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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20209C8901999-07-0808 July 1999 Application for Renewal of License R-37 & Increase in Reactor Power from 5000 Kw to 6000 Kw.Listed Repts Are Encl, Per NRC ML20207E4501999-05-27027 May 1999 Application for Amend to License R-37 to Change Basis of TS 3.10 as Listed.Ts Page 3-29 Included ML20217G2091997-10-0303 October 1997 Application for Amend to License R-37,permitting Operation of Subcritical Fission Converter Facility to Provide Superior Epithermal Neutron Beam for Program on Neutron Capture Therapy.Also Includes SER & Proposed TS ML20100J9711996-02-23023 February 1996 Application for Amend to License R-37 for Temporary Increase in Possession Limit for U-235 from 29 Kg to 41 Kg.Safety Review 0-96-2 Encl ML20079A0991995-02-22022 February 1995 Application for Amend to License R-37,revising Surveillance Frequency Requirement for One Cell of Emergency Battery Sys. W/Encl ML20059E3021993-10-29029 October 1993 Application for Amend to License R-37,authorizing Temporary Increase in Possession Limit for U-235 from 29 Kg to 41 Kg ML20085D7691991-10-11011 October 1991 Application for Amend to License R-37,authorizing Continuation of Temporary Increase in Possession Limit for U-235 from 29 Kg to 41 Kg Due to Continued Unavailability of Shipping Cask for Transfer of Spent Fuel Offsite ML20235K6071989-02-14014 February 1989 Application for Amend to License R-37,increasing Possession Limit for U-235 in Paragraph 2B(2) of License to 45 Kg. Related Info Encl ML20235J0621989-02-13013 February 1989 Application for Amend to License R-37,revising Tech Spec Re Fission Density Limit & Changing Percentage of Voids Permitted in UA1(x) Type Fuel ML20112J1631985-01-11011 January 1985 Application to Amend License R-37,revising Tech Specs Governing Variable Reactivity & Performance of Experiments Re Closed Loop Control of Reactor Power ML20079J9211982-12-22022 December 1982 Application to Amend License R-37,consisting of Tech Spec Changes Revising Frequencies for Surveillance Testing of ECCS & Charcoal Filters in Bldg Pressure Relief Sys & Revision 28 to SAR Revising Testing Frequency for ECCS ML19345H4171981-05-14014 May 1981 Application to Amend License R-37,changing Tech Spec 3.10 Re Fuel Element & Core Component Handling & Storage.Forwards Revision 21 to Sar,Revising Description & Analysis of Fuel Handling & Storage Facilities ML20235K6811975-09-25025 September 1975 Application for Amend to License R-37,reducing Possession Limit for U-235 to 29 Kg 1999-07-08
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20209C8901999-07-0808 July 1999 Application for Renewal of License R-37 & Increase in Reactor Power from 5000 Kw to 6000 Kw.Listed Repts Are Encl, Per NRC ML20207E4501999-05-27027 May 1999 Application for Amend to License R-37 to Change Basis of TS 3.10 as Listed.Ts Page 3-29 Included ML20217G2091997-10-0303 October 1997 Application for Amend to License R-37,permitting Operation of Subcritical Fission Converter Facility to Provide Superior Epithermal Neutron Beam for Program on Neutron Capture Therapy.Also Includes SER & Proposed TS ML20137L5741997-04-0303 April 1997 Amend 30 to License R-37,allowing Mit to Conduct boron-neutron Capture Therapy on Patients from NRC & Agreement State Medical Use Licensees Whose Licenses Contain boron-neutron Specific Conditions ML20100J9711996-02-23023 February 1996 Application for Amend to License R-37 for Temporary Increase in Possession Limit for U-235 from 29 Kg to 41 Kg.Safety Review 0-96-2 Encl ML20079A0991995-02-22022 February 1995 Application for Amend to License R-37,revising Surveillance Frequency Requirement for One Cell of Emergency Battery Sys. W/Encl ML20059E3021993-10-29029 October 1993 Application for Amend to License R-37,authorizing Temporary Increase in Possession Limit for U-235 from 29 Kg to 41 Kg ML20128P4301993-02-16016 February 1993 Amend 27 to License R-37,adding Requirements to TSs for Use of MITR-II Medical Therapy Facility Beam for Human Therapy ML20085D7691991-10-11011 October 1991 Application for Amend to License R-37,authorizing Continuation of Temporary Increase in Possession Limit for U-235 from 29 Kg to 41 Kg Due to Continued Unavailability of Shipping Cask for Transfer of Spent Fuel Offsite ML20235K6071989-02-14014 February 1989 Application for Amend to License R-37,increasing Possession Limit for U-235 in Paragraph 2B(2) of License to 45 Kg. Related Info Encl ML20235J0621989-02-13013 February 1989 Application for Amend to License R-37,revising Tech Spec Re Fission Density Limit & Changing Percentage of Voids Permitted in UA1(x) Type Fuel ML20112J1631985-01-11011 January 1985 Application to Amend License R-37,revising Tech Specs Governing Variable Reactivity & Performance of Experiments Re Closed Loop Control of Reactor Power ML20079J9211982-12-22022 December 1982 Application to Amend License R-37,consisting of Tech Spec Changes Revising Frequencies for Surveillance Testing of ECCS & Charcoal Filters in Bldg Pressure Relief Sys & Revision 28 to SAR Revising Testing Frequency for ECCS ML20054K0831982-06-11011 June 1982 Corrected Page 2 to Amend 21 to License R-37,issued 820528 ML19345H4171981-05-14014 May 1981 Application to Amend License R-37,changing Tech Spec 3.10 Re Fuel Element & Core Component Handling & Storage.Forwards Revision 21 to Sar,Revising Description & Analysis of Fuel Handling & Storage Facilities ML20235K7001975-11-17017 November 1975 Amend 11 to License R-37,reducing Quantity of U-235 to 29 Kg ML20235K6811975-09-25025 September 1975 Application for Amend to License R-37,reducing Possession Limit for U-235 to 29 Kg ML20235K6491975-07-23023 July 1975 Amend 10 to License R-37,authorizing Operation of Modified Reactor & Use of Addl 27.5 Kg U-235 1999-07-08
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. MASSACHUSETTS INSTITUTE OF TECHNOLOGY O. K. HARLING 138 Albany Street. Cambridge, Mass. 02139 4296 J. A. BERNARD lJR.
Director Telefax No (617) 253-7300 Director of Reactor Operations.
Telex No. 92-1473-MIT CAM Tel. No.(617) 253 4202 29 October 1993 ,
U.S. Nuclear Regulatory Commission ,
Washington, D.C. 20555 Attn.: Document Control Desk
Subject:
Expiration of Temporary Increase in U-235 Possession Limit for License No.
R-37, Docket No. 50-20, Massachusetts Institute of Technology Research Reactor Gentlemen:
Amendment No. 26 to License No. R-37 (MIT Research Reactor) authorized a temporary increase in the possession limit for U-235 from 29 kg to 41 kg. The reason for that increase was to perniit continued facility operation pending the return of spent fuel to the U.S. Department of Energy (DOE). This temporary increase expires 31 December '
1993. We are pleased to report that we were able to return a substantial portion of our inventory of spent fuel to DOE and that, as a result, our inventory is now below the i original 29 kg limit. Accordingly, license amendment No. 26 should be allowed to expire.
This will occur automatically and no action is needed by either MIT or NRC.
As you are aware, the U.S. Department of Energy has not yet established a
, pemianent arrangement for the return of spent fuel from research reactors and it is unlikely that any returns will be possible after mid 1994. Accordingly,it is possible that MIT will require a reissuance of a temporary increase in the possession limit at some point in the future, perhaps as early as a year from now (October 94). In this regard, the following information may be of use:
't Temporary possession limit: 41.0 kg Inventory prior to 1 ilreturn to DOE: 36.5 kg Pemianent possession limit: 29.0 kg Current inventory: 25.9 kg Inventory if remaining spent fuel were returned to DOE: 18.9 kg Our present inventory (25.9 kg) would allow us to receive six additional elements. If one ,
, accounts for the depletion of the existing fuel that will occur over the next year, then several onn n, gI 0, 9311030162 931029 m PDR P
ADOCK 05000020 l pyg W[5; ;
"U.S. Nuclear Regulatory Commission
. Page 2 more elements could be obtained. However, it is evident that the 29 kg limit would.
,be approached fairly soon. Accordingly, a reissuance of the temporary possession limit may be necessary. The only alternative would be for DOE to' accept the return of our-remaining spent fuel. This would lower the current inventory to 18.9.kg and probably allow continued operation until the time at which DOE now estimates that it will be able to-accept returns of spent fuel on a routine basis. We are pursuing this option.
Sincerely, I <- ( 6( k ohn A. Bernard, P .D. l Director of Reactor Operations i MIT Research Reactor -
JAll/CRM cc: USNRC - Project Manager, NRR/ONDD ,
USNRC - Region I - Chief, Effluents Radiation Protection Section (ERPS)
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