DOE/CBFO-11-3479

Panel Closure System Design

Planned Change Request to the

EPA 40 CFR Part 194 Certification of

the Waste Isolation Pilot Plant

September 26, 2011
i

Table of Contents

Acronyms....................................................................................................................................... ii

Glossary of Terms........................................................................................................................iii

Executive Summary..................................................................................................................... iv

1.0 Introduction............................................................................................................................ 1

1.1 PCS Background................................................................................................................... 2

2.0 Nature and Scope of This Request ....................................................................................... 3

2.1 Scope of the Proposed Design Change ................................................................................. 3

2.2 Rationale for the Proposed Request...................................................................................... 4

3.0 Long-Term Performance of the ROMPC............................................................................. 7

3.1 Earlier Panel Closure Investigations..................................................................................... 7

3.2 Recent PA Analysis.............................................................................................................. 8

3.3 Results from the PC3R PA................................................................................................. 11

4.0 Conclusions........................................................................................................................... 13

References.................................................................................................................................... 14

Attachment A: Radiolytic Hydrogen Generation and Methanogenesis in WIPP: An Empirical 

Point of View

Attachment B: Effective Permeability of the Redesigned Panel Closure System

Attachment C: Summary Report for the AP-151 (PC3R) Performance Assessment, Revision 1
ii

Acronyms

CBFO Carlsbad Field Office

CCA Title 40 CFR Part 191 Compliance Certification Application for the Waste 

Isolation Pilot Plant (DOE, 1996)

CCDF Complementary Cumulative Distribution Function

CFR Code of Federal Regulations

DOE U.S. Department of Energy

DRZ Disturbed Rock Zone

EPA U.S. Environmental Protection Agency

NMED New Mexico Environment Department

OPC Ordinary Portland Cement

PA Performance Assessment

PABC Performance Assessment Baseline Calculations

PAVT Performance Assessment Verification Test

PCS Panel Closure System

PCR Planned Change Request

PC3R Panel Closure Redesign and Repository Reconfiguration Performance 

Assessment

RCRA Resource Conservation and Recovery Act

ROM Run-of-Mine

ROMPC Run-of-Mine Panel Closure

SMC Salado Mass Concrete

TRU Transuranic

VOC Volatile Organic Compound

WIPP Waste Isolation Pilot Plant
iii

Glossary of Terms

40 CFR Part 191 Environmental Radiation Protection Standards for the Management and 

Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive 

Wastes; Final Rule (EPA, 1993).

40 CFR Part 194 Criteria for the Certification and Re-Certification of the Waste Isolation 

Pilot Plant’s Compliance with the 40 CFR Part 191 Disposal Regulations: 

Certification Decision; Final Rule (EPA, 1998a).

Certification Any action taken by the Administrator of the U.S. Environmental 

Protection Agency under Section 8(d) of the Waste Isolation Pilot Plant 

Land Withdrawal Act.

Run-of-mine Salt produced from mining operations in the WIPP facility underground 

(ROM) salt without undergoing any additional treatment.
iv

Executive Summary

The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) requests that the U.S. 

Environmental Protection Agency (EPA) modify Condition 1 of the Final Certification 

Rulemaking for 40 CFR Part 194 (EPA, 1998a). This condition specifies that the Panel Closure 

System (PCS) to be used in the Waste Isolation Pilot Plant (WIPP) repository should be the one 

designated as “Option D” in the Compliance Certification Application (CCA) (DOE, 1996), and 

that the concrete components of that closure should be constructed using Salado Mass Concrete

(SMC). In the 12 years since the WIPP facility commenced waste handling operations the DOE 

has acquired considerable experience in the behavior of the underground, and in the nature and 

behavior of disposed transuranic (TRU) waste, including the potential for generation of 

explosive gases. In addition large scale testing has demonstrated that SMC cannot meet the 

design requirements for the closure as specified in the original certification application (WTS, 

2003). The DOE has established a revised design which is much simpler and easier to construct. 

Accordingly the DOE is requesting that Condition 1 be changed, and that the new closure design 

be approved for use in all panels. 

The DOE is making this proposal based on the following rationale:

The primary purpose of the PCS is to meet the Resource Conservation and Recovery Act 

(RCRA) requirements for closure of a disposal unit as defined in the WIPP Hazardous Waste 

Facility Permit (Permit). As noted in the CCA (Section 3.3.2), “Panel closures have been 

included for the purpose of Resource Conservation and Recovery Act (RCRA) disposal unit 

closure and to prevent potentially unacceptable levels of volatile organic compound release 

during waste management operations.”

The panel closure system was not designed or intended to support long-term repository 

performance. However it is important to be able to represent the long-term behavior of the 

closure system in performance assessment (PA) calculations, in so far as it affects the flow of 

brine between waste panels under the various PA scenarios. 

Attempts to develop SMC have shown that the material as specified did not meet the 

performance requirements laid out in the design specifications (WTS, 2003).

The simpler design will meet the same operational performance requirements of the Option D 

closure and will be simpler construction, will have less adverse impact on waste disposal 

operations and will be less expensive to construct.

The analyses provided with this planned change request (PCR) demonstrate that long-term 

releases are insensitive to a broad range of panel closure permeabilities, and that the impact of 

the proposed new closure design on long-term performance is negligible.

The revised design, known as the Run-of-Mine Panel Closure (ROMPC) comprises 100 ft of 

run-of-mine (ROM) salt backfill placed between two typical underground bulkheads. The 

construction methods and materials to be used to implement the design have been proven in 

previous mining and construction projects. The fabrication, installation, and maintenance of 

bulkheads are standard mining practices. The ROM salt backfill will be pushed up tight to all salt 
v

surfaces of the drifts, including the back or roof. Over time creep closure of the drifts will cause 

the salt backfill to consolidate to a condition approaching intact salt with a low permeability.

Performance Assessment (PA) results demonstrate that the long-term performance of the revised 

design will be essentially the same as that to be expected from the Option D closure. Based on an 

analysis of creep and salt consolidation data, the permeability of the ROMPC is expected to fall 

within the range analyzed in earlier PAs. That is the short-term permeability might be high, but 

after 100 years, as the salt backfill consolidates further under the influence of creep closure of 

the entries, the permeability will approach that assumed for the Option D closure. A recent PA 

termed the Panel Closure Redesign and Repository Reconfiguration Performance Assessment 

(PC3R) has been run which combines a proposed reconfiguration of the repository as well as the 

modified panel closure system. Comparison of the PC3R results with that included in the most 

recent recertification (PABC-2009; DOE, 2009) indicated that the overall mean complimentary 

cumulative distribution functions (CCDF) obtained in the two analyses are virtually identical. 

The panel closure design and repository configuration changes investigated in the PC3R PA 

therefore have only a very minor impact on performance. It is also noted that the results of an 

earlier impact analysis in which a panel closure system consisting of 100 ft of ROM salt and a 30 

ft explosion wall give a similar result (Vugrin and Dunagan, 2006). In this PA it was assumed 

that the explosion wall had no influence on long-term permeability which was given the same 

values as in PC3R. These results indicated that without the reconfiguration included in the PC3R 

PA the change in panel closure design had only a minor effect on long-term performance.

Based on these analyses and results, the DOE is requesting that the EPA remove Condition 1 as 

presented in the Final Rule (EPA, 1998a), and accept the revised design for panel closures as 

described herein.
Page 1 of 15

1.0 Introduction

The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) is submitting this Planned 

Change Request (PCR) to the U.S. Environmental Protection Agency (EPA) to request 

modification of Condition 1 of the Final Certification Rulemaking for 40 CFR Part 194. 

Specifically, the Final Certification Rulemaking, Appendix A (EPA, 1998a), states:

In accordance with the Agency’s authority under 194.4(a), the certification of compliance is 

subject to the following conditions:

Condition 1: 194.14(b), Disposal system design, panel closure system. The Department shall 

implement the panel seal design designated as Option D in Docket A-93-02, Item II-G-1 

(October 29, 1996, Compliance Certification Application submitted to the Agency). The Option 

D design shall be implemented as described in Appendix PCS of Docket A-93-02, Item II-G-1, 

with the exception that the Department shall use Salado mass concrete (consistent with that

proposed for the shaft seal system, and as described in Appendix SEAL of Docket A-93-02, 

Item II-G-1) instead of fresh water concrete.

The Option D closure consists of the installation of a concrete block explosion isolation wall, 

removal of the majority of the disturbed rock zone (DRZ) in the area of the closure, and 

emplacement of a large Salado Mass Concrete (SMC) monolith. This closure would be installed 

in each panel of the repository after waste emplacement in that panel is completed. 

In addition to specifying the use of the “Option D” Panel Closure System (PCS) design in 

Condition 1, the EPA allowed the DOE to revisit the design of the PCS. Specifically, in the 

preamble to the Final Certification Rulemaking (EPA, 1998a), the EPA stated:

Nothing in this condition precludes DOE from reassessing the engineering of the panel seals at 

any time. Should DOE determine at any time that improvements in materials or construction 

techniques warrant changes to the panel seal design, DOE must inform EPA. If EPA concurs, 

and determines that such changes constitute a significant departure from the design on which 

certification is based, the Agency is authorized under 194.65 to initiate a rulemaking to 

appropriately modify the certification.

Based upon 12 years of experience in the disposal of waste in the underground, including 

observation and monitoring of the behavior of active and closed panels, together with 

engineering issues associated with Option D closure construction with SMC, the DOE has 

reassessed the engineering of the panel closure. As a result, the DOE has developed an alternate 

design which will not have an effect on the long-term performance of the repository, and will 

meet the requirements of the New Mexico Environment Department (NMED) in regard to 

operational period performance. Additionally, this new design will be simpler and can be 

installed at a significantly lower cost than the currently approved design. Accordingly, the DOE 

is requesting that this revised design be approved and Condition 1 of the 1998 Certification 

Decision be modified as appropriate.

The revised panel closure design, known as the Run-of-Mine Panel Closure System (ROMPC), 

was developed as part of CBFO’s ongoing review of engineering aspects of the repository. The 
Page 2 of 15

design involves the use of bulkheads at either end of a 100 foot backfill comprised of run-ofmine (ROM) salt. The ROM salt backfill will be pushed up tight to all salt surfaces of the drifts, 

including the back or roof. 

Section 2.0 of this request provides a description of the nature and scope of the proposed change 

to the design of the closure system. Section 3.0 provides an analysis of the long-term 

performance of the repository using this design, and discusses the results of recent performance 

assessment (PA) calculations which evaluate this performance. The analyses provided with this 

request demonstrate that long-term repository releases are unchanged over a broad range of panel 

closure permeabilities, and that the impact of the proposed new closure design on long-term 

performance is negligible relative to the performance of the Option D design.

In addition, three attachments are included with this request. Attachment A, Radiolytic 

Hydrogen Generation and Methanogenesis in WIPP: An Empirical Point of View summarizes 

monitoring data from closed panels, and Attachment B, Effective Permeability of the Redesigned 

Panel Closure, describes the expected behavior of the ROMPC in the context of the modeling 

results. Attachment C, Summary Report for the AP-151 (PC3R) Performance Assessment

Revision 1, provides the results of the recent PA calculations conducted to demonstrate the 

performance of this closure. 

1.1 PCS Background 

The Compliance Certification Application (CCA: DOE, 1996) in Chapter 3 and Appendix PCS 

established the purpose of installing panel closures. The introduction to the facility description in 

Chapter 3 states, 

The DOE will close each panel of waste with a panel closure system to provide for 

operational protection of workers, the public, and the environment from emplaced waste. 

In addition, Section 3.3.2 states: 

Panel closures have been included for the purpose of Resource Conservation and 

Recovery Act (RCRA) disposal unit closure and to prevent potentially unacceptable levels 

of volatile organic compound release during waste management operations. The panel 

closure system was not designed or intended to support long-term repository 

performance.

In the design report included in the CCA as Appendix PCS several designs were presented 

(Options A – D). These designs were to be used depending on the age and condition of the panel 

entries. The design report specified the use of Ordinary Portland Cement (OPC) for the concrete 

elements, but allowed the use of Salado Mass Concrete (SMC) as an option. SMC is a salt 

saturated concrete developed for use in the Shaft Seals and described in Appendix SEAL of the 

CCA. As noted above, in its Final Rule (EPA, 1998a) the EPA specified the use of Option D for 

all closures, and also the use of SMC rather than OPC. 

During a series of test pours, it was determined that SMC as formulated would not be able to meet 

the specification requirements in the design report (WTS, 2003). As a result the DOE has, with the 

approval of EPA and NMED, emplaced temporary closures in various filled panels while gathering 
Page 3 of 15

information for a revised final closure. Panels 1 and 2 have used the explosion wall component 

from Option D, combined with periodic monitoring and assessment of the closure performance. 

Panels 3 – 4 use a simpler temporary closure comprising a ventilation bulkhead and a substantial 

barrier. These simpler closures have been used, again with the approval of EPA and NMED, to 

allow monitoring of potential explosive gas generation in the closed panels. This monitoring has 

established that the measured concentrations of methane and hydrogen are far below the 

minimum explosive concentrations for these gases, thereby allowing simplification of the design 

which is presented here (Attachment A). Panel 5 is currently undergoing closure, beginning with 

the explosion wall component. Option D continues to be the WIPP baseline panel closure design 

while the EPA considers this PCR.

2.0 Nature and Scope of This Request

2.1 Scope of the Proposed Design Change

The proposed design change presented here affects only the design of the panel closure system, 

as detailed in Condition 1 of the Final Certification (EPA, 1998a) and in the Permit (NMED, 

2010) issued by the NMED. Condition 1 currently prescribes the installation of Option D with 

SMC. This design consists of emplacing a 12-foot concrete block explosion wall, removing 

most of the DRZ in the area of the closure, and emplacing a large concrete monolith (26 feet 

long). The concrete monolith would be keyed into the surrounding salt and the upper 

concrete/salt interface would be grouted. Figure 1 is a schematic representation of Option D 

provided in the CCA, Attachment PCS (DOE, 1996). 

During the time since the initial certification of the WIPP facility, the DOE has reviewed various 

aspects of the required design and as a result has developed a new design which will be, easier to 

install, and less expensive while still achieving the performance objectives of protecting workers, 

the public and the environment. Information developed during this period include the testing of 

the SMC formulation specified in the CCA, Appendix SEAL and the development of a 

monitoring program to establish whether explosive concentrations of gas could develop in closed 

panels. The SMC testing (WTS, 2003) showed that the material as specified could not meet the 

performance requirements outlined in Appendix PCS, while the gas monitoring has shown that 

neither methane nor hydrogen concentrations approach anywhere near the lower explosive limits 

of these gases (Attachment A). Specifics of the rationale for the design change are given in the 

next section.

As a result of these activities, as well as the monitoring of the repository performance during its 

12 years of operation, it has been determined that a simpler design is appropriate, and will be 

equally effective in meeting the performance requirements of the closure system. The ROMPC, 

shown in Figure 2, has two components: two bulkheads and a ROM salt backfill. The 

construction methods and materials to be used to implement the design have been proven in 

previous mining and construction projects. The ROM salt backfill will be pushed up to be in 

contact with the salt surfaces of the drifts, including the back or roof. A variety of techniques are 

available for placing the ROM salt. The bulk of the salt can be placed using load-haul-dump 

units and final placement against the back could use flingers or blowers. The ROM salt will be 

placed until the entire drift is filled over a minimum distance of 100 feet. Over time, creep 

closure of the drifts will ensure that the salt backfill consolidates to a condition approaching 

intact salt with a low permeability (Attachment B). The fabrication, installation, and maintenance 
Page 4 of 15

of ventilation bulkheads, such as those proposed for the closure, are standard practices at the 

WIPP facility.

2.2 Rationale for the Proposed Request

The CBFO is making this proposal based on the following rationale:

The primary purpose of the PCS is to control volatile organic compound (VOC) emissions 

during the operational life of the facility. The panel closure system was not designed or intended 

to support long-term repository performance. However it is important to be able to represent the 

long-term behavior of the closure system in performance assessment (PA) calculations, in so far 

as it affects the flow of brine between waste panels under the various PA scenarios.

Attempts to develop SMC have shown that the material as specified did not meet the 

performance requirements in Appendix PCS if prepared according to the specifications in 

Appendix SEAL (WTS, 2003).

An evaluation of the construction means and methods required to emplace Option D have 

determined that it will be hazardous to those involved in its construction, while the proposed 

simpler design will meet the same operational performance requirements of this closure (NMED 

Attachment G, see G-1e(1)). 

The design of the ROMPC reduces complexity, enhances constructability, reduces the impacts 

on on-going repository operations, and reduces construction cost.

The analyses provided with this request, discussed in Section 3, and Attachment C, demonstrate 

that long-term releases are insensitive to a broad range of panel closure permeabilities, and that 

the impact of the proposed new closure design on long-term performance is negligible relative to 

the performance of the Option D design.
Page 

5 of 15

Concrete Barrier

Explosion-Isolation Wall

Waste Disposal Side

Figure 1. Option D Panel Closure System
Page 6 of 15
Page 7 of 15

3.0 Long-Term Performance of the ROMPC

3.1 Earlier Panel Closure Investigations

During the certification process in 1996 for the CCA, the CBFO used a model for the PA 

calculations with equal panel closure and DRZ permeability of 10-15 m

2

to demonstrate 

compliance with 40 CFR Part 191, Subparts B and C. As part of the EPA certification decision, a 

second EPA-mandated PA was run, the Performance Assessment Verification Test (PAVT) 

(McKinnon and Freeze, 1997a and 1997b) in which the panel closure retained a permeability of 

10-15 m

2

, but the DRZ was represented by a permeability which could vary between 10-12.5 and 

10-19.4 m

2

. The Option D panel closure design, mandated by EPA in Condition 1 of its 

certification of the WIPP in 1998, was not explicitly represented in the PA for the CCA or for the 

PAVT.

The Option D panel closure was introduced explicitly in an impact assessment in 2002 (Hansen, 

2002). This assessment analyzed the panel closure's effects on repository performance. In this 

analysis, two panel closure cases were considered: one case represented the mandated Option D 

panel closure design, and a second case is based on the generic panel closure included in the PAs

conducted for the CCA and the PAVT. The primary distinction between these two panel closure 

cases is the permeability of the panel closure material, which is quite low in the case of the 

Option D panel closure to fairly permeable in the CCA and PAVT panel closure case. 

This impact assessment used the PAVT grid and developed an effective permeability for the 

panel closure. This effective permeability is a combination of the permeability for the concrete 

monolith and the open drift/explosion wall permeabilities surrounding the monolith. The 

concrete permeability was assigned a constant value equal to the mode of the distribution for 

SMC, 1.78 x 10-19 m

2

. The effective permeabilities, the porosity, and the initial brine saturation

of the two closures are shown in Table 1. It was found that releases for the Option D panel 

closure case and for the CCA/PAVT panel closures were nearly identical. This analysis 

concluded that releases from the repository were not sensitive to the permeability of the panel 

closures (Hansen 2002, Executive Summary).

Table 1. Effective Panel Closure Properties for the Panel Closure Impact Assessment.

Parameter CCA/PAVT Closure Option D Closure

Permeability (along the drift) 10-15 m

2

9.01 x 10-19 m

2

Permeability (perpendicular to the drift) 10-15 m

2

1.93 x 10-13 m

2

Porosity 0.075 0.15

Initial Brine Saturation 0.99 0.21

The results of this modeling established the long-term performance of the repository within a 

broad range of permeabilities for different panel closure configurations. Modeling completed 

with the Option D design represents a low-permeability closure, and the original PA results for 

the CCA and PAVT represented a high-permeability closure. 

Based on an analysis of creep closure and salt consolidation data (Attachment B), the long-term 

permeability of the ROMPC is expected to fall near a value analyzed in the impact assessment. 

Within the first 100 years after closure installation, the effective permeability would be relatively 

high, but after 100 years, as the salt backfill consolidates further under the influence of creep 
Page 8 of 15

closure of the entries, the permeability will fall near the value assumed for the Option D closure 

in the 2002 PA. For this reason the influence of the ROMPC design on long-term repository 

performance is expected to be negligible, similar to the results for other closure designs assumed

in earlier PAs. This result is again confirmed by the most recent PA calculations, as discussed 

below.

3.2 Recent PA Analysis

The DOE is in the process of submitting two PCRs to the EPA that propose changes to the 

repository. The first PCR is that discussed here, centered on the new design of the WIPP panel 

closure system. The second PCR (DOE, 2011) proposes the relocation of future waste panels 9 

and 10 to the south end of the repository ( i.e. south of panels 4 and 5) where they will be 

denoted as panels 9A and 10A. With panels 9 and 10 relocated, the current repository 

configuration will be modified to one with an open central drift area with panel closures installed 

only at the end of filled waste panels. In order to evaluate the effects of these changes on longterm performance, the DOE has conducted a single PA, called the PC3R PA, to determine the 

overall impact of the repository changes proposed in the two PCRs. Impacts of these changes 

are determined by way of a comparison of normalized releases and probabilities to those 

calculated in the current PA baseline from the second recertification application (DOE, 2009), 

called the Performance Assessment Baseline Calculation-2009 (PABC-2009) (Clayton et. al., 

2009). The results from the PC3R PA and a comparison with the PABC-2009 are discussed in 

Camphouse et al., 2011 “Summary Report for the AP-151 (PC3R) Performance Assessment, 

Revision 1” which is included as Attachment C, and the results are briefly summarized here. 

In the PC3R PA Panels 9 and 10 are relocated south of panels 4 and 5 and are denoted as panels 

9A and 10A. This new configuration is shown in Figure 3. In addition to this reconfiguration, 

the PC3R PA changes the representation of the panel closures for panels 1through 8, 9A, and 

10A. Panel closures are proposed to be modified from the current “Option D” design to that of a 

new design consisting of 100 feet of ROM salt emplaced in front of a bulkhead on the waste 

disposal side. The majority of PC3R PA parameter changes are due to the changes in the panel 

closure design, as discussed below. 

The PC3R PA representation of the panel closure system has initial and short-term permeabilities 

and porosities that are significantly different from the permeabilities and porosities expected to 

be present for the vast majority of the 10,000 year regulatory timeframe. The short-term 

permeability of the panel closures is assumed to be controlled by the bulkheads at either end of 

the ROM salt backfill, and will have a high value, assumed to be 10-11m

2

. It is assumed that this 

permeability value will remain in effect for an initial time period of 100 years after closure. This 

initial time period is selected to be consistent with the length of time required for the porosity of 

the ROM salt used in the panel closures to consolidate to less than 5 percent, and is based on 

numerical simulations which have demonstrated this period of time to be less than 100 years 

(Callahan and DeVries, 1991). This time duration is also consistent with that proposed during 

the impact assessment for the 2002 panel closure redesign (Hansen and Thompson, 2002: 

Attachment B).
Page 9 of 15

The permeability of the panel closure after 100 years is assumed to have decreased significantly 

due to the consolidation of the ROM salt driven by the creep closure of the entries. The values 

used for this permeability have been based on a panel closure redesign impact assessment 

performed in 2006 (Vugrin and Dunagan, 2006). In that analysis, the panel closure design 

consisted of 100 feet of ROM salt emplaced against a 30-foot mortared, solid concrete block wall 

on the waste disposal side. The parameter distributions for the long-term permeability of the 

ROM salt component developed during the impact assessment in 2006 (Vugrin, Hansen, and 

Thompson, 2006) are used to describe the long-term permeability of the panel closure 

implemented in the PC3R PA. The resulting probability distribution is shown in Table 2. 

The value for permeability of the portion of the DRZ directly above and below the panel closure 

system is based on the analysis of Stein (2002). In the PC3R analysis the properties of this 

portion of the DRZ were prescribed so as to reflect the changing material properties of the 

redesigned closure system as a function of time. During the first 100 years while the ROM salt 

panel closures are reconsolidating, it is assumed that the DRZ directly above and below the panel 

closure is unaffected by the changing panel closure properties. Values used in this time frame 

are given in Table 2. After the first 100 years, permeability values of the DRZ above and below 

the panel closure are prescribed so as to be consistent with the permeabilities of the 

reconsolidated panel closures; that is, it is assumed that the creep closure which consolidates the 

ROM salt also leads to backpressure that facilitates the healing of the DRZ. As a result, the DRZ 

permeabilities around the closure are assigned the permeability distributions given to material 

PCS_T2 as shown in Table 3. 

Table 2: Log of Intrinsic Permeability Values used for the DRZ-PCS around the PCS in the PC3R PA for the 

first 100 years.

Parameter (units) Description Distribution Statistic Value

DRZ_PCS:PRMX_LOG (log(m2))

DRZ_PCS:PRMY_LOG (log(m2))

DRZ_PCS:PRMZ_LOG (log(m2))

Log of 

intrinsic 

permeability, 

x,y,z

directions

Triangular Mean -16.0

Median -16.0

Stan. Deviation 2.0

Minimum -19.4

Maximum -12.5

Table 3: Log of Intrinsic Permeability Values used for the long-term PCS in the PC3R PA

Parameter (units) Description Distribution Statistic Value

PCS_T2:PRMX_LOG (log(m2))

PCS_T2:PRMY_LOG (log(m2))

PCS_T2:PRMZ_LOG (log(m2))

Log of intrinsic 

permeability, 

x,y,z directions

Triangular Mean -20.2

Mode -20.2

Stan. Deviation 1.06

Minimum -22.8

Maximum -17.6
Page 10 of 15

Figure 3: WIPP Layout Modeled in PC3R PA
Page 11 of 15

3.3 Results from the PC3R PA

The total normalized releases for the PC3R PA, which combines the proposed reconfiguration of 

the repository and the modified panel closure system, are represented in Figure 4 as a mean 

CCDF. This figure also presents the results of the most recent recertification PA (PABC-2009, 

Clayton et al., 2009) which used the Option D panel closure design. As seen in that figure, the 

total mean normalized releases obtained in the two analyses are virtually identical for normalized 

release values less than approximately 0.1 EPA units. For normalized releases between 0.1 and 

1.0 EPA units, the overall total release mean CCDF curve obtained in the PC3R PA is slightly 

above that calculated in the PABC-2009. For releases greater than 1 EPA unit, the CCDF curve 

obtained in the PABC-2009 is higher than that found in the PC3R PA. The results from the 

PC3R PA demonstrate that the cumulative changes for the new panel closure design and for the 

revised repository configuration produce only slight changes in total mean normalized releases 

relative to the current PA baseline, the PABC-2009. The small differences between the PABC2009 and the PC3R PA are due to changes in direct brine releases, as discussed in Camphouse et 

al., 2011 (Attachment C).

A comparison of the statistics on the overall mean for total normalized releases obtained in the 

PC3R PA and the PABC-2009 can be seen in Table 4. At a probability of 0.1, values obtained 

for mean total releases are identical in both analyses. At a probability of 0.001, the decrease in 

direct brine releases (DBRs) in the PC3R PA results in a decrease in the mean total release by 

approximately 0.21 EPA units. Reductions are also seen in the upper and lower 95% confidence 

limits at a probability of 0.001 when compared to the PABC-2009 results. 

Table 4: PC3R PA and PABC-2009 Statistics on the Overall Mean for Total Normalized Releases in EPA 

Units at Probabilities of 0.1 and 0.001

Probability Analysis Mean Total

Release

90th

Percentile

Lower

95% CL

Upper

95% CL

Release

Limit

0.1 PC3R PA 0.09 0.16 0.09 0.10 1

PABC-2009 0.09 0.16 0.09 0.10 1

0.001 PC3R PA 0.89 1.00 0.34 1.41 10

PABC-2009 1.10 1.00 0.37 1.77 10

Finally it is noted that the results of the earlier impact analysis in which a PCS consisting of 100 

ft of ROM salt and a 30 ft explosion wall also found that normalized releases were insensitive to 

the panel closure design (Vugrin and Dunagan, 2006). In this 2006 impact analysis, it was 

assumed that the explosion wall had no influence on long-term permeability of the panel closure 

system, and the ROM salt backfill had the same permeability values as in the PC3R PA. These 

results indicated that, without the reconfiguration included in the PC3R PA, the change in panel 

closure design had only a minor effect on long-term performance.
Page 12 of 15

Figure 4: PC3R PA and PABC-2009 Overall Mean CCDFs for Total Normalized Releases
Page 13 of 15

4.0 Conclusions

As a result of increased understanding of the repository and the stored waste obtained over 12 

years of operation, the DOE has determined that a revision of the approved panel closure design 

can be made. The revised design described in this PCR will enhance constructability, reduce the 

impacts on on-going repository operations, and reduce construction cost. A change in the design 

specified in Condition 1 of the Final Rule (EPA, 1998a) is also required because of the problems 

in manufacturing SMC to the specifications in the CCA while meeting the design requirements 

of the Option D design.

An analysis of the results of earlier PAs suggests that this revised design will have essentially the 

same impact on long-term performance as the option D design. This is supported by new PA 

results in which the performance of the revised design is explicitly modeled, together with a 

proposed reconfiguration of Panels 9 and 10.

Based on these analyses and results, the DOE is requesting that the EPA remove Condition 1 as 

presented in the Final Rule (EPA, 1998a), and accept the revised design for panel closures as 

described herein.
Page 14 of 15

References

Callahan, G.D. and K.L. DeVries. 1991. Analysis of Backfilled Transuranic Waste Disposal 

Rooms. SAND91-7052. Sandia National Laboratories, Carlsbad, New Mexico.

Camphouse, R. C., D. J. Clayton, D.J. Kicker, and J. J. Pasch. 2011. Summary Report for the 

AP-151 (PC3R) Performance Assessment, Revision 1, Sandia National Laboratories, Carlsbad, 

New Mexico, ERMS 555489.

Clayton, D.C., R. C. Camphouse, J. W. Garner, A. E. Ismail, T. B. Kirchner, K. L. Kuhlman, and 

M. B. Nemer. 2010. Summary Report of the CRA-2009 Performance Assessment Baseline 

Calculation, Revision 1, Sandia National Laboratories, Carlsbad, New Mexico, ERMS 553039.

DOE (U.S. Department of Energy). 1996. Title 40 CFR Part 191 Compliance Certification 

Application for the Waste Isolation Pilot Plant, DOE/CAO-1996-2184, U.S. Department of 

Energy, Carlsbad Area Office, Carlsbad, New Mexico.

DOE (U.S. Department of Energy), 2009. Title 40 CFR Part 191 Compliance Re-Certification 

Application for the Waste Isolation Pilot Plant, DOE/CBFO, U.S. Department of Energy, 

Carlsbad Field Office, Carlsbad, New Mexico.

DOE (U.S. Department of Energy), 2011. Planned Change Request, Waste Isolation Pilot Plant 

Repository Reconfiguration, U.S. Department of Energy, Carlsbad Field Office, Carlsbad, New 

Mexico. 

EPA (U.S. Environmental Protection Agency). 1993. Environmental Radiation Protection 

Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic 

Radioactive Wastes; Final Rule, Federal Register, Vol. 58, No. 242, pp. 66398-66416, 

December 20, 1993, U.S. Environmental Protection Agency, Office of Radiation and Indoor Air, 

Washington, D.C. 

EPA (U.S. Environmental Protection Agency). 1998a. Criteria for the Certification and 

Re-Certification of the Waste Isolation Pilot Plants Compliance with the 40 CFR Part 191 

Disposal Regulations: Certification Decision; Final Rule, Federal Register, Vol. 63, No. 95, 

pp. 27353-27406, May 18, 1998, U.S. Environmental Protection Agency, Office of Air and 

Radiation, Washington, D.C.

Hansen, C.. 2002. Analysis Report for the Panel Closure Impact Assessment, Revision 1, Sandia 

National Laboratories, Carlsbad, New Mexico, ERMS 523935.

MacKinnon, R. and G. Freeze. 1997a. Summary of EPA-Mandated Performance Assessment 

Verification Test (Replicate 1) and Comparison with the Compliance Certification Application 

Calculations, Revision 1, Sandia National Laboratories, Albuquerque, New Mexico, 

ERMS 422595.
Page 15 of 15

MacKinnon, R. and G. Freeze. 1997b. Supplemental Summary of EPA-Mandated Performance 

Assessment Verification Test (All Replicates) and Comparison with the Compliance Certification 

Application Calculations, Revision 1, Sandia National Laboratories, Albuquerque, New Mexico, 

ERMS 414880.

NMED (State of New Mexico Environment department). 2010. Hazardous Waste Facility 

Permit, New Mexico Environment Department, Water and Waste Management Division.

Stein, J.S. 2002. Analysis Plan for Calculations of Salado Flow: Technical Baseline Migration 

(TBM) AP-086. Sandia National Laboratories, Carlsbad, New Mexico, ERMS 520612.

Vugrin, E.D. and S.C. Dunagan. 2006. Analysis Package for the Impact Assessment of the 

Redesigned WIPP Panel Closure. Sandia National Laboratories, Carlsbad, New Mexico, ERMS 

543865.

Vugrin, E., F., Hansen, and B. Thompson.. 2006. Recommendation and Justification of 

Parameter Values Required for Representation of the Redesigned Panel Closure System, Memo 

to David Kessel dated March 23, 2006, Sandia National Laboratories, Carlsbad, New Mexico, 

ERMS 542894.

WTS (Washington TRU Solutions). 2003. Salado Mass Concrete Test Program Final Report. 

Mine Engineering Repository Development Project, Revision 1. July 17, 2003, Waste Isolation 

Pilot Plant, Carlsbad, New Mexico.
ATTACHMENT A

Radiolytic Hydrogen Generation and Methanogenesis in WIPP: An Empirical Point of View
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Page 1 of 11

Radiolytic Hydrogen Generation and Methanogenesis in WIPP:

An Empirical Point of View – 11040

R. A. Nelson

U.S. Department of Energy

PO Box 3090, Carlsbad, NM 88220

ABSTRACT

Geologic disposal of radioactive waste is internationally recognized as the most prudent 

management approach to the back end of the nuclear fuel cycle. Alpha-emitting isotopes in 

waste matrices containing hydrogenous materials generate radiolytic hydrogen, which must be 

managed to ensure concentrations never exceed flammability limits. In addition, past concerns 

have been raised that methanogenesis could also present explosion hazards during a geologic 

repository’s operational lifetime.

Early (pre-operational) planning for the Waste Isolation Pilot Plant (WIPP) lead its original 

design to include explosion walls as part of the closure design in the event of a build-up of 

hydrogen or methane. This conservative approach simply assumed explosive gases could be 

present without detailed prediction of their concentration and extent. As the Department of 

Energy (DOE) emplaced waste after opening, the first two disposal panels were isolated from the 

ventilation circuit with the previously planned 4-meter thick explosion walls of robust concrete 

blocks. A separate requirement for an additional massive panel closure structure, which would 

make the closure system even more robust is also required, however a regulatory decision on 

their need is proposed for the near future.

When the third disposal panel was filled (WIPP plans a total of 10), DOE petitioned its primary 

repository regulators (The New Mexico Environment Department – NMED, and the 

Environmental Protection Agency – EPA) to allow monitoring of gases interior to the disposal 

panel in lieu of installing explosion walls. DOE argued that by routine monitoring, it could 

determine if flammable gases were building to potentially explosive levels or not. If 

concentrations approached action levels or if the monitoring system failed, DOE proposed to 

construct the explosion walls as originally conceived. This approach allowed DOE to conduct 

monitoring to potentially demonstrate that explosion walls, and eventually even more robust 

panel closures, might not be necessary for safe operation of the repository.

This paper describes the results of the first 3 years of hydrogen and methane monitoring in 

Panels 3 and 4 at WIPP. Flammable volatile organic compounds are also present in many of the 

waste streams emplaced at WIPP, but liquids are prohibited. Measurements of these flammable 

organic compounds are also made, but they play a minor role in the argument to eliminate 

explosion walls as part of the closure design at WIPP. Over 1000 air samples from all interior 

reaches of Panels 3 and 4 have been collected to date. Every single methane sample has been

determined as “Non Detectable” at detection levels of about 30 parts per million. Radiolytically 

generated hydrogen in these same samples was typically found at levels in the few hundred parts 

per million, well below the action levels specified in the permit (~4 parts per thousand). The 

monitoring results indicate that the initial WIPP planning was overly conservative and that 

explosion walls and robust panel closures may not be needed during the operational lifetime of 

WIPP.
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INTRODUTION

WIPP was constructed and its first disposal panel mined by the end of 1988. Although DOE 

considered WIPP ready for waste receipt, an 11-year period of regulatory licensing and 

permitting passed before the first shipment arrived for emplacement (1999). During this delay, 

several iterations of planning for final disposal panel closure resulted in a design for the panel 

closures that was based on very conservative assumptions [1].

With limited data on the expected concentrations of volatile organic compounds (VOCs) in the 

diverse array of transuranic (TRU) waste streams, and limited understanding of the potential for 

gas generation within the waste, conservative calculations resulted in a proposed design that 

included a massive concrete structure to be placed in the inlet and outlet drifts of each disposal 

panel. An assumed potential for a build-up of explosive gases within each panel also led to the 

proposal to install a massive explosion wall that would itself protect the panel closure from the 

blast effects so that the closure would continue to serve as a barrier to the VOCs.

In retrospect, these very conservative assumptions and calculations now appear unnecessary. It 

is prudent to re-examine the need for such robust structures to avoid cost and industrial accident 

vulnerability. Based on all the monitoring (both within the waste drums before ever shipping to 

WIPP, and monitoring of conditions in the filled disposal rooms of the repository), it is likely

that a much lower cost closure can protectively serve the purpose.

GAS GENERATION MECHANISMS

This section describes the 3 primary sources of flammable gases that might pose a risk to WIPP 

workers and, to a much lesser extent, potentially exposed members of the public.

Hydrogen can be generated by two widely different radiological and chemical processes: 

Potential Sources of Hydrogen

1) Radiolysis (ionizing radiation breaks bonds as it slows in hydrogenous materials), and

2) Corrosion of iron based materials under inundated conditions (no oxygen present).

Of the three primary types of ionizing radiation, radiolytic production of hydrogen is dominated 

by alpha radiation because of its high energy deposition rate as the alpha particles slow down in 

a solid matrix. This high energy deposition rate also comes with a short stopping range. The 

reader may recall their high school physics lesson when shown that a piece of paper is adequate 

to shield from alpha radiation. All the hydrogen bonds that the alpha particle can break are in the 

first few microns of the sheet of paper because the alpha radiation does not penetrate further into 

the solid. This short range also leads to another attribute of radiolysis in a solid matrix that is 

typically ignored. Because there is no physical movement of the matrix to expose new hydrogen 

atoms within the solid, radiolytic hydrogen generation rates monotonically decrease over time in 

all solids. This effect, known as “matrix depletion” occurs because the alpha radiation is coming 

from a solid source. In the case of transuranic (TRU) waste destined for disposal in WIPP, the 

dominant source of radiation is plutonium. Plutonium in intimate contact with organic matter 

(e.g., paper or plastic) will generate hydrogen at a rate that continually declines over time as 

more and more available hydrogen is released from the matrix. Because the source doesn’t move 

with respect to the available hydrogen atoms, the probability of breaking a hydrogen bond and 

releasing that proton declines over time (and in direct proportion to cumulative dose deposited. 
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Note this decline in hydrogen generation rate is not associated with the radioactive lifetime of the 

source. The matrix depletion effect is more a measure of the homogeneity of mixing the 

radioactive source material within the hydrogenous matrix than of the specific radioactivity of 

the source [2].

In addition to radiolysis, hydrogen can be generated by anoxic (without oxygen) corrosion of 

various metal components of the waste and packaging (primarily iron and aluminum based 

materials). Anoxic conditions can only be expected under inundated conditions, where brine has 

somehow accumulated and completely surrounds the waste [3]. It should be noted that 

aluminum and aluminum alloy corrosion rates are much slower than those for iron based 

materials. Estimates of the rates of hydrogen production under anoxic and fully brine inundated 

conditions may be made, however these rates are quite uncertain in the short-term during 

disposal operations, and the likelihood of inundating brine accumulation in this time frame is 

highly unlikely in light of its observed absence since the first disposal rooms was mined over 20 

years ago.

Other arguments against significant hydrogen generation by corrosion include the obvious fact 

that waste containers (typically drums) are painted. Initially corrosion will be inhibited until 

painted drum surfaces become exposed and internal steel components become accessible. In 

addition, after initial closure of a panel, oxygen-rich conditions will prevail, and the iron will 

oxidize (rust) with no hydrogen generation possible until all of the oxygen has been consumed. 

The oxidation rate is highly dependent on humidity as well [4]. The low humidity in deep 

reaches of the WIPP (away from fresh air intakes) minimizes oxidation, even of unpainted steel 

surfaces. This is evidenced from observation of un-rusted surfaces on many pieces of equipment 

or structures installed when the first openings were mined at WIPP in the early 1980’s. In the 

routinely low humidity levels found in WIPP, steel surfaces become passivated and oxidation 

slows. Therefore, oxygen depletion in closed disposal panels is not expected quickly. But only 

after oxygen is depleted and in the presence of brine, could anoxic corrosion be expected to 

generate significant hydrogen.

In 2007, a calculation was made to bound the upper limit of hydrogen generation in panel 3 [5]. 

This radiolysis estimate was based on the actual waste types that had been emplaced at the time, 

and used the actual hydrogen measurements of head-space gas in individual payload containers 

made to demonstrate compliance with the license requirements of the shipping containers. That 

conservative estimate of the production rate of hydrogen by radiolysis was about 4.5E-05 moles 

per second for the entire inventory of waste in panel 3 (about 1 ml/s). Generation at this rate 

would lead to an average concentration of 4% by volume in an air-tight sealed panel in about 20 

years (neglecting any loss of hydrogen by diffusion). This should be considered a lower bound 

on the time required to reach a lower flammability limit since the accumulation of hydrogen is 

mitigated by its ease of diffusion through even highly impermeable materials. The reader is also 

reminded of the many fractures and openings in the disturbed rock zone of a salt mine, which 

will not completely heal for many decades after disposal operations cease.

Methanogenesis or biomethanation is the formation of methane by microbes known as 

methanogens. Methanogenesis in microbes is a form of anaerobic respiration [6]. Methanogens 

do not use oxygen to breathe; in fact, oxygen inhibits the growth of methanogens. Organisms 

capable of producing methane have been identified only from the domain Archaea, a group 

Potential Source of Methane
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phylogenetically distinct from both eukaryotes and bacteria, although many live in close 

association with anaerobic bacteria. The production of methane is an important and widespread 

form of microbial metabolism. In most environments in the biosphere, it is the final step in the 

decomposition of biomass.

In addition, methanogenesis also requires the presence of liquid water, within which the 

methanogens metabolize. If there is oxygen present, methanogenesis is not. Conversely, if 

liquid water is not present, neither is methanogenesis. Therefore, just like hydrogen generation 

via anoxic iron corrosion, no methane can be expected as long as oxygen is present and 

inundating brine is not.

There are flammable VOCs in the waste. However these represent a fixed source which will 

deplete over time, and a source which is limited to levels well below flammability by the 

transportation requirements. Thus, flammable VOC components in filled panels are expected to 

remain quite small and further diminish over time. Hence they are not considered a significant 

issue related to the development of an explosive atmosphere in a full panel.

Flammable Volatile Organic Compounds

GAS MONITORING PROGRAM DESCRIPTION

In 2001, the National Academy of Sciences recommended DOE conduct pre-closure monitoring 

of gases in WIPP [7]:

The committee recommends pre-closure monitoring of gas generation rates, as well as 

the volume of hydrogen, carbon dioxide, and methane produced. Such monitoring could 

enhance confidence in the performance of the repository, especially if no gas generation 

is observed. Observation should continue at least until the repository shafts are sealed 

and longer if possible. The results of the gas generation monitoring program should be 

used to improve the performance assessment for recertification purposes.

Then in 2003 [8] and again in 2004 [9], Congress directed the DOE to change the process used to 

characterize waste for WIPP (these statutes are referred to as Section 311 in this paper). Using 

nearly identical language in both years, Congress stated:

(a) The Secretary of Energy is directed to file a permit modification to the Waste Analysis 

Plan (WAP) and associated provisions contained in the Hazardous Waste Facility Permit 

for the Waste Isolation Pilot Plant (WIPP) .... (b) Compliance with the disposal room 

performance standards of the WAP hereafter shall be demonstrated exclusively by 

monitoring airborne volatile organic compounds in underground disposal rooms in 

which waste has been emplaced until panel closure. 

Section (b) essentially directed DOE to monitor VOC concentrations in the WIPP underground 

in lieu of the intrusive sampling and analysis required under the permit from the NMED. This 

gave DOE a way to conduct the hydrogen and methane monitoring recommended by the 

National Academy of Science by using the same sampling lines that were mandated by Section 

311 for monitoring VOC concentrations in closed disposal rooms. While unrelated, the Section 

311 permit modification was linked to approval to dispose of remote-handled waste at WIPP, 
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which was strongly rejected by WIPP critics. This delayed implementation of the sampling 

program until the modification became effective in October 2006, and sampling for VOCs began

shortly thereafter in Panel 3, the active disposal unit at that time. It took several more months to 

obtain a permit modification to delay construction of explosion walls in panel 3 and begin 

making hydrogen and methane measurements in lieu of installing explosion walls. Sampling for 

hydrogen and methane began in August 2007.

The sampling is performed using long stainless steel tubing with a passivated inner surface and 

~7mm in diameter. Sampling tubes were installed along the outer walls of each disposal room 

after panel excavation, and before waste emplacement operations began. There are two sampling 

tubes per disposal room; one that terminates at the inlet side of each room and another that 

terminates at the outlet side. Each sampling line terminates at a 3-way splitter that allows air to 

be simultaneously drawn from locations about 50 cm above the floor, 50 cm below the roof, and 

approximately at the mid-height of each room. Figure 1 schematically shows the sampling line 

network in a typical disposal panel (blue diamonds represent sample intake locations).

Fig. 1 Plan view of typical disposal panel showing disposal rooms separated by brattice cloth 

ventilation barriers (room closures) and gas sampling locations in the inlet and outlet sides of 

each of the seven disposal rooms.

In addition to the VOC monitoring lines, five more sampling locations are used to monitor for 

hydrogen and methane. These additional locations use a single inlet sampling point placed near 

the roof and include:
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 the inlet of room 1,

 the waste side of the exhaust bulkhead,

 the accessible side of the exhaust bulkhead,

 the waste side of the intake bulkhead,

 the accessible side of the intake bulkhead.

Samples for analysis of hydrogen and methane concentrations are collected using the subatmospheric pressure grab sampling technique described in EPA Method TO-15 [10]. This 

method, which is the same for VOC sampling, uses an evacuated canister under vacuum (~0.05 

mmHg) to draw an air sample through sample lines into a ~6 liter stainless steel canister with 

passivated interior surfaces. The passivation of tubing and canisters effectively seals the inner 

walls and prevents compounds from being retained on the surfaces of the sampling equipment. 

Sample lines are purged prior to collection as recommended by the method (about 3 times the 

sample line volume). At the end of each sampling period (about 6 minute grab sample at ~1 

lpm), the canisters reach near atmospheric pressure.

There are no EPA-specific analytical methods which address hydrogen or methane. However, 

non-EPA methods are available. For the hydrogen and methane sampling, DOE uses a specially 

developed analytical test method for determination of hydrogen and methane using Gas 

Chromatography/Thermal Conductivity Detection.

The permit provisions include Action Levels based on the lower flammability limits for 

hydrogen and methane, referred to in the permit as lower explosive limits (LELs). In air, the 

lower flammability limit for hydrogen is generally considered to be 4 percent while that for

methane is 5 percent. Both limits assume atmospheric oxygen levels are present.

The permit Action Level 1 for hydrogen and methane in a panel is 10 percent of the LEL which, 

for hydrogen, is 0.4 percent or 4000 ppm and for methane is 0.5 percent or 5000 ppm. If this 

Action Level is reached or exceeded, the monitoring will be increased to weekly. If the 

concentrations measured in subsequent sampling fall back below Action Level 1, the sampling 

frequency relaxes back from weekly to monthly.

Action Level 2 for hydrogen and methane in a panel is 20 percent of the LEL which, for

hydrogen is 0.8 percent or 8000 ppm and for methane is 1 percent or 10,000 ppm. If Action 

Level 2 is achieved or exceeded for two successive weekly samples, the permit requires that 

monitoring cease and DOE is required to install the explosion isolation walls within 180 days.

When two flammable gases are mixed, the mixture may exhibit a different LEL than the 

individual gases. This is referred to as the composite LEL for the mixture. DOE evaluated 

whether or not the composite LEL should be used in determining the Action Levels and 

concluded that using the 10 percent and 20 percent thresholds was sufficiently conservative to 

assure action would be taken before potentially explosive levels of hydrogen or methane built up 

in filled panels. The additional conservatism added by using the composite LEL was not 

justified considering the additional complexity for demonstrating compliance (i.e., compliance 

using the composite value is based upon application of a mathematical formula and not on fixed, 

tabulated values in the permit).
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As waste emplacement operations progress and each disposal room is filled within a panel, the 

filled room is cut off from ventilation by a barrier called a brattice curtain (or cloth), which is a 

simple canvas-like cloth suspended from the roof and attached to the sides and floor of the drift 

to effectively cut off the filled room from air ventilation underground. While some attention is 

given to sealing air flow from going around the barrier, the brattice cloth is by no means an airtight seal. Small (millimeter scale) gaps remain. After panels 3 and 4 were filled, a metal 

bulkhead was constructed in both the inlet and outlet drifts (see Figure 1). This final ventilation 

barrier in each panel was augmented by a rubber (conveyor belt material) gasket bolted to the 

salt and bulkhead to form a seal. Again, small gaps remained. The reader is reminded that the 

salt creep process results in fractures and partings within the rock salt walls themselves that 

make the concept of a perfect gas seal impossible during the operational phase of the repository. 

Figure 2 shows photos of typical brattice cloth and metal bulkhead construction in WIPP.

Fig. 2 Photos of a typical ventilation barrier called a brattice curtain (top) separating each 

disposal room, and of a typical metal bulkhead (bottom) “sealing” the inlet and outlet drifts of 

each disposal panel from ventilation air in the rest of the mine.
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DOE believes the use of the bulkhead, the accompanying monitoring, and related Action Levels 

will maintain safe and protective operations by ensuring that:

 physical access to the full panel is prevented,

 the panel is removed from active ventilation, and

 conditions inside the panel are regularly monitored so that preventive actions can be 

taken well in advance of the existence of a hazardous condition.

MONITORING RESULTS

Panel 3 was filled and closed in August 2007, while panel 4 was filled and closed in May 2009. 

Monthly hydrogen and methane sampling began in both panels the same month they were 

closed. Two results from over 1,000 samples collected since then stand out:

 All samples assayed less than the minimum detectable level for methane (<~20-30 ppm).

 Hydrogen results typically assay at several hundred ppm, when detected at all.

The monthly monitoring results for hydrogen in panels 3 and 4 are presented in Figures 3 and 4, 

respectively.

Fig. 3 Time series history of hydrogen monitoring results taken from the outlet sides of disposal 

rooms in closed panel 3 over a 3-year period.
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In these time series plots, only the results from sampling the outlet sides of each disposal room 

are plotted. Only a handful (out of over 500) of samples taken from the inlet side assayed above 

the minimum detectable limit for hydrogen (~20-30 ppm), and therefore are not plotted. When 

outlet sample results assayed below the minimum detectable limit, the value was plotted at a 

concentration of zero in Figures 3 and 4.

Fig. 4 Time series history of hydrogen monitoring results taken from the outlet side of disposal 

rooms in closed panel 4 over an 18-month period.

Interpreting these results is easy. There is no detectable methanogenesis occurring in either 

panels 3 or 4, and thereby by inference, no methanogenesis in panels 1 or 2 either. In contrast 

hydrogen generation by radiolysis is occurring and at levels easily detected by the analytic 

method used for assay. No steadily rising concentrations imply that the hydrogen is removed 

from the disposal rooms on a continuous basis. The removal process appears to be two-fold. 

The fact that the results from samples collected on the inlet side almost always assay below 

minimum detectable limits and those from the outlet side typically range in the few hundred ppm 

levels implies that there is a leakage flow due to differential pressure between the inlet and outlet 

sides of each disposal panel. The high sample-to-sample variability from each location implies 

that the release of hydrogen from the waste containers themselves varies over periods of weeks 

to months. This can be explained by normal barometric breathing.

The highest value of hydrogen measured to date was 923 ppm at the outlet side of room 7 

(furthest into the disposal panel) in panel 4 in June 2010. This value is 25% of the Action Level 

1 for hydrogen established in the permit (which in turn is 10% of the concentration considered 
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flammable - if oxygen were present at atmospheric levels). It should be noted that actions to 

minimize leakage ventilation through panel 4 began in earnest in November 2009, when running 

annual average carbon tetrachloride levels in the exhaust flow from the entire underground began 

climbing. A companion paper in session 063 (11039) at this symposium describes this effort in 

more detail [11].

Active disposal operations with high carbon tetrachloride content were ongoing in panel 5 at that 

time, but it was prudent to assume that some of the carbon tetrachloride originated from leakage 

flow through closed panel 4 since it held some of the high carbon tetrachloride waste as well. 

Therefore, DOE built an additional bulkhead at the inlet and outlet drifts of panel 4 and made

extra efforts to seal panel 4 from leakage ventilation. These efforts were coincident with the 

slight step increase in the peak hydrogen concentration results as seen in Figure 4 in November 

2009. The apparent increase may be attributed to the enhanced sealing efforts to minimize 

carbon tetrachloride leakage out of panel 4. However, the fact that hydrogen concentrations vary 

so much from one sample to the next indicates that it easily escapes the systems designed to 

block the carbon tetrachloride.

ELIMINATING EXPLOSION WALLS AND OPTIMIZING PANEL CLOSURES

Based on the monitoring results from 2007 to date, it would seem that massive panel closures 

and explosion walls to protect those closures might not be necessary and yet still be protective of 

workers and the environment. A companion paper in session 063 at this symposium discusses 

DOE’s plans to seek regulatory approval to modify the massive closure design and replace it 

with a simple 30 meter long wall of run of mine salt [12]. Such a panel closure would likely be a 

better barrier in preventing panel-to-panel hydrologic communication in an assumed future 

human intrusion scenario, and would be a lot less costly. Upon filling a disposal panel with 

waste, the run of mine salt closure would simply be placed in the inlet and outlet drifts. A 

blower may be used to bring the pile up to the full height of the drifts. While this closure would 

not be air-tight, it would behave at least as well as the metal bulkheads in panels 3 and 4 

described herein (the same leaky pathways around the closure through the disturbed rock zone 

would exist). Over time (a few decades), the salt creep closure would compact and begin 

reconsolidating the run of mine salt. Within a few hundred years, this panel closure would 

resemble the properties of intact salt. In contrast a massive monolith of concrete (the current 

panel closure stipulated for WIPP by its regulators) would not exhibit the immeasurably low 

permeability of healed intact salt, but would be considered more permeable.

CONCLUSIONS

Although basic knowledge and laboratory measurements made during the licensing and 

permitting phase showed that little or no gas generation would occur during the operational life 

of WIPP, in an abundance of caution, DOE and its regulators still proposed massive panel 

closures and large explosion walls to protect them. Based on monitoring results (at least for 

panel 3 and 4), these do not appear to be necessary, since levels of flammable gases and VOCs 

are present in only trace levels. The only VOC present in significant amounts in the TRU waste 

stream inventory (and then only in a small fraction of drums) is carbon tetrachloride, which 

ironically is not flammable.

Over 1000 gas samples collected in all areas of panels 3 and 4 show undetectable levels of 

methane, thereby confirming the expectation that methanogenesis is not occurring (oxygen is 
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present, and brine inundation is not). Hydrogen levels in those same samples are in the few 

hundred ppm range and vary significantly from sample to sample, thereby implying a continuous 

source, but an intermittent pathway out. This is consistent with barometric pumping of waste 

containers, superimposed on a steady leakage air flow, even through the further back disposal 

rooms in a panel.

DOE will continue to monitor for flammable gases in filled disposal panels and take steps to 

protect workers and the environment if levels rise and explosions walls become necessary. In the 

meantime, DOE will continue to make the case that there are more prudent and cost effective

panel closure designs that should be considered.

REFERENCES

1. Conceptual Design for Operational Phase Panel Closure Systems

2. Idaho National Engineering and Environmental Laboratory, 1990, “TRUPACT-II Matrix 

Depletion Program Final Report,” INEL/EXT-98-00987, Rev. 1, prepared for the U.S. 

Department of Energy, Idaho Operations Office, Idaho Falls, Idaho.

, DOE-WIPP-95-2057,

US Department of Energy, 1995.

3. Francis, A.J., Gillow, J.B., and M.R. Giles, 1997. Microbial Gas Generation Under 

Expected Waste Isolation Pilot Plant Repository Conditions

4. Gillow, J.B. and A.J. Francis, 2002,

. SAND96-2582, Sandia 

National Laboratories, Albuquerque, New Mexico.

Re-Evaluation of Microbial Gas Generation Under 

Expected Waste Isolation Pilot Plant Conditions, Data Summary and Progress Report 

(February 1 – July 15, 2002)

5. Devarakonda, M., 

. Section 3.1 of Sandia Technical Baseline Report, July 31, 

2002. Sandia National Laboratories, Albuquerque, New Mexico.

Estimation of Hydrogen Generation Rates From Radiolysis in WIPP 

Panels

6. Thauer, R. K., 

, Letter from Washington TRU Solutions to D. Mercer, TS:06:02012, July 20, 

2006

Biochemistry of Methanogenesis

7. National Academy of Sciences, 2001, 

, Microbiology, 1998, volume 144, pages 

2377-2406.

Improving Operations and Long-Term Safety of 

the Waste Isolation Pilot Plant,

8. Section 311 of the Energy and Water Development Appropriations Act, 2004, Public 

Law 108-137 (December 1, 2003) 

Board on Radioactive Waste Management.

9. Section 310 of the Consolidated Appropriations Act for 2005, Public Law 108-447 

(December 8, 2004)

10. Compendium of Methods for the Determination of Toxic Organic Compounds in 

Ambient Air: Methods TO-15, Second Edition, US Environmental Protection Agency, 

Research Triangle Park, NC, January 1999; EPA 600/625/R-96/010b.

11. Nelson, R.A., WIPP Status and Plans – 2010, Waste Management 2011 Conference, 

Phoenix, AZ, March, 2011.

12. Patterson, R.L., S. Kouba, and T. Klein, Panel Closure: A Change in WIPP's Future 

Operations through Regulatory Compliance, Waste Management 2011 Conference, 

Phoenix, AZ, March 2011.
ATTACHMENT B

Effective Permeability of the Redesigned Panel Closure System

Paul E. Shoemaker, MS-1395 (6820) - 2 - August 29, 2002 

The resistance to fluid flow of this closure system will be a composite of the resistance to flow of the 

different elements, including the wall, the crushed salt and the surrounding disturbed rock zone (DRZ). 

Each of these components will vary in its flow resistance over time, and each will dominate over a 

particular time period. Since the intent of this memorandum is to review the flow resistance of the 

closure itself for comparison to the range examined in the impact analysis, the effect of the DRZ is not 

considered here, although it will be relevant to overall performance. 

During the operational period the conductivity of this closure will be dominated by the mortared cement 

block wall, which is estimated in the design report to have a permeability of 2x10-15 m

2

. Over time the 

concrete wall will gradually fracture and fail under the loads applied by the creep of the surrounding 

salt, and its permeability will gradually increase. However, the same creep closure which causes the 

concrete block wall to fail will also gradually compact the salt backfill, thus slowly decreasing its 

permeability and this element will come to dominate the flow performance of the closure system. 

It should be noted that the relevant parameter for flow performance is in fact the flow conductance, 

which is a function of permeability, area, and length. However the length of the closure considered in 

the Compliance Certification Application (CCA) and Performance Assessment Verification Test 

(PAVT) calculations, and in the accompanying impact analysis, is 40 m or 131 ft, which is essentially 

the same as the redesigned closure, while the area is the same in the CCA, PAVT and for the redesigned 

closure, so the comparison may be made on the basis of permeability alone. 

Salt Consolidation 

Closure of the entry due to creep around the crushed salt backfill will cause the backfill to consolidate 

leading to loss of porosity, increase in density and reduction in permeability. The backfill void volume 

will be approximately 33% when placed, this being a typical value for loosely emplaced disaggregated 

materials and being in the range anticipated by Saeb and Case (2002). When the salt is compressed and 

the porosity is reduced, its permeability decreases appreciably. It has been shown that when crushed salt 

re-consolidates to a density approaching 95% of intact salt, its permeability is approximately 10-19 m2

(Hurtado et al., 1997). It has been postulated and confirmed that consolidation of granular rock salt 

occurs by two primary mechanisms: grain boundary pressure solution and dislocation creep (Spiers and 

Brzesowsky, 1993). As crushed salt is loaded, the principal densification mechanism of fluid-phase 

grain boundary solution/redeposition is rampant. As consolidation proceeds, the material attains 

sufficient density so that its response assumes the constitutive response of intact salt, and dislocation 

creep becomes important. Estimates of the rate of closure and the resulting loss of permeability can be 

made using measured closure rates from the Panel 1 entries and laboratory data on salt consolidation. 

 

Data on the relationship between porosity and permeability of crushed salt have been obtained in a 

number of laboratory experiments evaluating the behavior of backfill material in rooms and of shaft seal 

components. A comprehensive data set is reported by Hurtado et al., (1997) and is included as Figure 

A7 in Appendix SEAL of the CCA (DOE, 1996). These data are presented in Figure 2, and show that 

for fractional densities above about 0.9 (equivalent to a porosity of 10%) permeabilities may be expected 

to be 10-15 m

2

 or lower. If, as noted above, the run-of-mine salt is expected to have a porosity of the 

order of 33%, then to reach a porosity of 10% will require a volume strain of the order of 23%. 

Unimpeded closure of entry drifts has been modeled and shows closure of the order of 10% in 10 years 

(Hansen et al., 1993). Actual measurements of roof-to-floor and rib-to-rib closure in the entries 
Paul E. Shoemaker, MS-1395 (6820) - 3 - August 29, 2002 

corroborate these closure rates. Figures 3 and 4 show closure data for S1600 (the Panel 1 exhaust drift) 

and S1950 (the Panel 1 intake drift) respectively. These data are from the E407 monitoring point which 

is located approximately midway between the E300 main entry and Panel 1, or in the center of the 

proposed panel closure locations (DOE, 2001). These data indicate that closure rates, which are 

summarized in the following table, are reasonably stable, and uniform, and are similar for the mid and 

third points of each entry. If it is assumed that the rates measured over the last ten years will continue, 

then the volume closure expected of the two entries is as shown in Figure 5, with closure by 25% in 

between 20 or 30 years. 

Closure Measurement Location Exhaust Drift (S1600) 

(in/day) 

Air Intake Drift (S1950) 

(in/day) 

Vertical (Center) 0.00203 0.00364 

Vertical (S. third point) 0.00185 0.00300 

Vertical (N. third point) 0.00196 0.00365 

Mean Vertical 0.00195 0.00333 

Horizontal (Upper third point) 0.00230 0.00250 

Horizontal (Center) 0.00216 0.00266 

Horizontal (Lower third point) 0.00200 0.00261 

Mean Horizontal 0.00215 0.00259 

Closure to this extent in the presence of crushed salt may be expected to be slower for three reasons. 

First, it is likely that a long-term slow down of closure rates may be expected, although closure by 25% 

in say twice the calculated time, or 40 – 60 years, is not unreasonable. Second, as the backfill 

consolidates it may be expected that it will stiffen and apply some back stress that will slow the closure. 

Case (1994) used data from Holcomb and Hannum (1982) to estimate consolidation pressure-strain 

curves for loosely placed backfill (Figure 6), indicating that at strains of the order of 25% imposed under 

rapid loading quasi-static conditions back stress of the order of 2500 psi may be expected. However 

creep tests carried out on similar materials by Holcomb and Hannum show that under constant stress of 

this magnitude the crushed salt will consolidate over time (Figure 7). This creep will result in relaxation 

of any potential stress build up over the tens of years being considered here, so the potential for large 

back stresses being induced is small. Note that this behavior is confirmed by numerical calculations of 

the closure of backfilled rooms (Figure 8) (Callahan and DeVries, 1991) which show closure to very low 

porosities in a matter of a few tens of years, and by calculations of the consolidation of dynamically 

emplaced crushed salt in the shaft at a depth of 600m (Figure 9). 

Third, back pressure could also be applied as a result of pore pressure build-up due to gas generation in 

the waste. Any microbial gas generation will occur fairly rapidly, at least within the time frame 

discussed here, and this gas may be expected to flow through the concrete wall and into the salt backfill. 

However through the early parts of its consolidation, where the permeability was greater than or equal to 

10-15 m2

, any gas generated will flow out of the backfill into any remaining void space adjacent to the 

closure. As the permeability reduces still further the crushed salt may resist further consolidation, but 

the permeability will still be in the range estimated here. 

Conclusion 

When the redesigned closure is emplaced the flow resistance will be controlled by the mortared concrete 

block wall, and is expected to be of the order of 10-15 m2

. This permeability will be maintained at least 
Paul E. Shoemaker, MS-1395 (6820) - 4 - August 29, 2002 

through the operational period of 35 years. After this time the permeability of this element may be 

expected to increase somewhat as the wall degrades on an unknown time frame under creep load. At the 

same time the run-of-mine salt backfill will be consolidating under the creep closure of the salt 

surrounding the entry. Extrapolation of existing closure data suggest volume closure of the order of 

25% would occur in as little as 20 to 40 years; however it is likely that this will take longer as creep 

closure rates will probably reduce somewhat over time. Back stress due to the consolidation is expected 

to be minimal over the time scales of interest (tens of years) since any tendency for stress build up will 

be relaxed by creep consolidation of the backfill. Once a fractional density of about 0.9 (representing a 

porosity of about 10%, or about 25% closure from an original porosity of 35%) is reached permeabilities 

of the order of 10-15 m

2

 may be expected, and it is reasonable to expect these conditions to be reached in 

a maximum of 100 years. Beyond that time, permeability may be expected to decrease further with 

additional consolidation and values of the order of 10-19 m

2

 may be achieved. If gas generation occurs 

and the gas penetrates the backfill, then as the permeability decreases, pore pressures may build up 

leading to a slowing or stopping of consolidation. However this will not occur until the backfill 

permeability reaches at least 10-15 m2

: at higher permeabilities the pore pressures will be relieved by 

flow of gas. The permeability of the closures will therefore be expected to fall in the range covered in 

the accompanying impact assessment, i.e. 10-19 to 10-15 m2

. 

References 

Callahan, G. D. and K. L. DeVries. 1991. Analyses of Backfilled Transuranic Wastes Disposal Rooms. 

SAND91-7052. Sandia National Laboratories, Albuquerque, NM. 

Case, J.B., 1994, “Backfill Evaluation Analysis Report,” Westinghouse Waste Isolation Division, 

Carlsbad, NM, 1994. 

Hansen, C., “Analysis Report for the Panel Closure Impact Assessment,” Sandia National Laboratories, 

Carlsbad NM, August, 2002. 

Hansen, F.D., M.S. Lin, L.L. VanSambeck, 1993. “Concept for Operational Period Seal Design at the 

Waste Isolation Pilot Plant,” SAND93-0729, July 1993. 

Holcomb, D.J. and D.W. Hannum, 1982, “Consolidation of Crushed Salt Backfill Under Conditions 

Appropriate to WIPP,” SAND82-0630, November 1982. 

Hurtado, L.D., M.K. Knowles, V.A. Kelley, T.L. Jones, J.B. Ognitz, T.W. Pfeifle, 1997. “WIPP Shaft 

Seal System Parameters Recommended to Support Compliance Calculations,” SAND97-1287, 

December 1997. 

Saeb, S and J. Case, 2002, “Design Report For A Revised Panel Closure System At The Waste Isolation 

Pilot Plant,” Report to Westinghouse TRU Solutions, LLC., Rocksol Inc., Boulder CO. 

Spiers, C.J., and R.H. Brzesowsky. 1993. “Densification Behavior of Wet Granular Salt: Theory Versus 

Experiment,” Seventh Symposium on Salt, Kyoto, Japan, April 6-9, 1992. Eds. H. Kakihana, H.R. 

Hardy, Jr., T. Hoshi, and K. Toyokura. Amsterdam; New York, New York: Elsevier Science 

Publishers B.V. Vol. I, 83-92. 
Paul E. Shoemaker, MS-1395 (6820) - 5 - August 29, 2002 

U.S. Department of Energy, 1996, “Title 40 CFR 191 Compliance Certification Application for the 

WIPP: Appendix SEAL,” Carlsbad NM, 1996. 

U.S. Department of Energy, 2001, "Geotechnical Analysis Report for July 1999-June 2000," 

DOE/WIPP 01-3177, Waste Isolation Pilot Plant, Carlsbad, New Mexico. 
Figure 1. Explosion Isolation Wall in Combination with the Run-of-Mine Salt Backfill (Saeb and Case, 2002)
Figure 2. Permeability of Consolidated Crushed Salt as a Function of Fractional Density 

(DOE, 1996)
Figure 3: Closure Data for the Exhaust Drift (S1600) (DOE, 2001)
Figure 4: Closure Data for the Air Intake Drift (S1950) (DOE, 2001)
Figure 5. Calculated Drift Closure Assuming Constant Closure Rates and no Backstress

Drift Closure

0

20

40

60

80

100

120

0.0% 10.0% 20.0% 30.0% 40.0% 50.0% 60.0% 70.0% 80.0% 90.0% 100.0%

Volume Closure 

Time (Years)

S1600 (Exhaust)

S1950 (Intake)
Figure 6: Quasi-Static Consolidation Data for Dry Crushed Salt (after Holcomb and Hannum, 1982 and Case, 1994)

Quasi-Static Consolidation Data

0

500

1000

1500

2000

2500

3000

3500

4000

0% 5% 10% 15% 20% 25% 30%

Volume Strain

Stress (psi)

Strain
15%

16%

17%

18%

19%

20%

21%

22%

23%

24%

0 2 4 6 8 10 12

Time (Years)

Volume Strain

Figure 7: Creep Consolidation Data for Dry Crushed Salt (after Holcomb and Hannum, 1982)
Figure 8. Void Reduction in a Disposal Room filled with Crushed Salt as a Function of Time (Callahan and DeVries, 1991).
Figure 9. Calculated Fractional Density Versus Time for Crushed Salt Compacted in the Shaft.

0.88

0.90

0.92

0.94

0.96

0.98

1.00

0 100 200 300 400 500

Time Since Emplacement (years)

Fractional Density

Shear Database Parameters

Combined Database Parameters

Depth = 600 m

515 m

430 m
ATTACHMENT C

Summary Report for the AP-151 (PC3R) Performance Assessment, Revision 1
Information Only 

Sandia National Laboratories 

Waste Isolation Pilot Plant 

Summary Report for the AP-151 (PC3R) 

Performance Assessment 

Revision 1 

Author: __ ___,Re..:. c"'hre!!dQis_,c,am!!.!l'ph,o,_.,u~se'--_.l....C""':/[:::.._--"'--C..::o..... ... ~::..------.:::.S:/J~7.L/.L/t-l __ _ 

Print /? A _..S.igna_wre Date 

Author:. __ ---""D~an~i!e!el_,!.J~. C~IQ;av!.!Cto~n!.._ __ J.VLe:::_----=::::::.....:~=--~_c{~&t:=.ue..·2L_ __ ___J,?J;_ilu.?:L/ull __ _ 

Print Date 

Author: ___ D""-"'w"'-ayn'-""-e-'=C"-'. K.,J,·c,ke"-r ___ -=:---=.-9''---''--'~"'-"-"""'.,._ ___ ~s/..;;u_-'-I::.,O/,_,z.=o:.c/l,_ Print Date 

Author: ___ J,_,a""m""e"-'s J,_,_. -'-P"'as""ch"---------~"'-'-'-"«""-1f--L--""""""=----"'S:,L..J/~6f-.=.Zc::O::JI/ 

Print Date 

Technical 

Review: Sean C. Dunagan .L / 

~- s/;o/1\ 

Print Signature Date 

QA 

Review Mario J. Chavez fY\= '0 ~ . ~s ;, toll£ 

Print l Signature V I I Date 

Management 

Review: Moo Lee __....------ ~~ s-/!7/IJ 

7 i 

Print Signature Date 

WIPP: 1.4.1.2:PA:QA-L:554612 
Information Only 

Table of Contents 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

Executive Summary ...................................................................................................................................... 5 

1 Introduction ........................................................................................................................................... 6 

2 Repository Configuration Changes ....................................................................................................... 7 

2.1 Repository Reconfiguration ............................................................................................................... 7 

2.2 Parameters ....................................................................................................................................... !! 

Panel Closure Parameters .............................................................................................................. 11 

Panel Reconfiguration Parameters ................................................................................................. 14 

2.3 Computational Grid Changes ........................................................................................................... 15 

2.4 FEPS Re-assessment ........................................................................................................................ 20 

3 Methodology ....................................................................................................................................... 20 

4 Run Control ......................................................................................................................................... 22 

5 Resu Its ................................................................................................................................................. 22 

5.1 Salado Flow Results ......................................................................................................................... 22 

Undisturbed Scenario S 1-BF .......................................................................................................... 23 

Disturbed Scenario S2-B F .............................................................................................................. 28 

Disturbed Scenario S4-BF .............................................................................................................. 31 

5.2 Brine Isolation after Intrusion .......................................................................................................... 35 

5.3 Actinide Mobilization and Transport ............................................................................................... 40 

5.4 Cuttings and Cavings ....................................................................................................................... 43 

5.5 Spallings ........................................................................................................................................ .46 

5.6 Direct Brine Releases .......................................................... , ............................................................ 48 

5.7 Total Normalized Releases ............................................................................................................... 50 

6 Summary .............................................................................................. ., ............................................. 55 

7 References ................................... , ....................................................................................................... 56 

Acknowledgement 

A portion of this summary report was written by James W. Garner. James became unavailable 

during the review and comment phase of report preparation, and was not available to sign the 

title page of the final document. 

Page 2 of 58 
Information Only 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

List of Figures 

Figure 2-1: Historical WIPP Repository Layout ......................................................................................................... 9 

Figure 2-2: WIPP Layout Modeled in PC3R PA ......................................................................................................... 10 

Figure 2-3: PABC-2009 BRAG FLO grid (Ax, Ay, and Az dimensions in meters) ....................................................... /6 

Figure 2-4: PC3R PA BRAGFLO grid (Ax, Jy, and Jz dimensions in meters). .......................................................... /7 

Figure 2-5: PABC-2009 DBR material map (logical grid) ......................................................................................... l8 

Figure 2-6: PC3R FA DBR material map (logical grid} ............................................................................................ J9 

Figure 5-I: Overall Means of Volume Averaged Porosity for the Waste Panel, Scenario 81-BF .............................. 25 

Figure 5-2: Overall Means of Volume Averaged Pressure for the Waste Panel, Scenario S1-BF .............................. 25 

Figure 5-3: Overall Means of Volume Averaged Pressure for the Waste Panel During the First 150 Years After 

Closure, Scenario Sl-BF. ............................................................................................................................................ 26 

Figure 5-4: Overall Means of Brine Saturation in the Waste Panel, Scenario S1-BF. ............................................... 26 

Figure 5-5: Overall Means of Total Brine Flow Out of the Waste Panel, Scenario Sl-BF ........................................ 27 

Figure 5-6: Overall Means of Total Brine Flow Up the Shaft, Scenario SI-BF. ........................................................ 27 

Figure 5-7: Overall Means of Volume Averaged Porosity for the Waste Panel, Scenario S2-BF .............................. 29 

Figure 5-8: Overall Means of Volume Averaged Pressure for the Waste Panel, Scenario 52-BF. ............................. 29 

Figure 5-9: Overall Means of Brine Saturation in the Waste Panel, Scenario 52-BF ................................................ 30 

Figure 5-10: Overall Means of Total Brine Flow Out of the Waste Panel, Scenario S2-BF ...................................... 30 

Figure 5-11: Overall Means of Total Brine Flow Up the Borehole, Scenario 52-BF ................................................. 31 

Figure 5-12: Overall Means of Volume Averaged Porosity for the Waste Panel, Scenario S4-BF ............................ 32 

Figure 5-13: Overall Means of Volume Averaged Pressure for the Waste Panel, Scenario S4-BF ..... ..................... 33 

Figure 5-14: Overall Means of Volume Averaged Pressure for the Waste Panel During the First 700 Years After 

Closure, Scenario S4-BF ............................................................................... ............................................................ 33 

Figure 5-15: Overall Means ofBrine Saturation in the Waste Panel, Scenario 54-BF .............................................. 34 

Figure 5-16: Overall Means of Total Brine Flow Out of the Waste Panel, Scenario 54-BF ...................................... 34 

Figure 5-17: Overall Means of Total Brine Flow Up the Borehole, Scenario 84-BF ................................................. 35 

Figure 5-18: PC3R PA Overall Waste Panel Pressure Means, Scenarios Sl-BF S2-BF, S4-BF, S6-BF .................. 37 

Figure 5-19: PC3R FA Overall Waste Panel Brine Volume Means. Scenarios SI-BF, S2-BF, S4-BF, 86-BF. ......... 38 

Figure 5-20: PC3R FA Overall Waste Panel Brine Saturation Means, Scenarios SI-BF, S2-BF, S4-BF, S6-BF ...... 38 

Figure 5-21: PC3R FA Overall Central Region Brine Saturation Means, Scenarios Sl-BF, S2-BF, S4-BF, S6-BF. 39 

Figure 5-22: PC3R PA Overall Central Region Brine Volume Means, Scenarios SI-BF, 52-BF, S4-BF, S6-BF ...... 39 

Figure 5-23: PC3R PA Overall Central Region Pressure Means, Scenarios Sl-BF, 52-BF. S4-BF, 56-BF .............. 40 

Figure 5-24: PC3R FA and PABC-2009 Replicate Means of Cumulative Flow up the Borehole ............................... 41 

Figure 5-25: PC3R PA and PABC-2009 Overall Means of Cumulative Flow up the Borehole ................................. 42 

Figure 5-26: PC3R FA and PABC-2009 Replicate Mean CCDFsfor Normalized Transport Releases to the Culebra 

..................................................................................... ,,,, ......................................................... ,,,,,, ............... , ............. 42 

Figure 5-27: PC3R PA and PABC-2009 Overall Mean CCDFsfor Transport Releases to the Culebra ................... 43 

Figure 5-28: PC3R FA and PABC-2009 Overall Mean CCDFsfor Normalized Cuttings and Cavings Releases ..... 45 

Figure 5-29: Cuttings and Cavings Area as a Function of Waste Shear Strength ........................... .......................... 45 

Figure 5-30: PC3R PA and PABC-2009 Overall Mean CCDFsfor Normalized Spallings Releases ........................ .47 

Figure 5-31: DBR Volume vs. Pressure, Scenario 52-DBR, Replicate I, Lower Intrusion, PC3R PA ....................... 49 

Figure 5-32: PC3R FA and PABC-2009 Overall Mean CCDFs for Normalized Direct Brine Releases .................... 50 

Figure 5-33: PCJR PA Replicate l Total Normalized Releases ................................................................................. 52 

Figure 5-34: PC3R PA Replicate 2 Total Normalized Releases ................................................................................. 52 

Figure 5-35: PC3R FA Replicate 3 Total Normalized Releases ................................................................................. 53 

Figure 5-36: PC3R PA Mean and Quantile CCDFsfor Total Normalized Releases, Replicates 1-3 ......................... 53 

Figure 5-37: PC3R PA Confidence Limits on Overall Mean for Total Normalized Releases ..................................... 54 

Page 3 of 58 
Information Only 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision l 

Figure 5-38: PC3R PA and PABC-2009 Overall Mean CCDFs for Total Normalized Releases ............................... 54 

Figure 5-39: PC3R PA Primary Components Contributing to Total Releases ........................................................... 55 

List of Tables 

Table 1: Constant Parameters Used for Material PCS_T/ ......................................................................................... 13 

Table 2: Sampled Parameters Used for Material PCS_T/ ......................................................................................... 13 

Table 3: Log of Intrinsic Permeability Values used for Material PCS_T2 in the PC3R PA ....................................... l4 

Table 4: Log of Intrinsic Permeability Values used for Material DRZ-PCS in the PC3R ?A for the first 100 years. 14 

Table 5: PC3R PA Parameters Updated/Created Due to the Repository Reconjiguration ........................................ 14 

Table 6: BRAG FLO Modeling Scenarios .................................................................................................................... 23 

Table 7: PA Intrusion Scenarios Used in Calculating Direct Solid< Releases ............................................................ 44 

Table 8: Cavings Area Statistics for the PABC-2009 and PC3R PA .......................................................................... 44 

Table 9: Summary of Spa/lings Releases by Scenario ................................................................................................. 46 

Table 10: PABC-2009 and PC3R PA DBR Volume Statistics ..................................................................................... 48 

Table II: PC3R PA and PABC-2009 Statistics on the Overall Mean for Total Normalized Releases in EPA Units at 

Probabilities of 0.1 and 0. 00 I ..................................................................................................................................... 51 

Page 4 of 58 
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Summary Report for tile AP-lSl (PC3R) Performance Assessment 

Revision l 

EXECUTIVE SUMMARY 

Following the recertification of the WIPP in November of20!0 (U.S. EPA 2010), the DOE will 

submit two PCRs to the EPA that propose changes to the repository. The first PCR is centered 

on a new design of the WIPP panel closure system. The panel closure "Option D" design 

considered in the PABC-2009 (Clayton et al. 20 10) is modified to a configuration consisting of 

I 00 feet run of mine salt emplaced against a "significant barrier" on the waste disposal side. The 

second PCR proposes the relocation of future waste panels 9 and 1 0 to the south end of the 

repository where they are denoted as panels 9a and 1 Oa. With panels 9 and I 0 relocated, the 

current repository configuration is modified to one with an open central drift area with installed 

panel closures located only at the end of filled waste panels. The DOE has requested that SNL 

conduct a single P A to determine the overall impact of the repository changes proposed in the 

two PCRs. Impacts of these changes are determined by way of a comparison of results obtained 

with the reconfigured repository and panel closure redesign to those calculated in the PABC2009. This report summarizes the results of the panel closure redesign and repository 

reconfiguration performance assessment, henceforth referred to as the PC3R PA. 

Total normalized releases calculated in the PC3R PA remain below their regulatory limits. As a 

result, the panel closure design and repository configuration changes investigated in the PC3R 

P A would not result in WIPP non-compliance with the containment requirements of 40 CFR Part 

191. Cuttings and cavings releases and direct brine releases are the two primary release 

components contributing to total releases in the PC3 R P A. Cuttings and cavings releases are 

indistinguishable from those calculated in the PABC-2009. Changes in total releases are 

attributed to changes calculated in direct brine releases from the PABC-2009 to the PC3R PA. 

Differences are observed in PC3R PA spallings releases as compared to the PABC-2009, but 

these differences are relatively minor and do not have a significant impact on the overall total 

normalized releases found in the PC3R P A. 

Page 5 of 58 
Information Only 

1 INTRODUCTION 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, has been 

developed by the U.S. Department of Energy (DOE) for the geologic (deep underground) 

disposal oftransuranic (TRU) waste. Containment ofTRU waste at the WIPP is regulated by the 

U.S. Environmental Protection Agency (EPA) according to the regulations set forth in Title 40 of 

the Code of Federal Regulations (CFR), Part 191. The DOE demonstrates compliance with the 

containment requirements according to the Certification Criteria in Title 40 CFR Part 194 by 

means of performance assessment (PA) calculations performed by Sandia National Laboratories 

(SNL). WIPP PA calculations estimate the probability and consequence of potential 

radionuclide releases from the repository to the accessible environment for a regulatory period of 

10,000 years after facility closure. The models are maintained and updated with new 

information as part of a recertification process that occurs at five-year intervals following the 

receipt of the first waste shipment at the site in 1999. 

In addition to its role in certification decisions for the repository, P A is used to determine the 

impacts of repository modifications proposed by the DOE as part of plarmed change requests 

(PCRs). Previous analyses have been performed to assess the impacts of modifications to the 

panel closure system implemented in the repository (Hansen 2002, Vugrin and Dunagan 2006). 

The 1998 rulemaking that certified WIPP to receive TRU waste had several conditions, one of 

which involved the design of the panel closure system. The EPA based its certification decision 

on the condition that the DOE implement the most robust panel closure design, referred to as the 

"Option D" design in the CCA (U.S. EPA 1998). With the recertification of the WIPP in 

November of 2010 (U.S. EPA 2010), a new PA baseline was established by the 2009 

Performance Assessment Baseline Calculation (PABC-2009). 

Following recertification of the facility, the DOE plans to submit two PCRs to the EPA that 

propose changes to the repository. The first PCR is centered on a new design of the WIPP panel 

closure system (PCS). The panel closure "Option D" design considered in the PABC-2009 

(Clayton et al. 2010) is to be modified to a configuration consisting of 100 feet run of mine salt 

emplaced against a "significant barrier" on the waste disposal side. The second PCR proposes 

the relocation of future waste panels 9 and 10 to the south end of the repository, i.e. south of 

panels 4 and 5, where they will be denoted as panels 9a and lOa. With panels 9 and 10 relocated, 

the current repository configuration will be modified to one with an open central drift area with 

installed panel closures located only at the end of filled waste panels. The DOE has requested 

that SNL conduct a single P A to determine the overall impact of the repository changes proposed 

in the two PCRs. Impacts of these changes are determined by way of a comparison of release 

probabilities to those calculated in the PABC-2009. This report provides a summary of 

Page 6 of 58 
Information Only 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

calculations and analyses performed in the panel closure redesign and repository reconfiguration 

performance assessment, henceforth referred to as the PC3R PA. 

The work undertaken in the PC3R PAis prescribed in AP-151, Analysis Plan for the WIPP 

Panel Closure Redesign and Repositmy Reconfiguration Performance Assessment (Camphouse 

2010a), which was specifically written to determine the impact of changes proposed in the two 

PCRs on long-term repository performance. In order to isolate the impacts of the repository 

configuration and panel closure design changes, the PC3R PA was designed to deviate as little as 

possible from the PABC-2009 implementation. In particular, the PC3R PA utilizes the same 

waste inventory information, drilling rate and plugging pattern parameters, and radionuclide 

solubility parameters as were used in the PABC-2009. The PC3R PA examines all aspects of 

repository performance that are potentially impacted by the proposed changes to the repository. 

2 REPOSITORY CONFIGURATION CHANGES 

The following sections detail the changes to the repository configuration and panel closure 

design investigated in the PC3R PA. Following the discussion of the repository changes, the 

impacts of these changes on the parameters and computational grids used in the PC3R P A are 

presented. 

2.1 Repository Reconfiguration 

A schematic that depicts the WIPP spatial layout as it has been modeled in PA is shown in 

Figure 2-1. As seen in that figure, the waste disposal region consists of I 0 waste panels. Panels 

1-4 are located east of the central area with panels 5-8 located to the west. Panels 9 and I 0 are 

located in the center area between panels l-4 and panels 5-8. Additionally, panel closures are 

located at the innermost ends of panels 1-8. A set of panel closures is located between waste 

panels 9 and I 0. Another set of closures is located between panels 1-10 and the southern end of 

the operations region. A final set of closures is located in the operations region south of the 

repository shafts. These locations of waste panels and panel closures have been implemented in 

the models used in performance assessments since the original CCA, including the PABC-2009. 

The changes to the repository configuration that are modeled in the PC3R PA include the 

relocation of panels 9 and I 0, the removal of panel closures in the central drift area, and a 

redesign of panel closures that remain. Panels 9 and l 0 are relocated south of panels 4 and 5 in 

the PC3R PA and denoted as panels 9a and I Oa. In effect, the waste area is lengthened with 

duplicate copies of panels 4 and 5, and their corresponding panel closures, located at the 

southernmost end of the repository. The resulting waste panel configuration consists of panels 1-

4, 9a east of the central area and panels 1 Oa, 5-8 west of the center. Panels 1-8, 9a, and 1 Oa are 

modeled as having identical panel closures located at their innermost ends. 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

With the relocation of panels 9 and I 0 to the southernmost end of the repository, panel closures 

located in the central drift area are removed. Consequently, the set of panel closures located 

between current panels 9 and 10, between the waste disposal region and the operations area, and 

between the southern portion of the operations area and the repository shafts are not present in 

the PC3R PA representation of the repository. 

Finally, the representation of panel closures that remain for panels 1-8, 9a, and lOa is changed in 

the PC3R PA. "Option D" panel closures were modeled in the PABC-2009, and are represented 

in Figure 2-1 by black segments at the ends of waste panels and at appropriate locations in the 

central drift area. Panel closures are proposed to be modified from the current "Option D" 

design to that of a new design consisting of 100 feet of run of mine salt emplaced against a 

significant barrier on the waste disposal side. As the characterization of the significant barrier is 

still underway, the redesigned panel closures are modeled in the PC3R PA as consisting solely of 

100 feet of run of mine salt. The reconfigured repository modeled in the PC3R PA is shown in 

Figure 2-2, where redesigned closures are depicted by oval segments at the innermost ends of 

waste panels. 

Page 8 of 58 
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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

j7 Jl n nn 

El<perim""tal Region I DOD DOD! ID~~ ol 

I ~~ u 

• I 1 

Air Intake Sllaft Salt Handling Shaft i-

~-~ Exhaust 

Shaft 

_1 

- Vl'ute~ Shalt 

Future Panel 

Closure S~tems~ (nol lo scale) 

·-------······· ... ( 

PineiS 

:

1

.,,-.... :l .. "~:c· .. : . .-":;:~:o~: .... -

i : 

I 

I 

j 

Op erations: 

R eglon 

Panel1 ! . . 

' ....• : ... i .... ;: ___ ;, ___ ,~ -i i :; __ ,_ '······.·.·.-.-.. ·.··.-.· .. ·.-····--·· ................... ·•'· :[ "o·.-y· ·i' c···c .. 

Wa<J.e 

Disposal 

Region 

Panat 7 

p..,el6 

Panel 5 

,

1 p..,e110 

·:· ·:·:· .. -;; ·-;:- --~.-- -~~ ............ . 

+.,...._-PanelS 

' i -~ T ;: ,_[: :: 1:. 

- - · · - .L.. _ ~-~~~-•_ .. __ .J_l_.,_. __ i_J..-.· .. · .. :.:-::::.::.·::.~::::.:::::.':::::.'::::::--:.':: -- -- -

Figure 2-1: Historical WIPP Repository Layout 

Page 9 of 58 

·• Panel 2 

Plmel3 

Panel 4 

......... ; 

200 

I 

(meters) 
Information Only 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision l 

n n n nn 

Experimental Region DODD DO ~~D 

I 

l~ u u • I 

Air Intake Shaft Salt Handling Shaft rWaste 

Disposal 

Region 

~fl": 

' 

~ 

- Waste~ Shaft 

Future Panel 

Exhaust 

Shaft 

Operati ons 

Regi on 

(not to scale) 

Closure Syslems\ 

.. . , .. -, .. , ..... ,, ... , •.. .......... 

. ,,,,,,._:_,,,_,_._, 'l..,_.l .. :,,,,i:·;·-·-·-'.' ... i ··.·.•.-.·-.·.-.•.··· •• ,. 

:; ;, :: 

Panel1 

:: ir-1 :·]r·',•r ,. :\ !\ ,:,• ' : . ' . ' 

' .!; ;_!_·~~·;;::!.>.-,)\ "~·-~-

Panel 7 Panel2 

Panel 6 Panel3 

-'--·{.!,~, 

. i_i i )'·<~ . !' 

!-

- --·····- •.. ;.J ....................... . -----,~--: i ---~----:---, :·-- i ,--·-jr-·]:·--i:·-·:r··:_:_r···;: 

ll-::JL)L __ -.LJ~ __ U; ~!_.._;:: .• ;___ ~.-.LJLf .. !~ .:! ....... -~! 

Panel 5 

Pa.nei10a 

, __ ; 

Panel 4 

Panel9a 

1 110 ~0 

(meters) 

Figure 2-2: WIPP Layout Modeled in PC3R PA 

Page 10 of 58 
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2.2 Parameters 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

In order to isolate the impacts of the repository changes discussed above, the PC3R PA was 

designed to deviate as little as possible from the PABC-2009 implementation. However, 

changes due to the reconfigured waste panel and closure arrangement, as well as the 

implementation of panel closures consisting of 100 feet of run of mine salt, impact a subset of 

the parameters prescribed in the PABC-2009. Justifications of new and modified parameters 

used in the PC3R PA are provided in Camphouse (2010b, 2010c, 2011a). The same material 

property values and ranges used in the PABC-2009 were also used in the PC3R PA, with the 

exception of the material and property changes discussed below. 

Panel Closure Parameters 

The majority of PC3R PA parameter changes are due to the incorporation of run of mine salt 

panel closures, and these changes are now discussed. The PC3R PA panel closure system has 

initial permeabilities and porosities that are significantly different than the permeabilities and 

porosities expected to be present for the vast majority of the 10,000 year regulatory timeframe. 

In other words, PC3R panel closures have "short-term" initial characteristics and "long-term" 

characteristics. As a result, two materials are used to describe PC3R panel closures. Material 

PCS _ Tl is the material used to represent panel closures for an initial time period of 100 years. 

Material PCS_T2 is the material used to represent closures for the remaining 9,900 years. Initial 

and long-term time periods are selected to be consistent with the lengths of time required for the 

porosity of the run of mine salt used in the panel closures to fall below 5 percent. Numerical 

simulations demonstrate this period of time to be less than 100 years (Callahan and DeVries 

1991 ). This time duration is also consistent with that proposed during the 2002 panel closure 

redesign impact assessment (Hansen and Thompson 2002). 

Constant values and probability distributions used for parameter sampling were established for 

properties associated with materials PCS_Tl and PCS_T2. Constant values and probability 

distributions corresponding to material PCS_Tl are shown in Table I and Table 2, respectively. 

Constant values and probability distributions established for material PCS _ T2 properties 

COMP_RCK, SAT_RBRN, SAT_RGAS, RELP_MOD, CAP_MOD, KPT, PC_MAX, 

PO_MIN, PCT_A, PCT_EXP, and PORE_DIS are identical to those established for material 

PCS_Tl. The value specified for the porosity of material PCS_T2, i.e. parameter 

PCS_T2:POROSITY, is 0.05 (dimensionless). 

The panel closure redesign impact assessment performed in 2006 (Vugrin and Dunagan 2006) 

also used materials PCS _ T1 and PCS _ T2 to model the changing material properties of the panel 

closure as a function of time. In that analysis, the panel closure design consisted of I 00 feet of 

run of mine salt emplaced against a 30 foot mortared, solid concrete block wall on the waste 

disposal side. Parameter distributions for the long-term permeability of the run of mine salt 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision l 

component were developed during the 2006 impact assessment (Vugrin, Hansen, and Thompson 

2006). The permeability distribution developed in that analysis is used to describe the long-term 

permeability of the panel closure implemented in the PC3R P A. The resulting probability 

distribution used to specifY the log of intrinsic permeability of material PCS _ T2 is shown in 

Table 3. 

Stein (2002a) introduced material DRZ_PCS as the portion of the disturbed rock zone directly 

above and below the panel closure system. This material is used in P A to describe temporal 

characteristics of the DRZ about a panel closure. For the I 00 foot run of mine salt panel closures 

implemented in the PC3R PA, the properties prescribed to material DRZ_PCS were done so as to 

reflect the changing material properties of the redesigned closure system as a function of time. 

During the first 100 years while the run of mine salt panel closures are reconsolidating to their 

steady-state properties, material DRZ _PCS is specified to have identical properties to the 

remaining DRZ. In other words, it is assumed that the DRZ directly above and below the panel 

closure is unaffected by the changing panel closure properties during the first I 00 years. The 

permeabilities prescribed for material DRZ _PCS during the first 100 years are identical to those 

prescribed to the DRZ overall, i.e. those specified for PA material DRZ _I. These permeability 

distributions are given in Table 4. After the first 100 years, permeability values of material 

DRZ_PCS are prescribed so as to be consistent with the permeabilities of the reconsolidated 

panel closures. As a result, they are assigned the permeability distributions given to material 

PCS_T2 as shown in Table 3. 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

Table 1: Constant Parameters Used for Material PCS_Tt 

Parameter (units) Description Value 

PCS Tl: COMP RCK (Pa-1

) Bulk compressibility 8x!O·II 

PCS Tl:POROSITY (n/a) Effective porosity 0.33 

PCS Tl:PRMX LOG (log(m2

)) Log of intrinsic permeability, -11.0 

PCS Tl:PRMY LOG (log(~) x,y,z directions 

PCS Tl:PRMZ LOG (log(m2

)) 

PCS T1:SAT IBRN (n/a) Initial brine saturation 0.054 

PCS_T1:RELP_MOD (nla) Model number, relative 4.0 

permeability model 

PCS T1 :CAP MOD (n/a) - - Model number, capillary 1.0 

pressure model 

PCS T1:KPT (n/a) Flag for permeability 0.0 

determined threshold 

PCS_Tl:PC_MAX (Pa) Maximum allowable capillary lxlO' 

pressure 

PCS Tl:PO MIN (Pa) - - Minimum brine pressure for 1.01325xl0' 

capillary model KPC~3 

PCS TI:PCT A (Pa) Threshold pressure linear 0.0 - -

parameter 

PCS Tl:PCT EXP (n/a) - - Threshold pressure 0.0 

exponential parameter 

Table 2: Sampled Parameters Used for Material PCS_TI 

Parameter( units) Descrintion Distribution Statistic Value 

PCS_Tl: SAT_RBRN (n/a) Residual Brine Cumulative with Mean 0.25 

Saturation (Prob.,Value) Pairs Median 0.2 

(0,0) Stan. Deviation 0.176 

(0.5,0.2) Minimum 0.0 (1.0,0.6) Maximum 0.6 

PCS_TI: SAT_RGAS (nla) Residual Gas Uniform Mean 0.2 

Saturation Median 0.2 

Stan. Deviation 0.1155 

Minimum 0.0 

Maximum 0.4 

PCS_Tl: PORE_DIS (n/a) Brooks-Corey Cumulative with Mean 2.52 

pore distribution (Prob.,Value) Pairs Median 0.94 

parameter (0,0.11) Stan. Deviation 2.48 

(0.5,0.94) Minimum 0.11 (1.0,8.1) Maximum 8.1 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

Table 3: Log oflntrinsic Permeability Values used for Material PCS_T2 in the PCJR PA 

Parameter (units) Descrintion Distribution Statistic Value 

PCS_T2:PRMX_LOG (log(m')) Log of intrinsic Triangular Mean -20.2 

PCS_T2:PRMY _LOG (log(m2

)) permeability, Mode -20.2 

PCS_T2:PRMZ_LOG (log(m2

)) x,y ,z directions Stan. Deviation 1.06 

Minimum -22.8 

Maximum -17.6 

Table 4: Log of Intrinsic Permeability Values used for Material DRZ-PCS in the PC3R PA for the first 100 years. 

Parameterlunits) Description Distribution Statistic Value 

DRZ_PCS:PRMX_LOG (log(m2

)) Log of Triangular Mean -16.0 

DRZ_PCS:PRMY_LOG (log(m2

)) intrinsic Median -16.0 

DRZ_PCS:PRMZ_LOG (log(m2

)) permeability, Stan. Deviation 2.0 

x,y,z Minimum -19.4 directions Maximum -12.5 

Panel Reconfiguration Parameters 

The relocation and re-sizing of current panels 9 and I 0 to their 9a and I Oa counterparts invoked 

modifications to some of the reference constants (material REFCON) used in the PABC-2009 as 

well as an updated value for parameter DRZ_l:EHEIGHT. Moreover, in the PC3R PA, the 

central drift area was assigned properties corresponding to material OPS_AREA in the PABC2009. As the central drift area in the reconfigured repository has a much larger extent than did 

OPS AREA in the PABC-2009, and is located between west and east waste panels, a new 

parameter OPS_AREA:EHEIGHT was established for use in the PC3R PA. The values 

specified for these remaining parameters in the PC3R PA are shown in Table 5. 

Table 5: PC3R PA Parameters Updated/Created Due to the Repository Reconfiguration 

Parameter (units) Description Value 

REFCON:VREPOS (m') Excavated storage volume of 4.609765xl0' 

repository 

REFCON:FVW (n/a) Fraction of repository volume 0.367 

occupied by waste in 

CCDFGF 

REFCON:AREA CH (m') Area for CH Waste Disposal l.l64xl05 

inCCDFGF 

REFCON:ABERM (m') Berm Area 7.85625xl0' 

DRZ I :EHEIGHT (m) Effective height of the 41.3 

disturbed rock zone for DBR 

calculations 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision l 

OPS AREA:EHEIGHT (m) Effective height ofthe 10.7 - operations area for DBR 

calculations 

2.3 Computational Grid Changes 

PA code BRAGFLO is used in two ways in WIPP PA calculations. First, it is used to calculate 

the flow of brine and gas in and around the repository for undisturbed and disturbed conditions. 

Second, it is used for the calculation of direct brine releases (DBRs). These two uses of 

BRAGFLO require different computational grids. The grid used to calculate brine and gas flow 

in and around the repository is different than that used to calculate DBRs. However, results 

obtained from the brine and gas flow calculation are used to initialize conditions in the DBR 

calculation. The changes proposed to the WIPP repository configuration impact the 

computational grids used in both applications of BRAGFLO. For the sake of completeness in 

this summary report, these changes are now briefly discussed. More detailed discussions of the 

PC3R PA BRAGFLO computational grids, and their differences in regard to the grids used in the 

PABC-2009, can be found in Camphouse and Clayton (2011) & Pasch and Camphouse (2011). 

The historical WIPP configuration shown in Figure 2-1 has been the underlying motivation for 

the repository representation in prior BRAGFLO numerical grids, including the PABC-2009. 

Using that configuration, panel closures located in the central drift area were used to decompose 

the repository waste area into three regions in the PABC-2009. The southwest panel, panel 5 in 

Figure 2-1, was the panel in which inadvertent human intrusion was modeled in BRAGFLO. As 

a result, the southwest panel was modeled separately from the rest of the waste area. The 

remaining waste panels comprised two additional waste regions in the PABC-2009 BRAGFLO 

grid, namely the south rest of repository (SROR) (panels 3, 4, 6, and 9), and the north rest of 

repository (NROR) (panels I, 2, 7, 8, and 10), with each region being separated by a panel 

closure. The location of a panel closure slightly south of the waste shaft resulted in the 

operations (Ops) and experimental (Exp) regions being separated by a material combining panel 

closure and waste shaft properties. The PABC-2009 BRAGFLO grid is shown in Figure 2-3. In 

that figure, regions labeled DRF _PCS and CONC_PCS represent components of "Option D" 

panel closures. 

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' 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

Row 

·······~~ " 

y Col -- ... ·-· ~ -- .., ___ ~,... •- ''~'"'"" -..~~ ..,,..., :-,>-1"~"'·"""''--~ll~~~,~ :.•1'1 ;.;:.oJx::.;li'!JOI~:..-'-> <t::S 'tl""'"' ""-. "'"'"'"'"""'"' "'"'lliu~"' D<~~IIIIIIL Ill 

)-."""""> 

Figure 2-3: PABC-2009 BRAG FLO grid (t.x, t.y, and t.z dimensions in meters). 

"' " " " ,. 

" ,. 

" ,. 

~ 

~ 

" " " " 

.. "

" " " " • • ' • ' 

Following a similar strategy as for the historical WIPP layout shown in Figure 2-1, the 

reconfigured repository shown in Figure 2-2 guides the BRAGFLO computational grid 

implementation in the PC3R PA. In the PABC-2009, panel closures in the central area provided 

a natural way to demarcate the repository into northern and southern regions. In the reconfigured 

repository layout, the open central drift region between west and east waste panels results in a 

BRAGFLO grid with a west-to-east orientation. Panel 1 Oa is used to model inadvertent human 

intrusion. This waste panel is separated from the remaining panels by the open central drift area. 

As a result, remaining panels are lumped together in a rest of repository (ROR) region in the 

PC3R PA BRAGFLO grid. The waste panel, center area, and ROR are separated by panel 

closures comprised of 100 feet run of mine salt. The PC3R PA BRAGFLO computational grid is 

shown in Figure 2-4. 

Page 16 of 58 
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ay 

0.10 

15 66 

43.30 

106.00 

17.30 

6.50 

24.80 

7.70 

36.00 

54.73 

54.73 

5U~ 

54.73 

54.73 

54.73 

503 

Ota 

'" 4.53 

0.27 

2.52 

U1 

1.32 

1.32 

"' "' 0.85 

1.00 

6572 

66.72 

66.72 

52.27 

125.83 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision l 

Figure 2-4: PC3R PA BRAG FLO grid (Ax, Ay, and Az dimensions in meters). 

ll 

" " JO 

29 

" " " 25 

" " 22 

" 20 

" " " " " ,. 

" " " !0

9 

' 

Results from the PABC-2009 BRAGFLO calculation were used to initialize conditions in the 

PABC-2009 DBR calculation. The representation of the waste area by three waste regions in the 

PABC-2009 BRAGFLO grid yielded initial conditions to waste regions comprising the waste 

panel, the SROR, and the NROR in the PABC-2009 BRAGFLO DBR calculations (Clayton 

2010). The initialization of these three regions in the DBR calculation resulted in the 

consideration of drilling intrusions into these regions in the PABC-2009 DBR analysis. These 

locations can be seen in the PABC-2009 DBR computational grid of Figure 2-5. 

Page l7of58 
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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision l 

:;; 6.:0 rimimm!iiiii~mmim~ JO.~O 

30.50 

!OJO 

..... 

Wl 

s.:2 

45.~15 

H~ 

5."~0 

~J-0 

:.o.m 

30.50 

J.0.50 

6AO 

3.60 

:1::s 

~0.00 

:.!.~S 

5.":'0 

..J.JO 

30.50 

30.50 

.!0.~0 

..... 

3.60 

s.:2 

43.96 

~.:l 

~.":'() 

•. JO 

30.50 

3-0.~0 

!0.30 

6.-UI 

HO 

Y s.:2 

X 

~~]!~~~~~~~3~~s~~~A~~~~s~~~~~~~@~§~$~~~ 

~~~~~~~~~2~~~~~~~~~~t~~~M~$z;~~~~~g~~~~ 

Nole: Model cells 11re oot to &eale. The actual 

dimonsiODS of the gnd bloch .,. indicated along 

the edge of the dia~ 

Figure 2-5: PABC-2009 DBR material map (logical grid). 

• 

~Dip North to South 

c::::::JWaste 

(2.4>JQ-U m" penmeabaily) 

-Equivaleat Paoel Oosure 

-lq>ure Haliho 

(Impenueable) 

-Equivalettt DRZIC"""""" 

• BoUDdary coodition well 

forpra'i""' El illtm>iou 

• Do\"\u-dip well,. fint or 

second iotnJsion 

* Up-dip well lint or 

second intrusion 

" h-liddle \Vell first or 

second intcosion 

The reconfigured repository seen in Figure 2-2 resulted in several changes to the numerical grid 

used to analyze direct brine releases in the PC3R P A. First, waste panels 9 and I 0 were removed 

from the central drift area, relocated to the southernmost end of the repository, and denoted as 

panels 9a and I Oa. As panels 9 and I 0 have slightly less area than waste panels 1-8, panels 9a 

and lOa were resized to have areas equal to those of panels 1-8. Second, "Option D" panel 

closures in the PABC-2009 were replaced by panel closures consisting of 100 feet run of mine 

salt with properties corresponding to materials PCS _ Tl and PCS _ T2. Third, panel closures 

located in the central drift area in the PABC-2009 DBR grid were removed in the PC3R PA 

DBR grid. Fourth, the representation of the waste area by two regions in the PC3R PA 

BRAGFLO grid resulted in two drilling locations, an upper and a lower location, in the direct 

brine release analysis undertaken in the PC3R PA. These locations can be seen in the PC3R PA 

DBR computational grid of Figure 2-6. 

Page 18 of 58 
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i.ll 

1.90 

i.IO 

~·).<;0 

3-).50 

3·>.50 

uo 

>.10 

i.ll 

4).96 

i.ll ,,,0 

;.1o 

H.'.iO 

H. 50 H. SO 

uo 

i.70 

i.ll 

4i.96 

i.ll 

1.90 

),10 

3·).50 

3-).50 

3->.50 

l,JO 

).70 

i.ll 

4i.96 

Ul 

3.90 

i.10 

3-).50 

H. 50 H. 50 

uo 

;.JO 

i.l2 

4).96 

i.l2 

'·"' ;.10 

3->.50 'an~llO<l lJ.50 

~·).~0 

uo 

,L:' 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

Panel! 

Panel 2 

Panel 3 

Panel4 

Panel9a 

(Grid Spacincs in Meters) 

N 

s 

1° Dip North to £outh 

~Waste 

-DRZ 

c=::::J Opan Central Drift 

• Boondatycond:itionweU 

forprwiow F. I intruo:icn. 

j, Down-dip veil, fint 0!" 

secondintrJ.Sion. 

* Up-dip wet, first. o: secondintr.lsion 

Figure 2-6: PC3R PA DBR material map (logical grid). 

Material properties for the open central drift area in the PC3R PA are assigned values 

corresponding to the operations area (material OPS AREA) in the PABC-2009. Parameter 

OPS_AREA:EHEIGHT was established for use in the PC3R PA DBR calculations in order to 

achieve agreement between the three-dimensional representation of the central region in 

BRAGFLO and the two-dimensional representation of this region in the DBR numerical grid. 

This property provides a means of matching porosity and pore compressibility in the central drift 

region across the BRAG FLO and DBR calculations. Its value is given in Table 5. 

In both the PABC-2009 and the PC3R PA, consideration of drilling events was restricted to those 

repository regions with emplaced waste. Waste is not emplaced in the operations and 

experimental areas of the historical WIPP repository configuration, nor in the central drift area of 

the PC3 R P A configuration. As a result, potential drilling intrusions into these areas will not 

result in cuttings, cavings, or spallings releases. Potential releases following an intrusion into 

these areas require that they contain a sufficient volume of waste-contaminated brine under 

sufficient pressure. For this to occur, brine must interact with waste in a panel and migrate to a 

non-waste containing region to be available for release at the time of intrusion. In all cases 

investigated in the Salado flow modeling of the PC3R PA (see Section 5.1 of this summary 

report), the total flow of brine out of the waste panel was reduced (on average) when compared 

Page 19 of 58 
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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

to results obtained in the PABC-2009. The panel closure redesign and repository configuration 

implemented in the PC3R PA does not result in an increase in contaminated brine leaving a 

waste panel. Furthermore, as discussed and demonstrated in Section 5.2, an intrusion into a 

waste panel will not result in a consequential increase in brine volume in the central drift area to 

later be released to the surface by a subsequent intrusion in that area The brine available for 

release to the surface following a drilling event into the central drift region is brine present under 

undisturbed conditions, regardless of previous intrusions into a waste panel. In addition, drilling 

intrusions into the central drift region can only reduce releases following an intrusion into a 

waste panel. For quantification of releases, the consideration of drilling intrusions into wastecontaining regions is sufficient, and is conservative. 

2.4 FEPS Re-assessment 

An assessment of the FEPs baseline was conducted to determine if the current FEPs basis 

remains valid in consideration of changes introduced by the PC3R PA, and was performed 

according to SP 9-4, Performing FEPs Impact Assessment for Planned or Unplanned Changes. 

The FEPs analysis concludes that no additional FEPs are needed to accurately represent the 

changes that represent the repository layout (including the location of the PCS) and the PCS 

design and construction. Additionally, no FEPs screening arguments and associated screening 

decisions require modification to account for the changes represented in the PC3R PA (Kirkes 

2011). 

3 METHODOLOGY 

The performance assessment methodology accommodates both aleatory (i.e. stochastic) and 

epistemic (i.e. subjective) uncertainty in its constituent models. Aleatory uncertainty pertains to 

unknowable future events such as intrusion times and locations that may affect repository 

performance. It is accounted for by the generation of random sequences of future events. 

Epistemic uncertainty concerns parameter values that are assumed to be constants and the 

constants' true values are uncertain due to a lack of knowledge about the system. An example of 

a parameter with epistemic uncertainty is the permeability of a material. Epistemic uncertainty is 

accounted for by sampling of parameter values from assigned distributions. One set of sampled 

values required to run a WIPP PA calculation is termed a vector. In the PC3R PA, models were 

executed for three replicates of I 00 vectors, each vector providing model realizations resulting 

from a particular set of parameter values. Parameter sampling performed in the PC3R PA is 

documented in Camphouse (20 11 b), and the sensitivities of variable output to sampled 

parameters are documented in Hansen (2011). A sample size of 10,000 possible sequences of 

future events is used in PA calculations to address aleatory uncertainty. The releases for each of 

I 0,000 possible sequences of future events are tabulated for each of the 300 vectors, totaling 

3,000,000 possible sequences. 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision l 

For a random variable, the complementary cumulative distribution function (CCDF) provides the 

probability of the variable being greater than a particular value. By regulation, performance 

assessment results are presented as a distribution of CCDFs of releases (U.S. EPA 1996). Each 

individual CCDF summarizes the likelihood of releases across all futures for one vector of 

parameter values. The uncertainty in parameter values results in a distribution of CCDFs. 

Releases are quantified in terms of "EPA units". Releases in EPA units result from a 

normalization by radionuclide and the total inventory. For each radionuclide, the ratio of its 

10,000 year cumulative release (in curies) to its release limit is calculated. The sum of these 

ratios is calculated across the set of radionuclides and normalized by the transuranic inventory 

(in curies) of a-emitters with half-lives greater than 20 years. Mathematically, the formula used 

to calculate releases in terms of EPA units is ofthe form 

1 X 106 curies'\' Qi 

R= c LT 

i ' 

where R is the normalized release in EPA units. Quantity Q, is the I 0,000 year cumulative 

release (in curies) of radionuclide i. Quantity L, is the release limit for radionuclide i, and Cis 

the total transuranic inventory (in curies) of a-emitters with half-lives greater than 20 years. 

The PC3 R P A was developed so that the structure of calculations performed therein was as 

similar as possible to that used in the PABC-2009. PABC-2009 calculated results potentially 

impacted by the repository reconfiguration and panel closure redesign discussed above were 

updated, while the results from previous PAs were used for individual numerical codes not 

affected by these changes. The PC3R PA utilized the same waste inventory information, drilling 

rate and plugging pattem parameters, and radionuclide solubility parameters as were used in the 

PABC-2009. In addition, transport releases through the Culebra calculated in the PABC-2009 

were also used in the PC3R PA. Separate documentation was prepared describing calculations 

performed and results obtained for each code executed in the PCJR P A. Citations for this 

additional documentation are included in the references section of this summary report, and are 

indicated in the list below. 

• Parameter Sampling (Camphouse 2011b) 

• Sensitivity Analysis (Hansen 2011) 

• Salado Flow (Camphouse and Clayton 2011) 

• Cuttings, Cavings, and Spallings (Kicker 2011) 

• Actinide Mobilization and Transport (Camphouse and Garner 2011) 

• Direct Brine Releases (Pasch and Camphouse 2011) 

• CCDF Normalized Releases (Camphouse 201lc) 

Page21 of 58 
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4 RUN CONTROL 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

Execution of Performance Assessment Codes for the WIPP Panel Closure Redesign and 

Repository Reconfiguration (Long 2011) provides documentation of run control and code 

execution for the PC3R PA. This document contains: 

I. A description of the hardware platform and operating system used to perform the 

calculations. 

2. A listing of the codes and versions used to perform the calculations. 

3. A listing of the scripts used to run each calculation. 

4. A listing of the input and output files for each calculation. 

5. A listing of the library and class where each file is stored. 

6. File naming conventions. 

5 RESULTS 

Summary results obtained from PC3R PA calculations are broken out in subsections below, and 

are compared to PABC-2009 results. Salado flow modeling results are presented in Subsection 

5.1. The effectiveness of the redesigned panel closures in regard to the isolation of drilling 

intrusion effects is discussed in Subsection 5.2. Impacts of the repository reconfiguration and 

panel closure redesign on actinide mobilization and transport are shown in Subsection 5.3. 

Results obtained for cuttings and cavings are presented in Subsection 5.4. Spallings results are 

presented in Subsection 5.5. Direct brine releases are presented in Subsection 5.6. The impact 

of the changes investigated in the PC3R PA on regulatory compliance is discussed in terms of 

total normalized releases in Subsection 5. 7. As the CCDF is the regulatory metric used to 

demonstrate compliance, comparisons of CCDFs obtained in the PC3R PA and the PABC-2009 

are compared for each component of release in the appropriate subsection. 

5.1 Salado Flow Results 

The BRAGFLO software calculates the flow of brine and gas in the vicinity of the WIPP 

repository over the I 0,000-year regulatory compliance period. During BRAG FLO calculations, 

stochastic uncertainty is addressed by defining a set of six scenarios for which brine and gas flow 

is calculated for each of the vectors generated via parameter sampling. The total number of 

BRAGFLO simulations executed in the PC3R PAis 1,800 (300 vectors times 6 scenarios). 

The six scenarios used in the PC3R PA are unchanged from those used for the PABC-2009. The 

scenarios include one undisturbed scenario (Sl-BF), four scenarios that include a single 

inadvertent future drilling intrusion into the repository during the 10,000 year regulatory period 

(S2-BF to S5-BF), and one scenario investigating the effect of two intrusions into a single waste 

panel (S6-BF). Two types of intrusions, denoted as El and E2, are considered. An E1 intrusion 

assumes the borehole passes through a waste-filled panel and into a pressurized brine pocket that 

Page 22 of 58 
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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

may exist under the repository in the Castile formation. An E2 intrusion assumes that the 

borehole passes through the repository but does not encounter a brine pocket. Scenarios S2-BF 

and S3-BF model the effect of an El intrusion occurring at 350 years and 1000 years, 

respectively, after the repository is closed. Scenarios S4-BF and S5-BF model the effect of an E2 

intrusion at 350 and 1000 years. Scenario S6-BF models an E2 intrusion occurring at 1000 

years, followed by an E 1 intrusion into the same panel at 2000 years. Transport releases to the 

Culebra are captured in Scenario S6-BF. Scenario S6-BF is used for determining the 

radionuclide source term to the Culebra in the P A code PANEL, and results of this scenario are 

discussed in Subsection 5.3. Table 6 sunnnarizes the six scenarios used in this analysis. 

Table 6: BRAG FLO Modeling Scenarios 

Scenario Description 

51-BF Undisturbed Repository_ 

52-BF E 1 intrusion at 350 years 

53-BF E1 intrusion at 1,000 years 

54-BF E2 intrusion at 350 years 

55-BF E2 intrusion at 1,000 years 

56-BF E2 intrusion at 1,000 years; E1 intrusion at 2,000 years. 

Computed results are presented for the PC3R PA and compared with those obtained in the 

PABC-2009. Results are discussed in terms of overall means. Overall means are obtained by 

forming the average of the 300 realizations calculated for a given quantity and scenario. Results 

are presented for undisturbed scenario Sl-BF. Intruded results are presented for scenarios S2-BF 

and S4-BF, as these are representative of the intrusion types considered in scenarios S2-BF to 

S5-BF with the only differences being the timing of drilling intrusions. The computational grids 

used to generate Salado flow results in the PABC-2009 and the PC3R PA are shown in Figure 

2-3 and Figure 2-4, respectively. 

Undisturbed Scenario Sl-BF 

Scenario Sl-BF overall means of porosity in the waste panel, quantity WAS_POR, for the PC3R 

PA and the PABC-2009 are shown together in Figure 5-l. As is clear from that figure, there is 

very little difference in the time-histories of waste panel porosities for both analyses. Porosities 

in both analyses reduce rapidly, with the average porosity nearing its steady-state value within 

hundreds of years following facility closure. 

Overall means of volume-averaged pressure in the waste panel, quantity WAS_PRES, for the 

PC3R PA and the PABC-2009 are shown together in Figure 5-2. As seen in that figure, the 

volume averaged pressure for the PC3R PAis slightly lower than that seen in the PABC-2009. 

The reason for this reduction is seen in Figure 5-3. In Figure 5-3, the overall mean of quantity 

WAS _pRES is plotted on a time scale of 0 to 150 years for both the PC3R PA and the PABC2009. As the porosity of the waste panel rapidly decreases in the time period immediately after 

Page 23 of 58 
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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

facility closure, the higher permeability and porosity of the run of mine salt panel closure for the 

first 100 years allows the increasing pressure to be released into the open central area between 

the waste panel and the rest of the repository. At t = I 00 years, the porosity and permeabilities 

of the panel closures are reduced to their steady-state values. At t = 100 years in Figure 5-3, 

there is a distinct increase in the rate of pressure rise in the waste panel. By this time, however, 

the porosity in the waste panel is nearing its steady-state value, and so much of the increasing 

pressure in the waste panel responsible for the decreasing porosity has been vented into the open 

central area. The net effect is a slightly reduced volume-averaged pressure in the waste panel for 

the PC3R PA. 

The overall mean of brine saturation in the waste panel, quantity WAS_ SA TB, is shown in 

Figure 5-4. As seen in that figure, waste panel brine saturation results obtained in the PC3R PA 

for the undisturbed repository condition are nearly identical to those found in the P ABC-2009. 

The overall means of total brine flow out of the waste panel, quantity BRNW ASOC, is shown in 

Figure 5-5. As seen in that figure, the brine flow out of the waste panel decreased for Scenario 

Sl-BF in the PC3R PA. This reduction is due to the lower waste panel pressure as compared to 

the PABC-2009. The slightly lower long-term permeabilites of the PC3R PA panel closures also 

contributed to the reduction of brine flow out of the waste regions. While the larger initial 

porosity and permeabilities of the panel closures investigated in the PC3R PA allow pressure 

release from the waste panel into the center area for the first 100 years, their use does not result 

in an increase in brine flow out of the waste panel. 

Overall means of total brine flow up the shaft, quantity BNSHUDRZ, are shown in Figure 5-6. 

In the PC3R PA, the shaft is directly above the open central region in the BRAGFLO grid. The 

open central region contains the open volume of the operations and experimental area as well as 

the open volume associated with panels 9 and 10 in the PABC-2009 grid. The increase in 

volume translates to a reduction in pressure in the center area. The total brine flow up the shaft 

decreased for Scenario Sl-BF in the PC3R PA due to the lower pressure in the open central 

regwn. 

Page 24 of 58 
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1 

0.9 

0.8 

0.7 

0:: 

0.6 

0 

0.. 

I 0.5 

(fJ 

~ 0.4 

0.3 

0.2 

0.1 

0 

0 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

O.erall 81-BF Means 

1000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

lime (years) 

Figure 5-1: Overall Means of Volume Averaged Porosity for the Waste Panel, Scenario SI-BF 

X 106 

10 

9 

8 

7 

'@' 

e:. 6 

(fJ 

UJ 

0:: 5 

D.. I 

(fJ 

~ 4 

3 

2 

1 

0 

0 

O.erall 81-BF Means 

~--~----------------------­ ...... --

I-PC3R I ----- PABC2009 

·! 

1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 

lime (years) 

Figure S-2: Overall Means of Volume Averaged Pressure for the Waste Panel, Scenario Sl-BF 

Page 25 of 58 
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7 

3 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

O~.erall S 1-BF Means 

I-PC3R I =----- PABC200~ 

OL_ ____________ L_ ____________ L_ __ _ 

0 50 100 

lime (years) 

Figure S-3: Overall Means of Volume Averaged Pressure for the Waste Panel During the First !50 Years After 

Closure, Scenario S1-BF 

O~.erall S 1-B F Means 

1r-~~~~~~~~~~~=-~~~==~ 

I ' -PC3R I 

o.9c 

0.8 

0.7 

m 0.6 

!;( 

(/)1 0.5 

(/) 

,; 

;_;: 0.4 

0.3 

0.1 

0 .__\. 

----- PABC2009_. 

0 1 000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

lime (years) 

Figure 5-4: Overall Means of Brine Saturation in the Waste Panel, Scenario S1-BF 

Page 26 of 58 
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250 

200 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

O~.erall S1-BF Means 

g 150 

(/) 

~ z 

a:: 

m 100 

0 L__ _L_ __ .•..• _L_ _ _j 

0 1 000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

Time (years) 

Figure 5-S: Overall Means of Total Brine Flow Out of the Waste Panel, Scenario St-BF 

~ 

§.. 

~ 0 

:::> 

I 

(/) 

z 

cc 

O~.erall S1-BF Means 

,---~--,---~-~--~-~--~--~-~-

7 

6 

5 ---PC3R ~ 

----- PABC2009 

4 

3 

2 

o~~10~0~0~2~0~00~~3~00~0~4~00~0~5~00~0~600~~0~7=oo~o~~80~00~~9~0~00~~10~000 

Time (years) 

Figure S-6: Overall Means of Total Brine Flow Up the Shaft, Scenario St-BF. 

Page 27 of 58 
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Disturbed Scenario 82-BF 

Summary Report for tbe AP-151 (PC3R) Performance Assessment 

Revision 1 

PC3R PA results for intrusion scenario S2-BF are now presented and compared with results 

obtained in the PABC-2009. As before, comparisons are made by use of overall means obtained 

in both analyses. A comparison of the PC3R PA and the PABC-2009 overall means of volume 

average porosity in the waste panel is provided in Figure 5-7. As can be seen in that figure, there 

is very close agreement between the porosities obtained in both analyses. 

The overall means of volume averaged pressure obtained in the PCJR PA and the PABC-2009 

are shown together in Figure 5-8. As seen in that figure, there is an increase in pressurization of 

the waste panel for a period of time following the drilling intrusion. This increase is due to the 

lower long-term permeability ranges of the PC3R panel closures. The result of this increased 

pressure, in combination with the "tighter" panel closures, is a reduction (on average) in the 

volume of brine in the waste panel. The reduction in waste panel brine volume as compared to 

the PABC-2009 yields a corresponding reduction in brine saturation, as seen in Figure 5-9. Gas 

generation processes in the waste panel require the availability of brine to proceed. The 

reduction in brine saturation seen in the PC3R PA for intrusion Scenario S2-BF results in an 

overall decrease in gas generation in the waste panel. The result is a gradual decrease over time 

in the volume-averaged pressure seen in the waste panel in the PC3R PA as compared to the 

PABC-2009, with the pressure seen in the PC3R PA eventually falling below that of the PABC2009. 

The overall means of total brine flow out of the waste panel for intrusion Scenario S2-BF are 

shown in Figure 5-10 for both the PC3R PA and the PABC-2009. As seen in that figure, there is 

very good agreement between the PC3R PA and PABC-2009 results, with a slight reduction 

evident in the average total flow out of the intruded waste panel for the PC3R PA. The 

repository configuration and panel closure design implemented in the PC3R PA does not result 

in an increase in brine flow out of the waste panel for E I intrusion scenarios. 

The overall means of total brine flow up the borehole, quantity BNBHUDRZ, are shown together 

for both analyses in Figure 5-11. As is clear in that figure, very good agreement is apparent 

between the PC3R PA and PABC-2009 results. 

Page 28 of 58 
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0.9 

0.8 

0.7 

0.6 rr 

0 

0.. 

(/)1 0.5 

"' $: 0.4 

0.3 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

O~.erall S2-BF Means 

I-PC3R I :-·--- PABC2009 

J 

0.2 ~------------.:=---=-----=----~---- 0.1 

OL_ ___ L_ __ ~--~--~--_L __ _L __ _l __ ~--~--~ 

0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 

Time (years) 

Figure 5-7: Overall Means of Volume Averaged Porosity for the Waste Panel, Scenario S2-BF 

X 106 O~.erall S2-BF Means 

10 I-PC3R 1; .......... PABC2009 

9 

-------------------------------- 8 

.., 7 

(l;. 

(/) 6 

LJ.J 

rr 

0.. 5 I 

(/) 

~ 4 

3L 

2 

0 

0 1000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

Time (years) 

Figure 5-8: Overall Means of Volume Averaged Pressure for the Waste Panel, Scenario S2-BF 

Page 29 of 58 
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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

0\.erall 82-BF Means 

1~~--~~---~~--~~~~==~ 

1

-PCJR 1 

.......... PABC20091- 0.9 

0.8 

0.7 

"' 0.6 

~I 0.5 

~ 0.4 

0.3 

0.2 

0.1 

~-- ... 

~~~~~~-~-----------------~-----~-

_.., _________ _ 

0 .........L. _L..._ __ ..J. __ .L_ _ __j 

0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 

Time (years) 

Figure 5-9: Overall Means of Brine Saturation in the Waste Panel, Scenario S2-BF 

0\.erall S2-BF Means 

15000 

"'- 10000 I-PC3R I .......... PABC2009 

.s 

() 

0 

"' 

~ z 

0:: 

"' 5000. 

0~--~---L __ _L __ ~ ____ l_ __ J_ __ _L __ ~----L_~ 

0 1000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

Time (years) 

Figure 5-10: Overall Means of Total Brine Flow Out of the Waste Panel, Scenario S2-BF 

Page 30 of 58 
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9000 ~ soooL 

7000 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

Owrall S2-BF Means 

1--PC3R I 

............. PABC2009 

"'E' 6000. 

S! 

0 

:J 

J: 

"' z 

"' 

5000 

4000 

3000 ;_ 

~_____j_______~~- -

2000-

1000 

0 

0 1 000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

Time (years) 

Figure 5-11: Overall Means of Total Brine Flow Up the Borehole, Scenario S2-BF 

Disturbed Scenario S4-BF 

PC3R P A results for intrusion scenario S4-BF are now presented and compared with results 

obtained in the PABC-2009. As before, comparisons are made by use of overall means obtained 

in both analyses. The overall means of volume averaged porosity for the waste panel in Scenario 

S4-BF are shown together in Figure 5-12 for both the PC3R PA and the P ABC-2009. As seen in 

that figure, there is very close agreement in this quantity across both analyses, with the mean 

obtained in the PC3R PA attaining a slightly lower value by the end of the 10,000 year 

regulatory period. 

The overall means of volume averaged pressure for the waste panel found in Scenario S4-BF for 

the PC3R PA and the PABC-2009 are shown in Figure 5-13. As seen in that figure, the waste 

panel mean average pressure found in the PC3R PAis lower than that seen in the PABC-2009. 

As discussed for Scenario Sl-BF, the higher permeability values of the PC3R PA panel closures 

during the first I 00 years allows some pressure release from the waste panel to the center region. 

The effect of this in Scenario S4-BF is clearly seen in Figure 5-14. In that figure, the rate of 

pressure increase in the waste panel found in the PC3R PA is lower during the first 100 years 

than that seen in the PABC-2009. The net result is a reduction in the overall mean pressure in 

the waste panel by the time the panel closures attain their long-term permeabilities. This reduced 

Page31 of58 
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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

pressure is maintained after the Scenario S4-BF drilling intrusion at 350 years, resulting in lower 

average pressure in the waste panel for the remaining duration of the I 0,000 year regulatory 

period. 

The waste panel pressure reduction seen in the PC3 R P A calculations results in a corresponding 

slight increase in brine volume in the waste panel. The slight increase in brine volume translates 

to a slight increase in the mean brine saturation as seen in Figure 5-15. The lower mean pressure 

seen in the PC3R PA combined with the lower long-term perrneabilities of the panel closures 

implemented therein results in an overall reduction in the overall mean of total brine flow out of 

the waste panel, as is illustrated in Figure 5-16. The repository configuration and panel closure 

design implemented in the PC3R PA did not yield an increase in brine flow out of the waste 

panel for E2 intrusion scenarios. 

A slight increase was seen in the overall mean of total brine flow up the borehole in the PC3R 

PA as compared to the PABC-2009, as is shown in Figure 5-17, most likely due to the slight 

increase in the waste panel brine volume seen in the PC3R PA. This increase is slight, however, 

amounting to less that 50m3 by the end of the 10,000 year regulatory period. 

0.9 

0.8 

0.7 

0:: 0.6 

0 

Q. 

(j)l 0.5 

3! 0.4 

0.3 

0.2 

0.1 

0-.erall S4-BF Means 

~ PC3R I ----- PABC20091-

OL---~---L--~ ____ L_ __ ~ __ _L __ ~----L---~--~ 

0 1 000 2000 3000 4000 5000 6000 7000 8000 9000 10000 

Time (years) 

Figure 5-12: Overall Means of Volume Averaged Porosity for the Waste Panel, Scenario S4-BF 

Page 32 of 58 
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-m 

e, 

(/) 

UJ 

0: 

a. I 

(/) 

~ 

6 

5 

4 

3 

2 

1 . 

I 

/ 

I 

/ 

/ 

/ 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

;; 

;; 

Owrall 54-BF Means 

~~~ ~~-----------------­

------------- ;' 

;~~----1 

1-PCJR I 

----- PABC2009 

0 _--.....-L._ __ ~~; ~~~_L_ ____ _ 

0 1 000 2000 3000 4000 5000 6000 7000 8000 9000 10000 

Time (years) 

Figure 5-13: Overall Means of Volume Averaged Pressure for the Waste Panel, Scenario S4-BF 

-m 

e, 

(/) 

UJ 

a: 

a. I 

(/) 

~ 

Owrall 54-BF Means X 106 

5,-----~----.---

4.5 

4 

3.5 

3 

2.5 

2 

1.5 

0.5 / 

/ 

/ 

_.., , \ 

/ \ , \ 

/ \ , \ 

/ ' ,,' '"-. ............... --

1-PCJR I 

.............. PABC2009 

OL----~----~~--~~---L~--~----~--~ 

0 100 200 300 400 500 600 700 

Time (years) 

Figure 5-14: Overall Means of Volume Averaged Pressure for the Waste Panel During the First 700 Years 

After Closure, Scenario S4-BF 

Page 33 of 58 
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0.9 

0.8 

0.7 

CD 0.6 

!;( 

u>, 0.5 

U) 

<{ 

s: 0.4 

0.3 

0.2 

0.1 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

Overall S4-BF Means 

i=-PC3R = I -- PABC2009 

::::---~---~----~------------~---------- -----~----

o~~10~0~0~2~00~0~~3~00~0~40~0~0~5~00~0~~600~0~7~00~0~~800~0~00~00~~10~000 

lime (years) 

Figure 5-15: Overall Means of Brine Saturation in the Waste Panel, Scenario S4-BF 

1000 

800 

"'-

s 

(.) 600 0 

U) 

~ z 

a: 

CD 400 

200 

O;erall S4-BF Means 

--PC3R ~ ............... PABC2009 

1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 

Time (years) 

Figure 5-16: Overall Means of Total Brine Flow Out ofthe Waste Panel, Scenario S4-BF 

Page 34 of 58 
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250 

200 

50 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

Overall 84-BF Means 

I-PC3R::] =----- PABC2009 

o~~l_--~ __ _L __ ~--~----L_ __ i_ __ _L __ _L __ __ 

0 1000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

lime (years) 

Figure 5-17: Overall Means of Total Brine Flow Up the Borehole, Scenario S4-BF 

5.2 Brine Isolation after Intrusion 

As discussed and demonstrated in the PC3R PA BRAGFLO results above, the cumulative brine 

flow out of an intruded waste panel was reduced on average as compared to the PABC-2009 

results. One may also ask how the presence of relatively high pressures and brine volumes on 

one side of a redesigned panel closure impact brine volumes and saturations on the opposite side. 

In particular, is additional brine in the waste panel following an intrusion relocated to the central 

drift area where it can be released to the surface by a subsequent drilling intrusion in that region? 

To answer this question, the PC3R PA overall pressure means in the waste panel for the 

undisturbed scenario and intrusion scenarios S2-BF, S4-BF, and S6-BF are shown together in 

Figure 5-18. As seen in that figure, there is significant variance in the average waste panel 

pressure in the scenarios considered. During the time duration of 0 to 2,000 years, for example, 

the average waste panel pressure varies from 0 Pa to over l 0 MPa. Similar variance is seen in 

the average brine volume in the waste panel, as shown in Figure 5-19. Over the same time 

period of 2,000 years, the average brine volume in the waste panel varies from 0 m3 to over 

10,000 m

3 for intrusion scenario S2-BF. These substantial pressure and brine volume changes 

result in similar changes in the average waste panel brine saturation. As seen in Figure 5-20, the 

average brine saturation in the waste panel varies in the first 2,000 years from a value of 0 to a 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

value of nearly 0.9, representing nearly saturated conditions. Obviously, the influx of additional 

brine in the waste panel following an intrusion has a corresponding impact on the brine 

saturation therein. Moreover, there is a direct correspondence in the shape of the average brine 

volume curves of Figure 5-19 and the brine saturation curves of Figure 5-20. Time values at 

which brine volumes substantially increase correspond to time values at which brine saturations 

also increase. From these results, it is reasonable to conclude that an influx of brine into the 

center area following an intrusion in the waste panel would result in a corresponding change in 

the brine saturation of the central area. 

The brine saturation for the central drift area is denoted by quantity OP8 _ 8ATB in the PC3R PA 

as that region is assigned material properties corresponding to the operations region of the 

PABC-2009 repository configuration. The overall PC3R PA brine saturation curves obtained for 

the central drift area for undisturbed scenario 81-BF and disturbance scenarios 82-BF, 84-BF, 

and S6-BF are shown together in Figure 5-21. As is clear in that figure, there is no discemable 

difference in the average brine saturation obtained in the central drift region for all scenarios 

considered, regardless of pressure and brine volume/saturation changes in the intruded waste 

panel. Brine saturation curves obtained for the central drift area in all intrusion scenarios are 

virtually unchanged from the brine saturation curve obtained for undisturbed conditions. 

Furthermore, as seen in Figure 5-22 there is very close agreement in the overall average brine 

volume in the central drift area, denoted as BRNVOL_O, for the undisturbed and all intrusion 

scenarios considered. All curves obtained for the average brine volume in the central drift area 

for all conditions considered are nearly identical to the curve obtained for undisturbed 

conditions. The reasonable conclusion to make is that changing repository conditions following 

an intrusion on one side of a redesigned panel closure do not result in consequential brine 

saturation and volume changes on the opposite side of the closure. More specifically, an EI or 

E2 drilling intrusion into the waste panel will not result in a consequential increase in brine 

volume inside the central drift region to later be released to the surface by a subsequent intrusion 

in that area. The brine available for release to the surface following a drilling event into the 

central drift region is brine present under undisturbed conditions, regardless of previous 

intrusions into a waste panel. 

While a drilling intrusion into a waste panel has an inconsequential impact on brine volumes and 

saturations in the central drift region, a waste panel intrusion does have an impact on pressure in 

the central region. The overall PC3R PA average pressures obtained for the central drift region, 

denoted as quantity OP8 PRES, for undisturbed scenario 81-BF and disturbance scenarios 82-

BF, 84-BF, and 86-BF are shown together in Figure 5-23. As seen in that figure, there is 

actually a reduction in the average pressure of the central drift region for all intrusion scenarios 

considered as compared to undisturbed scenario 8 1-BF. This is due to eventual reductions in 

waste panel pressures following an intrusion as compared to undisturbed conditions. Given 

sufficient time, the tendency is for pressure on opposite sides of a panel closure to equilibrate. A 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

pressure reduction on one side of a panel closure corresponds to an eventual pressure reduction 

on the opposite side. 

From the discussion above, a drilling intrusion on one side of a panel closure results in a 

reduction in pressure on the opposite side, but no consequential change to brine volume or brine 

saturation. As a result, it can be concluded that drilling intrusions in the central drift region will 

not impact brine volumes and saturations in a waste panel, but will cause reductions in pressure. 

Pressure reductions translate directly to reductions in spallings releases. Likewise, pressure 

reductions without an accompanying increase in brine saturation can only result in a reduction in 

direct brine releases. Therefore, drilling intrusions in the central drift region can only reduce 

releases due to a waste panel intrusion. For the quantification of releases in the PC3R PA, the 

consideration of drilling intrusions into waste-containing regions is sufficient, and is 

conservative. 

WAS_PRES O""rall Means 

10 ........ . 

9 rv- ........ t~~~,,. _____________________ l : I '• 

8 .

·. I ... ,.. ··············· ......... . ................................................ . ......... ___ ... _______________________ _ 

I 

m 7. ; 

e:. I ; : 

Ul 6,- I W 1 : I 

DC I : : -·-·-·-·-·-·-·-·-·-·-·-·-·--·-·-·-·-·-·-·-·-·-·-· 

Ul

a..l 5 t ................ . 

.... J ...=.~·:J 

~ 4 :. ' : ~/ 

• 

3 

2 

-~--

-51-BF 

• S2-BF 

- S4-BF 

- S6-BF 

Q -L~--·--·· 

0 1000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

Time (years) 

Figure 5·18: PC3R PA Overall Waste Panel Pressure Means, Scenarios Sl-BF, S2-BF, S4-BF, S6-BF 

Page 37 of 58 
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11000 

10000 I 

9000 

8000 

"'- 7000 

.s 

$1 6000 

--' 0 5000 > z 

oc 4000 "' 

3000 

2000 

1000 

0 

0 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

BRNVOL_W Owrall Means 

-- 81-BF 

.......... 82-BF 

-·-·-·- 84-BF 

----- 86-BF 

····· ......... <~ ............................................................................ . ............. 

-~---------------------------------

,·-·-·-·-·r·-·-·-·-·~·-·~·-·-·-·-·-·-·-·-·-·-·-·-·~·-·-·-·-·--·~·-·­ ,---

1000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

Time (years) 

Figure 5-19: PC3R PA Overall Waste Panel Brine Volume Means, Scenarios Sl-BF, S2-BF, S4-BF, S6-BF 

0.9 

0.8 

0.7 

"' 0.6 

~ UJI 0.5 

UJ 

:g; 

> 0.4 

0.3 

0.2 

0.1 

WA8_8AlB Owrall Means 

!. 

=~.·-::············································ . .. .............................. . ........................ . 

r .... ..,~.. ----... --------------· 

-------------------

/ 

.-·-·-·-·· , ... --·-·-·-·-·-·-·-·-·-·---·-·-·-·-·-·-·-·-·-·-::.::::·~~~:;·- i : 

I 

I 

.......... 82-BF 

-·-·-·· 84-BF 

----- 86-BF 

0L ____ l_ __ ~ __ _L __ _L __ ~ ____ L_ __ l_ __ ~ __ _L ___ ~ 

0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 

Time (years) 

Figure 5-20: PC3R PA Overall Waste Panel Brine Saturation Means, Scenarios S1-BF, S2-BF, S4-BF, S6-BF 

Page 38 of 58 
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0.9 

0.8 

0.7 

cc 0.6 

~I 0.5 

U) 

0.. 

0 0.4 

0.3 

0.2 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

OPS_SA TB 0\era/1 Means 

--S1-BF 

•·····•··• S2-BF 

-·-·-·· S4-BF 

----- S6-BF 

·-iooo --c2o='o:-::o-3=-=o"=oc:-o--c4-='oo=-=o=--~so::"coc:co--cs:::':ooo 1ooo 8ooo 9ooo 1oooo 

Time (years) 

Figure 5~21: PC3R PA Overall Central Region Brine Saturation Means, Scenarios Sl-BF, 82-BF, 84-BF, S6-BF 

MBRNVOL_ 0 Owra/1 Means 

7000,--,---,--,--,--,---,--,--,---,, --

.... ,al~~uM~~ 

6000 

5000 

-BF 

-BF 

4-BF 

6-BF 

~ 

•. 

E 

- 40001 

~I 0 

> 3000 z 

a: 

cc 

2000 

1000 

0 o':-.....,-1 o='o=-=o-2=-=ooLo.,-...,30-='o=-=o=--40-,Lo_,.o--cs=-=-oLoo=---c-soo::':-:co--=7:-::oo'::-o=---::8o='o:c:o=--9:-::o"=oo:--c:1 oooo 

Time (years) 

Figure 5-22: PC3R PA Overall Central Region Brine Volume Means, Scenarios SI-BF, Sl-BF, 84-BF, S6-BF 

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X 106 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

OPS_PRES Owrall Means 

OL_ __ L_ ~----L_ __ l_ ______ ~---~--~~~L_~-

0 1 000 2000 3000 4000 5000 6000 7000 8000 9000 10000 

lime (years) 

Figure 5-23: PC3R PA Overall Central Region Pressure Means, Scenarios Sl-BF, S2-BF, 84-BF, S6-BF 

5.3 Actinide Mobilization and Transport 

Waste panels 9a and I Oa in the reconfigured repository are slightly larger than their 9 and 10 

counterparts in the historical WIPP configuration, and are of identical volume to panels 1-8. As 

a result, the waste inventory of a standard panel in the PC3R PA is exactly 10% of the overall 

inventory, a slight decrease from the value of 10.53% implemented in the PABC-2009. As the 

repository waste inventory, and corresponding actinide solubilities, used in the PABC-2009 were 

also prescribed in the PC3R PA calculations, the slight decrease in waste panel inventory has 

practically no impact on actinide concentration curves obtained in the two analyses. For all 

practical purposes, the concentration curves obtained in the two analyses are the same. As a 

result, changes in the amount of brine volume flowing up a borehole following an intrusion is the 

primary indicator of changes in transport releases between the PC3R PA and the PABC-2009. 

Consequently, Salado modeling results obtained for quantity BNBHUDRZ in intrusion scenario 

S6-BF are now presented and compared with their PABC-2009 counterparts. 

The scenario S6-BF means of BNBHUDRZ for replicates I - 3 are shown in Figure 5-24 and 

compared to their PABC-2009 counterparts. In that figure, solid curves represent replicate 

means obtained in the PC3R PA. Dashed curves denote replicate means obtained in the PABC2009. As is evident, there is very close agreement between the replicate means obtained in the 

two analyses. The PC3R PA and PABC-2009 overall means of brine volume up the borehole, 

calculated over all 300 vector realizations, are shown together in Figure 5-25 for intrusion 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

scenario S6-BF. Again, there is very close agreement between PC3R PA and PABC-2009 

results. 

As the volumes of brine flow up the intrusion borehole obtained in the PC3R PA and the PABC2009 are very similar for intrusion scenarios S2-BF to S6-BF, it is concluded that transport 

releases obtained in these two analyses are also very similar as the waste inventory and 

corresponding actinide solubilities were unchanged from the PABC-2009 to the PC3R PA. This 

conclusion is further supported by the CCDF curves of normalized releases to the Culebra shown 

in Figure 5-26 and Figure 5-27. As seen in Figure 5-26, the replicate means of normalized 

transport releases to the Culebra obtained in the PC3R PA and the PABC-2009 are nearly 

identical. The same is true of the overall mean CCDF curves for transport releases to the 

Culebra, as evident in Figure 5-27. 

'"'.s. 

[;! 

0 

:::> 

J: 

"' z 

Cll 

10000 

9000 

8000 

7000 

6000 

5000 

4000 

3000 

Scenario S6-BF Replicate Means 

--PC3RPAR1 

• ••••• •• • • PABC2009 R 1 

--PC3RPAR2 

•••••••••• PABC2009 R2 

--PC3RPAR3 

•••••••••• PABC2009 R3 

l 

-

'--'-------L__L___~______,_ _ _j 

2000c 

1000 

0 

0 1000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

lime (years) 

Figure 5-24: PC3R PA and PABC-2009 Replicate Means of Cumulative Flow up the Borehole 

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"' A 

!! 

• 

.. 

"' ! 

;;; 

.ll 

a 

.!: 

10000 

9000 

8000 

7000 

'l 6000 

iJ::! 

0 5000. 

::> 

I 

m 

z 4000 

m 

3000 

2000 

1000 

0 

0 

Summary Report for the AP-151 (PCJR) Performance Assessment 

Revision I 

Scenario S6-BF Owrall Means 

---PC3R 

-•••• PABC2009 

1 000 2000 3000 4000 5000 6000 7000 8000 9000 1 0000 

Time (years) 

Figure 5-25: PCJR PA and PABC-2009 Overall Means of Cumulative Flow up the Borehole 

1 ....... . . . .................... :: 

0.1 

0.01 

o.nm 

0.0001 

0.0001 0.001 

-

0.01 

- - --~-- --~--

0.1 

R = Total To Culebra Release (EPA Units) 

--Rf'piCi!l>"l Mf~-w Pf" __ :I,RPA 

••••••• Rep ic11te 1 Me.1r PABC-2009 

--Kcp ICJtC!L Me..1r 1-'{...:H~ I' A 

••••••• Rep lcate 2 Me<~r PABC-2009 

-Rep ic<tl.:o 31\1&lr PC3R PA 

·•••••• Rep icat~ J Moor PABC-2009 

-t------' 

10 100 

Figure 5-26: PC3R PA and PABC-2009 Replicate Mean CCDFs for Normalized Transport Releases to the 

Culebra · 

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1 

0.1 

0.01 

0 0()1 

············ ················ 

0.0001 

0.0001 0001 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

... 

' ' ' ' ' I ' " ' I 

0.01 0 I 1 

R = Transport Release to culebra ! EPA Units) 

OVN<lll Me~n PC-\~ 

·•·•··• overall Mc<ln PA~ 

10 100 

Figure 5-27: PC3R PA and PABC-2009 Overall Mean CCDFs for Transport Releases to the Culebra 

5.4 Cuttings and Cavings 

Cuttings and cavings are the solid waste material removed from the repository and carried to the 

surface by the drilling fluid during the process of drilling a borehole. Cuttings are the materials 

removed directly by the drill bit, and cavings are the material eroded from the walls of the 

borehole by shear stresses from the circulating drill fluid. The volume of cuttings and cavings 

material removed from a single drilling intrusion into the repository is assumed to be in the shape 

of a cylinder. 

The PA code CUTTINGS S calculates the cuttings and cavings areas removed for a set of 

vectors, scenarios, times, and locations. Results obtained by BRAGFLO in scenarios S 1-BF to 

S5-BF are used to initialize the flow field properties necessary for the calculation of DBRs. This 

requires that results obtained on the BRAGFLO grid be mapped appropriately to the DBR grid. 

Code CUTTINGS_ S is used to transfer the appropriate scenario results obtained with 

BRAGFLO to the DBR grid. These transferred flow results are used as initial conditions in the 

calculation of DBRs. As a result, intrusion scenarios used in the calculation of cuttings and 

cavings correspond to those used in the calculation of DBRs. Five intrusion scenarios are 

considered in the DBR calculations, and are listed in Table 7. 

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Scenario 

S1-DBR 

S2·DBR 

S3-DBR 

S4-DBR 

S5-DBR 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision l 

Table 7: PA Intrusion Scenarios Used in Calculating Direct Solids Releases 

Conditioning (or I") Intrusion 

Time (year) and Type Intrusion Times- Subsequent (year) 

None 100,350,1000,3000,5000,10000 

350, E1 550,750,2000,4000,10000 

1000, E1 1200,1400,3000,5000,10000 

350,E2 550,750,2000,4000,10000 

1000,E2 1200,1400,3000,5000,10000 

While CUTTINGS_ S uses these standard DBR scenarios as a basis for its calculations, it does so 

to provide flow field results (generated with BRAGFLO) as initial conditions to the DBR 

calculation at each subsequent intrusion time. CUTTINGS_ S does not model the intrusion 

scenario itself. Scenario Sl-DBR corresponds to an initial intrusion into the repository, with 

repository flow conditions at the time of intrusion transferred from BRAG FLO scenario S 1-BF 

results. Scenarios S2-DBR through S5-DBR are used to model an intrusion into a repository that 

has already been penetrated. The times at which intrusions are assumed to occur for each 

scenario are outlined in the last column of Table 7; six intrusion times are modeled for scenario 

Sl-DBR, while five times are modeled for each of scenarios S2-DBR through S5-DBR. 

Cuttings and cavings results obtained for the PC3R PA are the same as for the PABC-2009, as is 

evident in the results of Table 8 and the CCDF curves of normalized cuttings and cavings 

releases shown in Figure 5-28. 

Table 8: Cavings Area Statistics for the PABC-2009 and PC3R PA 

Replicate Cavin2s Area (m') Vectors with no 

Maximum Mean Cavines 

R1 0.748 0.177 9 

R2 0.785 0.175 10 

R3 0.753 0.178 11 

Two uncertain sampled parameters affect the cavings calculations. The uncertainty in cavings 

areas arises primarily from the uncertainty in the shear strength of the waste (Kicker 2011). 

Lower shear strengths tend to result in larger cavings as is evident in Figure 5-29. The 

uncertainty in the drill string angular velocity has a smaller impact on the cavings results, but the 

combination of a low angular velocity and high shear strength can prohibit cavings from 

occurring. In fact, cavings did not occur in ten percent of all vectors (Table 8). 

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1 

0.1 ~-' 

0.01 

0.001 

0.0001 

0.0001 0.001 

Summary Report for the AP-151 (PCJR) Performance Assessment 

Revision 1 

0.01 0.1 1 

R"' Cuttlnss and Cavings Release {EPA Units) 

--PC3RPA Overall MC>an 

----PA8C·20090verall Mean 

- -Release Limits 

I 

I 

I 

I 

I 

I 

I 

I 

L----

Figure 5-28: PC3R PA and PABC-2009 Overall Mean CCDFs for Normalized Cuttings and Cavings Releases 

1 

;< 

.s 

~ 

~ ~ 

.. • 

c 

-~ 

.., 

c 

~ 

~ c 

~ u 

0.1 

0.01 0.1 1 

Waste shear strength (Pa) 

o Replicate 1 

c Replicate 2 

A Replicate 3 

10 100 

Figure 5-29: Cuttings and Cavings Area as a Function of Waste Shear Strength 

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5.5 Spallings 

Summary Report for the AP-151 (PCJR) Performance Assessment 

Revision 1 

Calculation of the volume of solid waste material released to the surface from a single drilling 

intrusion into the repository due to spallings is a two-part procedure. The code DRSPALL 

calculates the spallings volumes from a single drilling intrusion at four values of repository 

pressure (1 0, 12, 14, and 14.8 MPa). The second step in calculating spallings volumes from a 

single intrusion consists of using the code CUTTINGS S to interpolate the DRSPALL volumes. 

The spallings volume for a vector is then determined in CUTTINGS_ S by linearly interpolating 

the volume calculated by DRSPALL based on the pressure calculated by BRAGFLO. 

Table 9: Summary of Spallings Releases by Scenario 

Scenarios Total 

S1-DBR I S2-DBR SJ-DBR S4-DBR I SS-DBR 

PCJRPA ·. ..... · . ·'• ··.··· 

Maximum (m3) 1.67 13.56 12.70 1.67 1.67 13.56 

Average nonzero volume (m3 ( 0.31 0.74 0.78 0.27 0.30 0.53 

Rl 

Number of nonzero volumes 84 102 86 40 53 365 

Percent of nonzero volumes 7.0% 10.2% 8.6% 4.00/o 5.3% 7.0% 

Maximum [m3

] 1.43 8.48 6.64 0.60 0.60 8.48 

Average nonzero volume [m3

[ 0.22 0.40 0.34 0.23 0.22 0.30 

R2 

Number of nonzero volumes 89 114 96 36 53 388 

Percent of nonzero volumes 7.4% 11.4% 9.6% 3.6% 5.3% 7.5% 

Maximum [m3

) 5.00 6.80 4.52 3.93 4.52 6.80 

Average nonzero volume [m3

) 0.42 0.59 0.39 0.37 0.32 0.44 

R3 

Number of nonzero volumes 79 98 83 33 51 344 

Percent of nonzero volumes 6.6% 9.8% 8.3% 3.3% 5.1% 6.6% 

PABC-2009 . 

·. ... Maximum [m3

] 2.24 8.29 7.97 1.67 1.67 8.29 

Average nonzero volume (m3

) 0.37 0.54 0.50 0.30 0.37 0.43 

R1 

Number of nonzero volumes 142 117 Ill 59 77 506 

Percent of nonzero volumes 7.9% 7.8% 7.4% 3.9% 5.1% 6.5% 

Maximum [ m3

] 2.36 2.76 1.86 2.26 1.93 2.76 

Average nonzero volume (m'l 0.32 0.39 0.37 0.50 0.47 0.39 

R2 

Number of nonzero volumes 168 122 122 57 84 553 

Percent of nonzero volumes 9.3% 8.1% 8.1% 3.8% 5.6% 7.1% 

Maximum [m3

] 4.91 6.23 2.62 1.47 1.49 6.23 

Average nonzero volume (m3( 0.53 0.39 0.28 0.30 0.28 0.38 

R3 

Number of nonzero volumes 156 113 118 45 72 504 

Percent of nonzero volumes 8.7% 7.5% 7.9% 3.0% 4.8% 6.5% 

DRSPALL volumes used in the PABC-2009 were also used in the PC3R PA. Utilizing these 

volumes and the PC3R PA repository pressures calculated by BRAGFLO, the impact of the 

repository reconfiguration and panel closure design on spallings volumes can be determined. 

Average and maximum statistics of spallings volumes for the intrusion scenarios considered by 

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Summary Report for the AP-151 (PCJR) Performance Assessment 

Revision 1 

CUTTINGS_S are shown in Table 9 for both the PC3R PA and the PABC-2009. While the 

results for the PABC-2009 and the PC3R PA calculations are similar for some scenarios, some 

significant differences in the spallings volumes are noted. For scenarios S2-DBR and S3-DBR, 

in which the borehole intrusion encounters a pressurized brine pocket, a sharp increase in 

spallings volume occurs across all three replicates. The results for scenarios Sl-DBR, S4-DBR, 

and S5-DBR are mixed compared to the PABC-2009, showing both increases and decreases in 

spallings volume. Overall, the general trend shows a slightly higher average nonzero spallings 

volume, a larger maximum volume, and a larger percentage of vectors with spallings considering 

the total from all scenarios across all three replicates. 

0.1 •••• 

0.:)1 

o.oo:n 

0.0001 0.001 (Ull 0.1 

R" Spa!linss Rektase I EPA Units) 

I 

I 

I 

I 

PC3~ PA Overall Mean 

•••·••• PABC·20J90oe·all Mean 

--EPA Release Limit~ 

~----, 

I 

I 

I 

I 

I 

I 

I 

I 

I 

L..----

10 

Figure 5-30: PC3R PA and PABC-2009 Overall Mean CCDFs for Normalized Spallings Releases 

Spallings volumes are a function of repository pressure. The change in spallings volumes 

between the PC3R PA and the PABC-2009 is the result of changing repository pressures 

observed in BRAGFLO calculations for the PC3R PA. For intrusion scenarios that involve an 

encounter with a pressurized brine region below the repository, the slight reduction in the longterm PC3R P A panel closure permeabilities resulted in a slight increase in pressurization of the 

waste panel for a period of time following the intrusion. Since there is a minimum threshold 

pressure required to create spallings, an increase in repository pressure also increases the 

percentage of vectors with spallings. Repository pressures are also impacted by the slight 

increase in repository volume resulting from the slightly larger volumes of panels 9a lOa. 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

The impacts of the changes in spallings volumes on the overall mean CCDF for normalized 

spallings releases obtained in the PC3R PA can be seen in Figure 5-30. As seen in that figure, 

the CCDFs of spallings releases obtained in the PABC-2009 and the PC3R PA are similar. 

However, the PC3R PA CCDF curve shown in Figure 5-30 exhibits both increases and decreases 

in spallings releases when compared to PABC-2009 results. These changes are due to the 

spallings volume changes seen in the PC3R PA. 

5.6 Direct Brine Releases 

In this subsection, DBR results from the PC3R PA and the PABC-2009 are compared. Summary 

statistics ofthe calculated DBR volumes for replicates 1-3 and scenarios S 1-DBR to S5-DBR are 

provided in Table 10. In that table, maximums shown are the maximum DBR volumes over all 

replicates, times, vectors and drilling locations. As seen by the statistics for the maximum DBR 

volumes in Table 10, the panel closure redesign and repository configuration implemented in the 

PC3R PA resulted in an increase in the maximum DBR volume as compared to the PABC-2009. 

The maximum DBR volume realized in the PABC-2009 was 48.2 m3 while that seen in the 

PC3R PAis 52.0 m3

• However, the average DBR volume remained equal or decreased in the 

PC3R PA for all scenarios considered except for scenario S5-DBR. When calculated over all 

intrusion scenarios, the average volume reduced from a value of 1.34 m

3 in the PABC-2009 to a 

value of 1.14 m3 in the PC3R P A. This reduction in the average DBR volume seen in the PC3R 

PAis a result of the lower number of vectors producing nonzero DBR volumes in that analysis. 

In the PABC-2009, a total of2,474 vectors resulted in a nonzero DBR volume realization. The 

number of vectors resulting in nonzero DBR volumes in the PC3R PAis 2,273, a reduction by 

201 vectors when compared to the PABC-2009 results. 

Table 10: PABC-2009 and PC3R PA DBR Volume Statistics 

Maximum Volume (m') Avera2e Volume (m') Number of Vectors 

Scenario PABC-2009 PC3RPA PABC-2009 PC3RPA PABC-2009 PC3RPA 

Sl-DBR 21.9 29.7 0.1 0.1 258 257 

S2-DBR 48.2 52.0 4.2 3.7 1071 962 

S3-DBR 40.6 49.7 2.2 1.6 791 682 

S4-DBR 20.4 28.1 0.1 0.1 145 148 

S5-DBR 21.1 24.0 0.1 0.2 209 224 

SI-DBR to 

S5-DBR 48.2 52.0 1.34 1.14 2474 2273 

DBR releases are less likely to occur during upper drilling intrusions when compared with the 

lower drilling location. Of all the intrusions that had a non-zero DBR volume for the PC3R PA, 

74.8% occurred during a lower drilling intrusion. Furthermore, of all the intrusions that had a 

non-zero DBR volume and occur during a lower drilling intrusion, 82.8% are found in scenarios 

S2-DBR and S3-DBR. Therefore, the majority of the non-zero DBR volumes occur when there 

is a previous E 1 intrusion within the same panel. Not only are DBRs less likely to occur during 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

upper drilling intrusions, but also the DBR volumes from such intrusions tend to be much 

smaller than DBR volumes from lower drilling intrusions. For all three replicates of the PC3R 

PA, the maximum DBR volume for the upper drilling location is 22.0 m3 compared to 52.0 m

3 

for the lower drilling location (Pasch and Camp house 2011 ). These observations support the 

conclusion that lower drilling intrusions are the primary source for significant DBRs. 

60 

0 0-0.2 

c 0.2-0.4 

50 r;. 0.4-0.6 

'0.6-0.8 

- 0.8-1.0 

t:\' 40 

!, 

~ 

8 

= 30 

~ ~ 

= <=l 20 

10 

2 4 6 8 

q< 0 X 

X 

10 

Pressure, (MPa) 

0 

X 

12 

X X 

0 

' 

14 16 18 

Figure 5-31: DBR Volume vs. Pressure, Scenario 82-DBR, Replicate 1, Lower Intrusion, PCJR PA 

The combination of relatively high pressure and brine saturation in the intruded panel is required 

for direct brine release to the surface. Figure 5-31 shows a scatter plot of DBR volume versus 

pressure in the intruded panel at different intrusion times for the S2-DBR scenario, replicate 1, 

lower drilling intrusion for the PC3R PA. In that figure, symbols indicate the value of the 

mobile brine saturation, defined as brine saturation minus residual brine saturation in the waste. 

As prescribed by the conceptual model, there are no DBRs until pressures exceed 8 MPa as 

indicated by the vertical line in that figure. Above 8 MPa, a significant number of vectors have 

zero volumes; these vectors have mobile brine saturations less than zero and thus no brine is 

available in a mobile form to be released. Figure 5-31 shows a high concentration of results that 

are near a line extending from (8 MPa, 0 m3

) to (12 MPa, 30 m\ As mobile saturation 

increases, the correlation between pressure and DBR volumes also increases. 

To further facilitate comparisons of DBRs calculated in the PC3R PA to those obtained in the 

PABC-2009, the overall mean CCDFs obtained in these two analyses are plotted simultaneously 

in Figure 5-32. As seen in that figure, the CCDF curves obtained for direct brine releases in the 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

PABC-2009 and the PC3R PA are very similar. For releases up to roughly 0.1 EPA units, the 

CCDF curves obtained in both analyses are virtually identical. For releases between 0.1 and 1 

EPA unit, the CCDF curve obtained in the PC3R PA is slightly above that calculated in the 

PABC-2009. For releases greater than I EPA unit, the CCDF curve obtained in the PABC-2009 

is higher than that obtained in the PC3R PA. The decrease in the number of realizations with a 

nonzero DBR volume in the PC3R PA combined with the slight increase in the maximum DBR 

volume is most likely the cause for the differences observed in the DBR CCDF curves obtained 

in the PABC-2009 and the PC3R PA. 

---------------------------------------r--------------------1 

0.1 

0.01 

0.001 

:J.OOOl 

0.0(·01 COOl 0.01 

'• ' ' 

0.1 

' ' ' ' ' ' ' ' ' ' ' ' ' 

R"' Direct Brine Release I EPA Units) 

I --PC3R PA 0\oerall Mean 

I ---·PABC<W090veralll\lec;n 

I - -EPA Rclca~c limits 

I 

~----. 

·-. 

\ 

' ' I 

• \ 

\ 

' • • \ 

I 

I 

I 

I 

I 

I 

I 

I 

I '-----

10 

Figure 5-32: PC3R PA and PABC-2009 Overall Mean CCDFs for Normalized Direct Brine Releases 

5. 7 Total Normalized Releases 

Total normalized releases for PC3 R P A are presented in this section and subsequently compared 

to results obtained in the PABC-2009. Total releases are calculated by forming the summation 

of releases across each potential release pathway, namely cuttings and cavings releases, spallings 

releases, direct brine releases, and transport releases. As prescribed in AP-151 (Camphouse 

2010a), transport results obtained in the PABC-2009 were used in the PC3R PA. PC3R PA 

CCDFs for total releases are presented in Figure 5-33, Figure 5-34, and Figure 5-35 for replicates 

I, 2, and 3, respectively. Mean and quantile CCDF distributions for the three replicates are 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

shown together in Figure 5-36. Figure 5-37 contains the 95 percent confidence limits about the 

overall mean of total releases. As seen in Figure 5-37, the overall mean for normalized total 

releases and its lower/upper 95% confidence limits are well below acceptable release limits. As 

a result, the panel closure design and repository configuration changes investigated in the PC3R 

PA do no result in WIPP non-compliance with the containment requirements of 40 CFR Part 

191. 

PC3R PA and PABC-2009 overall mean CCDFs for total releases are shown together in Figure 

5-38. As seen in that figure, the overall mean CCDFs obtained in the two analyses are virtually 

identical for release values less than approximately 0.1 EPA units. For releases between 0.1 and 

1.0 EPA units, the overall total release mean CCDF curve obtained in the PC3R PA is slightly 

above that calculated in the PABC-2009. For releases greater than I EPA unit, the CCDF curve 

obtained in the PABC-2009 is higher than that found in the PC3R PA. These trends correspond 

exactly to the differences found for direct brine releases between the two analyses as discussed in 

Section 5.6 and illustrated in Figure 5-32. Indeed, as seen in Figure 5-39, cuttings and cavings 

releases and direct brine releases are the two primary release components contributing to total 

releases found in the PC3R PA. PC3R PA cuttings and cavings results are unchanged from those 

found in the PABC-2009. The panel closure design and repository configuration changes 

investigated in the PC3R PA have a slight impact on direct brine releases. The changes in the 

overall mean of total releases from the PABC-2009 to the PC3R PA are due to the changes in 

direct brine releases calculated in those analyses. 

A comparison of the statistics on the overall mean for total normalized releases obtained in the 

PC3R PA and the PABC-2009 can be seen in Table 11. At a probability of 0.1, values obtained 

for mean total releases are identical in both analyses. At a probability of 0.001, the decrease in 

DBRs seen at that probability in the PC3R PA result in a decrease in the mean total release by 

approximately 0.21 EPA units. Reductions are also seen in the 901

h percentile and the 95% 

confidence limits when compared to the PABC-2009 results. 

Table 11: PC3R PA and PABC-2009 Statistics on the Overall Mean for Total Normalized Releases in EPA Units at 

Probabilities of 0.1 and 0.001 

Probability Analysis Mean Total 90"' Lower Upper Release 

Release Petcentile 95%CL 95%CL Limit 

0.1 PC3RPA 0.09 0.16 0.09 0.10 I 

PABC-2009 0.09 0.16 0.09 0.10 l 

0.001 PC3RPA 0.89 1.00 0.34 1.41 10 

PABC-2009 . LIO 1.00 0.37 1.77 10 

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0.1 

0.01 

0.001 

0.0001 

U.UUUl 

0.1 

0.01 

U.UUl 

0.0001 

0.0001 

lJ.UOl 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

1--Tot<JI Relt!<~~t!~ I 

U.Ul 0.1 10 

R"' Total Rel~il:'if! (EPA Units) 

Figure 5-33: PC3R PA Replicate I Total Normalized Releases 

Total Releases I 

0.001 0.01 0.1 10 

R =Total Rele;n;e (EPA Unit!>) 

Figure 5-34: PC3R PA Replicate 2 Total Normalized Releases 

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1 

0.1 

0.01 

0.001 

0.0001 

0.0001 

, 1 

0.01 I 

r 

0.001 

00001 

0.0001 

0.001 

Summary Report for the AP-151 (PC3R) Performance Assessment 

· Revision l 

I --Total neleases j 

0.01 0.1 1 10 

R= Tot01l Release (EPA Units) 

Figure 5-35: PC3R PA Replicate 3 Total Normalized Releases 

- -Rele;;se Lirn1ts 

.__ __ _ 

0.001 0.01 D.l 10 

R= Tot.al Release CEPA Unitsl 

Figure 5-36: PC3R PA Mean and Quantile CCDFs for Total Normalized Releases, Replicates 1-3 

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1 

0,1 

0.01 

0.001 

0.0001 

O.UUUl U.UlH 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision l 

U.Ol U,l 

' ' ' \ ',, 

\ --~,~-----

\ '\ 

' 

I -overall Mean 

I - -Lower 95% CL 

I ----Upper '3S'X:.Cl 

I 

L---~--~-, 

I 

I 

I , __ ,,_______ I ' -------- 1 

\ \ 

I 

I 

I \ \ 

' ' - \-- --L--

1 

' ' ' ' ' I 

• • 

"-~ 

' • lU 

R • Total Release tEPA Units) 

Figure 5-37: PC3R PA Confidence Limits on Overall Mean for Total Normalized Releases 

).1 

IJ.Ol 

0.001 

0.0001 

0.0001 0.001 0.01 

--PORPAOverdl Mean 

---· f'ABC-2009 O·Jorall Me-an 

- -Fiek•ascUnit-s ------" 

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I 

I 

I 

I 

I 

I 

I 

I 

____ I ..., ___ _ 

0,) ) 

R"' Total Release IE~A Units) 

\ 

• • ' ' \ 

• ' \ 

' • 

Figure 5-38: PC3R PA and PABC-2009 Overall Mean CCDFs for Total Normalized Releases 

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Q.l 

I 0.01 -·-

0.001 

J.OOOl 

0.0001 0.0':\1 

Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

0.01 0.1 

R• Release(EPAUnits) 

--PCJRPA Total5 O•Jer;;~l Me;~n 

•·····• PC3RPA C\ltlings and C.uirg~ O:Je';;~ll Mciln 

- --· PC3RPA DBR Over;;~ I Mc~n 

- - RCI('iiS(' lilnits 

'-----, 

I 

I 

I 

I 

~----

10 

Figure 5-39: PC3R PA Primary Components Contributing to Total Releases 

6 SUMMARY 

Total normalized releases calculated in the PC3R PA remain below their regulatory limits. As a 

result, the panel closure design and repository configuration changes investigated in the PC3R 

PA would not result in WIPP non-compliance with the containment requirements of 40 CFR Part 

191. Cuttings and cavings releases and direct brine releases are the two primary release 

components contributing to total releases in the PC3R P A. Cuttings and cavings releases are 

unchanged from those calculated in the PABC-2009. Changes in total releases are attributed to 

changes calculated in direct brine releases from the PABC-2009 to the PC3R P A. Differences 

are observed in PC3R PA spallings releases as compared to the PABC-2009, but these 

differences are relatively minor and do not have a significant impact on the overall total 

normalized releases found in the PC3R PA. 

Several conclusions can be made regarding the impact of the panel closure redesign, the open 

central drift region, and the placement of panel closures in the reconfigured repository. Most 

significant among these are the following: 

• The combination of initially high panel closure permeability and comparatively low 

pressure in the central drift region allows for pressure release from the waste regions into 

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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision 1 

the central drift area until the panel closures attain their steady-state permeability values 

at 1 00 years. 

• The reconfigured repository and the redesigned panel closures implemented therein do 

not result in an increase in brine flow out of the waste regions when compared to the 

PABC-2009. 

• The redesigned panel closures in combination with their placement in the repository 

reconfiguration effectively limit the impacts of drilling intrusion to the region being 

intruded. In particular, the brine available for release to the surface during a drilling 

event into the central drift region is equal to that present under undisturbed conditions, 

even ifthere have been prior intrusions into a waste panel. 

7 REFERENCES 

Callahan, G.D. and K.L. DeVries. 1991. Analysis of Backfilled Transuranic Waste Disposal 

Rooms. SAND91-7052. Sandia National Laboratories, Carlsbad, NM. 

Camphouse, R.C. 2010a. Analysis Plan for the WIPP Panel Closure Redesign and Repository 

Reconfiguration. Sandia National Laboratories, Carlsbad, NM. ERMS 554595. 

Camphouse, R.C. 2010b. Recommendation and Justification of Parameter Values Required for 

the WIPP Panel Closure Redesign and Repository Reconfiguration Performance Assessment, 

Memo to Records dated December 13, 2010. Sandia National Laboratories, Carlsbad, NM. 

ERMS 554614. 

Camphouse, R.C. 2010c. Value Recommendation and Justification for Properties CAP _MOD, 

PCT_A and PCT_EXP for Materials PCS_Tl and PCS_T2 used in the WIPP Panel Closure 

Redesign and Repository Reconfiguration Performance Assessment, Memo to Records dated 

December 20,2010. Sandia National Laboratories, Carlsbad, NM. ERMS 554623. 

Camphouse, R.C. 2011a. Value Recommendation and Justification for Parameters 

DRZ_1:EHEIGHT and OPS_AREA:EHEIGHT needed during calculation of direct brine 

releases in the PC3R PA. Memo to Records Center, January 5, 2011. Sandia National 

Laboratories, Carlsbad, NM. ERMS 554694. 

Camphouse, R.C. 20llb. Generation of the LHS Samples for the AP-151 (PC3R) PA 

Calculations. Sandia National Laboratories, Carlsbad, NM. ERMS 555232. 

Camphouse, R.C. 20llc. CCDFGF Analysis Package for the AP-151 (PC3R) Performance 

Assessment. Sandia National Laboratories, Carlsbad, NM. ERMS 555244. 

Page 56 of 58 
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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

Camphouse, R.C. and Clayton, D.J. 2011. Analysis Package for Salado Flow Modeling Done in 

the AP-151 (PC3R) Performance Assessment. Sandia National Laboratories, Carlsbad, NM. 

ERMS 555204. 

Camphouse, R.C. and Gamer J.W. 2011. Impacts of PC3R PA Repository Configuration 

Changes on Calculated Transport Releases, Memo to Records dated March 29, 2011. Sandia 

National Laboratories, Carlsbad, NM. ERMS 555241. 

Clayton, D.J. 2010. Analysis Package for Direct Brine Releases: CRA-2009 Performance 

Assessment Baseline Calculation, Revision 0. Sandia National Laboratories. Carlsbad, NM. 

ERMS 552829. 

Clayton, D.J., R.C. Camphouse, J.W. Gamer, A.E. Ismail, T.B. Kirchner, K.L. Kuhlman, M.B. 

Nemer. 2010. Summary Report of the CRA-2009 Performance Assessment Baseline Calculation. 

Sandia National Laboratories, Carlsbad, NM. ERMS 553039. 

Hansen, C. W. 2002. Analysis Report for the Panel Closure Impact Assessment. Sandia National 

Laboratories, Carlsbad, NM. ERMS 523935. 

Hansen, C.W. 2011. Sensitivity of the AP-151 (PC3R) PA Calculation Releases to Parameters. 

Sandia National Laboratories, Carlsbad, NM. ERMS 555288. 

Hansen, F.D. and Thompson, T.W. 2002. Effective Permeability of the Redesigned Panel 

Closure System, Memo to Paul E. Shoemaker dated August 29, 2002. Sandia National 

Laboratories, Carlsbad, NM. ERMS 523476. 

Kicker, D.C. 2011. Analysis Package for Cuttings, Cavings, and Spallings: Panel Closure 

Redesign and Repository Reconfiguration Performance Assessment (PC3R PA). Sandia National 

Laboratories, Carlsbad, NM. ERMS 555209. 

Kirkes, G.R. 2011. Features, Events and Processes Assessment for Changes Described in 

Analysis Plan- 151, Revision 0. Sandia National Laboratories, Carlsbad, NM. ERMS 555237. 

Long, J.J. 2011. Execution of Performance Assessment Codes for the WIPP Panel Closure 

Redesign and Repository Reconfiguration. Sandia National Laboratories, Carlsbad, NM. ERMS 

555266. 

Pasch, J.J. and Camp house, R.C. 20 ll. Analysis Package for Direct Brine Releases: Panel 

Closure Redesign and Repository Reconfiguration Performance Assessment (PC3R PA). Sandia 

National Laboratories, Carlsbad, NM. ERMS 555249. 

Page 57 of 58 
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Summary Report for the AP-151 (PC3R) Performance Assessment 

Revision I 

Stein, J.S. 2002a. Analysis Plan for Calculations of Salado Flow: Technical Baseline Migration 

(IBM) AP-086. Sandia National Laboratories, Carlsbad, NM. ERMS 520612. 

U.S. Environmental Protection Agency (EPA). 1996. 40 CFR Part 194: Criteria for the 

Certification and Recertification of the Waste Isolation Pilot Plant's Compliance with the 40 

CFR Part 191 Disposal Regulations; Final Rule. Federal Register, Vol. 61, 5223-5245. 

U.S. Environmental Protection Agency (EPA). 1998. 40 CFR 194, Criteria for the Certification 

and Recertification of the Waste Isolation Pilot Plant's Compliance with the Disposal 

Regulations: Certification Decision: Final Rule, Federal Register. Vol. 63, 27354-27406. ERMS 

251924. 

U.S. Environmental Protection Agency (EPA). 2010. 40 CFR Part 194 Criteria for the 

Certification and Recertification of the Waste Isolation Pilot Plant's Compliance With the 

Disposal Regulations: Recertification Decision, Federal Register No. 222, Vol. 75, pp. 70584-

70595, November 18,2010. 

Vugrin, E.D., S.C. Dunagan. 2006. Analysis Package for the Impact Assessment of the 

Redesigned WIPP Panel Closure. Sandia National Laboratories, Carlsbad, NM. ERMS 543865. 

Vugrin, E., Hansen, F., and Thompson, B. Recommendation and Justification of Parameter 

Values Required for Representation of the Redesigned Panel Closure System, Memo to David 

Kessel dated March 23, 2006. Sandia National Laboratories, Carlsbad, NM. ERMS 542894. 

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Camphouse, Russell Chris 

From: 

Sent: 

To: 

Subject: 

Clayton, Daniel James 

Tuesday, April 05,2011 1:37PM 

Camphouse, Russell Chris 

RE: sig authority 

I give R. Chris Camphouse signature authority for the PC3R PA summary report 

From: (amphouse, Russell Chris 

Sent: Tuesday, April 05, 2011 1:36PM 

To: Clayton, Daniel James 

Subject: sig authority 

Hi Dan, 

Can you send someone signature authority for the title page of the summary report? 

Thanks, 

Chris 

-------------rccamph@sandia.gov-------------------

R. Chris Camphouse 

Sandia National Laboratories 

Carlsbad Programs Group 

Performance Assessment and Decision Analysis Department 

41 00 National Parks Highway MS 1395 

Carlsbad, NM 88220 

Phone: (575) 234-0130 

Fax: (575) 234-0061 

1