ML20212N985

Requests Submittal by 860818 of Encl List of Selected Ref Matl for Operator/Senior Reactor Operator Licensing Exams Scheduled for Wks of 860922 & 861103 at Facility Simulator. Dates in Jan & Feb 1987 to Be Determined

ML20212N985
Person / Time
Site:	Harris
Issue date:	08/18/1986
From:	Verrelli D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Utley E CAROLINA POWER & LIGHT CO.
References
NUDOCS 8609020120
Download: ML20212N985 (5)

Text

I b ,

Ausgust 18, 1986

. Carolina Power and Light Company C:p "

ATTN: .Mr. E. E. Utley /

Senior Executive Vice President Power Supply and Engineering and Construction P. O. Box 1551

~Raleigh, NC 27602

' Gentlemen:

SUBJECT:

OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr. Lloyd Hancock of your office and Mr. John F. Munro, Operator Licensing Section, arrangements were made for -

administration of the simulator examinations at the Shearon Harris Nuclear Power Plant.

The examinations will be _ given to three groups scheduled for the weeks of

. September 22 and November 3, 1986, and during~ January or February 1987, at the Harris _ simulator. The exact dates in January or February 1987, will be determined at a later date.

In order for us to meet the above schedule, it will be necessary for the facility to furnish the selected reference material from the approved list in Enclosure 1 by August 18, 1986.- Any delay in receiving this material will result in a delay i j in administration of the examinations. Our examinations are scheduled far in advance-'with considerable planning to utilize our present limited examiner

', manpower and to meet the examination date requested by the various ' facilities.

Therefore, missing the August 18, 1986 deadline, even by a few days, will likely result in a long delay, since it would not be~possible to reschedule examinations

! at other facilities. Mr. Hancock has been advised of 'our selected reference

- material requirements, the number of reference material sets that are required,

! and the examiners' names and addresses where each set is to be mailed.

4 This request for information was approved by the Office of Management and Budget

under a blanket Clearance Number 3150-0101 which expires on May 31, 1989.

[ Comments on burden and duplication may be directed to the Office of Management i and Budget, Reports Management, Room 3208, New Executive Office Building, '

Washington, DC 20503.

l l For retake examinations all operator and senior license applications should be

! submitted on Form NRC-398 at least 60 days-prior to the examination date so that we will be able to review the training and experience of the candidates, process

the medical certifications, and prepare final examiner assignments after candidate eligibility has been determined.

i l G B609020120 860918 PDR ADOCK 05000400 f# Y M V PDR -1

a Carolina Power and Light Company 2 August 18, 1986 Thank you for your consideration in this matter. If yoJ have any questions regarding the examination procedures and requirements, please contact Mr. John F. Munro at 404/331-5544, or Mr. D. J. Nelson at 404/331-5483.

Sincerely, (original signed by)

David M. Verrelli, Chief Projects Branch No. 2 Division of Reactor Projects

Enclosure:

Reference Material Requirements cc w/encls:

C. Olexik, Training Supervisor J. L. Willis, Plant Manager bec w/encls:

Senior Resident Inspector Document Control Desk State of North Carolina i

RII, RII RII RII I RI'I PRSiaw D elson Munro CA u ian DVeFy lli 8/p/86 8/6 /86 8/;7k/LJ 8/ /86 8/,(/86 G

i ENCLOSURE 1 REFEREfiCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS

1. Existing learnina objectives and lesson plans (including training nanuals, plant orientation manual, system descriptions, recctor theory, thermo-

~

dynamics,etc.)

i Training materials should include all substantive written material used for l preparing candidates for initial R0 and SR0 licensing. The written material l should be inclusive of learning objectives and the details presented during lecture, rather than outlines. Training materials should be identified by plant and unit, bound, and indexed. Failure to provide complete properly bound and indexed plant reference material will result in canceling and ,

rescheduling of the examinations. Training naterf 31s which include the following should be provided:

l a. System descriptions including descriptions of all operationally relevant t flow paths, components, controls and instrumentation. System training material should draw parallels to the actual procedures used for operating the applicable system.

itaj' r b. Complete and operationally useful descriptions of all safety-system -

, JS4i ' ~ interactions and, where available, BOP system interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure. -

i c. Training material used to clarify and strengthen understanding of emergency operated procedures.

d. Comprehensive theory material that includes fundamentals in the area of

! theory of reactor oparacion, thermodynamics, heat transfer and fluid i

flow, as well as specific 3pplication to actual in-plant components.

For example, mechanical theory material on pumps should include pump theory as well as descriptions of how these principles actually apply to major plant pumps and the systems in which they are installed (i.e.,

Reactor Coolant pumps, all ECCS pumps, Recirculation pumps, Feedwater l pumps and Emergency Feedwater pumps). Reactor Theory material should ,

! include descriptions th?.t draw explicit ties between the fundamentals i and the actual operating limits followed in the plant (i.e., reactor theory material. should contain explanations how principles related to the actual curves used by operators to verify shutdown margin or calculate an ECP).

2. Procedure Index (alphabetical by subject)

Enclosure 1 ,

2 1

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

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

5. Emergency procedures (emergency instructions, abnormal or specit.1 procedures)

6. St'anding orders (important orders that are safety-related and may supersede the regular procedures)

7. Fuel-handling and core-loading procedures, (initial core-loading procedure, when appropriate)

8. Annunciator procedures (alarm procedures, including set points)

9. Radiation protection manual (radiation control manual or procedures)

10. Emergency plan implementing procedures

11. Technical Specifications

12. System operating procedur's e

13. Piping and instrumentation diagrams, electrical single-line diagrams, or 1' flow diagrams

14. Technical Data Book, and/or plant curve information as used by operators and

~

facility precautions, limitations, and set points (PLS) for the facility

15. Questions and answers that licensee has prepared (voluntary by licensee)

16. The following on the plant reference simulator

a. List of all readily available initialization points.

b. List of all preset malfunctions with a clear identificaticn number.

The list should include cause and effect information. Specifically, for each malfunction a concise description of the expected result, or range of resultr, that will occur upon implementation should be provided. Additionally, an indication of which annunciators are to be initially expected should be given.

c. A description of simulator failure capabilities for valves, breakers, indicators and alarms.

Enclosure 1 3

d. Where the capability exists, an explanation of the ability to vary the severity of a particular malfunction should be provided, i.e., ability

, to vary the size of a given LOCA or steam leak, or the ability to cause a slow failure of a component such as a feed pump, turbine' generator or major valve (e.g., drifting shut of a main feedwater control valve).

e. An indication of modeling conditions / problems that may impact the examination.

f. Ider.tification of significant differences between the simulator end the control room.

g. Copies of facility generated scenarios that expose the candidates' to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR) and containment challenges (BWR) may be provided (voluntary by licensee).

h. Simulator instructors manual (voluntary by licensee)

1. Description of the scenarios used for the training class (voluntary by

, licensee)

17. Additional material required by the examiners to develop examinations that meet the requirements of :hese standards and the regulations.

- 2:i<

-iEjr The above reference material should be approved, final issues and should be o '

? M 4 N marked. If a plant has not finalized some of the material, the chief examiner shall verify with the facility 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 examination. All procedures and reference material should be bound with appropriate indexes or tables of contents so that they can be used efficiently.

l

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