ML19259D473
| ML19259D473 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 06/05/1975 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19259D472 | List: |
| References | |
| 75-01, 75-1, NUDOCS 7910240740 | |
| Download: ML19259D473 (1) | |
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ENCLOSURE Metropolitan Edison Company Three Mile Island Nuclear Station Unit 1 (TMI-1)
Docket No. 50-289 Operating License No. DPR-50 Nonroutine 7-Day Environmental Report 75-01 Report of an Anomalous Measured Level of Radioactivity in the Environment Description of Measured Level honthly composites of weekly grab samples of river water collected at approximately 0.5 miles (Station 9A2) and 1.5 miles (Station 9B1) downstream from the 'IMI-l discharge showed tritium concentrations as follows :
1.4510.01 x 10-5 C1/ml 9A2 9B1 -
6.44 1 0.11 x 10-6 pCi/ml These values are great:r than ten times the control station value of 2.5 x 10-7 uCi/cc which was determined by Met-Ed's consultants during the TMI-l pre-operation period. Analysis of the sample by gamma spectroscopy indicated all other isotopes were less than minimum detectable levels.
Dischargas are made from the TMI-1 Liquid Waste Evaporator Condensate Tanks based on operating conditions. Processing of liquid radioactive waste water by liquid waste evaporators was unusually heavy during April due to backup from previous months when the evaporators exhibited reduced availability.
Ana_1ys_is of Measttred Levels It has been determined that neither the health nor safety of the public was threatened by the activity levels represented by these sample results in that:
a.
The level of tritium activity was less than lf112% of the Maximum Permissable Concentration given in 10CFR20 for un-restricted areas.
b.
The level of tritium activity at the nearest downstream source of public water use was at a normal background level (3.70 1 0.75 x 10-7 ACi/ml).
c.
No Technical Specification limits were exceeded.
d.
The discharge of effluents from the Liquid Waste Evaporator Condensate tank is a normal process associated with unit operations,
and is described in the Final Safety Analysis Report.
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