ML20195G508
| ML20195G508 | |
| Person / Time | |
|---|---|
| Issue date: | 06/08/1999 |
| From: | James Smith NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Sherr T NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9906160079 | |
| Download: ML20195G508 (13) | |
Text
1 wn k UNITED STATES j
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- NUCLEAR REGULATORY COMMISSION
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June 8, 1999_
MEMORANDUM TO : Theodore S. Sherr, Chief Licensing and International Safeguards Branch, FCSS THROUGH: Charles W. Emelgh, Section Chief 1f.
Licensing Section W Licensing and Intemational Safeguards Branch, FCSS FROM: Jeremy Smith, Project Manager fb G[f/41 l Licensing Team 2 Licensing and international {
Safeguards Branch, FCSS l l
SUBJECT:
MEETING
SUMMARY
FOR DOE / NRC MEETING TO DISCUSS LICENSING A MOX FACILITY l
On May 27,1999, a public meeting was held at Nuclear Regulatory Commission (NRC) )
Headquarters regarding proposed plans by the Department of Energy (DOE) to fabricate and l burn mixed oxide (MOX) fuel utilizing plutonium deemed excess to the U.S. nuclear weapons i program. Information was presented by the DOE-selected consortium consisting of Duke l Power, Cogema Fuels, and Stone & Webster (DCS). Attendees included DCS management, i their primary subcontractors, DOE representatives, members of the public, and representatives from the NRC's Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor i Regulation, Office of Nuclear Regulatory Research, Office of the General Counsel, and Office of Administration. Attachment 1 is a copy of the attendance list for this meeting. The main topics discussed were the DCS strategy for the building and licensing the MOX facility, an overview of the MOX fuel production process, and the estimated schedule for the project.
Attachment 2 contains a copy of the meeting handouts.
DCS plans to utilize proven technology in their design of the MOX fuel fabrication facility as much as possible; such as that demonstrated by facilities overseas that have more than 20 years of experience in handling MOX fuel (i.e., MELOX, A-MIMAS, etc.). The MOX facility will use the lessons learned from other fuel fabricators (e.g., AVLIS, LES, NFS) in their application for a license, if the application is approved, the MOX facility will be licensed under the provisions of 10 CFR 70 by the NRC. /0 The proposed MOX facility will utilize a fabrication process that consists of homogenization of the plutonium, ball milling, sieving, addition of uranium, homogenization of the uranium / plutonium mixture, pelletizing, sintering, grinding, and finally sorting of the finished fuel pellets. After fabrication of the pellets is complete, they will be loaded into rods, bundled into l assemblies, and shipped to the fuel irradiation location.
DCS's MOX fuel fabrication facility project schedule consists of four phases. The first is the base contract which is a three year effort and entails the design of the MOX facility, submission of environmental impact reports and authorization from the NRC to begin construction. The t
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third phase is a one year systems check (approximate completion in 2007) followed by I operation of the facility for an estimated 12 years. The final phase is the deactivation of the plant, which is planned to take place during the early part of the 2020s.
~ Attachments: As stated QJJITRIBUTION:
NRC File Center PUBLiC FCSS R/F NMSS R/F HAstwood ' AElss MLamastra JWilson(NRR) JOlivier JDavis CTripp ' UShoop TMo LSilvious RCaruso Alevin RLee JDunleavy LRoche HScott STurk ' APersinko ERossi JWerniel KWinsburg STreby Hfelsher . TMartin (ADMIN) FEltawila in small Box on "OFC:" line enter: C = Cover E = Cover & Enclosure N = No Copy Path & File Name:
OFC FLlB FLIB f, NAME JSmith dN CEmh i DATE (, / I/99 (9 / f( /99 OFFICIAL RECORD COPY l
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second' phase is'the construction of the MOX facility, which is estimated to take 3-4 years. The -l third phase is a one year systems check (approximate completion in 2007) followed by operation of the facility for an estimated 12 years. . The final phase is the deactivation of the
- pla'nt, which is planned to take place during the early part of the 2020s. j Attachments
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C3 . Meeting Objectives and Agenda
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- - Meeting Objectives 1- Introduce DCS
- Engage NRC in dialog on MOX fabrication facility Agenda
- Opening Remarks'
- Introduction / Points of Contact ,
- Overview of MOX project, fabrication facility '-
- Discussion of DCS Licensing Strategy and information needs Thwuta). May 27. IPM Pagei
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l DUKE COGEMA STONE & WEBSTER integrates the safety of the worker, the public, and the environment into a)Iaspects ofprojectperformance
.from DCS' Guiding Principles
'I 1hwsday, May 27.1999 Page 2 1
Introducing c)
Duke Cogema Stone & Webster, LLC Private-sector consortium contracted by DOE Mission: convert plutoniue. to spent nuclear fuel j
- Design, license, construct, and operate a MOX fuel fabrication facility (MFFF)
- Perform qualification program for MOX fuel lead assemblies j
- Design shipping containers for MOX fuel assemblies
-- Irradiate MOX fuel at commercial reactors lhursday. Mas 2' 19W Page 3 1
D Duke, Cogema, Stone & Webster, LLC !
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C6 DCS Organization / Points of Contact.
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D MOX Project Overview
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' Complements immobilization as part of DOE's surplus plutonium disposition program
. MOX contract divided into four phases
- Base contract: MFFF plant design and license application qualification program identification of utility modifications
- Option one: construction of MFFF l
- Option two: startup and operation of MFFF irradiation of MOX fuel .
- Option three: deactivation
' Thursday. May 2', Jw9 Page 6 h
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C9 MOX Project Schedule Overview MOX Fuel Fabrication Facility Design March 2002 Complete Construction March 2006 Facility Startup April 2006 Commence batch irradiation at mission reactors September 2007 (please note all dates are preliminary planning estimates)
Thurutas. M.n 2".1+P) Page 7 c Brief Overview of MFFF:
9
, , .. .. .. .. .. .. .. .. . A-MIMAS Measuring of Homogenization PuO2 Can aster Ex posing) gg % e Homogenization (_' '%
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u C3 NRCRegulatory Authority Fuel Fabrication Facility 10 CFR Part 70 Fuel Packaging and Transportation 10 CFR Part 71
- Conveyance by DOE SSTs j Fuel Qualification and Irradiation 10 CFR Part 50 ;
- Topical Reports !
- Lead assembly irradiation, batch irradiation at mission reactors (McGuire, Catawba, North Anna) l
' Thursday. May 2'.1999 Page 9
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DCS' Licensing Strategy '
..:::'. ::::?..
Implementation of proven technology adapted to US standards
- MELOX (A-MIMAS fabrication process)
- La Hague (aqueous polishing)
- Systems engineering approach to satisfying NRC requirements Conformance with 10 CFR Part 70
- Follow rulemaking activities, understand effect of evolving NRC requirements
- Participation in development of MOX-specific guidance Corporate and individual experience
- Application oflessons learned from Erwin, AVLIS, LES, FCF Thursday. Mav 27.1999 Page 10 5
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C3 DCS' Licensing Strategy (continued)
Engaging the regulators
- Identifying / tracking key issues and licensing risks
' - Optimal use of existing environmental assessments
- Demonstration of proven technology and' validation of MELOX safety basis
- Frequent interactions Integration of MFFF with other project elements
- Project integration of common issues / concerns
- Integration of NRC safety requirements with DOE host site safety requirements for MFFF 1
1 Thunday MAY 27,1999 Pagg ll
., . c C3 Information Needs from NRC
..:::'.' ::::t..
. Feedback on planning assumptions
- Anticipated NRC review scheduie/ resources for MFFF License Application reviews
- Readiness to support mission 18 months for NRC review and SER
- 12 months for hearings (if required)
- Licensing process
- Sequencmg of submittals, design, and construction
- Afrect of use of existing environmental assessments
- NRC support fees /manhour estimates
-Identification of key issues Protocols for future meetings Thursda), May 27.1999 Page 12 4
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