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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20212D4441999-09-20020 September 1999
Amend 31 to License R-103,authorizing Conduct of Moveable & Unsecured Experiments in Center Test Hole of Reactor
ML20203H4121998-02-26026 February 1998
Amend 30 to License R-103,clarifying TS Requirements for Procedures for Preparation for Shipment of Byproduct Matl Produced Under Reactor License
ML20136D7161997-03-0606 March 1997
Amend 29 to License R-103,changing Aspects of Administrative Structure Having Oversight Authority for MURR & Correcting Inconsistency in TS Re Meeting Requirements of Reactor Advisory Committee
ML20149H0631994-11-0404 November 1994
Amend 27 to Amended License R-103,allowing Installation of Single Pool Cooling Sys Heat Exchanger in Place of Two Existing Heat Exchangers
ML20141M5701992-08-17017 August 1992
Amend 22 to License R-103,removing Temporary Possession Limit Increases in Special Nuclear Material Granted by Amends 19 & 21
ML20058K9651990-08-0101 August 1990
Amend 20 to License R-103,revising Tech Specs to Allow Use of Extended Life Aluminide Fuel
ML20246M1311989-05-0808 May 1989
Amend 18 to License R-103,shifting Administrative Authority to Univ of Missouri at Columbia
ML20235J7581989-02-16016 February 1989
Amend 17 to License R-103,correcting Error in Requested Change to Tech Spec 6.1.c Issued as Amend 16 on 881020 Re Univ Administration
ML20205B3251988-10-20020 October 1988
Amend 16 to License R-103,authorizing Increase in Amount of Depleted U That May Be Received,Possessed & Used from 20 Kg to 50 Kg
1999-09-20
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20212D4441999-09-20020 September 1999
Amend 31 to License R-103,authorizing Conduct of Moveable & Unsecured Experiments in Center Test Hole of Reactor
ML20206K7441999-05-0404 May 1999
Application for Amend to License R-103,changing Tech Specs 3.6.e That Would Authorize Movable & Unsecured Experiments in Ctr Test Hole as Allowed in All Other Experimental Regions of Reactor
ML20203H4121998-02-26026 February 1998
Amend 30 to License R-103,clarifying TS Requirements for Procedures for Preparation for Shipment of Byproduct Matl Produced Under Reactor License
ML20199B7781998-01-22022 January 1998
Application for Amend to License R-103,revising TS 6.1.b, as Part of follow-up Actions to 971103-07 Insp Concern Re Procedures Used for Preparation of Byproduct Matl for Shipping
ML20136D7161997-03-0606 March 1997
Amend 29 to License R-103,changing Aspects of Administrative Structure Having Oversight Authority for MURR & Correcting Inconsistency in TS Re Meeting Requirements of Reactor Advisory Committee
ML20134F3261996-10-29029 October 1996
Application for Amend to License R-103,requesting Approval to Revise Figure 6.0 of TS 6.1,administrative Structure Showing Line of Authority for Mgt & Operation of Umrr & TS 6.1.d
ML20078N5011995-02-0707 February 1995
Application for Amend to License R-103,increasing Stable U-235 Possession Limit from 45 Kg to 60 Kg & Increasing U-235 Temporary Possession Limit to 75 Kg Until 970331
ML20149H0631994-11-0404 November 1994
Amend 27 to Amended License R-103,allowing Installation of Single Pool Cooling Sys Heat Exchanger in Place of Two Existing Heat Exchangers
ML20065E0591994-03-28028 March 1994
Application for Amend to License R-103,revising TS in Order to Replace Parallel 50% Capacity Pool Sys HXs W/Single New 100% Capacity HX
ML20065B9361994-03-28028 March 1994
Application for Amend to License R-103 to Temporarily Increased Limit for Possession,Receipt & Use of Contained U-235 to 60 Kg Until 950531
ML20058L8841993-12-10010 December 1993
Application for Amend to License R-103,revising TS 6.1.h.(4) to Submit half-yr Rept (930701-1231) Containing Radiological Health Sections That Demonstrates Compliance W/Existing 10CFR20 within 60 Days of 931231
ML20141M5701992-08-17017 August 1992
Amend 22 to License R-103,removing Temporary Possession Limit Increases in Special Nuclear Material Granted by Amends 19 & 21
ML20099B9201992-07-28028 July 1992
Suppls 920702 Application for Amend to License R-103 to Replace 920702 Amend Request & to Include Addl Phrases & Clarifications of License Conditions 2.B.(2) & 2.B.(3)
ML20101M3761992-07-0202 July 1992
Application for Amend to License R-103,rescinding Temporary SNM Possession Increases Requested in 891226 & s to Reflect Establishment of Capability for Offsite Shipment of Spent Fuel Using BMI-1 Shipping Cask
ML20058K9651990-08-0101 August 1990
Amend 20 to License R-103,revising Tech Specs to Allow Use of Extended Life Aluminide Fuel
ML20042D4361989-12-26026 December 1989
Application for Amend to License R-103,increasing Matl Possession Limit to 60 Kg U-235.Criticality Aspects of Fuel Storage Not Changed by Requested Amend
ML20246M1311989-05-0808 May 1989
Amend 18 to License R-103,shifting Administrative Authority to Univ of Missouri at Columbia
ML20248G8651989-03-31031 March 1989
Application for Amend to License R-103,shifting Administrative Authority to Univ of Missouri-Columbia
ML20235J7581989-02-16016 February 1989
Amend 17 to License R-103,correcting Error in Requested Change to Tech Spec 6.1.c Issued as Amend 16 on 881020 Re Univ Administration
ML20196C0311988-11-30030 November 1988
Application for Amend to License R-103,revising Tech Spec 6.1.e Re Additions,Mods or Maint to Sys
ML20205B3251988-10-20020 October 1988
Amend 16 to License R-103,authorizing Increase in Amount of Depleted U That May Be Received,Possessed & Used from 20 Kg to 50 Kg
ML20210B7581986-09-12012 September 1986
Application for Amend to License R-103,revising Tech Specs to Base Specs on Technical Limits Instead of Values for Specific Fuel Element Loading
ML20155K5731986-05-21021 May 1986
Application for Amend to License R-103,revising Section 2.B.(4) to Permit Up to 20 Kg Each of Normal & Depleted U & Thorium Based on Proposed Study of Effects of few-eV Neutrons for Therapy
ML20137Y5461985-11-22022 November 1985
Application for Amend to License R-103,changing Tech Specs to Replace Obsolete Administrative Title,Correct Tech Spec 5.1 Ref to Bldg Leak Rate Design Limits,Replace Refs to AEC W/Nrc & Reflect Change in Organizational Structure
ML20069P8341982-12-0303 December 1982
Application for Amend to License R-103,increasing Inventory of Irradiated Fuel
ML20002C6451980-11-14014 November 1980
Application by Cb Edwards for Renewal of Senior Operator License SOP-1123
ML20002C6481980-11-14014 November 1980
Application by Ne Tritschler for Renewal of Senior Operator License SOP-2863
ML19263D6091979-01-22022 January 1979
Application for Renewal of Senior Operator License 2426
1999-09-20
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Text
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Uc uq O" & UNITED STATES l , ,g .g NUCLEAR REGULATORY COMMISSION i
, t WASHnNGTON, D.C. 30666-4001
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UNIVERSITY OF MISSOURI- COLUMBIA DOCKET NO. 50-186 AMENDMENT TO AMENDED FACILITY LICENSE Amendment No. 31 License No. R-103
- 1. The U.S. Nuclear Regulatory Commission (the Commission)'has found that A. The application for an amendment to Amended Facility License No. R-103 filed by the University of Missouri- Columbia (the licensee) on May 4,1999, as supplemented on July 23,1999, conforms to the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as stated in Chapter I of Title 10 of the Code of FederalRegulations (10 CFR);
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) such activities will be conducted in complia.nce with the regulations of the Commission; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. This amendment is issued in accordance with the regulations of the Commission as I stated in 10 CFR Part 51, and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105 and publication of a notice for this amendment is not required by 10 CFR 2.106.
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this lice.nse amendment, and paragraph 3.B. of Amended Facility License No. R-103 is hereby amended to read as follows:
3.B. Technical Specifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 31, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. i
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Marsh, Chief .
Event Assessment, Generic Communications and Non-Power Reactors Branch l Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation
Enclosure:
Appendix A, Technical Specifications Changes -
4 Date of issuance: SepW 20,1999 I
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l ENCLOSURE TO LICENSE AMENDMENT NO. 31 AMENDED FACILITY LICENSE NO. R-103 l
DOCKET NO 50-18Q i
I Replace the following pages of Appendix A, " Technical Specifications," with the enclosed pages. The revised pages are identified by amendment number and contain verticallines i indicating the areas of change.
f Remove n 1.n31r1 3.6 - 2 3.6 -2 3.6 - 4 3.6 -4 l
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TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY '
Number 3.6 Page 2 of 5 Date September 20,1999 Amendment No. 31 l
SUBJECT:
Exoeriments (continued) airbome concentration of radioactivity averaged over a year will not exceed the limits of Appendix B, Table I of 10 CFR Part 20. Exception: Fueled experiments (See Specification 3.6.a).
- d. Explosive materials shall not be irradiated or allowed to generate in any experiment in quantities over 25 milligrams.
- e. Only movable experiments in the center test hole shall be removed or installed l with the reactor operating. All other experiments in the center test hole shall be l removed or installed only with the reactor shut down. Secured experiments shall l be rigidly held in place during reactor operation. l
- f. Experiments shall be designed and operated so that identifiable accidents such as loss of reactor coolant flow, loss of experiment cooling, etc., will not result in a release of fission products or radioactive materials from the experiment.
- g. Experiments shall be designed such that a failure of an experiment will not lead to a direct failure of other experiments, a failure of reactor fuel elements, or to interference with the action of the reactor control elements or other operating components.
- h. Cooling shall be provided to prevent the surface temperature of a submerged inadiated experiment from exceeding the saturation temperature of the cooling medium.
TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 3.6 Page 4 of 5 Date September 20,1999 Amendment No. 31
SUBJECT:
Exoeriments(continued)
- o. Fueled experiments containing inventories oflodine 131 through 135 greater than 1.5 Curies or Strontium 90 greater than 5 millicuries shall be vented to the exhaust stack system through HEPA and charcoal filters which aie continuously monitored for an increase in radiation levels.
Bases
- a. Specification 3.6.a restricts the generation of hazardous materials to levels that can be handled safely and easily. Analysis of fueled experiments containing a greater inventory of fission products has not been completed, and therefore their use is not permitted.
- b. Specification 3.6.b is intended to reduce the likelihood of accidental voiding in the core or water annulas surrounding the center test hole by restricting materials which could generate or accumulate gases or vapors.
- c. The limitation on experiment materials imposed by specification 3.5.c assures that the limits of Appendix B of 10 CFR 20 are not exceeded in the event of an experiment failure.
- d. Specification 3.6.d is intended to reduce the likelihood of damage to reactor or pool components resulting from detonation of explosive materials.
- c. Specification 3.6.e is intended to limit the experiments that can be moved in the center l test hole while the reactor is operating, to those that will not introduce reactivity l transients more severe than one that can be controlled without initiating safety system j action (Ref. Add. 5 to HSR). l l