ML20149E499

Forwards Amend 4 to License R-113 & Safety Evaluation.Amend Authorizes Postponement of Certain Tech Spec Surveillance Requirements When Reactor Defueled

ML20149E499
Person / Time
Site:	U.S. Geological Survey
Issue date:	01/04/1988
From:	Alexander Adams Office of Nuclear Reactor Regulation
To:	Millard H INTERIOR, DEPT. OF, GEOLOGICAL SURVEY
Shared Package
ML20149E502	List: ML20149E499 ML20149E516 ML20149E558
References
NUDOCS 8801130367
Download: ML20149E499 (4)

Text

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.[ UNITED STATES

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y NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 2n555

• .. t j f January 4, 1988 Docket No. 50-274 Dr. Hugh T. Millard, Jr.

Reactor Administrator Department of the Interior United States Geological Survey Box 25046 - Mail Stop 424 Denver Federal Center Denver, Colorado 80225

SUBJECT:

ISSUANCE OF AMENDMENT NO. 4 TO FACILITY LICENSE NO. R-l'3 -

UNITED STATES GEOLOGICAL SURVEY (USGS)

The Commission has issued the enclosed Amendment No. 4 to Facility License No. R-113 for the USGS TRIGA Mark I reactor. The amendment consists of changes to the Technical Specifications in response to your submittal dated October 21, 1987. -

The amendment allows the USGS to postpone certain surveillance requirements of the Technical Specifications when the reactor is defueled, making the surveillance requirements impossible to meet. Also, the OsGS is allowed to postpone the surveillance requirement for measurement of pool conductivity when the pool water level is lowered below the intake for the water treatment system, making this measurement impossible.

In addition to these changes, to make the license condition more complate.

Paragraph 3.A. of License No. R-113 is amended to include the maximum reactivity insertion allowed in the pulsing mode. A change is also made in the Technical Specifications definition of steady-state mode, to eliminate the exception in the definition to the 1.0 megawatt maximum operating power level for the purpose of safety circuit testing. Safety circuits must be tested by a method other tha.1 raising the reactor power level above tI1e licensed power limit. We understand that this circuit is tested by the .

introduction of an electrical signal. Also, the definition of square wave mode is changed to bring it into consistency with the definition used in other TRIGA reactors that possess this capability.

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-2 A copy of the related Safety Eysluation supporting Amendment No. 4 is enclosed.

Sincerely, W0, if Alexander Adams, Jr., tr ject Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No. 4

2. Safety Evaluation cc w/ enclosures:

See next page ,

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po 37'( January'4, 1988 A copy of the related Safety Evaluation supporting Amendment No. 4 is enclosed.

Sincerely, i

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Alexander Adams, Jr., Project Manager Standardization and Non-Power  ;

Reactor Project Directorate i Division of Reactor Projects III, IV, '

V and Special Projects  !

Office of Nuclear Reactor Regulation >

Enclosures:

1. Amendment No. 4

2. Safety Evaluation cc w/ enclosures: -

See next page 4

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U. S. Geological Survey Docket Nc. 50-274 -

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City Hall Denver, Colorado 80202  ;

i fir. Albert J. Hazle, Director Radiation Control Division t Department of Health 4210 East lith Avenue ,

Denver, Colorado 80220 ,

Mr. Donald Rusling i Reactor Director j U. S. Geological Survey l Box 25046 - Mail Stop 424 Denver Federal Center

• Denver, Colorado 80225  !

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