IR 05000254/2019010: Difference between revisions
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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 | | author name = Daley R | ||
| author affiliation = NRC/RGN-III | | author affiliation = NRC/RGN-III | ||
| addressee name = Hanson B | | 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 | {{#Wiki_filter: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 | ==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. | |||
-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. | |||
-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, | |||
. | |||
Sincerely, | Sincerely, | ||
/RA/ Robert C. Daley, Chief Engineering Branch 3 Docket | /RA/ | ||
-30 | 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== | ==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 | |||
=SUMMARY= | =SUMMARY= | ||
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the | 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 | |||
No findings or violations were identified. | No findings or violations were identified. | ||
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 | ||
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, | 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 | ||
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 | The inspectors evaluated the following: | ||
(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 | ||
Exposure (CAVEX) Limit | |||
(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 | ||
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 | ||
(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 | |||
-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 | |||
-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 | ||
(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 | |||
-8941-727/728/729/701 During Q1R24 | Q1R24 | ||
(14) QC-S-2017-0008; Provide Temp Power Feed To U1 TB Lighting During Q1R24 When | |||
-Unit 1 | 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 | ||
(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% | OOS | ||
Maintenance | (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% | |||
-Unit 2 | (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 | |||
and Stability Scheme Upgrade | Ground Fault Alarm | ||
(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 | ||
(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 | |||
-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 | ||
(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 | INSPECTION RESULTS | ||
No findings of significance were identified. | No findings of significance were identified. | ||
EXIT MEETINGS AND | EXIT MEETINGS AND DEBRIEFS | ||
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/ | 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; | (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 | * 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; | 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-2017-0008; 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-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- | * 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 | * 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 | * 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 06:28, 2 November 2019
ML19045A423 | |
Person / Time | |
---|---|
Site: | Quad Cities ![]() |
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) | |
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
(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
07/31/2018
(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
- ER-AA-330-008; Exelon Safety-Related (Service Level I) Protective Coatings;
Revision 12
- ER-QC-330-1000; Primary Containment and Coatings Inspection; Revision 7
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
- QC-S-2018-0015; 345KV Switchyard Line L0404 MOD and Stability Scheme Upgrade;
Revision 1
- IR 02682387; 50.59 Screening Records Retention - Scaffolds > 90 Days; 06/16/2016
- IR 04077416; Obsolete RHR, ADS & CREV Relays Require DCP For Replacement;
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
- 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
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