IR 05000263/2021001

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Integrated Inspection Report 05000263/2021001
ML21120A065
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 04/30/2021
From: Hironori Peterson
Region 3 Branch 3
To: Conboy T
Northern States Power Company, Minnesota
References
IR 2021001
Download: ML21120A065 (14)


Text

April 30, 2021

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000263/2021001

Dear Mr. Conboy:

On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Monticello Nuclear Generating Plant. On April 6, 2021, the NRC inspectors 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,

/RA/

Hironori Peterson, Chief Branch 3 Division of Reactor Projects

Docket No. 05000263 License No. DPR-22

Enclosure:

As stated

Inspection Report

Docket Number:

05000263

License Number:

DPR-22

Report Number:

05000263/2021001

Enterprise Identifier: I-2021-001-0041

Licensee:

Northern States Power Company

Facility:

Monticello Nuclear Generating Plant

Location:

Monticello, MN

Inspection Dates:

January 01, 2021 to March 31, 2021

Inspectors:

T. McGowan, Resident Inspector

V. Myers, Senior Health Physicist

C. Norton, Senior Resident Inspector

Approved By:

Hironori Peterson, Chief

Branch 3

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at 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.

PLANT STATUS

Monticello began the inspection period at rated thermal power. Except for planned load drops for control rod sequence exchange and control rod line adjustments, Monticello remained at rated thermal power until February 14, 2021, when the unit began coast down at the end of the operating cycle. Monticello ended the inspection period at 85 percent rated thermal power.

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 Disease 2019 (COVID-19),resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions 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

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending extreme low temperatures throughout the weekend starting on February 5, 2021

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) High pressure cooling injection (HPCI) system during the reactor core isolation cooling maintenance window on February 16, 2021
(2) Control rod drive (CRD) pump room on March 18, 2021
(3) Standby liquid control system on March 17, 2021
(4) Core spray system/train 'A' on March 18, 2021

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations of emergency diesel generator (EDG) 12 on January 25, 2021

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Fire zone 2-H, west shutdown cooling area on March 3, 2021
(2) Fire zone 1-C, reactor core isolation cooling (RCIC) room on March 3, 2021
(3) Fire zone 1-E, HPCI room on March 3, 2021
(4) Fire zone 1-G, CRD pump room on March 9, 2021
(5) Fire zone 33, emergency filtration train building, third floor on March 9, 2021
(6) Fire zone 12-A, lower 4 kv bus area (13 & 15) on March 9, 2021
(7) Fire zone 14-A, upper 4 kv bus area (14 & 16) on March 9, 2021

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during power increase following rod pattern adjustment on January 5, 2021

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated a newly promoted shift manager evaluated scenario on March 10, 2021

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples 1 Partial)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Inspectors evaluated various maintenance work activities performed on EDG 11 from January 11, 2021 through January 14, 2021 (2)10 CFR 50.69 integrated decision-making panel for portions of the emergency service water system on March 12, 2021 (3)10 CFR 50.69 functional assessment of core spray on March 15, 2021 (4)

(Partial)

Evaluation of CAP 501000043960, No Appendix J test for instrument replacements

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Reactor building exhaust damper maintenance on February 10, 2021
(2) Standby gas treatment system exhaust fan breaker on February 10, 2021
(3) HPCI work window on March 24, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) QIM 501000048364, non-conservative coefficient of friction assumption results in artificially high allowable values for the torque arm set screws on the division II residual heat removal (RHR) heat exchanger bypass valve
(2) QIM 501000048542, broken sight glass window on 13 RHR service water pump seal water supply
(3) QIM 501000048750, no grease in lantern ring seal on reactor core isolation cooling (RCIC) vacuum pump
(4) QIM 501000048755, packing leak on high pressure coolant injection drain pot level switch upper rood valve
(5) QIM 501000049574, seal leak in radwaste door 47

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) EDG 11 overspeed trip check and auxiliary systems testing on January 21, 2021
(2) CRD 11 pump relay maintenance, calibration and test tripping on March 11, 2021

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1)

(Partial)

The inspectors evaluated refuel outage preparations for refuel outage 30 during the first quarter 2021

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Functional test and calibration of the low reactor pressure - emergency core cooling system pump start permissive pressure switches on March 25, 2021
(2) EDG 12 monthly load test on March 29, 2021

Inservice Testing (IP Section 03.01) (1 Sample)

(1) HPCI quarterly pump and valve test on March 25, 2021

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Primary containment isolation valve exercise on March 26,

RADIATION SAFETY

71124.04 - Occupational Dose Assessment

Special Dosimetric Situations (IP Section 03.04) (1 Sample)

The inspectors evaluated the following special dosimetric situation:

(1) Declared Pregnant Worker for declaration on August 31, 2020

71124.05 - Radiation Monitoring Instrumentation

Calibration and Testing Program (IP Section 03.02) (12 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) RM-14, Unit Tracking Code 310331
(2) HV-1, Unit Tracking Code 310273
(3) REM500B, Unit Tracking Code 600003
(4) RO-7, Unit Tracking Code 310410
(5) SAM-11, Unit Tracking Code 310413
(6) DARM 3090-3, Unit Tracking Code 502321
(7) GEM-5, Unit Tracking Code 600019
(8) Containment High Range Radiation Monitor, RM-7860A
(9) ARGOS 5AB, Unit Tracking Code 491666
(10) Telepole, Unit Tracking Code 515544 (11)5XLB Automatic Smear Counter, Unit Tracking Code 525006
(12) AMS-4 Continuous Air Monitor, Unit Tracking Code 512848 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) Reactor Building Vent Wide Range Gas Monitor, RM-7859A
(2) Service Water Monitor, RM-17-351

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 03.01)===

(1) January 2020 - December 2020

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 03.02) (1 Sample)

(1) January 2020 - December 2020

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 03.03) (1 Sample)

(1) January 2020 - December 2020

===71153 - Follow-up of Events and Notices of Enforcement Discretion

Event Follow-up (IP Section 03.01)===

(1) The inspectors evaluated site's response to a steam leak outside of containment related to the reactor water cleanup system (train 'A') on January 26, 2021

Reporting (IP Section 03.05) (1 Sample)

(1) Medical emergency, potentially contaminated transportation to hospital on February 2,

INSPECTION RESULTS

Observation: Licensee Response to Steam Leak Outside of Containment 71153 On January 26, 2021, the licensee entered abnormal operating procedures in response to a steam leak outside containment. The leak was a fatigue failure through wall on a relief valve on the non-safety related rad waste side of the 'A cleanup system train. The licensee successfully isolated and repaired the leak. The inspectors identified no findings or violations of regulatory requirements.

Observation: Medical Emergency 71153 On February 2, 2021, a worker suffered a non-work-related medical emergency while working in a potentially contaminated area. The licensee placed a priority on getting the worker medical attention and notified the local hospital that a potentially contaminated injured individual was in transport to their facility. Radiation protection was able to radiologically clear the individual in the ambulance before the ambulance left the site and the individual was transported as non-contaminated. The local hospital was notified of the change in classification. The licensee did not enter an emergency action level. The inspectors identified no findings or violation of regulatory requirements.

EXIT MEETINGS AND DEBRIEFS

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

  • On April 6, 2021, the inspectors presented the integrated inspection results to Mr. T. Conboy, Site Vice President, and other members of the licensee staff.
  • On March 11, 2021, the inspectors presented the radiation protection inspection results to Mr. D. Barker, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Procedures

1444

Pre and Post Severe Weather Inspection Checklist

B.08.07-05

Operations Manual - Heating and Ventilating

C.4-B.08.03.A

Operations Manual Abnormal Procedures Ventilation

System Failure

C.4-B.08.7.A

Operations Manual Abnormal Procedures Ventilation

System Failure

71111.04

Drawings

NH-36244 (M-

118)

Control Rod Hydraulic System

NH-36245 (M-

119)

Control Rod Hydraulic System

NH-36248 (M-

2)

Core Spray (Train A)

NH-36249 (M-

23)

P&ID HPCI (Steam Side)

NH-36250 (M-

24)

P&ID HPCI (Water Side)

NH-36253 (M-

27)

Standby Liquid Control System

Procedures

24

Plant Prestart Checklist Diesel Generators and Fuel Oil

System

2154-14

Fuel Oil System Prestart Valve Checklist

2154-28

Diesel Generator Air Start System Prestart Valve Checklist

2173

Plant Prestart Checklist AC Power System - Plant

FP-OP-PEQ-01

Protected Equipment Program

71111.05

Fire Plans

Strategy A.3-01-C

Fire Zone 1-C, RCIC Room and Appendix R Cable

Strategy A.3-01-E

Fire Zone 1-E, HPCI Room - Reactor Building Elevation

896'

Strategy A.3-01-G Fire Zone 1-G, CRD Pump Room

Strategy A.3-02-H

Fire Zone 2-H, West Shutdown Cooling Area

Strategy A.3-12-A

Fire Zone 12-A, Lower 4 kv Bus Area (13 & 15)

Strategy A.3-14-A

Fire Zone 14-A, Upper 4 kv Bus Area (14 & 16)

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Strategy A.3-33

Fire Zone 33, EFT Building Third Floor

71111.11Q Miscellaneous

RQ-55-190

Evaluated Scenario, Unisolable Reactor Core Isolation

Cooling Leak Requiring Blowdown

08/20/2020

Procedures

2300

Reactivity Adjustment

71111.12

Corrective Action

Documents

501000047671

EDG Lister Diesel Fuel Leak

01/09/2021

501000047675

EDG Oil Weepage Found on TS-7206

01/12/2021

501000047690

G-3A Main Bearing Stud Nut Play

01/11/2021

501000047695

EDG Fuel Oil Weepage

01/12/2021

501000047696

EDG: Lube Oil Filter Drip Tray Crack

01/12/2021

501000047733

EDG Overspeed Limit Switch

01/13/2021

501000047750

EDG Local Governor Switch Defective

01/12/2021

501000047764

Potential Switch Adverse Trend

01/13/2021

50100047697

MCE Phase 3 to 1 mH Reading Low V-SF-10

01/12/2021

Miscellaneous

Core Spray Function Matrix

03/15/2021

XCELCORP007-

REPT-MT-FSW

Monticello Nuclear Generating Station 10 CFR 50.69

Categorization Document - FSW System

Procedures

OSP-MSC-0542-

Breaker Alignment and Indicated Power Availability

Verification of Required Offsite Circuits

Work Orders

700048277-0010

V-SF-10/MTR, Electrical Offline PM

71111.13

Corrective Action

Documents

501000048487

B3310 Overload Relay INOP

2/08/2021

501000048505

CR124 Overload Relays are Obsolete

2/09/2021

501000048524

Actuator not Available from Warehouse

2/09/2021

501000049819

Pomona Jacks Unable to be Installed

03/23/2021

71111.15

Corrective Action

Documents

501000048364

MO-2010 Weak Link Limit

2/03/2021

501000048542

FG-3171B Broken Sight Glass Window

2/08/2021

501000048750

P-211, RCIC Vac Pump Lantern Ring Issue

2/16/2021

501000048755

1-HPCI-R-6, LS-23-90 Upper Root Iso Leak

2/16/2021

501000049574

Seal Leak in Radwaste Door 47

03/14/2021

Procedures

FP-OP-OL-01

Operability

71111.19

Procedures

0187-01A

Emergency Diesel Generator / 11 ESW Comprehensive

Pump and Valve Tests

0192

Diesel Fuel Quality Check

NSP-DOL-0604

EDG Diesel Oil Pump Quarterly/Comprehensive Test

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

OSP-EDG-0550-

Emergency Diesel Generator - Consolidated Testing

Work Orders

700051052

2-506, 11 CRD Pump Relay Maintenance, Calibration,

and Test Tripping

03/10/2021

71111.22

Corrective Action

Documents

50100049859

Contact Resistance During ISP-ECC-0033

03/25/2021

Procedures

0032

ECCS Pump Start Permissive Sensor

0187-02B

Emergency Diesel Generator

255-06-1A-1

HPCI Quarterly Pump and Valve Test

03/24/2021

255-10-IA-1

Primary Containment Isolation Valve Exercise

71124.04

Miscellaneous

Unborn Child Protection Program Declaration

08/31/2020

71124.05

Calibration

Records

248

Reactor Building Vent Wide Range Gas Monitor Calibration

06/04/2020

290

Service Water Monitor Calibration

2/05/2021

28-01

Containment High Range Radiation Monitors Calibration

Procedure

01/12/2021

28-02

Containment High Range Radiation Detectors Calibration

Procedure

04/26/2019

21569

West Technology Inc Certificate of Calibration for REM500B

10/28/2020

5150

MG Telepole Calibration

10/30/2020

5158

Canberra Tennelec 5XLB Calibration Verification

08/03/2020

5171

RO-7 Calibration for 310410

2/04/2021

5175

DARM Calibration - Model #3090-3

11/04/2020

5712

Frisker Calibration Record

08/26/2020

5733

Air Sampler Calibration Data Sheet

04/01/2020

5854

SAM-11/LAM Calibration

06/22/2020

5871

ARGOS Calibration

2/02/2020

Miscellaneous

NX-19774

High Range Gamma Radiation Monitoring System Vendor

Manual

Procedures

R.09.22

Frisker Calibration and Functional Check

R.09.35

Air Sampler Calibration

R.09.50

DCA Area Radiation Monitor Checks

R.09.55

RO-7 Operation, Function Check and Calibration

R.09.61

SAM-11/LAM Operation and Calibration

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

R.09.62

ARGOS Contamination Monitors: Function Check and

Calibration

R.09.69

Operational and Functional Checks for Canberra Tennelec

5XLB

71151

Miscellaneous

QF0445

Unplanned Scrams per 7000 Critical Hours, Monthly

Submission Forms (January - December 2020)

QF0445

Unplanned Scrams/Complications, Monthly Submission

Forms (January - December 2020)

QF0445

Unplanned Power Changes per 7000 Critical Hours, Monthly

Submission Forms (January - December 2020)

71153

Drawings

NH-36047-1

(MONTI CAD

DWG: M-141)

Radwaste Solids Handling System Piping and

Instrumentation Diagram

NH-36255 9

(MONTI CAD

DWG: M-129)

Unit 1 Reactor Water Clean-Up Filter/Demineralizer System

P&ID

Procedures

A-5-100

On-Site Medical Emergency

Ops Man C.4-

B.02.04.A

Steam Leaks Outside Primary Containment

15