IR 05000285/2006003

IR 05000285-06-003 on 04/01/2006 - 06/30/2006 for Fort Calhoun Station, Integrated Resident and Regional Report; Adverse Weather Protection, Fire Protection, Operator Performance During Nonroutine Evolutions and Events, Event Follow-up

ML062190495
Person / Time
Site:	Fort Calhoun
Issue date:	08/04/2006
From:	Graves D NRC/RGN-IV/DRP/RPB-E
To:	Ridenoure R Omaha Public Power District
References
IR-06-003
Download: ML062190495 (45)

Text

August 4, 2006

SUBJECT:

FORT CALHOUN STATION - NRC INTEGRATED INSPECTION REPORT 05000285/2006003

Dear Mr. Ridenoure:

On June 30, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Fort Calhoun Station. The enclosed integrated inspection report documents the inspection findings, which were discussed on July 7, 2006, with Mr. Jeff Reinhart, Site Director, and other members of your staff.

The inspections examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

This report documents three NRC-identified findings and one self-revealing finding that were evaluated under the risk significance determination process as having very low safety significance (Green). The NRC has also determined that three violations are associated with these issues. These violations are being treated as noncited violations (NCVs), consistent with Section VI.A of the Enforcement Policy. The NCVs are described in the subject inspection report. If you contest the violations or significance of the NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.

20555-0001, with copies to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011-4005; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555-0001; and the NRC Resident Inspector at the Fort Calhoun Station facility.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, and its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records 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).

Omaha Public Power District

- 2 -

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

Sincerely,

/RA/

David N. Graves, Chief Project Branch E Division of Reactor Projects Docket: 50-285 License: DPR-40

Enclosure:

NRC Inspection Report 05000285/2006003 w/Attachment: Supplemental Information

REGION IV==

Docket:

50-285 License:

DPR-40 Report:

05000285/2006003 Licensee:

Omaha Public Power District Facility:

Fort Calhoun Station Location:

Fort Calhoun Station FC-2-4 Adm.

P.O. Box 399, Highway 75 - North of Fort Calhoun Fort Calhoun, Nebraska Dates:

April 1 through June 30, 2006 Inspectors:

J. Hanna, Senior Resident Inspector L. Willoughby, Resident Inspector G. Werner, Senior Project Engineer R. Lantz, Senior Emergency Preparedness Inspector G. Pick, Senior Reactor Inspector, Engineering S. Alferink, Reactor Inspector, Engineering K. Clayton, Operations Engineer Approved By:

David N. Graves, Chief, Project Branch E Division of Reactor Projects

Enclosure-2-

SUMMARY OF FINDINGS

.................................................... 3

REPORT DETAILS

REACTOR SAFETY

......................................................... 6 1R01 Adverse Weather Protection....................................... 6 1R04 Equipment Alignments............................................ 8 1R05 Fire Protection.................................................. 9 1R06 Flood Protection Measures....................................... 12 1R07 Heat Sink Performance.......................................... 12

1R11 Licensed Operator Requalification Program.......................... 13

1R12 Maintenance Effectiveness....................................... 15

1R13 Maintenance Risk Assessments and Emergent Work Control............. 15 1R14

Operator Performance During Nonroutine Evolutions and Events.......... 16 1R15 Operability Evaluations.......................................... 18 1R19 Post-maintenance Testing........................................ 19 1R20 Refueling and Other Outage Activities............................... 20

1R22 Surveillance Testing

............................................ 20

1R23 Temporary Plant Modifications

.................................... 21 1EP2 Alert Notification System Testing................................... 22 1EP3 Emergency Response Organization Augmentation Testing

.............. 22 1EP4 Emergency Action Level and Emergency Plan Changes................. 23 1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies..... 24 1EP6 Drill Evaluation

OTHER ACTIVITIES

........................................................ 25

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

................................................ A-1

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

........................... A-1

LIST OF DOCUMENTS REVIEWED

.......................................... A-2