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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20206K7501999-05-0404 May 1999
Proposed Tech Specs 3.6.e,authorizing Movable & Unsecured & Experiments in Ctr Test Hole as Allowed in All Other Experimental Regions of Reactor
ML20199B7901998-01-22022 January 1998
Proposed Tech Specs Page,Revising TS 6.1.b Re Preparation of Byproduct Matl for Shipping
ML20134F3511996-10-29029 October 1996
Proposed Tech Specs,Requesting to Revise Figure 6.0 of TS 6.1,administrative Structure Showing Line of Authority for Mgt & Operation of Umrr & TS 6.1.d
ML20072R4291994-09-0202 September 1994
Proposed TS 3.3,Page 2 of 5 Re Reactor Safety Sys
ML20065E0681994-03-28028 March 1994
Proposed Tech Specs Involving Change in Pool Coolant Sys Description from Two HX Legs to One HX Leg & Change in Pool Coolant Flow Scram Setpoint to Indicate Measurement of Total Pool Flow Instead of Measurement of Half Pool Flow
ML20055C5591990-05-17017 May 1990
Proposed Tech Specs Re Fuel Elements Used in Reactor Core
ML20248G8701989-03-31031 March 1989
Proposed Tech Specs,Shifting Administrative Authority to Univ of Missouri-Columbia
ML20150A7981987-08-0303 August 1987
Proposed Tech Specs,Authorizing Use in Reactor of Newly Developed Extended Life Aluminide Fuel Element
ML20210B7771986-09-12012 September 1986
Proposed Tech Specs,Reflecting Basis on Technical Limits Instead of Values for Specific Fuel Element Loading
ML20210B7971986-05-0202 May 1986
Spec for Univ of Missouri Fuel Elements Withheld for Univ of Missouri Research Reactor
ML20137Y5531985-11-22022 November 1985
Proposed Tech Spec Changes,Replacing Obsolete Administrative Title,Correcting Tech Spec 5.1 Ref to Bldg Leak Rate Design Limits,Replacing Refs to AEC W/Nrc & Reflecting Change in Administrative Organizational Structure
ML19347C9801981-03-0303 March 1981
Proposed Revision to Tech Spec Sections 1.20(d) & 1.20.b(2), Clarifying Statement of Control Rod Work
ML19341B4931981-01-26026 January 1981
Proposed Revision to Tech Spec 6.1,Figure 6.0,reflecting Administrative Reorganization
1999-05-04
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20206K7501999-05-0404 May 1999
Proposed Tech Specs 3.6.e,authorizing Movable & Unsecured & Experiments in Ctr Test Hole as Allowed in All Other Experimental Regions of Reactor
ML20199B7901998-01-22022 January 1998
Proposed Tech Specs Page,Revising TS 6.1.b Re Preparation of Byproduct Matl for Shipping
ML20134K0201997-02-0707 February 1997
Corrected Pp to MURR Requalification Program
ML20133G3381997-01-0707 January 1997
Revised Operator Requalification Program for Univ of Mo Research Reactor
ML20134F3511996-10-29029 October 1996
Proposed Tech Specs,Requesting to Revise Figure 6.0 of TS 6.1,administrative Structure Showing Line of Authority for Mgt & Operation of Umrr & TS 6.1.d
ML20072R4291994-09-0202 September 1994
Proposed TS 3.3,Page 2 of 5 Re Reactor Safety Sys
ML20065E0681994-03-28028 March 1994
Proposed Tech Specs Involving Change in Pool Coolant Sys Description from Two HX Legs to One HX Leg & Change in Pool Coolant Flow Scram Setpoint to Indicate Measurement of Total Pool Flow Instead of Measurement of Half Pool Flow
ML20127P2781993-01-31031 January 1993
Initial Loading & Testing of Low Enriched U Fuel at Univ of Missouri-Rolla Reactor Facility
ML20055C5591990-05-17017 May 1990
Proposed Tech Specs Re Fuel Elements Used in Reactor Core
ML20248G8701989-03-31031 March 1989
Proposed Tech Specs,Shifting Administrative Authority to Univ of Missouri-Columbia
ML20236G5391987-10-0202 October 1987
Revised Procedure SEP-8, Emergency Equipment Maint Procedure
ML20150A7981987-08-0303 August 1987
Proposed Tech Specs,Authorizing Use in Reactor of Newly Developed Extended Life Aluminide Fuel Element
ML20214G0581986-10-28028 October 1986
SOP HP-30, Evaluation of Exhaust Gas Stack Monitor Filters in Emergency
ML20210B7771986-09-12012 September 1986
Proposed Tech Specs,Reflecting Basis on Technical Limits Instead of Values for Specific Fuel Element Loading
ML20210B7971986-05-0202 May 1986
Spec for Univ of Missouri Fuel Elements Withheld for Univ of Missouri Research Reactor
ML20137Y5531985-11-22022 November 1985
Proposed Tech Spec Changes,Replacing Obsolete Administrative Title,Correcting Tech Spec 5.1 Ref to Bldg Leak Rate Design Limits,Replacing Refs to AEC W/Nrc & Reflecting Change in Administrative Organizational Structure
ML20063F9191981-10-31031 October 1981
Std Operating Procedures
ML19347C9801981-03-0303 March 1981
Proposed Revision to Tech Spec Sections 1.20(d) & 1.20.b(2), Clarifying Statement of Control Rod Work
ML19341B4931981-01-26026 January 1981
Proposed Revision to Tech Spec 6.1,Figure 6.0,reflecting Administrative Reorganization
ML19208A7961979-08-0202 August 1979
SOP Radiation Protection Program,Vol 5, Health Physics.
1999-05-04
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Text
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TECHNICAL SPECIFICATION i
(@*Dff]j?ij-i UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY
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1 Number 6.1 l Page 2 of 8
SUBJECT:
Administration (continue.d) Date i
Board of Curators for the University of Missouri i m l
University President l
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I Chancellor UM-Columbia l M i
! Office of Provost ----------------
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Reactor Manager Reactor Health Physics __j Manager M M 9611050172 961029 Figuro 6.0 PDR ADOCK 05000186 P PDR ,
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9 TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 6.1 Page 4 of 8 Date
SUBJECT:
Administration (continued)
The Reactor Advisory Committee and its subcommittees are to maintain minutes of meetings in which the items considered and the committees recommendations are recorded. Independent actions of the subcommittees are to be reviewed by the parent committee at the next regular meeting. A quorum of the committee or the subcommittees consisting of at least fifty percent of the appointed members must be present at any meeting to conduct the business of the committee, or subcommittee.
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 at least once during each calendar quarter.
- e. Any additions, modifications or maintenance to the systems described in these i
specifications shall be made and tested in accordance with specifications to which the system was originally designed and fabricated or to specifications approved by the U.S. Nuclear Regulatory Commission.
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- f. Following a favorable review by the U.S. Nuclear Regulatory Commission, the I Reactor Advisory Committee, or the Reactor Facility Management as appropriate and prior to conducting any experiment, the Reactor Manager shall sign an authorizing form which contains the basis for the favorable review. )
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