IR 05000285/2015301

Er 05000285/2015301; 12/07/2015 - 01/13/2016; Fort Calhoun Station; Initial Operator Licensing Examination Report

ML16020A322
Person / Time
Site:	Fort Calhoun
Issue date:	01/20/2016
From:	Vincent Gaddy Operations Branch IV
To:	Marik S Omaha Public Power District
References
50-285/15-301
Download: ML16020A322 (12)

Text

ary 20, 2016

SUBJECT:

FORT CALHOUN STATION - NRC EXAMINATION REPORT 05000285/2015301

Dear Mr. Marik:

On December 10, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator license examination at Fort Calhoun Station. The enclosed report documents the examination results and licensing decisions. The preliminary examination results were discussed on December 10, 2015, with Mr. L. Cortopassi, Vice President and Chief Nuclear Officer, and other members of your staff. A telephonic exit meeting was conducted on January 13, 2016, with Mr. M. Joe, Initial License Training Supervisor, who was provided the NRC licensing decisions.

The examination included the evaluation of three applicants for reactor operator licenses, four applicants for instant senior reactor operator licenses, and two applicants for upgrade senior reactor operator licenses. The license examiners determined that seven of the applicants satisfied the requirements of 10 CFR Part 55 and the appropriate licenses have been issued. There was one post examination comment submitted by your staff. Enclosure 1 contains details of this report and Enclosure 2 summarizes post examination comment resolution.

No findings were identified during this examination.

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 (PARS) ) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety Docket No. 50-285 License No. DPR-40

Enclosures:

1. Examination Report 05000285/2015301 w/Attachment 2. Post Examination Comment Resolution

REGION IV==

Docket: 05000285 License: DPR-40 Report: 05000285/2015301 Licensee: Omaha Public Power District Facility: Fort Calhoun Station Location: Fort Calhoun Station FC-2-4 P.O. Box 550 Fort Calhoun, NE 68023-0550 Dates: December 7, 2015, through January 13, 2016 Inspectors: C. Osterholtz, Chief Examiner, Senior Operations Engineer M. Bloodgood, Operations Engineer N. Hernandez, Resident Inspector J. Kirkland, Senior Operations Engineer Approved By: Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety-1- Enclosure 1

SUMMARY

ER 05000285/2015301; 12/07/2015 - 01/13/2016; Fort Calhoun Station; Initial Operator

Licensing Examination Report NRC examiners evaluated the competency of three applicants for reactor operator licenses, four applicants for instant senior reactor operator licenses, and two applicants for upgrade senior reactor operator licenses at Fort Calhoun Station.

The licensee developed the examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10. The written examination was administered by the licensee on December 14, 2015. NRC examiners administered the operating tests on December 7-10, 2015.

The examiners determined that seven of the applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses, as well as two denial letters, have been issued

NRC-Identified and Self-Revealing Findings

None

Licensee-Identified Violations

None

REPORT DETAILS

4OA5 Other Activities (Initial Operator License Examination)

.1 License Applications

a. Scope

NRC examiners reviewed all license applications submitted to ensure each applicant satisfied relevant license eligibility requirements. Examiners also audited two of the license applications in detail to confirm that they accurately reflected the subject applicants qualifications. This audit focused on the applicants experience and on-the-job training, including control manipulations that provided significant reactivity changes.

b. Findings

No findings were identified.

.2 Examination Development

a. Scope

NRC examiners reviewed integrated examination outlines and draft examinations submitted by the licensee against the requirements of NUREG-1021. The NRC examination team conducted an on-site validation of the operating tests.

b. Findings

NRC examiners provided outline, draft examination, and post-validation comments to the licensee. The licensee satisfactorily completed comment resolution prior to examination administration.

NRC examiners determined the written examinations and operating tests initially submitted by the licensee were within the range of acceptability expected for a proposed examination.

.3 Operator Knowledge and Performance

a. Scope

On December 14, 2015, the licensee proctored the administration of the written examinations to all none applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis and post examination comments to the NRC on December 21, 2015.

The NRC examination team administered the various portions of the operating tests to all applicants on December 7-10, 2015.

b. Findings

No findings were identified.

Eight of the nine applicants passed the written examination and eight of the nine applicants passed all portions of the operating test. The final written examinations, and post examination analysis and comments, may be accessed in the ADAMS system under the accession numbers noted in the attachment. There was one post-examination comment as indicated in the licensee submittal.

The examination team noted the following generic weakness:

• A majority of operating crews were unable to successfully isolate a raw water leak prior to exceeding component cooling water temperature reactor trip criteria limits even though there was ample time and resources to do so. The licensee generated Condition Report CR-2015-13846 to address this issue.

• A majority of senior reactor operator applicants were unable to determine that shutdown cooling discharge was unavailable with HCV-347, Shutdown Cooling Loop 2 Isolation Valve, failed closed. The licensee generated Condition Report CR-2015-13845 to address this issue.

.4 Simulation Facility Performance

a. Scope

The NRC examiners observed simulator performance with regard to plant fidelity during examination validation and administration.

b. Findings

No findings were identified.

.5 Examination Security

a. Scope

The NRC examiners reviewed examination security for examination development during both the onsite preparation week and examination administration week for compliance with 10 CFR 55.49 and NUREG-1021. Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

The chief examiner presented the preliminary examination results to Mr. L. Cortopassi, Vice President and Chief Nuclear Office, and other members of the staff on December 10, 2015.

A telephonic exit was conducted on January 13, 2016, between Mr. C. Osterholtz, Chief Examiner, and Mr. M. Joe, Initial License Training Supervisor.

The licensee did not identify any information or materials used during the examination as proprietary.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

L. Cortopassi, Site Vice President

T. Barry, Manager, Operations Services

A. Berck, Examination Author

B. Blume, Manager, Regulatory Assurance

M. Chambers, Initial License Training Instructor

S. Dean, Plant Manager

R. Hugenroth, Manager, Nuclear Oversight

M. Joe, Manager, Operations Training

R. Peter, Initial License Training Instructor

R. Rem, Initial License Training Instructor

S. Swanson, Operations Director

T. Uehling, Manager, Training

NRC Personnel

M. Schneider, Senior Resident Inspector