IR 05000263/2023002

Plant–Integrated Inspection Report 05000263/2023002

ML23219A155
Person / Time
Site:	Monticello
Issue date:	08/07/2023
From:	Hironori Peterson NRC/RGN-III/DORS/RPB3
To:	Hafen S Northern States Power Company, Minnesota
References
IR 2023002
Download: ML23219A155 (1)

Text

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT-INTEGRATED INSPECTION REPORT 05000263/2023002

Dear Shawn Hafen:

On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Monticello Nuclear Generating Plant. On July 20, 2023, the NRC inspectors discussed the results of this inspection with G. Brown, 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, Hironori Peterson, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket No. 05000263 License No. DPR22

Enclosure:

As stated

Inspection Report

Docket Number:

05000263

License Number:

DPR-22

Report Number:

05000263/2023002

Enterprise Identifier:

I2023002-0056

Licensee:

Northern States Power Company, Minnesota

Facility:

Monticello Nuclear Generating Plant

Location:

Monticello, MN

Inspection Dates:

April 01, 2023 to June 30, 2023

Inspectors:

S. Bell, Health Physicist

N. Bolling, Project Engineer

J. Cassidy, Senior Health Physicist

E. Fernandez, Senior Reactor Inspector

T. McGowan, Senior Resident Inspector

V. Myers, Senior Health Physicist

J. Nance, Operations Engineer

C. Norton, Senior Resident Inspector

J. Reed, Health Physicist

Approved By:

Hironori Peterson, Chief

Reactor Projects Branch 3

Division of Operating Reactor Safety

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

Type Issue Number Title Report Section Status LER 05000263/2022001-00 LER 2022001-00 for Monticello Nuclear Generating Plant, Loss of Control Room Envelope Operability 71153 Closed

PLANT STATUS

The unit began the inspection period at 80 percent rated thermal power in coast down. The licensee took the unit offline on April 15, 2023. The licensee commenced a reactor startup and brought the unit critical on May 13, 2023. The licensee increased reactor power and synchronized to the grid on May 14, 2023, to end refuel outage 31. The licensee continued to increase reactor power and reached rated thermal power on May 16, 2023. On May 26, 2023, the licensee lowered reactor power to 80 percent to perform a control rod pattern adjustment and returned to rated thermal power the same day. The unit remained at rated thermal power until the end of the inspection period.

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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed onsite portions of IPs. 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.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of summer (extreme heat and potential drought) for the following systems:

cooling tower structures 11 and 12, division 1 and division 2 125-volt dc battery rooms, and intake structure traveling screens that are required to be protected from the seasonal extreme weather conditions on June 21, 2023

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) Protected reactor vent path, RV271D (SRV D) on April 17, 2023

(2) Protected make up source, condensate service pumps 11 and 12 on April 17, 2023

(3) Uninterruptible power supply, Y81 after testing on May 9, 2023

(4) Meteorological tower walkdown on May 16, 2022

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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 (FZ) 2B, east hydraulic control unit area on April 15, 2023

(2) FZ 19C, feedwater pipe chase on April 17, 2023

(3) FZ 16, corridor, turbine building east and west, elevations 911' and 931' on April 18, 2023

(4) FZ 17, turbine building north cable corridor 941' on April 19, 2023

(5) FZ 9, main control room on April 27, 2023

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on June 17, 2023

71111.08G - Inservice Inspection Activities (BWR)

BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding

Activities (IP Section 03.01)

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1)

1. Ultrasonic examination (UT) residual heat removal (RHR) pipe-to penetration

weld component ID: W1

3. Magnetic particle examination (MT) carbon steel variable spring /slide

component ID: H1WA

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 shutdown operations including taking the generator offline, and a transition from Mode 1 to Mode 3 using a planned scram of the mode switch for refuel outage 31 on April 14, 2023

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

(1) The inspectors observed and evaluated operations crew 1 just in time training for reactor startup, turbine overspeed test, and reactor vessel pressure test in support of refuel outage (RFO) 31 on April 12, 2023

71111.12 - Maintenance Effectiveness

Aging Management (IP Section 03.03) (1 Sample)

The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:

(1) Physical inspection of pipe penetration RWN53-HC, condensate drip tank to waste collector tank, extent of condition for November 22, 2022, failure of control rod drive suction pipe failure on April 26, 2023

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 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) Observed and validated risk mitigating actions were used during reactor pressure vessel head detention and lift on April 17, 2023

(2) Contingency to refill of emergency diesel generator day tanks on April 18, 2023

(3) Reviewed the planning for, and observed, the risk mitigation strategies implemented for deenergizing and isolating Bus 16, division 2 - 4.16 KV safety-related Bus, on April 17 and 18, 2023

(4) Observed and evaluated risk management actions associated with recirculation pump 11 speed control issues on May 15 and 16, 2023

(5) Observed and evaluated risk management actions associated with Y81 UPS inverter unexpected static switch transfer (partial group II isolation) on May 04, 2023

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

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

(1)

===501000072718, Failure to complete asfound diagnostic on MO2397 reactor water cleanup isolation valve within American Society of Mechanical Engineers (ASME)required interval (2)501000073646 Jet pump flow discrepancy (3)501000072235, RHR 11 pump failed to start manually (4)501000072261, Fuse 10A-F19A (panel C32) found open

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01)===

(1) The inspectors evaluated refueling outage 31 activities from April 14,2023 to May 14, 2023

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01) (10 Samples)

(1)1624 Relay, PMT/ return to service, time delay tripping relay, work orders

===7000856320010 and 7000856320030

(2) Bus 16 relay testing following relay preventative maintenance on April 24, 2023 (3)011302, automatic depression system bypass timer test following maintenance on May 2, 2023 (4)138605, 'B' loop RHR service water system external pipe inspection following maintenance window on May 2, 2023 (5)138601, 'B' loop emergency diesel generator emergency service water external pipe inspection following maintenance on May 2, 2023 (6)0456, Testing following drywell and suppression chamber valve seal replacement on May 2, 2023 (7)025504-IA2, 'B' loop RHR system cold shutdown valve operability tests following maintenance window on May 2, 2023 (8)025504-1A12, 'B' loop RHR system quarterly pump and valve tests following maintenance window on May 2, 2023 (9)0127, Drywell-torus vacuum breaker functional test following maintenance on May 5, 2023

(10) HPCI torus suction check valve operability test following inspection and maintenance on May 5, 2023 Surveillance Testing (IP Section 03.01)===

(1) Source range monitor and Intermediate range monitor functional and logic system functional test, on April 14, 2023

(2) Core spray, shutdown pump and valve operability testing during cavity flood up on April 18, 2023

(3) Alternate shut down system functional test for diesel generator 12, on April 25, 2023

(4) Low pressure emergency core cooling system (ECCS) automatic initiation and loss of auxiliary power test, division 2 on May 04, 2023

(5) Control rod drive scram insertion time test on May 08, 2023

(6) HPCI pump flow and valve tests with reactor pressure less than or equal to 165 psig on May 14, 2023

Inservice Testing (IST) (IP Section 03.01) (2 Samples)

(1) Reactor coolant pressure boundary leakage test on May 8, 2023

(2) Control rod drive scram insertion time test on May 8, 2023

Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)

(1) P506 (FLEX) portable diesel fire pump testing, on June 21,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Workers exiting the radiologically controlled area (RCA) at Unit 1 during a refueling outage

(2) Radioactive material inventory of the spent fuel pool, 1027' reactor building

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1)

1R31 Turbine building stop valves/control valves/bypass valves; radiological work

permits (RWP) 235211 and associated radiation protection job plan (2)

1R31 Drywell checklist activities and associated radiation protection job plan

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)

The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas:

(1) Reactor building 935' drywell access area

(2) Reactor building 935' 'A' RHR

(3) Reactor building 1027' reactor head stand area

(4) Radioactive waste building 935' barrel storage aisle Radiation Worker Performance and Radiation Protection Technician Proficiency (IP

Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.03 - InPlant Airborne Radioactivity Control and Mitigation

Temporary Ventilation Systems (IP Section 03.02) (1 Sample)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) Reactor building 1027' reactor head stand

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (8 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) Portable ion chambers in the radiation protection instrument calibration facility

(2) Portable neutron radiation instruments ready for use

(3) Portable friskers in the radiation protection instrument calibration facility

(4) Tool and equipment monitor at the primary RCA exit

(5) Whole-body contamination monitors at the primary RCA exit

(6) Portal monitors at the guardhouse exit

(7) High range dose rate meters in the radiation protection instrument calibration facility

(8) Wide range gaseous monitor in the reactor building

Calibration and Testing Program (IP Section 03.02) (13 Samples)

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

(1) AFC-90L air sample calibrator 13116

(2) AMP100 A10003

(3) ARGOS 5AB Zeus AZ14

(4) ISolo 532278

(5) DMC 2000 EDMG30047

(6) FastScan 1 whole-body counter

(7) HPGe (A) detector 1

(8) Model 93 - 9316 dose rate meter

(9) AMS4 8 serial number: 02657

(10) H809 air sampler R2

(11) Gem-5 portal monitor PM1

(12) RO7 dose rate meter RO79

(13) SAM11 SAM4 Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (2 Samples)

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

(1) Wide range gas monitor for the site stack release

(2) Containment area high range radiation monitor in the drywell

OTHER ACTIVITIES-BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===

(1) April 01, 2022 through March 31, 2023 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)

(1) October 1, 2022 through April 30, 2023

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

(1) April 01, 2022 through March 31, 2023

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) October 1, 2022 through April 30, 2023 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) October 1, 2022 through April 30, 2023

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Reviewed and evaluated licensee corrective actions for 501000052353, Startup delay-deviation in predictors experienced during RFO 30

(2) The inspectors reviewed the licensees corrective actions related to the onsite monitoring well that indicated tritium activity above the Offsite Dose Calculation Manual and Nuclear Energy Institute Groundwater Protection Initiative reporting levels. Specifically, the inspectors -

reviewed the methodology used to quantify the amount of radioactive material leaked to groundwater reviewed the methodology used to characterize the plume of contaminated groundwater onsite, including observation of collection and analysis of contaminated groundwater.

assessed whether contaminated groundwater migrated offsite.

walked down the recovery system, including the temporary above ground storage locations and processing using temporary hoses to move the contaminated groundwater around the site.

reviewed incidental spills that occurred as a result of handling more than one million gallons of contaminated groundwater.

discussed future plans for longer term treatment of the collected contaminated groundwater.

reviewed the criteria, methodology, and requirements for reporting leaks and spills that contain licensed radioactive materials.

(3) The inspectors reviewed the safety culture work environment at Monticello to ensure that an environment exists where individuals can raise safety concerns without fear of retaliation.

71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01)

(1) The inspectors evaluated dropped blade guide over reactor core and recovery on April 23, 2023.

Event Report (IP Section 03.02) (1 Sample)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 2022001-00, Monticello Nuclear Generating Plant, Loss of Control Room Envelope Operability (ADAMS Accession No. ML22189A111). On May 13, 2022, the licensee identified an unplanned loss of control room operability, TS limiting condition of operation (LCO) 3.7.4.B, due to excessive through wall steam leakage from an air ejector that exceeded alternate source term limits. The inspectors determined that the licensee took timely corrective actions to mitigate the steam leakage and exit LCO.

The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is closed.

Reporting (IP Section 03.05) (1 Sample)

(1) The inspectors reviewed and evaluated the following licensee event notification (EN)made by the station to the NRC Headquarters Operations Center:

Review and assessment of the licensee's non-emergency report made under 10 CFR 50.73(a)(1) and 10 CFR 50.73 (a)(2)(iv)(A) for an invalid actuations of Division 2 primary containment isolation logic that occurred while in a refueling outage on April 28, 2023, and May 4, 2023, as documented in NRC EN

INSPECTION RESULTS

Assessment 71152A During the refuel outage April 15 through May 14, 2023, the inspectors conducted a baseline problem identification and resolution sample to evaluate safety-conscious work environment (SCWE) in accordance with Inspection Procedure (IP) 71152, Problem Identification and Resolution, Section 3.04 using guidance provided in IP 93100, Safety-Conscious Work Environment Issue of Concern Follow-up, as applicable to determine whether a chilled work environment existed at the site. Inspection activities included, daily corrective action document reviews, individual worker interviews, work activity observations, an interview with the Employee Concerns Program representative, and review of independent safety culture assessment. The inspectors assessed that individuals exhibited a readiness to raise safety concerns and admit to errors without of a fear of retaliation. No SCWE issues were identified.

Observation: Onsite Monitoring Well with Tritium Activity Above Reporting Levels 71152A On November 22, 2022, the licensee reported an onsite monitoring well that indicated tritium activity above the Offsite Dose Calculation Manual and Nuclear Energy Institute Groundwater Protection Initiative reporting levels. Since that date, the licensee identified the location of the underground leak, repaired the leak, and implemented a recovery system to remove contaminated groundwater from the beneath the plant.

The inspectors determined -

the methodology used to quantify the amount of radioactive material leaked to groundwater was adequate.

the methodology used to characterize the plume of contamination onsite, including observation of collection and analysis of contaminated groundwater was adequate.

contaminated groundwater did not migrate offsite.

the recovery system, including the temporary above ground storage locations and processing using temporary hoses to move the contaminated groundwater around the site, was adequate.

incidental spills that occurred as a result of handling more than one million gallons of contaminated groundwater did not require new strategies to mitigate groundwater contamination.

future plans for longer term treatment of the collected contaminated groundwater would likely be able to meet NRC requirements.

the criteria, methodology, and requirements for reporting leaks and spills that contain licensed radioactive materials were consistent with the industry initiative and were performed in accordance with NRC requirements.

The inspectors concluded the licensee developed a holistic plan with significant input from contracted vendor with expertise in groundwater management and cleanup. The inspectors noted a high level of support (time and resources) from all levels of the organization to recover and store the contaminated groundwater onsite and prevent any uncontrolled release from the site.

Observation: Assessment of Corrective Actions for Deviation in Core Thermal Predictors during Startup form RFO 30 71152A In 2021, during the startup from refuel outage (RFO) 30, the licensee loaded the control rod sequence from RFO 29 into the rod worth minimizer. This resulted in two core thermal predictors exceeding thermal limits. The licensee was forced to hold power below 100 megawatts with the turbine online while a correction to the sequence was developed and implemented. Holding at this power threatened turbine integrity and placed the unit at risk for transient initiation. The licensee documented this issue in corrective action program item 501000052353. Corrective actions included a requirement to develop sequences for the new core designs when starting up after an RFO. The inspectors reviewed the startup sequence after RFO 31 to verify that the sequence was prepared and verified for the new core design.

The inspectors observed start up activities in the control room. No issues were identified.

Minor Performance Deficiency 71153 Minor Performance Deficiency: On April 23, 2023, during Monticellos refuel outage 31 core component movement activities, cell 1407 (containing a control blade, fuel support piece and two half blade guides (HBG)), was lifted using a Westinghouse multi-lift tool. During this activity, the two HBGs dropped from the lift tool. This resulted in one HBG coming to rest on the drywell radiation shield and the other on the shroud steam dam and a Westinghouse inspection tool. The blade guides did not contact nuclear fuel. The Westinghouse multi-lift tool is designed to lift a fuel support piece containing a control blade, fuel support piece, and a full blade guide. The performance deficiency was the licensee's use of the Westinghouse multi-lift tool to lift the two HBGs, for which it was not designed.

Screening: The inspectors determined the performance deficiency was minor. HBGs do not have sufficient mass to damage fuel when dropped in water from any height at any location over the core. The performance deficiency could not reasonably be viewed as a precursor to a significant event; if left uncorrected, it would not have the potential to lead to a more significant event; and it did not adversely affect a cornerstone objective.

EXIT MEETINGS AND DEBRIEFS

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

On July 20, 2023, the inspectors presented the integrated inspection results to G. Brown, Plant Manager, and other members of the licensee staff.

On April 20, 2023, the inspectors presented the radiation protection baseline inspection results to K. Nyberg, Director Site Performance & Operations Support, and other members of the licensee staff.

On April 28, 2023, the inspectors presented the Inservice Inspection Activities for Monticello M1R31 Outage inspection results to J. Ohotto, General Manager Fleet Operations, and other members of the licensee staff.

On May 25, 2023, the inspectors presented the groundwater protection inspection results to C. Domingos, Site Vice President, and other members of the licensee staff.

On June 8, 2023, the inspectors presented the Radiation Protection inspection results to S. Hafen, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Procedures

1150

Summer Readiness

Corrective Action

Documents

501000071357

Old MEET Tower Booms Still Up

03/14/2023

Drawings

NH362411

Reactor Pressure Relief

29201

Operability Testing of the Uninterruptible Power Supply

1308

MET Tower Inspection Procedure

B.08.0905

Condensate Storage System

Ops Man B

09.1305

20 Volt Uninterruptible AC Power Supply Startup

71111.04

Procedures

Ops Man

B.05.1604

Meteorological Monitoring

STRATEGY

A.302-B

East HCU Area

STRATEGY

A.309

Control Room

STRATEGY

A.316

Corridor, Turbine Building East and West (Elevations 911'

and 931')

STRATEGY

A.317

Turbine Building North Cable Corridor 941'

Fire Plans

STRATEGY

A.319-C

Feedwater Pipe Chase

Miscellaneous

A.341

Fire Brigade Drill Guide, Biocide Pump Fire (Drill Guide

"41.01")

06/17/2023

2176

Fire Drill Procedure

71111.05

Procedures

STRATEGY

A341

Sodium Hypochlorite Building (Bleach House)

501000071050

SWMIC Pitting Detected Line SW1018-GF

03/01/2023

Corrective Action

Documents

501000071164

CV1728, Evidence of Erosion and Pitting

03/07/2023

71111.08G

Corrective Action

Documents

Resulting from

501000072311

Torus External General Visual Examination Where Various

Locations of Coating Degradation was Noted Such that the

Base Metal was Exposed

04/13/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

501000072468

Thread Damage Observed while Performing IWE Program

Required VT1 Exams on the Bolted Connections for the

Drywell Equipment Hatch

04/19/2023

Inspection

501000072621

Examinations Performed per ASME XI Inservice Inspection

(ISI) Program. Visual Exam (VT3) of SR79 (Seismic

Restraint for RHRSW piping) Found Relevant Crack Like

Indications in the Weld Area

04/18/2023

201UT022

UT Report of Past Relevant Indication on T.H. Meridional

Weld Component ID: W7

05/03/2021

21UT050

UT Report of Past Relevant Indication on Pipe-toPipe Weld

Component ID: W2

05/05/2021

MN23MT-002

Magnetic Particle Examination (MT) of CS Variable Spring

/Slide Component ID: H1WA

04/25/2023

MN23UT-001

Ultrasonic Examination (UT) of RHR Pipe-to Penetration

weld Component ID: W2

04/20/2023

MN23VT-006

Visual Examination (VT3) of RHR Seismic Restraint

Component ID: SR79

04/21/2023

MNUT002

Ultrasonic Examination (UT) of RHR Pipe-to Penetration

weld Component ID: W1

4/20/2023

NDE Reports

MNVT007

Visual Examination (VT3) of RHR Box Restraint

Component ID: H4

04/20/2023

FPPE-NDE300

Dry Magnetic Particle Examination - Yoke/Coil

FPPE-NDE4001

Ultrasonic Examination of Ferritic Pipe Welds - Supplement

FPPE-NDE420

Ultrasonic Thickness Examination

FPPE-NDE530

Visual Examination, VT3

PDI-UT1

PDI Generic Procedure for the Ultrasonic Examination of

Ferritic Pipe Welds

G

Procedures

PEI-01.02.05

Monticello Nuclear Generating Plant 5th Interval ISI

Detailed Schedule

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

LP MTLOR-JIT-

20S

Turbine Overspeed Test JIT

SEG MTLOR-

JIT-011S

Reactor Vessel Pressure Test Simulator Exercise Guide

Miscellaneous

SEG MTLOR-

JIT-2023002S

Startup JIT

2167

Plant Startup

108

71111.11Q

Procedures

204

Plant Shutdown

71111.12

Work Orders

70012174330

RWN53-HC Perform Inspection

04/22/2023

501000072461

2401 Breaker Cubicle FME

04/18/2023

501000072462

Racking Shutter Stuck Mid-Position

04/18/2023

501000073154

Y81 Failure Caused Plant Transient

05/04/2023

Corrective Action

Documents

501000073594

Recirc Speed Adjust Not Raising

05/15/2023

2000005747

Operational Decision-Making Evaluation Checklist/11

Reactor Recirculation Pump

05/15/2023

2000005747

Operational Decision-Making Evaluation Checklist/Y81,

UPS Inverter

05/11/2023

Miscellaneous

QF2007

FPWM1RM-01

Planning and Approval of High Risk or Scheduled Risk

Work

485814-OCD

4KV Bus 14 Maintenance

485816-OCD

4KV Bus 16 Maintenance

210

Master RPV Disassembly Procedure

20

Remove RPV Head

Ops Man

B.09.0605

Operations Manual Section: 4.16 kV Station Auxiliary

System Operation

Tagout 14KV

485814-OCD

Bus Isolated Per 485814-OCD (This Tag does NOT

Ground Bus 14, and does NOT Isolate Power to Breaker

Secondary Contacts)

04/18/2023

Procedures

Tagout 14KV

485816-OCD

Bus Isolated Per 485816-OCD (This Tag Section does

NOT Ground Bus 16, and does NOT Isolate Power to

Breaker Secondary Contacts)

04/19/2023

71111.13

Work Orders

7001109170055

Contingency Refuel Day Tanks

71111.15

Corrective Action

501000072235

RHR Pump Failed to Start Manually

04/12/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

501000072261

Fuse 10A-F 19 (Panel C32) Found Open

04/12/2023

501000072718

Mech PM Done Prior to AsFound Diagnostic

04/24/2023

Documents

501000073646

Jet Pump Flow Discrepancy

05/17/2023

NX790546-3

S/D RHR System

Drawings

NX79050464

RHR S/D System

501000073372

CRD 3023 Position Indication Faulty

05/09/2023

501000073404

CRD 3023 Bad Reed Switches

05/09/2023

Corrective Action

Documents

501000073405

SCRAM Time App Errors During 0081

05/09/2023

Drawings

NH36248

(M122)

P&ID Core Spray System

Miscellaneous

Relay Field Test -

Test Values

Record CT Ratio

200/5; Switch

BKR 408

Monticello, 4.16 kV - Card HMN1 2615A; Switch BKR 408;

CT Ratio 1200/5; Breaker Ser. No. 1416 BT

04/20/2023

0081

Control Rod Drive SCRAM Insertion Time Test

0108

HPCI Pump Flow and Valve Tests with Reactor Pressure

Less Than or Equal to 165 PSIG

011302

ADS System Bypass Timer Test

27

Drywell-Torus Vacuum Breaker Inspection, Functional Tests

and Calibration of Position Indication Alarm Systems

25504-IA12

RHR Quarterly Pump and Valve Tests

105

25504-IA2

RHR System Cold Shutdown Valve Operability Tests

25506-IA4

HPCI 31 Torus Suction Check Valve Operability Test

25520-II C1

Reactor Coolant Pressure Boundary Leakage Test

041901

ASDS Cycle Functional Test for Diesel Generator 12

Switches

0456

Drywell and Suppression Chamber Valve Seal

Replacement

138601

EDG-ESW External Pipe Inspection Loop A and B

138605

RHRSW External Pipe Inspection Loop A and B

71111.24

Procedures

OSP-ECC-

056602

Low Pressure ECCS Automatic Initiation and Loss of

Auxiliary Power Test - Division 2 Outage

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

OSP-FIR-0608

P506 Portable Diesel Pump Testing

OSP-NIS-0013

SRM and IRM Functional and Logic System Functional Test

25503-IA2A

Core Spray - Shutdown Pump and Valve Operability Test

4850408-PM

2408, Bus 14/16 Tie Breaker Relay Calibration,

Maintenance, and Test Tripping

04/20/2023

7000854600010

Bus 16 Outage Relay Maintenance

Work Orders

7000856320030

24 RLY, PMT (Post-Maintenance Test) / RTS (Return to

Service)

04/21/2023

ALARA Plans

RWP 235506, 1R31 Drywell Checklist Activities, Work in

Progress Review and Associated Station ALARA

Committee Notes

04/19/2023

501000056045

Percent of Current PCE's from Uncontaminated Areas

09/15/2021

501000060298

Dose Rate Increase Following RWCU 'B' Backwash

2/10/2022

501000060815

Potential Trend in Airborne Radiation Levels

2/24/2022

501000060850

Radiological Condition Not as Expected

2/24/2022

501000063752

Irradiated Material in the Spent Fuel Pool

06/13/2022

501000064920

Equipment Reliability is Negatively Affecting Station

Collective Radiation Exposure

07/21/2022

501000066983

Contamination Found in RCA Clean Area

10/06/2022

501000068896

1001' RWCU Vault Air Sample >1.0 DAC

2/01/2022

Corrective Action

Documents

501000069147

Gap in Radiation Protection Survey Documentation

2/12/2022

Corrective Action

Documents

Resulting from

Inspection

501000072454

Ram Tags Not Per FPRP-NISP-04

04/18/2023

Radioactive Material Unconditional Release Log

04/15/2023

General Area Alpha Characterization

Undated

21 Annual Dose Report

Undated

21 1R30 Outage ALARA Report

Undated

Miscellaneous

High Radiation Area/Locked High Radiation Area Posting

and Boundary Checklist

04/16/2023

AWI-.04.05.13

Control of Items in the Spent Fuel Pool

71124.01

Procedures

FPRP-NISP-02

Radiation and Contamination Surveys

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

FPRP-NISP-05

Access Controls for High Radiation Areas

FPRP-SAC-01

Station ALARA Committees

FPRP-SEN-02

Radiological Work Planning and Controls

R.06.02

Unconditional Release of Equipment or Material

R.06.09

Storage and Inventory of Radioactive Material Outside the

Power Block

1R31 Refueling Outage Posting Change Matrix

04/15/2023

1R30 Refueling Outage Initial Shutdown Surveys for the

Drywell

Various

1R31 Refueling Outage Shutdown Surveys for the Drywell

Various

Reactor Building 962' General Area Surveys (09/25/2021,

09/22/2022, 03/26/2022, and 04/01/2023)

Various

Radiation

Surveys

VSDS-

M2023041917

Turbine Control Valves

04/19/2023

235211

1R31 Turbine Building Stop Valves/Control Valves/Bypass

Valves RWP and Associated Radiation Protection Job Plan

235506

1R31 Drywell Checklist Activities RWP and Associated

Radiation Protection Job Plan

235509

1R31 Control Rod Drive Changeout RWP and associated

Radiation Protection Job Plan

Radiation Work

Permits (RWPs)

235700

1R31 Refuel Floor Activities RWP and associated Radiation

Protection Job Plan

606000001645

Radiological Hazard Assessment and Exposure Controls

2/10/2022

Self-Assessments

606000001645

InPlant Airborne Control and Mitigation

2/10/2022

FP-RPAM-01

Alpha Monitoring Program

Procedures

FP-RP-RPP-01

Respiratory Protection Program

71124.03

Radiation

Surveys

Air Sample Analysis for Turbine Stop/Control Valve

Replacement

04/19/2023

2657

AMS-4 8

01/06/2022

13116

Air Sampler Calibrator AFC -90L

03/18/2021

310280 / R-2

H-809 Air Sampler

2/26/2023

2278

ISolo Calibration

2/06/2022

71124.05

Calibration

Records

9316

Model 93 Dose Rate Meter

01/04/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

A10003

AMP-100

01/28/2022

AZ-14

ARGOS 5AB Zeus

2/09/2023

EDMG30040

DMC-2000GN

2/16/2023

FastScan 1

Whole-Body Counter

10/21/2022

HPGE 'A'

Detector 1

High Purity Germanium Detector

05/03/2023

PM-1

Gem-5 Portal Monitor

03/29/2023

RO-79

RO-7 Dose Rate Meter

01/09/2023

SAM-4

SAM-11 Tool and Equipment Monitor

04/15/2023

501000062766

Smear Counter Efficiency Calculation Error

05/04/2022

501000063790

RP Instrument Failure

06/11/2022

Corrective Action

Documents

501000070730

HPGe Report Software Mislabeling Co-60

2/16/2023

501000074267

Beta Correction Factors Not Posted

06/07/2023

501000074272

Ni-63 Sealed Source Leak Tests

06/07/2023

Corrective Action

Documents

Resulting from

Inspection

501000074307

Frisker Source Checks Lowest Range Only

06/07/2023

5XLB Analysis of

Ni-63 Leak Test

Calculation

Technical White Paper

Technical Basis

Document 12002

Ni-63 Detection Capability of the Tennelec 5XLB

Technical Basis

Document 19002

Sensitivity Study of ARGOS 4/5, PM7, and GEM-5 Monitors

for Passive Whole-Body Counting

Technical Basis

Document 19003

Neutron DLR, SRD, and Rem Ball Characterization

Engineering

Evaluations

Technical Basis

Document 22001

Neutron Factor for Drywell Startup/Power Entries

0163

Stack Wide Range Gas Monitor Calibration

248

Reactor Building Vent Wide Range Gas Monitor Calibration

2802

Containment High Range Radiation Detectors Calibration

Procedure

Procedures

FP-RP-ICC-01

Instrument Control and Calibration/Function Check

Frequencies of RP Instruments

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

R.09.61

Sam-11/LAM Operation and Calibration

R.09.62

ARGOS Contamination Monitors: Function Check and

Calibration

R.09.72

Model 3030P Alpha-Beta Smear Counter Operation

QF0445

NRC and Data Collection and Submittal - SSFFs (April 2022

through March 2023)

Miscellaneous

QF0445

NRC Data Collection and Submittal - RCS Total Leakage

(April 2022 through March 2023)

71151

Procedures

FP-PA-PI-02

NRC and MOR Performance Indicator Reporting

0501000073805

FRAC Tank Notifications Missing the Mark

0501000073805

501000052353

Startup Delay-Deviation in Predictors

05/20/2021

501000073752

Pump in T-GW-13 Found Tripped

05/21/2023

501000073770

Pump in T-GW-16 Found Tripped

05/21/2023

501000073788

FRAC Tank Overflow Due to Gauge Issue

05/22/2023

501000073795

FRAC Tank Farm in ISFSI Parking

05/22/2023

501000073804

FRAC Tank Overflowed While Filling

05/22/2023

501000073826

[Four] 4 Hour Non-Emergency Event Notification

05/23/2023

501000073833

Groundwater Transfer - Incorrect Risk

05/23/2023

501000073852

State Report Recorded Incident Date

05/23/2023

501000073870

Elevation - GW Mitigation Efforts

05/23/2023

Corrective Action

Documents

501000073892

FRAC Tank #20 Level Gauge Removed

05/24/2023

501000073778

RAM Labels Not Filled Out on FRAC Tanks

05/22/2023

501000073787

FRAC Tack Overflowing from Weather

05/22/2023

501000073791

Berms at MW-12 and FRAC Tanks Folded

05/22/2023

501000073807

NRC Request for Observation - Construction of Retention

Ponds

05/22/2023

501000073809

Unable to Locate Level Gauge Calibration

05/23/2023

501000073823

No Definition of "Abnormal Discharge"

05/23/2023

501000073824

ODCM-02.01 2.4.1 Incorrect Reference

05/23/2023

501000073843

Procedure 0369 Incorrect ODCM Reference in A.1

05/23/2023

501000073859

Basis for Monitoring Well Purge Volume

05/24/2023

501000073860

Shift Manager Not Properly Notified

05/23/2023

71152A

Corrective Action

Documents

Resulting from

Inspection

501000073875

NRC Question on Lake Tank Level Monitor

05/24/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

501000073876

NEI 07-07 Periodic Briefings

05/24/2023

501000073885

Minimum Dilution Flow

05/25/2023

501000073902

Monitoring Well Label Degraded

05/24/2023

501000073905

RP Notification for FRAC Tank Filling

05/25/2023

501000073911

Evaluate Installation of Anti-Siphon

05/25/2023

501000073917

Question on NEI 07-07

05/26/2023

Engineering

Evaluations

601000004237

Intermediate Groundwater Storage

Miscellaneous

ODCM-08.01

Reporting Requirements

0369

Temporary Outdoor Radioactive Liquid Tanks Level

Instrumentation Functional Test

2300

Reactivity Adjustment

5148

Monitoring Well Sample Log

FP-OP-REP-01

Event Reporting and Notification Process

Procedures

I.05.50

Sampling Groundwater Monitoring Wells

700116710

Water Removal

700117970

Groundwater Processing - Water Demand Demineralizer

Skid and Transfer

700117970

Groundwater Processing

Work Orders

700166710

Sample at Lake Tank

Corrective Action

Documents

501000072688

Two Half Blade Guides, HBGs, Released

04/23/2023

71153

Work Orders

2000014849

Foreign Material Recovery Plan

04/23/2023