IR 05000263/2017011

NRC Design Bases Assurance Inspection (Programs): Inspection Report 05000263/2017011 (DRS-B.Jose)

ML17306B195
Person / Time
Site:	Monticello
Issue date:	11/01/2017
From:	Jeffers M T NRC/RGN-III/DRS/EB2
To:	Church C Northern States Power Company, Minnesota
References
IR 2017011
Download: ML17306B195 (11)

Text

November 1, 2017

SUBJECT: MONTICELLO NUCLEAR GENERATING PLANTNRC DESIGN BASES ASSURANCE INSPECTION (PROGRAMS): INSPECTION REPORT 05000263/2017011

Dear Mr. Church:

On October 6, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed a triennial baseline Design Bases Assurance Inspection (Programs) at your Monticello Nuclear Generating Plant. The inspection reviewed the implementation of the Environmental Qualification Program for electrical equipment. The enclosed report documents the results of this inspection, which were discussed on October 6, 2017, with Mr. Kent Scott and other members of your staff. Based on the results of this inspection, no violations of significance were identified. 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

Sincerely,

/RA/ Mark T. Jeffers, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 50263 License No. DPR22 Enclosure: IR 05000263/2017011 cc: Distribution via LISTSERV Letter to Christopher Church from Mark T. Jeffers dated November 1, 2017 SUBJECT: MONTICELLO NUCLEAR GENERATING PLANTNRC DESIGN BASES ASSURANCE INSPECTION (PROGRAMS): INSPECTION REPORT 05000263/2017011 DISTRIBUTION: Theresa Clark RidsNrrDorlLpl3 RidsNrrPMMonticello RidsNrrDirsIrib Resource Cynthia Pederson Richard Skokowski Allan Barker Carole Ariano Linda Linn DRPIII DRSIII ROPreports.Resource@nrc.gov ADAMS Accession Number ML17306B195 OFFICE RIII RIII RIII RIII NAME BJose:cl MJeffers DATE 10/25/17 11/01/17 OFFICIAL RECORD COPY Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50263 License No: DPR22 Report No: 05000263/2017011 Licensee: Northern States Power Company Facility: Monticello Nuclear Generating Plant Location: Monticello, MN Dates: September 18, 2017, through October 6, 2017 Inspectors: B. Jose, Senior Reactor Inspector (Lead) I. Khan, Reactor Inspector I. Hafeez, Reactor Inspector Observers: N. Khan, NRR Inspector Trainee Approved by: M. Jeffers, Chief Engineering Branch 2 Division of Reactor Safety 2

SUMMARY

Inspection Report 05000263/2017011; 09/18/201710/06/2017; Monticello Nuclear Generating Plant; Design Bases Assurance Inspection (Programs). The inspection was a 2-week onsite baseline inspection that focused on the implementation of the Environmental Qualification Program. The inspection was conducted by three regional engineering inspectors. No findings were identified by the inspectors. The significance of inspection findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter Process,October 8, 2015. Cross-cutting aspects are determined using Inspection Manual Chapter -Cutting Areas,d December 4, 2014. All violations of U.S. Nuclear Regulatory Commission (NRC) requirements are dispositioned in Policy, dated November 1, 2016. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-,dated July 2016.

NRC-Identified

and Self-Revealed Findings

===Cornerstone: Mitigating Systems, Barrier Integrity No findings were identified.

Licensee-Identified Violations

None===

3

REPORT DETAILS

REACTOR SAFETY

===Cornerstone: Mitigating Systems and Barrier Integrity

1R21 Design Bases Assurance Inspection (Programs)

.1 Introduction

This is a baseline inspection of a licensee program conducted per U.S. Nuclear Regulatory Commission (NRC) Inspection Procedure 71111.21N, Attachment 1. The objective of the Design Bases Assurance Inspection is to gain reasonable assurance that structures, systems, and components can adequately perform their design basis function. This includes reasonable assurance that electrical equipment important-to-safety for which a qualified life has been established can perform its safety functions without experiencing common cause failures before, during, and after applicable design equipment Environmental Qualification (EQ) Program, as required by their license, for maintaining the qualified status of equipment during the life of the plant. The inspection components. This inspectable area verifies aspects of the Mitigating Systems and Barrier Integrity cornerstones for which there are no indicators to measure performance. The inspectors assessed the implementation of the EQ Program, established to meet the requirements of Title 10 of the Code of Federal Regulations, Part 50.49, -related equipment relied upon to remain functional during and following design basis events, nonsafety-related equipment whose failure under postulated environmental conditions could prevent safety-related equipment from performing design functions, and certain post-accident monitoring equipment. The NRC Program implementation through a series of onsite inspections from 19841989. The EQ Program at that time established measures to ensure components met the EQ rule through the 40-year operating license period. Specific documents reviewed during the inspection are listed in the Attachment to the report.

.2 Inspection Sample Selection Process The inspectors selected components for review using information provided by the licensee.

The Monticello Nuclear Generating Plant, Probabilistic Risk Assessment was reviewed and used for selecting components, generally components that had a high Fussell Vesely Importance factor. Additional selection criteria included discussions with plant staff, reviewing procurement, maintenance, and design records, and walking down plant areas susceptible to high-energy line break. Based on these reviews, the inspectors focused the inspection on EQ Program elements and components repaired, modified, or replaced. Components selected included motor-operated valves, air operated valves, and transmitters (pressure, flow, and level) located both inside and outside of containment.===

4 For each component selected, the inspectors evaluated the equipment qualifications of supporting sub-components including seals, lubricants, connectors, control and power cables, solenoids, transducers, limit switches, and terminal blocks. This inspection constituted 10 samples (2 components of which were located in primary containment) as defined in Inspection Procedure 71111.21N, Attachment 1, Section 02.01.

.3 Component Design

a. Inspection Scope

The inspectors assessed the licenseeProgram as required by Title 10 of the Code of Federal Regulations, Part 50.49. The inspectors evaluated whether the licensee staff properly maintained the EQ of electrical equipment important to safety through plant life (repair, replacement, modification, and plant life extension), established and maintained required EQ documentation records, and implemented an effective Corrective Action Program (CAP) to identify and correct EQ-related deficiencies and evaluate EQ-related industry operating experience. This inspection effort included a review of EQ Program-related procedures, component EQ files, EQ test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, and calculations. The inspectors interviewed operators, engineers, maintenance staff, and procurement staff. Additionally, the inspectors performed in-plant walkdowns of accessible components to verify installed equipment was the same as described in the EQ component documentation files, verify components were installed in their tested configuration, determine whether equipment surrounding the EQ component may fail in a manner that could prevent the EQ component from performing its safety function, and verify that components located in areas susceptible to a high-energy break line were properly evaluated for operation in a harsh environment. Components removed from the EQ Program were reviewed to ensure an adequate basis existed to no longer require the components to meet EQ requirements. The inspectors reviewed procurement records and inspected a sample of replacement parts stored in the warehouse to verify EQ parts approved for installation in the plant were properly identified and controlled; and that qualified life or service life. Documents reviewed for this inspection are listed in the Attachment. The following 10 EQ components (samples) were reviewed: K10B-MTR, 12 Residual Heat Removal (RHR) Auxiliary Air Compressor Motor SV-2379, Torus to Reactor Building Vacuum Breaker Air Operated Valve AO-2-86A/SV1, 11 Outboard Main Steam Isolation Valve Main Control Valve SV-2-71C, SRV C, Air Operator Solenoid Valve MO-2076, Reactor Core Isolation Cooling Inboard Steam Isolation Valve (Limitorque Motor Operated Valve) Raychem Low and Medium Voltage Splices LT-7338B, Torus Wide Range Level Transmitter MO-2011, RHR Division 1 to Torus Spray Inboard Motor Operated Valve; PS-10-101B, Drywell Pressure Transmitter; EP-1728, RHR E to P Converter 5

b. Findings

No findings were identified.

.4 Operating Experience

a. Inspection Scope

The inspectors reviewed two EQ-related operating experience issues associated with the selected components to ensure that associated generic concerns had been adequately evaluated and addressed by the licensee. The operating experience issues listed below were reviewed as part of this inspection: Information Notice 2014-Containment Penetrations, Mechanical Seals and Other Components; Information Notice 84-d to Moisture Intrusion in Safety-Related Electrical Equipment at Commercial Power Plants.

b. Findings

No findings were identified.

4OA2 Identification and Resolution of Problems

.1 Review of Items Entered Into the Corrective Action Program

a. Inspection Scope

The inspectors reviewed a sample of the selected component problems identified by the licensee and entered into the CAP. The inspectors reviewed these issues to assess the threshold for identifying issues and the effectiveness of corrective actions related to design issues. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problem into the CAP. The specific corrective action documents sampled and reviewed by the inspectors are listed in the attachment to this report.

b. Findings

No findings were identified.

4OA6 Management Meeting

.1 Exit Meeting Summary The inspectors presented the inspection results to Mr. K. Scott, and other members of the licensee staff on October 6, 2017.

The licensee acknowledged the issues presented. The inspectors confirmed that some of the potential report input discussed was considered proprietary and will be handled in accordance with NRC policy. ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

K. Scott, Director, Site Operations

M. Lingenfelter, Site Engineering Director

A. Ward, Regulatory Assurance Manager

D. Bosnic, Director, Support Services

J. Oquist, EQ Engineer

B. Dixon, Programs Engineering

R. Loeffler, Design Engineering

J. Hill, Design Engineering

P. Nordmier, Programs Engineering

A. Kouba, Regulatory Assurance

U.S. Nuclear Regulatory Commission P. Zurawski, Senior Resident Inspector

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened, Closed and

Discussed

None LIST OF ACRONYMS USED CAP Corrective Action Program EQ Environmental Qualifications NRC U.S. Nuclear Regulatory Commission RHR Residual Heat Removal

LIST OF DOCUMENTS REVIEWED

The following is a list of documents reviewed during the inspection.

Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort.

Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report. CORRECTIVE ACTION DOCUMENTS GENERATED DUE TO THE INSPECTION Number Description or Title Date 501000003415 Rosemount O Ring Replacement 10/05/2017 501000003384 EQ Reference Number Transposed 10/05/2017 501000003404 Procedure 0424 Bases Clarification 10/05/2017 501000003328 NRC Question on EQ File 13-006 10/04/2017 501000003351 Raychem Installation Instructions 10/04/2017 501000003293 EQ File Reference Update 10/03/2017 501000002980 EQ File 98-051 Clarification 09/22/2017 501000002906 EQ File 13-006 Quarterly Cycles 09/22/2017 501000002884 Monticello Response to

IN 2014-04 Enhancement 09/20/2017 501000002802

EQINSP-MOV Actuator Serial Numbers Wrong 09/18/2017

CORRECTIVE ACTION DOCUMENTS REVIEWED DURING THE INSPECTION Number Description or Title Date 500001527265 Elevated Temperature in SBGT Room 06/21/2012

01363359 SSE EQ PM Frequency not Aligned with Qualified Lives 12/14/2012

01364249 Fire Penetration Degradation in HPCI and Tank Room 12/21/2012

01470658

MO-2008 Exceeds EQ Cycle Limit 03/18/2015

01475626 Discovery of VCI Device Challenges Operability of EQ MOVs 04/21/2015

01510144 Previously Unrecognized Impact of AREVA Transition on

EQ 01/27/2016

01424726 NRC INFORMATION NOTICE 2014-04: Potential for Teflon Material Degradation in Containment Penetrations, Mechanical Seals A07174 03/31/2014 and Other Components 03/31/2014

DRAWINGS Number Description or Title Revision

NX-7822-22-5b RCIC Steam Supply Line Isolation

MO-2076 Scheme 78 B-208-199 Elementary Diagram 1P57-F015B K

EQ FILES Number Description or Title Revision 98-004 ASCO Solenoid Valves (50.49) 1 13-006 AVCO MSIV Solenoid Valves (50.49) 2 98-051 Reliance Motors (50.49) 2 08-016 Rosemount 1154 Transmitters 2 98-017 G. E. Cable (POR) 2

EQ FILES Number Description or Title Revision 98-020 General Electric Containment Penetration (POR) 2 98-026 Limitorque Motor Operators (50.49) 2 98-036 Raychem Low Voltage Splices (50.49) 1 98-039 Rosemount Pressure Transmitter Series A (DOR) 2 98-043 Rotork Valve Operators (50.49) 2 98-107 Rockbestos Firewall III/SIS Cable (50.59) 2

MISCELLANEOUS Number Description or Title Date or Revision

NEDC-32303P Qualification Test Report of MSIV Solenoid Valve Cluster Assemblies Hiller 975-30710 (AVC B6930-082) 01/1994

PII-55235 NPKV Nuclear Plant Kit Stub Connection AA

PII-55244 Heavy Wall, Flame-Retardant Nuclear Cable Sleeves AD

PII-57879 Nuclear Plant Kit End Sealing Kit AA

PCR 01496687 Electrical Product List 26

MODIFICATIONS

Number Description or Title Revision 26038 EQ MOV Cycling Limit Extension to 4000 Cycles for Limitorque and Rotork NA1 Actuators 1

EC-20636 Door 45 Blocked by SCISSORS Lift 0

EC-27157 HELB Flow Through FZ1330 0

PROCEDURES

Number Description or Title Date or Revision 4920-PM Change out Procedure for ASCO Solenoid Valves 28

MMP-007 MOV Actuator Installation/Removal 10

DI-0910-001-234 Westinghouse Qualification Testing of Rosemont Model 1153 Series A Electronic Transmitters 01/04/1979

MWI-8-M-4.15 Conductor Splicing and Cable Jacket Repair

14 4302 Model 1153 Series B Alphaline Pressure Transmitters for Nuclear Service

E

SVI-P57-T2001 Safety-Related Instrument Air MOV Operability Test 7

WORK DOCUMENTS

Number Description or Title Date

00543465-01 Replace

MO-2397 Actuator to Resolve

OBN 04/15/2017

00543467-10 Replace

MO-2398 Actuator to Resolve

OBN 04/20/2017

00460213-02

PM 4920 (Replace Solenoid Valve

SV-2379

EQ) 04/23/2015

00444158-04 PM:

AO-2-86A Replace Air Control Assembly 04/21/2017

00533974-05 PM:

AO-2-86A 4240-02-PM MSIV General Inspection 04/20/2017

00455535-02

PM 4183 (12 RHR Aux Air Compressor K-10B) 01/29/2013

WORK DOCUMENTS

Number Description or Title Date

00440958-01 I&C

PCT, Performance Outage I&C

PM 7267 on

PCT-7 Instruments 05/20/2013

00344467-01 Perform Outage I&C

PM 7627 on

PCT-7 Instruments 02/16/2009

00343746 01 (XX)-CNST,

CV-2790, Install Scaffolding 03/10/2010

00343889 01 Elec-A0-2-86D, Perform 4910-PM 05/11/2009

00394445 01 Elec-SV-2791, Bench Test 11/12/2010

00411853 01

IC-FS-2950, Replace Flow Switch 08/26/2010

00498191 01 Replace Solenoid Valve

SV-2380 per 4920

PM 09/09/2014

20006149 02 Perform Full

PMI-0030 on MOV 1P57-F015B 03/15/2005