IR 05000263/2021003

Plan, Integrated Inspection Report 05000263/2021003

ML21299A318
Person / Time
Site:	Monticello
Issue date:	10/27/2021
From:	Hironori Peterson Region 3 Branch 3
To:	Conboy T Northern States Power Company, Minnesota
References
IR 2021003
Download: ML21299A318 (17)

Text

October 27, 2021

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLAN - INTEGRATED INSPECTION REPORT 05000263/2021003

Dear Mr. Conboy:

On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Monticello Nuclear Generating Plan. On October 5, 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, Signed by Peterson, Hironori on 10/27/21 Hironori Peterson, Chief Branch 3 Division of Reactor Projects Docket No. 05000263 License No. DPR-22

Enclosure:

As stated

Inspection Report

Docket Number: 05000263 License Number: DPR-22 Report Number: 05000263/2021003 Enterprise Identifier: I-2021-003-0097 Licensee: Northern States Power Company, Minnesota Facility: Monticello Nuclear Generating Plan Location: Monticello, MN Inspection Dates: July 1, 2021 to September 30, 2021 Inspectors: C. Norton, Senior Resident Inspector T. McGowan, Resident Inspector V. Myers, Senior Health Physicist Approved By: Hironori Peterson, Chief Branch 3 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Monticello Nuclear Generating Plan, 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 Nuclear Generating Plant began the inspection period at rated thermal power.

During this inspection period, due to low Mississippi river flow and level, the licensee made several power adjustments to maintain river appropriation and river effluent temperature within environmental limits. On July 4, 2021, the unit was down powered to 90 percent to maintain average discharge canal temperature within environmental limits. The unit was returned to rated thermal power on July 4, 2021. On July 22, 2021, the unit was down powered to 82 percent to maintain average discharge canal temperature within environmental limits. The unit was returned to rated thermal power on July 22, 2021. On July 24, 2021, the unit was down powered to 82 percent to maintain average discharge canal temperature within environmental limits. The unit was returned to rated thermal power on July 24, 2021. On July 27, 2021, the unit was down powered to 86 percent to maintain river appropriation within environmental limits.

The unit was returned to rated thermal power on July 29, 2021. On August 16, 2021, the unit was down powered to 80 percent to maintain river appropriation within environmental limits.

The unit was returned to rated thermal power on August 22, 2021. On September 10, 2021, the unit was down powered to 75 percent to perform a control rod sequence exchange. The unit was returned to rated thermal power on September 10, 2021 and remained at or near rated thermal power 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 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 (COVID-19), resident and regional 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, increasing the amount of time on-site as local COVID-19 conditions permitted.

As part of their on-site activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution, 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 a portion 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.

71111.01 - Adverse Weather Protection

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

(1) The inspectors evaluated readiness for seasonal low river level and flow on

===July 13, 2021.

External Flooding Sample (IP Section 03.03) (1 Sample)===

(1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on September 28, 2021.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Security uninterruptable power supply on July14, 2021

(2) Circulating water system during low river level conditions on July 22, 2021

(3) High pressure coolant injection system steam line drains on July 25, 2021

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 03-A, Recirc MG set room on September 9, 2021

(2) Fire zone 13-C, Turbine building 911' elevation east MCC area on September 9, 2021

(3) Fire zone 31-A, EFT building 1st floor (Division I) on September 10, 2021

(4) Fire zone 13-B, Reactor feed pump and lube oil reservoir room on September 10, 2021

(5) Fire zone 05-C, Fuel pool skimmer tank room on September 10, 2021

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

(1) The inspectors evaluated the onsite fire brigade training and performance during live burn training on September 3, 2021.

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) High pressure coolant injection room on July 21, 2021

Cable Degradation (IP Section 03.02) (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) Cable vaults: NMH 305, 306, 101, 302, 301, 334, 335, 336, 331, 332, 333, and 310

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 while increasing power form 85 percent to 100 percent on July 23, 2021.

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

(1) The inspectors observed and evaluated licensed operator requalification training on July 26, 2021.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 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) Residual heat removal service water system heat exchanger flow control valve replacement on August 31, 2021

(2) Emergency service water pipe replacement preparations on September 29, 2021

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) Residual heat removal service water system flow control valve controller failure during system testing on September 1, 2021

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (9 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) Loss of security intrusion detection and assessment equipment on July 7, 2021

(2) Isolation of the 'D' 10 125V battery charger on July 13, 2021

(3) Division 1 emergency diesel generator start and load testing on July 13, 2021

(4) Actions associated with 12 control rod drive (CRD) pump degradation on July 30, 2021

(5) Replacement of Division 1 Rosemont analog trip module on August 12, 2021

(6) Management of secondary containment during reactor building closed cooling water heat exchanger inspection and cleaning on August 24, 2021

(7) Replacement of Division 1 anticipated transient without SCRAM (ATWS) inverter on August 31, 2021

(8) Division 2 residual heat removal service water system flow control valve trouble shooting on September 2, 2021

(9) Loss of hydrogen water chemistry system on September 20, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

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

(1) QIM 501000054248, VD-9216B (outside air damper for 'B' control room ventilation train) Actuator Failure on July 22, 2021

(2) QIM 501000054319, LS-23-90 (high pressure coolant injection turbine inlet high drain pot level) Issue Causes Control Room. Annunciator on July 25, 2021.

(3) QIM 501000054458, PFDA1 Relay not in Tolerance (12 diesel air start logic) on July 29, 2021

(4) QIM 501000054707, 12 emergency diesel generator oil leak on August 5, 2021

(5) QIM 501000054991, P-210/MTR motor (RCIC barometric condenser condensate pump motor) commutator discoloration on August 12, 2021

(6) QIM 501000055533, ATWS CAB 9-95 trouble on August 27, 2021

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (1 Sample)

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

(1) Division 2 residual heat removal service water flow control valve post maintenance testing following valve replacement on September 1, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) 0255-02-III, Standby liquid control quarterly pump and valve tests on August 5, 2021

(2) 0255-05-1A-1-2, 'B' RHRSW Quarterly Pump and Valve Test on September 1, 2021

FLEX Testing (IP Section 03.02) (1 Sample)

(1) Portable Diesel Pump Testing (FLEX) on September 16,

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (1 Sample)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Reactor building ventilation

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (7 Samples)

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

(1) Ludlum model 3030P alpha-beta sample counter located in the count room

(2) Canberra Tennelec 5 XLB alpha-beta sample counter located in the count room

(3) Thermo small article monitor at the radiologically controlled area exit

(4) Eberline SK-1 frisker located in the instrument room

(5) Fisher RO-20 dose rate meter located in the instrument room

(6) Canberra ARGOS 5AB personal contamination monitor located at the radiologically controlled area exit

(7) Canberra iSolo alpha-beta sample counter located in the chemistry lab

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (3 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Reactor building vent

(2) Plant stack

(3) Service water

Sampling and Analysis (IP Section 03.02) (3 Samples)

Inspectors evaluated sampling and analysis for the following discharge paths:

(1) Plant stack

(2) Turbine building normal waste sump

(3) Drywell purge

Dose Calculations (IP Section 03.03) (2 Samples)

The inspectors evaluated the following dose calculations:

(1) Plant stack releases for the first quarter of 2021

(2) Drywell purge for April 16-17, 2021

Abnormal Discharges (IP Section 03.04) (1 Sample)

The inspectors evaluated the following abnormal discharges:

(1) Tritium release from the turbine building normal waste sump identified on April 27, 2021

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,

& Transportation

Radioactive Material Storage (IP Section 03.01)

Inspectors evaluated the licensees performance in controlling, labelling, and securing radioactive materials for the following areas.

(1) Rotor storage building

(2) Warehouse number four

Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)

The inspectors walked down accessible portions of the following radioactive waste systems and evaluated system configuration and functionality.

(1) Reactor water cleanup

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) July1, 2020 through June 30, 2021

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

(1) July1, 2020 through June 30, 2021

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

(1) July1, 2020 through June 30, 2021 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)

(1) October 01, 2020 through June 30, 2021

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

(1) October 01, 2020 through June 30, 2021 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 01, 2020 through June 30, 2021

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (3 Samples)

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

(1) Equipment issues with the reactor water cleanup (RWCU) system that contributed to an uncontrolled locked high radiation area.

(2) General Electric Hitachi 10 CFR 50.21 notification of security vulnerabilities associated with the GEH NUMAC power range neutron monitoring system (PRNMS)installed at Monticello.

(3) Assessment of Monticello Nuclear Generating Plant (MNGP) maintenance of flood protection portions of procedure A.6, "Acts of Nature," such that it can support the timely implementation of flood protection activities within the timeframe credited in the updated safety analysis report (USAR.)

INSPECTION RESULTS

Observation: Corrective Actions Associated with General Electric Hitachi 71152 10 CFR Part 21 Communication of Cyber Security Vulnerabilities associated with GEH NUMAC PRNMS In January of 2021, the licensee identified and informed General Electric Hitachi (GEH) of a potential security vulnerability in the power range neutron monitoring system (PRNMS). GEH issued a 10 CFR Part 21 notification describing how the system as designed and installed allowed unauthorized adjustment of local power range monitors. The licensee entered the issue into its corrective program and determined that the vulnerability was a substantial safety hazard. Corrective actions included hardware, software, and procedure changes. The inspectors verified the corrective actions effectively eliminated the PRNMS security vulnerability. The inspectors identified no violations or findings during this review.

Observation: Assessment of Monticello Nuclear Generating Plant Maintenance 71152 of Flood Protection Portions of Procedure A.6, "Acts of Nature," Such that it can Support the Timely Implementation of Flood Protection Activities Within the Timeframe Credited in the Updated Safety Analysis Report (USAR)

In 2013, the NRC completed an inspection at Monticello Nuclear Generating Plant to independently verify that the licensees external flood protection walkdown activities were conducted using walkdown methodology endorsed by the U.S. Nuclear Regulatory Commission (NRC). During this inspection, the NRC identified a Yellow finding with substantial safety significance associated with licensee failure to maintain a flood plan to protect the site from external flooding events. Specifically, the licensee failed to maintain flood procedure A.6, Acts of Nature, such that it could support the timely implementation of flood protection measures within the timeframe stated in the USAR.

In 2016, after the licensee had taken corrective actions, the NRC performed a follow up inspection of the design, material condition, and procedures for coping with the design basis probable maximum flood as described in the USAR. The NRC determined that procedure A.6, Acts of Nature, could support the timely implementation of flood protection measures within the timeframe stated in the USAR. No findings were identified.

During this inspection period, the inspectors reviewed licensee maintenance of the flood protection portions of A.6, "Acts of Nature," to ensure that licensee ability for coping with the design basis probable maximum flood had not degraded. The inspectors verified that the material required to implement the flood protection measures of A.6 was well maintained, segregated, labeled, and dedicated exclusively for flood protection. The inspectors reviewed monthly, annual, and five-year surveillances that verified the readiness of the dedicated material. The inspectors confirmed that the security plan adequately supported A.6 implementation. The inspectors ensured that the necessary memoranda of understanding with local law enforcement and local contractors were in place and up to date.

The inspectors determined that the licensee has maintained the flood protection portions of procedure A.6, "Acts of Nature," such that it can successfully cope with the design basis probable flood within the timeframe stated in the USAR. The inspectors identified no violations or findings during this review.

Observation: Equipment issues with the reactor water cleanup (RWCU) system 71152 that contributed to an uncontrolled locked high radiation area.

In January 2021, the licensee failed to comply with locked high radiation area (LHRA)requirements while addressing issues encountered during a backwash of the RWCU filter (Green NCV documented in inspection report 05000263/2021002). The inspectors observed that multiple equipment issues contributed to the LHRA event. The inspectors reviewed documents associated with the corrective action program and work management process over the previous three years and conducted interviews with staff familiar with the RWCU backwash system.

The inspectors determined that unresolved maintenance issues had existed for over three years, including incorrect valve position indication, malfunctioning valve actuators, and valve leakage. The review also indicated that troubleshooting and maintenance efforts were not effective in correcting underlying issues. In addition, the inspectors found several examples involving scheduled RWCU work that was repeatedly cancelled due to the lower priority of this system.

Due to extended RWCU outage times, the licensee recently performed a thorough review of RWCU equipment issues and prioritized maintenance on several components. The licensee planned to conduct at least one more RWCU outage this year to perform further maintenance on the system.

EXIT MEETINGS AND DEBRIEFS

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

On October 5, 2021, the inspectors presented the integrated inspection results to Mr. T. Conboy, Site Vice President, and other members of the licensee staff.

On July 1, 2021, the inspectors presented the radiation protection inspection results to Mr. D. Thurston, Acting Chemistry Manager, and other members of the licensee staff.

On October 5, 2021, the inspectors presented the radiation protection inspection results to Mr. T. Conboy, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Calculations 140046 External Flooding Protection Features 2B

Procedures 1478 External Flood Monthly and Annual Surveillance 24

1478-01 External Flood Five Year Surveillance 4

A.6 Acts of Nature 63

71111.04 Drawings NF-85716 Security System Circuit Diagram 79

NH36249 High Pressure Coolant Injection System 85

Procedures A.6 Acts of Nature 63

71111.05 Fire Plans Strategy A.3-03-A Fire Zone 3-A, RECIRC MG Set Room 9

Strategy A.3-05-C Fire Zone 5-C, Fuel Pool Skimmer Tank Room 6

Strategy A.3-13-B Fire Zone 13-B, Rx Feedpump and Lube Oil Reservoir 14

Room

Strategy A.3-13-C Fire Zone 13-C, Turbine Building 911' Elevation East MCC 12

Area

Strategy A.3-31-A EFT Building 1st Floor (DIV I) 12

Procedures A.3-002 Fire Brigade Organization 17

A.3-003 Operation of Fire Fighting Equipment 19

A.3-004 Fire Fighting Procedures and Strategies 8

71111.06 Procedures DBD-S.01 Reactor Building 6

DBD-T.08 Internal Flooding 5

Work Orders 700074741 Inspection of Manholes and Vaults for Water 07/12/2021

71111.11Q Miscellaneous RQ-55-99 Manual Initiation of High Pressure Coolant Injection to 1

Maintain Reactor Level

Procedures 2300 Reactivity Adjustments 24

Ops Man C.2-5 Power Operation 80

71111.12 Procedures 0255-05-11C-2 RHR Service Water System Leakage-Loop B 11

FP-OP-RSK-01 Risk Monitoring and Risk Management 13

Work Orders 700052484 12 RHR HX RHRSW Outlet 08/31/2021

71111.13 Corrective Action 501000053835 Loss of Security Power during 0298-02 07/07/2021

Documents 501000054030 Risk Inaccurate on Plant Status Report 07/13/2021

501000054473 12 CRD Pump Internal Degradation 07/28/2021

501000054568 12 CRD Post Filter Isolation Valves Leak 07/29/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

501000055693 50 Percent LCO Completion Time Exceeded 09/02/2021

(Division 2 Residual Heat Removal Service Water)

501000056184 Unexpected Alarm HWC014 HWC H2 High Diff 09/18/2021

501000056196 Plant Chemistry Impact of HWC OOS 09/19/2021

Drawings NF-85716 Security System Circuit Diagram 79

NF74259 External Connection Diagram ATWS Panel 9-95 E

NH-36242 P&ID Vessel Instrumentation Nuclear Boiler System 81

NX 16162-1-3 ATWS Elementary Drawing 76

NX-1-162-1-8 ATWS Elementary Diagram 78

NX-1612-1-5 Elementary Diagram-Recirc Pump Trip System 77

NX-16162-5-4 Trip Unit Cabinet 9-95 76

NX-7831-93-2 Elementary Diagram Boiler Process Instrumentation 78

Procedures 4131-PM RBCCW Heat Exchanger Inspection and Cleaning 24

FP-OP-OL-01 Operability 22

QF 1152 Reactor Plant Event Notification Worksheet 4

QF 2010 Risk Assessment Worksheet 33

QF0571 Troubleshooting Plan 7

Work Orders 700017507 Replace Rosemont Analog Trip Division 1 08/12/2021

700095731 9-95, Troubleshoot ATWS 08/31/2021

71111.15 Corrective Action 501000054248 VD-92B Actuator Failure 07/21/2021

Documents 501000054319 LS-23-90 Issue Causes C.R. Annunciator 07/24-2021

501000054458 PFDA1 Relay not in Tolerance 07/27/2021

501000054707 12 EDG Oil Leak 08/04/2021

501000054991 P-210/MTR Motor (RCIC Barometric Condenser 08/11/2021

Condensate Pump) Commutator Discoloration

501000055533 ATWS CAB 9-5 Trouble 08/27/2021

Corrective Action 501000054373 NRC Question on C.6-003-B-10 Basis 07/25/2021

Documents

Resulting from

Inspection

Drawings NX 16162-1-3 ATWS Elementary Diagram 77

Procedures C.6-003-B10 HPCI Turbine Inlet Hi Drain Pot Level 9

71111.19 Work Orders 700052484-0020 Post Maintenance Test 1RSW CV-1729 09/01/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Procedures 0255-02-III SBLC Quarterly Pump and Valve Tests 68

255-05-1A-1-2 'B' RHRSW Quarterly Pump and Valve Test 91

OSP FIR 0609 Portable Diesel Pump Testing 6

71124.06 Corrective Action 501000051131 Turbine Building Normal Waste Sump Abnormal Discharge 04/27/2021

Documents

Engineering 0000028235 Basis for Stack Wide Range Noble Gas Monitor Effluent 0

Changes Reporting Methodology

Miscellaneous 1_2021-01- Charcoal Filter Gamma Spectrum Analysis for Plant Stack 01/05/2021

05_001

1_2021-01- Particulate Filter Gamma Spectrum Analysis for Plant Stack 01/05/2021

05_005

1_2021-01- Noble Gas Gamma Spectrum Analysis for Plant Stack 01/17/2021

17_005

1_2021-04- Noble Gas Gamma Spectrum Analysis for Drywell Purge 04/15/2021

15_007

3_2021-04- Charcoal Filter Gamma Spectrum Analysis for Drywell Purge 04/15/2021

15_009

5_2021-04- Particulate Filter Gamma Spectrum Analysis for Drywell 04/15/2021

15_008 Purge

MTGB2021-032 Gaseous Effluent Release Report for Drywell Purge 04/17/2021

MTGB2021-032 Gaseous Effluent Release Report for Drywell Purge 04/15/2021

MTGC2020-115 Gaseous Effluent Release Report for Plant Stack 01/06/2021

MTLC2021-001 Turbine Building Normal Waste Sump Release Report 05/03/2021

MTLC2021-001 Liquid Effluent Release Report for Turbine Building Normal 05/03/2021

Waste Sump

N/A Turbine Building Normal Waste Sump Tritium Results 04/26/2021

Procedures I.02.06 Airborne Continuous Release Report 3

I.02.08 Airborne Batch Release Report 3

71124.08 Procedures R.06.09 Storage and Inventory of Radioactive Material Outside the 25

Power Block

71151 Miscellaneous QF0739 NRC Performance Indicator Data; MSPI Emergency AC 09/28/2021

Power Systems, 3rd Quarter 2020 through 2nd Quarter 2021

QF0739 NRC Performance Indicator Data; MSPI High Pressure 09/28/2021

Injection System; 3rd Quarter 2020 through

Inspection Type Designation Description or Title Revision or

Procedure Date

2nd Quarter 2021

QF0739 NRC Performance Indicator Data; MSPI Heat Removal 09/28/2021

Systems; 3rd Quarter 2020 through 2nd Quarter 2021

Procedures FP-R-PI-01 Preparation of NRC Performance Indicators 9

71152 Corrective Action 501000027322 AO-12-4-14A Failed to Close During Filter Isolation for 05/12/2019

Documents Backwash

501000038667 RV-3112 Leaks Past its Seat 03/11/2020

501000040145 Suspected RC-50-2 Seat Leakage 04/30/2020

501000040885 AO-12-4-20A Leaks by Seat 05/22/2020

501000045378 AO-12-4-14A Will Not Close During Backwash/Precoat 10/12/2020

501000045580 RV-3112 Step Change 10/16/2020

501000046699 RV-3112 Leakage 11/26/2020

501000047959 AO-12-4-14A Will Not Close During Backwash/Precoat 01/23/2021

501000048004 Potential Security Flaw in PRNMS/PPC 01/22/2021

501000048130 AO-12-4-14A Won't Close 01/26/2021

501000049135 AO-12-4-14A Cycling Issues 03/01/2021

501000049162 Adverse Trend in Reactor Water Cleanup Performance 03/02/2021

501000049396 Part 21 SC 21-02 Rev 0 Issued 03/11/2021

501000051668 RC-50-1 Failed Post Maintenance Testing 05/10/2021

Miscellaneous Memorandum of XCEL Energy and Wright County Sherriff's Office 06/21/2021

Understanding

QF0588 10 CFR Part 21 Engineering Evaluation CAP Number 2

501000048004

SC 21-02 Safety Communication 03/09/2021

006N4945

Procedures C.2-05 Power Operation 80

FP-S-FSIP-01 Security Compensatory Measures 17

OSP-NIP-0546 LPRM Calibration 16

Work Orders 700055880 Repair AO-12-14A for QIM 501000027322 03/19/2020

700071578 Replace RV-3112 01/29/2021

700081029 Repair AO-12-4-14A for QIM 501000045378 03/17/2021

700085036 Repair of AO-12-4-14A for QIM 501000047959 01/24/2021

700085292 Repair of AO-12-4-14A for QIM 501000048130 01/29/2021

15