IR 05000282/2022001
| ML22123A140 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/03/2022 |
| From: | Hironori Peterson Region 3 Branch 3 |
| To: | Domingos C Northern States Power Company, Minnesota |
| References | |
| IR 2022001 | |
| Download: ML22123A140 (17) | |
Text
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000282/2022001, 05000306/2022001, AND 07200010/2020001
Dear Mr. Domingos:
On March 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant. On April 15, 2022, 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, Branch 3 Division of Reactor Projects Docket Nos. 05000282, 05000306, and 07200010 License Nos. DPR-42, DPR-60, and SNM-2506
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000282, 05000306, and 07200010
License Numbers:
Report Numbers:
05000282/2022001, 05000306/2022001, and 07200010/2020001
Enterprise Identifier:
I-2022-001-0068 and I-2021-001-0164
Licensee:
Northern States Power Company
Facility:
Prairie Island Nuclear Generating Plant
Location:
Welch, Minnesota
Inspection Dates:
January 01, 2022, to March 31, 2022
Inspectors:
K. Pusateri, Resident Inspector
D. Tesar, Senior Resident Inspector
Approved By:
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 began the inspection period at rated thermal power. On March 21, 2022, the unit was down powered to 7 percent for Turbine Control Valve Testing and repairs to the turbine control system. The unit was returned to rated thermal power on March 22, 2022, and remained at or near rated thermal power for the remainder of the inspection period. Unit 2 operated at or near rated thermal power for the entire 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 activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, 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) Walkdowns of Exterior Temp Structures, D6 Fuel Oil Vault, CST Warming for Cold Weather on February 1, 2022
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)21 Motor-Driven Auxiliary Feedwater Pump Post-Surveillance Walkdown on January 6, 2022 (2)21 Battery During D6 Risk Informed Completion Time (RICT) on February 3, 2022 (3)21 and 22 Auxiliary Feedwater Pump Walkdown During D6 (RICT) on January 31, 2022 (4)11 Safety Injection Pump Walkdown on February 16, 2022
- (5) Cardox System Walkdown Following Out-of-Service Period on March 4, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) D1 (A Train) and D2 (B Train) Emergency Diesel Generators (Following Maintenance Window) on February 24, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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) Zone 2, Auxiliary Feedwater Pump Rooms, El. 695' on January 6, 2022
- (2) Zone 12, Relay and Cable Spreading Room, El. 715' on January 12, 2022
- (3) Zone 14, Old P250 Room, El. 715' on January 18, 2022
- (4) Zone 17, Access Control, El. 715' on February 24, 2022
- (5) Zone 3, 11, and 12 Feedwater Pumps, El 695' on March 10, 2022
- (6) Zone 1, Battery Rooms 11 and 12, El 695' on March 9, 2022
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) Turbine Building Unit 1, El. 695' on March 14, 2022
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) Internal Flooding Sample Units 1 and 2 on March 14, 2022
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 Downpower for Turbine Valve Test and 'C' Kernel Replacement on March 23, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated Licensed Operator Requalification Training (LORT) As-Found Simulator Scenario (DEP) on March 15, 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) D6 Unavailability on February 10, 2022
- (2) Unit 1 Turbine Stop Valve Testing on March 22, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (7 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) Contingency Risk Informed Completion Time (RICT) for D6 Work Window Review of Availability Form 4's on January 30, 2022
- (2) Phoenix Update for Pressurizer Heater "C" Bank Unavailability on February 22, 2022
- (3) WW 2203 D6 Emergency Diesel Generator Maintenance Window on January 18, 2022 (4)22 Reactor Coolant Pump (RCP) Lower Bearing Oil Level Decrease on January 14, 2022 (5)
"B" Cooling Water Return Header Work and RICT Implementation on February 24, 2022
- (6) D1 Emergency Diesel Generator Work Window on March 7, 2022 (7)22 Diesel Driven Cooling Water (DDCL) Pump Work Window on March 21, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Reactor Coolant Pump Casing ASME Code Compliance on January 14, 2022
- (2) Door 56 From U2 Side Relay Room to Turbine Building Out-of-Service on February 9, 2022
- (3) Fire Protection Change Evaluation 22-002 on March 7, 2022 (4)22 Condensate Pump Offline Predictive Motor Analysis (PDMA) Testing on February 11, 2022
- (5) Residual Heat Removal (RHR) System Voids on January 3, 2022 (6)22 DDCL Pump ASME OM Code Non-Compliance on March 29, 2022
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) EC 601000001587 Bypass Computer Room UPS Trip and Halon Automatic Initiation on February 24, 2022
- (2) EC 601000003309 Unit 2 Diesel Fuel Oil Storage Tank (FOST) Piping MOD Wax Tape Code Compliance on January 6, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) WO 700102208-0600 Bypass D6 Magnetic Pickup Unit (MPU) per ECR 601000003587 on February 11, 2022 (2)
"B" Cooling Water Header Return to Service (RTS) Post-Maintenance Testing on February 24, 2022 (3)122 Control Room Cleanup Fan on March 1, 2022
- (4) SP 1194 CARDOX (Carbon Dioxide) 18-month System Test as Post-Maintenance Testing on March 4, 2022
- (5) WO 700102961-0010 Replace Actuator 1/D6 on February 11, 2022 (6)22 Diesel Driven Cooling Water (DDCL) Pump Post-Maintenance Testing Following Work Window on March 28, 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) (5 Samples)
- (1) SP 2095 Bus 26 Load Sequencer on February 1, 2022
- (4) SP 2856 Bus 26 Undervoltage Relay Test on February 3, 2022
- (5) SP 1054 Turbine Control Valve Testing on March 28, 2022
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) SP 2101 21 Motor-Driven Auxiliary Feedwater Pump Quarterly Flow and Valve Test on January 6, 2022
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) Emergency Preparedness INPO Evaluated Exercise on March 15,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (January 1, 2021, through December 31, 2021) on January 26, 2022
- (2) Unit 2 (January 1, 2021, through December 31, 2021) on January 26, 2022 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (January 1, 2021, through December 31, 2021) on January 26, 2022
- (2) Unit 2 (January 1, 2021, through December 31, 2021) on January 26, 2022
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (January 1, 2021, through December 31, 2021) on January 26, 2022
- (2) Unit 2 (January 1, 2021, through December 31, 2021) on January 26, 2022
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Annual Follow-up of the Solenoid Valve Failure for the D2 Emergency Diesel Generator.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) Trend Evaluation for the Quality of Information Provided to NRC on March 16, 2022 71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01) (2 Partials)
(1)
(Partial)10 CFR 50.9 URI Follow-Up on January 10, 2022 (2)
(Partial)
Follow-Up Violation of T.S. 5.6.6 on January 19,
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60853 - On-Site Fabrication of Components and Construction on an ISFSI The inspectors evaluated the licensees Independent Spent Fuel Storage Installation (ISFSI)pad expansion activities from February 2021 to January 18, 2022. The expansion and pad design were previously approved by the NRC through a license amendment (ML20237F365). Throughout construction, the inspectors evaluated the following:
Preparation of the subsurface, formwork, and type and condition of reinforcing steel.
The materials used were consistent with the design and procurement specifications.
Aggregates were tested for potential reactivity.
Design changes, modifications, and non-conformance reports.
Qualifications of individuals performing Quality Assurance (QA) functions including non-destructive evaluations.
QA oversight; and
American Concrete Institute (ACI) and American Society for Testing and Materials (ASTM) concrete sample test results, including verifying compressive strength tests met design specifications.
The inspectors were onsite on September 15-16, 2021, and observed the following during construction:
Placement of reinforcing steel was consistent with design requirements.
Concrete placement was consistent with ACI standards.
Concrete testing was consistent with ASTM and ACI standards.
Overall pad dimensions were consistent with the design documents.
INSPECTION RESULTS
Observation: Follow up of D2 Emergency Diesel Generator Solenoid Valve Failure 71152A The Safety-Related (SR), D2 Emergency Diesel Generator (EDG) B air start solenoid valve (SV) failed to change state on August 16, 2021, and was documented in CAP 501000055123, with an action to evaluate the condition and perform an Extent of Condition (EOC) review.
The failed SV was replaced, restoring the system to normal operation on August 19, 2021.
Based upon Operating Experience (OE) data for recent failures of this type of (SV), a CAP action was created for an Engineering Change (EC) to acquire a different SV for installation in 2023. The inspectors also reviewed the procedures and documents from a Part 21 perspective and did not identify any issues with the forensics report which determined that no Part 21 report was required. During the review, inspectors identified that CAP action 500000314662 for the EOC review had been marked as complete, yet it did not include appropriate documentation for action closure. The licensee-initiated CAP 501000062261 to document inadequate closure of the action and to reopen the action for proper completion.
CAP 501000055123 remains open awaiting closure following the EC action completion. The inspectors determined that the actions being taken and/or planned were reasonable and commensurate with the safety significance of the issue. The inspectors did not identify any findings or violations of more than minor significance.
Observation: Semiannual Trend Review of Quality of Documents Provided to the NRC 71152S On September 8, 2021, the inspectors performed a semi-annual trend review regarding a potential adverse trend in the quality of documents being provided to the NRC. These documents were used by the NRC, in part, to evaluate conditions and to determine if, and how much additional inspection is required in specific areas. Inspectors reviewed Corrective Action Program (CAP) items generated in the last year documenting deficiencies with the technical rigor being applied for documents prior to submittal. Some examples of these deficiencies included:
CAP 501000060402 Update NRC response, dated 2/7/2022 Quality Issue Management (QIM) 501000058054 documented that based off H10.1 and H10.1.B the site did not use or implement the SI [Safety Injection] accumulator discharge check valves Check Valve Condition Monitoring (CVCM) plans. The CAP implied that the standard ISTC code requirements were being applied. This information was provided to the NRC on November 5, 2021, via QF0739. However, this information was not fully accurate as CVCM Plans were prepared and signed for the Residual Heat Removal (RHR) cold leg Safety Injection (SI) accumulator discharge check valves to allow for partial flow testing, during the summer of 2019. This was then used as justification to update the surveillance procedures to implement the partial flow testing.
CAP 501000056770 Incorrect information provided to NRC, dated 10/05/2021 This CAP identified that the In-Service Inspection (ISI) Engineer provided information as part of the response to a Request for Information (RFI) for the 2R32 ISI Inspection. However, the information was not fully accurate, in that the response to question B8 SP 2408 was listed as "Containment Power Quarterly Inspection. This was incorrect in two respects, 1) SP 2408 is Walkdown of the Shield Building Annulus and 2) SP 2554 was Containment at Power Quarterly Inspections but was changed to Containment Power Inspection on June 7, 2021.
CAP 501000057560 Rev 8 of PTLR submitted with error, dated 10/21/2021 On September 8, 2021, CAP 501000055874 PTLR 54 EFPY fluence not bounding was issued to document that the fluence values used for developing the Pressure Temperature Limits Report (PTLR) and the associated curves used to limit heat up and cool down, were higher than previously determined.
On October 5, 2021, CAP 501000056729 Fluence Analysis Unexpected High W2 Weld was issued to document an error in the current calculation used to determine fluence values and adjusted reference temperatures (ART). Specifically, the calculation used a wrong dimension for the W2 weld location resulting in fluence values higher than what was previously reported.
As a result, the PTLR heat up and cooldown curves and ARTs needed revision; this also impacted other items that relied on the ARTs and/or PTLR curves as inputs.
On October 8, 2021, Westinghouse provided a letter to Prairie Island Nuclear Generating Plant (PINGP) Impact Assessment for Prairie Island Units 1 and 2 - PTLR Non-Conservatism. This letter identified the calculational error discussed above and determined that the previously calculated fluence values and ARTs at end of life (54 EFPY)and the existing PTLR curves were non-conservative and required revision.
On October 12, 2021, PINGP submitted Revision 8 of the PTLR (previously approved on February 16, 2021) to restore compliance with Technical Specification 5.6.6.C. However, the report referenced the incorrect PTLR curves and apparently had not accounted for the calculational errors discussed in the previous CAPs.
The inspectors reviewed the PINGP Fleet Procedures FP-R-LIC-13, Communications with the NRC, and FP-R-LIC-02, Regulatory Correspondence, which discussed the licensee's requirements and commitments for ensuring that adequate technical rigor was applied prior to submitting information to the NRC. These documents require that reviewers, in part, confirm the following:
Is the information provided complete?
Is the information provided correct? Was the preparer of the response a subject matter expert?
Does the response answer the question being asked? Is the response on topic and clear?
Are inputs and assumptions appropriately validated?
If there is an embedded calculation, is it correct?
If the response contains a condition adverse to quality, was it documented in the CAP?
On January 18, 2022, the Corporate Functional Area Manager (CFAM) of Engineering identified an Area of Concern (AOC) with multiple instances where engineering personnel have provided incorrect information to external stakeholders. An action was developed to stress the What Your Signature Means with Engineering personnel. This action was completed at an Engineering All Hands Meeting in February of 2022, followed by action closure on February 18, 2022. The inspectors review concluded that for the first two examples above where incorrect information was provided to the NRC, the consequences of those were minimal and did not adversely affect the NRCs ability to perform its regulatory function. The third example above is being tracked in the Unresolved Item (URI) documented in Report 2021-004. The licensee implemented corrective actions to assure plant operations are within proper safety limits and have taken actions to correct and update the PTLR and its associated documents. The inspectors have no immediate concerns with the licensees corrective actions; however, based on the relatively short runtime of these actions, the inspectors could not make an assessment regarding their effectiveness for this trend review.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 15, 2022, the inspectors presented the integrated inspection results to Mr. C. Domingos, Site Vice President, and other members of the licensee staff.
THIRD PARTY REVIEWS Inspectors reviewed Institute on Nuclear Power Operations reports that were issued during the inspection period.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000051919
Concrete Mix Options Not Meet Design Req
05/13/2021
501000053098
Soil Densometer Equipment Deltas
06/11/2021
501000054279
ISFSI Subgrade Compaction Test
07/22/2021
501000054336
Concrete Delivery Rejected at Job Site
07/23/2021
501000054983
NOS: Contractor Uncalibrated M&TE
08/11/2021
501000055049
ISFSI Expansion - Plate Load Test Data
08/13/2021
501000055298
ISFSI Const Subgrade Density Test Missed
08/20/2021
501000059357
ISFSI Expansion - Concrete Pad Thickness
2/30/2021
Westinghouse IR-
21-10020
Near Miss During Concrete Pour at Prairie Island ISFSI
09/16/2021
Westinghouse IR-
21-10068
Water Cement Ratio Exceeded Requirement
09/17/2021
Westinghouse IR-
21-10905
Flatness Inspection of Safety Related Pad
10/06/2021
Westinghouse IR-
21-11816
Pad Flatness at Pullboxes Exceeds Specified Criteria
10/28/2021
Westinghouse IR-
21-12181
Re-Inspection of Flatness for ISFSI Pad
11/06/2021
Westinghouse IR-
21-13392
PINGP ISFSI Concrete Pad Thickness Variations
2/13/2021
Westinghouse IR-
21-6629
Soil Densometer Calibration Results Delta
06/11/2021
Corrective Action
Documents
Westinghouse IR-
21-8876
Braun Intertec Plate Load Test Data Loss
08/16/2021
501000056098
ISFSI Worker Stumbled on Rebar
09/16/2021
Corrective Action
Documents
Resulting from
Inspection
501000059767
ISFSI Exp. - Errors in Concrete Tickets
01/14/2022
Engineering
Changes
601000000444
ISFSI Expansion Project
Braun Intertec Co. Letter: Plate Load Test Results
08/17/2021
60853
Miscellaneous
S&L Review of Braun's "Plate Load Test Results - Braun
08/25/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Letter;"
FCR 001
PINGP ISFSI Pad Expansion - Excavation Work Plan
05/30/2021
FCR 002
PINGP ISFSI Pad Expansion - Excavation Work Plan
06/03/2021
FCR 003
PINGP ISFSI Pad Expansion - Excavation Work Plan
06/03/2021
FCR 005
PINGP ISFSI Pad Expansion - Excavation Work Plan
06/08/2021
FCR 006
PINGP ISFSI Pad Expansion - Excavation Work Plan
07/14/2021
FCR 019
PINGP ISFSI Pad Expansion - Pad Installation Work Plan
10/13/2021
FCR 020
Prairie Island ISFSI Pad Expansion - Pad Installation Work
Plan
10/13/2021
FCR 025
PINGP ISFSI Pad Expansion - Pad Installation Work Plan
11/06/2021
FCR 028
PINGP ISFSI Pad Expansion - Pad Installation Work Plan
11/09/2021
PO4500828442
Concrete Purchase Order
05/18/2021
ASTM D6951 Braun Intertec Quality Manual; MnDOT
Dynamic Cone Penetrometer Testing
Section 3.5.I.31
Braun Intertec Quality Manual; Potential Reactivity of
Aggregates - Mortar Bar Method
Procedures
Section 3.5.V.10
Braun Intertec Quality Manual; Moisture-Density Relation of
Soil-Modified Proctor
ISFSI Expansion: Concrete Pad Install
Work Orders
ISFSI Expansion: Excavation
2C1.5
Operation Without Computer
FP-EP-EQP-01
Equipment Important to Emergency Response
Procedures
PINGP 1672, FP-
Equipment Important to Emergency Response
Calculations
M-4163-001
C02 Concentrations in the Relay and Cable
Spreading/Computer Room
DBD Top 06
Design Bases Document for Fire Protection
Fire Plans
PINGP 1676
Unit #1 Hydrogen Seal Oil Unit Fire Drill and Critique
03/14/2022
Work Orders
70100056221
SP 1275 10-Month Safe Shutdown Fire Barrier Inspection
08/14/2020
NF 39303-2
Miscellaneous Drain and Vent Piping
NF 39303-4
Miscellaneous Drain and Vent Piping-Unit 1
Drawings
NF-39303
Miscellaneous Drain and Venting Pipe-Unit 1
06/30/1970
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NF-39303-H3
Miscellaneous Drain and Vent Piping-Unit 1
06/30/1970
Engineering
Evaluations
EC: 0000008754
Evaluate the Relay and Cable Spreading Compartment for
Procedures
H36
Plant Flooding
Corrective Action
Documents
501000059179
One Year Turbine TE
2/17/2021
Engineering
Evaluations
1067-0096-LTR-
001
Prairie Island Turbine Valve Test Interval Extension
Evaluation (1 and 2)
01/07/2022
Maintenance Rule Expert Panel Meeting Minutes of
January 7, 2022
01/07/2022
Miscellaneous
Agenda
Prairie Island Maintenance Rule Expert Panel
Meeting - January 7, 2022
01/07/2022
5AWI 4.10.0
Technical Specification Bases and Technical Requirements
Manual Control Programs
Procedures
FP-E-MR-01
Maintenance Rule Process
Work Orders
700095602
Troubleshooting Plan for C Kernel
01/05/2022
Corrective Action
Documents
501000060757
Group C PZR HTRs PRA Entry Time
2/22/2022
Procedures
H10.1
ASME Inservice Testing Program
Work Orders
700007434
1-CL 7434 Clg Return HDR
2/28/2022
501000059495
Residual Heat Removal Voids
01/05/2022
501000059751
Operating Experience Evaluation (OEE) Westinghouse Tech
Bulletin 22-1: Reactor Coolant Pump (RCP) Casing Design
Analysis
01/13/2022
501000060104
"C" Phase Amperage Dropping 22 CD Pump
01/26/2022
Corrective Action
Documents
CE 501000058196
Conduct of Condition Evaluations (from FP-PA-ARP-01)
Frequency/Scope of GL-08-01 Locations Like
2RH-01/2RH-06
11/10/2021
2000019672
Troubleshooting Plan - Unit 2 Residual Heat Removal
System Voids
01/05/2022
608000000834
Review of Void at 2RH-14-500IN3-Part 1 (Void Loads)
608000000834
Review of Void at 2RH-14-500IN3-Part 2 (Structural
Investigation)
Engineering
Evaluations
608000000834
Unit 2 Residual Heat Removal System - Void at 2RH-14
01/05/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operability
Evaluations
501000059495
(ECR
60800000000834)
Evaluation to Support Past Operability of Voiding on the
"B" Train of RHR
H10.1
ASME Inservice Testing Program
Procedures
SP 1106B
Diesel Cooling Water Pump Monthly Test
103
Work Orders
700102337
"C" Phase Voltage Dropping 22 CD Pump
2/08/2022
IP-ENG-001
Standard Design Process (EB-17-06)
Procedures
IP-ENG-001
Design Equivalent Change Package
700070278
D5 Fuel Oil Replacement Piping Coat - Activity 60
08/12/2021
Work Orders
70100093990
D6 Vault Inspection UNS
01/18/2022
Procedures
SP 1106A
Diesel Cooling Water Pump Monthly Test
100
7000062859
2 CR/CU Fan Timer Faulty
2/16/2022
700007134
Wall Thinning Due to MIC-Repair/Replace
05/03/2021
700007434
Post Maintenance Testing 6" Piping - Wall Thinning Due to
MIC - Repair/Replacement
05/03/2021
70001029610010
Replace D6 E1 Gov Actuator
2/07/2022
700062859
2CR C/U Fan Timer Faulty - Bench Test Replacement
Timer
2/17/2022
700102961
Replace D6 E1 Governor Actuator
2/07/2022
Work Orders
701000062590020
2 CR/CU Fan Timer Faulty
2/16/2022
501000020741
NOS: F5 App K Cardox System and Doors 56/57
2/05/2018
Corrective Action
Documents
501000061537
Turbine Valve Leak
03/22/2022
Drawings
NF-39335-185
Residual Heat Removal A-73-97
11/10/1971
Procedures
SP 2468.01
Unit 2 GL-08-01 Inspections for Mode 1, 3, and 4
700079294
SP 1194 18-Month Cardox (CO2) Systems Test
01/05/2022
700092505
SP 2089A-2A Residual Heat Removal Pump and Suction
Valve From RWST
01/28/2022
70090687
SP 2856 BUS 26 Undervoltomnicron Test
01/18/2022
70100091894
SP 2095 BUS 26 Load Sequencer Test
01/18/2022
Work Orders
SP 2468.1 Unit 2 GL-08-01 Inspections for Modes 1, 3,
and 4
01/18/2022
71152S
Corrective Action
501000059609
AST NRC RAI Response Incorrect
01/10/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000059748
NRC Violation Partial ACE Request
01/13/2022
Documents
501000060402
Update NRC Response
2/07/2022
501000056770
Incorrect Information Provided to the NRC
10/05/2021
Corrective Action
Documents
Resulting from
Inspection
501000057560
Rev 8 of PTLR Submitted with Errors
10/21/2021
ENG-ME-819
Adjusted Reference Temperatures for Unit 1 and Unit 2
Reactor Vessel Materials at 54 EFPY
SIR-99-75
Update to the Generic Letter 92-01 Reactor Vessel
Structural Integrity for Prairie Island Units 1 and 2
2
Calculations
Prairie Island Unit 2 Heat up and Cooldown Limit Curves for
Normal Operation
Corrective Action
Documents
500001473878
Reactor Vessel Fluence Calculations
04/11/2015
Corrective Action
Documents
Resulting from
Inspection
501000060322
NRC Question Fluence Methodology Change
2/03/2022
Procedures
H44
Reactor Vessel Integrity Program
2