IR 05000282/2019004
| 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
January 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:
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
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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
- (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) (3 Samples)
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) (5 Samples)
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) (1 Sample)
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
- 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 Sample)
- (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) (1 Sample)
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) (3 Samples)
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) (6 Samples)
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) (7 Samples)
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 Sample)
- (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 Sample)
- (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) (1 Sample)
The inspectors evaluated:
- (1) Licensed operator re-qualification training with Drill and Exercise Performance Indicator opportunities on 11/20/2019
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 02.01) (1 Sample)
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) (1 Sample)
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) (1 Sample)
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 Sample)
- (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 Active/Passive Concern 71152 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
501000034574
Seasonal Readiness Preparation
11/12/2019
501000035542
No Prompt Exists for Cold Temperature Checks
2/10/2019
Procedures
TP 1637
Winter Plant Operation
71111.04Q Corrective Action
Documents
Resulting from
Inspection
501000034697
DDCLP Filter Question from NRC Resident
11/14/2019
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
NF-39252
Flow Diagram Caustic Addition System Units 1 and 2
Procedures
C1.1.20.5-2
Unit 2 4.16kV System Switches and Indication Checklist
C1.1.20.6-2A
Unit 2 480V System Switches and Indication Checklist
71111.05Q Drawings
F5 Appendix A
Fire Detection Zone 35; 21 and 22 Battery Rooms; Floor
Elevation 695'
Fire Plans
F5 Appendix A
Fire Detection Zone 54; Fire Area 71; Reactor Building Unit
2; Elevation 755'
F5 Appendix A
Fire Detection Zone 52; Fire Area 71; Reactor Building Unit
2; Elevation 733' 9"
F5 Appendix A
Fire Detection Zone 42; Fire Area 71; Reactor Building Unit
2, Elevation 697' 6"'
F5 Appendix A
Fire Detection Zone 56; Fire Area 71; Reactor Building Unit
2; Elevation 711' 6"
Procedures
F5 APP K
Fire Protection Systems Functional Requirements
Fire Detection
Zone 40-
Appendix A
Unit 2 Auxiliary Building, Elevation 695'
Procedures
GMP YUBA-001
CC Heat Exchanger Periodic Maintenance
H21
Generic Letter 89-13 Implementing Program
Work Orders
GMP YUBA-001
WO 498516; GMP YUBA-001
10/30/2015
Corrective Action
20015381
Shelf Life for Liquid Penetrant Materials
07/26/2011
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Reactor Coolant System, Component ID W-6
10/10/2019
2019U016
Ultrasonic Examination (UT) of Elbow to Elbow Weld on
Reactor Coolant System, Component ID W-5
10/10/2019
2019V013
Visual Examination (VT) of Intergal Attachment (Snubber)
Component ID CCH-182/IA
10/09/2019
Procedures
2000004765
PDI Generic Procedure for Ultrasonic Examination of
Austenitic Pipe Welds PDI-UT-2
10/04/2017
FP-PE-NDE-200
Solvent Removable Visual Dye Penetrant Examination
FP-PE-NDE-402
Ultrasonic Examination of Austenitic Pipe Welds-
Supplement 2
FP-PE-NDE-408
Straight Beam Ultrasonic Examination of Bolts and Studs
FP-PE-NDE_510
Visual Examination, VT-1
01/13/2017
71111.11Q Work Orders
SP 1106B-22 DD CL PMP (245-392) 1 M Test
2/27/2019
Corrective Action
Documents
501000035273
Hole Found in 3" Fuel Oil Supply Line
2/02/2019
501000036061
2/24/2019
Corrective Action
Documents
501000028115
Auxiliary Building Roof Leak
06/06/2019
501000031050
Passive MOV Usage Procedural Steps
08/21/2019
501000031973
Missed Surveillance on Sampling CIVs
09/16/2019
501000031991
MOVs to be Rescoped to GL PGM
09/16/2019
501000032539
Prompt Operability Determination POD 500000300508
501000033348
D6 FO Valves Forming Signs of Drip
10/15/2019
High Temperature Cycle 8 Engine 1 D6
10/15/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000033349
501000033362
D6 Electric Governor Fail
10/15/2019
501000033567
245-071, 21 SI PMP Outboard Seal Leak
10/19/2019
501000033567
245-071, 21 SI Pump Outboard Seal Leak
10/19/2019
501000033944
TDAFP Governor Adjustment
10/26/2019
501000033975
PMT Work Plan has PEG Step Prevention SUPR
10/26/2019
501000033986
TD AFWP High Outboard BRG Temperature
10/28/2019
Procedures
FP-E-MR-03
Maintenance Rule Monitoring
FP-E-MR-07
Maintenance Rule - Structures Monitoring
H24.3
Structures Monitoring Program
Periodic Structures Inspection
Periodic Structures Inspection
Shield Building Caulking Inspection
SP 2036
Turbine Overspeed Trip Exercise
SP 2088A
Train A Safety Injection Quarterly Test
SP 2103B
Unit 2 Train B AFW Comprehensive IST Pump and Valve
Test
Corrective Action
Documents
501000033056
Bus 26 Inspection
10/09/2019
501000033362
D6 Electric Governor Fail
10/15/2019
SP 2083B
Unit 2 Integrated SI Test with a Simulated Loss of Offsite
Power Train B
Corrective Action
Documents
501000033397
Entered C17 AOP3
10/15/2019
501000033412
Bowed Fuel Bundle Critical Path Lost Time
10/14/2019
Procedures
Unit 2 Shutdown to Mode 5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2C4.1
RCS Inventory Control Refueling
2R31
Prairie Island Refueling Outage October 2019
09/03/2019
CP# 2R31-1
Outage Contingency Planning Form-Decay Heat Removal
Single Point Vulnerability to Orange
06/04/2019
CP# 2R31-2
Outage Contingency Planning Form - Protect SFP CC Flow
for all Alignments
06/04/2019
CP# 2R31-3
Lowered Inventory Pre-Refuel
06/04/2019
CP# 2R31-4
Outage Contingency Planning Form - 2R31 Lowered
Inventory Post-Refuel
06/04/2019
CP# 2R31-5
Outage Contingency Planning Form-SSA Power Single
Point Vulnerability to Orange
06/04/2019
CP# 2R31-8
Outage Contingency Planning Form-CC HX Open Flood
Plan
06/04/2019
D2-15
Unit 2 Reduced Inventory SI Lineup
D2-9
Draining the Reactor Coolant System Unit 2-MV-32169
Open Breaker Off Highlighted
D30
Post Refueling Startup Testing
PRA No:
V.SMN.17.002
Reactor Cavity GOTHIC Time to Boil
SP 2294
Installation/Removal of Automatic SI Reset Bypasses
Corrective Action
Documents
501000033076
CV-31620 Exceeded Admin Limit on LLRT
10/09/2019
Operability
Evaluations
2C20.9 AOP4
Failure of 22 Battery Charger
Procedures
H19
Containment Leakage Rate Testing
SP 2072.11
Local Leakage Rate Test of Penetration 11 (Letdown Line)
SP 2083B
Unit 2 Integrated SI Test With a Simulated Loss of Offsite
Power Train B
SP 2314
Battery Refueling Outage Discharge Test
Work Orders
SP 2083B
Protected Equipment Work Approval Form - Bus 25-1
10/22/2019
Install Temp Charger on 22 Battery
SP 2083B-Integrated SI Test w/Simulated Loop B Train
08/14/2019
SP 2072.11-LLRT 2 PEN 11 Post-Maintenance
06/10/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SP 2072.11-LLRT 2PEN Letdown Line
10/09/2019
Corrective Action
Documents
05000022935
NOS ID: Question Regarding EAL Calculation
2/08/2019
501000022887
NOS-ID: Emergency Plan PAR Dose Rate Estimate
2/07/2019
Miscellaneous
PI-2018-617
50.54(q) Screening/Evaluation
2/17/2018
PI-2018-633
50.54(q) Screening/Evaluation
01/31/2019
PI-2019-656
50.54(q) Screening/Evaluation
2/22/2019
PI-2019-679
50.54(q) Screening/Evaluation
06/18/2019
Corrective Action
Documents
501000020798
Invalid Dose Rate Alarm Received
2/07/2018
501000032736
Potential for Unbriefed Dose Rate Alarm
10/05/2019
501000032786
Radiological Near Miss HRA Posting
10/07/2019
Corrective Action
Documents
Resulting from
Inspection
501000032971
Dose Rates Missing from Routine Survey
10/09/2019
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
RPIP 1120
Posting of Restricted Areas
RPIP 1201
Airborne Radioactive Particulate and Iodine Sampling
Self-Assessments
Inspection Procedure 71124.01 Self-Assessment
10/07/2019
Work Orders
700050449
Radioactive Source Inventory/Leak Test
08/16/2019
ALARA Plans
181071
1R31 Steam Generator Primary Work
2040
2R31 Reactor Refueling
2042
2R31 Reactor Dissassebly/Re-assembly
Corrective Action
Documents
501000012071
Work Order Over Dose Estimate
05/16/2018
501000018176
Station Alara Committee Dose Estimate Increased
10/07/2018
501000031456
SP-1544 Over Dose Estimate
09/04/2019
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
2/16/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Job Evaluation
181071
50% Work In Progress Review Steam Generator Primary
Side Work
10/06/2018
181071
80% Work In Progress Review Steam Generator Primary
Side Work
10/08/2018
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
Disassembly/Re-assembly
10/18/2019
2042
80% Work In Progress Review 2R31 Reactor
Disassembly/Re-assembly
10/19/2019
Procedures
FP-RP-SAC-01
Station Alara Committees
Radiation Work
Permits (RWPs)
181071
1R31 11 & 12 Steam Generator Primary Side Work
2040
2R31 Refuel Work
2042
2R31 Reactor Disassebly/Re-assembly
Corrective Action
Documents
Resulting from
Inspection
501000008440
SCBA Inspection Incomplete
2/15/2018
Miscellaneous
Operations RO/SRO Dayshift Crew #1 Respiratory
Protection Records
2/04/2019
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
H26
Respiratory Protection Program
RPIP 1215
Respiratory Equipment Control
Calculations
ENG-ME-448
Auxiliary Building Flooding Analysis
Corrective Action
Documents
501000031131
Improvement Opp in CAP Evaluation and Closure
08/23/2019
501000034128
Decline in Licensee ID Finding/Violation
10/30/2019
Procedures
H36
Plant Flooding
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
501000030520
Potential Diaphragm Degraded: MV-32410
08/07/2019
Procedures
SP 2072.17
Local Leakage Rate Test of Penetration 17 (Hot Leg Loop B
Sample Line)
19