IR 05000324/2014301

Er 05000325/2014301 and Er 05000324/2014301; Operating Test October 6 - 14, 2014, & Written Exam October 21, 2014; Brunswick Steam Electric Plant, Units 1 & 2; Operator License Examinations

ML14323A888
Person / Time
Site:	Brunswick
Issue date:	11/19/2014
From:	Gerald Mccoy Division of Reactor Safety II
To:	Hamrick G Duke Energy Carolinas
References
ER 2014301
Download: ML14323A888 (9)

Text

UNITED STATES ber 19, 2014

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT - NRC EXAMINATION REPORT 05000325/2014301 AND 05000324/2014301

Dear Mr. Hamrick:

During the period of October 6 - 14, 2014, the Nuclear Regulatory Commission (NRC)

administered operating tests to employees of your company who had applied for licenses to operate the Brunswick Steam Electric Plant. At the conclusion of the tests, the examiners discussed preliminary findings related to the operating tests with those members of your staff identified in the enclosed report. The written examination was administered by your staff on October 21, 2014.

All applicants passed both the operating test and written examination. There were no post-administration comments concerning the written examination.

The initial examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and your staff were made according to NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1.

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room).

If you have any questions concerning this letter, please contact me at (404) 997-4551.

Sincerely,

/RA: Eugene F. Guthrie for/

Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety Docket Nos: 50-325, 50-324 License Nos: DPR-71, DPR-62

Enclosures:

1. Report Details 2. Simulator Fidelity Report

REGION II==

Docket No.: 05000325, 05000324 License No.: DPR-71, DPR-62 Report No.: 05000325/2014301 and 05000324/2014301 Licensee: Duke Energy Progress, Inc.

Facility: Brunswick Steam Electric Plant, Units 1 and 2 Location: Southport, NC Dates: Operating Tests - October 6 - 14, 2014 Written Examination - October 21, 2014 Examiners: P. Capehart, Chief Examiner B. Caballero, Senior Operations Engineer A. Goldau, Operations Engineer Approved by: Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety Enclosure 1

SUMMARY OF FINDINGS ER 05000325/2014301 and ER 05000324/2014301; operating test October 6 - 14, 2014, &

written exam October 21, 2014; Brunswick Steam Electric Plant, Units 1 & 2; Operator License Examinations.

Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in accordance with the guidelines in Revision 9, Supplement 1, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable.

Members of the Brunswick training staff developed both the operating tests and the written examination. The NRC developed the written examination outline.

The NRC administered the operating tests during the period of October 6 - 14, 2014. The Brunswick training staff administered the written examination on October 21, 2014. Four Reactor Operators (RO) and seven Senior Reactor Operators (SRO) applicants passed both the operating test and written examination. All applicants were issued licenses commensurate with the level of examination administered.

There were no post-examination comments.

No findings were identified.

REPORT DETAILS 4. OTHER ACTIVITIES 4OA5 Operator Licensing Examinations a. Inspection Scope Members of the Brunswick training staff developed both the operating tests and the written examination. All examination material was developed in accordance with the guidelines contained in Revision 9, Supplement 1, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." The NRC examination team reviewed the proposed examination. Examination changes agreed upon between the NRC and the licensee were made per NUREG-1021, and incorporated into the final version of the examination materials.

The NRC reviewed the licensees examination security measures while preparing and administering the examinations in order to ensure compliance with 10 CFR §55.49, Integrity of examinations and tests.

The NRC examiners evaluated four RO and seven SRO applicants using the guidelines contained in NUREG-1021. The examiners administered the operating tests during the period of October 6 - 14, 2014. Members of the Brunswick training staff administered the written examination on October 21, 2014. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses to operate the Brunswick Steam Electric Plant, met the requirements specified in 10 CFR Part 55, Operators Licenses.

b. Findings No findings were identified. The NRC determined, using NUREG-1021, that the licensees initial examination submittal was within the range of acceptability expected for a proposed examination.

All applicants passed both the operating test and written examination and were issued licenses.

Copies of all individual examination reports were sent to the Training Manager for evaluation and determination of appropriate remedial training.

The licensee submitted no post-examination comments concerning the written examination. A copy of the final RO written examination and answer key, final SRO written examination and answer key, with all changes incorporated, may be accessed not earlier than October 4, 2016, in the ADAMS system (ADAMS Accession Numbers ML14316A366 and ML14316A391).

4OA6 Meetings, Including Exit Exit Meeting Summary On October 13, 2014, the NRC examination team discussed generic issues associated with the operating test with you and members of the Brunswick Steam Electric Plant staff. The examiners asked the licensee if any of the examination material was proprietary. No proprietary information was identified.

KEY POINTS OF CONTACT Licensee Personnel M. Similey, Superintendent of Operator Training B. Bolin, Exam Writer L. Sosler, Exam Writer F. Jefferson, Engineer Manager J. Barry, Simulator Supervisor J. Angel, Operator Training Supervisor J. Kalamaja, Operations Manager A. Padleckas, Shift Operations Manager L. Grzeck, Regulatory Affairs Manager S. Braown, NOS Manager J. Krakuszeki, Plant Manager

SIMULATOR FIDELITY REPORT Facility Licensee: Brunswick Steam Electric Plant Facility Docket No.: 05000325 and 05000324 Operating Tests Administered on: October 6 - 14, 2014 This form is to used only to report observations. This observation does not constitute audit or inspection findings and, without further verification and review in accordance with Inspection Procedure 71111.11, is not indicative of noncompliance with 10 CFR 55.46. No licensee action is required in response to these observations.

While conducting the simulator portion of the operating test, examiners observed the following:

Item Description Inadequate labeling of H2- 2OP-15, SAMPLING SYSTEM OPERATING PROCEDURE, step O2 monitor 8.1.2.1.A states to ensure H2-O2 monitor, CAC-AT-4410 (CAC-AT4410) is in OFF. This step should be enhanced to add that this step is performed on the XU-51 panel to prevent the confusion of placing the 4409/4410 power to OFF on the XU-75/79 panel. PR-713615 written to document this issue.

Alarm Panel Procedure 2APP-A-06 contains action steps that reference the wrong directs operators to wrong procedure sections for OP-02. The procedure was revised to the procedure section new Duke format and the APP actions were not revised to the new procedure sections from the format change. This issue is addressed as part of PR-713615 and has been previously addressed by PR-690669 during the 2013 NRC exam.

Improper labeling of drip An Engineering Change Request (ECR) has been submitted to drain valves for CRD have the names of the Drain Isolation Valves for both unit CRD pumps pumps changed to Drip Tray Drain Valves, or something more descriptive. The ECR number is 17561.

Enclosure 2