ML20217K119

Summary of 970605 Meeting W/Nac,Ornl & Public to Discuss Preliminary Design of New Transport Package for Californium. Meeting Handouts Encl

ML20217K119
Person / Time
Issue date:	07/30/1997
From:	David Tiktinsky NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Chappell R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9708150140
Download: ML20217K119 (26)

Text

._

MEMORANDUM FOR:

Ross Chappell, Chief July 30, 1997 Package Certification Section, SFP0 FROM:

David Tiktinsky, Project Manager Package Certificatic,n Section, SFP0

SUMMARY

OF MEETING HELD BETWEEN NUCLEAR ASSURANCE CORPORATION (NAC), OAK RIDGE NATIONAL LABORATORIES (0RNL)

AND THE NUCLEAR REGULATORY COMMISSION (NRC) ON A PROPOSED CALIFORNIUM TRANSPORT SYSTEM Attendees:-

BBC ILAL Ogt{L Public David Tiktinsky Bill Lee Cathy Simmons Robert Sweeney Li Yang Mike Yaksh Chris Brown Tom Thompson Andrew Gaunt John J. McCarthy Ross Chappell Introduction On June 5,1997, a public meeting was held between NAC, ORNL and NRC to discuss the preliminary design of a new transport package for Californium.

NAC is under contract to ORNL to design the package.

Discussion 1.

Discussed the general design of the cask and impact limiter for the Californium Transport System.

2.

Discussed general testing requirements to demonstrate compliance with 10 CFR Part 71.

3.

Discussed shielding requirements and potential designs for the Californium Transport System.

4.

Discussed future need for meetings prior to testing of the package.

Attachment:

Meeting Handouts

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Distribution:

PDR NMSS r/f SFP0 r/f SShankman CHaughney MYaksh, NAC,

'JMcCarthy, NAC

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Californium Transport System I

Presentation to the U.S. Nuclear Regulatoly Commission Thursday, June 5,1997 w, - = 9,-

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Bill Lee, Vice President & Chief Engineer, Cask Technology u

i Tom Thompson, Manager, Licensing n

John McCarthy, CTS Project Manager m

Mike Yaksh, Manager, Structural / Thermal Analysis a

i Oak Ridge National Laboratory Cathy Simmons, CTS Project Manager a

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j Califomium Transport System Design Overview l

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Califomium Transport System Source 60 mg (maximum) Californium252 a

Californium contained in sealec capsules that conform to a

the requirements for special form radioactive material Cask shall accommodate four basket designs:

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- One 6-hole basket to accommodate 6 OR-Cf-3000 capsu:es with individual spacers to change to OR-Cf-100 j

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- One 4 hole ba.sket to acmmmodate 4 NSD capsules with individual spacers to change to NSS capsules

- One basket to accommodate 1 OR-Cf-1000 capsu!e

- One basket to accommodate pneumatic adapters

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~ Califomium Transport System Project Integration Project integration Philosophy 1

- Quality assurance

- Design and analysis l

- Certification and licensing

- Cask operations

- Transportation i

- Fabrication 7,,,....----

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Californium Transport System Quality Quality assurance is the cifference r

Integrated throughout the project from project a

planning through design into fabrication i

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I gNAC EiPEINTERNATIONAL At NAC International, Quality means:

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m Leadership that is recognized industry wide i

a Performance that sets the standard for excellence e Integrity that enhances safety i

m Dedication that exceeds l

customer expectations a Commitment that makes a difference l

Taato taru van==e i

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Tota. Qua.ity Management Initiatives Summary for 1996 Recruitmen of a nationally recognized Quality Assurance (OA) director and former m

QA director for the DOE h1PC program Elevation of the lead QA position from director to vice president, quality a

Completion of an extensive company wide internal audit (summer '96) e Comprehensive revision of the NAC Ouality Assurance hianual, including:

e a Restatement of NAC's quality program commitments a Restatement of applicable regulatory requirements Sweeping revision and reissuance of Quality Procedures used to implement a

OA h1anual procedures Addition of a quality assurance manager and a quality assurance engineer a

Establishment of a manageriallevel position, within the Engineering Department, to a

oversee documentation management for QA program compliance Reassignment of non-QA responsibilities from OA coordinator to other personnel a

Recruitment of a document control and records management administrator e

Developed a comprehensive action program in response to NRC audit a

Accelerated annual maintenance of the NAC L%T transport cask fleet e

Complete review, revision and upgrade of cask maintenance procedures a

initiation of a review oflicensing basis documents used in support of basic design and e

modifications to transportation packaging and storage systems In-depth training sessions for management, engineering, operations and QA personnel a

1 to ensure an effective understanding of NAC's OA program Establishment of an ongoing total quality management campaign to elevate employee a

awareness i

Ilow ard Smith Vice lhedent, Quahty NAC 1niemanonal 6A5 Engmeenna Dme 4N.I'l 4 Fu 770 4471797

NAC international Quality Assurance Initiatives in 1996 Nationally known QA expert serves as vice president, quality; m

overall QA staff increase QA program description; QA manual revision a

New quality procedures issued November 1996 a

Quality Assurance Task Force of senior staff and CEO m

Enhanced project planning; numerous staff training sessions m

Company-wide " Quality is the Difference" program focus a

The CTS SAR is being prepared as a safety-related document a

in full accordance with NRC-approved quality assurance orogram The CTS will have cornprehensive design reviews conducted s

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i Califomium Transport System Cask De'scription l

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a Tube assembly - tube, guice tube, alug tube anc cover i

a Primary shielcing - 3rompt 3hoton slielc 1

(tungsten), primary neutron shielc (h S4FR with 6.5% B C), anc primary slie.c plate (stainless 4

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= Secondary shieLcing - seconcary neutron slielc (NSLFR with 6.5% B C) and seconcary slield plate 4

(stainless stee )

m Other features - cask stand and melt alugs

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CaHfomium Transport System l

Impact Limiter Description I

e Impact limiter shell i

l m Impact limiter foam (General Plastics LAST-A-FOAM #FR-6700) l m Lifting operations a Tie-down oaerations l

m Other features - melt plugs i

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Californium Tran. sport System Design Criteria Normal conditions of transport in accordance with 10CFR71.71 a

Hypothetical accident conditions in accordar.ce with 10CFR71.73 m

Air transport requirements in accordance with IATA Resolution 618, m

Attachment A, Dangerous Goods Regulations, and ICAO Technical Instructions for the Safe Transport of Dangerous Goods by Air Load combinations in accordance with Regulatory Guide 7.8, Load a

Combinations for Structural Analysis of Shipping Casks Rail transport requirements in accordance with Association of a

American Railroad Interchange Rules a

Calculated and allowable stresses consistent with the criteria provided in ASME Section 111 Subsection NF, Supports fhf a

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Califomium Transport System Shielding r

Dose rates for normal conditions of transport at the secondary shield a

plate shall comply with 10CFR71.47 Dose rates for hypothetical accident conditions shall comply with s

10CFR71.51(a)(2) i

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CTS dose rates shall be limited to:

- 120 mrem /hr at the outer stainless steel surface of the secondary neutron shield under normal conditions of transport

- 7.5 mrem /hr at two meters from the outer stainless steel surface of 61e secondary neutron shield under normal conditions of transport

- 0.8 rem / hour at 1 meter from the outer stainless steel surface of the primary neutron shield under hypothetical accident conditions

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Califomium Transport System Therma l Evaluation Normal Condition of Trans3 ort (10 CFR Part 71)

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Heat loads

- Source -insignificant

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Steady state thermal evaluation:

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- Finite element modelis comprised oflimiters/ shells /NS4FR/ tubes 1

m Thermal criteria

- NS4FR for primary / Secondary Shield: 210 F maximum Preliminary results:

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- Maximum NS4FR steady state temperature: <150 F v- 7mW : -

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Californium Transport System l

Thermal Evaluation T7ermal-Accident Condition (10CFR71) a Heat loads

- Fire condition is applied to the outer shield shell

- Fire condition includes additional convection term

- Post fire condition includes solar insolance on the inner shell e Transient thermal evaluation:

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- Finite element modelis comprised of shells /NS4FR/ Tubes a Thermal criteria:

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- Secondary shield: assumed to be lost

- Primary shield: 210 F maximum Preliminary results:

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- Maximum NS4FR temperature: <190 F

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Califomium Trans,oort System Structural Evaluation l

m Impact limiter

- Foam enclosed in stainless steel shells

- Operating limits:-40 F to 150 F i

a Normal operating condition

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- Targel deceleration: 20 g's m Accicent concitions

- Designed for 30-foot drop

- Target deceleration: 65 g's i

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Californium Transport System Structural Evaluation l

Package Body Normal conditions of transport m

- Secondary shielding is designed to support and back the outer shell l

- Quasi-static analysis

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- Finite element modelincludes j

Simulation of pressure load on secondary shell 1

Half symmetry model Compression modulus for NS4FR Gap between the NS4FR and shells Includes weight of prompt photon shield Includes the weight of the primary shield wu c>..n

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Califomium Transport System Structural Evaluation Package Body (continued)

Normal conditions of transport (continued)

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- Drop impact loading orientations l

End CG over limiter corner Oblique Side

- Structural criteria General primary membrane stress intensity is less than the design stress intensity value, P

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Primary membrane plus primary bending stress intensity is less than l

1.5 times the design :+ress intensity value, P +P < 1.SS m

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Califomium Transport System Structural Evaluation l

Package Body a Accident Concitions

- Impact limiter is backed by the secondary shield

- Quasistatic analysis l

- Finite element model is identical to the model for l

the normal conditions of transport i

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Califomium Transport System Structural Evaluation Package Bocy (continued) a Accident concitions (continuec)

- Drop impact loading orientations

- End CG over limiter corner Oblique

- Side

- Structural criteria t

General primary membrane stress intensity is less than the 1.5 times the design stress intensity value, P

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m Primary membrane plus primary bending stress intensity is less than 2.25 times the design stress intensity value, P +P < 2.25S m

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Californium Transport System l

Cask CertMcation i

a DOE Certificate of Compliance

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(Type B'U)-85 per DOE Order 1540.2) f 4

l m NRC Certificate of Compliance l

(Tyae B(U)-85 per 10 CFR 71) i l

m DOT Certificate of Com3etent Authority l

'Per IAEA Regulations)

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Californillm Transport System Project Schedule i

Key milestones and/or points of significant interest are:

s Project Kick-off Meeting

- February 1997 m Des:un and Analysis Complete

- July 1997 m NAC Internal SARP Review Complete

- August 1997

= Final SARP Preparation Complete -

- September 1997 m Submit SARP to Department of Energy

- September 1997 m Submit SARP to NRC

- October 1998 m Certification / Licensing Complete

- February 1999 m Start Fabrication

- March 1999 m Deliver CTS to ORNL

- December 1999

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i Califomium 1~ransport System Summarf a Purpose i

n Quality assurance a Design 1

a Certification a

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P War.22.1997 10:39AM NACINiltNAT10NAl.17704471797 No.9870

?. 2/2, MEETING AGENDA USNRC SPENT FUEL PROJECT OFFICE NACINTERNATIONAL JUNE 05,1997 (1:00 PM 1:00 PM)

CALIFORNIUM TRANSPORT SYSTEM (CTS)

INTRODUCTIONS CTS PROECT OVERVIEW CASK CERTIFICATION MATERIAL TO BE TRANSPORTED REVIEW OF PACKAGING PRELIMINARY DESIGN DESIGN CRITERIA SHIELDING STRUCTURAL IMPACT LIMm!RS HANDLING OPERATIONS PROJECT SCHEDULE

SUMMARY

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