ML20135A727

Summary of 961031 Meeting W/Doe in Rockville,Md Re NRC Role in Review of DOE Aluminum Based Research Reactor Spent Nuclear Fuel Disposition Program.Agenda,List of Attendees & Associated View Graphs Encl

ML20135A727
Person / Time
Issue date:	11/22/1996
From:	Gruss K NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Brooks D NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9612040018
Download: ML20135A727 (41)

Text

'

November 22, 1996 I

MEMORANDUM T0

David J. Br:oks, Acting Branch Chief l

ENGB/DWM/NMSS l 6 THRU: Richard. A. Weller, Section Leader ENGB/DWM/NHSS /s/

FROM: Kimberly A. Gruss, Engineer ENGB/DWM/NMSS /s/ RAW for KAG

SUMMARY

OF THE U.S. NUCLEAR REGULATORY COMMISSION AND THE U.S. DEPARTMENT OF ENERGY MEETING (NRC'S ROLE IN THE REVIEW 0F DOE'S ALUMINUM-BASED RESEARCH REACTOR SPENT NUCLEAR FUEL DISPOSITION PROGRAM)

DATE OF MEETING: October 31, 1996 PLACE OF MEETING: One White Flint North, Rockville, MD (0-6B11) l ATTENDEES: See Attachment 2 The meeting was held at the U.S. Department of Energy's (D0E's) request to discuss the U.S. Nuclear Regulatory Commission's involvement in the review of DOE's aluminum-based research reactor spent nuclear fuel disposition program. '

The meeting agenda, list of attendees, and associated view graphs are attached (Attachments 1,2 and 3, respectively). DOE presented an overview of the aluminum-based research reactor spent nuclear fuel, project organization, preliminary schedule, and key milestones. An outline of DOE's strategy for I interim storage and ultimate disposal of the fuel, the program goals, and a suggested timetable for preparation and review of documentation were also presented.

DOE would like to obtain assistance from staff in identifying issues pertaining to NRC disposal requirements for a geologic repository. The i initial phase of this activity involves a technology development program to '

define disposition concepts and waste forms that would likely be acceptable for geologic disposal. A Memorandum of Understanding (MOU) and an Interagency Agreement (IA) with NRC would be the primary vehicles for establishing the framework for cooperation between DOE and NRC. The MOU and IA are currently being reviewed by NRC.

NRC activities may include the review of approximately 18 documents within the next 2 years. These documents are expected to contain information regarding DOE's technical approach on, and schedule of, activities leading to the storage and ultimate disposal of aluminum-based fuel. NRC made no commitment to DOE regarding the number of documents or the scheduling of documentation review. DOE also requested a meeting with NRC during the next several months, at the Savannah River site, to continue the technical discussions and to develop schedules for NRC's activities. ,-

Attachments: As stated cc: G. F. Cole, DOE-EM C. Hansen, DOE-EM M I p (.,, m hv)

DISTRIBUTION:

g Central File DWM r/f NMSS r/f ENGB r/f KPUBLIC dH10 JGreeves MFederline MBell JAustin KHcConnell JDavis TAhn KChang RCodell EWReamer/0GC DVinson NShridhar/CNWRA DOCUMENT NAME: S:\DWM\ENGB\KAG\AL-B-SFN.MTG

\\ OFFICIAL RECORD COPY gD OFC ENGB ENGB. Eb / J h

D NAME KGrNsYh"*dN RWelYeN DBds _

DATF # M 7/96 9612040018 961122 l // /* t/96 [/96\ l j

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i Attachment I f I

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! Agenda for NRC - DOE Meeting on Aluminum Based Research Reactor Spent Nuclear Fuel Disposition Program h

I October 31,1996,1:00 - 3:00 l l i

. 1 G.F. Cole, EM

1. Introduction and Openina Remarks (15 min)  :

J.R. Williams, RW ]

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! 2. Overview of Aluminum SNF (20 min) S.D. Burke, WSRC  :

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3. Project Oraanization and Schedule (15 min) J.M. Ridley, SR l

M.W. Barlow, WSRC

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4. Technolony Development Proaram (40 min) M.W. Barlow, WSRC j

5. Open Discussion and Next Steos (30 min) All 4

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l NRC/D0E Meeting on Aluminum-Based Research i Reactor Spent Fuel Disposition Program j October 31, 1996 l

l fLAttf, ORGANI ?, TION PHONE Margaret Federline NRC/DWM (301) 415-6708 Bill Reamer NRC/0GC (301) 415-1640 Rick Weller NRC/DWM/ENGB (301) 415-7287 Michael Bell NRC/DWM/ENGB (301) 415-7286 Richard Codell NRC/DWM/PAHL (301) 415-8167 Tae Ahn NRC/DWM/ENGB (301) 415-5812 Dennis Vinson NRC/DWM/PAHL (301) 415-6074 Kim Gruss NRC/DWM/ENGB (301) 415-6680 Carl Everett DOE-SR (803) 557-3828 Jean M. Ridley l DOE-SR (803) 557-3758 Charlie Hansen DOE-EM (301) 903-3849 Frank Cole DOE-EM (301) 903-1450 Howard Eckhert DOE-EM (301) 903-7173 Jon Thompson 00E/EM-67 (301) 903-7433  !

l Steven Jomberg DOE /RW-51 (202) 586-6497 Jeff Williams DOE /RW-51 (202) 586-9620 Chris Einberg DOE /RW-52 (202) 586-8869 David Burke WSRC (803) 557-9565 Edward Burns WRSC (301) 515-6783 J. Richard Murphy WRSC (803) 557-9737 Matraj. C. Iyer WRSC (803) 725-2695 Mark Barlow WRSC (803) 557-8021 Rita Bowser Studsvik, Inc. (703) 327-2400 Marshall David Scientech (301) 428-9583 l Jim Linhart Lockheed-Martin (301) 515-6782 Narasi Sridhar (on conf call) CNWRA (210) 522-5538 l

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i Attachment 3 l i

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.l Presentation to the NRC on the DOE Aluminum Spent Nuclear Fuels Disposition Program October 31,1996 i

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i Presentation to NRC on the DOE Aluminum Spent ~

Nuclear Fuels Disposition Program October 31,1996 1 L- --

e introduction t

J.R. Williams, DOE-RW

. G.F. Cole, DOE-EM e Overview of Aluminum SNF S.D. Burke, WSRC e Organization J.M. Ridley, DOE-SR M.W. Barlow, WSRC e Technology Development Program M.W. Barlow, WSRC

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t introduction  :

- * - - .t i

DOE /NRC MOU and Interagency Agreement e DOE, through RW, provides technical basis for selecting interim storage and ultimate disposal approach e NRC reviews technical basis and provides technical input to DOE e DOE and NRC will develop schedule for accomplishing activities to support the bidding for a privatized transfer and dry storage facility in October 1997 and a final DOE decision on technology in 1999

4 .

.j Introduction (cont'd)

Purpose of today's meeting t

i e Present an overview of aluminum based SNF  !

e Present Project Organization and Schedule e Outline the technology program, including deliverables l Consistent with the Research Reactor Task Team Recommendations (Presented Previously) .

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introduction-(cont'd)

Desired Outcomes from today's meeting:

4 s Agreement to meet at SRS by December to continue technical  !

discussions e Development of the proposed schedule for reviews and future

. i meetings with the NRC 4

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OVERVIEW OF ALUMINUM SNF S.D. BURKE, WSRC i

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e Types of Aluminum SXF I

I Physical Chorocteristics f, .

g Dimensions - 1.2 meters long (0.8 meter with

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Materials - Uranium-aluminum, uranium

'de-aluminum, or uranium silicide-aluminum alloy, clad with aluminum y4 ,

f Uranium -Typically less than 2 kg of uranium per element

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cross-section containing up to 25 flat or curved plates com- Number of Elements rowns. HEU - approx. 22,000 by 2015 LEU - approx. 9,200 by 2015 Sources and Condition y, .

f* University research reactors in U.S., foreign research reactors Fuelisintact with good cladding integeiry

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k lhysical Chorocteristics

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• t Dimensions - 0.80 meters long wih an outside f" * "" diameter of 43 cm  !

Materials - Uranium oxide-aluminum matrix, clad with aluminum

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Uranium - 10 kg of uranium per element (total

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Enrichment - U 235 enrichment of 93%  !

Construction - Primarily aluminum w'ith 171 l

!!.! involute fuel plates in the inner annulus. .nd 369 j  ;  ; j involute fuel plates in the outer annulus l l  ! i Number of Elements

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ll ti 284 HEU elements expected by 2015 (one element

!i discharged from the reactor per mon h) t l l. I Sources and Condition I!

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ii Fuel is intact with good cladding integrity

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e Uranium-Aluminum, Uranium oxide-Aluminum, Uranium silicide-Aluminum alloys e Typical Core thickness: 0.50mm e 12 - 25 plates per assembly Cladding:

o Aluminum o Typical Cladding thickness: 0.385mm Operational Parameters:

e Enrichment: < 20% - 93%

i e Burnup: 47% - 55%

e SNF Heat Generation: 4 - 70 watts / assembly

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e Fuel Cladding & Core Corrodes similar to standard aluminum i

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e Function of oxide layer e Low fission product release rates Breached cladding effects are different than for commercial SNF i

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Typical Corrosion Characteristics Rapid Passivation Day a A Rate '

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PROJECT ORGANIZATION &

SCHEDULE J.M. RIDLEY, DOE-SR j

M.W. BARLOW, WSRC l

O SNF Alternate Technology Project WSRC Organization I.B. (Ben) New Vice President & General Manager Spent Fuel Storage Program Division M.W. (Mark) Barlow Project Manager J.R. (Dick) Murphy _

Technical Staff ,

I B.A. (Brett) Cederdahl N.C. (Natraj) lyer TSF Project Manager SNF Technology Manager m__

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Rev4ews Existine Plan i Protocols I Assesesments i protocol Developrnent (waste Form Quahhcation) M M )

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TECHNOLOGY DEVELOPMENT ,

PROGRAM ,

M.W. BARLOW, WSRC f

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t Technical Program Approach

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i Technical Resource for DOE-RW e Characterize Waste Form Performance and Develop Performance Database Needed for DOE-RW's Performance Assessment

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e Develop Characterization Requirements / Techniques to

Ensure Predictability of Aluminum Waste Form i

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Disposition of Aluminum SNF ~!

Alternative SNF Treatment Technologies Program Goals e Support Transfer Facility Project

- Functional Requirements for Facility Design Description .

e initiate Waste Form Qualification Studies

- Evaluate Potential for Aluminum Waste Forms

- Enable Technology Selection by FY99 e Develop Technical Basis

- Road Ready Package

- Disposalin Repository

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_ _ _ , __________ _ _ _ _ _____________ ______.__.. _-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - " - - - - - - - - - - - - - - - - - - - - - - ^ - ^ - - - - ^ - ~ - - ^ - - - ' - - ------ - - - ' - - - -

O SNF Alternate Technology Project - WSRC Organization M.W. (Mark) Barlow Project Manager i

J.R. (Dick) Murphy ,

Technical Staff I I B.A. (Brett) Cederdahl N.C. (Natraj) lyer TSF Project Manager SNF Technology SRTC Manager I

l l l l R.L. (Bob) Sindelar H.B. (Harold) Peacock, Jr. M.R. (Mac) Louthan, Jr. E.(Eric) Skidmore  ;

Direct Disposal Team Dilution Tech. Team Test Protocal Team Characterization j

. i Direct Disposal Melt / Dilute Dry Storage Press / Dilute

Disposition of Aluminum SNF Program Strategy  ;

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e Technology Base for interim Storage

- SNF Performance in Basin Storage t n Life Prediction Model ' '

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- SNF Performance in Dry Storage (50 years) 1

'I n Acceptance Criteria Systems Design Requirements e Build On and Extend Technology Base  !

- SNF Performance in Road Ready Package

- Waste Form Qualification for Repository .

Leverage DOE Laboratory Expertise  !

Facilitate Development of ASTM Standard f

Technology Program Team

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SRS PNNL INEL i

Test Protocol National DOE-SNF for Al SNF Program l

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Characterization Dilution Technology Database Off Gas System Engineered Barrier &

_. Accelerated Environmental Testing ,

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Disposition of Aluminum SNF Technical Documents for Review

, initial Documents:

e Review of Existing SNF Performance Database for interim (50 years) Storage Available:

e 10/96 Materials issues in Interim Storage and Direct Disposal of Aluminum SNF

- Creep Analysis for Materials Test Reactor Fuel Assemblies in Dry Storage Evaluation of Corrosion of Al Reactor Fuel Cladding Materials

- Acceptance Criteria for Interim Dry Storage of Al SNF NRC Response:

e Review and Comment on Technical Approach e Review Fundamental Metallurgical Science i

Disposition of Aluminum SNF Technical Documents for Review (cont'd) l i;

Planning Documents:

e Technical Task Plans on Major Activities i

Available:

l e Direct Disposal Technology / Requirements (11/96) e Characterization Requirements / Techniques Development (1/97) e Development of Test Protocol for Metallic Waste Form (1/97) e Dilution Technology Development (1/97) i NRC Response:

e Review and Comment on Technology Development Plans  !

Disposition of Aluminum SNF Technical Documents for Review (cont'd) . . . ... . . . .

Criticality Documents:

e A document presenting a criticality analysis for high-enriched aluminum-based fuel l

- Describes methodology, assumptions, and results

, - Prepared by RW and expands upon preliminary work conducted by the Research Reactor Task Team t

Available:

e Preliminary 2/97  ;

e Final 6/97 i

i NRC Response:

e Review and comment on technical approach and results e Provide indication of no objections  ;

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i Disposition of Aluminum SNF Technical Documents for Review (cont'd)

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t Status Documents:

e Interim Technology Reports .

! e Waste Technical Feasibility Report Available:

e 4/97  !

i e 10/97 -

l e 6/98 (Feasibility Report)

NRC Response:

e Review and Comment on Technical Content of Interim Reports i

-l e Review and concur with Waste Form Technical Feasibility Report by 12/98 l t

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__ _ . _ _ _ _ _-_ ___ - __ _____ __ _ ___ ____ _ ._ __ _?

9 y Disposition of Aluminum SNF Technical Documents for Review (cont'd) . ...

Supplemental Documents: ,

o Tcpical Reports Available:

e Corrosion of Aluminum SNF in Vapor Environment (4/97) 1 i

e Effect of Temperature on Fission Product Release (10/97) e Al SNF Characterization Database (12/97)

NRC Response:

e Review and Comment on Technical Content

c Disposition of Aluminum SNF Technical Documents for Review (cont'd) -

i 4

Project Documents:

e Facility Functional Requirements Documents Available:

o Preliminary Functional Requirements for Direct Disposal (10/97) e Preliminary Functional Requirements for Dilution Technology (10/97) e Preliminary Characterization Requirements (10/97)

NRC Response:

e Primarily provided for information only e NRC welcome to review and comment on Technical Adequacy

Disposition of Aluminum SNF Key Technical Milestones - Summary maammamawa:n -n ,

e r_

Existing Aluminum SNF Performance Database 10/96 i Complete Task Plans 11/96, 1/97 Preliminary Criticality Analysis and Methodology 2/97 Topical Report - Corrosion of Aluminum SNF in Vapor Environment 4fgy  ;

interim Technology Report i 4fg7 Final Criticality Analysis and Methodology 6/97 Preliminary Functional Requirements 10 37 i Preliminary Characterization Requirements 10/97 i Topical Report - Effects of Temperature on Fission Product Release 10/97  ;

interim Technology Reportil 10/97 Topical Report - Aluminum SNF Characterization Database 12/97 Waste Form Technical Feasibility Report 6/98 NRC Response .

Technical Review and Comment within 60 days of Document Receipt i

- - . ,