IR 05000298/2023001
| ML23101A121 | |
| Person / Time | |
|---|---|
| Site: | Cooper |
| Issue date: | 04/17/2023 |
| From: | Jeffrey Josey NRC/RGN-IV/DORS/PBC |
| To: | Dia K Nebraska Public Power District (NPPD) |
| Josey J | |
| References | |
| IR 2023001 | |
| Download: ML23101A121 (16) | |
Text
April 17, 2023
SUBJECT:
COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2023001
Dear Khalil Dia:
On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On April 10, 2023, the NRC inspectors discussed the results of this inspection with John Dent 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, Jeffrey E. Josey, Chief Projects Branch C Division of Operating Reactor Safety Docket No. 05000298 License No. DPR-46
Enclosure:
As stated
Inspection Report
Docket Number:
05000298
License Number:
Report Number:
Enterprise Identifier:
I-2023-001-0012
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
Brownville, NE
Inspection Dates:
January 1, 2023, to March 31, 2023
Inspectors:
K. Chambliss, Senior Resident Inspector
Approved By:
Jeffrey E. Josey, Chief
Projects Branch C
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Cooper Nuclear Station, 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
Type Issue Number Title Report Section Status LER 05000298/2022-003-00 Actuation of Reactor Protection System Initiates a Full Reactor Scram 71153 Closed
PLANT STATUS
Cooper Nuclear Station began the inspection period at rated thermal power. On February 10, 2023, power was lowered to approximately 60 percent for a planned rod pattern adjustment. The plant returned to rated thermal power on February 11, 2023.
The unit remained at rated thermal power for the remainder 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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather during a winter weather advisory on January 23, 2023.
- (2) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather during a winter storm warning on February 17, 2023.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)division 1 emergency diesel generator on January 11, 2023 (2)reactor equipment cooling subsystem A on February 2, 2023 (3)standby liquid control on February 22, 2023 (4)division 2 standby gas treatment on March 17, 2023
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)division 2 emergency diesel generator room, 917-foot 6-inch and 903-foot 6-inch elevations, on January 11, 2023 (2)fire pump building on January 23, 2023 (3)waste collector drain tank room on February 1, 2023 (4)intake structure, 903-feet 6-inch elevation, on February 10, 2023 (5)reactor building reactor equipment cooling area, 931-foot elevation, on February 22, 2023 (6)office building penthouse, 946-foot 11-inch elevation, on March 14, 2023
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on March 12, 2023.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the reactor building northeast quadrant on January 13, 2023.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during quarterly down power for core management on February 11, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator emergency preparedness scenario on January 13, 2023.
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)residual heat removal function PF02B near (a)(1) on January 9, 2023 (2)high pressure coolant injection function PF01 at (a)(1) on March 6, 2023
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)planned Yellow online risk during emergency diesel generator 1 maintenance window on February 1, 2023 (2)planned Yellow online risk during 4160 V bus 1F undervoltage relay testing on February 8, 2023 (3)planned Yellow online risk during reactor core isolation cooling maintenance window on March 6, 2023 (4)planned Yellow online risk during high pressure coolant injection maintenance window on March 17, 2023
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)repeated alarms for control rod drive accumulator 34-35 on January 23, 2023 (2)safety relief valve B spline nuts not replaced as planned on February 17, 2023 (3)emergency station service transformer voltage below technical specification limits on February 17, 2023 (4)two control rods failed to fully withdraw on February 17, 2023
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (8 Samples)
(1)emergency diesel generator maintenance window post-maintenance test on February 22, 2023 (2)emergency service station transformer current transformer rewiring post maintenance test on March 13, 2023 (3)reactor core isolation cooling maintenance window post maintenance test on March 14, 2023 (4)reactor core isolation cooling turbine steam supply valve refurbishment and adjustment on March 31, 2023 (5)high pressure coolant injection hydraulic actuator replacement on March 31, 2023 (6)high pressure coolant injection turbine steam supply valve refurbishment and adjustment on March 31, 2023 (7)high pressure coolant injection 250 Vdc overload relay for injection valve replacement on March 31, 2023 (8)alternate shutdown panel emergency diesel generator 2 relay post maintenance testing on March 31, 2023
Surveillance Testing (IP Section 03.01) (3 Samples)
(1)division 2 main steam isolation valve channel logic test on January 24, 2023 (2)4160 V bus undervoltage relay channel functional test on February 8, 2023 (3)service water division 2 annual pump test on February 24, 2023
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
(1)high pressure coolant injection quarterly pump vibration in-service test on January 25, 2023 (2)reactor equipment cooling biennial in-service test on January 31, 2023
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
(1)emergency preparedness drill on January 24,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) January 1, 2022, through December 31, 2022
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) January 1, 2022, through December 31, 2022
MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
- (1) January 1, 2022, through December 31, 2022
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) January 1, 2022, through December 31, 2022
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) January 1, 2022, through December 31, 2022
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
(1)adverse trend of inadequate vendor performance potentially resulting from poor vendor oversight on March 31, 2023
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 05000298/2022-003-00, "Actuation of Reactor Protection System Initiates a Full Reactor Scram," (ML23011A111). The inspection conclusions associated with this LER, and a Green, non-cited violation, are documented in Cooper Nuclear Station Integrated Inspection Report 05000298/2022004 (ML23024A125) under Inspection Results section 71153 (NCV 05000298/2022004-02). This LER is closed.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 10, 2023, the inspectors presented the integrated inspection results to John Dent and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-CNS-
23-00203, 2023-00743, 2023-00746
Procedures
5.1WEATHER
Operation During Weather Watches and Warnings
Corrective Action
Documents
CR-CNS-
2017-05597, 2021-03024, 2022-02184, 2022-06441, 2022-
06714, 2023-00113
DWG 2013,
Sheet 1
Flow Diagram Reactor Building Closed Cooling Water
System
DWG 2013,
Sheet 2
Flow Diagram Reactor Building Closed Cooling Water
System
DWG 2013,
Sheet 3
Flow Diagram Reactor Building Closed Cooling Water
System
DWG 2037
H&V Standby Gas Treatment & Off Gas Filters
DWG KSV-47-8
Diesel Generator 1 & 2 Cooling Water Schematic
DWG KSV-48-5,
Sheet 1
Starting Air Schematic
Drawings
DWG KSV-51-6
Fuel Oil Piping Schematic
2.2.20
Standby AC Power System (Diesel Generator)
115
2.2.20.1
Diesel Generator Operations
2.2.20.2
Operation of Diesel Generator from Diesel Generator
Rooms
2.2.74
Standby Liquid Control System
2.2.74A
Standby Liquid Control System Component Checklist
2.2.74B
Standby Liquid Control System Instrument Valve Checklist
2.2A.DG.DIV1
Standby AC Power System (Diesel Generator) Component
Checklist (DIV 1)
2.2A.REC.DIV0
Reactor Equipment Cooling Water System Non-Divisional
Component Checklist
2.2A.REC.DIV1
Reactor Equipment Cooling Water System Component
Checklist (DIV 1)
2.2A.RED.DIV3
Reactor Equipment Cooling Water System Common
Divisional Component Checklist
Procedures
2.2A.SGT.DIV2
Standby Gas Treatment System Component Checklist (DIV
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2)
2.2B.DG.DIV1
Standby AC Power System (Diesel Generator) Instrument
Valve Checklist (DIV 1)
2.2B.REC.DIV0
Reactor Equipment Cooling Water System Non-Divisional
Instrument Valve Checklist
2.2B.REC.DIV1
Reactor Equipment Cooling Water System Instrument Valve
Checklist (DIV 1)
2.2B.REC.DIV3
Reactor Equipment Cooling Water System Common
Divisional Instrument Valve Checklist
Corrective Action
Documents
CR-CNS-
21-00826, 2021-00881, 2021-01584, 2021-01683, 2021-
01686, 2021-02690, 2021-05349, 2021-05352, 2021-05610,
21-05786, 2022-00032, 2022-00732, 2022-00758, 2022-
01128, 2022-02378, 2022-02509, 2022-02510, 2022-02869,
22-02945, 2022-03443, 2022-03875, 2022-04609, 2022-
05105, 2022-05784, 2022-05842, 2022-06568, 2023-00024,
23-00279, 2023-01108, 2023-01109
CNS-FP-218
Reactor Building - Second Floor Elevation 931-6
CNS-FP-237
Diesel Generator Building D.G. #2 Elevations 917-6" and
903-6"
CNS-FP-256
Intake Structure Elevation 903-6
CNS-FP-257
Radwaste Building Basement Floor Elevation 877-6
CNS-FP-262
Augmented Radwaste Building Basement Floor Elevation
877-6
CNS-FP-265
Fire Protection Pump Rooms, Elevation 9036
Fire Plans
CNS-FP-269
Office Building Penthouse Elevation 956-11
Fire Brigade Scenario #12
03/07/23
Miscellaneous
NEDC 10-041
Recovery Action Feasibility Assessment Report Review
EPM Report R1006-004-005
0-BARRIER-
REACTOR
Reactor Building
Procedures
5.1INCIDENT
Site Emergency Incident
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
DWG 2038,
Sheet 1
Reactor Building Floor & Roof Drain Systems
Miscellaneous
NEDC 09-102
Internal Flooding - HELB, MELB, and Feedwater Line
Break
0-BARRIER
Barrier Control Process
0-BARRIER-
REACTOR
Reactor Building
5.1FLOOD
Flood
5.8.19
Reference Leg Injection
6.1CS.101
Core Spray Test Mode Surveillance (IST)(DIV 1)
6.RCIC.102
Alternate Level/Pressure Control
Procedures
RPV Flooding
Corrective Action
Documents
CR-CNS-
23-00476, 2023-00602
10.13
Control Rod Sequence and Movement Control
2.0.3
Conduct of Operations
106
2.1.10
Station Power Changes
23
2.2.17
Emergency Station Service Transformer
2.4PCIV
Primary Containment/Secondary Containment Isolation
Valve Failure
6.RPS.302
Main Turbine Stop Valve Closure and Steam Valve
Functional Test
RPV Control (1-3)
Procedures
Secondary Containment Control (1-3)
Corrective Action
Documents
CR-CNS-
20-00338, 2020-00354, 2020-00388, 2022-01789, 2022-
01798, 2022-06139
HPCI-PF01
Maintenance Rule Function HPCI-PF01 Performance
Criteria Basis
Miscellaneous
RHR-PF02
Maintenance Rule Function RHR-PF-02 Performance
Criteria Basis
3-CNS-DC-324
Preventative Maintenance Program
Procedures
6.HPCI.311
HPCI Turbine Trip and Initiation Logic Functional Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
6.HPCI.313
HPCI (< OR = 165 PSIG) Beginning of Cycle Test
6.HPCI.318
HPCI Simulated Actuation Test (IST)
Protected Equipment Tagout RCIC-1-WK 2309 RCIC
WORK
Protected Equipment Tagout HPCI-1-HPCI WK 2311
Protected Equipment Tagout DGA-1-DG1 Week 2305
Protected Equipment Tagout DGA-1-WK 2305 DG1 ELECT
WORK
Protected Equipment Tagout DGA-1-WK 2305 DG1 H&V
WORK
Protected Equipment Tagout DGA-1-WK 2305 DG1
MASTER HANG
Protected Equipment Tagout DGA-1-WK 2305 DG1 MECH
WORK
Protected Equipment Tagout DGA-1-1WK 2305 DG1
Clearance Order
HPCI-1-WK 2311 HPCI ELECT
Miscellaneous
Clearance Order
HPCI-1-WK 2311 HPCI MECH
0-CNS-WM-104
On-Line Schedule Risk Assessment
2.0.2
Operation Logs and Reports
23
Procedures
2.0.3
Conduct of Operations
106
Work Orders
WO 25351, 5325567, 5389881, 5441343, 5450163, 5450164,
5450218, 5450316
Corrective Action
Documents
CR-CNS-
22-00682, 2022-02263, 2022-06440, 2022-06608, 2022-
06662, 2022-06943, 2023-00034, 2023-00090, 2023-00099,
23-00505, 2023-00602, 2023-00627, 2023-00629, 2023-
01613, 2023-01616, 2023-01656
2009-23 Setpoint Change Request, Drywell High Range
Area Rad
10/02/2009
Document 950-
364
LOCA Temperature Profile Test for Victoreen, LLC Model
875 High Range Containment Monitor System
VM-0013
Model 7567F Relief & Safety Valves
Miscellaneous
VM-0023
CRD Hydraulic Control Units 729E950G1 729E950G2
29E950G3 729E950G4 729E950G5 & 729E950G6
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
VM-0903
Victoreen-Fluke Biomedical High Range Containment
Monitor 875
2.2.17
Emergency Station Service Transformer
2.4CRD
CRD Trouble
6.CRD.301
Withdrawn Control Rod Operability IST Test
6.EE.610
Off-Site AC Power Alignment
6.PRM.321
Containment High Range Area Monitor Functional Test
6.PRM.329
Containment High Range Monitors A/R/H Determination
Procedures
EPIP 5.7.1
Emergency Classification
Work Orders
Corrective Action
Documents
CR-CNS-
21-03591, 2022-05195, 2023-01187, 2023-01352
Drawings
VM-0180
Service Water Pumps
Miscellaneous
VM-0136
Start Up & Emergency Power Transformers - SSST/ESST
6.1DG.101
Diesel Generator 31 Day Operability Test (IST) (DIV 1)
6.1EE.306
4160V Bus 1F Undervoltage Relay Channel Functional Test
(DIV 1)
6.2RPS.305
MISV Channel Logic Test (DIV 2)
6.HPCI.103
6.HPCI.201
HPCI Valve Operability Test (IST)
6.MISC.401
Position Indicator Inservice Test (IST)
6.PRM.322
Containment High Range Area Monitor Channel Calibration
6.PRM.323
High Range Containment Area Monitor Victoreen 875
Source Calibration Check
6.RCIC.102
6.REC.101
REC Surveillance Operation (IST) (DIV 1)
6.SW.101
Service Water Surveillance Operation (DIV 2) (IST)
7.3.16
Low Voltage Relay Removal and Installation
7.5.6
Packing Maintenance With Diagnostics
Procedures
7.5.8
Limitorque Mechanical/Electrical Examination
Work Orders
WO 25567, 5381971, 5384507, 5384540, 5384545, 5385251,
5389145, 5389881, 5395121, 5444081, 5444270, 5444287,
5450218, 5450316, 5463262, 5463976, 5466797
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-CNS-
22-01551
2.4CRD
CRD Trouble
2.4OG
Off-Gas Abnormal
2.4PC
Primary Containment Control
2.4PCIV
Primary Containment/Secondary Containment Isolation
Valve Failure
5.1RAD
Building Radiation Trouble
5.2FUEL
Fuel Failure
5.7.1
Emergency Classification
5.7.2
Emergency Director EPIP
EOP1-A
RPV Control (1-3)
EOP3-A
Primary Containment Control (1-3)
EOP6-A
RPV Pressure/Reactor Power (Failure to Scram)
Procedures
EOP7-A
RPV Level (Failure-To-Scram)
Corrective Action
Documents
CR-CNS-
23-00565
MSPI Derivation Reports 1Q22 thru 4Q22
Miscellaneous
Operator Logs 1Q22 thru 4Q22
71151
Procedures
0-CNS-LI-114
Regulatory Performance Indicator Process
Corrective Action
Documents
CR-CNS-
20-05623, 2021-02055, 2021-02358, 2022-04299, 2022-
05548, 2022-05648, 2022-05710, 2022-05712, 2022-05783,
22-05942, 2022-06262, 2022-06491
7.0.4
Conduct of Maintenance
7.4DISASSEMBLY
Reactor Vessel Disassembly
Procedures
7.4REASSEMBLY
Reactor Vessel Reassembly
Corrective Action
Documents
CR-CNS-
22-06139, 2022-06143, 2022-06147, 2022-06154, 2023-
00397
3-CNS-DC-141
Design Inputs
6.HPCI.311
HPCI Turbine Trip and Initiation Logic Functional Test
6.HPCI.313
HPCI (< OR = 165 PSIG) Beginning of Cycle Test
Procedures
6.HPCI.318
HPCI Simulated Actuation Test (IST)
14