IR 05000315/2021001

Integrated Inspection Report 05000315/2021001 and 05000316/2021001

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: DPR-58 and DPR-74 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 Enclosure

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/ Unit 1 and Unit 2 Train B 71153 Open 2021001-01 Reserve Feed Declared Inoperable Due to Fault Current LER 05000315/2020-001-00 LER 2020-001-00 for Donald 71153 Closed C. Cook Nuclear Plant,

Unit 1, Containment Closure Requirements Not Met During Refueling Operations LER 05000316/2020-002-00 LER 2020-002-00 for Donald 71153 Closed C. Cook Nuclear Plant,

Unit 2, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Leakage LER 05000316/2020-003-00 LER 2020-003-00 for Donald 71153 Closed C. Cook Nuclear Plant Unit 2, Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve LER 05000316/2020-004-00 LER 2020-004-00 for Donald 71153 Closed C. Cook Nuclear Plant Unit 2, Automatic Reactor Trip on Low-Low #24 Steam Generator Water Level LER 05000316/2020-004-01 LER 2020-004-01 for Donald 71153 Closed C. Cook Nuclear Plant Unit 2 Regarding Unit 2 Automatic Reactor Trip on Low-Low

1. 24 Steam Generator Water Level

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.

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.

(4) AR 2021-2081; Slight Ground Indication on 600V Bus 21A on March 10, 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.

(3) Unit 1 AB EDG surveillance on January 19, 2021.

(4) East control room pressurization/cleanup filter system operability test on March 8, 2021.

(5) Unit 2 CD EDG surveillance on March 10,

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,

& Transportation

Waste Characterization and Classification (IP Section 03.03)

(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 71152 CPN-16 & 47 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 Unit 1 and Unit 2 Train B Reserve Feed Declared Inoperable 71153 (Open) Due to Fault Current URI 05000315,05000316/2021001-01

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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures 1-OHP-4021-057- Placing and Removing from Service Circulating Water 28

2 Deicing System

71111.01 Procedures 12-IHP-5040- Plant Winterization and De-Winterization 24

EMP-004

71111.01 Procedures 12-OHP-4022- Severe Weather 21

001-010

71111.04 Procedures 2-OHP-4021-032- Operating DG2AB Subsystems 37

008AB

71111.04 Procedures 2-OHP-4021-032- Operating DG2AB Subsystems 33

008C

71111.05 Fire Plans Fire Zone 15 1 CD Diesel Generator Room Unit 1 Elevation 587' 38

71111.05 Fire Plans Fire Zone 42D E.P.S. AB Batter Room Unit 1 Elev. 609'-6" 38

71111.11Q Miscellaneous RQ-E-ANN-22 Licensed Operator Annual Requalification Scenario #22 2

71111.11Q Miscellaneous RQ-E-ANN-37 Licensed Operator Annual Requalification Scenario #37 4

71111.13 Corrective Action AR 2020-8528 Question Regarding Containment Integrity 0

Documents

71111.13 Corrective Action AR-2021-0702 AB2 Tripped Thermal Overload Following Restoration 0

Documents

71111.13 Corrective Action AR-2021-0875 2-QT-106-AB2 Pressure Failed to Return to Desired Setting 0

Documents

71111.13 Miscellaneous Units 1 & 2 Cycle 117, Week 04 0

71111.13 Miscellaneous Units 1 & 2 Cycle 117, Week 07 0

71111.13 Miscellaneous Units 1 & 2 Cycle 117, Week 12 0

71111.13 Miscellaneous Operational Narrative Logs 01/25/2021 -

01/29/2021

71111.13 Miscellaneous Operational Narrative Logs 02/16/2021 -

2/19/2021

71111.13 Miscellaneous Unit 1/2 Online Risk for Cycle 117, Week 07 0

71111.13 Miscellaneous IACE2020-8528 Apparent Cause Evaluation - AR 2020-8528 0

71111.13 Procedures 1-OHP-4030-127- Refueling Integrity 047

041

71111.13 Procedures 10IHP-4030-114- Containment Integrity 018

Inspection Type Designation Description or Title Revision or

Procedure Date

010

71111.13 Procedures PMP-4100-SDR- Plant Shutdown Safety and Risk Management 50

001

71111.13 Work Orders 55400525 Unit 2 2-QT-106-AB2 0

71111.13 Work Orders 5555089021 Unit 2 Train B RPS/ESF/RTB/SSPS Test 0

71111.13 Work Orders 5555089208 Rack In/Out Reactor Trip Bypass Breaker Train B 0

71111.15 Corrective Action AR 2020-10495 Unit 1 - West CCW Heat Exchanger Leakage 0

Documents

71111.15 Corrective Action AR 2020-8692 Unit 2 - East CCW Pump Shaft Seal Leakage 0

Documents

71111.15 Corrective Action AR 2021-0022 CVCS Unit Cross Tie Leakage Unit 2 to Unit 1 0

Documents

71111.15 Corrective Action AR 2021-1389 Unit 2 - 2-ECR-17, Containment Upper Volume West Air 0

Documents Sampler ESR-7 Containment Isolation Valve Failed Open

Stroke Time

71111.15 Corrective Action AR 2021-2081 Unit 2 - Slight Ground Indication on 21A 0

Documents

71111.15 Corrective Action AR 2021-2098 Unit 2 - 12 OME-129-3 Tripped Twice on HP1 Error Code 0

Documents

71111.15 Corrective Action AR 2021-2290 Unit 2 - Damaged Cable 2-3420R-2 to Unit 2 CCRP 0

Documents

71111.15 Miscellaneous ODMI1-21-001 CVCS Unit Cross Tie Leakage Unit 2 to Unit 1 2

71111.19 Miscellaneous 55234168-01 Open/Clean Inspect Unit 2 West Essential Service Water 02/18/2021

Vent Trap 2-T-131-3

71111.19 Miscellaneous 55267657-02 Perform PMT Leak Inspection Unit 2 West Essential Service 02/17/2021

Water Vent Trap 2-T-131-3

71111.19 Miscellaneous 55267657-03 Perform PMT Leak Inspection Unit 2 West Essential Service 02/18/2021

Water Vent Trap 2-T-131-4

71111.19 Procedures 1-OHP-4030-119- East Essential Service Water System Test 36

2E

71111.19 Work Orders 55511830-01 1-HV-AFP-T1AC Perform Investigation 03/09/2021

71111.19 Work Orders 55511830-04 1-HV-AFP-T1AC; Perform Post Maintenance Test 03/10/2021

71111.22 Procedures 1-IHP-4030-111- Train 'A' Solid State Protection System (SSPS) Automatic 14

1A Trip and Actuation Logic Operational Test (TADOT,

Inspection Type Designation Description or Title Revision or

Procedure Date

Actuation Logic Test and Master Relay Test) and Reactor

Trip Breaker Operational Test (TADOT)

71111.22 Procedures 1-OHP-4030-128- East Control Room Pressurization/Cleanup Filter System 6

24E Operability Test

71111.22 Procedures 1-OHP-4030-132- AB Diesel Generator Operability Test (Train B) 62

27AB

71111.22 Procedures 2-IHP-4030-266- Unit 2 CD Diesel Generator Room CO2 Fire Suppression 3

Test

71111.22 Procedures 2-OHP-4030-232- CD Diesel Generator Operability Test (Train A) 64

27CD

71111.22 Work Orders 55553689 Perform 1-THP-4030-111-01A; Solid State Protection 01/03/2021

System Logic/Reactor Trip Breakers

71124.08 Corrective Action AR 2019-6715 CESA Boxes Not Used in Five Years 07/09/2019

Documents

71124.08 Corrective Action AR 2020-10116 Minor Documentation Errors Found in RP Shipping 12/10/2020

Documents Paperwork

71124.08 Corrective Action AR 2020-6352 Radioactive Material Container 08/11/2020

Documents

71124.08 Corrective Action AR 2020-9868 Rad Waste Discrepancy with UFSAR 12/02/2020

Documents

71124.08 Corrective Action AR 2021-0427 Minor Shipping Documentation Error 01/13/2021

Documents

Resulting from

Inspection

71124.08 Miscellaneous Radioactive Material Transportation Training Documents Various

71124.08 Miscellaneous DC Cook 10 CFR 61 Scaling Factor Report for 2017 12/04/2018

71124.08 Miscellaneous 474095005 10 CFR 61 Laboratory Analysis of Primary Radioactive 02/12/2019

Resin

71124.08 Miscellaneous DCC 19-094 Radioactive Waste Shipment of Spent Demineralizer Resin 12/09/2019

71124.08 Miscellaneous DCC 20-016 Radioactive Material Shipment Consisting of Contaminated 05/26/2020

Equipment

71124.08 Miscellaneous DCC 20-023 Radioactive Waste Shipment of Primary Resin 05/26/2020

71124.08 Miscellaneous RP-C-PB31 Radioactive Material Transportation Security Plan Lesson 5

Plan

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.08 Procedures 12-THP-6010- Preparation of Radioactive Shipments 35

RPP-900

71124.08 Procedures 12-THP-6010- Activity Determination and Waste Classification 8

RPP-903

71124.08 Procedures 12-THP-6010- High Integrity Containers 8

RPP-904

71124.08 Procedures PMP-6010-PCP- Radioactive Waste Process Control Program 14

900

71124.08 Procedures PMP-6010-PCP- Shipment of Radioactive Material and Waste 7

901

71124.08 Procedures PMP-6010-RPP- Control of Material in a Radiation Controlled Area 35

301

71151 Miscellaneous Operational Narrative Logs 01/01/2020 -

2/31/2020

71151 Procedures PMP-7110-001 Reactor Oversight Program Performance Indicators and 19

Monthly Operating Report Data Sheets (January 2020

through December 2020)

71152 Calculations MD-12-CONT- Fatigue Analysis of Penetrations 3

004-N

71152 Calculations SD-000504-003 Stress Analysis for Unit 1 Penetrations CPN-17, CPN-47 and 2

CPN-39 for Piping End Loads

71152 Corrective Action AR 2020-4198 Design Basis Non-Conformance of Containment 05/18/2020

Documents Penetrations CPN-16 & 47

71152 Corrective Action AR 2021-1900 Both Units Lost Train B Reserve Feed 0

Documents

71152 Miscellaneous 1V040.1-RPT- Vendor Report: DC Cook Unit #1 and #2, Containment and 1

001 Crane Wall Piping Penetration Analysis and Qualification

Guideline

71152 Miscellaneous DCC-PM-201- ASME Design Specification for Containment Piping 6

QCN Penetrations

71152 Miscellaneous PORC 4811 Plant Operating Review Committee 4811, 'IPTE Unit 0

Shutdown for Both Units with Train B Reserve Feed

Deenergized'

71152 Miscellaneous PORC 4840 Plant Operating Review Committee 4840, 'Request for 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Notice of Enforcement Discretion for Technical Specifications 3.8.1, "AC Sources - Operating"'

71153 Corrective Action AR 2020-6941 U2 Manual Reactor Trip and Auto Safety Injection 09/04/2020

Documents

71153 Corrective Action AR 2020-8488 Unit 2 Reactor Trip - 12 October 2020 10/12/2020

Documents

71153 Corrective Action AR 2021-1900 Both Units Lost Train B Reserve Feed 0

Documents

71153 Drawings E-2508 34.5kV Bus Wiring Diagram 24

71153 Drawings RSC1-4249 Relay Diagram 34.5kV Reserve Feed Lead Differentials 2

71153 Engineering E-1300 345/34.5kV One Line Diagram 36

Changes

71153 Miscellaneous AEP NRC-2021- Compensatory Action 1-21-CCA-0030 per NOED AEP NRC- 03/01/2021

2021-20

71153 Miscellaneous AEP NRC-2021- Compensatory Action 2-21-CCA-0028 per NOED AEP NRC- 03/01/2021

2021-20

71153 Miscellaneous LER 315/2020- Unit 1 Containment Closure Requirements Not Met During 00

001-00 Refueling Operations

15