ML20082K306
| ML20082K306 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 04/06/1995 |
| From: | ILLINOIS, UNIV. OF, URBANA, IL |
| To: | |
| Shared Package | |
| ML20082K304 | List: |
| References | |
| NUDOCS 9504190221 | |
| Download: ML20082K306 (6) | |
Text
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4 UIUC Nuclear Reactor Laboratory LOPRA Reactor Changes to Technical Specifications Sections 4.1 and 4.3 4/6/95 i
9504190221 950406 PDR ADOCK 05000356 P
9 Bases
- a. Corrosion may occur continuously in a water-metal system. In order to limit the rate of corrosion, and thereby extend the life and integrity of the fuel cladding, a water clean-up system is required. Experience with water quality control at many reactor facilities has shown that maintenance within the specified limit provides acceptable corrosion control.
- b. Limiting the concentration of material dissolved in the water limits the radioactivity of neutron activation products. This tends to decrease the inventorf of radionuclides in the entire coolant system, which will decrease personnel radiation exposures during both maintenance and operations. This trend is consistent with the ALARA principle.
4.0 SURVEILLANCE REOUIREMENTS 1
4.1 Control Rods Applicability This specification applies to the surveillance requirements for the control rods.
I Obiective The objective is to assure the integrity of the control rods.
Specifications
- a. The reactivity worth of each control rod shall be determined semiannually, but at intervals not to exceed eight months. 4f LOPRA is inoperative at the end of the eight month period,-the interval may be extended-to fourteen months-erdheLOPRA4seade-operab!:, whichever occurs 4irst-The surveillance may be deferred when the LOPRA is inoperative. but shall be the first activity performed after the reactor is made operable and taken critical for the first time since being inoperative.
- b. Control rod drop times shall be determined semi-annually, but at intervals not to exceed eight months.
- c. The control rods shall be visually inspected for deterioration at intervals'not to exceed two years.
Bases j
The reactivity worth of the control rods is measured to assure that the required shutdown margin is available and to provide a means for determining the reactivity worths of experiments inserted in the core. The visual inspection of the control rods and measurements of their drop -
times are made to determine whether the control rods are capable of performing properly.
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S' 4.2 Fuel Elements Applicability This specification applies to the surveillance requirements for the fuel elements.
Objective The objective is to assure the integrity of the fuel elements.
Specification The fuel elements shall be visually inspected yearly, but at intervals not to exceed 14 months. If indication of deterioration or distortion is found, the fuel element (s) shall be replaced.
Bases The visual inspection of the fuel elements specified has been shown to be adequate from experience with other low power TRIGA reactors.
4.3 LOPRA Safety System Applicability This specification applies to the surveillance requirements for the measuring channels of the LOPRA safety system.
Objective The objective is to assure that the safety system will remain operable to prevent the safety limits from being exceeded.
Specifications a.
A channel test of each of the LOPRA safety system channels shall be performed prior to each day's or prior to each operation extending more than one day.
- b. A channel check of the power level measuring channels shall be performed daily whenever the LOPRA is in operation.
i c.
A channel calibration using the prompt negative temperature coefficient technique or by comparative flux measurements shall be made on the power level monitoring channels semi-annually, but at intervals not exceeding eight months. If the LOPRA is inoperative nt the end of4he-eight-month eriod,-the-intervabmayhextended40-fourteen 4nonthser-untitthe-t LOPRA i: =de operdle,.vhichever coeurs4irst-The surveillance may be deferred when the LOPRA is inoperative. but shall be performed after the reactor is made operable and taken critical and before any other non-surveillance reauired reactor operations.
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UIUC Nuclear Reactor Laboratory l
LOPRA Reactor Changes to Technical Specifications Sections 4.1 and 4.3 as they will appear when inserted.
4/6/95 5
Y
i Bases
' a. Corrosion may occur continuously in a water-metal system. In order to limit the rate of corrosion, and thereby extend the life and integrity of the fuel cladding, a water clean-up system is required. Experience with wate: quality control at many reactor facilities has shown that maintenance within the specified limit provides acceptable corrosion control.
i
- b. Limiting the concentration of material dissolved in the water limits the radioactivity of neutron activation products. This tends to decrease the inventory of radionuclides in the entire coolant
{
system, which will decrease personnel radiation exposures during both maintenance and operations. This trend is consistent with the ALARA principle.
j i
4.0 SURVEILLANCE REOUIREMENTS 4.1 Control Rods Applicability This specification applies to the surveillance requirements for the control rods.
Obiective The objective is to assure the integrity of the control rods.
Specifications
~ The reactivity worth of each control rod shall be determined semiannually, but at intervals not a.
to exceed eight months. The surveillance may be deferred when the LOPRA is inoperative, but shall be the first activity performed after the reactor is made operable and taken critical for the first time.since being inoperative.
- b. Control rod drop times shall be determined semi-annually, but at intervals not to exceed eight months.
- c. The control rods shall be visually inspected for deterioration at intervals not to exceed two years.
Bases The reactivity wonh of the control rods is measured to assure that the required shutdown margin is available and to provide a means for determining the reactivity wonhs of experiments inserted in the core. The visual inspection of the control rods and measurements of their drop times are made to determine whether the control rods are capable of performing properly.
10 4
4.2 Fuel Elements Applicability This specification applies to the surveillance requirements for the fuel elements.
Obiective The objective is to assure the integrity of the fuel elements.
Soecification The fuel elements shal! be visually inspected yearly, but at intervals not to exceed 14 months. If indication of deterioration or distortion is found, the fuel element (s) shall be replaced.
Bases The visual inspection of the fuel elements specified has been shown to be adequate from
)
experience with other low power TRIGA reactors.
4.3 LOPRA Safety System i
Applicability This specification applies to the surveillance requirements for the measuring channels of the LOPRA safety system.
Obiective The objective is to assure that the safety system will remain operable to prevent the safety limits from being exceeded.
Specifications
- a. A channel test of each of the LOPRA safety system channels shall be performed prior to each day's or prior to each operation extending more than one day.
- b. A channel check of the power level measuring channels shall be performed daily whenever the LOPRA is in operation.
A channel calibration using the prompt negative temperature coefficient technique or by c.
comparative flux measurements shall be made on the power level monitoring channels semi-annually, but at intervals not exceeding eight months. The surveillance may be deferred when -
the LOPRA is inoperative, but shall be performed after the reactor is made operable and taken t
critical and before any other non-surveillance required reactor operations.
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