IR 05000269/2002301

NRC Examination Report 50-269/2002-301, 50-270/2002-301 and 50-287/2002-301

ML020950234
Person / Time
Site:	Oconee
Issue date:	04/04/2002
From:	Ernstes M Division of Reactor Safety II
To:	Mccollum W Duke Energy Corp
References
50-269/02301, 50-270/02301, 50-287/02301
Download: ML020950234 (9)

Text

ril 4, 2002

SUBJECT:

OCONEE NUCLEAR STATION - NRC EXAMINATION REPORT 50-269/2002-301, 50-270/2002-301 AND 50-287/2002-301

Dear Mr. McCollum:

During the period of February 11-18, 2002, and on March 21, 2002, the Nuclear Regulatory Commission (NRC) administered operating examinations to employees of your company who had applied for licenses to operate the Oconee Nuclear Station Units 1, 2 and 3. The enclosed report documents the examination results and findings which were discussed on February 15, 2002, with you and other members of your staff. The written examination was administered by your staff on February 18, 2002.

The written and operating examinations were administered to three Reactor Operators and seven Senior Reactor Operator applicants. All applicants passed both the written and operating examinations. There were no Post Examination comments.

No findings of significance were identified.

In accordance with 10 CFR 2.790 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 NRCs document system (ADAMS).

ADAMS is accessible from the NRC Web site at at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Michael E. Ernstes, Chief Operator Licensing and Human Performance Branch Division of Reactor Safetyy Docket Nos. 50-269, 50-270, 50-287 License Nos. DPR-38, DPR-47, DPR-55

Enclosures:

(See page 2)

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

REGION II==

Docket Nos.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55 Report Nos.: 50-269/2002-301, 50-270/2002-301, 50-287/2002-301 Licensee: Duke Energy Corporation Facility: Oconee Nuclear Station Location: 7800 Rochester Highway Seneca, SC 29672 Dates: Operating Tests - February 11-15, 2002 March 21, 2002 Written Examination - February 18, 2002 Examiners: George T. Hopper, Chief, Senior Reactor Inspector D. Charles Payne, Senior Reactor Inspector Jonathan H. Bartley, Senior Resident Inspector Approved by: Michael E. Ernstes, Chief Operator Licensing and Human Performance Branch Division of Reactor Safety Enclosure 1

SUMMARY OF FINDINGS ER 05000269-02-301, ER 05000270-02-301, and ER 05000287-02-301 on 2/11-18/2002 and 3/21/2002, Duke Energy Corporation, Oconee Nuclear Station, licensed operator examinations.

The operator licensing initial examinations were developed jointly by the NRC and the licensee and administered by NRC examiners in accordance with the guidance of NUREG-1021, Examiner Standards, Revision 8, Supplement 1. The examination implemented the operator licensing requirements of 10 CFR §55.41, §55.43, and §55.45. No significant issues were identified.

The NRC administered the operating tests during the period of February 11-15, 2002 and March 21, 2002. The licensee administered the written examination on February 18, 2002. All applicants passed both the written and the operating examinations. Nine applicants were issued operator licenses commensurate with the level of examination administered. One applicants license was withheld and will be issued pending notification from the facility that he has completed his on-shift training requirements.

Report Details 4. OTHER ACTIVITIES (OA)

4OA5 Operator Licensing Initial Examinations a. Inspection Scope The NRC developed the written examinations and the licensee developed the operating tests in accordance with NUREG 1021, Operator Licensing Examination Standards for Power Reactors, Revision 8, Supplement 1. The facility licensees submittal was within the range of acceptability expected for a proposed examination. The NRC and licensee 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 NRC administered the approved operating tests during the period of February 11-15, 2002, to three RO applicants and seven SRO applicants. However, one RO applicant was unable to complete his operating test that week due to illness. Four additional JPMs were developed by the licensee and approved by the NRC. The NRC completed the administration of this applicants operating test on March 21, 2002. The licensee staff administered the approved written examination on February 18, 2002 to ten applicants. The examiners reviewed the licensee examination security measures while preparing and administering the examinations to ensure examination security and integrity.

b. Issues and Findings No findings of significance were identified.

All of the applicants passed both written and operating examinations. Details of each applicants deficiencies are described in the individuals examination report, Form ES-303-1, Operator Licensing Examination Report. Copies of the evaluations have been forwarded under separate cover to the Training Manager in order to enable the licensee to evaluate these deficiencies and provide appropriate remedial training for those operators as necessary. Nine applicants were issued operator licenses commensurate with the level of examination administered. One RO applicant was granted a waiver of the eligibility requirements and was allowed to take the examination. This applicants license was withheld and will be issued pending notification from the facility that he has completed his on-shift training requirements.

The licensee did not submit any post-examination comments concerning the written examination. The written examinations and answer keys may be accessed in the ADAMS system (ADAMS Accession Number ML020920552 and ML020920618).

4OA6 Meetings Exit Meeting Summary The Chief Examiner presented the preliminary examination results on February 15, 2002, to members of licensee management. An additional exit meeting was held on March 21, 2002 following the completion of one applicants operating test. The licensee acknowledged the examination results presented.

The inspectors asked the licensee whether any materials examined during the examination should be considered proprietary. No proprietary information was identified.

PARTIAL LIST OF PERSONS CONTACTED Licensee W. Foster, Safety Assurance Manager P. Gillespie, Shift Operations Manager R. Jones, Station Manager W. McCollum, Vice President L. Nicholson, Regulatory Compliance Manager R. Repko, Operations Superintendent R. Robinson, Operations Representative J. Steely, Initial Training Supervisor P. Stovall, Manager Operator Training J. Smith, Regulatory Compliance Specialist G. Washburn, Operations Training Specialist

SIMULATION FACILITY REPORT Facility Licensee: Oconee Facility Docket Nos.: 50-269, 50-270, and 50-287 Operating Tests Administered on: February 11-15, 2002 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, are not indicative of noncompliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information that may be used in future evaluations. No licensee action is required in response to these observations.

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

ITEM DESCRIPTION DC Lighting Incorrect DC lighting is only provided in the horse-shoe area of the control room and not in the area behind the RPS cabinets. (WR # 20020019)

Model Problem with After recall of SNAP 221, the A SG pressure would increase A SG Pressure instead of remaining low as it should have due to an existing steam line break. (WR # 20020021)

Rod Group Avg Position Group 5, 6, and 7 average position indications on the OAC Indication on OAC incorrectly read 0 with reactor at power. (WR # 20020018)

Enclosure 2