IR 05000315/2021001
| ML21118A879 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/28/2021 |
| From: | Nestor Feliz-Adorno Reactor Projects Region 3 Branch 4 |
| To: | Gebbie J Indiana Michigan Power Co |
| References | |
| EA-21-024 IR 2021001 | |
| Download: ML21118A879 (18) | |
Text
April 28, 2021
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2021001 AND 05000316/2021001
Dear Mr. Gebbie:
On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant. On April 15, 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:
05000315/2021001 and 05000316/2021001
Enterprise Identifier: I-2021-001-0031
Licensee:
Indiana Michigan Power Company
Facility:
Donald C. Cook Nuclear Plant
Location:
Bridgman, MI
Inspection Dates:
January 01, 2021 to March 31, 2021
Inspectors:
S. Bell, Health Physicist
A. Dahbur, Senior Reactor Inspector
I. Hafeez, Reactor Inspector
J. Mancuso, Resident Inspector
J. Neurauter, Senior Reactor 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 NCV is documented in report section: 71111.1
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 05000315,05000316/
2021001-01 Unit 1 and Unit 2 Train B Reserve Feed Declared Inoperable Due to Fault Current 71153 Open LER 05000315/2020-001-00 LER 2020-001-00 for Donald C. Cook Nuclear Plant,
Unit 1, Containment Closure Requirements Not Met During Refueling Operations 71153 Closed LER 05000316/2020-002-00 LER 2020-002-00 for Donald C. Cook Nuclear Plant,
Unit 2, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Leakage 71153 Closed LER 05000316/2020-003-00 LER 2020-003-00 for Donald C. Cook Nuclear Plant Unit 2, Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve 71153 Closed LER 05000316/2020-004-00 LER 2020-004-00 for Donald C. Cook Nuclear Plant Unit 2, Automatic Reactor Trip on Low-Low #24 Steam Generator Water Level 71153 Closed LER 05000316/2020-004-01 LER 2020-004-01 for Donald C. Cook Nuclear Plant Unit 2 Regarding Unit 2 Automatic Reactor Trip on Low-Low
- 24 Steam Generator Water Level 71153 Closed
PLANT STATUS
Donald C. Cook began the inspection period with both Unit 1 and Unit 2 operating at approximately 100 percent power and, with the following exception, remained at that level throughout the inspection period. On March 19-20, 2021, Unit 1 power was reduced to 92 percent for scheduled main turbine and main feedwater pump testing. The unit was returned to 100 percent on March 20,
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 Disease 2019 (COVID-19), resident 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; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; 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 portions 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 readiness for seasonal extreme weather conditions prior to the onset of severe cold temperatures on February 10, 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) Unit 2 AB & CD fuel oil transfer pumps with fuel oil transfer pump AB2 inoperable on January 21, 2021.
- (2) Unit 1 AB emergency diesel generator (EDG) while guarded for essential service water (ESW) maintenance on February 10, 2021.
- (3) Unit 2 critical control power inverter and direct current (DC) supply breaker MDAB-6 due to Unit 2 600 volt alternating current (AC) supply breaker EZC-A-4AL tripped on March 18, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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 2 east 4 KV rooms on February 2, 2021.
- (2) Fire Zone 42D; emergency power supply AB battery room Unit 1 elevation 609'-6" on March 31, 2021.
- (3) Fire Zone 15; 1 CD EDG room Unit 1 elevation 587' on March 31, 2021.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated Unit 2 Training Session 3, RQ-S-4505-U2, on March 3, 2021.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 Samples 1 Partial)
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) Completion of the Unit 1 airlock equalizing valve removal begun on November 18, 2020.
- (2) Maintenance risk for cycle 117 week 04 with significant switchyard work and Unit 1/2 EDGs protected on January 25, 2021.
- (3) Emergent work; Unit 2 AB2 EDG fuel oil transfer pump failure on February 1, 2021.
- (4) Maintenance risk for cycle 117 week 07 with Unit 1 Train B solid state protection system (SSPS) testing and maintenance of the following on February 16, 2021:
- Unit 2 ESW pump discharge and strainer
- West diesel driven fire pump
- Unit 2 middle hotwell pump
- (5) Maintenance risk for cycle 117 week 012 with Unit 1 closed cooling water heat exchanger outlet maintenance on March 22, 2021.
- (6) Risk management for Unit 2 AB2 fuel oil transfer pump out of service on February 2, 2021.
(7)
(Partial)
Unit 1 SI line voiding on March 24, 2021.
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) Action Request (AR) 2020-10495; Unit 1 West Closed Cooling Water Heat Exchanger Leakage on January 2, 2021.
- (2) AR 2020-8692; Unit 2 East Component Cooling Water (CCW) Pump Shaft Seal Leakage on January 15, 2021.
- (3) AR 2021-022; Chemical and Volume Control System (CVCS) unit Cross Tie Leakage Unit 2 to Unit 1 on February 1, 2021.
- (5) AR 2021-1389; Unit 2 Containment Upper Volume West Air Sampler Containment Isolation Valve Failed Stroke Test on February 24, 2021.
- (6) AR 2021-2290; Unit 2 - Damaged Cable 2-3420R-2 to Unit 2 Critical Control Power Cabinet on March 24, 2021.
- (7) AR 2021-2098; Unit 2 Glycol Chiller #3 Tripped on March 15, 2021.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 1 ESW maintenance on February 10, 2021.
- (2) Unit 1 ESW discharge pump and strainer maintenance on February 17, 2021.
- (3) Unit 1 turbine driven auxiliary feedwater pump room cooler on March 9, 2021.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 2 EDG surveillance on January 5, 2021.
- (2) Unit 1 Train A SSPS on January 14, 2021.
- (4) East control room pressurization/cleanup filter system operability test on March 8, 2021.
- (5) Unit 2 CD EDG surveillance on March 10,
RADIATION SAFETY
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
& Transportation
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
- (1) The inspectors evaluated the licensees characterization and classification of radioactive waste for shipment DCC 20-023 consisting of primary resin.
- (2) The inspectors evaluated the licensees characterization and classification of radioactive waste for shipment DCC 19-094 consisting of spent resin.
Shipping Records (IP Section 03.05) (3 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) Shipment DCC20-016, Radioactive - SCO material shipment consisting of radioactive samples packaged in a general design package.
- (2) Shipment DCC20-023, Radioactive - LSA waste shipment consisting of primary resin packaged in a Type A package.
- (3) Shipment DCC19-094, Radioactive - LSA waste shipment consisting of spent demineralizer resin packaged in a general design package.
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 03.01)===
- (1) Unit 1 (January 1, 2020 - December 31, 2020)
- (2) Unit 2 (January 1, 2020 - December 31, 2020)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 03.02) (2 Samples)
- (1) Unit 1 (January 1, 2020 - December 31, 2020)
- (2) Unit 2 (January 1, 2020 - December 31, 2020)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 03.03) (2 Samples)
- (1) Unit 1 (January 1, 2020 - December 31, 2020)
- (2) Unit 2 (January 1, 2020 - December 31, 2020)
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 03.04) (2 Samples)
- (1) Unit 1 (January 1, 2020 - December 31, 2020)
- (2) Unit 2 (January 1, 2020 - December 31, 2020)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) AR 2020-4198: Design Basis Non-Conformance of Containment Penetrations CPN-16 & 47 on January 1, 2021.
- (2) AR 2021-1900; Both Units Lost Train B Reserve Feed on February 26, 2021.
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 05000315/2020-001, "Unit 1 Containment Closure Requirements Not Met During Refueling Operation," on December 9, 2020, (ADAMS Accession Number ML20353A109), during the week of March 29, 2021. The inspection conclusions associated with this LER are documented in the Results Section 71152 of this report.
- (2) LER 05000316/2020-02-00, "Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Leakage" on May 1, 2020, (ADAMS Accession No.
ML20188A216.) The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.
- (3) LER 05000316/2020-03-00, "Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve," (ADAMS Accession No. ML20188A216) on September 4, 2020. The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.
- (4) LERs 05000316/2020-004-00 & 05000316/2020-004-01, "Unit 2 Automatic Reactor Trip on Low-Low #24 Steam Generator Water Level" (ADAMS Accession Nos.
ML20353A108 & ML21063A250) on October 12, 2020. The inspection conclusions associated with these LERs are documented in Inspection Report 05000316/2020004 under Inspection Results Section 71153.
Notice of Enforcement Discretion (NOED) (IP Section 03.04) (1 Partial)
(1)
(Partial)
The inspectors evaluated the licensee actions surrounding NOED EA-21-024 Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating "
due to Unit 1 and Unit 2 Train B reserve feed being declared inoperable due to fault current which can be accessed at https://www.nrc.gov/docs/ML2106/ML21063A568.pdf on March 1,
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.13 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 an NCV, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Donald C. Cook, Unit 1, TS 3.9.3 requires, in part, that, during movement of irradiated fuel assemblies within containment, the status of each containment penetration providing direct access from the containment atmosphere to the outside atmosphere is either
- (1) closed by a manual or automatic isolation valve, blind flange, or equivalent; or
- (2) capable of being closed by an operable containment purge supply and exhaust system. The associated Required Action A.1 requires the immediate suspension of movement of irradiated fuel assemblies within containment when one or more containment penetrations are not in the status required by TS 3.9.3.
Contrary to the above, from October 4, 2020 (1616) to October 6, 2020 (1444), the licensee failed to maintain the status of each containment penetration providing direct access from the containment atmosphere to the outside atmosphere during movement of irradiated fuel assemblies within containment as either
- (1) closed by a manual or automatic isolation valve, blind flange, or equivalent; or
- (2) capable of being closed by an operable containment purge supply and exhaust system. Specifically, the equalization valves of the containment penetration associated with the Unit 1 containment personnel airlock door at the 612 elevation were removed as part of preventative maintenance Work Order 5553058301-01.
The removal of these equalization valves caused the containment penetration to provide direct access from the containment atmosphere to the outside atmosphere and movement of irradiated fuel assemblies within containment was not suspended.
Significance/Severity: Green. The inspectors assessed the significance of the finding using Inspection Manual Chapter (IMC) 0609, Appendix G, Shutdown Operations Significance Determination Process; Exhibit 4, Barrier Integrity Screening Questions; under Block B, Containment Barrier. Because the finding degraded the physical integrity of reactor containment, Question B.9 directed the inspectors to IMC 0609, Appendix H, Containment Integrity Significance Determination Process. The inspectors determined the finding was Type B related to Containment isolation valves in lines using Table 4.1 and required Phase 2 evaluation using Section 07.01/Table 7.1. Using Section 07.02 (Step 2.1),the inspectors screened the finding as Green since the finding did not occur within eight days of the outage start. The licensee reported this event to the NRC as LER 05000315/2020-001-00,Unit 1 Containment Closure Requirements Not Met During Refueling Operation, on December 9, 2020, (Adams Accession Number ML20353A109).
Corrective Action References: Action Request (AR) 2020-8528, Question Regarding Containment Integrity
Observation: Design Basis Non-Conformance of Containment Penetrations CPN-16 & 47 71152 The inspectors assessed the licensee's corrective actions taken to address the non-conforming condition captured in AR 2020-4198; " Design Basis Non-conformance of CPN-16/47. The non-conforming condition was that revision 1 of calculation SD-000504-003 did not consider the thermal stress effects in the evaluations for containment piping penetrations at containment penetration numbers CPN-16 and CPN-47. Therefore, the effects of the thermal stresses were not considered in the evaluation at the flued head to sleeve junction structural discontinuity which is not in conformance with the requirements of the applicable design code (i.e., the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section III Division 1 (1968)). The inspectors reviewed the licensees evaluation of the thermal stress effects at structural discontinuities as well as the evaluation of stress and fatigue against the allowable limits specified in the ASME Section III-1968 design code. Based on the inspectors review, no concerns were identified.
Unresolved Item (Open)
Unit 1 and Unit 2 Train B Reserve Feed Declared Inoperable Due to Fault Current URI 05000315,05000316/2021001-01 71153
Description:
On February 26, 2021, at 1008 hours0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.83544e-4 months <br />, a fault current occurred between the high side of reserve auxiliary transformer and associated breaker on the Train B reserve feed for both units. This caused the circuit breakers to open, removing access to one of the two immediate offsite power sources at both units. The Unit 1 and Unit 2 Train B reserve feed were declared inoperable and required action A of TS 3.8.1 was entered for both units. TS 3.8.1 Condition A.3 requires operability be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the plant be in Mode 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Mode 5 within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Licensee investigation identified a failed bus structure in loop feeder enclosure #1 which feeds both Unit 1 and Unit 2. Repair/replacement was required to return the circuit to operable status, however the time to complete repairs exceeded the 72-hour completion time of TS 3.8.1 Condition A.3. The other immediate offsite power source, all four emergency diesel generators, and the backup offsite power source remained fully functional.
On February 28, 2021, the licensee requested enforcement discretion to not enforce compliance with the TS 3.8.1 Condition A.3 completion time for an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to allow time to repair the failed bus structure and perform necessary post-maintenance testing.
Unit 1 and Unit 2 were operating at approximately 100 percent power. Without this enforcement discretion, Unit 1 and Unit 2 were required to be in MODE 3 by 1608 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.11844e-4 months <br /> on March 1, 2021, and Mode 5 by 2208 hours0.0256 days <br />0.613 hours <br />0.00365 weeks <br />8.40144e-4 months <br /> on March 2, 2021.
The NRC granted the verbal request and subsequently issued NOED No. EA-21-024 to (ML21063A568) exercise discretion and not enforce compliance with TS 3.8.1.A.3 Condition A.3, for a 48-hour period starting on March 1, 2021, and ending at 1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br />, on March 3, 2021. The NOED approval basis and required compensatory measures were documented by NRC letter to I&M, dated March 4, 2021. The repair and post-maintenance activities were completed with equipment restored to service at 0522 hours0.00604 days <br />0.145 hours <br />8.630952e-4 weeks <br />1.98621e-4 months <br /> on March 2, 2021. During the NOED period, inspectors verified the required NOED actions were performed.
Planned Closure Actions: The licensee was evaluating the cause to the electrical fault at the conclusion of this inspection period. The inspectors opened this unresolved item (URI) to review the licensee's cause determination and other information to determine whether performance deficiencies or violations of more than minor significance occurred leading to the need for the NOED.
Licensee Actions: The licensee inspected the affected equipment for damage, replaced necessary components, and restored the equipment back to service. The licensee also placed temporary heaters in the affected loop feed enclosure for moisture control and established a future action to install permanent heaters along with preventative maintenance measures.
Corrective Action References: AR 2021-1900
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 15, 2021, the inspectors presented the integrated inspection results to Mr. J. Gebbie, Senior Vice President, and other members of the licensee staff.
- On January 14, 2021, the inspectors presented the radiation protection baseline inspection results to Mr. J. Gebbie, Senior Vice Present, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
1-OHP-4021-057-
2
Placing and Removing from Service Circulating Water
Deicing System
Procedures
2-IHP-5040-
EMP-004
Plant Winterization and De-Winterization
Procedures
2-OHP-4022-
001-010
Severe Weather
Procedures
2-OHP-4021-032-
008AB
Operating DG2AB Subsystems
Procedures
2-OHP-4021-032-
008C
Operating DG2AB Subsystems
Fire Plans
Fire Zone 15
CD Diesel Generator Room Unit 1 Elevation 587'
Fire Plans
Fire Zone 42D
E.P.S. AB Batter Room Unit 1 Elev. 609'-6"
71111.11Q Miscellaneous
RQ-E-ANN-22
Licensed Operator Annual Requalification Scenario #22
71111.11Q Miscellaneous
RQ-E-ANN-37
Licensed Operator Annual Requalification Scenario #37
Corrective Action
Documents
AR 2020-8528
Question Regarding Containment Integrity
Corrective Action
Documents
AR-2021-0702
AB2 Tripped Thermal Overload Following Restoration
Corrective Action
Documents
AR-2021-0875
2-QT-106-AB2 Pressure Failed to Return to Desired Setting
Miscellaneous
Units 1 & 2 Cycle 117, Week 04
Miscellaneous
Units 1 & 2 Cycle 117, Week 07
Miscellaneous
Units 1 & 2 Cycle 117, Week 12
Miscellaneous
Operational Narrative Logs
01/25/2021 -
01/29/2021
Miscellaneous
Operational Narrative Logs
2/16/2021 -
2/19/2021
Miscellaneous
Unit 1/2 Online Risk for Cycle 117, Week 07
Miscellaneous
IACE2020-8528
Apparent Cause Evaluation - AR 2020-8528
Procedures
1-OHP-4030-127-
041
Refueling Integrity
047
Procedures
Containment Integrity
018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
010
Procedures
PMP-4100-SDR-
001
Plant Shutdown Safety and Risk Management
Work Orders
55400525
Unit 2 2-QT-106-AB2
Work Orders
5555089021
Unit 2 Train B RPS/ESF/RTB/SSPS Test
Work Orders
5555089208
Rack In/Out Reactor Trip Bypass Breaker Train B
Corrective Action
Documents
AR 2020-10495
Unit 1 - West CCW Heat Exchanger Leakage
Corrective Action
Documents
AR 2020-8692
Unit 2 - East CCW Pump Shaft Seal Leakage
Corrective Action
Documents
AR 2021-0022
CVCS Unit Cross Tie Leakage Unit 2 to Unit 1
Corrective Action
Documents
AR 2021-1389
Unit 2 - 2-ECR-17, Containment Upper Volume West Air
Sampler ESR-7 Containment Isolation Valve Failed Open
Corrective Action
Documents
AR 2021-2081
Unit 2 - Slight Ground Indication on 21A
Corrective Action
Documents
AR 2021-2098
Unit 2 - 12 OME-129-3 Tripped Twice on HP1 Error Code
Corrective Action
Documents
AR 2021-2290
Unit 2 - Damaged Cable 2-3420R-2 to Unit 2 CCRP
Miscellaneous
ODMI1-21-001
CVCS Unit Cross Tie Leakage Unit 2 to Unit 1
Miscellaneous
234168-01
Open/Clean Inspect Unit 2 West Essential Service Water
Vent Trap 2-T-131-3
2/18/2021
Miscellaneous
267657-02
Perform PMT Leak Inspection Unit 2 West Essential Service
Water Vent Trap 2-T-131-3
2/17/2021
Miscellaneous
267657-03
Perform PMT Leak Inspection Unit 2 West Essential Service
Water Vent Trap 2-T-131-4
2/18/2021
Procedures
1-OHP-4030-119-
2E
East Essential Service Water System Test
Work Orders
55511830-01
1-HV-AFP-T1AC Perform Investigation
03/09/2021
Work Orders
55511830-04
1-HV-AFP-T1AC; Perform Post Maintenance Test
03/10/2021
Procedures
1-IHP-4030-111-
1A
Train 'A' Solid State Protection System (SSPS) Automatic Trip and Actuation Logic Operational Test (TADOT,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Actuation Logic Test and Master Relay Test) and Reactor
Trip Breaker Operational Test (TADOT)
Procedures
1-OHP-4030-128-
24E
East Control Room Pressurization/Cleanup Filter System
Operability Test
Procedures
1-OHP-4030-132-
27AB
AB Diesel Generator Operability Test (Train B)
Procedures
2-IHP-4030-266-
Unit 2 CD Diesel Generator Room CO2 Fire Suppression
Test
Procedures
2-OHP-4030-232-
27CD
CD Diesel Generator Operability Test (Train A)
Work Orders
55553689
Perform 1-THP-4030-111-01A; Solid State Protection
System Logic/Reactor Trip Breakers
01/03/2021
Corrective Action
Documents
AR 2019-6715
CESA Boxes Not Used in Five Years
07/09/2019
Corrective Action
Documents
AR 2020-10116
Minor Documentation Errors Found in RP Shipping
Paperwork
2/10/2020
Corrective Action
Documents
AR 2020-6352
Radioactive Material Container
08/11/2020
Corrective Action
Documents
AR 2020-9868
Rad Waste Discrepancy with UFSAR
2/02/2020
Corrective Action
Documents
Resulting from
Inspection
AR 2021-0427
Minor Shipping Documentation Error
01/13/2021
Miscellaneous
Radioactive Material Transportation Training Documents
Various
Miscellaneous
DC Cook 10 CFR 61 Scaling Factor Report for 2017
2/04/2018
Miscellaneous
474095005
CFR 61 Laboratory Analysis of Primary Radioactive
Resin
2/12/2019
Miscellaneous
DCC 19-094
Radioactive Waste Shipment of Spent Demineralizer Resin
2/09/2019
Miscellaneous
DCC 20-016
Radioactive Material Shipment Consisting of Contaminated
Equipment
05/26/2020
Miscellaneous
DCC 20-023
Radioactive Waste Shipment of Primary Resin
05/26/2020
Miscellaneous
RP-C-PB31
Radioactive Material Transportation Security Plan Lesson
Plan
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
2-THP-6010-
RPP-900
Preparation of Radioactive Shipments
Procedures
2-THP-6010-
RPP-903
Activity Determination and Waste Classification
Procedures
2-THP-6010-
RPP-904
High Integrity Containers
Procedures
PMP-6010-PCP-
900
Radioactive Waste Process Control Program
Procedures
PMP-6010-PCP-
901
Shipment of Radioactive Material and Waste
Procedures
PMP-6010-RPP-
301
Control of Material in a Radiation Controlled Area
71151
Miscellaneous
Operational Narrative Logs
01/01/2020 -
2/31/2020
71151
Procedures
PMP-7110-001
Reactor Oversight Program Performance Indicators and
Monthly Operating Report Data Sheets (January 2020
through December 2020)
Calculations
MD-12-CONT-
004-N
Fatigue Analysis of Penetrations
Calculations
SD-000504-003
Stress Analysis for Unit 1 Penetrations CPN-17, CPN-47 and
CPN-39 for Piping End Loads
Corrective Action
Documents
AR 2020-4198
Design Basis Non-Conformance of Containment
Penetrations CPN-16 & 47
05/18/2020
Corrective Action
Documents
AR 2021-1900
Both Units Lost Train B Reserve Feed
Miscellaneous
1V040.1-RPT-
001
Vendor Report: DC Cook Unit #1 and #2, Containment and
Crane Wall Piping Penetration Analysis and Qualification
Guideline
Miscellaneous
DCC-PM-201-
QCN
ASME Design Specification for Containment Piping
Miscellaneous
PORC 4811
Plant Operating Review Committee 4811, 'IPTE Unit
Shutdown for Both Units with Train B Reserve Feed
Deenergized'
Miscellaneous
PORC 4840
Plant Operating Review Committee 4840, 'Request for
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Notice of Enforcement Discretion for Technical Specifications 3.8.1, "AC Sources - Operating"'
Corrective Action
Documents
AR 2020-6941
U2 Manual Reactor Trip and Auto Safety Injection
09/04/2020
Corrective Action
Documents
AR 2020-8488
Unit 2 Reactor Trip - 12 October 2020
10/12/2020
Corrective Action
Documents
AR 2021-1900
Both Units Lost Train B Reserve Feed
Drawings
E-2508
34.5kV Bus Wiring Diagram
Drawings
RSC1-4249
Relay Diagram 34.5kV Reserve Feed Lead Differentials
Engineering
Changes
E-1300
345/34.5kV One Line Diagram
Miscellaneous
AEP NRC-2021-
Compensatory Action 1-21-CCA-0030 per NOED AEP NRC-
21-20
03/01/2021
Miscellaneous
AEP NRC-2021-
Compensatory Action 2-21-CCA-0028 per NOED AEP NRC-
21-20
03/01/2021
Miscellaneous
LER 315/2020-
001-00
Unit 1 Containment Closure Requirements Not Met During
Refueling Operations
00