ML20141C955

Special Rept:During Fourth Quarter 1985,river Water Sample Determined to Exceed Control Station by Factor of Ten. Caused by Increased Amount of Primary Water Processed.No Corrective Actions Required Due to Insignificant Levels

ML20141C955
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/01/1986
From:	Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8604070356
Download: ML20141C955 (3)

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,w CONNECTICUT YANKEE ATOMIC POWER COMP ANY B E R L I N. CONNECTICUT P.O. BOX 270 HARTFORD, CONNECTICUT 06141-0270 TELEPHONE '

203-665-5000 Dr. T. E. Murley Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Reference:

Facility Operating License No. DPR-61 Docket No. 50-213 ETS-NR/50-213/86-01

Dear Dr. Murley:

During the fourth quarter of 1985 a river water sample was obtained that was determined to require a written report because of the level of radioactivity observed. The result of the analysis on this sample was received on February 19, 1986 and therefore was during the period for which new Technical Specification requirements were in place. (The Radiological Effluent Technical Specifications were implemented January 1, 1986). Under these new Specifications no report is required. However, because the sampling occurred during the fourth quarter of 1985, pursuant to the now outdated Haddam Neck Environmental Technical Specification Section 3.2, the Haddam Neck Plant hereby forwards the following report regarding the measurement of anomalous radioactivity in river water.

Very truly yours, M"

Richard H. Graves  ;

Plant Superintendent j RilG/RC/kav Enclosure cc: Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 j

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Facility: Haddam Neck Nuclear Facility Report Number: ETS/NR/50-213/86-01 Report Date: March 1, 1986 Occurrence Date: Fourth Quarter, 1985 DESCRIPTION OF OCCURRENCE:

The following level of tritium (H-3) activity was observed in the quarterly composite of river water near the discharge area. This value exceeded the control station (Middletown) by greater than a factor of ten.

Analysis Results Sample Dates Report Date (pCi/1)

Discharge Area Continuous 9/30-12/30 2/19 870170 Middletown Weekly grabs 10/1-11/5 -

74166 (control)

PLANT OPERATING CONDITIONS PRIOR TO OCCURRENCE:

The plant was operating at about 100% power except for a coast down during December in advance of a January 4, 1986 refueling outage. During the quarter, primary systems were being processed in preparation for the refueling outage.

CAUSE OF OCCURRENCE:

Due to the increased amount of primary water which must be processed in preparation for a refueling outage, the amcunt of radioactivity released in liquid discharges is typically higher during the few months preceding plant shutdown. The levels at the control location were lower than normal due to the higher than routine sensitivity of the analysis.

These factors resulted in river water tritium levels approximately 20% greater than an overly conservative reporting limit (see Dose Consequences).

DOSE CONSEQUENCES: 1

% l A dose calculation using Regulatory Guide 1.109 methodology was performed.  :

The calculation assumed an individiual could have consumed fish, resident in l river water having the tritium concentration as measured. The whole body dose would be 0.0005 mrem. There is no drinking sater pathway. A more conservative calculation is to again use the Regulatory Guide 1.109 methods and the measured plant discharges for this quarter. This results in the calculation of 0.0035 mrem for the 4th quarter. These calculations are conservative in that the fish do not reside at this location of maximum l activity 100% of the time. The calculated dose of 0.0035 mrem is an extremely small fraction (approximately 0.0001) of the natural background radiation (30 l

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mrem) to which this individual is normally exposed over this period of time (three months). Thus the dose consequence of this event is insignificant.

4 Since these samples were collected during the 4th quarter of 1985, the reporting requirements effective at that time were used. As of January 1986, 4

these over conservative reporting requirements-have been changed with the implementation of the radiological effluent technical specifications (RETS).

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The revised safety technical-specifications which incorporate the RETS, would not require any such action until tritium levels' reach 20,000 pCi/1.

Therefore, no other corrective actions are required due to the insignificance of the measured levels.

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