ML20053C027
| ML20053C027 | |
| Person / Time | |
|---|---|
| Site: | 05000054 |
| Issue date: | 05/07/1982 |
| From: | Ruzicka W UNION CARBIDE CORP. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8206010432 | |
| Download: ML20053C027 (2) | |
Text
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UNION CARBIDE CORPORAT;ON n a nox 324. Tuxeoo. NEW YoAK 10987 MEDICAL PRODUCTS DIVISION TELERONE NUMBER [914)351-2131 May 7, 1982 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Chief, Operation Reactor Branch 4
Reference:
Docket 50-54
References:
a.
Amendment No. 14 to License R-81, dated May 17, 1979:
Technical Specifications.
b.
Supplement No. 2 to the Final Hazards Summary Report dated April 1, 1977 Gentlemen:
It is requested that item 3.5.1.c (10) of the Technical Specifications for the Union Carbide Nuclear Reactor, as contained in Reference a above, be changed to read as follows:
(10) Total primary coolant flow utilized by all in core experiments shall meet the following requirement:
Fractionofcoreflowinexperiments<1-f[ oju h
- t d
w n u Item 3.5.1.c (10) of the Technical Specifications at present reads "the total primary coolant flow utilized by all in core experiments shall be limited to the same as six standard fuel elements." The basis for this requirement is from the Thermal Hydraulics Safety Analysis Section A of Reference b above. The analysis applies to a core containing 30 fuel elements (each control element counts as a 1/2 element), and experiments equivalent in flow to six fuel elements. The n,(, u) S*i ko An a
c 8206010R% "2
Director of Nuclear Reactor Regulations May 7, 1982 analysis therefore assumes that one sixth of the total core flow is through the experiments. This one sixth fraction is used in the above formula as the fraction of core flow allowed through the experiments if all the core power is produced in the fuel elements.
Section 3.5.1 applies to all experiments, fueled and unfueled.
Item 3.5.1.c (10) as it presently exists is only appropriate for unfueled experiments in which case all fission power is produced in the fuel elements.
Section 3.5.2 of the Technical Specifications entitled " Fueled Experiments" allows for up to 13 kW of fission poser per fueled experiment capsule.
If less than 5 MW of power is produced in the fuel elements, then the fraction of cooling flow to the elements can be reduced proportionally as proposed. This change would implement Basis 3.5.1 d (10) properly for both fueled and unfueled experiments.
The requested change is administrative in nature in that it does not change the basis or the safety analysis but rather states the condition in a more appropriate manner relative to fueled experiments.
If no power were produced in the experiments, the proposed specification would be analogous to the present one.
We consider this' requested change a Class II Amendment in the research reactor category and enclose our check for 5600.00 pursuant to 10 CFR 170.22.
Sincerely,
- 6. O qi Ak b0 W
W. G. Ruzicka Reactor Supervisor WGR:js Enclosure D576J 0054C