IR 05000254/2019010

Evaluations of Changes, Tests, and Experiments Inspection Report 05000254/2019010 and 05000265/2019010 (DRS-A.Shaikh)

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

February 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

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

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

• EC 406699; Unit 1 Containment Coatings Condition and Deferral of Inspection;

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

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

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

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