IR 05000483/2014301

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Er 05000483/2014301; December 8, 2014, to January 7, 2015; Callaway Plant; Initial Operator Licensing Examination Report
ML15021A562
Person / Time
Site: Callaway Ameren icon.png
Issue date: 01/21/2015
From: Vincent Gaddy
Operations Branch IV
To: Diya F
Union Electric Co
TJ Farina
References
50-483/14-301 50-483/OL-14
Download: ML15021A562 (15)


Text

January 21, 2015

SUBJECT:

CALLAWAY PLANT - NRC EXAMINATION REPORT 05000483/2014301

Dear Mr. Diya:

On December 17, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator license examination at Callaway Plant. The enclosed report documents the examination results and licensing decisions. A preliminary debrief was held on December 11, 2014, with Mr. R. Farnam, Director, Training, and other members of your staff. A telephonic exit meeting was conducted on January 7, 2015, with Mr. B. Cox, Senior Director, Nuclear Operations, who was provided the NRC licensing decisions.

The examination included the evaluation of one applicant for a reactor operator license and six applicants for instant senior reactor operator licenses. The license examiners determined that six of the seven applicants satisfied the requirements of 10 CFR Part 55 and the appropriate licenses have been issued. There were two post-examination comments 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.

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION IV

1600 E LAMAR BLVD ARLINGTON, TX 76011-4511 In accordance with 10 CFR 2.390 of the NRCs 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 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).

Sincerely,

/RA/

Vincent G. Gaddy, Chief Operations Branch

Division of Reactor Safety

Docket: 50-483 License: NPF-30

Enclosure:

Examination Report 05000483/2014301 w/Attachments:

1. Supplemental Information 2. NRC Post-Examination Comment Resolution 3. Simulator Fidelity Report

- 1 -

Enclosure

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket:

50-483 License:

NPF-30 Report:

05000483/2014301 Licensee:

Union Electric Company Facility:

Callaway Plant Location:

P.O. Box 620 Fulton, MO 65251 Dates:

December 8, 2014 to January 7, 2015 Inspectors:

T. Farina, Chief Examiner, Operations Engineer C. Osterholtz, Senior Operations Engineer T. Buchanan, Operations Engineer Approved By:

Vincent G. Gaddy Chief, Operations Branch Division of Reactor Safety

- 2 -

SUMMARY

ER 05000483/2014301; December 8, 2014, to January 7, 2015; Callaway Plant; Initial Operator

Licensing Examination Report.

NRC examiners evaluated the competency of one applicant for a reactor operator license, and six applicants for instant senior reactor operator licenses at Callaway Plant.

The licensee developed the examinations using NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1. The written examination was administered by the licensee on December 17, 2014. NRC examiners administered the operating tests on December 8-11, 2014.

The examiners determined that six of the seven applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.

NRC-Identified and Self-Revealing Findings

None

Licensee-Identified Violations

None

REPORT DETAILS

OTHER ACTIVITIES (OA)

4OA5 Other Activities (Initial Operator License Examination)

.1 License Applications

a. Inspection Scope

NRC examiners reviewed all license applications submitted to ensure each applicant satisfied relevant license eligibility requirements. Examiners also audited all 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. Inspection 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 onsite 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. Inspection Scope

On December 17, 2014, the licensee proctored the administration of the written examinations to all seven applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis and post-examination comments to the NRC on December 23, 2014.

The NRC examination team administered the various portions of the operating tests to all applicants on December 8-11, 2014.

b. Findings

No findings were identified.

Six of seven applicants passed the written examination and all applicants passed all parts of the operating test. The final written examinations, post-examination analysis, and comments may be accessed in the ADAMS system under the accession numbers (ML) noted in the attachment.

The examination team noted one generic weakness associated with applicant performance on the dynamic scenario section of the operating tests. Specifically, two out of three crews failed to recognize entry conditions for off-normal Procedure OTO-BB-00005, RCS High Activity. One of the entry conditions is Dose equivalent I-131 greater than 60 µCi/gm OR rising [emphasis added]. When presented with an I-131 reading of less than 60 µCi/gm but rising, these crews failed to enter OTO-BB-00005. Copies of all individual examination reports were sent to the facility training manager for evaluation and determination of appropriate remedial training.

.4 Simulation Facility Performance

a. Inspection Scope

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

b. Findings

No findings were identified at this time. However, the examination team noted what appeared to be a repeat simulator anomaly in that an automatic safety injection signal was being generated on low pressurizer pressure and low steamline pressure following an anticipated transient without scram (ATWS) and a manually induced reactor trip.

There was no Loss of Coolant or Excess Steam Demand event in progress. A similar, if not identical, issue was identified by the NRC in 2011 and documented as a Green non-cited violation of 10 CFR Part 55.46(c), Plant-Referenced Simulators (NCV 05000483/2011005-02, Failure to Maintain Simulator Fidelity). The NRC intends to evaluate the licensees response to this issue further, following relaxation of examination security as part of the planned 2015 biennial requalification inspection.

The licensee documented this issue in Condition Report (CR) 201409327.

Additionally, the simulator demonstrated an unexpected response to a rapid cycling of the rod control switch in manual. Specifically, during an ATWS event, simulator records showed that an operator rapidly cycled the rod control switch in, out, and in, in less than a second. Due to the speed with which this action occurred and the simulator programming design, this resulted in the simulator seeing simultaneous insert and withdraw signals, which resulted in a Rod Control Urgent Failure Alarm, preventing any control rod motion. Per the system engineer, actual plant design would not have given a Rod Control Urgent Failure Alarm under these conditions, as the buffer memory card associated with rod control inhibits additional input while rod motion is in progress. The licensee documented this issue in Simulator Information Formal Tracking (SIFT)

Number 20140094.

.5 Examination Security

a. Inspection 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 conducted a preliminary debrief with Mr. R. Farnam, Director, Training, and other members of the staff on December 11, 2014. A telephonic exit was conducted on January 7, 2015, between Mr. Thomas Farina, Chief Examiner, and Mr. Barry Cox, Senior Director, Nuclear Operations.

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

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

M. Covey, Manager - Operations Support
M. Otten, Exam Group Supervisor
L. Morgan, Exam Writer

NRC Personnel

T. Hartman, Senior Resident Inspector

ADAMS DOCUMENTS REFERENCED