ML19220C513
| ML19220C513 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/12/1979 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905110119 | |
| Download: ML19220C513 (4) | |
Text
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.. -,,i ~Ic April 12, 1979 TO: B. Grimes, flRR, T:11-2 Si te FRO:1: F. J. iiirag'.ia, Ccordinator Team B Attached is primary coolant sample analysis information you requested. This material was developed by S. Bland and F. Kantor. 0 . A. 0,,,,.\\. n n,..,,
- rafda, Frank Team B Coordinator oos n o 96 086 r
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SUBJECT:
PRIMARY COOLAlli SAMPLE AtlALYSIS 4/12/79 Discussion The first sample (100 ml) of the primary coolant was taken at approximately 1700 on March 29. Direct radiation readings of the sample were 1,000R/hr on contact (70-80R/hr at one foot and 10-30R/hr at three feet). A secondary primary coolant sample (60 ml) was collected at approximately 0730 on April 10. Direct radiation reading of the sample was 17R/hr at 5 inches. (tiote: Sample was in lead pig; it is assumed that the reading was with the top plug off). This sample was split with the licensee; fiRC sent sample to Bettis, Savannah River Laboratory, and ORtil for analysis. (As of the time of the memorandum, the results from Bettis had not been received). Evaluation The enclosed table is an evaluation and ccmparison of the analysis of the two primary coolant samples. This table is an update and simplification of a preliminary table that was informally sent to B. Grimes at 1200, 4/12/79. In determining the fraction of the core inventory in the primary coolant, a 5 3 total primary coolant inventory of 7.4 x 10 lbs. (3.8 x 10 ml) was assumed (reference, flRC Appendix I Evaluation). It should be noted, however, that approxicately 9 x 10 ml of make-up water (BWST) was added to the primary system durir.g the early hours of the event (0400 to 2400 on 3/28). gh
. 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 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 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 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 somewhere between the value presented in the table and the higher value calculated when considering the make-up water. The core inventories that were assumed for the analysis were from ORIGIN ccmputer code runs which were performed using the actual TMI-2 fuel history. Hcwever, an incorrect computer run (wrong value for MTU) was used in determining the decayed core inventories for the 1st sample analysis evaluation. For comparison purposes the previcus, incorrect values have been included in the table. For short lived radionuclides (I-131, Cs-136), the first computer run calcu-lates core inventories about a factor cf 1.2 higher than the 2nd computer run. For long lived radionuclides the difference is negligible. The core inventories for the first sample analysis have been decay corrected (2 days) to roughly correspond to the analysis time. The second samole core inventories have also been decay corrected (14 days to correspond to the analysis. 96 088 .i
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