ML20207R531

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Confirms Site Visit During Wk of 870406 to Evaluate Requalification Program.Written Exams Administered on 870403 & 10 Must Be Received No Later than 870320 to Allow Adequate Review Prior to Administration
ML20207R531
Person / Time
Site: Arkansas Nuclear 
Issue date: 03/10/1987
From: Gagliardo J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Campbell G
ARKANSAS POWER & LIGHT CO.
References
NUDOCS 8703170335
Download: ML20207R531 (5)


Text

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MAR ' 0198T In Reply Refer To:

Docket:- 50-313 Arkansas Power & Light Company ATTN: Mr. Gene Campbell Vice President, Nuclear Operations P. O. Box 551 Little Rock, AR 72203 Gentlemen:

SUBJECT:

Pilot Requalification Program Evaluation In a telephone conversation between Mr. Ed Force, Unit 1 Training Coordinator, and Mr. Ralph Cooley, Chief, OLS, arrangements were made for an evaluation of the requalification program at Arkansas Nuclear One Unit 1.

This effort will involve one site visit during the week of April 6, 1987.

NRC examiners will audit written and oral examinations and administer one oral examination as part of the requalification program evaluation. When the NRC examiners arrive at the site, they will meet with the appropriate facility personnel and arrange a final schedule for these examinations.

Approved copies of the required reference material listed in Attachment 1,

" Reference Material Requircnents for Reactor / Senior Reactor Operator Licensing Examinations," are currently maintained in the Regien IV office. No additional material is required.

The facility management is responsible for conducting the requalification examinations in accordance with the-approved facility training program. specifies the level of NRC involvement in the requalification examination process under the pilot program. Copies of the written examinations, including answer keys to be administered on April 3 and 10, must be sent to the Region IV Office to arrive not later than March 20, 1987, to allow adequate NRC review prior to administration. The NRC audit-examiner will meet with the facility training staff upon arrival on site to finalize specific details. Mr. Force has been informed of these requirements.

This request for information was approved by the Office of Management and Budget under Clearance Number 3050-0101, which expires May 31, 1989. Comments on burden and duolication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D. C. 20503.

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Thank you for your consideration in this matter. If you have any questions regarding requalification examination audit procedures and requirements, please contact Mr. S. L. McCrory, Examiner, at (817) 860-8265, or Mr. R. A.

Cooley, Chief, Operator Licensing Section, at (817) 860-8147.

Sincerely, Original S! ned by:

R.E. HALL J. E. Gagliardo, Chief Reactor Projects Branch

Enclosures:

As Stated cc w/ enclosures:

J. M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 J. Vandergrift, Training Superintendent Arkansas Nuclear One P.O. Box 60B Russellville, Ar 72801 E. Force, Unit 1 Training Coordinator Arkansas Nuclear One P.O. Box 608 Russellville, Ar 72801 Arkansas Radiation Control Program Director bec to DMB (IE01) bec distrib. by RIV:

RPB RRI R. D. Martin, RA Section Chief (RPB/B)

D. Weiss, RM/ALF R. Cooley, OL RIV DRSP RSB Project Inspector J. Pellet S. McCrory E. Haycraft

,6 ATTACHMENT 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS 1.

Procedure Index (alphabetical by subject).

2.

All administrative procedures (as applicable to reactor operation or safety).

-3.

All integrated plant procedures (normal or general operating procedures).

4.

Emergency procedures (emergency instructions, abnormal or special procedures).

5.

Standing orders (important orders that are safety related and may supersede the regular procedures).

6.

Fuel handling and core-loading procedures, (initial core-loading procedure,whenappropriate).

7.

Annunciatorprocedures(alarmprocedures,includingsetpoints).

8.

Radiation protection manual (radiation protection manual or procedures).

9.

Emergency plan implementing procedures.

10. Technical Specifications.

11.

Lesson plans (training manuals, plant orientation manual, system descriptions,reactortheory, thermodynamics,etc.).

12. System operating procedures.

13.

Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams.

14. Technical data book, and/or plant curve information as used by operators.
15. Any other material the examiner feels is necessary to adequately prepare a written examination, such as reactor traces of significant plant evolutions.
16. Questions and answers that licensee has prepared (voluntary by licensee).
17. Malfunction and initial condition material for simulator (if applicable).

I

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2 The above reference material should be approved, final issues, and so marked.

If a plant has not finalized some of the material, the chief examiner is responsible for ensuring that the most complete, up-to-date material is available and that agreement has been reached with the licensee for limiting changes before the administration of the eyamination. All procedures and reference material should be bound or in the form used by the control room operators, with appropriate indexes or tables of contents so that they can be used efficiently.

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ATTACHMENT 2 PILOT REQUALIFICATION EXAMINATION AUDIT PROGRAM NRC participation under the. pilot program will be limited to:

1.

Prior NRC review / approval of the written requalification examination developed by the facility training staff.

2.

Parallel grading of this examination.

3.

Prior review, observation and independent evaluation by an NRC examiner of the operating examination conducted by the facility i

staff.

In general, the level of the NRC participation will be commensurate with the review required by the Examiner Standards for NRC contractor developed

. examinations.

l The facility written examination should follow the guidance contained in ES-601 (Rev. 2) with respect to examination format, content, and length. The review of this examination should emphasize depth of knowledge required, comprehensiveness of the examination with respect to broad coverage of systems and procedures, and the relationship with the facility requalification program learning objectives.

Parallel grading of the written examination should be conducted on-20% of the examinations completed by the facility licensed operators. The grading can be

- random selection performed concurrently with the facility staff grading or can be the selection of high, medium,.and low score after the facility staff has graded the examinations. The review of grading ~should emphasize the awarding of. partial credit, consistency of scores, compliance with the answer key, and equivalency to the NRC grade (+ 10% per category).

t Evaluation of the operating examination should emphasize depth and breadth of

- questioning and comprehensiveness of simulator scenarios. An independent operating evaluation should be performed by the NRC for one operator per operating examination crew observed. NRC procedures (ES-302) for documenting this operator's performance are to be used. Comparison of NRC and facility evaluations (i.e., parallel grading) will be used to determine if operator weaknesses are properly evaluated and documented. Additionally, a subjective evaluation of the facility administered operating examination should be performed using procedures similar to those for NRC examiner certification (ES-105) for each facility examiner observed.

The facility requalification examination results, including their overall requalification program evaluation should be subjectively evaluated using ES-601 criteria as a guide.

Facility evaluation of the examination weaknesses should be reviewed to determine the adequacy of corrective action for programmatic weaknesses in the facility training program.

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