IR 05000315/2021002
| ML21204A037 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/22/2021 |
| From: | Nestor Feliz-Adorno Reactor Projects Region 3 Branch 4 |
| To: | Gebbie J Indiana Michigan Power Co, Nuclear Generation Group |
| References | |
| IR 2021002 | |
| Download: ML21204A037 (23) | |
Text
July 22, 2021
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2021002 AND 05000316/2021002
Dear Mr. Gebbie:
On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant. On July 6, 2021, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)
consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Donald C. Cook Nuclear Plant. 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/
Néstor J. Féliz Adorno, Chief Branch 4 Division of Reactor Projects
Docket Nos. 05000315 and 05000316 License Nos. DPR-58 and DPR-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000315 and 05000316
License Numbers:
Report Numbers:
05000315/2021002 and 05000316/2021002
Enterprise Identifier: I-2021-002-0083
Licensee:
Indiana Michigan Power Company
Facility:
Donald C. Cook Nuclear Plant
Location:
Bridgman, MI
Inspection Dates:
April 01, 2021 to June 30, 2021
Inspectors:
S. Bell, Health Physicist
B. Bergeon, Operations Engineer
J. Corujo-Sandin, Senior Reactor Inspector
E. Fernandez, Reactor Inspector
J. Mancuso, Resident Inspector
C. St. Peters, Resident Inspector
P. Zurawski, Senior Resident Inspector
Approved By:
Néstor J. Féliz Adorno, Chief
Branch 4
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Donald C. Cook Nuclear 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. A licensee-identified non-cited violation is documented in report section: 71111.08P.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 and Unit 2 began the inspection period at rated thermal power. Unit 1 remained at full power throughout the period. On April 17, 2021, Unit 2 was shutdown for a scheduled refueling outage and returned to full power on May 24, 2021. On June 22, 2021, Unit 2 had an unplanned shutdown to Mode 3 due to a steam leak related to the main turbine. Repairs were in progress at the end of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems on May 18, 2021.
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding after the National Oceanic and Atmospheric Administration issued a seiche and meteotsunami notice on June 21, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)2CD Emergency Diesel Generator (EDG) with 2AB EDG inoperable on April 22, 2021
- (2) Unit 1 Essential Service Water (ESW) during Unit 2 outage maintenance on April 28, 2021
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:
- (2) Fire Zone 47B; 4kV CD Switchgear Room, Unit 2, Elevation 609'-6" on May 18, 2021
- (3) Fire Zone 46D; Emergency Power System AB Battery Room, Elevation 609'-6" on May 18, 2021
- (4) Fire Zone 60; Switchgear Room Cable Vault, Unit 2, Elevation 625'-10" on May 18, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) ESW System on June 4, 2021
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) 2-OHP-5030-19-002E; Unit 2 East Component Cooling Water (CCW) flow test on April 6, 2021
===71111.08P - Inservice Inspection Activities (PWR)
PWR Inservice Inspection Activities Sample (IP Section 03.01)===
- (1) The inspectors verified the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk significant piping system boundaries, and containment boundary were appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from April 26th, 2021 to May 7th, 2021:
03.01.a - Nondestructive Examination and Welding Activities.
- Ultrasonic (UT) examination of 384 lower support column bolts for the Unit 2 Reactor Vessel
- Liquid Penetrant (PT) examination of 2:1 Socket welds on Charging Pump equalizing lines, Component ID 2-PP-50E
- Work Order (WO) 55550041-01, Modify Socket Welds to 2:1 on Charging Pump equalizing lines, Component ID 2-PP-50E
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities
- Bare Metal Visuals (VE) of 58 Reactor Vessel Head Penetrations
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
- AR 2020-6342; Boric Acid Leak on 2-CS-353 East Charging Pump PP-50E discharge vent valve
- AR 2020-0926; Boric Acid Leak on 2-CS-623E Seal Line Vent Valve
- AR 2020-0927; Boric Acid Leak on 2CS-312E East Charging Pump PP-50E drain shutoff valve
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the Control Room during a Unit 2 downpower to 50 percent Main Steam Safety Valve testing on April 15, 2021
- (2) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 2 shutdown for Refueling Outage (RFO) U2C26 on April 16, 2021
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification training during as-found scenarios in the simulator on June 14 and June 16, 2021
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 2 Containment a(1) plan on May 27, 2021
- (2) Unit 2 Non-Essential Service Water a(1) plan on June 15, 2021
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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) Unit 2 reactor vessel head removal (heavy lift) on April 21, 2021
- (2) Unit 1 online risk and Unit 2 outage risk due to significant outage maintenance on April 26, 2021
- (3) Unit 2 risk management during reduced inventory on May 12, 2021
- (4) Unit 2 risk management during scheduled Auxiliary Feedwater (AFW) work on May 25, 2021
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) Engineering Change (EC) 57999; Reactor Coolant (RC) Support Coolers Closed Cooling Water Return Train A Containment Isolation Valve on May 13, 2021
- (2) EC-56679; Replace RC Normal Letdown Train A Shutoff Valve QRV-111 Open and Closed Limit Switches on June 1, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
(1)2-PP-50E; East centrifugal charging pump as set forth in WO 55550041-04 on May 10, 2021 (2)2-NRV-164; RC Loop #4 to Pressurizer Spray Control Valve as set forth in WO 55552476-04 on May 11, 2021 (3)2-FRV-255; 2-PP-3E; East Motor Driven Auxiliary Feedwater (AFW) Pump Test as set forth in WO 55557861-02 on May 18, 2021 (4)2-PP-10E; East Closed Cooling Water Pump PMT-Operability Test as set forth in WO 555549546-29 on May 19, 2021 (5)2-IMO-325; West Residual Heat Removal (RHR) and Safety Injection (SI) to Reactor Coolant System (RCS) Loops 2 & 3 Hot Legs Shutoff as set forth in WO 55496732-02 on May 20, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample 1 Partial)
- (1) The inspectors evaluated Unit 2 RFO U2C26 activities from April 17 to May 25, 2021.
(2)
(Partial) The inspectors evaluated activities resulting from the Unit 2 unplanned manual reactor trip due to the 'B' Main Steam Crossover Pipe large steam leak from June 23, 2021 through the end of the inspection period.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 2 Main Steam Safety Valve testing on April 16, 2021
- (2) Unit 2 Turbine Driven AFW Pump on May 18, 2021
Ice Condenser Testing (IP Section 03.01) (1 Sample)
- (1) Ice Condenser basket weighing on April 5, 2021
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) EPS-S-19EE; 2019 Evaluated Exercise on June 3,
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)
The inspectors evaluated instructions to workers including radiation work permits (RWPs)used to access high radiation areas.
- (1) The inspectors reviewed the following:
Radiation Work Packages
- RWP 212102, U2C26 Reactor Reassembly Activities, Revisions 0 and 1
- RWP 212128, U2C26 Valve Activities in the Auxiliary Building, Containment, and Plant Radiologically Controlled Areas (RCA), Revision 0
Electronic Alarming Dosimeter Alarms
- Dosimeter dose rate alarm which occurred on April 25, 2021 at 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br />
- Dosimeter dose rate alarm which occurred on April 21, 2021 at 1640 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.2402e-4 months <br />
- Dosimeter dose rate alarm which occurred on April 25, 2021 at 1632 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20976e-4 months <br />
Labeling of Containers
- Containers located at the exit to the Unit 2 lower containment access during the U2C26 refueling outage
Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) Observed workers exiting the RCA at the Turbine Building Access Facility during the Unit 2 U2C26 refueling outage
- (2) Evaluated the radiological controls associated with the contents of the spent fuel pool
- (3) Observed the posting and labels for the temporary Radioactive Material Storage Facility located with the protected area during the Unit 2 U2C26 refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors observed work associated with radiography in the Unit 2 Turbine Building Elevation 591' performed under RWP 212130
- (2) The inspectors observed work associated with valve repair in the Auxiliary Building performed under RWP 212128
- (3) The inspectors observed work associated with the number 4 reactor coolant pump located in the Unit 2 containment with performed under RWP 212151 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Unit 2 Containment Reactor Pit
- (2) Auxiliary Building 587' Unit 2 RC/Seal Filter Rooms
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
71124.02 - Occupational ALARA Planning and Controls
Radiation Worker Performance (IP Section 03.04) (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician performance during:
- (1) Unit 2 RCP Number 4 seal inspection and other activities conducted in Unit 2 lower containment during the Unit 2 refueling outage
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) Systems located on the 612' and 598' of the Unit 2 Containment Building during the U2C26 refueling outage
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (5 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Portable ion chambers and friskers available for use in the Auxiliary Building
- (2) Hopewell Designs instrument calibrator located in the Auxiliary Building
- (3) Gamma spectroscopy systems located at the RCA exit and Administration Building
- (4) JL Shepherd Model 89 instrument calibrator located in the RP Calibration Facility
- (5) Non-portable radiation monitoring equipment located at the RCA Exit
Calibration and Testing Program (IP Section 03.02) (12 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Eberline RO20, SN 12678
- (2) Unit 1, Train A, Containment Radiation Area Monitor; 1VRA-1310
- (3) Unit 2, Train A, Containment Radiation Area Monitor; 2VRA-2310
- (4) Canberra Argos-5, Personnel Monitor, SN 11
- (5) Canberra GEM-5, Portal Monitor, SN 3
- (6) Eberline ESP/HP270, Radiation Dose Rate Instrument, SN 1137
- (7) Thermo Scientific SAM-12, Small Article Monitor, SN 148
- (8) MGP Telepole, Radiation Dose Rate Instrument, SN 169
- (9) Hopewell Designs Model BX-3 Instrument Calibrator, SN 0615-4127
- (10) JL Shepherd Model 89 Instrument Calibrator, SN 1
- (11) Thermo Scientific AMS4, Continuous Air Monitor, SN 579
- (12) Ortec Fastscan Whole Body Counter, SN FS-1
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 2, Steam Generator Blowdown Radiation Detector; 2 DRA-300-DET
- (2) Unit 1, Auxiliary Building Vent Radiation Monitor; 1VRS-1500
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
& Transportation
Shipment Preparation (IP Section 03.04)
The inspectors observed the preparation of the following activities:
- (1) Radioactive waste shipment DCC21-030; consisting of dry active waste in a shielded transport cask
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 03.06)===
- (1) Unit 1 (October 1, 2020 - March 31, 2021)
- (2) Unit 2 (October 1, 2020 - March 31, 2021)
MS10: Cooling Water Support Systems (IP Section 03.09) (2 Samples)
- (1) Unit 1 (July 1, 2020 - March 31, 2021)
- (2) Unit 2 (July 1, 2020 - March 31, 2021)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 03.10) (2 Samples)
- (1) Unit 1 (October 1, 2020 through March 31, 2021)
- (2) Unit 2 (October 1, 2020 through March 31, 2021)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 03.16) (1 Sample)
- (1) April 1, 2020 through March 31, 2021
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in Human Performance that might be indicative of a more significant safety issue on June 14,
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.08P This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Title 10 CFR 50.55a(b)(2)(xx)(B) stated, in part, The nondestructive examination method and acceptance criteria of the 1992 Edition or later of Section III shall be met when performing system leakage tests (in lieu of a hydrostatic test) in accordance with IWA-4520 after repair and replacement activities performed by welding or brazing on a pressure retaining boundary using the 2003 Addenda through the latest edition and addenda of Section XI incorporated by reference in paragraph (a)(1)(ii) of this section. Paragraph (a)(1)(ii) of this section included the 2013 Edition of ASME Section XI. ASME Section III ND-5222 further stated circumferential welded joints in piping, pumps, and valves greater than NPS 2 (DN 50) shall be examined by either the magnetic particle, liquid penetrant, or radiographic methods.
Contrary to the above, on February 9, 2021, the licensee failed to meet the nondestructive examination methodology of the 1992 Edition or later of ASME Section III when performing system leakage tests (in lieu of a hydrostatic test) on a pressure retaining boundary after it was repaired/replaced by welding using the 2013 Edition of ASME Section XI. Specifically, the licensee repaired/replaced a portion of the piping downstream of the Unit 1 ESW pump (i.e., component 1-WRV-766) and conducted a system leakage test in lieu of a hydrostatic test of the slip-on flange (a pressure retaining boundary). However, the licensee did not examine the associated circumferential welded piping joints by either magnetic particle, liquid penetrant, or radiographic methods as required by ASME Section III ND-5222.
Significance/Severity: Green. The inspectors assessed the significance of the finding using Inspection Manual Chapter (IMC) 0609, Attachment 4, Initial Characterization of Findings, dated December 20, 2019, and IMC 0609, Appendix A, The Significance Determination Process for Findings At-Power, dated January 1, 2021. Using Exhibit 2, Mitigating Systems Screening Questions, the inspectors determined that the finding was of very low safety significance (i.e., Green) because it did not result in the loss of operability or functionality of mitigating systems. Specifically, the licensee performed an operability determination which reasonably concluded the Unit 1 essential service water system reasonably remained operable.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 6, 2021, the inspectors presented the integrated inspection results to Mr. J. Gebbie, Senior Vice President, and other members of the licensee staff.
- On May 3, 2021, the inspectors presented the radiation protection baseline inspection results to Mr. J. Gebbie, Senior Vice President, and other members of the licensee staff.
- On May 7, 2021, the inspectors presented the in-service baseline inspection results to Mr. J. Gebbie, Senior Vice President, and other members of the licensee staff.
- On May 27, 2021, the inspectors presented the radiation protection baseline inspection results to Mr. J. Gebbie, Senior Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
2-OHP-4022-
001-010
Severe Weather
2
2-OHP-4022-
009
Seiche
PMP-5055-SWM-
001
Severe Weather Guidelines
010
Self-Assessments PMP-5091-FLD-
001
Flood Protection Program Implementation
Drawings
OP-2-5151D-69
Flow Diagram Emergency Diesel Generator "CD" Unit No. 2
Procedures
2-OHP-4021-
019-001
Operation of the ESW System
2-OHP-4021-032-
008CD
Operating DG2CD Subsystems
2-OHP-4021-032-
008CD
Operating DG2CD Subsystems
033
Fire Plans
Fire Zone 46D
E.
- P.S. AB Battery Room Unit 2, Elevation 609'-6"
Fire Zone 47A
4Kv AB Switchgear Room Unit 2, Elevation 609'-6"
Fire Zone 47B
4Kv CD Switchgear Room Unit 2, Elevation 069'-6"
Fire Zone 60
Switchgear Room Cable Vault Unit 2 Elev. 625-10
Calculations
MD-12-CW-005
Flooding due to Circulating Water Expansion Joint Failure
MD-12-FLOOD-
19-N
Mitigating Strategies Assessment for Flooding
PRA-FLOOD-014
Flood Detailed Analysis
Procedures
2-OHP-5030-019-
2E
East Essential Service Water System Flush and Flow Test
Corrective Action
Documents
AR 2021-3339
AEP Welding Manual NDE Table Issue
04/21/2021
AR 2021-3703
U2C26 Lower Support Column Bolt UT Results
04/29/2021
Engineering
Changes
Use 2 to 1 Taper Fillet Welds on Unit 2 Charging Pump
Balance Lines
NDE Reports
55550041-01
Liquid Penetrant Exam of 2 to 1 Socket Welds on Charging
Pump Balance Lines
04/29/2021
U2-VT-21-003
Bare Metal Visuals of Reactor Vessel Head Penetrations
05/04/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
2-QHP-5050-
NDE-001
Liquid Penetrant Examination
011
2-QHP-5050-
NDE-002
Magnetic Particle Examination
008
2-QHP-5050-
NDE-005
Visual Weld and Brazing Examination
2-QHP-5050-
NDE-010
Radiographic Examination of Welds
007
WDI-STD-1176
Procedure for the Ultrasonic Inspection of Lower Support
Column Bolts in Westinghouse 4-Loop Original Downflow
Reactors
WPS 1.2TS
Welding Procedure for P1 to P1
WPS 8.1TS
Welding procedure for P8 to P8
Miscellaneous
DIT-S-06386-00
Design Information Transmittal: Unit 2 Cycle 25,
End-of-Cycle (EOC) Time-to-Boil Information
03/03/2021
71111.11Q Miscellaneous
U2C26 MSSV Setpoint Trevi Testing (Pre-Outage)
Design
Information
Transmittal DIT-
S-06386-00
Unit 2 Cycle 25, End-of-Cycle (EOC) Time-to-Boil
Information
03/03/2021
Design
Information
Transmittal DIT-
S-06387-00
Unit 2 Cycle 26 Beginning-of-Cycle (BOC) Time-to-Boil
Information
03/02/2021
DIT-S-06387-00
Design Information Transmittal: Unit 2 Cycle 26,
Beginning-of-Cycle (BOC) Time-to-Boil Information
03/02/2021
R-S-4602-U1-T1
Period 4602 U1 Training Scenario 1
RQ-E-4602-U2-A
Period 4602 As-Found Simulator Evaluation Unit 2 Primary
Procedures
2-EHP-4030-
051-256
Main Steam Safety Valve Setpoint Verification with Lift
Assist Device
24
2-OHP-4023-E-
Emergency Operating Procedures
2-OHP-4021-001-
003
Power Reduction
059
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RQ-E-4602-U2-A
Period 4602 As-Found Simulator Evaluation Unit 2 Primary
RQ-S-4602-U1-
T1
Period 4602 U1 Training Scenario 1
Corrective Action
Documents
2019-7047
Received Ann 204 Drop 13 South NESW PP Strainer DP
High
07/21/2019
20-5641
2-NLI-320 CNTMT Water Level Indicator has Erratic
Indications
07/15/2020
Miscellaneous
(a)(1) Action Plan, Unit 2 Containment, 2-NLI-320, Lower
Containment Train 'B' Water Level Indicator Transmitter
2/16/2021
(a)(1) Action Plan, Unit 2 Non-Essential Service Water
2/03/2020
Miscellaneous
Unit 1 & 2 Cycle 118, Week 04 Risk
Risk Evaluation Plan
05/12/2021
Risk Evaluation Plan
05/25/2021
Procedures
2-MHP-4050-
FHP-001
Refueling Procedure Guidelines
009
2-MHP-4050-
FHP-023
Reactor Vessel Head Removal with Fuel in the Vessel
2
2-MHP-4050-
FHP-034
Reactor Vessel Head Installation with Fuel in the Vessel
PMP-4050-CHL-
001
016
PMP-5020-MHP-
001
Lifting and Rigging Program
046
Engineering
Changes
2-33-QRV-111-OP/2-33-QRV-111CL/CVCS/Replace
Reactor Coolant Normal Letdown Train'A' Shutoff Valve
QRV-111 Open Limit Switch and Close Limit Switch
2/25/2019
Anti-Rotation Coupling for Valve Actuator 2-CCR-456-ACT
03/31/2021
Miscellaneous
OHI-4016
Conduct of Operations Data Sheet 3, IST Valve Operability
After Maintenance
Procedures
2-OHP-4021-003-
001
Letdown, Charging, and Sealwater Operation
2-OHP-4030-208-
053B
ECCS Valve Operability Test Train B
2-OHP-4030-216-
East Component Cooling Water Loop Surveillance Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20E
(Attachment 1)
2-OHP-4030-234-
033
IST Valve Operability Test - Cold Shutdown; Attachment 3
(CCW to/from Reactor Support Coolers IST Valve
Testing - Cold Shutdown)
2-OHP-4080-256-
017E
East Motor Driven Feedwater System Test
Work Orders
55357861-02
2-FRV-255, East Motor Driven Auxiliary Feedwater Pump
Stroke for PMT
05/07/2021
55496732-02
2-IMO-325, West RHR Hx and South SI Pump to RC Loops
& 3 Hot Legs
05/04/2021
55516277-05
2-CCR-456, IST/PMT Stroke
05/10/2021
55549546-29
2-PP-10E East CCW Pump Perform Operability/PMT
05/08/2021
55552476-04
2-PP-50E, East Component Cooling Pump Perform
Operability/PMT
05/08/2021
55552476-04
2-NRV-164, Reactor Coolant Loop #4 to Pressurizer Spray
Control Valve
05/06/2021
Corrective Action
Documents
AR 2021-5596
Unit 2 Manual Reactor Trip
Drawings
DC-16722
48" Nominal Diameter Universal Expansion Joint
Sub-Assembly
Miscellaneous
Support/Refute Matrix - Why did Liner Fail on 2-XJ-113-5
Sammons to Parikh Email RE: Engineering Report
06/25/2021
SD-070405
Analysis of Postulated Reactor Head Load Drop onto the
Reactor Vessel Flange
Procedures
2-EHP-4030-
2-316
Subcritical Physics Test and ITC Measurement
2-EHP-4030-
2-356
Low Power Physics Tests with Dynamic Rod Worth
Measurement
2-EHP-4050-
FHP-301
Reload-No-N32
2-EHP-4050-
FHP-301
Fuel Sequence Development
2-MHP-4050-
FHP-005
Core Unload/Reload and Incore Shuffle
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-MHP-4050-
FHP-023
Reactor Vessel Head Removal with Fuel in the Vessel
2
2-OHP-4021-001-
2
Reactor Start-Up
2-OHP-4021-001-
006
Power Escalation
PMP-2060-WHL-
001
Work Hour Limitation and Fatigue Management (UZRZ6;
Various Individuals)
Various
Dates
Procedures
1-OHP-4030-156-
017E
East Motor Driven Auxiliary Feedwater System Test
2-MHP-4030-
010-001
Ice Condenser Basket Weighing Surveillance
2-OHP-4030-256-
017T
Turbine Driven Auxiliary Feedwater System Test
VTD-TREV-0001
Trevitest (Owned by Furmanite) Operations Manual for
Setting Safety and Relief Valves
Miscellaneous
21 June 2, 2021 Training Drill Team 1 Scenario Manual
Procedures
2019 Evaluated Exercise
Corrective Action
Documents
AR 2020-10218
Contaminated Material Bags Opened in a
Non-Contaminated Area
2/15/2020
AR 2020-3134
RP Needs to have Procedures to Operate RMS Rad
Monitors
04/08/2020
AR 2021-1606
Contamination Found in Clean Areas
2/18/2021
AR 2021-2097
Wrong RWP Task Assigned to Demin Sluice
03/07/2021
AR 2021-3503
Worker Unable to Pass PCM
04/25/2021
AR 2021-3604
Radiological Survey's Final Review not Timely
04/27/2021
Miscellaneous
Radiography Shot Plan Unit 2 MDA FP 591'
04/28/2021
Procedures
2-THP-6010-
RPP-206
Internal Dose Assessment and Calculation
2-THP-6010-
RPP-401
Performance of Radiation and Contamination Surveys
PMP-6010-RPP-
006
Radiation Work Permit Program
Radiation
21-192
Radiological Air Sample Survey of RCP#4 Seal Work
04/28/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Surveys21-193
Radiological Air Sample Survey of RHR Hz Breach of
2-IMO-340
04/28/2021
SW-VSDS-M-
210420-15
Radiological Survey of U2 TECSA Seal Breach
04/20/2021
SW-VSDS-M-
210425-15
Radiological Survey of U2 Reactor Head Pre-Job for CO2
Cleaning
04/25/2021
SW-VSDS-M-
210426-17
Radiological Survey of RCP#4 Seal Work
04/26/2021
SW-VSDS-M-
210427-17
Radiological Survey of Breach of 2-IMO-350
04/29/2021
Radiation Work
Permits (RWPs)
2102
U2C26 Reactor Reassembly Process
0, 1
2128
U2C26 Valve Activities in the Auxiliary Building,
Containment, and Plant Radiologically Controlled Areas
(RCAs)
2130
U2C26 Perform Radiography in Auxiliary Building,
Containment, Turbine Buildings, and Plant Radiologically
Controlled Areas (RCAs)
2151
U2C26 RCP #4 Maintenance Setup and Support
Procedures
PMP-6010-ALA-
001
ALARA Program - Review of Plant Work Activies
Calibration
Records
Eberline RO20 Calibration; Serial Number 12678
05/26/2021
Canberra Argos-5, Personnel Monitor, Serial Number 11
2/04/2021
Canberra GEM-5 Portal Monitor, Serial Number 3
11/10/2021
Eberline ESP-HP270 Radiation Dose Rate Instrument, Serial
Number 1137
01/01/2021
Bicron T50 Radiation Dose Rate Instrument, Serial Number
304
03/08/2021
Thermo Scientific SAM-12 Small Article Monitor, Serial
Number 148
06/10/2020
MGP Telepole Radiation Dose Rate Instrument, Serial
Number 169
05/03/2021
JL Shepherd Model 89 Characterization and Validation,
Serial Number 1
11/04/2020
Thermo Scientific AMS4 Continuous Air Monitor, Serial
11/22/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Number 579
Ortec Fastscan Whole Body Counter, Serial Number FS-1
07/28/2020
Unit 1 Auxiliary Building Vent Radiation Monitor
11/18/2020
1-0014-03453
Hopewell Designs Model BX3 Instrument Calibrator Serial
Number 0615-4127
11/19/2020
55532682-01
1VRA-1310, Unit 1 Train A Containment Radiation Area
Monitor
05/06/2020
55536961-01
2VRA-2310, Unit 2, Train A Containment Radiation Area
Monitor
08/24/2020
55549407-09
Unit 2 Steam Generator Blowdown Radiation Detector; 2
DRA-300-DET
2/14/2020
Corrective Action
Documents
2019-10885
Electrometer is not Available to Certify Sources
11/04/2019
2019-11319
Use History Analysis for RO20-352 Failing as Found Data
11/12/2019
20-4813
UHA, RP Sample Counter Failed as Found Calibration
06/11/2020
20-5175
Beta Only Count on WPC does not Meet Minimum Time
Requirements
06/25/2020
20-5182
Argos-5 Went Past Cal Due Date
06/25/2020
20-7456
Use History Analysis for TP-038 Failing as Found Data
09/20/2020
Procedures
2-THP-6010-
RPC-517
Calibration of Portable Dose Rate Instruments
2-THP-6010-
RPI-510
Use of the Calibration Facility and Satellite Facilities
Work Orders
55547642-01
Radiation Protection Radioactive Source Leak Tests
11/17/2020
71151
Miscellaneous
U1 and U2 Reactor Coolant System Dose Equivalent
Determinations, October 1, 2020 through March 31, 2021
Various
Radiation Effluent Dose Summary Reports, April 1, 2020
through March 31, 2021
Various
MSPI Deviation Report MSPI High Pressure Systems
(10/01/2020 - 03/31/2021) Unit 1
MSPI Deviation Report MSPI High Pressure Systems
(10/01/2020 - 03/31/2021) Unit 2
MSPI Deviation Report MSPI Cooling Water Systems
(10/01/2020 - 03/31/2021) Unit 1
MSPI Deviation Report MSPI Cooling Water Systems
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(10/01/2020 - 03/31/2021) Unit 2
Operational Narrative Logs (January 2021 - June 2021)
Corrective Action
Documents
ARs Generated January 2021 - June 2021
AR 2016-7865
U2 B Right MSR Joint Failure
AR 2021-5596
Unit 2 had a Manual Reactor Trip at 23:31 due to a Steam
Leak on the Right Moisture Separator Reheater
0