IR 05000245/1985004
| ML20128B061 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/21/1985 |
| From: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Opeka J NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| NUDOCS 8505240395 | |
| Download: ML20128B061 (2) | |
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s MAY 211985 Docket No. 50-245 Northeast Nuclear Energy Company
~ ATTN: Mr. J. F. ~ 0peka Senior Vice President - Nuclear Engineering and Operations Group P.O.. Box 270 Hartford, Connecticut 06141-0270 Gentlemen:
Subject: Inspection Report No._50-245/85-04 This refers to your letter dated March 7, 1985, in response to our let'ter dated February-7,~1985. Thank you for informing us of the corrective and preventive actions documented in your letter.
Further violations of NRC/ DOT regulations have resulted.in the State of South Carolina taking enforcement' action (dose rate at the external surface of a package exceeded the regulatory limit). Although we have chosen not to take enforcement action.at this time, it.is our intent to perform a comprehensive
~ inspection of your transportation program in the immediate future. The results of that appraisal will determine if any further action on our part is
. warranted.
Your cooperation with us is appreciated.
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Sincerely, Ori inal. Signed BY:
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Thomas T. Martin, Direc o Division of Radiation Safety and Safeguards
.cc:
E. J. Mroczka, Vice President - Nuclear Operations W. D. Romberg, Station Superintendent D. O. Nordquist, Manager of Quality Assurance R. T. Laudenat, Manager, Generation Facilities Licensing Cerald Garfield, Esquire Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety. Information Center (NSIC)
NRC. Resident Inspector State of Connecticut h
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Dr. Thomas Regional Administrator Region I U.S. Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Reference: (1) Letter, Thomas T. Ihrt!n to W.G. Counsil, dated February 7, 1985, Inspection Report Nos. 50-245/85-03 and 50-336/85-04
Dear Mr. Murley:
Millstone Nuclear Power St!ation Response to 18E Inspection Nos. 50-245/85-03 and 50-336/85-04
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Pursuant to the provisions of Section 2.201 of the NRC's Rules of Practice, Part 2, Title 10, Code of Federal Regulations, this report is submitted in reply to Reference (1).
G Reference (1) informed the Northeast Nuclear Energy Company (NNECo) of a
Severity Level III violation as a result of an item of non-compliance noted during an inspection conducted by a representative of the South Carolina Department of Health and Environmental Control on a tractor-trailer containing Cask Model No. OH-142.
Violation As a result of the inspection conducted on December 28, 1984, by a representative of the South Carolina Department of Health and Environmental Control of a shipment of licensed material sent from your facility in Waterford, Connecticut, on or about November 21, 1983, and in accordance with the NRC Enforcement Policy,10 CFR 2, Appendix C, the following violation was identified.
p 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. Condition 32.B of South Carolina License No. 097, an Agreement State license issued to Chem-Nuclear Systems, Inc., prohibits the receipt of solidified waste with
" detectable free standing liquid" which is defined as liquid in excess of 0.5 percent by waste volume of non-corrosive liquids per container.
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Contrary to.the above, on December'28,'1984, a waste shipment of byproduct
. material, containing 2,310 Curies -of solid metal oxides on thermal shield chips
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Jand. filters, was transmitted.to Chem-Nuclear Systems, Inc., at Barnwell, South Carolina,'with detectable free standing liquid (0.7%) between the inner liner
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Response-As discussed in -telephone conversations with Mr. P. Clemons of your staff, the
- amount' of free standing liquid was never measured. The-Barnwell burial site
. personn'el' looked into the. shipping cask and estimated that there was capproximately five-(5)' gallons present.
The burial. site personnel then dumped eight to ten bags of speedy-dry into the shipping cask. This has made it impossible to make an accurate determination as to the exact' amount of free standing liquid.
The 0.5 percent liquid limit represents approximately 3.6 gallons.
cCorrective Action The Millstone.5tation. Inspection P1an 'for sh'ipment of the OH-142 cask was
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revised to. include an inspection for free standing liquid after the solidification has been completed and prior to placing the cover on the shipping cask. 'This revision was effective on February 24,.1985.
In order to prevent future violations, the Millstone Inspection Plans for all radioactive shipments have been revised to include inspections for free standing. liquid in the shi ping cask. These revisions were also effective on February 24,i1985.
It is our opinion that the 'above actions have put us in full compliance with the
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Very truly yours,
' NORTHEAST NUCLEAR ENERGY COMPANY n.
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W. G. Counsil Senior Vice President By:
C. F. Sears Vice President
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