ML20034D411
| ML20034D411 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 04/01/1992 |
| From: | Caldwell J Office of Nuclear Reactor Regulation |
| To: | Poston J TEXAS A&M UNIV., COLLEGE STATION, TX |
| References | |
| NUDOCS 9204060135 | |
| Download: ML20034D411 (4) | |
Text
APR 011992 i'
Dr. John W. Poston Head of Nuclear Engineering fo-Si Texas A&M University Coke Building Second Floor College Station, Texas 77843-1246
Dear Dr. Poston:
In a telephone conversation between Mr. Brian Hughes and Mr. Robert Berry arrangements were made for the administration of an operator upgrade examination at the AGN-201. The operating examination is scheduled for the week of July 6-10, 1992.
In order for us to meet this schedule, please furnish sets of the reference material listed in the Enclosure, " Reference Material for Reactor / Senior Reactor Operator Licensing Examinations" at least 60 days prior to the examination date to the following address:
U. S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTN: James L. Caldwell, Mail Stop 10/D/22 Preliminary reactor operator and senior reactor operator license applications should be submitted at least 30 days before the first examination dates 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 applicant eligibility has been determined.
Final signed applications certifying that all training has been completed must be submitted at least 14 days before the examination date in order to process the license application.
If our review cannot be completed in time to make a determination of applicant eligibility, the candidate may not be permitted to sit for the examination.
Therefore, it is recommended that license applications be provided as soon as possible to ensure an appropriate level of review.
This request is covered by Office of Management and Budget Clearance Number 3150-0101 which expires May 31, 1992. This 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 comment 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, MNBB-7714, Division i
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, NE0B-3019, Office of Management and Budget, Washington, 9.C. 20503.
~
( 9,7.0406DBb Xb s\\u 170078 94\\\\
u
v; Dr. John W. Poston APR 0113d If you have any questions regarding the examination procedures and requirements, please contact Mr. James L. Caldwell at (301) 504-1042.
Sincerely, James L. Caldwell, Chief Nonpower Reactor Section Operator Licensing Branch Division of Licensee Performance and Quality Evaluation Office of Nuclear Reactor Regulation
Enclosure:
Reference Material for Reactor / Senior Reactor Operator Licensing Examinations cc w/ encl:
R. Berry, Texas A&M University Distribution:
RGallo JCaldwell DMcCain Central Files Facility File BHughes, OLB Examiner TMichaels, PM 04%h 0
LPQ L
LPQ aWCain:dlm BHughes ldwell 04/l/92 04/or /92 04/ /92
6 i
i 4
ENCLOSURE REFERENCE MATERIAL FOR REACTOR / SENIOR REACTOR OPERATOR.
LICENSING EXAMINATIONS (NON-POWER) 1.
Existing learning objectives, students handouts and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, etc.)
Training materials should include all substantive written material used for preparing applicants for initial R0 and SR0 licensing. The written material should include learning objectives if available and the details presented during lectures, rather than outlines. Training materials should be identified, bound, and indexed. Training materials which include the following should be provided:
System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual procedures used for operating and applicable system.
Complete and operationally useful descriptions of all safety-system interactions, secondary interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
Training material used to clarify and strengthen understanding of emergency operating procedures.
2.
Complete Procedure Index (including temporary procedures).
3.
All administrative procedures as applicable to reactor operation or safety.
4.
All integrated plant procedures, normal or general operating procedures and procedures for experiments.
i 5.
All emergency procedures, emergency instructions, abnormal or special procedures.
6.
Standing orders or procedures changed by reactor supervision and important orders or changes that are safety related and may supersede the reonlar procedures.
7.
Applicable procedures (procedures that are run frequently).
8.
Fuel-handling and core-loading procedures and initial core-loading procedure, when appropriate.
9.
Any annunciator / alarm procedures, as applicable.
10.
Radiation protection manual, radiation control manual or procedures.
II.
Emergency plan implementing procedures.
t e
I~
\\
i (continued) l l
2 12.
Safety Analysis Report, Technical Specifications and interpretations, if available.
l 13.
System operating procedures, including experiments.
14.
Piping and instrumentation diagrams, electrical single-line diagrams, or i
flow diagrams, as applicable.
15.
Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points for the facility.
16.
Questions and answers specific to the facility training program which may be used in the written or operating examinations (voluntary by
~
facility licensee).
t' 17.
Additional material as requested by the examiners to develop examinations that meet the requirements of the Non-power Reactor Examiner Standards and Regulations.
The above reference material should be approved final issues and so marked.
If a facility has not finalized some of the material, the Chief Examiner should 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.
i
' t t
i A.