ML20052F975
| ML20052F975 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/08/1982 |
| From: | Clemons P, Knapp P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20052F961 | List: |
| References | |
| 50-245-81-15, 50-336-81-13, NUDOCS 8205140203 | |
| Download: ML20052F975 (1) | |
See also: IR 05000245/1981015
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U. S. NUCLEAR REGULATORY COMMISSION
OFFICE CF INSPECTION AND ENFORCEMENT
Region I
50-245/81-15
Report Nos. 50-336/81-13
50-245
Docket Nos. 50-336
License Nos. DPR-65
Priority
--
Category
C
Licensee:
Northeast Nuclear Energy Company
P. O. Box 270
Hartford, Connecticut 06101
Facility Name:
Millstone Nuclear Power Station
Inspection At:
Barnwell, South Carolina
Prepar,esLBy:- @Mk W
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P. Clemonsw T tion S cialist
date signed-
Approved
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PX Kn' app, Criief, F&cilitWRadiological
dated signed
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Protection Section
Inspection Summary:
Inspection on September 29, 1981 by a representative of
the Region II office of the U. S. Nuclear Regulatory Commission (Report No.81-10A)
Northeast Nuclear Energy Company was the originator of a waste. shipment which
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was inspected at the Chem-Nuclear Systems, Inc. burial site.
Results: One apparent item of noncompliance was identified (the transfer of
byproduct material in a form the recipient was not authorized to. receive).
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8205140203 020122
PDR ADOCK 05000245
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DETAILS
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In a telephone conversation on January 4,1981 between a Nuclear Regulatory
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Commission Region II inspector and P. Clemons of this office, the following
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information was revealed:
1.
On September 25, 1981, Northeast Nuclear Energy Co. made an LSA radioactive
waste shipment (Volume Allocation No. 0981-100-L) to the Barnwell, SC
burial site. The shipment was made in a Chem-Nuclear cask No. CNSI 7-
100. The cask. contained seven 55 gallon drums.
Four of these drums
. contained waste solidified using urea formaldehyde.
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2.
On September 29, 1981,'a State of South Carolina representative, at
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the burial site, inspected the four drums for free standing liquid.
Several holes were drilled through the walls of each drum.
Three of
the four drums contained free standing liquid.
3.
The inspector was informed by a representative of the State of South
Carolina that 55 gallon drums were not designated as high integrity
containers.
Condition no. 27 of.the South Carolina Radioactive License No. 097 states,
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"The licensee may receive aqueous liquids solidified with one of the
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following solidification media provided the requirements of other
conditions as specified in this license are met:
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a.
Dow media
b.
Cement
c.
Urea Formaldehyde
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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
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Control, Bureau of Radiological Health."
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10 CFR 30.41, " Transfer of Byproduct Material", requires that no licensee
shall transfer byproduct material except as authorized pursuant to this
section. Among other provisions, this section permits transfer to persons
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authorized to receive byproduct material under terms of a license issued by
an Agreement State.
Chem-Nuclear Systems, Inc.'s, Agreement State License for the Barnwell,
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South Carolina, burial site (South Carolina Radioactive Material License
No. 097) specifies in license condition 26 that solidified radioactive
waste shall have no detectable free standing liquid. The license defines
"no detectable free standing liquid" as follows:
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"a.
One percent (1%) liquid by waste volume until December 31, 1980.
b.
Effective January 1,1981, one-half percent (0.5%) by waste
volume or one gallon of non-corrosive liquids per container,
whichever is less.
In-lieu of the requirements-of sub paragraph (b) above, solidified
waste containing liquids in excess of one-half percent (0.5%) by waste
volume, but less than one percent (1%) liquid by waste volume, may be
received and disposed of in approved high integrity containers."
As stated in the above telephone conversatien, 55 gallon drums are not
designated as high integrity containers.
The 0.5% limit is applicable,
which represents a permissible volume of 0.275 gallons of free standing
liquid per drum. The drums, identified as Drum #1, Drum #3, and Drum #4,
contained 3.5 gallons, 3.0 gallons, and 0.5 gallons of free standing liquid,
and these are respectively 12.7 times, 10.9 times, and 1.9 times the burial
site limit.
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.
Therefore, the transfer of byproduct material on July 29, 1981, to Chem-
Nuclear Systems, Inc. containing free standing liquid in excess of the
Chem-Nuclear Systems, Inc license limit, represents noncompliance with 10 CFR 30.41 (81-15-01).
The Northeast Nuclear Energy Company Plant Superintendent was informed of
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this apparent item of noncompliance with NRC requirements in a telephone
conversation with Mr. P. Clemons of the Region I Office on October 22,
1981.
On September 29, 1981, at the Chem-Nuclear Disposal Site, Barnwell, South
Carolina, a Region II inspector inspected the shipment. The inspection
consisted of a review of shipping papers, placarding and labeling, radiation
measurements, selective contamination surveys, observations by the inspector,
and examination of the packages and the tractor trailer. A copy of the
report designated " Waste Packaging Inspection of Licensee-Shippers Report
No. 81/10A" is attached.
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