ML17254A548
| ML17254A548 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/11/1985 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| IEIN-83-05, IEIN-83-5, NUDOCS 8509170122 | |
| Download: ML17254A548 (10) | |
Text
REGULATO INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR ~ 8509170122 DOC ~ DATE: 85/09/11 NOTARIZED:
NO DOCKET FACIL:50 g44 Robert Emmet Ginna Nuclear Planti Unit li Rochester G
05000244 AUTH
- BYNAME, AUTHOR AFFILIATION KOBER'iR.W.
Rochester.
Gas 8 Electri'c Corp, REC IP ~ NAME'ECIPIENT AFFIL'I ATION ZWOLINSKIg J", A ~
Operating Reactors Branch 5
SUBJECT:
'equests permission to dispose'f slightly contaminated oil by burning in house heating boiler' offsite at fossil fired plantiper-IE>> Notice 83 05'Disposal of Very Low Leve.l Radwastei
. L 10CFR20e302
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DISTRIBUTION CODE:
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ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14849-0001 ROGER W. KOBER VICE PRESIDENT ELECTRIC&STEAM PRODUCTION TELEPHONE AREA CODE t>6 546-2700 September ll> 1985 Director of Nuclear Reactor Regulation Attention:
Nr. John A. Zwolinski> Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington<
D.C.
20555
Subject:
Exemption per 10 CFR 20.302 R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Nr. Zwolinski:
In accordance with IE Notice No.83-05I Disposal of Very Low Level Radioactive Waste and 10 CFR 20.302I we request permission to dispose of slightly contaminated oil by burning in the house heating boiler at Ginna Station and off site at a fossil-fired plant owned by the Rochester Gas and Electric Corporation.
The waste oil is from the reactor coolant pumps>
charging pumps>
and-laundry dry cleaning units of the R.
E. Ginna Nuclear Power Plant.
Approximately 600 gallons of waste oil is produced annually.
The concentration to be disposed of by burning would not exceed 5 x 10 uCi/ml.
The average concentration is lower by an order of magnitude.
(See Attachment I.)
The alternative to burning is solidification and disposal as low level radioactive waste.
This results in about twice the original volume and currently costs about
$ 10>000 per year for disposal of 150 cubic feet of waste.
Of the two disposal sites operating<
only one now accepts solidified oil and shipment to that site may be terminated on January 1,
1986.
No contamination of clean systems is would be utilized to detect any buildup.
small quantities (55 gallon drums) limits spill.
Absorbent materials are available anticipated but surveys Handling the oil in the consequences of a for cleanup.
If offsite disposal is utilized> the waste oil would be shipped in 55 gallon drums to Russell Station.
The concentrations and quantities of isotopes present are exempt according to 10 CFR 30 and New York State Industrial Code Rule 38< Ionizing Radiation Protection (12NYCRR38).
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ROCHESTER GAS AND ELECTRIC CORP.
DATE September 11, 1985 To
.Mr. John A. zwolinski SHEET NO.
2
-5 The annual dose from inhalation would be 5.3 x 10 mrem for a ground level release from the Ginna plant (see Attachment II).
The Russell Station> like Ginna< is located on the south shore of Lake Ontario and has similar meteorology.
In addition<
the 250 foot stack and the buoyant plume at Russell Station makes the calculated dose conservative.
The radiological impact of this type of disposal is negligible.
V truly yours<
ng 9 Roger W. Kober Attachments
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Attachment I Gamma isotopic analysis of typical waste oil samples shows the following radionuclides to be present:
Cobalt-60 33%
Cesium-134 13%
Cesium-137 54%
-5 The maximum total activity is 5 x 10 uCi/ml The maximum activity that could be released annually to the environment is as follows:
Naximum Activity x gallons x ml/gallon x isotope fraction = uCi/year of isotope 5 x 10 5 uCi/ml x 600 gallons x 3<785 ml/gallon x.33 =
37.5 uCi/year Co-60 5 x 10 5 uCi/ml x 600 gallons x 3I785 ml/gallon x.13 =
14.8 uCi/year Cs-134 5 x 10 uCi/ml x 600 gallons x 3<785 ml/gallon x.54 =
61.3 uCi/year Cs-137 Total Activity = <113.6 uCi/year 11 The average total activity is significantly less than the maximum.
For examplei reactor coolant pump waste oil, w)ich comprises 400 of the 600 gallons of annual production>
had an activity of 7.55 x 10 uCi/ml in 1985.
The 1984 semi-annual effluent release reports for Ginna show that 3.4 uCi of particu-lars with greater than 85day half lives were released.
The release rate was 1.06 x 10 uCi/st or 1.0 x 10
% of the limit.
Burning 600 gallons of oil with an activity of 5 x 10 uCi/ml would result in an additional 113.6 uCi being released annually.
The total regl ase would then be 117 uCi with a release rate of 3.7 x 10 uCi/sec.
This is 3.5 x 10
% of the limit of 1.06 uCi/second.
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'l II
Attachment II The dbse to an individual from inhalation of radioactive materials is determined by using equation 13 in Regulatory Guide 1.109.
D
= 3.17 x 10 R.
(x/Q x Q )
< 15 mrem/year D
= total dose per year from inhalatjon< mrem/year R.
= dose factor in mrem/yr per uCi/m for radionuclide i Ii Cs-137
= 9.05E5 Cs-134 = 1.01E6 Co-60
= 7.06E6 x/Q = average annual dispersion para~ter for estimating the dose to the individual at the critical location~ sec/m For Ginna> x/Q = 5 x 10 sec/m at the nearest point to the exclusion area boundary (500 meters) for a ground level release.
Q
=, radioactive material released of radionuclide i'in uCi/year.
= 61.3 Cs-134 = 14.8 Co-60
= 37.5 mrem/year Cs-137 = (3.17 x 10 8)(9.05 x 106)(5 x 10 6)(61.3)
= 8.8 x 10~
mrem/year Cs-134 = (3.17 x 10 8)(1.01 x 106)(5 x 10 6)(14.8)
= 2.4 x 10 5 mrem/year Co-60
= (3.17 x 10
)(7.06 x 10 )(5 x 10
)(37.5)
= 4.2 x 10
-5 mrem/year total 5.32 x 10
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