IR 05000390/2002301

NRC Examination Report 05000390/02-301, on 11/26/2002 & 12/09-12/2002, Licensed Operator Examinations

ML030210084
Person / Time
Site:	Watts Bar
Issue date:	01/17/2003
From:	Ernstes M Operator Licensing and Human Performance Branch
To:	Scalice J Tennessee Valley Authority
References
50-390/02-301 ER 02-301
Download: ML030210084 (11)

Text

ary 17, 2003

SUBJECT:

WATTS BAR NUCLEAR PLANT - NRC EXAMINATION REPORT NO. 50-390/02-301

Dear Mr. Scalice:

During the period December 9-12, 2002, the Nuclear Regulatory Commission (NRC)

administered operating examinations to employees of your company who had applied for licenses to operate the Watts Bar 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 November 26, 2002.

Five of seven applicants passed both the written and operating examinations. There were three post examination comments which are identified in Enclosure 2.

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 No.: 50-390 License No.: NPF-90

Enclosures:

(See page 2)

TVA 2 Enclosures: 1. Report Details 2. NRC Resolution of Facility Comments

REGION II==

Docket No.: 50-390 License No.: NPF-90 Report No.: 50-390/02-301 Licensee: Tennessee Valley Authority (TVA)

Facility: Watts Bar Nuclear Plant Location: 1260 Nuclear Plant Road Spring City, TN 37381 Dates: Operating Tests - December 9-12, 2002 Written Examination - November 26, 2002 Examiners: L. Miller, Chief Examiner R. Baldwin, 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 ER 05000390/02-301, Tennessee Valley Authority, 12/09/2002 -12/12/2002, Watts Bar Nuclear Plant, Unit 1, 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 December 9-12, 2002. Members of the Watts Bar Nuclear Plant training staff administered the written examination on November 26, 2002. The operator licensing initial written examinations were developed by the NRC. The operating tests were developed by the Watts Bar staff from an outline submitted by the NRC. Two Reactor Operators and three of five Senior Reactor Operators 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 developed the written examinations in accordance with the guidelines specified in NUREG-1021, Revision 8, Supplement 1. The examiners reviewed the operating examinations, which the licensee developed from an outline submitted by the NRC, for compliance with the guidelines specified in NUREG-1021.

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 two Reactor Operator and five Senior Reactor Operator applicants who were being assessed under the guidelines specified in NUREG 1021.

They administered the operating tests during the period December 9-12, 2002.

Members of the Watts Bar Nuclear Plant training staff administered the written examination on November 26, 2002. The evaluations of the applicants and review of documentation were performed to determine if the applicants, who applied for licensees to operate Watts Bar Nuclear Plant, met requirements specified in 10 CFR Part 55.

b. Findings No findings of significance were identified.

The licensee submitted three post examination comments concerning the written examination. The post examination comments may be accessed in the ADAMS system (ADAMS Accession Number ML023440122). The written examination and answer key may be accessed in the ADAMS system (ADAMS Accession Numbers ML023510331 and ML023510338).

4OA6 Meetings Exit Meeting Summary On December 13, 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. Evans, Operations Training Manager K. Parker, Maintenance and MOPS Manager T. Wallace, Operations Manager D. Kulisek, Assistant Plant Manager G. Laughlin, Acting Training Manager P. Pace, Licensing and Industry Affairs J. Cox, Training Manager NRC J. Reece, Resident Inspector

NRC RESOLUTION OF FACILITY COMMENTS QUESTION #6 SRO:

Recommendation accepted:

The NRC agrees with the licensees comment that answer C and D are correct answer.

The NRC reviewed the licensees comments, the licensees supporting information, and AOI-2, Malfunction of the Reactor Control System. The intent of the question was to determine if the applicant was aware of 1) which circumstances allow the Bank to be aligned to the Rod (Distractors A and B) and 2) the differences in the requirements to align a Control Bank rod and a Shutdown Bank rod (Answer C and distractor D, respectively). The stem of the question was not clear enough to prevent D from also be considered correct.

In conclusion, the NRC has determined, based on the above discussion, that answer C and D are correct answers.

QUESTION #32 SRO Recommendation accepted:

The NRC reviewed the licensees comments, the licensees supporting information and agrees with the licensees comment that with annunciator 92C, PZR LEVEL LO-HTRS OFF & LTDN CLOSED illuminated, Pressurizer level would be increasing and that none of the responses could describe this condition.

In conclusion, the NRC has determined, based on the above discussion, the question will be deleted from the exam.

QUESTION #99 SRO:

Recommendation not accepted:

The NRC agrees with the licensees comment that answer A is the correct answer. The NRC disagrees with the licensees comment that distractor B is also a correct answer.

The NRC reviewed the licensees comments, the licensees supporting information, FR-H.2, Steam Generator Overpressure and FR-H.3, Steam Generator High Level. Distractor B is different from answer A, in that, distractor B states that the operator will continue with FR-H.2 to reduce S/G pressure. The pressure reduction in FR-H.2 occurs in Step 4 of the procedure.

To be at this step, the operator would have to have taken the wrong path at Step 3, which is the appropriate transition step to FR-H.3 as described in answer A.

In conclusion, the NRC has determined, based on the above discussion, that answer A is the only correct answer.

Enclosure 2