ML20247R893

Summary of 890817 Meeting W/Nuclear Assurance Corp in Rockville,Md Re Submittal of dual-purpose Storage/Transport Cask Design for Approval Under 10CFR72 & Certification of 10CFR71.Attendance List & Agenda Encl

ML20247R893
Person / Time
Issue date:	08/25/1989
From:	Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 8910020098
Download: ML20247R893 (4)

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MEMORANDUM FOR: Leland C. Rouse, Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety.

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FROM:

John P. Roberts, Section Leader Irradiated Fuel Section

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Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS

SUBJECT:

MEETING WITH NUCLEAR ASSURANCE CORPORATION DATE/ TIME:

August 17, 1989; 9 a.m.

l LOCATION:

Room 48-11. One White Flint North Building, Rockville, MD ATTENDEES:

See enclosure 1 PURPOSE:

To discuss the submittal of a dual-purpose storage / transport I

cask design for approval under 10 CFR Part 72 and certification under 10 CFR Part 71.

DISCUSSION:

Nuclear Assurance Corporation (NAC), Empresa Nacional de Residuos Radiactivos, S.A. (the Spanish equivalent of the U.S. Department of Energy), and Virginia Power met with NRC staff from the Transportation Branch (SGTB) and the Fuel Cycle Safety Branch (IMSB). An aid from Spain's Consejo de Seguridad Nuclear (the Spanish equivalent of the U.S. Nuclear Regulatory Commission) also attended. The main topics of discussion concerned meeting transportation requirements (see enclosure 2, Agenda) for a stainless steel and lead (with solid resin neutron shield) dual-purpose cask. Separate requirements for dry storage were also addressed. A topical report for dry storage design approval will be submitted in October 1989. An application for shipping cask certification will be sutaitted in January or February 1990, although information on testing will be submitted in 1989. SGTB and IMSB staff have already discussed the need to coordinate safety reviews to avoid duplication of effort. The cask body design is similar to that of NAC dry h:910020098 8*082E'ToeseescNg p

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J storage ~ cask designs previously reviewed by :IMSB. However, the' cask body is-modified to' allow two lids. With an outer: lid, seal replacement could be made on the storage' pad for__ direct offsite shipment. The cask weight will be about

.125 tons. Casks are being fabricated in Santander. Spain. An inspection' trip

-by SGTB staff in-fall'1988 was discussed, but no commitment was made.

Original Signed by.

John P. Roberts John P. Roberts, Section Leader Irradiated Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS

Enclosures:

1) Attendance List

2) Agenda Distributionig C ile Center >

NMSS R/F-IMIF R/F.

JRoberts LCRouse FBrown Beveridge/ Cornell 1-23 ns

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as ATTENDANCE LIST'

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Meeting with Nuclear Assurance Corporation _

August. 17.'1989

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NAME.-

' ORGANIZATION Carl Withee-NRC - Transportation Henry Lee-NRC.- Transportation

. Daniel Huang NRC. Transportation-Curt Lindner.

NRC - Transportation:

Maruin Smith Virginia Power Jose R. Martin Consejo Segguridad Nuclear

'1-Pedro Carboneras Enresa.

. Alan Wells NAC-

C. E. MacDonald NRC - Transportation Norm Meinert NAC Suzanne Schuyler<

NRC/ International Programs Michae1~Yaksh.

NAC Trinidad Perez.

.Enresa Eduardo Ramirez Enresa

. John Cook

.NRC - Transportation John P. Roberts

.NRC/IMSB Carol'S. Thorup

'NAC a

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L U.S. NRC MEETING AGENDA August 17, 1989 Introductory Remarks:

Empresa Nacional de Residuos Radiactivos, S.A.

Virginia Power Corporation Nuclear Assurance Corporation Cask Basket Desian

• 1/9th Scale Model of 28 Element Basket

• 1/4 Scale Model Fuel Assembly

• Basket Structural Analysis Cask Body

• Inner & Outer Lid Bolt Stresses and comparison with allowable stresses

• SCANS Side Drop Analysis Results Impact Limiters

• Limiter Design

- Stainless Steel Skin

- Two Crush Strength Honeycomb

- Mechanical Joint

• Impact Limiter Test Plan

- Eighth-scale Quasi-static Tests

- Quarter-scale Dynamic Tests Proiect Milestones and Specifics

• Project Status

• Use of Reg. Guide. 3.48 or Reg. Guide 3.61 for TSAR submittal 4

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