ML18011A843

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Confirms Arrangements Made During 950302 Telcon Re Administration of Licensing Exams at Plant.List of Ref Matls Encl
ML18011A843
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 03/13/1995
From: Peebles T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Robinson W
CAROLINA POWER & LIGHT CO.
References
NUDOCS 9503200297
Download: ML18011A843 (7)


Text

March 13, 1995 Carolina Power 8 Light Company ATTN:

Mr." W.

R. Robinson Vice President

- Harris Plant Shearon Harris Nuclear Power Plant P. 0.

Box 165, Mail Code:

Zone 1

New Hill, NC 27562-0165

SUBJECT:

REACTOR OPERATOR AND SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS EXAMINATION REPORT NO. 50-400/95-300 Gentlemen:

The purpose of this letter is to confirm arrangements made in a telephone conversation on March 2,

1995, between Mr. Jim Pierce, and Mr. Paul Steiner, Licen'se
Examiner, NRC Region II Operator Licensing Section, for the admin.'stration of licensing examinations at the Shearon Harris Nuclear Plant.

The examination preparation visit is scheduled for June 12, 1995.

The written examinations are scheduled for June 26,

1995, and the operating examinations are scheduled for the week of June 27 through 29, 1995.

Your staff will be given an opportunity to review the licensing examinations in accordance with the guidelines in Revision 7 of NUREG-1021, "Operator Licensing Examiner Standards,"

(ES-201, ) during the week of June 5,,1995.

To prepare the examinations and meet the above schedule, it will be necessary for your staff to furnish the reference materials specified in the enclosed List of Reference Materials by March 12, 1995.

Any delay in receiving approved and indexed reference material or the submittal of inadequate or incomplete reference material may result in the examinations being rescheduled.

The NRC will prepare and administer the written examinations in accordance with ES-401 and ES-402 of NUREG-1021.

In order to conduct the requested examinations, it will be necessary for your staff to provide adequate space and accommodations on the date noted above.

The NRC's guidelines for administering the written examinations are described in ES-402, Attachment 1.

The NRC will prepare and administer the operating tests in accordance with ES-301 and ES-302 of NUREG-1021.

In order to conduct the requested operating tests, it will be necessary for your staff to make the simulation facility available on the dates noted above.

Your staff should retain the original simulator performance data (e.g.,

system pressures, temperatures, and levels) generated during the dynamic operating tests until the examination results are final.

ES-402, Attachment 2,

and ES-302, Attachment 1, contain a number of NRC policies and guidelines that will be in effect while the written examination and operating tests are. being administered.

9503200297 9503l3 PDR ADOCK 05000400 V

PDR

CPKL Your staff should submit preliminary reactor operator and senior reactor operator license applications and waiver requests at least 30 days before the first examination date so that the NRC will be able to review the applications and the medical certifications and evaluate any requested waivers.

If the applications are not received at least 30 days before the examination date, a

postponement may be necessary.

Final, signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date.

This request is covered by Office of Management and Budget (OMB) Clear ance Number 3150-0101, which expires October 31, 1995.

The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering,

xeroxing, and mailing the required material.

Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestion.

for reducing this burden, to the Information and Records Management

Branch, T-6 F33, Division of Information Support Services, Office of Information Resources Management, U.

S. Nuclear Regulatory Commission, Washington, D.

C.

20555; and to the Paperwork Reduction Project (3150-0101),

Office of Information and Regulatory Affairs, NE08-10202, Office of Management and

Budget, Washington, D.

C.

20503, From the requested reference materials identified in the enclosure, we would appreciate retaining your EOPs and AOPs for reference use in our Incident

Response

Center.

,If you have any concerns about this proposed

use, please contact me at (404) 331-5541.

Thank you for your cooperation in this matter.

Hr. Jim Pierce has been advised of the policies and guidelines referenced in this letter.

If you have any questions regarding the NRC's examination procedures and guidelines, please contact Mr. Lawrence L. Lawyer, Chief, Operator Licensing Section, at (404) 331-4700, or myself at (404) 331-5541.

Sincerely, ORIGINAL SIGNED BY P. J,

KELLOGG, FOR

Enclosure:

List of Reference Materials Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety cc w/encl:

H.

W. Habermeyer, Jr.

Vice President Nuclear Services Department Carolina Power 8 Light Company P. 0.

Box 1551

- Hail OHS7

Raleigh, NC 27602 cc w/encl cont'd:

(see page 2)

CPKL cc w/encl cont'd:

J.

W. Donahue Plant Manager

- Harris Plant Carolina Power 8 Light Company Shearon Harris Nuclear Power Plant P. 0.

Box 165, MC:

Zone 1

.New Hill, NC 27562-0165 Mr. J.

M. Collins Manager

- Training Shearon Harris Nuclear Power Plant Route 1,

Box 327 New Hill, NC 27562-0291 R.

E. Jones General Counsel

- Legal Department Carolina Power and Light Co.

P. 0.

Box 1551

Raleigh, NC 27602 Oayne H. Brown, Director Division of Radiation Protection N.

C. Department of Environmental Commerce 8I Natural Resources P. 0.

Box 27687

Raleigh, NC 27611-7687 Karen E.

Long Assistant Attorney General State of North Carolina P. 0.

Box 629

Raleigh, NC 27602 Public Service Commission State of South Carolina P. 0.

Box 11649

Columbia, SC 29211 N. Le, NRR A. Gibson, RII/DRS G. A. Hallstrom, RII/DRS C.

D. Payne, RII/ORS PUBLIC NRC Resident Inspector U.

S. Nuclear Regulatory Commission 5421 Shearon Harris Road New Hill, NC 27562-9998 Chairman of the North Carolina Utilities Commission P. 0.

Box 29510

Raleigh, NC 27626-0510 Robert PE Gruber Executive Director Public Staff NCUC P. 0.

Box 29520

Raleigh, NC 27626 SEND TO PUBLIC DOCUMENT ROOM7 YES NO OFFICE SIGNATURE NAME DATE Rll:ORS f'ineC e/ed 03)g /95 All:DRS LLewy 03 I ) I 95 Rll'IDRP HChrie eneen 03 I

/ 95 Rll;ORS TPeeble 03 I I 95 03 I I 95 03/

/95 OFF1CIAL CORD COPY DOCUHENT NAHE:

G ANNARXI3D09D HS

LIST OF REFERENCE MATERIALS I.

Materials used by the facility licensee to ensure operator competency:

The following types of materials used to train applicants for initial RO and SRO licensing should be provided.

The material should be complete, comprehensive, and of sufficient detail to support the development of accurate and valid examinations without being redundant.

learning objectives, student

handouts, and lesson plans system descriptions of all operationally relevant flow paths, components,
controls, and instrumentation material used to clarify and strengthen understanding of
normal, abnormal, and emergency operating procedures
complete, operationally useful descriptions of all safety system interactions
and, where available, balance-of-plant system interactions under emergency and abnormal conditions, including consequences of anticipated operator errors, maintenance
errors, and equipment failures b.

questions and answers specific to the facility training program that may be used in the written examinations or operating tests (voluntary by facility licensee).

c.

Copies of facility-generated simulator scenarios that expose the applicants to abnormal and emergency conditions, including degraded pressure

control, degraded heat removal capability, and containment challenges, during all modes of opera'.'on, including low power conditions.

A description of the scenarios used for the training class may also be provided (voluntary by facility licensee).

d. 'll job performance measures (JPMs) used to ascertain the competence of the operators in performing tasks within the control room complex and outside the control room (i.e., local operations) as identified in the facility JTA.

JPMs should evaluate operator responsibilities during normal,

abnormal, and emergency conditions and events and during all modes of operation, including cold shutdown,
low, and full power.

2.

Complete index of procedures (including all categories sent).

3.

All administrative procedures applicable to reactor operation or safety.

4.

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

ENCLOSURE

List of Reference Materials 5.

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

6.

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

7.

Surveillance procedures that are run frequently (i.e., weekly) or that can be,run on the simulator.

8.

Fuel handling and core loading procedures (if SRO applicants will be examined).

9.

All annunciator and alarm procedures.

10.

Radiation protection manual (radiation control manual or procedures.

11.

Emergency plan implementing procedures.

12.

Technical Specifications (and interpretations, if available) for all units for which licenses are sought.

(If merits Tech Specs, include all removed programs such as ODCM, etc.)

13.

System operating procedures.

14.

Technical data

book, and plant curve information as used by operators, and facility precautions, limitations, and set points document.

15.

The following information pertaining to the simulation facility:

a.

List of all initial conditions.

b.

List of all malfunctions with identification numbers.

C.

Malfunction cause and effect information and a concise description of the expected result or range of results that will occur upon initiation, including an indication of which annunciators will be actuated.

d.

A description of the simulator's failure capabilities for valves,

breakers, indicators, and alarms.

e.

The range of severity of each variable malfunction (e.g.,

the size of a reactor coolant or steam leak or the rate of a component failure such as a feed pump, turbine generator, or major valve).

f.

A list of modeling conditions (e.g., simplifications, assumptions, and limits) and problems that may affect the examination.

g.

A list of any known performance test discrepancies not yet corrected.

ENCLOSURE

List of Reference Materials h.

A list of differences between the simulator and the reference plant's control room.

i.

Simulator instructors'anual.

16.

Any additional plant-specific material that has been requested by the examiners to develop examinations that meet the guidelines of these Standards and the regulations.

ENCLOSURf