IR 05000298/2017007

NRC Design Bases Assurance Inspection (Programs) Report 05000298/2017007

ML17277A291
Person / Time
Site:	Cooper
Issue date:	10/03/2017
From:	Thomas Farnholtz Region 4 Engineering Branch 1
To:	Dent J Nebraska Public Power District (NPPD)
References
IR 2017007
Download: ML17277A291 (14)

Text

ber 3, 2017

SUBJECT:

COOPER NUCLEAR STATION - NRC DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) REPORT 05000298/2017007

Dear Mr. Dent:

On August 31, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. NRC inspectors discussed the results of this inspection with Mr. J.

Kalamaja, General Manager-Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings 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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Thomas R. Farnholtz, Branch Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-298 License No. DPR-46

Enclosure:

Inspection Report 05000298/2017007 w/Attachment: Supplemental Information

REGION IV==

Docket: 05000298 License: DPR-46 Report Nos.: 05000298/2017007 Licensee: Nebraska Public Power District Facility: Cooper Nuclear Station Location: 72676 648A Ave Brownville, NE Dates: August 14 through August 31, 2017 Team Leader: G. George, Senior Reactor Inspector, Engineering Branch 1 Inspectors: R. Latta, Senior Reactor Inspector, Engineering Branch 1 W. Smith, Reactor Inspector, Engineering Branch 1 Approved By: Thomas R. Farnholtz, Branch Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

IR 05000298/2017007; 08/14/2017 - 08/31/2017; COOPER NUCLEAR STATION; Inspection

Procedure 7111121N, Design Bases Assurance (Programs)

This inspection was performed between August 14, 2017, and August 31, 2017, by three inspectors from the NRCs Region IV office. No findings were identified during this inspection. The significance of inspection findings is indicated by their color (Green, White,

Yellow, or Red), which is determined using Inspection Manual Chapter 0609, Significance Determination Process. Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, Aspects Within the Cross-Cutting Areas. Violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.

No findings were identified.

REPORT DETAILS

1R21 N Design Basis Assurance Inspection (Programs)

a. Inspection Scope

The inspection team performed an inspection as outlined in NRC Inspection Procedure 71111.21N, Attachment 1, Environmental Qualification under 10 CFR 50.49 Programs, Processes, and Procedures. The team assessed Cooper Nuclear Stations implementation of the environmental qualification program as required by 10 CFR 50.49, Environmental qualification of electric equipment important to safety for nuclear power plants. The team evaluated whether Cooper Nuclear Station staff properly maintained the environmental qualification of electrical equipment important to safety throughout plant life, established and maintained required environmental qualification documentation records, and implemented an effective corrective action program to identify and correct environmental qualification-related deficiencies.

The inspection included review of environmental qualification program procedures, component environmental qualification files, environmental qualification test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, and calculations. The team interviewed program owners, engineers, maintenance staff, and warehouse staff. The team performed in-plant walkdowns (where accessible) to verify equipment was installed in its qualified configuration as described in Cooper Nuclear Stations environmental qualification component documentation files. Additionally, the team performed in-plant walkdowns to determine whether equipment surrounding the components could fail in a manner that could prevent the safety functions of the components and to verify that components located in areas susceptible to a high energy line break were properly evaluated for operation in a harsh environment. The team inspected the storage of replacement parts and associated procurement records to verify environmental qualification parts approved for installation in the plant were properly identified and controlled, and that storage and environmental conditions did not adversely affect the components qualified lives.

Documents reviewed for this inspection are listed in the attachment.

The inspection procedure requires the team to select 6 to 10 components to assess the adequacy of the environmental qualification program. The team selected 10 components for this inspection. Component samples selected for this inspection are listed below:

• CNS-0-PC-PENT-X101E, Electrical Cable Penetration, Imaging and Sensing Technology Type NY 10275

• CNS-0-MS-TS-123D, Main Steam Leak Detection Temperature Switch, EGS/Fenwal Model 01-170020-090

• CNS-1-EE-PNL-AA3, 125 V dc Electric Control Power Distribution Panel Board, General Electric Model QMR

• CNS-0-EE-PNL-CA, 125 V dc Electric Distribution Panel, Hatch Inc.,

Model V2B221LR

• CNS-1-SW-MO-MO89A, Service Water Discharge Valve Motor, Limitorque Model SMB-3

• CNS-2-NBI-PIS-52B, Reactor Pressure Switch, Barton Model 288A

• CNS-2-RHR-MOT-RHRP1D, Residual Heat Removal Pump D Motor, General Electric Model 5K6346XC74A/5K6339XXC185A

• CNS-1-MS-LMS-AO80CA, Main Steam Isolation Valve Open Indication Limit Switch, NAMCO Model EA180-32402

• CNS-1-RHR-MO-MO34A, Residual Heat Removal Torus Loop Inboard Throttle Valve Motor, Limitorque Model SMB-4

• CNS-2-EE-MCC-RB, 480 VAC Distribution Center, ITE Gould Model 9600

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

Exit Meeting Summary

On August 31, 2017, the inspectors presented the inspection results to Mr. J. Kalamaja, General Manager, Plant Operations, and other members of the licensee staff. The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

A. Able, Supervisor, Design Engineering

V. Balanskas, Director/Chief Engineer, Entergy Operations, Inc.

D. Buman, Director, Nuclear Safety Assurance

L. Dewhirst, Manager, Corrective Actions and Assessments

K. Dia, Director, Engineering

R. Dia, Supervisor, Design Engineering

R. Estrada, Program Manager, Nuclear Oversight

M. Ferguson, Supervisor, Materials Purchasing and Controls

J. Grauerholz, Administrative Assistant, Design Engineering

J. Houston, Manager, Production

C. Johnson, Engineer, Design Engineering

J. Kalamaja, General Manager, Plant Operations

D. Kirkpatrick, Leader, Performance Assessment, Quality Assurance

C. Pelchat, Manager, Nuclear Projects

K. Porter, Manager, Business Services

J. Reimers, Manager, System Engineering

J. Shaw, Manager, Licensing

P. Tetrick, Manager, Operations

K. Tom, Assistant to Director, Engineering

M. Unruh, Senior Engineer, Engineering Programs and Components

D. Van Der Kamp, Technical Specialist, Licensing

M. Van Winkle, Acting Manager, Design Engineering

J. Wilson, Engineer, Design Engineering

R. Wise, EQ Subject Matter Expert, Centech

NRC Personnel

C. Jewett, Acting Resident Inspector

P. Voss, Senior Resident Inspector