ML20149M669

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Forwards Amend 9 to License R-106 & Safety Evaluation. Amend Changes Organizational Structure of Oregon State Univ Triga Reactor & Surveillance Requirements Time Intervals to Agree W/Current Practice of non-power Reactors
ML20149M669
Person / Time
Site: Oregon State University
Issue date: 02/11/1988
From: Alexander Adams
Office of Nuclear Reactor Regulation
To: Andrea Johnson
Oregon State University, CORVALLIS, OR
Shared Package
ML20149M670 List:
References
NUDOCS 8802260231
Download: ML20149M669 (4)
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February 11, 1988 Docket No. 50-243 Dr. A. G. Johnson, Director Radiation Center Oregon State University Corvallis, Oregon 97331

Dear Dr. Johnson:

SUBJECT:

ISSUANCE OF AMENDMENT NO. 9 TO FACILITY OPERATING LICENSE NO. R-106 - OREGON STATE UNIVERSITY TRIGA REACTOR (OSTR)

The Commission has issued the enclosed Amendment No. 9 to Facility Operating License No. R-106 for the Oregon State University TRIGA reactor. The amendment consists of changes to the Technical Specifications in response to your submittals dated July 19, 1983 and October 12, 1987.

The amendment changes the organizational structure of the OSTR. Also, the surveillance requirements time intervals are updated to be in agreement with current practice for non-power reactors.

In addition to these changes, to make the license condition more complete, we have discussed with your staff and have amended Paragraph 2.C.(1) of Facility Operating License No. R-106 to include the maximum reactivity 4tertion allowed in the pulse mode. We have also discussed with your staff and have changed Technical Specification 3.1 and 3.5.3 to eliminate an inconsistency between the license condition for the maximum power at which the reactor may >

operate and the Technical Specification for the maximum operating power level j by eliminating the exception to the 1000 kilowatt maximum power limit for the t 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 this testing will be conducted by introducing an -

electrical signal into the circuit. j A copy of the related Safety Evaluation supporting Amendment No. 9 is '

enclosed.

Sincere'ly, original sianed by Alexander Ad'ams, Jr., Project Manager Standardization and Non-Power i Reactor Project Directorate 243 Division of Reactor Projects III, IV, 880226 PDR A  % 8$$ DR V and Special Projects P

Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No. 9 , DISTRIBUTION: , "
2. Safety Evaluation CDocket F11e' LRubenstein JPartlow NRC & Local PDRs DCRutchfield TBarnhart (4) l cc w/ enclosures: PDSNP Reading OGC-ROCKVILLE WJones See next page EHylton DHagan EButcher AAdams EJordan ACRS (10)

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February 11, 1988 Docket No. 50-243 Dr. A. G. Johnson, Director Radiation Center Oregon State University Corvallis, Oregon 97331 .

Dear Dr. Johnson:

SUBJECT:

ISSUANCE OF AMENDMENT NO. 9 TO FACILITY OPERATING LICENSE NO. R-106 - OREGCN STATE UNIVERSITY TRIGA REACTOR (OSTR) .

The Commission has issued the enclosed Amendment No. 9 to Facility Operating ,

License No. R-106 for the Oregon State University TRIGA reactor. The amendment  !

consists of changes to the Technical Specifications in response to your  !

submittals dated July 19, 1983 and October 12, 1987. j The amendment changes the organizational structure of the OSTR. Also, the i surveillance requirements time intervals are updated to be in agreement with .

current practice for non-power reactors. (

In addition to these changes, to make the license condition more complete, we have discussed with your staff and have amended Paragraph 2.C.(1) of Facility l Operating License No. R-106 to include the maximum reactivity insertion j allowed in the pulse mode. We have also discussea with your staff and have  ;

changed Technical Specification 3.1 and 3.5.3 to eliminate an inconsistency j between the license condition for the maximum power at which the reactor may  ;

operate and the Technical Specification for the maximum operating power level j by eliminating the exception to the 1000 kilowatt maximum power limit 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 this testing will be conducted by introducing an  ;

electrical signal into the circuit.  ;

i A copy of the related Safety Evaluation supporting Amendment No. 9 is enclosed.

< Sincerely, 1

original siened bv I

. Alexander Ad'ams, Jr., Project Manager  :

l Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No. 9 DISTRIBUTION:
2. Safety Evaluation Docket File LRubensteir. JPartlow NRC & Local PDRs DCRutchfield TBarnhart (4) cc w/ enclosures: PDSNP Reading OGC-ROCKVILLE WJones See next page EHylton DHagan EButcher AAdams EJordan ACRS (10)

, A/PA ARM /LFMB v

L PDSNP PDQdL)i tj OGC-BETH l PSSHP fyiton AAda LRubenstein l OI/6/88 02/$ /88 02/i'/88 02/ / >/88

/ 'o g UNITED STATES NUCLEAR REGULATORY COMMISSION

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February 11, 1988 k ..... p Docket No. 50-243 ,

Dr. A. G. Johnson, Director Radiation Center Oregon State University Corvallis, Oregon 97331

Dear Dr. Johnson:

SUBJECT:

ISSUANCE OF AMENDMENT NO. 9 TO FACILITY OPERATING LICENSE

. NO. R-106 - OREGON STATE UNIVERSITY TRIGA REACTOR (OSTR)

The Commission has issued the enclosed Amendment No. 9 to Facility Operating License No. R-106 for the Oregon State University TRIGA reactor. The amendment consists of changes to the Technical Specifications in response to your submittals dated July 19, 1983 and October 12, 1987.

The amendment changes the organizatfonal structure of the OSTR. Also, the surveillance recuiremeats time intervals are updated to be in agreement with current practice for .-power reactors.

'In addition to these changes, to make the license condition more complete, we have discussed with your staff and have amended Paragraph 2.C.(1) of Facility Operating License No. R-106 to include the maximum reactivity insertion allowed in the pulse mode. We have also discussed with your staff and have changed Technical Specification 3.1 and 3.5.3 to eliminate an inconsistency between the license condition for the maximum power at which the reactor may operate and the Technical Specification for the maximum operating power level ,

by eliminating the exception to the 1000 kilowatt maximum power limit for the purpose of safety circuit testing. Safety circuits must be tested by a i method other than raising the reactor power level above the licensed limit. '

We understand that this testing will be conducted by introducing an electrical signal into the circuit.

A copy of the related Safety Evaluation supporting Amendment No. 9 is enclosed.

Sincerel ,

hah- .,

fro- et anager l

l Alexander'4 dams,Jr.,dn Standardization and N ower Reacter Project Dire' torate i Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation ]

Enclosures:

l

1. Amendment No. 9  !
2. Safety Evaluation J cc w/ enclosures-See next page j

Oregon State University Docket No. 50-243 cc: Mayor of the City of Corvallis Corvallis, Oregon 97331 ,

Mr. Donald W. Godard, Administrator Siting and Regulation Oregon Dept. of Energy Labor and Industries Bldg.

Room 111 Salem, Oregon 97310 4

A O 4

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