ML20248C184

Forwards Response to Request for Addl Info Re Armed Forces Radiobiology Research Institute Proposed Reactor Operator Requalification Program

ML20248C184
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	09/21/1989
From:	Irving G DEFENSE, DEPT. OF, DEFENSE NUCLEAR AGENCY
To:	Alexander Adams Office of Nuclear Reactor Regulation
References
NUDOCS 8910030389
Download: ML20248C184 (4)

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SUBJECT:

DEFENSE NUCLEAR AGENCY ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE BETHESDA, MARYLAND 20814 5145 Docket No. 50-170, Response to USNRC Request for Additional Information Concerning AFRRI's Proposed 21 September 1989 Reactor Operator Requalification Program .

Mr. Alexander Adams, Jr.

Office of Nuclear Reactor Regulation

• United States Nuclear Regulatory Commission Washington, D.C. 205E5

{ 1. In response to your request for additional information concerning our new Reactor Operator Requalification Program, we offer the enclosed material for your review.

2. First of all, we wish to clarify our reasoning concerning our proposed requalification lecture series found in Section V,A. of the plan. In addition, we agree with your second recommendation concerning the content of our requalification examinations and have submitted proposed wording that should clarify the plan in Section V,C. Thank you for your time and efforts in reviewing our new plan. If you need any further information, please contact either myself, Mr. Mark Moore, or Major Jim Felty at (202) 295-1290.

GEORG . IRVING, II Colon , USAF, BSC Direc r

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Enclosure ADDITIONAL INFORMATION REQUESTED BY THE USNRC CONCERNING THE AFRRI TRIGA REACTOR FACILITY OPERATOR REQUALIFICATION PROGRAM DOCKET 50-170 I

1. SECTION V, A. Preplanned Lecture Subjects. '

Our Operator Requalification Plan addresses only 8 categories  ;

in our requalification lecture-series, not 9 as described in i 10 CFR 55.59(o)(2). However, in accordance with the provisions in 10 CFR 55.59(o)(7), we have deviated slightly from the lecture series' requirements in one instance, that being plant protection systems. No plant protection systems erint and therefore substituted " Facility changes, modifications, and malfunctions" to our list of lecture topios. In addition, we combined 10 CFR 55.59(o)(2)(iii) and (v) into one topio area called " Plant instrumentation, control and engineered safety systems." Given the substitution of what we believe to be an extremely important and relevent topio area for our facility, coupled with the combination of two topio areas into one, we  !

believe that we adequately meet the 10 CFR 55.59(o)(2) requirement as specifically tailored for our facility.

2. SECTION V, C. Periodio Evaluations.

Section V.C, Periodio Evaluations, should be changed to reflect which items are applicable to our fboility and are to be  !

included in the written and operating requalification examinations. Specifically, the following paragraphs should be inserted after paragraph one of this section.

"The operating examination shall be prepared in  ;

accordance with 10 CFR 55.59(a)(2)(ii). In addition, only j sections of 10 CFR 55.45(a) that are applicable to the AFRRI l TRIGA Reactor Facility shall be used to develop the examination.

This examination will require the operator to demonstrate i an understanding of and the ability to perform the actions  !

necessary to accomplish a representative sample from among the i following 8 items lderived from 10 CFR 55.4M(a)). j (1) Manipulate the console controls as required to safely operate the facility.

(2) Identify annunciators and condition-indicating signals and perform appropriate remedial actions if '

necessary.

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(3) Identify the reactor instrumentation systems and significance of their readings.

(4) Perform control manipulations required to obtain desired operating results during normal, abnormal, and emergency situations.

(5) Demonstrate or describe the use and function of the facility's radiation monitors and alarms and portable survey instruments.

(6) Demonstrate knowledge of significant radiation hazards and techniques for reducing personnel exposure.

(7) Demonstrate knowledge of the emergency plan for the facility.

(8) Demonstrate knowledge of the operational procedures and facility license insuring that the operational procedures are adhered to and that the limitations in the license and amendments are not violated.

The written examination for each licensed operator i shall be prepared in accordance with 10 CFR 55.59(a)(2)(1).

In addition, only sections of 10 CFR 55.41 and 10 CFR 55.43 that are applicable to the AFRRI TRIGA Reactor Facility shall be used to develop the examination. This examination will include a representative sample from among the  ;

following 12 items (derived from 10 CFR 55.41 and 55.43):

(1) Conditions and limitations in the facility license.

(2) Facility operating limitations in the technical specifications.

(3) Fundamentals of reactor theory, including the fission process, neutron multiplication, source effects, control rod effects, criticality indications, reactivity coefficients, and poison effects. l (4) General design features of the core, including oore structure, fuel elements, control rods, and core instrumentation.

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(5) Mechanical components and design features of the reactor cooling system.

(6) Reactor operating characteristics during all modes of operation.

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(7) Design, components, and functions of control and Cafety systems, including instrumentation, intorlocks, and automatio and manual features.

(8) Administrative, operational, and emergency procedures for the facility.

(9)' Purpose and operation of radiation monitoring systems, including alarms and survey equipment.

(10) Radiological safety principles and procedures.

l (11) Radiation hazards that may arise during normal and abnormal situations.

(12) Procedures for handling and disposal of radioactive I

material."

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