ML18153A513

Confirms 970331 Telcon Re Arrangements Made Concerning Reactor Operator & Senior Reactor Operator Licensing Exam Scheduled for Wk of 970721.Ref Matls in Encl List of Ref Matls Should Be Furnished by 970501

ML18153A513
Person / Time
Site:	Surry
Issue date:	04/04/1997
From:	Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
NUDOCS 9704160339
Download: ML18153A513 (6)

Text

,r i

., :i,

,)

f

.I..,

\\

• j

=.1 l A 1

e April 4, 1997 Virginia Electric and Power Company ATTN:

Mr. J. P. O'Hanlon Senior Vice President - Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060

SUBJECT:

REACTOR OPERATOR AND SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS - EXAMINATION REPORT NOS. 50-280/97-300 AND 50-281/97-300

Dear Mr. O'H~nlon:

The purpose of this letter is to confirm arrangements made in a telephone conversation on March 31, 1997, between Mr. Harold Mccallum, Supervisor, Operations Training, and Mr. D. Charles Payne, Senior License Examiner, NRC Region II Operator Licensing and Human Performance Branch, for the administration of licensing examinations at the Surry Power Station. The examination preparation visit is scheduled for the week of July 21, 1997.

The written examinations are scheduled for August 4, 1997, and the operating examinations are scheduled for August 5-8, 1997.

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, Attachment 4) during the week of July 7, 1997.

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 May 1, 1997.

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.

9704160339 970404 PDR ADOCK 05000280 V

PDR 11111i m~ i111in nm m11 ~m ~mm~ 11111111 9

1 I

I I

I I

1

_;-~ : I e

VEPCO 2

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 (0MB) Clearance Number 3150-0101, which expires April 30, 1997. 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 suggestions 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, NEOB-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.

Thank you for your cooperation in this matter.

Mr. Mccallum 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 me at (404) 562-4638.

Sincerely, (Original signed by T. A. Peebles)

Thomas A. Peebles, Chief Operator Licensing and Human

• Performance Branch Division of Reactor Safety

Enclosure:

List of Reference Materials cc w/encl: See page 2

,I" c;

J

• • i j

1 i

VEPCO cc w/encl:

M. L. Bowling, Manager Nuclear Licensing & Operations Support Virginia Electric & Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060 David A. Christian, Manager Surry Power Station Virginia Electric & Power Company 5570 Hog Island Road Surry, VA 23883 W.R. Matthews, Manager North Anna Power Station P. 0. Box 402 Mineral, VA 23117 Ray D. Peace, Chairman Surry County Board of Supervisors P. 0. Box 130 Dendron, VA 23839 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, VA 23209 Michael W. Maupin Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, VA 23219 Robert B. Strobe, M.D., _M.P.H.

State Health Commissioner Office of the Commissioner Virginia Department of Health P. 0. Box 2448 Richmond, VA 23218 Attorney General Supreme Court Building 900 East Main Street Richmond, VA 23219 Mr. D. T. Llewellyn, Superintendent Nuclear Training Surry Power Station P. 0. Box 315 Surry, VA 23883 Distribution w/encl: See page 4 3

i **

• • j

{

VEPCO Distribution w/encl:

G. Edison, NRR J. Jaudons, RII G. Belisle, RII L. Garner, RII R. Gibbs, RII P. Fillion, RII D. Jones, RII W. Stansberry, RII C. Payne, RII B. Michael, RII PUBLIC NRC Resident Inspector U.S. Nuclear Regulatory Commission Surry Nuclear Power Station 5850 Hog Island Road Surry, VA 23883 NRC Resident Inspector U.S. Nuclear Regulatory Commission 1024 Haley Drive Mineral, VA 23117 4

04 /

/ 97 04 /

/ 97 YES NO YES NO

I"'

l

• i 'j

-i j.,

• 1 J

e LIST OF REFERENCE MATERIALS

1. Materials used by the facility licensee to ensure operator competency:

a.

• 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

b.

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 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 operation, including low power conditions. A description of the scenarios used for the training class may also be provided (voluntary by facility licensee).

d.

All 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).

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

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

Enclosure

~

1 i

List of Reference Material 2

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.

h.

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

i.

Simulator instructors' manual.

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.

Enclosure