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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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- R: search Reactor Center Research Park Columbia, Missouri 65211 iI- Telephone (573) 882-4211 FAX [573] 882=3443 UNIVERSITY OF MISSOURI-COLUMBIA October 29,1996 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station PI-37 Washington,DC 20555 REIERENCE: Docket 50-186 University of Missouri Research Reactor Licensa R-103
SUBJECT:
l'echnics . Specification changes requested pursuant to 10CFR50.59(c) and 10CF' J.90.
The University of Missouri Research Reactor (MURR) requests approval to revise Figure 6.0 of Technical Specification 6.1 and Technical Specification 6.1.d. as described and evaluated below:
A) Proposed Chawes to Fieure 6.0:
Figure 6.0 of Technical Specification 6.1 is the administrative structure showing the line of authority for the management and operation of the University of Missouri Research Reactor ;
(MURR). '
The University of Missouri requests three rev.% ions to the administrative structure. The first revision request is to delete the specific person (/ ice Provost or Associate Provost) within the Provost's Office to whom the Reactor Director reports. Currently the Director reports to the Vice Provost for Research. The University would like to change this reporting line to the Associate Provost in the Provost's office. The University would like the administrative structure to reflect the Dire : tor reporting to the Office of the Provost rather than a specific person in the Office of the Provost, albwing the University the flexibility to delegate the responsibility and authority for MURR to the appropriate person in the Office of the Provost. The Provost will assure the assignment of n:sponsibility will not decrease the effectiveness of management oversight of MURR. This is consistent with ANSI /ANS-15.1, "The Development of Technical Specifications for Research Reactors," Section 6.1.2 where it states " responsibilities of one level may be assumed by designated alternates or by higher levels, conditional upon appropriate qualifications."
NUREG-1537, " Guidelines for Preparing and Review of Applications for Licensing of Non-Power Reactors," Section 14, Technical Snecifications. states the NRC accepts the responsibility ;
guidance provided in ANSI /ANS- 15.1.
/
9611050165 961029 PDR A' P ADOCK 05000186 /l PDR 050079 1
1 Letter to Director of Nuclear Reactor Regulation October 29,1996 Page two l
The second revision request is to have the Reactor Advisory Committee be appointed by and report l to the Office of the Provost,instead of the Chancellor. This request is consistent with the guidance !
in ANSI /ANS 15.1, under organization structure regarding the reporting and communications lines for the reactor review group designated to advise reactor management (in our case, tue Reactor Advisory Committee). i The third revision request does not involve a change to the direct line of authority, but substitutes a new communications / consultation link from the MURR Health Physics Manager to University of l Missouri upper administration in place of the communications / consultation link from the Facility Director via the Radiation Safety Officer (RSO) for the University of Missouri System materials ;
license (#24-00513-32) to the Vice President for Academic Affairs. Before July 1993, the University of Missouri System materials license provided oversight for authorized activities involving licensed radioactive materials at the UM-Columbia campus, including at the MURR. At that time, in a shift from central oversight and managemere, the University was granted five ,
individual broadscope materials licenses, one for each cartpus and one for MURR. l l
Now that MURR has its own broadscope materials license, the UM-Columbia materials license RSO has no direct responsibility for radiation protection for broadscope materials use at the i MURR. The consultation / communications link therefore serves little purpose.
We feel that the Technical Specification administrative organizational chart for the R-103 license ,
should be revised to include a different consultation / communications link fmm the Health Physics l Manager to upper administration. This link would formalize a line of communication for the Reactor Health Physics Manager to use if there were unaddressed radiation protection concerns at MURR.
B) Pronosed Change to Technical Soccification 6JgL: .
l The last two sentences of Technical Specification 6.1.d. state:
"The Reactor Advisory Committee shall meet at least once during each calendar quarter.
A meeting of a subcommittee shall not be deemed to satisfy the requirement of the parent committee meeting quarterly."
We would like the second sentence to be revised to be consistent with the preceding sentence regarding the schedule for Reactor Advisory Committee meetings. We request the second sentence be revised to read: ,
"A meeting of a subcommittee shall not be deemed to satisfy the requirement of the parent committee meeting at least once during each calendar quarter."
The inconsistency between the two existing sentences results from the difference between " meeting at least once each calendar quarter" and the Technical Specification definition of quanerly implied by T.S.1.2 regarding interpretation of time intervals. Quarterly implies meetings will be held within four months of each other. Meetir,g each calendar guarter implies meetings will occur within four distinct three month periods with no specified mterval between meetings.
The University finds that meeting each calendar quarter is conducive to long term planning and scheduling of meetings for the non-MURR Reactor Advisory Committee members.
)
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e 0
l Letter to Director of Nuclear Reactor Regulation '
October 29,1996 '
Page three i !
4 q
j Attached are the Technical Specification pages that will implement the proposed changes described P
in this letter. The administrative change proposed for Figure 6.0 continues to meet the administrative needs of a Class 104 license as outlined in Section 6.0 of ANSI /ANS-15.1 (1990)
- " Development of Technical Specifications for Research Reactors." i These requested changes have no affect on the safety of reaction operations, no reduction in 1
management oversight,' involve no changes to the reactor safety systems; and are requested j pursuant to 10CFR50.59(c) and 10CFR50.90. 4 j~ If you have any questions, please call me or J. Charles McKibben at (314) 882-4211.
4 i Sincerely, ENDORSEMENT:
Reviewedand App ved 4
h i
J AL FM '
3 Walt A. Meyer, Jr." J. Charles McKibben
- Reactor Manager Interim Director attachments xc
- Reactor Advisoty Committee RAC Safety Subcommittee j i
Dr. Elaine Charlson, Associate Provost i Mr. Tim Reidinger, U.S. NRC, Region III i
- Mr. Al Adams, U.S. NRC, Washington, D.C.
h i
M ]tlAS l 0 QUt1STINE M.ERRANTE Noisy Public-Notary Seal STNIE OF MISSOURI Boone County My twnminalen Expires: April 14,1999
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