IR 05000263/2022012
| ML22348A211 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/15/2022 |
| From: | Richard Skokowski NRC/RGN-III/DORS/EB2 |
| To: | Domingos C Northern States Power Company, Minnesota |
| References | |
| IR 2022012 | |
| Download: ML22348A211 (11) | |
Text
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000263/2022012
Dear Christopher Domingos:
On November 22, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Monticello Nuclear Generating Plant and discussed the results of this inspection with Mr. S. Hafen, Plant Manager 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, Richard A. Skokowski, Chief Engineering Branch 2 Division of Operating Reactor Safety Docket No. 05000263 License No. DPR-22
Enclosure:
As stated
Inspection Report
Docket Number:
05000263
License Number:
Report Number:
Enterprise Identifier:
I-2022-012-0020
Licensee:
Northern States Power Company, Minnesota
Facility:
Monticello Nuclear Generating Plant
Location:
Monticello, MN
Inspection Dates:
November 14, 2022 to November 22, 2022
Inspectors:
M. Abuhamdan, Reactor Inspector
M. Gangewere, Reactor Inspector
D. Melendez-Colon, Reactor Inspector
E. Sanchez Santiago, Senior Project Engineer
Approved By:
Richard A. Skokowski, Chief
Engineering Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline 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.
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.
REACTOR SAFETY
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from March 2019 through November 2022.
- (1) SCR-19-006, Temporarily Isolate B CRV Via RO-4258B
- (2) SCR-19-0094, Removal of D311-04 and D312-05 Components from Scope of EQ Program
- (4) SCR-20-0050, 11 EDG Droop Modification
- (5) SCR-19-0056, OffGas Recombiner Controller Upgrades
- (6) SCR-19-0068, Increase Design Temp for RWN60-1 1/2-HJ
- (8) SCR-20-0054, Normally Closed Air Valves
- (9) SCR-20-0071, 13 ESW Quarterly Pump and Valve Test New Rev. 64
- (10) SCR-20-0104, Use of Uncertainties for HPCI/RCIC Pump Discharge Pressure in Surveillance Acceptance Criteria
- (11) SCR-20-0101, Update ISP-RHR-0552-02 to Perform LSFT Testing
- (13) SCR-20-0130, (evaluation) Use of Atrium 10XM Lead Test Assemblies
- (14) SCR-20-0140, Revise USAR-14 Table 14.7
- (16) SCR-21-0022, Correct ISP-RHR-0552-02 Setpoints
- (18) SCR-21-0064, 0136 ILRT - Lower Torus Water Temperature Band
- (19) SCR-21-0080, Cranes and Heavy Loads - System Operation
- (20) SCR-21-0102, RHRSW Pump In-Service Testing
- (21) SCR-22-0072, Change to Intercell Acceptance Criteria for D8 Battery
- (22) SCR-22-0080, Primary Containment Isolation Valve Exercise
- (23) SCR-22-0029, Revision of 2167 Plant Startup
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On November 22, 2022, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. S. Hafen, Plant Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
01-082
Basis for Monticello DBLFPB for 10CFR50.59 Criterion 7
10-082
2C
10-117
0A
10-118
0A
11-325
Functional Analysis for Non GL 89-10 Program MOVs13-055
Core Spray and LPCI Flow Delivered to Reactor Vessel for
Safety Analysis
Rev.2
16-006
Hard Pipe Vent D8 Battery HCVS 125VDC Battery
Calculation
Rev.1
16-014
Monticello LOCA Break Spectrum for EPU/EFW with
ATRIUM 10XM Fuel and Revised Modeling Parameters
Rev.1
Calculations18-002
HPCI/RCIC Discharge Pressures for Tech Spec Surveillance
Testing
01001494
Review of Assumptions in Accidents and License Bases
Events for Control of Plant Initial Conditions & Operator
Actions
03/13/2001
01476976
Action Request-Question on the 12 EDG Voltage Regulator
Wiring
06/12/2015
01496761
Potential Non-Conservative Tech Spec for EDG Voltage
2/10/2015
500001496761
Potential Non-Conservative Techl Spec for EDG Voltage
10/14/2015
501000039632
94-142 Weak Link Error
04/13/2020
501000044839
TMOD Extension Form Not Completed for EC
09/30/2022
501000045266
94-142 Additional Weak Link Errors
10/08/2020
501000047373
CFR 50.59 Screening Required
2/25/2020
501000048821
Unable to Adjust Switch to New Setpoint
2/18/2021
501000052371
Prolonged Operation Below 100 MWE
06/25/2021
501000055651
CV-1729 Controller Issue
09/13/2021
501000055698
CV-1729 ECR Testing Not Performed
09/03/2021
501000057242
EC Approved w/o Qual'd 50.50 Review
10/14/2021
501000057287
EOC-EC Approved w/o Qual'd 50.59 Review
10/16/2021
Corrective Action
Documents
501000057444
TCR Roll-Up CAP 10.19
10/19/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000059567
CFR 50.59 Screening Required
01/08/2022
501000059582
CFR 50.59 Screening Required
01/07/2022
501000059636
NRC Scaffold Question
01/11/2022
501000060154
1047-01 Tags Hanging >70 Days
01/29/2022
501000060155
FZ-3795 Temporary Configuration > 70 Days
01/29/2022
501000060510
CFR 50.59 Screening Required
2/11/2022
501000062038
CFR 50.59 Screening Required
04/08/2022
501000062298
CFR 50.59 Screening Required
04/15/2022
501000062487
CFR 50.59 Screening Required
04/22/2022
501000062628
Sub-Standard 50.59 Screenings
04/28/2022
501000063094
CFR 50.59 Scm for Tags Hang > 70 Days
05/13/2022
501000063269
Tags Hanging Greater than 70 Days 50.59
05/20/2022
601000002203
Close/Isolate/Abandon Drywell Air Line
03/12/2020
2000014958
B.01.04-05 R55 Complete
2/27/2020
2000015997
ISP-RHR-0552-02 Rev 5 Complete
05/01/2020
2000019462
C.5-2007 rev 23 EOP SAMG Update
01/29/2021
2000019785
C.5-GM-02.01 Rev 24 EOP/SAMG Update
2/22/2021
2000020067
C.5-2001 Rev 1 EOP SAMG Updates
03/11/2021
501000068477
225059-SCR-21-22 Typo
11/14/2022
501000068564
225059: Obs. Re: Clearance Orders
11/17/2022
501000068605
225059: Generic Screening Concern
11/17/2022
Corrective Action
Documents
Resulting from
Inspection
5011000068595
225059: Obs. Re: Scaffolds
11/16/2022
NF-93216-1
Instrument Air Line Isometric
NH-36049-12
P&ID Instrument Air Reactor Building and Drywell
Drawings
NH-36665
P&ID Service Water System & Make-up Intake Structure
104
0000028104
EC 26083 ECN - Battery Connection Resistance
Rev.0
601000000149
601000000149 - 11 EDG Voltage Regulator Droop
Modification
Rev.0
601000000429
OffGas Recombiner Controller Upgrades
Rev.0
601000000661
Replace DC Overloads in EQ Buckets
Rev.0
601000001143
Isolation of FSW D2 via RO-4258B
601000001564
Increase Design Temp for RWN60-1 1/2-HJ
Rev.0
Engineering
Changes
601000002221
Evaluate MOV Functions
2/04/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60100001549
Revise Calculation 08-055 - RHR Aux Air Compressor
Rev.0
Engineering
Evaluations
600000845060
Evaluate the Impact of the EPG/SAG Revision 4 Changes on
the ATWS Event
19-0068
Increase Design Temp for RWN60-1 1/2-HJ
Rev.0
19-056
OffGas Recombiner Controller Upgrades
Rev.0
20-0101
Update ISP-RHR-0552-02 to Perform LSFT Testing
Rev.0
20-0108
New Online LSFT Procedures to Support ECCS Testing
Efficiency
Rev.0
AWI-09.04.01
Technical Position Number TP 13
601000001552
Drywell Equipment Drain Sump
11/02/2020
601000002969
05/01/2021
2000021383
2167 Revision 104 Complete
08/09/2022
2000022857
255-05-III-4A Rev 35 One Time Use TCR
09/29/2021
2000022859
255-05-III-2A Rev 35 Once Time Use TCR
09/29/2021
ANSI 831.1 -
1977Property "ANSI code" (as page type) with input value "ANSI 831.1 -</br></br>1977" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. EDITION
Power Piping
05/01/1977
B.02.03-01
Reactor Core Isolation Cooling
B.03.02-05
IST-BASIS
Pump and Valve In-Service Testing Program Basis
SCR-04-0932
Procedure, Drawing, VTM & Database Changes that are
Editorial as Defined in Part I
Rev. 6
(02/11/2020)
SCR-19-0006
Temporarily Isolate B CRV Via RO-4258B
SCR-19-0094
Removal of D311-04 and D312-05 Components from Scope
of EQ Program
Rev.0
SCR-19-0105
03-009 AOV Component Calculation AO-2541A,B &
AO-2561A,B
SCR-20-0047
Evaluation of MOV and IST Program Valve Functions
SCR-20-0050
EDG Droop Modification
Rev.0
SCR-20-0054
Normally Closed Air Valves
SCR-20-0071
ESW Quarterly Pump and Valve Test New Rev. 64
SCR-20-0104
Use of Uncertainties for HPCI/RCIC Pump Discharge
Pressure in Surveillance Acceptance Criteria
Miscellaneous
SCR-20-0130
Use of ATRIUM 10XM Lead Test Assemblies
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SCR-20-0138
SCR-20-0140
Revise USAR-14 Table 14.7
Rev.0
SCR-21-0012
Evaluation for Implementation of BWROG Rev 4 EOP
SCR-21-0022
Correct ISP-RHR-0552-02 Setpoints
SCR-21-0054
SCR-21-0064
0136 ILRT - Lower Torus Water Temperature Band
SCR-21-0080
Cranes and Heavy Loads - System Operation
Rev.0
SCR-21-0102
RHRSW Pump In-Service Testing
SCR-22-0029
Revision of 2167, Plant Startup
SCR-22-0072
Change to Intercell Acceptance Criteria for DS Battery
Rev.0
SCR-22-0080
PCR 602000026536 Primary Containment Isolation Valve
Exercise
Operability
Evaluations
01496761-01
Potential Non-Conservative Tech Spec for EDG Voltage
10/23/2015
0108
HPCI Pump Flow and Valve Tests with Reactor Pressure
Less than or Equal to 165 psig
0114
RCIC Pump Flow and Valve Tests with Reactor Pressure
Less than or Equal to 165 psig
0136
Integrated Primary Containment Leak Rate Test
255-05-III-2A
Comprehensive 12 RHRSW Pump and Valve Tests
255-05-III-4A
Comprehensive 14 RHRSW Pump and Valve Tests
255-06-IA-1
HPCI Quarterly Pump and Valve Tests
110
255-06-III-1
HPCI Comprehensive Pump and Valve Tests
255-08-IA-1
RCIC Quarterly Pump and Valve Tests
255-08-III-1
RCIC Comprehensive Pump and Valve Tests
255-10-IA-1
Primary Containment Isolation Valve Exercise
and 49
255-11-III-3
ESW Quarterly Pump and Valve Tests
1047-01
Shift Supervisor Checklist
B.08.15-05
Operations Manual Section: Cranes an Heavy Loads
Rev.31
C.5-1100
RPV Control
C.5-1100
RPV Control (MODE 1, 2, 3)
C.5-3502
Procedures
D8 125V DC Battery Check
Rev.6
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EWI-08.03.02
Logic System Testing Program
Rev.10
FG-E-SE-03
50.59 Resource Manual
FG-E-SE-03
50.59 Resource Manual
FP-E-SE-03
CFR 50.59 and 72.48 Processes
FP-G-DOC-04
Procedure Processing
39, 43
FP-MA-FSC-01
FP-PE-MOV-07
Motor Operated Valve Program
Reactor LO-LO Level ECCS Initiation & HI Level RCIC/HPCI
Turbine Trips Trip Unit Test and Calibration Procedure with
Rev.0
ECCS HIGH Drywell Pressure Sensor with LSFT
Rev.0
ECCS Pump Start Permissive Sensor with LSFT
Rev.0
Reactor Recirculation LOOPS DP, LPCI Select Interlock
Channel Calibration
5, 7, 8
Reactor Steam Dome Pressure Low - Channel Calibration
and Channel Functional Test with LSFT
Rev.0
MPS-1100
Specification for the Analysis of Piping and Piping Support
Systems
Rev. 11
Ops Man B.01.04-
Reactor Recirculation System
55, 56
Ops Man B.03.04-
Residual Heat Removal System
QF0501
50.59 Screening
14