ML19322B451
| ML19322B451 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/30/1975 |
| From: | Thies A DUKE POWER CO. |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 7912030290 | |
| Download: ML19322B451 (4) | |
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i Ietter to N. C. Moseley from Duke Power Company dated April 30, 1975 DISTEIW TION:
50-269 H. D. Thornburg, IE 50-270 IE:1Rs (5) 50-287 Office of Standartis Development
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Powna Surt.orwa 4aa Sourn Gnunca SrazzT, CnAnzorrz,N.C.seso P.o. Box as76 A. C. THits SENION VICE PasseDENT PA DDUCTION AND TR AN,telStaON April 30,1975 Mr. Norman C. Moseley, Director U. S. Nuclear Regulatory Commission Suite 818 230 Peachtree Street, Northwest Atlanta, Georgia 30303 Re:
Oconee Nuclear Station Docket Nos.:
50-269, -270 and -287
Dear Mr. Moseley:
Duke Power Company, through the Oconee Nuclear Station, has participated in the radioactive-effluent verification split-sampling program with the Nuclear Regulatory Commission and the State of f.,outh Carolina since October 24, 1973.
The purpose of this program has been to verify capabilities to correctly s.nalyze effluent samples prior to their release.
In our experience with this program, several inconsis,cencies between NRC and Oconee Nuclear Station analysis results have been identified.
It is considered that the apparent causes of these inconsistencies have been variations of sample volumes, geometry, activity and that the analyses have been performed at different times.
Consequently, the following recommendations for improvement of the split-sampling program are submitted:
1.
It is recommended that the sample volumes collected for the split-sampling program be of the same size as that normally used for routine station samples.
The recommended volumes are:
Type of Sample Normal Station Sample Liquid 2 liters Gas 100 cc In the past, only a one liter sample was provided by the NRC.
This has not been adequate for all analyses as the contractor that performs the strontium analysis requires a one liter sample. Also, the gas container provided has had a volume of 20 - 30 cc and this has varied from semple to sample.
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Mr. Norman C. Moseley Page 2 April 30, 1975 It is recommended that a cylindrical 100 ce container, similar to 2.
the Oconee container, be used for gas samples. The sample containers furnished in the past have been 20 - 30 cc spherical containers.
This has resulted in inaccuracies because the sample geometry has been changed for each sample.
It is reccamended that a particulate and iodine filter sample of the 3.
proper size and expected activity normally found in effluents be supplied by the NRC for use in split-sampling program, rather than the use of an actual sample collected at the station.
Presently, only one sample is collected and it must be analyzed within 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> so that the NRC inspector can take the sample off site for analysis. This method is not adequate in that only one analysis is possible, and in addition, the samples are analyzed by the Oconee Station and the NRC at different times.
This allows short lived isotopes and adsorbed gases to produce activity seen by the station analysis but not seen by the reference laboratory at the time it analyzes the sample.
Also, it appears that daughter produce ingrowth has not been considered in the analysis of the sample by the reference laboratory.
4.
It is recommended that the effluent-verification sample be more In representative of the waste being discharged from the station.
the past, all liquid samples have been collected from the low activity waste tank (LAWT).
In reality, however, nearly all releases are from the condensate test tank (CTT). This results in much lower levels of effluent releases.
5.
It is recommended that effluent capability standards Which are sub-mitted by the NRC for analysis have activity of the r,ame order of magnitude and isotopic composition as that which is routinely expected in station analysis. The following is a listing of expected activities at the Oconee Nuclear Station.
Type of Sample Station Activity p Ci/M1 Liquid
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-6 Gamma 10 to 10 10-5 to 10-6 89 r, 90Sr S
10-2 3H 10-10 to 19-12 Cas Particulate Filter 10-10 to 10-12 10-10 to 10-12 Charcoal Absorber 1
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Mr. Norman C. Moraley Page 2 April 30, 1975 When these recommendations are instituted, we are confident that the results achieved by our laboratory and yours will be more consistent and thus verification of our ability to correctly analyze effluent samples will be confirmed.
Very truly yours, a
A. C. Thies ACT:vr 4
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