IR 05000298/2023001

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Integrated Inspection Report 05000298/2023001
ML23101A121
Person / Time
Site: Cooper Entergy icon.png
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:

DPR-46

Report Number:

05000298/2023001

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

71111.01

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

71111.04

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

71111.05

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

RCIC IST and 92 Day Test

EOP-1B

Alternate Level/Pressure Control

71111.06

Procedures

EOP-2B

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

EOP-1A

RPV Control (1-3)

71111.11Q

Procedures

EOP-5A

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

71111.12

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

MEGGER LO HTR

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

71111.13

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

71111.15

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

WO 5381585

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

HPCI IST and 92 Day Test Mode

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

RCIC IST And 92 Day Test

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

71111.24

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)

71114.06

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

71152S

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

71153

Procedures

6.HPCI.318

HPCI Simulated Actuation Test (IST)

14