IR 05000263/2021003

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Plan, Integrated Inspection Report 05000263/2021003
ML21299A318
Person / Time
Site: Monticello Xcel Energy icon.png
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

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, 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

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.

REACTOR SAFETY

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,

RADIATION SAFETY

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 10 CFR Part 21 Communication of Cyber Security Vulnerabilities associated with GEH NUMAC PRNMS 71152 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 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)71152 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 that contributed to an uncontrolled locked high radiation area.

71152 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

Procedure

Type

Designation

Description or Title

Revision or

Date

Calculations

140046

External Flooding Protection Features

2B

1478

External Flood Monthly and Annual Surveillance

1478-01

External Flood Five Year Surveillance

71111.01

Procedures

A.6

Acts of Nature

NF-85716

Security System Circuit Diagram

Drawings

NH36249

High Pressure Coolant Injection System

71111.04

Procedures

A.6

Acts of Nature

Strategy A.3-03-A

Fire Zone 3-A, RECIRC MG Set Room

Strategy A.3-05-C

Fire Zone 5-C, Fuel Pool Skimmer Tank Room

Strategy A.3-13-B

Fire Zone 13-B, Rx Feedpump and Lube Oil Reservoir

Room

Strategy A.3-13-C

Fire Zone 13-C, Turbine Building 911' Elevation East MCC

Area

Fire Plans

Strategy A.3-31-A

EFT Building 1st Floor (DIV I)

A.3-002

Fire Brigade Organization

A.3-003

Operation of Fire Fighting Equipment

71111.05

Procedures

A.3-004

Fire Fighting Procedures and Strategies

DBD-S.01

Reactor Building

Procedures

DBD-T.08

Internal Flooding

71111.06

Work Orders

700074741

Inspection of Manholes and Vaults for Water

07/12/2021

Miscellaneous

RQ-55-99

Manual Initiation of High Pressure Coolant Injection to

Maintain Reactor Level

2300

Reactivity Adjustments

71111.11Q

Procedures

Ops Man C.2-5

Power Operation

255-05-11C-2

RHR Service Water System Leakage-Loop B

Procedures

FP-OP-RSK-01

Risk Monitoring and Risk Management

71111.12

Work Orders

700052484

RHR HX RHRSW Outlet

08/31/2021

501000053835

Loss of Security Power during 0298-02

07/07/2021

501000054030

Risk Inaccurate on Plant Status Report

07/13/2021

501000054473

CRD Pump Internal Degradation

07/28/2021

71111.13

Corrective Action

Documents

501000054568

CRD Post Filter Isolation Valves Leak

07/29/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

501000055693

Percent LCO Completion Time Exceeded

(Division 2 Residual Heat Removal Service Water)

09/02/2021

501000056184

Unexpected Alarm HWC014 HWC H2 High Diff

09/18/2021

501000056196

Plant Chemistry Impact of HWC OOS

09/19/2021

NF-85716

Security System Circuit Diagram

NF74259

External Connection Diagram ATWS Panel 9-95

E

NH-36242

P&ID Vessel Instrumentation Nuclear Boiler System

NX 16162-1-3

ATWS Elementary Drawing

NX-1-162-1-8

ATWS Elementary Diagram

NX-1612-1-5

Elementary Diagram-Recirc Pump Trip System

NX-16162-5-4

Trip Unit Cabinet 9-95

Drawings

NX-7831-93-2

Elementary Diagram Boiler Process Instrumentation

4131-PM

RBCCW Heat Exchanger Inspection and Cleaning

FP-OP-OL-01

Operability

QF 1152

Reactor Plant Event Notification Worksheet

QF 2010

Risk Assessment Worksheet

Procedures

QF0571

Troubleshooting Plan

700017507

Replace Rosemont Analog Trip Division 1

08/12/2021

Work Orders

700095731

9-95, Troubleshoot ATWS

08/31/2021

501000054248

VD-92B Actuator Failure

07/21/2021

501000054319

LS-23-90 Issue Causes C.R. Annunciator

07/24-2021

501000054458

PFDA1 Relay not in Tolerance

07/27/2021

501000054707

EDG Oil Leak

08/04/2021

501000054991

P-210/MTR Motor (RCIC Barometric Condenser

Condensate Pump) Commutator Discoloration

08/11/2021

Corrective Action

Documents

501000055533

ATWS CAB 9-5 Trouble

08/27/2021

Corrective Action

Documents

Resulting from

Inspection

501000054373

NRC Question on C.6-003-B-10 Basis

07/25/2021

Drawings

NX 16162-1-3

ATWS Elementary Diagram

71111.15

Procedures

C.6-003-B10

HPCI Turbine Inlet Hi Drain Pot Level

71111.19

Work Orders

700052484-0020

Post Maintenance Test 1RSW CV-1729

09/01/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

255-02-III

SBLC Quarterly Pump and Valve Tests

255-05-1A-1-2

'B' RHRSW Quarterly Pump and Valve Test

71111.22

Procedures

OSP FIR 0609

Portable Diesel Pump Testing

Corrective Action

Documents

501000051131

Turbine Building Normal Waste Sump Abnormal Discharge

04/27/2021

Engineering

Changes

0000028235

Basis for Stack Wide Range Noble Gas Monitor Effluent

Reporting Methodology

1_2021-01-

05_001

Charcoal Filter Gamma Spectrum Analysis for Plant Stack

01/05/2021

1_2021-01-

05_005

Particulate Filter Gamma Spectrum Analysis for Plant Stack

01/05/2021

1_2021-01-

17_005

Noble Gas Gamma Spectrum Analysis for Plant Stack

01/17/2021

1_2021-04-

15_007

Noble Gas Gamma Spectrum Analysis for Drywell Purge

04/15/2021

3_2021-04-

15_009

Charcoal Filter Gamma Spectrum Analysis for Drywell Purge

04/15/2021

5_2021-04-

15_008

Particulate Filter Gamma Spectrum Analysis for Drywell

Purge

04/15/2021

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

Waste Sump

05/03/2021

Miscellaneous

N/A

Turbine Building Normal Waste Sump Tritium Results

04/26/2021

I.02.06

Airborne Continuous Release Report

71124.06

Procedures

I.02.08

Airborne Batch Release Report

71124.08

Procedures

R.06.09

Storage and Inventory of Radioactive Material Outside the

Power Block

QF0739

NRC Performance Indicator Data; MSPI Emergency AC

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

09/28/2021

71151

Miscellaneous

QF0739

NRC Performance Indicator Data; MSPI High Pressure

Injection System; 3rd Quarter 2020 through

09/28/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2nd Quarter 2021

QF0739

NRC Performance Indicator Data; MSPI Heat Removal

Systems; 3rd Quarter 2020 through 2nd Quarter 2021

09/28/2021

Procedures

FP-R-PI-01

Preparation of NRC Performance Indicators

501000027322

AO-12-4-14A Failed to Close During Filter Isolation for

Backwash

05/12/2019

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

Corrective Action

Documents

501000051668

RC-50-1 Failed Post Maintenance Testing

05/10/2021

Memorandum of

Understanding

XCEL Energy and Wright County Sherriff's Office

06/21/2021

QF0588

CFR Part 21 Engineering Evaluation CAP Number

501000048004

Miscellaneous

SC 21-02

006N4945

Safety Communication

03/09/2021

C.2-05

Power Operation

FP-S-FSIP-01

Security Compensatory Measures

Procedures

OSP-NIP-0546

LPRM Calibration

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

71152

Work Orders

700085292

Repair of AO-12-4-14A for QIM 501000048130

01/29/2021