ML20198D541
ML20198D541 | |
Person / Time | |
---|---|
Site: | 07109244 |
Issue date: | 05/19/1992 |
From: | Osgood N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
References | |
NUDOCS 9205210066 | |
Download: ML20198D541 (2) | |
Text
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I 1,
MAY 1 u 1992 o
SGTB:NLO 71-9244 MEMORANDUM FOR: The Files FROM: Nancy L. Osgood, SGTB, SGTR, NMSS
SUBJECT:
MEETING
SUMMARY
REGARDING TRANSPORT OF MILLSTONE 2 STEAM GENERATORS hit.tadf21 lE IN [ hem-Nuclear Ross Chappell Bill Allen Bob Anderson Henry Lee Raj Harnal Mirza Baig Nancy Osgood holf Koste Iqbal Husain Steva Ruffin Robert Lefebvre Hal Young Hechtel Alice Cummings latroduction A meeting was held on April 16, 1992, in Rockville, Maryland, at the request of Northeast Utilities (NU). NU has submitted an application for certification of the Millstone 2 steam generators as radioactive material transport packages. The meeting was held to discuss the tie-down system to be used during the transport of the steam generators.
Discussion
- 1. Tie-down system description. NU has revised the tie-down system for the package. There are no tie-down points which are a structural part of the package. The current concept for the tie-down system includes two cradles with cables strapped around the steam generator, and a key block to restrain the package longitudinally.
- 2. Tie-down standards. NU has evaluated the tie down standards of DOT, AAR, -
NRC, and ANSI. NU proposed to follow the standards in ANSI N14.24 which are for barge transport of highway-route controlled quantities of radioactive material. The ANSI standard has provisions for accelerations due to collision, wave action, etc., as well as stress limits.
- 3. Tie-down system evaluation. NU has evaluated the proposed steam generator '
tie-downs against the ANSI standard. NRC stated +' at the allowable stress
, limits appeared too high, and it was not clear that the standards should be applied to the trailer. NRC stated that the stresses in the trailer members y
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should also be subject to a set of Allowable stresses and that the adequacy of this set of allowables should be justified. NRC stated that a block could be welded on the steam generator at the transition to bear against a fixture on the trailer, provided there were no attachments to the block.
- 4. Certification of package tie-downs. NRC recuested that HU dettraine if I the package tie-down system will be reviewed and certified by an independent agency, such as the Coast Guard or the insurer. NU stated that t5ey would provide that information by telephone within a week.
- 5. Shipment schedule. NV stated that the removal of the old steam generators i is scheduled to begin in May. NU stated that they had hoped to have package certification by the time the steam generator removal started.
Original signed by <
Nancy L. Osgood Transportation Branch Division of Safeguards and
- Transportation NMSS 8
8 8
DISTRIBUTION:
NRC PDR NRC File Center-NMSS r/f SGTB r/f CEMacDonald-Meeting Attendees Meeting Notebook GVissing 6ii, :SGIB g :SGTB
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NAME:NL0sgood : CRC a pell DATE:5/13 /92 :5/ /92 0FFICIAL RECORD CO)Y
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