ML20034C528
| ML20034C528 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 04/25/1990 |
| From: | MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | |
| Shared Package | |
| ML20034C527 | List: |
| References | |
| NUDOCS 9005040076 | |
| Download: ML20034C528 (5) | |
Text
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TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY i
Number 3.8 Page 1 of 2 Date
SUBJECT:
Reactor Fuel Acolicabilltv-i
-This specification applies-to fuel. elements used in the reactor core, Obiective The objective of this specification is_ to assure 'that.the reactor fuel is.
operated:within acceptable de' sign considerations thus maintaining fuel integrity, Soecification
- a. The peak burnup-for UAi intermetallic fuel shall not exceed a calculated
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x 2.3 x 1021 f ssions per cubic centimeter.
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- b. The reactor will not be operated using fuel in which anomal!es have been detected or in which dimensional changes of any coolant channel between fuel plates exceed ten (10) mils.
- c. The reactor core shall consist of eight fuel assemblies for which the associated ]
power peaking results in a greater than or equal maximum allowable power than ]
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that given in figures 2.0, 2.1, 2.2 of specification 2.1' for the various combina-
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tions of core flow rate, reactor inlet temperature and pressurizer pressure.
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l Exception: The reactor may be operated to 100 watts above shutdown. power on ]
less than eight assemblies or with greater' power-peaking for purpose. of
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reactor calibration or multiplication' studies.
- d. All fuel elements or fueled devices outside the reactor core shall be stored in a geometry such that the calculated K i
eff s less than 0.9 under all conditions
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of moderation.
9005040076 900425 PDR ADOCK 05000186 i
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a TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 3.8-
' Page 2 of 2 i
Date
SUBJECT:
' Reactor Fuel (continued)
- c. Irradiated fuel elements shall: be stored in an array which.will permit'
- sufficient natural convection cooling 'such' that the fuel elementLtemperature=
-will not exceed design values.
Bases
- a. The fuel burnup limit restricts the peak fissionsiper em3 burnup.--to values
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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. '4Ldated-August 12,1968, Change = No. 6 dated November 25,1970, and Application
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dated September 12,1986-with supplements).
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- b. Specification 3.8.b assures that fuel elements which -have been insp'ected and found to be defective-are no longer used for reactor operation.
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- c. To assure the validity of the safety limit curves (specification 2.1) and
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l-other safety analysis, specification 3.8.c limits the core to eight.' fuel
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elements and their maximum power peaking for operation at_ any. significant power level.
- d. The limits imposed by specifications 3.8.d and 3.8.e are conservative and assure safe fuel storage.
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TECHNICAL SPECIFICATION R
i UNIVERSITY OF MISSOURI
- l RESEARCH REACTOR FACILITY 3
Number 4.1 Page 1 of 2 -
1 Date
SUBJECT:
Reactor Fuel r
Aoolicabilitv
'This specification applies to reactor fuel elements.
Objective The objective of this specification is to assure-that reactor fuel elements-are of the type designed for use in the reactor.
Snecification
- a. Each reactor fuel element shall contain 24 fuel bearing. plates with nominal active length of 24 inches and plate thickness of 0.05 inches.
The' nominal distance between plates shall be 0.080 inches.
Plate nominal cladding thickness shall be 0.015 inches,
- b. The fuel meat shall-be fully enriched U235-aluminide, UAl -
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x
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- c. Each of the reactor fuel elements shall be either of two types; one with a
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maximum U235 loading of 1270 grams (Extended Life Aluminide-Fuel) and a
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second one with a maximum U235 loading of 775 grams. The reactor shall
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operate with any possible combination of these two fuel element types. The
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fuel meat of the Extended Life Aluminide Fuel (ELAF) may also contain boron
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carbide (B C) as burnable poison. The boron content shall not exceed 1.08
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4 grams of natural boron per element.
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O RESEARCH REACTOR FACILITY TECHNICAL SPECIFICATION L
UNIVERSITY OF MISSOURI-.
Number 4.1 1
i Page 2 of 2 Date
SUBJECT:
Reactor Fuel J
Basas
- a. and b.
-The fuel elements for the University of Missouri Research-Reactor (MURR)- are
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1 one of a configuration -(aluminide UAlx plate. type) successfully and extensively- )
used for many years in test and research reactors..The specifications' 4.1.a
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and 4.1.b require fuel content and dimensions of the fuel elements to be in
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accordance wtih the design basis criteria for proper heat transfer and, hence,:
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can be safely used to the burnup limits of Technical. Specification 3.8.
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- c. The ELAF fuel elements have the same physical dimensions as:the' 775 gram-
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elements. The only changes-will be in the U235 loading per plate and the
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-addition of burnable poison.
Extensive neutronic and. thermal hydraulic analy-
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ses indicate that the performance of the ELAF. fuel elements. care satisfactory
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and that the University of Missouri Research Reactor can operate' safely at
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10 MW steady state power leyei with ELAF fuel: elements or;with 'any_ mixed
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combination of 775 gram and 1270 gram fuel elements'without= violating. the
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current safety limits (Technical Specification 2.1).
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References
- 1) Hazards Summary Report, July 1965, Section 4.2
- 2) Hazards Summary Report, July 1965, Section: 5.5
- 3) Letter, September 12, 1986, University of Missouri to Nuclear Regulatory
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Commission (NRC)' requesting amendment to R-103 operating license.
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- 4) Letter, September 11, 1987, University of Missouri to NRC as a response to
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NRC request for additional information--dated May 7,1987.
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5)' Letter, March 11, 1988,- University of Missouri to NRC'as a. response to '
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NRC request for additional information--dated January 11, 1988
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F
TECHNICAL SPECIFICATION UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY Number 5.5 Page 1 of 1 Date -
SUBJECT:
Fuel Elements 1
Aoolicability This specification shall apply to -the surveillance of' the reactor fuel elements.
Oblective 1i The objective of this specification is to reasonably assure proper performance of the reactor fuel.
i a
Soecification
.One fuel element from each. consecutively numbered series of eight elements
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l will be randomly selected and the fuel plates inspected for anomalies after a
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peak fuel element burnup corresponding-to greater than 90 percent of the peak:
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burnup limit (specification 3.8.a),
if all of a series of eight elements are removed
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from use before they reach 90 percent of the peak:burnup limit, then.one of the -
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four fuel elements with the higher average power l histories will be inspected.
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l Bases
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l The specified inspections of fuel elements provide for the detection of anomalies s
resulting from reactor operation and therefore reduce the possibility that fission I
products could be released to the reactor coolant.
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