ML051810170

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IR 05000298-05-002 - Errata for Cooper Nuclear Station NRC Integrated Inspection Report
ML051810170
Person / Time
Site: Cooper Entergy icon.png
Issue date: 06/29/2005
From: Kennedy K
NRC/RGN-IV/DRP
To: Edington R
Nebraska Public Power District (NPPD)
References
IR-05-002
Download: ML051810170 (6)
v • d • e


See also: IR 05000298/2005002

Text

June 29, 2005

Randall K. Edington, Vice

President-Nuclear and CNO

Nebraska Public Power District

P.O. Box 98

Brownville, NE 68321

SUBJECT: ERRATA FOR COOPER NUCLEAR STATION - NRC INTEGRATED

INSPECTION REPORT 05000298/2005002

Dear Mr. Edington:

Please remove enclosure page 29 and attachment page A-2 from NRC Integrated Inspection

Report 05000298/2005002 and replace with the pages enclosed with this letter. The purpose of

the change is to correct the tracking number of the noncited violation (NCV) for Inadequate

Instructions for Restoration of the Service Water System Following Maintenance, documented

in Section 4OA5 of the inspection report.

In accordance with 10 CFR 2.390 of the NRC's Rules of Practice, a copy of this letter and its

enclosure will be made available electronically for public inspection in the NRC Public

Document Room or from the Publicly Available Records (PARS) component of NRCs

document system (ADAMS). ADAMS is accessible from the NRC Web site at

http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Should you have any questions concerning this inspection, we will be pleased to discuss them

with you.

Sincerely,

/RA/ by Wayne C. Walker acting for

Kriss M. Kennedy, Chief

Project Branch C

Division of Reactor Projects

Docket: 50-298

License: DPR-46

Enclosure:

Replacement pages to NRC Inspection

Report 05000298/2005002 and

Supplemental Information attachment

Nebraska Public Power District -2-

cc w/enclosure:

Michael T. Boyce, Nuclear Asset Manager

Nebraska Public Power District

1414 15th Street

Columbus, NE 68601

John C. McClure, Vice President

and General Counsel

Nebraska Public Power District

P.O. Box 499

Columbus, NE 68602-0499

P. V. Fleming, Licensing Manager

Nebraska Public Power District

P.O. Box 98

Brownville, NE 68321

Michael J. Linder, Director

Nebraska Department of

Environmental Quality

P.O. Box 98922

Lincoln, NE 68509-8922

Chairman

Nemaha County Board of Commissioners

Nemaha County Courthouse

1824 N Street

Auburn, NE 68305

Sue Semerena, Section Administrator

Nebraska Health & Human Services

Dept. of Regulation & Licensing

Division of Public Health Assurance

301 Centennial Mall, South

P.O. Box 95007

Lincoln, NE 68509-5007

Mike Wells, Deputy Director

Missouri Department of Natural Resources

P.O. Box 176

Jefferson City, MO 65101

Director, Missouri State Emergency

Management Agency

P.O. Box 116

Jefferson City, MO 65102-0116

Nebraska Public Power District -3-

Chief, Radiation and Asbestos

Control Section

Kansas Department of Health

and Environment

Bureau of Air and Radiation

1000 SW Jackson, Suite 310

Topeka, KS 66612-1366

Daniel K. McGhee

Bureau of Radiological Health

Iowa Department of Public Health

Lucas State Office Building, 5th Floor

321 East 12th Street

Des Moines, IA 50319

William J. Fehrman, President

and Chief Executive Officer

Nebraska Public Power District

1414 15th Street

Columbus, NE 68601

Jerry C. Roberts, Director of

Nuclear Safety Assurance

Nebraska Public Power District

P.O. Box 98

Brownville, NE 68321

Chief Technological Services Branch

National Preparedness Division

Department of Homeland Security

Emergency Preparedness & Response Directorate

FEMA Region VII

2323 Grand Boulevard, Suite 900

Kansas City, MO 64108-2670

Nebraska Public Power District -4-

Electronic distribution by RIV:

Regional Administrator (BSM1)

DRP Director (ATH)

DRS Director (DDC)

DRS Deputy Director (vacant)

Senior Resident Inspector (SCS)

Branch Chief, DRP/C (KMK)

Senior Project Engineer, DRP/C (WCW)

Team Leader, DRP/TSS (RLN1)

RITS Coordinator (KEG)

RidsNrrDipmIipb

DRS STA (DAP)

J. Dixon-Herrity, OEDO RIV Coordinator (JLD)

RidsNrrDipmIipb

CNS Site Secretary (SLN)

W. A. Maier, RSLO (WAM)

SISP Review Completed: _wcw___ ADAMS: : Yes G No Initials: __wcw_____

Publicly Available G Non-Publicly Available G Sensitive  : Non-Sensitive

R:\_REACTORS\_CNS\2005\CN2005-02RP Errata.wpd

RIV:PE:DRP/C C:DRP/C

RVAzua;df KMKennedy

WCWalker for WCWalker for

6/29/05 6/29/05

OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

-29-

NRC transmitted its final conclusion regarding the safety significance of this event. The

letter stated that the finding is of very low safety significance (Green) and that this

apparent violation is being treated as a noncited violation, consistent with Section VI.A

of the Enforcement Policy (NCV 05000298/2005002-10: Inadequate Instructions for

Restoration of the Service Water System Following Maintenance). This apparent

violation is closed.

4OA6 Meetings, Including Exit

On January 28, 2005, the inspectors presented the inspection results regarding access

to radiologic significant areas and inservice inspection to R. Edington, Vice President,

and other members of his staff who acknowledged the findings.

On April 14, 2005, the inspectors presented the results of the resident inspector

activities to Mr. S. Minahan and other members of his staff who acknowledged the

findings.

The inspectors confirmed that proprietary information was not provided or examined

during the inspection.

40A7 Licensee-Identified Violations

The following violation of very low significance (Green) was identified by the licensee

and is a violation of NRC requirements which meet the criteria of Section VI of the

NRC Enforcement Policy, NUREG-1600, for being dispositioned as an NCV.

valves in the heating and ventilation system did not have position limit switches

and associated equipment that could support environmental qualification under

10 CFR 50.49 requirements. Based upon a new radiation analysis, it was

determined that these limit switches could be exposed to a more harsh

environment than previously considered. The licensee determined the switches

would need to be replaced to comply with 10 CFR 50.49 requirements. This NCV

was considered to have very low safety significance because the position limit

switches do not adversely affect the safety function of the valves.

sign or signs bearing the radiation symbol and the words "CAUTION, RADIATION

AREA. However, on December 11, 2004, a radiation protection technician found

an unposted area outside the RHR B heat exchanger room with general area dose

rates of 7 millirem per hour. This same dose rate had been previously identified

on November 29, 2004, but the radiation protection staff did not post the area as

required. Consequently, the radiation area outside the RHR B heat exchanger

room remained unposted for 11 days. Using the Occupational Radiation Safety

Significance Determination Process, the inspector determined that the finding was

of very low safety significance because it was not an ALARA finding, there was no

Enclosure

Opened and Closed

05000298/2005002-01 FIN Inadequate Maintenance Resulted in Failure of Reactor

Protection System Power Supply (1R12)05000298/2005002-02 NCV Failure to Implement Emergency Plan During a Fire (1R14)05000298/2005002-03 NCV Failure to Follow Operability Determination

Procedure (1R15)05000298/2005002-04 NCV Failure to Conspicuously Post and Barricade Two Areas in

the Drywell as Locked High Radiation Area in Accordance

with TS 5.7.2 (2OS1.1)05000298/2005002-05 NCV Failure to Perform an Adequate Survey to Evaluate

Radiological Hazards per 10 CFR 20.1501 (2OS1.2)05000298/2005002-06 NCV Failure to Gain Authorized Access to a High Radiation Area

in Accordance with TS 5.7.1 (2OS1.3)05000298/2005002-10 NCV Inadequate Instructions for Restoration of the SW System

Following Maintenance (4OA5)

Closed

05000298/2004004-00 LER Loss of Safety Function Due to Past Inoperabilities of HPCI

system (4OA3.1)05000298/2004014-01 AV Inadequate Instructions for Restoration of the SW System

Following Maintenance (4OA5)

LIST OF DOCUMENTS REVIEWED

Section 1R08: Inservice Inspection Activities

Procedures

3.28, Inservice Inspection and Testing Programs, Revision 20

3.28.1, Inservice Inspection Program Implementation, Revision 9

54-ISI-124-02, Ultrasonic Examination of Ferritic Piping Welds and Vessel Welds Two Inches

or Less in Thickness, Revision 2

54-ISI-130-41, Procedure for the Remote Ultrasonic Examination of BWR Core Shroud

Assembly Seam Welds, Revision 37

54-ISI-135-05, Linearity and Beam Spread Measurements, Revision 5

A-2 Attachment

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