ML20065M297
| ML20065M297 | |
| Person / Time | |
|---|---|
| Site: | 05200001, 05200002, 05200003, 05200004 |
| Issue date: | 05/31/1994 |
| From: | ENERGY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20065M289 | List: |
| References | |
| PROJECT-672A, PROJECT-674A PROC-940531, NUDOCS 9404250198 | |
| Download: ML20065M297 (37) | |
Text
- _ _. . . . _ ._ ._._____ _ __ _ .-- __.. _ ___._ __ _ __ _ __ _
Advanced Reactor
- Research and
- Development Programs DRAFT May 1994
. U.S. Department of Energy Office of Nuclear Energy 3
DO s bO 01 1
j 4
U.S. DEPARTMENT OF ENERGY !
F OFFICE OF NUCLEAR ENERGY 1 - -
g :
l CIVILIAN REACTOR DEVELOPMENT PROGRAMS 5-YEAR PLAN FOR .
ADVANCED REACTOR-ACTIVITIES UNDER THE ENERGY POLICY ACT OF 1992 '
May 1994 5
DRAFT :
i l
l i
4 1
I 1
TABLE OF CONTENTS !
i l
i 1
- Executive Smnmary Prog ram M ission . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...... 2 Program Objectives ....... ......... ............ ............. ... 2 1
~
Program Milestones . . . . . . . . . . . . . .. .............................. 2 The Advanced Light Wnter Reactor Program Program Mission . . . . . . . . . . ..... . ... ............................ 3 Program Relationships . . . . . . . . . . . . . ........................... .... 3 Planning Assumptions . ......... .......... ............... ....... . 3 Program Plan .............. .. ....... ........ .... ......... 3 Program Scheduto ................. . ................... ......... 5 Resource Requirements . . . . ..... .. ...... .......................... 5 Program Progress . . . . . . . . . . . . . . . . ..... ... . .. ........... 6 Contingencies . . . . . . . . . . . . . . . .. ...... . ... . ... ... . 6 Figure 1 - ALWR Program Milestone Schedule .. . .... ..................... 7 Figure 2 - Annual ALWR Program Projected Costs to Meet Energy Policy Act Milestones ... .. .. . ..... ........ . 8 The Actinide Recycle Program Program Mission . . .................... ........ ...... ........... 9 Termination Justification ......... ......,............................. 9 i Program Relationships and Termination Impacts . . . . . . . ........... . .......... 9 Planning Assumptions . . . . ........ ....... ........................10 Program Plan . . . . . . . . . . . . . . . . . . . ....................... . . . . . . . . 10 Program Schedule ............ .................. ...... .. . . . . . . 12 Resource Requirements . . . . . . . ... ... .... ............. . . . . . . . . . . 12 Contingencies . . . . . .................... .........................12 Figure 3 - Actinide Recycle Program Milestone Schedule ...................... . . 14 Figure 4 - Annual Actinide Recycle Program Projected Costs to Meet Energy Policy Act Milestones . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 i The Gas Turbine-Modular Helium Reactor Program )
Program Mission . . . . . . . . . . . . . .. ........ ..... ......... . . . . . . . . 16 Termination Justification ................ ..... ...... .... . . . . . . . . . . 16 i Program Relationships and Termination Irnpacts . . . ............. ... . . . . . . . . . 17 Planning Assumptions . . . . ........ ............. .. ........ ... . . 17 Program Plan . . . . . . . . . . . . . . . . . .. ... . .... . ................ 17 Program Schedule ............. . ....... ............ . . . . . . . . 18 Resource Requirements ... ............. .. .......................18 ,
., Contingencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . .....................18 Figure 5 - GT-MHR Program Milestone Schedule . . . . . . . . . . . . . ..... .... . . . . 19
-l Figure 6 - Annual GT-MHR Program Projected Costs to meet Energy Policy Act Milestones . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 l 1
4 1
Appendices j Appendix A - Narrative Program Summary Tables .............................21 Appendix B - Program Schedules and 1.ogic ....... .........................25 Appendix C - Resource Requirements ...... ...... .......................30 Appendix D - Acronyms List . . . . . . . . . . . . . . . . . . ...... .................33 ;
i l
1 l
1
'l
U.S. DEPARTMENT OF ENERGY CIVILIAN REACTOR DEVELOPMENT PROGR AMS 5-YEAR PLAN FOR ADVANCED REACTOR ACTIVITIES UNDER THE ENERGY POLICY ACT OF 1992
^
EXECUTIVE
SUMMARY
=
This five-year plan for the Department of behind schulule, any fimding shortfalls, and any Energy's (DOE) Civilian Reactor Development other circumstances that might affect the ability Program is based on both the Department's and of the Secretary to meet the goals set forth in the Office of Nuclear Energy's Strategic Plans, subsection 2122(b). In confoimance with this as well as the requirements of the Energy Policy requirement, this Plan reflects the Act of 1992 (EPACT). The time frame covered Administration's policy to focus on research and by this Phn is FY 1994 through FY 1998. development programs that have near-term commercial applications, such as the Advanced Among its other provisions, EPACT codifies the Light Water Reactor program, and to place
. Nuclear Regulatory Commission's (NRC) Part greater budgetary priority on other energy 52 licensing reform rule, which provides for supply and conservation options, certification of standardized designs, issuance of
.:ombined construction and operating licenses, Consistent with EPACT requirements, the and informal hearings on new nuclear plant ALWR design certification program is designed construction. The Act also authorizes the NRC to achieve NRC pre-certification of four ALWR I
to allow interim operation of completed reactora designs. In addition, for two of these designs, under certain conditions. the First-of-a-Kind Engineering (FOAKE) program will provide cost and schedule certainty In addition, EPACT provides multi-year to the marketplace by ensuring standardization of authorization for DOE's Advanced Light Water plant components r ot covered under the program Reactor (ALWR) design certification and First- to achieva NRC design certification, of-a-Kind engineering programs to support commercialization of ALWR reactor designs Design activities for the Advanced Liquid Metal during the 1990s. The Act also supports Reactor (ALMR) and MHTGR (now known as programs focused on continued research and the Gas Turbine-Modular llelium Reactor or development of the Actinide Recycle system and GT-MHR) are scheduled for termination the Modular liigh-Temperature Gas-cooled beginning in 1995, in conformance with the Reactor (MHTGR). EPACT also requires the Administration's policy to restrict reactor Secretary of Energy to recommend to Congress research to the more near-term advanced light by 1998 one or both of these technologies for water reactor activities, construction of a prototype demonstration reactor. Continued support of the Actinide Recycle program is inconsistent with the Administration's EPACT subsection 2122(c) requires the position concerning the use of plutonium for Secretary of Energy to update the Office of civilian power production in the future.
Nuclear Energy's Five-Year Program Plan Therefore, termination of the Actinide Recycle annually and to submit such updates to program is proposed, starting in FY 1994.
Congress, describing any activities that are 1
h: ,
In compliance with the Energy Policy Act and These objectives are:
the Administration's directives, this Plan details j the current mission, relationships, activities,
- Assisting utilities in maintaining operation milestone schedule, and resource requirements of current nuclear units as long as they for each of DOE's civilian advanced reactor can be operated saf(ly and economically.
research and development programs, as well as
~
- the budgetary appropriations approved by the
- Making available to the marketplace Congress, certified, standardized advanced light
, water reactors that meet customer Program mission requirements and offer significant advances in safety.
DOE's advanced reacter programs are managed
- DOE s c.d. i .ian reactor development programs though its Office of Nuclear Energy (NE). The are nw ing restructund to focus on primary mission of these programs is to meet the Advanced Light Water Reactors that have near-projected future need for new baseload wm c nummia appHeations.
genera:Ing capacity by enabling safe, economical ,
nuclear power technologies as an option for the Nation's electric utilities. In addition to EPACT, this mission is based on the Atemic Energy Act Program Milestones of 1954, the Energy Reorganization Act of 1974 (Public Law 93-438), and the DOE Organization To meet its mission objectives, the Department Act (Public Law 95-91). of Energy has established the following milestones.
Activities in progress to support this primary mission include: (1) encouraging institutional Milestone Date Milestone reform to reduce the initial financial risk of new nuclear plant construction; (2) continuing (September 1997) Complete design of two interaction with the NRC and the public; standardized ALWRs.
(3) assisting in reseaich and development of competitive, innovative reactor designs for (December 1997) Achieve NRC certification eventual commercial deployment; (4) ensuring of four ALWR designs, that all nuclear testing and research facilities overseen by NE are operated in a safe and In accordance with the Energy Policy Act of environmentally sound manner; and (5) 1992, the Department will carry out its civilian emphasizing cost-sharing with industry to spread nuclear programs, within budgetary limits, to development risks and lower costs. foster the continued availability of nuclear power as a clean, safe, and economical alternative option for electricity generation.
Program Objectives .
Office of Nuclear Energy recommends that long-To meet the EPACT requirements and fulfill its term nuclear energy research and development legislative mandate under current and projected needs be examined by an orgamzation such as budgetary constraints, the DOE Office of Nuclear Energy has identified several objectives the National Academy of Science, m
consultation with other outside experts, related to the operation of existing nuclear power plants and the development of new, advanced plants as a viable option for near-term commercial application.
2
l
.7 .
W l
l l
l 1
THE ADVANCED LIGHT WATER REACTOR PROGRAM 4
4 I
, j l
THE ADVANCED LIGHT WATER REACTOR PROGRAM Program Mission expertise is beneficially applied to the development of ALWRs.
~
The mission of the Advanced Light Water .
Reactor (ALWR) program is to make available Interagency coordinat. ion with the Nuclear Regulatory Commission (NRC) is mamtalned m
. to the marketplace certified, standardized ,
ALWRs that meet customer requirements and areas related to the safety and licensmg of current and Advanced Light Water Reactors offer significant advances in safety. Successful completion of this mission would en ble nuclear (ALWRs). H,is coordination is particularly
' important m meetmg program goals such as the power to contribute to projected future electrical generating capacity requirements by 2010. This design certificat,on i of evolutionary and mid-sized ALWR plants.
goal is consistent with the U.S. utility industry and plant vendor goal of obtaining new nuclear .
Remgm. .zmg that effect.iveness m des,ign and powerplant orders later in the 1990s to allow the perational safety a e mmmon global concerns, first new plants to enter service near the turn of ,
cooperat,ve i mternational programs are the century' maintained with a number of organizations in the Far East, Europe, and in countries of the former Soviet Union. Cooperative arrangements have Program Relat.ionslu.ps also been established with several Organization for Economic Cooperation and Development DOE has coordinated its ALWR activities member countries, as well as with the closely with those of the private sector. All of International Atomic Energy Agency.
the ALWR programs are cost-shared with the private sector (e.g., utilities and vendors) to ensure their relevance. In addition, day-to-day Planning Assumptions management responsibilities for several of the programs are placed with the private sector to
- The private sector will continue its ensure a marketplace orientation, mplementation of the Nuclear Power Industry cooperation includes program cost-sharing with U.S. utilities through the Advanced
- Current cost-sharing arrangements will be Reactor Corporation (ARC), the Electric Power maintained with the private sector.
Research Institute (EPRI), and other utility
. groups; and with reactor plant designers (ABB
- NRC will maintain its schedule for Combustion Engineering, General Electric (GE), certifying ALWR designs through 1996 and Westinghouse). The program also maintains and 1997.
coordination with industry associations such as the Institute of Nuclear Power Operations and the Nuclear Energy Institute, to ensure overall Program Plan consistency between government and ,ndustry i
approaches to policy issues.
Light water reactors are utilized throughout the The program utilizes national laboratories, such world to provide safe, dependable electric as those at Oak Ridge, Tennessee, and Sandia, power. The ALWR program builds upon this New Mexico, to ensure that their specialized experience by working to incorporate the lessons learned from over three decades of plant 3
operation into simpler phnt designs. Greater Reactor, have been submitted to the NRC for simplicity of design will make ALWRs easier to certification. In addition to building on the construct and operate and enable a lower core experience of currently operating plants, these damage probability than current plants. designs incorporate significant advances in safety, component and systems performance, and Major ALWR program elements include: instrumentation and controls.
- Demonstration of an improved regulatory The ABWR and System 80+ designs are
. process through certifying standardized, currently under intensive review by the NRC.
evolutionary ALWR designs that meet Agreement has been reached with the NRC on utility requirements. the level of design detail required for cartification, and agreement on technical irsues
- Development and certification of simpler, and acceptance criteria is near. DOE anticipates standardized, mid-sized ALWR plants that the NRC will issue its final design approval with passive / innovative safety features. for the ABWR and System 80+ during 1994.
Certification of the ABWR and System 80+ is
- Encouragement of industry-wide plant expected in 1996.
standardization Passive Plant Develonment and Certification
- Assistance in resolving institutional and d
economic regulatory impediments to The Department of Energy also is collaborating nuclear power. with indastry in a progre:n to design and certify two simplified, mid-sized (600 MWe) ALWRs These activities are scheduled to be completed which employ passive safety systems. These ,
by the late 1990s to allow utilities to consider a plants would require a smaller capital investment new plant order for operation around the turn of and, therefore, involve a reduced financial risk.
the century. They also would be more flexible, allowing the incremental matching of supply with growth in ALWR life-cycle costs are expected to be demand in addition, these mid-sized ALWRs competitive with alternative, base-load offer the prospect for significant simplifications technologies, such a coal and natural gas and innovations in design, construction, and combined-cycle plants. ALWR design operation, all made possible by their reduced standardization is primarily responsible for size, This, in turn, permits .much shorter reducing such costs to below the level of current construction schedules and competitive nuclear powerplants, economics.
Certification of Evolutionary Piar'ts These simplified ALWR designs will primarily employ passive features to ensure essential safety During the certification process, the NRC functions. Use of these passive features will performs a complete safety review of a design result in greatly increased time for operator
- and, when results are acceptable, certifies the response and an improved level of safety design. A utility can then elect to construct this compared to currently operating plants.
certified design with a reduced risk of redesign or retrofit after the start of construction. Applications for certification of these mid-sized designs, the Westinghouse AP600 and the
- Two large (1300 MWe) evolutionary ALWR General Electric Simplified Boiling Water designs, the GE Advanced Boiling Water Reactor (SBWR), were submitted to the NRC in Reactor (ABWR) and the ABB Combustion mid-1992. Certification is scheduled fcr 1997. l l Engineering System 80+ Pressurized Water l
- 1 l
4 l
)
-1,
-l
k '
- 1. .
i Standardization Program Schedule In 1992, DOE initiated a standardization
, The Energy Policy Act of 1992 provides a program in which the utility industry is taking a multi-year authorization for ALWR design strong leadership role. This cooperative, cost-cenification and FOAKE programs to support shared program focuses on completmg First-of-
, commercialization of ALWR designs by the a-Kind Engmeeting (FOAKE) on selected mid-1990s. The following milestones have been ALWR design concepts. These designs will g established to achieve the ALWR program:
, beyond the level of detail required for certification and will be sufficiently detailed t Desien Certification provide the cost and schedule certainty necessary to permit the consideration of new nuclear
- Receive NRC design certification of the powerplant orders by the marketplace later m the
, ABWR and System 80+ designs by 1990s. This level of FOAKE will be performed August 1996' generically and applied to all plants of the same design. The design can then serve as the basis
- Receive NRC design cenincation of the for a series of standardized plants.
AP600 and SBWR designs by December The ARC has selected two designs for this program, the Westinghouse AP-600 (a 600 MWe
' Standardization PWR) and the General Electric ABWR (a 1300
- MWe BWR). Contracts with Westinghouse and
- Develop key equipment and procurement General Electric have been s,igned.
specifications by July 1995.
Total costs for this cost-shared program are
- Complete First of-a-Kind Engineering projected at more than $200 Milh,on. Maximum activities by December 1997.
Federal Government funding for this program is set at $100 Million. Private sector contributions A detailed ALWR program Milestone Schedule melude nearly $50 Milhon from the utility is provided in Figure 1.
mdustry, and more than $100 Milhon from nuclear suppliers. The program will be completed by 1997.
Resource Requ.irements Institutional and Reculatory Activities Annual projected funding (govermnent and DOE sponsors several programs aimed at nongovernment) required for the ALWR improving the institutional and regulatory Program to meet the Energy Policy Act environment to promote the stability necessary milestones is summarized in Figure 2. FY 1993 for a new plant order. An improved institutional DOE program funding for the ALWR program and regulatory climate requires a stable, was $57.8 Million. Additional DOE funding of predictable safety regulatory process in which $186 Million is required through FY 1998 (see final decisions are made with full public Figure 2). After FY 1998, when NRC-certified, participation prior to plant construction, standardized ALWR designs are expected to be Codification of the NRC's rules for future available in the marketplace, further research reactor licensing (10 CFR 52) in the Energy and development is expected to be performed by Policy Act of 1992 was a significant step the private sector, with DOE providing forward in this direction. assistance where needed.
l 5
l l
1
- j Program Progress
]
- All program activities are underway under I
ag:eements with the private sector.
Required private sector cost-sharing has
. been pledged and industry organizations are in place for all programs.
-
- All certification reviews by the NRC are underway, and certifications for all designs are expected by the end of 1997.
- Re standardization program begar. ,
design-specific activities in early 1993. !
Completion of the program is scheduled for 1997.
- Enactment of the licensing reform provisions required by the Energy Policy Act of 1992 is expected to provide the regulatory stability required to enable new plant orders.
In summary, all major ALWR elements are expected to be completed in accordance with the F" ACT directives.
Contingencies ALWR Program cost and schedule estimates assume that no major design changes will be required as a result of NRC design reviews. ;
This assumption is based on NRC/ industry ;
interactions on the ALWR Utility Requirements I Document, which have resolved most of the !
.ALWR technical and safety policy issues. !
Should unforeseen technical policy issues arise
~
during NRC reviews, program costs, and schedule estimates would have to be -l reevaluated. )
1 l
l l
I 1
l \
.~. .. ..
FIGURE 1 ALWR PROGRAM MILESTONE SCHEDULE FY 1993 FY 1994 FY 1995 FY 1996 FY 1997 FY 1998 ABWR System ABWR and Revised 80+ System 80+ A' 600 & SBWR FDA FDA Design Cert. Design Cert.
(6/94) (8/94) (8/96) (12/97)
YY Y Y ALWRs a
Key Complete Initiate Design Standardization Equipment First-of-a-Kind Work Plan Specs Engineering (3/93) (12/93) (7/95) (12/97)
Commercial y y y y Standardization I -l
FIGURE 2 ANNUAL ALWR PROGRAM PROJECTED COSTS TO MEET ENERGY l
POLICY ACT MILESTONES 200 TotalRequirements 150 - -
- ^
Cost Non-Govemment in -
Millions 100 - .
$ '..~ '. ..
~
~.
Govemment 50 - .
^
0 1994 1995 1996 1997 1998 TOTAL Fiscal Year Govemment R&D 57.6 51.0 51.5 15.9 10.0 186.0*
Non-Govemment: SSE 11ZE 515 153 10A 2918 Total Requirements: 156.4 168.6- 103.0 31.8 20.0 479.8
- Figure includes funding for current and advanced reactor safety and licensing support
l 1
1 j' i l
l 1
1 1
-1 l
l 1
I
. )
l I
1 l
l 1
l 1
-l i
l i
I I
l l
THE ACTINIDE RECYCLE PROGRAM i l
l 1
.l l
1 i
l i
i l
1 I
I i
l ,
l
, TIIE ACTINIDE RECYCLE PROGRAM I
l Program Mission plutonium, the Department has recommended j termination of the Actinide Recycle Program.
Continuation of the program is inconsistent with The m. .ission of the Actinide Recycle program the Administration's views concerning the use of has been to conduct the research, development, plutonium for civil power production.
. and testmg activities required to demonstrate by 7 , Furthermore, termination of the program is l 1997 the techm, cal and economic feasibility of an
, consistent with the Administration's policy to mnovative and highly d,i version-resistant nuclear restrict reacter research to the more near-term fuel cycle technology. If successfully developed, advanced light water reactor certification i actinide recycle could sigmficantly contribute t activities, placing greater budgetary priority on radioactive waste management by produemg alternative energy supplies and conservation l electricity from material that would otherwise '
E "8' require disposal in the planned geologic i
repository.
The program has been focused on development Program Relationships of a synergistic system comprised of three and Termination Impacts technology components: (1) an advanced liquid metal reactor, (2) an integral fasi reactor / closed in conducting the Actinide Recycle program, metal fuel cycle processing and fabrication coordination is maintained between contractors, system, and (3) a pyroprocessing system capable national laboratories, associations, universities, of recovering actinide elements from spent Light federal agencies, ,md foreign participants.
Water Reactor (LWR) fuel. In addition to providing electric power, this system has the Actinide recycle technologies were being l potential to extract the most toxic and long-lived developed as an extension of the metal fuel cycle I elements (actinides) from LWR spent fuel and to technology development conducted at Argonne economically recycle this " waste" material as National Laboratory (ANL). ANL had fuel in an integral fast reactor to produce implemented a metal fuel cycle research and electricity. development program that includes demonstration in ANL's Fuel Cycle Facility of l The Administration has made a serious review of pyroprocessing technologies that provide {
the Actinide Recycle technology program, efficient actinide recycling and enhanced I including the Integral Fast Reactor and ALMR proliferation-resistance. 'Ihese actinide recycle programs as part of the FY 1995 budget technologies tdilize pyrochemical processes to discussions. The Department believes that the extract actinides directly from LWR spent fuel program's continuation is inconsistent with the for use as fuel in an integral fast reactor Other Administrations's position concerning the use of national laboratories, including Oak Ridge plutonium for civilian power production in the National Laboratory (ORNL) and Lawrence future, and, therefore, has proposed terminating Livermore National Laboratory (LLNL), as well the program in FY 1995. as an industrial team led by General Electric Company, were also involved in supporting the Termination Justification Independent studies have also been underway, Consistent with Presidential Decision Directive such as the National Academy of Sciences' ,
13 of September 27,1993, which states that the three-year study (initiate 1 in 1991) to evaluate United States does not encourage the civil use of the impacts of waste partitioning and 9
l
(
l I transmutation technologies on radioactive waste
- Congress will provide the FY 1995 management, including a review of the actinide termination funding needed to meet the recycle system. In addition, Japan has been program's close-out obligations. 1 f_ cooperating with the U.S. on metal fuel cycle demonstration, including actinide recycling. In June 1992, DOE and Japan initiated a Program Plan cooperative multi-year program to develop LWR spent fuel pyroprocessing. In October 1992, Program activities will be funded in FY 1994 as DOE and Japan also extended a cooperative 7
authorized and appropriated by Congress.
agreement, signed on July 7,1989, for a joint Efforts will continue through September 30 to pyroprocessing development program that complete ongoing evaluations, studies, and o includes s,gmficant i financial and manpower critical research and development needed to suppen fmm Japan.
support a technical and economic feasibility l . evaluation.
l Concurrent'y, DOE has been participatm.g in actinide :ecycle information exchange programs Activities currently scheduled for FY 1994 l with the Orgamzation for Economic Cooperation l include (1) demonstration of high burnup l l and Development's Nuclear Energy Agency, as potential and fuel performance characterization; well as expsoring possible enhanced bilateral (2) engineering-scale demonstration of cooperation with Agency members Continumg electrorefining prototype equipment at ANL-technical exchanges have been conducted with East; (3) development of a safety data base to the European Fast Reactor group.
support design team interactions with the NRC; Nat.ional laboratory and . dustry in pan. .icipants and (4) EBR-Il core conversion with the uranium-zirconium and uranium-plutonium-affected by termination of the Actinide Recycle zirconium metal fuels.
program include Argonne Nat,onal i Laboratoiles in Illinois and Idaho, EG&G in Idaho, Lawrence Orderly program closcout activities will begin by Livermore National Laboratory and the General October 1, 1994, contingent on receiving Electric Company m Califorma. Oak Ridge Congressional approval by that date.
National Laboratory in Tennessee, and Westinghouse Hanford Company in Washington. Actinide Reevele Development With termination of the Actinide Recycle As of the beginning of 1994, the Actinide program, Japanese contracts with CRIEPI, Recycle program had investigated several MITSUI, and JAPC would be termmated.
process flow sheets that are considered attractive for processing LWR spent fuel. One that uses lithium as tne reducing agent was chosen for the Plann.ing Assumpt, ions 20-kg process development test that began operation in October 1993.
- Termination of the Actinide Recycle program is contingent upon Congressional Actinide Recycle program activities include:
approval.
- Completion of small-scale testing with
- Termination activities must begin by simulated LWR spent fuei; October 1,1994, in order to minimize termination and severance cost liabilities.
- Completion of engineering-scale equipment design; 10
i
- Freparation of a draft waste qualification disposal in a long-term geologic repository.
strategy; and Following completion of these fuel processing activities, the FCF will be placed in an l
- Documentation of the behavior of high- industrially and radiologically safe condition.
actinide fuel irradiation to less than or equal to 5 atom-percent burnup. Analytical Laboratory l Eacihties The Analytical Laboratory contains six small,
[ shielded hot cells that are used to conduct fuels i The Department will work with Congress to and materials examinations. This facility is being
- redirect the valuable intellectual and physical presently modified to conduct the sample s l resources fiom this program to support one or analyses required for processing of EBR-Il l more of the Department's higher priority blanket and driver fuel in the FCF.
programs. The Administration is committed to mitigating any job loss associated with Following completion of activities necessary to termination and to utilizing this highly trained support the EBR II blanket and fuel processing workforce. in the FCF, the Analytical Laboratory will be I
placed in an industrially and radiologically safe Termination plans for IFR/ LWR Actinide condition and transferred to EM.
Recycle facilities include the following:
Transient Reactor Test Facility (TREAT)
Erperimental Breeder Reactor-II (EBR-H)
The TREAT facility is an air-cooled, paise-type The EBR-II is a 62.5 MWt, liquid metal-fueled reactor used to simulate postulated reactor reactor that has been in continuous operation transients and transient undercooling events, since 1964. This reactor has been used to conduct a variety of test programs, including The TREAT facility will be defueled, and the metal and oxide fuel irradiation tests, reactor reactor building will be placed in an industrially l safety tests, materials tests, and instrumentation and radiologically safe shutdown condition for and control tests. transfer to EM in FY 1999.
Starting in FY 1995, EBR-II will be shut down, Hot Fuel Eramination Facility (HFEF) defueled, and placed in an industrially and radiologically safe condition in preparation for The liFEF consists of an air-atmosphere hot cell transfer of the reactor to the Office of and an argon-atmosphere hot cell that provides Environmental Restoration and Waste capabilities for remote assembly, disassembly, Management (EM) in FY 1999. and examination of irradiated subassemblies, materials, and other experiments. The IIFEF Fuel Cycle Facility (FCF) will be placed in an industrially and radiologically safe condition for transfer to EM The FCF is a shielded, hot cell facility that in FY 1999, consists of an air-atmosphere hot cell and an argon-atmosphere hot cell. This facility is Fuel Afanufacturing Facility (FblF) adjacent to EBR-II and is presently in the final stages of preparation for demonstration of metal The FMF consists of materials vaults and fuel fuel processing technology. fabrication equir < +. The facility is used to manufacture driw : ,el, controi rods, blanket, The FCF will be used to process EBR-II blanket and experimental wemblies for EBR-II.
and driver fuel into an acceptable form for 11 .
4 The FMF will be utilized to fabricate stainless IFR Metal Fuel Cvele Development iteel " dummy" subassemblies for insertion into the EBR-Il to replace the blanket and fuel
- Degin process equipment testing in ANL's subassemblies that are removed for processing. Fuel Cycle Facility by April 1994.
Insertion of these dummy elements is required to maintain EUR-Il core integrity during the
- Complete Fuel Cycle Facility blanket and fuel handling and removal construction in FY 1994, operations.
LWR Actinide Reevele Development Following fabrication of the stainless steel
" dummy" subassemblies, the FMF will be
- Complete design and construction of all placed in an inclustrially and radiologically safe components of the 20-kg simulated LWR shutdown condition for transfer to Eh! in spent fuel process demonstration facility.
FY 1999. De prepared to initiate hot-operation by the end of FY 1994.
Actinide Recycle System Reactor Desi2u The IFR/ Actinide Recycle schedule is provided The actinide recycle system reactor design effort in Figure 3.
( was in the final stages of advanced conceptual design. The design had evolved over the five-year design period (FY 1989-93) to a passively Resource Requirements safe, modular, metal-fueled, actinide-consuming reactor system. International cooperation had FY 1994 research and development funding for provided several milhon dollars in design the IFR/ LWR Actinide Recycle Program totals research and development. The reactor system
$30.4 hiillion. Facility costs total $6.7 hiillion.
had been reviewed by the NRC and the Advisory Comm,ttee i on Reactor Safeguards, Termination costs for FY 1994 total $82.2 hiillion, which includes $5.7 hiillion for ALhtR esign actWes.
A favorable " Preapplication Safety Evaluation Report" on the Power Reactor Innovative Small Module (PRISM) design is expected from the During FY 1995, the Department will require
$28.1 hiillion to fund personnel salaries and NRC m FY 1994. FY 1994 program activities severance pay, as well as environmental include final, izing the advanced conceptual design restorathn obligations. An additional $76.6 to enable a sound technical and economic hiillion of termination funds will be required to decision for prototype development and begin shutdown of attendant facilities.
establishing a basis from which a preliminary design phase can be restarted without loss of Figure 4 details the fimding requirements for the mformation. Fore,ign contribution to research Actinide Recycle program close out, and development efforts will continue m Fi, 1994, as will interaction with the Nuclear Regulatory Commission.
Contingencies I,rogram Schedule During the upcoming months, the Depattment will develop a proposal to Congress, after extensive consultation on how the valuable Actinide Recycle program activities will continue intellectual and physical resources from this through FY 1994. The following milestones program can be redirected to support one or have been established for the Actinide Recycle more of the Department's higher priority program.
12 e
l
- programs. The Administration is committed to mitigating any job loss associated with termination, and to utilizing this highly trained workforce.
~
Possible applications include:
Processing spent DOE reactor fuel to put it
, into a form suitable for disposal in the repository.
- Testing the feasibility of denaturing weapons-grade plutonium by mixing it with fission products prior to disposal.
Improving the stability of DOE spent nuclear fuel now in storage.
9 13
FIGURE 3 .
ALMR ACTINIDE RECYCLE PROGRAM MILESTONE SCHEDULE FY 1993 FY 1994 FY 1995 FY 1996 FY 1997 FY 1998 Comp. Comp.
Start NRC Advanced Fuel Test Safety Eval. Concept Program ALMR Design Program - Report Design Termination and Development (8/93) (12/93) (9/94) Completed VV V V (12/94)
- BaseTech Development :
Initiate Fuel trradiation IFR Metal Fuel (2/93) Initiate initiate Program u Cycle _ Recycle Program Termination Development Testing Termination Completed (4/93) (10/94) (9/98)
VV V V LMetal FuelCycle Demonstration; Select Process initiate ;
LWR Actinide Testing 20kg Commence Program l
Recycle Flow Processing Program Termination ;
Development Sheet Test Closecut Completed j
(7/93) (10/93) (10/94) (9/95) i V V V V l l- Simulated Fuel Development l' .- l
FIGURE 4 .
ANNUAL PROJECTED COSTS FOR THE ACTINIDE RECYCLE PROGRAM (including ANL-E and ANL-W Termination Costs) 140 3
Non-Govemment 120 - .
3r -
MLM TotalRequirements 99 _ _ _ Termination Cost , ,
Mi! tons S 60 - *V' *'"'
R&D 40 -
20 - :,u 4
O 1994 1995 1996 1997 1998 TOTAL Government R&D: 30.4 28.1 7.1 0 0 65.6 ANL-W Termination Costs 82.2* 76.6 71.6 69.8 78.8 379.0 Total Govemment 112.6 104.7 78.7 69.8 78.8 444.6 Non-Govemment ELQ Q Q 0 0 9.0 Total Requirements 121.6 104.7** 78.7 69.8 78.8 453.6
- Includes $5.7 million of termination funding to fund ALMR design activities
- *The FY 1995 Congressional Budget does not include funding for alt required termination activities. $104.7 million will be required.
f.
i l
THE GAS TURBINE-MODULAR !
HELIUM REACTOR PROGRAM !
1 1.
l-(
l
)
,f l
1 1
= - . _ _ _ _ _ . _ _ _ - - _ _
i THE GAS TURBINE -
MODULAR HELIUM REACTOR PROGRAM Program Mission have prompted the program to redirect its efforts towards developing a direct-cycle, gas-turbine vari nt f the plant design. While preliminary The mission of the Gas Turbine-Modular Helium studies have shown that the revised GT-MHR Reactor (GT-MHR) program has been to conduct the design, research, technology design promises to improve efficiency and economics, it would also result in a more development, and testing required to establish extensive, costly, and uncertain development the GT-MHR as a cost- and risk-competitive
' program. Commercialization and cost-generat,on i nuclear option for a broad range of owners and operators. This program was a continuation of estimates completed by the program m ,
November 1993 project that government funding both worldwide and domestic efforts to bring the safety advantages and high-temperature f appt xim tely $800 Million would be mquired to emuinue the GT-MHR pmgram capabilities of gas reactors to the commercial ,
through completion of preh,mmary des,gn i m FY nuclear industry.
1999. This level of nuclear energy research and development funding is not avcilable in the near Recent events and studies, however, have tem.
indicated that, in this current budgetary climate, such a program must be given a low funding priority. n,ecordingly, the program is bem, g 1992 MM Mg d Mm M study, " Nuclear Power-Technical and Institutional Options for the Future," concluded that the gas-cooled reactor had a low market potential. This study recommended that, with the Term. mat. ion Justificat. ion exception of fuel particle development, I government funding for the gas-cooled reactor Termination of the GT-MHR Program is program should be discontinued.
consistent with the President's proposal to curtail long-term nuclear reactor research and In view of present budgetary constraints, fuel i development, as well as the Administration's development has been designated as a top I desire to redirect DOE's research and priority, and funding has been allocated development priorities. To date, the government
.f '
accordingly. Recent fuel irradiation tests of both has spent in excess of $900 Million to advance commercial and NPR design fuels have indicated I gas-cooled reactor technology. With the close- that fuel coating integrity was about two orders I out of the New Production Reactor program of magnitude less than needed for design (NPR) in FY 1993, commonality benefits once objectives. Extensive post-irradiation obtained from the NPR Modular High examinations and analyses have indicated that Temperature Gas-Cooled Reactor (MHTGR) additional testing and associated funding will be design no longer exist. The commercial program required. The GT-MHR fuel program, once mu, now bear the entire cost of commercial viewed as confirmatory, must now be considered GT-MHR development, developmental, with attendant schedule and cost uncertainties. ,
Furthermore, program cost estimates have !
indicated that the steam-cycle design is not i economical or cost-effective. These findings 16
Uncertainties related to waste management Program termination will result in termination of concerns, such as disposing and packaging spent program support of nuclear research and GT-MilR fuel, have yet to be addressed and will applications at the Massachusetts Institute of ultimately escalate established cost estimates. Technology (MIT), which has been eugaged in work on the gas turbine concept since 1984.
Consequently, given the current budgetary Smaller efforts at the University of Tennessee climate, the GT-MilR's low market potential, and University of West Virginia will also cease.
estimated high development costs, and the Administration's desire to focus on nuclear With the termination of the GT-MHR program, research and development that has near-term participation in International Atomic Energy commercial applications (such as the ALWR), Agency-sponsored cooperative research l the current GT-MilR program is being programs and working groups will also l terminated, and technical development and terminate. Additionally, a recently extended gas-l deployment should be deferred until a cooled reactor implementing arrangement l commercial need exists. between DOE and the Japanese Atomic Energy Research Institute (JAERI) will no longer receive funding, i
Program Relationships and Termination Impacts Planning Assumptions The GT-MilR program is involved in a Termination of the GT-MlIR program is cooperative efforts with a number of governmental, private sector, and international contingent upon Congressional approval, organizations.
- Termination activities will begin by Private industry contracts for gas-cooled reactor October 1,1994, development, initiated in 1986, have been
- Congress will provide additional FY 1995 l extended through June 1994 in order to evaluate termination funds for the Office of whether to continue with GT-MilR development. The program anticipates that an Nuclear Energy to fund completion of I additional no-cost extension through September close-out obligations.
1994 will provide ample time and funds for an orderly contract and program close-out.
Pro 2 ram Plan
- Industry participants affected by the program's termination will include corporate entities such Program activities will be funded at the FY 1994 as General Atomics and Bechtel National in level approved by Congress. Efforts will California, ABB Combustion Engineering in continue through September 1994 and will Connecticut, and Stone and Webster in concentrate on completing ongoing evaluations, Massachusetts. Gas-Cooled Reactor Associates, studies, and conceptual design. Major activities a California-based, nonprofit association of that will be funded include
utilities and energy users that provides utility / user design requirements and assessments
- Development of an optimized gas turbine and overall program development support will plant layout and power level, also be affected. The program's lead technology contractor, Oak Ridge National Laboratory
- Evaluation of special development and (ORNL), is located in Tennessee. technology needs, including heat exchangers, rotating machinery, and the code-acceptability of proposed materials.
17
. l Evaluation of fuel failure mechanisms and Contingencies preparation of a fuel development strategy.
The GT-MHR program could continue with Support to the NRC in providing required Administration and Congressional support.
l information for completion of the draft hiinimal funding at level 3 similar to that
) '
Preapplication Safety Evaluation Report appropriated in past years, however, would not l (PSER) for the h1HTGR scheduled for be sufficient. $800 Million will be required to September 1994.
continue the program through detailed design in FY 1999.
Orderly program closemut activities will begin on October 1,1994, contingent on receiving Industry and international organization Congressional approval by that date.
i contributions could offset some projected costs.
Significant cost-sharing through detailed design, however, is unlikely.
Program Schedule Program activities will continue at a reduced level through September 30, 1994. Contract close-out will begin on October 1,1994, and will culminate with program termination. Close-out requirements, including document and technology archiving, will be completed in 1995.
Hot cell cleanup at ORNL and fuel line and hot cell cleanup at General Atomics will continue into mid-FY 1995.
The GT-MHR program close-out schedule is provided in Figure 5.
Resource Requirements FY 1994 funding for the GT-MHR program includes a combination of advanced reactor research and development and termination appropriations totalling $13.5 Million.
To complete termination obligations, an additional $10.5 Million will be required in FY 1995. This will require appropriation of additional FY 1995 termination funds.
Figure 6 and Appendix C detail the funding requirements for an orderly GT-MHR program close-out commencing on October 1,1994 18
FIGURE 5 GT-MHR TERMINATION SCHEDULE l FY 1993 FY 1994 FY 1995 FY 1996 FY 1997 FY 1998 Termination Con e nce Schedule Program Closecut Extend Contracts Begin (10/94) Through December Reduced (12/94) l
- E Complete Hot Cell I
and Facilities I Y YYY Cleanup I E I gg (3/95)
Program Contracts Termination Expire (9/94) (12/94)
FIGURE 6 GT-MHR PROJECTED COSTS 14
/, ,' TotalRequirements 12 - ::'::':s.'s. .- - -- - -- - - - - -
././.!.! .. ..
.! ./././.!.!./ ..
ll#f,!,'fl,.',!,.#,. ,.
10 - .!.!!!!.!!!! ///. '/ '///.'/. . --- - - --
- ///////////
Cost '/:// -:/:/:/:s:/:s:/:/:/:/.,
/ Termination
/ / , , / / , / , , ,-
g9_ .B- ;,,,,',-
/,, ,. ,,, ./., ,,. -7,. ,,.- , . , -
Millions ~, ' /. jjjj,
/ / / / /. /j, /. j/jjj, ///
g _$~ 6- -:s:/:s:/:/:/:/:/:/:/:/./:
//;ii///////
Govemment R&D
! .!/.! .s.!.s.! !
4- .!.!/.! .!/.! ! ...!.
.s.!.!.! ! . .!//.!
!!! //:.!//.!.
2- :::::::
. / ././.i.. ././././.. .
.s.! ,.i.e.!.!.!.!.!
0 1994 :1995 1996 1997 1998 TOTAL Govemment R&D: . 9.0 0 .0 0 0 9.0 I Termination: 15 10.5- .O Q 0 .15.0 l
Total Requirements: 13.5* - 10.5*
- O .0- 0 24.0 l 1
i l
- Figure reflects reductions for SBIR, M&O pay freeze, and FY 1994 general reduction. -l l
- The FY 1995 Congressional Budget does not include funding for termination activities. $10.5 million is required.
d
_ - _ _ _ - _ . _ = _ -_ . -. . - - _ _ _ _ _ _ _ _ m
k D
e l
l l
l i
APPENDICES
)
APPENDIX A NARRATIVE PROGRAM
SUMMARY
TABLES TIIE ALWR PROGRAM
[ALWR Design Certification]
ACTIVITY DESCRIPTION OBJECTIVES OUTPUT / BENEFITS PROGRAM PROGRESS Demonstrate the 10 DOE is co-sponsoring To obtain certification for the Make two plants with NRC Final Design Approval CFR Part 52 design certification of two evolutionary designs. improved safety available of the ABWR is expected in regulatory process by two evolutionary 1300 as options for orders and 1994.
certifying standardized MWe plards, the GE demonstrate the process to evolutionary ALWR ABWR and the certify plant designs. NRC Final Design Approval designs with greater Combustion Engineering of the System 80+ is safety features. System 80+. expected in 1994.
An NRC decision on ABWR certification is expected in 1996.
An NRC decision on System 80+ certification is expected in 1996.
Develop and certify Development of two To obtain final design approval Make two plants with Submission of Standard Safety simpler, standardized, advanced mid-sized and NRC certification. improved safety and lower Analysis Reports to the NRC mid-sized ALWR designs with passive power levels available as in 1992.
plants with greater safety systems is To develop plant designs that options for orders.
safety features. underway to enable meet NRC requirements for NRC decisions on passive certification by 1997. ITAAC. Demonstrate the plant certifications are certification process for expected in 1997.
To develop plant designs that plants with passive safety meet the passive ALWR Utility features.
Requirements Document.
u
TIIE ALWR PROGRAM
[ALWR Design Certification (continued)]
ACTIVITY DESCRIPTION OBJECTIVES OUTPUT / BENEFITS PROGRAM PROGRESS Encourage industry- DOE has initiated a To complete design of selected Enable vendors to market A cooperative agreement with wide plant First-of-A-Kind ALWRs, except for site-specific standardized plants on a the U.S. utility industry has standardization. engineering program and and procurement-specific firm-price basis, using been negotiated.
is working to provide a features. well-justified construction basis for plant schedules, reducing risk, Program designs were selected standardization. and providing greater by utilities in 1993.
financial certainty.
Detailed designs, plant cost estimates, and construction schedules will be completed in 1997.
U 1
THE IFR/ LWR ACTINIDE RECYCLE PROGRAM
[IFR/ Actinide Recycle Termination]
ACTIVITY DESCRIPTION OBJECTIVES OUTPUT / BENEFITS PROGRAM PROGRESS Termination Consistent with the Commence an orderly close+ut Program closemut Termination efforts are President's policy to ofIFR/ LWR Actinide Recycle documentation; organized co: tingent upon Congressional focus on nuclear energy activities on October 1,1994, archived documents; cost approval.
research and with the objective of saving measure. Consistent development that has terminating the program by with the Administration's l near term applications, September 30, 1995. position concerning the use and the Administration's of existing plutonium for desire to redirect DOE civilian power production in research and the future.
development priorities, terminate the IFR/ LWR Actinide Recycle program.
U
TIIE GT-MIIR PROGRAM
[GT-MIIR Termination Costs]
ACTIVITY DESCRIPTION OBJECTIVES OUTPUT / BENEFITS PROGRAM PROGRESS Termination Consistent with the Commence an orderly c: - ,>ut Program close-out Termination efforts are President's policy to of GT-MHR activities by documentation; organized contingent upon Congressional focus on nuclear energy October 1,1994 with the archived documents; cost approval.
research and objective of terminating during saving measure.
development that has FY 1995.
near term applications, and the Administration's desire to redirect DOE research and development priorities, terminate the GT-MHR program.
APPENT)IX B PROGRAM SCHEDULES AND LOGIC l
ALWR PROGRAM
[ALWR Design Certification]
MILESTONE DATE DESCRIPTION ACIIVITIES Submit final General Electric I/94 Develop technical, design and licensing documents to
- Develop Inspections, Tests Analyses, and Advanced Boiling Water Reactor support submittal of final SSAR Amendment for Acceptance Criteria for all plant systems SSAR Amendment ultimate Final Design Approval
- Develop description of Tier I design to be certified
- Resolve open items from NRC reviews
- Revise Safety Analysis Report to reflect the above Submit final Combustion 2/94 Develop technical, design and licensing documents to
- Develop Inspections, Tests, Analyses, and d Engineering System 80+ Standard support submittal of final SSAR Amendment for Acceptance Criteria for all plant systems Safety Analysis Report (SSAR) ultimate Final Design Approval
- Develop description of Tier I design to be Amendment certified
- Re.olve open items from NRC reviews
- Revise Safety Analysis Report to reflect the above Receive Nuclear Regulatory 5/96 Finalize certified design and licensing documents.
- Complete analyses and calculations Commission Design Certification Obtain Final Design Approval. Obtain Nuclear
- Complete system design description I
for the Advanced Boiling Water Regulatory Commission certification for the Advanced
- Complete test demonstration (i.e.,
Reactor Concept Boiling Water Reactor passive systems)
- Complete Probability Risk Assessment / Reliability, Accessibility, Maintainability, and Inspectability
- Complete cost estimate for new construction
- Obtain Final Design Approval
- Submit Final Safety Analysis Report
ALWR PROGRAM
[ALWR Design Cettification (continued)]
MILESTONE DATE DESCRIPTION ACTIVITIES Receive Nuclear Regulatory 8/96 Finalize certi'ied design and licensing documents.
- Complete analyses and calculations Commission Design Certification Obtain Final Design Approval. Obtain Nuclear
- Complete system design description for the Combustion Engineering Regulatory Commission certification for the System
- Complete test demor.stration (i.e.,
System 80+ Concept 80 + passive systems)
- Complete Probability Risk Assessment / Reliability, Accessibility, Maintainability, and Inspectability
- Complete cost e<timate for new construction
- Obtain Final Design Approval
- Submit Final Safety Analysis Report Receive Nuclear Regulatory 12/97 Develop and finalize technical, design and licensing
- Develop Inspections, Tests, Analyses, and Commission Design Certification documents to support submittal of advanced passive Acceptance Criteria for all plant systems o for the Westinghouse AP600 and plant designs
- Develop description of Tier I design to be the General Electric Simplified certified Boiling Water Reactor
- Resolve open items from NRC reviews
- Revise Safety Analysis Report to reflect the above
- Complete analyses and calculations
- Complete system design description l
- Complete test demonstration (i.e.,
passive systems)
- Complete Probability Risk Assessment / Reliability, Accessibility, Maintainability, and Inspectability
- Complete cost estimate for new construction
- Obtain Final Design AP r-oval
- Submit Final Safety Analysis R.eport 1
s , .
~
ALWR PROGRAM
[ALWR Standardization]
MILESTONE DATE DESCRIPTION ACTIVITIES Initiate Specific Design Work for 3/93 Complete negotiation and award of the program
- Select major contractors Standardization contracts
- Develop statement of work
- Define test program milestones Standardization Plan for First-Of- 12/93 Define and develop scoping for the design basis, testing
- Perform retrospective review of previous
( A-Kind Engineering programs and interface requirements to support the plant performance Wes'.inghouse AP-600 approach to standardization
- Determine engineering approaches to GE ABWR simplify design, maintenance, and operational requirements
- Target key plant features requiring further analysis, test, or demonstration
- Deve!op milestones to implement standardization plan g Develop Key 7/95 Perform engineering analyses and calculations and
- Develop functional structural and physical 4 Equipment / Procurement develop drawings to ensure long lead time and critical design details for critical systems, Specifications equipment availability structures or components
- Examine manufac uring, both domestic and foreign, to ensure infrastructure exists to support design approach
- Perform cost and schedule analysis Design for First-Of-A-Kind 12/97 Additional development of the technical and design
- Preliminary Nuclear Steam Supply System Engineering dooments and drawings for two ALWR concepts component design
- Complete turbine-generator design
- Initial system schematic / logic drawings
- Initial major component procurement and other mechanical specifications
- Complete containment vessel design
- Mechanical Modularization Plan
- Electrical and instrumentation / control modularization plan
- Complete balance of turbine-generator system design
i
~
ACTINIDE RECYCLE PROGRAM
[IFR Metal Fuel Cycle Development] l MILESTONE DATE DESCRIPTION ACTIVITIES Program Termination 9/98 Complete program termination efforts, including
- Terminate contracts / subcontracts shutdown of facilities, by September 30, 1998.
[ LWR Actinide Recycle Development]
MILESTONE DATE DESCRIPTION ACTIVITIES Initiate 20-kg. process 10/93 This test will utilize simulated LWR spent fuel and is Provide Data on:
u development test. considered a key component in providing thermochemical data for the technical feasibility
- Reduction evaluation milestone.
- Waste streams
- Uranium Recovery
- Product Purity Program Termination 9/98 Complete program termination efforts by September 30,
- Terminate contracts / subcontracts ,
1998.
GT-MHR PROGRAM i
MILESTONE DATE DESCRifrTION ACTIVITIES Extend current contracts through 4/94 Extend contracts from June 1994 to December 1994 to
- DOE OAK initiate no-cost contract 12/94. allow for conduct of orderly close-out activities. extensions.
Commence program close-out 10/94 Commence program close-out activities on October 1,
- Publish reports.
1994, pending Congressional approval.
- Archive information.
- Cleanup hot cells.
- Shut down laboratory facilities.
- Cleanup fuel lines.
- Dispose of fuel and equipment.
Complete program termination. 12/94 Complete program termination efforts on December,
- Terminate contracts.
1994.
- Continue hot cell and fuel line clean up activities.
Complete hot cell and fuel line 3/95 Complete hot cell cleanup and fuel line cleanup
- Dispose of fuel.
cleanup activities. responsibilities at ORNL and General Atomics.
- Dispose of equipment.
w
- Decommission and decontaminate facilities.
l
[,
~_ -
~ -
. a APPENDIX C RESOURCE REQUIREMENTS ALWR PROGRAM COST ACTIVITY FY 94 FY 95 FY 96 FY 97 FY 98 TOTAL DESIGN CERTIFICATION COSTS Evolutionary Plants 8.7 5.5 1.5 0.0 0.0 15.7 Passive Plants 11.8 6.3 0.0 0.0 0.0 18.1 TOTAL (CERTIFICATION) 20.5- 11.8 1.5 0.0 0.0 33.8 FIRST-OF-A-KIND ENGINEERING (FOAKE) COSTS Total First-of-a-Kind Engineering Costs 31.7 34.2 25.0 3.9 0.0 94.8 Minimize Premature Plant Retirements 0.0 0.0 20.0 7.0 5.0 32.0 Other Project Costs- 5.4 5.0 5.0 5.0 5.0 25.4 i
TOTAL PROJECT COSTS 57.6 51.0 51.5 15.9 10.0 186.0
- O ACTINIDE RECYCLE PROGRAM COST ACTIVITY FY 1994 FY 1995 FY 1996 FY 1997 FY 1998 TOTAL Actinide Recycle Research and Development 30.4 28.1 7.1 0.0 0.0 65.6 Termination / Operation Costs 82.2 76.6 71.6 69.8 78.8 379.0 l TOTAL PROJECT COSTS 112.6 104.7 78.7 69.8 78.8 444.6 GT-MIIR PROGRAM COST ACTIVITY FY 94 FY 95 FY 96 FY 97 FY 98 - TOTAL M R&D COSTS Design costs 5.4 3.1 (October 1993 - April 1994)
)
Fuel / Technology Development costs 7.6 4.6 (October 1993 - April 1994)
Licensing costs - .5 .1 (October 1993 - April 1994) l TOTAL (R&D) 13.5* 7.8
- Reflects reductions for Small Business Innovative Research, Management and Operating pay freeze, and Fiscal Year 1994 general reduction.
GT-MIIR PROGRAM (continued) ,
COST ACTIVITY FY 94 FY 95 FY 96 FY 97 FY 98 TOTAL TERMINATION COSTS Disposition of excess equipment 1.2 Cleanup of GA fuel line/ facilities 4.5 Disposal of irradiated fuel and hot cell 3.0 cleanup at ORNL COMEDIE material disposal (Note 1) 0.5 ORNL subcontract closcout (COMEDIE) 0.5 ORNL subcontract closcout (KFA) 0.2 ORNL subcontract closcout (MIT) 0.1 ORNL irradiated graphite disposal 0.1 ORNL laboratory shutdown (Note 2) 0.2 Report publication 0.2 TOTAL (TERMINATION) 10.5*
Note 1: Materials fmm COMEDIE BD-1 experiment will be returned to the U.S. fmm CENG in France for packaging and disposai.
Note 2: Creep laboratories in Buildings 201I and 4500s, Materials Aging laboratory in Building 4500S
- The FY 1995 Congressional Budget does not include funding for termination activities. $10.5 Mihn is required.
APPENDIX D ACRONYMS LIST ABWR Advanced Boiling Water Reactor ADM Action Description Memorandum
, ALMR Advanced Liquid Metal Reactor l ALWR Advanced L ight Water Reactor l ANL Argonne National Laboratory l APWR Advanced Pressurized Water Reactor ARC Advanced Reactor Corporation CE ABB Combustion Engineering CENG Centre d' Etudes Nucleaire de Grenoble CDD Certified Design Description CY Calendar Year DEIS Draft Environmental Impact Statement DOE Department of Energy EBR-Il Experimental Breeder Reactor-Il EIS Environmental Impact Statement EPRI Electric Power Research Institute ER Environmental Report FCF Fuel Cycle Facility FDA Final Design Approval FOAKE First+f-a Kind Engineering FSAR Final Safety Analysis Report FY Fiscal Year GCRA Gas-Cooled Reacmr Associates GE General Electric Corporation llTGR liigh-Temperature Gas-Cooled Reactor IAEA International Atomic Energy Ag...cy IFR Integral Fast Reactor ITAAC Inspections, Tests Analyses, and Acceptance Criteria Kg Kilogram LWR Light Water Reactor MilTGR Modular Iligh-Temperature Gas-Cooled Reactor MIT Massachusetts Institute of Technology M&O Management and Operating MWe Megawatts Electric NE Office of Nuclear Energy NEPA National Environmental Policy Act NES National Energy Strategy NOI Notice of Intent NPR New Production Reactor l
NRC Nuclear Regulatory Commission i
OAK Oakland Operations Office ORNL Oak Ridge National Laboratory PDA Preliminary Design Approval 33
ACRONYMS LIST (continued) a y
PElS Programmatic Environmental Impact Statement PIE Post Irradiation Examination PSAR Preliminary Safety Analysis Report PSER Preapplication Safety Evaluation Report l PSID Preliminary Safety Identification Document l , QA Quality Assurance l R&D Research and Development i RCCS Reactor Cavity Cooling System RFP Request for Proposals l SAR Safety Analysis Report SBIR Small Business Innovative Research SBWR Simplified Boiling Water Reactor SER Safety Evaluation Report '
SSAR Standard Safety Analysis Report '
TDP Technology Development Plan TREAT Transient Reactor Test (Facility)
.r 4
4 l
34
- .__ ___. _ _ _ _ _ _ _ _ _ _ _