IR 05000254/2021010

Design Basis Assurance Inspection (Programs) Inspection Report 05000254/2021010 and 05000265/2021010

ML21328A052
Person / Time
Site:	Quad Cities
Issue date:	11/24/2021
From:	Karla Stoedter NRC/RGN-III/DRS/EB2
To:	Rhoades D Exelon Generation Co, Exelon Nuclear
References
IR 2021010
Download: ML21328A052 (10)

Text

November 24, 2021

SUBJECT:

QUAD CITIES NUCLEAR POWER STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000254/2021010 AND 05000265/2021010

Dear Mr. Rhoades:

On November 18, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Quad Cities Nuclear Power Station and discussed the results of this inspection with Mr. B. Wake, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Signed by Stoedter, Karla on 11/24/21 Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety 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: 05000254/2021010 and 05000265/2021010 Enterprise Identifier: I-2021-010-0057 Licensee: Exelon Generation Company, LLC Facility: Quad Cities Nuclear Power Station Location: Cordova, IL Inspection Dates: November 01, 2021 to November 18, 2021 Inspectors: B. Daley, Senior Reactor Inspector M. Jones, Reactor Inspector B. Jose, Senior Reactor Inspector Approved By: Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at Quad Cities Nuclear Power Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)

The inspectors:

a. Determined whether the sampled power operated valves (POVs) are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.

b. Determined whether the sampled POVs are capable of performing their design-basis functions.

c. Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.

d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).

(1) 1-2301-004-MO; High Pressure Coolant Injection (HPCI) Inboard Steam Supply from Reactor Pressure Vessel (RPV) Primary Containment Isolation Valve (PCIV)

(2) 2-1301-017-MO; Reactor Core Isolation Cooling (RCIC) Turbine Steam Supply from RPV PCIV

(3) 1-1001-026A-MO; Residual Heat Removal (RHR) A Loop Inboard Drywell Spray PCIV

(4) 2-0302-022A-AO; Control Rod Drive Scram Discharge Volume Drain Valve

(5) 2-0203-001A-AO; 1A Inboard Main Steam Isolation Valve

(6) 1-1201-005-MO; Reactor Water Cleanup Outboard PCIV

(7) 2-1001-005B-MO; RHR Service Water B Loop Flow Control Valve

(8) 2-1001-016A-MO; RHR A Loop Heat Exchanger Bypass Line Isolation Valve

(9) 2-2301-005-MO; HPCI Outboard Steam Supply from RPV PCIV

(10) 2-1001-034B-MO; RHR B Loop Torus Cooling and Spray Isolation Valve

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On November 18, 2021, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. B. Wake, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21N.02 Calculations 002N3585 Main Steam Isolation Valve (MSIV) Calculation Bases for 12/03/2014

Minimum Air Supply Pressure

04692920 C Residual Heat Removal (RHR) Service Water Pump 06/18/2019

Comprehensive Test

0591-544-03 Motor Operated Valve (MOV) Accumulator 1-220-82A 0

Capacity Check

27.02000.1100 MOV Structural Integrity Calculation 0

AOV-MEDP- Inboard Main Steam Isolation Valve - Design Basis 0

QDC-RX-002 Calculation Report

AOV-MEDP- Inboard Main Steam Isolation Valve 0

QDC-RX-002

MIDACALC QUA- MIDACALC Results 11

2-1001-5B

NED-M-MSD-075 The Thrust Seismic Limits of the Quad Cities Non-Mark I 0A

MOVs

QC-MISC-010 Quad Cities MOV Risk Ranking Input 003

QDC-0203-M- Main Steam Isolation Valves Sizing Calculation 1

0968

QDC-0203-M- Main Steam Isolation Valve Sizing Calculation 1

0968

QDC-1000-M- Residual Heat Removal System Combined Design Basis 000

1318 Document and Differential Pressure Calculation

QDC-1000-S- Review of Flowserve Seismic and Maximum Thrust 0

27 Analysis Report RAL-20588 for FLowserve 12" Class 300

Carbon Steel Globe Valve with SMB-0-25

QDC-1200-M- Reactor Water Cleanup (RWCU) System Combined 000

1319 Design Basis Document and Differential Pressure

Calculation

QUA-1-1201-5 MIDACALC Results QUA-1-1201-5 14

QUA-2-1001-16A MIDACALC Results QUA-1-1001-16A 7

RAL-70296 Weak Link Supplement to Report R89.124 Analysis of the 03/05/2018

Stem-Wedge Threaded and Pinned Connection

Inspection Type Designation Description or Title Revision or

Procedure Date

Corrective Action 04116815 MO 2-1301-16 Reactor Core Isolation Cooling (RCIC) 04/19/2018

Documents Inboard Valve Local Leak Rate Exceeds Alert Limit

04132420 Main Steam Isolation Valves 2-0203-1A and 2-0203-1C 03/19/2018

Closure Times Exceeded the Maximum Technical

Specification Limit of 5 Seconds

04442618 Power Operated Valve Self-Assessment GAP Discovered 11/01/2021

on 1-1001-26A MIDAS Calculation

Corrective Action 04458885 NRC POV DBAI QUA-2-2301-5, MIDAS Calculation 11/05/2021

Documents Revision

Resulting from 04461879 NRC DBAI POV: SharePoint Issues for External Users 11/18/2021

Inspection

Drawings DR-33834 18" - 300 Pound Cast Steel Globe Valve 09/27/1968

DR-34289 20 Inch Y Pattern Globe Valve 4

M-79 Diagram of RHR Service Water Piping BJ

M-81 Diagram of RHR Piping BL

Miscellaneous LAR Application to Revise Technical Specifications to Adopt 07/26/2016

Technical Specifications Task Force (TSTF)-545

NA Quad Cities Station 180-Day Response to Generic Letter 11/09/1995

(GL) 95-07

Procedures ER-AA-200 Preventive Maintenance Program 6

ER-AA-200-1001 Equipment Classification 6

ER-AA-200-1003 Maintenance Strategy Analysis 1

ER-AA-302-1009 Final Joint Owners Group (JOG) MOV Periodic 3

Verification Program Implementation

MA-AA-716-012 Post Maintenance Testing 25

MA-AA-716-230 Predictive Maintenance Program 12

NES-EIC-10.02 Standard for Thermal Overload Relay Element Selection 0

for Motor Operated Valves

NES-MS-06.6 MOV Valve Factors 2

Work Orders 00587694 Stem Needs Replacement 2-1301-17 01/20/2004

00979119 Perform Mechanical MOV Inspection Only 2-1001-16A 08/01/2011

01010549 Open and Inspect Valve for Corrosion/Erosion 03/05/2008

01126921 Replace MO 2-1001-5B IN Q2R20 12/10/2009

255655 Mechanical Inspection and Stem Lube (MOV) 1-1201-5 02/12/2011

Inspection Type Designation Description or Title Revision or

Procedure Date

01470514 Prog Diagnostic Test - MOV 2-1001-16A PMID 25505-01 10/07/2011

01547997 Perform Static Testing MO 2-1301-17 04/25/2014

01578831 Prog Mechanical Inspection and Stem Lube (MOV) 02/03/2014

01611462 MOV Grease Inspection and Stem Lube 2-1301-17 04/10/2014

01630656 High Pressure Coolant Injection Steam Supply Local Leak 03/02/2015

Rate Test (LLRT)

01722591 Perform Borescope Inspection on MOV 2-1001-16A 12/07/2015

01752229 1A MSIV Air/Hydraulic O/H 10/09/2015

01775693 Program Diagnostic Test 02/06/2016

01794491 RHR B Loop Valve Position Indication 06/12/2016

01819374 HPCI Steam Supply LLRT 03/27/2017

01819403 Prog Mechanical Inspection and Stem Lube (MOV) 07/03/2017

01834738 Program Diagnostic Test 10/15/2016

01908235 RCIC Steam Supply LLRT In-Service Test (IST) 03/19/2018

01908692 MOV Grease Inspection and Stem Lube 2-1001-16A 12/06/2017

01916764 LLRT - Main Steam Isolation Valves (IST) 03/11/2018

01933785 Perform Diagnostic Test MO 2-1001-16A 10/16/2017

01955867 Drywell Valve Position Indication Verification (IST) 04/04/2018

04580778 RHR B Loop Valve Position Indication (IST) 06/12/2018

04620642 Mechanical Maintenance (MM) Part 21 Action Item for 11/08/2018

MOV 1-1201-5 IN Q1R25

0462944 HPCI Low-Medium Risk Power Operated Valve Test 03/22/2019

04682289 Drywell Valve Position Indication Verification (IST) 04/04/2019

04682302 Reactor Water Cleanup (RWCU) Valve Timing Test (IST) 03/21/2019

04687701 Replace Flexible Hose - 'A' Inboard Main Steam Isolation 04/02/2020

Valve

04690786 Electrical Maintenance Perform Diagnostic Test 03/19/2021

MO 1-1201-5

04712364 RWCU System LLRT, (IST) 03/11/2019

0471941 MM Replace Q2R24 2-0203-1A MSIV Airpack Manifold 03/21/2018

04798515 MSIV Closure Time (IST) 03/23/2020

04800217 Drywell Valve Position Indication Verification Test (IST) 04/12/2020

04818043 LLRT - Main Steam Isolation Valves (IST) 03/30/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

04914708 RWCU System LLRT (IST) 03/08/2021

04918468-24 HPCI Preventive Maintenance Tests (PMTs) Required 04/12/2020

Prior to Mode 2

04918468-25 RCIC PMTs Required Prior to Mode 2 04/12/2020

04962559 HPCI Low-Medium Risk Power Operated Valve Test 03/19/2021

0497715 RWCU Valve Timing Test (IST) 03/24/2021

05010921 Lube MO 1-1201-5 Valve Stem 03/15/2021

05073968 RHR A Pump Flow Rate (IST) 11/22/2020

05120452 Scram Discharge Volume (SDV) Vent and Drain Valve 04/21/2021

Test

05140184 Drywell Valve Position Indication Verification 03/29/2021

WO 04750335 RHR Low Risk Power Operated Valve Test 12/12/2019

WO 04829572 RCIC Low-Medium Risk Power Operated Valve Test 04/02/2020

WO 04867443 RHR Low Risk Power Operated Valve Test 05/27/2020

WO 05053088 RHR Low Risk Power Operated Valve Test 10/21/2020

WO 05063982 Scram Discharge Volume (SDV) Vent and Drain Valve 10/21/2020

Test

WO 05090424 SDV Vent and Drain Valve Test 01/19/2021

WO 05120452 SDV Vent and Drain Valve Test 04/21/2021

8