ML20035B281

Summary of 930310 Meeting W/Util in Rockville,Md Re Discussions on Universal Canister Sys Proposal to DOE for Development of Integrated Sys Approach to Spent Fuel Storage,Transportation & Disposal.List of Attendees Encl

ML20035B281
Person / Time
Issue date:	03/29/1993
From:	Sturz F NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Haughney C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
REF-PROJ-M-38 NUDOCS 9304010138
Download: ML20035B281 (24)

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WASHINGTON. D.C. 20555-0001

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f gv MAR 2 91993 Docket No. M-38 MEMORANDUM FOR:

Charles J. Haughney, Chief Source Containment and Devices Branch Division of Industrial and Medical Nuclear Safety FROM:

Frederick C Sturz, Section Leader Irradiated Fuel Section Source Containment and Devices Branch Division of Industrial and Medical Nuclear Safety i

SUBJECT:

MEETING WITH VIRGINIA POWER ON ITS UNIVERSAL CANISTER SYSTEM PROPOSAL TO THE DEPARTMENT OF ENERGY ATTENDEES:

See attached list (Enclosure I) r DISCUSSION:

A meeting was held on March 10, 1993, in Rockville, Maryland, to allow Virginia i

Power (VP) an opportunity to brief NMSS on its proposal to the Department of i

Energy (DOE) on a Universal Container System (UCS) for the development of an integrated systems approach to spent nuclear fuel storage, transportation, and disposal.

VP first discussed its proposal to design, construct prototypes, license, and demonstrate the UCS in a cooperative agreement with the DOE with the goal of delivering 60 units for storage, to utilities by January 1998.

Discussions generally followed VP's UCS proposal presentation provided as Enclosure 2.

The UCS consists of a sealed inner metal container (IMC) with separate overpacks for -

storage, transportation, and disposal.

Phase I (1993-1994) of VP's proposal calls for the preparation' of designs for the IMC, storage and transportation overpacks and the safety analysis reports.

Phase II'(1995-1996) would consist of the licensing reviews, fabrication of prototypes, and testing.

In 1997, VP proposes to conduct transportation system and licensed storage demonstrations.

Phase III (1997-1998) would consist of fabrication of 60 IMCs for delivery to.

utilities for storage and production of transportation overpacks based on DOE needs for 1998.

l The second phase of the meeting's discussions focused on the UCS licensing requirements and processes which generally followed VP's handout provided as Because of the more rigorous requirements for a transportation cask, NRC staff encouraged VP, in its quest for Part 71 and 72 certifications, to. consider submitting the safety analysis report for 10 CFR Part 71 certification first.

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l 9304010138 930329

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6 MAR 2 91993 4

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l The meeting' concluded with VP providing a copy of its " Proposal To The DOE,

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Development And Demonstration Of A Universal Container System," (without l

proprietary cost data) for docketing.

original. Signed by:

rrederick c. sturn i

Frederick C Sturz, Section Leader Irradiated Fuel Section Source Containment and i

Devices Branch Division of Industrial and Medical Nuclear Safety 1

i

Enclosures:

As stated i

cc: LDessell, DOE /0CRWM i

Distribution:

PDR Docket File M-38 Attendee list NRC File Center IMIF R/F IMNS Central File SCDB R/F HThompson RBernero GArlotto RECunningham s

JYoungblood JLinehan RBallard CMacDonald FSturz RChappell EShum KCleu MRaddatz JSchneider FBrown BBuckley, NRR HLarson, ACNW AEiss JSpraul 0FC IMd h

IMIF, i

C NAME

'fh z:jc FLB'robb ObAh/93 03f(h93 DATE C = COVER E = COVER & ENCLOSURE N = NO COPY G:VPVCS.MRS.

i

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gR 2 91933 i-NAME AFFILIATION Fritz Sturz NRC/NMSS Glenn Williams Weston/ICF i

V. Lewis Killpack Weston/ URIC j-Hal Cleary Weston/Jacobs Eng.

Charley Haughney NRC/NMSS l

Charles E. MacDonald NRC/NMSS Marvin L. Smith VEPC0 Ronald Berryman VEPCO H. L. Bowling VEPC0 Jim Schneider NRC/NMSS Ross Chappell NRC/NMSS i

Rick Weller NRC/NMSS l

John Stokley SAIC.

K. C. Leu NRC/NMSS David M. Dancer NRC/NMSS i

Robert G. Morgan Duke Engineering & Service Ron Ballard NRC/NMSS H. M. Fontecilla VEPC0 B. J. Youngblood NRC/NMSS John P. Jankovich NRC/NMSS Earl Easton NRC/IMNS l

King Stablein NRC/0EDO l

Bill Reamer NRC/0GC Bob Bernero NRC/NMSS 1

Richard Cunningham NRC/NMSS i

Joe Holonich NRC/NMSS i

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Phase HI(199'7-1998)

Produce 60 IMCs For DeliveryTo Utilities Beginning January,1998 ProduceTransportation Overpacks Based On DOE Needs For 1998 Publish Documentation l

PSO4310

e Universal Container System Proposal 1993 1994 1995 1996 1997 1998 1

2 3

4 1

2 3

4 1

2 3

4 1

2 3

4 1 2 3

4 1

2 3

4 1

Develop Design Requirements j2n Design Of IMCs ty w 2;a1 l

DesignTransfer And Storage bem Overpacks Prepare StorageTopical Safety p" ", ~,,...

Analysis Report

~

NRC Storage Licensing tn:rw]

I Design Transportation Overpacks IWi+J PrepareTransportation Safety

1. "d Analysis Report For Packaging NRCTransportation Licensing

'ca M w w # 1 Fabricate Prototypes Of IMCs And Overpacks ki'yff

~3. n

Universal Container Systern Proposal (Continued) 1 1993 1994 1995 1996 1997 1998 1

2 3

4 1

2 3

4 1

2 3

4 1

2 3

4 1

2 3

4 1

2 3

4 1

Conduct Storage PrototypeTests b++Al Perform Full ScaleTransport Drop g

And FireTests l

Provide Disposal Protot $ds For j g.g RepositoryTesting Select Utilities For Demonstrations

[E Fabricate IMCs For Demonstrations g ~3:;.:,;rg At Utility Sites

~ ^

UCS Storage Demonstration 11 e =-

N Fabricate Production Transportation Overpack, impact Limiters, Rail Car, a r i!::: M I And Auxiliary Equipment Production Of 60 Inner Metal ymmeye;gnyj Containers Deliver First 60 Units EMNJ

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i UNIVERSAL CONTAINER SYSTEM LICENSING REQUIREMENTS UCS Must Be Licensed Under.Several NRC-Regulations:

i 10 CFR 50 Handling Of UCS Containers in Spent Fuel L

Pools Must Be Reviewed Under 10 CFR 50.59 May: Require License Amendments At Some Reactors 10 CFR 71 IMC Plus Transport Overpack 10 CFR 72 IMC And Storage Overpacks Will Be Licensed

.Under Generic Licensing Provisions Of-Part 72 IMC And Storage ~Overpacks Would Also Have To Be. Licensed For Storage' At Federal Sites-(MRS And Repository)-

10 CFR 60 IMC.Plus Disposal Overpack

UNIVERSAL CONTAINER SYSTEM l

~

LICENSING PROCESS Frequent Interaction With NRC Planned During Design, Safety l

Analysis Report Preparation, Prototype Testing, Licensing, And Demonstration Of UCS Inner Metal Container (IMC), Storage Overpack, And Transport Overpack Would Be Licensed Together For Transport (10 CFR 71)

And Storage (10 CFR 72)

Part 72 Topical Safety Analysis Report To Be Submitted Fourth O.uarter,1994 Part 71 Topical Safety Analysis Report To Be Submitted First Quarter,1995 Virginia Power Proposal includes Full Scale Prototype Testing in 1996 With Test Plans Provided To The NRC Mechanisms For Licensing UCS IMC For Disposal (With Disposal Overpack To Tailor Package To Final Repository Environment)

Would Be Discussed With NRC Virginia Power Believes That One NRC Project Manager Responsible For Coordination Of Reviews Under The Different NRC Regulations Could improve Review Process t

.z REGULATORY ISSUES AFFECTING UCS LICENSING b

10 CFR 50,60,71, And 72 Should Be Reviewed For Consistency in a

R UCS Requirements Duration Of License Compared With Projected Repository Operation Dates (Approximately 2010 To 2050)

Five Year Renewable License For Transportation 20 Year Renewable License For Storage Engineered Barrier System Licensed For 300 To 1000 Years Of Substantially Comp.lete Waste Confinement:

Generic Licensing For Storage Under 10 CFR 72 Of Pro arietary Vendor Designs Versus Specification Of Design Or Perlormance 3

Requirements.

Mechanisms For Early NRC Approval Of.UCS IMC As Part Of Engineered Barrier System 1

i

.-.__.._...-..__.,-...-__.__......___.__..__.-...._.._....__._.:,,.______.._...I

4 3

1 l

EXAMPLES OF TECHNICAL / LICENSING ISSUES REQUIRING EARLY' RESOLUTION l

Criticality Control Methods NRC Requirements To Extend Acceptance Of Burnup Credit 1

For Spent Fuel Storage Under 10 CFR 50 To Storage,.

Transport,: And Disposal Under 10 CFR 60,-71, And 72 Requirements Under 10 CFR 60,71, And 72 For Neutron Absorber Materials And Structures To Ensure Fuel Assembly Separation.

Use Of Shielded IMC Versus Controls Required For Transfer Of Unshielded IMC At Utility And DOE Sites Fuel inspection-Requirements l

~

NRC QUESTIONS ON UCS What Analyses Has Virginia Power Performed That Indicates That The UCS Would Reduce Exposure And Risk?

DOE Studies Show That The UCS Would Reduce Spent Fuel Handling Operations From About 1,000,000 To 300,000 Use Of A Sealed IMC Will Help Reduce Spread Of Contamination And, if A Shielded IMC is Used, Will Provide Substantial Shielding And Structural Integrity During Spent Fuel Transfer Operations Virginia Power's Proposal To DOE includes PRA And ALARA Studies To Compare Risks And Exposure With The UCS And The DOE Reference System Will The IMC Consider 10 CFR 60.135?

The IMC Design in Our Proposal To DOE Would Consider 10 CFR 60.135 Requirements The IMC Proposed By Virginia Power Would Support Use Of A Self-Shielded Waste Package The IMC Plus Overpack Could Provide A Robust Engineered Barrier System To Balance Reliance On Geology And Engineered Barriers The UCS System Can Simplify Repository Operations And improve Ability To Retrieve Spent Fuel

.