IR 05000250/2002301

NRC Examination Report Nos. 50-250/2002-301 and 50-251/2002-301

ML023110471
Person / Time
Site:	Turkey Point
Issue date:	11/07/2002
From:	Ernstes M NRC/RGN-II
To:	Stall J Florida Power & Light Co
References
50-250/02-301, 50-251/02-301
Download: ML023110471 (12)

Text

ber 7, 2002

SUBJECT:

TURKEY POINT NUCLEAR PLANT - NRC EXAMINATION REPORT NOS. 50-250/2002-301 AND 50-251/2002-301

Dear Mr. Stall:

During the period October 7-11, 2002, the Nuclear Regulatory Commission (NRC) administered operating examinations to employees of your company who had applied for licenses to operate the Turkey Point Nuclear Plant. 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 October 15, 2002.

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

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 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 Safety Docket Nos.: 50-250, 50-251 License Nos.: DPR-31, DPR-41

Enclosures:

(See page 2)

FP&L 2 Enclosures: 1. Report Details 2. Simulation Facility Report

REGION II==

Docket Nos.: 50-250, 50-251 License Nos.: DPR-31, DPR-41 Report Nos.: 50-250/02-301, 50-251/02-301 Licensee: Florida Power & Light Company (FP&L)

Facility: Turkey Point Nuclear Plant Location: 9762 S. W. 344th Steet Florida City, FL 33035 Dates: Operating Tests - October 7-11, 2002 Written Examination - October 15 , 2002 Examiners: R. Aiello, Chief Examiner E. Lea, Senior Operations Engineer R. Monk, Operations Engineer Approved by: M. Ernstes, Chief Operator Licensing and Human Performance Branch Division of Reactor Safety Enclosure 1

SUMMARY OF FINDINGS Examinations Report 05000250-02-301, 05000251-02-301 Florida Power & Light Company, on October 7-11, 2002, Turkey Point Nuclear Power Plant, Units 3 and 4, licensed operator examinations.

The NRC examiners conducted operator licensing initial examinations in accordance with the guidance of Examiner Standards, NUREG-1021, Revision 8, Supplement 1. 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 October 7- 11, 2002. Members of the Turkey Point Nuclear Plant training staff administered the written examination on October 15, 2002. The operator licensing initial written examinations were developed by the NRC. The operating tests were developed by the Turkey Point staff from an outline submitted by the NRC. All applicants, two Reactor Operators (RO) and five Senior Reactor Operators (SRO) passed the operating and written examinations and were issued operator licenses commensurate with the level of examination administered.

No significant issues were identified.

Report Details 4. OTHER ACTIVITIES (OA)

4OA5 Operator Licensing Initial Examinations a. Inspection Scope The examiners evaluated two RO and five SRO applicants who were being assessed under the guidelines specified in NUREG 1021, Revision 8, Supplement 1, and reviewed written examinations that were administered under the guidelines specified in the NUREG. The NRC administered the operating tests during the period October 7- 11, 2002. Members of the Turkey Point Nuclear Plant training staff administered the written examination on October 15, 2002. The evaluations of the applicants and review of documentation were performed to determine if the applicants, who applied for licensees to operate Turkey Point Nuclear Plant, met requirements specified in 10 CFR Part 55.

b. Findings No findings of significance were identified.

The licensee did not submit any post examination comments concerning the written examination. The written examination and answer key may be accessed in the ADAMS system (ADAMS Accession Number ML023100593).

4OA6 Meetings Exit Meeting Summary On October 11, 2002, the Chief Examiner discussed generic applicant performance and examination development issues with members of licensee management.

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 R. Bretton, Operations Continuing Training Supervisor D. Henry, Acting Operations Initial Training Supervisor D. Hutchins, Support Services Supervisor T. Jones, Plant General Manager M. Lacal, Operations Manager G. Laughlin, Acting Training Manager J. McElwein, Site Vice President W. Parker, Licensing Manager B. Stamp, Operations Supervisor NRC R. Reyes, Resident Inspector

SIMULATION FACILITY REPORT Facility Licensee: Turkey Point Facility Docket No.: 050-00250, 050-00251 Operating Tests Administered on: 10/07-11/2002 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 SGTR A SGTR of 200 gpm from the A SG was initiated. With all feedwater isolated to the A SG, blowdown isolated and all steam stops were open, it was noted that the A SG level decreased. The B and C SGs were carrying one Terry Turbine each with the steam from A SG isolated to the Terry Turbines. When asked the reason the level in the ruptured SG was decreasing, the Examiner was told by the Simulator Engineer and shown on a monitor that the A SG was supplying about three times as much steam to the common header as were the B and C SGs, even though all steam stops were open to a common header.

He explained that this was due to higher enthalpy in the A SG due to the RCS water entry through the rupture. The level decrease was counter to any previous experience of the Examiner. As the scenario played out, break flow would stop without any mitigating actions by the crew as specified in the SGTR procedure E-3. In order to exercise the crew and the procedure, the leakrate was increased to 700 gpm. This did provide a level rise in the A SG.

Enclosure 2