ML20197J613
| ML20197J613 | |
| Person / Time | |
|---|---|
| Issue date: | 08/16/1996 |
| From: | Linehan J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Yoshimura R SANDIA NATIONAL LABORATORIES |
| Shared Package | |
| ML20197J465 | List: |
| References | |
| CON-FIN-J-5160, FOIA-97-417, RTR-NUREG-0170, RTR-NUREG-170 NUDOCS 9801050037 | |
| Download: ML20197J613 (35) | |
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- e. moe p \ um mso STATES g NUCLEAR REGULATORY COMM88800N WASNmGTON O.C. Sammert
\e.,,e August 16, 1996 Mr. Richard Yoshimura Manager. Transportation Systems Analysis Department 6641 MS 0718 Sandia National Laboratory P.O. Box 5800 Albuquerque, NH 87185
SUBJECT:
PROJECT ENTITLED " REVALIDATION OF NUREG-0170 SPENT FUEL SHIPME RISK ESTDMTES" Job Code d H00
Dear Mr. Yoshimura:
This letter is to request a preliminary proposal for performance of the enclosed statement of work (S0W) under Jnb Code J5160, for the Nuclear Regulatory Comission Office of Nuclear Material Safety and Safeguards. The enclosed 50W details the required work and should be used as the basis for proposal prepardion.
Cost Proposal The task order proposal should contain the cost information as is recuired on the NRC Form 189. DOE Laboratory Project and Cost Proposal for N.tC kork."
A spending plan should also be submitted as part of your cost proposal.
Guidance for c letion of the plan is contained in the instructions portion of the NRC Form 89.
Technical Proposal Content As a minimum the technical proposal must contain the following:
a) A discussion to substantiate the laboratory's understanding of the scope of work.
b) A discussion of the laboratory's technical approach to meet the project's objective.
c) A discussion of the experience and ca] abilities of key personnel and the laboratory in performing similar wort.
d) Identification of key personnel and the number of staff hours that will be comitted to completion of work. Resumes for key personnel must be included.
e) Identification of administrative support personnel and/or facilities needed to assist professional personnel in completing work, f) A discussion of any potential organizational conflict of interest issues.
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98 10 g 7 971217 RESNIKO97-417 PDR L7 vv i v - - ,
R. Yoshimura 9) A discussion of anticipated problem areas or deviations from the NRC's S0W.
This recuest is not an authorization to begin work. Authorization will be providec via a NRC Fonn 113. " Standard Order for 00E Work."
Work under this project is anticipated to be unclassified.
The proposal should be faxed to the NRC within 30 days. Please advise the individual meni n.ned below by telephone if there is any difficulty in meeting this due date.
The proposal should be sent in an original and two copies to the U.S. Nuclear Regulatory Conrnission. ATTN: Mr. David Tiktinsky Office of Nuclear Material Safety and Safeguards. Mail Stop T-8 A-23. Washington. DC 20555.
Questions concerning this request should be addressed to David Tiktinsky on (301) 415-7818. Thank you for assistance in this matter.
Sincerely.
DMJohnJ.Linehme ,
John J. Linehan ' Director Program Management. Policy Development and Analysis Staff. NMSS
Enclosures:
As stated cc: J. Sprung. SNL Distribution: .Ed69 NMSS r/f 0FC RMB , A. E RM-/ N SFP0 E RH8,, E NAME DT1((fis'ky GBev81dge N2JCook KMcdai$E DATE 8/\\/96 8/ 0 /96 @ 8/r>/96 8//[,/96 C = COVER ' E = COVER & ENGLOSURE N = NO COPY OFC /m PR _ N NAME DddNIan oArt- //Fus#96 N = NO COPY Cy E = COVER & ENL'LOSURE
l ProjectTitle: Revali M tion of NUREG 0170 Spent Fuel Shipment Risk Estimates Job Code: J5160 Contractor: SNL B&R No.: 65015221000 Project Manager: David Tiktinsky Technical Monitor: John Cook
1.0 Background
The Nuclear Regulatory Comission's " Final Environmental Statement on the Transportation of Radioactive Material by Air and Other Modes." NUREG 0170, dated December 1977, is NRC's generic environmental inpact statement (EIS).
covering all types of radioactive material transportation by all modes (road, rail, air, and water). This EIS provides the regulatory basis for issuance of the general licenses for transportation of radioactive material in 10 CFR 71.
Based in part on the findings of NUREG-0170, the Commission " concluded that present regulations are adequate to protect the public against unreasonable risk from the transport of radioactive materials" (46 FR 21629. April 13, 1981). The Conmission also stated that " regulatory policy concerning transpogation of radioactive materials be subject to close and continuing review.
Due to recent changes in industry and government spent fuel management strategies, new spent fuel shipments are anticipated that were not considered when NUREG-0170 was prepared. These anticipated shipments include the use of dual-purpose and multi-purpose canisters (MPCs) for spent fuel shipments, and shipments to Interim Spent Fuel Storage Installations (both on and off reactor sites), and centralized storage facilities. Further, other studies have been completed that are directly related to spent fuel transportation including Shipping Container Response to Severe Highway and Ratlway Accident Conditions (NUREG/CR 4829. Vols. I and 2. February. 1987. often referred to as "the Modal Study"). Most recently. Argonne National Laboratory completed) a Draft Mtf-purpose Canister Environmental impact Statenent. Transportation risk assessment models have also been revised and updated since the EIS was prepared.
The Office of Nuclear Material Safety and Safeguards (NMSS) has received several applications for dual-purpose (storage and transport) spent fuel casks. and additional applications are expected in the near future. NMSS considers that it is now approariate to review and revalidate if possible, the conclusions of the EIS wita respect to the anticipated spent fuel shipments. The Office of the General Counsel has indicated that the extent to which the existing EIS analyses bound anticipated spent fuel transportation activities should be addressed in a timely manner, and if possible prior to cask certification.
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l c 2.0 Objectives-
- 1. Estimate the transportation risks associated with the anticipated s)ent fuel shipments, and determine whether those risks are bounded by tw NUREG 0170 estimates and projections of spent fuel shipment risks.
Radiological and non radiological risks under both routine and accident conditions should be considered for vehicle, rail, and vessel transportation.
- 2. Provide the rationale sup>orting the data and asstantions used in the risk estimates for the anticipated spent fuel shipments,
- 3. Address any outstanding issues from NUREG 0170, the Modal Study, or environmental concerns.
3,0 Purpose The purpose of this effort is to >rovide the technical basis and documentation for revalidating the adequacy of OREG-0170 risk estimates with respect to anticipated spent fuel shipments. The revalidation may also be used in preparation of the transportation portion of the environmental document prepared for the Part 72 rulemaking to list a storage / transport cask, or for a storage or disposal facility license, 4.0 Expertise and Disciplines Required The contractor shall assure that the Project team has the proper mix of nationally and internationally recognized technical experts, i.e. scientists and engineers with training and experience in radiological and non-radiological transportation risk assessment under routine and accident conditions. Specific disciplines required include, but are not limited to, structural and thermal engineering. and health physics. The principal, and other senior, investigators shall have the professional credentials to qualify as expert witnesses at public hearings. The principal investigator shall 3rovide technical oversight and continuity over all work performed on this
)roject.
5.0 Work to be Performed The work to be perfonned under this project is to be perfonned in three phases in series. The proposal prepared should clearly discuss each phase separately (including the cost proposal). Funding will be provided on a phase by phase level with each phase treated similarly to a separate task order (all costs should be tracked and controlled by phase).
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Phase I REVIEW OF Sii!PMENT_ FACTORS /RD (MTA, AND IDENTIFICATION OF ANALYSES NEEDED Characterization of Anticipated Spent fuel Shipments TASK 1 Identify and quantify as appropriate the factors that are needed to adequately-characterize anticipated spent fuel shipments. Possible factors include:
> Source Term shipment of older fuel (radiological and thermal esbrittlement :onsiderations) shipment of 7 eater than Class C waste
- Packaging Designs greater capacities and weights igact of dual storage / transport u multi function designs
> Logistict s)en', fuel inventories sifpping schedules potential routes new storage facilities multi-unit shipments (rail) greater shipment distances transport by vessel stop times
> Assessment data and tools i revised radiation risk coefficients
! accident statistics population densities shipment radiation levels j RISKIND code TASK 2 Identify the most ap)ropriate basis for comparison between the NUREG-0170 and the revalidation rist estimates, e.g., total health i gact to ship all spent fuel, the igact in a single year of shipments, the impact per shipping
'ccpaign, etc. -
TASK 3 Develop shipment models that address the above factors, and that would be representative of the anticipated shipments.
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TASK 4 incorporation of Related Studies Determine the ap)licability of the Argonne Draft MPC EIS data, enalyses, and results to this >roject. The Draft MPC EIS data and results should be used to Identify the the fullest extent consistent with objectives of this Project.
information that should be obtained from Argonne for use in this Project.
Also, estimate how the use of this infomation would affect SNL's effort.
costs, deliverables and schedule.
TASK 5 Determine the applicability of the Hodal Study's results to the anticipated shi )sents. In particular. address whether the representative road and rail cast designs used in the Hodal Study are appropriate for use in the revalidation effort. Identify and address any issues that might arise regarding the use of the Hodal Study for the revalidation risk estimates.
TASK 6 Revised Proposal Based on the reviews performed in tasks 1-S. SNL shall identify any additional packaging engineering analyses, and/or spent fuel shipment logistical Information or risk analyses required to be perfonned to complete this Project. SNL shall prepare a revised proposal detailir.g the computer and engineering analysis that needs to be performed and the cost anti schedule for completing the analyses. The plan shall also describe hcw the final report will communicate the results of the risk analysis to the public.
The letter reports that will be prepared for the above tasks are identified in section 6.0.
SNL will not proceed to the next phase until authorization is provided by the NRC.
Phase II - ENGINEERING AND COMPUTER ANALYSES A. Perform engineering analyses, as needed. Details of the analyses to be performed are to be provided by SNL. for NRC approval. at the conclusion of task 6.
B. Perform RADTRAN and RISKIN0 analyses, as needed. Details of the analyses to be perfomed are to be provided by SNL. for NRC approval at the conclusion of task 6.
The following letter reports are anticipated to be prepared in support of this phase: 1) draft reports (2) showing results of analyses performed at the 33%
and 661 spending levels: 2) a draft final report: and 3) a final report following receipt of NRC coments. Meetings will be held following the 33%
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e draft, the 663 draft, and the draft final report.
At the conclusion of this phase. SNL shall prepare a revised proposal
~ detailing the risk analysis that needs to be performed and the cost and schedule for conpleting the analyses.
The details for this phase will be negotiated following the receipt of the proposal from task 6 above.
Phase III - RISK ANALYSIS AND 00CtM 6 A, Cospare the risks from the NUREG-0170 and revalidation shipment models. Details of these conparisons to be perfomed are to be provided by SNL, for NRC approval, at the conclusion of Phase II.
B. Doctment the findings and rationale. Details of the findings and rationale to be included in the final remrt are to be provided by SNL, for NRC approval, at the conclusion of P1ase II.
The following letter reports should are anticipated to be prepared in support of this phase: 1) draft reports (2) showing results cf analyses performed at the 338 and 66% spending levels: 2) a draft final report: and 3) a final report following receipt of NRC coments. Meetings will be held following the 33% draft, the 661 draft, and the draft final report.
The details for this phase will be negotiated following the receipt of the proposal from phase 11 above.
6.0 Deliverables and Schedule (including meetings)
HILESTONE MONTHS FROM INITIATION Kickoff meeting 0 Phase 1 -
Task 1 Draft at 33% expenditure Meeting with NRC Draft at 66% expenditure Meeting with NRC Draft final Remrt Meeting with NRC Final Report Task 2 Draft Final Re mrt Meeting with NRC Final Report 5
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e Task 3 Oraft at 508 expenditure ,
Meeting with NRC Draft final Re mrt Meeti witn NtC Final rt.
Task 4 Draft at 50% exxmditure Meeting with NR; Draft Final Report Meeting with NRC Final Report Task 5 Draft at 501 expenditure Meeting with NRC Draft Final Re mrt Meeting with NRC Final Report Task 6 Revised Pro msal Meeting witi NF Final Proposal 15 Phase II Engineering and Computer Analysis 331 Draft Report lieeting with NRC 665 Oraft Report Meeting with NRC Draft Final Report Meeting with NRC NRC Coments Final' Report Revised Proposal showing Risk Assessment to be Performed 24 6
Phase !!! Risk Analysis 338 Draft Report Meeting with NRC 668 Draft Report .
Meeting with NRC.
Draft Pinal Report Heeting with NRC WC Coments Final Report Project draft Final Report 33 Meeting with NRC NRC Causents 34 Final Report 35 The Performing Organi/stion shall prepare a comprehensive final report in NUREG/CR fomat, stamarizing all work performed under tr.1s project. The report shall include an executive sumary of the findings of this Project. It shall also include a couplete description of the shipment models developed, and rationale for the use of data and assumptions.
All reports shall be edited and reviewed by the performing organization and checked in accordance with the quality assurance requirements addressed bel w.
The NHSS TN will provide coments to the performing organization to be considered in the preparation of the final task report. These coments will identify potential problem areas, discrepancies, and technical insights on the draft report. The coments will be for the purpose of clarification only and will not be construed as to prejudge the performing organization's work or technical findings. Within the above schedule, after receipt of NRC coments.
the performing organization shall revise the draft task report incorporating resolution of comments, and submit a camera ready copy and an NRC compatible, electronic media copy of the final task report.
7.0 Period of Performance The period of performance for this project is 35 months from the time of initiation.
8.0 Estimated Level of Effort The estimated level of effort for all three phases of this project is 1.5 staff years.
Phase ! 0.6 staff years Phase II 0.6 staff years Phase III 0.3 staff years 9.0 Meetings and Travel 7
Toc meetings required are shown above in section 6 above. As was mentioned earlier the location of the meetings are expected to be alternated between SNL and NRC. There are 19 meetings identified of which 9 should be planned to be held at NRC headquarters. It is expected that the meetings to be held at NRC will need no more than two contrac+or staff members to attend each meeting.
10.0 Monthly Letter Status Report (MLSR)
The performing organization shall submit a Monthly Letter Status Rexrt (MLSR) submitted by the 20th day of each month with distribution as shown 210w. The M.SR should cont 6in. at J ainimum, all of the required information as shown in 2 11.7. Exhibic 12, " Monthly Letter Status Report Requirements". .
11.0 Distribution of Deltierables The following stannarizes the required report distribution under this 50W. The IMSS PM shall provide the performing organization with current NRC mailing addresses for this distribution.
Monthly Meetings. Draft Final Letter Workshops. Formal Formal Status & Trip Tech. Tech.
31stribution Reports Reports R< orts Reports 1 1 1
- #tSS PM 1 StSS TM 1 1 5 1*
Div. of Freedom of Info, and Pub.
Services (FIPS) 0 0 0 1
- Camera ready and electronic media 12.0 Technical / Project Direction Project Manager - David Tiktinsky Technical Monitor - John Cook The NMSS PM is the focal point for all contract related activities. All work assignments and program funding actions are initiated by the NMSS PM. All proposed work scop or schedule changes must be processed tnrot$ the NHSS PM.
The StSS TN is responsible for providing technical guidance to the performing organization regarding staff interpretations of the technical aspects of regulatory requirements along with copies of relevant documents (e.g.
Regulatory Guides) when requested by the parforming organization. All work products must be reviewed and approved by the NMSS TH before they are submitted as final documents. All technical directions given to the performing organization must be consistent with the wort scope and schehle.
The NMSS IM is not authorized to unilaterally rmke changes to the approved work scope or schedule or give the performing organization any direction that would increase costs over approved levels.
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Directions for changes tri cost or period of perfonnance will be provided by the DOE Operations Office after receist of an appropriated Standard Order for DOE Work (SOEW) (NRC Fom 173) from tie Office of Nuclear Material Safety and Safeguards, if the performing organization receives guidance which is believed to be invalid under the criteria cited above. the )erfoming organization shall immediately notify the NHSS PM. If the MSS PM and the perfoming organization are unable to resolve the question within five days, the perfoming organization shall notify the 00E Operations Office.
13.0 00ALITY ASSURANCE 13.1 For all draft and final reports delivered under this agreement, the perfoming organization shall assure that an independent review and verification of all numerical computations and mathematical equations and derivations are verified by qualified personnel other than the original author (s) of the reports. If the perfoming organization proposes to verify / check less than 100 percent of all computations and mathematical equations and derivations in the re) ort (s). (such as might be the case when there are a large num)er of routine, repetitive calculations), the perfomintorganization must first obtain written approval from the NMSS m. Computer generated calculations will not require verification where the conputer program has already been verified.
The NHSS TM has the option of auditing all documentation including project correspondence, drafts, calculations and unrefined data.
13.2 in addition, all re numerical analyses, must ports including be reviewed by thethose perfoming which do not contain organization's management and approved with two signatures, one of which is for the perfoming organization's management at a level above the program manager.
13.3 When revisions for the reports are issued, a section must be included in the revised report to document dates of, reasons for, and scope of all changes nude since the issuance of the first performing organization's approved report.
13.4 NRC has the o) tion of appointing a Peer Group to review the draft report and mate changes to the final report. The performing organization may recomend candidates for the Peer Group for approval by the NMSS TM. In the occasion of dissent in the content of the final report, the dissenting party will have the option of stating its viewpoints and findings in a section of the report.
Alternative QA plans should be submitted for NRC review and approval.
14.0 Disposal of Property Management of property purchased under this Interagency Agreement will follow the procedures as stated in Part Vill of MD 11.7.
15.0 00E Acquired Material 9
The performing organization must notify the Office of Nuclear Material Safety and Safeguards (Attn: Director. PPEM) and the NMSS PM prior to acquisition of any capital. Federal Infomation Processing (FIP), or word processing equipment.
16.0 NRC furnished Material None anticipated.
17.0 Special Bidding Instructions This project is to be managed at the task level (both fiscally and technically). Costs shoulc be proposed and tracked at the task level. The draft reports identified are at percent e of funds for the particular task (each task should be handled similarl to a task order).
At the completion of each phase a proposal is to be prepared detailing the recuirements for the next phase. The initial proposal should bound the needs anc requirements for phases 11 and III.
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NRC FORM 347 USNRC )OBCODE DOE SOURCE SELECTION JUSTIFICATION pleo
- 2. JOB CODE TIT 1.E amedde af NUREG41703:wn Feel 24mma het Ammunes
- 3. SELECT SOURCE sm
- 4. BA545 FOR SELECDON (DESCRitS THE BASIS FOR SELECHON OF SOURCE.
NARRATIVE MUST BE SUPPORTED BY FACTS. SEE HANDSOOK 11.7, PART 11) the semem d sNL hr et an$ms k how sn == omeh. thee almh an Assued Kasumen ad ag+- er fumem, ad Lkdque Tedsdal Dheshes er Can'deseos of Dhduties.
As est of sw adenha pecem, NM$$ smN aut ute SNL m dhnmu to 50W ad pendber asemende a pertede te amt autend h ese SOW.
SNL desuhped du artshd duassume (NUREG4170) est has been used br en Nec hr asur 15 yees. A moder af tw ter paramad dost use busessedin es sW deemnant properadan uG be husehod b et pn$ set.
TMs @=edes perused h en som of m ammanuma nhand er sansenseen see, paranus eingsnaden nised e amusemens tur DOE tugues pnyuus muh a see swupert uIde av esser suhad es die musk est uS be pertunned nouder ads putect. 384. k te pounder teensary b canganesen set ammsunset and k mesed seedsely by DOL SDE has she estam ansny of me e mamanas emmpuur emes out av wahmL the pu$ist she sagtes tussainte of spent tal cads and hair budessler esha Wengerenden (bedues N). SN. has a cue
, adys pen, uN6 pertmu hoort ames en celu ad luse asnsed a past del of basutedy ruheed a gent esd cad.
- on es whsh, see, deselsped en utilne NUREG 0170 and usany of en same seers uW be song en to gdens. In adeden, SNL he esque ceanusens of AdpAnas nhed a sagenuhn stk amasunas ad gent tal ces aufph, thuuten, SNL k sw seesmananded eswie air ade pniert.
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i I SIGNATURE DATE
- 5. PROJECT MANAGER ORGANIZATION otiatomavocoon NMss (//l/4 l 6. INTERMEDIATE APPROVAL (ASSOCIATE SIGNATURE DATE COMPETITION ADVOCATE)
! [/ [
Abraham Eks, PMDA, NMSS .
- 7. FINAL APPROVAL OFFICE DIR. OR DES. mSIGNATURE DATE l (TYPED NAME)
- Jolm Lirwhan, PMDA, NMSS j [
y .
l 1 I 09/16,96 09:01- G 505 844 0244 ORG.o 6320 0001 3andia National Laboratories
, P. O. Box 5800
. Albuquerque, New Mexico 87185 FAX TO: DATE:
_Name: Duid Tik.}-;a,ky ,
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Organization: A/HsS Address: _.
Phone: --
Total Pages (including this cover sheet):
MESSAGE:
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I FROM: FAX Number: 844-0244 Name: Terenv 9prunt Phone: Sad 8'/h-o/$Y O
\
opeisees 09:01 C so$ 844 0244 ORG o 6320 @ o02 JCN J5160 Sandia National Laberatories (SNL)
Proposal for Project Entitled
" Revalidation of NUREG-0170 Spent Fuel Shipment Risk Estimates" Job Code J5160 (Reference NRC request for a prelhainary proposal dated August 16,1996)
1.0 INTRODUCTION
A. Background In September of 1977, the Nuclear Regulatory Commission (NRC) issued a generic environmental impact statement (EIS), entitled " final Environmental Statement on the Transponation of Radioactive Material by Air and Other Modes," NUREG-0170, that covered the transport of all types of radioactive material by all transport modes (road, rail, sir, and water).
That EIS provides the regulatory basis for issuance of general licenses for transportation of radioactive material under 10 CFR 71. Based in part on the findings of NUREG-0170, NRC staff concluded (1) that "the average radiation dose to the population at risk from normal transportation is a small fraction of the limits recommended for members of the general public from all sources of radiation other than natural and medical sources and is a small fraction of natural background dose," and (2) that "the radiological risk from accidents in transportation is small, amounting to about one half percent of the n% mal transportation risk on an annual basis" (Summary and Conclusions, NUREG-0170, p. vii); and the NRC Commission concluded that "present regulations are adequate to protect the public against unreasonable risk from the transport of radioactive materials"(46 FR 21629, April 13,1981). The Commission also stated that " regulatory policy concerning transportation of radioactive materials be subject to close and Continuing review."
Due to recent changes in industry and government spent fuel management strategies, shipment of spent fuel in canisters and along routes not specifically considered by the generic analyses performed for NUREG-0170 is articipated. For example, spent fuel may now be shipped in the dual-purpose or multi purpose canisters (MPCs) from commercial reactors to Intenm Spent Fuel Storage Installations and/or Centralized Storage Facilities in addition to shipment to a permanent geologic repository, la fact, the OfDee of Nuclear Material Safety and Safeguards (NMSS) has received several applications for dual purpose (storage and transport) spent fuel casks, and additional applications are expected ic the near future. In addition, many changes have been i made to the risk assessment models implemented in the RADTRAN code since the initial version of that code was used to estimate spent fuel transportation risks for NUREG 0170; and several
( studies of spent fuel transportation risks have been recently completed, e.g., " Shipping Container
- Response to Severc Highway and Railway Accident Conditions," NUDEG/CR-4829, February 1987, often called the Modal Study, and Argonne National Laboratory's " Draft Multi-Purpose Canister Environmental Impact Statemen!," that contain new or improved risk assessment l models and data.
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09/16e96 09: 02 Osos 644 0244 oRG.o 6320 @ 003 l ,
Because new data and analytical methods are now available to apply to the analysis of spent fuel transportation risks, and because spent fuel is likely to be shipped to facilities along routes ard in casks not specifically examined by hVREG 0170 NMSS believes that it is now approprit.te to review and revalidate the conclusions reached in NUREG 0170. Specifically, NMSS wishes to know whether the risks of the anticipated spent fuel shipments are bounded by the risks estimated in NUREG 0170.
II. Objectives This study has three objectives:
Estimation of the radiological and non-radiological, routine and accident, transportation risks associated with the anticipated spent fuel shipments and determination of whether those risks are bounded by the estimates and projections of spent fuel shipment risks reached in NUREG-0170.
Examination of any outstanding spent fuel transportation issues or emironmental concems not resolved by NUREG-0170 and the Modal Study, Documentation of the approach, data, and computational methods used to reestimatt spent fuel transportation risks in detail sufficient to allow other transportation experts to fully understand the analyses performed, and preparation of brief and detailed summaries of the results in a form accessible to concerned citizens.
C. Purpose This study has a three part purpose: (1) Revalidation of the conclusions regarding the shipment of spent fuel reached in NUREG-0170; (2) demonstration that those conclusions apply to currently anticipated shipments of spent fuel; and (3) development and documentation of the technical basis on which the revalidation is based. After revalidation, NUREG-0170 conclusions about the safety of spent fuel shipments could be cited in the transportation portion of environmental impact documents prepared to support the licensing of spent fuel storage or disposal facilities and could also be used to support the listing (as the result of a Part 72 rulemaking) of casks that are suitable both for transport of spent fuct to such facilities and for storage of spent fuel at these facilitics.
2.0
SUMMARY
OF PRIOR EFFORTS NUREG-0170 was prepared for the NRC by Sandia National Laboratories (SNL). Sh1 also developed RADTRAN 1, the computer code used to calculate the RAM transportation risk estimates reported in NUREG-0170. SNL has prepared Environmentd Assessments (EAs),
Environmental Impact Statement (EISs), and performed supporting anlyses (for NEPA documents issued by the DOE) that address transportation of RAM by road and/or rail These include: (1) Transportation impacts af the Commercial Radioactive Waste Management 1
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. 0948<96 09:02 0505 644 0244 ORG.c 6320 @ 004 Program, Cashwell et al.,1986, SAND 85 27]S; (2) Environmental Assessment of the Proposed Adoption and Implementation of a United States Policy on Receipt and Reprocessing of Spent Research Reactor Fuel (Off Site Fuels Felicy),1991, DOE /EA-0M3; (3) Environmental Assessment on Shipment of Taiwanese Research Reactor Spent Nuclear Fuel,1986, DOE /EA-0321; (4) Environmental Assessment on Shipment of Taiwanese Reasearch Reactor Spent Nuclear Fuel (Phase I),1988, DOE /EA-0363; (5) An Assessment of the Safety of Spent Fuel Transportation in Ubran Environs, Sandoval ct al.,1983, SAND 82-2365; and (6) Transportation of Radionuclides in Urban Envimns: Draft Envirocmental Assessment,1980, NUREG/CR 0743.
3,0 WORK TO BE PERFORMED AND EXPECTED RESULTS A. Scope of Work The estimates of spent fuel transportation risks developed by the performance of RADTRAN calculations for NUREG-0170 are believed to be quite conservative. Thus, the accident risks associated with the transportation of spent fuel in real casks are likely to be bounded by the accident risks estimated for the generic cask examined for NUREG-0170. This conclusion could be demonstrated by performing a very large number of risk calculations that treat all possible combinations of the real transport casks and routes that may actually be used to transport spent fuel from reactors to interim or permanent storage facilities. His computationally intensive approach is not warranted. Instead, development of distributions for those RADTRAN input parameters th t specify route and cask characteristics and examination of the impact of these distributions upon spent fuel transponation risks using stmetured Monte Carlo analysis mithods is proposed. Performance of structured Monte Carlo analyses is proposed because such aulyses allow estimates of expected (mean) risks and the rcnge of these risks to be efficiently developed without having to develop specif;c input for a very large number of RADTRAN calculations.
Thus, to meet the principal objective of this study, demonstration that the NUREG 0170 estimates of spent fuel transportation risks cound the risks that will be associated with the currently anticipated shipments of spent fuel in real casks, only a carefully structured set of RADTRAN analyses needs to be performed, provided that the technic 31 bases for the input data used in these calculations are fully described and documented.
B. Approach RADTRAN input parameters will be divided into two groups: more important input parameters, for which distributions will be developed; and less important parameters, for which best estimate values will be developed. The division will be made using the results of past RADTRAN calculations, especially parameter sensitivitv calculations. Distributions will be developed for route parameters (route lengths; urban, suburban, and rural length fractions, population densities, and accident rates for cask transport by truck and train), for cask dependent parameters (accident source term release probabilities and release fractions), and for any other RADTRAN input parameters that strongly affect risk estimates. For all other RADTRAN input parameters, a best estimate value will be selected and briefly justified.
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Rotac parameter distributions will be constructed using the results of the very large number of II!GHWAY and NTERLINE calculations that have been performed to support past RADTRAN calculations, including if possible those recently performed by ANL hs part of the MPC EIS.
I Truck and train accident rates will be developed from literature data, especially from the state-level accident data published by ANL.
Accident release fracticas and release probabilitics will be developed using a Modal Study accident matrix. Accident velocities and fire durations will most likely be used to define matrix breakpoints so that the response of several representative casks can be treated by a single matrix.
Durations of hydrocarbon fuel fires required to fail cask seals, to cause the radiation shield layer to slum, and to significantly increase the release of volatile fission products will be esumated using a bimple lumped parameter model of the themial response of each representative cask to an l engulfing pool fire. Representative casks will be selected by review of the properties and designs l
of the casks that might be used to transport and temporarily store spent commercial reactor fbel, especially the casks considered in the MPC EIS.
For each representative cask examined, accident velocities that lead to minimal and major cask failures (i.e., hole sizes that lead to slow and rapid depressurization of the cask) will be estimated using the results of the many r:tudien and tests of cask behavior during impact events that have been performed since the publication of NUREG 0170. Results will be developed for representative sets of impact surfaces and impact enr,les. Wherever possible, Modal Study l methodologies and data will be used to estimate or extrapolate the response to impact events of l
the representative casks selected for study. Itaving developed distributions of cask failure hole sires, release fractions will be estimated for each hole size using fuel rod release fractions taken from the literature and cask-to-enyhenment release fracuens developed by MELCOR vapor and aerosol transport calculations performed for the TN 125 cask.
Accident malth bin probabbities (i.e., acciNnt source tenn probabilitics) Will be developed by
- i conoucting simple truck and train accident event trees. Branch point probabilities on these trees will 1 developed by review of past tmek and train tnmsportation risk studies, especially the Modal Study, modified if necessary to reficct more recent accident de'.a where available.
Given best estimate values for less important RADTRAN input parameters and distributions for more important input parameters, a series of structured Mor.te Carlo (Latin Hypercube Sampling)
RADTRAN analyses will be performed. Standard regression methods will then allow cxpected (mean) values of risk results and the rnge of the>e results to be developed from the results of the Individual RADTRAN calculations (eletrnts of the 1;stin Hypercube Sample). Comparison of these results to the results previously developed by NUREG-0170 will . hen she,v whether the NUREG-0170 results bound the results obtained using representative casks and routes that typify
- he anticipated shipments of spent nuclear reactor fuel.
C. Tasks This section describes each program task, specifies the task deliverable, and presents estimates of the task completion date and of the level of effort required to ecmplete the task.
6
09el4/90 09:08 Csos 644 0244 oRG.o 6320 2006 I. Phase ! Tasks
- a. Resicw of RADTRAN Input Parameters (8 man weeks)
Results of transportation risk studies that used RADTRAN and of sensitivity studies of RADTRAN input parameters will be reviewed to identify those RADTRAN input parameters that strongly influence risk (Important Parameters) and those parameters that have a les>er impact on risk (Less Important Parameters). The following criteria will be used to identify important and Less important Parameters. Important parameters (C,) should approximately double or halve risk estimates (R) when their input values are doubled (R-k,C i or R=k/C i where kpl.0). Less imprtant parameters have a much smaller impact on risk (R-k,C i or R-k,/Ci where k i 1.0).
Best estimate values will be selected for all Less important RADTRAN input parameters, and the basis for the selected value will be briefly summarized. Subsequent tasks will develop ranges and distiilrctions for important RADTRAN input parameters (e.g., mute parameten, cask inventories, and parameters that depend strongly on cask designs and material properties, specifically source term probabilities and release fractions).
Some RADTRAN input parameters, or the models in which they are implemented, have been extensively studied since NUREG 0170 was published. For example, the DEIR V study indicates that radiation risk coefficients should be revised upward by about a factor of two; and as a part of the development of RAIyTRAN Version 5, the models used in RADTRAN to calculate doses incurred when a RAM transport vehicle stops a'some facility (STOP doses) have been extensively revised. Discussion of the selection basis for the values of less important parameters will be more thorough whenever a patameter value or the model in which the parameter is implemented has been extensively studied since NUREG-0170 was published.
After the review of RADTRAN input has been completed, the consequence measures (e.g.,
population dose, latent cancer fatalities) and the reference number of shipments (single shipment, number of shipments per year, full shipment campaign), that will be used to compare the results of this study to those developed for NUREG 0170, will be chosen. Likely shipping schedules for the shipment of spent commercial power reactor fuel will be reviewed before these selections are made.
Deliverable: Initial draft of chapter for final report Completion Date: December 31.1996
- b. Updated Truck and Train Accident Statistics (5 man-weeks)
The truck and train accident statistics used in NUREG-0170 will h updated to reflect more recent data, especially the data developed for the Modal Study and the state truck and train acci dent data developed by ANL and used by ANL during the preparation of the MPC EIS. To facilitate the use of Modal study and MPC EIS accident data, LLNL and ANL will be asked to 7
,' os<t6 se 09: 04 Csos 644 0244 ORG.o esto ZoM provide the new data in electronic form. The NRC technical monitor will be promptly notified if this data can not be obtained in electronic form or can not be easily converted to electronic fonn by scanning ofpublished documents.
13ecause US interstate speed limits have recently been increased and the American Association of Railroads has proposed the abandonment of the rail roads'self imposed operating restrictions for trains that are carrying RAM (the 35 mph speed limit for trains carrying RAM and the requirement that one train stop and the other restrict its speed to 35 mph when a RAM train is passed by another train), the impact of higher operating speeds on truck and train accident statistics will be carefully examined.
Deliverable: Initial draft of chapter for final report Completion Date: March 31,1997
- e. Route Charseteristics (7 man weeks)
RADTRAN transponation routes are constructed as sets of route segments (links). For many RADTRAN analyses, only dure aggregate links are used, an urban, a suburban, and a rural link.
These three aggregate links are constructed by weighted summation of the characteristics of all of the individual urban, suburban, and mral links that define the full transportation route. For this study, ranges and distributions will be developed for total route length, the fractions of that length that pass through urban, suburban, and rural areas, and the truck and train accident rates and population densities that characterize those areas. Initial distributions for these parameter values will be constmeted using results from the very large number of HIGIIWAY and INTERLINE calculations that have been perfanned for past transportation studies. Next, a representative sample of possible locations for new interim RAM storage facilities will be reviewed to determine whether the characteristics (RADTRAN route panuneter values) of routes to and from these facilities are well represented by the initial dirributions. If this review shows that the charucteristics of routes to and from these interim facilities are not well represented by the initial distributions, the characteristics of a representative set of routes that involve these facilities as route tennini will be developed by the performance of additional HIGilWAY and INTERLINE calculations, and the initial distributions of route parameter values will be modified to reflect the results of the additional lilGHWAY and INTERLINE calculations. Finally, transport of ILui by barge, ship, or heavy haul truck to rail termini from reactor sites and interim facilitics will be examined in order to update the accident statistics that apply to such transport originally developed for NUREG 0170.
Delivetable: Initial draft of chapter for final report Completion Date: June 30,1997 8
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- d. Representative Casks (5 man wccks) !
The casks that are likely to be used to ship power reactor spent fuel will be reviewed in order to identify a representative set of casks for which release probabilities and release firactions will be -
i developed. This review will consider (1) the Multi Purpose Canister and alternative ca>ks i examined by the MPC EIS, (2) other single purpose casks, dual purpose storage / transport casks, and multipurpose casks that either have been licensed by NRC or are in the licensing process, and (3) any other casks that might be extemively used for the tramport or storage of spent reactor fuel for which design data can be readily obtained. Particular attention will be paid to casks that !
have capacities and weights substantially greater than those of the generic casks that were examined by NUREO 0170 and the Modal Study. Next, two or three representative casks will be selected that have properties that typify the range of properties exhibited by the large set of caska reviewed, and which thus are suitable candidates for the development of release probabilities and release fractions for use in this study. Finally, the properties of these representative casks will be compared to the properties of the generic casks examined by NUIEG 0170 and the Modal Study.
Deliverable: laltlal draft of chapter for final report Completion Date: July 31,1997
- c. Cask Mechaalcal Response Methodology (6 man weeks)
Release of radioactive materials from transportstion casks as the result ofimpact failures depends strongly on the size of the failme. This is because large falhues (hole sizes 2: 10 cm') lead to rapid cask depressiriztlon and consequently efficient transport out of the cask of radioactivit7 released from spent fuel to the cask interior. Conversely, for small failures (hole sizes s 1 mm )
cask depreuuriration is slow and consequently deposition of radioactive vapors and aerosols onto cask surfaces is substantial which greatly attenuates release magnitudes. In order to quantify these effects, the results of the Modal Study, other theoretical studies of the mechanical response of casks to impacts, and experimental studies of the effects ofimpact onto surfaces on cask integrity will be reviewed. Correlations between the magnitude of the cask failures that might be produced by impact and impact angle, impact velocity, and the hardness of the impact surface will be identified. Following completion of the review, a set of approximate correlations will be developed that can be used to credibly estimate the impact velocities, 3 angles, and surface hardnesses required to cause minimal (1 mm holes) and major (10 cm holes) failures in typical transportation casks. Note that the NRC Technical Monitor will be promptly notified if this review indicates that a credible method for estimating the magnitude of cask impact failures can not be developed from available models and data without the performance of new tests and/or intensive computations.
Deliverable: Initial draft of chapter for final report Completion Date: August 31,1997 9
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- f. Revised Proposal (! man. week)
After all Phase I tasks have been completed, the results of these tasks will be presented to NRC at a review meeting. Discussions at that meeting will identify any changes in program direction that are required by the Phase I results. If significant changes in program direction are required ,
by the review of the Phaw I results, a revised proposal will be submitted to NRC that reflects the i' needed changes.
Delherable: Revised Proposal i Completion Date: September 30,1997 II. Phase !! Tasks .
- a. Cask Moebanleal Response Model (10 man. weeks)
The responw of the representative casks to impact onto surfaces will be estimated using the correlations developed for Task 3.3.1.5. Specifically, threshold and catastrophic failure velocities will be estimated for au combinations of the set of representative casks, four impact ;
surfaces (rigid, hard rock, soft rock /hard soil and soft soll) and four impact angles (angles of 90, 70,10, and O' between the cask axis and the impact surface). In developing these estimates, extrapolation of the results of less severe impacts to more severe conditions will be bar,cd on analytical results, and the analytical results used to make these extrapolations will be conelated with available test data wherever possible. Impact onto a rigid target of each of the typical casks examined will be modeled using finite element methods and a coarse mesh. The velocities that 8
lead to the two damages levels (1 mm and 10 cm3 holes) predicted by these analyses will be increased for accidents onto real targets using methods available in the literature. All estimates will reflect the effects of thermal and radiological embrittlement of cask and/or cladding material.
DcIlverable: Initial draft of chapter for final report Completion Date: January 31,1998
- b. Simple Cask Thermal Response Model(3 man weeks)
A simple one dimensional lumped parameter thermal model of each representative cask will be developed and used to estimate the durations of engulfing hydrocarbon pool fires that are required (a) to heat cask seals to their failure temperature, (b) to heat cask radiation shield materials to the temperatures at which they slump, and (c) to heat the spent fuel carried in the cack to temperatures that cause volatile fission products (e.g., Cs and Ru) to be released in significant quantities as vapots from the fuel.
Deliverable: Initial draft of chapter for final report Completion Date: February 28,1998 10
opssess os:ce C sos aid c:44 cc.c.o esto 0 010
- c. Aceldent Source Terms (8 man weeks)
Accident source terms will be expressed as the product of a cask inventory and a set of accident release fractions. Accidents will be binned into a generic accident matrix, one matrix for truck accidents, and one for train accidents. Matrix break points (bin boundaries) will be defined by accident velocities on the y axis and the durations of engulfing hydroca: bon pool fires on the x.
axis. The relationship of these generic accident metrics (velocities and fire durations) to reguletory test conditions and the reasons for selecting such simple metrics to represent complex mechanical and thermal accident environments will be clearly explained.
c.1 Hin Release Fractions Bin release fractions will be developed for five chemical element groups: Co (CRUD), Kr (noble gases Cs which will be assumed to be released as CsOll, Ru which will be assumed to be released as RuO4 , and particles. Element group release fractions (F) i will be expressed as the product of a release fraction from spent fuel to the cask interior (Fra) and a release fraction from the cask interior to the emironment (Fw). Thus, Fi = Fra Fw. Fra values will be based on Wilmot's application to transportation accidents of the experimental results of Lorenz, modified as is appropriate to reflect impact nacturing of fuel. Fw values will be based on the results of fission product transport calculations performed for a TN 125 cask using the MELLOR thennal hydraulic / fission product transport compartment code. The Feci values will be estimated assuming that *.he size of the failure hole produced by an impact increases linearly with increase 2
of accident velocity between a threshold velocity that generates a 1 mm hole and a larger velocity that leads to a failure that allows rapid cask depressurization, which for this study will be taken to be a 10 cm' hole.
e.2 CaskInventories Inventories will be calculated for each representative cask using the ORIGEN code. The calculated inventories will reflect shipment of older fuel, shipment of greater than Class C wastes, and the possibility of multi cask rail shipments. To support examination of the impact of the length of time that spent fuel is stored at the reactor site before it is shipped to an interim or -
pennanent storage facility, inventories will be calculated at a variety of times afler removal of the spent fuel from the reactor, e.3 Bin Probabilities: Simple Event Trecs Din probabilities will be estimated by constmeting simple event trees. Event tree branch-point probabilities will be estimated from accident data or from Modal Study results. Accident scenario (event tree path) probabilities will be calculated by taking the product of all of the branch point probabilities that lie along a single path on the tree. Accident matrix bin probabilities will then be generated by nosting these path probabilities into the matrix bins and averaging the probabilities that fall into individual bins.
Deliverable: Initial draft of chapter for final report Completion Date: April 30,1998 11
op2pse 09:07 C oos 644 0844 oRG.a esto 0 011 f
- d. MADTRAN LIIS Calculations (7 man weeks)
The distributions constructed for the RADTRAN parameters that were determined to be important Parameters by the review of RADTRAN input parameters, and the point estimate values selected for the Less Important parameters, will be med to calculate updated incident free risks and accident risks for the transportation of comrnercial rpent reactor fuel by truck and train.
Because previous tasks have developed distributions for toute parameters, inventories, and source term sciene fractions, this task needs to develop distributions only for any remaining important parameters, Distributions for these parameters will be defmed using the rnost recent data available.
Input values for a set of RADTRAN calculations of size N will next be dieveloped by selecting values for Important Parameters from their distributions by means of Latin Hypercube Sampling (LilS). 'Ihe value of N will be large enough to produce statistically significant results (typically N ? 2No,, m ). The LliS procedure will generate N sets of values for the important Parameters. Each set of input values for the important Parameters will be combined with the point estimate values selected for the Less important Parameters, thereby generating N complete RADTRAN input files. After all of the N individual RADTRAN calculations have been performed, standard statistical methods will be used to develop estimates for the mean,10th, and 90th percentile values of the distributions of consequence measures ofinterest (e.g., population dose, latent cancer fatalities). Comparison of the resulting distributions to the results previously developed during NUREG-0170 is then expected to show (1) that for any consequence the mean result developed for a range of real casks and routes lies well below the mean resuh developed for NUREO.0170, and (2) that the mean result developed by NUREG 0170 bounds most of the range of the results developed by this task using LliS methods.
Deliverable Initial draft of chapter for final report Completion Datet September 30,1998 111. Phase til Tasks
- a. Other Topics (5 man weeks)
This task will also examine the following topics, document the results of the examination, and incorporate the documented results into the fmal report: Any changes since NUREG-0170 to the models implemented in the RADTRAN code, conservatisms in the NUREO-0170 dose models, centerline individual doses, cumulative individual doses, the impact on cumulative individual doses of the movement (i.e., change of residence location) of peopic into and out of a region (route link) where transportation accidents inay occur, worker doses, evacuation times, conservatisms in the estimation of the cancer risks associated with low doses delivered at low dose rates, envirotunental justice, and the ymdity assurance methods employed to assure the credibility of the results obtained by this study.
Deliverable: Initial draft of chapter for final report Completion Date: December 31,1998 12
09/1s/96 09:07 C s0s $44 0244 ORG.0 6320 @ 013
- b. Anal RepoH (10 man. weeks) ,
The results of the preceding tasks will be documented in a final report that consists of brief and extended summaries of the technical results, written so as to be accenible to concerned citizens, followed by chapters that describe and discuss the technient methods and computational results developed by the study in sufficient detail to allow transportation risk assessment experts to Judge the valldhy of methods used and the results obtained. The report will summarize and discuss the new risk estimates, compare these estimates to those developed by NUREG-0170, and thoroughly discun the differences.
Deliverable: Draft of final report for review by NRC ,
Completion Date: March 31,1999 L D. Completion Date The proposed completion date for this program is March 31,1999. Revisions to program tasks or schedule could cause this date to change.
4.0 PROPOSED PERSONNEL A. NRC John Cook is the NMSS Techrdcal Monitor for this program. Technical instructions may be issued by Mr. Cook from time to time during the performance of this program. Techrdeal instructions shall not constitute new task assignments, er changes to existing task assignments that alter program costs or schedules. If task revisions are required that entall additional wo:L or ,
changes in program schedules, these revisions will be made by submission by SNL for approval l by NRC of a revised program proposal. Directions for changes in scope of work, cost, or period of performance will be coordinated through the NMSS Project Manager, David Tiktinsky H. SNL The technical lead for this program will be J. L Sprung. Dr. Sprung is a Ph.D. chemistry graduate of UCLA with 20 years of experience at Sandia National Laboratories managing and performing radioactive material safety, risk, and consequence assessments. Major assignments performed by Dr. Sprung include assessment of fission product transport models for the development of the MELCOR code, direction of the consequence calculations performed for NUREO.ll50, and assessment of the risis associated with ship accidents that occue in ports that l was performed for the Foreign Research Reactor Spent Fuel EIS.
l S. Neuhauser will be the technical lead for Transportation Risk Analysis tasks. Dr. Neuhauser j has a Ph.D. in Biology from Harvard University. She has been task leader for RADTRAN l
l l
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(
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09/16/96 09:08 C505 644 0244 oRG o 6HO @ 013 development for the past ten years, during which time RADTRAN 4 and P ADTRAN $ have been developed. She has perfonned ntunerous risk analyses and auisted it, the preparation of NEPA documents for the DOE and other customers. She has developed new analytical methods to address problems unique to RAM tran>portation Prior to joining the transportation group, Dr.
Neuhauser worked on the WIPP FE1S and the UMTRA and Beneficial Uses of Radiation Programs.
G. S. Mills will be the technical lead for RADTRAN LilS Calculations. Dr. Mills, a Ph.D.
phystes graduate of the University of Texas, has 30 years of experience in applied physics research and development and transportation risk analysis. IIis experience in transportation risk analysis includes work on numerous radioactive material EAs and EISs (e.g., Foreign Research Reactor Spent Fuel EA, Sapphire II EA, Plutonium Disposition EA). In addition, he has applied the Latin liypercube Sampling technique to sensitivity studies of accident-risk inptrt variables and demonstrated the improvements in risk estimates obtainable from application of LHS to imnportant input parameters. Other, transportation risk related, development work has included acquisition of data for improved defmition of input parameten and distnbution ibnctions. Before working in transportation risk analysis, he supported underground nuclear effects testing with radiation diagnostic development, fielding, and radiation transport / material interaction modeling D. J. Ammerman, a ph.D. Chil Engineering graduate of the University of Minne>ota, will be the technical lead for Cask Mechanical Behavior tasks. For the past eight years, Dr. Ammerman has served as project leader for structural analysis issues related to radioactive material transportation packages, has directed anNor perfonned non linear dynamic analyses of transportation packages, stnictural code benchmarking studies, structural testing of transportation packages, evaluation of the stmetural response of packages to transportation accident conditions, determination of the safety factors for NRC Reg. Guide 7.6 designed pacutges, and assessments of off site radioactive material tnmsportation capabilities for Rocky Flats and Hanford.
J. A. Koski will be the technical lead for Cask Thermal Behavior tasks. Dr. Koski has a Ph.D. in l Thermal Science from Texas Tech University.11is 33 years of experience working on thermal i
science problems includes five years in thermal modeling for radioactive material transportation studies, eight years of thermal modeling of magnetic fusion high heat flux components, and two l
years of modeling and development of data acquisition methods for the measurement of thermophysical properties of materials. Defore joining Sandia, Dr. Koski had nine years of nuclear industry design experience with Bechtel Power Corporation.
l 5.0 MEETINGSTFRAVEL l
It is anticipated that program review meetings will need to be held at the conclusion of each program phase. If any of these meetings are held in Washington, DC, then SNL travel costs will be about $3000 per meeting.
l 14 i
4 ** OS/18/to 09:09 G s0s $44 0244 oRG.s 6320 @0t4 I i
1 This study is not anticipated to require any foreign travel. An Outside Continental United States i (OCONUS) aethity form will be submitted to Doe with this proposal for any anticipated foreign l travel. An NRC Fonn 445 will be processed 40 days prior to OCONUS travel.
Deviations from the travel submitted as part of NRC form 189 and accepted by lauance of an NRC form 173 will be coordinated with the NRC project manager as soon as the need for such a deviation is identified to ensure it will not interfere with the timely completion of proposed work.
6.0 NHC FURNISiiED MATERIALS No program tasks are expected to require materials that must be fumished by the NRC in order to be performed. De final report for this program will be published by NRC.
7.0 RELATIONSHIP TO OTHER PROJECTS SNL pro]cets that are develop risk assessment metnods or data pertinent to this program include:
Development of RADTRAN 5.0; periodic updates of the RAGR and RAMPOST databases; development of OIS based route analysis methodology with environmental justice applications (proposed for FY97); and publication of RADTRAN 5.0 sensitivity analyses that parallel earlier analyses performed for RADTRAN 4 and RADTRAN 111 as part of on going code QA and applications efforts.
8.0 REPORTING REQUIREMENTS AND SCHEDULE A. DcIlverables The final report for this study will contain separate chapters that document the results of each program task. To facilitate the preparation of that report, initial chapter drafts will be prepared as each program task is completed. Accordingly, the deliverable for each program task is the initial draft of the final report chapter that describes and discusses the data gathered, analyses perfonned, and results generated to complete the task documented by that chapter.
No more than 30 copies of any interim report will be fumished to the NRC project nianager.
N. R. Ortir, Director, Nuclear Energy Technology, Organization 6400, Sandia National
. Laboratories. Albuquerque, NM, has been designated as the authorizing official for publications of NRC Form 426A.
l H. Monthly Letter Status Report (MLSR)
A Monthly Letter Status Report (MLSR), following the Management Directive i1.7 instmetions, will be submitted to NRC by the 20th of each month. The MLSR shall be delivered to the David Tiktinsky, the NMSS Project Manager for this program, and to the Division of Contracts and I$
- opets'se opios O sos s44 c:44 oRG.0 6320
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Property Management (DCPM), Office of Administration. Additional distribution will be made to John Cook, the Technical Monitor for this program, and to Earl Easton, both of NMSS. The .
Financial Status section of the MLSR will follow NRC Management Directive 11.7's MLSR Financial Status Report format to the extent permitted by the current SNL Financial System.
C. Milestone Chart The following Milestone Chart sununarizes the esthnstes of task schedules and costs describes more fully below. Task costs are based on an estimate of $5K per man week of effort, which j includes computing and support services, but not travel costs or DOE Albuquerque overhead.
Timelines in the Milestone chart depict clapsed time, not man weeks of work.
Mllestone Chart Task ww kg lrrs7 Irres Inps l OstDJrmassJJAsouDJrathasJJAsempJrauusJJAs
, Phase I Review of RADTRAN input Parameters a 40 ...
Updated Truck and Train Accident Statistics 5 25 ..>
Route Characteristics 7 35 -->
Representative Casks s 25 >
1mpact Methodology 6 30 .>
Revned hopmal 1J x FY97 Labor 32 16o Travel 3 DOE Overhead (at 4.3 %) I FY97 Cost 170 Phase 11 Cask Mec.hanical Response Model 10 50 --->
Simple Cask Thermal Response htodel 3 1s ->
Accident Source Tenns 9 40 ..=
- RADTRAN LilS Calculations 2u ----> I FY98 Labor 28 140
' travel 3 DOE Overhead (at 4,3 %) 6.
FY98 Totals 14s Phase III Other Topics 5 25 -->
Final Report 1.0 10 ">
TY99 Labor - 15 75 Travol 3 DOE Overhead (at 4.3 %) 1 FY99 Totals 81 Program Totals 75 400 16
8
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D. Level of Effort (estimated at $$600 per man week) 14velof Effbrt Estlasted (man weeks) NRC Cost Phase ! Task Review of RADTRAN !nput Pararneters 8 840,000 Updated Truck and Trair Accident Stanstics 5 25,000 Route Characterisdcs 7 35,000 iteptmentative Casks 5 25,000 ,
Impact Methodology 6 30,000 Revned Proposal 1 5,000 Phase !! Teoks Cask Mechanical Response Model 10 so,000 Simpic Caak Thermal Response Model 3 15,000 Accident Source Terms e 40,000 RADTRAN 1.HS Calculadom 7 36,000 Phase III Task Other Topics 5 25,000 FinalReport 10 En con ,
Labor Subtotals 75 $375,000 Travel (at $3,000 per Waldugton meeting) s,000 DOE Overhead (at 4.3 %) 1a.ono Tntsicost $400,000 9,0 SUHCONTRACTOR/CONSULTANTINFORMATION Use of subcontractors or consultants on this study is not presently anticipated. Needed technical support that might require the use of subcontractors or consultants will be first discussed with the NRC Technical Monitor in crder to establish technical requirements and then with the NRC Project Manager to identify any impacts on program fhnding or schedules.
Resumes for proposed subcontractors, if applicable, have been provided under Section 4 of this proposal. Acceptance of this proposal Indicates approval of personnel proposed herein.
Subsequent subcontractor efforts not described in this proposal will be managed per NRC Directive 11.7, Part X(B)(c)(page 61) conflict ofinterest issues are covered in section 11 of this proposal which considers all proposed personnel, including subcontractors.
10.0 SPECIAL FACILITIES,IF REQUIRED This study is not expected to require any special facilities.
17
9 ** 09/16e96 09:36 C808 644 0244 ORG.o 6320 2,003 11.0 CONFLICT.OF INTERESTINFORMAT10N No significant contractual or orgamzational relationships of Sandia National Laboratories, its employees, or anticipated subcontractors and/or consultants exist with industries regulated by NRC and suppliers thereof that might give rise to an apparent or actual conflict ofinterest.
US Nuclear Regulatory Commission (NRC) recognizes that Sandia National laboratories will perform the work assigned to DOE under this project pursuant to the "Non Department of EnerEy Funded Work" provision of the DOE /Sandia Corporation contract for the management and operation of Sandia National Laboratories.
The DOE approved Sandia Corporation OCl Management Plan goveming access to and flow of Information between Sandia Corporation and its Lockheed Martin afnliated orgardations will apply to all work performed under the terms of this project. This Sandia Corporation OCI Management plan and the procedures resulting form the plan are subject to DOE audit at all times. A copy of the Sandia Corporation OCI Management Plan is available upon request to Ken
}{aug, Contracts Center, M/S 0185, Sand:a National Laboratories, Albuquerque, NM 87185 0185,(505) 845 7750).
In accordance with the Organizational Conflicts ofInterest terms of the DOE /Sandia Corporation contract, Sandia Corporation, including any ofits officials who may acquire information as part of their management responsibilities, is prohibited from further disseminating any third party proprietary data or government sensitive data or information (as indicated by restrictive markings identifying the data and information so protected) to its Lockheed Martin afDliated organizations.
In view of the above, the NRC hereby agrees that Lockheed Martin affiliates of Sandia Corporation shall not be restrained or restricted from competing for any related follow-on contracts or subcontracts to be awarded by the NRC that relate to work under this project.
12.0 CLASSIFICATION OR SENSITIVITY,IF APPLICAHLE Tids study is not expected to pmduce any classified or sensitive information or material.
13.0 ADDENDUM COST AND SCHEDULE INFORMATION 1
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most.h 0 N D J F M A M J J A & I k$ 15.7 15.7 10.4 4.3 8.3 9.4 12.5- 12.5 25.0 20.2 15.7 8.3 i rrps l Month 0 W D J F M A M J J A 8 I k$ 15.6 18.6 10.4 18.8 23.0 15.6 10.4 7.3 7.3 7.3 7.3 10.4 Fff9 Meath o N D J F M k$ 9.4 s.4 7.3 17.6 17.6 19.7 A S,m<tlas Plan. NRC Form 189 (Part 3), is included. j 15.0 DOE OVERHEAD DOE departmental overhead charges of 4.3 percent for FY97 and subsequent years will be added l on all billings.
s 16,0 DOE ACQUIRED MATERIAL No propeny purchases over $500 are currently planned.
Purchases ofitems $500 or greater not identified in this proposal will be requested separately in writing. When property is purchased, it will be reported in the MLFR. Property will only be tracked at the $5000 or greater level by DOE, or if property is sensitive. -
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Total Pages (including this cover sheet):
~ MESSAGE:
hi*,pstujbns in $ csh cltauf hu A 6 i p }& A)U/?EG 017a rpmt JL0 sN<fwaf m A n .5 n e. a d d b a A d 4 Cetseg cat <. m m a sfpurh pmjeM h4 FROM: FAX Number: 844 0244 Name: ~~Te n.i % r%L Phone: / foI- de-o/37
99/19/96 09:42 C505 444 0244 oRG.o 6330 @ 002
, r L Phase 1 Tasks
- a. Heview of RADTRAN Input Parameters (8 man.*ccks) ;
i' Results of transportation risk studies that used RADTRAN and of sensitivity studies of RADTRAN input parwneters will be reviewed to identify those RADTRAN input parameters i that strongly influence nsk (Important Parameters) and those parameters that have a lesser spact !
on risk (Less Important parameters). The following criteria will be used to identify important and Less important parameters. Important parameten (C i) should approximately double or halve risk estimates (R) when their input values are doubled (R=k i i C or R=k,/C i where kpl.0). Less important parameters have a much smaller impact on risk (R-k i C, or R=k/C3 where ik al.0).
Dest estimate values will be selected for all Len important RAD TRAN input parameters. and the basis for the selected value will be briefly summarized. Submquent tasks will develop ranges and distributior.) for Important RADTRAN input parameters (e.g., route parameters, cask inventories, and parameters that depend strongly on cask designs and material properties, specifically source term probabilities and release fractions).
Some RADTRAN Input parameters, or the models in which they aie implemented, have been t extensively studied since NUREO.0170 was published. For example, the BEIR V study
, indicates that radiation risk coefficients should be revised upward by about a factor of two; and as a part of the development of RADTRAN Version 5, the models used in RADTRAN to calculate doses incurred when a RAM transport vehicle stops at some facility (STOP doses) have been extensively revised. Discussion of the selection basis for the values of less important parameters will be more thorough whenever a parameter value or the model in which the parameter is implemented has been extensively studied since NUREO.0170 was published.
After the review of RADTRAN input has been completed, the consequence measures (e.g.,
population dose, latent cancer fatalities) and the reference nurnber of shipments (single shipment,
! number of shipments per year, full shipment campaign), that will be used to compare the results l of this study to those developed for NUREO 0110, will be chosen. Before v -ie selections are
! made, the NUREG-0170 standud shipment model for spent fuel will be updat using MFC EIS data and data in the Integrated Data Base.
Deliverable: Initial draft of chapter for final report Completion Date: December 31,1996 l b. Updated Truck and Trala Accident Statistics (5 man. weeks) l The truck and train accident statistics used in NUREG 0170 will be updated to reflect more recent data, especially the data developed for the Modal Study and the state truck and train accident data developed by ANL and used by ANL during the preparation of the MPC EIS. To facilitate the use of Modal study and MPC EIS accident data, LLNL and ANL will be asked to 7
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i 09/19<p6 09:43 Csos $44 0244 oRG.o 6320 2003
- d. RADTRAN LHS Calculations (7 man weeks)
The distnbutions constructed for the RADTRAN parameters that were determined to be Important Parameters by the review of RADTRAN input parameters, and the point estimate values selected for the Less important Parameters, will be used to calculate updated incident free risks and accident risks for the transportation of commercial spent reactor fuel by truck and train.
Because previous tasks have developed distributions for route parameters, inventories, and source term release fractions, this task needs to develop distributions only for any remaining Important Parameters. Distributions for these parameters will be defined using the most recent data available.
Input values for a set of RADTRAN calculations of size N will next be developed by selecting values for important parameters from their distributions by means of Latin liypercube Sampling (LilS). The value of N will be large enough to produce statistically significant results (typically N k 2N,,, % ). The Lits procedure will generate N sets of values for the important Parameters. Each set of input values for the important Parameters will be combined with the point estimate values selected for the Less important Parameters, thereby generating N complete RADTRAN input Sles. After all of the N individual RADTRAN calculatie:s have been perfonned, standard statistical methods will be used to develop estimates for the mean,10th, and 90th percentile values of the distributions of consequence measures ofinterest (e.g., population dose, latent cancer fatalities). Consequence values will be developed for single r,hipments and for the number of shipments per year predicted by the updated spent fuel shipment model.
Comparison of the resulting values to the values previously developed for NUREO-0170 is then expected to show (1) that for any consequence the mean result developed for a range of real casks and routes lies well below the mean result developed for NUREO-0170, and (2) that the mean result developed by NUREG-0170 bounds most of the range of the results developed by this task using LHS methods.
Dellverable: Initial draft of chapter for final report Completion Date: September 30,1998 III.' Phase III Tasks
- a. Other Topics (5 man weeks)
This task will also examine the following topics, document the results of the examination, and incorporate the documented results into the final report: any changes since NUREG 0170 to the models implemented in the RADTRAN code, conservatisms in the NUREO 0170 dose models, centerline indhidual doses, cumulative individual doses, the impact on cumulative individual doses of the movement (i e, change of residence location) of people into and out of a region (route link) where transportation accidents may occur, worker doses, evacuation times, conservatisms in the estimation of the cancer risks associated with low doses delivered at low dose rates, environmental justice, and the quality assurance methods employed to assure the credibility of the results obtained by this study.
Deliverable: Initial draft of chapter for final report Completion Date: December 31,1998 1:
URC.* 0830 2 001 06/ft/98 08:36 9 806 844 0244 ,
/(0 (0, uss 3
oandia Nationali.aboratories '
P. O. Box 5600 .
Albuquerque, New Mexico 87185 q
O r. H psipoN3 FAX TO: DATE: -
Name: Dw:.( 7ikbky' _
Fax Number: 3o1-df-Ste/
Organization: A/M SS Address:
, [ Phone: .
Total Pages (including this cover sheet):
MESSAGE:
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SasMlla Nosonal Laboratodos 3 P.O.esase00 Anwousnps. New usmos of tesenewt yew tse nwel j i
t Sepussber 24,1996 i
ur. John J. unensi oheter Proomm Menseen*t Poky Development and Analyse etst !
omos of Nuoiser Metertal SoIMy and asinguents !
Am Mr. Oeved T11 ensky, M8 Th28 U. s. Nuclear Regulatory Commiselon WeehWglen. D. C. J00664001 Deer Mr.t.hohari:
tulq>et NRC Rommet for Ptollrrinary Proposal for Job Code: J6100, Rev. O, teed. *Revelid NUREG4170 Spent Fuel Shipment Risk Esemates' anetened ter yow consuwonon is tu wismal plus two copies of N pmeminary out# eat proposal Sinos this is e M ;.ai proposet, he cost sammetas may very supNey tom he final proposal ftpures please note that the Request tar e Fhel Proposal can now be addressed caractiy to SNL per etteched instrussens ousesone conoeming this preeminary proposet should be esemesed to Juomy L sprurg et (sos)04441H.
smoerWy, M A.cI d ~
Richwd YoeMimum,idenager orpenteston eM1 M14:Dh Enclosus Originalplus two copes >
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When regwsting a Final Proposal, faxing as adynace copy of the request to the SNL Project Manager, consuneet with mailing of the f<rmal regwst, will Mlitsee a timely subadual of the FlaalPropoest.
OR10lNAL RBQUEST FOR HNAL PR0f05AL. Addreas to:
Dr. RicheniYoshhnws '
MS 0742, Organlantion 6641 sandiaNationalLaborosories P.O. Box 5800 Albuquerque,NM 87185 xxxx (xxxx = MS number)
COPIES OF REQUEST FOR HNAL PROPOSAL Addrons to:
- 1) Dr. John E.Kally, Manager Nuclear Ranctor SafWy Program Ane MS4742.Organisation 6414 SadiaNM Labwasories P.O. Box 5000 Albuquerque,NM 87185 4742
- 2) Mr. J. D.Chever, Pav}ects Manager Work for Others ManagementTeam Science and Technology Transfer Division U.S. Departmaant of Energy Albuquerque Operations Office P.O. Box 5400 Albuquerque,NM 871855400
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SammaNedemollabernendes(eft) l Propeast for Pn$ set Eatidad "Revaudselse of NUREG 4IM Apeet Feel Sh5snamt Risk Eselmaeus' JobCode J81de (EsAwenee NRC regnest for a prealmenary propeeni dated Aagast 16,19N) ,
1.4 INTRODUCrlON t
A. anstegrosed (NRC) lasued a generie I
InA gepesmher of 1977,
==a==== tbs Nuclear (EIS), antitled Raguis+
" Final Enviri=h Sistement cry on thera==lantaa^ i
,
- of Radioactive Maanrial by Air and other Mos.s," NURBO4170, that covered En; l the transport of all typse of radioactiw maesrial by all transport modes (road, rai l That E!$ provides tw reguistory basis br issunnoe of gemaral liomass ter trans i
radioastin materW under 10 CFA 71. Based in part ca the findings of NUREG-C
' staff conclaled (1) that "the average redist:aa dose to the p;;Mt at risk fhan no transportatiam is a small tension of the lladis reocens i
asneal baskground does," and (2) that "the ranological risk toen ecoldsats in t l-small, amoundag to about omehalf poroset of the mennel . - ; JM risk on an s
' (Summary and Conclusions, NURBO4170, p. vil); and the NRC C = ' 'n cen "presset regulations are adequate to protect the public against L r: =* risk transport of radiaaadw materials"(46 FR 21629, April 13,1 contiadas review."
the in recent chansa in industry and sovemment spent fut manapement strateg spent fuel in assdsters and along meses not spec 1Acally aaantA=ed by t
, perfunned for NURE04170 is anticipated. For exam Storage Installations and/or Contraliasd Storage Facilities in addition to shipme geologic repository. In hat, the OfBoo of Nuolent M additional appuestions are upscend la ihm near futwo, in addition, many chanse made to the risk maamamamat models haplammarad la the RADTRAN code s of that code was used to estimets spent Ami transportationc risks for NURE041 e mudies of spent fhol r; <= risks how beam mosatly compassed, e s.,"shippins o Raspons to Severs Highway and Rauway Accident Constions," NUREG/CR 4 19:7. onen caued no Modal Study, and Argonne Nedanal Laboretury's "Drah M
' Canister Favirana===t Impact Statamant," that contain new or impmved risk maaa=
readels and data.
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Becanas asw das and aanlytical methods me now available to apply to the analysis of spent furi f 2f r r;As, sad because spot fbal is libaly a be shipped to isoikties along soutes and in !
casks not spechelly cannised by NUREO 0!M, NM85 believes that it is row appsprisse to review and evalidate the conclusions reached in NURE04170. Specineally, NMsg wishes to imow whether the risks of the antcpated ii spent fuel shipmaats me bounded by the risks ,
estissesdin NUREG41M. i B. Objeselros
%is study has three objectivw:
Esthussion of the radiological nad nonradiologleal, routine and socidsst, trasportation riaks associated with the asticipated speet that shipasses and dessemination of whether those risks are h=maat by the entiestos and pmjections of spent fuel shipment risks reached in NURBO4170.
R===landan of any outstanding spent that transportation issues or 4em -' coassms not resolved by NUREG 0170 sad the Modal Study.
Documentattom of the approeck, data, and computettonal nesthods used to reestimats spent fuel teasponseios deks in detail suf8ciset to allow other transponstion expens to fh!!y understemd tbs analyses per8mmed, sad pnparados of brief and detailed sammaries of the neutes in a Iban soesssible to comoereed chimes C. Purpsse This study has a three part purpose: (1) Revalidation of the conclusions regarding the ahlpnaast of spent fbst reached in NUREO 0170; (2) dancestration that thoes e-lM- apply to carently anticipated Mpmaan of spent fuel; and (3) developosat and i.
% of the technical bests on which the ev=HA= dam la based. Aner revalidssion, NURBO4170 conclusions about the safmy of spent fuel ablpments couki be cited in the ;,+^ fu portion of _
enviromnental impset docensats prepnied to support the licensing of spent fuel serop or ,
disposal theilities and could also be used to support the listlag (as the result of a Part 72 ruleenaking) of casks that are suitable both for transport of spent fhol to sucii fheilities and for storage of spent fuel et these isollities.
P 1.0
SUMMARY
OFPRIOREFftNtt1B NUREG 0170 was prepared for the NRC by Sandia Naticent Labormories (SNL). SNL also 1ssi x risk
&c:':,:f RADMAN 1, the computer code used to calculats the RAM transpo:
21 Assessments (EAs),
a6==a== reported in NUREG 0170. SNL has prepared Pse Envirnemanent impact St=ta==rda (E15e), and perfonned supporting analyses (for NEPA documents issued by the DOE) that address tansportation of RAM by med and/or rail, nose laelude: (1) Transportation Impacts of the Coaimercial Radioactive Waste Managemsat :
4 f
s-.-,.
. _ _ _ _ ~ _ _ . . _ - - _ _ - _ _ _
otC.8 sais g er) ss/ss/ss esI41 (Dess s44 sled Pmpen, Cashwell at al.,1946, SAND 65 271$;(2) Environmanel Awessment of tis Proposed
"= of a Unhed teases Poi 6ey on Ases@ sad ? -t of spent 4 Adopties and ' . ' -
Rasserch Rasseor Fuel (Of She Tusla Policy),1991, DOFAA4443; (3) Favimmsmosesi A 8 on Shipment of Taiwanses Rasenmh Rasseor IdpmW Nuoiser Fest,1986, DOE /EA.
0321;(4) Envimmasmaal Asessssmet on Shipment of Teismosse Rasserch Rasator Speas Naciser Fuel (Phans !),1988, DOEMA43631 (5) As Assemansat of the Safety of Spent Fus!
' Transportsalon la Urban Havimos,5sadoval et al.,1983, SANDt2 2M5; sad (6) Tr Was of B a&==laa in Urban Environs: DmA Envirossasatal Assessment,1900, NURBOCR4743, 3.0 WORK TO BE PERFORMED AND REFECTED RESULTS j A. Pseps of Werk I
, -Ss rids developed by the y fw- of RADTRAN ne satimates of spent fbsl omloulations for NURBO4170 are believed to be quite conservatin. Dus, the sooident risks i associated with the transportstlen of spor t fhol in real ends are likely to be bounded by the '
scoidset risks estimated for the generic osak taal for NURB04170. his oceshmies could be demoasersted by perdenlos a very largs number of risk esiculations that trwt all poem %is combiassions of the rest transport essks and routes that may sotually be used to transport syset fuel Aom vasoners to interim or paresenset stornes fboulties. This ~ ; ""8v lassasiw arpsonob is not weaumesd. lastead, &;i;~ of distribudeus for those RAD 11AN input -
panamens the spairy muts and cask cheresortsda and amminsden of the impaat of them disedbutions upon spent fbal transportation rids using structund hdonte Carlo sastysis mesbods is g- , : Perfbrmanos of struotmed Moses Coelo analyses is isoposed boosass such analysse t
' adow sedrasess of esposeed (mean) risks and tbs range of these risks tc hs anW=wly developed l=h t witimt havies to dowlep sysoins laput Ibr a vwy large number of RADTRAN nus, to swet the pdacapal objectin of 6 m:dy, descasumien 6st de NUR500!?0 '
estimates of spent fhol transportadon risks bound the tids that will be associated with the ounsedy saticipseed shipsasats of spent fb61 in real casks, only a omrefully structured set of RADTRAN smalysos assde to be y fw ', provided that the tschalons bases fbr the input data used la thans osiculations are Ailly described and documented. ,
R. Appreesh {
RADTRAN loput paramstm3 will be dividnJ into two groups: most importsat input paranwwss, for which distributions will be dowloped; and less important persensors, Ibr widah best estims s values will be kd;:' The division will be made using the renuits of past RADTRAN omiculations, aspeointly persawier sensitivity calculations. Distribudons will be developed fbr roues parameters (routs Isagths; whas, suburban, and rural insgeh Anstions, populasion damside and accident reams for cask transport by truck and train), for ossk depsodsat persesters (socident source term reisses probabiHties sad solosse Aactions), and for any other RADTRAN isput paremsens that strongly asset risk estimates. For all other RAIy!RAN input pommsters, a best estimses valus will be selected and brisey jusdeed.
S r I
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__ _ . _ _ _ . . _ _ . - . _ _ . _ . . . _ _ _ _ . _ . _ _ . _ . . _ _ _ _ _ _ _ _ . _ . _ _ _ _ . ~ _ _ _ _
- s/33/9s solda Sett sed $344 oeC.O $890 R oss i
Roues paressear distribudons will be onestrucasd ming the resuks of the wry .ngc number of IDOHWAY and INTERLJNE enleulseions that have base perfonned to suppen past FAD 1RAN l
omieulsdons, neeluding if positde thne :nnsatly per(wasd by_ ANL m part of tim MpC Bis.
Tnsk and train sooidset seems will be dmloped Does thansum dels, especially Dean the stats-level assedsat data publiabad by ANL. -
Ace &dset rolsens Aanthes sad please pcbabilities will be developed ashig a Model Stady sooidset reserh. Aceidset wlosides and Are denticas will most likely be used to de8as masix 1
beenkpaints so thei the respoem of sevesal repressnesdw casks can be treemd by a slagic meerh.
Dermions of hydronerban fasi fba mauimd to ihn cask mais, io er., ibe adimion F< isyn
! to sheep, and to sisalSeestly increase the renese of volatile Ass 6am products wiu be 6.,amsted using a simple insped permaneter snodel of tbs thennel maponse of each reprenanteein omsk to an i
engulfing pool Am. Represselstin oasks will be solested oy myiew of the , :;:2 and doeless i
of the oenks that might be used to innsport and temporarily assa spent ar-narcial roaster fuel, j
espnlary the casks considsed in abe Mpc EIS.
For each :spressatalin osak amamina4 asoldaat w1ocities tbst need to maan=al and askr cask thuures (l.a, hole sinom that lead to slow and repkt depresswintion of the cask) nul be d==nad uslag the resolu of the many stuises and tests of ensk bobsvlor during bapest eysses that how been performed since the publiundan of NURBO 0170. Rasuhe wiu be developed for spew antin seu of imput swesen and impoet angla. whomver possibis, Medal study w M,/- and data will be used to estinses or estreponses the respones to impact everns of "w casks selected fbr stasy. Having denloped distribuelons of omsk failure hole the .m slass, reisess Anotions will be osdmased for each bene slas using Amt md slause 6moticas tahan tems tbs litarenne and sank 5 & M release bactions developed by MELCOR vapw and assumot transport coloulsetool. per#onned for the1%125 eesk.
Accidset astrix bin probabuities (i.e., accident sourse tem probabdities) wul be developed by l
constructing sienple truck and train c.acidert event trees. Brunob point prebebuitise on these tross will be denloped by myiew of past innok and trois transpwtation risk studies, especially the Modal Study, = Wad if noosemary in reflect mor roosat mucident data whers avaliable.
Olven best eschnete values fair Isas important RADTRAN lapat panum 6ers and distributions for snore important input parameters, a series of structured Monte Carlo (Lain Hypercube sempting)
RATyrR AW analyses wiu be perfonned. Standard regresson method; will then nuow supscoed (meen) values of risk results and the rengs of these results to be developed tom the resula of the individeal RAD 1RAN miculations (alsesmes of the Leda Hypercube Sample). Comparison of these results to the tasults paviously developeJ by NUREO 0170 wiu than show whsiber the NURBO-0170 n;s.dte bound the moults obtained unies spoonsatedve casks sad ' emes that typify ,
tbs anticipated skipaments c(spent nuclear rescent fuel.
C. Teobs lhls seccion describes each program ta4, specifle the task delinenble, and presones estimmens of the task casapletion does and of the levpl of effbet required to cornplete the task.
6
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es/is/es set 48 96es s44 e844 ORC.8 sere 3 333 I. Phase ITasks
- a. Reviser of RAIFrRAN !apet Parnassesrs (8 enes weeks)
Rmtes of menspatmios dak medies ibst uomi RAD 1RAN and of seasidvity audies of RADTRAN input parenstam will be miewed to klusify thom RAD 1RAN imput peansem that strongly inBuenos risk (1suportant Perumsents) and thoes parencesrs that have a lesser impact as risk (IAss IMPOrlant Passwears). The following cdteria will be used to identiPy imponset and 14es leponert Parameters, important paramwears (Ci) should approskastely doelde or halw risk esdesens (R) when ibstr input values are doubled (R4,C i or R4/Ci whee 1y=1.0). Iam imponent passesters have a much maaller iespect on risk (R4:C i or RM where ki 1.0).
Beat estimate values will be salasted for all Lass huport, M RAD 1RAN ieput paramseers, and the basis for the solamed vahas wn! be bdeSy sununariand. Subesquent tasks will develop ranges and distributions ist hopenant RADTRAN input penunsters (e.g., rouer perumseurs, cask i inventories, and paranseurs that depend streegly on oask designs and estadal properties, l spedAnally source earni probaldlities and releans testions).
Seems RADTRAN imput perumsters, or the naisle in widd they are inipimamatal hsw been ,
extensively muted sinec NURBO 0170 was pubilahed. For museple, the BFIR V sandy
' ladieseos that radiatlas risk =asAame abound be revised upward n about a amear of two; and as a part of tbs development of RAD 1RAN Vusion 5, the models used in RADTRAN to i
odeulate oases insurred when a RAM transport voldele stops at some hallity (STOP doses) baw been smesnaively revised. Discussion of the selection bests fbr the values ofless hnportest ;
perumstas wul be more sharough whensvar a paremmer votes or the usedel in w'.iah ths .
persantar is haplemented has been examosively studied since NURBO 0170 was published.
AAer tbs review of RADTRAN input has been oornplated, the consequence meanmes (e.g.,
l g; % does, latent censer hih) and the reisesnoo number o(shipresets (singis shipment, nanbar of abipunsets per year, Aill shipment campelsn), that will be used to compers tbs results of this mudy to those developed for NURV) 0170, will be choess. Before thans selecdons are innde, the NUREG-0170 standard shipment model for spent fuel will be updated using MPC EIS dann and dans in tbs lassyssed Data Bass.
Detversble: latetal draft of abspear for Saal report C: , " ^'- Does: Denemsbar 31,19M ,
- b. Updated Tmak and Trehn Aesteset Senaistems (5 man wesis)
- nn truck and trois accident statisdos used in NUREG 0170 will be updated to reflect more rooses data, espeelally the does M,M for the Medal sandy and etw state truck and train accident desa developed by ANL sad used by ANL during tbs pmperadon ofIbe MPC EIS. To fbcSitsee tbs use of Model stu$ and MPC EIS accident data, LLNL and ANL will be asked to 7
onc.e saro gets ee/ss/es esi44 esos e44 es44
)
provide the new data in alsovonic form. Tbc NRC technical monitor will be promptly nac is fem or can am be seedy ommned io .l.omonic fann l ih e dem o.a m be obinia.d in el l by sananing of published desansus. l l
Because US laisrame speed limits beve tusently been inonneed and tbs Amerioen Association of Railroads has psoposed the ah of the railroads'self-insposed operedag sostrictions for trains that me carrylag RAM (the 35 mph speed ihnit fbr trains omrying RAM sad the I regurunes that one anla stop and the other remrict its speed to 35 mph when a RAM tada '
t passed by another train), the impact of higher operating speeds on tvt and train a/Adast .
matisties will be onnAnny exanland.
Deliverable: Intelal dran of skapter be unal report Compleeles Date: Mareb 31.1997
- e. Reste Charseterbeiss(7 anne wesia)
RADTRAN transportation routes are constructed as sets of rouse sesssenes (links). For saany RADTRAN analyses, only thee aggresse links are used, an when, a puterben, and a rwal link.
nose three segresses links are comarusted by weighted ==nmmtan of the charenteristics of all of the ladividual urban, suburban, and rud links that denna the Ad1 transponscion soute. For this study, rense and diswibudens will be deloped for total route hveh, the frestions of that lensib that pass through urban, suburban, and rwal erums, and the truck and tala accident raise and popuisson denshies that chaemerim show amas, iminal distritusome for these paranseer vahes will be ennstaasted using results floss the very large number" of H10HWAY and DifERUNE antadataan that have been r f.c9 for past ; - ; -: = smidies. Next, a repasselstive sample of possible locations ihr new inserim RAM storegs thellities will be avviewed to detennine whether the characteristics (RADTRAN roues paramstar values) of routes to and ihwn these facilities as well represented by the initial distribudum if this review shows that the characteristics of rouses te, and frosi these laterim biliel= are am well represented by tbs laidal distributions, the characterLatics of a repressetative set of routes that involve these facilities as route tannini will be developed by ths ; fyr= of additional HIGHWAY and INTERIJNE colouladons, and the initial distributions of route parameter values will be modified to ro6ect the results ( the additional HIORWAY and NIT.RLDrJ calculaticem Finally, tmnsport of RAM by berge, ship, or heavy haul truck to rail Mrmini ihan nector sites and interim facilities will be namniand in order to update the accidset stadsdes that apply to such transport originally !.ed , d for NUREG Ol?O.
Deitymble laitial drun of shapter for smal report Compasstem pose Jane 30,1997 s
m es/ss/as asses 980s s44 e344 orc.s sarc E 01:
f
- d. Representathe Casks (5 saan-weeks)
The casks that are likely to be used to ship power reactor spent fbcl will be miewed in order to identify a reprenantative set of canks for which release probabilities and release fractions will be developed. This review will consider (1) the Multi Purpose th and alternative casks examined by the MPC EIS,(2) other single. purpose casks, dual-p wee n Wi. c.po:t ensks, and muldpurpose casks that either have been licensed by NRC or are in the llocasing process, and (3) any other casks that might be extensively used fer the transport or storage of spat reactor fuel for w: % design data can be re:elily obtained. Particular attention will be paid to casks that have capacities and weights W *ially sneter than those of the generic cash that were
==mt-4 by NUREG 0170 and the Modal Study. riert, two or three .w dve casks will be selected that have properties that typify the range of properties exhibited by the lange set of casks reviewed, and which thus are suitable candidata= for the development of release probabilities and release fractiorm for use in this study. Flaally, the properties of these repreecatative casks will be compared to tim properties of the generic casks -alaad by NURBO-0170 and the Modal Study.
Dekkerable: Initial draft of chapter for Gael repart Coesploden Ds.te: July 31,1997
- e. Cesk M*A==k=1 P=Ta=a Methodology (6 enan-weeks)
Release of radioactive materials from L -pi.Gon casks as the reaut ofimpact falhves depends 2
strongly on the size of the failure. This is because large failures (hole sins :t 10 cm ) lead to npid cask depressuriztion and consequently efBeient transport out of the cask of rad released from W fuel to the cask interior. Conversely, for small fhlhres (hole slees s 1 mm cask depressa.iudet is slow and consequently deposition of radioactive vapors and acrosols onto cask surfaces is substantial which greatly anenuates release magnitudes. In order to quantify thcee effects, the results of the Modal Study, othat theoretical atudies of the mechanical response of casks to impas, and experimetal studies of the effects ofimpact onto surfaces on cet Mt 7 will J b mieww1. Corielations between the magnitude of the cask is'sures that rat @t S dwed by impact and impact angle, impact velocity, and the hartiness of the impact surina di be Llantified. Following cornpletion of the review, a set of approximate correlations will be developed that can be used to ucdibly estimate the impact velocitica, anglos, and surface hardnesses required to cause mimmal (1 mm holes) and major (10 cm' holes) failures in typical L-,ps.non casks. Note that the NRC Technical Monitor will be prompdy notiSed if this review indicates that a credible method for estimating the magnitude of cask impact failures can not be developed from available models and data without the gLi-se of new tests and/or intensiV J aLgmamema, Deliverable: Initial draft of ekapter for flaal report Cesspistlos Date: August 31,1997 9
08:48 ORC.8 8320 2 013 09/3s/99 Clos $44 Or44
- f. Revised Proposal (1 mat. week)
AAar au Phase I tasks have been completed, the rr. Lits ci hese tasks will be presented to NRC at a review meeting. Discussions at that meeting vdit identty any changes in program direction that are required by the Phase I results. If significet chan*,,a in ,76run direction are required by the review of the Phase t results, a mined propou aiii be submitted to NRC that reflects the neded changes Ddivorabla: Revised Procesal Completion Date: Sep6essber 30,1997
- 11. PhaseIITasks
- a. CaskMechaalcal? ;m Model(It man-weeks)
The responses of the representative casks to impact onto surfaces will be estirnated using the contlations developed for Task 3.3.1.5. SpeciScauy, velocities that Iced to mia! mal (1 mm*
3 hole) and major (10 cm hole) onnk failures will be esthneted for all comMnations of the set of reposentative casks, four impact surfhoes (rigid, hard rock, sofl rockhard soll and soA soil) and four impact angles (engles of 90,70,10, and O' between the cask axis and the impact surface),
la developing these entr* extrapolation of the results ofless severe impacts to more severe conditions will be based on analytimi results, and the analytical results used to make these extrapolation wiu be correlated with avausble test data wherever possible. Impact onto a rigid target of each of the typical casks erammad wiu be modeled using Snite element 2 methods and a coarse mesh. The velocities that lau! to the two damages levels (1 mm* and 10 cm holes) prodleted by these analyses wiu be incseased for accidents onto real targets using rnededs 2
avaRable in the Uterature. AU estimates will reflect the effects of thermal and radiological embrittlement of cask and/or cladding mate:ial.
Deliverable: Initial draft of chapter for flual report Conspleties Date: January 31,1998
- b. Simpie Cask Therraal Respense Modd (3 : nan-weeks)
A simple one-dimensional lumped parameter thennal model of each representative cask will be developed and used to esthnate the durations of engulfing haw ben pool Gres that are requirul (a) to best cask seals to their failure touw,d=, (b) to heat cask radiation shield materials to the temperatures at which they slump, and (c) to beat the spent foal carried in the cask to tampantures that cause votatile fbudon products (e g., Cs and Ru) to be released in significant quantities as vapors from the fuel.
Dellverable: Ialtialdraft of chapter for flaal report Completion Date: Febrtsary 28,1996 to i
es/rs/es os:47 Caos s44 e 44 onc.e esen g ois
- c. A.cident Soaree Tornas(8 maa weeks)
Accident source terms will be expreued as th geduct of a cask inventory and a set of socident release fractions. Accidents will be binned into a generic accidcot matrix, one matrix for truck accidents, and one for train accidents. Matrix break points (b!n boundaries) will be denned by accident velocities on the y. axis and the durations of engulfmg hydrocarbon pool fires on the x-axis. The r%n=Mp cf them generic accmdent meries (velocities and fue durations) to regulatory test conditions and the reasons for selecting such simple meets to repiceoct complex Maatcal and thermal accident envirenments will be clearly explained.
c.1 Bia Renesse Frsedens Bin release fractions will be developed fo: five Mai element groups: Co (CRUD), Kr (neble gases, Cs which will be assumed to be released as CsOH, R'. which will be assumed to be released as RuO4 , and particles. Element group release &act.ons (F) will be expressed as the product of a release frac lon fmm spent fuel to the cask interior (Fu) and a release fraction from the cask intedor to the environment (F.,d. ha, Fi = Fu F, Fu values will be based on Wilmot's application to transportation accidents of the experimental resuha of Lorenz, modified as is appropriate to reSoct impact fracturing of fuel. F i values will be based on the results of fission product LW calN% performed for a TN.125 cask using the MELCOR thermal hydraulle/ fission product transport convis. sat code. The Fca values will be estimated assuming that the size ef the failure hole produced by an impact increases linearly with inciense of accident velocity between a threshold velocity that gencrutes a 1 mm' hole and a largar velocity that leads to a failure that allows rapid cask depressurization, which ihr this study will be taken to be a 10 cm' hole, e.2 Casklaventeries Tnventories will be calculated for oech representative cask using the ORIGEN code. The calculated inventories will reflect shipment of older fbcl, shipment of greater than Class C wastes, and the possibility of multi-cask rail ablpments. To support examinatice of the impact of the length of time that spent fuel is stored at the reactor site before it is shipped to an interim or perm-mt storage facility, inventories will be calculated at a variety of G ws aAer removal of the spent fbelfromthe reactor.
c3 Bin Probabilldes: Simple EventTrees Bin probabilities will be edm*H by constructing simple event trees. Event-tree branch point probabilities will be estimated fmm accident data and from Modal Study results. Accident scenado (event tree path) probabilities will be calculated by taking the product of all of the branch point probabilities that lie along a single path on the tree. Accident matrix bin probabilities will then be gerersted by sorting these path probablittles into the matrix bins and averaging the probabilities that fall into ladividual bins.
Dollve 3ble: Initial draft of chapter for Saal report Consplation Date: April 30,1996 11
et/3s/98 #st48 Cass s44 0244 CRC.8 saro 3 033 i .
- d. RADTRAN LHS Calculations (7 man weeks) m distributions constructed for the RADTRAN paramatus tint were detsnained to be imponant Parametae by the review of RADTRAN input pammetes, and de point sotimate values selected for tin Lees Imponent Parameters, will be used to calculate updsted incident 4ee risks and accident risks fbr the transportation of commercial spent reactor fuel by unck and train.
Became previous tasks have developed distributions for route parameters, inventories, and source term release fractions, this tank needs to develop distributions only for any remaining Important Pasamsters. Distributions for thsee parameiste will be defined using the most recent das available.
Input values for a ad of RADTRAN calculations of size N will next be developed by selecting values for 1-i~.M Panumsters fican their distdbutions by manna of Latin Hypercube Sampling (LHS). The value of N will be large enough to produce statictically significant results (typically N lt 2N ). N LHS procedure will generate N sets of values for the ImW Panemotore Each act ofinput values for the Important Parametere will be combined with the point estimata values selected for the Less importarit Parameters, thereby ganarating N counplete RADTRAN input files. After all of the N Individual RADUtAN calculations have been perfonned, standard statistical methods will be used to develop w==e== for the mean,10th, and 90th persendle values of the distributions of consequenos measures ofinterest (e.g., populadon dose, lasant cancer thsalities). Consequence values will be developed for single ablpments and for the number of shipments per yst predicted by the updated spent fuel shipment model.
Comperison of the resulting values to the values previously developed for NUREG-0170 is then
-W to show (1) that for any consequence the mean madt developed for a range of real casks and routes lies well below the mean resuk devebred for NUREO-0170, and (2) that the l
mean resuk developed by NUREG-0170 bounds most of the range of the results developed by l
this task using LHS methods.
Deliverable: Iaisial dran of chapter for incal report Completten Date: Septomsber 38,1998 HL PhaseIIITania
- n. Other Topies($ man weeks)
This task will also examine the following topics, document the results of the examination, and incerf-e. the dos- 2--4 results lato the final report, any changes since NUREG 0170 to the models implen-mad in the RADULAN code, conservatisms in the NUREG 0170 dose models, centerine individual doses, cumulative individual dosas, the impact on cumulative individual doses of the movement (i.e., change of residence location) of people imo and out of a region (route link) where transportation accidents may occur, worker dosos, evacuation times, conservatisma in the sotimation of the cancer risks associated with low doses delivered at low dose rates, enviroumcatal justice, and the quality assurance methodt waphyed to assure the emiibility of the results obtained by this study.
Denverable: Inith,i dran of skapter for Saal report Consplaties Date: Decentur 31,1998 12
Os/3s/es as 4s Osts see 0344 orc.o ss20 R0le l
- b. FlaalReport(10 asan-weeks) m results of the procedlag tasks will be documented in a fmal report that consists of brief and evta=W summaries of the teh*=1 muhs, wrinen so as to be edble to concerood citizens, followed by chapters that describe and discuss the technical methods and e===adonal mults developed by the study in sufEcient deta!! to allow transportation risk assessment experts to judge the validity of methods used and the results obtained b report will summariae and discuss the new risk andma'*a, compare these esthnates to those developed by NURE04170, and thoroughly discuss the difforcoces.
Deliverable: Dnna of nasl report for review by NRC Cosayistlos Dates: Preitssinary Flaal Dran for NRC Review, Marsh 31,1999 Flaal Dran, May 31,1999 D. Cossplet6ee Date b proposed completion date for this program is May 31,1999. Revisions to program tasks or achedule could cause this date to change. ,
4.0 PROPO6EDPERSONNEL A. NRC John Cook is the NMSS Technical Monitor for this program. Technical instructions may be issued by Mr. Cook from time to time during the performance of this program. Tec'mical lastructions aball oct constitute ra task assigmnents, or changes to adsting tank assignments that alter program costs or r%1** If task revisions are required that entall additional work or changes in program schedules, these revisions will be made by subrnission by SNL for approval by NRC of a revised prograrn proposal. Directions for changea in scope of work. cost, or period of perfonnance will be coordinated through the NMSS Project Manager, David Tiktinsky.
B. SNL The technical lead for this program will be J. L Sprung Dr. Slrung is a Ph.D. chemistry graduate of UCLA with 20 years of expenence at Sandia Nstional Laboratories managing and performing radioactive material safety, risk, and consequence assessments. Major assignrnents W immed by Dr. Sprung include assessment of fission product transport models for the development of the MELCOR code, direction of the consequence calculations performed for NUREO-1150, and anaaament of the risks associated with ship accidents that occur in ports that was peeformed for the Foreign Research Reactor Spent Fuel ETS.
S. Neuhsumer will be the tesnical lead for Transportation Risk Analysis tasks. Dr. Nah===
has a Ph.D. In Biology from Harvard University. She has been task leader for RADTRAN development for the past ten years, dunng which time RADTRAN 4 and RADTRAN 5 have been developed. She has performed numerous risk analyses and assisted in the mm.Gon of 13
~ - - - _ - - - - _ __
Ds/28/08 08:ss C stS 844 el44 ORC.o Isr0 gen 1 .
NEPA documents for the DOE and other customers. She has developed new analytical methods to address problems unique to RAM transportatica Prior to joining the transportatice group, Dr.
Neuhauser worked on the WIPP FFlS and the UMTRA and Beno6cla! Uses of Radiation Programs.
O. S. Mills will be the technical lead for RADTRAN UlS c'ileidons. Dr. Mills, a Ph.D.
physics gradusas of the University of Texas, has 30 years of WE.:4 in applied physics research and development and t+600n risk analysis. Es experience in L--ymmion risk analysis includes work on numerous radioactive maserial EAs and EISs (e.g., Foreign Raseemh Reactor Spent Fuel EA, happhhe D EA, Plutonium Disposition EA), in addition, he has apphod the Latin Hypercube Sampling technique to sensitivity studies of accident <isk input variables and d-anented the improvemems in risk totimates okealaahle from applicadon of LHS to impor. ant input i .or.. Odwr, transportation risk-nlated, dev4==* work has included acquisition of data for improved definition of input p .oc;ci and distdbution functions. Before working in transportation risk analysis, he supr4.4 underground nuclear effects testing with radiation diagnostic development, fielding, and radiation L pt/ material interaction modeling D. J. Am-aa; a Ph.D, Civil Paala-ing graduato of the University of Minna=ata, will be the technical lead for Cask Mach =nical Behavior tasks. For the past eight years, Dr. Ammerman has served as project leader for structural analysis issues related to radioactive material Lpi. don packages, has directed and/or performed non-linear dynamic analyses of U.espm6 don packages, structural code Wmarking studies, structural testing of U.nspadon packages, evaluation of the stnxtural response of packages to c.L;ponation oxident conditions, determination of tbc safety factors for NRC Reg. Oulde 7.6 designed packages, and assessments of off. site radioactive material transportation capabilities for Rocky Flats and Hanford.
J. A. Koski will bc the technical lead for Cank normal Behavior tasks. Dr. Koski has a Ph.D. in Thermal Science from Texas Tech University.11is 33 years of experience working on thermal science problems includes five years in thermal modeling for radioactive material L, sp don studies, eight years of thermal modeling of magnetic fusion high best Dux componems, and two years of modeling and development of data acquisition methods for the measurement of thermophysical properucs of anatorials. Before joining Sandia, Dr. Koski had nine years of nuclost industry design experience with Bechtel Power Corporation.
%is preliminary Proposal designates Key Personnel on NRC Form 189, Part 1. During project negotiations, Randla National Laboratories (SNL) and the Nuclen Regulatory Comminaion (NRC) will finalize the list of " Key Pctsonnel" which will be documented in the Final Proposal.
However, it should be clear that SNL can remove any personnel from an NRC work order, inelnAine " Key Personnel," without NRC approval, but the NRC must approve any proposed substitution ice those " Key Personnel" identified on the Final Proposal.
5.0 MEETLNG8frRAVEL lt is anticipated that prugram review meetings will need to bc held at the conclusion of each program phase. If any of these meetzgs am held in Washington, DC, then SNL travel costs will be about $3000 per meeting.
14 l
0 /2 / estal Clos s44 0 44 ORC.s esto 3 03:
1 nis study is not antkiW to require any foreign travel. An Outside Continemal Ualted States (OCONUS) activity forrn will be submitted to DOE with this proposal for any anticipated foreign travel. AnNRC Foun 445 will be p:=amad 40 days prior to OCONUS travel.
Deviations from the travel submitted as part of NRC Form 189 and accepted by issuance of ar NRC Parm 173 will be coorMaatarl with the NRC project manager as soon as the need for such a deviation is identifled to ensure it will not in:erfere with the timely completion of proposed work.
6.0 NRCFURNISHEDMATERIALS No prograrn tasks are expected to toqube materials that must be furnished by the NRC in order to be performed. The final report for this program will be published by NRC.
7.0 RELATIONSHIP TO OTTIEk PROJECTS SNL pri$octs that are develop risk nemame methods or data pertinent to this program include:
Development of RADTRAN 5.0; periodic updates of the RMIR and RAMPOST databases; development of GIS-based route-analysis methodology with environmental justice applications (proposed for FY97); and publicadon of RADTR AN 5.0 sensitivity analyses that parallel earlier analyses performed for RADTRAN 4 and RAD' IRAN IU as part of on-going code QA and
@does efforts.
SA REPORTING REQUIREMENTS AND SCHEDULE A. Douverables ne final report for this stody will contain separere chapters that det the results of each program task. To facilitase the preparation of that report, inidal chapter drafts will be prepared as each program task is completed. Accordingly, the deliverable for oech program task is the initial draft of the final report chapter that describes and discusses the data gathered, analyses performed, and results generated to complete the task documented by that chapter.
No more than 30 copies of any interim report will be fumished to tbc NRC project manager.
N. R. Ortiz, Director, Nuclear Energy Technology, Organnation 6400, bndia National Laboratories, Albuquerque.NM. has been Ad=4 as the au*harizmg official for publications of NRC Form 426A.
B. Montlity Letter Status Report (MLSR)
A Monthly Letter Status Report (MLSR), following the Management Directive 11.7 instructions, will ha submitted to NRC by the 20th of each month The MLSR shall be dehvered to the David Tiktinsky, the NMSS Project Manager for this program, and tc, the Division of Contracts and Property Management (DCPM), Office of Administration. Additional distnhtlon will be made to John Cook, the Technical Monitor for this program, and to Earl raer% both of NMSS. De Financial Status section of tbc MLSR will follow NRC Management Direcdve 11.7's MLSR Financial Starus Report format to the extent permitted by the current SNL Financial System.
1s
onc.e sino gors os/as/es esis Cass esa c:44 l
C. Milestone Chart The following Milestone Chart munmarizes the estimates of task schedules and costs. Task costs are based on eA~ of 55.9,6.1, and 6.3 K per man-week of # fort (including cornputing, support services, and management tv. not travel costs or DOE Albcquerque overhead) for fiscal a
years 97,98, and 99, zwspectively. Travel costs are based on the following mer uydons:
program review meeting in Wanhington after every second program task, travel to each of those mootings by three SanAane and travel costs per meeting per person of $1000 ($750 airfare, $150 o
hotel, $100 food / car /other). Timelines in the Milestone chart depict elapsed time, not man-weeks ofwork.
Milestone Chart 1E5 kllFf97 l F's98 lFT99 l Tsek oupJFMLMJJheCIEDJnIMUJA50MDJREMUJAS Fbees !
Review of RADTRAN input Paremeters e 47 -->
s 29 ->
Updesad Truck an! Trata Accident Betlalce 7 41 ->
Rode Chereraeristics
- 2s -a Representative CJke impactMethodology 6 35 ->
Revised Proposal 1A x FY97 taber 32 its Travel (3 Washington tripe et $3000 per tip) s DOE Overhead (at 4.3 %) l FY97 coot 2os PhaseII Cask MechanicalResponse Model 10 61 --->
Shaple Cask Thermal Response Model 3 18 ->
B 4s -->
Accident Saurse Terms RADTRAN LHS Lalculanons 1 Al FY98 Labor se 171 Trevel(2 Weekington trips at $3000 per trip) 6 DOE Overhead (at 4.3 %) 1 FY98 Totale IB:
PheosIII -->
Other Topka 5 32 Final Report 1Q 11 FY99 Labor 15 95 Travel (1 Weekington trip et $3000 per trip) 3 DOE Overbead(at 4.3 %) A FY19 Totale 102 7s 4s2 Pr*6rse Te* ens 16 l
.- -- -. - - - . . . . - .. -. - - . - . - - - . - . - ~ - - . _ _ . ~ - _ _ - _ _ -.-
09/30/0s et:Ss Cseg s44 0844 ORC.8 $sr0 S cie ,
t D. Level of E8ert (esdneted at $9900,6148, and 6300 per man week for FY97, FY98, and FYpp,r e aQ)
Inval of EAwt Estasted (man weeks) Imc Cast enase I rests Revww e(RADTRAN1aput Pasensese 8 $47,300 5 29,300 Updsend Trusk med Train Assident Semelsene 7 41,100 Maule Charestartedes 5 2s,300 Repressnestive Cats a 35,300 Impost Malhadology Revised Ptopoemi 1 s,too Phase E Tasks Cask MerhanicalRaspause Model to si,000 3 18,400 Shaple Cask 1harmel Raspense Model e es,000 Aeoidmet Saures Tasms 7 42,e00 RADTRAN LMS Colonishees PhaosIS Test 5 33,000 Other Topies 10 n.ean Final Rapest 78 8454,900 ImberSabestok is,000 hovel (6 Wenhington irlpe at 53,000 per messing) se. nan DOE Overksed(at 4J 96)
$493,000 ToisiCast 9A SUBCONTRACTOR /CONSULTANTINFORMATION Use of subcontractors or consultants on this study is not preseedy anticipened. Needed technical support that might require the use of subcontractors or conschents will be first discussed with th
. NRC Tanhataal Monitor in order to establish technical requirements and then with the NRC Project Manneer to identify any impacts on program funding or schedules.
Rasurnes fbr proposed subcontractors,if applicable, have been provided under haa 4 of this proposal Acceptance of this proposal indicates approval of personnel proposed herein.
Subsequent subcontractor efforts not described in this proposal will be managed per NRC Directive 11.7, Part X(BXeXPas 61). conflict ofinterest issues are covered in section 11 of this proposal which considers all proposed personnel, lach. ding subcontreetors.
18.0 SPECIAL FACIIJTIES,IF REQUIRED
- 1his study is not expected to require any speelal theilities.
17
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u s. a
ee/ss/se satse Cass s44 es44 onc.e saro ten ILS CONFLICT OF D(TERESTINFORMATION No sisaisonat contractual or s;- '-%! . "-r-7= of sandia Nasional Laboratories, its employees, or saticipated subocadractors and/or consultants udst with industries regulated by NRC and suppliers thereof that might give rise to an appenet or actual con 6ict ofinierest.
US Nuclear Regulatory N=is (NRC) recognima that W'a National laboratories will perfonn tbs work assigned to DOE under this project pursuant to tbs "Non-Department of Energy Funded Work" provisloa of the DOE /Sandia Corporation contract for the managernant and operst:en of Sandia National laboratories.
'Ibe DOE-approved Sandia Corpontion OCI .Y-';-' Plas govsming socess to sad flow of inibunation between Sandia Corporation and its T~haart Martin afRHamad orgmalastions will apply to all work perfonned under the terms of this project. 'This Sandia Corpoetion OCI Mansomment Plan and tbs procedures resulting form the plan s's subject to DOE sudk as all thess. A copy of the Sandia Corporation OCI Management Plan le available upon request to Ken Haug, Contracts Center, M/S 01:5, Sandia National Laborssories, Albuquerque, NM 87185-01g5,(505) 845-7750).
In accardance with the Organientional Conflicts ofIaearest tenas of the DOE,1!!andia Corporation contact, Sandia Corporation, including any of its of5mials who may acquire infbanation a part of their management responsibluties,is prohibited fhun further F i=*= any third. party proprietary data or govenunant sensitive data or infonnstion (as indicated by restriedvs maridags identifying the dass and information so protected) to its f ~haad Martin mMIHaand organizations.
In view of the above, the NRC hereby agress that i~ha=d Martin afEHatma of Saadia Corporation shall not be restrained or restncted from competing fbr any toissed followen contreets or subcontracts to be awarded by the NRC that relate to work under this project.
11.0 CLASSIFICATIONORSEN8ITIVITY.IF APPLICABLE
' Ibis study is not expected to produce any classified or sensitive information or muerial.
13.0 ADDENDUM COIFT AND SCHEDULEINFORMATION n/a 14.0 SpeedingPlan(kS)
A spendias Na,NRC Form 189 (Part 3), is included.
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cs/svos estas esos e44 ossa onc.o saio 3 022 15.4 DOE OVERHEAD DOE departmental overhead charges of 4.3 percent for l'Y97 and subsequent years will be added on all Mllings.
16.4 DOE.ACQUIREDMATERIAL No property purchases over $500 are cumedy planaai Purchases of items $500 or greater not idendfied in this proposal will be requested sepersasly in writing. When ev ty is purchased, it will be reported in the MLSR. Property will only be tracked at the $5000 or speater level by DOE, or if property is sensitive.
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