IR 05000315/2020003
| ML20302A422 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/28/2020 |
| From: | Nestor Feliz-Adorno Reactor Projects Region 3 Branch 4 |
| To: | Gebbie J Indiana Michigan Power Co |
| References | |
| IR 2020003 | |
| Download: ML20302A422 (13) | |
Text
October 28, 2020
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2020003 AND 05000316/2020003
Dear Mr. Gebbie:
On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Donald C. Cook Nuclear Plant. On October 8, 2020, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/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: 05000315/2020003 and 05000316/2020003 Enterprise Identifier: I-2020-003-0024 Licensee: Indiana Michigan Power Company Facility: Donald C. Cook Nuclear Plant Location: Bridgman, Michigan Inspection Dates: July 01, 2020 to September 30, 2020 Inspectors: J. Bozga, Senior 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 the 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.
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. On September 16, 2020, Unit 1 was shutdown for a scheduled refueling outage and remained shutdown through the end of the inspection period. Unit 2 had an unplanned shutdown on September 4, 2020, due to a failed pressurizer relief valve. After correction of the issue, the unit was returned to rated thermal power on September 9, 2020, where it remained for the rest 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 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 and during that time 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 readiness for seasonal extreme weather (summer hot temperature conditions) for the following systems, July 2 through July 9, 2020:
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems below from impending severe weather [Midwest Derecho High Winds] on August 10, 2020:
- Circulating Water
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 CD EDG with Unit 1 AB EDG inoperable on July 7, 2020
- (2) Unit 2 AB EDG with Unit 2 CD EDG inoperable on July 27, 2020
- (3) Unit 2 control room instrument distribution alternate power source with main power source inoperable on July 28, 2020
- (4) Unit 1 west charging pump with Unit 1 east charging pump inoperable on July 30, 2020
- (5) Unit 2 west motor-driven auxiliary feedwater pump (MDAFWP) with Unit 2 east MDAFWP inoperable for maintenance on August 5, 2020
- (6) Unit 1 component cooling water (CCW) heat exchanger on September 24, 2020
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 1 east and west CCW heat exchanger inspection on August 17, 2020
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Reserve auxiliary transformer maintenance the week of July 6, 2020
- (2) 2AB EDG maintenance the week of July 20, 2020
- (3) 2CD EDG maintenance the week of July 27, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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) Scheduled Unit 1 work (reserve auxiliary transformer and EDG) for the week of July 6, 2020
- (2) 2AB EDG due to room ventilation supply fan and day tank enclosure fan motor fire on July 13, 2020
- (3) Scheduled Unit 2 work (2CD EDG, emergency service water, safety injection pump)for the week of July 27, 2020
- (4) Maintenance Rule (a)(1) - Unit 2 non-essential service water (NESW) System on July 21, 2020
- (5) Maintenance Rule (a)(1) - Unit 2 Nuclear Instrument NI-01 on July 24, 2020
- (6) Unit 1 east essential service water (ESW) backwash air fitting - unplanned limiting condition for operation on August 7, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Action Request (AR) 2020-5522 & 5534; Increase of leaks on 1AB EDG jacket water and 1-HE-47-ABS EDG aftercooler leaking from two bolts on July 13, 2020
- (2) AR 2020-5502; Unverified assumption - calculation 2-E-N-ELCP-120-002 on July 13, 2020
- (4) AR 2020-6007; Thru wall leak at equalizing line on Unit 1 East centrifugal charging pump on August 1, 2020
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 0000057627; Replace 2-HV-DGX-3 Motor on July 27, 2020
- (2) Unit 1 ESW temporary configuration change for broken airline on August 7, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) 2-IMO-312; Unit 2 residual heat removal (RHR) heat exchanger on July 1, 2020
- (2) Unit 1 CO2 fire suppression system following maintenance on July 1, 2020
- (3) 1-HV-CLV-1A; Unit 1 lower containment vent unit on July 2, 2020
- (4) Unit 2 west containment spray system test on July 20, 2020
- (5) 2-OHP-4040-208-051N; Unit 2 north safety injection (SI) pump surveillance on July 31, 2020
- (6) Unit 2 CD EDG after maintenance on August 3, 2020
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample 1 Partial)
- (1) The inspectors evaluated activities during a forced outage for Unit 2 due to a failed pressurizer spray valve from September 4 to September 7, 2020.
(2) (Partial)
The inspectors evaluated Unit 1 Refueling Outage activities from September 15 to September 30, 2020. The refueling outage remained ongoing as of 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) 2CD EDG operability surveillance on July 27, 2020
- (2) Unit 1 north SI pump on July 29, 2020
- (4) Unit 1 Train B reactor protection system and engineered safety feature reactor trip breaker and solid-state protection system automatic trip and logics test on
August 17, 2020 Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2 west containment spray system test on July 20, 2020
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) An emergency planning drill on August 25,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===
- (1) Unit 1 (January 1, 2019 through December 31, 2019)
- (2) Unit 2 (January 1, 2019 through December 31, 2019)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)
(2 Samples)
- (1) Unit 1 (January 1, 2019 through December 31, 2019)
- (2) Unit 2 (January 1, 2019 through December 31, 2019)
IE04: Unplanned Scrams with Complications Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (January 1, 2019 through December 31, 2019)
- (2) Unit 2 (January 1, 2019 through December 31, 2019)
MS05: Safety System Functional Failures Sample (IP Section 02.04) (2 Samples)
- (1) Unit 1 (January 1, 2019 through December 31, 2019)
- (2) Unit 2 (January 1, 2019 through December 31, 2019)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2019 through June 30, 2020)
- (2) Unit 2 (July 1, 2019 through June 30, 2020)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2019 through June 30, 2020)
- (2) Unit 2 (July 1, 2019 through June 30, 2020)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (July 1, 2019 through June 30, 2020)
- (2) Unit 2 (July 1, 2019 through June 30, 2020)
71152 - Problem Identification and Resolution
Annual Follow-Up of Selected Issues (IP Section 02.03) (2 Samples 1 Partial)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1) (Partial)
AR 2020-4198; Design Basis Non-Conformance of Containment Penetrations CPN-16 & 47 (RHR Normal Cooldown Flow Path, Supply & Return) on July 1, 2020
- (2) AR 2020-5344; Unexpected Control Rod Motion (Unit 1) - Power Range N-32 Spiked High on July 6, 2020
- (3) AR 2020-6007; Thru-Wall Leak at Equalizing Line on Unit 1 East Centrifugal Charging Pump on August 1,
INSPECTION RESULTS
Observation: Active Leak at Unit 1 East Charging Pump (1-PP-50E) Discharge 71152 Side Flange Equalization Line The inspectors performed a detailed review of AR 2020-6007; "Leak at Equalizing Line of U1 E CCP. For the Problem Identification and Resolution Annual Sample, the inspectors focused on assessment of the licensee's corrective actions taken to date and those planned from this point forward. The licensee performed a repair to the leak at the equalization line for the Unit 1 East Charging Pump (1-PP-50E). The inspectors reviewed the work order associated with this repair as well as the post repair non-destructive examination information.
The inspectors concluded that the licensee's actions taken in accordance with their corrective action program were reasonable given the overall safety significance of the issue. Based on the inspector's review, no concerns were identified.
Observation: Unexpected Control Rod Motion 71152 The inspectors performed a detailed review of AR 2020-6603, U-1 control rod stepped in one-half step and AR-2020-5344, "Unexpected Control Rod Motion in Unit 1." On July 3, 2020, AR 2020-5344 identified unexpected control rod motion in Unit 1 by control bank D unexpectedly moving inward 0.5 steps. Immediate operational action was taken, and the appropriate procedures were entered. Operators noted a temperature error from a power mismatch (momentary spike) had occurred which appeared to originate from nuclear instrumentation N-42. On August 24, 2020, AR 2020-6603 identified a similar occurrence of an unexpected one-half step on the control rods with an associated spike on nuclear instrumentation N-42. For this Problem Identification and Resolution Annual Sample, the inspectors focused on assessment of the licensee's corrective actions taken to date and those planned from this point forward. The licensee evaluated the occurrences, determined that power range indications were related to end of core life behavior and established end of core life procedural guidance. The inspectors concluded that the licensee's actions taken in accordance with their corrective action program were reasonable given the overall safety significance of the issue. Based on the inspector's review, no concerns were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 8, 2020, the inspectors presented the integrated inspection results to Mr. J. Gebbie, Senior Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.01 Procedures 12-OHP-4022- Severe Weather 21
001-010
PMP-5055-SWM- Severe Weather Guidelines 10
001
71111.04 Procedures 1-OHL-5030- Unit 1 Tours - Unit 1 Auxiliary Tour 40
SOM-005
1-OHP-4021-003- Letdown, Charging, and Seal Water Operations 78
001
1-OHP-4030-156- East Motor Driven Auxiliary Feedwater System Test 19
017E
71111.07A Procedures 12-EHP-8913- Heat Exchange Inspection 13
001-02
Work Orders 12-EHP-8913- Unit 1 West Component Cooling Water Heat Exchanger 0
001-002 (1-HE-15W)
55509691-06 Unit 1 East Component Cooling Water Heat Exchanger 0
(1-HE-15E)
55510487-08 West Component Cooling Water Heat Exchanger 0
71111.12 Procedures 2-OHP-4030-232- AB Diesel Generator Operability Test (Train B) 062
27AB
2-OHP-4030-232- CD Diesel Generator Operability Test (Train A) 61
27CD
Work Orders 55522389-01 CD Diesel Generator 0
55532220-01 Unit 1 Reserve Auxiliary Transformer TR101CD 0
71111.13 Corrective Action AR 2020-5542 2-HV-DGS-2 Found Not Running During EDG Surveillance 0
Documents AR 2020-5542 2-HV-DGS-2 Found Not Running During EDG Surveillance 0
AR 2020-5545 Fire U2 AB EDG Room 0
AR 2020-5545 Fire U2 AB EDG room 0
Engineering EC 57627 2-HV-DGX-3 Motor Replacement 0
Changes
Miscellaneous Cook Unit 1 & 2 Online Risk Cycle 115, Week 05 07/27/2020
Risk Profile for the Week of July 27, 2020 0
Risk Profile for the Week of July 7, 2020 0
Inspection Type Designation Description or Title Revision or
Procedure Date
Cook Unit 1 & 2 Online Risk Cycle 115, Week 02 07/06/2020
Cook Nuclear Plant Key Maintenance and Testing Schedule 07/06/2020
Work Orders 55549208 Fire U2 AB Room 07/13/2020
55549287 AB EDG Room Vent Abnormal Vent Alarm Came in During 07/14/2020
Extended EDG Run
55550267 1-WRV-761 Unit 1 East ESW Strainer Outlet Valve 08/07/2020
71111.15 Calculations 2-E-N-ELCP-120- 120VAC Control Room Instrumentation Distribution (CRID) 10
Loading and Voltage Drop Analysis - Unit 2
Corrective Action AR 2020-5502 Track Unverified Assumption - Calculation 2-E-N-ELCP-120- 0
Documents 002
AR 2020-5522 Increase of Leaks on 1AB EDG Jacket Water 0
AR 2020-5860 Dirty EDG Sub-Panel Air Supply Screens 0
AR 2020-6007 Thru Wall Leak at Equalizing Line on Unit 1 East Centrifugal 0
Charging Pump
AR-2020-5534 1-HE-47-ABS EDG Aftercooler Leaking from Two Bolts 0
Engineering 0000055545-TP- Unit 2 Control Room Instrumentation Diagram Steady State 11
Changes 002 Circuit Current Recording
Miscellaneous DIT-B-00197-09 Design Information Transmittal - Area Temperature and 02/16/2000
Relative Humidity for Selected Plant Areas Outside
Containment
71111.18 Engineering EC0000057627 Replace 2-HV-DGX-3 Motor 07/22/2020
Changes
71111.19 Procedures 12-MHP-5021- Emergency Diesel Generator System Mechanical 12
2-146 Maintenance
2-OHP-4030-208- HE-17E Outlet Flow Control Valve 2-IRV-310 Stroke Test - 37
053A RHR in Service
2-OHP-4030-209- West Containment Spray System Test 43
007W
Work Orders 55530794-02 East RHR Heat Exchanger 2-IMO-312 0
55535313-21 1-HV-CLV-1A-MTR, Containment Lower Compartment Quad 06/30/2020
- 1 Vent Unit Exhaust Fan HV-CLV-1A Motor
71111.22 Procedures 1-IHP-4030-001B Train 'B' Solid State Protection System (SSPS) Automatic 13
Trip and Actuation Logic Operational Test (TADOT,
Actuation Logic Test and Master Relay Test) and Reactor
Inspection Type Designation Description or Title Revision or
Procedure Date
Trip Breaker Operational Test (TADOT)
2-OHP-4030-208- North Safety Injection Pump System Test 15
051N
2-OHP-4030-209- West Containment Spray System Test 43
007W
2-OHP-4030-232- 2CD Diesel Generator Operability Test (Train A) 07/26/2020
27D
PMP-2291-WMP- PMP-2291-WMP-001 56
001
Work Orders 55543997-01 Unit 1 - Perform Procedure 1-IHP-4030-111-01B 08/12/2020
55546678-01 West Containment Spray System Test 07/20/2020
55546679-01 2-OHP-4030-208-051N; North Safety Injection Pump System 07/28/2020
Test
55549335-01 PMP-2291-WMP-001, 4kV Bus Loss of Voltage and 4kV Bus 07/15/2020
Degraded Voltage Relay test
71114.06 Miscellaneous August 25, 2020 Emergency Planning Drill Scenario 0
71151 Miscellaneous Operational Narrative Logs (January 1, 2019 through 0
December 31, 2019)
71152 Corrective Action AR 2020-4198 AR 2020-4198; Design Basis Non-Conformance of 0
Documents Containment Penetrations CPN-16 & 47
AR 2020-5344 Unexpected Control Rod Motion in Unit 1 0
AR 2020-6007 Leak at Equalizing Line of U1 E CCP 07/29/2020
AR 2020-6043 WOs Requested for 2 to 1 Fillet Welds on CCP Balance 07/30/2020
Line
AR 2020-6603 U1 Control Rods Stepped in One Half Step 0
Miscellaneous 2020-5344 White Reactor Engineering (Verteramo) White Paper (2020-5344) 0
Paper
Work Orders 55549905-01 1-PP-50E Repair Leak at Equalizing Line on U1 CCP 07/29/2020
55549905-02 1-PP-50E Perform Leak Inspection (PMT) 07/30/2020
11