ML20101F987

Proposed Tech Specs Re Visual Insp of Fuel Elements for Damage or Deterioration

ML20101F987
Person / Time
Site:	University of Utah
Issue date:	05/20/1992
From:	UTAH, UNIV. OF, SALT LAKE CITY, UT
To:
Shared Package
ML20101F983	List: ML20101F976 ML20101F987
References
NUDOCS 9206250241
Download: ML20101F987 (5)

Text

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i APPENDIX A g TECINICAL SPECIFICATIONS FOR TIIE UNIVERSITY OF UTAll TRIGA REACTOR DOCKET NO. 50-407 FACILITY-LICENSE-NO. R-126

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4. SURVEILLAf!CE REOUIREi'.E!iTS l- .

r FUEL_

Applicability.

This specification applies to the surveillance requirement for the fuel elements.

Objective The objective is to assure that the dimensions of the fuel elements remain within acceptable limits. .

Specification All fuel elements shall be inspected visually for damage or a.

deterioration every tvio years. Any fuel element which appears damaged shall be measured for length and bend. EA foal element shall be considered damaged and must be removed -from the_ core if:

. 1. In measuring the transverse bend,.its sagitta exceeds'0.125 LI ,

inches over the length of the cladding. .

) 2. In measuring the elongation, its length exceeds its original length by 0.250 inch (a)

3. A clad defect exists as indicated by release of fission products,

b. Fuel elements in the hottest assumed location as well as representative elements in each of the B and C hexagonal rings shall be measurea for possible damage in the event that there is indication that fuel temperatures greater than the limiting safety system setting may n*ve

, been exceeded.

(a) Original length shall be deemed -to be the length of each respective fuel element as measured before the initial criticab startup of the

reactor.

1 Bases Biannual visual inspection of the' TRICA fuel has been shown adequate to

< insure fuel element int q;rit f throu';h a Icng _ history of standard operatica in the s teady-s ta te n. ode- Ine Iimit of. transverse bend'has been shc.s.n to result in no difficulty in disassentaling he core. Analysis of the removal of heat f rom toucning fuel elements shows that there will be no hot space result.ing in dwaage to the fuel caused.bv this touching.

ExperienceJ. tith iRIM ceactors har sto.sn : hat'2ven fuel element bo.-ting which results in touching can occur without deleterious ef fects. The i

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s FACILITY LICENSE NO. R-125 TECHNICAL SPECIFICATIONS AND BASES FOR THE UNIVERSITY OF UTAH TRIGA REACTOR DOCKET NO. 50-407 6

d DATE:' March 1985 Amendment No. 5 i

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insures the same degree of control of release of radioactive materials

.(SAR Section 8.7.5).

4.3.5 Experiment and Irradiation Limits t'

Aeolicability: This specification appites to the surveillance reqatre-ments for experiments installed in the reactor and its experimental

facilities and for irradiations performed in the irradiation facilities.

Specifications:

c (1) A new experiment shall not be- installed in the reactor or its i

experimental facilities untti a hazards analysis has been per-formed by the Reactor Supervisor and reviewed by the Reactor Safety Comittee. Minor modifications to reviewed and approved experiments may be made at the discretion of the senior operator-1 i responsible for the operation, prodded thet the -hazards asso-ciated with the modifications have been reviewed and a determin-

ation has been made that the modifications do not create a significantly differeht, a 'new', ~ or a greater. hazard than the original approved experiment.

4 (2) An irradiation of a new type of device or material shall not be performed until an analysis of the irradiation has been perfonned snd reviewed by the Reactor Supervisor.

Basis:

It has been demonstrated over a number of years that experiments i anc irradiations reviewed by the reactor staff and the Reactor Safety i

Comittee, as appreeriate, can be conducted without endangering the safety of the reattur or exceeding the limits in the Technical Specifica-tions.

4.4 Reactor Fuel Elements

_Acolicab111ty:

ments for the fuel This elements, specification applies to the surveillance require-f i Objective:

fuel element cladding.

The objective is to verify the continuing integrity of the i

I Soecifications:

i All fuel elements shall be~1nspected visually for damage or deterioration ? everyitw'o years. The reactor. shall not be operated-with damaged fuel. - A- fuel element shall be considered damaged. and must.

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. be removed from the. core if: ,

(1) in measuring the transverse bend, its sagitta exceeds 0.125 3

. inches over the length of the cladding, l (2) in measuring the- elongation, its length exc:ees its original length by 0.250 inches, 19 i Amendment No. 5

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i (3) a clad defect exists as indicated by release of fission products. j However, the reactor may be operated on a short-term basis as 1 needed to assist in determining the source of the leakage.

Bases: The frequency of inspection and measurement schedule is based on l the parameters most likely to affect the fuel cladding. The limit of transverse bend has been shown to result in no difficulty in disassembling the core. Analysis of the removal of heat from touching fuel elements shows that there will be no hot spots resulting in damage to the fuel caused by this touching. Experience with TRIGA reactors has shown that fuel element bowing that could result in touching has occurred without deleterious ef fects. The elongation limit has been specified to ensure that the cladding material will not be subjected to stressee that could cause a loss of integrity in t'he fuel containment and to enure adequate coolant flow.

4.5 Primary Coolant Conditions Applicability: This specification applies to the surveillance of primary water quality.

_Objecti ve: The objective is to ensure that water quality does not deteriorate over extended periods of time if the reactor is not operated.

Specification: The conductivity and pH of the primary coolant water shall be measureo monthly and shall be as follows:

(1) conductivity <5x10-6mhos/cm, (2) pH between 5.0 a.d 8.0 Bases: Section 3.8 ensures that the water quality is adequate during reactor operation.

Section 4.5 ensures that water quality is not per.

mitted to deteriorate over extended periods of time even if the reactor does not operate.

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Amendment No. 5 l

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