IR 05000285/2004002

IR 05000285-04-002 and IR 05000285-04-003 Errata; Omaha Public Power District; Fort Calhoun Station

ML050340011
Person / Time
Site:	Fort Calhoun
Issue date:	02/02/2005
From:	Hay M NRC/RGN-IV/DRP/RPB-C
To:	Ridenoure R Omaha Public Power District
References
EA-04-078 IR-04-002, IR-04-003
Download: ML050340011 (8)

Text

ary 2, 2005

SUBJECT:

ERRATA FOR FORT CALHOUN NUCLEAR STATION, NRC INTEGRATED INSPECTION REPORTS 05000285/2004002 AND 05000285/2004003

Dear Mr. Ridenoure:

Please add Section 1R11, Licensed Operator Requalification (Enclosure 1), to NRC Inspection Report 05000285/2004002 dated May 14, 2004. Also please add Section 1EP4, Emergency Action Level and Emergency Plan Changes, and Section 4OA6, Meetings, Including Exit (Enclosure 2), to NRC Inspection Report 05000285/2004003 dated August 11, 2004. The purpose of this change is to provide information that was inadvertently omitted from the Report Details section of these two reports.

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/

Michael C. Hay, Chief Project Branch C Division of Reactor Projects Docket: 50-285 License: DPR-40

Omaha Public Power District -2-

Enclosures:

Erratas of NRC Inspection Reports 05000285/2004002 and 05000285/2004003

REGION IV==

Docket No.: 50-285 License No.: DPR-40 Report No.: 05000285/2004002 Licensee: Omaha Public Power District Facility: Fort Calhoun Station Location: Fort Calhoun Station FC-2-4 Adm.

P.O. Box 399, Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska Date: February 4, 2004 Inspector: T. O. McKernon, Senior Operations Engineer Approved By: Anthony T. Gody, Chief, Operations Branch Division of Reactor Safety

REPORT DETAILS 1R11 Licensed Operator Requalification (71111.11B)

.1 Biennial Inspection a. Inspection Scope The inspector reviewed the annual operating examination test results for 2003. Since this was the first half of the biennial requalification cycle, the licensee had not yet administered the written examination. These results were assessed to determine if they were consistent with NUREG 102, "Operator Licensing Examination Standards for Power Reactors," Revision 8, Supplement 1, guidance and Manual Chapter 0609, Appendix I, "Operator Requalification Human Performance Significance Determination Process," requirements. This review included examination of test results for a total of 51 licensed operators, which included shift-standing senior operators, staff senior operators, shift-standing reactor operators, and staff reactor operators.

b. Findings No findings of significance were identified.

Licensee D. Weaver, Operations Training Supervisor

ENCLOSURE 2 U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket No.: 50-285 License No.: DPR-40 Report No.: 05000285/2004003 Licensee: Omaha Public Power District Facility: Fort Calhoun Station Location: Fort Calhoun Station FC-2-4 Adm.

P.O. Box 399, Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska Date: June 3, 2004 Inspector: Ryan E. Lantz, Senior Emergency Preparedness Inspector Approved By: Anthony T. Gody, Chief, Operations Branch Division of Reactor Safety

REPORT DETAILS 1. Reactor Safety 1EP4 Emergency Action Level and Emergency Plan Changes (71114.04)

a. Inspection Scope The inspector performed an in-office review of Revision 11 to Section L, "Medical and Public Health Support," of the Fort Calhoun Station Radiological Emergency Response Plan, submitted January 12, 2004. The revision updated the location of the radiation health center.

The revision was compared to the previous revisions; to the criteria of NUREG-0654,

"Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," Revision 1; and to the requirements of 10 CFR 50.47(b) and 50.54(q) to determine if the revisions decreased the effectiveness of the plan. The inspector completed one sample during the inspection.

b. Findings No findings of significance were identified.

4. Other Activities 40A6 Meetings, Including Exit The inspector conducted an exit interview by telephone on June 3, 2004, and presented the inspection results to Mr. C. Simmons, Emergency Preparedness Supervisor. The inspector confirmed that proprietary information was not provided or examined during the inspection.