IR 05000263/2020013

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

ML20287A319
Person / Time
Site:	Monticello
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 Enterprise Identifier: I-2020-013-0004 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 Enclosure

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 Type Designation Description or Title Revision or

Procedure Date

71111.21N.02 Calculations01-081 AOV Component Calculation, PCT Butterfly Valves, 1

AO-2379 & AO-2380

03-022 AOV Component Calculation, PCT, Vent & Purge 4A

Butterfly Valves08-077 AOV System Calculation 0A

08-193 AOV System Calculation - PCT 1B

10-082 RHR MOV Functional Analysis 2

11-044 Containment Purge Butterfly Valve Margin Predictions 0

Using KVAP 3.1 and CFD Derived Coefficients14-001 Monticello Stem Lubrication Study 0

14-039 250VDC Coordination Study 0

15-022 Performance Prediction Methodology (PPM) for MO-2008 0

and MO-2009

15-034 Weak Link Analysis of an 18" Fisher 9200 Butterfly Valve 0

3494 Seismic Analysis of 1-inch Class 1500 Stainless Steel 0

Valtek Mark One Globe Control Valve

2-299 Valve Thrust Assessment 16" Anchor Darling Globe 3

Valves MO-2012 & MO-2013

94-037 Calculation of AN2 System Pneumatic Pressure 8A

Requirements94-141 Valve Thrust Assessment 10" Globe Valve: MO-2008 and 8A

MO-2009

96-091 Effects of RHR/CS Pump Motor Starting Transients on 2

MOV Performance

96-200 Stem Thrust Assessment 3" A/D Globe Valve MO-2078 1A

98-026 Limitorque Motor Operators (50.49) 3

98-315 MO-2067, MO-2068, MO-2071 Capability During HPCI 5

Pressurization

99-007 MOV Environmental Temperatures 3

99-195 Piping Evaluation of RCIC Drain Line D14-1 1

MOVDS- Thrust and Torque Calculation MO-2012 (MNGP-1) 0

Inspection Type Designation Description or Title Revision or

Procedure Date

MT:1:RHR:MO-

2012

MOVDS- Thrust and Torque Calculation MO-2009 0

MT1RHRMO-

2009

Calibration 16294C05 As-Left Spring Pack Calibration Data 10/20/2016

Records

Corrective Action 01512332 MO-20178 As-Found Diagnostic Test Anomalies 03/03/2016

Documents 01512335 MO-2078 Valve Stem Found with Rub/Scratch Mark 03/03/2016

01534266 MO-2078, RCIC Turbine Steam Supply Gearbox Leaking 10/07/2016

Oil

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 06/15/2017

Thrust

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 501000043391 POV Inspection: Typo in WO435472 08/20/2020

Documents 501000043618 NRC POV Inspection: Cal 15-022 Errors 08/27/2020

Resulting from 501000043727 NRC POV Inspection: PMCR 613000001672 Typo 09/01/2020

Inspection 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 Type Designation Description or Title Revision or

Procedure Date

Drawings FSK-726-1 RCIC Room Line No. D14-1-ED D

NE-36404-14 Reactor Core Isolation Cooling System 77

NF-36298-2 DC Electrical Load Distribution One Line Diagram 92

NH-36049-14 P&ID Instrument Air - Reactor Building 81

NH-36246 P&ID Residual Heat Removal System 88

NH-36251 P&ID RCIC Steam Side 81

NH-36253 P&ID Standby Liquid Control System 80

NH-36258 P&ID Primary Containment & Atmospheric Control 80

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 76

Control System Elementary Diagram

NX-8292-12-5 Elementary Diagram-HPCI System 78

NX-9231-12 Monticello Nuclear Generating Plant MO-2009, 10" 300# 76

Globe Valve

Engineering 601000000642 Replace Overloads Relays MCC311 & MCC312 0

Changes

Engineering 21912 Kalsi Engineering Evaluation of Overthrust Condition on 05/17/2013

Evaluations MO-2012

293337 Prompt Operability Determination 01/29/2019

EC 25635 Evaluation of Thermal Overloads for Safety Related 07/17/2015

MOVs with Design Basis Throttle Functions

Miscellaneous MOVDS- MO-2068 (MNGP-1) DC Motor Operated GL96-05 Gate 0

MT:1:HPC:MO- Valve

2068

NX-1018 Joint Owners Group Air Operated Valve Program 1

NX-16932-1 Motor Operated Valve-Limitorque 26

NX-16932-3 Limitorque Critical Component List 0

NX-17491 Instruction and Maintenance Manual - Control Valves 3

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

and CV-2082B

NX-9235-86 Anchor Darling Gate, Swing Check and Glober Valves 18

600-900#

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures 0255-03-IA-2B Valve Position Indication Test 25

255-06-IA-1 HPCI Quarterly Pump and Valve Tests 105

255-06-III-1 HPCI Comprehensive Pump and Valve Tests 31

255-08-IA-1 RCIC Quarterly Pump and Valve Test 83

1069 HPCI Flow Control System Dynamic Test Procedure 27

AWI-09.04.01 Inservice Testing Program 59

B.02.03-01 RCIC Function and General Description of System 6

B.02.03-02 RCIC Description of Equipment 11

B.02.03-05 RCIC System Operation 39

B.03.04-02 Residual Heat Removal System 21

B.03.04-05 Residual Heat Removal System - System Operation 92

B.04.01-02 Operations Manual Section: Primary Containment - 14

Drywell, Suppression Chamber, Containment

Penetrations

B.04.01-05 Operations Manual Section: Primary Containment 44

EMP-01.11 Motor Operated Valve Testing 21

FP-PE-AOV-01 Air Operated Valve Program 2

FP-PE-AOV-02 Air Operated Valve Program Design Standard 0

IST-BASIS Pump and Valve In-Service Testing Program Basis 6

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 Type Designation Description or Title Revision or

Procedure Date

Tests

486711 PM 4900-01 for MO-2012 09/08/2015

490717 Primary Containment Purge and Vacuum Breaker, 05/04/2015

Pressure, and Isolation Valve LLRT Test

490894 Reactor Building to Torus Vacuum Breaker Actuator Air 04/19/2015

Supply Check Valve Functional Test

491333 Valve Position Indication Test 05/25/2015

491333-01 0255-03-IA-2B Core Spray Valve Position Indication Test 04/11/2015

505358 MOV Post-Test Data Review Worksheet 02/16/2016

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- 09/07/2017

01-PM

533441 Primary Containment Purge and Vacuum Breaker 04/25/2017

Pressure and Isolation Valve LLRT Test

533610XP-11- SBLC Refueling Tests 07/18/2017

14A

533649 EPRO-MO-2012 - Perform 4907-PM: Magnesium Rotor 09/07/2017

Inspection

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 02/28/2018

700018286 Drywell and Suppression Chamber 18 Inch Purge and 05/06/2019

Vent Valve Seat Seal Replacement

700019450 Primary Containment Purge and Vacuum Breaker, 04/20/2019

Pressure and Isolation Valve LLRT Test

700025922 Reactor Building to Torus Vacuum Breaker Actuator Air 04/28/2019

Supply Check Valve Functional Test

700033553 Reactor Building to Torus Vacuum Breaker Operability 10/18/2018

Check

700039856 MO-2012 - Mechanical Parts 4900-01-PM 02/12/2020

700040118 RCIC Comprehensive Pump and Valve Tests 11/14/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

700060014 Primary Containment Isolation Valve Exercise 12/19/2019

700060260 RHR Loop B Quarterly Pump and Valve Tests 12/23/2019

700063062 Motor Operated Valve Testing 02/19/2020

700063702 RCIC Quarterly Pump and Valve Tests 02/11/2020

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 04/15/2020

Check

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 92

10