ML20133J765
| ML20133J765 | |
| Person / Time | |
|---|---|
| Issue date: | 01/13/1997 |
| From: | Martin T NRC (Affiliation Not Assigned) |
| To: | Sohinki S ENERGY, DEPT. OF |
| References | |
| PROJECT-697 NUDOCS 9701210130 | |
| Download: ML20133J765 (3) | |
Text
._.
January 13, 1997
[
Stephen M. Schinki, Director Office of Commercial Light Water Reactor Production l
Defense Programs Department of Energy Washington, DC 20585
SUBJECT:
SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION REGARDING TOPICAL REPORT ON THE TRITIUM-PRODUCING BURNABLE ABS 0RBER R0D LEAD TEST ASSEMBLY
Dear Mr. Sohinki:
The staff is reviewing your topical report PNNL-11419, " Report on the Evaluation of the Tritium Producing Burnable Absorber Rod Lead Test Assembly," submitted by letter dated December 4, 1996.
By letter dated January 3, 1997, the staff transmitted its initial request for additional information.
The staff has identified an additional issue as a result of experience with iridium capsule irradiation at the Oak Ridge HFIR reactor that should be considered in the lead test assembly topical report.
You are requested to provide a response to the enclcsed request for additional information within 30 days of the date of this letter.
j If you have any questions regarding this request, please contact the project manager, J. H. Wilson, at (301) 415-1108.
Sincerely, David B. Matthews/for Thomas T. Martin, Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Project No. 697
Enclosure:
as stated DISTRIBUTION:
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January 13, 1997 Stephen M. Sohinki, Director Office of Commercial Light Water Reactor Production Defense Programs Department of Energy Washington, DC 20585
SUBJECT:
SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION REGARDING TOPICA!.
REPORT ON THE TRITIUM-PRODUCING BURNABLE ABSORBER R0D LEAD TEST ASSEMBLY
Dear Mr. Schinki:
The staff is reviewing your topical report PNNL-ll419, " Report on the Evaluation of the Tritium Producing Burnable Absorber Rod Lead Test Assembly," submitted by letter dated December 4, 1996.
By letter dated January 3, 1997, the staff transmitted its initial request for additional information.
The staff has 4
identified an additional issue as a result of experience with iridium capsule irradiation at the Oak Ridge HFIR reactor that should be considered in the lead 4
test assembly topical report.
Yoa are requested to provide a response to the enclosed request for additional information within 30 days of the date of this letter.
If you have any questions regarding this request, please contact the project manager, J. H. Wilson, at (301) 415-1108.
Sincerely, i
d
'Ju*/
/2ThomasT. Martin, Director Division of Reactor Program Management Office of Nuclear Reactor Regulation 4
i Project No. 697
Enclosure:
as stated
6 0FFICE OF NUCLEAR REACTOR REGULATION SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION REGARDING
" REPORT ON THE EVALUATION OF THE TRITIUM PRODUCING BURNABLE ABSORBER R0D LEAD TEST ASSEMBLY" PROJECT NO. 597 Reactor Systems 10)
Section 2.2.6.3 - The staff has identified an additional type of accident that should be considered in the TPBAR LTA topical report.
A weld in an iridium capsule failed during irradiation at the Oak Ridge HFIR reactor, allowing water to enter the capsule. As long as the capsule was in the spent-fuel pool, the heat removal was adequate to keep the water in the capsule in liquid form.
However, when the capsule was withdrawn from the pool and placed in a dry shipping cask, the water boiled and the resulting pressure increase ruptured the capsule.
Although Section 2.2.6.3 mentions a water-logged TPBAR, the increase and rate of change of temperature due to dry shipping have not been analyzed and the resulting maximum pin temperature and pin internal pressure have not been calculated. The heat generation of the TPBAR at 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> after irradiation, given in Section 6.2.1.2, is 0.024 kW per LTA, or 3 watts per pin.
At this power level, it seems unlikely that the pin temperature would ever exceed the boiling point. However, a simple assertion is not adequate to make the case.
Provide an analysis of the increase and rate of change of temperature in a water-logged TPBAR pin due to dry shipping and calculate the resulting maximum pin temperature and pin internal pressure.
The analyses should consider the dry conditions during dry shipping that result in a low heat removal rate in spite of the enhanced heat transfer provided by the water in the interior of the pin. The analysis should also consider the effect on tube failure pressure (normally 3000 psi) bicause of the assumed failed weld or clad.
Enciosure