ML19199A526
| ML19199A526 | |
| 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 7905030130 | |
| Download: ML19199A526 (4) | |
Text
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Central Files PSS Rdg. File i
r April 18, 1979 i
1 I
t NOTE TO:
V. Stello, Jr., Director, TMI Operations l
l FROM:
F. J. Miraglia, Jr., Coordinator, Team B I
On April 14, 1979, R. Mattson requested that the NRR Teams in Bethesda provide information which would be useful in assessing 6
i off-site consequences associated with the use of SG-B in a I
steaming mode. The attached infomation was developed by F. Kantor and L. W. Bell.
i i
F. J. Miraglia, Jr.
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Coordinator Team B
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Radiological Consequences of Steamina With EG-B This memorandum presents a preliminary evaluation of the possible radiological consequences _ of placing steam generator "B" in operation in a steaming mode at TMI-2. Tube leaks are thought to have occurred
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in the early stages of the incident (as a result of some as yet un-identified mechanism) and SG-B has remained isolated since then. There does not appear to have been any significant leakage following isolation as the water level and activity in SG-B have not shown any noticeable increases.
However, there is concern that tube leaks may reappear when SG-B is placed back in service.
We have ttempted to develop a model to evaluate the offsite doses and in-plant concentrations of I-131 as a function of t~be leaks ranging from zero to six gallons per minute. The assumptions used in our evaluation are listed in the attached table. Some of our assumptions concerning equipment volumes, flow rates, and partitioning factors are best esti-mate values which can be modified if necessary as better information becomes available.
The results of our analysis, shown in the attached figure, indicate the kind of offsite doses and activity concentrations which can occur as a result of SG tube leakage. The results also illustrate the relationship between I-131 concentrations in the steam generator water volume and I-131 concentrations at the air ejector exhaust. This suggests an ap-proach for maintaining the air ejector exhaust concentration of I-131 activity below some prescribed level by monitoring the activity in the steam generator.
!/
TABLE 1_
ASSUMPTIONS USED IN EVALUATING RADIOLOGICAL CONSEQUENCES OF SG B STEAMING 3
1.
1-131 concentration in primary coolant = 5.68 x 10 pCi/cc (decay corrected to 04/14/79) 2.
I-131 concentration in SG B = 1.22 pCi/cc (decay corrected to 04/14/79) 3.
Steam Rate = 25,000 lb/hr 4.
Fraction of SG tube leakage sprayed to steam dome = 0.37 3
5.
SG volume = 80,000 ft of which 94% was assumed to be water filled and 6% steam filled 6.
Partition factor for I-131 in steam generator = 500 7.
Condenser hot well (water) volume = 7,000 ft 8.
Condenser steam volume = 140,000 ft 9.
Partition factor for I-131 in condenser = 10
- 10. Air ejector exhaust flow rate = 50 and 100 cfm (two cases)
- 11. Filter officiency on air ejector exhaust = 99%
-4 3
- 12. X/Q = 1.0 x 10 sec/m to exclusion area boundary
-4 3
- 13. Breathing rate = 3.47 x 10 m /sec 6
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