ML20086R030

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Forwards Rev 0 to SAR for Transport of Millstone Unit 2 Steam Generator Sub-Assemblies
ML20086R030
Person / Time
Site: Millstone Dominion icon.png
Issue date: 12/23/1991
From: Opeka J
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20086R033 List:
References
B14007, NUDOCS 9112310121
Download: ML20086R030 (3)


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J03) t.t& WG December 23, 1991 D%h1Jk W 2%

El1@l Re: 10Cf P.71 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Millstone Nuclear Power St tion, Unit No. 2 Application for Certification of Steam Generator Subassembliet ALlype A PacAqqu for TrJnitatation to_Dhonal_ Site With regard to our letter of September 18,1991,II) Northeast Nuclear Energy Company (NNECO) respectfully requests certification of the Millstone steam generator suoassemblies (SGSAs) described in the enclosed Safety Analysis Report (SAR) as a Type ?, transport package. The packages described in this application consist primarily of steam generator lower subassemblies that will be removed from Millstone Unit No. 2 and prepared for transport in accordance with the requirements of 10CfR71 for transport of radioactive waste. They will contain greater than Type A quantities of low-specific activity radioac-tive material in the form of a tightly adhered corrosion film on the surface of the primary sides of the steam generators.

NNECO is applying to transport the 5GSAs because Millstone Unit No. 2 is replacing the lower subassemblies on its two steam generators with new units and has determined that transporting the removed subassemblies for disposal rather than storing them on site reprennts the optimum course of action.

Since they are being disposed of at the destination, each of the two packages will be transported only a single time. 1hese shipments will be from the Millstone facility in Waterford, Connecticut, to the low-level waste disposal facility near Barnwell, South Carolina.

NNECO's goal is safe and uneventful transport of the SGSAs to the disposal facility. To ensure this, precautions will be taken in the preparation of the packages for shipment and in the procedures used in their handling and trans-port. We show in the enclosed SAR that the packages will be prepared for transport in accordance with the requirements for normal conditions of (1) E. J. Hroczka letter to U.S. Nuclear Regulatory Commission, Mill s t one Unit No. 2, Transport of Steam Generator Sub-Assemblies from Millstone Station to Barnwell, SC, low-Level Waste Disposal facility," dated September 18, 1991.

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O 9115310121 911223 0 0k PDR ADOCK 05000336 P  ;

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U.S. Nuclear Regulatory Commission 814007/Page 2 December 23, 1991 transport as defined in 10CFR71. Beyond these requirements, extraordinary care will also be taken to ensure their safety during handling and transport.

These safety measures are described in the SAR and include such precautions as filling the vessels with concrete, traveling only over a carefully planned route, and using a second tug for escorting the transport barge.

NNECO believes the best alternative for all interests is to dispose of the SGSAs rather than to store them on-site, lhe packages will be in a safer and more stable environment and in a less exposed location by being buried at the disposal f acility rather than stored on the Millstone site, if they were to be stored on-site, even for a short period of time, an opportunity for dis-posal may be missed because of the projected closing of the Barnwell site at the end of 1992. lhe uncertain status of the Connecticut low-level waste disposal facility wou'd make the next opportunity for disposal difficult to project.

As discussed with the NRC Staff in our November 19, 1991, meeting on this project, NNECO's goal is to obtain the Certificate of Compliance for the package by mid-May 1992. We realize that this is an cmbitious review schedule and will assist in whatever manner necessary, including a meeting with the Staff, at your convenience, to review the contents of the SAR.

It is noted that the calculations associated with this SAR have undergone multilevel review by Chem Nuclear Systems, Inc., and NNEC0, but have not as yet completed the final quality assurance verification as required by Chem Nuclear Systems, Inc., procedures, NNEC0 will submit, by January 31, 1992, confirmation of quality assurance verification and any correctiors as neces-sary. NNECO has high confidence that the methodology used and the mathe matical computations are valid as submitted herewith, but conclude quality assurance verification is warranted.

We trust you will find this information satisf actory, and we remain available to answer any questions you may have, i

Very truly yours, NORTiiEAST NUCLEAR ENERG( COMPAFY t

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J. f. Opeka 7 Executive Vice President cc: T. T. Martin, Region I Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 W. J. Raymond, Senior Resident inspector, Millstone Unit Hos 1, 2, and 3 C. E. MacDonald, Chief, Transportation Branch, Division of Safeguards and Transportation, NMSS v E. M. Kelly, Chief, Reactor Projects Section 4A, Reg.on I

Ds!Lket_llo. h 3J5 El1@l Attachment 1 Millstone lluclear Power Station, Unit f40, 2 Application for Certification Steam Generator Subassemblies As Type A Packages for Transport to Disposal Site December 1991 l

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