Aging System Design Development Strategy Rev 00, ICN 00

170-PLN-HA00-00100-000-000

February 2005 


1. Introduction and Background 
This plan provides an overview, work to date, and the path forward for the design development 
strategy of the Aging cask for aging commercial spent nuclear fuel (CSNF) at the Yucca 
Mountain Project (YMP) repository site. Waste for subsurface emplacement at the repository 
includes U.S. Department of Energy (DOE) high-level radioactive waste (HLW), DOE SNF, 
commercial fuel in dual-purpose canisters (DPCs), uncanistered bare fuel, naval fuel, and other 
waste types. The following table lists the types of radioactive materials that may be aged at 
YMP, and those materials that will not be placed in an aging cask or module. 
Table 1-1 Aging System Waste Types 
Radioactive Waste Type Candidate for Aging in a Loaded Directly into Waste Packages 
Site-Specific Cask or and Emplaced Underground 
Module 
Horizontal DPCs with CSNF Yes 
Vertical DPCs with CSNF I Yes 
Uncanistered (bare) CSNF I Yes Yes (if heat output is within established 
limits) 
Naval SNF 1 No Yes 
Multi-Canister Overpacks (MCO) No Yes 
DOE High-Level Waste No Yes 
DOE Spent Nuclear Fuel 1 No Yes 
'DPCs are not currently certified for emplacement underground. They must be cut open and the SNF assemblies 
transferred to a waste package prior to subsurface emplacement. 
This plan presents the strategy for design development of the Aging system. The Aging system 
will not handle naval fuel, DOE HLW, MCOs, or DOE SNF since those materials will be 
delivered to the repository in a state and sequence that allows them to be placed into waste 
packages for emplacement. Some CSNF from nuclear reactors, especially CSNF that is 
thermally too hot for emplacement underground, will need to be aged at the repository. 
2. Overview of Process 
The Aging system design development strategy will include design, fabrication, and placement 
into service of vertical aging casks and horizontal aging modules (HAM)s. The vertical casks, 
HAMS, and their transportation equipment will be similar to existing systems that are currently 
licensed under 10 CFR 72, Licensing Requirements for the Independent Storage of Spent Nuclear 
Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste (10 CFR 
72 [DIRS 1272671) and in service at nuclear power plants around the nation. As with the 
existing storage systems, the Aging cask at YMP will be designed and fabricated by companies 
that have experience with dry storage of CSNF. 
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 Aging System Design Development Strategy 
designs. Differences between 10 CFR 63 and 10 CFR 72 will be noted and addressed as the 
evaluation of existing cask designs is moved forward. 
2.3 Final Design 
Final design of the Aging system components (aging casks, transfer equipment, foundations, 
alara concerns, etc.) is expected to commence during the licensing phase of YMP. After 
submittal of the SAR, the NRC is expected to take up to three years to review the documentation 
(see Section 8). The current YMP SAR information for the Aging system is based on a 
conceptual design. As the SAR is reviewed and preliminary design details are finalized, the final 
configuration of the Aging systim can be further developed. The final design will incorporate 
changes that result from the NRC's review of the SAR. 
2.4 Fabrication and Implementation 
In the future, when licensing activities are completed, the Aging system components will be 
acquired. The vertical site-specific casks and HAMS, along with the transfer trailers and cask 
transporters, will be procured by DOE. The strategy will be to use, to the extent practicable, 
existing vendors and fabricators who are currently providing dry cask storage services to the 
nuclear power industry. Due to the variety of CSNF types that may be received at the repository, 
Aging system cask fabrication, delivery, and implementation will need to be coordinated with 
the waste stream being delivered to the repository. Matching the procurement of aging casks 
with the transportation schedule and delivery of CSNF from around the nation will require 
considerable lead time to assure that necessary Aging systems are available as needed. The 
strategy for implementation will require considerable flexibility for handling an incoming waste 
stream that contains a variety of materials with differing aging requirements. 
3. Summary of Completed Activities 
Design development of Aging structures, systems, and components (SSC)s is currently in the 
conceptual stage. Initial work to support the submittal of the SAR for geologic disposal of 
CSNF at YMP included compiling requirements and producing a conceptual design. The SNF 
Aging System Description Document (BSC 2004 [DIRS 1711611) contains the current set of 
design requirements and a conceptual design of the system. The conceptual design of the Aging 
system is nearing completion and will be followed by a preliminary design phase. 
3.1 Conceptual Design Development 
The project has completed a number of conceptual studies, calculations, and drawings that 
provide details of the Aging system that must be further developed. The current strategy for 
fiscal year 2005 is to advance the current conceptual design and further refine the Yucca 
Mountain Repository License Application Safety Analysis Report (DOE 2005 [DIRS 1707651). 
Table 3-1 summarizes the work accomplished by listing currently controlled Aging system 
calculations. The Aging strategy includes building upon and refining the work accomplished to 
date. The summary of calculations does not include thermal management reports or 
transportation analyses since those issues are handled by other departments. However, the Aging 
system design does consider those issues and the present design is flexible. The aging 
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 Aging System Design Development Strategy 
conceptual design and strategy have been integrated with repository thermal management and 
-
transportation strategies to the extent practicable at this time. 
Table 3-1 Summary of Controlled Aging System Calculations 
1 Document Title I Document Identifier I Effective Date 
I Aging Facility Criticality Safety Calculations I 170-00C-HA00-00100-000-008 I September 10,2004 
Design of a Concrete Slab for Storage of SNF 170-00C-HAPO-00100-000-00B Pending 
and HLW casks (February 2005)
I 
Shielding Evaluations for Spent Nuclear Fuel 170-00C-HAPO-00200-000-00A May lo* 2004
I 
Aging Areas 
Dose Rate Evaluations for Spent Nuclear Fuel 170-00C-HAPO-00400-000-00A December 16,2004
I 
Aging Areas 
Midway Valley Aging Site Layout Drawing 170-COC-C000-00100-000-OOA March 26*2004
I I 
Support Calculation 
Project drawings of the Aging system have also been prepared to support the YMP SAR. 
Drawings include block flow diagrams, mechanical equipment envelopes, mechanical flow 
diagrams, site layout plans, and instrumentation diagrams that are available to support forward 
moving design development. These drawings are part of the conceptual design. Table 3-2 
summarizes currently controlled Aging system drawings. These drawings represent the work 
completed through the first quarter of fiscal year 2005. 
Table 3-2 Summary of Controlled ~ging 
System Drawings 
rAging System Drawing Title I Document ldentifier I Approval Date 1 
Geologic Repository Operations Area Aging 
Site Plan 
170-COO-MGRO-00101-000-00A I March 26*2004 I 
Spent Nuclear Fuel Aging Area 1000MTHM 170-DBO-HAPO-00101-000-00A 
Aging Module Concrete Plan and Sections 
SNF Aging System Instrument Systems I Functional Block Diagram 
SNF Aging System Block Flow Diagram I Level 2 
SNF Aging System Block Flow Diagram 1 Level 3 (Sheet 1 of 2) 
SNF Aging System Block Flow Diagram I Level 3 (Sheet 2) 
SNF Aging System Mechanical Flow Diagram 
(Sheet 1 of 3) 
SNF Aging System Mechanical Flow Diagram 
(Sheet 2) 
SNF Aging System Mechanical Flow Diagram 
(Sheet 3) 
SNF Aging System Mobile Crane Mechanical 
Equipment Envelope 
170-JOO-HAOO-00101-000-OOA 
170-MHO-HAOO-00101-000-OOA 
170-MHO-HAOO-00201-000-00A 
170-MHO-HAOO-00202-000-OOA 
170-MHO-HA00-00301-000-00A 
170-MHO-HA00-00302-000-00A 
170-MHO-HA00-00303-000-00A 
170-MJO-HAPO-00101-000-00A 
I April 26,2004 I April 23.2004 I April 23.2004 I April 22,2004 I April 22,2004 I April 22.2004 I April 22.2004 I April 22.2004 
I 
I 
I 
I 
I 
I 
I 
I 
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 Aging System Design Development Strategy 
Aging System Drawing Title Document Identifier Approval Date 
SNF Aging System NUHOMS MP187 170-MQO-HATO-00101-000-00A April 21,2004 
Transport Cask Cart Mechanical Equipment 
Envelope 
-
SNF Aging System NUHOMS MP197 170-MQO-HATO-00201-000-00A April 21,2004 
Transport Cask Cart Mechanical Equipment 
Envelope 
SNF Aging System MSC Transporter 
SNF Aging System Cask Tractor Mechanical 
Equipment Envelope I 170-MQO-HATO-00401-000-00A 
170-MQO-HATO-00301-000-00A 
I April 21.2004 
April 22, 2004 
Mechanical Equipment Envelope 
SNF Aging System HMSC Cart Mechanical 
Equipment Envelope 
SNF Aging System Mobile Platform 
I 
I 170-MQO-HATO-00501-000-OOA 
170-MXO-HAPO-00101-000-OOA 
I 
I April21,2004 
April 21,2004 
Mechanical Equipment Envelope 
3.2 Nuclear Safety Design Bases 
The YMP has established a set of requirements to assure preclosure nuclear safety of the Aging 
system. As the Aging system design moves forward, satisfaction of the nuclear safety design 
bases will provide reasonable assurance that the performance objective of 10 CFR 63 (10 CFR 
63 [DIRS 1566051) will be met. The design development strategy will progress with the specific 
intention to assure that the design bases from Nuclear Safety Design Bases for License 
Application (BSC 2005 [DIRS 1715121, Table A-11) are satisfied. The proposed design bases for 
Aging system SSCs are summarized in Tables 3-3 through 3-9. 
Table 3-3 Cask Tractor, HAM System -Nuclear Safety Design Bases 
Aging Subsystem Nuclear Safety Design Basis 
Cask Tractor -HAM The cask tractor shall be designed to limit collision impact loads to values that assure waste 
Subsystem container integrity. 
The cask tractor brake system shall be designed to prevent a cask tractor runaway event. 
The design of the horizontal cask transfer trailerltractor shall limit the size, mass, maximum 
speed, and motive force to limit potential damage caused by collisions. 
Fires and explosions shall be precluded from initiating a cask tractor event sequence. 
Loss of power events shall be precluded from initiating a cask tractor event sequence. 
Tip-over during transfer shall be precluded by ensuring that minimum tip-over 
resistancelstandards are maintained consistent with roadway design. 
The design of the horizontal cask transfer trailer tractor shall provide reliable means to stop 
and maintain stability. 
The cask tractor shall be designed for loading conditions associated with a Design Basis 
Ground Motion-2 level seismic event and demonstrate sufficient margin to a "no runaway" 
safety function for loading conditions associated with a Beyond Design Basis Ground Motion- 
level seismic event. 
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 Aging System Design Development Strategy 
Table 3-4 Transfer Trailer, HAM System -Nuclear Safety Design Bases 
Nuclear Safety Design Basis 
The design of the hydraulic ram shall ensure that it cannot fail or be operated in a manner 
that can cause DPC loss of function through excess force or ram over-travel. 
The horizontal cask transfer trailer shall be designed for loading conditions associated with a 
Design Basis Ground Motion-2 level seismic event and demonstrate sufficient margin to "no 
slapdown" and "no runaway" safety functions for loading conditions associated with a Beyond 
Desian Basis Ground Motion-level seismic event. 
The design of the horizontal cask transfer trailer shall limit the maximum potential drop 
height. 
The design of the horizontal cask transfer trailerltractor shall limit the size, mass, maximum 
speed, and motive force to limit potential damage caused by collisions. 
The design of the horizontal cask transfer trailer shall preclude tip-over during transfer by 
ensuring that the transfer equipment design precludes failure modes that could result in tip- 
over under design basis load handling conditions. 
The design of the horizontal cask transfer trailer shall preclude tip-over during transfer by 
ensuring minimum tip-over resistancelstability standards are maintained consistent with 
roadway design. 
Fires and explosions shall be precluded from initiating a HAM transfer trailer event sequence. 
Table 3-5 Site-Specific Cask Transporter -Nuclear Safety Design Bases 
Aging Subsystem 
Site-Specific Cask The site-specificcask transporter shall be designed forloading conditions associated with a 
Transporter Design Basis Ground Motion2 level seismic event and demonstrate sufficient margin to "no 
slapdown" and "no runaway" safety functions for loading conditions associated with a 
Design Basis Ground Motion-level seismic event. 
A speed limit for the site-specific cask transporter shall be established such that a collision 
with shield or airlock doors or other heavy objects does not overturn the site-specific cask 
transporter or cause it to drop its load. 
he cask transporter shall prevent lifting the aging and transfer casks above their maximum I
handling height. 
The design of the site-specific cask transporter shall limit the maximum potential drop height. I 
The design of the site-specific cask transporter shall limit the size, mass, maximum speed, 
and motive force to limit ~otential damaae caused bv collisions. 
The design of the site-specific cask transporter shall preclude tip-over during transfer by 
ensuring that the transfer equipment design precludes failure modes that could result in tip- 
over under design basis load handling conditions. 
The design of the site-specific cask transporter shall preclude tip-over during transfer by 
ensuring minimum tip-over resistancelstability standards are maintained consistent with 
roadway design. 
The design of the site-specific cask transporter shall provide reliable means to stop and 
maintain stability. 
Fires and explosions shall be precluded from initiating a site-specific cask transporter event 
sequence. 
Loss of power events shall be precluded from initiatinq a site-specific cask event sequence. 
Upon a loss of power, the transporter shall be designed to stop, retain the load, and enter a 
locked mode; upon a restoration of power, the transporter shall stay in the locked mode until 
operator action is taken. 
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 Aging System Design Development Strategy 
Table 3-6 Site-Specific Transfer Cask -Nuclear Safety Design Bases 
subsystem Nuclear Safety Design Basis 
~Sng 
Site-Specific The design of aging and transfer casks shall ensure that they can withstand a drop from the 
Transfer Cask maximum handling height of a horizontal cask transfer trailer without loss of function. 
The design of the horizontal transportation and transfer casks shall ensure that they can 
withstand a drop of heavy objects handled during transfer operations; e.g., access cover 
plate, from the maximum handlina heioht without adverse effects. 
~i~htzn~
strikes shall be precluded from initiating a site-specific transfer cask event 
sequence. 
Table 3-7 Aging Pad -Nuclear Safety Design Bases 
Aging Subsystem Nuclear Safety Design Basis 
Aging Pad The design of the aging pad shall ensure that it is capable of performing functions that are 
important to safety durino a maximum probable flood. 
The aging pad shall be located to avoid placement directly over surface or near-surface 
faults. 
The surface aging pad shall be designed for loading conditions associated with a Design 
Basis Ground Motion-2 level seismic event and demonstrate sufficient margin to a "no 
significant cracking/displacement" safety function for loading conditions associated with a 
Beyond Design Basis Ground Motion-level seismic event. 
To reduce the likelihood of a meteorite strike that could breach a cask, the exposed area on 
the aging pads shall not exceed 15 percent density of the pad area, with an associated 
aggregate exposed cross-sectional area less than 360,000 square feet, for the case involving 
20,000 metric tons of heavy metal. 
The structure shall be designed for the loads associated with a precipitation intensity of 
2.1 5 in./hr. 
Lightning strikes shall be precluded from initiating an aging pad event sequence. 
Surface facilities associated with the Aging system, where CSNF is handled or stored shall 
be designed to withstand the effects of a regional volcanic eruption without loss of capacity to 
perform their safety function. 
A barrier surrounding the aging pads shall ensure that the conditional probability of a skid-in 
impact and entry by aircraft from the side of the aging pad that would result in radiological 
consequences is 0.01 or less. 
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 Aging System Design Development Strategy 
Aging Subsystem 
Site-Specific Cask 
Table 3-8 Site-Specific Cask -Nuclear Safety Design Bases 
Nuclear Safety Design Basis 
The site-specific casks and other vertical aging systems shall be designed for loading 
conditions associated with a Design Basis Ground Motion-2 level seismic event and 
demonstrate sufficient margin to "no tip-over" and "no breach" safety functions for loading 
conditions associated with a Beyond Design Basis Ground Motion-level seismic event. 
Tip-over or displacement of aging casks as a result of extreme wind or tornado events shall 
be precluded. 
Tip-over or displacement of aging casks as a result of differential pressure associated with a 
passing tornado shall be precluded. 
The design of aging casks shall ensure that they can withstand the differential pressure 
associated with a passing tornado without loss of function. 
Tip-over or displacement of aging casks as a result of being struck by a design basis tornado 
missile shall be precluded. 
The design of aging casks shall ensure that they can withstand being struck by a design 
basis tornado missile without loss of function. 
The design of aging casks shall ensure that they can withstand a drop from the maximum 
handling height of a site-specific transporter without loss of function. 
The design of aging casks shall ensure that they can withstand limited hydrogen explosions 
or fires involving batteries or limited quantities of fuel without loss of function. 
The design of the casks shall ensure acceptable thermal design performance during extreme 
temperature events based on YMP historical climate data. 
Short-duration vent blockage events involving site-specific casks shall be precluded from 
initiating an event sequence. 
Maximum snow, sand, or ash loads shall be precluded from initiating an event sequence 
involving site-specific casks. 
The design of the casks shall ensure that welded closure caskslcanister confinement system 
designs preclude loss of confinement during life cycle operations and events following 
closure. 
The design of the site-specific cask shall ensure that bolted closure cask design protects 
seals from damage during life cycle operations and events following closure to maintain its 
primary confinement boundary function. 
Site-specific casks shall be designed to ensure nuclear criticality safety with optimum 
moderation and the most reactive waste forms despite any geometric rearrangements due to 
a drop or other handling incident. 
In case of a fire, the wall temperature of a loaded site-specific cask, being handled or at rest, 
shall not exceed its allowable operatina ranqe. 
-
In case of a fire, the wall temperature of a loaded site-specific cask with docking ring installed 
shall not exceed its allowable operating range. 
Liqhtninq strikes shall be precluded from initiatinq a site-specific cask event sequence. 
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 Aging System Design Development Strategy 
Table 3-9 Horizontal Aging Module -Nuclear Safety Design Bases 
Rging Subsystem Nuclear Safety Design Basis 
iorizontal Aging The HAM systems shall be designed for loading conditions associated with a Design Basis 
Module Ground Motion-2 level seismic event and demonstrate sufficient margin to a "no collapse" 
safety function for loading conditions associated with a Beyond Design Basis Ground Motion- 
level seismic event. 
Lightning strikes shall be precluded from initiating a HAM event sequence. 
Tip-over or displacement of HAMs as a result of extreme wind or tornado events shall be 
orecluded. 
Tip-over or displacement of HAMs as a result of differential pressure associated with a 
passing tornado shall be precluded. 
I 
The design of HAMs shall ensure that they can withstand the differential pressure associated 
with a passing tomado without loss of function. 
I 
Tip-over or displacement of HAMs as a result of being struck by a design basis tornado 
missile shall be precluded. 
I 
The design of HAMs shall ensure that they can withstand being struck by a design basis 
tornado missile without loss of function. 
I 
The design of HAMs shall ensure that they can withstand limited hydrogen explosions or fires 
involving batteries or limited quantities of fuel without loss of function. 
The design of the HAMs shall ensure acceptable thermal design performance during extreme 
temperature events based on YMP historical climate data. 
Short-duration vent blockage events involving HAMs shall be precluded from initiating an 
event sequence. 
Maximum snow, sand, or ash loads shall be precluded from initiating an event sequence 
involving HAMs. 
The design of the HAMs shall ensure that welded closure caskslcanister confinement system 
designs preclude loss of confinement during life cycle operations and events following 
closure. 
Fires and explosions shall be precluded from initiating a HAM event sequence. 
The HAMs shall be designed to withstand the effects of a regional volcanic eruption without 
loss of capacity to perform their safety function. 
The design of the horizontal DPC shall ensure that it has sufficient structural design margin 
to withstand maximum ram force events. 
3.3 Recent Aging Strategy, Performance Specification 
With the completion of the conceptual design for the YMP SAR (DOE 2005 [DIRS 1706751, 
Section 1.2.7), the Aging design team has advanced the aging program by issuing a subcontract 
for the development of a technical performance specification for vertical site-specific casks, 
HAMs, and supporting site transport equipment. A subcontractor has been requested to prepare 
a technical performance specification for the design and fabrication of site-specific casks with 
matching cask transfer equipment (BSC 2004 [DIRS 1727461). The technical performance 
specification must be developed to meet the proposed nuclear safety design bases in Tables 3-3 
through 3-9. 
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 Aging System Design Development Strategy 
Table 4-1 Preliminary Design Activities 
Activity Activity Description Time Frame 
Package Contents Establish preliminary calculations, drawings, FY 2006 
reports, and specifications that comprise the YMP 
Establish 
Requirements . other Aging SSCs. ldentify appropriate codes and 
Establish Interfaces 
standards. 
Specify interfaces between cask and surface I FY 2006 
repository facility systems. 
Evaluate Existing Summarize the existing horizontal and vertical FY 2005 
Storage Cask storage systems that may be used at Yucca 
Systems Mountain and establish which features will need 
evaluation to adapt the existing design to Yucca 
Mountain. 
Develop Design Specify the inputs for the site-specific cask systems FY 2005 
Inputs derived from the repository design, spent fuel 
configurations, and other considerations. 
Bounding 
Conditions 
Establish bounding conditions for cask designs. I FY 2006 
Develop Storage Complete design of horizontal and vertical systems FY 2006 
Cask Designs to approximately 30 percent complete. Complete 
required structural, seismic, thermal, and 
radiological analyses. 
---
Develop Transfer Complete design of horizontal and vertical transfer FY 2006 
System Designs systems to approximately 30 percent complete. 
Complete required analyses. 
Reliability and Identify the risks associated with the preliminary FY 2006 
Risks design and any reliability issues. 
Perform Reviews Conduct preliminary design reviews FY 2006 
ldentify any Needed 
Testing 
ldentify any unresolved issues that may need 
further testing or evaluation. I Fy 2006 
4.2 Final Design 
Final design of the Aging system components will be based on the preliminary design that was 
submitted to the NRC as part of the YMP SAR. Final design will produce a suite of detailed 
drawings and specifications that will be used to procure the Aging system vertical casks, HAMS, 
and transfer equipment. 
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 Aging System Design Development Strategy 
Table 4-2 Final Design Activities 
Final Design Activity Activity Description 
(100 percent 
complete) 
Final Design Final Design Complete set of drawings for vertical and horizontal FY 2007 and 
Drawings cask system. FY 2008 
Establish Baseline Formally control the final design and ensure that 
and Implement changes are appropriately controlled, documented, 
Formal Change and communicated. 
Control 
Verification of Conduct formal verification of the horizontal and 
Design vertical designs. Verify implementation of the 
design inputs, requirements, and satisfaction of 
acceptance criteria. 
Approval of 
Package for 
Issue approval package for the storage and 
transfer systems. I FY 2008 
4.3 Licensing 
Licensing activities span all phases of the Aging system program. The SAR will be based on 
conceptual and preliminary design details. Submittal of the SAR to the NRC will be at the 
discretion of DOE. The state of the design at the time of the SAR submittal will be reflected in 
the SAR. As the design progresses, additional details will be provided to the NRC through 
amendments to the SAR. As the NRC reviews the SAR, the design development strategy 
recognizes that there will be requests for additional information. Those requests will be 
addressed during the final design phase of the Aging system. 
Table 4-3 Licensing Activities 
Activity Description Time Frame 
Licensing Prepare Preliminary Prepare, review, and finalize the aging section of 
Safety Analysis the Yucca Mountain Repository License Application 
Report Safety Analysis Report (DOE 2005, [DIRS 1706751) 
Submit Final Safety Finalize SAR input for aging and submit to NRC via 
Analysis Report amendments to the SAR. 
Respond to Respond to NRC requests for additional FY 2006 
Requests for information. through FY 
Additional 2008 
Information 
Receive License for Receive license for aging components needed to 
Storage Cask store CSNF in dry storage casks at YMP. 
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 Aging System Design Development Strategy 
4.4 Fabrication and Implementation 
Fabrication of the Aging SSCs and implementation at YMP is included in this design 
development strategy plan for completeness only. Fabrication and implementation are the 
culmination of the design development program. 
Table 4-4 Fabrication Activities 
(To be developed and expanded at a future time.) 
Fabrication Activity Activity Description Time Frame 
Fabrication Award Fabrication Contracts FY 2008 
I 1 Fabricate Vertical Casks and HAMS I FY 2009 I 
Conduct Acceptance Testing FY 2009 
Certify Storage Systems for Use FY 2009 
I I Ship to Yucca Mountain I FY 2009 I 
Accept at Yucca Mountain FY 2009 I 
Table 4-5 lmplementation Activities 
Implementation I Activity 
(To be developed and expanded at a future Time.) 
I Activity Description Time Frame 
Implementation Load Casks and HAMS FY 201 0 
Transfer Casks and HAMS FY 201 0 
1 I Monitor Casks and HAMS ( FY 2010 
Return Aged CSNF to Handling Facility Future 
Transfer Aged CSNF to Waste Package Future 
5. Conclusions 
An Aging system at YMP is necessary to accomplish project goals for thermal management as 
discussed in Thermal Management Study (BSC 2005 [DIRS 1727391, Section 7.3). The design 
development strategy of the Aging system envisions the utilization and implementation of SSCs 
that are very similar to currently licensed systems. A performance specification for the aging 
casks and a comparative report to evaluate existing casks against YMP specific criteria will be 
completed in the near-term. Existing designs that are currently in service at nuclear power plants 
will be analyze for suitability for use at YMP. 
6. Acronyms 
CFR Code of Federal Regulations 
CSNF commercial spent nuclear fuel 
DOE U.S. Department of Energy 
DPC dual-purpose canister 
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 Aging System Design Development Strategy 
FY fiscal year 
HAM 
HLW 
horizontal aging module 
high-level radioactive waste 
MCO multi-canister overpack 
NRC U.S. Nuclear Regulatory Commission 
RFP request for proposal 
SAR 
SNF 
SSC 
Safety Analysis Report 
spent nuclear fuel 
structure, system, and component 
YMF Yucca Mountain Project 
7. References 
NRC (U.S. Nuclear Regulatory Commission) 1997. Standard Review Plan for 
Dry Cask Storage Systems. NUREG-1536. Washington, D.C.: U.S. Nuclear 
Regulatory Commission. ACC: MOL.20010724.0307. 
10 CFR 72. Energy: Licensing Requirements for the Independent Storage of 
Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater 
than Class C Waste. Readily available. 
10 CFR 63. Energy: Disposal of High-Level Radioactive Wastes in a Geologic 
Repository at Yucca Mountain, Nevada. Readily available. 
NRC (U.S. Nuclear Regulatory Commission) 2003. Yucca Mountain Review 
Plan, Final Report. NUREG-1804, Rev. 2. Washington, D.C.: U.S. Nuclear 
Regulatory Commission, Office of Nuclear Material Safety and Safeguards. TIC: 
254568. 
BSC (Bechtel SAIC Company) 2004. SNF Aging System Description Document. 
170-3YD-HA00-00100-000-003. Las Vegas, Nevada: Bechtel SAIC Company. 
ACC: ENG.200409 16.0001. 
BSC (Bechtel SAIC Company) 2004. Nuclear Safety Design Bases for License 
Application. 000-30R-MGRO-00400-000-001.Las Vegas, Nevada: Bechtel SAIC 
Company. 
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170675 DOE (U.S. Department of Energy) 2005. Yucca Mountain Repository License 
Application Safety Analysis Report. DOEJRW-0573, Rev 0. Washington, D.C.: 
U.S. Department of Energy, Office of Civilian Radioactive Waste Management. 
172739. BSC (Bechtel SAIC Company) 2005. Thermal Management Study. 000-30R-
MGRO-00600-000-000. Las Vegas, Nevada: Bechtel SAIC Company. ACC: 
ENG.20050202.0053. 
172746 BSC (Bechtel SAIC Company) 2004. Scope of Work, SNF Aging CaskdSite- 
Specific Casks. 170-3SW-WA42-00100-000-001.Las Vegas, Nevada: Bechtel 
SAIC Company. ACC: ENG.20040915.0005. 
172747 BSC (Bechtel SAIC Company) 2005. Scope of Work, Confirmation Report -
Yucca Mountain CSNF Aging Casks. 170-3SW-WA42-00200-000-000. Las 
Vegas, Nevada: Bechtel SAIC Company. ACC: ENG.20050203.0024. 
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