|
---|
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
[Table view] |
Text
. . . - . . . - - . . -
n 4 TECHNICAL SPECIFICATION-q UNIVERSITY OF MISSOURI -
m RESEARCH REACTOR FACILITY. .i
<o i l
Number 3.8 i p Page 1 of 2 I Date
. L
SUBJECT:
Reactor Fuel ,
' Anolicability This specification' applies to fuel elements used in the ' reactor- core.
Objective -
lThe; objective of this specification is to assure that the reactor fuel is I Loperated within acceptable design considerations thus maintaining fuel l(
" i
' integrity, f Soecificatio n ' !
-i n
- a. The peak burnup for. UAl x intermetallic fuel shall not exceed a calculated ]
!.2.3 x 1021 fissions per cubic centimeter. ]
]
- b. TheLreacto'r will not be operated using' fuel in which anomalies- have been ;
- detected or 'in which dimensional changes of any coolant channel between-_ j ifuel: plates exceed ten (10) mils.
l
' c. .The- reactor core shall consist of eight fuel assemblies. ] l
- Exception: The reactor may be operated to 100 watts above shutdown power on -]
less than eight assemblies for purposes of reactor calibration or multiplication ]
studies.- ) l
- d. All fuel elements or fueled devices outside the reactor core shall be stored in -!
a geometry..such that the calculated K eff si less than 0.9 under all conditions ] ;
of moderation.
i 9005250058 900517 gon Anockosoog6
' '].
- b~ -
. - + -- - - , ._.___-__._..-.__-__-._--____-J
j 9 ,1
, n.
i " - TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI
} , .
K RESEARCH REACTOR FACILITY Number 3.8 Page 2 of 2 Date -,
L
SUBJECT:
Reactor Fuel (continued) u
' e; Irra'hted fuel elements shall be stored in an array which will permit suf'he,nt. natural convection cooling such that the fuel element temperature 1 - will not exceed design values.
Bases !
- a. The fuel burnup limit restricts the. peak fissions per cm 3 burnup to values ]
L correlated to result in less than a 10% swelling of the fuel plates, it has - -
been' found that fuel plate swelling of less than 10% has no detrimental effect~ on fuel plate performance. (Ref. License R-103 Change No. 4 dated i
- August 12,1968, Change No. 6 dated November 25,1970, and Application- ]
.' dated September 12,1986 with supplements). ]
.b; Specification 3.8.b assures that fuel . elements which have been inspected and found-to be defective are no longer used for reactor operation.
cc1To assure the validity of the safety limit curves (specification 2.1) and ]
other safety analysis, specification 3.8.c limits the core to eight fuel _ ]
elements at any significant power level. ]
d.- The' limits imposed b'y specifications 3.8.d and 3.8.e are conservative and-assure safe fuel storage. ,
i t
9
4
, t c,
7 TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI
,' RESEARCH REACTOR FACILITY Number 5.5 L Page 1 of 1 Date i
SUBJECT:
- Fuel Elements Acolicability This specification shall apply to the surveillance of the reactor fuel ' elements.
Objective The objective of this specification is to reasonably assure proper performance -
'of the reactor fuel. -
j Soecification '
i One out of every eight (8) fuel elements that have reached their end-of-life ]
will be inspected for' anomalies. )
Bases The specified inspections along with the on-line fission product monitoring - )
and the routine water chemistry inspection of the primary coolant provides for )
-the detection of anomalies resulting from reactor operation and reduce the ]
possibility of fission product release to the primary coolant.
Inspecting the ) ;
fuel elements at the end of their life has the added advantage of allowing for ]-
the decay of the fuel elements and, hence, reducing the personnel exposure. ]
4
, , _ . - - . . . _ . - .i