ML19220B826
| ML19220B826 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/18/1979 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904270421 | |
| Download: ML19220B826 (5) | |
Text
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- v DISTRIBUTION:
Central Files,-
f PSS Rdg. File I
April 18, 1979 r
- NOTE TO:
V. Stello, Jr., Director, TMI Operations FROM:
F. J. Miraglia, Jr., Coordinator, Team B On April 16,1979,.a compilation of analyses of the March 22 and April 10, 1979 primary coolant samples was sent to R. Mattson at g
the site. Attached is a text revision of that compilation prepared l
by B. Grimes. No changes were made to the table.
5!
F. J. Miraglia, Jr.
Coordinator
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Team B
Attachment:
As Stated cc: see attached distribution list I
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Text Revision B. X. Grimes SUBJECT PRWARY COOLANT SAMPLE ANALYSIS 4/18/79 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 ' llected at approximately 0730 on April 10.
This sample was split with the
- ensee with NRC sending ap-proximately 3 ml samples to Bettis, Savannah River Laboratory, and ORNL for analysis.
Evaluation The enclosed table is a ccepilation 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 thc 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 j
been calculated and included in the table for comparison purposes.
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 comparison 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:
63 3 I C "/
. SRL-1000 on 4/11; ORfil - 0800 on 4/11; Bettis - 1200 on 4/11; B&W - 0730 ti 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 fiRC staff to simplify the comparisons.)
8 A total primary coolant inventory of 7.4 x 10 lbs. (3.8 x 10 ml) was assumed 8
(reference, flRC 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).
This 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 buildi*g.
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 8
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 major release of activity may have occurred some time af ter the blowdown of the primary system to the sumps had initiated.
This is confirmed by the relatively low concentrations of fission products in containment build-ing sump water which was pumped to the auxiliary building in the early hours of the event. Therefore, the actual fraction of the core inventory that has been lost to the coolant is probably somewhere between the value presented in the table and the higher value calculated when considering the make-up water.
83 IG
,.The increases in Cs and I between the first and second samples may either indicate chemical removal or local elevated temperatures which resulted in continued diffusion of nucifdes to the fuel / water interface.
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