IR 05000263/2024003

Integrated Inspection Report 05000263/2024003

ML24318C235
Person / Time
Site:	Monticello
Issue date:	11/13/2024
From:	Richard Skokowski NRC/RGN-III/DORS/RPB3
To:	Hafen S Northern States Power Company, Minnesota
References
EPID I-2024-003-0062 IR 2024003
Download: ML24318C235 (1)

Text

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000263/2024003

Dear Shawn Hafen:

On September 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Monticello Nuclear Generating Plant. On October 22, 2024, 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, Richard A. Skokowski, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket No. 05000263 License No. DPR-22

Enclosure:

As stated

Inspection Report

Docket Number:

05000263 License Number:

DPR-22 Report Number:

05000263/2024003 Enterprise Identifier:

I2024003-0062 Licensee:

Northern States Power Company, Minnesota Facility:

Monticello Nuclear Generating Plant Location:

Monticello, MN Inspection Dates:

July 01, 2024, to September 30, 2024 Inspectors:

N. Bolling, Resident Inspector J. Kutlesa, Sr. Emergency Preparedness Inspector T. McGowan, Resident Inspector C. Norton, Senior Resident Inspector J. Reed, Health Physicist Approved By:

Richard A. Skokowski, 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

None.

PLANT STATUS

Monticello began the inspection period at rated thermal power. On September 12, 2024, the unit was down powered to 50 percent of rated thermal power for turbine testing and main steam isolation valve testing. The unit was returned to rated thermal power the same day and remained at or near rated thermal for the remainder 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 seasonal heavy rains for the following systems:

Intake structure and residual heat removal (RHR) service water system on August 27, 2024

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) Fire protection system on July 10, 2024

(2) Division 1 control room ventilation (CRV) and emergency filtration train (EFT),protected equipment on July 24, 2024

(3) Division 2 RHR on September 24, 2024

(4) Division 2 250Vdc electrical system on September 27, 2024

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) Recirculation pump motor-generator set room on July 8, 2024

(2) Emergency filtration building 1st floor, division 1 on July 9, 2024

(3) Fuel pool skimmer tank room on July 10, 2024

(4) Reactor feed pump and lube oil reservoir room on July 15, 2024

(5) Lube oil storage tank room on July 16, 2024

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 July 20, 2024

===71111.07 A - Heat Exchanger/Sink Performance Annual Review (IP Section 03.01) (1 Partial)

The inspectors evaluated readiness and performance of:

(1)

(Partial)

Division 2 emergency diesel generator heat exchanger watched data gathering on July 29, 2024

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Requalification Training/Examinations (IP Section 03.02)===

(1) The inspectors observed and evaluated reactor operator as found simulator examination on August 19, 2024.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples)

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

(1) Change out of LC 1057 (14 B high pressure dump valve level controller)on July 31, 2024, and August 6, 2024

(2) Replacement of components and load test of 250 Vdc safety-related (D80)battery charger for battery 16 on August 20, 2024

(3) Drainage of waste collector tank T25 involving short limiting condition for operations shutdown action for secondary containment on September 9, 2024

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)

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) Verification that set screw on the pinion gear on motor operated valve (MO) 2012, division 2 outboard low pressure coolant injection valve, was in place on August 7, 2024

71111.15 - Operability Determinations and Functionality Assessments

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

The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:

(1)

===501000088600, MO2012 pinion may not be secured on the division 2 outboard low pressure coolant injection valve (2)501000088828, core spray header differential pressure switch failed to reset (3)501000089259, APRM2 [average power range monitor] non-critical self-test fault (4)501000087690, EQASCO activation energy issue SV2379 and SV2380

[torus to drywell vacuum breakers]

(5)501000090055, VD9216B [control room fresh air damper] did not open as expected

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

=

The inspectors evaluated the following temporary or permanent modifications:

(1) Temporary disconnect of relief valve annunciator for 2R transformer on August 21, 2024

Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)

(1) The inspectors verified the site SAMG were updated in accordance with the BWR generic sever accident technical guidelines and validated in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, Revision 1.

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) (5 Samples)

(1) Reactor core isolation cooling (RCIC) room air cooling unit on August 16, 2024

(2) Division 2 250 Vdc battery charger D80 on August 20, 2024

(3) APRM 2 after replacement of circuit card on August 29, 2024

(4) RHR division 1 torus spray inboard valve following corrective maintenance on September 9, 2024

(5) Hydraulic control unit (HCU) 3815 after replacement of accumulator on September 12, 2024

Surveillance Testing (IP Section 03.01) (5 Samples)

(1) Emergency filtration treatment system, division 1 operability test on July 9, 2024

(2) Security system emergency generator operability check and alarm on July 10, 2024

(3) Local power range monitor (LPRM) calibration on July 11, 2024

(4) RCIC steam line high area temperature test and calibration on August 13, 2024

(5) Division 2 RHR system quarterly pump and valve testing on September 25, 2024

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

(1) P505 portable diesel fire pump test on August 1, 2024

71114.02 - Alert and Notification System Testing

Inspection Review (IP Section 02.0102.04) (1 Sample)

(1) The inspectors evaluated the following maintenance and testing of the alert and notification system:

• Annual siren inspection and maintenance records for the period of July 2022 to Jul 2024

• Weekly alert notification system (siren) tests for the period of July 2022 to July 2024

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.0102.02) (1 Sample)

(1) The inspectors evaluated the readiness of the emergency preparedness organization.

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the maintenance of the emergency preparedness program.

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

In addition to the normal inspection of this inspection procedure, the NRC inspectors utilized additional resources to review the progress and results of the licensees 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, which was previously reviewed (ML23219A155) in 2023. The additional inspection scope of the licensees actions included:

• The revised methodology used by the licensee to quantify the amount of radioactive material leaked to groundwater

• The revised recovery system which was changed from temporary above ground storage tanks to permanent engineered retention ponds

• The methodology and results used to determine the tritium activity in the Mississippi River from background or other sources not attributed to plant operations

• The methodology and results for the calculations of tritium moving to the river and the associated dose to the nearest receptor for this abnormal discharge The results from this additional scope are included as an observation within this report.

Walkdowns and Observations (IP Section 03.01) (4 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Unit 1, reactor building ventilation stack and monitor

(2) Unit 1, offgas stack and monitor

(3) Water storage pond, pumphouse, and sample hut

(4) Unit 1, service water system and monitor

Sampling and Analysis (IP Section 03.02) (4 Samples)

Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:

(1) Reactor building weekly wide range gas monitor (WRGM) sample

(2) Plant offgas stack weekly WRGM sample

(3) Water storage pond sample

(4) Drywell purge sample

Dose Calculations (IP Section 03.03) (2 Samples)

The inspectors evaluated the following dose calculations:

(1) Reactor building weekly vent stack dose calculation

(2) Water storage pond monthly dose calculation

Abnormal Discharges (IP Section 03.04) (1 Sample)

The inspectors evaluated the following abnormal discharges:

(1) Abnormal liquid discharge from 2022 leak into groundwater

OTHER ACTIVITIES - BASELINE

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

MS06: Emergency AC Power Systems (IP Section 02.05)===

(1) July 1, 2023, through June 30, 2024

MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)

(1) July 1, 2023, through June 30, 2024

MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)

(1) July 1, 2023, through June 30, 2024 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)

(1) May 1, 2023, through May 30, 2024

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

(1) May 1, 2023, through May 30, 2024 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) May 1, 2023, through May 30, 2024

EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)

(1) April 1, 2022, through June 30, 2024 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)

(1) April 1, 2022, through June 30, 2024 EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)

(1) April 1, 2022, through June 30, 2024

71152 A - 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) Reactor SCRAM that occurred during turbine testing on September 27,

INSPECTION RESULTS

Observation: Subsurface Tritium Activity 71124.06 The inspectors had the following observations from the reviews performed in addition to scope defined by Inspection Procedure 71124.06, Radioactive Gaseous and Liquid Effluent Treatment:

• The revised methodology used by the licensee to quantify the amount of radioactive material leaked to groundwater.

o The original method utilized the observed leak rate from the pipe, and estimated the time the pipe was leaking and the concentration of tritium in the pipe. This method was adequate for the purpose of characterizing the event and estimating the annual dose to a member of the public. The licensee subsequently performed a more detailed mass balance calculation to determine that total activity leaked into the subsurface of plant property.

The licensees revised value is 14 Curies of tritium leaked from the plant into the subsurface on plant property.

• The revised recovery system which was changed from temporary above ground storage tanks to permanent engineered retention ponds.

o The inspectors noted the licensee adequately evaluated and accounted for evaporative losses from the ponds.

• The methodology and results used to determine the tritium activity in the Mississippi River from background or other sources not attributed to plant operations.

o These results indicate no plant impact can be seen on the concentration of Tritium (i.e., above natural background level) in the Mississippi River.

• The methodology and results for the calculations of tritium moving to the river and the associated dose to the nearest receptor for this abnormal discharge.

o The NRC requires licensees to quantify the concentration of radioactive material, tritium in this case, at the point of release to the unrestricted area.

To this end, the licensees contracted hydrogeologist firm used MODFLOW, a U.S. Geological Survey computer code to model/simulate the groundwater flow from the plant site to the Mississippi River. Additionally, licensees are required to demonstrate by measurement or calculation that the total dose equivalent to an individual likely to receive the highest dose does not exceed the annual dose limit. The resulting doses calculated were far below the regulatory requirements and the methodology used to determine the movement of tritium to the Mississippi River was adequate.

These results support and reaffirm the conclusions from the previous inspection (ML23219A155). Specifically, 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 mitigate any uncontrolled release from the site. Additionally, these results indicate the abnormal discharge was monitored and evaluated with regard to the environment and public exposure. Finally, the inspections confirm our earlier assessment that the discharge has no impact on public health and safety.

Observation: Corrective Actions for SCRAM That Occurred During Turbine Testing 71152 A On September 27, 2023, an unplanned SCRAM, group I primary containment isolation, and group II primary containment isolation occurred. The SCRAM was attributed to testing the control valves at 75 percent reactor power, a power just below the transition between the large outer piston and the smaller inner piston of the control valve actuators. When one control valve was closed the other control valves did not respond, and reactor pressure increased, resulting in the transient. Corrective actions included revising the turbine control valve test procedure to be performed at 50 percent reactor power, away from the control valve transition between the large outer piston and the smaller inner piston.

On September 12, 2024, the inspectors observed the licensee lower reactor power to 50 percent to perform control valve testing. No issues of concern were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On October 22, 2024, the inspectors presented the integrated inspection results to S. Hafen, Site Vice President, and other members of the licensee staff.

• On August 2, 2024, the inspectors presented the emergency preparedness inspection results to G. Brown, Plant Manager, and other members of the licensee staff.

• On August 28, 2024, the inspectors presented the radiation protection baseline inspection results to S. Hafen, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Corrective Action

Documents

501000089312

Roof Section Blown Off During Storm

08/27/2024

NH36048

(M134)

P&ID Fire Protection System Interior Locations

NH36246

(M120)

P&ID Residual Heat Removal System

NH36516

(M810)

P&ID Fire Protection System Yard Areas

Drawings

NH36666

(M812)

P&ID Intake Structure Screen Wash

Fire & Water Treatment System

100

269

Fire Protection Valve Check

201

Plant Prestart Checklist CRV-EFT System

B.03.0405

Residual Heat Removal System

B.08.0505

Fire Protection - System Operation

B.08.1305

Control Room Heating and Ventilation (H&V) and

Emergency Filtration Train (EFT)

B.09.0905

250 VDC System

71111.04

Procedures

EWI11.01.06

Battery Monitoring and Maintenance Program

Strategy A.303-A

Fire Zone 3A, Recirc MG Set Room

Strategy A.305-C

Fire Zone 5C, Fuel Pool Skimmer Tank Room

Strategy A.313-A

Fire Zone 13A, Lube Oil Storage Tank Room

Strategy A.313-B

Fire Zone 13B, Rx Feedpump and

Lube Oil Reservoir Room

Fire Plans

Strategy A.331-A

Fire Zone 31A, EFT Building 1st Floor (DIV I)

71111.05

Miscellaneous

Drill Guide 24.01

Fire Brigade Drill Guide (Fire Zone 24)

07/20/2024

71111.07A

Procedures

140101

Emergency Diesel Generator Emergency Service Water

Heat Exchanger Performance Test

Miscellaneous

RQSS173

RPV Flood

C.51100

Reactor Pressure Vessel Control

C.51200

Primary Containment Control

71111.11Q

Procedures

C.52006

Reactor Pressure Vessel Flood

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Corrective Action

Documents

501000089045

D80 Circuit Card Replacement Part

08/19/2024

28OCD

Waste Collector Filter T25 Cleaning

Procedures

25PM

No. 23 & 16 Battery Charger Preventive Maintenance

2000032398

Type 2Operational Decision Making Issue Evaluation,

LC1057 (HIP HTR 14B Level Dump Controller)

07/22/2024

71111.12

Work Orders

700118940020

28 Waste Collector Filter T25 Cleaning

09/09/2024

71111.13

Work Orders

70001417310010

MO 2012 Secure Motor Pinion

08/07/2024

501000087690

EQASCO Activation Energy Issue

07/12/2024

501000088600

MO2012 Motor Pinion May Not be Secured

08/05/2024

501000088828

Switch Not Reset

08/14/2024

501000089259

APRM2 Non-Critical Self-Test Fault

08/26/2024

Corrective Action

Documents

501000090055,

VD9216B [Control Room Fresh Air Damper]

Did Not Open as Expected

09/20/2024

Engineering

Evaluations

EE

608000001175

Evaluation of ASCO Solenoid Valve Activation Energy Issue

N/A

A4993AN003

Continuous Energization of ASCO Catalog NP1 Valves

During a Loss-ofCoolant Accident

2/11/1979

71111.15

Miscellaneous

N03651ASCO

Environmental Qualification Temperature Test of ASCO 206

and NP Series Solenoid Valves

June 2000

Drawings

ECR5149NX-

23674450-1

2R Auxiliary Transformer Wiring Diagram

08/21/2024

Engineering

Changes

601000005149

Temporary Disconnect 2R Relief Valve Annunciator

08/21/2024

A.7SAMG01

RPV and Primary Containment Injection (Modes 14)

A.7SAMG02

RPV, Containment, and Radioactive Release Control

(Modes 14)

A.7SAMG03

Refueling (Mode 5)

C.5GM-02.01

Plant Specific Technical Guidelines

C.5GM-02.02

Plant Specific Technical Guidelines

C.6008-B01

No. 2R XFMR Trouble

71111.18

Procedures

Ops Man

C.5.11004

SAMG Technical Bases (Modes 1, 2, 3, 4)

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Ops Man

C.5.11005

SAMG Technical Bases (Mode 5)

Work Orders

7001414770020

Install TMOD (601000005149)

08/21/2024

501000088823

Error Likely Situation with Procedure 0062

08/13/2024

501000089259

APRM2 Non Critical Self Test Fault

08/26/2024

501000089397

APRM DNSCL/TRBL

08/29/2024

501000089804

HCU 3815

09/16/2024

Corrective Action

Documents

501000089861

RHR86 Spins Freely

09/15/2024

0062

RCIC Steam Line High Area Temperature Test and

Calibration Procedure

0074

Control Rod Dive Exercise

0081

Control Rod Drive SCRAM Insertion Time Test

25504-IA12

RHR Loop B Quarterly Pump and Valve Tests

105

29802

Security System Emergency Generator Operability Check &

Alarm

046501

Emergency Filtration Treatment System (A Train, Control

Room Emergency Filtration)

7100

CRD-HCU Instrument Maintenance Procedure

ISP-NIP058901

APRM Channel Functional Test - Run Mode

NUC02.02

OD1/LPRM Calibration

OSP-FIR0582

P505, Portable Diesel Fire Pump Testing

OSP-NIP0546

LPRM Calibration

OSP-RHR0012

MO2023 Open Supplemental Position Indication Test

Procedures

OSP-RHR0556

RHR Water Fill Verification

70001306360020

PMT: Charger, D6A (16) Battery

08/20/2024

7001079900040

PMT: RCIC Room Air Cooling Unit

08/16/2024

7001224460020

PMT: RHR DIV I Torus Spray Inboard Valve

09/04/2024

700135027

046501 DIV 1 EFT Quarterly Operation

07/09/2024

700136224

04651 DIV 1 CRV Monthly Operation

07/09/2024

700136227

OSP-NIP0546 LPRM CAL (1000 MWD/T)

07/11/2024

7001388010010

25504-21 RHR Loop B Quarterly Pump and Valve Test

09/25/2024

7001407490020

PMT: Hydraulic Control Unit for CRD3815

09/12/2024

71111.24

Work Orders

700142944

PMT: Perform APRM Channel 2 Functional Test

08/29/2024

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Part B of Procedure ISP-NIP058901

EPLAN10

Monticello Alert and Notification System (ANS)

Design Report

Miscellaneous

N/A

ANS Testing Raw Data

07/06/2022

through

07/10/2024

71114.02

Procedures

FPEP-WI01

Public Alert Notification System (Pans) Maintenance and

Testing

Corrective Action

Documents

501000080918

(MT)

NOS Finding: EP OnShift Staff Analysis

01/17/2024

LXE22006 10 CFR 50.90

Response to a Request for Additional Information RE: Xcel

Energy Amendment Request to Create a Common

Emergency Plan and Emergency Operations Facility for

Monticello and Prairie Island (EPID: L2021LLA0210)

06/10/2022

Miscellaneous

N/A

EP Training Records

Various

EPLAN08

OnShift Staffing Analysis

71114.03

Procedures

Plan Revision: 0

Standard Emergency Plan

Corrective Action

Documents

Resulting from

Inspection

501000088419

EVES Building Condition Observation

08/01/2024

N/A

NELCOM Service Report

07/01/2022

through

05/01/2024

Miscellaneous

N/A

LOA & MOU: GE Labs; US Dept. of Energy; MN Homeland

Security and Emergency Management; North Memorial

Med. Center: Sherbune County; Wright County;

CNTNRACARE Monticello & St. Cloud: Regions Hospital;

City of Monticello

Various

71114.05

Procedures

255360F

Model DCFCTB Installation, Operation & Service Manual

Rev 7/06

MTGC2024055

Gaseous Effluent Release Report via Pond

06/04/2024

Calculations

MTGC2024073

Gaseous Effluent Release Report via Reactor Building

Ventilation

07/17/2024

71124.06

Corrective Action

501000068729

Elevated Monitoring Well 9 Tritium Result

11/21/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

501000069072

MW9 Iodine Results

2/07/2022

501000073844

Groundwater Data in 2022 ARERR

05/22/2023

501000077554

ODCM-APP-A Error Found

10/09/2023

501000081265

Missed ODCM Surveillance Requirements

01/25/2024

Documents

501000087801

Lake Tanks 3&4 Outside Gaseous Boundary

07/16/2024

Miscellaneous

NBGAS

Stack-Vent

Compensatory Sampling Gamma Isotopic for Noble Gas

05/13/2022

0066B

Reactor Building Vent Release Rate Determination

29

Off-Gas/Storage Tank Gross Activity Limit

0362

Monitoring for Containment Purging

0505

Radioactive Effluent Release Report Preparation and

Review

I.02.06

Airborne Continuous Release Report

Monticello

Updated Safety

Analysis Report

Monticello USAR

Procedures

ODCM01

Offsite Dose Calculation Manual

Miscellaneous

QF2116

EP Quarterly Performance Indicator

April 1, 2022,

through

June 30,

24

22

Reactor Coolant I131 Dose Equivalent Activity

71151

Procedures

QF0444 (FPR-

PI01)

NRC and MOR Data Collection and Submittal Forms

501000077129

50.72 Non-Emergency Report to NRC

09/27/2023

501000077170

Reactor SCRAM Number 141

09/27/2023

Corrective Action

Documents

501000077171

Potential Equipment Malfunction CV4

09/27/2023

104001

Turbine - Generator

09/09/2024

71152 A

Procedures

2300

Reactivity Adjustment

27