ML20205A124

Forwards Amend 37 to License R-67 & Safety Evaluation.Amend Increases Number of fueled,in-core,thermionic,direct Conversion Devices Which May Be Irradiated Simultaneously from Four to Seven

ML20205A124
Person / Time
Site:	General Atomics
Issue date:	03/19/1987
From:	Alexander Adams Office of Nuclear Reactor Regulation
To:	Asmussen K GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
Shared Package
ML20205A132	List: ML20205A124 ML20205A179 ML20205A193
References
NUDOCS 8703270386
Download: ML20205A124 (3)

Text

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'Docret No. 50-163'

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,. .Mr..fdIth E.' Asmussen P

ManMier Licensing and Nuclear

-Material Control

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GATechndlogies,Inc.= '

0 Post Office Box 85608-

' San Diego n California 92138

Dear' Mr.' Asmussen:

4

SUBJECT:

ISSUANCE OF AMENDMENT NO. 37 TO FACILITY OPERATING LICENSE NO. R-67 GA TECHNOLOGIES, INC. ~

The Commission has issued Amendment No. 37 to Facility Operating License No. . 7 ,

R-67 for the TRIGA Mark F non-power reactor. The amendment consists of; y i 3 , , %vember changes to the Technical Specifications in response to your' submittal. dated 14.-1986. 4 The amindment authorizes . increasing the number of fueled,in-core,thermionic, direct-conversion devices which may be irr. 'iated simultaneously from four to seven.

In addition to this change, to make the license condition more complete, we have discussed with ~your staff and have-amended Paragraph 2.C.1 of Licer.se No. R-67.to include the maximum reactivity insertion allowed in the pulsing

,- . mode. We also have discussed with your staff and have changed Technical Specification 9;1.1 to eliminate an inconsistency between the license conditio.n for the maximum power level at which the reactor may operate and the 1 A Technical: Specification for the maximum operating power level by eliminating b !'

iU the ex:eption to the 1.5 megawatt maximum power' level for. the purpose of safety, circuit testing. Safety circuits must be tested by a method other than raising the reactor power level above the -licensed limit. We understand that GA has conducted this testing for several. years by introducing an electrical.

signal into the circuit.

Copies of Amendment No. 37 and the related Safety Evaluation are enclosed.

' Sincerely, t .

. /

"* Alexander Adams, Jr., Project Manager g 33r1 % %PDHh ~ Standardization snd Special Projects Directorate P Division of PWR Licensing-B Office of Nuclear Reactor Regulation 3 .

, 4

Enclosures:

' DISTRIBUTION:

1. Amendment No. 37 lDocketfile EJordan AAdams 2., Safety Evaluation NRC'PDR

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Local PDR JPartlow RCarter 3 .

cct</ enclosures: , FMiraglia TBarnhart,(4) HThompson See next page PNoonan WJones Olynch ACRS (10) HBerkow OPA 1

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• (og UNITED STATES I p, t NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20$55 5 j

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March 19,1987 )

Docke; No. 50-163

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\' Mr. Keith E. Asmussen

Manager, Licensing and Nuclear Material Control i L GA Technologies Inc. ,

Post Office Box 85608 . . >

s San Diego, California 92138

Dear Fr. Asmussen:

l

SUBJECT:

ISSUANCE OF AMENDMENT NO. 37 TO FACILITY OPERATING LICENSE s l ,NO. R GA TECHNOLOGIES, INC. g The Commission has_ issued Amendment No. 37 to Facility Operating License No.

R-67 for the TRIGA Mark F non-power reactor. The amendment consists of t

changes to the Technical Specifications in response to your submittal dated November 14, 1986.

The amendment authorizes increasing the number of fueled, in-core, thermionic, i direct conversion devices which may be irradiated simultaneously from four to seven. ,

In addition to this' change, to make the license condition more complete, we ,

1 have discussed with,your staff and have amended Paragraph 2.C.1 of Licenst No. R-67 to include the maximum reactivity insertion allowed in the pulsing mode. We also have, discussed with your staff an'd have changed Technical Specification 9.1.1 to eliminate an inconsistency between the license condition for the maximum power level at which the reactor may operate and the Technical Specification for the maximum operating power level by eliminating the exception to the 1.5 megawatt maximum power level for the purpose of safety circuit testing. Safety circuits must be tested by a method other than raising the reactor power level above the licensed limit. We understand that

[

, CA has conducted this testing for several years by introducing an electrical i signal into the circuit.

Copies of Amendment No. 37 and the related Safety Evaluation are enclosed.

Sincerely.

6 C -

• i Alexander Adams, J . Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B

o ,

Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No. 37

2. Safety Evaluation cc w/ enclosures:

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.; GA! Technologies, Inc. Docket l;o. 50-16?

cc: Attorney General 555 Capitol Mall Sacramente,-California 95814 California Department o' _Heelth -

ATTN: Chicf, Envircemental

. Radiation Centrol Unit RadidlogicHealthSection 714 P' Street, Room 498 Sacramento, California 95814 Director Energy Facilities Siting Division Energy Resources Conservation &'

Development Commissien 1516 - 9th Street Sacramento. California 95814

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