IR 05000373/2021011

County Station - Design Basis Assurance Inspection (Programs) Inspection Report 05000373/2021011 and 05000374/2021011

ML21232A036
Person / Time
Site:	LaSalle
Issue date:	08/23/2021
From:	Karla Stoedter NRC/RGN-III/DRS/EB2
To:	Rhoades D Exelon Generation Co
References
IR 2021011
Download: ML21232A036 (12)

Text

August 23, 2021

SUBJECT:

LASALLE COUNTY STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000373/2021011 AND 05000374/2021011

Dear Mr. Rhoades:

On July 15, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at LaSalle County Station and discussed the results of this inspection with Mr. J. Washko, 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 08/23/21 Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 05000373 and 05000374 License Nos. NPF-11 and NPF-18

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000373 and 05000374 License Numbers: NPF-11 and NPF-18 Report Numbers: 05000373/2021011 and 05000374/2021011 Enterprise Identifier: I-2021-011-0035 Licensee: Exelon Generation Company, LLC Facility: LaSalle County Station Location: Marseilles, IL Inspection Dates: June 14, 2021 to July 16, 2021 Inspectors: J. Corujo-Sandin, Senior Reactor Inspector M. Farnan, Mechanical Engineer J. Park, 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 LaSalle County 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. Evaluate maintenance activities including a walkdown of the sampled POVs (if accessible).

(1) 1B21-F013S; 'B' Main Steam Line Safety Relief Valve with Automatic Depressurization System

(2) 1E12-F042B; 'B' Residual Heat Removal Low Pressure Coolant Injection (LPCI)

Injection Line Isolation Valve

(3) 1E12-F068B; 'B' Residual Heat Removal Heat Exchanger Service Water Outlet Valve

(4) 1E22-F004; High Pressure Core Spray Injection Isolation Valve

(5) 1E51-F008; Reactor Core Isolation Cooling Steam Supply Outboard Isolation Valve

(6) 2E12-F004B; 'B' Residual Heat Removal Pump Suppression Pool Suction Isolation Valve

(7) 2E12-F016B; 'B' Residual Heat Removal Containment Spray Upstream Isolation Valve

(8) 2E51-F063; Reactor Core Isolation Cooling Steam Supply Inboard Isolation Valve

(9) 2G33-F040; Reactor Water Cleanup Return to Feedwater Stop Valve

(10) 2VQ026; Suppression Chamber Vent/Purge Inlet Upstream 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 July 15, 2021, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. J. Washko, 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 CE-LS-003 Calculation for Stem Allowable Load Limits for Motor 9

Operated Valves

L-000175 LaSalle Stations Unit 1 & 2 RCIC MOV Differential 0 and 01A

Pressure Calculations

L-002678 Design Calculations for MS Safety Relief Valves (ASME 0

Stress Report), Crosby Report No. 3012

L-002763 SRV Flexi-Disk Qualification (Anderson, Greenwood, 0

Crosby Engineering Calculation EC-2014)

L-002850 High Pressure Core Spray System Motor Operated Valve 1

Differential Pressure Calculation

L-003263 Volume Requirements for ADS Back-Up Compressed Gas 3, 3A, and

System (Bottle Banks) 3B

L-004226 Weak Link Analyses for Anchor Darling Double Disc Gate 0

Valves

LADP 002-M-046 RHR System MOV DP Calculation 03/11/1994

LAS-1E12-F042B Minimum Required Thrust/Torque for 1E12-F042B 9

MIDACALC R9

LAS-1E12-F068B Minimum Required Thrust/Torque for 1E12-F068B 9

MIDACALC R9

LAS-1E22-F004 MIDACALC Results LAS-1E22-F004 (LAS-1) 9

LAS-2E12-F004B Minimum Required Thrust/Torque for 2E12-F004B 8

MIDACALC

LAS-2E12-F016B Minimum Required Thrust/Torque for 2E12-F016B 8

MIDACALC

LAS-2G33-F040 MIDACALC Results LAS-2G33-F040 9

MIDACALC LAS- AC Motor Operated GL96-05 Gate Valve Calculation 10

1E51-F008 Results

MIDACALC LAS- AC Motor Operated GL96-05 Gate Valve Calculation 10

2E51-F063 Results

Corrective Action 04339836 NEB-20-05: Evaluate Risk of Wedge Spring Failures in 04/30/2020

Documents ADDDGVs

Corrective Action 04429540 Issue with Legacy paperwork for 1E12-F042B 06/15/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 04432739 NRC POV DBAI ID'd Incorrect Midacalc Input for 07/01/2021

Resulting from 1E22-F004

Inspection 04432800 Motor Nameplate Discrepancy in MIDAS for 2E12-F004B 07/01/2021

04432837 Valve 1E12-F068B Previously Exhibited Hammering 07/01/2021

When Closing

04432908 NRC ID - Enhancements Needed to MA-AA-723-301 07/01/2021

04432910 NRC ID - 1E12-F042B EQ Soft Clutch Question 07/01/2021

04433090 NRC ID - Analysis Detailing SRV Disc Impact Eval Not 07/02/2021

Found

04433141 NRC Borescope Observations (1E22-F004) 07/02/2021

04433178 NRC ID - Stroke Time Not Documented in WO# 07/02/2021

01814381-01

Drawings 93-14454 Anchor Darling 20 Gate Valve with SMB-0 Actuator G

94-13757 Anchor Darling 12 Gate Valve with SMB-1-40 Actuator F

94-13775 Anchor Darling 16 Gate Valve with SMB-1 Actuator G

94-13780 Anchor Darling 24 Gate Valve with SMB-00 Actuator F

D-0805 Clow 26 Wafer Stop Valve Assembly (Butterfly Valve) H

M-101 P&ID Reactor Core Isolation Coolant (R.C.I.C) BH

M-147 P&ID Reactor Core Isolation Coolant System (R.C.I.C) BL

M-95 P&ID High Pressure Core Spray AQ

P&ID M-138 Sh 1 Primary Containment Vent and Purge System AL

P&ID M-142 Sh 2 Residual Heat Removal AZ

P&ID M-87 Sh 1 Core Standby Cooling System Equipment Cooling Water BS

System

P&ID M-96 Sh 2 Residual Heat Removal BB

RI01-1401G, Component Support Assembly D

Sheet 1

RI01-1401G, Component Support Assembly D

Sheet 2

RI01-1401G, Component Support Assembly D

Sheet 3

VPF 3173-009 12" - 900# Motor Control Valve Outline 8

VPF-6115-001(1) Safety Relief Valve Main Steam 8

Inspection Type Designation Description or Title Revision or

Procedure Date

VPF-6115-001(2) Safety Relief Valve Main Steam 7

VPF-6115-001(3) Safety Relief Valve Main Steam C

W9223688 4-900 Weld Ends Carbon Steel Double Disc Gate Valve E

for Limitorque SMB-00-25 Actuator

W9223690 10-900 Weld Ends Carbon Steel Double Disc Gate Valve I

for Limitorque SB-2-80 Actuator

Engineering 620382 Replacement Parts for Anchor Darling Double Disc Gate 1

Changes Valves (ADDDGVS)

Engineering EQ-LS042 Limitorque Valve Actuators, Model SMB/SB (Inside 14A

Evaluations Containment)

EQ-LS079 Exelon Nuclear LaSalle County Nuclear Station, Units 1 21

and 2, Environmental Qualification of Limitorque Actuators

Model SMB/SB

LaSalle's Review Horizontally Installed Motor Operated Gate Valves 1

of Information Notice (IN) 92-59

LAVD Anchor Anchor Darling (Flowserve) Seismic and Weak Link A

Darling Valve Analysis

Report

Miscellaneous DC-SE-02-LS Seismic Response Spectra Design Criteria for LaSalle 3

County Station, Units 1 and 2

EQ-LS079 EQ Binder Limitorque Valve Actuator Model SMB/SB 22

Inservice Test LaSalle 4th Interval IST Program Plan 07/18/2018

Program

IST-LAS-PLAN LaSalle Inservice Testing Program Plan Fourth Ten-Year 02/23/2020

Interval

J-0184 Instruction Manual for Crosby Style 6xRx10 HB-65-BP 1

Safety Relief Valve for Main Steam Service

J-0687 Limitorque Vendor Manual 10

J-2500 General Requirements for Motor Operated Valve 0

Actuators

LAS-1E22- Jog Evaluation Report LAS-1E22-F004 8

F004_JOG

Spec J-2938-01 Gate, Globe, and Check Valves (Section III) LaSalle 07/25/1980

Inspection Type Designation Description or Title Revision or

Procedure Date

County Station - Units 1 and 2 Commonwealth Edison

Company

Spec T-3750 Replacement High Performance Butterfly Valves 08/23/1985

(Section III) LaSalle County Station - Units 1 and 2

Commonwealth Edison Company Project No. 6854-30

Specification Safety Relief Valves, Direct Acting, Spring Loaded, Dual 3

2A6441 Function (Modification of Crosby-Designed)

Specification Replacement of Motor-Operated Valves 04/15/1991

T-3794

Tech Specs and LaSalle Technical Specifications and Bases 05/27/2021

Bases

Procedures CC-AA-309-1011 General Station Piping Analysis 8

ER-AA-300 Motor-Operated Valve Program Administrative Procedure 12

ER-AA-300-1001 MOV Program Performance Indicators 14

ER-AA-302 Motor-Operated Valve Program Engineering Procedure 7

ER-AA-302-1001 MOV Rising Stem Motor Operated Valve Thrust and 11

Torque Sizing and Set-Up Window Determination

Methodology

ER-AA-302-1003 MOV Margin Analysis and Periodic Verification Test 10

Intervals

ER-AA-302-1006 Motor-Operated Valve Maintenance and Testing 19

Guidelines

ER-AA-302-1007 MOV Limitorque Actuator Capability Determination 11

Methodology

ER-AA-302-1009 Final Jog MOV Periodic Verification Program 3

Implementation

ER-AA-321 Administrative Requirements for Inservice Testing 13

ER-AA-321-1006 Inservice Testing of Motor Operated Valves 4

ER-AA-410 Air Operated Valve Program Implementing Procedure 6

ER-AA-410-1000 Air Operated Valve Categorization 4

ER-AA-410-1001 Air Operated Valve Design Basis Review and Setpoint 3

Control

ER-AA-410-1002 Air Operated Valve Testing Requirements 3

Work Orders 00405666-01 Perform EQ Inspection and Votes Test 02/17/2015

Inspection Type Designation Description or Title Revision or

Procedure Date

235433-01 Perform EQ Inspection and Votes Test 02/28/2011

01814283-01 Perform EQ Inspect & Diagnostic Test 2G33-F040 02/24/2017

WO 1234233-01 MM Perform Grease Sample on Valve Actuator 08/09/2010

WO 1235218 2E12-F004B Diagnostic Test 02/23/2011

WO 1318009-01 EQ Inspect, Boroscope & QSS 1E22-F004 02/16/2012

WO 1318040 1E12-F042B Diagnostic Test 02/28/2012

WO 1427062 2E12-F016B Diagnostic Test 02/20/2013

WO 1443897 1E12-F068B Diagnostic Test 04/07/2014

WO 1637912-01 Check Grease in Valve Operator Gearbox 11/14/2015

WO 1712040-01 EQ Inspect, Boroscope, Diagnostic 1E22-F004 in L1R16 02/29/2016

WO 1712732 1E12-F042B Position Indication Verification Test 02/19/2016

WO 1716165-01 EM EQ Inspect, Votes and Borescope 2E51-F063 02/09/2015

WO 1716770 1E12-F042B Water Leak Test 02/25/2016

WO 1727017 1E12-F042B Valve Inservice Exercise Test 02/19/2016

WO 1727602-01 MM Perform Stem Lube and Minimal Stem Rotation 02/29/2016

Check

WO 1763398-01 EWP MM Perform Grease Sample of Valve Actuator 06/21/2017

WO 1814257-01 MM Perform Stem Lube and Minimal Stem Rotation 02/11/2017

Check - OPCC 3

WO 1814258-01 MM Perform Grease Sample on Valve Actuator 02/11/2017

2E51-F063 - OPCC3

WO 1814381 2E12-F004B Diagnostic Test 02/11/2017

WO 1901421 1E12-F042B Position Indication Verification Test 02/22/2018

WO 1905451 1E12-F042B Water Leak Test 02/27/2018

WO 1906997-01 EM Perform LES-NB-101B Tech Spec. Surveillance 03/07/2018

WO 1907982-01 EM Perform LES-NB-101A Tech Spec. Surveillance 03/07/2018

WO 1909986-01 MM Perform Stem Lube on 1E22-F004 02/20/2018

WO 1910010-03 EP PMT - As Left LLRT Per LTS-100-24 On 1E51-F008 03/04/2018

WO 1910608 1E12-F042B Valve Inservice Exercise Test 02/27/2018

WO 1910686-01 Perform EQ Inspect, Test, Support Part 21 WO #4627469 02/28/2018

WO 1914062 2E12-F016B Diagnostic Test 02/12/2019

WO 4568762-01 CM (CONT) Remove/Replace SRV 1B21-F013S (OPCC) 03/07/2018

WO 4582723 1E12-F068B Diagnostic Test 10/05/2017

Inspection Type Designation Description or Title Revision or

Procedure Date

WO 4627477-04 EP PMT - As Left LLRT Per LTS-100-24 on 2E51-F008 03/02/2019

WO 4627478-02 As-Found/Left Diagnostic Test, D/R, Borescope/EQ Insp 03/01/2019

WO 4697918 1E12-F068B Diagnostic Test 10/03/2019

WO 4753598 1E12-F042B Position Indication Verification Test 02/22/2020

WO 4758057-01 EWP MM Perform Stem Lube for 1E51-F008 02/19/2020

WO 4758062-01 Change Valve Stem Lubricant 02/11/2020

WO 4758372 1E12-F042B Valve Inservice Exercise Test 02/21/2020

WO 4765564-01 EP ASME XI High Pressure Water Test - RVP Boundary 02/11/2020

WO 4810933-01 Check Grease in Valve Operator Gearbox 10/26/2020

WO 4827832-01 CM L1R18 Remove/Replace SRV 1B21-F013S 02/23/2020

WO 4902695-01 MM Verify Packing Torque 2E51-F063 02/26/2021

WO 4902696-01 Change Valve Stem Lubricant & Visual Inspection 02/25/2021

WO 5155346-01 OP LOS-AA-W1 U1 Tech Spec Weekly Att 1A 05/30/2021

WO 5157430-01 OP LOS-AA-W1 U1 Tech Spec Weekly Att 1A 06/06/2021

WO 5159515-01 OP LOS-AA-W1 U1 Tech Spec Weekly Att 1A 06/13/2021

WO 584826 2E12-F004B Diagnostic Test 02/19/2005

WO 703532-01 EM Perform Inspection and Votes Test for 1E22-F004 02/26/2006

WO 703585 1E12-F042B Diagnostic Test 02/28/2006

10