ML19290A406
| ML19290A406 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/23/1975 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911060643 | |
| Download: ML19290A406 (3) | |
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NRC "'STF.
JTICN FOR PART C0 DOCV' T f,1 A RIAL
' (TEMPORARY FORM)
-i CONTROL NO: / U 9 /
FILE: C M t W FROM: Metropolitan Edison Co DATE OF DOC DATE REC'D LTR TWX RPT OTHER Reading, Pa R C Arnold 12-23-75 12-31-75 XX TO:
ORIG CC OTHER SENT URC PDR Yv DL one si,gned SENT LOCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXXXXX 1
50-289 DESCRIPTION:
ENCLOSURES:
Ltr furnishing a correction to their 7 day enviro rpt 475-02 dtd 10-17-75...........
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POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 December 23, 1975 GQL 0084
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Mr. J. P. O'Reilly, Director U. S. Nuclear Regulatory Commission
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Dear Sirs:
THREE MILE ISLAND NUCLEAR STATION UNIT 1 _
DOCKET NO. 50-289 OPERATING LICENSE NO. DPR-50 Regarding our Nonroutine Seven-Day Environmental Report 75-02 dated October 17, 1975, please note that a typographical error was made on the " Description of Measured level" section of the report. The last part of the second sentence in this section should read "...less than the Minimum Detectable Level (MDL) of <0.02 pCi/ gram." vice "...less than the Minimum Eetectable level (MDL) of
<0.2 pC1/ gram.".
Please substitute the attached corrected page for page one of the subject report.
Sincerely, R. C.
'iOLD VICE PRESIDENT RCA:JMC:rk Enclosure 1556 297 143s1'
Metropolitan Edison t _.:pany (Met-Ed)
Three Mile Island Ituelear Station Unit 1 (TIC-1) h OD f.O f3 Docket No. 50-289 f
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Operating License No. DPR-50 Nonroutine 7-Day Environmental Report 75-02 Report of an Anomalous Measured Level of Radioactive Material Descriution of Measured Level As reported to Met-Ed on October 10,1975 (by the consultant (RMC) laboratory),
the concentration of Co-58 in the semi-annual river bottem sediment sa=ples collected on July 30, 1975 exceeded ten (10) times the control station value.
The control station, (TM-AQS-1A2) located approximately 0.5 miles north of TMI-1 discharge, had concentrations of Co-58 of less than the Mini =um Detectable Level (MDL) of <042 pCi/ gras. The concentration of Co-58 at TM-AQS-11A1, 0.2 miles and TM-AQS-932 at 1.4 miles downstrea= of the TMI-1 discharge equaled 0.470 pCi/6 ram and 0.3ho pCi/ gram respectively.
Possible Cause Discharges of the Liquid Waste Evaporator Condensate Tanks are made from DII-1 on an irregular basis based on unit operating conditions as described in the Final Safety Analysis Report. It is thought that the unusually lov river flow rates durin6 July may have caused the sedimentation rate to increase significantly.
Analysis of Measured Level It is believed that neither the health nor safety of the public vas threatened by the occurence represented by this sample in that:
a.
The estimated total body dose associated with this measured value from the only significant dose pathway (shoreline deposition) is less than 0.2 mren per year to the maximus hypothetical individual.
b.
The level of Co-58 activity in the river water at the nearest dcwnstream source of public drinking water was belov minimum detectable levels.
c.
None of the DiI-l Technical Specifications vere exceeded.
d.
The event resulted from normal unit operations as described in the TMI-l Final Safety Analysis Report.
The level of Co-58 activity detected in the river sedi=ent is a very lov e.
level of activity and is expected to have little or no environ = ental impact.
Corrective Actions Due to the scouring effect of the flooding associated with Hurricane Eloise it is thought that an increased sa=pling effort vould be non-productive.
Sa=pling vill continue in acccrdance with TMI-l Environ = ental Technical Specifications. The next sedi=ent sa=pling period vill be October 1975 1556 298