IR 05000282/2019004

Integrated Inspection Report 05000282/2019004 and 05000306/2019004

ML20028F249
Person / Time
Site:	Prairie Island
Issue date:	01/27/2020
From:	Hironori Peterson Region 3 Branch 3
To:	Sharp S Northern States Power Company, Minnesota
References
IR 2019004
Download: ML20028F249 (22)

Text

ary 27, 2020

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000282/2019004 AND 05000306/2019004

Dear Mr. Sharp:

On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant. On January 16, 2020, 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,

/RA/

Hironori Peterson, Chief Branch 3 Division of Reactor Projects Docket Nos. 05000282 and 05000306 License Nos. DPR-42 and DPR-60

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000282 and 05000306 License Numbers: DPR-42 and DPR-60 Report Numbers: 05000282/2019004 and 05000306/2019004 Enterprise Identifier: I-2019-004-0056 Licensee: Northern States Power Company, Minnesota Facility: Prairie Island Nuclear Generating Plant Location: Welch, Minnesota Inspection Dates: October 01, 2019 to December 31, 2019 Inspectors: S. Bell, Health Physicist E. Fernandez, Reactor Inspector L. Haeg, Senior Resident Inspector K. Pusateri, Resident Inspector N. Shah, Project Engineer 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 Prairie Island 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

Unit 1 operated at or near full power for the entirety of the inspection period. Unit 2 began the inspection period at approximately 74 percent power, coasting down for a refueling outage that began on October 4, 2019. The unit was returned to full power on October 31, 2019, and operated at full 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 performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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 03.02)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures on 12/16/2019 for the following systems:

Unit 2 emergency diesel generators and cooling water systems

71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

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

(1) Unit 2 A train 480V and 4160V systems with B train equipment out-of-service during

2R31 on 10/17/2019

(2) Unit 2 A train containment spray system following surveillance testing on 11/07/2019

(3) 22 diesel-driven cooling water pump seal water system on 11/13/2019

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Unit 2 containment on 10/16/2019

(2) Unit 2 A containment spray pump room on 11/07/2019

(3) Plant screenhouse during fire header maintenance on 11/12/2019

(4) Unit 2 emergency diesel generator D5/D6 building on 12/19/2019

(5) Bus 150/160 and no. 22 battery rooms on 12/19/2019

71111.07A - Heat Sink Performance Annual Review (IP Section 02.01)

The inspectors evaluated readiness and performance of:

(1) 22 component cooling water heat exchanger on 10/10/2019

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from 10/07/2019 to 10/11/2019:

03.01.a - Nondestructive Examination and Welding Activities.

• Ultrasonic Examination (UT) of Reactor Coolant 6-inch Elbow-to-Pipe Weld, W-6

• Ultrasonic Examination (UT) of Reactor Coolant 6-inch Elbow-to-Elbow Weld, W-5

• Liquid Penetrant Examination (PT) of Reactor Coolant Intergal Attachment,

• H-4/IA

• Visual Examination (VT-1) of Intergal Attachment (Snubber), CCH-182/IA

• Repair Cracked Weld on Alignment Lugs for Equipment Hatch

• (WO-700001472)

• Replace 3/4" Valve 2RC-8-37 Loop A RCS Shutdown Communication Line Vent (WO-700028252)03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

• Issue ID-501000027988 Boric Acid Evaluation of 22 Containment Spray Pump Mechanical Seal

• Issue ID-501000005225 Boric Acid Evaluation of Bolted Connection on 22 RHR Pump Discharge Line

• Issue ID-501000004041 Boric Acid Evaluation of Bolted Connection on Valve CV-31229 RCP Loop BPRPZR Spray CV

• Issue ID-501000005466 Boric Acid Evaluation of Bolted Connection on Valve 2VC-28-2 22 Charging Pump Discharge Relief

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) The inspectors observed and evaluated licensed operator performance in the control room on 12/27/2019 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated operator re-qualification in the simulator on 12/05/2019

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Maintenance effectiveness for cooling water system components on 11/14/2019

Quality Control (IP Section 02.02) (1 Sample)

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:

(1) Quality control program regarding equipment approaching end of qualified life on 10/15/2019

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Maintenance risk during reduced inventory in preparation for reactor head lift on 10/7/2019

(2) Emergent work associated with D5 emergency diesel generator fuel oil transfer system leak on 12/4/2019

(3) Maintenance risk during work week beginning 12/22/2019

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Unit 2 letdown orifice isolation valve issue past operability review (AR 501000032151)on 10/11/2019

(2) U2 B train residual heat removal void issue past operability review (AR 501000031667) on 10/08/2019

(3) Cooling water piping corrosion issue (AR 501000032539) on 10/02/2019

(4) 22 turbine-driven auxiliary feedwater pump high outboard bearing temperature issue (AR 501000033986) on 10/28/2019

(5) Passive motor-operated valve usage procedural issue (AR 501000031050) on 10/31/2019

(6) Fuel oil leak on D5 emergency diesel generator (AR 501000034334) on 11/04/2019

71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance tests:

(1) Bus 26 following refueling outage modifications and maintenance on 11/05/2019

(2) D6 diesel generator following refueling outage maintenance on 10/15/2019

(3) 22 component cooling water heat exchanger following maintenance on 10/17/2019

(4) 21 safety injection pump following seal replacement on 10/22/2019

(5) 22 containment spray pump following seal replacement on 10/19/2019

(6) D2 diesel generator air start solenoid following failure to close after surveillance testing on 11/12/2019

(7) 12 motor-driven auxiliary feed water pump following replacement of auxiliary lubricating oil pump auxiliary relay on 11/26/2019

71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)

(1) The inspectors evaluated Unit 2 refueling outage 2R31 activities from 10/04/2019 to 10/31/2019

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)

(1) SP 2314; 22 Battery Discharge Test on 10/15/2019

(2) SIP 2036; Unit 2 Turbine Overspeed Trip Test on 10/28/2019

Inservice Testing (IP Section 03.01) (1 Sample)

(1) SP 2083B, Unit 2 Integrated SI Test With a Simulated Loss of Offsite Power Train B on 10/22/2019 Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) SP 2072.11; Local Leakage Rate Test of Penetration 11 (Letdown Line) on 10/09/2019

71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03)

(1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.

• PI-2018-617, 12/17/18

• PI-2018-633, 01/31/19

• PI-2019-656, 02/22/19

• PI-2019-679, 06/18/19 This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation Drill/Training Evolution Observation (IP Section 03.02)

The inspectors evaluated:

(1) Licensed operator re-qualification training with Drill and Exercise Performance Indicator opportunities on 11/20/2019

71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 02.01)

The inspectors evaluated radiological hazards assessments and controls.

(1) The inspectors reviewed the following:

Radiological Surveys

• U2 Containment Refueling Floor 10/02/2019 through 10/10/2019

• U2 Containment Reactor Cavity 10/02/2019 through 10/10/2019

• U1 Containment 10/07/2019 through 10/10/2019 Risk Significant Radiological Work Activities

• U1 Containment Entry at Full Reactor Power

• U2 Containment Reactor Refueling Activities

• U2 Outboard Main Steam Isolation Valve Repairs Air Sample Survey Records

• U2 Containment 10/02/2019 23:32

• U2 Containment Upper Reactor Cavity 10/08/2019 13:45

• U1 Containment 10/09/2019 01:06

• U2 Containment Reactor Cavity 10/10/201901:32

Instructions to Workers (IP Section 02.02) (1 Sample)

The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.

(1) The inspectors reviewed the following:

Radiation Work Packages

• Radiation Work Permit 190002; U1 Containment and Annulus at Power Activities - Online; Revision 01

• Radiation Work Permit 190000; GL-08 Work - Online; Revision 01

• Radiation Work Permit 192042; 2R31 Reactor (Rx) Head Disassembly

/Reassembly; Revision 01

• Radiation Work Permit 192040; 2R31 Refuel Work; Revision 00 Electronic Alarming Dosimeter Alarms

• Electronic dosimeter dose rate alarm 12/07/2018 09:42

• Electronic dosimeter dose rate alarm 12/19/2018 08:35

• Electronic dosimeter dose rate alarm 10/02/2019 19:47

• Electronic dosimeter dose rate alarm 10/05/2019 22:45 Labeling of Containers

• Five equipment storage containers in the radioactive waste barrel yard Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.

(1) The inspectors verified the following sealed sources are accounted for and are intact:

• Cs-137 Source Number AC3498

• Ni-63 Source Number 941 Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

(1) There were no radiological work package for areas with airborne radioactivity available for inspection.

High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)

(1) The inspectors evaluated risk-significant high radiation area and very high radiation area controls.

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)

(1) The inspectors evaluated radiation worker performance and radiation protection technician proficiency.

71124.02 - Occupational ALARA Planning and Controls Radiological Work Planning (IP Section 02.01)

The inspectors evaluated the licensees radiological work planning.

(1) The inspectors reviewed the following activities:

• RWP 181071; 1R31 11 & 12 Steam Generator (SG) Primary Side Work

• RWP 192040; 2R31 Refuel Work

• RWP 192042; Reactor Head Disassembly/Reassembly Implementation of ALARA and Radiological Work Controls (IP Section 02.03) (1 Sample)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls.

(1) The inspectors reviewed the following activities:

• RWP 181071; 1R31 11 & 12 Steam Generator (SG) Primary Side Work

• RWP 192040; 2R31 Refuel Work

• RWP 192042; Reactor Head Disassembly/Reassembly

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation Self-Contained Breathing Apparatus for Emergency Use (IP Section 02.03)

The inspectors evaluated self-contained breathing apparatus program implementation.

(1) The inspectors reviewed the following:

Status and Surveillance Records for Self-Contained Breathing Apparatus

• 090900SG

• 095924KS

• 090920SG Self-Contained Breathing Apparatus Fit for On-Shift Operators

• On-shift crew number #1; 12/04/2019 Self-Contained Breathing Apparatus Maintenance Check

• 090890SG

• 095933KS

• 090900SG

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) Unit 1 between 10/01/2018 and 9/30/2019

(2) Unit 2 between 10/01/2018 and 9/30/2019 MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)

(1) Unit 1 between 10/01/2018 and 09/30/2019

(2) Unit 2 between 10/01/2018 and 09/30/2019 MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)

(1) Unit 1 between 10/01/2018 and 09/30/2019

(2) Unit 2 between 10/01/2018 and 09/30/2019 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)

(1)

(1) Unit 1 July 1, 2018 through September 30, 2019 (2)

(2) Unit 2 July 1, 2018 through September 30, 2019 OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1)

(1) July 1, 2018 through September 30, 2019 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)

(1) July 1, 2018 through September 30, 2019

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) The inspectors reviewed existing Unit 2 degraded, non-conforming, and adverse condition monitoring issues resolved during 2R31 on 10/17/2019 Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

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

(1) AR 501000030644, "NRC Question: Flood Barriers" and internal flood program on 12/03/2019

(2) Apparent Cause Evaluation 501000031050 regarding equipment classifications on 12/06/2019

71153 - Followup of Events and Notices of Enforcement Discretion Reporting (IP Section 03.05)

(1) The inspectors reviewed LER 2019-001-00 and the subsequent cancellation of this LER on 12/16/2019

INSPECTION RESULTS

Minor Violation 71152 Minor Violation: On August 12, 2019, the inspectors identified a Unit 2 RHR flood barrier that was shorter in height than other similar flood barriers. Specifically, a steel sleeve surrounding the floor penetration of Unit 2 RHR heat exchanger discharge piping was 15.5 inches tall, while similar sleeves installed on adjacent RHR piping were 24 inches tall. The inspectors questioned the discrepancy and the licensee evaluated this issue under AR 501000030644, NRC Question: Flood Barriers. The inspectors reviewed the licensees evaluation of this AR, the corrective actions, and they also performed a corrective action program review of the licensees internal flooding program.

The licensee determined that the existing auxiliary building design basis flooding analysis, ENG-ME-448, Auxiliary Building Flooding Analysis, Revision 1B, dated November 28, 2013, did not differentiate between postulated flooding caused by high energy line break (HELB)events and postulated flooding caused by ruptures of non-high energy piping. Additionally, the analysis did not distinguish between those systems specifically credited for safe shutdown following the different postulated flood events. The licensee also determined that RHR was not a credited system for safe shutdown following flooding from HELB-induced actuation of the fire protection system; however, RHR was credited for safe shutdown following postulated flooding caused by ruptures involving certain non-high energy piping. The licensee refined the calculation methodology and adjusted inputs to account for the shorter barrier. Based on this, the licensee determined that with the shorter barrier, RHR room flooding would not begin until 513 minutes after the onset of the postulated flood. This conclusion provided additional margin to the USAR Section 6.1.2.8.2 stated time of 296 minutes for this scenario. Because margin was added following re-calculation, and the associated time critical operator action to isolate flood water for this scenario was validated to occur within approximately 37 minutes, Unit 2 RHR operability was not affected by the shorter flood barrier.

Screening: The inspectors determined the performance deficiency was minor. Although the licensee's internal flooding design basis analysis for the auxiliary building contained an incorrect input for the maximum postulated flood height, revision of the analysis demonstrated that more margin existed than was previously understood. Therefore, the performance deficiency did not have the potential to lead to a more significant safety concern if left uncorrected.

Enforcement:

The failure to assure that the postulated internal flood design basis was correctly translated into the specifications for a Unit 2 RHR flood barrier per the requirements of Title 10 CFR, Appendix B, Criterion III, "Design Control," constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy. To restore compliance, the licensee revised ENG-ME-448, and planned to update Prairie Island USAR Section 6.1.2.8.2.

Observation: Apparent Cause Evaluation for Containment Isolation Valve 71152 Active/Passive Concern The inspectors reviewed an apparent cause evaluation associated with AR 501000031050 regarding Technical Specification testing requirements for 12 sample containment isolation valves. The inspectors reviewed the apparent cause, corrective actions, and extent of condition/cause, and did not identify any issues of concern.

Observation: Unit 2 Refueling Outage Item Resolution 71152 The inspectors performed a trend review of corrective action program items scheduled for resolution during the Unit 2 refueling outage conducted in October of 2019. These items included degraded, non-conforming, and adverse condition monitoring issues, as well as removal of any temporary modifications that were scoped into the outage schedule. The inspectors reviewed whether any trends existed in the bases for deferred items and/or aggregate impacts. The inspectors also reviewed final corrective actions taken for those issues that were addressed during the refueling outage. The inspectors did not identify any concerns during these reviews.

Observation: Cancellation of LER 2019-001-00 on 12/16/2019 71153 The inspectors reviewed LER 2019-001-00 and the subsequent cancellation of this LER on 12/16/2019. The inspectors reviewed the reporting basis under a partial sample in Section 71153 of Prairie Island Inspection Report 2019003. After the LER was submitted, the licensee subsequently determined during inspections and testing during a Unit 2 refueling outage that a condition prohibited by Technical Specifications did not occur. Therefore, the licensee cancelled the LER. The inspectors reviewed the basis for the cancellation and did not identify any issues of concern. This LER is closed.

EXIT MEETINGS AND DEBRIEFS

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

• On January 16, 2020, the inspectors presented the integrated inspection results to Mr. S. Sharp, Site Vice President and other members of the licensee staff.

• On October 10, 2019, the inspectors presented the Radiation Protection Baseline inspection results to Mr. S. Sharp, Site Vice President and other members of the licensee staff.

• On October 24, 2019, the inspectors presented the ISI Inspection for Prairie Island 2R31 inspection results to Ms. S. Schwartz, Fleet Regulatory Affairs and other members of the licensee staff.

• On December 5, 2019, the inspectors presented the radiation protection baseline inspection results to Mr. H. Hanson, Plant Manager and other members of the licensee staff.

• On December 6, 2019, the inspectors presented the Emergency Preparedness Inspection Exit inspection results to Mr. P. Beyers, Director of Emergency Preparedness and other members of the licensee staff.

• On January 16, 2020, the inspectors presented the Integrated Inspection Report inspection results to Mr. S. Sharp, Site Vice President and other members of the licensee staff.

THIRD PARTY REVIEWS Inspectors reviewed an Institute of Nuclear Power Operations report that was issued during the inspection period.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action AR Seasonal Readiness Preparation 11/12/2019

Documents 501000034574

AR No Prompt Exists for Cold Temperature Checks 12/10/2019

501000035542

Procedures TP 1637 Winter Plant Operation 56

71111.04Q Corrective Action AR DDCLP Filter Question from NRC Resident 11/14/2019

Documents 501000034697

Resulting from

Inspection

Drawings NF-39216-1 Flow Diagram Cooling Water - Screenhouse Unit 1 & Unit 2 04/11/2007

NF-39237 Flow Diagram Containment Spray System Units 1 and 2 12

NF-39252 Flow Diagram Caustic Addition System Units 1 and 2 12

Procedures C1.1.20.5-2 Unit 2 4.16kV System Switches and Indication Checklist 30

C1.1.20.6-2A Unit 2 480V System Switches and Indication Checklist 40

71111.05Q Drawings F5 Appendix A Fire Detection Zone 35; 21 and 22 Battery Rooms; Floor 30

Elevation 695'

Fire Plans F5 Appendix A Fire Detection Zone 54; Fire Area 71; Reactor Building Unit 44

2; Elevation 755'

F5 Appendix A Fire Detection Zone 52; Fire Area 71; Reactor Building Unit 44

2; Elevation 733' 9"

F5 Appendix A Fire Detection Zone 42; Fire Area 71; Reactor Building Unit 44

2, Elevation 697' 6"'

F5 Appendix A Fire Detection Zone 56; Fire Area 71; Reactor Building Unit 44

2; Elevation 711' 6"

Procedures F5 APP K Fire Protection Systems Functional Requirements 32

Fire Detection Unit 2 Auxiliary Building, Elevation 695' 41

Zone 40-

Appendix A

71111.07A Procedures GMP YUBA-001 CC Heat Exchanger Periodic Maintenance 9

H21 Generic Letter 89-13 Implementing Program 26

Work Orders GMP YUBA-001 WO 498516; GMP YUBA-001 10/30/2015

71111.08P Corrective Action 20015381 Shelf Life for Liquid Penetrant Materials 07/26/2011

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 501000031647 Framatone SG Welding Issues 09/23/2019

NDE Reports 2019P001 Liquid Penetrant Examination (PT) of Class 1 Intergral 10/10/2019

2019U014 Ultrasonic Examination (UT) of Elbow to Pipe Weld on 10/10/2019

Reactor Coolant System, Component ID W-6

2019U016 Ultrasonic Examination (UT) of Elbow to Elbow Weld on 10/10/2019

Reactor Coolant System, Component ID W-5

2019V013 Visual Examination (VT) of Intergal Attachment (Snubber) 10/09/2019

Component ID CCH-182/IA

Procedures 602000004765 PDI Generic Procedure for Ultrasonic Examination of 10/04/2017

Austenitic Pipe Welds PDI-UT-2

FP-PE-NDE-200 Solvent Removable Visual Dye Penetrant Examination 1

FP-PE-NDE-402 Ultrasonic Examination of Austenitic Pipe Welds- 7

Supplement 2

FP-PE-NDE-408 Straight Beam Ultrasonic Examination of Bolts and Studs 8

FP-PE-NDE_510 Visual Examination, VT-1 01/13/2017

71111.11Q Work Orders WO 700055782 SP 1106B-22 DD CL PMP (245-392) 1 M Test 12/27/2019

71111.13 Corrective Action AR Hole Found in 3" Fuel Oil Supply Line 12/02/2019

Documents 501000035273

AR Oil Addition 22 CC PMP OB 12/24/2019

501000036061

71111.15 Corrective Action AR Auxiliary Building Roof Leak 06/06/2019

Documents 501000028115

AR Passive MOV Usage Procedural Steps 08/21/2019

501000031050

AR Missed Surveillance on Sampling CIVs 09/16/2019

501000031973

AR MOVs to be Rescoped to GL PGM 09/16/2019

501000031991

AR Prompt Operability Determination POD 500000300508 0

501000032539

AR D6 FO Valves Forming Signs of Drip 10/15/2019

501000033348

AR High Temperature Cycle 8 Engine 1 D6 10/15/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

501000033349

AR D6 Electric Governor Fail 10/15/2019

501000033362

AR 245-071, 21 SI PMP Outboard Seal Leak 10/19/2019

501000033567

AR 245-071, 21 SI Pump Outboard Seal Leak 10/19/2019

501000033567

AR 22 TDAFP Governor Adjustment 10/26/2019

501000033944

AR PMT Work Plan has PEG Step Prevention SUPR 10/26/2019

501000033975

AR 22 TD AFWP High Outboard BRG Temperature 10/28/2019

501000033986

Procedures FP-E-MR-03 Maintenance Rule Monitoring 7

FP-E-MR-07 Maintenance Rule - Structures Monitoring 2

H24.3 Structures Monitoring Program 16

PM 3586-10 Periodic Structures Inspection 11

PM 3586-10 Periodic Structures Inspection 11

PM 3586-11 Shield Building Caulking Inspection 6

SP 2036 Turbine Overspeed Trip Exercise 38

SP 2088A Train A Safety Injection Quarterly Test 31

SP 2103B Unit 2 Train B AFW Comprehensive IST Pump and Valve 1

Test

71111.19 Corrective Action AR Bus 26 Inspection 10/09/2019

Documents 501000033056

AR D6 Electric Governor Fail 10/15/2019

501000033362

SP 2083B Unit 2 Integrated SI Test with a Simulated Loss of Offsite 12

Power Train B

71111.20 Corrective Action AR Entered C17 AOP3 10/15/2019

Documents 501000033397

AR Bowed Fuel Bundle Critical Path Lost Time 10/14/2019

501000033412

Procedures 2C1-3-M5 Unit 2 Shutdown to Mode 5 17

Inspection Type Designation Description or Title Revision or

Procedure Date

2C4.1 RCS Inventory Control Refueling 46

2R31 Prairie Island Refueling Outage October 2019 09/03/2019

CP# 2R31-1 Outage Contingency Planning Form-Decay Heat Removal 06/04/2019

Single Point Vulnerability to Orange

CP# 2R31-2 Outage Contingency Planning Form - Protect SFP CC Flow 06/04/2019

for all Alignments

CP# 2R31-3 Lowered Inventory Pre-Refuel 06/04/2019

CP# 2R31-4 Outage Contingency Planning Form - 2R31 Lowered 06/04/2019

Inventory Post-Refuel

CP# 2R31-5 Outage Contingency Planning Form-SSA Power Single 06/04/2019

Point Vulnerability to Orange

CP# 2R31-8 Outage Contingency Planning Form-CC HX Open Flood 06/04/2019

Plan

D2-15 Unit 2 Reduced Inventory SI Lineup 8

D2-9 Draining the Reactor Coolant System Unit 2-MV-32169 15

Open Breaker Off Highlighted

D30 Post Refueling Startup Testing 66

PRA No: Reactor Cavity GOTHIC Time to Boil 1

V.SMN.17.002

SP 2294 Installation/Removal of Automatic SI Reset Bypasses 19

71111.22 Corrective Action AR CV-31620 Exceeded Admin Limit on LLRT 10/09/2019

Documents 501000033076

Operability 2C20.9 AOP4 Failure of 22 Battery Charger 15

Evaluations

Procedures H19 Containment Leakage Rate Testing 24

SP 2072.11 Local Leakage Rate Test of Penetration 11 (Letdown Line) 18

SP 2083B Unit 2 Integrated SI Test With a Simulated Loss of Offsite 12

Power Train B

SP 2314 22 Battery Refueling Outage Discharge Test 34

Work Orders SP 2083B Protected Equipment Work Approval Form - Bus 25-1 10/22/2019

WO 700025162 Install Temp Charger on 22 Battery 0

WO 700030150 SP 2083B-Integrated SI Test w/Simulated Loop B Train 08/14/2019

WO 700038207 SP 2072.11-LLRT 2 PEN 11 Post-Maintenance 06/10/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

WO 70029825 SP 2072.11-LLRT 2PEN Letdown Line 10/09/2019

71114.04 Corrective Action 05000022935 NOS ID: Question Regarding EAL Calculation 02/08/2019

Documents 501000022887 NOS-ID: Emergency Plan PAR Dose Rate Estimate 02/07/2019

Miscellaneous PI-2018-617 50.54(q) Screening/Evaluation 12/17/2018

PI-2018-633 50.54(q) Screening/Evaluation 01/31/2019

PI-2019-656 50.54(q) Screening/Evaluation 02/22/2019

PI-2019-679 50.54(q) Screening/Evaluation 06/18/2019

71124.01 Corrective Action 501000020798 Invalid Dose Rate Alarm Received 12/07/2018

Documents 501000032736 Potential for Unbriefed Dose Rate Alarm 10/05/2019

501000032786 Radiological Near Miss HRA Posting 10/07/2019

Corrective Action 501000032971 Dose Rates Missing from Routine Survey 10/09/2019

Documents

Resulting from

Inspection

Miscellaneous Prairie Island Plant Alpha Characterization Study 03/29/2019

National Source Tracking System Annual Reconciliation 01/02/2019

Procedures RPIP 1118 Conducting Radiological Surveys 29

RPIP 1120 Posting of Restricted Areas 46

RPIP 1201 Airborne Radioactive Particulate and Iodine Sampling 12

Self-Assessments Inspection Procedure 71124.01 Self-Assessment 10/07/2019

Work Orders 700050449 Radioactive Source Inventory/Leak Test 08/16/2019

71124.02 ALARA Plans 181071 1R31 Steam Generator Primary Work 0

2040 2R31 Reactor Refueling 0

2042 2R31 Reactor Dissassebly/Re-assembly 0

Corrective Action AR Work Order Over Dose Estimate 05/16/2018

Documents 501000012071

AR Station Alara Committee Dose Estimate Increased 10/07/2018

501000018176

AR SP-1544 Over Dose Estimate 09/04/2019

501000031456

Miscellaneous 1R31 Radiation Protection Post Outage Report 01/08/2019

2R31 Radiation Protection Post Outage Report 11/22/2019

181071 1R31 11 & 12 Steam Generator Primary Side Work Post 12/16/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

Job Evaluation

181071 50% Work In Progress Review Steam Generator Primary 10/06/2018

Side Work

181071 80% Work In Progress Review Steam Generator Primary 10/08/2018

Side Work

2040 50% Work In Progress Review 2R31 Refuel Work 10/15/2019

2040 80% Alara Work In Progress Review 2R31 Refuel Work 10/16/2019

2042 50% Alara Work In Progress Review 2R31 Reactor 10/18/2019

Disassembly/Re-assembly

2042 80% Work In Progress Review 2R31 Reactor 10/19/2019

Disassembly/Re-assembly

Procedures FP-RP-SAC-01 Station Alara Committees 8

Radiation Work 181071 1R31 11 & 12 Steam Generator Primary Side Work 1

Permits (RWPs) 192040 2R31 Refuel Work 0

2042 2R31 Reactor Disassebly/Re-assembly 0

71124.03 Corrective Action AR SCBA Inspection Incomplete 02/15/2018

Documents 501000008440

Resulting from

Inspection

Miscellaneous Operations RO/SRO Dayshift Crew #1 Respiratory 12/04/2019

Protection Records

Respiratory Protection Checks 07/05/2019

Respiratory Protection Checks 08/21/2019

Respiratory Protection Checks 09/13/2019

Procedures C40.5 Control Room Breathing Air System 3

H26 Respiratory Protection Program 14

RPIP 1215 Respiratory Equipment Control 10

71152 Calculations ENG-ME-448 Auxiliary Building Flooding Analysis 2

Corrective Action AR Improvement Opp in CAP Evaluation and Closure 08/23/2019

Documents 501000031131

AR Decline in Licensee ID Finding/Violation 10/30/2019

501000034128

Procedures H36 Plant Flooding 11

Inspection Type Designation Description or Title Revision or

Procedure Date

71153 Corrective Action AR Potential Diaphragm Degraded: MV-32410 08/07/2019

Documents 501000030520

Procedures SP 2072.17 Local Leakage Rate Test of Penetration 17 (Hot Leg Loop B 19

Sample Line)

20