ML19220C526
| ML19220C526 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/16/1979 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Mattson R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905110151 | |
| Download: ML19220C526 (5) | |
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UNITED STATES f
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4 NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 tN April 16, 1979 0;'6 MEMORANDUM FOR:
R. Mattson, NRR, TMI-2 FROM:
F. J. Miraglia, Coordinator, Team B F'
Attached is compilation of the analysis of the March 29 and April 10,1979 primary coolant samples. This report was prepared by R. Emch and S. Bland.
L. Barrett who is now on-site is aware of the data and the limitations of its interpretation.
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f0 FL41.igglia, Coordinator Team B Attachment -
As sta+.ed 00511OtS\\
b l90 9%d 1978 e.
SUBJECT:
PRIMARY COOLANT SAMPLE ANALYSIS 4/16/79 Discussion The first sample (100 ml) of the primary coolant was taken at approximately 1700 on March 29. This sample was sent to Bettis for radiochemical analysis.
A second primary coolant sample (60 ml) was collected at approximately 0730 on April 10.
This sample was split with the licensee with NRC sending ap-proximately 3 ml samples to Bettis, Savannah River Laboratory, and ORNL for analysis.
Evaluation The enclosed table is a ccmrilation of the analysis of the two primary coolant samples.
Included in the table are the Bettis analysis of the first sample and the Bettis, SRL, and ORNL analysis of the second sample.
Prelimina ry results from the licensee's analysis (B&W) have also been included.
The fraction of the core inventory that is present in the primary coolant has been calculated and included in the table for comparison purpose;.
The total radionuclide inventory in the coolant was determiend by multiplying the con-centrations by the primary coolant inventory.
The total core inventories used for the ccmpariscn were those calculated by the ORIGEN computer code using the actual TMI-2 fuel history.
The core inventories for the first sample analysis have been decay corrected to 2 days to roughly correspond to the time of analy-sis.
The second sample core inventories have likewise been decay corrected to 14 days.
(Note the following times of decay corrections for the second sample:
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. SRL-1000 on 4/11; ORNL - 0800 on 4/11; Bettis - 1200 on 4/11; B&W - 0730 on 4/11.
These decay corrections are not exactly those reported by the Laboratories in their analysis of the samples but have been applied by the NRC staff to simplify the comparisons.)
5 8
A total primary coolant inventory of 7.4 x 10 lbs. (3.8 x 10 ral) was assumed 8
(referer.ce, NRC Appendix I Evaluation), however, approximately 9 x 10 ml of make-up water (BWST) was added to the primary system during the early hours of the event (0400 to 2400 on 3/28).
Tnis addition to the primary system yields a large volume of water (primary coolant and BWST water) in the containment sumps, some of which was pumped out to the auxiliary building.
If it is assumed that this sump water is at the same concentrations as the primary coolant samples, the fraction of the 9
core inventory that is in this total coolant (1.2 x 10 ml including sump water) is about a factor of 3 higher than the inventory fraction calculated by assuming only the normal primary coolant inventory (3.8 x 10 ml).
How-ever, this approach will over-estimate the fraction of the core in the cool-ant, since the gross fuel failures occurred some time after the blowdown of the primary system to the sumps had initiated. Therefore, the actual fraction of the core inventory that has been lost to the coolant is probably scaewhere between the value presented in the table and the higher value calculated when considering the make-up water.
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f Conclusion Due to the ther al gradient in reactor fuel, cesium and iodine tend to be concentrated near or in the gap. This is true to a much lesser extent with rolybdenium, barium and strontium. The cesium and iodine would be readily soluble in the coolant; the molybdenium, barium and strontium again to a much lesser extent will be soluble.
The rare earths, such as lanthanum and cerium, are chemically similar to uranium and would be dispersed throughout the fuel as very water insoluble oxides.
The presence of cerium in solution may indicate finely dispersed fuel in the coolant. The presence of La-l?O lends support to this indication of finely dispersed fuc' however, La-140 being the daughter of Ba-140 makes the use of the La-140 as an indicator questionable.
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