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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20206K7441999-05-0404 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 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 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 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 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 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 ML20248G8651989-03-31031 March 1989 Application for Amend to License R-103,shifting Administrative Authority to Univ of Missouri-Columbia 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 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 1999-05-04
[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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REFERENCE:
l Docket 50-186
- University of Missouri Research Reactor E
, License R-103 '
SUBJECT:
Request s C' hange to Technical Specification 3.6.e Pursuant to 10 CFR50.59(c) .
and 10CFR50.90 De University of Missouri Research Reactor ' (MURR) requests a change to Technical Specification 3.6.e that would authorize movable and unsecured experiments in the center test hole as are allowed in all other
% experimental regions of the reactor. Technical Specification (T.S.) 1.6 defines Flux Trap as "Ihat portion of the reactor through the center of the core bounded by the 4.5 inch inside diameter tube and 15 inches above and below the core vertical center line." T.S.1.3 defines the center test hole as "The volume in the flux trap occupied by the removable experiment test tubes." His request is to expand the allowable experiments in the center test hole from secured experiments to include movable and unsecured experiments.
Movable, secured and unsecured experiments are defined in Technical Specifications as followc T.S.1.11 Movable Experiment "A movable experiment is one which is designed with the intent that it may be moved into and out of the reactor while the reactoris operating." ~ ' , .
T.S.1.24 Secured Expenment "A secured experiment is any experiment which is rigidly held in place by mechanical means with sufficient restraint to withstand any anticipated forces to which the experiment might be subjected."
T.S.1.25 Unsecured Expenment "An unsecured experiment is any experiment widch is not secured as defined in T.S.1.24, or the moving parts of secured experiments when they are in motion." ;
Technical Specifications 3.1.g through 3.1.k places limits on: the reactivity worth of each secured removable experiment, total for all experiments in the center test hole, each movable experiment, each unsecured experiment, and total for all unsecured experiments. No' change is requested to these limits. De limits for movable and unsecured experiments are based on Hazards Summary Report (HSR) Addendum 5 section 3-
" Step Reactivity insertion Analysis for Determination of Experiment Reactivity Limits."
Technical Specification 3.6.c currently stateithat " experiments in the center test hole shall be removed or installed only with the reactor shutdown and shall be rigidly held in place during reactor operation." Original HSR (July 1; 1%5) in section 8.2, Flux Tran. imposed this " , , ; high degree of administrative control to minimize me possibility ofinserting or removing a sample which would result in increased reactivity . . ."
and to eliminate the possibility of imerting or removing a sample which could result in a large reactivity.
effect. This section of the HSR also recognized that at some point in time adequate information would be obtained, which would allow removing this restriction on use of the center test hole. Page 8-3 of Original HSR states:-
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"It is feh that alternate'means for usage of this facility should be provided only after operational . .~
- . experience has provided complete data on reactivity value. ' At some future date, after the acquiring x of suitable information pertaining to the flux trap' worth, a request will be made to the AEC [NRC) ? ' '
fs . for license amendment to permit insertion and removal of samples during reactor operation."
< The Original HSR under Accident Analysis also states on page 13-2:; 4
$ a4 d j.*The initial use of the center test hole will be limited to ' xperiments e Ehich can be moved or altered -
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q( '+' ; only aAer reactor shutdownc It is intended however that at some future date techniques for an 2
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4 request be submitted to the Atomic Energy Commission [NRC] for an addendum to the operating -i license to alter the mode of sample entry into the flux trap position."
he basis for T.S. 3.6.e states: "Although the reactivity worth of experiments in the center test hole is restricted to less than the reactivity insertion which could cause fuel element failure, this specification .
climinates a potential rnechanism for uncontrolled addition of reactivity "
It is requested to revise the Technical Specification 3.6.e to read as:
Only movable experiments in the center test hole shall be removed or installed with the reactor operating. All other experiments in the center test hole shall be removed or installed only with the reactor shut down. Secured experirnents in the center test hole shall be rigidly held in place during reactor operation.
During the intervening years since the Original HSR was written we have refined our rneasurements and our methods to characterize the reactivity of samples at specific heights in the center test hole. The experiments --
in the center test hole are run in aluminum cans. Approximately 20,000 different sample cans have been irradiated in the center test hole accumulating 50,000 can-weeks of experience. The target material has varied from large neutron absorbers like boron and iridium to small absorbers like aluminum and sulfur.
After 30 years of this operating experience, there no longer is the uncertainty about reactivity worth of experiments in the flux trap as there was before the reactor was taken critical. ne uncertainty, which created the need to impose the limitation, is no longer valid so we are requesting the unnecessary limitation be removed.
The safety evaluation in liSR Addendum 5 shows that movable experiments with reactivity worth not to exceed 0.001 Ak and unsecured experiments with reactivity worth not to exceed 0.0025 Ak do not create a safety problem. It is based on the affect of a step insertion of reactivity and thercibre limits the reactivity worth for these two classes of experiments. His analysis is applicable for any location of the sample.
It is requested to change the basis for T.S. 3.6.e to: q
'i Specification 3.6.e is intended to limit the experiments that can be moved in the center test hole j while the reactor is operating, to those that will not introduce reactivity transients more severe than one that can be controlled without initiating safety system action (Ref. Add. 5 to HSR).
Attached for your reference are revised Technical Specification pages with this change incorporated. If there are any further questions, please contact me at (573) 882 52% or Charlie McKibben at (573) 882-5204.
Sincerely, Reviewedand Approved:
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Anthony Schoone J. Charles McKibben Reactor Manager Associate Director attachments
- xc: Mr. Al Adams. USNRC M Mr. Tom Burdick, USNRC, Region til Dr. Edward Deutsch CHRISTINE M.ERRANTE Notary Public-State of Missotsi countyor soon.
My Commission Expires 04/142003