ML20062A441

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Forwards AFRRI-TRIGA(R-084 Yae)Annual Rept
ML20062A441
Person / Time
Site: Armed Forces Radiobiology Research Institute
Issue date: 10/06/1978
From: Mcindoe D
DEFENSE, DEPT. OF, DEFENSE NUCLEAR AGENCY
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 7810130227
Download: ML20062A441 (4)


Text

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._Y DEFENSE NUCLEAR AGENCY I

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  • gg-Anato roact$ aAoioniotoov at$tAacH INSTITUTE BETHt$D A, M AaVL AND 20014 j./

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Director of Nuclear Reactor Regulation l '

U.S. Nuclear Regulatory Comission Washington, D.C.

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Dear Sir:

In accordance with Titic 10, Code of Federal Regulations, Part 50.59, the inclosed report is submitted for the AFRRI-TRIGA Reactor, NRC License R-084

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(YAE).

Sincerely yours, DARRELL W. McINDOE

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1 Enc 1 Colonel, USAF, MC as Director

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AFRRI (R-084 YAE) ANNUAL REPROT October 1978 PART A - FACILITIES AND PROCEDURES 4

Chapter I - Site l

A new road has been constructed in front of the facility to provide better access to the hospital.

No permanent changes were required to the

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environmental monitoring plan or the emergency evacuation plan as a result t

of this construction. The control point was moved temporarily to the side entrance but has been reestablished at the front.

Chapter II - Facility The access security of the entire complex has been upgraded by the installation of a card entry system and the enclosing of the main entrar.ce i

vestibule. A card entry lock has also been placed on the entrance tc the t -:

reactor facility. No changes to the reactor security plan were required as a result of this since it is still an " electro - mechanical" locking

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system.

Chapter III - Reactor 1.

In February 1976, two m-irradiated standard 'IRIGA fuel elements and two ua-irradiated instrunented fuel elements were received from the U.S. Army, Harry Diamond Laboratory.

These elements were imediately

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inspected, measured, and placed into the B-ring of the reactor core. The elements which had been in the B-ring were placed in storage.

2.

In August 1978 updated power monitoring instrunentation and j

controls were installed.

The console was the Standard General Atomic 1

control console which has been in use at Harry Diamond Laboratory's Reactor

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Facility (DORF).

Mr. Marcus L. Moore, who had been in charge of the instrunentation at DORF and was hired to replace Mr. Robert Bates who retired, directed the installation effort.

No change was made to the I^

reactor which ' effected the use or intent of any system and no changes to the technical specifications were required.

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Chapter IV - Experimental Facilities s - w.

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No changes have been made in the experimental facilities.

Chapter V - Hazard Analysis r

5 No changes have been made which affect the hazard analysis.

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Chapter VII - Organization 1.

The advisory panel structure was changed by Admendment 16 to license R-84 to combine the Radiation Safety Review Committee and the Reactor Safeguards Panel into the Reactor and Radiation Safety Comittee.

The current membership of this comittee is:

a.

Colonel Darrell W. McIndoe, AFRRI, Chairman b.

Mr. Bruce Cranford, AFRRI c.

Maj Felix E. Owens, AFRRI d.

CPT Ronald E. Schaffer, AFRRI i

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LtCol Lavrance F. Winans, AFRRI l

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Mr. Lester A. Slaback, AFRRI i

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Mr. L. A. Brauch, NRL L

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Mr. Walter L. Geisler, HDL

i. Mr. T. G. Hobbs, NBS 6

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j. Mrs. Betty Markovitch, Recorder

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2.

The personnel presently assigned to the reactor branch are:

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a.

CPT Ronald E. Schaffer, PIC, FRO

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b.

SFC Willard R. Yuna, RO V.

c.

INI Lamar Creel, R0 d.

Capt Robert Savage, trainee

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Mr. Marcus L. Moore, trainee k : <,

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Chapter VIII - Procedures 1.

The weekly check of the Pneumatic Tube System was made a semi-I~ ~,

annual check or prior to experimental use. This system is not used very

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Radiation Facility Safety Comittee to be excessive..

frequently at present and the weekly checks were felt by the Reactor and h'

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Minor changes were made to the daily start-up checklist and weekly instrtmentation checklist to allow for the new console.

PART B - TESTS AND EXPIRIMBTS 1.

Tests No tests were conducted that exceeded the limits specified in the Technical t

Specifications.

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Experiments The experiments conducted during the year were in accordance with the Technical Specifications to the Reactor License and previously approved as

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either " Routine" or "Special" experiments.

3; Reactor Utilization a.

During the period 1 October 1977 to 30 September 1978, a I ',

total of 14,085.19 kw-hrs of thermal power was generated in the reactor for i;

a total of 316,592.19 kw-hrs over the lifetime of the core.

b.

The distribution of reactor utilization at the various experimental facilities is as follows:

(1) Exposure room #1 8 5350 kwh (2) Exposure room i2 8 1617 kwh i

(3) Pnetnatic tubes 8 2821 kwh I

(4) Infinite water 8 4297 kwh s.

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