ML20211J993
| ML20211J993 | |
| Person / Time | |
|---|---|
| Issue date: | 08/31/1999 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-1437, NUREG-1437-AD01, NUREG-1437-V01-AD01, NUDOCS 9909070083 | |
| Download: ML20211J993 (91) | |
Text
NUREG-1437, Vol.1 Addendum I Generic Environmental n
Impact Statement for License Renewal of Nuclear Plants Main Report Section 6.3 Transportation Table 9.1 Summary of findings on NEPA issues for license renewal of nuclear power plants e
2 Final Report o
7, rl,
- u i U.S. Nuclear Regulatory Commission
/'
-\\
Office of Nuclear Reactor Regulation i
~
Washington, DC 20555-0001
'%.... /
>oast t-g s,
1 NUREG-1437, Vol.1 Addendum 1 Generic Environmental Impact Statement for License Renewal of Nuclear Plants Main Report Section 6.3 Transportation l
Table 9.1 Summary of findings on NEPA issues for license renewal of nuclear power plants
_=
_.m Final Report i
'(
pfat U.S. Nuclear Regulatory Commission
/
3 Office of Nuclear Reactor Regulation 5
Washington, DC 20555-0001
(
joy 990831
~
/R PDR
\\
NUREG-1437, Vol.1 Addendum 1 Generic Environmental Impact Statement License Renewal of Nuclear Plants Main Report Section 6.3 Transportation Table 9.1 Summary of findings on 'NEPA issues for license renewal of nuclear power plants Final Report Manuscript Completed: August 1999 Date Published: August 1999 Division of Regulatory Improvement Programs
(
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 NRC Job Code
T Supple:'
lysesfor Cumulative EnvironmentalImpacts.
-~
ABSTRACT This addendum to NUREG-1437, Generic EnvironmentalImpact Statement for Ucense Renewalof Nuclear Plants, documents the staff's analysis of the potential cumulative impacts of transporting spent nuclear fuel in the vicinity of a single high-level waste repository, and summarizes the staff's analyses undertaken to determine whether the environmentalimpacts of the transportation of higher enrichment and higher burnup spent nuclear fuel are consistent with the values of 10 CFR 51.52, Table S-4. The intent of the study is a generic analysis of the cumulative impacts associated with transportation of spent nuclear fuel as a result of nuclear power plant license renewal. The results of the analysis will be used to amend 10 CFR Part 51.53 and Appendix B to Subpart A of 10 CFR Part 51, and is not intended to support any other regulatory decision by the NRC. This addendum also includes an appendix that summarizes comments on the draft of the addendum, and documents the staff's responses to those comments.
l l
iii NUREG.1437, Addendum 1
supplemental Analysesfor cumulative EnvironmentalImpacts...
(
CONTENTS ABSTRAC T...........................................................
iii LI ST OF FI GU R E S..................................................... vii LI ST OF TABLES...................................................... vii ACRONYMS AND ABBREVIATION........................................
ix
- 1. I NTRODUCTION..................................................... 1 1.1 PURPOSE OF THE ADDENDUM..................................... 1 1.2 SCOPE OF THE ADDENDUM....................................... 1 1.3 BAC KG R OUN D.................................................. 2
- 2. CUMULATIVE IMPACTS OF SPENT NUCLEAR FUEL TRAN SPO RTATION.................................................. 4
2.1 BACKGROUND
ON THE PROPOSED HLW REPOSITORY................ 5 2.2 APPROACH TO ANALYSIS......................................... 5 2.2.1 Transportation and Route Scenarios.............................. 7 2.2.2 Analysis of Routes Using the HIGHWAY Model.................... 11 2.2.3 The RADTRAN Model........................................ 11 2.3 CUMULATIVE HEALTH RISKS OF SPENT FUEL TRANSPORTATION IN CLARK COUNTY, NEVADA...................................... 15 2.3.1 Radiological Risks........................................... 15 2.3.2 Nonradiological Risks........................................ 19 2.4 CUMULATIVE IMPACTS OF ADDITIONAL RADIOACTIVE WASTE SHIPMENTS 21 2.5
SUMMARY
OF SNF TRANSPORT IMPACTS.......................... 22 2.6 ENVIRONMENTAL JUSTICE '....................................... 24
- 3. IMPLICATIONS OF HIGHER BURNUP FUEL FOR THE CONCLUSIONS IN TABLE S-4......................................... 26 3.1 BAC KG ROU ND................................................. 26
- 3.2 ANALY SES..................................................... 27 3.3 CONC LU SIONS................................................. 29
- 4.
SUMMARY
AND CONCLUSIONS....................................... 30
- 6. LI ST OF PREPAR ER S.............................................. 34 APPENDIX 1: STAFF RESPONSES TO PUBLIC COMMENTS ON ADDENDUM 1 AND TH E PROPO SED RU LE........................................... A1 APPENDIX 2: LISTINGS OF HIGHWAY ROUTES EXAMINED IN TH I S STU D Y....................................................... A2 APPENDIX 3: SELECTED PAGES FROM THE RADTRAN 4 COMPUTER CODE R UN S............................................ A3 i
V NUREG.1437, Addendum 1 l
Supplemental Analysesfor Cumulative EnvironmentalImpacts.
LIST OF FIGURES 1.
Proposed Las Vegas beltway.......................................... 9 2.
Routes analyzed in this study........................................ 10 LIST OF TABLES 1.
Transportation route parameters for RADTRAN analysis.................... 12 2.
Radionuclide inventory for the SNF shipments............................ 14 3.
Estimated cumulative radiation exposure resulting from SNF transport in Clark County............................................ 17 4.
Cumulative radiological transportation risks resulting from SNF transport in Clark County........................................... 18 5.
Total non-radiological truck fatalities, injuries, and accidents resulting from SNF shipments........................................ 21 6.
Estimated cumulative radiation exposure resulting from transport of SNF and DOE radioactive waste in Clark County........................ 23 7.
Cumulative radiological transportation risks resulting from transport of SNF and DOE radioactive wastes in Clark County......................... 23 8.
1990 distribution (in percent) of racial and ethnic population grou in Clark County, Nevada...............................ps
..............25 9.
Ethnic and racial groups (in percent) living within 0.5 mile (0.8 km) of the transportation routes........................................... 25
- 10. Fraction of persons along the transportation routes who are in poverty (percent)
........................................26 1
Vii NUREG-1437. Addendum 1
._ __1
r i
Supplemental Analysesfor Cumulative Environmentalimpacts.
I f
ACRONYMS AND ABBREVIATIONS CFR Code of FederalRegulations em centimeter DOE U.S. Department of Energy
)
l DOT U.S. Department of Transportation EIS environmentalimpact statement FR FederalRegister ft foot GE!S Generic EnvironmentalImpact Statement for License Renewal of Nuclear Plants (NUREG-1437)
HLW high-level waste in inch i
km kilometer Ib pound j
LRFC lifetime risk of fatal cancer m
meter mrem millirem mSv millisievert MTHM metric tons of heavy metal (a conventional unit for high-level nuclear waste)
MT metric ton (i.e.,1000 kilograms (about 2200 pounds)]
MTU metric tons uranium mwd megawatt-days NRC U.S. Nuclear Regulatory Commission NWPA Nuclear Waste Policy Act SNF spent nuclear fuel Sv sievert ix NUREG-1437, Addendum i
Supplemental Analysesfor Cumulative EnvironmentalImpacts.
- 1. INTRODUCTION 1.1 PURPOSE OFTHE ADDENDUM This Addendum to NUREG-1437, Generic EnvironmentalImpact Statement for License Renewalof Nuclear Plants, May 1996, supplements the analyses reported in Section 6.3
" Transportation," and especially Section 6.3.2, " Table S-4-Environmental Impacts of Transportation of Fuel and Waste to and From One Light-Water-Cooled Nuclear Power Reactor" of that report. The analyses reported in this addendum specifically address whether the environmentalimpacts of the transportation of higher enrichment and higher burnup spent nuclear fuel are consistent with the values of 10 CFR 51.52, Table S-4 as applicable to license renewal, continue to be applicable given that it is likely that spent fuel will be shipped to a single destination, such as the proposed repository at Yucca Mountain in Nye County, Nevada, and given that spent fuel shipments will involve higher enrichment and higher burnup fuel than was assumed in calculating the impacts shown in Table S-4. The analyses reported in this Addendum provide the basis for amending the U.S. Nuclear Regulatory Commission's (NRC) regulations for addressing the environmental impacts associated with the transportation of fuel and waste to and from a commercial nuclear power plant within the context of the license renewal review process. The amendment is to the provisions in 10 CFR 51.53(c) and in Appendix B to Subpart A of 10 CFR Part 51 which specify how Table S-4 is to be used in individual license renewal reviews. The values in Table S-4 are found to be bounding when accounting for spent fuel shipments to a single destination and for the shipment of higher enriched and higher burnup fuel. The amendment affects only the provisions in 951.53(c) and Appendix B to Subpart A that govern the use of impact values codified in 10 CFR 51.52 as it applies to reviews to renew the operating license of individual nuclear power plants. It is not intended that this Addendum support any other regulatory decision by the NRC.
1.2 SCOPE OF THE ADDENDUM in NUREG-1437, Section 6.3 (" Transportation"), the radiological and nonradiological environmental impacts resulting from transportation of low-level radioactive waste and mixed waste' to off-site disposal facilities and of spent fuel to a monitored retrievable storage facility or a permanent repository were assessed. The environmentalimpacts from the transportation of fuel and waste attributable to license renewal were found to be small when they are within the impact parameters identified in 10 CFR 51.52. The findings in NUREG-1437 were codified in an amendment to 10 CFR Part 51 published in the Federa/ Registeron June 5,1996 (61 FR 28467). Public comments were solicited on the use of Table S-4 and several other areas of the final rule. This comment process identified two questions that should be addressed generically Iather than requiring each license renewal applicant to address them individually. The first question is whether the environmental impact values contained in Table S-4 are still appropriate for use in license renewal reviews if spent fuel is transported to a single destination such as the candidate repository at Yucca Mountain, Nevada, even though the values in Table S-4 were developed from data reflecting spent fuel
' Mixed waste is low-level radioactive waste that also contains chemically hazardous constituents.
I NUREG-1437. Addendum I
Supplemental Analysesfor Cumulative EnvironmentalImpacts..
. shipments to several destinations. The second question is whether the environmental impact values contained in Table S-4 are still appropriate for use in license renewal reviews given
~ that applicants will be shipping spent fuel that is more highly enriched and irradiated longer than is accounted for in the analysis to develop Table S-4. Paragraph 51.52(a) requires a plant-specific analysis of transportation impacts if the uranium-235 enrichment exceeds 4 percent or if the average level of irradiation exceeds 33,000 megawatt-days per metric ton of uranium (mwd /MTU). The analyses in this Addendum are limited to these two questions.
Numerous public comments that question the scope of the analyses were submitted on the draft Addendum. These comments and the NRC responses found in Appendix 1 provide further understanding of the purpose and scope of this Addendum to NUREG-1437.
1.3 BACKGROUND
On June 5,1996, the Commission published in the Federal Register (61 FR 28467) a final rule amending its environmental protection regulations in 10 CFR Part 51 to improve the efficiency of the process of environmental review for applicants seeking to renew a nuclear power plant operating license for up to an additional 20 years. The rulemaking was based on the analyses reported in NUREG-1437 and was initiated with the objectives of (1) improving the efficiency of the license renewal process by drawing on the considerable experience of operating nuclear power plants in generic assessments of many of the environmental impacts, (2) reporting the analyses and findings in NUREG-1437, (3) codifying the findings in the Commission's environmental protection regulations so that repetitive reviews of those impacts that are well understood could be avoided.
In the statement accompanying the final rule, the Commission solicited comments on the treatment of low-level waste storage and disposal impacts, the cumulative radiological effects from the uranium fuel cycle, and the effects from the dispcsal of high-level waste (HLW) and spent fuel. The final rule would not become effective until these comments had been considered. A number of commentors argued that the requirements for the review of transportation of high-level waste in the rule were unclear with respect to (1) the use and legal status of 10 CFR 51.52," Environmental effects of transportation of fuel and waste-Table S-4," in plant-specific license renewal reviews; (2) the conditions that must be met before an applicant may adopt Table S-4; and (3) the extent to which the generic effects of transporting spent fuel to a high-level waste repository should be considered in a plant-specific license renewal review.
After considering the comments received on the rule, the Commission republished the rule in the FederalRegisteron December 18,1996 (61 FR 66537). The rule at 10 CFR 51.53(3)(c)(ii)(M) continued to require that "The environmental effects of transpottation of fuel and waste shall be reviewed in accordance with 10 CFR 51.52." However, because of the comments received, the Commission added to that paragraph the requirement that The review of impacts shall also discuss the generic and cumulative impacts associated with transportation operation in the vicinity of a high-level waste repository site. The candidate site at Yucca Mountain should be used for the purpose of impact analysis as long as that site is under consideration for licensing.
NUREG-1437, Addendum 1 2
Supplemental Analysesfor Cumulative EnvironmentalImpacts.
l l
Also in response to the comments, the Commission stated that As part of its effort to develop regulatory guidance for this rule, the Commission will consider whether further changes to the rule are desirable to generically address: (1) the issue of cumulative transportation impacts and (2) the implications that the use of higher burn-up fuel have for the conclusions in Table S-4. After consideration of these issues, the Commission will determine whether the issue of tranportation impacts should be changed to Category 1.2 Chapter 6 of NUREG-1437 addresses the environmental impacts associated with the management of radiological and nonradiological wastes resulting from license renewal.
Section 6.3," Transportation," addresses the environmentalimpacts resulting from the shipment of (1) low-level radioactive waste and mixed waste to off-site disposal facilities, 8
(2) fresh fuel to the plant, and (3) spent nuclear fuel (SNF) from the plant to a monitored retrievable storage facility or permanent repository. Section 6.3 also provides an assessment of the applicability to license renewal of 10 CFR 51.52. In Section 6.3.4, the NRC concluded that "The environmental impacts from the transport of fuel and waste attributable to license renewal are found to be small when they are within the range of impact parameters identified in Table S-4." This finding was codified in Table B-1, " Summary of findings on NEPA issues for license renewal of nuclear power plants," of Appendix B to Subpart A of 10 CFR Part 51 in order to extend the use of Table S-4 to license renewal reviews. There were, however, certain circumstances not accounted for in the original analyses supporting Table S-4 and not adequately treated in the 1996 amendment for license renewal.
Summary Table S-4 was published in 10 CFR Part 51 to be used by an applicant for a nuclear power plant construction permit in its environmental report and by the NRC in its environmental impact statements. Table S-4, which accounts for the environmental effects of transportation of fuel and waste to and from the nuclear power plant, was intended to be a generic statement of transportation impacts that can be adopted in the review of any plant, as long as certain conditions identified in Part 51 are met. The environmental impact values in Table S-4 were developed from information available from actual shipments from nuclear power plants to a number of different destinations. Because a single destination at Yucca Mountain is now under consideration, it is necessary to determine whether it is reasonable to continue using the environmental impact values in Table S-4 in license renewal reviews. This Addendum provides the assessment to make that determination.
The environmentalimplications of the use of more highly enriched and higher burnup fuel than is considered in 10 CFR 51.51 (Table S-3) and in 10 CFR 51.52 (Table S-4) are assessed in NUREG-1437, Section 6.2.3. However, the analysis and conclusions relative to Table S-4 are not brought forward to Section 6.3, " Transportation." This Addendum corrects 8 in NUREG 1437 and in the rule. Category 1 issues are those environmental issues for which the analysis and findings have bean determined to be applicable to all nuclear power plants or to plants with specific types of cooling systems 'e other common plant or site characteristics. Absent new information that significantly changes the finding. these generic findings may be adopted in plant license renewal reviews. Category 2 issues are those environmental issues for which the analysis did not result in a finding common to all plants or to plants with common characteristics. Plant-specific reviews are required for Category 2 issues.
'Because only the radiological aspects of transportation cre of interest here, in the remainder of this report, mixed waste will not be distinguished from other low level-Waste.
3 NUREG-1437, Addendum 1 l
T Supplemental Analysesfor Cumulative EnvironmentalImpacts..
that omission and expands the assessment of the impacts of transportation of higher enriched and higher bumup fuel. Previously, if ruel enrichment was to exceed 4 percent and burnup was to exceed 33,000 mwd /MTU during the license renewal period, the applicant had to provide a full review of the environmentalimpacts of transportation of fuel and waste to and from the reactor. For a number of years, licensees have been moving to the use of higher enriched fuel and longer burnup of that fuel than was specified for Table S-4. This Addendum contains an assessment of transportation of fuel having a uranium-235 enrichment of up to 5 percent and irradiated up to 62,000 mwd /MTU. That assessment indicates that the values shown in Table S-4 continue to be a reasonable estimate of environmental impacts of transportation of fuel and waste for the purpose of license renewal reviews.
- 2. CUMULATIVE IMPACTS OF SPENT NUCLEAR FUEL TRANSPORTATION The purpose of this analysis is to determine whether the Commission can reach a generic conclusion about the cumulative impacts of spent fuel transport in the vicinity of a repository due to the renewal of a nuclear power plant operating license. If the Commission can reach such a conclusion, the issue can be designated a Category 1 issue and the finding codified in 10 CFR Part 51. For an issue to be designated Category 1, the following criteria must be met:
(1) The environmental impacts associated with the issue have been determined to apply either to all plants or, for some issues, to plants having a specific type of cooling system or other specified plant or site characteristic; (2) A single significance level (i.e., small, moderate, or large) has been assigned to the impacts (except for collective off site radiologicalimpacts from the fuel cycle and from high level waste and spent fuel disposal *); and (3) Mitigation of adverse impacts associated with the issue has been considered in the analysis, and it has been determined that additional plant-specific mitigation measures are likely not to be sufficiently beneficial to warrant implementation.
Section 2.1 is a description of the status of the Yucca Mountain site as a potential geologic repository in order to provide a context for the analysis.5 Section 2.2 describes the approach
- This exception only applies to the two entries in Table B-1 labeled "Offsite radiological impacts (collective effects)* and "Offsite radiological impacts (spent fuel and high level waste disposal).
- Any generic conclusions by the Commission conceming the cumulative impacts of transportation associated with nuclear power plant license renewal would in no way affect any U.S. Department of Energy (DOE) decision concoming the suitability of Yucca Mountain, any consideration that DOE may give to transportation impacts in making that decision, and is not intended to support any other regulatory decision by the NRC.
NUREG-1437, Addendum 1 4
L
Supplemental Analysesfor Cumulative EnvironmentalImpacts...
employed by the NRC staff to analyze the cumulative effects of SNF transport in the vicinity
- of the proposed repository due to the renewal of a nuclear power plant operating license.
Section 2.3 presents the results of those arv. lyses, Section 2.4 discusses impacts of additional radioactive waste shipments, and Section 2.5 presents a summary of SNF transport impacts. Finally, Section 2.6 exan,hes the potential for environmental justice issues related to radioactive waste transpon in Clark County, Nevada.
2.1 BACKGROUND
ON THE PROPOSED HLW REPOSITORY The Nuclear Waste Policy Act of 1982 (NWPA) gave the U.S. Department of Energy the responsibility for finding a site for disposal of commercial SNF and other high-level waste, and for building and operating an underground disposal facility called a geologic repository.
In 1987, Congress amended the NWPA and directed DOE to study only Yucca Mountain, Nevada, to decide whether it is suitable for a repository for high-level nuclear waste. Under the NWPA, DOE has been studying Yucca Mountain for 15 years as a potential geologic repository for the disposition of the nation's spent nuclear fuel and high-level radioactive waste. However, a number of decisions remain to be made before Yucca Mountain could ever be considered for development of a repository; any one of these decisions can stop the approval process. The Secretary of Energy plans to make a decision in 2001 on whether to recommend the site to the President for development as a repository. If DOE finds the Yucca Mountain site suitable and recommends the site, then the President must decide whether to recommend the site to Congress. If the President recommends the site and if Nevada submits a notice of disapproval, then Congress must decide whether to allow the recommendation of the President to take effect. Only if the decisions remaining to be made ultimately support development of a repository at Yucca Mountain, then DOE would submit a license application to the NRC. If the repository is licensed, then SNF and HLW would be shipped to the site using only NRC-certified transportation packages, i
2.2 APPROACH TO ANALYSIS The staff's overall approach was to use NRC's current knowledge base and transportation experience, to develop assumptions that reasonably estimate and bound the risks associated with the increased number of spent fuel transports that might occur if license renewal of nuclear power plants were to occur. These assumptions are generic in nature, meaning they could be applied to any licensed nuclear power plant. The NRC staff made a number of ' conservative' assumptions, whi6 means that the assumptions would lead to an overestimate of what the NRC staff believet, to be the actualimpacts. Examples of where the NRC staff believes conservative assumptions have been used appear later in this section. The goal is for the results to be used by a license renewal applicant as it would any other Category 1 issue.
In accordance with the NWPA, DOE is required to prepare an environmental impact statement (EIS) for Yucca Mountain. The EIS will consider the proposal to construct, operate, and eventually, close a repository at Yucca Mountain. See DOE Notice of Intent (60 FR 40164). DOE is expected to assess national and regional (i.e., within the State of Nevada) transportation options that cover the full range of operating conditions relevant to 5
NUREG-1437. Addendum 1
I Supplemental Analysesfor Cumulative EnvironmentalImpacts...
potentialimpacts to human health and the environment.' in its response to public scoping comments, DOE indicated that its draft EIS transportation analysis would include both truck
' and rail transport, and use Department of Transportation routing regulations and representative routes and actual route characteristics. Thus, DOE's expected transportation analyses will be detailed; however, DOE does not plan to complete its final EIS until 2000.
DOE recently issued its draft EIS for a 180-day public comment period beginning on August 13,1999.
This analysis aims to address the cumulative impacts of SNF transportation to a HLW repository from a generic perspective.7 Because Congress, at this time, has directed DOE to study only Yucca Mountain for the proposed repository, the NRC staff began with the assumption that all SNF would be transported through Clark County, Nevada (i.e., the Las Vegas area) en route to the repository. This assumption is conservative in several ways.
First, current law would not allow more than 70,000 metric tons of heavy metal (MTHM), with an estimated -63,000 MTHM of that total being from commercial SNF, to be disposed of at Yucca Mountain. Nevertheless, the NRC staff used estimates of quantities of SNF that would need to be disposed of that are considerably larger than the 63,000 MTHM for the purpose of evaluating the entire inventory of SNF produced by nuclear power plants. Second, there are other routes to Yucca Mountain rather than through Clark County, but none of the other routes would encounter as high a population as found in Clark County. The NRC staff also adopted this assumption because-whether Yucca Mountain or another site is selected for a repository-- estimates of transportation impacts are maximized in the case where all SNF is transported through a major metropolitan area. The NRC staff believes it important to emphasize that, while conservative, the assumption may not be at all representative or realistic.
Transportation to Yucca Mountain or another repository site may make heavy use of rail transportation, for example, because rail transport is expected to be less costly than truck transport. The overall radiological impacts of rail as compared to highway shipments may be lower. In part, this is because of the higher capacity of rail cars which allow fewer shipments and because population densities along most rail routes are typically lower than along the interstate highways that trucks wouid use to transport SNF. Additionally, when non-radiological accident rates between truck and rail shipments are normalized for payload size and mileage, the accident rate for rail shipments is about 3 percent of the comparable accident rate for truck shipments (Dyer and Reich 1993). Evaluation of cumulative impacts in the vicinity of Las Vegas carried out in this analysis, therefore, represents an upper bound because it assumes all SNF would move by legal-weight truck rather than by rail or by a combination of rail and truck to reach the repository.' Further, to ensure that the impacts
- DOE's Notice of Intent indicates that its analyses of impacts of regional transportation issues will include (a) technical feasibility, (b) socioeconomic impacts. (c) land use and access impacts. and (d) impacts of constructing and operating a rail spur, a heavy haul route, and/or a transfer facility. 60 FR 40168.
7 After DOE's publication of the final EIS for Yucca Mountain, the Commission will consider whether the information contained therein would be considered new and significant in the context of decisions related to the renewal of nuclear power plant operating licenses such that some additional action may be required.
- The NRC staff did not consider conservative analyses that would be outside the reasonable range of assumptions, e.g., routing shipments on indirect routes through densely populated areas. While the NRC staff did make many conservative assumptions, consistent with U.S. Department of Transportation regulations for highway route controlled quantities of nuclear materials (49 CFR 397.101), the NRC staff assumed that the NUREG-1437, Addendum I '
6 i
I
(
l Supplemental Analysesfor Cumulative EnvironmentalImpacts.
l I
estimated here are conservative, the NRC staff assumed that shipments would be by legal-weight trucks rather than heavy-haul trucks because fewer shipments would be required if heavy-haul trucks were used.
To examine the effects of license renewal, the NRC staff used two estimates of SNF that would be transported to the repository. The first was based on the assumption that no
{
nuclear plants have their licenses renewed, and the second was based on the assumption that all existing nuclear plants would operate for the full duration of a 20-year license renewal i
i period. This means that the amount of SNF shipped for the license renewal case was assumed to be 50 percent greater than the amount of SNF for the no-license renewal case.
l The assumption used for the license renewal estimate is conservative because some plant l
owners have already decided not to request renewal of plant operating licenses.
As noted above, the NWPA prohibits DOE from accepting more than 70,000 MTHM of HLW at the Yucca Mountain repository, only 63,000 MTHM of which would be SNF. Based on this limit, DOE estimates on the order of 37,600 truck shipments of SNF to Yucca Mountain, assuming all SNF travels by truck in legal-weight casks (K. Skipper, Yucca Mountain Site i
Office, personal communication to D. P. Cleary, NRC, July 11,1997). For this analysis, the NRC staff assumed that all current and committed SNF, about 84,000 MTHM, would be disposed of at Yucca Mountain. [The Nuclear Waste Technical Review Board (1997) made a very similar estimate of current and committed SNF.] Using DOE's estimated number of shipments and the total amount of SNF leads to an estimate of the order of 50,000 truck shipments without license renewal. Assuming all plants renew their licenses and operate for an additional 20 years, the estimate is on the order of 75,000 truck shipments.'
The analysis used the RADTRAN computer code (Section 2.2.3) to estimate the radiation doses to the people of Clark County and to transportation workers. The route and population density numbers used by RADTRAN computer code were generated by the HIGHWAY computer code and modified by the NRC staff to account for population growth (Section 2.2.1). The human health implication of the radiological exposures were estimated by use of BEIR V radiation-dose-to-cancer-risk factors (Section 2.2.3). The risk of non-radiological accidents were estimated by using U.S. Department of Transportation statistics (Section 2.3.2).
2.2.1 Transportation and Route Scenarios i
The HIGHWAY computer code (Johnson et. al.1993) was used to select routes. The HIGHWAY computer code models the U.S. highway system. Its data base includes all interstates, most U.S. highways, and many State, county, or local roadways, it represents l
about 380,000 km [240,000 miles) of roadway. Several different routing options are available in the highway program, including probable commercial routes, routes on the interstate highway system, routes that bypass major urban areas, and preferred routes designated by the States. Additional detailed routing analysis can be performed by blocking individual or trucks would be routed on interstate highways to the maximum possible extent.
- Although these estimates exceed the 70,000 MTHM limit for the first repository in the NWPA, they represent conservative essumptions (i.e., overestimates) that would define an upper bound of potential impacts for a repository at Yucca Mountain.
7 NUREG-1437, Addendum 1
Supplemental Analysesfor Cumubtive EnvironmentalImpacts...
sets of highway segments or intersections contained in the data base, a feature the NRC staff utilized to analyze the downtown routes.
l The selection of preferred routes assumes that each shipment consists of highway-route-controlled quantities of radioactive materials. Travel time is optimized based on maximum utilization of the interstate highway system, with preference given to bypasses around major cities, except where alternate routes have been designated by state officials. Selected information considered by the NRC staff in using the HIGHWAY computer code is given in Appendix 2. These inputs and outputs provide a detailed listing of each highway route as well as mileage and population density zones considered in the analysis.
A beltway is being constructed in Clark County (Clark County 1997) which is expected to consist of three connected segments including a southern, western, and northern route; these segments will create a freeway " ring" around the Las Vegas Valley to route vehicles around, rather than through, the congested urban core (Figure 1). The southem segment of the beltway is being built in sections, with each segment opening to traffic upon completion.
The first phase of the project, from I-15 to McCarran Airport (Airport Connector), was opened in 1994. The second section, from Warm Springs Road to Windmill Lane, opened to traffic in Oct.1995. In Feb.1997, the third portion of the project-from Windmill Lane to Eastem Ave.-became fully operational. The fourth section of the southern beltway, Eastern Ave. to Pecos Road, was completed in 1997.
The proposed northem and westem beltway is expected to be a 10-lane facility with adequate right-of-way to permit construction of a fixed guideway facility (e.g., a commuter rail line). This is called the " ultimate facility" and will require a right-of-way width of 107 to 137 m [350 to 450 ft), plus land for interchanges or access to other transportation facilities.
Because the beltway is expected to be complete before the repository begins operation and because regulations require that spent fuel shipments use bypasses where possible, j
analysis of transportation on the route through downtown on the current interstate system yields higher exposure' estimates than might actually occur. In addition, there are two I
plausible routes into Clark County; from the south on 1-15, and from the northeast on 1-15.
SNF from westem and southwestem states would likely arrive via the southern route. SNF from eastem states would likely arrive via the northeastern route. To ensure that the j
conclusions of this analysis are conservative, the NRC staff analyzed scenarios in which all SNF arrived via the northeastem route and scenarios in which all SNF arrived via the southem route. The combination of the northeastern and southern scenarios, and the downtown and beltway scenarios gives four transportation route scenarios that were analyzed by the NRC staff.
The NRC staff analyzed the potential impacts of SNF transport along the four routes (illustrated in Figure 2). The route named "from the northeast through dowritown" starts at the Arizona-Nevada state line and follows 1-15 to near downtown Las Vegas and then i
proceeds northwest on U.S. 95 beyond the northwestem comer of Clark County, Nevada.
j The route named "from the south through downtown" starts at the California-Nevada state line and proceeds north on 1-15 to near downtown Las Vegas and then proceeds northwest j
on U.S. 95 through the northwestem portion of Clark County. The other routes are similar to the first two except each route will use the 1-215 beltway that is currently planned and under construction around the north, west, and southern portions of the Las Vegas metropolitan area. The route named "from the northeast using the beltway" follows 1-15 from the NUREG-1437, Addendum 1 8
Supplemental Analysesfor Cumulative EnvironmentalImpacts..
ORNL 98-6791/rra SR 157 7
h a**"
g 3
\\
W 8
ts
/
\\
p' N
w Lo.E _T.m a yNELUS
/
X'%
caso, //
T-g
,p '
e Aa ronce s4Se
\\g h
y cHEYEme 0
CHEYENNE g
g 3
uty
\\
CAREY L,A
\\
K WASHBGToN i
m
]
-Ur 3
sonanzA g
g
[f/
s STEWART
/,
cuantsSTom A I s,
h 8[f
\\
h sananal h
iE
\\
E f
i OESERT Dn h
I
/N,_samos rtaamwoo 11 \\
(
L, Ynopic/na 1
,J.
% l\\
i l-f
" 88 L
-wTEmanoNAL SunsETI N
,h.
<.sm)
A**0"1 1
i
..4 suusET
'9 1
T
Ec "D' h3c(e* @533k3EC33g '
6 _
9 _
5 5
0 9 _
9 _
1 1
1
- 56 _
- 19 _
2 2
5 89 _
59 _
2 2
1 0
317 0
344
- - 65.
1 123 21.
6 6
9 111 38 _
V.
35 _
5 5 3
N ttt s
aaa -
L.
a C. r i
0 999 r
O. I B
0 999 L
P 00
/// - 16 _
l 777 62 _
0 0
5
. 7 l
111
- 83 _
5 4
o
///
13 _
5 5
3 9
T U. 3 666 1
e 0
k
- r S. t i
ede 084 3
a p
neh 001
- 11 _
0 n
adt 26 _
9 9
4
. 9 r
LiO 012 88 _
93 u
v 1 _
4 4
3 T
ei S
/4
. 71 s
ld L
. 1 a
gn0 000 E
. /
i nU V
Y. 6 :
B 00 i
23 E
R s
Se 84 L61 _
U e e n
1 22 _
8 8
4 l
C
- l l
sa Y38 _
w R
gi i
sl T
4 4
3 E. nM M ei:
I o
M. i cts S
b
. vl cl y N
ia 0 er Aua e
E g
i rt 7 te Mw a _. 0 NVV D t
4.
. ro ah d h t
INN 96 _
e 3
AT tt e
g e_4 N32 _
3 8
8 4
SO t
i 5L I13 _
h l
. T i H i
_1 1C H
4 4
3 g
o D
e m
M_
5O T
a Y.
t P
s s
00 i h 1L I
A.
a u
L g
e_
W p
W
. 3 i :
1 u
t s
H.
. 3 B
tk 6
o a.V 55 E
G I
cc r
1 e eu 0 0.h S_N G 7.3 t
19 9 _
e 1U A
6 6
5 h
H.
. 1 m
f r 49T E91 _
t 4
i ft 94 L5 - _
3 3
2 V
t1 T e
.l R S I
h N. a:
g 2
nn S. ca E
M 0
V g
. 9 ii s Uo O
u tg
. 9
)
o
. /: s ein :
L ed T
ne T
77 _
7e rbi e
ead I
(
r 3
3 1
1m r
ais p
pli LS 29 _
h
/i e hs y00 yi v A
7 7 5
25_
t 6T v soo T Tti:
5GY i trr 2
lDs 1ER s
.d r npc n8 eu y IVU a
a D i g
nMea W C g
o asy i a nw rSR R. gR 2
rkr S Lsah ZAE 07 _
e E
. n tnr sl g ALM V
V il h sie yey yeii 52 _
2 2 0 O
va t
nlf att actH 2 _
7 7
9 s
T. at i o wan wcl 2
2 1
a T
eo w css htu haul I
LT dd gso g Ma L
L C
gii i rC id p
f noo He He i o
5
- ivv t
t c
00 _
1 e waa yn yi n
n 5
5
- 1. o t
I p o bI bm i S5 05 _
s N
y l ee i r I9 4
4 1i T
ltt e
eL P
IU 4
4 3t a
PZ ouu g
g a
e A
e foo a a
l h
t RR e e
000 u
t u e l
l p
r o h i
i 21 0
o o
R T M
M 86 6
6
- 1. p n
1 1
20 5
3 3
22 0
1 2
I d
m s __
e o
e_
0 0
t l
a r
3 3
m i __
F M_
4 4s i 1
1e t
g s a E 1
t e
e __
n :
t ele s tu a __ Vtac i t
Nutr s
o S_
ooe a R
RTP B zCxmoL y [ 5QC3~
>I.t JJ 1
e ye[k, q:l n::4 g:8 ho$aI'9%
aE.
r.
n o
i t
a l
u p
o P
0 0
0 2
1 0
n 2
w V.
l o N.
d ah s
e us L.
a l01 t
d C.
M 0
i a
a ie O
B 0
t30 m
vg L
P 00 o43 i i a l
T12 t
de
. 8 l
s nl 5
o 1
E ii 9
T m
U. 3 e
. 1 e
hl 0
k
- :r n
79 305 6
t a S
t i
ede 3
a 2
t a
p neh b
71 956 3
no 0
n adt r
53 1
3 i t 9
r LiO U
55
. 93 u
v 62 ee
. /0 T
ei gh
. 71 s
ld at 1
a gn0 e
/
i nU ll Y
6:
B 00 i
n 45 546 6
i a R
s Se a
2 mu U.
e e n
b 03 913 3
q C. :l l
sa r
06 131 3
ee R
gi i
sl u
24 h
E nM M ei:
b 1
9 tt M. i cts u
3 o
. vl cly S
1 f n ia 0
er Aua o
rt 7
te Mw y
. ro ah d h l
09 289 9
ma
- 4..
. AT tt e
g a
3 um 3
SO t
i r
03 439 1
s
. F i H T
u 1
187 s
o. I e
m R
11 ee Y
t P
s s
00 i h hi A.
a u
L g
t r W
. 4 i :
1 u
H I
B tk 6
o o
3
)
,g G
cc 0 0.hr ge
. 1 e eu i
nt t H.
. 1 m fr 49T n
m iar 5
i ft 54 a
oim dco V
t4 T e
- .l t
imk n
p N. a:
g a
a t
q une 1
nn S. c 0
D a..
se s
oor
. 9 iis Uo l qq rg
/
ri 9
)
ein tg L
ed t
uss ea e
t s
/:
(
ais p
pli s
- ne u
p//
tt l
oai
. 7e rbi e
ead p
oee en p
tl h
. 1m r n
Pl l sme o
ut
. /i e hs y00 yi v I
pp eoc e
ep L
. 6T v soo T Tti:
doo ell r A
tPP nMKP (p
uon w
i trr 2
lDs N
eee ciie Dpo o
d r npc n4 eu y
b
. : a D i g
nMea R
h a
s
. o asy i a nw i
g t
i e
t A. gR 2
rkr S Lsah M
t i
s s
t e
O. n tnr sl g A
e i
a o
h L. il h sie yey yeii R
W D
B N
g S
. va t
nlf att actH h
ap T. at i o wan wcl s
P
. eo w css htu haul I
. LT dd gso g Ma w
e h
N.
C gii irC id p
t noo He He i ivv t
t c
h 5
g 1
e waa yn yi n
u I
p o bI bm i o
V y lee i r r
N T
ltt e
eL P ht A.
ouu g
g s
C.
e foo a a
a t
RR e
e g
u e l
l e
o h i
i V
R T M
M s
a d)
L f
e o
u h
t n
u i
o t
s n
5 1
o I
c
(
mo 1
r e
F.
t 2
u e
t o
ue R
R g=clM9 gw*. >c.
s3.
C
%kw3gf~ >gq$* ew O$=k.,4 N{agg$~ E}nE :
g 6 _
9 _
4 4
2 9 _
9 _
5 5
5 n
o
- 56 _
i t
- 19 _
8 8
7 a
- 89 _
59 _
3 3
3 l
u p
o 428 P
311
- 65 _
0 9
9 8
123
- 21.
2 0
n 111
- 38 _
- 35.
4 4
4 2
w ttt l o aaa d
ah e
us 999 l08 t
d 999 a
a ie
///
- 16 _
t3 5 m
vg 1
1 0
o06 i i a 777
- 62 _
T11 t
de 111
- 83 _
///
- 13 _
3 3
3 s
nl 666 E
ii m
e hl 085 n
63 177 6
t a 034
- 11 _
a 2
t
- 26 _
7 7
6 b
40 423 3
no 001 88 _
r 11 121 3
it 1 _
2 2
2 U
32 S
83 ee L
gh 000 E
at V
e 23 E
ll 40 L61 _
n 32 611 6
i a 1
1 0
a 2
mu 1
22.
Y38 _
b 11 555 3
q T
3 3
3 r
67 121 3
ee I
u 93 h
S b
9 tt N
u 3
o E
S 1
f n e_0 g
VVV D
o a.
NNN 96 _
y l
02 302 9
ma e_3 N32 _
7 7
5 l
_0 5L I13 _
a 3
um i _ 1 1 C H
6 6
6 r
66 381 1
s M _
5O T
u 1
717 s
IL I
R 1
ee e __
W hi t r tt. V 55 E
o a.N 9 _
)
,g G 7.3 19 A
ge.
S _
IU 1
1 0
E91 _
i nt t m i ar L5 - _
5 5
5 n..
A S
I a
oim dco n
p O
M t
imk L
a t
q une S
D a..
se s
oor T
l qq rg
/
ri P
- 77.
t uss ea e
t s 1'
1 9
u p//
t t l
oai I
p oee en p
tl h NS
- 29 _
A
- 25 _
7 7
6 n
Pl l sme o
ut 5GY I
pp eoc e
ep 1ER doo ell r p
uon Dpo IVU N
eee ciie
(
V C
A tPP nMKP NSR R
h a
s AAE
- 07 _
T g
t i
e:
6 6
0 D i s
s t
CLM A
e i
a o
- 52 _
2 _
1 1
1 R
W D
B N
2 2
2
- 00 _
7 7
9 n 55
- 05 _
o 19 8
8 7i IU 2
2 2 t a
l 000 u
p 21 0 _
o 8
8
- 5. P 46 d) 0 0
00 e
1 1
12 0
u 2
n i
d t
s_
e n
e_
0 0
t o
l a
i _
3 3
m c
M _
0 0 s i
(
1 1 e t
g s
a E
2 t
e_
n e
t l e s
t Veac i a._
u Ntt r s
t o
S uoe a
oTP B
R R
- Z nQ.zt*>
E=3 -
>Nb i
4kg
~E gcQgQo' h3::kE' 3E83k3,R g2aP 6 _
9 _
2 2
9 9 _
9 _
1 1
0
- 56.
- 19.
7 7
3
- 89
- 59 1
1 1
0 3358 0
3343
- : : : - 6 5 __
1 1223 21 7
7 5
1111 38 _
V.
35 _
4 4
3 N.
tttt s
aaaa -
L.
a C. r i
0 9999 r
O I
B 0
9999 L
P 00
//// - 16 _
l 7777
- 62 _
8 8
8
. 8 l
1111
- 83 _
5 3
o
//// - 13 _
3 3
2 9
T
. 1 e:
6666 U. 3 0
k
- :r S. t i
ede 0026 3
a p
neh 0010
- 11 _
0 n
adt
- : : : - 26 _
1 1
3 r
LiO 0112 88 _
. 9
- 96 u
v 1 _
3 3
2
- /3 T
ei S
71 s
ld L
. 1 a
gn0 0000 E
. /
i nU V
Y. 6:
B 00 i
476 E
R.
s Se 783 L61 _
U.
e e n
1 22 _
1 1
3 C. :l l
sa Y38 _
R gi i
sl T
3 3
2 E
nM M ei:
I M.i cts S
. vl cl y N
. ia 0
er Aua e_
E 7
te Mw
- rt VVVY D g_0.NNNN
. ro ah d
h 4.
a_6 96 _
. AT tt e
g e_3 N32 _
3 3
2 3
SO t
i 5
L I13 _
l T
i H i_1 15C H
4 4
3 o. D e
m M_
29O T
Y.
t P
s s
00 i h IUL I
A.
a u
L g
e_
W W.
3 l
9 u
t 5
s H.
. 3 B
tk 4
o
_V 515 E
a_N G
cc I
0 0.hr s
G 7.3 t
129 9 _
. 1 e eu S _
IIU A
5 5
6 ap H
. 1 m fr 79T E91.
6 i
ft 84 EW L5 - _
3 3
2 y
V. t0 T e
.l RNNS I
N. a:
g S. ca E
M b
2 nn
. 9
)
tg L
ed:0 V
9 ii s Uo O
g T
n
. / : s ein
- ne TS 77 _
i
. 7e
(
rbi e
ead IA 3
3 4
s
. 1m r ais p
pli LGS 29 _
. /i e hs y00 yi v EA 25 _
7 7
5 u
. 6T v soo T Tti:
5VGY i trr 7
lDs 1
ER s
d r npc n8 eu y
ISVU a
. ;a D i g
nMea VA C
g o
asy i a nw NLSR R
gR 2
rkr S Lsah Z
AE 0 7.._
e E
n tnr sl g ANLM V
V. il h
sie yey yeii
- 52.
2 2
0 0
va t
nlf att actH 2.
7 7
0 s
T at i o wan wcl 2
2 2
a T. eo w css htu haul I
. LT dl gso g Ma L
L C
gi i i rC id p
f aoo He He i e ivv o
5 t
t c
- 00 waa yn yi n
5 1
n 5
5
- 7. o t
I p o bI bm i 515 05 _
s V.
y l ee i r 129 4
4 2i a
N.
T ltt e
eL P
IIU 4
4 3t Z
ouu g
g a
e A.
e f oo a a
l h
t RR e
e 0000 u
t u e l
l p
r o h i
i 439 0 _
o o
R T M
M 714 6
6
- 2. p n
1 1
30 5
3 3
22 0
1 2
I d
m s_
e o
e __
0 0
t l
a r
i.
6 6
m F
M.
3 3s i 1
1e t
g s
3 a
E t
e e_
n :
t el e s t
Vtac i a __
Nutr s u
t o
S_
ooe a R
RTP B
.u hpmOd &4. ygS&B.
g e
wke3ga Amb{g5,Ohhm. 6 p53l3a~ y1np n
o i
t a
n l
o u i p
t o
a.
p l t 0
ur 0
0 po 2
op 1
0 pe 2
r V.
l N.
d as s
e ui L.
a l09 t
dh C. T i
0 a
a it O
D B
0 t68 m v L
P 00 o31 i i n l
T12 t
d o
. 3 l
s n
S
. 2 o
E i n S
T w
U 3
eo 1
e hh 0
k
- r i
ede n
66 626 6
t s S
t 3
p neh a
2
. a b
95 725 3
ne 0
n adt r
80 1
3 i g 9
r LiO U
45 a
. 90 u
v T
ei 62 ee
. /1 gl
. 71 s
ld ai
. 1 a
gn0 em
. /
i nU l
Y. 6:
B 00 i
n 13 305 6
il R
s Se a
2 ma U
e e n
b 43 430 3
t C. :l l
sa r
75 121 3
eo R
gi i
sl u
14 ht E
nM M ei:
b 1
9 t
M i
cts u
3 e
vl cl y S
1 fh ia 0
er Aua ot rt 7 te Mw ro ah d h 4.
AT tt e
g l
08 169 9
ml SO t
i a
3 ua 3
r 03 433 1
su
. T i H u
1 188 q
o. D e
m R
11 ee Y.
t
. P s
s 00 i h h
A.
a u
L g
~
t t W.
. 4 i :
9 u
o H.
. 3 B
tk 4
o 0 0.hr
)
,n G
cc I
1 e eu g
1 m fr 19T i
ny H.
m ia 9
i ft 64 n
V t4 T e
.l a
oim dm
. n s
N a:
g S. c a
t i mk a
t q
us s
1 nn 0
. 9 iis Uo D
a..
se s
oe a
tg ed
/ : s ein :
.L
- ne l qq rg
/
ri p
. 9
)
t uss ea e
r u
p//
tt l
oo y
7e rbi e
ead
(
. 1m r ais p
pli p
oee en p
t g b
n Pll sme o
e
. /i e hs y00 yi v I
pp eoc e
et g
. 6T v soo T Tti:
i trr 1
lDs doo el l r p
ua n
r npc n6 eu y
.d Dc N
eee ciie
(
i a D i g
nMea A
tPP nMKP s
o asy i a nw R
h a
s u
A gR 2 rkr S Lsah r
g t
i e
I i
s s
t s
O n
tnr f
slg L. il h sie yey yeii A
e i
a o
a R
W D
B N
S
. va t
nlf att actH g
T. at i o wan wcl e
P
. eo w css htu haul I
LT dd gso g Ma V
N C
gii irC id p
s noo He He i 5
- ivv t
t c
a 1
e waa yn yi n
L I
p o bI bm i V
y lee i r f
N T
ltt e
eL P o
A ouu g
g C
e foo a a
h t
RR e
e t
u e l
l u
o h i
i o
R T M
M s
d) 5 e
1 u
I n
m i
tn o
o r
c F
(
3 4
e e
t t
u u
o o
R R
zC:mOgw" >o.ggc5 ~
>wd h
=
-L4RkESAE(Qb' 3fE54h$g3SE' e
F L
r-3 nf.
6.
9 _
5 5
3 9 _
9 _
2 2
2 n
o
- 56 _
i
- 19 _
6 6
3 t
- 89 _
a
- 59 _
3 3
3 l
u p
o 4503 P
3032
- 65 _
0 1223
- 21 _
0 0
1 2
1111
- 38 _
0 n
- 35 _
0 0
9 2
w tttt 1
1 l o a a a a-d ah e
us 9999 l00 t
d 9999 a
a i e
////. - 16 _
t07 m
vg 7777 62 _
5 5
9 o17 i i a 1111
- 83.
T11 t
d e
////
- 13 _
6 6
5 s
nl 6666 E
ii m
e hl 0159 n
60 196 6
t a 0354:
- 26 _
- 11 _
a 2
t 5
5 1
b 98 654 3
no 0001 88 _
r 69 1 21 3
i t 1.
4 4
4 U
44 S
62 ee L
gh 0000 E
at V
e 410 E
ll 361 L61 _
n 63 627 6
i a 1
22 _
2 2
9 a
2 mu Y38 _
b 21 038 3
q T
3 3
2 r
79 231 3
ee I
u 24 h
S b
1 9
tt N
u 3
o e _ 0. N N I E
S 1
f n g
VVNY D
o a _
N 96 _
y e_1 N32 _
_0 4
4 8
l 02 306 9
ma 5
L I13 _
l a
3 um 15C H
6 6
5 r
66 386 1
s i_1 M
29O T
u 1
716 s
IUL I
R 1
ee e.V W
hi t
5 t r a.
51 5 E
o
_N t
G 7. 3 129 9
)
,g A
1 1
6 S
IIU ge.
E91 _
W L5 - _
5 5
4 n..
i nt t a
m iar ASNS I
a oim O
M t
imk
. dco n
p L
a t
q une S
D a..
se s
oor T
l qq rg /
ri P
- 77 _
t uss ea e
t s I
1 1
5 u
p//
tt l
oai NSS 29 _
p oee en p
tl h AA 25.
7 7
6 n
Pll sme o
ut 5GGY I
pp eoc e
ep 1 EER doo ell r p
uon IVVU N
eee ciie Dpo
(
V C
A t PP nMKP NSSR R
h a
s AAAE
_ 07 _
T g
t i
e 6
6 6
U i s
s t
CLLM
_ 52 _
A e
i a
o 2 _
1 1
9 R
W D
B N
2 2
1
_ 00 _
7 7
1 n
5 S15
. 05 _
o I29 8
8 6
i IIU 2
2 2
t a
l 0000 u
p 479 0 _
o 324 8
8 8
P
)
0 0
9 0
d 1
1 2
e 0
u 2
n d
i s.
e tn e.
0, 0
t l
a o
i _
0 0
m c
M _
1 1 s i
(
1 1 e t
g s
a E
4 t
e e_
n a
t l e s
t Veac i
a.
Ntt r s
u t
o S.
uoe a
oTP B
R R
>tg4
- h]. 4d' ySgc.h-E 5
ll
Supplemental Analysesfor Cumulative Environmentalimpacts.
I APPENDIX 3 SELECTED PAGES FROM THE RADTRAN 4 COMPUTER CODE RUNS l
l l
A3-1 NUREG-1437, Addendum 1
Supplemental Analysesfor Cumulative EnvlronmentalImpacts..
ECHO CHECK
&& Edited Mon Jun 21 15:00:18 1999
&& _ North _ route _via_ beltway _with_rx_ life _ extension.
TITLE RADTRAN 4.0 INPUT FORM UNIT DIMEN 31 8 3 10 18 PARM 1.3 2 1 0 PACKAGE' LABGRP SOLID CAS VOLATIL SHIPMENT LABISO CR51 MN54 FESS FE59 C058 C060 KR85 SR89 SR90 Y91 ZR95 NB95 RU103 RU106 SB125 TE125M-TE127 TE127M CS134 CS137 CE141 CE144 PM147.
.EU154 PU238 PU239 PU240 PU241 AM241 CM242 CM244 NORMAL NMODE=1~
9.000E-01 5.000E-02 5.000E-02 8.849E+01 4.025E+01 2.416E+01 4.000E+00 3.100E+00 0.000E+00 1.100E-02 1.000E+00 0.000E+00 0.000E+00 3.000E+01 2.000E+01 0.000E+00 1.000E+02 1.000E+02 2.000E+00 8.000E-02 5.000E-02 8.500E-01 4.700E+02 7.800E+02 2. t100E+ 03 ACCIDENT l
SEVFRC l
NPOP=1 NMODE=1
)
4.62E-01 3.02E-01 1.76E-01 4.03E-02 1.18E-02 6.47E-03 J
5.71E-04' 1.13E-04 NPOP=2 l
NMODE=1 4.35E-01 2.85E-01 2.21E-01 5.06E-02 6.64E-03 1.74E-03 6.72E-05 5.93E-06 NPOP=3~
NMODE=1 5.83E-01 3.82E-01 2.78E-02 6.36E-03 7.42E-04 1.46E-04 1.13E-05 9.94E-07 RELEASE RFRAC GROUP =1 0.00r+00 6.00E-08 2.00E-07 2.00E-06 2.00E-06 2.00E-06 2.00E-05 2.00E-05 GROUP =2 0.00E+00 9.90E-03 3.30E-02 3.90E-01 3.30E-01 3.30E-01
' 6.30E-01 6.30E-01 GROUP =3 0.00E+00 6.00E-06 2.00E-05 2.00E-04 2.00E-04 2.00E-04 2.00E-03 2.00E-03 EOF ISOTOPES
-1 75278 1.00 13.000 1.00 0.00 VEGAS 1 CR51 7.40E-16
-SOLID 2
MN54 4.80E+01 SOLID 2
FESS 3.82E+03 SOLID 2
FES9 3.84E-10 SOLID 2
C058 3.67E-04 SOLID 2
C060
- 1. 2 0 E + 0 4 SOLID 2
KR85 1.96E+04 GAS 10 SR89 1.42E-05 SOLID 2-SR90 2.20E+05-SOLID 2
Y91' 5.81E-04 SOLID 2
ZR95 1.7BE-04 SOLID 2
NB95 1.24E-02 SOLID 2
RU103. 2.40E-08 VOLATIL 7
RU106 4.04E+04.
VOLATIL 7
SB125 5.80E+03 SOLID 2
TE125M 1.63E+02 SOLID 2
TE127 2.09E-01 SOLID 2
TE127M 2.12E-01
-SOLID 2
NUREG-1437, Addendum 1 A3-2
Supplemental Analysesfor Cumulative EnvironmentalImpacts..
CS134 1.09E+05 VOLATIL 7
CS137 3.21E+05 VOLATIL 7
CE141 2.71E-11 SOLID 2
CE144-' 2.21E+04 SOLID 2
PM147 9.17E+04 SOLID 2
EU154 1.77E+04 SOLID 2
PU238 1.72E+04 SOLID 2
PU239 7.09E+02 SOLID
'2 PU240 1.32E+03 SOLID 2
PU241 2.88E+05 SOLID 2
AM241' 3.17E+03 SOLID 2 CM242 1.14E+02 SOLID 2
CM244 -2.18E+04 SOLID 2 LINK 1 1.84E+02 8.80E+01 3.80E+00 4.70E+02 2.25E-07 R 1 LINK 1 2.30E+01 4.00E+01 4.53E+02 7.80E+02 2.25E-07 S 1 LINK 1 1.22E+01 2.40E+01 2.51E+03 2.80E+03 3.60E-07 U 1 PKGSIZ VEGAS 1 5.00 EOF A3-3 NUREG-1437, Addendum I
. Supplemental Analysesfor Cumulative EnvironmentalImpacts...
INCIDENT-FREE
SUMMARY
INCIDENT-FREE POPULATION EXPOSURE IN PERSON-REM PASSENGR CREW HANDLERS OFF LINK ON LINK STOPS STORAGE' TOTALS LINK 1 0.00E+00 1.27E+03 0.00E+00 1.74E+00 1.13E+02 1.60E+03 0.00E+00 2.99E+03 LINK 2 0.00E+00 3.49E+02 0.00E+00 4.97E+01 1.19E+02 7.91E+02 0.00E+00 1.31E+03 LINK 3 0.00E+00 3.09E+0? 0.00E+00 5.04E+00 6.68E+02 7.91E+02 0.00E+00 1.77E+03 RURAL 0.00E+00 1.27E+03 0.00E.00 1.74E+00 1.13E+02 1.60E+03 0.00E+00 2.99E+03 SUBURB 0.00E+00 3.49E+02 0.00E+00 4.97E+01 1.19E+02 7.91E+02 0.00E+00 1.31E+03 URBAN 0.00E+00 3.09E+02 0.00E+00 5.04E+00 6.68E+02 7.91E+02 0.00E+00 1.77E+03 TOTALS: 0.00E+00 1.93E+03 0.00E+00 5.65E+01 9.00E+02 3.18E+03 0.00E+00 6.07E+03 i
MAXIMUM INDIVIDUAL IN-TRANSIT DOSE LINK 1 4.03E-02 REM LINK 2 ~4.03E-02 REM j
LINK 3 4.03E-02 REM EXPECTED VALUES OF POPULATION RISK IN PERSON-REM GROUND INHALED RESUSPD CLOUDSH
- INGESTION TOTAL LINK 1 1.56E+01 2.37E-01 6.68E-01 7.41E-04 0.00E+00 1.65E+01 LINK-2 2.35E+02 3.46E+00 9.78E+00 1.12E-02 0.00E+00 2.49E+02 LINK 3 1.83E+02 2.35E+00 6.65E+00 7.46E-03 0.00E+00 1.92E+02 RURAL 1.56E+01 2.37E-01 6.68E-01 7.41E-04 0.00E+00 1.65E+01 SUBURB 2.35E+02 3.46E+00 9.78E+00 1.12E-02 0.00E+00 2.49E+02 URBAN
-1.83E+02 2.35E+00 6.65E+00 7.46E-03 0.00E+00 1.92E+02 1
TOTALS:
4.34E+02 6.05E+00 1.71E401 1.94E-02 0.00E+00 4.57E+02
- NOTE THAT INGESTION RISK IS A SOCIETAL RISK; THE USER MAY WISH TO TREAT THIS VALUE SEPARATELY.
l NUREG-1437, Addendum 1 A3-4
p Supplemental Analysesfor Cumulative EnvironmentalImpacts...
ECHO CHECK
&& Edited Mon Jun 21 15:19:54 1999
&& _ North _. route _via_ beltway _without_rx_ life _ extension _
' TITLE RADPRAN 4.0 INPUT FORM UNIT.
DIMEN 31 8 3 10 18 PARM 1 3 2 1 0 PACKAGE LABGRP SOLID
= GAS VOLATIL SHIPMENT LABISO CR51 MN54 FESS FE59 C058-C060 KR85
'SR89 SR90.
Y91 ZR95 NB95 RU103 RU106 SB125 TE125M TE127 TE127M CS134 CS137 CE141 CE144-PM147 EU154 PU238 PU239 PU240 PU241 AM241 CM242 CM244 NORMAL NMODE*1 9.000E-01 5.000E-02 5.000E-02 8.849E+01 4.02SE+01 2.416E+01 4.000E+00 '3.100E+00 0.000E+00 1.100E-02 1.000E+00 0.000E+00 0.000E+00 3.000E+01 2.000E+01 0.000E+00 1.000E+02 1.000E+02 2.000E+00 8.000E-02 5.000E-02 8.500E-01 4.700E+02 7.800E+02 2.800E+03 ACCIDENT SEVFRC NPOP=1 NMODE=1 4.62E-01 3.02E-01 1.76E-01 4.03E-02 1.18E-02 6.47E-03 5.71E-04. 1.13E-04' NPOPs2' NMODE=1 4.35E-01 2.85E-01 2.21E-01 5.06E-02 6.64E-03 1.74E-03 6.72E-05 5.93E-06 NPOP=3 NMODE=1 5.83E-01 3.82E-01 2.78E-02 6.36E-03 7.42E-04 1.46E-04 1.13E-05 9.94E-07 RELEASE RTRAC GROUP =1 0.00E+00 6.00E-08 2.00E-07 2.00E-06 2.00E-06 2.00E-06 2.00E-05 2.00E-05 GROUP =2 0.00E+00 9.90E-03 3.30E-02 3.90E-01 3.30E-01 3.30E-01 6.30E-01 6.30E-01 GROUP =3 0.00E+00' 6.00E-06 2.00E-05 2.00E-04 2.00E-04 2.00E-04 2.00E-03 2.00E-03 EOF ISOTOPES
-1 50185 1.00 13.000 1.00 0.00 VEGAS 1 CR51 7,40E-16 SOLID 2
MN54 4.80E+01 SOLID 2
FESS 3.82E+03 SOLID 2
FE59 3.84E-10 SOLID 2 C058 3.67E-04 SOLID 2
C060 1.20E+04 SOLID 2 KR85 1.96E+04 GAS 10 SR89 '1.42E-05 SOLID 2 SR90 2.20E+05 SOLID 2 Y91 5.81E-04 SOLID 2
.ZR95 1,78E-04' SOLID 2 NB95 1.24E-02 SOLID 2
RU103 2.40E VOLATIL 7
l RU106 4.04E+04 VOLATIL 7
i SB125 5.80E+03 SOLID' 2 TE125M 1.63E+02 SOLID 2
TE127 2.09E-01 SOLID 2
TE127M 2.12E-01 SOLID 2
CS134 1.09E+05 VOLATIL 7
CS137 3.21E+05 VOLATIL 7
A3 5 NUREG-1437, Addendum I
N Supplemental Analysesfor Cumulative Environmentalimpacts...
'~
CE141 2.71E-11 SOLID 2
CE144 2.21E+04 SOLID 2
PM147 9.17E+04
. SOLID. 2 EU154 1.77E+04
' SOLID 2
PU238 1.72E+04 SOLID 2
PU239 7.09E+02 SOLID 2
PU240 1.32E+03 SOLID 2
PU241 2.88E+05 SOLID 2
AM241 - 3.17E+03 SOLID 2
CM242 1.14E+02 SOLID 2
CM244 2.18E+04 SOLID 2
LINK l' 1.84E+02 8.80E+01 3.80E+00 4.70E+02 2.25E-07 R 1 LINK 1 2.30E+01 4.00E+01 4.53E+02 7.80E+02 2.25E-07 S 1 LINK 1 1.22E+01 2.40E+01 2.51E+03 2.80E+03 3.60E-07 U 1 PKGSIZ VECAS1 5.00 EOF 4
i i
NUREG-1437. Addendum 1 A3-6
Supplemental Analysesfor Cumulative Environmental Impacts...
INCIDENT-FREE
SUMMARY
INCIDENT-FREE POPULATION EXPOSURE IN PERSON-REM
.PASSENGR CREW HANDLERS OFF LINK ON LINK STOPS STORAGE TOTALS LINK 1 0.00E+00 8.46E+02 0.00E+00 1.16E+00 7.53E+01 1.07E+03 0.00E+00 1.99E+03 LINK 2 0.00E+00 2.33E+02 0.00E+00 3.32E+01 7.94E+01 5.28E+02 0.00E+00 8.73E+02 LINK 3 0.00E+00 2.06E+02 0.00E+00 3.36E+00 4.45E+02 5.28E+02 0.00E+00 1.18E+03 RURAL 0.00E+00 8.46E+02 0.00E+00 1.16E+00 7.53E+01 1.07E+03 0.00E+00 1.99E+03 SUBURB 0.00E+00 2.33E+02 0.00E+00 3.32E+01 7.94E+01 5.28E+02 0.00E+00 8.73E+02 URBAN 0.00E+00 2.06E+02 0.00E+00 3.36E+00 4.45E+02 5.28E+02 0.00E+00 1.18E+03 TOTALS: 0.00E+00 1.28E+03 0.00E+00 3.77E+01 6.00E+02 2.12E+03 0.00E+00 4.05E+03 l
i-l MAXIMUM INDIVIDUAL IN-TRANSIT DOSE l-LINK 1 2.69E-02 REM
\\
LINK 2 2.69E-02 REM LINK 3 2.69E-02 REM EXPECTED VALUES OF POPULATION RISK IN PERSON-REM GROUND INHALED RESUSPD CLOUDSH.* INGESTION TOTAL LINK 1 1.04Et01 1.58E-01 4.46E-01 4.94E-04 0.00E+00 1.10E+01 LINK 2 1.57E+02 2.31E+00 6.52E+00 7.46E-03 0.00E+00- 1.66E+02 LINK 3 1.22E+02 1.57E+00 4.43E+00 4.97E-03 0.00E+00 1.28E+02 RURAL 1.04E+01 1.58E-01 4.46E-01 4.94E-04 0.00E+00 1.10E+01 SUBURB 1.57E+02 2.31E+00 6.52E+00 7.46E-03 0.00E+00 1.66E+02 URBAN 1.22E+02 1.57E+00 4.43E+00 4.97E-03 0.00E+00 1.28E+02 TOTALS:
2.90E+02 4.03E+00 1.14E+01 1.29E-02 0.00E+00 3.05E+02
- NOTE THAT INGESTION RISK IS A SOCIETAL RISKt THE USER MAY WISH TO TREAT THIS VALUE SEPARATELY.
A3-7 NUREG-1437, Addendum 1
Supplemental Analysesfor Cumulative Environmentalimpacts...
ECHO CHECK
&& Edited Mon Jun 21 15:23:48 1999
&& _ North _ route _via_ city _with rx_ life _ extension _.
TITLE o.ADTRAN 4.0 INPUT FORM UNIT DIMEN 31 8 3 10 18 PARM 1 3 2 1 0 PACKAGE LABGRP SOLID GAS VOLATIL SHIPMENT LABISO CR51 MN54 FESS FE59 C058 CO60 KR85 SR89 SR90 Y91 ZR95 NB95 RU103 RU106 SB125 TE125M TE127 TE127M CS134 CS137 CE141 CE144 PM147 EU154 PU238 PU239 PU240 PU241 AM241 CM242 CM244 NORMAL NMODE=1 9.000E-01 5.000E-02 5.000E-02 8.849E+01 4.025E+01 2.416E+01 4.000E+00 3.100E+00 0.000E+00 1.100E-02 1.000E+00 0.000E+00 0.000E+00 3.000E+01 2.000E+01 0.000E+00 1.000E+02 1.000E+02 2.000E+00 8.000E-02 5.000E-02 8.500E-01 4.700E+02 7.800E+02 2.800E+03 ACCIDENT SEVFRC NPOP=1 NMODEa1 4.62E-01 3.02E-01 1.76E-01 4.03E-02 1.18E-02 6.47E-03 5.71E-04 1.13E-04 NPOP=2 NMODE=1 4.35E-01 2.85E-01 2.21E-01 5.06E-02 6.64E-03 1.74E-03 6.72E-05 5.93E-06 NPOP=3 NMODE=1 5.83E-01 3.82E-01 2.78E-02 6.36E-03 7.42E-04 1.46E-04 1.13E-05 9.94E-07 RELEASE RFRAC CROUP =1 0.00E+00 6.00E-08 2.00E-07 2.00E-06 2.00E-06 2.00E-06 2.00E-05 2.00E-OS GROUP =2 0.00E+00 9.90E-03 3.30E-02 3.90E-01 3.30E-01 3.30E-01 6.30E-01 6.30E-01 GROUP =3 0.00E+00 6.00E-06 2.00E-05 2.00E-04 2.00E-04 2.00E-04 2.00E-03 2.00E-03 E01 ISOTOPES
-1 75278 1.00 13.000 1.00 0.00 VEGAS 1 CR51 7.40E-16 SOLID 2
Kd34 4.80E+01 SOLID 2
FE55 3.82E+03 SOLID 2
FES9 3.84E-10 SOLID 2
C058 3.67E-04 SOLID 2
CO60 1.20E+04 EOLID 2
KR85 1.96E+04 GAS 10 SR89 1.42E-05 SOLID 2
SR90 2.20E+05 SOLID 2
Y91 5.81E-04 SOLID 2
ZR95 1.78E-04 SOLID 2
NB95 1.24E-02 SOLID 2
RU103 2.40E-08 VOLATIL 7
RU106 4.04E+04 VOLATIL 7
SB125 5.80E+03 SOLID 2
TE125M 1.63E+02 SOLID 2
TE127 2.09E-01 SOLID 2
~~
TE127M 2.12E-01 SOLID 2
CS134 1.09E+05 VOLATIL 7
CS137 3.21E+05 VOLATIL 7
NUREGl437, Addendum 1 A3-8 A_
Supplemental Analysesfor Cumulative EnvironmentalImpacts..
CE141 2.71E-11 SOLID 2
CE144 2.21E+04 SOLID 2
PM147 9.17E+04 SOLID 2
EU154 1.77E+04 SOLID 2
44 PU238 1.72E+04 SOLID 2
PU239 7.09E+02 SOLID 2 PU240 1.32E+03 SOLID 2
PU241 2.88E+05 SOLID 2
AM241 3.17E+03 SOLID 2 CM242 1.14E+02 SOLID 2
CM244 2.18E+04 SOLID 2
LINK 1 1.84E+02 8.80E+01 3.90E+00 4.70E+02 2.25E-07 R 1 LINK 1 3.14E+01 4.00E+01 4.64E+02 7.80E+02 2.25E-07 S 1 LINK 1 1.50E+01 2.40E+01 2.53E+03 2.80E+03 3.60E-07 U 1 PKGSIZ VEGAS 1 5.00 EOF A3-9 NUREG-1437, Addendum I i
~'
6 m
Supplemental Analysesfor Cumulative EnvironmentalImpacts...
INCIDENT-FRE.E
SUMMARY
INCIDENT-FREE POPULATION EXPOSURE IN PERSON-REM PASSENGR CREW HANDLERS OFF LINK ON LINK STOPS STORAGE TOTALS LINK 1 0.00E+00 1.27E+03 0.00E+00 1.79E+00 1.13E+02 1.60E+03 0.00E+00 2.99E+03 LINK 2 0.00E+00 4.77E+02 0.00E+00 6.95E+01 1.63E+02 7.91E+02 0.00E+00 1.50E+03 LINK 3 0.00E+00 3.79E+02 0.00E+00 6.25E+00 8.21E+02 7.91E+02 0.00E+00 2.00E+03 RURAL 0.00E+00 1.27E+03 0.00E+00 1.79E+00 1.13E+02 1.60E+03 0.00E+00 2.99E+03 SUBURB 0.00E+00 4.77E+02 0.00E+00 6.95E+01 1.63E+02 7.91E+02 0.00E+00 1.50E+03 URBAN 0.00E+00 3.79E+02 0.00E+00 6.2SE+00 8.21E+02 7.91E+02 0.00E+00 2.00E+03 TOTALS: 0.00E+00 2.13E+03 0.00E+00 7.76E+01 1.10E+03 3.18E+03 0.00E+00 6.48E+03 MAXIMUM INDIVIDUAL IN-TRANSIT DOSE LINK 1 4.03E-02 REM LINK 2 4.03E-02 REM LINK 3 4.03E-02 REM EXPECTED VALUES OF POPULATION RISK IN PERSON-REM GROUND INHALED RESUSPD CLOUDSH
- INGESTION TOTAL LINK 1 1.60E+01 2.43E-01 6.86E-01 7.60E-04 0.00E+00 1.69E+01 LINK 2 3.29E+02 4.84E+00 1.37E+01 1.56E-02 0.00E+00 3.48E+02 LINK 3 2.27E+02 2.91E+00 8.24E+00 9.24E-03 0.00E+00 2.38E+02 RURAL 1.60E+01 2.43E-01 6.86E-01 7,60E-04 0.00E+00 1.69E+01 SUBURB 3.29E+02 4.84E+00 1.37E+01 1.56E-02 0.00E+00 3.48E+02 URBAN 2.27E+02 2.91E+00 8.24E+00 9.24E-03 0.00E+00 2.38E+02 TOTALS:
5.72E+02 7.99E+00 2.26E+01 2.56E-02 0.00E+00 6.03E+02
- NOTE THAT INGESTION RISK IS A SOCIETAL RISK; THE USER MAY WISH TO TREAT THIS VALUE SEPARATELY.
NUREG-1437, Addendum i A3-10 l
Supplemental Analysesfor Cumulative EnvironmentalImpacts..
ECHO CHECK
&& Edited Mon Jun 21 15:25:58 1999
&& _ North _ route _via_ city _without_rx_ life _ extension.
TITLE RAIYTRAN 4.0 INPUT FORM UNIT DIMEN 31 8 3 10 18 PARM 1 3 2 1 0 PACKAGE LABGRP SOLID GAS VOLATIL SHIPMENT LABISO CR51 HN54 FESS FE59 C058 CO60 KR85 SR89 SR90 Y91 ZR95 NB95 RU103 RU106 SB125 TE125M TE127 TE127M CS134 CS137 CE141 CE144 PM147 EU154 PU238 PU239 PU240 PU241 AM241 CM242 CM244 NORMAL NMODE*1 9.000E-01 5.000E-02 5.000E-02 8.849E+01 4.025E+01 2.416E+01 4.000E+00 3.100E+00 0.000E+00 1.100E-02 1.000E+00 0.000E+00 0.000E+00 3.000E+01 2.000E+01 0.000E+00 1.000E+02 1.000E+02 2.000E+00 8.000E-02 5.000E-02 8.500E-01 4.700E+02 7.800E+02 2.800E+03 ACCIDENT SEVFRC NPOPs1 NMODE=1 4.62E-01 3.02E-01 1.76E-01 4.03E-02 1.38E-02 6.47E-03 5.71E-04 1.13E-04 NPOP=2 NMODE=1 4.35E-01 2.85E-01 2.21E-01 5.06E-02 6.64E-03 1.74E-03 6.72E-05 5.93E-06 NPOP=3 NMODE=1 5.83E-01 3.82E-01 2.78E-02 6.36E-03 7.42E-04 1.46E-04 1.13E-05 9.94E-07 RELEASE RFRAC GROUP =1 0.00E+00 6.00E-08 2.00E-07 2.00E-06 2.00E-06 2.00E-06 2.00E-05 2.00E-05 GROUP =2 0.00E+00 9.90E-03 3.30E-02 3.90E-01 3.30E-01 3.30E-01 6.30E-01 6.30E-01 GROUP =3 0.00E+00 6.00E-06 2.00E-05 2.00E-04 2.00E-04 2.00E-04 2.00E-03 2.00E-03 EOF ISOTOPES
-1 50185 1.00 13.000 1.00 0.00 VEGAS 1 CRS1 7.40E-16 SOLID 2
MN54 4.00E+01 SOLID 2
FESS 3.82E+03 00 LID 2
FE59 3.84E-10 SOLID 2
C058 3.67E-04 SOLID 2
CO60 1.20E+04 SOLID 2
KR85 1.96E+04 GAS 10 SR89 1.42E-05 SOLID 2
SR90 2.20E+05 SOLID 2
Y91 5.81E-04 SOLID 2
ZR95 1.78E-04 SOLID 2
NB95 1.24E-02 SOLID 2
RU103 2.40E-08 VOLATIL 7
RU106 4.04E+04 VOLATIL 7
SB125 5.80E+03 SOLID 2
TE125M 1.63E+02 SOLID 2
TE127 2.09E-01 SOLID 2
TE127M 2.12E-01 SOLID 2
CS134 1.09E+05 VOLATIL 7
CS137 3.21E+05 VOLATIL 7
A3-11 NUREG-1437, Addendum 1 I
WI
Supplemental Analysesfor Cumulative EnvironmentalImpacts...
CE141-2.71E-11 SOLID 2
CE144 2.21E+04 SOLID 2
PM147 9.17E+04 SOLID 2
EU154 1.77E+04 SOLID 2
PU238 1.72E+04 SOLID
'2 PU239 7.09E+02 SOLID 2
PU240 1.32E+03 SOLID 2
PU241-2.88E+05 SOLID 2
AM241 3.17E+03 SOLID 2
CM242 1.14E+02 SOLID 2
.CM244 2.18E+04 SOLID 2
LINK 1 1.84E+02 8.80E+01 3.90E+00 4.70E+02 2.25E-07 R 1 LINK 1 3.14E+01 4.00E+01 4.64E+02 7.80E+02 2.25E-07 S 1 LINK 1 1.50E+01 2.40E+01 2.53E+03 2.80E+03 3.60E-07 U 1 PKGSIZ VEGAS 1 5.00
- COP NUREG-1437, Addendum 1 A3-12 '
Supplemental Analysesfor Cumulative Environmentalimpacts.
INCIDENT-FREE
SUMMARY
INCIDENT-FREE POPULATION EXPOSURE IN PERSON-REM PASSENGR CREW HANDLERS OFF LINK ON LINK STOPS STORAGE TOTALS LINK 1 0.00E+00 8.46E+02 0.00E+00 1.19E+00 7.53E+01 1.07E,03 0.00E+00 1.99E+03 LINK 2 0.00E+00 3.18E+02 0.00E+00 4.64E+01 1.08E+02 5.28E+02 0.00E+00 1.00E+03 LINK 3 0.00E+00 2.53E+02 0.00E+00 4.16E+00 5.47E+02 5.28E+02 0.00E+00 1.33E+03 RURAL 0.00E+00 8.46E+02 0.00E+00 1.19E+00 7.53E+01 1.07E+03 0.00E+00 1.99E+03 SUBURB 0.00E+00 3.18E+02 0.00E+00 4.64E+01 1.00E+02 5.28E+02 0.00E+00 1.00E+03 URBAN 0.00E+00 2.53E+02 0.00E+00 4.16E+00 5.47E+02 5.28E+02 0.00E+00 1.33E+03 TOTALS: 0.00E+00 1.42E+03 0.00E+00 5.17E+01 7.31E+02 2.12E+03 0.00E+00 4.32E+03 MAXIMUM INDIVIDUAL IN-TRANSIT DOSE LINK 1 2.69E-02 REM LINK 2 2.69E-02 REM LINK 3 2.69E-02 REM A3-13 NUREG-1437, Addendum 1
Supplemental Analysesfor Cumulative EnvironmentalImpacts.
EXPECTED VALUES OF POPULATION RISK IN PERSON-REM CROUND INHALED RESUSPD CLOUDSH
- INGESTION TOTAL LINK 1 1.07E+01 1.62E-01 4.57E-01 5.07E-04 0.00E+00 1.13E+01 LINK 2 2.19E+02 3.22E+00 9.11E+00 1.04E-02 0.00E+00 2.32E+02 LINK 3 1.51E*02 1.94E+00 5.49E+00 6.16E-03 0.00E+00 1.59E+02 RURAL 1.07E+01 1.62E-01 4.57E-01 5.07E-04 0.00E+00 1.13E+01 SUBURB 2.19E+02 3.22E+00 9.11E+00 1.04E-02 0.00E+00 2.32E+02 URBAN 1.51E+02 1.94E+00 5.49E+00 6.16E-03 0.00E+00 1.59E+02 TOTALS:
3.82E+02 5.33E+00 1.51E+01 1.71E-02 0.00E+00 4.02E+02
- NOTE THAT INGESTION RISK IS A SOCIETAL RISKS THE USER MAY WISH TO TREAT THIS VALUE SEPARATELY.
NUREG-1437, Addendum 1 A3-14
Supplemental Analysesfor Cumulative EnvironmentalImpacts.
ECHO CHECK
&& Edited Mon Jun 21 15:43:05 1999
&& _ South _ route _via_ city with_rx life _ extension _
TITLE RADTRAN 4.0 INPUT FORM UNIT DIMEN 31 8 3 10 18 PARM 1 3 2 1 0 PACKAGE LABCRP SOLID GAS VOLATIL SHIPMENT LABISO CR$1 MN54 FESS FE59 C058 CO60 KR85 SR89 SR90 Y91 ZR95 NB95 RU103 RU106 58125 TE125M TE127 TE127M CS134 CS137 CE141 CE144 PM147 EU154 PU238 PU239 PU240 PU241 AM241 CM242 CM244 NORMAL NMODE=1 9.000E-01 5.000E-02 5.000E-02 8.849E+01 4.025E+01 2.416E+01 4.000E+00 3.100E+00 0.000E+00 1.100E-02 1.000E+00 0.000E+00 0.000E+00 3.000E+01 2.000E+01 0.000E+00 1.000E+02 1.000E+02 2,000E+00 8.000E-02 5.000E-02 8.500E-01 4.700E+02 7.800E+02 2.800E+03 ACCIDENT SEVFRC NPOP=1 NMODE=1 4.62E-01 3.02E-01 1.76E-01 4.03E-02 1.18E-02 6.47E-03 5.71E-04 1.13E-04 NPOP=2 NMODE=1 4.35E-01 2.85E-01 2.21E-01 5.06E-02 6.64E-03 1.74E-03 6.72E-05 5.93E-06 NPOP=3 t@40DE=1 5.83E-01 3.82E-01 2.78E-02 6.36E-03 7.42E-04 1.46E-04 1.13E-05 9.94E-07 RELEASE RFRAC GROUP =1 0.00E+00 6.00E-08 2.00E-07 2.00E-06 2.00E-06 2.00E-06 2.00E-05 2.00E-05 GROUPS 2 0.00E+00 9.90E-03 3.30E-02 3.90E-01 3.30E-01 3.30E-01 6.30E-01 6.30E-01 GROUPS 3 0.00E+00 6.00E-06 2.00E-05 2.00E-04 2.00E-04 2.00E-04 2.00E-03 2.00E-03 EOF ISOTOPES
-1 75278 1.00 13.000 1.00 0.00 VEGAS 1 CRS1 7.40E-16 SOLID 2
MN54 4.80E+01 SOLID 2
FE55 3.82E+03 SOLID 2
FE59 3.84E-10 SOLID 2
C058 3.67E-04 SOLID 2
CO60
- 1. 2 0 E+ 0 4 SOLID 2
KR85 1.96E+04 GAS 10 SR89 1.42E-05 SOLID 2
SR90 2.20E+05 SOLID 2
Y91 5.81E-04 SOLID 2
ZR95 1.78E-04 SOLID 2
NB95
- 1. 2 4 E-02 SOLID 2
RU103 2.40E-08 VOLATIL 7
RU106 4.04E+04 VOLATIL 7
SB125 5.80E+03 SOLID 2
TE125M 1.63E+02 SOLID 2
TE127 2.09E-01 SOLID 2
TE127M 2.12E-01 SOLID 2
CS134 1.09E+05 VOLATIL 7
CS137 3.21E+05 VOLATIL 7
A3-15 NUREG-1437, Addendum I
Supplemental Analysesfor Cumulative EnvironmentalImpacts...
CE141 2.71E-11 SOLID 2
CE144 2.21E+04 SOLID 2
PM147 9.17E+04' SOLID 2 EU154 1.77E+04 SOLID 2
PU238 1.72E+04 SOLID 2
PU239 7.09E+02 SOLID 2 PU240 1.32E+03 SOLID 2
PU241. 2.88E+05 SOLID 2
AM241 3.17E+03 SOLID 2
CM242 1.'14 E+ 02 SOLID 2
CM244 2.18E+04 SOf.ID 2
LINK 1 1.18E+02 8.80E+01 6.2(lE+00 4.70E+02 2.25E-07 R 1 LINK 1 2.51E+01 4.00E+01 3.71E+02 7.80E+02 2.25E-07 S 1 LINK 1 2.27E+01 2.40E+01 3.21E+03 2.80E+03 3.60E-07 U 1 PKCSIZ VEGAS 1 5.00 EOF NUREG-1437, Addendum I A3-16
Supplemental Analysesfor Cumulative EnvironmentalImpacts...
I.NCIDENT.-FREE
SUMMARY
INCIDENT-FREE POPULATION EXPOSURE IN PERSON-REM PASSENGR CREW HANDLERS OFF LINK ON LINK STOPS STORAGE TOTALS LINK 1 0.00E+00 8.14E+02 0.00E+00 1.82E+00 7.24E+01 1.03E+03 0.00E+00 1.92E+03 LINK 2 0.00E+00 3.81E+02 0.00E+00 4.44E+01 1.30E+02 7.91E+02 0.00E+00 1.35E+03 LINK 3 0.00E+00 5.74E+02 0.00E+00 1.20E+01 1.24E+03 7.91E+02 0.00E+00 2.62E+03 RURAL 0.00E+00 8.14E+02 0.00E+00 1.82E+00 7.24E+01 1.03E+03 0.00E+00 1.92E+03 SUBURB 0.00E+00 3. 81E+02 0.00E+00 4.44 E+01 1.30E+02 7.91E+02 0.00E+00 1.35E+03
)
URBAN 0.00E+00 5.74E+02 0.00E+00 1.20E+01 1.24E+03 7.91E+02 0.00E+00 2.62E+03 j
TOTALS: 0.00E+00 1.77E+03 0.00E+00 5.83E+01 1.44E+03 2.61E+03 0.00E+00 5.88E+03 MAXIMUM INDIVIDUAL IN-TRANSIT DOSE LINK 1 4.03E-02 REM LINK 2 4.03E-02 REM LINK 3 4.03E-02 REM EXPECTED VALUES OF POPULATION RISK IN PERSON-REM GROUND INHALED RESUSPD CLOUDSH ' INGESTION TOTAL LINK 1 1.63E+01 2.47E-01 6.99E-01 7.75E-04 0.00E+00 1.73E+01 LINK 2 2.10E+02 3.09E+00 8.74E+00 1.00E-02 0.00E+00 2.22E+02 LINK 3 4.36E+02 5.60E+00 1.58E+01 1.78E-02 0.00E+00 4.58E+02 RURAL 1.63E+01 2.47E-01 6.99E-01 7.75E-04 0.00E+00 1.73E+01 SUBURB 2.10E+02 3.09E+00 8.74E+00 1.00E-02 0.00E+00 2.22E+02 URBAN 4.36E+02 5.60E+00 1.58E+01 1.78E-02 0.00E+00 4.58E+02 TOTALS:
6.63E+02 8.94E+00 2.53E+01 2.85E-02 0.00E+00 6.97E+02
- NOTE THAT INGESTION RISK IS A SOCIETAL RISKt THE USER MAY WISH TO TREAT THIS VALUE SEPARATELY.
A3-17 NUREG-1437, Addendum I
Supplemental Analysesfor Cumulative EnvironmentalImpacts..
ECHO CHECK
&& Edited Mon Jun 21 15:45:28 1999
&& _ South _ route _via city _without_rx_ life _ extension.
TITLE RArrrRAN 4.0 INPUT FORM UNIT DIMEN 31 8 3 10 18 PARM 1 3 2 1 0 PACKAGE LABCRP SOLID GAS VOLATIL SHIPMENT LABISO CR51 MN54 FESS FE59 C058 CO60 KR85 SR89 SR90 Y91 ZR95 NB95 RU103 RU106 SB125 TE125M TE127 TE127M CS134 CS137 CE141 CE144 PM147 EU154 PU238 PU239 PU240 PU241 AM241 CM242 CM244 NORMAL NMODE=1 9.000E-01 5.000E-02 5.000E-02 8.849E+01 4.025E+01 2.416E+01 4.000E+00 3.100E+00 0.000E+00 1.100E-02 1.000E+00 0.000E+00 0.000E+00 3.000E+01 2.000E+01 0.000E+00 1.000E+02 1.000E+02 2.000E+00 8.000E-02 5.000E-02 8.500E-01 4.700E+02 7.800E+02 2.800E+03 ACCIDENT SEVFRC NPOPs1 NMODEs1 4.62E-01 3.02E-01 1.76E-01 4.03E-02 1.18E-02 6.47E-03 5.71E-04 1.13E-04 NPOP=2 NMODE=1 4.35E-01 2.85E-01 2.21E-01 5.06E-02 6.64E-03 1.74E-03 6.72E-05 5.93E-06 NPOPs3 NMODEs1 5.83E-01 3.82E-01 2.78E-02 6.36E-03 7.42E-04 1.46E-04 1.13E-05 9.94E-07 RELEASE RFRAC GROUPS 1 0.00E+00 6.00E-08 2.00E-07 2.00E-06 2.00E-06 2.00E-06 2.00E-05 2.00E-05 GROUPS 2 0.00E+00 9.90E-03 3.30E-02 3.90E-01 3.30E-01 3.30E-01 6.30E-01 6.30E-01 GROUPS 3 0.00E+00 6.00E-06 2.00E-05 2.00E-04 2.00E-04 2.00E-04 2.00E-03 2.00E-03 EOF ISOTOPES
-1 50185 1.00 13.000 1.00 0.00 VEGAS 1 CR51 7.40E-16 SOLID 2
MN54 4.80E+01 SOLID 2
FE55 3.82E+03 SOLID 2
FE59 3.84E-10 SOLID 2
C058 3.67E-04 SOLID 2
CO60 1.20E+04 SOLID 2
KR85 1.96E+04 GAS 10 SR89 1.42E-05 SOLID 2
SR90 2.20E+05 SOLID 2
Y91 5.81E-04 SOLID 2
ZR95 1.78E-04 SOLID 2
NB95 1.24E-02 SOLID 2
RU103 2.40E-08 VOLATIL 7
RU106 4.04E+04 VOLATIL 7
SB125 5.80E+03 SOLID 2
TE125M 1.63E+02 SOLID 2
TE127 2.09E-01 SOLID 2
TE127M 2.12E-01 SOLID 2
CS134 1.09E+05 VOLATIL 7
CS137 3.21E+05 VOLATIL 7
NUREG-1437 Addendum 1 A3-18
Supplemental Analysesfor Cumulative EnvironmentalImpacts.
CE141 2.71E-11 SOLID 2
CE144 2.21E+04 SOLID 2
PM147 9.17E+04 SOLID 2
EU154 1.77E+04 SOLID 2
PU238 1.72E+04 SOLID 2
PU239 7.09E+02 SOLID 2
PU240 1.32E+03 SOLID 2
PU241 2.88E+05 SOLID 2
AM241 3.17E+03 SOLID 2
CM242 1.14E+02 SOLID 2
CM244 2.18E+04 SOLID 2
LINK 1 1.18E+02 8.80E+01 6.20E+00 4.70E+02 2.2SE-07 R 1 LINK 1 2.51E+01 4.00E+01 3.71E+02 7.80E+02 2.25E-07 S 1 LINK 1 2.27E+01 2.40E+01 3.21E+03 2.POE+03 3.60E-07 U 1 PKGSIZ VEGAS 1 5.00 Eor A3-19 NUREG-1437, Addendum 1
Supplemental Analysesfor Cumulative EnvironmentalImpacts.
INCIDENT-FREE
SUMMARY
INCIDENT-FREE POPULATION EXPOSURE IN PERSON-REM PASSENGR CREW HANDLERS OFF LINK ON LINK STOPS STORAGE TOTALS LINK 1 0.00E+00 5.43E+02 0.00E+00 1.22E+00 4.83E+01 6.85E+02 0.00E+00 1.28E+03 LINK 2 0.00E+00 2.54E+02 0.00E+00 2.96E+01 8.67E+01 5.28E+02 0.00E+00 8.98E+02 LINK 3 0.00E+00 3.83E+02 0.00E+00 8.00E+00 8.28E+02 5.28E+02 0.00E+00 1.75E+03 RUhAL 0.00E+00 5.43E+02 0.00E+00 1.22E+00 4.83E+01 6.85E+02 0.00E+00 1.28E+03 SUBURB 0.00E+00 2.54E+02 0.00E+00 2.96E+01 8.67E+01 5.28E+02 0.00E+00 8.98E+02 URBAN 0.00E+00 3.83E+02 0.00E+00 8.00E+00 8.28E+02 5.28E+02 0.00E+00 1.75E+03 TOTALS: 0.00E+00 1.18E+03 0.00E+00 3.88E+01 9.63E+02 1.74E+03 0.00E+00 3.92E+03 MAXIMUM INDIVIDUAL IN-TRANSIT DOSE LINK 1 2.69E-02 REM LINK 2 2.69E-02 REM LINK 3 2.69E-02 REM EXPECTED VALUES OF POPULATION RISK IN PERSON-REM GROUND INHALED RESUSPD CLOUDSH
- INGESTION TOTAL LINK 1 1.09E+01 1.65E-01 4.66E-01 5.17E-04 0.00E+00 1.15E+01 LINK 2 1.40E+02 2.06E+00 5.83E+00 6.67E-03 0.00E+00
- 1. 4 8 E+ 02 LINK 3 2.91E+02 3.73E+00 1.05E+01 1.18E-02 0.00E+00 3.05E+02 RURAL 1.09E+01 1.65E-01 4.66E-01 5.17E-04 0.00E+00 1.15E+01 SUBURB 1.40E+02 2.06E+00 5.83E+00 6.67E-03 0.00E+00 1.48E+02 URBAN 2.91E+02 3.73E+00 1.05E+01 1.18E-02 0.00E+00 3.05E+02 TOTALS:
4.42E+02 5.96E+00 1.68E+01 1.90E-02 0.00E+00 4.65E+02
- NOTE THAT INGESTION RISK IS A SOCIETAL RISK; THE USER MAY WISH TO TREAT THIS VALUE SEPARATELY.
NUREG-1437, Addendum 1 A3-20
Supplemental Analysesfor Cumulative EnvironmentalImpacts.
ECHO CHECK
&& Edited Mon Jun 21 15:48:15 1999
& & _Sou th_rou t e_via_ bel twa y_wi t h_rx_l i f e_ ext ens ion _
TITLE RAtrTRAN 4.0 INPUT FORM UNIT DIMEN 31 8 3 10 18 PARM 1 3 2 1 0 PACKAGE LABGRP SOLID CAS VOLATIL SHIPMENT LABISO CR$1 MN54 FESS FE59 C058 CO60 KR85 SR89 SR90 Y91 ZR95 NB95 RU103 RU106 SB125 TE125M TE127 TE127M CS134 CS137 CE141 CE144 PM147 EU154 PU238 PU239 PU240 PU241 AM241 CM242 CM244 NORMAL NMODE=1 9.000E-01 5.000E-02 5.000E-02 8.849E+01 4.025E+01 2.416E+01 4.000E+00 3.100E+00 0.000E+00 1.100E-02 1.000E+00 0.000E+00 0.000E+00 3.000E+01 2.000E+01 0.000E+00 1.000E+02 1.000E+02 2.000E+00 8.000E-02 5.000E-02 8.500E-01 4.700E+02 7.800E+02 2.800E+03 ACCIDENT SEVFRC NPOP=1 NMODE=1 4.62E-01 3.02E-01 1.76E-01 4.03E-02 1.18E-02 6.47E-03 5.71E-04 1.13E-04 NPOP=2 NMODE=1 4.35E-01 2.85E-01 2.21E-01 5.06E-02 6.64E-03 1.74E-03 6.72E-05 5.93E-06 NPOP=3 NMODE=1 5.83E-01 3.82E-01 2.78E-02 6.36E-03 7.42E-04 1.46E-04 1.13E-05 9.94E-07 RELEASE RFRAC GROUP =1 0.00E+00 6.00E-00 2.00E-07 2.00E-06 2.00E-06 2.00E-06 2.00E-05 2,00E-05 GROUP =2 0.00E+00 9.90E-03 3.30E-02 3.90E-01 3.30E-01 3.30E-01 6.30E-01 6.30E-01 GROUP 3 0.00E+00 6.00E-06 2.00E-05 2.00E-04 2.00E-04 2.00E-04 2.00E-03 2.00E-03 EOF ISOTOPES
-1 75278 1.00 13.000 1.00 0.00 VEGAS 1 CRS1 7.40E-16 SOLID 2
MN54 4.80E+01 SOLID 2
FESS 3.82E+03 SOLID 2
FE59 3.84E-10 SOLID 2
C058 3.67E-04 SOLID 2
CO60 1.20E+04 SOLID 2
KR85 1.96E+04 GAS 10 SR89 1.42E-05 SOLID 2
SR90 2.20E+05 SOLID 2
Y91 5.81E-04 SOLID 2
ZR95 1.78E-04 SOLID 2
NB95 1.24E-02 SOLID 2
RU103 2.40E-08 VOLATIL 7
RU106 4.04E+04 VOLATIL 7
SB125 5.80E+03 SOLID 2
TE125M 1.63E+02 SOLID 2
TE127 2.09E-01 SOLID 2
TE127M 2.12E-01 SOLID 2
CS134 1.09E+05 VOLATIL 7
CS137 3.21E+05 VOLATIL 7
A3-21 NUREG-1437, Addendum I
1 Supplemental Analysesfor Cumulative EnvironmentalImpacts...
1 CE141 2.71E-11 SOLID 2
.CE144 2.21E+04 SOLID 2
PM147 9.17E+04 SOLID 2 EU154 1.77E+04-SOLID.
2-PU238 1.72E+04 SOLID 2
PU239 7.09E+02 SOLID 2
PU240 1.32E+03 SOLID 2
PU241 2.88E+05
~ SOLID 2
AM241 3.17E+03 SOLID 2
CM242 1.14E+02 SOLID 2
CM244 2.18E+04
. SOLID-2 LINK 1 1.18E+02 8.80E+01 6.20E+00 4.70E+02 2.25E-07 R 1 LINK 1 3.32E+01 4.00E+01 4.91E+02 7.80E+02 2.25E-07 S 1 LINK 1 2.59E+01 2.40E+01 2.50E+03 2.80E+03.3.60E-07 U 1 PKGSIZ VEGAS 1 5.00
- EOF s
NUREG 1437, Addendum i A3-22
Supplemental Analysesfor Cumulative EnvironmentalImpacts..
INCIDENT-FREE
SUMMARY
INCIDENT-FREE POPULATION EXPOSURE IN PERSON-REM PASSENGR CREW HE.LERS OFF LINK ON LINK STOPS STORAGE TOTALS LINK 1 0.00E+00 8.14E+02 0.uoE+00 1.82E+00 7.24E+01 1.03E+03 0.00E+00 1.92E+03 LINK 2 0.00E+00 5.04E+02 0.00E+00 7.78E+01 1.72E+02 7.91E+02 0.00E+00 1.55E+03 LINK 3 0.00E+00 6.55E+02 0.00E+00 1.07E+01 1.42E+03 7.91E+02 0.00E+00 2.87E+03 RURAL 0.00E+00 8.14E-02 0.00E+00 1.82E+00 7.24E+01 1.03E+03 0.00E+00 1.92E+03 SUBUP.B 0.00E+00 5.04E+02 0.00E+00 7.78E+01 1.72E+02 7.91E+02 0.00E+00 1.55E+03 URBAN 0.00E+00 6.55E+02 0.00E+00 1.07E+01 1.42E+03 7.91E+02 0.00E+00 2.87E+03 TOTALS: 0.00E+00 1.97E+03 0.00E+00 9.03E+01 1.66E+03 2.61E+03 0.00E+00 6.34E+03 MAXIMUM INDIVIDUAL IN-TRANSIT DOSE LINK 1 4.03E-02 REM LINK 2 4.03E-02 REM LINK 3 4.03E-02 REM EXPECTED VALUES OF POPULATION RISK IN PERSON-REM GROUND INHALED RESUSPD CLOUDSH
- INGESTION TOTAL LINK 1 1.63E+01 2.47E-01 6.99E-01 7.75E-04 0.00E+00 1.73E+01 LINK 2 3.68E+02 5.41E+00 1.53E+01 1.75E-02 0.00E+00 3.89E+02 LINK 3 3.88E+02 4.97E+00 1.41E+01 1.58E-02 0.00E+00 4.07E+02 RURAL 1.63E+01 2.47E-01 6.99E-01 7.75E-04 0.00E+00 1.73E+01 SUDURB 3.68E+02 5.41E+00 1.53E+01 1.75E-02 0.00E+00 3.89E+02 URBAN 3.88E+02 4.97E+00 1.41E+01 1.58E-02 0.00E+00 4.07E+02 TOTALS:
7.72E+02 1.06E+01 3.00E+01 3.41E-02 0.00E+00 8.13E+02
- NOTE THAT INGESTION RISK IS A SOCIETAL RISK; THE USFR MAY WISH TO TREAT THIS VALUE SEPARATELY.
A3-23 NUREG-1437, Addendum 1
Supplemental Analysesfor Cumulative EnvironmentalImpacts...
ECHO CHECK
&& Edited Mon Jun 21 15:51:08 1999
&& _Souttt_ route yla_ beltway without_rx_ life _ extension.
TITLE RAIFTRAN 4.0 INPUT FORM CNIT DIMEN 31 8 3 10'18 PARM 1 3 2 1 0-PACKAGE-LABGRP SOLID CAS VOLATIL SHIPMDIT LABISO CRS1 MN54 FESS FES9 C058 CO60 XR85 SR89 SR90 Y91 ZR95 NB95' RU103 RU106
.SB125 TE125M TE127 TE127M CS134 CS137 CE141 CE144 PM147 EU154 PU238 PU239 PU240 PU241 AM241 CM242
'CM244 NORMAL NMODE=1 9.000E 5.000E-02 5.000E-02 8.849E+01 4.025E+01 2.416E+01 4.000E+00 3.100E+00 0.000E+00 1.100E-02. 1.000E+00 0.000E+00 0.000E+00' 3.000E+01 2.000E+01 0.000E+00 "1.000E+02 1.000E+02 2.000E+00 8.000E-02 5.000E-02 8.500E-01 4.700E+02 7.800E+02 2.800E+03 ACCIDENT SEVFRC NPOPal NMODE=1 4.62E-01' 3.02E-01 1.76E-01 4.03E-07 1.18E-02 6.47E-03 5.71E-04 1.13E-04 NPOP=2 NMODE=1 4.35E-01 2.85E-01 2.21E-01 5.06E-02 6.64E-03 1.74E-03 6.72E-05 5.93E-06 NPOP=3-NMODE=1 5.83E-01 3.82E-01 2.78E-02 6.36E-03 7.42E-04 1.46E-04 1.13E-05 9.94E-07 RELEASE RFRAC GROUP =1 0.00E+00 6.00E-08 2.00E-07 2.00E-06 2.00E-06
- 2. 00E -06 2.00E-05 2.00E-05 GROUPS 2 0.00E+00 9.90E-03 3.30E-02 3.90E-01 3.30E-01 3.30E-01 6.30E-01 ' 6.30E-01
' GROUP =3 0.00E+00 '6.00E-06 2.00E-05 2.00E-04 2.00E-04 2.00E-04 2.00E-03 2.00E-03 EOF'
'-1 50185 1.00 13.000 1.00 0.00 VEGAS 1 ISOTOPES CRS1 7.40E-16 SOLID 2
MN54 4.80E+01 SOLID 2
FESS 3.82E+03 SOLID 2
.FES9 3.84E-10 SOLID 2
-C058 3.67E-04 SOLID 2
CO60 1.20E+04 SOLID 2
KR85 1.96E+04 CAS 10 SR89 1.42E-05 SOLID 2
SR90 2.20E+05 SOLID 2
Y91 5.81E-04 SOLID 2
ER95 1.78E-04 SOLID 2
NB95 1.24E-02 SOLID 2
RU103. 2.40E-08 VOLATIL 7
RU106 4.04E+04' VOLATIL 7
5B125.5.80E+03 SOLID 2
TE125M '1.63E+02 SOLID 2
.TE127 2.09E-01 SOLID 2
TE127M 2.12E-01 SOLID 2
CS134 '1.09E+05 VOLATIL 7
CS137-3.21E+05 VOLATIL 7
NUREG-1437, Addendum I A3-24
Supplemental Analysesfor Cumulative EnvironmentalImpacts.
CE141 2.71E-11 SOLID 2
CE144 2.21E+04 SOLID 2
PM147 9.17E+04 SOLID 2
EU154 1.77E+04 SOLID 2
PU238 1.72E+04 SOLID 2
PU239 7.09E+02 SOLID 2
PU240 1.32E+03 SOLID 2
PU241 2.88E+05 SOLID 2
AM241 3.17E+03 SOLID 2
CM242 1.14E+02 SOLID 2
CM244 2.18E+04 SOLID 2
LINK 1 1.18E+02 8.80E+01 6.20E+00 4.70E+02 2.25E-07 R 1 LINK 1 3.32E+01 4.00E+01 4.91E+02 7.80E+02 2.25E-07 S 1 LINK 1 2.59E+01 2.40E+01 2.50E+03 2.80E+03 3.60E-07 U 1 PKGSIZ VEGAS 1 5.00 EOF l
/L3-25 r4URE(3-1437, Addendunn i
Supplemental Analysesfor Cumulative Environmental Impacts...
INCIDENT-FREE
SUMMARY
)
INCIDENT-FREE POPULATION EXPOSURE IN PERSON-REM PASSENGR CREW HANDLERS OFF LINK ON LINK STOPS STORAGE TOTALS LINK 1 0.00E+00 5.43E+02 0.00E+00 1.22E+00 4.83E+01 6.85E+02 0.00E+00 1.28E+03 LINK 2 0.00E+00 3.36E+02 0.00E+00 5.19E+01 1.15E+02 5.28E+02 0.00E+00 1.03E+03 LINK 3 0.00E+00 4.37E+02 0.00E+00 7.10E+00 9.45E+02 5.28E+02 0.00E+00 1.92E+03 RURAL 0.00E+00 5.43E+02 0.00E+00 1.22E+00 4.83E+01 6.85E+02 0.00E+00 1.28E+03 SUBURB 0.00E+00 3.36E+02 0.00E.00 5.19E+01 1.15E+02 5.28E+02 0.00E+00 1.03E+03 URBAN 0.00E+00 4.37E+02 0.00E+00 7.10E+00 9.45E+02 5.28E+02 0.00E+00 1.92E+03 TOTALS: 0.00E+00 1.32E+03 0.00E+00 6.02E+01 1.11E+03 1.74E+03 0.00E+00 4.22E+03 MAXIMUM INDIVIDUAL IN-TRANSIT DOSE LINK 1 2.69E-02 REM LINK 2 2.69E-02 REM LINK 3 2.69E-02 REM EXPECTED VALUES OF POPULATION RISK IN PERSON-REM CROUND INHALED RESUSPD CLOUDSH
- INGESTION TOTAL LINK 1 1.09E+01 1.65E-01 4.66E-01 5.17E-04 0.00E+00 1.15E+01 LINK 2 2.45E+02 3.61E+00 1.02E+01 1.17E-02 0.00E+00 2.59E+02 LINK 3 2.58E+02 3.32E+00 9.37E+00 1.05E-02 0.00E+00 2.71E+02 RURAL 1.09E+01 1.65E-01 4.66E-01 5.17E-04 0.00E+00 1.15E+01 SUBURB 2.45E+02 3.61E+00 1.02E+01 1.17E-02 0.00E+00 2.59E+02 URBAN 2.58E+02 3.32E+00 9.37E+00 1.05E-02 0.00E+00 2.71E+02 TOTALS:
5.15E+02 7.09E+00 2.00E+01 2.27E-02 0.00E+00 5.42E+02
- NOTE THAT INGESTION RISK IS A SOCIETAL RISK; THE USER MAY WISH TO TREAT THIS VALUE SEPARATELY.
NUREG-1437, Addendum i A3-26
NRc FORM 33s u.s. NUCLEAR REGuLAToitY coMMiss6oN
- 1. REPORT NUMBER (2 49)
NRCM 1102.
(Assigned by NRC, Add Vel, Supp., Rev.,
and Addendum Numbers, of any )
m 32a2 BIBLIOGRAPHIC DATA SHEET
- "'"*~#
NUREG-1437, Vol.1,
- 2. TITLE AND SuBnrLE Addendum 1 Generic Environmental Impact Statement for License Renewal of Nuclear Plants Main Report 3
DATE REPORT PUBLISHED Section 0.3-Transportation uoNm YEAR Table 9.1 Summary of findings on NEPA issues for license renewal of nuclear power plants Final Report August 1999 4 FIN OR GRANT NUMBER S AUTHOR (S)
- 6. TYPE OF REPORT Regulatory
- 7. PERIOD COVERED (fictusae Dates)
- 8. PERFORMING ORGANtlATION - NAME AND ADDRESS (If NRC, prowde Owoon, oince w Repon. U s Nuclear Regulatwy Comemsson, and rnakg address, dcontractor.
promoe name and mau adeess >
e Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 i SPONSORING ORGANIZATION NAME AND ADORESS (dNRC, type "same as acow* dcontractor, prowde NRC Dumon ovnce or Repon u s Nuciear Regulato and modng address J Same as above
- 10. SuPPLEMENIARY NOTES
- 11. ABSTRACT (200 mvos w Aess)
This addendum to NUREG-1437 Generic Environmental Impact Statement for License Renewal of Nuclear Plants, documents the staffs analysis of the potential cumulative impacts of transporting spent nuclear fuelin the vicinity of a single high-level wasts repository, and summarizes the staffs analyses undertaken to determine whether the environmental impacts of the transportation of higher enrichment and higher bumup spent nuclear fuel are consistent with the values of 10 CFR 51.52, Table S4 The intent of the study is a generic analysis of the cumulative impacts associated with transportation of spent nuclear fuel as a result of nuclear power plant license renewal. The results of the analysis will be used to amend 10 CFR Part 51.53 and Appendix B to Subpart A of 10 CFR Part 51, and is not intended to support any other regulatory decision by the NRC. This addendum also includes an appendix that summarizes comments on the draft of the addendum, and documents the staffs responses to those comments.
- 12. KEY WORDS/DESCRIPTORS (Ust woros or phrases that sw# assst researctwrs e Aacatmg the report; 13 AVAltA8:uTV STATLMENI Generic Environmental impact Statement unlimited License renewal 14 SECuRATY CLASSIFICATION Nuclear Power Plant
'(This engei Environmental Protection Spent Nuclear Fuel unclassified (Th,s Report) unclassified 15 NUMBER OF PAGES 16 price NHC f OHM 336 9 4W TNs form was electroncaNy produced by Eine Federas Forms Inc
o 6T.S Federal Recycling Program
l 1Ii O5 E, -
9991 TSUG U
I I LD A
DS RE AE D F ND AN TA S E M
L G R AI A E
CT P
5NlCfTR dO F
S NI TN MA EIP TAR
'T A 5E fL CC A U P N MF IO L L A A TN WE NR NE NE C
IR EN YE N
O IS 1
S 0 0
I 0 0
M 0 3$
M-5 S
SS C5 SU E
0 E
TY2 E
N AR I T TO C SA ST D UN B R DA N, LP A
EL R
TUO CO I
1 N G T I
I FF l
U E G F Y oV,1 R N OT I
L 3M RH A
7 4U A S N
E A EP 1
D LW GN C
EE U
RD N
UD NA