ML14181A672

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Informs of Retake Written SRO Licensing Exam Scheduled for 950509.Advises That NRC Has Reviewed & Approved Waiver Request Submitted W/Candidate Application.No Operating Exam Will Be Administered
ML14181A672
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 04/18/1995
From: Peebles T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Hinnant C
CAROLINA POWER & LIGHT CO.
References
NUDOCS 9504240066
Download: ML14181A672 (6)


Text

April 18, 1995 Carolina Power and Light Company ATTN: Mr. C. S. Hinnant Vice President H. B. Robinson Steam Electric Plant Unit 2 3581 West Entrance Road Hartsville, SC 29550

SUBJECT:

SENIOR REACTOR OPERATOR LICENSING RETAKE EXAMINATION EXAMINATION REPORT NO. 50-261/95-300 Gentlemen:

The purpose of this letter is to confirm arrangements made in a telephone conversation between, Mr. Tom Natale, Manager, Operations Training and Mr. D. Charles Payne, Senior License Examiner, NRC Region II Operator Licensing Section, for the administration of a retake written examination for one individual at the H. B. Robinson Plant Unit 2. There will be no examination preparation visit.

The written examination will be administered on May 9, 1995 by Mr. Mike Ernstes, Senior License Examiner, NRC Region II.

Your staff has furnished an up-to-date set of reference materials specified in the enclosed List of Reference Materials. The NRC prepared and will administer the written examinations in accordance with ES-401 and ES-402 of NUREG-1021. Members of your staff reviewed the licensing examination in accordance with the guidelines in Revision 7 of NUREG-1021, "Operator Licensing Examiner Standards," (ES-201, Attachment 4) during the week of April 17, 1995.

In order to conduct the requested examination, 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. Also, ES-402, Attachment 2, contains the NRC policies and guidelines that will be in effect while the written examination is being administered.

The NRC has reviewed and approved the waiver request submitted with the candidate's application. Therefore no operating examination will be administered.

From the provided 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.

9504240066 950418 PDR ADOCK 05000261 V

PDR

CP&L 2

Thank you for your cooperation in this matter. Mr. Natale 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. D. Charles Payne, Operator Licensing Section, at (404) 331-4666, or myself at (404) 331-5541.

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

Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety

Enclosure:

List of Reference Materials cc w/encl:

R. E. Jones Dale E. Young General Counsel - Legal Department Plant Manager Carolina Power and Light Co.

H. B. Robinson Steam Electric Plant P. 0. Box 1551 3581 West Entrance Road Raleigh, NC 27602 Hartsville, SC 29550 Karen E. Long H. W. Habermeyer, Jr.

Assistant Attorney General Vice President State of North Carolina Nuclear Services Department P. 0. Box 629 Carolina Power & Light Company Raleigh, NC 27602 P. 0. Box 1551

- Mail 0HS7 Raleigh, NC 27602 Robert P. Gruber Executive Director R. M. Krich, Manager Public Staff - NCUC Regulatory Affairs P. 0. Box 29520 H. B. Robinson Steam Electric Plant Raleigh, NC 27626-0520 3581 West Entrance Road Hartsville, SC 29550 Public Service Commission State of South Carolina Max Batavia, Chief P. 0. Box 11649 Bureau of Radiological Health Columbia, SC 29211 Dept. of Health and Environmental Control Hartsville Memorial Library 2600 Bull Street 147 W. College Avenue Columbia, SC 29201 Hartsville, SC 29550 Dayne H. Brown, Director Mr. M. E. Herrell Division of Radiation Protection Manager - Training N. C. Department of Environmental H. B. Robinson Steam Electric Commerce & Natural Resources Generating Plant*

P. 0. Box 27687 Robinson Nuclear Project Department Raleigh, NC 27611-7687 P. 0. Box 790 Hartsville, SC 29550 Distribution w/encl.

(See page 3)

CP&L 3

Distribution w/encl:

D. Verrelli, RII A. Gibson, DRS B. Mozafari, NRR G. A. Hal1strom, RH PUBLIC NRC Resident Inspector U. S. Nuclear Regulatory Commission 2112 Old Camden Road Hartsville, SC 29550 SEND TO PUBLIC DOCUMENT ROOM?

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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 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 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).

Enclosure

List of Reference Materials 2

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.

Endlosure

List of Reference Materials 3

h. A list of differences 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