IR 05000282/2022004
| ML23025A401 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/26/2023 |
| From: | Hironori Peterson NRC/RGN-III/DORS/RPB3 |
| To: | Domingos C Northern States Power Company, Minnesota |
| References | |
| IR 2022004 | |
| Preceding documents: |
|
| Download: ML23025A401 (1) | |
Text
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000282/2022004 AND 05000306/2022004
Dear Christopher Domingos:
On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant. On January 13, 2023, 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 Reactor Projects Branch 3 Division of Operating Reactor Safety 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:
05000282/2022004 and 05000306/2022004
Enterprise Identifier:
I-2022-004-0053
Licensee:
Northern States Power Company
Facility:
Prairie Island Nuclear Generating Plant
Location:
Welch, MN
Inspection Dates:
October 01, 2022, to December 31, 2022
Inspectors:
S. Bell, Health Physicist
J. Bozga, Senior Reactor Inspector
A. Demeter, Project Engineer
T. Iskierka-Boggs, Senior Operations Engineer
V. Myers, Senior Health Physicist
K. Pusateri, Resident Inspector
D. Tesar, Senior Resident Inspector
Approved By:
Hironori Peterson, Chief
Reactor Projects Branch 3
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at 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
Type Issue Number Title Report Section Status URI 05000282/2022004-
Bus 15 Failure to Meet Acceptance Criteria 71111.15 Open URI 05000306,05000282
/2018-011-02 Potential Failure to Protect Class I Structures, Systems, and Components from Tornado Generated Missiles 71111.21M Closed LER 05000282,05000306
/2022-001-00 LER 2022-001-00 for Prairie Island Nuclear Generating Plant, Units 1 and 2, Fuel Assemblies Incorrectly Placed in Spent Fuel Pool 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On September 20, 2022, at 09:27, the unit entered coast down to the refueling outage. On October 14, 2022, at 10:45, unit 1 was shut down from 84 percent power, starting the 1R33 refueling outage (RFO). The unit was taken critical on November 7, 2022, at 22:23, and was synched to the grid on November 9, 2022, at 10:21, ending the 1R33 RFO. The unit was returned to full-rated thermal power on November 12, 2022, at 15:35, and remained at or near rated thermal power for the remainder of the inspection period except for brief power reductions to perform surveillance testing or flexible power operations.
Unit 2 operated at or near rated thermal power for the entire inspection period with the exception of brief power reductions to perform surveillance testing or flexible power operations.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, appendix D, Plant Status, observed risk-significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset, inspectors reviewed implementation of TP 1637, Revision 58, "Annual Winter Plant Operation," on September 26, 2022.
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather freeze/thaw/snow cycles on susceptible risk-significant components on November 21, 2022.
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) Unit 1 auxiliary feedwater system following integrated safety injection testing on October 17, 2022
- (2) Unit 1 4.16kV 'B' train electrical walkdown during Yellow risk on October 19, 2022
- (3) Unit 1 4.16kV system following restoration of bus 15 on October 26, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the spent fuel pool cooling during unit 1 refueling outage system on October 18, 2022.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Unit 1 containment reactor coolant pump vaults fire walkdown on October 15, 2022
- (2) Spent fuel pool during fuel moves fire walkdown on October 21, 2022
- (3) Unit 1 containment general areas for 715', 735', and 755' elevations on October 25, 2022
- (4) Walkdown of screenwash pump with motor-driven and diesel-driven fire pumps out of service on October 24, 2022
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) Auxiliary feedwater pump and hot shutdown panel room
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (5) Year Containment Fan Coil Unit Performance Test"
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 October 17 to October 28, 2022:
03.01.a - Nondestructive Examination and Welding Activities
ultrasonic testing (UT) exam of reactor coolant (RC) pipe-to-pipe weld for component W-5
UT exam of RC elbow-to-pipe weld for component W-4
magnetic particle examination of 11 steam generator feedwater nozzle-to-shell weld component N-1
visual examination (VT-3) of 11 component cooling heat exchanger support
11 RC pump support indication evaluation
welds 1 thru 12 for cooling water piping replacement 24-CL-13 (WO 700072740-0340)03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities
bare metal visual examination (VE) of the unit 2 reactor vessel upper head penetrations nozzles 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities
boric acid leakage evaluation on component ID SI-14-1 (Issue Report 501000054481)
boric acid leakage evaluation on component ID CV-31201 (Issue Report 501000049320)
boric acid leakage evaluation on component ID CV-31200 (Issue Report 501000045188)
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating tests administered from April 25 thru June 6, 2022. One licensed operator that was unable to take the 2021 licensed operator examinations due to medical restrictions, has since been remediated, and was administered a makeup biennial written examination and applicable annual operating test to meet CFR requirements for standing watch as a senior reactor operator.
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 during the unit 1 cooldown operations on October 15, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator requalification simulator sessions on December 5, 2022.
- (2) The inspectors observed and evaluated simulator scenarios on November 14, 2022.
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) 'A' train cooling water header valve replacements on October 20, 2022
- (2) RS-19-1 Furmanite found on December 7, 2022
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) Bus 15 maintenance during outage - aging management on November 1, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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) Risk evaluation for reactor vessel drain down evolution to 1' below flange on October 17, 2022
- (2) WO 700098197, "Zebra Mussel Treatment"
- (3) WO 700107193-23, "Inverter Corrective Maintenance"
- (4) RICT implementation on Unit 2 during unit 1 outage on October 24, 2022
- (5) Risk assessment during Yellow risk due to reduced inventory and single train of decay heat removal period on October 18, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)1N32 operability evaluation Technical Specification (TS) 3.3.1
- (2) Cooling water header RTO and 22 diesel-driven cooling water pump (DDCLP)relief lifting (3)12 DDCLP speed switch timing, as documented in CAP 501000067737
- (4) CAP 501000068275, "N35 Operability in Mode 2 Above P6"
- (5) Makeup air handling unit (MUAH) post-maintenance SP's
- (6) D5 rack differential detector
- (7) Bus 15 following maintenance on November 1, 2022
71111.18 - Plant Modifications
Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)
- (1) The inspectors verified the site SAMG were updated in accordance with the PWR generic severe accident technical guidelines and validated in accordance with Nuclear Energy Institute (NEI) 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, revision 1 on November 1, 2022.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post-maintenance testing (PMT) activities to verify system operability and/or functionality:
- (1) WOs 700094054-02, -04, -06, -08, "Power Range Detector Bypass Modification Installation for NIs 41, 42, 43, and 44"
- (2) WO 700114928, "Inspect and Test 22 DDCLP Jacket HX Relief"
- (3) Breaker 15-2 PMT via D1 emergency diesel generator slow start on October 26, 2022
- (4) SP 1373, "RS-19-1 U1 Loop A MSIV Non-Return Check Valve IST Test," on October 31, 2022 (5)11TDAFW, "Testing Post Refueling Maintenance," on November 10, 2022
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated RFO 1R33 activities from October 14, 2022, thru November 9, 2022.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (4 Samples)
- (2) SP 1083, "Integrated Safety Injection Test," on October 16, 2022
- (3) SP 1092B, "Safety Injection Check Valve Test (Head Off) part B," on October 19, 2022
- (4) SP 1092A, "Safety Injection Check Valve Test (Head Off) part A," on October 28, 2022
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) SP 1090B, "Containment Spray Pump Quarterly IST Test," on December 15, 2022
RCS Leakage Detection Testing (IP Section 03.01) (2 Samples)
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:
FT-2021-756, FP-S-FSIP-07 Revision, 10/27/2021
PI-2021-753, F3-17 Revision, 11/20/2021
PI-2021-754, EDCM 300 Revision, 08/30/2021
PI-2021-757, F3-13.3 Revision, 11/08/2021
PI-2021-758, F3-23-1C and F3-23-2C Revisions, 11/10/2021
PI-2022-764, PING 580 Revision, 01/27/2022 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) Emergency preparedness exercise walkthrough with drill and exercise performance on December 13,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Licensee surveys of potentially contaminated material leaving the radiologically controlled area
- (2) Workers exiting the radiologically controlled area
- (3) Workers exiting unit 1 containment
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) RC pump motor replacement under RWP 221020
- (2) Valve maintenance in the regenerative heat exchanger room under RWP 221007
- (3) Reactor head O-ring removal under RWP 221042 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Regenerative heat exchanger area
- (2) Spent fuel pool skimmer pump room
- (3) Reactor head stand
- (4) Reactor cavity sump 'C' Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Auxiliary building sump pit
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (6 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Portable ion chambers survey instruments stored ready for use at the radiologically controlled area exit facility
- (2) Observed the calibration of the Raddos personnel contamination monitor, Serial Number 479902
- (3) Observed the operation of the Hopewell Designs gamma irradiator
- (4) Observed the calibration of the MG Telepole, Serial Number 6605-075
- (5) Observed the performance of source checks on the Canberra Fastscan whole body counter
- (6) Portable GM contamination survey instruments stored and ready for use at the radiologically controlled area exit facility
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Canberra Fastscan whole body counter
- (2) JL Shepherd Model 89 gamma irradiator
- (3) Hopewell Designs Model G10-2-2600-2SR gamma irradiator
- (4) MGP DMC 3000 electronic dosimeter, serial number 100511
- (5) MGP IRD 2000 gamma calibrator (6)1/2 R-48 containment high range monitor
- (7) Thermo Scientific SAM 12 small article monitor, serial number 537597
- (8) Rados personnel contamination monitor, serial number 479900
- (9) Control room ventilation system train A
- (10) Ludlum Model 2241-4/42-31H, serial numbers 279858/PR296854
- (11) Area radiation monitor 2R53, SI pump area
- (12) Eberline AMS4 air sampler, serial number 1289
- (13) Gamma spectroscopy system #13 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 1 steam generator blowdown liquid effluent monitor (1R-19)
- (2) Unit 1 shield building ventilation monitor (1R-22)
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06)===
- (1) Unit 1 (October 1, 2021, through September 30, 2022)
- (2) Unit 2 (October 1, 2021, through September 30, 2022)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (October 1, 2021, through September 30, 2022)
- (2) Unit 2 (October 1, 2021, through September 30, 2022)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (October 1, 2021, through September 30, 2022)
- (2) Unit 2 (October 1, 2021, through September 30, 2022)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2021, through September 30, 2022)
- (2) Unit 2 (October 1, 2021, through September 30, 2022)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 (April 1, 2021, through September 30, 2022)
- (2) Unit 2 (April 1, 2021, through September 30, 2022)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) April 1, 2021, through September 30, 2022 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) April 1, 2021, through September 30, 2022
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2022-001-00 Fuel Assemblies Incorrectly Placed in Spent Fuel Pool (ADAMS Accession No. ML22290A172). The inspection conclusions associated with this LER are documented in Inspection Report 05000282/2022003 and 05000306/2022003 (ADAMS Accession No. ML22300A183) under Inspection Results Section
INSPECTION RESULTS
Unresolved Item (Open)
Bus 15 Failure to Meet Acceptance Criteria URI 05000282/2022004-01 71111.15
Description:
During maintenance on safety-related safeguards bus 15, the resistance values obtained failed to meet acceptance criteria. The licensee took additional actions to disassemble, clean, and reassemble the bus bars in an attempt to improve the resistance readings. However, the as-left values were higher than the as-found values. Engineering performed an evaluation to disposition the as-left data not meeting acceptance criteria. Upon reviewing the documents associated with this activity, the inspectors had several questions regarding the work performed, documentation of work performed, and technical justification for the engineering evaluation.
Planned Closure Actions: Inspectors need to evaluate the adequacy of the work performed and/or work order documentation for compliance with 10 CFR 50, appendix B, criterion V requirements as well as the licensee quality assurance program and implementing procedures. In addition, inspectors will need to assess and evaluate the technical justification in the licensee's engineering evaluation to determine reasonable assurance that the safeguards bus will continue to perform its specified safety function until the next performance of the maintenance which is scheduled in 4 years.
Licensee Actions: Based upon the data not meeting the acceptance criteria, the licensee disassembled at least some of the connections, cleaned, and reassembled the bus bar connections. In addition, they reduced the period between inspections from 8 years to 4 years per the EPRI recommendations. Since the licensee had restored the bus bar to operable condition, the inspectors have no immediate safety concerns.
Corrective Action References: 501000054247, "PE 009 Acceptance Criteria Change-Update" 501000068630, "PE 0009 In Need of Update" 501000067574, "Over-Limit High Cubicle-to-Cubicle Res" 501000067578, "Hi Stab Resist: Bus 15 Cub 7 Hi Side" 501000067646, "Relay Testing Failure - Sol. Coil" Very Low Safety Significance Issue Resolution Process: Closure of Unresolved Item 05000282/2018011-02 and 05000306/2018011-02 - Potential Failure to Protect Class 1 Structures, Systems and Components from Tornado Generated Missiles 71111.21M This issue is a current licensing basis question and inspection effort is being discontinued in accordance with the Very Low Safety Significance Issue Resolution (VLSSIR) process. No further evaluation is required.
Description:
Prairie Island Nuclear Generating Plant Design Basis Assurance Inspection Report 05000282/2018011 and 05000306/2018011 identified an unresolved item regarding the potential failure to protect class I structures, systems and components from tornado generated missiles as described in chapters 1 and 12 of the Updated Safety Analysis Report.
Specifically, the team postulated the design basis tornado missile (either a 4x12x12 plank traveling end on at 300 miles per hour or a 4,000 pound automobile flying through the air at 50 miles per hour and not more than 25 feet above ground level) could impact one of the following combinations of equipment rendering the equipment non-functional during a tornado:
-
the D1 and D2 EDG engine exhaust piping
-
the D1 and D2 EDGs fuel oil day tank vent piping
-
the D1 and D2 EDGs fuel oil storage tank vent piping
-
the 12 and 22 DDCLP fuel oil day tank vent piping
-
the 12 and 22 DDCLP fuel oil storage tank vent piping
-
the 12 and 22 DDCLP engine exhaust piping
-
the 12 and 22 DDCLP room ventilation intake and exhaust equipment Licensing Basis: The licensees position is that the site has always met the licensing basis based on the following:
-
a tornado event is not concurrent with any other event or accident
-
no single failure is taken during a tornado event
-
only one tornado missile is required to be assumed per tornado event
-
tornado missile protection is provided via separation and redundancy
-
susceptible vents and exhausts are stacks (Class III components) and do not require tornado missile protection The inspectors, using the resource estimate in the applicable inspection procedure as a guideline and involvement with NRC headquarters support, have not been able to conclude whether adequate tornado missile protection is provided via separation and redundancy. In addition, the inspectors have not been able to determine whether the vents and exhausts listed above are class I (require protection) or class III (do not require protection)components.
Significance: Initiating events, hypothetical situations, and other failures, including multiple equipment failures are treated probabilistically in the probabilistic risk assessment itself. If an SSC is the subject of a performance deficiency and is degraded only under a very specific set of hypothetical circumstances, then it is likely to be of very low safety significance. To the VLSSIR process, a February 28, 2019, letter from Ho Nieh, Office of Nuclear Reactor Regulation Director, to the Nuclear Energy Institute (ADAMS Accession Number ML18338A085), also indicated that based upon information gathered during post-compliance inspections at each plant, and considering the additional defense-in-depth benefits of mitigating strategies implemented at each U.S. nuclear plant as part of NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, the NRC has confidence the safety significance of tornado missiles is very low. Based upon the significance evaluation discussed above and the information provided in the February 28, 2019, letter, the NRC does not plan to expend additional resources to determine whether the components listed above are adequately protected from a tornado missile via separation and redundancy, nor does the NRC plan to determine whether the vents and exhausts listed above are class I or class III components. Unresolved Item 05000282/2018011-02 and 05000306/2018011-02 is closed.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On January 13, 2023, the inspectors presented the integrated inspection results to C. Domingos, Site Vice President, and other members of the licensee staff.
On October 11, 2022, the inspectors presented the licensed operator requalification program annual operating test inspection results to F. Collins, Operator License Program Manager, and other members of the licensee staff.
On October 27, 2022, the inspectors presented the radiation protection inspection results to H. Hanson, Plant Manager, and other members of the licensee staff.
On October 28, 2022, the inspectors presented the Unit 1 inservice inspection results to C. Turner, Director of Site Performance, and other members of the licensee staff.
On November 30, 2022, the inspectors presented the emergency action level and emergency plan changes inspection results to J. Bremer, Regulatory Assurance Manager, and other members of the licensee staff.
On December 1, 2022, the inspectors presented the radiation protection baseline inspection results to H. Hanson, Plant Manager, and other members of the licensee staff.
On December 15, 2022, the inspectors presented the closure of unresolved item 05000282/2018011-02 and 05000306/2018011-02 inspection results to J. Bremer, Regulatory Assurance Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
C1.1.20.5-1
Unit 1 4.16kV System Switches and Indication Checklist
C1.1.20.5-1
Unit 1 4.16 kV System Switches and Indication Checklist
C16-1
Spent Fuel Pool Cooling
Procedures
C28-17
Turbine Driven Auxiliary Feedwater Pump
Procedures
SP 1424
Unit 1 Five (5) Year Containment Fan Coil Unit Performance
Test
SP 1424 CTMT Fan Coil Unit Perf Test
10/24/2022
Work Orders
SP 1424 CTMT Fan Coil Unit Perf Test
09/29/2022
501000044650
ISI Indications On 11 RCP Support
09/25/2020
501000059447
Relief Request Rx Vessel Fluence Error
01/04/2022
501000067456
1R33 ISI Indication 11 CC HX Support
10/17/2022
501000067641
RV Closure Head 157-051 Inspection 1R33
10/22/2022
501000067694
Late Response to NRC Questions
10/24/2022
Corrective Action
Documents
610000000561
OEER: NRC RIS 2018-06 PWR UH Visual Exam
2/11/2018
PI-1R33-MT-001
Steam Generator Feedwater Nozzle to Shell Weld
Component N-1
10/22/2022
PI-1R33-UT-002
Pipe to Pipe Weld Component W-5
10/22/2022
PI-1R33-UT-003
Elbow to Pipe Weld Component W-4
10/22/2022
PI-1R33-VT-020
Reactor Vessel Closure Head Bare Metal Visual Examination
10/25/2022
NDE Reports
PI*1R33*VT*008
10/20/2022
FP-PE-NDE-300
Dry Magnetic Particle Examination - Yoke/Coil
FP-PE-NDE-402
Ultrasonic Examination of Austenitic Pipe Welds -
Supplement 2
FP-PE-NDE-530
Visual Examination, VT-3
H-2
Boric Acid Corrosion Control Program
Procedures
SWI NDE-VT-6.0
Visual Examination for Leakage on Reactor Vessel
Work Orders
0340
Cl Hdr Pipe Replace on 24-CL -13 & -16
2/09/2021
Miscellaneous
22 LOR NRC
Annual Op Test
Prairie Island 2022 Licensed Operator Requalification Exam
Summary Which Provides the Exam Results for the Annual
10/01/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Summary
Operating Tests and a Make-up Biennial Written Examination
Administered from 04/25/2022 - 06/06/2022
Calculations
ENG-ME-185
Unit 1 - 4160V Switchgear Rm Ventilation Sys Design
501000067574
Over-Limit High Cubicle-to-Cubicle Res.
10/22/2022
501000067578
Hi Stab Resist: Bus 15 Cub 7 Hi Side
10/22/2022
Corrective Action
Documents
501000067646
Relay Testing Failure - Sol. Coil
10/23/2022
Develop Construction Standard for Bolting 4kV and 480V Bus
Bar Connections
000
Develop Construction Standard for Bolting 4kV and 480V Bus
Bar Connections
EC-0441 EC Closeout Package Report (Rev. 4)
Engineering
Changes
ENG-E-185
EC 25112, Cable Reroute Heat Load Affects
0C
Engineering
Evaluations
608000000492
PE 0009 Bus Contact Resistance Acceptance Criteria Update
10/15/2019
ANSI/NETA ATS-
2009
Standard for Acceptance Testing Specifications for Electrical
Power Equipment and Systems
ASME NQA-1-
1994 Edition
Quality Assurance Requirements for Nuclear Facility
Applications
07/29/1994
EM 4.3.1-B.3
Bolting Standard for Electrical Bus Connections
EM 4.3.1-T.1
Termination
NSPM-1
Quality Assurance Topical Report
NSPM-1
Quality Assurance Topical Report
QF0739, Request
Number 240
EPRI TR 104213, Section 7 Has Temperature Limitations
Associated With the Torque Tables Contained With This
Section.
11/16/2022
Miscellaneous
QF0739, Request
Number 268
EC 608000000896, Was the Engineering Recommendation
for Additional Work Completed and What Work Was Done and
What Were the Results?
11/02/2022
FP-NO-QC-02
Inspection Planning
FSG-25
Isolation and Repower Bus 25 During ELAP
H65
License Renewal Implementation and Aging Management
Programs
H65.2.6
Bolting Integrity Aging Management Program
Procedures
H65.2.6
Bolting Integrity Aging Management Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MSIP 3026
Bolting Standard for Electrical Bus Connections
MSIP 3026
Bolting Standard for Electrical Bus Connections
PE 0009
4kV Switchgear Preventive Maintenance
PE 0009
4kV Switchgear Preventive Maintenance
PE 0009
4kV Switchgear Preventative Maintenance
PE-B15-2BUS 15 Inspection/Doble
09/01/2022
PE-B15-2BUS 15 INSPECTION/DOBLE
10/27/2022
Work Orders
PE-B15-2BUS 15 INSPECTION/DOBLE
10/27/2022
Procedures
B20.8
Instrument AC Distribution System
501000054247
PE 0009 Acceptance Criteria Change/Update
07/21/2021
501000067737
DDCLP Speed Switch 7030037
10/25/2022
Corrective Action
Documents
501000068630
PE 0009 in Need of Update
11/17/2022
608000000492
PE 0009 Bus Contact Resistance Acceptance Criteria Update
10/15/2019
608000000614
Evaluate Contact Resistance for Bus 16
608000000896
Bus 15 Contact Resistance Evaluation
608000000896
Bus 15 Contact Resistance Evaluation
608000000896
Bus 15 Contact Resistance Evaluation
10/24/2022
Engineering
Evaluations
608000000896,
Rev. 2
Bus 15 Contact Resistance Evaluation
11/03/2022
LER 05000282;
01-05-00
Fault and Fire in Non-Safeguards Circuit Breaker Results in
10/02/2001
QF0739, Request
Number 241
In EC Eval 896, Why Do We Not Consider All the Heat Load
Above the Design Bases?
11/16/2022
QF0739, Request
Number 242
The Engineering Evaluation 608000000896 Says the Current
Heat Load is Acceptable, However the Maintenance is
Performed Every 4 years. Based on the Upward Trend, is That
Acceptable?
11/16/2022
QF0739, Request
Number 264
EC 608000000896, PE 0009 Acceptance Criteria for Each
Phase Is Determined by 50% Deviation From a Three Data
Set Rolling Average From Previous Readings.
11/02/2022
Miscellaneous
QF0739, Request
Number 265
EC 608000000896 Did Not Evaluate the High Stab Resistance
as Identified in QI 501000067578, for the Potential Impact for
Fire Based on the High Resistance as Left Value Being Higher
than the As Found
11/02/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
QF0739, Request
Number 266
EC 608000000896 Attachment 6 is the decision tree to work
through to Address Potential High Resistance
11/02/2022
QF0739, Request
Number 267
EC 608000000896; The Increase Documented in the
Engineering Evaluation is Greater Than the Margin in
ENG-ME-185, Why is a Calculation Update Not Required?
11/02/2022
B35
Cooling Water System
C18.1
Engineered Safeguards Equipment Support Systems
FSG-20
Cooling Water Management Following a Loss of AC Power
PE 0009
4kV Switchgear Preventive Maintenance
PM 3002-2-12
DDCLP Diesel Minor Periodic Maintenance
Thermographic Inspection of Prairie Island Components
Procedures
SP 1106A
Diesel Cooling Water Pump Monthly Test
103
LP P9112L-0902
EDMG/SAMG Review
P7480L-001
SAMG Overview
PI-BEP-CNT-
005F
SAMG Overview
Miscellaneous
PINGP 1237
SAMG Evaluation Team Leader Checklist
1DPG
Diagnostic Process Guideline
Main Control Room Severe Accident Guideline Initial
Response
Main Control Room Severe Accident Guideline TSC
Recommending Strategies
Inject Into the Steam Generators
Depressurize the RCS
Inject Into the RCS
Inject Into Containment
Reduce Containment Hydrogen
Control Containment Pressure
Mitigate Fission Product Releases
Instrumentation
Site Capabilities
2DPG
Diagnostic Process Guideline
Procedures
Main Control Room Severe Accident Guideline Initial
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Response
Main Control Room Severe Accident Guideline TSC
Recommending Strategies
Inject Into the Steam Generators
Depressurize the RCS
Inject Into the RCS
Inject Into Containment
Reduce Containment Hydrogen
Control Containment Pressure
Mitigate Fission Product Releases
Instrumentation
Site Capabilities
CD 10.2
Severe Accident Management Guidelines (SAMGs) Program
SAG-10
Control Spent Fuel Pool Level
Ultimate Decision Maker
Benefit Consequence
Computational Aids
Drawings
XH-112-1
Main Steam Isolation Valve and Check Valve
2C20.7
D5/D6 Diesel Generators
D72
Check Valve Disassembly and Inspection Procedures
D72 ATT R
Schutte and Koerting Check Valves
MSIP 6004
Rigging from Grating
SP 1070
Reactor Coolant System Integrity Test
SP 1072
Local Leakage Rate Test of Containment Penetrations
SP 1072.41A
Local Leakage Rate Test of Penetration 41A No. 11 Vacuum
Breaker
SP 1072.41B
Local Leakage Rate Test of Penetration 41B No. 12 Vacuum
Breaker
SP 1373
RS-19-1 Unit 1 Loop A MSIV Non-Return Check Valve IST
Test
Procedures
SP 2295
D5 Diesel Generator 6 Month Fast Start Test
SP 1072.41A - LLRT 11 Vacuum Breaker
10/04/2022
Work Orders
SP 1072.41B - LLRT 12 Vacuum Breaker
10/04/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10/04/2022
U1 Westnghse NIS Pwr Range BTI Panels
06/06/2022
U1 Westnghse NIS Pwr Range BTI Panels
06/07/2022
U1 Westnghse NIS Pwr Range BTI Panels
06/07/2022
U1 Westnghse NIS Pwr Range BTI Panels
06/07/2022
Replace D5 Low Voltage/Low Current RLYS
08/23/2022
RS-19-1 Disassembly and Inspection
10/31/2022
501000067235
1N32 CPS Did Not Come on Scale
10/14/2022
501000067253
CV-31095 Leaks By
10/14/2022
501000067257
FM in Containment
10/14/2022
501000067261
1N32 Did Not Come on Scale With 1N31
10/14/2022
501000067270
Oil Leak On 11 Turb Oil Cooler End Bell
10/14/2022
501000067271
Unit 1 Turbine Stop Valve SV-1 Leaks By
10/15/2022
501000067288
DEHC Micronet Modules Contain Capacitors
10/17/2022
501000067290
Both A and B Door Can Open at Same Time
10/15/2022
501000067296
Fault on Relay Room Incipient Detector
10/15/2022
501000067310
CV-31255 Timed Out of Limiting Stroke
10/15/2022
501000067311
SP 1168.3, RHR Pit Pressure Test Missed
10/16/2022
501000067312
Valve Stem in Containment Leak Level 696'
10/16/2022
501000067327
CV-31423 Partially Open
10/17/2022
501000067328
Rifle Round Found in Sec. Search Train
10/17/2022
501000067342
SP 1083A Table 20 Data
10/16/2022
501000067345
Security Radio and Communication Checks
10/17/2022
501000067346
Temp Designated Hot Work Area
10/17/2022
501000067352
SP 1083A Expected Lights not Received
10/16/2022
501000067357
AMP Requirements for Diving Activities
10/17/2022
501000067360
Containment Spray Pump Run Time
10/17/2022
501000067368
Boric Acid Around Reactor Vessel Studs
10/17/2022
Corrective Action
Documents
501000067539
1R33 ISI Indication SP 1392 Bolted Conn
10/21/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000067562
Place 5 to 4 Mode Hold for Sump C Repair
10/20/2022
501000067572
CST Tmod Cold Weather Effectiveness
10/21/2022
501000067580
MV-32072: Packing Leak Identified
10/21/2022
501000067589
Bus 112 Undervoltage Relay Failed
10/21/2022
501000067591
Anonymous CAP-Anonymous Condition Report
10/21/2022
501000067597
Unable to Verify Closed
10/23/2022
501000067598
Valve Testing Open Outside Ref Range
10/23/2022
501000067600
Damaged Thrusts Bearing on 11 CC PMP
10/21/2022
501000067616
Traveling Screen Broken Sheer Pin
10/21/2022
501000067629
APP J: CV-31929 Leak Rate Exceeded Admin
10/23/2022
501000067635
Indications of T/C Inst. Ports
10/22/2022
501000067652
PENC 17 Potential Rock UP With BA
10/23/2022
501000067658
Solenoid Failed Open
10/25/2022
501000067665
RCP Motor Oil Drain Not Identified
10/23/2022
501000067698
Cont Plan/Prot Equip Misalignment
10/24/2022
501000067746
CV-31637 Stroked Outside of Band
10/25/2022
501000067750
MV-32165 Running Load High
10/25/2022
501000067814
CV-31369 High Friction
10/27/2022
501000067817
As Found Readings Below Range Cycle
10/27/2022
501000067824
Minor Leakage from Dome of CV-31224
10/27/2022
501000067829
I/P Trending QIM
10/28/2022
501000067843
RCP Terminal Bar Issue
10/28/2022
501000067848
1R33 ISI Indication SP 1168.3 RHR Pits
10/28/2022
501000067862
VC-2-1, 11 VCT OUT CHECK VLV Leak By
10/27/2022
501000067863
U1 Incipient Detector 2 LED Fault
10/28/2022
501000067868
Possible Charging Pmp Suct Overpressure
10/28/2022
501000067879
CV-31622 Is Leaking
10/28/2022
501000067885
I/P Would Not Calibrate to Tolerance
10/29/2022
501000068034
Inverter, North Fan Not Running
11/01/2022
501000068061
MV-32016 Low Packing Load
11/02/2022
501000068071
Contractor RP Staffing
11/02/2022
501000068118
1R33 LLRT Nitrogen Blanket Bleed Off
11/03/2022
501000068128
Unterminated Cable
11/05/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000068141
Uncontrolled Badges in the PA
11/03/2022
501000068151
MV-32027 Running Load High
11/03/2022
501000068188
Mode 4 Dose Equivalent Xenon-133
11/06/2022
501000068189
1R33 ISI Indication SP 1168.1 RCS Press
11/06/2022
501000068195
Air Leak From Tubing for CV-31637
11/06/2022
501000068197
CV-39426
11/06/2022
501000068237
MD AFW PMP Inner Seal Pck Leakage >60
11/07/2022
501000068237
MD AFW PMP Inner Seal Pck Leakage >60
11/07/2022
501000068238
Suspected Leakby On CV-31998
11/07/2022
501000068244
Existing 86B/105 Relay Did Not Function
11/06/2022
501000068261
Flammable Storage Locker Does Not Latch
11/06/2022
501000068357
Unable to Close or Reposition 2HS-21-15
11/10/2022
501000068358
New B Kernel Power Supply Failed
11/10/2022
501000068361
Flux Trace Deviation Outside Guidance
11/10/2022
501000068361
Flux Trace Deviation Outside Guidance
11/10/2022
501000068375
11/10/2022
501000068376
11/10/2022
501000068377
TP 1626 90% Rectifiers Op Not Met
11/10/2022
501000068381
GAMP: Acceptable Voids in RHR Suction
11/09/2022
501000068391
11/10/2022
501000068393
ASME Post Work Review for WO 700108241
11/10/2022
501000068405
Failed 1N-44 Bistable
11/10/2022
501000068413
Camera 45 Fail
11/11/2022
501000068415
U1 Incore Drive A & C Erratic Behavior
11/11/2022
501000068446
D5 Rack Diff >1.5mm (.258V) When Stopped
11/14/2022
501000068461
Xcel Energy TD Oversight
11/13/2022
501000068500
NRC Red Phone in CR not Working
11/15/2022
Corrective Action
Documents
Resulting from
Inspection
501000068093
Sr. Resident Questions about EC Eval
11/02/2022
Miscellaneous
ASME NQA-1-
22
SUBPART 2.18 Quality Assurance Requirements for
Maintenance of Nuclear Facilities
1994
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CS Resource
NRC
1R33 Unit 1 Refueling Outage (TRN A)
10/11/2022
Schedule Critical
Path
1R33 Unit 1 Refueling Outage (TRN A)
10/11/2022
D30
Post Refueling Startup Testing
D58.1.9
Unit 1 Reactor Vessel Head Removal
H10.1
ASME Inservice Testing Program
SP 1136.2
Volumetric Leakage Rate Test of Containment Maintenance
Airlock
SP 1168.1
Unit 1 Reactor Coolant System Pressure Test
SP 1177
Core Inventory Verification
Procedures
SP 1750
Post Outage Containment Close-Out Inspection
SP 1177 - RFL Core Inventory Verif
10/27/2022
U1 Westnghse NIS Pwr Range BTI Panels
06/06/2022
U1 Westnghse NIS Pwr Range BTI Panels
06/07/2022
U1 Westnghse NIS Pwr Range BTI Panels
06/07/2022
Work Orders
U1 Westnghse NIS Pwr Range BTI Panels
06/07/2022
Corrective Action
Documents
501000012997
2018 DBAI: FOST Vent Line Classification
06/06/2018
NF-38550
Architectural Screen House Plan Elevation 695'-0" and
Elevations
NF-39232
Flow Diagram Fuel and Diesel System Unit 1 and 2
Drawings
NF-39601
HVAC Flow Diagram Turbine Building-Diesel Generator Unit 1
and 2
APC 18-04
NEI Position on Tornado-Generated Missile Analysis
Considerations for Single Missile and Single Failure Criterion
2/16/2018
Miscellaneous
White Paper
Response to NRC Question on Fuel Oil Storage Tank Vents
unknown
SP 1070
Reactor Coolant System Integrity Test
Procedures
SP 1092A
SI Check Valve Test (Head Off) Part A: High Head SI Flow
Path Verification
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SP 1092B
Safety Injection Check Valve Test (Head Off) Part B: RWST to
RHR Flow Path Verification
SP 1111A
Train A Main Steam Power Operated Relief Valve Test
09/06/2022
SP 2155B
CC System Quarterly Test Train B
SP 1168.1 - U1 RX Coolant Sys Press Test
11/06/2022
SP 1111A TRN A POWER OPER RLF VLV TEST
09/17/2022
Work Orders
09/28/2022
FT-2021-756
FP-S-FSIP-07 Revision
10/27/2021
PI-2021-753
F3-17 Revision
11/20/2021
PI-2021-754
EDCM 300 Revision
08/30/2021
PI-2021-757
F3-13.3
11/08/2021
PI-2021-758
F3-23-1C and F3-23-2C Revisions
11/10/2021
Miscellaneous
PI-2022-764
PING 580 Revision
01/27/2022
EDCM 300
Liquid Release to River Dose Calculation
EPlan
EPlan
F3-13.3
Manual Dose Calculations
F3-17
Core Damage Assessment
Procedures
F8-3
Activation and Operation of the Emergency Operations Facility
Miscellaneous
Prairie Island Plant Alpha Characterization Study
07/26/2022
FP-RP-AM-01
Alpha Monitoring Program
FP-RP-NISP-02
Radiation and Contamination Surveys
FP-RP-NISP-05
Access Controls for High Radiation Areas
PING 1560
Posting Changes for Fuel Handling
Procedures
PINGP 1236
Reactor Coolant System and Draindown Radiation Protection
Requirements
Air Sample Report
10/22/2022
PI-M-20221015-
Regen Room Initial Entry
10/15/2022
PI-M-20221015-
Regen Room Post Shielding
10/16/2022
PI-M-20221018-5
Regen Room Insulation Removal
10/16/2022
Radiation Surveys
PI-M-20221019-
Chemical Volume Control System Passageway Down Posting
10/19/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PI-M-20221019-
Down Posting Internals Lift Rig Area
10/19/2022
PI-M-20221022-
Reactor Head O-Ring Removal
10/22/2022
PI-M-20221022-
- 12 Steam Generator Secondary Side
10/22/2022
RWP 221007
1R33 Regenerative Heat Exchanger Room Work
RWP 221020
1R33 Reactor Coolant Pump Work
Radiation Work
Permits (RWPs)
RWP 221042
1R33 - Reactor Head Disassembly/Reassembly Work
Thermo Scientific SAM-12 Small Article Monitor, Serial
Number 537597
09/02/2021
Rados Personnel Contamination Monitor, Serial Number
479900
05/25/2020
JL Shepherd Model 89 Gamma Irradiator Calibration
2/07/2021
Daily and Weekly Portal Monitor Checks
11/20/2022
MGP DMC 3000 Electronic Dosimeter, Serial Number 100511
09/08/2022
MGP IRD 2000 Gamma Calibrator
08/24/2021
Ludlum Model 2241-4/42-31H Serial Numbers
279858/PR296854
01/18/2022
Eberline AMS-4 Air Sampler Serial Number 1289
08/03/2022
Chemistry Gamma Spectroscopy System #13
09/30/2022 -
10/04/2022
Mirion/Canberra Whole Body Counter Calibration
08/10/2022
2-0067-03673
Hopewell Designs Gamma Irradiator Calibration
07/26/2022
1R19 Liquid Calibration
08/25/2010
Area Radiation Monitor Calibrations
04/03/2020
Control Room Ventilation System Train A
07/22/2021
1R-22 Shield Building Radiation Monitor
10/05/2022
1/2 R-48 Containment High Range Monitor Electronic
Calibration
05/17/2022
Calibration
Records
SP 1027.4 High Range Radiation Monitor
08/17/2022
Corrective Action
501000050540
Aging Rados RCA Exit Monitors
04/15/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000058741
2R-48 Containment Hi Range Area Radiation Meter B
2/01/2021
501000061995
M-177 Frisker Failed Function Check
04/06/2022
501000062414
Weld Break on JL Shepherd
04/19/2022
Documents
501000062547
As Found Calibration Failure
04/26/2022
Radiochemistry Cross Check Performance Data Fourth
Quarter 2020 through Third Quarter 2022
Various
NSPM RP Instrument Response Investigation Report for
Instrument Model 2241-4, Serial Number 600072
06/25/2022
Miscellaneous
National Source Tracking System Annual Inventory
Reconciliation Report
01/05/2022
Procedures
FP-RP-EDC-01
DMC 2000S/DMC3000SOR Electronic Dosimeter and IRD
2000 Calibration
Corrective Action
Documents
501000069038
MSPI Coefficients Not Revised Timely
2/08/2022
MSPI Indicator
Margin Remaining
in Green
Prairie Island Unit 1, System ROP-MSPI-CWS MSPI Cooling
Water System, P/E March 2022
March 2022
MSPI Indicator
Margin Remaining
in Green
Prairie Island Unit 1, System ROP-MSPI-CWS MSPI Cooling
Water System, P/E June 2022
June 2022
MSPI Indicator
Margin Remaining
in Green
Prairie Island Unit 2, System ROP-MSPI-CWS MSPI Cooling
Water System, P/E December 2021
December
21
MSPI Indicator
Margin Remaining
in Green
Prairie Island Unit 2, System ROP-MSPI-CWS MSPI Cooling
Water System, P/E March 2022
March 2022
MSPI Indicator
Margin Remaining
in Green
Prairie Island, Unit 2, System ROP-MSPI-CWS MSPI Cooling
Water System, P/E June 2022
June 2022
71151
Miscellaneous
QF0739, Request
Number 244
For the Performance Indicator MSPI 10 (Cooling Water), Why
Is There a Difference Between the NRC Website Numbers
and the INPO Reports?
2/07/2022
501000051933
DBAI - OM 2017-06 Not Fully Evaluated
05/12/2021
71152A
Corrective Action
Documents
2000013088
QF2900, Fire Protection Program Impact Screen, IN 2017-06
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR
610000000170
OEER-NRC IN 2017-06 BATTERY & BATTERY CH
05/08/2019
OEE AR
501000051933
DBAI - IN 2017-06 Not Fully Evaluated
08/13/2021
OEE AR
501000051933
Revise IN 2017-06 Response
2/25/2022
Corrective Action
Documents
Resulting from
Inspection
501000062449
NRC Question on Updates to PRA for OE
04/21/2022
Change Number:
PI-22-0014 (FP)
IN 2017-06 Battery Charger Fault Current Could Trip DC
Output Breaker
2/22/2022
Miscellaneous
QF0739
Provide Response to the Item of Interest Regarding
Information Notice 2017-06 as It Pertains to Coordination
Between the Battery Charger Output Breaker and
Downstream Fusing.
05/26/2021