IR 05000263/2020013

Design Basis Assurance Inspection (Programs) Inspection Report 05000263/2020013

ML20287A319
Person / Time
Site:	Monticello  (DPR-022)
Issue date:	10/13/2020
From:	Karla Stoedter NRC/RGN-III/DRS/EB2
To:	Conboy T Northern States Power Company, Minnesota
References
IR 2020013
Download: ML20287A319 (12)

Text

October 13, 2020

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000263/2020013

Dear Mr. Conboy:

On September 4, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Monticello Nuclear Generating Plant and discussed the results of this inspection with you 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, Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety

Docket No. 05000263 License No. DPR-22

Enclosure:

As stated

Inspection Report

Docket Number:

05000263

License Number:

DPR-22

Report Number:

05000263/2020013

Licensee:

Northern States Power Company, Minnesota

Facility:

Monticello Nuclear Generating Plant

Location:

Monticello, MN

Inspection Dates:

August 17, 2020 to September 04, 2020

Inspectors:

I. Hafeez, Reactor Inspector

M. Jones, Reactor Inspector

E. Sanchez Santiago, Senior Reactor Inspector

Approved By:

Karla K. Stoedter, Chief

Engineering Branch 2

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at the Monticello Nuclear Generating Plant, 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 SCOPE

The inspection was conducted using the appropriate portions of the inspection procedure (IP) 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), regional inspectors were directed to begin telework. The NRC determined the objectives and requirements stated in the IP below could be met by performing the inspection remotely.

REACTOR SAFETY

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

The inspectors:

a.

Determined whether the sampled 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).

The following valves were chosen for review:

(1) AO-2378, Suppression Chamber Purge Inboard Containment Isolation Valve

(2) AO-2379, Suppression Chamber Vacuum Relief Air Operated Valve

(3) MO-2009, Residual Heat Removal to Torus Cooling Isolation Valve

(4) MO-2012, Residual Heat Removal Low Pressure Core Injection Outboard Isolation Valve

(5) MO-2036, High Pressure Core Injection Turbine Steam Supply Isolation Valve

(6) MO-2068, High Pressure Core Injection Isolation Valve

(7) MO-2078, Reactor Core Isolation Cooling Turbine Steam Supply Isolation Valve

(8) CV-2082A, Reactor Core Isolation Cooling Steam Line Drain Isolation Valve

(9) CV-2065, High Pressure Core Injection Minimum Flow Control Valve

(10) XP-11-14A, Standby Liquid Control 'A' Explosive Actuated Squib 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 September 4, 2020, the inspectors presented the design basis assurance inspection (programs) inspection results to Thomas Conboy, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21N.02 Calculations01-081

AOV Component Calculation, PCT Butterfly Valves,

AO-2379 & AO-2380

03-022

AOV Component Calculation, PCT, Vent & Purge

Butterfly Valves

4A

08-077

AOV System Calculation

0A

08-193

AOV System Calculation - PCT

1B

10-082

RHR MOV Functional Analysis11-044

Containment Purge Butterfly Valve Margin Predictions

Using KVAP 3.1 and CFD Derived Coefficients14-001

Monticello Stem Lubrication Study

14-039

250VDC Coordination Study

15-022

Performance Prediction Methodology (PPM) for MO-2008

and MO-2009

15-034

Weak Link Analysis of an 18" Fisher 9200 Butterfly Valve

3494

Seismic Analysis of 1-inch Class 1500 Stainless Steel

Valtek Mark One Globe Control Valve

2-299

Valve Thrust Assessment 16" Anchor Darling Globe

Valves MO-2012 & MO-2013

94-037

Calculation of AN2 System Pneumatic Pressure

Requirements

8A

94-141

Valve Thrust Assessment 10" Globe Valve: MO-2008 and

MO-2009

8A

96-091

Effects of RHR/CS Pump Motor Starting Transients on

MOV Performance

96-200

Stem Thrust Assessment 3" A/D Globe Valve MO-2078

1A

98-026

Limitorque Motor Operators (50.49)98-315

MO-2067, MO-2068, MO-2071 Capability During HPCI

Pressurization

99-007

MOV Environmental Temperatures99-195

Piping Evaluation of RCIC Drain Line D14-1

MOVDS-

Thrust and Torque Calculation MO-2012 (MNGP-1)

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MT:1:RHR:MO-

2012

MOVDS-

MT1RHRMO-

2009

Thrust and Torque Calculation MO-2009

Calibration

Records

294C05

As-Left Spring Pack Calibration Data

10/20/2016

Corrective Action

Documents

01512332

MO-20178 As-Found Diagnostic Test Anomalies

03/03/2016

01512335

MO-2078 Valve Stem Found with Rub/Scratch Mark

03/03/2016

01534266

MO-2078, RCIC Turbine Steam Supply Gearbox Leaking

Oil

10/07/2016

01541433

MO-2078 Grease Separation from Limitorque Actuator

11/19/2016

01541857

MO-2078 Test Anomaly; High Thrust

05/11/2017

1477935

Corrective Actions for 2012 Violation Inadequate

05/06/2015

1478122

Bounding Worst Case Voltage Drop for Electrical Calcs

06/10/2015

1556660

As-Found Testing for MO-2012 Shows High Closing

Thrust

06/15/2017

501000008780

MOV Classification Logic Outdated

06/18/2018

501000022876

11-297 Incorrect Stroke Time Criteria

03/14/2019

501000027499

MO-2014 Leaking By

06/07/2019

501000030796

RCIC IST PIT Was Not Performed

09/19/2019

501000037733

MO-2-53 Calc 12-044 Requires Revision

07/17/2020

501000037819

MO-2009 As-Found Anomaly

03/23/2020

608000000308

Evaluate MO-2012 Open Capability

08/09/2019

613000001672

Deferral for MO-2009 Diagnostic Testing

05/01/2020

Corrective Action

Documents

Resulting from

Inspection

501000043391

POV Inspection: Typo in WO435472

08/20/2020

501000043618

NRC POV Inspection: Cal 15-022 Errors

08/27/2020

501000043727

NRC POV Inspection: PMCR 613000001672 Typo

09/01/2020

501000043818

NRC POV Inspection: MO-2078 C-Clamp Issues

09/03/2020

501000043821

NRC POV Inspection: 96-200 Editorial Error

09/02/2020

501000043842

NRC POV Inspection: MO-20178 Thrust Eval Def

09/03/2020

501000043880

NRC POV Inspection: Inconsistent MOV Test Doc

09/03/2020

501000043881

NRC POV Inspection: Lack of Attention to Detail

09/03/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Drawings

FSK-726-1

RCIC Room Line No. D14-1-ED

D

NE-36404-14

Reactor Core Isolation Cooling System

NF-36298-2

DC Electrical Load Distribution One Line Diagram

NH-36049-14

P&ID Instrument Air - Reactor Building

NH-36246

P&ID Residual Heat Removal System

NH-36251

P&ID RCIC Steam Side

NH-36253

P&ID Standby Liquid Control System

NH-36258

P&ID Primary Containment & Atmospheric Control

System

NX-13142-43

RCIC Primary Steam

E

NX-41827-2

1"-1500 LB Valtek Mark 1 Globe Valve

B

NX-7879-5

Monticello Nuclear Generating Plant Standby Liquid

Control System Elementary Diagram

NX-8292-12-5

Elementary Diagram-HPCI System

NX-9231-12

Monticello Nuclear Generating Plant MO-2009, 10" 300#

Globe Valve

Engineering

Changes

601000000642

Replace Overloads Relays MCC311 & MCC312

Engineering

Evaluations

21912

Kalsi Engineering Evaluation of Overthrust Condition on

MO-2012

05/17/2013

293337

Prompt Operability Determination

01/29/2019

EC 25635

Evaluation of Thermal Overloads for Safety Related

MOVs with Design Basis Throttle Functions

07/17/2015

Miscellaneous

MOVDS-

MT:1:HPC:MO-

2068

MO-2068 (MNGP-1) DC Motor Operated GL96-05 Gate

Valve

NX-1018

Joint Owners Group Air Operated Valve Program

NX-16932-1

Motor Operated Valve-Limitorque

NX-16932-3

Limitorque Critical Component List

NX-17491

Instruction and Maintenance Manual - Control Valves

CV-2043, CV-2046A, CV-2046B, CV-2079, CV-2082A

and CV-2082B

NX-9235-86

Anchor Darling Gate, Swing Check and Glober Valves

600-900#

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Procedures

255-03-IA-2B

Valve Position Indication Test

255-06-IA-1

HPCI Quarterly Pump and Valve Tests

105

255-06-III-1

HPCI Comprehensive Pump and Valve Tests

255-08-IA-1

RCIC Quarterly Pump and Valve Test

1069

HPCI Flow Control System Dynamic Test Procedure

AWI-09.04.01

Inservice Testing Program

B.02.03-01

RCIC Function and General Description of System

B.02.03-02

RCIC Description of Equipment

B.02.03-05

RCIC System Operation

B.03.04-02

Residual Heat Removal System

B.03.04-05

Residual Heat Removal System - System Operation

B.04.01-02

Operations Manual Section: Primary Containment -

Drywell, Suppression Chamber, Containment

Penetrations

B.04.01-05

Operations Manual Section: Primary Containment

EMP-01.11

Motor Operated Valve Testing

FP-PE-AOV-01

Air Operated Valve Program

FP-PE-AOV-02

Air Operated Valve Program Design Standard

IST-BASIS

Pump and Valve In-Service Testing Program Basis

Work Orders

289154

MO-2009, Replace Div II Rotork Actuator

04/19/2007

2785-01

PM 4900-1 for MO-2078 Perform Electrical PM

08/08/2007

345608-03

SBLC Refueling Tests

07/17/2009

383367

AOV As-Left Testing Using Viper 20

04/14/2011

3911303

Motor Operated Valve Testing Using Viper 20

03/21/2011

411393

EC-15613, Replace Spring and Adj Lever Arm Length

04/24/2013

435203

Viper Test - MO-2012

04/06/2013

435472-07

AOV As-Left Testing Using Viper 20

03/15/2013

440736

OPS - PMT - 150#

05/10/2016

441394

PM 4321 (Torus Purge Inbd Isol AO-2379)

04/21/2013

441395

PM 4321 (Vacuum Relief Damper AO-2379)

04/24/2013

441397

PM 4321 (Torus Purge Inbd Isol AO-2378)

05/09/2013

458828

PM 4900-1 for MO-2009

04/30/2013

465526-01

OPS-RCI, 0255-08-IA-1 RCIC Quarterly Pump and Valve

09/03/2013

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Tests

486711

PM 4900-01 for MO-2012

09/08/2015

490717

Primary Containment Purge and Vacuum Breaker,

Pressure, and Isolation Valve LLRT Test

05/04/2015

490894

Reactor Building to Torus Vacuum Breaker Actuator Air

Supply Check Valve Functional Test

04/19/2015

491333

Valve Position Indication Test

05/25/2015

491333-01

255-03-IA-2B Core Spray Valve Position Indication Test

04/11/2015

505358

MOV Post-Test Data Review Worksheet

2/16/2016

506230

OPS-MO-2078, Perform 8154 Procedure

08/26/2016

508620

B4337 - Minor PM (MO-2009, RHR Div 2)

06/29/2015

29915

MECH - MO-2012 - Perform Mechanical Portions of 4900-

01-PM

09/07/2017

533441

Primary Containment Purge and Vacuum Breaker

Pressure and Isolation Valve LLRT Test

04/25/2017

533610XP-11-

14A

SBLC Refueling Tests

07/18/2017

533649

EPRO-MO-2012 - Perform 4907-PM: Magnesium Rotor

Inspection

09/07/2017

534225

ELEC - MO-2012 - Perform Periodic Verification Test

09/27/2017

534225

LPCI Loop "A" Injection Valves Local Leak Rate Test

04/25/2017

534225

Motor Operated Valve Testing

04/22/2017

2379-01

Mechanical: MO-2078, Replace Spring Pack

2/28/2018

700018286

Drywell and Suppression Chamber 18 Inch Purge and

Vent Valve Seat Seal Replacement

05/06/2019

700019450

Primary Containment Purge and Vacuum Breaker,

Pressure and Isolation Valve LLRT Test

04/20/2019

700025922

Reactor Building to Torus Vacuum Breaker Actuator Air

Supply Check Valve Functional Test

04/28/2019

700033553

Reactor Building to Torus Vacuum Breaker Operability

Check

10/18/2018

700039856

MO-2012 - Mechanical Parts 4900-01-PM

2/12/2020

700040118

RCIC Comprehensive Pump and Valve Tests

11/14/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

700060014

Primary Containment Isolation Valve Exercise

2/19/2019

700060260

RHR Loop B Quarterly Pump and Valve Tests

2/23/2019

700063062

Motor Operated Valve Testing

2/19/2020

700063702

RCIC Quarterly Pump and Valve Tests

2/11/2020

700064825

RHR Loop A Quarterly Pump and Valve Tests

03/05/2020

700065738

Primary Containment Isolation Valve Exercise

03/19/2020

700066965

Reactor Building to Torus Vacuum Breaker Operability

Check

04/15/2020

700069303

RHR Loop A Quarterly Pump and Valve Tests

06/08/2020

700071904

AOV Diagnostic Testing

08/11/2020

NH-36247

P&ID Residual Heat Removal System

2