IR 05000263/2021001
ML21120A065 | |
Person / Time | |
---|---|
Site: | Monticello ![]() |
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:
Report Number:
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
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
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)
NH-36250 (M-
24)
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
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
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
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
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
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
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
Corrective Action
Documents
50100049859
Contact Resistance During ISP-ECC-0033
03/25/2021
Procedures
0032
ECCS Pump Start Permissive Sensor
0187-02B
255-06-1A-1
HPCI Quarterly Pump and Valve Test
03/24/2021
255-10-IA-1
Primary Containment Isolation Valve Exercise
Miscellaneous
Unborn Child Protection Program Declaration
08/31/2020
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)
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
Procedures
A-5-100
On-Site Medical Emergency
Ops Man C.4-
B.02.04.A
Steam Leaks Outside Primary Containment
15