Conditions; Revision 0
CWE097.0200.41; Minimum Suppression Pool Water Level Required During Cold Shutdown and Refueling Conditions; Revision 0
* CWE097.0200.41; Minimum Suppression Pool Water Level Required During Cold
IR 4036334; NOS ID: 50.59 Screening Weaknesses Noted; 07/27/2017
Shutdown and Refueling Conditions; Revision 0
IR 4158916; EO ID: 1
* IR 4036334; NOS ID: 50.59 Screening Weaknesses Noted; 07/27/2017
-4601-B, Service Air Compressor Leak; 07/26/2018
* IR 4158916; EO ID: 1-4601-B, Service Air Compressor Leak; 07/26/2018
QC-S-2016-0043; Install Jumper Around Unit 1 Non
* QC-S-2016-0043; Install Jumper Around Unit 1 Non-Essential 250VDC Battery Cell 45;
-Essential 250VDC Battery Cell 45; Revisio n 0 QC-S-2017-0002; 345KV Switchyard Line L0401 System 1 Relay Protection Upgrade; Revision 0
Revision 0
QC-S-2017-0007; Temp Power For HRSS Valves 1
* QC-S-2017-0002; 345KV Switchyard Line L0401 System 1 Relay Protection Upgrade;
-8941-727/728/729/701 During Q1R24; Revision 1
Revision 0
QC-S-2017-0008; Provide Temp Power Feed To U1 TB Lighting During Q1R24 When Bus 15 is OOS; Revision 0
* QC-S-2017-0007; Temp Power For HRSS Valves 1-8941-727/728/729/701 During
QC-S-2017-0010; Reactor Recirc Pump Motor Lube Oil Level Indication
Q1R24; Revision 1
-Unit 1; Revision 0 QC-S-2017-0011; Provide Temp Power For EDG Equipment Associated with Bus 15 OOS; Revision 0
* QC-S-2017-0008; Provide Temp Power Feed To U1 TB Lighting During Q1R24 When
QC-S-2017-0014; 345KV Bus Tie (BT) 3
Bus 15 is OOS; Revision 0
-4 Gas Circuit Breaker (GCB) Replacement; Revision 0
* QC-S-2017-0010; Reactor Recirc Pump Motor Lube Oil Level Indication-Unit 1;
QC-S-2017-0022; Perform Field Mod of HU
Revision 0
-1 for 2nd Harmonic Restraint From 15% to 7.5%; Revision 0
* QC-S-2017-0011; Provide Temp Power For EDG Equipment Associated with Bus 15
QC-S-2017-0022; Operation of Transformer Severon Monitors for Maintenance; Revision 0
OOS; Revision 0
QC-S-2017-0033; Temporarily Isolate Turbine Bearing #* Deluge Detector to Remove Ground Fault Alarm; Revision 0
* QC-S-2017-0014; 345KV Bus Tie (BT) 3-4 Gas Circuit Breaker (GCB) Replacement;
QC-S-2017-0059; Reactor Recirc Pump Motor Lube Oil Level Indication
Revision 0
-Unit 2; Revision 0 QC-S-2018-0015; 345KV Switchyard Line L0404 MOD and Stability Scheme Upgrade; Revisio n 1 IR 02682387; 50.59 Screening Records Retention  
* QC-S-2017-0022; Perform Field Mod of HU-1 for 2nd Harmonic Restraint From 15% to
- Scaffolds > 90 Days; 06/16/2016
7.5%; Revision 0
IR 04077416; Obsolete RHR, ADS & CREV Relays Require DCP For Replacement; 11/22/2017
* QC-S-2017-0022; Operation of Transformer Severon Monitors for Maintenance;
QC-E-2017-002; Perform 50.59 Evaluation of UFSAR Change in Accordance with Recommendation of IR 01418982
Revision 0
QC-S-2016-0029; H2 Area Leak Detectors Set Point Change
* QC-S-2017-0033; Temporarily Isolate Turbine Bearing #* Deluge Detector to Remove
QC-S-2016-0030; Structural Analysis of the Quad Cities Low Profile Transporter
Ground Fault Alarm; Revision 0
QC-S-2017-0089; Lifting Devices for the 2B Core Spray Motor Replacement
* QC-S-2017-0059; Reactor Recirc Pump Motor Lube Oil Level Indication-Unit 2;
QC-S--2017-0078; Perform Field
Revision 0
MODs of HU
* QC-S-2018-0015; 345KV Switchyard Line L0404 MOD and Stability Scheme Upgrade;
-1 Relays for 2nd Harmonic Restraint From 15% to 7.5%
Revision 1
 
* IR 02682387; 50.59 Screening Records Retention - Scaffolds > 90 Days; 06/16/2016
QC-S-2016-0042; Revise Outdated UFSAR Description of Reactor Building Penetration Seal Material
* IR 04077416; Obsolete RHR, ADS & CREV Relays Require DCP For Replacement;
QC-S-2018-0046;Technical Support Center (TSC) HVAC Upgrade
11/22/2017
IR02676983; MODA/50.59 CISA DEF  
* QC-E-2017-002; Perform 50.59 Evaluation of UFSAR Change in Accordance with
- 50.59 Screening Records Retention
Recommendation of IR 01418982
GE-NE-A22-00103-56-01-Q; Appendix R Fire Protection Extended Power Uprate; Revision 0C
* QC-S-2016-0029; H2 Area Leak Detectors Set Point Change
QDC-0030-S-2306; Evaluation of New 5 Ton Trolley Beam and IP Turbine Building Steel at Elevation 611'
* QC-S-2016-0030; Structural Analysis of the Quad Cities Low Profile Transporter
-6" in Support of the 2B Core Spray Motor Replacement; Revision 9
* QC-S-2017-0089; Lifting Devices for the 2B Core Spray Motor Replacement
EC 395566; Evaluation of GODWIN DPC300 Pump Capacity to Provide Sufficient Makeup Flow to the Ultimate Heat Sink; Revision 1
* QC-S--2017-0078; Perform Field MODs of HU-1 Relays for 2nd Harmonic Restraint
QDC-0000-N-1481; Quad Cities Units 1 and 2 Post LOCA EAB, LPZ, and CR Dose - AST Analysis; Revision
From 15% to 7.5%
HI-2114950; Structural Analysis of the Quad Cities Low Profile Transporter; Revision 001A QCAP 1500-02; Administrative Technical Requirements for Non
* QC-S-2016-0042; Revise Outdated UFSAR Description of Reactor Building Penetration
-Functional Safe Shutdown Equipment; Revision 35
Seal Material
EC 620686; Lifting Devices for the 2B Core Spray Motor Replacement; Revision 1
* QC-S-2018-0046;Technical Support Center (TSC) HVAC Upgrade
* IR02676983; MODA/50.59 CISA DEF - 50.59 Screening Records Retention
* GE-NE-A22-00103-5601-Q; Appendix R Fire Protection Extended Power Uprate;
Revision 0C
* QDC-0030-S-2306; Evaluation of New 5 Ton Trolley Beam and IP Turbine Building Steel
at Elevation 611-6 in Support of the 2B Core Spray Motor Replacement; Revision 9
* EC 395566; Evaluation of GODWIN DPC300 Pump Capacity to Provide Sufficient
Makeup Flow to the Ultimate Heat Sink; Revision 1
* QDC-0000-N-1481; Quad Cities Units 1 and 2 Post LOCA EAB, LPZ, and CR
Dose - AST Analysis; Revision 2
* HI-2114950; Structural Analysis of the Quad Cities Low Profile Transporter;
Revision 001A
* QCAP 1500-02; Administrative Technical Requirements for Non-Functional Safe
Shutdown Equipment; Revision 35
* EC 620686; Lifting Devices for the 2B Core Spray Motor Replacement; Revision 1
7
}}
}}

Latest revision as of 05:28, 2 November 2019

Evaluations of Changes, Tests, and Experiments Inspection Report 05000254/2019010 and 05000265/2019010 (DRS-A.Shaikh)
ML19045A423
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 02/13/2019
From: Robert Daley
NRC/RGN-III
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
References
IR 2019010
Download: ML19045A423 (9)
v • d • e


Text

UNITED STATES ary 13, 2019

SUBJECT:

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS INSPECTION REPORT 05000254/2019010 AND 05000265/2019010

Dear Mr. Hanson:

On January 18, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Quad Cities Nuclear Power Station, Units 1 and 2, and discussed the results of this inspection with Mr. Hal Dodd and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more-than-minor significance.

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/

Robert C. Daley, Chief Engineering Branch 3 Docket Nos.: 05000254 and 05000265 License Nos.: DPR-29 and DPR-30

Enclosure:

IR 05000254/2019010; 05000265/2019010

Inspection Report

Docket Number(s): 05000254 and 05000265 License Number(s): DPR-29 and DPR-30 Report Number(s): 05000254/2019010 and 05000265/2019010 Enterprise Identifier: I-2019-010-0035 Licensee: Exelon Generation Company, LLC Facility: Quad Cities Nuclear Power Station, Units 1 and 2 Location: Cordova, IL Inspection Dates: January 14, 2019 to January 18, 2019 Inspectors: M. Domke, Reactor Inspector I. Hafeez, Reactor Inspector A. Shaikh, Senior Reactor Inspector Approved By: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Evaluations of Changes, Tests, and Experiments 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.

No findings or violations were identified.

TABLE OF CONTENTS

INSPECTION SCOPES

REACTOR SAFETY

...............................................................................................................

INSPECTION RESULTS

...........................................................................................................

EXIT MEETINGS AND DEBRIEFS

............................................................................................ 5

DOCUMENTS REVIEWED

........................................................................................................ 5

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.

REACTOR SAFETY

71111.17T - Evaluations of Changes, Tests, and Experiments

2.01 Sample Selection (29 Samples)

The inspectors evaluated the following:

(1) QC-S-2016-0028; TSI -Bypass Unit 1 Turbine Rotor Expansion

(2) QC-E-2017-001; Updated QDC Dose Calculations to Increase the Core Average

Exposure (CAVEX) Limit

(3) QC-S-2016-0043; Install Jumper Around Unit 1 Non-Essential 250VDC Battery Cell 45

(4) QC-S-2016-0031; Return 2-4601 Service Air Compressor to Original Design and

Incorporate Vendor (NEAC) Recommended Upgrades

(5) QC-S-2016-0036; Unit 1 Containment Coatings Condition and Deferral of Inspection

(6) QC-S-2017-0025; RHR Pump/Loop Operability Test

(7) QC-S-2017-0026; Removing the Actuator from the 1-5772-32A Damper and Gagging

the Damper in the Open or Closed Position

(8) QC-S-2017-0029; Update Procedures and Calculation QDC-1000-M-0131 for Unit 0

DGCW Upper Flow Limit

(9) QC-S-2017-0053; Return 1-3999-56 to Normal Open Position by Installing a Disc Lifting

Gag to Mitigate Stem-Disc Separation Problem

(10) QC-S-2017-0079; Replace SBLC Tank Heater Controller TIC 1(2)-1154

(11) QC-S-2018-0038; Diesel Generator Cooling Water Pump Flow Rate Test

(12) QC-S-2017-0002; 345KV Switchyard Line L0401 System 1 Relay Protection Upgrade

(13) QC-S-2017-0007; Temp Power For HRSS Valves 1-8941-727/728/729/701 During

Q1R24

(14) QC-S-2017-0008; Provide Temp Power Feed To U1 TB Lighting During Q1R24 When

Bus 15 is OOS

(15) QC-S-2017-0010; Reactor Recirc Pump Motor Lube Oil Level Indication-Unit 1

(16) QC-S-2017-0011; Provide Temp Power For EDG Equipment Associated with Bus 15

OOS

(17) QC-S-2017-0014; 345KV Bus Tie (BT) 3-4 Gas Circuit Breaker (GCB) Replacement

(18) QC-S-2017-0022; Perform Field Mod of HU-1 for 2nd Harmonic Restraint From 15% to

7.5%

(19) QC-S-2017-0022; Operation of Transformer Severon Monitors for Maintenance

(20) QC-S-2017-0033; Temporarily Isolate Turbine Bearing #* Deluge Detector to Remove

Ground Fault Alarm

(21) QC-S-2017-0059; Reactor Recirc Pump Motor Lube Oil Level Indication-Unit 2

(22) QC-S-2018-0015; 345KV Switchyard Line L0404 MOD and Stability Scheme Upgrade

(23) QC-E-2017-002; Perform 50.59 Evaluation of UFSAR Change in Accordance with

Recommendation of IR 01418982

(24) QC-S-2016-0029; H2 Area Leak Detectors Set Point Change

(25) QC-S-2016-0030; Structural Analysis of the Quad Cities Low Profile Transporter

(26) QC-S-2017-0089; Lifting Devices for the 2B Core Spray Motor Replacement

(27) QC-S--2017-0078; Perform Field MODs of HU-1 Relays for 2nd Harmonic Restraint

From 15% to 7.5%

(28) QC-S-2016-0042; Revise Outdated UFSAR Description of Reactor Building Penetration

Seal Material

(29) QC-S-2018-0046;Technical Support Center (TSC) HVAC Upgrade

INSPECTION RESULTS

No findings of significance were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public

disclosure.

  • On January 18, 2019, the inspector presented the Evaluations of Changes, Tests, and

Experiments inspection results to Mr. Hal Dodd and other members of the licensee staff.

DOCUMENTS REVIEWED

  • QC-S-2016-0028; TSI -Bypass Unit 1 Turbine Rotor Expansion; Revision 0
  • QC-S-2016-0031; Return 2-4601 Service Air Compressor to Original Design and

Incorporate Vendor (NEAC) Recommended Upgrades; Revision 0

  • QC-S-2016-0036; Unit 1 Containment Coatings Condition and Deferral of Inspection;

Revision 0

  • QC-S-2017-0025; RHR Pump/Loop Operability Test; Revision 0
  • QC-S-2017-0026; Removing the Actuator from the 1-5772-32A Damper and Gagging

the Damper in the Open or Closed Position; Revision 0

  • QC-S-2017-0029; Update Procedures and Calculation QDC-1000-M-0131 for Unit 0

DGCW Upper Flow Limit; Revision 0

  • QC-S-2017-0053; Return 1-3999-56 to Normal Open Position by Installing a Disc Lifting

Gag to Mitigate Stem-Disc Separation Problem; Revision 0

  • QC-S-2017-0079; Replace SBLC Tank Heater Controller TIC 1(2)-1154; Revision 0
  • QC-S-2018-0038; Diesel Generator Cooling Water Pump Flow Rate Test; Revision 0
  • ECR 428527; Provide Input to Procedure Change on QCOS 1000-06; 04/11/2017
  • ECR 48466; Develop Suction Head Pressure/Cavitation Limit for QCOS 1000-06;

2/25/1998

  • ECR 436259; Document the Basis for Moving the QCOS 6600-06 DGWP NPSH Limit;

07/31/2018

  • EC 404993; Updated QDC Dose Calculations to Increase the Core Average Exposure

(CAVEX) Limit

  • EC 619709; Return 1-3999-56 Valve to Normal Open Position by Installing a Disc Lifting

Gag to Mitigate Stem Disc Separation Problem; 08/02/2017

10/06/2016

Revision 12

  • QDC-1000-M-0131; NPSH Availability vs. Requirements for DGCW and RHRSW

Pumps; Revision 4

  • CWE097.0200.40; Base Suppression Pool Level Required for Proper Operation of the

RHR/LPCI and Core Spray Pumps During Plant Cold Shutdown and Refueling

Conditions; Revision 0

  • CWE097.0200.41; Minimum Suppression Pool Water Level Required During Cold

Shutdown and Refueling Conditions; Revision 0

  • IR 4036334; NOS ID: 50.59 Screening Weaknesses Noted; 07/27/2017
  • IR 4158916; EO ID: 1-4601-B, Service Air Compressor Leak; 07/26/2018
  • QC-S-2016-0043; Install Jumper Around Unit 1 Non-Essential 250VDC Battery Cell 45;

Revision 0

  • QC-S-2017-0002; 345KV Switchyard Line L0401 System 1 Relay Protection Upgrade;

Revision 0

  • QC-S-2017-0007; Temp Power For HRSS Valves 1-8941-727/728/729/701 During

Q1R24; Revision 1

  • QC-S-2017-0008; Provide Temp Power Feed To U1 TB Lighting During Q1R24 When

Bus 15 is OOS; Revision 0

  • QC-S-2017-0010; Reactor Recirc Pump Motor Lube Oil Level Indication-Unit 1;

Revision 0

  • QC-S-2017-0011; Provide Temp Power For EDG Equipment Associated with Bus 15

OOS; Revision 0

  • QC-S-2017-0014; 345KV Bus Tie (BT) 3-4 Gas Circuit Breaker (GCB) Replacement;

Revision 0

  • QC-S-2017-0022; Perform Field Mod of HU-1 for 2nd Harmonic Restraint From 15% to

7.5%; Revision 0

  • QC-S-2017-0022; Operation of Transformer Severon Monitors for Maintenance;

Revision 0

  • QC-S-2017-0033; Temporarily Isolate Turbine Bearing #* Deluge Detector to Remove

Ground Fault Alarm; Revision 0

  • QC-S-2017-0059; Reactor Recirc Pump Motor Lube Oil Level Indication-Unit 2;

Revision 0

Revision 1

  • IR 02682387; 50.59 Screening Records Retention - Scaffolds > 90 Days; 06/16/2016

11/22/2017

  • QC-E-2017-002; Perform 50.59 Evaluation of UFSAR Change in Accordance with

Recommendation of IR 01418982

  • QC-S-2016-0029; H2 Area Leak Detectors Set Point Change
  • QC-S-2016-0030; Structural Analysis of the Quad Cities Low Profile Transporter
  • QC-S-2017-0089; Lifting Devices for the 2B Core Spray Motor Replacement
  • QC-S--2017-0078; Perform Field MODs of HU-1 Relays for 2nd Harmonic Restraint

From 15% to 7.5%

  • QC-S-2016-0042; Revise Outdated UFSAR Description of Reactor Building Penetration

Seal Material

  • IR02676983; MODA/50.59 CISA DEF - 50.59 Screening Records Retention
  • GE-NE-A22-00103-5601-Q; Appendix R Fire Protection Extended Power Uprate;

Revision 0C

  • QDC-0030-S-2306; Evaluation of New 5 Ton Trolley Beam and IP Turbine Building Steel

at Elevation 611-6 in Support of the 2B Core Spray Motor Replacement; Revision 9

  • EC 395566; Evaluation of GODWIN DPC300 Pump Capacity to Provide Sufficient

Makeup Flow to the Ultimate Heat Sink; Revision 1

  • QDC-0000-N-1481; Quad Cities Units 1 and 2 Post LOCA EAB, LPZ, and CR

Dose - AST Analysis; Revision 2

  • HI-2114950; Structural Analysis of the Quad Cities Low Profile Transporter;

Revision 001A

  • QCAP 1500-02; Administrative Technical Requirements for Non-Functional Safe

Shutdown Equipment; Revision 35

7

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