IR 05000369/2005301

NRC Examination Report 05000369-05-301 and 05000370-05-301

ML050810093
Person / Time
Site:	Mcguire, McGuire
Issue date:	03/21/2005
From:	Moorman J Division of Reactor Safety II
To:	Gordon Peterson Duke Energy Corp
References
50-369/05-301, 50-370/05-301
Download: ML050810093 (8)

Text

rch 21, 2005

SUBJECT:

MCGUIRE NUCLEAR STATION - NRC EXAMINATION REPORT 05000369/2005301 AND 05000370/2005301

Dear Mr. Peterson:

During the period February 7-15, 2005, the Nuclear Regulatory Commission (NRC)

administered operating examinations to employees of your company who had applied for licenses to operate the McGuire Nuclear Station. At the conclusion of the examination, the examiners discussed the examination questions and preliminary findings with those members of your staff identified in the enclosed report. The written examination was administered by your staff on February 18, 2005.

All applicants passed both the written examination and operating test. A Simulation Facility Report is included in this report as Enclosure 2. There were no post examination comments.

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 NRC's 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 letter, please contact me at (404) 562-4647.

Sincerely,

/RA/

James H. Moorman, III, Chief Operator Licensing Branch Division of Reactor Safety Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17

Enclosures:

(See page 2)

DEC 2 Enclosures: 1. Report Details 2. Simulation Facility Report

REGION II==

Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17 Report No.: 05000369/2005301 and 05000370/2005301 Licensee: Duke Energy Corporation Facility: McGuire Nuclear Station Location: 12700 Hagers Ferry Road Huntersville, NC 28078-8985 Dates: Operating Tests - February 7-15, 2005 Written Examination - February 18, 2005 Examiners: G. Hopper, Chief License Examiner S. Rose, Senior Operations Engineer T. Kolb, Operations Engineer Approved by: James H. Moorman, III, Chief Operator Licensing Branch Division of Reactor Safety Enclosure 1

SUMMARY OF FINDINGS ER 05000369/2005301, ER 05000370/2005301; 2/7-15/2005; McGuire Nuclear Station, Units 1 and 2; Licensed Operator Examinations.

The NRC examiners conducted operator licensing initial examinations in accordance with the guidance in NUREG-1021, Revision 9, Operator Licensing Examination Standards for Power Reactors. This examination implemented the operator licensing requirements of 10 CFR

§55.41, §55.43, and §55.45.

The NRC administered the operating tests during the period February 7-15, 2005. Members of the McGuire Nuclear Station training staff administered the written examination on February 18, 2005. The written examinations and the operating tests were developed by the McGuire Nuclear Station training staff. Six Reactor Operators (RO) and Seven Senior Reactor Operators (SRO) passed both the operating test and written examination. All of the applicants were issued operator licenses commensurate with the level of examination administered.

No findings of significance were identified.

Enclosure 1

Report Details 4. OTHER ACTIVITIES 4OA5 Operator Licensing Initial Examinations a. Inspection Scope The licensee developed operating tests and written examinations in accordance with NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9. The NRC examination team reviewed the proposed examinations.

Examination changes agreed upon between the NRC and the licensee were made according to NUREG-1021 and incorporated into the final version of the examination materials.

The examiners reviewed the licensees examination security measures while preparing and administering the examinations to ensure examination security and integrity complied with 10 CFR 55.49, Integrity of examinations and tests.

The examiners evaluated six Reactor Operator (RO) and seven Senior Reactor Operator (SRO) applicants who were being assessed under the guidelines specified in NUREG-1021. The examiners administered the operating tests during the period of February 7-15, 2005. Members of the McGuire Nuclear Station training staff administered the written examination on February 18, 2005. The evaluations of the applicants and review of documentation were performed to determine if the applicants, who applied for licenses to operate the McGuire Nuclear Station, met requirements specified in 10 CFR 55, Operators Licenses.

b. Findings No findings of significance were identified.

The NRC determined that the licensees examination submittal was within the range of acceptability expected for a proposed examination. All of the applicants passed both the operating and written examinations. The RO and SRO written examinations and answer keys may be accessed in the ADAMS system (ADAMS Accession Numbers, ML050750414 and ML050750420).

The exam team noted generic weaknesses in the use of Technical Specifications (TS)

during the performance of administrative Job Performance Measures and during the simulator scenarios. Many applicants did not recognize all entry conditions for TS Limiting Conditions for Operations (LCO). During one JPM, six of seven SRO applicants failed to correctly determine the operability of the Leakage Detection System following an earthquake, and entered the wrong LCO. Following a simulator scenario, three SRO applicants failed to identify that pressurizer pressure had decreased below the Departure from Nucleate Boiling (DNB) limits and that TS (Section 3.4.1) was applicable. Also during a scenario, one SRO applicant incorrectly evaluated the plant Enclosure 1

status and entered the LCO for one Diesel Generator (DG) being inoperable. The other DG had been identified as Tagged Out at the start of the scenario. These and other examples of incorrect application of TS were documented in the Individual Examination Report (Form ES-303-1) packages. Copies of these reports were sent to the facility Training Manager for evaluation and determination of appropriate remedial training.

4OA6 Meetings Exit Meeting Summary On February 16, 2005, the examination team discussed generic issues with Mr. and members of his staff. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.

PARTIAL LIST OF PERSONS CONTACTED Licensee personnel S. Bradshaw, Superintendent of Operations K. Crane, Technical Specialist - Regulatory Compliance J. Kammer, Safety Assurance Manager T. Hamilton , Training Manager T. Harrall, Station Manager D. McCorkle, Operations Shift Manager A. Orton, Manager Operator Training G. Peterson, McGuire Site Vice President R. Pope, Supervisor, Initial Operator Training C. Sawyer, Operations Training G. Rumfelt, Operations Training NRC personnel J. Brady, Senior Resident Inspector Enclosure 1

SIMULATION FACILITY REPORT Facility Licensee: McGuire Nuclear Station Facility Docket Nos.: 05000369 and 05000370 Operating Tests Administered on: February 7-15, 2005 This form is to be used only to report observations. These observations do not constitute audit or inspection findings and, without further verification and review in accordance with IP 71111.11, are 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 tests, examiners observed the following items:

MAL NV - 1A : NV Pump trigger did not function during one out of four runs of scenario 2. The major transient (LOCA) resulted in a Safety Injection initiation and the 1A NV pump was suppose to trip. The simulator operator had to use the rack breaker out feature to turn pump off.

MAL IFE009D : Feedwater Regulating Valve Fails Open malfunction actually runs valve closed before it ramps back open to 100 %. Actual controller failure would initiate ramp to full open position from preexisting FRV position.

Enclosure 2