ML063520343

Ltr to P Paquin Special Package Authorization for the La Crosse Reactor Pressure Vessel Transportation Package - Revision 1 (TAC L24019) (with Enclosure 1)

ML063520343
Person / Time
Site:	La Crosse, 07109322  File:Dairyland Power Cooperative icon.png
Issue date:	12/15/2006
From:	Nelson R NRC/NMSS/SFPO
To:	Paquin P Duratek
Caverly J./SFST/NMSS/415-6699
Shared Package
ML063520339	List: ML063520343 ML063520350
References
TAC L24019
Download: ML063520343 (4)

Text

December 15, 2006 Mr. Patrick Paquin General Manager - Engineering & Licensing Duratek, Inc.

140 Stoneridge Drive Columbia, South Carolina 29210

SUBJECT:

SPECIAL PACKAGE AUTHORIZATION FOR THE LA CROSSE REACTOR PRESSURE VESSEL TRANSPORTATION PACKAGE - REVISION 1 (TAC NO. L24019)

Dear Mr. Paquin:

Under letter dated September 17, 2006, Duratek, Inc., submitted an application for a revision to the Special Package Authorization for the Model No. LACBWR RPV transportation package.

The package was authorized for transport under the provisions of 10 CFR 71.41(d) as a Special Package Authorization, dated April 27, 2006. The package will transport the Dairyland Power Cooperatives La Crosse Boiling Water Reactor decommissioned reactor vessel. The current application requests that the outer supplemental shielding component of the package design be revised as optional. This application was reviewed by staff of the U.S. Nuclear Regulatory Commission. The staff has approved the changes to the Special Package Authorization under the provisions of 10 CFR Part 71. The results of the staffs review are documented in the enclosed Safety Evaluation Report.

The package, Model No. LACBWR RPV, is the reactor vessel enclosed within a cylindrical steel canister and concrete grouting. The vessel consists of a cylindrical shell section with a formed integral hemispherical bottom head and a removable hemispherical top head, which is bolted to a mating flange on the vessel shell. The vessel wall has a nominal thickness of 4". The vessel is ferritic steel plate with integrally bonded Type 304L stainless steel cladding. The reactor internals consist of a thermal shield, a core support skirt, a plenum separator plate, a bottom grid assembly, steam separators, a thermal shock shield, a baffle plate structure with a peripheral lip, a hold-down mechanism, control rods, fuel assembly shrouds and reactor core support structures. The voids in the reactor vessel are filled with low-density cellular concrete.

The nozzles and lifting devices for the vessel will be cut prior to removing it from the reactor building.

The annulus between the reactor vessel and the canister is filled with medium-density concrete.

The canister is formed from 1.5' thick steel cylindrical shell with 4" end plates. The completed package is approximately 39' 7" long with an outer diameter of 10' 6". All joints of the canister are welded forming the containment boundary and providing a tamper-resistant seal. Shielding is welded to the exterior of the canister at the location of the core. The lower portion of the canister will have eight support legs where the lower section of the reactor vessel will be placed.

There are no lifting or tie-down devices that are a structural part of the package. The total design weight is approximately 624,500 lbs.

P. Paquin The package, Model No. LACBWR RPV, is authorized to transport irradiated steel reactor pressure vessel and internal components from the La Crosse Boiling Water Reactor. The maximum quantity of material per package is greater than a Type A quantity of radioactive material contained in an irradiated reactor vessel, mirror insulation, and internal components and associated surface contamination. Fissile material may be present provided the fissile material meets the exemption standards in 10 CFR 71.15.

In addition to the requirements of Subpart G of 10 CFR Part 71, the following conditions apply to the Special Package authorization:

(1) The package must be prepared for shipment and transported in accordance with Chapter 7 of the application, as supplemented.

(2) The package must be acceptance tested in accordance with Chapter 8 of the application, as supplemented.

(3) Transport of the package may only be initiated if the ambient temperature at the site is greater than 0oF. The ambient temperature will be monitored throughout the transport process and transportation will be stopped should the temperature fall to 0oF.

(4) The package authorized by this approval must be transported by motor vehicle or railroad car assigned for the sole use of the shipper.

(5) The package is constructed and assembled in accordance with Duratek, Inc.,

Drawings: C-068-163041-002, Rev. 1; C-068-163041-003, Rev. 0; C-068-163041-004, Rev. 0. The 1 3/4" supplemental shielding plates identified as optional on Drawing C-068-163041-002, Rev. 1, may be omitted or may be replaced with shield plates less than 1 3/4" thick, provided that the plates are of the same configuration, material of construction, and type of attachment as those specified.

(6) The package is a one-time only, exclusive use shipment.

(7) The package must be marked with the following:

Model Number - LACBWR RPV Package; Package Identification Number 9322; gross weight; and serial number.

P. Paquin The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.

The Special Package Authorization will expire on April 30, 2011.

The original application is dated December 16, 2005, and supplemented January 5, March 5 and 16, 2006. The original Special Package Authorization is dated April 27, 2006.

This revision supercedes previous revisions of this Special Package Authorization.

If you have any question regarding this matter, I may be contacted at 301-415-8500.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

/RA/

Robert A. Nelson, Chief Licensing Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket No. 71-9322 TAC No. L24019

Enclosure:

Safety Evaluation Report cc: R. Boyle, US DOT J. Williams, US DOT

P. Paquin The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.

The Special Package Authorization will expire on April 30, 2011.

The original application is dated December 16, 2005, and supplemented January 5, March 5 and 16, 2006. The original Special Package Authorization is dated April 27, 2006.

This revision supercedes previous revisions of this Special Package Authorization.

If you have any question regarding this matter, I may be contacted at 301-415-8500.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION Robert A. Nelson, Chief Licensing Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket No. 71-9322 TAC No. L24019

Enclosure:

Safety Evaluation Report cc: R. Boyle, US DOT J. Williams, US DOT Distribution:

NMSS r/f BWhite JCuadrado SBrown NOsgood JGlenny KHardin KBanovac, DWMEP MRahimi C:\FileNet\ML063520343.wpd OFC SFPO E SFPO E SFPO SFPO SFPO NAME JCaverly* MDeBose* LThompson* MWaters* RNelson DATE 11/29/06 11/30/06 11/30/06 12/01/06 12/15 /06