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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20199B9621998-01-26026 January 1998
Application for Amend to License R-83,changing TS to Include Listed Paragraph,Inserted as Paragraph 3.6.2(c). Proprietary SER Is Forwarded for Complete Regulatory Review of Application.Proprietary Encl Withheld
ML20148G5561997-05-26026 May 1997
Application for Amend to License R-83,changing License Condition II.B.3 & Adding License Condition II.B.7.Draft NSC Health Physics Procedure Formalizing Quarterly & Semiannual Sealed Source Leak Checks,Encl
ML20137Z0341997-04-15015 April 1997
Application for Amend to License R-83,adding License Condition II.B.3 for Disposal of LLW Similar to Conditions in NRC Matl Licenses
ML20115G5331996-07-15015 July 1996
Application for Amend to License R-83,allowing Steady State Operation Up to 1500 Kilowatts (Thermal).Increased Power Level Will Provide Improved Experimental Conditions for Various Reactor Users
ML20056H4451993-08-24024 August 1993
Application for Amend to License R-83 & Indemnity Agreement E-12 to Allow Greater Flexibility in Possession & Storage of Radioactive Matls Use to Support Research & Development within Nuclear Science Center Site
ML20085C7161991-09-10010 September 1991
Application for Amend to License R-83,appointing Wd Reece as DE Feltz Replacement as Director of Nuclear Science Ctr. Wd Reece Resume Re Academic & Professional Experience Encl. Encl Withheld
ML20247B9831989-09-0404 September 1989
Application for Amend to License R-83,revising Nuclear Science Ctr Reactor Organizational Structure & Changing Reporting Requirements of Reactor Administration Personnel
ML20196B9151988-01-21021 January 1988
Application for Amend to License R-83,changing Administration of Nuclear Science Ctr Reactor Per Tech Specs 6.1.1 by Replacing Position of Head,Nuclear Engineering Research W/Director,Nuclear Research Reactor Programs
ML20202G6971986-07-11011 July 1986
Application for Amend to License R-83,increasing Total Controlled Inventory of I-131 Through I-135 in Fueled Experiment from 1.5 Ci to 10 Ci
ML20070V0181983-02-0101 February 1983
Suppl to Jul 1979 Application for Renewal of License R-83, Consisting of Proposed Changes to Tech Spec 3.8 Re Primary Coolant Conditioning
ML20028F0631983-01-24024 January 1983
Suppl to Jul 1979 Application to Amend License R-83, Changing Tech Specs Re Pulse Mode Operation & Reactor Fuel Elements
ML20053E1261982-05-27027 May 1982
Application for Amend to License R-83,changing Administrative Controls to Require Director,Nuclear Science Ctr,To Rept to Director,Tx Engineering Experiment Station, Through Head of Nuclear Engineering Research
ML19339A6641980-10-20020 October 1980
Application to Change 790902 Request for Renewal of License R-83.Revisions Are Due to Administrative Changes. Safety Evaluation Encl
ML19246A9921979-07-0303 July 1979
Application for Renewal of License R-83
1998-01-26
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20199B9621998-01-26026 January 1998
Application for Amend to License R-83,changing TS to Include Listed Paragraph,Inserted as Paragraph 3.6.2(c). Proprietary SER Is Forwarded for Complete Regulatory Review of Application.Proprietary Encl Withheld
ML20149F3811997-07-15015 July 1997
Amend 14 to License R-83 Modifying License Conditions to Allow Greater Flexibility in Possession & Storage of Radioactive Matls Used to Support Research & Development within Site
ML20148G5561997-05-26026 May 1997
Application for Amend to License R-83,changing License Condition II.B.3 & Adding License Condition II.B.7.Draft NSC Health Physics Procedure Formalizing Quarterly & Semiannual Sealed Source Leak Checks,Encl
ML20137Z0341997-04-15015 April 1997
Application for Amend to License R-83,adding License Condition II.B.3 for Disposal of LLW Similar to Conditions in NRC Matl Licenses
ML20115G5331996-07-15015 July 1996
Application for Amend to License R-83,allowing Steady State Operation Up to 1500 Kilowatts (Thermal).Increased Power Level Will Provide Improved Experimental Conditions for Various Reactor Users
ML20059G0121993-10-26026 October 1993
Amend 13 to License R-83 Modifying License Conditions to Allow Greater Flexibility in Possession & Storage of Radioactive Matls Used to Support Research & Development
ML20056H4451993-08-24024 August 1993
Application for Amend to License R-83 & Indemnity Agreement E-12 to Allow Greater Flexibility in Possession & Storage of Radioactive Matls Use to Support Research & Development within Nuclear Science Center Site
ML20085C7161991-09-10010 September 1991
Application for Amend to License R-83,appointing Wd Reece as DE Feltz Replacement as Director of Nuclear Science Ctr. Wd Reece Resume Re Academic & Professional Experience Encl. Encl Withheld
ML20247B9831989-09-0404 September 1989
Application for Amend to License R-83,revising Nuclear Science Ctr Reactor Organizational Structure & Changing Reporting Requirements of Reactor Administration Personnel
ML20151L6541988-03-23023 March 1988
Amend 11 to License R-83,modifying Title of One Position in Organizational Structure for Station
ML20196B9151988-01-21021 January 1988
Application for Amend to License R-83,changing Administration of Nuclear Science Ctr Reactor Per Tech Specs 6.1.1 by Replacing Position of Head,Nuclear Engineering Research W/Director,Nuclear Research Reactor Programs
ML20202G6971986-07-11011 July 1986
Application for Amend to License R-83,increasing Total Controlled Inventory of I-131 Through I-135 in Fueled Experiment from 1.5 Ci to 10 Ci
ML20070V0181983-02-0101 February 1983
Suppl to Jul 1979 Application for Renewal of License R-83, Consisting of Proposed Changes to Tech Spec 3.8 Re Primary Coolant Conditioning
ML20028F0631983-01-24024 January 1983
Suppl to Jul 1979 Application to Amend License R-83, Changing Tech Specs Re Pulse Mode Operation & Reactor Fuel Elements
ML20058B4891982-07-16016 July 1982
Amend 8 to License R-83,amending Tech Specs Re Administrative Organizational Controls to Require Director of Nuclear Science Ctr to Rept to Director of Tx Engineering Experiment Station
ML20053E1261982-05-27027 May 1982
Application for Amend to License R-83,changing Administrative Controls to Require Director,Nuclear Science Ctr,To Rept to Director,Tx Engineering Experiment Station, Through Head of Nuclear Engineering Research
ML19339A6641980-10-20020 October 1980
Application to Change 790902 Request for Renewal of License R-83.Revisions Are Due to Administrative Changes. Safety Evaluation Encl
ML19246A9921979-07-0303 July 1979
Application for Renewal of License R-83
1998-01-26
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TEXAS ENGINEERING EXPERIMENT STATION TEXAS A&M UNIVERSITY cou.EGE STATION. TEXAS 77843-3575 [~ 'f ll W 1 L NUCLEAR SCIENCE CENTER 409/845-7551 96-0207 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 SUBJEC'; Amendment of Facility Operating Licensu REF: Facility Operating License R-83, Docket No. 50-128
Dear Sir:
i
'It is requested that the Texas A&M University System Nuclear l
Science Center Reactor (NSCR) Facility License R-83 be amended to allow steady state operation up to 1500 kilowatts i.
(thermal). This power level increase will provide improved experimental conditions for the various reactor users.
TRIGA fuel is designed to operate at 2 MW without forced cooling and GenerallAtomics has operated the Mark III reactor at 1.5 MW for many years. A recent safety analysis of the NSCR found the maximum steady-state power density to be 26.82 kW/ element at 1.49 MW. This is below the 32 l kW/ element for the Torrey Pines Mark III and the 28 kW/ element analyzed in the NSCR's original SAR.
We hope to have the license amended by September 1, 1996.
This is near the annual maintenance period for the NSCR and would allow equipment and reactor calibrations at the new power level.
The suppbrting safety analysis and requested changes are i attached for your review.
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l 9607190191 960715 4
PDR ADOCK 05000128 qO Q
1 P PDR RESEARCH AND DEVELOPMENT FOR MANKIND \ \
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96-0207 Page 2 -i l
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If you have any questions concerning this proposed amendment, please contact me or Sean O' Kelly at (409) 845- '
7551. !
Respectfully, 2 I of .
I W.D. Reec h.D. .
Director l WDR/sjm Attachments: Safety Analysis / Requested Changes xc: Dr. B.D. Russell, Deputy Director, TEES Dr. T.S. Michaels, Sr. Project Manager, USNRC Mr. L.J. Callan, Regional Admin, Region IV, USNRC
, 12110/ Central File i l
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Facility Licanos R-83
' Docket 50-128 Proposed Amendment to R-83 It is requested that section C.(1) of the licerme be amended to read as follows:
Maximum Power Level The Texas Engineering Experiment Station / Texas A&M University System is authorized to operate the reactor ;
at a steady state power level up to a maximum of 1500 kilowatts (thermal) and to pulse the reactor in accordance with the limitations in the Technical Specifications. l t
Further, it is requested that Section 3.1.1, Steady State i l Operation, of the Technical Specifications be amended to ;
read i
! i Specifications i The reactor power level shall not exceed 1.5 megawatts ,
under steady state conditions of operation. During l l periods of testing and instrument calibration, the ,
reactor may be operated up to a maximum of 1.75 '
megawatts.
Justification ;
There has been an increase in the demand for the high neutron flux areas of the NSCR in the past few years. A .
reactor power level of 1.5 MW would improve the flux in all I l NSCR experiment locations. The majority of the research j performed at the facility uses neutron activation analysis ;
which would benefit from the power increase. The General Atomic (GA) TRIGA fuel is designed to operate up to 2.0 MW with natural circulation cooling. GA Torrey Pines Mark III and Advanced TRIGA Prototype Reactors operated at 1.5 MW for !
many years. An analysis of an upgrade of the NSCR to 1.49 l MW (1.49 was chosen for academic reasons) has been performed !
and is attached as further support.
The decision to raise steady state reactor power to 1.5 vice 2.0 MW was based on the design capacity of the facility cooling system (2.0 MW cooling tower).
l Additional Safety Analysis l The recent safety analysis (August 1995) found that the
! maximum power density in the core would be 26.82 kW/ element.
j This is below the 28 kW/ element analyzed in the facility l Safety Analysis Report (SAR). Therefore, the SAR is more conservative for the limiting design basis accident and the loss of coolant accident.
I