IR 05000309/1981027
| ML20040A987 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/30/1981 |
| From: | Clemons P, Knapp P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20040A981 | List: |
| References | |
| 50-309-81-27, NUDOCS 8201230037 | |
| Download: ML20040A987 (3) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-309/81-27 Docket No.
50-309 License No.
OPR-36 Priority Category C
Licensee:
Maine Yankee Atomic Power Company 1671 Worcester Road Framinnham, Massachusetts 01701 i
Facility Name: Maine Yankee Nuclear Power Station Inspection At: Barnw 11, South Carolina
[ Jh giClemons,]hd tion Specialist date signed p-
/2-30 -P/
Report Prepared by:
Approved by:
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- 'Knapp, Chisft Facility date signed LRdiationPrdt/ctionSection, Technical Inspection Branch Inspection Summary:
Inspection on September 18,1981 by a representative of the South Carolina Department of Environmental Control.
Maine Yankee Atomic Power Company was the originator of a waste shipment which was inspected at the Chem-Nuclear Systems, Inc. burial sita.
R_e sul t s :
One apparent item of noncompliance was identified (the transfer of byproduct material in a form the recipient was not authorized to receive).
d 8201230037 820106 PDR ADOCK 05000309 G
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DETAILS
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On September 15, 1981, the Maine Yankee Atomic Power Company dispatched
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a shipment of licensed material consisting of 0.927 Curies of-solidified evaporator bottoms as LSA radioactive waste to the_ Chem-Nuclear Systems,
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Inc. burial site at Barnwell, South Carolina.
The shipment was made in
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a Chem-Nuclear shipping cask, No. 21-300-10.
On September 18, 1981, a representativc of the South 4arolina Department of Health and Environmental Control inspected the shipment. Jhe inspection
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consisted of a review of shipping papers, placarding, marking.and labeling, radiation measurements, selective contamination surveys, and examination of the packages and the tractor-trailer.
A copy of the report, without attachments, prepared by the representative is attached. The report states that the inner liner of the cask containing the solidified evaporator bottoms yielded a tota: of 300 gallons of free standing liquid.
This determination was made by drilling several holes in the unapproved liner and allowing the liquid to drain.
This informatic, was given to P. Clemons of the Region I Office during a telephone conversation with a representative of the State of South Carolina on or about October 15, 1981.
Condition No. 27 of the Chem-Nuclear Systems, Inc. Agreement State License, South Caroiii.a License No. 097, states:
"The licensee may receive aqueous liquids solidified with one of the following solidification media provided the requirements of other conditions as specified in this license are met:
(a) Dow media (b) Cement (c) Urea Formaldehyde (d) Asphalt (e) Delaware Custom Media (f) Solidification media and processes reviewed and approved by the U.S.N.R.C. Office of Nuclear Reactor Regulations, subject to final approval by the S.C. Department of Health and Environmental Control, Bureau of Radiological Health."
Condition No. 26 of License No. 097 states that solidified radioactive waste shall have no detectable free standing liquid.
License No. 097
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defines "no detectable free standing liquid" as follows:
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"(3)'One percent (l's) liquid by waste volume until December 31, m.
1980.
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(b) Effective Jsnuary 1, 1981, one-half percent (0.5?;) by waste
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volume or one gallon of r.on-corrosive liquids per container, l'
whichever is less.
knlieuoftherequirementsofsubparagraph(b)above, solidified waste containing liquids in excess of one-half percent (0.5?o) by waste volume, but less than one percent (lf;) liquid by waste volume,
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may be received and disposed of in approved high integrity containers."
The liner used in this shipment was unapproved, therefore, the 0.5 percent limit is applicable.
The 300 gallons of liquid radioactive waste draired # rom the linner corresponds to 12.5 percent of the waste volume.
10 CFR 30.41 prohibits transfer of byproduct material unless it is in a form authorized by the recipient's NRC or Agreement State license. As noted above, South Carolina License No. 097 prohibits the receipt of solidt fied waste with " detectable free standing liquid", which is defined l
in this case as liquid in excess of 0.5 percent by waste volume for non-approved containers.
This represents noncompliance with 10 CFR 30.41 (81-27-01).
The Maine Yankee Nuclear Power Station Plant Manager was informed of this apparent item of noncompliance with NRC requiremants in a telephone conversation with P. Clenons on October 23, 1981.
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