Nuclear Safety Design Bases for License Application Rev 01, ICN 00

000-30R-MGR0-00400-000-001

March 2005

1. PURPOSE 
The purpose of this report is to identify and document the nuclear safety design requirements that 
are specific to structures, systems, and components (SSCs) of the repository that are important to 
safety (ITS) during the preclosure period and to support the preclosure safety analysis and the 
license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, 
Nevada. The scope of this report includes the assignment of nuclear safety design requirements 
to SSCs that are ITS and does not include the assignment of design requirements to SSCs or 
natural or engineered barriers that are important to waste isolation (ITWI). 
These requirements are used as input for the design of the SSCs that are ITS such that the 
preclosure performance objectives of 10 CFR 63.111 [DIRS 156605] are met. The natural or 
engineered barriers that are important to meeting the postclosure performance objectives 
of 10 CFR 63.113 [DIRS 156605] are identified as ITWI. Although a structure, system, or 
component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the 
nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during 
the repository preclosure period. 
2. QUALITY ASSURANCE 
As established using information presented in Section 2 of Quality Assurance Requirements and 
Description (DOE 2004 [DIRS 171539]), this report is subject to quality assurance program 
requirements because the design bases that are identified are applicable to items classified as ITS 
as defined by 10 CFR 63.2 [DIRS 156605]. This report was developed in accordance with 
procedures LP-3.11Q-BSC, Technical Reports and AP-3.13Q, Design Control. Input data are 
identified and tracked in accordance with LP-3.15Q-BSC, Managing Technical Product Inputs. 
3. USE OF SOFTWARE 
No software required to be qualified under LP-SI.11Q-BSC, Software Management, was used for 
any part of this analysis. The text of this report is printed using Microsoft Word and is exempted 
from the requirements of LP-SI.11Q-BSC per Section 2.1.1 of the procedure. 
4. DESIGN INPUTS 
4.1 TECHNICAL INFORMATION 
4.1.1. In this analysis the acronym for the Dry Transfer Facility (DTF) represents both DTF 1 
and DTF 2 and implies that the same systems and components are located within both 
DTF 1 and DTF 2. Basis: Two identical DTFs are planned. Initially, only one will be 
constructed and operated. Throughput requirements will determine the timing of 
construction and operation of the second DTF (BSC 2004e [DIRS 167232], 
Section 1.1). 
4.1.2 Safety Classification of SSCs and Barriers (BSC 2005a [DIRS 171668], Table A-1) 
establishes the safety classification of the SSCs that are ITS. Basis: This input is 
appropriate for use because it represents the latest safety classification information 
available for this report. 

000-30R-MGR0-00400-000-001 2 March 2005 
4.1.3 Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7) establishes the categorization (as Category 1, Category 2, or 
Beyond Category 2) of the internal and external event sequences that may occur before 
permanent closure of the repository at Yucca Mountain. Basis: This input is 
appropriate for use because it represents the latest event sequence categorization 
information available for this report. 
4.1.4 Preclosure Consequence Analyses for License Application (BSC 2005c [DIRS 
171607], Section 7) describes the SSCs relied upon for prevention or mitigation of 
identified event sequences. Basis: This input is appropriate for use because it provides 
the consequences of potential event sequences and identifies the SSCs required to 
mitigate the consequences of event sequences in order to comply with the performance 
objectives of 10 CFR Part 63 [DIRS 156605]. 
4.1.5 Fire-Induced Event Sequence Analysis (BSC 2004c [DIRS 171488], Section 5) 
describes the SSCs relied upon for prevention or mitigation of identified fire-induced 
event sequences. Basis: This input is appropriate for use because it provides the basis 
for design requirements that are required to mitigate the consequences of fire-induced 
event sequences in order to comply with the performance objectives of 10 CFR Part 63 
[DIRS 156605]. 
4.1.6 Extreme Wind/Tornado/Tornado Missile Hazard Analysis (BSC 2004d [DIRS 171471], 
Section 9) describes the SSCs relied upon for prevention or mitigation of identified 
event sequences. Basis: This input is appropriate for use because it provides the basis 
for design requirements that are required to mitigate the consequences of event 
sequences associated with extreme winds, tornadoes, and tornado missile hazards in 
order to comply with the performance objectives of 10 CFR Part 63 [DIRS 156605]. 
4.1.7 Monitored Geologic Repository External Events Hazards Screening Analysis (BSC 
2004b [DIRS 167266], Section 6) describes the SSCs relied upon for prevention or 
mitigation of identified event sequences. Basis: This input is appropriate for use 
because it provides the basis for design requirements that are required to mitigate the 
consequences of event sequences associated with external events in order to comply 
with the performance objectives of 10 CFR Part 63 [DIRS 156605]. 
4.1.8 Frequency Analysis of Aircraft Hazards for License Application (BSC 2005d [DIRS 
171786], Section 5) describes the SSCs relied upon for prevention or mitigation of 
identified event sequences. Basis: This input is appropriate for use because it provides 
the basis for the design requirements associated with aircraft hazards that are required 
to prevent or mitigate the consequences of event sequences associated with aircraft 
hazards in order to comply with the performance objectives of 10 CFR Part 63 [DIRS 
156605]. 
4.1.9 Reliability Analysis of the Electrical Power Distribution System to Selected Portions of 
the Nuclear HVAC System (BSC 2004f [DIRS 171490], Table 9) describes the SSCs 
relied upon for prevention or mitigation of identified event sequences. Basis: This 
input is appropriate for use because it provides the basis for the design requirements 

000-30R-MGR0-00400-000-001 3 March 2005 
that are required to prevent or mitigate the consequences of event sequences associated 
with the electrical power system in order to comply with the performance objectives of 
10 CFR Part 63 [DIRS 156605]. 
4.1.10 Seismic Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Section 4) 
describes the functions of SSCs relied upon for prevention or mitigation of identified 
event sequences. Basis: This input is appropriate for use because it provides the basis 
for the design requirements that are required to prevent or mitigate the consequences of 
event sequences associated with seismic events in order to comply with the 
performance objectives of 10 CFR Part 63 [DIRS 156605]. 
4.1.11 SNF Aging System Safety Study (Cogema. 2004 [DIRS 171793], Section 6) describes 
the functions of SSCs relied upon for prevention or mitigation of identified event 
sequences. Basis: This input is appropriate for use because it provides the basis for the 
design requirements that are required to prevent or mitigate the consequences of event 
sequences associated with the SNF Aging System in order to comply with the 
performance objectives of 10 CFR Part 63 [DIRS 156605]. 
4.2 CRITERIA 
Federal Regulations 
The safety classification criteria used in this report are based on the performance objectives 
stated in 10 CFR 63.111 [DIRS 156605]. Transportation casks received at the repository comply 
with requirements of 10 CFR 71.55 [DIRS 104091], which states that casks are to be subcritical 
even with most reactive credible configuration of fissile material and moderation to the most 
reactive credible extent, and the design bases of 10 CFR 71.73 [DIRS 104091]. Event sequence 
categorization methodology is based on the 10 CFR 63.2 definition of event sequence. 
5. ASSUMPTIONS 
5.1 System architecture is established by Facility, Equipment and System Names for Use in 
the SAR (Lucas 2004 [DIRS 170073]). Rationale: This input is appropriate for use 
because it represents the latest design information and system architecture available for 
this report. 
5.2 Although the Remediation Facility is included in the system architecture provided in 
Lucas (2004 [DIRS 170073]), it is assumed to be included as an integral part of the DTF 
and will not exist as a separate facility. Rationale: The Remediation Facility is 
integrated within the DTF and provides the space, layout, structures, and embedded 
systems needed to recover from off-normal conditions during waste-handling operations 
(e.g., a damaged transportation cask, fuel form, or waste package [WP]). 

000-30R-MGR0-00400-000-001 4 March 2005 
6. ANALYSIS 
6.1 METHOD 
A distinction is made between the repository design bases and the 10 CFR 63.2 [DIRS 156605] 
design bases for SSCs that are ITS. All SSCs have design bases; however, only SSCs that are 
ITS have design bases as defined by 10 CFR 63.2. These 10 CFR 63.2 design bases are required, 
pursuant to 10 CFR 63.112 [DIRS 156605], to be included in the preclosure safety analysis of 
the license application for a repository at Yucca Mountain. 
The preclosure safety analysis of the license application provides a safety assessment of the 
10 CFR 63.2 repository design bases. The 10 CFR 63.2 design bases and the supporting design 
information are subjected to design control and the other quality assurance criteria of 10 CFR 
63.142 [DIRS 156605]. 
The methodology for developing the 10 CFR 63.2 design bases are summarized in the following 
paragraphs. 
The Category 1, Category 2, and Beyond Category 2 event sequences derived from the internal, 
external, and other applicable hazards analyses (such as fire hazards analysis, aircraft crash 
hazards analysis, etc.) are identified. The list of Category 1, Category 2, and Beyond Category 2 
event sequences form a part of the repository licensing bases and appear in the license 
application. Each Category 1, Category 2, and Beyond Category 2 event sequence involves 
SSCs that are evaluated within the preclosure safety analysis to assess the likelihood and 
consequences of an event sequence leading to a dose that exceeds the 10 CFR Part 63 [DIRS 
156605] preclosure performance objectives. These SSCs may change as the design matures. 
Changes in the list of event sequences result in a reassessment of affected SSCs and associated 
10 CFR 63.2 design bases. Design iterations, design improvements, or design modifications 
could potentially lead to changes in the list of event sequences and associated SSCs throughout 
the licensing process and beyond. 
Compliance with the 10 CFR Part 63 performance objectives for Category 1 and Category 2 
event sequences is significantly different for each category. Category 1 event sequence 
compliance assessments are based on annual performance requirements that require an 
aggregation of releases. A Category 2 event sequence compliance assessment is made on a perevent 
basis. No aggregation of releases is made for Category 2 event sequences. Because of 
these compliance differences, the design bases for SSCs that are ITS involved in Category 2 
event sequences are developed before the design bases associated with the Category 1 event 
sequences. ITS SSCs may be required to ensure that an event sequence is categorized as Beyond 
Category 2. 
The set of SSCs that has been classified as ITS based on the Category 1 and Category 2 event 
sequences is identified. In addition, those SSCs credited for ensuring that an event sequence is 
categorized as Beyond Category 2 are identified. These SSCs that have been classified as ITS 
require 10 CFR 63.2 design bases to be established. 

000-30R-MGR0-00400-000-001 5 March 2005 
A single SSC is then chosen from the set of SSCs classified as ITS and the Category 1, 
Category 2, and Beyond Category 2 event sequences that credit the function of that SSC are 
identified from the applicable supporting analyses. 
For the selected SSC that is ITS, the Category 2 and Beyond Category 2 10 CFR 63.2 design 
bases are developed. This selection process is repeated until the SSCs that are ITS have 
10 CFR 63.2 design bases developed for each of the Category 2 and Beyond Category 2 event 
sequences. 
After the design bases for the Category 2 and Beyond Category 2 event sequences are identified, 
an SSC that is ITS for meeting the Category 1 performance objective is selected. The 10 CFR 
63.2 design bases for the SSC that is ITS that meet the 10 CFR Part 63 preclosure performance 
objectives for Category 1 event sequences are then selected. This process is repeated until 
10 CFR 63.2 design bases are established for the SSCs that are ITS in the Category 1 event 
sequences. 
6.2 ARCHITECTURE 
The repository is comprised of the following facilities (Lucas 2004 [DIRS 170073]): 
1. Balance of Plant Facility 
2. Canister Handling Facility (CHF) 
3. DTF 
4. Fuel Handling Facility (FHF) 
5. Subsurface Facility 
6. Transportation Cask Receipt and Return Facility (TCRRF) 
7. Warehouse and Non-Nuclear Receipt Facility (WNNRF). 
Although the Remediation Facility is included in the system architecture provided in Facility, 
Equipment and System Names for Use in the SAR (Lucas 2004 [DIRS 170073]), it has since 
been included as an integral part of the DTF and does not exist as a separate facility 
(Assumption 5.2). 
Repository systems are subdivided into process systems and infrastructure systems. Process 
systems include systems that involve primary processes in the waste handling and waste isolation 
systems while the infrastructure systems are those systems that are needed to provide support to 
the process systems and the facilities. Process and infrastructure systems exist and operate in 
multiple facilities. 
The repository waste handling systems are evaluated to determine the applicability of 
Category 1, Category 2, and Beyond Category 2 event sequences associated with preclosure 
operations (BSC 2005b [DIRS 171429]). The Balance of Plant facilities have no Category 1, 
Category 2, or Beyond Category 2 event sequences associated with preclosure operations (BSC 
2005b [DIRS 171429]). The remaining repository facilities and the repository process systems 
that are present in these facilities include the following (Lucas 2004 [DIRS 170073]): 
 Transportation Cask Receipt/Return Facility 
- Cask Receipt/Return System 

000-30R-MGR0-00400-000-001 6 March 2005 
 Warehouse and Non-Nuclear Receipt Facility 
- DOE and Commercial Waste Package System 
- Naval Spent Nuclear Fuel Waste Package System 
- Non-Nuclear Handling System 
 Dry Transfer Facility 
- DOE and Commercial Waste Package System 
- Naval Spent Nuclear Fuel Waste Package System 
- Cask Receipt/Return System 
- Non-Nuclear Handling System 
- Cask/MSC/WP Preparation System 
- SNF/HLW Transfer System 
- Waste Package Closure System 
- Remediation System 
- Emplacement and Retrieval System 
- SNF Aging System 
 Canister Handling Facility 
- DOE and Commercial Waste Package System 
- Naval Spent Nuclear Fuel Waste Package System 
- Cask Receipt/Return System 
- Non-Nuclear Handling System 
- Cask/MSC/WP Preparation System 
- SNF/HLW Transfer System 
- Waste Package Closure System 
- Emplacement and Retrieval System 
- SNF Aging System 
 Fuel Handling Facility 
- DOE and Commercial Waste Package System 
- Naval Spent Nuclear Fuel Waste Package System 
- Cask Receipt/Return System 
- Non-Nuclear Handling System 
- Cask/MSC/WP Preparation System 
- SNF/HLW Transfer System 
- Waste Package Closure System 
- Emplacement and Retrieval System 
- SNF Aging System 
 Subsurface Facility 
- DOE and Commercial Waste Package System 
- Naval Spent Nuclear Fuel Waste Package System 
- Emplacement and Retrieval System 
- SNF Aging System 

000-30R-MGR0-00400-000-001 7 March 2005 
The applicable repository facility and process system SSCs provided in this report are presented 
with their corresponding 10 CFR 63.2 design bases. 
6.3 CATEGORIZATION OF EVENT SEQUENCES 
An event sequence is defined by the U.S. Nuclear Regulatory Commission to be a series of 
actions and/or occurrences within the natural and engineered components of a geologic 
repository operations area that could potentially lead to exposure of individuals to radiation (10 
CFR 63.2). Event sequences that are expected to occur one or more times before permanent 
closure of the geologic repository operations area are referred to as Category 1 event sequences 
(10 CFR 63.2). Other event sequences that have at least one chance in 10,000 of occurring 
before permanent closure are referred to as Category 2 event sequences (10 CFR 63.2). Less 
likely event sequences are considered Beyond Category 2. An event that has no potential for 
exposure of individuals to radiation is not considered an event sequence. 
The initial step of the process for determining the 10 CFR Part 63.2 design bases involves 
determining the Category 1, Category 2, and Beyond Category 2 event sequences. These event 
sequences are identified in the internal, external, and other applicable hazards analyses. 
Categorization of Event Sequences for License Application (BSC 2005b [DIRS 171429]) 
establishes the categorization (as Category 1, Category 2, or Beyond Category 2) of the internal 
and external event sequences that may occur before permanent closure of the repository at Yucca 
Mountain. 
6.4 CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS 
Safety Classification of SSCs and Barriers (BSC 2005a [DIRS 171668]) establishes the safety 
classification of the repository SSCs. If an SSC is determined to be ITS or ITWI, then it is 
classified as safety category (SC). An SSC can be ITS, ITWI, both, or neither. If an SSC is 
neither ITS nor ITWI, it is classified as Non-SC. The safety classifications of the repository 
SSCs, as established in Safety Classification of SSCs and Barriers (BSC 2005a [DIRS 171668]), 
are reproduced in the tables found in Appendix A of this analysis. The set of SSCs that have 
been classified as ITS based on the Category 1 and Category 2 event sequences, as well as those 
SSCs credited for ensuring that an event sequence is categorized as Beyond Category 2, are 
identified. 
6.5 EVENT SEQUENCE CONSEQUENCE ANALYSIS 
The worker and offsite radiation doses were calculated in Preclosure Consequence Analyses for 
License Application (BSC 2005c [DIRS 171607], Section 7) for the event sequences identified in 
Categorization of Event Sequences for License Application (BSC 2005b [DIRS 171429], 
Section 7). In addition, any mitigative functions performed by ITS SSCs that are credited in the 
dose calculations are identified (such as high-efficiency particulate air [HEPA] filters). 
6.6 DEVELOPMENT OF DESIGN BASES 
The development of the 10 CFR 63.2 design bases follows the methodology described in Section 
6.1 using the inputs described in Section 4.1. 

000-30R-MGR0-00400-000-001 8 March 2005 
The repository facilities, and the repository process systems that are present in these facilities, 
are listed in the following subsections based on the repository architecture described in Section 
6.2. The facilities and systems that have Category 1 or Category 2 event sequences that require 
SSCs to perform prevention or mitigation functions are identified. In some instances, 10 CFR 
63.2 design bases are developed for SSCs that provide prevention functions to ensure that the 
frequency of an event sequence is Beyond Category 2. 
The 10 CFR 63.2 design bases (the nuclear safety design bases) for the repository facilities, 
systems, subsystems, and selected SSCs that are developed using the methodology described in 
Section 6.1 are presented in Tables A-I and A-II of Appendix A. 
6.6.1 Waste Handling Area Facilities 
The repository facilities include the following: the Balance of Plant Facility, CHF, DTF, FHF, 
Subsurface Facility, TCRRF, and the WNNRF (Lucas 2004 [DIRS 170073]). The safety 
categories for these facilities are shown in Attachment A of Safety Classification of SSCs and 
Barriers (BSC 2005a [DIRS 171668]). 
6.6.1.1 Balance of Plant Facility 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
the facilities that comprise the Balance of Plant Facility to perform prevention or mitigation 
functions. The switchgear facility contains portions of the electrical power system that are ITS. 
Although the structure contains ITS components, there are no event sequences identified that 
prevent the ITS components from performing their ITS function. No Balance of Plant facility is 
required to function to protect an ITS or ITWI SSC or natural or engineered barrier. The safety 
category of the system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no 
nuclear safety design bases associated with the Balance of Plant Facility. 
6.6.1.2 Canister Handling Facility 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are Category 2 event sequences that could occur in this facility and 
there are features of the facility that are ITS for prevention or mitigation of event sequences. The 
Seismic Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Attachment III) has 
identified potential seismically initiated failures that could lead to undesired consequences. This 
facility contains SSCs that are ITS; it does not contain SSCs or natural or engineered barriers that 
are ITWI. The safety category of this facility is SC (BSC 2005a [DIRS 171668], Attachment A). 
Table A-I in Appendix A presents the nuclear safety design bases associated with the CHF. 
6.6.1.3 Dry Transfer Facility 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7) and Preclosure Consequence Analysis for License Application (BSC 2005c 
[DIRS 171607], Section 7), there are Category 1 and Category 2 event sequences that could 
occur in this facility and there are features of the facility that are ITS for prevention or mitigation 
of event sequences. Seismic Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], 

000-30R-MGR0-00400-000-001 9 March 2005 
Attachment III) has identified potential seismically initiated failures that could lead to undesired 
consequences. This facility contains SSCs that are ITS; it does not contain SSCs or natural or 
engineered barriers that are ITWI. The safety category of this facility is SC (BSC 2005a [DIRS 
171668], Attachment A). Table A-I in Appendix A presents the nuclear safety design bases 
associated with the DTF. 
6.6.1.4 Fuel Handling Facility 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7) and the Preclosure Consequence Analysis for License Application (BSC 
2005c [DIRS 171607], Section 7), there are Category 1 and Category 2 event sequences that 
could occur in this facility and there are features of the facility that are ITS for prevention or 
mitigation of event sequences. The Seismic Analysis for Preclosure Safety (BSC 2004a [DIRS 
171470], Attachment III) has identified potential seismically initiated failures that could lead to 
undesired consequences. This facility contains SSCs that are ITS; it does not contain SSCs or 
natural or engineered barriers that are ITWI. The safety category of this facility is SC (BSC 
2005a [DIRS 171668], Attachment A). Table A-I in Appendix A presents the nuclear safety 
design bases associated with the FHF. 
6.6.1.5 Subsurface Facility 
The Subsurface Facility consists of the emplacement drifts, subsurface development, and 
postemplacement subsystems (BSC 2005a [DIRS 171668], Section 6.3.1.5). In this report, the 
Subsurface Facility and its three component subsystems are considered separately in the 
development of nuclear safety design bases. 
The size and layout of the emplacement drifts component of the Subsurface Facility ensure that 
performance complies with rockfall modeling (preclosure and postclosure) and drift modeling 
(postclosure) because they provide the rock properties and emplacement drifts layout and 
dimensions for the rockfall analysis. The size and layout of drifts is both ITS and ITWI. 
Nonemplacement openings of the Subsurface Facility provide the size properties consistent with 
rockfall modeling for preclosure. A change of the size of the nonemplacement openings may 
allow a larger rockfall that could breach WPs as they are transported through the openings. 
Thus, the nonemplacement openings component is ITS. The safety category of the Subsurface 
Facility is SC (BSC 2005a [DIRS 171668], Attachment A). 
The emplacement drifts excavated openings component of the emplacement drift subsystem are 
ITS and ITWI because they provide the rock properties and emplacement drift layout dimensions 
for the rockfall analyses used in preclosure safety analyses and postclosure performance 
confirmation (BSC 2005a [DIRS 171668], Attachment A). The WP emplacement pallet 
component of the emplacement drift subsystem is ITS and ITWI for providing structural support 
to protect the WP from damage during surface handling operations and transport to, and into, an 
emplacement drift. During the preclosure and postclosure periods, the WP emplacement pallet 
provides support to the WP should a seismic event occur. The safety category of the 
emplacement drift subsystem is SC (BSC 2005a [DIRS 171668], Attachment A). There is no 
Category 1 or Category 2 event sequence that requires SSCs in the emplacement drift subsystem 
to perform prevention or mitigation functions (BSC 2005b [DIRS 171429], Section 7). The 

000-30R-MGR0-00400-000-001 10 March 2005 
Seismic Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Attachment III) has 
identified potential seismically initiated failures that could lead to undesired consequences. 
The postemplacement subsystem and its closure functions during postclosure are ITWI. 
This subsystem does not include ITS SSCs; it does include ITWI SSCs. The safety category of 
this subsystem is SC (BSC 2005a [DIRS 171668], Attachment A). There is no Category 1 or 
Category 2 event sequence that requires SSCs in the postemplacement subsystem to perform 
preclosure prevention or mitigation functions (BSC 2005b [DIRS 171429], Section 7). 
The subsurface development subsystem does not contain spent nuclear fuel (SNF) or HLW. 
There is no Category 1 or Category 2 event sequence that requires SSCs in this subsystem to 
perform prevention or mitigation functions (BSC 2005b [DIRS 171429], Section 7). Therefore, 
this subsystem does not include ITS SSCs or ITWI SSCs or natural or engineered barriers. The 
safety category of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). 
The nuclear safety design bases associated with the Subsurface Facility and its subsystems are 
presented in Table A-I in Appendix A. 
6.6.1.6 Transportation Cask Receipt/Return Facility 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), Category 2 event sequences could occur in the TCRRF and there are 
features of the facility that are ITS for prevention or mitigation of event sequences. The Seismic 
Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Attachment III) has identified 
potential seismically initiated failures that could lead to undesired consequences. This facility 
contains SSCs that are ITS; it does not contain SSCs or natural or engineered barriers that are 
ITWI. The safety category of this facility is SC (BSC 2005a [DIRS 171668], Attachment A). 
Table A-I in Appendix A presents the nuclear safety design bases associated with the TCRRF. 
6.6.1.7 Warehouse and Non-Nuclear Receipt Facility 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
the WNNRF to perform prevention or mitigation functions. Therefore, this facility consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this facility is Non-SC (BSC 2005a [DIRS 171668], Attachment A). 
6.6.2 Waste Process and Infrastructure Systems 
6.6.2.1 Cask/MSC/WP Preparation System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are Category 2 event sequences that could occur in this system and 
there are features of the system that are ITS for prevention or mitigation of event sequences. The 
Seismic Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Attachment III) has 
identified potential seismically initiated failures that could lead to undesired consequences. This 
system contains SSCs that are ITS; it does not contain SSCs or natural or engineered barriers that 
are ITWI. The safety category of this system is SC (BSC 2005a [DIRS 171668] Attachment A). 

000-30R-MGR0-00400-000-001 11 March 2005 
Table A-II in Appendix A presents the nuclear safety design bases associated with the 
Cask/MSC/WP Preparation System. 
6.6.2.2 Cask Receipt and Return System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are Category 2 event sequences that could occur in this system and 
there are features of the system that are ITS for prevention or mitigation of event sequences. 
This system consists of SSCs that are ITS; it does not contain SSCs or natural or engineered 
barriers that are ITWI. The safety category of this system is SC (BSC 2005a [DIRS 171668], 
Attachment A). Table A-II in Appendix A presents the nuclear safety design bases associated 
with the Cask Receipt and Return System. 
6.6.2.3 Communications System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Communications System. 
6.6.2.4 Digital Control and Management Information System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Digital Control and Management Information System. 
6.6.2.5 DOE and Commercial Waste Package System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), a Category 2 event sequence that requires the WP to perform prevention or 
mitigation functions could occur (BSC 2005b [DIRS 171429], Section 5.1.3). The Seismic 
Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Attachment III) has identified 
potential seismically initiated failures that could lead to undesired consequences. The WP 
functions during the preclosure and postclosure periods result in the WP being identified as ITS 
and ITWI, respectively (BSC 2005a [DIRS 171668], Section 6.3.2.5). The safety category of 
this system is SC (BSC 2005a [DIRS 171668], Attachment A). Table A-II in Appendix A 
presents the nuclear safety design bases associated with the DOE and Commercial Waste 
Package System. 
6.6.2.6 Electrical Power System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7]), there are Category 1 or Category 2 event sequences that require a function 

000-30R-MGR0-00400-000-001 12 March 2005 
or functions of the surface nuclear heating, ventilation, and air-conditioning (HVAC) system for 
mitigation of Category 1 event sequences (BSC 2005b [DIRS 171429], Section 7). The 
switchyard, normal power, and emergency power subsystems are required for operation and 
support of the surface nuclear HVAC system in the DTF and FHF to maintain doses within the 
performance objectives of 10 CFR 63.111 [DIRS 156605]. The electrical power system supports 
the availability of the switchyard, normal power, and emergency power to mitigate the 
consequences of an event sequence. It includes ITS SSCs; it does not include ITWI SSCs or 
natural or engineered barriers. The safety category of this system is SC (BSC 2005a [DIRS 
171668], Attachment A). Table A-II in Appendix A presents the nuclear safety design bases 
associated with the Electrical Power System. 
6.6.2.7 Electrical Support System 
As described in Safety Classification of SSCs and Barriers (BSC 2005a [DIRS 171668], 
Section 6.3.2.7), this system provides electrical support for construction and operation of the 
surface and subsurface facilities, including ITS functions of the surface nuclear HVAC system. 
Portions of the cable raceway subsystem that support the availability of electrical power to 
mitigate the consequences of an event sequence are ITS. SSCs in the remaining portions of the 
electrical support system do not prevent or mitigate the consequences of a Category 1 or 
Category 2 event sequence. This system includes ITS SSCs; it does not include ITWI SSCs or 
natural or engineered barriers. The safety category of this system is SC (BSC 2005a [DIRS 
171668], Attachment A). Table A-II in Appendix A presents the nuclear safety design bases 
associated with the Electrical Support System. 
6.6.2.8 Emplacement and Retrieval System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are Category 2 event sequences that could occur in this system and 
there are features of the system that are ITS for prevention or mitigation of event sequences. The 
Seismic Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Attachment III) has 
identified potential seismically initiated failures that could lead to undesired consequences. This 
system contains SSCs that are ITS; it does not contain SSCs or natural or engineered barriers that 
are ITWI. The safety category of this system is SC (BSC 2005a [DIRS 171668], Attachment A). 
Table A-II in Appendix A presents the nuclear safety design bases associated with the 
Emplacement and Retrieval System. 
6.6.2.9 Environmental/Meteorological Monitoring System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Environmental/Meteorological Monitoring System. 

000-30R-MGR0-00400-000-001 13 March 2005 
6.6.2.10 Fire Protection System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Fire Protection System. 
6.6.2.11 HVAC Plant Heating and Cooling System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the HVAC Plant Heating and Cooling System. 
6.6.2.12 Low-Level Radioactive Waste Generating System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429] Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Low-Level Radioactive Waste Generating System. 
6.6.2.13 Low-Level Radioactive Waste Management System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Low-Level Radioactive Waste Management System. 
6.6.2.14 Naval Spent Nuclear Fuel Waste Package System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), a Category 2 event sequence that requires the WP to perform prevention or 
mitigation functions could occur (BSC 2005b, Section 5.1.3). The Seismic Analysis for 
Preclosure Safety (BSC 2004a [DIRS 171470], Attachment III) has identified potential 
seismically initiated failures that could lead to undesired consequences. The WP functions 
during the preclosure and postclosure periods result in the WP being identified as ITS and ITWI, 
respectively (BSC 2005a [DIRS 171668], Section 6.3.2.14). The safety category of this system 
is SC (BSC 2005a [DIRS 171668], Attachment A). Table A-II in Appendix A presents the 
nuclear safety design bases associated with the Naval Spent Nuclear Fuel Waste Package 
System. 

000-30R-MGR0-00400-000-001 14 March 2005 
6.6.2.15 Non-Nuclear Handling System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Non-Nuclear Handling System. 
6.6.2.16 Non-Radiological Waste Management System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Non-Radiological Waste Management System. 
6.6.2.17 Plant Services System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Plant Services System. 
6.6.2.18 Radiation/Radiological Monitoring System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Radiation/Radiological Monitoring System. 
6.6.2.19 Remediation System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), a Category 2 event sequence could occur in this system and there are 
features of the system that are ITS for prevention or mitigation of event sequences. The Seismic 
Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Attachment III) has identified 
potential seismically initiated failures that could lead to undesired consequences. This system 
contains SSCs that are ITS; it does not contain SSCs or natural or engineered barriers that are 
ITWI. The safety category of this system is SC (BSC 2005a [DIRS 171668], Attachment A). 
Table A-II in Appendix A presents the nuclear safety design bases associated with the 
Remediation System. 

000-30R-MGR0-00400-000-001 15 March 2005 
6.6.2.20 Safeguards and Security System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Safeguards and Security System. 
6.6.2.21 SNF Aging System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), a Category 2 event sequence could occur in this system and there are 
features of the system that are ITS for prevention or mitigation of event sequences. The Seismic 
Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Attachment III) has identified 
potential seismically initiated failures that could lead to undesired consequences. This system 
contains SSCs that are ITS; it does not contain SSCs or natural or engineered barriers that are 
ITWI. The safety category of this system is SC (BSC 2005a [DIRS 171668], Attachment A). 
Table A-II in Appendix A presents the nuclear safety design bases associated with the SNF 
Aging System. 
6.6.2.22 SNF/HLW Transfer System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7) and Preclosure Consequence Analyses for License Application (BSC 2005c 
[DIRS 171607], Section 7), there are Category 1 and Category 2 event sequences that require 
SSCs in this system to perform prevention or mitigation functions. As established by Preclosure 
Consequence Analyses for License Application (BSC 2005c [DIRS 171607], Section 7), the 
worker radiation doses and offsite radiation doses for Category 1 and Category 2 event 
sequences meet the 10 CFR Part 63 [DIRS 156605] performance objectives. This system 
contains SSCs that are ITS; it does not contain SSCs or natural or engineered barriers that are 
ITWI. The safety category of this system is SC (BSC 2005a [DIRS 171668], Attachment A). 
Table A-II in Appendix A presents the nuclear safety design bases associated with the 
SNF/HLW Transfer System. 
6.6.2.23 Subsurface Ventilation System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Subsurface Ventilation System. 
6.6.2.24 Surface Industrial HVAC System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 5.1.2.4) there are Category 1 or Category 2 event sequences that require SSCs 

000-30R-MGR0-00400-000-001 16 March 2005 
in this system to perform prevention or mitigation functions. Therefore, this system includes 
SSCs that are ITS; it does not include ITWI SSCs or natural or engineered barriers. The safety 
category of this system is SC (BSC 2005a [DIRS 171668], Attachment A). Table A-II in 
Appendix A presents the nuclear safety design bases associated with the Surface Industrial 
HVAC System. 
6.6.2.25 Surface Nuclear HVAC System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7) and the Preclosure Consequence Analysis for License Application (BSC 
2005c [DIRS 171607]), there are Category 1 event sequences that require SSCs in this system to 
perform prevention or mitigation functions. The Seismic Analysis for Preclosure Safety (BSC 
2004a [DIRS 171470], Attachment III) has identified potential seismically initiated failures that 
could lead to undesired consequences. This system contains SSCs that are ITS; it does not 
contain SSCs or natural or engineered barriers that are ITWI. The safety category of this system 
is SC (BSC 2005a [DIRS 171668], Attachment A). Table A-II in Appendix A presents the 
nuclear safety design bases associated with the Surface Nuclear HVAC System. 
6.6.2.26 Waste Package Closure System 
As established by Categorization of Event Sequences for License Application (BSC 2005b [DIRS 
171429], Section 7), there are no Category 1 or Category 2 event sequences that require SSCs in 
this system to perform prevention or mitigation functions. Therefore, this system consists of no 
SSCs that are ITS or SSCs or natural or engineered barriers that are ITWI. The safety category 
of this system is Non-SC (BSC 2005a [DIRS 171668], Attachment A). There are no nuclear 
safety design bases associated with the Waste Package Closure System. 
6.7 OTHER ITEMS IMPORTANT TO SAFETY 
The transportation casks, standardized U.S. Department of Energy (DOE) SNF disposable 
canisters, DOE HLW canisters, DOE multicanister overpacks (MCOs), the naval SNF canisters, 
and the dual-purpose canisters (DPCs) are ITS, but are not a part of the repository architecture 
(Lucas 2004 [DIRS 170073]). In the Categorization of Event Sequences for License Application 
analysis (BSC 2005b [DIRS 171429], Section 7) it was established that a breach of a 
transportation cask with impact limiters installed is a Beyond Category 2 event sequence based 
on the 10 CFR 71.55 [DIRS 104091] and 10 CFR 71.73 [DIRS 104091] design requirements for 
the transportation casks (BSC 2005b [DIRS 171429], Section 7). A breach of a DOE MCO or a 
standardized DOE SNF canister is a Beyond Category 2 event sequence based on the acceptance 
requirements of the Waste Acceptance System Requirements Document (DOE 2002 [DIRS 
158873], Section 4.3.7). A breach of the DOE HLW canister, naval SNF canister, or DPC as a 
result of a credible fire is a Beyond Category 2 event sequence (BSC 2004c [DIRS 171488], 
Section 5). 
To ensure that transportation casks with impact limiters installed and that standardized DOE 
SNF canisters are capable of withstanding drops within the design basis without breach, they 
have been designated as ITS and classified as SC (BSC 2005a [DIRS 171668], Attachment A). 
Table A-II in Appendix A presents the nuclear safety design bases associated with transportation 

000-30R-MGR0-00400-000-001 17 March 2005 
casks, DOE HLW canisters, DOE MCOs, naval SNF canisters, standardized DOE SNF canisters, 
and DPCs. 
7. CONCLUSIONS 
The 10 CFR 63.2 design bases (nuclear safety design bases) selected in this report using the 
methodology presented in Section 6.1 are listed in Appendix A. These nuclear safety design 
bases are used as input to the design of the repository. These output results are reasonable 
compared to the input and are suitable for their intended use. As the design of the repository 
proceeds and further event sequences and consequence analyses of hazards are performed, this 
report will be reviewed for impact and revised as necessary. 
8. REFERENCES 
8.1 DOCUMENTS CITED 
[DIRS 171470] 
BSC (Bechtel SAIC Company) 2004a. Seismic Analysis for Preclosure Safety. 000-00CMGR0-
00700-000-00B. Las Vegas, Nevada: Bechtel SAIC Company. ACC: 
ENG.20041216.0031. 
[DIRS 167266] 
BSC 2004b. Monitored Geologic Repository External Events Hazards Screening Analysis. 000- 
00C-MGR0-00500-000-00A. Las Vegas, Nevada: Bechtel SAIC Company. ACC: 
ENG.20040712.0004. 
[DIRS 171488] 
BSC 2004c. Fire-Induced Event Sequence Analysis. 000-00C-MGR0-01300-000-00B. Las 
Vegas, Nevada: Bechtel SAIC Company. ACC: ENG.20041208.0001. 
[DIRS 171471] 
BSC 2004d. Extreme Wind/Tornado/Tornado Missile Hazard Analysis. 000-00C-WHS0- 
00100-000-00B. Las Vegas, Nevada: Bechtel SAIC Company. ACC: ENG.20041105.0001. 
[DIRS 167232] 
BSC 2004e. Dry Transfer Facility Description Document. 110-3YD-CD00-00100-000-000. 
Las Vegas, Nevada: Bechtel SAIC Company. ACC: ENG.20040712.0002. 
[DIRS 171490] 
BSC 2004f. Reliability Analysis of the Electrical Power Distribution System to Selected 
Portions of the Nuclear HVAC System. 100-PSA-EE00-00100-000-00A. Las Vegas, Nevada: 
Bechtel SAIC Company. ACC: ENG.20041216.0029. 
[DIRS 171599] 
BSC 2004g. Project Design Criteria Document. 000-3DR-MGR0-00100-000-003. Las Vegas, 
Nevada: Bechtel SAIC Company. ACC: ENG.20041124.0001. 

000-30R-MGR0-00400-000-001 18 March 2005 
[DIRS 171668] 
BSC 2005a. Safety Classification of SSCs and Barriers. 000-00C-MGR0-01000-000-001. Las 
Vegas, Nevada: Bechtel SAIC Company. ENG.20050215.0007. 
[DIRS 171429] 
BSC 2005b. Categorization of Event Sequences for License Application. 000-00C-MGR0- 
00800-000-00B. Las Vegas, Nevada: Bechtel SAIC Company. ACC: MOL.20050301.0445. 
[DIRS 171607] 
BSC 2005c. Preclosure Consequence Analyses for License Application. 000-00C-MGR0- 
00900-000-00B. Las Vegas, Nevada: Bechtel SAIC Company. ACC: ENG.20050112.0003. 
[DIRS 171786] 
BSC 2005d. Frequency Analysis of Aircraft Hazards for License Application. 000-00C-WHS0- 
00200-000-00B. Las Vegas, Nevada: Bechtel SAIC Company. ACC: ENG.20050214.0009. 
[DIRS 171793] 
Cogema 2004. SNF Aging System Safety Study. COGEMA-C0115-RP-04-005, Rev. 1. Las 
Vegas, Nevada: Cogema. ACC: ENG.20040917.0002. 
[DIRS 158873] 
DOE (U.S. Department of Energy) 2002. Waste Acceptance System Requirements Document. 
DOE/RW-0351, Rev. 4. Washington, D.C.: U.S. Department of Energy, Office of Civilian 
Radioactive Waste Management. ACC: MOL.20020326.0056. 
[DIRS 171539] 
DOE 2004. Quality Assurance Requirements and Description. DOE/RW-0333P, Rev. 16. 
Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste 
Management. ACC: DOC.20040907.0002. 
[DIRS 170073] 
Lucas, L. 2004. "Facility, Equipment and System Names for Use in the SAR." Interoffice 
memorandum from L. Lucas (BSC) to M.R. Bryan, June 24, 2004, 0521041674. ACC: 
MOL.20040625.0028. 
8.2 CODES, STANDARDS, AND REGULATIONS 
[DIRS 156605] 
10 CFR 63. Energy: Disposal of High-Level Radioactive Wastes in a Geologic Repository at 
Yucca Mountain, Nevada. Readily available. 
[DIRS 104091] 
10 CFR 71. Energy: Packaging and Transportation of Radioactive Material. Readily available. 

000-30R-MGR0-00400-000-001 19 March 2005 
8.3 PROCEDURES 
AP-3.13Q, Rev. 3, ICN 3. Design Control. ACC: DOC.20040202.0006. 
LP-3.11Q-BSC, Rev. 0, ICN 2. Technical Reports. ACC: DOC.20050215.0009. 
LP-3.15Q-BSC, Rev. 0, ICN 0. Managing Technical Product Inputs. ACC: 
DOC.20050113.0002. 
LP-SI.11Q-BSC, Rev. 0, ICN 1. Software Management. ACC: DOC.20040015.0008. 

000-30R-MGR0-00400-000-001 20 March 2005 
INTENTIONALLY LEFT BLANK 

000-30R-MGR0-00400-000-001 A-1 March 2005 APPENDIX A 
Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Balance of Plant Facilities 
Administration, 
Security, Utility, 
Emergency 
Response, Offsite, 
Materials and 
Consumables, Fire 
Water, Maintenance 
and Repair, 
Generator, 
Switchgear, 
Construction 
Support, Central 
Control Center, and 
Transportation 
Facilities 
Structure N/A Non-SC Not applicable. None of the SSC functions associated with these facilities are credited 
for the prevention or mitigation of an event sequence. 
Canister Handling Facility 
CHF Structure ITS SC  The structure shall: 
(1) be designed for the loads associated with a design basis extreme wind speed. 
(BSC 2004g Section 6.1.1.2 and BSC 2004d Section 9) 
(2) be designed for the loads associated with a design basis tornado maximum 
wind speed with a corresponding pressure drop and rate of pressure drop. 
(BSC 2004g Section 4.2.2.3.7 and BSC 2004d Section 9) 
(3) not allow the penetration of Spectrum II tornado missiles, except for the 
entrance and exit vestibules and the steel structures on top of the building. 
(BSC 2004d Sections 6.4.4.1.1 and 9) 
 The roof of the structure shall be designed for the loads associated with the 
maximum observed hourly precipitation event (with a 100-year return period). (BSC 
2004g Section 6.1.1.1.2 and BSC 2005b Section 4.3.2) 

000-30R-MGR0-00400-000-001 A-2 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
CHF (continued) 
Structure (continued) ITS SC  Facilities that could be damaged by flooding shall be located above the probable 
maximum flood elevation or must be appropriately protected from the probable 
maximum flood. (BSC 2004g Section 6.1.2.1 and BSC 2005b Section 4.3.2) 
 The structure shall be designed such that storm water runoff from the maximum 
observed hourly precipitation event (with a 100-year return period) does not enter the 
structure. (BSC 2004g Section 6.1.1.1.2 and BSC 2005b Section 4.3.2) 
 The roof of the structure shall be designed for the loads associated with a volcanic 
ash fall. (BSC 2004b Section 6.4.53) 
 Flooding of areas of the structure where moderators are controlled shall be 
precluded by passive design features such as drains, flood control channels, curbs, 
elevated processing areas, and walls. (BSC 2005b Section 5.1.1.21) 
 The CHF structure shall be designed for loading conditions associated with a 
DBGM-2 seismic event. In addition, it shall be demonstrated that the CHF structure 
has sufficient seismic design margin to ensure that a no structural collapse safety 
function3 is maintained for loading conditions associated with a BDBGM seismic event. 
(BSC 2004a Table IV-1) 
 The exterior walls of the CHF shall not be penetrated or collapsed by an F-16 
aircraft crashing into an exterior wall at the speed corresponding to the 95th percentile 
from a probability distribution estimated from historical F-16 crashes. (BSC 2005d 
Section 5.1.5) 
 Surfaces in the load paths through which WPs, standardized DOE SNF canisters, 
DOE MCOs, naval SNF canisters, DPCs, transportation casks, horizontal transfer 
casks, or site-specific casks are transferred by crane shall be kept free of structures, 
such as post and curbs, that could puncture a container in the event of a drop. (BSC 
2005b Section 5.1.1.40) 
 The severity of potential fires shall not jeopardize the structural integrity of structures 
where SNF/HLW is present. (BSC 2004c Section 5.1.3.2) 
 Portions, parts, subparts, or subsystems of a non-ITS SSC, which upon failure could 
adversely interact with an ITS SSC and prevent its safety function from being 
performed, shall be classified as ITS or redesigned to eliminate the potential 
unacceptable interaction with the identified ITS SSC. For seismic interactions, 
portions, parts, subparts, or subsystems of an otherwise non-ITS SSC shall be 
classified as ITS and shall be designed to the same seismic DBGM as the ITS SSCs 
subjected to the potential unacceptable interaction, or the non-ITS SSC may be 
redesigned to eliminate the potential unacceptable interaction. (BSC 2005b Section 
5.1.1.37) 

000-30R-MGR0-00400-000-001 A-3 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Rails for Trolleys, WP 
Transporters, and 
SRTCs 
ITS SC  The rails and rail anchorages within the structure shall be designed for loading 
conditions associated with a DBGM-2 seismic event. In addition, it shall be 
demonstrated that the rails and rail anchorages have sufficient seismic design margin 
to ensure that a no derailment safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
CHF (continued) 
Permanent Shielding 
(including shield doors, 
shield view ports, and 
viewing windows) 
ITS 
SC 
 The CHF permanent shielding (including shield doors, shield view ports, and viewing 
windows) shall be designed for loading conditions associated with a DBGM-1 seismic 
event to demonstrate sufficient seismic design margin to ensure that a shielding 
integrity remains intact safety function3 is maintained. (BSC 2004a Table IV-1) 
 Closure of airlock doors, shield doors, or other applicable doors on a trolley, SRTC, 
WP transporter, or other conveyance shall not cause a tipover of the conveyance or 
cause the conveyance to drop its load. (BSC 2005b Section 5.1.1.13) 
 Radiation exposure to workers due to inadvertent actuation of doors or pit protective 
covers shall be precluded such that this is not a Category 1 event. (BSC 2005b 
Section 5.1.1.57) 
Dry Transfer Facility 
DTF Structure ITS SC  The structure shall: 
(1) be designed for the loads associated with a design basis extreme wind speed. 
(BSC 2004g Section 6.1.1.2 and BSC 2004d Section 9) 
(2) be designed for the loads associated with a design basis tornado maximum 
wind speed with a corresponding pressure drop and rate of pressure drop. 
(BSC 2004g Section 4.2.2.3.7 and BSC 2004d Section 9) 
(3) not allow the penetration of Spectrum II tornado missiles, except for the 
entrance and exit vestibules and the steel structures on the DTF roof. (BSC 
2004d Sections 6.4.4.1.1 and 9) 
 The roof of the structure shall be designed for the loads associated with the 
maximum observed hourly precipitation event (with a 100-year return period). (BSC 
2004g Section 6.1.1.1.2 and BSC 2005b Section 4.3.2) 
 Facilities that could be damaged by flooding shall be located above the probable 
maximum flood elevation or must be appropriately protected from the probable 
maximum flood. (BSC 2004g Section 6.1.2.1 and BSC 2005b Section 4.3.2) 

000-30R-MGR0-00400-000-001 A-4 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
DTF (continued) Structure (continued) ITS SC  The structure shall be designed such that storm water runoff from the maximum 
observed hourly precipitation event (with a 100-year return period) does not enter the 
structure. (BSC 2004g Section 6.1.1.1.2 and BSC 2005b Section 4.3.2) 
 The roof of the structure shall be designed for the loads associated with a volcanic 
ash fall. (BSC 2004b Section 6.4.53) 
 Flooding of areas of the structure where moderators are controlled shall be 
precluded by passive design features such as drains, flood control channels, curbs, 
elevated processing areas, and walls. (BSC 2005b Section 5.1.1.21) 
 The DTF structure shall be designed for loading conditions associated with a 
DBGM-2 seismic event. In addition, an analysis shall demonstrate that the DTF 
structure has sufficient seismic design margin to ensure that a no structural collapse 
safety function3 is maintained for loading conditions associated with a BDBGM seismic 
event. (BSC 2004a Table IV-1) 
 The exterior walls of the DTF shall not be penetrated or collapsed by an F-16 aircraft 
crashing into an exterior wall at the speed corresponding to the 95th percentile from a 
probability distribution estimated from historical F-16 crashes. (BSC 2005d Section 
5.1.5) 
 Surfaces in the load paths through which WPs, standardized DOE SNF canisters, 
DOE MCOs, naval SNF canisters, DPCs, transportation casks, horizontal transfer 
casks, or site-specific casks are transferred by crane shall be kept free of structures, 
such as post and curbs, that could puncture a container in the event of a drop. (BSC 
2005b Section 5.1.1.40) 
 The severity of potential fires shall not jeopardize the structural integrity of structures 
where SNF/HLW is present. (BSC 2004c Section 5.1.3.2) 
 Portions, parts, subparts, or subsystems of a non-ITS SSC, which upon failure could 
adversely interact with an ITS SSC and prevent its safety function from being 
performed, shall be classified as ITS or redesigned to eliminate the potential 
unacceptable interaction with the identified ITS SSC. For seismic interactions, 
portions, parts, subparts, or subsystems of an otherwise non-ITS SSC shall be 
classified as ITS and shall be designed to the same seismic DBGM as the ITS SSCs 
subjected to the potential unacceptable interaction, or the non-ITS SSC may be 
redesigned to eliminate the potential unacceptable interaction. (BSC 2005b Section 
5.1.1.37) 

000-30R-MGR0-00400-000-001 A-5 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Remediation Pool ITS SC  The remediation pool structure shall be designed for loading conditions associated 
with a DBGM-2 seismic event. In addition, an analysis shall demonstrate that the 
remediation pool structure has sufficient seismic design margin to ensure that a no 
failure safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 The pool and pool area in the remediation system shall ensure that any lost water 
can be replaced with make-up water until the cause of the loss is corrected or waste 
forms are removed from the pool. The minimum available rate of make-up water shall 
be sufficient to replenish evaporation and the maximum potential leakage in the event 
of the failure of the recirculating cooling system over the minimum time period required 
to remove waste forms from the pool. The rate shall also be sufficient to prevent the 
uncovering of the waste forms over this same period. (BSC 2005b Section 5.1.2.5) 
Rail Systems for 
Trolleys, WP 
Transporters, and 
SRTCs 
ITS SC  The rails and rail anchorages within the structure shall be designed for loading 
conditions associated with a DBGM-2 seismic event. In addition, it shall be 
demonstrated that the rails and rail anchorages have sufficient seismic design margin 
to ensure that a no derailment safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
DTF (continued) 
Permanent Shielding 
(including shield doors, 
shield view ports, and 
viewing windows) 
ITS SC  The DTF permanent shielding (including shield doors, shield view ports, and viewing 
windows) shall be designed for loading conditions associated with a DBGM-1 seismic 
event to demonstrate sufficient seismic design margin to ensure that a shielding 
integrity remains intact safety function3 is maintained. (BSC 2004a Table IV-1) 
 Closure of airlock doors, shield doors, or other applicable doors on a trolley, SRTC, 
site-specific cask transporter, WP transporter, other conveyance, or transportation 
cask or site-specific cask suspended from an overhead crane shall not cause a tipover 
of the conveyance or cause the conveyance or crane to drop its load. (BSC 2005b 
Section 5.1.1.13) 
 Radiation exposure to workers due to inadvertent actuation of doors shall be 
precluded such that this is not a Category 1 event. (BSC 2005b Section 5.1.1.57) 
Fuel Handling Facility 
FHF Structure ITS SC  The structure shall: 
(1) be designed for the loads associated with a design basis extreme wind speed. 
(BSC 2004g Section 6.1.1.2 and BSC 2004d Section 9) 

000-30R-MGR0-00400-000-001 A-6 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
FHF (continued) 
Structure (continued) ITS SC  The structure shall (continued): 
(2) be designed for the loads associated with a design basis tornado maximum 
wind speed with a corresponding pressure drop and rate of pressure drop. 
(BSC 2004g Section 4.2.2.3.7 and BSC 2004d Section 9) 
(3) not allow the penetration of Spectrum II tornado missiles, except for the 
entrance and exit vestibules and the steel structures on the FHF roof. (BSC 
2004d Sections 6.4.4.1.1 and 9) 
 The roof of the structure shall be designed for the loads associated with the 
maximum observed hourly precipitation event (with a 100-year return period). (BSC 
2004g Section 6.1.1.1.2 and BSC 2005b Section 4.3.2) 
 Facilities that could be damaged by flooding shall be located above the probable 
maximum flood elevation or must be appropriately protected from the probable 
maximum flood. (BSC 2004g Section 6.1.2.1 and BSC 2005b Section 4.3.2) 
 The structure shall be designed such that storm water runoff from the maximum 
observed hourly precipitation event (with a 100-year return period) does not enter the 
structure. (BSC 2004g Section 6.1.1.1.2 and BSC 2005b Section 4.3.2) 
 The roof of the structure shall be designed for the loads associated with a volcanic 
ash fall. (BSC 2004b Section 6.4.53) 
 Flooding of areas of the structure where moderators are controlled shall be 
precluded by passive design features such as drains, flood control channels, curbs, 
elevated processing areas, and walls. (BSC 2005b Section 5.1.1.21) 
 The FHF structure shall be designed for loading conditions associated with a 
DBGM-2 seismic event. In addition, an analysis shall demonstrate that the FHF 
structure has sufficient design margin to ensure that a no structural collapse safety 
function3 is maintained for loading conditions associated with a BDBGM seismic event. 
(BSC 2004a Table IV-1) 
 The exterior walls of the FHF shall not be penetrated or collapsed by an F-16 aircraft 
crashing into an exterior wall at the speed corresponding to the 95th percentile from a 
probability distribution estimated from historical F-16 crashes. (BSC 2005d Section 
5.1.5) 
 Surfaces in the load paths through which WPs, standardized DOE SNF canisters, 
naval SNF canisters, DPCs, transportation casks, or site-specific casks are transferred 
by crane shall be kept free of structures, such as post and curbs, that could puncture a 
container in the event of a drop. (BSC 2005b Section 5.1.1.40) 
 The severity of potential fires shall not jeopardize the structural integrity of structures 
where SNF/HLW is present. (BSC 2004c Section 5.1.3.2) 

000-30R-MGR0-00400-000-001 A-7 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Structure (continued) ITS SC  Portions, parts, subparts, or subsystems of a non-ITS SSC, which upon failure could 
adversely interact with an ITS SSC and prevent its safety function from being 
performed, shall be classified as ITS or redesigned to eliminate the potential 
unacceptable interaction with the identified ITS SSC. For seismic interactions, 
portions, parts, subparts, or subsystems of an otherwise non-ITS SSC shall be 
classified as ITS and shall be designed to the same seismic DBGM as the ITS SSCs 
subjected to the potential unacceptable interaction, or the non-ITS SSC may be 
redesigned to eliminate the potential unacceptable interaction. (BSC 2005b Section 
5.1.1.37) 
Rail Systems for 
Trolleys and the WP 
Transporter 
ITS SC  The rails and rail anchorages within the structure shall be designed for loading 
conditions associated with a DBGM-2 seismic event. In addition, it shall be 
demonstrated that the rails and rail anchorages have sufficient seismic design margin 
to ensure that a no derailment safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
FHF (continued) 
Permanent Shielding 
(including shield doors, 
shield view ports, and 
viewing windows) 
ITS SC  Closure of airlock doors, shield doors, or other applicable doors on a trolley, SRTC, 
WP transporter, or other conveyance, or a site-specific cask suspended from the 
vestibule gantry crane, shall not cause a tipover of the conveyance or cause the 
conveyance or crane to drop its load. (BSC 2005b Section 5.1.1.13) 
 The FHF permanent shielding (including shield doors, shield view ports, and viewing 
windows) shall be designed for loading conditions associated with a DBGM-1 seismic 
event to demonstrate sufficient seismic design margin to ensure that a shielding 
integrity remains intact safety function3 is maintained. (BSC 2004a Table IV-1) 
 Radiation exposure to workers due to inadvertent actuation of doors shall be 
precluded such that this is not a Category 1 event. (BSC 2005b Section 5.1.1.57) 
Subsurface Facility 
Subsurface Facility Rails N/A Non-SC Not Applicable. None of the SSC functions associated with this subsystem are 
credited for the prevention or mitigation of an event sequence. 

000-30R-MGR0-00400-000-001 A-8 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Size and Layout of 
Drifts 
ITS 
ITWI 
SC  The design of the subsurface facility shall ensure that the size and layout of the 
emplacement drifts are consistent with the drift and rockfall modeling, including the 
evaluation of the characteristics of the credible bounding rockfalls. (BSC 2005b 
Section 6.3.6.1.20) 
 Portions, parts, subparts, or subsystems of a non-ITS SSC, which upon failure could 
adversely interact with an ITS SSC and prevent its safety function from being 
performed, shall be classified as ITS or redesigned to eliminate the potential 
unacceptable interaction with the identified ITS SSC. For seismic interactions, 
portions, parts, subparts, or subsystems of an otherwise non-ITS SSC shall be 
classified as ITS and shall be designed to the same seismic DBGM as the ITS SSCs 
subjected to the potential unacceptable interaction, or the non-ITS SSC may be 
redesigned to eliminate the potential unacceptable interaction. (BSC 2005b Section 
5.1.1.37) 
Nonemplacement 
Openings 
ITS SC  The design shall ensure size and layout of nonemplacement openings are 
consistent with drift and rockfall modeling. (BSC 2005b Section 6.3.6.1.20) 
 The ramp, portals, shafts, and shaft collar areas shall be protected from water inflow 
as a result of the probable maximum flood. (BSC 2005b Section 4.3.2) 
 Portions, parts, subparts, or subsystems of a non-ITS SSC, which upon failure could 
adversely interact with an ITS SSC and prevent its safety function from being 
performed, shall be classified as ITS or redesigned to eliminate the potential 
unacceptable interaction with the identified ITS SSC. For seismic interactions, 
portions, parts, subparts, or subsystems of an otherwise non-ITS SSC shall be 
classified as ITS and shall be designed to the same seismic DBGM as the ITS SSCs 
subjected to the potential unacceptable interaction, or the non-ITS SSC may be 
redesigned to eliminate the potential unacceptable interaction. (BSC 2005b Section 
5.1.1.37) 
Subsurface Facility 
(continued) 
Ground Support for 
Nonemplacement 
Openings 
N/A Non-SC Not Applicable. None of the SSC functions associated with this subsystem are 
credited for the prevention or mitigation of a preclosure event sequence. 
Subsurface Facility 
Emplacement Drift 
Emplacement Drift 
Excavated Opening 
ITS 
ITWI 
SC  The design shall ensure size and layout of emplacement drifts are consistent with 
drift and rockfall modeling. (BSC 2005b Section 6.3.6.1.20) 

000-30R-MGR0-00400-000-001 A-9 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Emplacement Drift 
Ground Support 
N/A Non-SC Not Applicable. None of the SSC functions associated with this subsystem are 
credited for the prevention or mitigation of a preclosure event sequence. 
Drift Invert (Steel) N/A Non-SC Not Applicable. None of the SSC functions associated with this subsystem are 
credited for the prevention or mitigation of a preclosure event sequence. 
Drift Invert (Ballast) ITWI SC None of the SSC functions associated with this subsystem are credited for the 
prevention or mitigation of a preclosure event sequence. 
WP Emplacement 
Pallet 
ITS 
ITWI 
SC  The WP emplacement pallet shall be designed for loading conditions associated 
with a DBGM-2 seismic event and to demonstrate sufficient seismic design margin to 
ensure that a no failure safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
Drip Shield ITWI SC None of the SSC functions associated with this subsystem are credited for the 
prevention or mitigation of a preclosure event sequence. 
Subsurface Facility 
Emplacement Drift 
(continued) 
Drip Shield 
Emplacement Gantry 
N/A Non-SC Not Applicable. None of the functions associated with this SSC are credited for the 
prevention or mitigation of a preclosure event sequence. 
Thermal Management N/A Non-SC Not Applicable. None of the functions associated with this SSC are credited for the 
prevention or mitigation of a preclosure event sequence. 
Decommissioning and 
Decontamination 
N/A Non-SC Not Applicable. None of the functions associated with this SSC are credited for the 
prevention or mitigation of a preclosure event sequence. 
Closure (includes 
keyways and backfill in 
access mains and 
exhaust mains; 
ventilation shafts and 
raises, and borehole 
seals) 
ITWI SC None of the SSC functions associated with this subsystem are credited for the 
prevention or mitigation of a preclosure event sequence. 
Subsurface Facility 
Postemplacement 
Performance 
Confirmation 
N/A Non-SC Not Applicable. None of the functions associated with this SSC are credited for the 
prevention or mitigation of a preclosure event sequence. 

000-30R-MGR0-00400-000-001 A-10 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Subsurface Facility 
Subsurface 
Development 
Excavation N/A Non-SC Not Applicable. None of the SSC functions associated with this subsystem are 
credited for the prevention or mitigation of a preclosure event sequence. 
Transportation Cask Receipt/Return Facility 
Cask Receipt and 
Return Area 
Structure ITS SC  The load carrying members of the structure shall: 
(1) be designed for the loads associated with a design basis extreme wind speed. 
(BSC 2004g Section 6.1.1.2 and BSC 2004d Section 9) 
(2) be designed for the loads associated with a design basis tornado maximum 
wind speed with a corresponding pressure drop and rate of pressure drop. 
(BSC 2004g Section 4.2.2.3.7 and BSC 2004d Section 9) 
(3) not allow the penetration of Spectrum II tornado missiles, except for the 
entrance and exit vestibules. (BSC 2004d Section 9) 
 The roof of the structure shall be designed for the loads associated with the 
maximum observed hourly precipitation event (with a 100-year return period). (BSC 
2004g Section 6.1.1.1.2 and BSC 2005b Section 4.3.2) 
 Facilities that could be damaged by flooding shall be located above the probable 
maximum flood elevation or must be appropriately protected from the probable 
maximum flood. (BSC 2004g Section 6.1.2.1 and BSC 2005b Section 4.3.2) 
 The structure shall be designed such that storm water runoff from the maximum 
observed hourly precipitation event (with a 100-year return period) does not enter the 
structure. (BSC 2004g Section 6.1.1.1.2 and BSC 2005b Section 4.3.2) 
 The roof of the structure shall be designed for the loads associated with a volcanic 
ash fall. (BSC 2004b Section 6.4.53) 
 The TCRRF load-carrying members shall be designed for loading conditions 
associated with a DBGM-2 seismic event. In addition, an analysis shall demonstrate 
that the TCRRF load carrying members have sufficient seismic design margin to 
ensure that a no structural collapse safety function3 is maintained for loading 
conditions associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The severity of potential fires shall not jeopardize the structural integrity of structures 
where SNF/HLW is present. (BSC 2004c Section 5.1.3.2) 

000-30R-MGR0-00400-000-001 A-11 March 2005 Table A-I. Nuclear Safety Design Bases of Facilities 
Facility, System, or 
Subsystem 
Component or 
Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Receipt and 
Return Area 
(continued) 
Structure (continued) ITS SC  Portions, parts, subparts, or subsystems of a non-ITS SSC, which upon failure could 
adversely interact with an ITS SSC and prevent its safety function from being 
performed, shall be classified as ITS or redesigned to eliminate the potential 
unacceptable interaction with the identified ITS SSC. For seismic interactions, 
portions, parts, subparts, or subsystems of an otherwise non-ITS SSC shall be 
classified as ITS and shall be designed to the same seismic DBGM as the ITS SSCs 
subjected to the potential unacceptable interaction, or the non-ITS SSC may be 
redesigned to eliminate the potential unacceptable interaction. (BSC 2005b Section 
5.1.1.37) 
Transportation Cask 
Buffer Area 
Structure N/A Non-SC Not Applicable. None of the SSC functions associated with this subsystem are 
credited for the prevention or mitigation of an event sequence. 
Warehouse & Non-Nuclear Receipt Facility 
WNNRF 
Structure N/A Non-SC Not Applicable. No function of this facility is credited for the prevention or mitigation of 
an event sequence. 
NOTES: BDBGM = beyond design basis ground motion; CHF = Canister Handling Facility; DBGM = design basis ground motion; DTF = Dry Transfer Facility; FHF 
= Fuel Handling Facility; ITS = important to safety; SC = safety category; SRTC = site rail transfer cart; SSC = structure, system, or component; SSCs = structures, 
systems, and components; TCRRF = Transportation Cask Receipt and Return Facility; WNNRF = Warehouse and Non-Nuclear Receipt Facility. 

000-30R-MGR0-00400-000-001 A-12 March 2005 
INTENTIONALLY LEFT BLANK 

000-30R-MGR0-00400-000-001 A-13 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask/MSC/WP Preparation System 
Cask Preparation Cask Handling 
Crane (CHF); 
200 ton 
ITS SC  The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limits for the casks handled by this crane are provided in Table C-1 in 
Appendix C, including the following: 
1. Transportation casks without impact limiters containing naval SNF canisters. 
2. Transportation casks without impact limiters containing standardized DOE SNF 
canisters. 
3. Transportation casks without impact limiters containing DOE HLW canisters and 
commercial SNF in vertical DPCs. 
4. Transportation casks without impact limiters containing a DOE MCO. 
5. Site specific casks with vertical DPCs. 
 This crane and its rigging shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
a no drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a transportation cask or 
site-specific cask. (BSC 2005b Section 5.1.1.19) 

000-30R-MGR0-00400-000-001 A-14 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Handling 
Crane (CHF); 
200 ton 
(continued) 
ITS SC  This crane shall not be capable of exerting sufficient force during transfer to breach a 
cask as the result of attempts to overcome mechanical constraints. (BSC 2005b Section 
5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Cask Preparation 
(continued) 
Cask Handling 
Crane (DTF); 
200 ton 
ITS SC  The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limits for the casks handled by this crane are provided in Table C-1 in 
Appendix C; these casks include: 
1. Transportation casks without impact limiters containing standardized DOE SNF 
canisters, DOE HLW canisters, commercial SNF, or vertical or horizontal DPCs. 
2. Site-specific casks containing commercial SNF or vertical or horizontal DPCs. 
3. Transportation casks without impact limiters containing a DOE MCO. 
 This crane and its rigging shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
a no drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-15 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Handling 
Crane (DTF); 
200 ton 
(continued) 
ITS 
SC 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a transportation cask or 
site-specific cask. (BSC 2005b Section 5.1.1.19) 
 This crane shall not be capable of exerting sufficient force during transfer to breach a 
cask as the result of attempts to overcome mechanical constraints. (BSC 2005b Section 
5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Cask Preparation 
(continued) 
Naval Cask 
Handling Crane 
(DTF); 200 ton 
ITS SC  The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limit for transportation casks without impact limiters containing a naval 
SNF canister is provided in Table C-1 in Appendix C. 
 This crane and its rigging shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
a no drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-16 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Naval Cask 
Handling Crane 
(DTF); 200 ton 
(continued) 
ITS SC  This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a naval SNF 
transportation cask. (BSC 2005b Section 5.1.1.19) 
 This crane shall not be capable of exerting sufficient force during transfer to breach a 
naval SNF transportation cask as the result of attempts to overcome mechanical 
constraints. (BSC 2005b Section 5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Crane Lifting 
Yokes 
ITS SC  Crane lifting yokes shall be designed for loading conditions associated with a DBGM-2 
seismic event and to demonstrate sufficient seismic design margin to ensure that a no 
drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
Cask Preparation 
(continued) 
Turntables (DTF) ITS SC  Turntables shall be designed for stability and prevention of a tipover of any waste 
container on the table for loading conditions associated with a DBGM-2 seismic event. In 
addition, an analysis shall demonstrate that the turntable has sufficient seismic design 
margin to ensure that a no tipover safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of machinery that handles or transports SNF/HLW shall not reach a level that would cause 
a drop of a cask while on a turntable. (BSC 2004c Section 5.1.3.1) 
 A tipover and breach of a cask while on a turntable that handles SNF/HLW due to 
uncontrolled movements produced by a loss of power or a spurious signal caused by a fire 
shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 

000-30R-MGR0-00400-000-001 A-17 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Docking 
Rings (DTF, FHF) 
N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
Cask Pit, 
Pedestal; 
(CHF) 
N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
Cask Pit 
Protective Cover 
(CHF) 
ITS SC  The cask pit protective cover shall be designed for loading conditions associated with a 
DBGM-1 seismic event and demonstrate sufficient seismic design margin to a shielding 
integrity remains intact safety function3. (BSC 2004a Table IV-1) 
 The cask pit protective cover shall be sturdy enough to prevent a WP or site-specific 
cask that is dropped on the pit cover from penetrating the pit cover and falling into the pit. 
(BSC 2005b Section 5.1.6.6) 
 Radiation exposure to workers due to inadvertent actuation of the pit protective covers 
shall be precluded such that this is not a Category 1 event. (BSC 2005b Section 5.1.1.57) 
Pit Crush Pads 
(CHF) 
ITS SC  Crush pads shall limit the impact energy of a dropped canister, cask, or WP to be less 
than or equal to the impact energy associated with a drop of a canister, cask, or WP onto 
an unyielding surface from their maximum specified drop height for the canister, cask, or 
WP6. (BSC 2005b Section 5.1.1.18) 
Cask Preparation 
(continued) 
Vestibule Gantry 
Crane 
(FHF); 200 ton 
ITS SC  The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 

000-30R-MGR0-00400-000-001 A-18 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Vestibule Gantry 
Crane 
(FHF); 200 ton 
(continued) 
ITS SC  The lift height limits for the transportation casks handled by this crane are provided in 
Table C-1 in Appendix C; these casks include: 
1. Transportation cask without impact limiters containing naval SNF canisters. 
2. Transportation cask without impact limiters containing standardized DOE SNF 
canisters or DOE HLW canisters. 
3. Transportation cask without impact limiters or site-specific cask containing 
commercial SNF or DPCs. 
 This crane and its rigging shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
a no drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a transportation cask or 
site-specific cask. (BSC 2005b Section 5.1.1.19) 
 This crane shall not be capable of exerting sufficient force during transfer to breach a 
cask, WP, or site-specific cask as the result of attempts to overcome mechanical 
constraints. (BSC 2005b Section 5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Cask Preparation 
(continued) 
Main Transfer 
Room Crane 
(FHF); 200 ton 
ITS SC  The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 The probability of dropping handling equipment from a crane onto a canister shall be 
less than or equal to 1  10-5 for each canister transferred. (BSC 2005b Section 5.1.1.11) 

000-30R-MGR0-00400-000-001 A-19 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Preparation 
(continued) 
Main Transfer 
Room Crane 
(FHF); 200 ton 
(continued) 
ITS SC  Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limits for the transportation casks, canisters, and WPs handled by this 
crane are provided in Table C-1 in Appendix C; these casks, canisters, and WPs include: 
1. Transportation casks without impact limiters, including casks containing naval 
SNF canisters, DOE HLW canisters, standardized DOE SNF canisters, vertical 
DPCs, or commercial SNF. 
2. Site-specific casks containing commercial SNF or vertical DPCs. 
3. Naval SNF canisters. 
4. DOE HLW canisters, standardized DOE SNF canisters, and vertical DPCs. 
5. Unsealed, loaded WPs. 
6. Sealed WPs. 
7. Sealed WPs in a horizontal orientation on an emplacement pallet. 
 This crane and its rigging shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
a no drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a loaded sealed sitespecific 
cask, a loaded sealed WP, a DOE HLW canister, a standardized DOE SNF 
canister, a naval SNF canister, or a DPC. (BSC 2005b Section 5.1.1.19) 
 This crane shall not be capable of exerting sufficient force to breach a cask, WP, 
canister, or site-specific cask during transfer as the result of attempts to overcome 
mechanical constraints. (BSC 2005b Section 5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 

000-30R-MGR0-00400-000-001 A-20 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Mobile Elevating 
Platform 
N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
Pit Movable 
Platforms (CHF) 
N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
Cask Preparation 
(continued) 
Cask Trolleys, 
Pedestals, and 
Hold-Down 
Devices (DTF, 
FHF) 
ITS SC  Upon a loss of power, this trolley shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this trolley shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.2) 
 The trolley system shall be designed for loading conditions associated with a DBGM-2 
seismic event to maintain trolley stability and prevent waste container slapdown. In 
addition, an analysis shall demonstrate that the trolley system has sufficient seismic design 
margin to ensure that a no slapdown safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 Pedestals and hold-down devices shall be designed for loading conditions associated 
with a DBGM-2 seismic event and to demonstrate sufficient seismic design margin to 
ensure that a no tipover safety function3 is maintained for loading conditions associated 
with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The trolley shall be designed with an inherent speed limit such that a collision at the 
trolley speed limit would not cause the trolley to drop its load. (BSC 2005b Section 
5.1.1.61) 
 Loaded transfer trolleys shall not derail or drop their loads. (BSC 2005b Section 
5.1.1.36) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the machinery that handles or transports SNF/HLW shall not reach a level that would 
make it drop its load. (BSC 2004c Section 5.1.3.1) 
 A tipover and breach of a cask while on machinery that transports SNF/HLW due to 
uncontrolled movements produced by a loss of power or a spurious signal caused by a fire 
shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 

000-30R-MGR0-00400-000-001 A-21 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP Trolleys, 
Pedestals, and 
Hold-Down 
Devices (DTF, 
CHF, FHF) 
ITS SC  Upon a loss of power, this trolley shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this trolley shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.2) 
 WP trolleys shall be designed for loading conditions associated with a DBGM-2 seismic 
event and to demonstrate sufficient seismic design margin to ensure that a no tipover 
safety function3 is maintained for loading conditions associated with a BDBGM seismic 
event. (BSC 2004a Table IV-1) 
 Pedestals and hold-down devices shall be designed for loading conditions associated 
with a DBGM-2 seismic event and to demonstrate sufficient seismic design margin to 
ensure that a no slapdown safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The trolley shall be designed with an inherent speed limit such that a collision at the 
trolley speed limit would not cause the trolley to drop its load. (BSC 2005b Section 
5.1.1.61) 
 Loaded transfer trolleys shall not derail or drop their loads. (BSC 2005b Section 
5.1.1.36) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the machinery that handles or transports SNF/HLW shall not reach a level that would 
make it drop its load. (BSC 2004c Section 5.1.3.1) 
 A tipover and breach of a cask while on machinery that transports SNF/HLW due to 
uncontrolled movements produced by a loss of power or a spurious signal caused by a fire 
shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
WP Preparation 
WP Docking Ring 
(DTF, FHF) 
N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 

000-30R-MGR0-00400-000-001 A-22 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP Preparation 
(continued) 
WP and Canister 
Handling Crane 
(CHF); 100 ton 
ITS SC  The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 The probability of dropping handling equipment from a crane onto a canister shall be 
less than or equal to 1  10-5 for each canister transferred. (BSC 2005b Section 5.1.1.11) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limits for the canisters and WPs handled by this crane are provided in 
Table C-1 in Appendix C; these canisters and WPs include: 
1. Naval SNF canisters, standardized DOE SNF canisters, DOE MCOs, or DOE 
HLW canisters. 
2. Vertical DPCs. 
3. Unsealed WPs containing standardized DOE SNF canisters, DOE HLW canisters, 
naval SNF canisters, or DOE MCOs. 
4. Sealed WPs containing standardized DOE SNF canisters, DOE HLW canisters, 
naval SNF canisters, or DOE MCOs. 
5. Sealed WPs in a horizontal orientation on an emplacement pallet. 
 This crane and its rigging shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
a no drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a loaded sealed WP, a 
standardized DOE SNF canister, a DOE HLW canister, a naval SNF canister, a DOE 
MCO, a loaded sealed site-specific cask, or a DPC. (BSC 2005b Section 5.1.1.19) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 

000-30R-MGR0-00400-000-001 A-23 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP and Canister 
Handling Crane 
(CHF); 100 ton 
(continued) 
ITS SC  This crane shall not be capable of exerting sufficient force during transfer to breach a 
canister or WP as the result of attempts to overcome mechanical constraints. (BSC 2005b 
Section 5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
Crane Lifting 
Yokes 
ITS SC  Crane lifting yokes shall be designed for loading conditions associated with a DBGM-2 
seismic event and to demonstrate sufficient seismic margin to ensure that a no drop 
safety function3 is maintained for loading conditions associated with a BDBGM seismic 
event. (BSC 2004a Table IV-1) 
WP/MSC Pit 
Protective Covers 
(CHF) 
ITS SC  The WP/MSC pit protective covers shall be designed for loading conditions associated 
with a DBGM-1 seismic event and demonstrate sufficient seismic design margin to a no 
failure safety function3. (BSC 2004a Table IV-1) 
 Pit covers shall be sturdy enough to prevent a WP or site-specific cask that is dropped 
on the pit cover from penetrating the pit cover and falling into the pit. (BSC 2005b Section 
5.1.6.6) 
 Radiation exposure to workers due to inadvertent actuation of the pit protective covers 
shall be precluded such that this is not a Category 1 event. (BSC 2005b Section 5.1.1.57) 
WP/MSC Pit 
Pedestals (CHF) 
N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
WP Preparation 
(continued) 
Crush Pad ITS SC  Crush pads shall limit the impact energy of a dropped unsealed WP to be less than or 
equal to the impact energy associated with a drop of an unsealed WP onto an unyielding 
surface from the maximum specified drop height for the unsealed WP6. (BSC 2005b 
Section 5.1.1.50) 
Cask Restoration Entire N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 

000-30R-MGR0-00400-000-001 A-24 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Receipt and Return System 
SRTC ITS SC  In the instances when the SRTC moves a cask without impact limiters (typically only 
within structures), the SRTC shall prevent slapdown of the cask for loading conditions 
associated with a DBGM-2 seismic event. In addition, an analysis shall demonstrate that 
the SRTC transporting a cask without impact limiters has sufficient seismic design margin 
to ensure that a no slapdown safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 A speed limit for which SRTCs will be pulled/pushed by the SRTC tractor shall be 
established such that a collision with shield or airlock doors or other heavy objects does 
not overturn the SRTC or cause it to lose its load. (BSC 2005b Section 5.1.1.38) 
 In the instances where the SRTC moves a cask without impact limiters (typically only 
within structures) an SRTC carrying a transportation cask or a site-specific cask shall not 
derail and the transportation cask or site-specific cask shall not fall from the SRTC under 
normal operating conditions or as the result of a collision. (BSC 2005b Section 5.1.1.35) 
SRTC Rails N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
SRTC Positioner N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
SRTC Positioner 
Turntable 
N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
SRTC Buffer 
SRTC Tractor N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 

000-30R-MGR0-00400-000-001 A-25 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Receipt and 
Return 
Cask Handling 
Crane (TCRRF); 
250 ton 
ITS SC 
 The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limits for the transportation casks handled by this crane are provided in 
Table C-1 in Appendix C; these casks include: 
1. Transportation casks without impact limiters. 
2. Transportation casks with impact limiters. 
 This crane and its rigging shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
a no drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a transportation cask. 
(BSC 2005b Section 5.1.1.19) 
 This crane shall not be capable of exerting sufficient force to breach a cask during 
transfer as the result of attempts to overcome mechanical constraints. (BSC 2005b 
Section 5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 

000-30R-MGR0-00400-000-001 A-26 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Crane Lifting 
Yokes 
ITS SC  The crane lifting yokes shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic margin to ensure that a no 
drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
Cask Receipt and 
Return (continued) 
Crush Pad ITS SC  Crush pads shall limit the impact energy of a dropped cask to be less than or equal to 
the impact energy associated with a drop of a cask onto an unyielding surface from the 
maximum specified drop height for the cask6. (BSC 2005b Section 5.1.1.18) 
Communications System 
Communications 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Digital Control and Management Information System 
Digital Control and 
Management 
Information 
Entire N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
DOE and Commercial WP System 
DOE and 
Commercial WP 
Entire ITS 
ITWI 
SC  Sealed WPs shall withstand without breaching the following drops: (BSC 2005b Section 
5.1.3.12) 
A. Free-drop of 6.5 ft from a vertical orientation onto a horizontal surface (trunnion 
collars installed) 
B. Free-drop of 7.8 ft from a horizontal orientation onto a horizontal surface (trunnion 
collars installed) 
C. Free-drop with the emplacement pallet from a horizontal orientation onto a horizontal 
surface (trunnion collars not installed) of 6.5 ft from the bottom of the emplacement 
pallet 

000-30R-MGR0-00400-000-001 A-27 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
DOE and 
Commercial WP 
(continued) 
Entire (continued) ITS 
ITWI 
SC  Sealed WPs shall withstand without breaching the following drops (continued): (BSC 
2005b Section 5.1.3.12) 
D. Tip-over onto a horizontal surface from a 6.5 ft elevated surface (trunnion collars 
installed) 
E. Tip-over onto the tilting machine, including contact with the trunnion cradles or the 
floor (trunnion collars installed). 
Note: Drop and tip-over event sequences shall be evaluated for worst possible (most 
damaging) credible conditions including initial geometric position and weight of 
contents. An unyielding, flat horizontal surface may be used to bound the 
consequences of a drop. Drops shall include attendant swing-down and/or slapdown 
from the indicated position, with or without trunnion collars attached, as 
appropriate. 
 WPs, in a horizontal orientation on an emplacement pallet, shall be lifted in accordance 
with the lift height limits in Table C-1 in Appendix C. 
 WPs in a vertical orientation shall be lifted in accordance with the lift height limits in 
Table C-1 in Appendix C. 
 WPs shall withstand a single rockfall of 1.2  105 joules or less without breaching. (BSC 
2005b Section 6.3.6.1.20) 
 WPs shall withstand two consecutive rockfalls having a total kinetic energy of 1.0  105 
joules or less without breaching. (BSC 2005b Section 6.3.6.1.20) 
 WPs shall be designed for loading conditions associated with a DBGM-2 seismic event 
and to demonstrate sufficient seismic design margin to ensure that no breach and no 
criticality safety functions3 are maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 The size of the berth in a WP shall be restricted such that a DOE MCO cannot be tilted 
more than an angle of 3 degrees from vertical upon impact with the floor of the berth. 
(BSC 2005b Section 5.1.1.15) 
 In the event of a credible fire, the wall temperature of a loaded but unsealed WP with 
only the inner lid installed (welded or not) shall not exceed its allowable operating range2, 5. 
(BSC 2004c Section 5.1.2.10) 

000-30R-MGR0-00400-000-001 A-28 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Entire (continued) ITS 
ITWI 
SC  In the event of a credible fire, the wall temperature of a sealed WP shall not exceed its 
allowable operating range5. (BSC 2004c Section 5.1.2.11) 
 In the event of a credible fire, the wall temperature of an open, loaded WP with a 
docking ring installed shall not exceed its allowable operating range2, 5. (BSC 2004c 
Section 5.1.2.17) 
 A WP shall not breach as a result of the credible fire5. 
 Sealed WPs shall be designed such that drops, collisions, and other handling impacts 
within the WP design bases (allowing for rearrangement of container internals and without 
credit for burnup) cannot lead to a nuclear criticality. (BSC 2005b Section 5.1.3.1) 
 WPs shall be designed, with credit for moderator control, such that: (BSC 2005b 
Section 5.1.3.2) 
A. WPs configured for commercial SNF can be loaded with any combination of 
commercial SNF assemblies that are acceptable for disposal without leading 
to a preclosure nuclear criticality. 
B. DOE codisposal WPs can be loaded with any combination of DOE canisters 
that fit in the basket positions without leading to a preclosure nuclear criticality. 
The demonstration of criticality safety must account for the bowing of fuel rods 
or other rearrangement of fissile material that may occur due to a drop or other 
handling incident. 
 A WP that is dropped from within 2 ft above an essentially unyielding flat surface shall 
not spill its contents. (BSC 2005b Section 5.1.3.11) 
DOE and 
Commercial WP 
(continued) 
Trunnion Collar ITS SC  Trunnion collars shall be designed for loading conditions associated with a DBGM-2 
seismic event and to demonstrate sufficient seismic design margin to ensure a no drop 
safety function3 is maintained for loading conditions associated with a BDBGM seismic 
event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-29 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
DOE SNF Disposable Canister 
DOE SNF 
Disposable 
Canister 
Standardized 
DOE SNF 
Canister 
ITS SC  The probability that a standardized DOE SNF canister is defective such that it may 
breach if dropped in any orientation from a height of 23 ft onto an essentially unyielding flat 
surface shall be 2.3  10-4 or less. (BSC 2005b Section 4.2.2) 
 A standardized DOE SNF canister in a cask, WP, staging rack, or staging pit, shall 
withstand without breach a drop of a DOE HLW canister onto it from 2 ft above the floor of 
the transfer cell and from 23 ft above the floor of the cask, WP, staging rack, or staging pit. 
(BSC 2005b Section 5.1.1.25) 
 A standardized DOE SNF canister shall not breach if lifted in accordance with the lift 
height limits in Table C-1 in Appendix C. 
 A standardized DOE SNF canister shall be designed for loading conditions associated 
with a DBGM-2 seismic event and to demonstrate sufficient seismic margin to ensure that 
no breach and no criticality safety functions3 are maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 A standardized DOE SNF canister shall withstand without breach a drop of another 
standardized DOE SNF canister drop on top of it from 23 ft above the floor of a cask, WP, 
staging rack or staging pit and from 2 ft above the floor of the transfer cell. (BSC 2005b 
Section 5.1.1.28) 
 A drop of a standardized DOE SNF canister shall not lead to a nuclear criticality 
assuming that the canister is not breached and moderator control is in effect. (BSC 2005b 
Section 5.1.1.3) 
 In the event of a credible fire, the wall temperature of a DOE standardized canister shall 
not exceed its allowable operating range. The operating temperature of a standardized 
DOE SNF canister, when it is not inside another canister, is 149 C (300 F), and 316 C 
(600 F), after placement into another canister. Containment can be maintained for 
temperatures as high as 343 C (650 F)5. (BSC 2004c Section 5.1.2.5) 
 A standardized DOE SNF canister shall not breach as a result of the credible fire5. 

000-30R-MGR0-00400-000-001 A-30 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
DOE MCO ITS SC  The probability that a DOE MCO is defective such that it may breach if dropped from 
less than a height of 23 ft in less than a 3-degree vertical orientation or 2 ft from any 
orientation shall be 2.3  10-4 or less. (BSC 2005b Section 4.2.2) 
 A DOE MCO in a cask or WP shall withstand without breach a drop of a DOE HLW 
canister onto it from 2 ft above the floor of the transfer cell and from 23 ft above the floor of 
the cask or WP. (BSC 2005b Section 5.1.1.25) 
 A DOE MCO shall withstand without breach a drop of another DOE MCO onto it from 2 ft 
above the floor of the transfer cell and from 23 ft above the floor of the cask or WP. (BSC 
2005b Section 5.1.1.28) 
 A DOE MCO shall not breach if dropped in accordance with the lift height limits in Table 
C-1 in Appendix C. 
 A DOE MCO shall be designed for loading conditions associated with a DBGM-2 seismic 
event and to demonstrate sufficient seismic design margin to ensure that no breach and 
no criticality safety functions3 are maintained for loading conditions associated with a 
BDBGM seismic event. (BSC 2004a Table IV-1) 
 A drop of a DOE MCO shall not lead to a nuclear criticality assuming that the canister is 
not breached and moderator control is in effect. (BSC 2005b Section 5.1.1.3) 
 In the event of a credible fire, the wall temperature of a DOE MCO shall not exceed its 
allowable operating range. The most restrictive temperature is the handling temperature, 
132 C5. (BSC 2004c Section 5.1.2.6) 
 A DOE MCO shall not breach as a result of the credible fire5. 
DOE SNF 
Disposable 
Canister 
(continued) 
DOE HLW 
Canister 
ITS SC  A DOE HLW canister shall be designed for loading conditions associated with a 
DBGM-1 seismic event and to demonstrate sufficient seismic design margin to a no 
breach safety function3. (BSC 2004a Table IV-1) 
 A DOE HLW canister shall not be subjected to a temperature exceeding its allowable 
operating range; the temperature limit of the waste form inside the canister is 400C5. 
(BSC 2004c Section 5.1.2.7) 

000-30R-MGR0-00400-000-001 A-31 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Internal Geometry 
Control 
ITS SC  The DOE SNF disposable canister internal geometry control shall be designed for 
loading conditions associated with a DBGM-2 seismic event and to demonstrate sufficient 
seismic design margin to ensure that a no criticality safety function3 is maintained for 
loading conditions associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
DOE SNF 
Disposable 
Canister 
(continued) 
Internal Neutron 
Absorbers 
ITWI SC  No function of this SSC is credited for the prevention or mitigation of a preclosure event 
sequence. 
Dual Purpose Canister 
DPC Entire ITS SC  In the event of a credible fire, the wall temperature of a loaded DPC, being handled or at 
rest, shall not exceed its allowable operating range5. (BSC 2004c Section 5.1.2.9) 
 A DPC shall not breach as a result of the credible fire5. 
 DPCs shall be designed to ensure nuclear criticality safety with optimum moderation and 
the most reactive waste forms. Criticality safety will be maintained despite any geometric 
rearrangements due to a drop or other handling incident. (BSC 2005b Section 5.1.1.4) 
Electrical Power System 
Switchyard Line End 
Transmission 
Tower; Line Side 
High Voltage 
Disconnect 
Switch; High 
Voltage Breaker 
(continued on next 
page) 
ITS SC  Electrical power system components shall provide reliable power to the DTF and FHF 
Surface Nuclear HVAC Primary Confinement Subsystem to meet the performance criteria 
in accordance with the Surface Nuclear HVAC Primary Confinement Subsystem nuclear 
safety design bases. (BSC 2005b Section 5.1.1.48, BSC 2004f Table 9) 

000-30R-MGR0-00400-000-001 A-32 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Switchyard 
(continued) 
(continued) Load 
Side High Voltage 
Disconnect 
Switch; Main 
Transformer; and 
Nonsegmented 
Bus to 12.17 kV 
Main Switchgear 
ITS SC  Electrical power system components shall provide reliable power to the DTF and FHF 
Surface Nuclear HVAC Primary Confinement Subsystem to meet the performance criteria 
in accordance with the Surface Nuclear HVAC Primary Confinement Subsystem nuclear 
safety design bases. (BSC 2005b Section 5.1.1.48, BSC 2004f Table 9) 
12.47 kV Main 
Switchgear; 12.47 
kV to 4.16 kV 
Distribution 
Transformer to 
Emergency 
Switchgear Bus A; 
12.47 kV to 4.16 
kV Distribution 
Transformer to 
Emergency 
Switchgear Bus B 
ITS SC  Electrical power system components shall provide reliable power to the DTF and FHF 
Surface Nuclear HVAC Primary Confinement Subsystem to meet the performance criteria 
in accordance with the Surface Nuclear HVAC Primary Confinement Subsystem nuclear 
safety design bases. (BSC 2005b Section 5.1.1.48; BSC 2004f Table 9) 
Normal Power 
4.16 kV 
Switchgear Bus A, 
B, C, and D; 12.47 
kV Switchgear C 
and D (located at 
South Portal), 
Standby Diesel 
Generators 
N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 

000-30R-MGR0-00400-000-001 A-33 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
4.16 kV 
Emergency 
Switchgear Bus A 
and B; Emergency 
Load Center 
Transformers for 
DTF1, DTF2, and 
FHF; Emergency 
Load Centers and 
MCC located in 
DTF 1, DTF2, and 
FHF; and Feeders 
up to and 
including the ITS 
Loads 
ITS SC  Electrical power system components shall provide reliable power to the DTF and FHF 
Surface Nuclear HVAC Primary Confinement Subsystem to meet the performance criteria 
in accordance with the Surface Nuclear HVAC Primary Confinement Subsystem nuclear 
safety design bases. (BSC 2005b Section 5.1.1.48, BSC 2004f Table 9) 
Emergency Power 
Emergency Diesel 
Generators A 
and B 
N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 
Electrical Support System 
Lighting Entire N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 
Grounding Entire N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 
Lightning 
Protection 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 
Cathodic 
Protection 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 

000-30R-MGR0-00400-000-001 A-34 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Heat Tracing Entire N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 
The Portion of 
Cable Raceway 
Subsystem that 
Supports ITS 
Functions of the 
Electrical Power 
System (including 
the switchyard, 
12.47 kV main 
switchgear A and 
B, 4.16 kV 
emergency bus A 
and B, 480 V 
emergency load 
centers and 
MCCs, 125 V DC 
and 120 V AC 
UPS 
ITS SC  The portion of the cable raceway subsystem that supports ITS functions of the 
emergency power subsystem shall provide reliable power to the DTF and FHF Surface 
Nuclear HVAC Primary Confinement System to meet the performance criteria in 
accordance with the Surface Nuclear HVAC Primary Confinement System nuclear safety 
design bases. (BSC 2005b Section 5.1.1.48) 
Cable Raceway 
The Portion of 
Cable Raceway 
Subsystem that 
Supports Non-SC 
Functions of the 
Electrical Power 
System (including 
portions of the 
normal power 
subsystem, 
standby power 
subsystem, and 
emergency diesel 
generators) 
N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 

000-30R-MGR0-00400-000-001 A-35 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Emplacement and Retrieval System 
WP 
Transportation 
WP Transporter 
ITS SC 
 The WP transporter shall transport the WP in a manner such that if a collision or 
derailment (excluding tipover) occurs, the WP impact energy will be low enough to 
preclude a WP breach; this impact energy translates into a maximum WP transporter 
speed of 15 mph. (BSC 2005b Section 5.1.7.3) 
 The WP transporter shall transport the WP in a manner such that if a collision or 
derailment leading to a WP transporter tipover occurs, the WP impact energy will be low 
enough to preclude a WP breach. (BSC 2005b Section 5.1.7.7) 
 While on the surface, the WP transporter shall be designed to function in extreme 
straight wind (90 mph). (BSC 2005b Section 4.1.13) 
 The WP transporter and its bedplate shall not collide with a WP on the WP turntable and 
cause a WP breach. (BSC 2005b Section 5.1.1.39) 
 The rate of a WP transporter runaway shall be less than 8.3  10-9 runaways per trip. 
(BSC 2005b Section 6.3.6.1.4) 
 The WP transporter (together with the locomotive and coupler) shall be designed to 
prevent runaway of the WP transporter for loading conditions associated with a DBGM-2 
seismic event. In addition, an analysis shall demonstrate that the WP transporter (together 
with the locomotive and coupler) has sufficient seismic design margin to ensure that a no 
runaway safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-36 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP 
Transportation 
(continued) 
WP Transporter 
(continued) 
ITS SC 
 The WP transporter shall be designed for loading conditions associated with a DBGM-1 
seismic event and demonstrate sufficient seismic design margin to a shielding integrity 
remains intact safety function3. (BSC 2004a Table IV-1) 
 The transporter shielded compartment shall withstand any fall of failed ground support 
materials, as well as a set of rockfalls having a total mass of 5.4 MT, without jeopardizing 
the structural integrity of the WP. (BSC 2005b Section 6.3.6.1.9) 
 Movement of the WP transporter shielded enclosure doors shall not breach the WP or 
cause it to fall from the bedplate of the transporter. (BSC 2005b Section 5.1.7.2) 
 The restraints used to immobilize the bedplate inside the shielded compartment of the 
WP transporter and the mechanism for locking the doors of the shielded compartment shall 
withstand a collision or derailment (including tipover) of the transporter without resulting in 
a Category 1 or Category 2 event sequence. (BSC 2005b Section 5.1.7.4) 
 Spurious or operator-induced opening of the WP shielded compartment followed by a 
bedplate roll-out shall be precluded when the transporter is in motion. (BSC 2005b Section 
5.1.7.6) 
 Radiation exposure to workers due to inadvertent actuation of the WP transporter 
shielded compartment doors shall be precluded such that this is not a Category 1 event. 
(BSC 2005b Section 5.1.1.57) 
 Upon a loss of power, the WP transporter shall be designed to stop, retain its load, and 
enter a locked mode; upon a restoration of power, the WP transporter shall stay in the 
locked mode until operator action is taken. (BSC 2005b Section 5.1.2.2) 

000-30R-MGR0-00400-000-001 A-37 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP Emplacement 
WP Emplacement 
Gantry 
ITS 
SC 
 The emplacement gantry shall have a drop rate of less than or equal to 1  10-5 
drops/transfer regardless of the cause, including equipment failures, human error, or some 
combination of the two. (BSC 2005b Section 5.1.8.1) 
 The lift height limit for WPs in a horizontal orientation on the emplacement pallet is 
provided in Table C-1 in Appendix C. 
 The WP emplacement gantry, carrying a WP, shall not be capable of running off the end 
of the emplacement drift or transfer dock rails. (BSC 2005b Section 5.1.8.3) 
 If the WP emplacement gantry were to fall on the WP transporter and impact the WP, it 
shall not cause the WP to be breached. (BSC 2005b Section 5.1.8.6) 
 The WP emplacement gantry shall be limited to a maximum speed of 15 mph such that a 
collision at this speed limit shall not result in a WP breach. (BSC 2005b Section 5.1.8.7) 
 Upon a loss of power, the WP emplacement gantry shall be designed to stop, retain its 
load, and enter a locked mode; upon a restoration of power, the WP emplacement gantry 
shall stay in the locked mode until operator action is taken. (BSC 2005b Section 5.1.2.2) 
 The conditional probability of the WP emplacement gantry having exceeded the lift 
height limit given that a drop occurred shall be 10-4 or less. (BSC 2005b Section 5.1.8.10) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of machinery that handles or transports SNF/HLW shall not reach a level that would make 
it drop its load. (BSC 2004c Section 5.1.3.1) 
 A tipover and breach of a WP due to uncontrolled movements produced by a loss of 
power or a spurious signal caused by a fire shall have a probability of less than 1  10-4 
over the life of the facility. (BSC 2004c Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
WP Retrieval Components of 
this System are 
the same as those 
in the WP 
Transportation 
and WP 
Emplacement 
Subsystems 
ITS SC The nuclear safety design bases for this system are the same as those in the WP 
Transportation and WP Emplacement Subsystems since they share the same 
components. 

000-30R-MGR0-00400-000-001 A-38 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Transport 
Locomotive 
ITS SC  The transport locomotive (together with the WP transporter and coupler) shall be 
designed to prevent the runaway of the WP transporter for loading conditions associated 
with a DBGM-2 seismic event. In addition, an analysis shall demonstrate that the transport 
locomotive (together with the WP transporter and coupler) has sufficient seismic design 
margin to ensure that a no runaway safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of machinery that handles or transports SNF/HLW shall not reach a level that would make 
it drop its load. (BSC 2004c Section 5.1.3.1) 
Support 
Equipment 
Gantry Carrier N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
Environmental/Meteorological Monitoring System 
Environmental/ 
Meteorological 
Monitoring 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with this subsystem are credited for 
the prevention or mitigation of an event sequence. 
Fire Protection System 
Fire Protection 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
HVAC Plant Heating and Cooling System 
HVAC Plant 
Heating and 
Cooling 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 

000-30R-MGR0-00400-000-001 A-39 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Low-Level Radiological Waste Management System 
Low-Level 
Radiological 
Waste 
Management 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Low-Level Radiological Waste Generating Systems 
Low-Level 
Radiological 
Waste Generating 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Naval Spent Nuclear Fuel Canister 
Naval SNF 
Canister Internals 
Naval SNF 
Canister Baskets, 
Loading Sleeves 
and Cans; Control 
Rods or Neutron- 
Absorbing 
Material, 
Attachment 
Hardware; SNF 
Cladding 
ITWI SC This SSC is ITWI; no function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
Naval SNF 
Canister 
Naval SNF 
Canister 
ITS 
ITWI 
SC  The naval SNF canister shall not breach as a result of the credible fire5, 7. 
 The naval SNF canister shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
a no breach safety function3 is maintained for loading conditions associated with a 
BDBGM seismic event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-40 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Naval Spent Nuclear Fuel Waste Package System 
Naval SNF WP Entire ITS 
ITWI 
SC  Sealed naval SNF WPs shall withstand without breaching the following drops: (BSC 
2005b Section 5.1.3.12) 
A. Free-drop of 6.5 ft (3.3 ft for the naval long SNF WP) from a vertical orientation onto 
a horizontal surface (trunnion collars installed) 
B. Free-drop of 7.8 ft from a horizontal orientation onto a horizontal surface (trunnion 
collars installed) 
C. Free-drop with the emplacement pallet from a horizontal orientation onto a horizontal 
surface (trunnion collars not installed) of 6.5 ft from the bottom of the emplacement 
pallet 
D. Tip-over onto a horizontal surface from a 6.5 ft (1.6 ft for the naval long SNF WP) 
elevated surface (trunnion collars installed) 
E. Tip-over onto the tilting machine, including contact with the trunnion cradles or the 
floor (trunnion collars installed). 
Note: Drop and tip-over event sequences shall be evaluated for worst possible (most 
damaging) credible conditions including initial geometric position and weight of 
contents. An unyielding, flat horizontal surface may be used to bound the 
consequences of a drop. Drops shall include attendant swing-down and/or slapdown 
from the indicated position, with or without trunnion collars attached, as 
appropriate. 
 A naval SNF WP in a horizontal orientation on the emplacement pallet shall be lifted in 
accordance with the lift height limits in Table C-1 in Appendix C. 
 A naval long SNF WP in a vertical orientation shall be lifted in accordance with the lift 
height limits in Table C-1 in Appendix C. 
 Naval SNF WPs shall withstand a single rockfall of 1.2  105 joules or less without 
breaching. (BSC 2005b Section 6.3.6.1.20) 

000-30R-MGR0-00400-000-001 A-41 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Entire (continued) ITS 
ITWI 
SC  Naval SNF WPs shall withstand two consecutive rockfalls having a total kinetic energy of 
1.0  105 joules or less without breaching. (BSC 2005b Section 6.3.6.1.20) 
 Naval SNF WPs shall be designed for loading conditions associated with a DBGM-2 
seismic event and to demonstrate sufficient margin to ensure that no breach and no 
criticality safety functions3 are maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 Sealed naval SNF WPs shall be designed such that drops, collisions, and other handling 
impacts within the WP design bases (allowing for rearrangement of container internals and 
without credit for burnup) cannot lead to a nuclear criticality. (BSC 2005b Section 5.1.3.1) 
 The naval SNF WP shall be designed such that it can be loaded with a naval SNF 
canister without leading to a preclosure nuclear criticality with credit for moderator control. 
(BSC 2005b Section 5.1.3.2) 
 A naval SNF WP that is dropped from within 2 ft above an essentially unyielding flat 
surface shall not spill its contents. (BSC 2005b Section 5.1.3.11) 
 An unsealed naval SNF WP containing a naval SNF canister shall be lifted in 
accordance with the lift height limits in Table C-1 in Appendix C. 
 In the event of a credible fire, the wall temperature of a loaded but unsealed naval SNF 
WP with only the inner lid installed (welded or not) shall not exceed its allowable operating 
range2, 5. (BSC 2004c Section 5.1.2.10) 
 In the event of a credible fire, the wall temperature of a sealed naval SNF WP shall not 
exceed its allowable operating range5. (BSC 2004c Section 5.1.2.11) 
 In the event of a credible fire, the wall temperature of an open, loaded naval SNF WP 
with a docking ring installed shall not exceed its allowable operating range2, 5. (BSC 2004c 
Section 5.1.2.17) 
 A naval SNF WP shall not breach as a result of the credible fire5. 
Naval SNF WP 
(continued) 
Trunnion Collar ITS SC  Trunnion collars shall be designed for loading conditions associated with a DBGM-2 
seismic event and to demonstrate sufficient seismic design margin to ensure that a no 
drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-42 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Non-Nuclear Handling System 
Non-Nuclear 
Handling 
Entire N/A Non-SC Not applicable. None the SSC functions associated with these subsystems are credited for 
the prevention or mitigation of an event sequence. 
Non-Radiological Waste Management System 
Non-Radiological 
Waste 
Management 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Plant Services System 
Plant Services Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Radiation/Radiological Monitoring System 
Radiation/ 
Radiological 
Monitoring 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Remediation System 
Dry Remediation 
Trolley, Pedestal, 
and Hold-Down 
Device 
ITS SC  Upon a loss of power, this trolley shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this trolley shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.2) 

000-30R-MGR0-00400-000-001 A-43 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Trolley, Pedestal, 
and Hold-Down 
Device 
(continued) 
ITS SC  Pedestals and hold-down devices shall be designed for loading conditions associated 
with a DBGM-2 seismic event and to demonstrate sufficient seismic design margin to 
ensure that a no tipover safety function3 is maintained for loading conditions associated 
with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The trolley system shall be designed for loading conditions associated with a DBGM-2 
seismic event to maintain trolley stability and prevent waste container slapdown. In 
addition, an analysis shall demonstrate that the trolley system has sufficient seismic design 
margin to ensure that a no slapdown safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The trolley shall be designed with an inherent speed limit such that a collision at the 
trolley speed limit would not cause the trolley to drop its load. (BSC 2005b Section 
5.1.1.61) 
 Loaded transfer trolleys shall not derail or drop their loads. (BSC 2005b Section 
5.1.1.36) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the machinery that handles or transports SNF/HLW shall not reach a level that would 
make it drop its load. (BSC 2004c Section 5.1.3.1) 
 A tipover and breach of a cask while on machinery that handles or transports SNF/HLW 
due to uncontrolled movements produced by a loss of power or a spurious signal caused 
by a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 
2004c Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Dry Remediation 
(continued) 
Turntable ITS SC  The turntable system shall be designed for loading conditions associated with a DBGM-2 
seismic event to maintain turntable stability and prevent waste container tipover. In 
addition, an analysis shall demonstrate that the turntable system has sufficient seismic 
design margin to ensure that a no tipover safety function3 is maintained for loading 
conditions associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-44 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Turntable 
(continued) 
ITS SC  In the event of a credible fire in an area where waste forms are present, the temperature 
of machinery that handles or transports SNF/HLW shall not reach a level that would cause 
a drop of a cask or a WP while on the turntable. (BSC 2004c Section 5.1.3.1) 
 A tipover and breach of a cask while on a turntable that handles SNF/HLW due to 
uncontrolled movements produced by a loss of power or a spurious signal caused by a fire 
shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Dry Remediation 
(continued) 
Docking Station 
ITS SC 
 A drop or collision involving components associated with a docking port shall not breach 
the lid of a transportation cask or site-specific cask situated at the docking port. (BSC 
2005b Section 5.1.1.17) 
Wet Remediation Cask Handling 
Crane; 
200 ton 
ITS 
SC 
 The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limit for transportation casks without impact limiters or site-specific 
casks is provided in Table C-1 of Appendix C. 
 This crane and its rigging shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
a no drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a transportation cask or 
site-specific cask. (BSC 2005b Section 5.1.1.19) 

000-30R-MGR0-00400-000-001 A-45 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Handling 
Crane; 
200 ton 
(continued) 
ITS 
SC 
 This crane shall not be capable of exerting sufficient force during transfer to breach a 
cask as the result of attempts to overcome mechanical constraints. (BSC 2005b Section 
5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Pit Crush Pad ITS SC  Crush pads shall limit the impact energy of a dropped canister, cask, or WP to be less 
than or equal to the impact energy associated with a drop of a cask or WP onto an 
unyielding surface from their maximum specified drop height for the cask or WP6. (BSC 
2005b Section 5.1.1.18) 
Pool Crush Pad ITS SC  The remediation pool shall be designed with the appropriate impact-absorbing capability 
to prevent loss of pool integrity given a drop of the most challenging transportation cask or 
site-specific cask into the pool. (BSC 2005b Section 5.1.2.6) 
Turntable N/A Non-SC Not applicable. No function of this SSC is credited for the prevention or mitigation of an 
event sequence. 
Wet Remediation 
(continued) 
Fuel Handling 
Machine and 
Grapples 
ITS SC  The fuel handling machine and grapples shall be designed for loading conditions 
associated with a DBGM-1 seismic event and demonstrate sufficient seismic design 
margin to a maintain waste form safety function3. (BSC 2004a Table IV-1) 
 The fuel handling machine and grapples shall be designed for loading conditions 
associated with a DBGM-2 seismic event and to demonstrate sufficient seismic design 
margin to ensure that a no fall down safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The fuel handling machine shall have a drop rate of less than or equal to 1  10-5 
drops/transfer, including transfers in single-assembly canisters. (BSC 2005b Section 
5.1.1.7) 

000-30R-MGR0-00400-000-001 A-46 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Fuel Handling 
Machine and 
Grapples 
(continued) 
ITS 
I 
SC 
 The rate of collisions during an assembly transfer operation shall be less than or equal to 
1  10-5 collisions/transfer. (BSC 2005b Section 5.1.1.8) 
 The probability of a drop of handling equipment onto a commercial SNF assembly with 
enough energy to breach the assembly shall be less than or equal to 1  10-7 
impacts/transfer for each assembly transferred. (BSC 2005b Section 5.1.1.9) 
 The fuel handling machine shall not be capable of lateral movements of handling 
equipment at a speed that could initiate an event sequence as a result of a collision with an 
SNF assembly. (BSC 2005b Section 5.1.1.54) 
 Upon a loss of power, the fuel handling machine shall be designed to stop, retain its 
load, and enter a locked mode; upon a restoration of power, this crane shall stay in the 
locked mode until operator action is taken. (BSC 2005b Section 5.1.2.1) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the machinery that handles or transports SNF/HLW shall not reach a level that would 
make it drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from machinery that handles SNF due to a spurious signal caused by a 
fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Crane Lifting 
Yokes and 
Grapples 
ITS SC  The crane lifting yokes and grapples shall be designed for loading conditions associated 
with a DBGM-2 seismic event. In addition, an analysis shall demonstrate that the crane 
lifting yokes and grapples have sufficient seismic design margin to ensure that a no drop 
safety function3 is maintained for loading conditions associated with a BDBGM seismic 
event. (BSC 2004a Table IV-1) 
Wet Remediation 
(continued) 
Staging 
Racks/Baskets in 
Remediation Pool 
ITS SC  The staging racks shall be designed for loading conditions associated with a DBGM-2 
seismic event for stability and distortion such as to maintain assembly geometry in the 
rack. In addition, analyses shall demonstrate that the staging racks have sufficient seismic 
design margin to ensure that distortion of the racks is limited and stability is maintained for 
loading conditions associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-47 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Wet Remediation 
(continued) 
Staging 
Racks/Baskets in 
Remediation Pool 
(continued) 
ITS SC  Fully loaded baskets in staging racks shall be subcritical when fully flooded with pure 
water (i.e., no credit for neutron absorbers dissolved in the water); the baskets shall have 
sufficient criticality controls to remain subcritical under the expected range of conditions 
resulting from handling incidents in and out of staging racks; and the baskets shall be 
closed during handling such that a closed basket being transferred in the pool will not spill 
SNF assemblies into the pool if the basket is dropped. (BSC 2005b Section 5.1.5.9) 
WP Remediation 
WP Remediation 
Crane; 100 ton 
ITS 
SC 
 The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 The probability of dropping handling equipment from a crane onto a canister shall be 
less than or equal to 1  10-5 for each canister transferred. (BSC 2005b Section 5.1.1.11) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limits for the WPs and canisters handled by this crane are provided in 
Table C-1 in Appendix C; these WPs and canisters include: 
1. Sealed WPs containing commercial SNF, standardized DOE canisters, DOE HLW 
canisters, naval SNF canisters, or DOE MCOs. 
2. Unsealed, loaded WPs containing commercial SNF, standardized DOE canisters, 
DOE HLW canisters, naval SNF canisters, or DOE MCOs. 
3. Standardized DOE SNF canisters, DOE HLW canisters, DOE MCOs, sealed 
vertical DPCs, or unsealed vertical DPCs. 
 This crane system shall be designed for loading conditions associated with a DBGM-2 
seismic event and maintain its load. In addition, an analysis shall demonstrate that this 
crane system has sufficient seismic design margin to ensure that a no drop safety 
function3 is maintained for loading conditions associated with a BDBGM seismic event. 
(BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-48 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP Remediation 
Crane;100 ton 
(continued) 
ITS SC  This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a loaded sealed WP, a 
DOE MCO, a standardized DOE SNF canister, a DOE HLW canister, or a DPC. (BSC 
2005b Section 5.1.1.19) 
 This crane shall not be capable of exerting sufficient force to breach a WP or a canister 
as the result of attempts to overcome mechanical constraints. (BSC 2005b Section 
5.1.1.20) 
 This crane, which can be used to transfer SNF assemblies, shall not be capable of 
lateral movements of handling equipment at a speed that could initiate an event sequence 
as a result of a collision with an SNF assembly. (BSC 2005b Section 5.1.1.54) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Crane Lifting 
Yokes 
ITS SC  Crane lifting yokes shall be designed for loading conditions associated with a DBGM-2 
seismic event and to demonstrate sufficient seismic design margin to ensure that a no 
drop safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
WP Remediation 
(continued) 
WP/DPC Trolley, 
Pedestal, and 
Hold-Down 
Devices 
ITS SC  Upon a loss of power, this trolley shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this trolley shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.2) 
 The trolley system shall be designed for loading conditions associated with a DBGM-2 
seismic event to maintain trolley stability and prevent waste container slapdown. In 
addition, an analysis shall demonstrate that the trolley system has sufficient seismic design 
margin to ensure that a no slapdown safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-49 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP Remediation 
(continued) 
WP/DPC Trolley, 
Pedestal, and 
Hold-Down 
Devices 
(continued) 
ITS SC  Pedestals and hold-down devices shall be designed for loading conditions associated 
with a DBGM-2 seismic event and to demonstrate sufficient seismic design margin to 
ensure that a no tipover safety function3 is maintained for loading conditions associated 
with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The trolley shall be designed with an inherent speed limit such that a collision at the 
trolley speed limit would not cause the trolley to drop its load. (BSC 2005b Section 
5.1.1.61) 
 Loaded transfer trolleys shall not derail or drop their loads. (BSC 2005b Section 
5.1.1.36) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the machinery that handles or transports SNF/HLW shall not reach a level that would 
make it drop its load. (BSC 2004c Section 5.1.3.1) 
 A tipover and breach of a cask while on machinery that transports SNF/HLW due to 
uncontrolled movements produced by a loss of power or a spurious signal caused by a fire 
shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Safeguards and Security System 
Safeguards and 
Security 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
SNF Aging 
Cask Transfer 
Cask Tractor ITS SC  The design of the horizontal cask transfer trailer tractor shall limit the potential damage 
caused by collisions. (Cogema 2004 No. S.23 Table 6-6) 
 Loss of power events shall be precluded. (Cogema 2004 No. S.4 Table 6-6) 
 Tip-over during transfer shall be precluded by ensuring that minimum tip-over 
resistance/standards are maintained consistent with roadway design. (Cogema 2004 No. 
S.25 Table 6-6) 

000-30R-MGR0-00400-000-001 A-50 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Tractor 
(continued) 
ITS SC  The design of the horizontal cask transfer trailer tractor shall provide reliable means to 
stop and maintain stability. (Cogema 2004 No. S.26 Table 6-6) 
 The cask tractor system shall be designed to prevent runaway of the tractor under 
loading conditions associated with a DBGM-2 seismic event. In addition, an analysis shall 
demonstrate that the cask tractor system has sufficient seismic design margin to ensure 
that a no runaway safety function3 is maintained for loading conditions associated with a 
BDBGM seismic event. (BSC 2004a Table IV-1) 
Cask Transfer 
(continued) 
Horizontal Cask 
Transfer Trailer 
ITS 
SC 
 The design of the hydraulic ram shall ensure that it cannot fail or be operated in a 
manner that can cause a DPC loss of function through excess force or ram over-travel. 
(Cogema 2004 No. S.28 Table 6-6) 
 The horizontal cask transfer trailer system shall be designed for stability and to retain the 
waste container and prevent a runaway for loading conditions associated with a DBGM-2 
seismic event. In addition, an analysis shall demonstrate that the horizontal cask transfer 
trailer has sufficient seismic design margin to ensure that no slapdown and no runaway 
safety functions3 are maintained for loading conditions associated with a BDBGM seismic 
event. (BSC 2004a Table IV-1) 
 The design of the horizontal cask transfer trailer shall limit the maximum potential drop 
height. (Cogema 2004 No. S.22 Table 6-6) 
 The design of the horizontal cask transfer trailer/tractor shall limit potential damage to a 
loaded SNF cask caused by collisions. (Cogema 2004 No. S.23 Table 6-6) 
 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 tipover 
under design basis load handling conditions and by ensuring that minimum tip-over 
resistance/stability standards are maintained consistent with roadway design. (Cogema 
2004 Nos. S.24 and S. 25Table 6-6) 

000-30R-MGR0-00400-000-001 A-51 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Transfer 
(continued) 
Site-Specific Cask 
Transporter 
ITS 
SC 
 The site-specific cask transporter system shall be designed for stability and to retain the 
waste container and prevent a runaway for loading conditions associated with a DBGM-2 
seismic event. In addition, an analysis shall demonstrate that the site-specific cask 
transporter system has sufficient seismic design margin to ensure that no slapdown and 
no runaway safety functions3 are maintained for loading conditions associated with a 
BDBGM seismic event. (BSC 2004a Table IV-1) 
 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 sitespecific 
cask transporter or cause it to drop its load. (BSC 2005b Section 5.1.1.38) 
 The cask transporter shall prevent the lifting of aging and transfer casks above their 
maximum handling height. (BSC 2005b Section 4.1.11) 
 The design of the site-specific cask transporter shall limit the maximum potential drop 
height. (Cogema 2004 No. S.22 Table 6-6) 
 The design of the site-specific cask transporter shall limit potential damage to a loaded 
SNF cask caused by collisions. (Cogema 2004 No. S.23 Table 6-6) 
 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 tipover 
under design basis load handling conditions and by ensuring that minimum tip-over 
resistance/stability standards are maintained consistent with roadway design. (Cogema 
2004 Nos. S.24 and 25 Table 6-6) 
 The design of the site-specific cask transporter shall provide reliable means to stop and 
maintain stability. (Cogema 2004 No. S.26 Table 6-6) 
 Loss of power events shall be precluded. (Cogema 2004 No. S.4 Table 6-6) 
 Upon a loss of power, this transporter shall be designed to stop, retain its load, and enter 
a locked mode; upon a restoration of power, this transporter shall stay in the locked mode 
until operator action is taken. (BSC 2005b Section 5.1.2.2) 

000-30R-MGR0-00400-000-001 A-52 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Cask Transfer 
(continued) 
Site-Specific 
Transfer Cask 
ITS SC  The design of the site-specific transfer casks shall ensure that they can withstand a drop 
from the maximum handling height of a horizontal cask transfer trailer without loss of 
function. (Cogema 2004 No. S.12 Table 6-6) 
 The design of the site-specific 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 handling height without adverse effects. (Cogema 2004 No. S.14 Table 6-6) 
Surface Aging 
Pad 
ITS SC  The aging pad shall be designed to preclude inundation during the maximum probable 
flood. (Cogema 2004 No. S.20 Table 6-6) 
 The aging pad shall be located to avoid placement directly over Quaternary faults with a 
potential for significant displacement. (Cogema 2004 No. S.21 Table 6-6) 
 The surface aging pad system shall be designed for loading conditions associated with a 
DBGM-2 seismic event. In addition, an analysis shall demonstrate that the surface aging 
pad system has sufficient seismic design margin to ensure that a no significant 
cracking/displacement safety function3 is maintained for loading conditions associated 
with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The structure shall be designed for the loads associated with the maximum observed 
hourly precipitation event (with a 100-year return period). (BSC 2004g Section 6.1.1.1.2 
and BSC 2005b Section 4.3.2) 
Support 
Structures 
(including Utility 
Buildings and 
Personnel 
Barriers) 
N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Aging Pad 
Aircraft Protection 
Barrier that 
Surrounds the 
Aging Pads 
ITS SC  A barrier, to be at least as tall as the aging casks and to be located in proximity to the 
fence line of the aging pads, shall be provided surrounding the aging pads such that the 
barrier would not be breached by an F-16 aircraft crashing into the barrier at the speed 
corresponding to the 95th percentile from a probability distribution estimated from historical 
F-16 crashes. (BSC 2005d Section 5.1.6) 

000-30R-MGR0-00400-000-001 A-53 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Aging Cask Site-Specific Cask ITS SC  The site-specific cask system and other vertical aging/staging systems employed shall 
be designed for loading conditions associated with a DBGM-2 seismic event. In addition, 
an analysis shall demonstrate that the site-specific cask system and other vertical 
aging/staging systems employed have sufficient seismic design margin to ensure that no 
tipover and no breach safety functions3 are maintained for loading conditions associated 
with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 Tip-over of aging casks and modules as a result of extreme wind or tornado events shall 
be precluded. (Cogema 2004 No. S.5 Table 6-6) 
 The design of aging casks and modules shall ensure that they can withstand the 
differential pressure associated with a passing tornado without loss of function. (Cogema 
2004 No. S.7 Table 6-6) 
 Tip-over of aging casks and modules as a result of being struck by a design basis 
tornado missile shall be precluded. (Cogema 2004 No. S.8 Table 6-6) 
 The design of aging casks and modules shall ensure that they can withstand being 
struck by a design basis tornado missile without loss of function. (Cogema 2004 No. S.9 
Table 6-6) 
 The design of the site-specific casks shall ensure that they can withstand a drop from 
the maximum handling height of a site-specific cask transporter without loss of function. 
(Cogema 2004 No. S.12 Table 6-6) 
 The design of the casks and modules shall ensure acceptable thermal design 
performance during extreme temperature events. (BSC 2004g Section 6.1.1.1.2 and 
Cogema 2004 No. S.15 Table 6-6) 
 Short-duration vent blockage events involving casks and modules shall be precluded. 
(Cogema 2004 No. S.16 Table 6-6) 
 The casks and modules shall not lose their intended function under conditions involving 
the maximum snow, sand, or ash loads. (Cogema 2004 No. S.17 Table 6-6) 
 The design of the casks and modules shall ensure that welded closure casks/canister 
confinement system designs preclude loss of confinement following closure of the casks to 
meet life cycle operations. (Cogema 2004 No. S.18 Table 6-6) 
 The design of the site-specific cask shall ensure that the bolted closure cask design 
protects seals from damage following closure to maintain its primary confinement boundary 
function to meet life cycle operations. (Cogema 2004 No. S.19 Table 6-6) 

000-30R-MGR0-00400-000-001 A-54 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Site-Specific Cask 
(continued) 
ITS 
SC 
 Site-specific casks shall be designed to ensure nuclear criticality safety with optimum 
moderation and the most reactive waste forms. Criticality safety will be maintained despite 
any geometric rearrangements due to a drop or other handling incident. (BSC 2005b 
Section 5.1.1.4) 
 In the event of a credible fire, the wall temperature of a loaded site-specific cask, being 
handled or at rest, shall not exceed its allowable operating range5. (BSC 2004c Section 
5.1.2.4) 
 In the event of a credible fire, the wall temperature of a loaded site-specific cask with 
docking ring installed shall not exceed its allowable operating range2, 5. (BSC 2004c 
Section 5.1.2.15) 
 A site-specific cask shall not breach as a result of the credible fire5. 
 The design of the horizontal DPC shall ensure that it has sufficient structural design 
margin to withstand maximum ram force events. (Cogema 2004 No. S.27 Table 6-6) 
Aging Cask 
(continued) 
Horizontal Aging 
Module 
ITS SC  HAMs shall be designed for loading conditions associated with a DBGM-2 seismic event. 
In addition, an analysis shall demonstrate that the HAMs have sufficient seismic design 
margin to ensure that a no collapse safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 Tip-over of aging casks and modules as a result of extreme wind or tornado events shall 
be precluded. (Cogema 2004 No. S.5 Table 6-6) 
 The design of aging casks and modules shall ensure that they can withstand the 
differential pressure associated with a passing tornado without loss of function. (Cogema 
2004 No. S.7 Table 6-6) 
 Tip-over of aging casks and modules as a result of being struck by a design basis 
tornado missile shall be precluded. (Cogema 2004 No. S.8 Table 6-6) 
 The design of aging casks and modules shall ensure that they can withstand being 
struck by a design basis tornado missile without loss of function. (Cogema 2004 No. S.9 
Table 6-6) 
 The design of the casks and modules shall ensure acceptable thermal design 
performance during extreme temperature events. (BSC 2004g Section 6.1.1.1.2 and 
Cogema 2004 No. S.15 Table 6-6) 

000-30R-MGR0-00400-000-001 A-55 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Aging Cask 
(continued) 
Horizontal Aging 
Module 
(continued) 
ITS SC  Short-duration vent blockage events involving casks and modules shall be precluded. 
(Cogema 2004 No. S.16 Table 6-6) 
 The casks and modules shall not lose their intended function under conditions involving 
the maximum snow, sand, or ash loads. (Cogema 2004 No. S.17 Table 6-6) 
 The design of the casks and modules shall ensure that welded closure casks/canister 
confinement system designs preclude loss of confinement following closure of the casks to 
meet life cycle operations. (Cogema 2004 No. S.18 Table 6-6) 
SNF/HLW Transfer System 
WP Loadout 
WP Handling 
Crane (DTF, 
Room 1044); 100 
ton 
ITS SC 
 The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limits for the sealed and unsealed, loaded WPs handled by this crane are 
provided in Table C-1 in Appendix C. These WPs include: 
1. Unsealed, loaded WPs containing commercial SNF, standardized DOE SNF 
canisters, DOE HLW canisters, naval SNF canisters, or DOE MCOs. 
2. Sealed WPs containing commercial SNF, standardized DOE SNF canisters, DOE 
HLW canisters, naval SNF canisters, or DOE MCOs. 
 This crane system shall be designed for loading conditions associated with a DBGM-2 
seismic event and maintain its load. In addition, an analysis shall demonstrate that this 
crane system has sufficient seismic design margin to ensure that a no drop safety 
function3 is maintained for loading conditions associated with a BDBGM seismic event. 
(BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-56 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP Handling 
Crane (DTF, 
Room 1044); 100 
ton (continued) 
ITS SC 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a loaded, sealed WP. 
(BSC 2005b Section 5.1.1.19) 
 This crane shall not be capable of exerting sufficient force to breach a WP as the result 
of attempts to overcome mechanical constraints. (BSC 2005b Section 5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
WP Loadout 
(continued) 
WP Loadout 
Handling Crane 
(DTF Room 
1088); 100 ton 
ITS SC  The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 This crane system shall be designed for loading conditions associated with a DBGM-2 
seismic event and maintain its load. In addition, an analysis shall demonstrate that the 
crane system has sufficient seismic design margin to ensure that a no drop safety 
function3 is maintained for loading conditions associated with a BDBGM seismic event. 
(BSC 2004a Table IV-1) 
 The lift height limits for the sealed WPs handled by this crane are provided in Table C-1 
in Appendix C. These WPs include sealed WPs containing commercial SNF, standardized 
DOE SNF canisters, DOE HLW canisters, naval SNF canisters, or DOE MCOs. 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a loaded, sealed WP. 
(BSC 2005b Section 5.1.1.19) 

000-30R-MGR0-00400-000-001 A-57 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP Loadout 
Handling Crane 
(DTF Room 
1088); 100 ton 
(continued) 
ITS SC  This crane shall not be capable of exerting sufficient force to breach a WP as the result 
of attempts to overcome mechanical constraints. (BSC 2005b Section 5.1.1.20) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Crane Lifting 
Yokes 
ITS SC  Crane lifting yokes shall be designed for loading conditions associated with a DBGM-2 
seismic event. In addition, an analysis shall demonstrate that the crane lifting yokes have 
sufficient seismic design margin to ensure that a no drop safety function3 is maintained 
for loading conditions associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
WP Loadout 
(continued) 
Trolley, Pedestal, 
and Hold-Down 
Devices (DTF) 
ITS SC  Upon a loss of power, this trolley shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this trolley shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.2) 
 The trolley system shall be designed for loading conditions associated with a DBGM-2 
seismic event to maintain trolley stability and prevent waste container slapdown. In 
addition, an analysis shall demonstrate that the trolley system has sufficient seismic design 
margin to ensure that a no slapdown safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The trolley shall be designed with an inherent speed limit such that a collision at the 
trolley speed limit would not cause the trolley to drop its load. (BSC 2005b Section 
5.1.1.61) 

000-30R-MGR0-00400-000-001 A-58 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Trolley, Pedestal, 
and Hold-Down 
Devices (DTF) 
(continued) 
ITS SC  Pedestals and hold-down devices shall be designed for loading conditions associated 
with a DBGM-2 seismic event. In addition, an analysis shall demonstrate that the 
pedestals and hold-down devices have sufficient seismic design margin to ensure that a 
no tipover safety function3 is maintained for loading conditions associated with a BDBGM 
seismic event. (BSC 2004a Table IV-1) 
 Loaded transfer trolleys shall not derail or drop their loads. (BSC 2005b Section 
5.1.1.36) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the machinery that handles or transports SNF/HLW shall not reach a level that would 
make it drop its load. (BSC 2004c Section 5.1.3.1) 
 A tipover and breach of a cask while on machinery that transports SNF/HLW due to 
uncontrolled movements produced by a loss of power or a spurious signal caused by a fire 
shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
WP Loadout 
(continued) 
WP Tilting 
Machine (DTF, 
CHF, FHF) 
ITS SC  The WP tilting machine system shall be designed for loading conditions associated with 
a DBGM-2 seismic event to maintain stability and prevent a WP drop or slapdown. In 
addition, an analysis shall demonstrate that the WP tilting machine system has sufficient 
seismic design margin to ensure that no drop and no slapdown safety functions3 are 
maintained for loading conditions associated with a BDBGM seismic event. (BSC 2004a 
Table IV-1) 
 The WP tilting machine shall be designed to prevent backward slapdowns. (BSC 2005b 
Section 5.1.1.53) 
 The WP tilting machine shall include measures to prevent movement or release of the 
lock on WP trunnions while the WP is being lowered onto the emplacement pallet. (BSC 
2005b Section 5.1.1.53) 
 An impact or collision between the WP tilting machine and a WP shall not breach the 
WP or cause it to fall off the emplacement pallet. (BSC 2005b Section 5.1.3.10) 

000-30R-MGR0-00400-000-001 A-59 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
WP Turntable 
(DTF, CHF, FHF) 
ITS SC  The WP turntable system shall be designed for loading conditions associated with a 
DBGM-2 seismic event to maintain turntable stability and prevent WP tipover. In addition, 
an analysis shall demonstrate that the WP turntable system has sufficient seismic design 
margin to ensure that a no tipover safety function3 is maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
 The premature actuation of the WP turntable (while holding the WP on an emplacement 
pallet) before the disengagement of the trunnion collar removal machine shall be 
precluded. (BSC 2005b Section 5.1.1.16) 
 An impact or collision between the WP turntable and a WP shall not breach the WP or 
cause it to fall off the emplacement pallet. (BSC 2005b Section 5.1.3.10) 
WP Loadout 
(continued) 
Trunnion Collar 
Removal Machine 
(DTF, CHF, FHF) 
ITS SC  The trunnion collar removal machine system shall be designed for loading conditions 
associated with a DBGM-2 seismic event to prevent slapdown of the WP. In addition, an 
analysis shall demonstrate that the trunnion collar removal machine system has sufficient 
seismic design margin to ensure that no slapdown and no breach safety functions3 are 
maintained for loading conditions associated with a BDBGM seismic event. (BSC 2004a 
Table IV-1) 
 The premature actuation of the WP turntable (while holding the WP on an emplacement 
pallet) before the disengagement of the trunnion collar removal machine shall be 
precluded. (BSC 2005b Section 5.1.1.16) 
 An impact or collision between the trunnion collar removal machine and a WP shall not 
breach the WP or cause it to fall off the emplacement pallet. (BSC 2005b Section 5.1.3.10) 
DPC Cutting 
DPC Cutting 
Machine (DTF) 
ITS SC 
 The design of the DPC cutting machine shall ensure that the DPC lid will prevent 
damage to the SNF assembly resulting in radiological release should the cutting machine 
fall into or make contact with the DPC. (BSC 2005b Section 5.1.5.3) 
 The DPC cutting machine shall preclude a radiological release due to damage inflicted 
upon the DPC contents during the cutting process. (BSC 2005b Section 5.1.5.4) 
 The DPC cutting machine shall be designed for loading conditions associated with a 
DBGM-2 seismic event and to demonstrate sufficient seismic design margin to ensure that 
no failure and no fall down safety functions3 are maintained for loading conditions 
associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-60 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
DPC Cutting 
(continued) 
DPC Docking 
Station 
ITS SC 
 A drop or collision involving components associated with a docking port shall not breach 
the lid of a transportation cask or site-specific cask situated at the docking port. (BSC 
2005b Section 5.1.1.17) 
Dry Transfer 
Spent Fuel 
Transfer Machine 
and Grapples 
(DTF, FHF) 
ITS SC  Upon a loss of power, the spent fuel transfer machine shall be designed to stop, retain 
its load, and enter a locked mode; upon a restoration of power, this machine shall stay in 
the locked mode until operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The spent fuel transfer machine shall have a drop rate of less than or equal to 1  10-5 
drops/transfer, including transfers in single-assembly canisters. (BSC 2005b Section 
5.1.1.7) 
 The spent fuel transfer machine and grapples shall be designed for loading conditions 
associated with a DBGM-1 seismic event to demonstrate sufficient seismic design margin 
to ensure that a maintain waste form safety function3 is maintained. (BSC 2004a Table 
IV-1) 
 The rate of collisions during an assembly transfer operation shall be less than or equal to 
1  10-5 collisions/transfer. (BSC 2005b Section 5.1.1.8) 
 The probability of a drop of handling equipment onto a commercial SNF assembly with 
enough energy to breach the assembly shall be less than or equal to 1  10-7 
impacts/transfer for each assembly transferred. (BSC 2005b Section 5.1.1.9) 
 The spent fuel transfer machine and anchorages shall be designed to prevent collapse 
of this system for loading conditions associated with a DBGM-2 seismic event. In addition, 
an analysis shall demonstrate that the spent fuel transfer machine and anchorages have 
sufficient seismic design margin to ensure that a no fall down safety function3 is 
maintained for loading conditions associated with a BDBGM seismic event. (BSC 2004a 
Table IV-1) 
 The spent fuel transfer machine shall not be capable of lateral movements of handling 
equipment at a speed that could initiate an event sequence as a result of a collision with an 
SNF assembly. (BSC 2005b Section 5.1.1.54) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of machinery that handles or transports SNF/HLW shall not reach a level that would make 
it drop its load. (BSC 2004c Section 5.1.3.1) 

000-30R-MGR0-00400-000-001 A-61 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Spent Fuel 
Transfer Machine 
and Grapples 
(DTF, FHF) 
(continued) 
ITS SC  A drop of a load from machinery that handles SNF due to a spurious signal caused by a 
fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
Dry Transfer 
(continued) 
Canister/HLW 
Handling Crane 
(DTF); 70 ton 
ITS SC  The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 The probability of dropping handling equipment from a crane onto a canister shall be 
less than or equal to 1  10-5 for each canister transferred. (BSC 2005b Section 5.1.1.11) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limits for the canisters handled by this crane (including the DOE MCO, 
standardized DOE SNF canister, and DOE HLW canister) are provided in Table C-1 in 
Appendix C. 
 The crane system shall be designed for loading conditions associated with a DBGM-2 
seismic event and maintain its load. In addition, an analysis shall demonstrate that the 
crane system has sufficient seismic design margin to ensure that a no drop safety 
function3 is maintained for loading conditions associated with a BDBGM seismic event. 
(BSC 2004a Table IV-1) 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a standardized DOE SNF 
canister, a DOE HLW canister, or a DOE MCO. (BSC 2005b Section 5.1.1.19) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 

000-30R-MGR0-00400-000-001 A-62 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Canister/HLW 
Handling Crane 
(DTF); 70 ton 
(continued) 
ITS SC  A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
 This crane shall not be capable of exerting sufficient force to breach a canister as the 
result of attempts to overcome mechanical constraints. (BSC 2005b Section 5.1.1.20) 
Dry Transfer 
(continued) 
Navy Canister 
Handling Crane 
(DTF); 70 ton 
ITS 
SC 
 The drop rate for cranes involved in handling waste forms and their associated 
containers shall be less than or equal to 1  10-5 drops/transfer, regardless of cause, 
including human error, failure of equipment such as yokes and grapples, or a combination 
of the two. (BSC 2005b Section 5.1.1.10) 
 Upon a loss of power, this crane shall be designed to stop, retain its load, and enter a 
locked mode; upon a restoration of power, this crane shall stay in the locked mode until 
operator action is taken. (BSC 2005b Section 5.1.2.1) 
 The conditional probability of the crane exceeding a lift-height limit, given that a drop has 
occurred, shall be less than or equal to 1  10-4. (BSC 2005b Section 5.1.1.12) 
 The lift height limits for the naval SNF canisters handled by this crane are provided in 
Table C-1 in Appendix C. 
 This crane system shall be designed for loading conditions associated with a DBGM-2 
seismic event and maintain its load. In addition, an analysis shall demonstrate that this 
crane system has sufficient seismic design margin to ensure that a no drop safety 
function3 is maintained for loading conditions associated with a BDBGM seismic event. 
(BSC 2004a Table IV-1) 
 This crane shall not be capable of moving above a speed limit for overhead crane 
transfers such that a collision at the speed limit would not breach a naval SNF canister. 
(BSC 2005b Section 5.1.1.19) 
 In the event of a credible fire in an area where waste forms are present, the temperature 
of the crane that handles or transports SNF/HLW shall not reach a level that would make it 
drop its load. (BSC 2004c Section 5.1.3.1) 

000-30R-MGR0-00400-000-001 A-63 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Navy Canister 
Handling Crane 
(DTF); 70 ton 
(continued) 
ITS 
SC 
 A drop of a load from a crane that handles SNF/HLW due to a spurious signal caused by 
a fire shall have a probability of less than 1  10-4 over the life of the facility. (BSC 2004c 
Section 5.1.3.4; BSC 2005b Section 6.1.1.1) 
 This crane shall not be capable of exerting sufficient force to breach a canister as the 
result of attempts to overcome mechanical constraints. (BSC 2005b Section 5.1.1.20) 
Crane Lifting 
Yokes 
ITS SC  The crane lifting yokes shall be designed for loading conditions associated with a 
DBGM-2 seismic event. In addition, an analysis shall demonstrate that the crane lifting 
yokes have sufficient seismic design margin to ensure that a no drop safety function3 is 
maintained for loading conditions associated with a BDBGM seismic event. (BSC 2004a 
Table IV-1) 
Cask/WP Docking 
Stations (DTF, 
FHF) 
ITS SC 
 A drop or collision involving components associated with a docking port shall not breach 
the lid of a transportation cask or site-specific cask situated at the docking port. (BSC 
2005b Section 5.1.1.17) 
Dry Transfer 
(continued) 
Canister and SNF 
Staging Racks 
(DTF) 
ITS 
SC 
 Criticality safety shall be ensured for the commercial SNF assembly staging racks 
loaded to capacity with the most reactive commercial SNF assembly accepted at the 
repository with moderator control in effect. (BSC 2005b Section 5.1.4.2) 
 Criticality safety shall be ensured for commercial SNF assemblies dropped into or onto a 
commercial SNF assembly staging rack with moderator control in effect. (BSC 2005b 
Section 5.1.4.3) 
 The most reactive configuration of standardized DOE SNF canisters shall be capable of 
being loaded into the canister staging racks (with credit for moderator control) without 
leading to a nuclear criticality. (BSC 2005b Section 5.1.1.2) 
 The canister and SNF staging racks shall be designed for loading conditions associated 
with a DBGM-2 seismic event for stability and distortion such as to maintain 
assembly/canister geometry in the rack. In addition, analyses shall demonstrate that the 
staging racks have sufficient seismic design margin to ensure that distortion of the racks is 
limited and stability is maintained for loading conditions associated with a BDBGM seismic 
event. (BSC 2004a Table IV-1) 

000-30R-MGR0-00400-000-001 A-64 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Dry Transfer 
(continued) 
Canister Staging 
Racks (CHF) 
ITS SC 
 The most reactive configuration of standardized DOE SNF canisters shall be capable of 
being loaded into canister staging racks (with credit for moderator control) without causing 
a nuclear criticality. (BSC 2005b Section 5.1.1.2) 
 The staging racks shall be designed for loading conditions associated with a DBGM-2 
seismic event for stability and distortion such as to maintain canister geometry in the rack. 
In addition, analyses shall demonstrate that the staging racks have sufficient seismic 
design margin to ensure that distortion of the racks is limited and stability is maintained for 
loading conditions associated with a BDBGM seismic event. (BSC 2004a Table IV-1) 
Subsurface Ventilation System 
Subsurface 
Ventilation 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Surface Industrial HVAC 
Surface Industrial 
HVAC 
Inlet and Outlet 
Dampers and 
Ventilation 
Ducting (including 
stack) for Fuel 
Element Staging 
Areas (DTF Only) 
ITS 
SC 
 The inlet and outlet dampers and ventilation ducting for the fuel element staging areas 
shall be designed for loading conditions associated with a DBGM-1 seismic event and 
demonstrate sufficient seismic design margin to a no failure safety function3. (BSC 
2004a Table IV-1) 
 The ventilation stack for the fuel element staging areas (DTF only) shall be designed for 
loading conditions associated with a DBGM-1 seismic event and demonstrate sufficient 
seismic design margin to a controlled failure safety function3. (BSC 2004a Table IV-1) 
 A loss of HVAC for up to 30 days in areas where SNF or HLW is handled or staged shall 
not cause waste form temperatures to exceed allowable limits. (BSC 2005b Section 
5.1.2.4) 

000-30R-MGR0-00400-000-001 A-65 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Surface Industrial 
HVAC (continued) 
SSCs Other Than 
the Inlet and 
Outlet Dampers 
and Ventilation 
Ducting (including 
stack) for Fuel 
Element Staging 
Areas (DTF Only) 
N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Surface Nuclear HVAC 
Primary 
Confinement 
Entire (DTF, FHF) 
ITS 
SC 
 To mitigate the worker and public doses following a Category 1 event sequence, the 
Surface Nuclear HVAC system shall be equipped with HEPA filters. A two-stage HEPA 
filtration system with a particulate removal efficiency of at least 99% per stage is required. 
This requirement applies to the DTF and the FHF. (BSC 2005c Section 4.8) 
 The HEPA filters and vent ducts (exhaust ducting and dampers) shall be designed for 
loading conditions associated with a DBGM-1 seismic event and demonstrate sufficient 
seismic design margin to a no discharge safety function3. (BSC 2004a Table IV-1) 
 The probability that the HVAC system, including HEPA filtration in the primary 
confinement areas of the DTF and FHF, becomes unavailable during a 4-hour mission time 
shall be 0.01 or less, without credit for backup electrical power. (BSC 2005b Section 
5.1.1.48) 
 The primary nuclear HEPA filtered ventilation system shall provide a decontamination 
factor of 104 for particulate. (BSC 2005c Section 4.8) 
 A loss of HVAC for up to 30 days in areas where SNF or HLW is handled or staged shall 
not cause waste form temperatures to exceed allowable limits. (BSC 2005b Section 
5.1.2.4) 
Secondary 
Confinement 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 

000-30R-MGR0-00400-000-001 A-66 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Tertiary 
Confinement 
Entire N/A Non-SC 
Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Transportation Cask 
Transportation 
Cask 
Entire ITS SC Transportation casks provide adequate protection against external hazards on the 
repository site. See footnotes 1, 4, and 5. 
WP Closure System 
Welding 
(Equipment) 
Entire N/A Non-SC 
Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Inerting 
(Equipment) 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Non-Destructive 
Testing 
(Equipment) 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Stress Mitigation 
(Equipment) 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
WP Identification Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Spread Ring 
Installation 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Material Handling Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 

000-30R-MGR0-00400-000-001 A-67 March 2005 
Table A-II. Nuclear Safety Design Bases of Systems and Subsystems 
System or 
Subsystem 
Component 
or Function 
ITS or 
ITWI 
Safety 
Category 
Nuclear Safety Design Bases 
Remote 
Equipment 
Maintenance 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
Operations 
Control 
Entire N/A Non-SC Not applicable. None of the SSC functions associated with these subsystems are credited 
for the prevention or mitigation of an event sequence. 
FOOTNOTES: 
1. Functions of the transportation casks are credited to prevent or mitigate event sequences. The certification process for transportation casks under 10 CFR Part 
71 [DIRS 104091] considers severe transportation accident conditions and conditions of normal transport. The precedent that licensed casks provide adequate 
protection against all hazards that apply during the transportation phase establishes the basis that the casks will continue to provide adequate protection on site at 
the repository. 
2. This requirement may be equivalently replaced by a set of two sub-requirements. The first sub-requirement is the fire requirement applicable to the waste form 
being sheltered by the waste form container. The second sub-requirement is as follows: the severity of the fire should be controlled such that the waste form 
container does not lose its structural integrity when handled (BSC 2004c [DIRS 171488], Section 6.2.2) 
3. The definitions of the Safety Functions are provided in Appendix B. 
4. Transportation casks must meet the flame emissivity and cask absorptivity requirements of 10 CFR 71.73(c)(4). 
5. Analyses, as appropriate, will be performed on the respective cask/canister/waste form to demonstrate that the cask, canister, and/or waste form does not fail 
as a result of the credible fire in all areas where it is handled. 
6. Analyses will confirm that sealed WPs shall withstand drops onto energy-absorbing crush pads without breaching and that the impact consequences associated 
with a drop of a canister or cask onto energy-absorbing crush pads shall be equal to, or less than, the impact consequences associated with the drop of a cask or 
canister from the maximum specified drop height onto an unyielding surface. 
7. The naval SNF canister will not be exposed to fire conditions more severe than those corresponding to a black body gas exposure flux of 50 kW/m2 and a 
temperature of 1000C (1832F) for 2 minutes. (BSC 2004c Sections 5.1.2.8 and 6.2.1.2.6) 
GENERAL NOTES: 
Lift height limits can be exceeded provided that energy-absorbing material is used to limit the impact energy to that of the drop height limit. 
The load drop probability includes components (lifting yokes, trunnions, and grapples) associated with the lifting and transferring of heavy loads. 
The trolley system includes the trolley, rails, pedestal, and control system. 

000-30R-MGR0-00400-000-001 A-68 March 2005 
The term cask refers to both the transportation cask and the site-specific cask, unless specified otherwise. 
Every facility may not use every component listed for each system. 
The term breach means an opening of the cask, canister, or WP initiating a Category 1 or Category 2 event sequence. 
BDBGM = beyond design basis ground motion; CHF = Canister Handling Facility; DBGM = design basis ground motion; DPC = dual-purpose canister; DOE = U.S. 
Department of Energy; DTF = Dry Transfer Facility; FHF = Fuel Handling Facility; HAM = horizontal aging module; HLW = high-level radioactive waste; HVAC = 
heating, ventilation, and air-conditioning; HEPA = high-efficiency particulate air; ITWI = important to waste isolation; MCC = motor control center; MCO = 
multicanister overpack; MSC = monitored geologic repository site-specific cask; SC = safety category; SNF = spent nuclear fuel; SRTC = site rail transfer cart; 
SSC = structure, system, or component; SSCs = structures, systems, and components; TCRRF = Transportation Cask Receipt and Return Facility; UPS = 
uninterruptable power supply; WNNRF = Warehouse and Non-Nuclear Receipt Facility; WP = waste package. 

000-30R-MGR0-00400-000-001 B-1 March 2005 
APPENDIX B 
DEFINITION OF SAFETY FUNCTIONS 
B.1 General 
Each SSC that is ITS that is credited in the prevention or mitigation of a seismically initiated 
event sequence is assigned a safety function (or functions) with regard to performance goals for 
the specific SSC during and after the initiating seismic event. This appendix defines the safety 
functions used in this report. These definitions of safety functions were obtained from Seismic 
Analysis for Preclosure Safety (BSC 2004a [DIRS 171470], Section 4). 
B.1.1 Safety Function: No Structural Collapse 
The no structural collapse safety function is assigned to facilities and structures assigned to 
either a DBGM-1 or DBGM-2 level. For seismic margin calculations, the function corresponds 
approximately to the state of large permanent distortion, short of collapse of a structure or 
facility, termed Limit State A. 
The no structural collapse safety function has the following performance goals during and after 
a seismic event: 
 No structural collapse occurs (i.e., column and support members remain upright, 
beams remain functional, and walls remain standing), and failure of the contents is 
not serious enough to cause severe injury or death, prevent evacuation, or induce a 
breach of a waste container. 
 Confinement of internal airflow is not required and may not be maintained. 
Concrete walls will remain standing, but may be extensively cracked; they may not 
maintain pressure differential with normal HVAC. Cracks will still provide a 
tortuous path for material release. The largest cracks are expected to be no greater 
than one-half in. 
 Distortion of the structure will be limited, but expected to be visible to the naked 
eye. 
 Components will remain anchored, but with no assurance that they will remain 
functional or easily repairable. 
An additional requirement of this safety function is that the failure of adjacent structures and 
other SSCs (whether ITS or not) shall be considered in seismic analyses, as appropriate, and 
shall not induce collapse of the designated structure. 
B.1.2 Safety Function: No Drop 
The no drop safety function is assigned to cranes assigned to a DBGM-2 level. The no-drop 
safety function has the following performance goals during and after a seismic event: 

000-30R-MGR0-00400-000-001 B-2 March 2005 
 The crane shall not release (or drop) a waste container or waste form either due to 
failure of crane components or controls due to a designated seismic event. 
 The crane, as a system, shall not collapse or fall down. The crane shall remain on 
its track or guide system (regardless if crane is holding a waste container or waste 
form at the time of the event). 
 Horizontal movement (swinging) of the cask or WP shall be restrained (if 
necessary) to preclude impacts with nearby walls and barriers. 
 The crane track or guide system shall remain intact and attached to the structure. It 
may be distorted and bent, however. 
 The crane shall not move in an uncontrolled manner or exceed its design speed 
limit. 
B.1.3 Safety Function: No Breach 
The no breach safety function is assigned to various waste containers assigned to either a 
DBGM-1 or DBGM-2 level. 
The no breach (leak tight) safety function has the following performance goals during and after a 
seismic event: 
 Containment of the waste form is maintained and no release or dispersement of 
radionuclides (either as gas or particulates) to the environment occurs. 
 Distortion and damage of the container will be limited. 
B.1.4 Safety Function: No Tipover 
The no tipover safety function is assigned to various SSCs handling casks and canisters (e.g., 
turntables and pedestals) assigned to either a DBGM-1 or DBGM-2 level. The no tipover safety 
function has the following performance goal during and after a seismic event: 
 The SSC shall not allow a tipover of a cask or canister (i.e., an overturn from an 
upright or normal position and impact the floor, ground, or other object), or tilting 
of the cask or canister resulting in an impact with an adjacent SCC that is ITS 
causing a domino effect. 
B.1.5 Safety Function: No Slapdown 
The no slapdown safety function is assigned to various SSCs handling casks and canisters 
(e.g., trolleys, WP transporters, transport locomotives, horizontal aging modules, site-specific 
cask transporters) assigned to either a DBGM-1 or DBGM-2 level. The no slapdown safety 
function has the following performance goals during and after a seismic event: 

000-30R-MGR0-00400-000-001 B-3 March 2005 
 The SSC shall not allow a slapdown or rapid drop of a cask or WP in transit (i.e., 
the fall of a cask or WP, a vertical distance and subsequent impact onto the floor, 
ground, or onto another object). 
 Any impacts to the cask or WP shall be within design specifications and, thereby, 
not induce a breach of the cask or WP in transit. 
 The SSC itself may sustain substantial damage and may no longer be operable. 
B.1.6 Safety Function: No Release 
The no release safety function is assigned to staging and storage racks assigned to either a 
DBGM-1 or DBGM-2 level. 
The no release safety function has the following performance goals during and after a seismic 
event: 
 No release or dispersement of radionuclides (either as gas and/or as particulates) to 
the environment due to shaking or deformation of the waste form or storage rack. 
 Distortion and damage of the waste form and rack(s) will be limited and will not 
preclude additional operations to retrieve the waste forms. 
B.1.7 Safety Function: No Failure 
The no failure safety function is assigned to various SSCs (e.g., limiters, collars, dampers) 
assigned to either a DBGM-1 or DBGM-2 level. The no failure safety function has the following 
performance goal during and after a seismic event: 
 The SSC will continue its designated safety function after a seismic event without 
significant degradation in the performance or requirement for repair. For structural 
elements, the load response shall be essentially elastic due to the seismic event. 
B.1.8 Safety Function: No Significant Cracking/Displacement 
The no significant cracking/displacement safety function is assigned to aging pads at the 
DBGM-2 level. The no significant cracking/displacement safety function has the following 
performance goals during and after a seismic event: 
 Aging pad is essentially intact. The concrete will remain structurally sound, but 
may contain several small cracks. The largest cracks are expected to be no greater 
than one-eighth in. and lengths shorter than 2 ft. 
 Distortion of the pad will be very limited and not expected to be immediately 
apparent to the naked eye. 
 Differential displacement across the pad shall be minimal, with differential 
displacements insufficient to cause a tipover of individual storage casks. 

000-30R-MGR0-00400-000-001 B-4 March 2005 
B.1.9 Safety Function: Controlled Failure 
The controlled failure safety function is assigned in special instances to SSCs (e.g., ventilation 
stacks) to preclude potential interactions with SSCs that are ITS. The controlled failure safety 
function has the following performance goals for ventilation stacks during and after a seismic 
event: 
 Failure of an SSC due to a seismic event shall not obstruct an open flow path to the 
environment of the corresponding ventilation system. 
 Failure of an SSC shall not impede the safety function of another SSC that is ITS. 
B.1.10 Safety Function: Shielding Integrity Remains Intact 
The shielding integrity remains intact safety function is assigned to shielding SSCs (e.g., shield 
view ports, shield windows, shield doors) at the DBGM-1 and DBGM-2 levels. The shielding 
integrity remains intact safety function has the following performance goals during and after a 
seismic event: 
 The SSC remains essentially intact and in-place, and provides sufficient (direct 
shine) shielding to permit workers to egress the area without receiving a significant 
dose (significant is defined as less than 10 percent of the worker dose limit). 
 Cracking of glass will be limited, and drainage of fluids (used in ports and windows 
for shielding) will be slow. 
B.1.11 Safety Function: Maintain Waste Form 
The maintain waste form safety function is assigned to fuel handling machines at either the 
DBGM-1 or DBGM-2 level. The maintain waste form safety function has the following 
performance goals during and after a seismic event: 
 The SSC continues to maintain (retain) the waste form. 
 The waste form remains intact and in-place. 
 Damage to the waste form is minimal. 
 Significant release or dispersement of radionuclides (either as gas and/or as 
particulates) to the environment due to shaking or deformation of the waste form is 
precluded. 

000-30R-MGR0-00400-000-001 B-5 March 2005 
B.1.12 Safety Function: No Criticality 
The no criticality safety function is assigned to various waste containers (e.g., casks, canisters, 
WPs) and staging and storage racks assigned to DBGM-2 level. 
For various waste containers, the no criticality safety function has the following performance 
goals during and after a seismic event: 
 The waste in the container shall remain nuclear subcritical as a result of a drop or 
impact within design limits with the most reactive credible configuration of the 
fissile material and moderation to the most reactive credible extent. 
 The container internal geometry shall retain the design waste configuration with 
only minor damage/distortion. 
For staging and storage racks, the no criticality safety function has the following performance 
goal during and after a seismic event: 
 The rack shall remain structurally intact (with minimal distortion of the rack) and 
prevent bare fuel assemblies (or other exposed waste forms) to become nuclear 
critical as a result, considering the most reactive credible configuration of the fissile 
material and moderation to the most reactive credible extent. 
B.1.13 Safety Function: No Runaway 
The no runaway (uncontrolled descent) safety function is assigned to transporters and 
locomotives assigned to the DBGM-1 and DBGM-2 levels. The no runaway safety function has 
the following performance goals during and after a seismic event: 
 The SSC shall stop the transport train (the trailer/car containing a waste form) after 
a seismic event (however, a tipover is not precluded). 
 The SSC shall not allow the speed of the transport train to exceed its maximum 
allowable limits. 
 The coupler shall remain connected between the locomotive and transport train. 
B.1.14 Safety Function: No Discharge 
The no discharge safety function is assigned to SSCs such as vent ducts, as well as HEPA 
filters and filter housings, which can contain a significant particulate dose and are assigned to 
either a DBGM-1 or DBGM-2 level. 
For filters, the no discharge safety function has the following performance goals during and after 
a seismic event: 
 No significant release or dispersement of radionuclides (particulates) to the 
immediate environment (to the structure interior or exterior) due to shaking of the 

000-30R-MGR0-00400-000-001 B-6 March 2005 
filter and/or deformation of the filter (housing) system occurs. A significant release 
is defined as a release that results in less than a small fraction of the applicable dose 
limit over a period of 24 hours. 
 No significant release or dispersement of radionuclides (particulates) back into the 
interior ventilation system (i.e., no back flow); this shall be precluded by 
valves/dampers or other appropriate devices. 
 External components of the system (e.g., housings and fans) shall be rigidly 
anchored to major building elements (walls, floors, partitions). 
 The system shall maintain its structural integrity, and distortion/damage of the 
housing and hangers (if applicable) will be limited. 
For vent ducts, the no discharge safety function has the following performance goals during and 
after a seismic event: 
 No significant release or dispersement of radionuclides (particulates) to the 
immediate environment. A significant release is defined as a release that results in 
less than a small fraction of the applicable dose limit over a period of 24 hours, and 
analyses shall consider potential accumulations within the duct re-entering the air 
stream. 
 The duct shall maintain effective confinement of internal airflow with minimal 
outflow through joints. 
 The duct shall maintain its structural integrity, and distortion/damage of the duct 
and hangers will be limited. 
B.1.15 Safety Function: No Derailment 
The no derailment safety function is assigned to trolley rails and rail tracks, which are assigned 
to either a DBGM-1 or DBGM-2 level. 
The no derailment safety function has the following performance goals during and after a seismic 
event: 
 No significant structural deformation of the rail occurs (i.e., the rails will not shear, 
heave, or warp) that is serious enough to cause a derailment or tipover of any waste 
transporter on the rail (e.g., WP trolley). 
 No significant failure of the rail occurs (e.g., shearing, separation) that could induce 
a derailment if a transporter would pass over the damaged section. 
 Distortion of the rail will be limited and not expected to be immediately apparent to 
the naked eye. 

000-30R-MGR0-00400-000-001 B-7 March 2005 
 The rail will remain, for the most part, anchored and functional (or easily 
repairable). 
 The rail system shall not impede the braking of any waste transporter on the rail. 
B.1.16 Safety Function: No Fall Down 
The no fall down safety function is assigned to large equipment (spent fuel handling machines, 
welders) that could impact SSCs if the specific equipment loses its anchorage and falls due to a 
seismic event. These SSCs can be assigned to either a DBGM-1 or DBGM-2 level. 
The no fall down safety function has the following performance goals during and after a seismic 
event: 
 The equipment, as a system, shall not collapse or fall down. The equipment shall 
remain on its track/guide system (if present). 
 Anchorage for the equipment shall maintain the equipment in-place. 
B.1.17 Safety Function: No Loss of Confinement 
The no loss of confinement safety function is assigned to facilities and structures assigned to 
either a DBGM-1 or DBGM-2 level where structural integrity and confinement after the seismic 
event must be credited for compliance or added for defense-in-depth. For seismic margin 
calculations, the function corresponds to the state of limited permanent distortion of a structure 
or facility, termed Limit State C. 
In the present dose consequence analysis, no credit is taken for confinement for limiting offsite 
dose to the public and, thereby, this safety function is not used. This definition was added for 
completeness. 
The no loss of confinement safety function has the following performance goals during and after 
a seismic event: 
 No structural collapse occurs (i.e., column and support members remain upright, 
beams remain functional, and walls remain standing), and failure of contents is not 
serious enough to cause severe injury or death, prevent evacuation, or induce a 
breach of a waste container. 
 Confinement of internal airflow is required and will be maintained. Concrete walls 
will remain standing, but may be cracked. This cracking however, is small enough 
to maintain the pressure differential with normal HVAC. The largest cracks are 
expected to be no greater than approximately one-eighth in. 
 Distortion of the structure will be very limited and not expected to be immediately 
apparent to the naked eye. 
 Components will remain anchored and functional or easily repairable. 

000-30R-MGR0-00400-000-001 B-8 March 2005 
An additional requirement of this safety function is that the failure of adjacent structures and 
other SSCs (whether safety-related or not) shall be considered in seismic analyses as appropriate 
and shall not induce collapse of the designated structure. 

000-30R-MGR0-00400-000-001 C-1 March 2005 
APPENDIX C 
LIFT HEIGHT LIMITS FOR CASKS AND CANISTERS 
The various casks, canisters, and WPs to be handled in the repository surface facilities shall be lifted by 
the various cranes in these facilities in accordance with the limits specified in 
Table C-1. 
Table C-I. Lift Height Limits 
Confinement Contents Lift Height Limit(s) (Note 1) Reference 
Transportation cask 
with impact limiters 
Any waste form 30 ft in the worst orientation above an 
essentially unyielding flat surface 
BSC 2005b Section 4.2.1 
DOE MCO 2 ft in any orientation above an 
essentially unyielding flat surface unless 
impact absorption feature is credited 
BSC 2005b Sections 5.1.1.18, 
4.2.2 
Naval SNF Canister 16 ft in any orientation above an 
essentially unyielding flat surface 
BSC 2005b Section 5.1.1.18 
Transportation cask 
without impact 
limiters; 
Any other waste form 23 ft in any orientation above an 
essentially unyielding flat surface 
BSC 2005b Section 5.1.1.18 
Site-specific cask Commercial SNF or 
DPC 
23 ft in any orientation above an 
essentially unyielding flat surface 
BSC 2005b Section 5.1.1.18 
DPC 23 ft in vertical orientation from the floor 
of the transportation cask or 
site-specific cask 
and 
2 ft in vertical orientation above the floor 
of the transfer cell 
BSC 2005b Section 5.1.1.43 
Standardized DOE 
SNF Canister 
23 ft in any orientation above an 
essentially unyielding flat surface 
and 
2 ft in vertical orientation above the floor 
of the transfer cell 
BSC 2005b Sections 5.1.1.14, 
4.2.2 
DOE MCO 23 ft in vertical orientation (3 degrees or 
less off vertical) onto an essentially flat 
unyielding surface 
and 
2 ft in any orientation above an 
essentially unyielding flat surface 
BSC 2005b Sections 5.1.1.15, 
4.2.2 
Unconfined 
DOE HLW Canister 23 ft in vertical orientation above the 
floor of a cask, WP, staging rack or 
staging pit 
and 
2 ft in vertical orientation above the floor 
of the transfer cell 
BSC 2005b Section 5.1.1.24 

Table C-I. Lift Height Limits (Continued) 
000-30R-MGR0-00400-000-001 C-2 March 2005 
Confinement Contents Lift Height Limit(s) (Note 1) Reference 
Unconfined 
(continued) 
Naval SNF Canister 28 ft in vertical orientation above the 
floor of a cask or WP 
and 
2 ft in vertical orientation above the floor 
of the transfer cell 
BSC 2005b Section 5.1.1.42 
Waste package 
(sealed; trunnion 
collars installed) 
Naval Long SNF 
Canister 
3.3 ft in vertical orientation onto an 
essentially unyielding flat surface 
and 
1.6 ft for tipover from an elevated 
surface onto an essentially unyielding 
flat surface 
BSC 2005b Sections 5.1.3.12 
and 5.1.3.9 
Any waste form 7.8 ft in a horizontal orientation onto an 
essentially unyielding flat surface 
and 
6.5 ft in a vertical orientation onto an 
essentially unyielding flat surface 
(except naval long WP) 
and 
6.5 ft for tipover from an elevated 
surface onto an essentially unyielding 
flat surface (except naval long WP) 
BSC 2005b Sections 5.1.3.12 
and 5.1.3.9 
Waste package 
(sealed; on 
emplacement pallet; 
trunnion collars not 
installed) 
Any waste form 6.5 ft from bottom of the pallet to an 
essentially unyielding flat surface, in a 
horizontal orientation 
BSC 2005b Sections 5.1.3.8 
and 5.1.3.12 
Waste package 
(unsealed) 
DOE MCO 2 ft in any orientation above an 
essentially unyielding flat surface 
BSC 2005b Sections 5.1.1.52, 
4.2.2 
Naval SNF Canister 2 ft in any orientation above an 
essentially unyielding flat surface 
BSC 2005b Sections 5.1.1.52, 
5.1.1.18 
Any other waste form 23 ft in any orientation above an 
essentially unyielding flat surface 
BSC 2005b Section 5.1.1.52 
Note 1: These lift height limits can be exceeded if an appropriate impact absorption feature is credited