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118th Advisory Committee on Nuclear Waste (ACNW) Meeting, March 27, 2000

                                                                1
 1                      UNITED STATES OF AMERICA
 2                    NUCLEAR REGULATORY COMMISSION
 3                                 ***
 4                 ADVISORY COMMITTEE ON NUCLEAR WASTE
 5                                 ***
 6                         118th ACNW MEETING
 7
 8                             U.S. Nuclear Regulatory Commission
 9                             11545 Rockville Pike
10                             Conference Room 2B3
11                             White Flint Building 2
12                             Rockville, Maryland
13
14
15                             Monday, March 27, 2000
16
17
18              The above-entitled proceedings commenced at 1:31
19    p.m., pursuant to notice, the Honorable Dr. B. John Garrick,
20    Chairman, presiding.
21
22
23
24
25
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 1    PRESENT FOR THE ACNW:
 2    Dr. B. John Garrick, Chairman, ACNW
 3    Dr. George M. Hornberger, Vice Chairman, ACNW
 4    Dr. Raymond G. Wymer, ACNW Member
 5    Mr. Milton Levenson, ACNW Consultant
 6    Mr. Howard J. Larson, Acting Associate Director, ACNW/ACRS
 7    Dr. John T. Larkins, Executive Director, ACRS/ACNW
 8    Mr. Richard K. Major, ACNW Staff
 9    Mr. John Randall, ACNW Staff
10    Mr. Amarjit Singh, ACRS Staff
11
12    PARTICIPANTS:
13    Mr. Wayne Hodges, Deputy Director, Spent Fuel Program
14    Office, NRC
15    Ms. Janice Owens, EDLOW International
16    Mr. Rob Lewis, Spent Fuel Program office, NRC
17    Mr. Earl Easton, Spent Fuel Program Office, NRC
18    Mr. Richard W. Boyle, Department of Transportation, Research
19    and Special Programs Administration, Hazardous Materials
20    Safety
21    Mr. Keith Brown, EDLOW International
22    Ms. Amy Shollenberger, Public Citizen, Critical Mass Energy
23    Project.
24
25
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 1                        P R O C E E D I N G S
 2                                                     [1:30 p.m.]
 3              DR. GARRICK:  The meeting will come to order. 
 4    This is the first day of the 118th meeting of the Advisory
 5    Committee on Nuclear Waste.
 6              My name is John Garrick, Chairman of the ACNW. 
 7    Other members of the Committee include George Hornberger,
 8    Raymond Wymer, and Consultant, Milton Levenson.
 9              During today's meeting, the Committee will discuss
10    planned ACNW reports on a number of topics such as the NRC's
11    proposed High Level Waste Regulation, 10 CFR Part 63, a
12    Joint Letter with the Advisory Committee on Reactor
13    Safeguards on the Defense-in-Depth philosophy, the ACNW Year
14    2000 Action Plan and Self-Assessment, and comments on site
15    sufficiency strategy.
16              We will also discuss Committee activities and
17    future agenda items, and we'll hear a review of the
18    activities underway in the NRC Spent Fuel Project Office.
19              Richard Major is the Designated Federal Official
20    for today's initial session.  As usual, this meeting is
21    being conducted in accordance with the provisions of the
22    Federal Advisory Committee Act.  We have received no written
23    statements from members of the public regarding today's
24    session.
25              Should anyone wish to address the Committee,
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 1    please make your wishes known to one of the Committee Staff.
 2              It is requested that each speaker use one of the
 3    microphones, identify himself or herself, and speak clearly.
 4              Before proceeding with the agenda items, I would
 5    like to cover some brief items of current interest:
 6              Number one, a review of risk assessment practices
 7    for a Congressional Committee will include the use of risk
 8    at the NRC, and may be used to shape federal legislation. 
 9    Representative Tom Bliley of Virginia, Chairman of the House
10    Commerce Committee, has asked the General Accounting Office
11    to conduct the study for the Committee, which intends to
12    review the strengths and weaknesses of federal risk
13    assessment practices.
14              In his February 2nd request, Bliley asked the GAO
15    to identify and compare general policies and practices
16    across federal agencies on risk assessment, including such
17    details as the treatment of uncertainties and the use of
18    distributions versus point estimates.
19              As a minimum, the GAO study should include EPA,
20    the Food and Drug Administration, the Occupational Safety
21    and Health Administration, the Consumer Product Safety
22    Commission, and the Nuclear Regulatory Commission.
23              Number two:  The International Commission on
24    Radiological Protection will soon publish two documents that
25    may be significant because they use the new individual
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 1    risk-based approach to resolve two of radiation protection's
 2    thorniest questions:  Addressing issues of long-term
 3    protection around solid waste repositories and protection
 4    from prolonged exposure to both background and artificial
 5    radiation.
 6              The documents are said to be a halfway point in
 7    the ICRP's transition, uncertain transition to a very
 8    different rad protection system than the one in use today.
 9              Like the new system recommended by ICRP Chairman,
10    Roger Clark, they emphasize individual dose and/or risk,
11    rather than collective dose and societal risk as the basis
12    for regulatory decisionmaking.
13              I guess there is no reason to get too excited
14    because it is indicated that these recommendations may not
15    be implemented in ICRP recommendations for another five
16    years.
17              But at least it's an attempt to address an issue
18    that has probably been ignored much too long.
19              Third:  Energy Secretary Bill Richardson recently
20    assigned a task force to review DOE policies governing the
21    release and recycling of contaminated metals and other
22    materials.  At the same time, Richardson also announced he
23    will continue a moratorium on the release of volumetrically
24    contaminated metals at Department facilities, at least until
25    the Nuclear Regulatory Commission decides whether to set a
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 1    standard for the use of such materials.
 2              A fourth item of interest is that a conference on
 3    DOE's draft solicitation for its waste program recently
 4    attracted more than 150 individuals representing 65
 5    companies.
 6              The meeting, held in Las Vegas, was to provide
 7    potential bidders with information on DOE's plans to hold a
 8    competition for a five-year, $3.1 billion contract to run
 9    the Agency's Office of Civilian Radioactive Waste
10    Management.
11              Comments on the draft were due March 6th.  DOE
12    plans to post the comments it receives on the Internet.
13              The final RFT is scheduled to be issued March
14    29th, and proposals will be due June 8th.
15              So, with that, I think we will proceed to the item
16    on our agenda that's scheduled for 1:30 to 4:00 p.m.  It's
17    Activities of the NRC Spent Fuel Program Office.
18              The Committee's Consultant, Milt Levenson, is
19    going to lead the discussion on this topic.  Milt, I turn it
20    over to you.
21              MR. LEVENSON:  Okay, thank you, John.  While there
22    are probably a number of activities under the Spent Fuel
23    Office, this afternoon's session is primarily focused on
24    some of the issue related to transportation.
25              I think the Committee recognizes that this is a
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 1    very complex issue, in no small measure due to the fact that
 2    various legislation has made it clear that no one agency has
 3    complete responsibility.  That makes it a little difficult
 4    to get at some or all of the details.
 5              So this afternoon's presentations are aimed at
 6    helping to update us on what some of the players in this
 7    complex issue of transportation are up to.
 8              Our first presentation was going to be from Bill
 9    Brach, who unfortunately couldn't be here today, and Wayne
10    Hodges is filling in for him.  Wayne?
11              MR. HODGES:  Thank you.  I'm Wayne Hodges.  I'm
12    the Deputy Director for Technical Review in the Spent Fuel
13    Project Office, and I am filling in for Bill Brach who was
14    called away for a funeral in his family, and so you get me
15    instead.
16              The purpose of the briefing is to provide the
17    Committee with an overview of our activities in the Spent
18    Fuel Project Office.  And here we have just an outline of
19    the presentation.
20              I'll be going through the first half of the
21    discussion, talking generally about the activities, and Mr.
22    Rob Lewis will talk about the transportation portion of it. 
23    We will be followed then by Rick Boyle, who will be talking
24    about the Department of Transportation activities.
25              Many of our activities are closely coordinated
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 1    with them, and I suppose that he should speak as well.
 2              First, we'll provide a brief summary of the SFPO
 3    responsibilities for storage of spent fuel and for the
 4    transportation review of all nuclear materials, including
 5    spent fuel transportation.
 6              I have a couple of slides that give a picture of
 7    the U.S. and we show the location and type of currently
 8    operating spent fuel storage facilities, and the planned and
 9    -- facilities.
10              Then I will discuss initiatives we have taken to
11    improve the cask certification and review process; the
12    status of casework completion over the past year; and
13    initiatives we are currently developing to further improve
14    the certification process.
15              As I say, Rob will talk about an overview of some
16    transportation activities, and two studies we have underway
17    to address spent fuel transportation issues, and then I will
18    conclude with a brief summary of our status of ongoing
19    activities.
20              The first two bullets here summarize the SFPO's
21    primary responsibilities which are to review and to certify
22    packages for the transportation of nuclear materials,
23    including spent fuel, under the requirements of Part 71, and
24    to license spent fuel storage facilities and certify storage
25    casks under Part 72.
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 1              We additionally have the responsibility to develop
 2    and maintain the inspection program for both transportation
 3    and for storage; to provide technical support to the
 4    Regional Offices on these inspections, and we conduct a
 5    limited number of inspections of cask and package vendors
 6    from our SFPO headquarters office.
 7              The third bullet notes our significant involvement
 8    with the U.S. Department of Transportation and the
 9    International Atomic Energy Agency on both storage and
10    transportation activities, and a later slide will address
11    our activities in this regard in a bit more detail.
12              We also review and approve licensees' and vendors'
13    QA program for both Part 71 and Part 72 activities.
14              This slide and the next one give a picture of the
15    current and planned independent spent fuel storage facility
16    installations in the U.S.
17              There are currently 15 operating and licensed
18    facilities in 13 states.  There are 10-site specific
19    licenses noted by the triangle on this diagram, and five
20    generally-licensed ISFSIs noted by the circles.
21              Basically a site-specific license requires that an
22    applicant for an ISFSI, that an applicant must describe in
23    detail, all aspects of the planned ISFSI, a site
24    description, the cask system design and operations, and the
25    ongoing controls and programs to be in place to ensure safe
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 1    operations.
 2              This process includes opportunities for hearings,
 3    and requires NRC licensing decisions and actions.  A general
 4    license is conveyed to all holders of Part 50 power reactor
 5    licenses to use a currently certified cask listed in Part 72
 6    without application to the NRC.
 7              The reactor licensee must assure that their site,
 8    planned use, and programs are all bounded by the cask design
 9    parameters.  Since the cask design is actually listed in the
10    rulemaking process, the opportunity for public comment on
11    that comes through the rulemaking process, rather than
12    through a hearing process.
13              Also note that the ISFSIs are for dry storage of
14    spent fuel, except for the one at G.E. Morris in Illinois,
15    which has the spent fuel pool for storage.
16              There are also two existing DOE licenses for
17    storage of spent fuel, the TMI II fuel debris ISFSI in
18    Idaho, and the Ft. St. Vrain ISFSI in Colorado.
19              There are approximately planed ISFSIs over the
20    next five years or so in 14 additional states.  So that once
21    that's completed, essentially half or more of the states
22    will have ISFSIs in them.
23              The mix of type of ISFSIs is changing as the slide
24    shows, but the most planned ISFSIs will be
25    generally-licensed ISFSIs, not requiring NRC issuance of a
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 1    license.
 2              This shows five site-specific licenses and 15
 3    general licenses.  Note that this information is based upon
 4    meetings with applicants and licensees and general
 5    informational future plans.
 6              There is also a third DOE site to be licensed by
 7    NRC, and this will be another ISFSI located in Idaho to
 8    store Peach Bottom shipping port and trigger fuel.  The
 9    application is expected from DOE later this calendar year.
10              Before we leave this page, I want to note that you
11    will see a number of decommissioning reactors which are
12    trying to have a general license for the storage of spent
13    fuel, for example, Maine Yankee and Connecticut Yankee and
14    Big Rock Point.
15              This will require that these reactor licensees
16    maintain and not terminate the Part 50 license.
17              The matter of how to transition from a general
18    license to a site-specific license is a topic that we have
19    been having discussions with the industry on.
20              In the next several slides, I will briefly cover a
21    recently implemented initiative to improve the process and
22    our current review status and initiatives under development.
23              We have implemented changes to Part 72
24    cask-specific rulemaking process this year, and all of these
25    changes have markedly improved our efficiency and
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 1    timeliness.
 2              Perhaps our biggest changes and gains have been in
 3    effectiveness and efficiency and have been due to some of
 4    our internal process improvements.
 5              Through our rules of engagement, we have developed
 6    review schedules with clear identification of dates and
 7    expectations for both NRC review activities and for the
 8    applicants.
 9              We have met these dates and expectations, and in
10    so doing we have brought both stability and predictability
11    in the cask review and certification process.
12              The remaining bullets identify some of the more
13    important tools that we have developed and implemented in
14    this process.
15              Our efforts to standardize our process and provide
16    clear review guidance have assist both the staff and the
17    applicants.  Our use of interim staff guidance documents
18    provides a means for us to implement early technical closure
19    on issues.
20              Now I will discuss the use of ISGs a little bit
21    more as we discuss the high priority technical issues.
22              The information on this page covers our fiscal
23    year 1999 and first quarter of fiscal year 2000.  Note that
24    there is a shift from the single-purpose storage cask to
25    dual-purpose storage and transportation casks, and we have
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 1    been extremely busy.  We have had four dual-purpose casks
 2    and one single-purpose cask specifically in the rulemaking
 3    now, and we expect them to be completed in the next few
 4    months, and two applications are under review, and a third
 5    application is scheduled for later this fiscal year.
 6              The transportation statistics include both spent
 7    fuel and non-spent fuel casework, and the bulk of the
 8    transportation reviews are for non-spent fuel cases, and the
 9    bulk of that work is for amendments to currently-certified
10    transportation packages.
11              I have already mentioned the two DOE ISFSIs for
12    TMI and Ft. St. Vrain that were completed last year, and the
13    third was completed also for Trojan.
14              These three ISFSIs under review include Ranch
15    Seco, which is very near to completion now, and Private Fuel
16    Storage, which we report on the status monthly to the
17    Commission and the Congress, and the third review is to
18    support DOE Naval reactors.
19              We are performing a technical review for their
20    planned Naval Reactor Fuel ISFSI in Idaho.
21              The technical support to the Naval reactors is
22    being done under a reimbursable agreement and will not
23    result in an NRC license.  I want to draw your attention to
24    the footnote which highlights the shift in casework from
25    reviewing new cask designs to amendments of
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 1    currently-certified cask designs.
 2              You can see that the workload shift and the number
 3    of cases, each cask amendment will result in a rulemaking to
 4    amend the certificate, and I will discuss this more on the
 5    next slide.
 6              I want to focus on the NRC Staff activities that
 7    are underway to streamline and improve the certificate
 8    process.  First, we're working to assure that certificates
 9    only contain conditions that are required; for example,
10    where the technical basis exists, to support parameters or
11    bounding numbers, we're using the data in the certificate,
12    instead of individual point numbers.
13              And you may have heard a phrase called "smarter
14    certificates," and that generally refers to this effort.
15              Secondly, we are standardizing the technical
16    specifications and building on the reactor initiatives in
17    this area.
18              Again, a goal is to assure that the tech spec
19    contains only what is truly needed, and that other
20    information stays in the safety analysis report.
21              Third, these efforts support the implementation of
22    the changes to 72.48, which will allow licensees and
23    certificate-holders to make changes to the cask systems
24    without NRC prior approval and review, as long as the
25    specific change does not result in a change to specific
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 1    conditions or technical specification.
 2              As noted in the slide, we are working with the
 3    industry to develop guidance for the implementation of
 4    72.48.  I believe that, collectively, these actions will
 5    improve the effectiveness of the amendment process.
 6              We recognize that alternative approaches to
 7    specific amendment rulemaking need to be examined.  One
 8    suggestion is to revise Part 72 to specifically identify the
 9    types of amendments which can be implemented through direct
10    rulemaking.
11              As long as an amendment falls within these
12    limitations, the amendment could be issued as a final
13    certificate change and final rule, and other options are
14    also being examined.
15              Another process area of high SFPO activity is the
16    preparation for license renewal.  We have a group that we
17    have formed to develop guidance and the technical basis to
18    support renewal, and we will be ready for the first dry cask
19    license renewal, which will be submitted early fall of this
20    year, and it will be for Surry -- excuse me -- early fall of
21    2001.  Excuse me, I got the year wrong.  It is for Surry and
22    their actual license expires in 2006, and I think they are
23    required by law to come in two years ahead of that, but
24    since this is the first one, they wanted to come in early
25    enough that there would be no particular problems, and so
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 1    they are coming in in the fall of 2001.
 2              And we, basically, we have a group that we have
 3    formed to develop guidance for that and discussing with them
 4    this summer what we need to see in an application.
 5              We had a meeting or a workshop in mid-December
 6    with the industry and the purpose was to identify and
 7    discuss the prioritization of technical issues needing
 8    resolution to support dry cask reviews, and there were two
 9    issues that stood out well above all the others.  One was
10    for high burnup fuel, which was the industry's highest
11    priority.  Plants have had fuel in reactors up to 62
12    gigawatt days per metric ton.
13              Our current limits have been up to 45 gigawatt
14    days, and we, as a part of the review that has been done
15    just recently for both the westflex design and for the MAC
16    design, we have come to a mechanism for approving for higher
17    burnups, and that will be issued fairly soon in an ISG
18    revision to be used generally by all the applicants.  And
19    this is one of our highest priorities that we are working on
20    as well.  In addition to the information that can be used in
21    short-term, there is also a long-term research effort, a
22    research effort to get more data in this area, and it is a
23    cooperative program with DOE and EPRI.
24              Now, we will probably point out, the slide here
25    says 60 megawatt days per ton, it should be gigawatt days,
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 1    not megawatt days.
 2              And the other issue, the second highest issue on
 3    their list was for high burnup fuel -- high burnup credit,
 4    and, traditionally, the cask reviews have proceeding
 5    assuming fresh fuel for the purposes of doing criticality
 6    analysis, and we have been exploring ways to give some
 7    credit for the burnup that actually occurs, and we issued
 8    two revisions, first an ISG last May, and then a revision to
 9    that ISG in September which gives some credit for the
10    actinides in order to give some credit for the burnup.  And
11    there is still work going on, we see other revisions coming
12    down the pike.
13              We think this is a success to be able to do that. 
14    We are proceeding towards more realism in what we do and it
15    allows putting more assemblies in the cask.  There is still
16    more to be done on both high burnup and burnup credit, and
17    from our meetings with industry, we are working to develop
18    additional revisions to our internal -- interim staff
19    guidance and we think we are making good progress.
20              At this point I will turn it over to Rob Lewis to
21    talk about transportation.
22              MR. LEVENSON:  Before we do that, I have two
23    questions about what you have covered so far.
24              MR. HODGES:  Sure.
25              MR. LEVENSON:  One is a matter of my not
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 1    understanding, I think, what you said.  You said that for
 2    operating reactors, or people with a Part 50 license, if
 3    they use preapproved casks, et cetera, they did not have to
 4    apply specifically for an NRC license, is that right?
 5              MR. HODGES:  That is correct.  They already have a
 6    license under Part 50.
 7              MR. LEVENSON:  But then why do they not show on
 8    your chart for existing licenses, if they already all have
 9    them?  Is there something different about those sites that
10    show on your map?
11              MR. HODGES:  Well, it is a Part 50 license as
12    opposed to a Part 72 license.
13              MR. LEVENSON:  Okay.  So this is not all of the
14    operating spent fuel license sites, this is --
15              MR. HODGES:  Well, the ones in triangles are
16    site-specific Part 72 licenses.  The ones --
17              MR. LEVENSON:  Right.  I am talking about the
18    circles.
19              MR. HODGES:  The ones in the circles are where
20    they have a Part 50 license, but have an ISFSI to store fuel
21    under a general license.
22              MR. LEVENSON:  I thought you said that every site
23    has that general license.
24              MR. HODGES:  Well, --
25              MR. LEVENSON:  That is what I am trying to clarify
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 1    is, what is different about these circles from other reactor
 2    sites?
 3              MR. HODGES:  These are ones where they are storing
 4    spent fuel.
 5              MR. LEVENSON:  Yeah.
 6              MR. HODGES:  The other reactors in dry storage. 
 7    The other reactors, I mean all reactors have a Part 50
 8    license, but if they don't have dry storage of fuel there,
 9    then they don't have a circle.
10              MR. LEVENSON:  Okay.  So this is just ones that
11    are now doing it, not the ones licensed to do it?  That is
12    what I am just trying to clarify.
13              MR. HODGES:  In a sense, they are all licensed
14    because they all have a Part 50 license.
15              MR. LEVENSON:  Right.
16              MR. HODGES:  And if they choose a cask it is
17    listed in the Part 72.
18              MR. LEVENSON:  So they don't need your approval to
19    add circles to this map.
20              MR. HODGES:  That is correct.
21              MR. LEVENSON:  Okay.  The second question, this is
22    one of ignorance, is on your Figure 5, what is the Owl Creek
23    site in Wyoming?
24              MR. HODGES:  That is a private -- I think it is
25    private -- private storage facility that is left from a
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 1    consortium of utilities.
 2              MR. LEVENSON:  Oh, okay.
 3              MR. LEWIS:  Okay.  This is slide -- I am Rob
 4    Lewis, I am the staff lead for one of the transportation
 5    risk studies that you wanted to hear about today, and the
 6    other staff lead, John Cook, is in the crowd, so, hopefully,
 7    we will be able to answer any questions you have about those
 8    studies.
 9              But this slide gives an overview of my talk, the
10    transportation part of today's talk, and I will start off
11    with a single slide on our role and activities that SFPO has
12    for transportation, and they will complement the talk that
13    DOT will give later.  Then I will have a couple of slides on
14    one of our major activities we have underway, which is
15    revisions to Part 71 for international compliance with the
16    IAEA regulations.  And then we will have several detailed
17    slides about the transportation risk studies.  Then I will
18    turn it over to Wayne to summarize the SFPO part of the talk
19    and then Rick Boyle will come up to talk about DOT's roles.
20              In SFPO we have the agency lead for all
21    transportation matters, whether it be reactor of materials,
22    and as that, we are the single point of contact with DOE --
23    DOE, excuse me, and we support DOT in the activities at the
24    International Atomic Energy Agency with respect to their
25    periodic revision of their transportation standards.
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 1              We have -- one major part of our role is to assist
 2    other NRC offices.  As an example of that, we recently
 3    participated in the review of the Yucca Mountain EIS, the
 4    Draft EIS from the Department of Energy, and we also
 5    participated in the Environmental Statement that was
 6    prepared in support of the nuclear power plant license
 7    extension rule, which were changes to 10 CFR Part 51.
 8              We daily receive calls from inspectors or regional
 9    offices that may be out in the field and see something they
10    are not to sure of, and they call us to find out what the
11    transportation requirements should be.
12              One of our major roles is to certify
13    transportation packaging designs for large quantity packages
14    and for fissile packages.  And, as Wayne mentioned, we have
15    50 transportation casks in-house under review.
16              We issue quality assurance program approvals and
17    instructions -- inspections in support of the transportation
18    program, as well as the storage program for spent fuel.  And
19    we do reviews of the routes that are selected.  With respect
20    to those routes, physical security, physical protection
21    aspects.  We look at the routes to see where the safe havens
22    have been identified and, in some cases, we actually have
23    regional staff that drive the routes.
24              And we also are the agency lead for resolving
25    generic issues.  Wayne mentioned high burnup and burnup
.                                                                22
 1    credit.  Burnup credit started as an issue for
 2    transportation casks.  We currently -- the standard has been
 3    that fresh fuel assumption is used in analyzing criticality
 4    for the transportation casks.  DOE has for several years
 5    tried to get a topical report approved on burnup credit and,
 6    also, more recently, we have issued an interim staff
 7    guidance on burnup credit.
 8              As for Part 71 rulemaking, periodically, the IAEA
 9    transportation standards, which appear in a document called
10    ST-1, are revised.  That occurs on a 10 year cycle
11    currently.  The U.S. regulations, as well as the regulations
12    of the rest of the world, are currently compatible with the
13    1985 versus of the IAEA standards.
14              The entire world is in the process of revising
15    their requirements to be compatible with the 1996 version. 
16    Now, the nature of those changes that were undertaken in
17    this revision cycle are fairly minor.  There is no change to
18    the overall approach to transportation safety or the cask
19    certification scheme.  There are some changes in details,
20    for example, certain packages transported by air, large
21    quantities by air have a higher package standard.  There is
22    some additional fissile material standard for transportation
23    by air, and there are some additional requirements for
24    uranium hexafluoride packages.  Those affect more the DOT, I
25    am sure that Rick could elaborate on that.
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 1              The thing we have done so far in our rulemaking
 2    process is we are in the process actually of identifying the
 3    provisions in Part 71 that will need to be changed in order
 4    to be compatible with the ST-1 standard.  And so far we have
 5    identified about 13 topics that paragraphs in Part 71 would
 6    need to be changed to bring us up to international
 7    compatibility.
 8              The implementation date, I should say, for 1996
 9    ST-1 is -- the worldwide implementation date is January 1st
10    of 2001.  Very few countries are on pace to meet that date,
11    but certain mobile organizations like the International
12    Civil Air Transport -- International Civil Aeronautics
13    Association are on pace to adopt it in that time.
14              There is also in Part 71 some non-IAEA changes,
15    and this is the second bullet, second main bullet.  For
16    example, we recently revised Part 72 to include a change
17    process that allows for small changes to be made to casks
18    without NRC proapproval, similar by reactor facilities,
19    similar to the existing authority reactor facilities have to
20    make changes to their plant without NRC proapproval if there
21    is no safety questions involved.
22              Another change is we have an outstanding petition
23    on the double containment of plutonium.  We currently have a
24    requirement in Part 71 that says that any packages bearing
25    greater than 20 curies of plutonium must, first of all, the
.                                                                24
 1    plutonium must be in solid form and, second of all, a double
 2    containment system, basically, a package within a package
 3    has to be provided for that system.  We have a petition that
 4    asks us to remove that requirement and, as part of this Part
 5    71 rulemaking, we intend to resolve that petition.
 6              We want to expand the scope of Part 71 to include
 7    certificate holders.  This is an issue that we have already
 8    changed in Part 72, and what it amounts to is, under the
 9    Atomic Energy Act, we have, we believe, the authority to
10    issue notices of violation to certificate holders.  But
11    right now there is no mechanism in Part 71 to do that, so we
12    have been issuing these notices of non-compliance or
13    something like that.  So this is the intent of that change,
14    to allow us to write notices of violations.
15              And, finally, in 1997, as a result of some
16    material being returned from the former Soviet Union that
17    contained beryllium, we recognize it though as a
18    nonconservatism in our regulatory approach, and we changed
19    that with an emergency rule.  That is called the Fissile
20    Exemptions Rule.  And the effect of that rule was that there
21    were certain requirements that beryllium is being a better
22    moderator than water, and the rule is being based upon water
23    moderation, the rules didn't handle it well, so we added
24    emergency, a final rule in 1997 to change that situation, to
25    correct that nonconservatism.
.                                                                25
 1              And that rule had some unintended impacts upon the
 2    industry and we solicited comments when we issued the final
 3    rule, and as part of the Part 71 rulemaking, we intend to
 4    resolve those comments.
 5              As far as the process for Part 71, the staff would
 6    like to use an enhanced public participatory approach for
 7    Part 71, similar to the approach that was used in 10 CFR
 8    Part 63 for Yucca Mountain, where we went out and actively
 9    did meetings and got people's comments at the meetings and
10    brought them back and included that in developed the
11    proposed rule, and also in resolving comments to the
12    proposed rule.
13              Part 70 rulemaking recently was -- the proposed
14    rule was issued and a final rule is pending, but that also
15    used the enhanced participatory approach.  We haven't -- we
16    have to describe in the near future to the Commission, I
17    think we owe them, in May, a plan that will describe the
18    approach we plan to use for Part 71.  So that is why I leave
19    it, we plan to do this, not we intend to do this, at this
20    point.
21              We are, of course, coordinating changes with Part
22    71 with DOT.  The DOT requirements and the NRC requirements
23    need to be consistent.  They both -- they overlap in a lot
24    of respects and we would promulgate our rule in concert with
25    them promulgating their rule so there is no period of dual
.                                                                26
 1    regulation that isn't consistent.  And our current schedule
 2    would have us issuing a proposed rule next March.
 3              Now for transportation studies that have been
 4    studying since, basically since NRC was created back in the
 5    1970s.  In 1977 we published the first comprehensive
 6    evaluation risk study of transportation safety.  I should
 7    say I have a detailed slide on each of these studies.  This
 8    just shows the overall picture of how things have evolved.
 9              Based upon the 1977 EIS, in 1981 the Commission
10    issued a finding that the current regulations provided an
11    adequate level of protection and no immediate changes were
12    needed but they stipulated that prudence dictated that we
13    continue to look at these issues of transportation and
14    subject them to close and continuing review, and that is
15    what we have been doing ever since.
16              In 1987 the next major study was issued.  It is
17    called "Shipping Container Response in Severe Accidents" but
18    everybody knows it as the Modal Study, because it looked at
19    the different modes of transport including highway and rail
20    modes.  That study was prompted more or less in response to
21    some questions that were raised regarding return of fuel to
22    reactors due to the closing of the West Valley Reprocessing
23    Facility.  That study looked in greater detail at the
24    accident portion of the Environmental Impact Statement
25    assessments.
.                                                                27
 1              That brings us to today and shortly I guess -- it
 2    is in publication right now -- we will issue this document
 3    called "The Re-Examination of Spent Fuel Risk Estimates,"
 4    which is akin to a revalidation of our conclusions from 1977
 5    based upon the newest technologies, not only the newest
 6    analysis tools but also the changes that have occurred as a
 7    result of larger, dual purpose casks being used, shipment
 8    instead of to a recycling facility, shipment to a repository
 9    and changes of that nature.
10              The next step in this ongoing process will be the
11    package performance study which we have just begun, and we
12    are in the scoping study phase of that project.  By the end
13    of this fiscal year we plan to move beyond the scoping
14    study.
15              NUREG-0170 once again was the first comprehensive
16    look at the transportation safety using the existing NRC and
17    DOT regulations.  This is not an EIS done in support of a
18    change to regulations.  It looked at the existing set of
19    regulations which for package certification purposes really
20    haven't changed all that much, but it looked at the existing
21    regulatory structure and decided what level of safety that
22    provided.
23              It assessed both public and transportation worker
24    impacts for both incident-free transportation and for
25    accidents, transportation accidents, for all radioactive
.                                                                28
 1    materials -- spent fuel is only one of 25 different
 2    materials.  Medical shipments I think are the biggest
 3    fraction of number of shipments and it included all those
 4    too.
 5              This document is still used as the basis for NRC's
 6    and DOT's regulations and the studies since 1977 have
 7    continually affirmed that its conclusions are valid, that
 8    being that NUREG-0170 will have predicted a certain amount
 9    of personrem.  In 1981 the Commission concluded that that
10    amount was acceptable and the subsequent studies have always
11    predicted lower personrem because of the conservatisms that
12    were built into the original project, because they didn't
13    understand or they didn't have good data on things like
14    accident response of casks and stuff like that.
15              So regarding spent fuel, the spent fuel was one of
16    five 25 materials studied.  The 0170 report assumed a
17    reprocessing economy and predicted shipments in 1978 and
18    predicted shipments in 1985 of about 2,000 per year -- 1500
19    truck and 600 rail or something like that.  Those of course
20    were never realized because the reprocessing economy was
21    abandoned, and the total population dose is from spent fuel
22    that NUREG-0170 predicted in personrem are stated in the
23    last line.
24              Very simple accident release was used in
25    NUREG-0170 and there was no modeling.  It was just if there
.                                                                29
 1    is an accident of this severity "x" amount will be released. 
 2    I think the maximum release was something like 300 curies of
 3    cesium or something.  It was just based on engineering
 4    judgment alone.
 5              The Modal Study, which was finished in 1987, only
 6    looked at spent fuel and it was done, as I said, partially
 7    because of the shipment, the questions that were asked
 8    during the return of shipments from West Valley to the
 9    utilities.  The Modal Study took advantage of some new tools
10    that were available, finite element analysis became more
11    feasible to do.  The computer power had increased enough and
12    so what we did in the Modal Study looked at some historical
13    accident rates, tried to calculate severities of those
14    accidents based upon developing a fault tree type thing of
15    what could go wrong in an accident and what fraction of the
16    route length would involve hard surfaces along the roads and
17    stuff along those lines, and looking at the impact forces
18    and the thermal forces that could be created in accidents
19    that tried to predict releases from casks, from spent fuel
20    casks using a finite element analysis of the cask wall.
21              It didn't try to model the seal mechanism, the
22    lid, because the computer power wasn't available at that
23    time and the cask wall was presumed to be an adequate
24    representation.
25              Also, one other thing it did was it related the
.                                                                30
 1    Part 71 hypothetical accident tests which are the 30 feet
 2    drop onto an unyielding surface, the 40 inch drop onto a
 3    mild steel bar, six inch mild steel bar, and the 30-minute
 4    fire immersion at 800 degrees, and it tried to see where you
 5    stood in the real world realm of accidents if you minimally
 6    met those tests.
 7              The conclusion there was that those tests
 8    encompass about 99.4 percent of accidents that could occur,
 9    whether they be rail or highway.
10              It also did some case studies of some historically
11    very severe accidents and postulated what would happen if
12    the spent fuel casks had been involved in those accidents. 
13    The Caldecott tunnel fire I think is one of the most famous
14    severe fires and they concluded that had spent fuel casks
15    been involved in that fire it would not have been damaged to
16    the point of releasing its contents.
17              The final conclusion it drew was it did compare
18    its results to -0170 and determined that the risks were
19    about one-third of those from NUREG-0170, so that brings us
20    up to the current study we have underway, about to publish. 
21    Actually it is, the study is done.
22              Once again this looks only at spent fuel
23    shipments, only at normal risks, and accident risks,
24    transportation accident risks, and instead of looking at
25    reprocessing economy this looks at possible combinations of
.                                                                31
 1    storage and repository locations and route length from
 2    reactors to those locations, and it looks at current cask
 3    designs, modern fuel properties like higher burnup, more
 4    realistic cooling time than was used, a 90-day cooling time
 5    in -0170 was assumed.
 6              One of the things it does is also models,
 7    explicitly models the closure, the cask closure system, with
 8    a finite element model to see what the cask closure system
 9    response is to impact and thermal forces, because the cask
10    closure system appears to be the most likely place were a
11    release path could be created in an accident.
12              It used RADTRAN 5.  RADTRAN 1 was the risk code
13    that was developed to perform NUREG-0170.  It is up to
14    RADTRAN 5 now and it is a much more detailed code, with many
15    different input parameters that can be chosen and actually
16    for this study we did do a little bit of sampling of some of
17    the key variables to see what the sensitivity of those
18    variables were to the result.  Some variables like the
19    package radiation level, the regulatory limit is 10 millirem
20    per hour, two meters.  That was a variable that was sampled
21    in this study to look at the effects, because not all
22    shipments are expected to be done at the regulatory limit,
23    especially as the cooling time of the fuel increases.
24              That turns out to be one of the most important
25    variables.  Population density is an important variable. 
.                                                                32
 1    Duration of truck stops is an important variable, and that
 2    is one we sampled to see -- it is kind of adding a little
 3    bit of probabilistic aspect to the study but by no means is
 4    it a probabilistic study.  It is still a very deterministic
 5    analysis.  The LHS sampling method was used for that.
 6              The result that we are getting for this report
 7    which we are about to issue is that the risks that this
 8    study calculate are in a best estimate type analysis less
 9    than the risks represented by the Modal Study, which are
10    subsequently about three times less than the risks
11    represented by NUREG-0170.
12              We have just started, as a matter of fact next
13    week we are going out to Sandia to help them in their
14    efforts to write a plain English complement to the technical
15    report that we are about to publish.
16              MR. LEVENSON:  Would you be willing to make a
17    guess as to what percent of the reduction in risk is due to
18    the fact that changes in the properties of the fuel, longer
19    cooling, et cetera, are a significant part compared to
20    improved methods of analysis?
21              MR. LEWIS:  The age of the fuel has an effect in
22    the accident risk but it is not as much a big effect in the
23    incident-free risk, which tends to dominate the overall risk
24    anyway because the incident-free risk is really only based
25    on the dose rate at two meters from the package.
.                                                                33
 1              MR. LEVENSON:  But that comes down also with
 2    longer cooling?
 3              MR. LEWIS:  Right, but the RADTRAN code doesn't
 4    calculate based on the cooling time of the fuel.  It just
 5    assumes that it is 10 millirem --
 6              MR. LEVENSON:  It assumes the limit.
 7              MR. LEWIS:  -- or in our case we might have gone
 8    down to 8 or something, but it assumes that everything is at
 9    the limit so the normal risks tend to dominate by a factor
10    of 10 or so the accident risks.
11              The accident risk though does change with the
12    different cooling time because of the source term change.
13              I could not give a quantitative guess off the top
14    of my head.
15              MR. LEVENSON:  No, but I think the important
16    comment was your one that the normal risks dominate.
17              MR. LEWIS:  Yes, because the 10 millirem per hour,
18    two meter exposes many people.  It exposes a greater number
19    of people along the entire route as compared to the accident
20    risk you have to calculate the probability of an accident
21    occurring in the first place and the probability of it being
22    in an urban area falls in there too.
23              MR. LEVENSON:  Would you care to comment on the
24    recent French decision to stop decontaminating casks because
25    yet more people are being exposed decontaminating casks than
.                                                                34
 1    would be exposed if they shipped them that way?
 2              MR. LEWIS:  Well, when you look at arguments like
 3    those, the contamination limit on the cask is going to be
 4    something, so there is a certain amount of exposure you get,
 5    that the workers at the power plant will get to determine
 6    the contamination level, whatever it may be.
 7              I think that even if the Europeans are not
 8    entertaining raising the contamination level that has been
 9    in existence, that contamination level, by the way, is not
10    really meant for spent fuel casks, it is meant for the
11    materials package that maybe a thousand packages a year goes
12    through some FedEx facility and the same guy handles each
13    one, and that is where the basis for that contamination
14    limit comes from.
15              So the short answer is that I don't buy into those
16    arguments.  I don't think it is a big impact.  Nobody in the
17    U.S. -- we have had also experience with casks.  I don't
18    think it's been an issue that has raised a lot of alarms.
19              DR. GARRICK:  Excuse me.  If you were to exclude
20    collective dose as a consideration and only look at it on
21    the basis of individual dose, would you change anything that
22    you are doing?
23              MR. LEWIS:  Well, I don't believe we would.  We
24    did look at the maximally exposed individuals for normal
25    transport and for accident transport, accidents that could
.                                                                35
 1    occur during transport and those values I don't have on the
 2    top of my head but they are definitely less than like 100
 3    millirem per year for the incident-free.
 4              You get into a lot of, you have to make a lot of
 5    assumptions like the amount of time -- say you are stuck
 6    next to it in a traffic jam.  Theoretically if you are stuck
 7    there you get 10 millirem per hour.  Say you are two meters
 8    from the cask.  Well, how many hours would you be stuck in a
 9    year and if there's multiple shipments, how many traffic
10    jams would you be stuck in next to a cask?  You have to make
11    some assumptions and I think that we are comfortable with
12    the assumptions we made and the doses we got.
13              DR. GARRICK:  Yes, but those are pretty reliable
14    assumptions.  I mean there's tremendous amounts of data on
15    traffic and traffic delays and of course it is coming at us
16    with much greater abundance now than ever before, so there
17    shouldn't be a great deal of uncertainty associated with
18    being able to represent and characterize how a cask would
19    move over a particular path, it would seem.
20              MR. LEWIS:  Yes, I don't think -- I wasn't making
21    that point.  What I was trying to say, I think, is you could
22    take a very simplistic assumption.  I think that the state
23    of Nevada maybe has tried to analyze this and for example
24    using the 10 millirem per hour they assumed a person could
25    be stuck in traffic for four hours.  Therefore, their dose
.                                                                36
 1    is 40 millirem from that traffic and I think that neglects a
 2    lot of factors that you could debate whether you should
 3    include, like shielding that is between the people, the
 4    actual distance, whether it is two meters or 2.5 meters
 5    tends to impact that a lot.
 6              It's an argument that you have to justify what you
 7    do.  Although you might not want to be ultra-conservative,
 8    you want to be on some middle ground there.
 9              MR. LEVENSON:  Let me ask a slightly different
10    question.  Since all of these shipments are monitored, the
11    data must exist.  What fraction of the shipments actually
12    are at the 10 MR limit?  What fraction of them are
13    significantly below that?  This is a case where we must have
14    a very large database.  Why do we continue with a
15    hypothetical number?  We have a database
16              MR. LEWIS:  And I don't know the answer to that. 
17    Maybe Earl does.
18              DR. GARRICK:  Microphone.  Identify yourself
19    first.
20              MR. EASTON:  Earl Easton.  I am with Spent Fuel
21    Project Office.
22              A lot of the newer casks have not been used yet. 
23    The ones that are going to be optimized to go to the
24    repository are being designed right up to the limit to get
25    the maximum amount of fuel in, so a lot of the data, yes, we
.                                                                37
 1    have is very good, but we are anticipating an optimization
 2    of casks to lower the number of shipments, to lower the
 3    expense.  It might be right up against the limit.
 4              MR. LEVENSON:  But do you have any data on
 5    historically what it has been?  That was really my question.
 6              MR. EASTON:  I think there is some data.  I think
 7    there is -- actually there was a NUREG done by the NRC that
 8    tried to predict the average TI.  That is the limit from
 9    transportation casks that the Department of Energy tried to
10    use in its Rad Protection Program.  I think it is referenced
11    average.
12              Do you know the number, Rick?
13              MR. BOYLE:  No, I don't.
14              MR. EASTON:  No?  Well, we could probably get that
15    to you but I think --
16              MR. LEVENSON:  My question is really a very simple
17    one.  All of these casks you have calculated would come out
18    10 MR and now they have all been measured, the ones that
19    have been used in the past.  The question is a very simple
20    one.  How good was your modeling?  Is the radiation from the
21    casks one or two orders of magnitude less than calculated or
22    is it more?
23              I am not sure -- I am not asking in pejorative way
24    whether it is less or more, but certainly by now every cask
25    that has moved has been monitored "x" times.  Don't we have
.                                                                38
 1    any data, real numbers compared to the postulated numbers?
 2              MR. LEWIS:  We did sample the dose rate that comes
 3    from the casks.  It is not a variable that varies orders of
 4    magnitude.  It is going to be between like five millirem per
 5    hour, 10 millirem per hour, in that area, because the cask
 6    is designed to hold its maximum contents and be 10 at that
 7    point.  That is one of the criteria we have in Part 71. 
 8    There's other criteria that may actually be more limiting on
 9    it, but that is one of the criteria, but what we have done
10    in risk assessments is two things.
11              First, we assume that all the casks are at the
12    limit of 10 and that gives us a data point if you will --
13    this is what, this would bound the risk certainly, and then
14    we have also looked at the distribution of the more
15    realistic cask dose rates and decided how that variance has
16    a sensitivity effect on the answer, and all that is wrapped
17    into this overall conclusion that risk is lower than -0170,
18    it is lower than the Modal Study.
19              MR. LEVENSON:  Go ahead.
20              MR. LEWIS:  Any other questions?
21              DR. GARRICK:  Well, I just wanted to pick up on
22    one thing before we get off the fuel cask business and onto
23    the regular transportation issues.
24              The studies that you have done, the risk study,
25    the Modal Study, these have been based basically on finite
.                                                                39
 1    element methods and risk assessment methods, fault tree
 2    methods and so forth.
 3              In the '70s there was a great deal of testing of
 4    casks at Sandia -- railroad crash tests, truck crash
 5    tests -- and I realize the design of the casks have changed
 6    with time, but how much of that experience has been brought
 7    forward into these particular analyses?  How much --
 8              MR. LEWIS:  Explicitly --
 9              DR. GARRICK:  -- are these analyses test
10    supported, I guess?
11              MR. LEWIS:  There was no explicit attempt to
12    incorporate that test information into the re-examination
13    study.  One thing we are doing, and it is a good segue into
14    the next slide, is the package performance study will
15    consider the benefits of testing and it has as part of its
16    scoping study to look at what testing had been done in the
17    past and how that could help us, but what I should say is
18    that that testing was done in Sandia Labs.  Sandia Labs has
19    done the re-examination and they are also our contractor for
20    the package performance study, which is the next one I will
21    talk about, but the NRC did not sponsor that testing, and
22    the testing was done for illustration purposes, in the
23    colloquial saying.  It was done for illustration purposes. 
24    It wasn't done for the intent of demonstrating any degree of
25    safety quantitatively against our Part 71 approach, so we
.                                                                40
 1    are incorporating what they have done insofar as they could
 2    assist us.
 3              We asked Sandia to include that in their issues
 4    report they are going to give us at the end of the scoping
 5    study, but in reality I don't believe that testing will give
 6    us very much useful information in terms of these new
 7    products.
 8              DR. GARRICK:  So, are you saying that the designs
 9    really haven't had an evolution or much of an evolution?  I
10    would think that people that are in the cask design business
11    would have relied very heavily on those tests.
12              They were very convincing, and there was a large
13    series of them and they were very expensive tests.  I'm a
14    little surprised that they're sort of just set aside as not
15    being applicable to Part 71 specifications when what we're
16    talking about here is the physics of failure of cask design
17    that can be reduced to some pretty fundamental
18    considerations, it would seem to me.
19              As a risk analyst, I would -- the first place I
20    would go to to get a sense of how to model these casks and
21    what kind of input to put into my model would be those
22    tests.  And I would look for differences between the design
23    and the way in which those casks were designed and the ones
24    that we're trying to analyze.
25              From a risk assessment standpoint, that's an
.                                                                41
 1    enormous insight with respect to the kinds of failure
 2    mechanisms that can take place, and the consequences of
 3    impact forces and heat and what have you.
 4              So I'm a little surprised that in all of this,
 5    there seems to be such a little tie with what at one time
 6    was a very intense activity of tests performance at a time
 7    when there were hearings and debates between the railroads
 8    and the utilities and law suits and tremendous amounts of
 9    information brought forward to try to correlate train
10    accidents, for example, and the kind of severities that you
11    could get with these kinds of accidents, with cask failures
12    and the consequences of those failure.
13              MR. HODGES:  Well, I'm not aware that those tests
14    were well implemented to get them the data you might need. 
15    As you say, they were used more to demonstrate that the
16    casks were robust than to get that kind of data.
17              But I think the number of non-spent fuel shipping
18    casks are tested and are analyzed with the same computer
19    codes that are used specifically for the spent fuel casks.
20              If you look at the crash tests that the automobile
21    industry does on automobiles, they analyze them with the
22    same computer codes we're doing for spent fuel casks, and so
23    there is a fair amount of validation of the physics that is
24    modeled in those codes.
25              DR. GARRICK:  Well, maybe what you're doing here
.                                                                42
 1    is not taking credit for that kind of knowledge and
 2    information base that exists.
 3              MR. HODGES:  Right.
 4              DR. GARRICK:  And you're maybe not doing yourself
 5    as much justice as you should, because the impression here
 6    is that these are just analyses.
 7              MR. HODGES:  These specific analyses were not
 8    based -- were not supported by testing, though.
 9              DR. GARRICK:  Well, I don't believe that.  I don't
10    believe that.  I think the people that were doing the hard
11    work were very much aware of the results of those tests and
12    the documentation that supported those tests, of which I've
13    still got some -- it's that much -- as being extremely
14    valuable in the way in which I would model these casks.
15              So I think that's a wrong statement.  I just don't
16    accept that, as an analyst.  I think that there is a
17    continuity here at the analysis level and the modeling level
18    that probably exists that you're not manifesting in these
19    kinds of presentations.
20              Or else the analysts that are doing it are not
21    taking advantage of it.  That's my only point.
22              MR. HODGES:  Okay.
23              MR. LEVENSON:  Let me just comment.  My view of
24    such things is normally quite different than John's because
25    I'm of the old school of engineering which makes any
.                                                                43
 1    analysis suspect if it isn't supported by a test.
 2              And even though the tests were completely
 3    different kinds of casks and different conditions, it seems
 4    to me that benchmarking what you now think is a proper code
 5    against those tests would certainly give a large amount of
 6    credibility to your current analytical methods and so forth.
 7              If you can't benchmark them against the newest
 8    designs that haven't been tested yet, but if you're code
 9    doesn't predict what really happened in the old ones, then I
10    think you've got a suspect code that I think you better take
11    a look at.
12              MR. LEWIS:  Maybe I could address that in the
13    context of when I talk about package performance studies. 
14    Because, I didn't mean to leave the false -- it is a false
15    impression that we don't think there's anything useful to
16    gain from the tests that were done in the past.
17              That was one of our reasons for selecting Sandia. 
18    Some of the people that are on our team at Sandia were
19    involved with those tests.
20              DR. GARRICK:  That's my point, that I suspect that
21    there is a continuity of knowledge here that is very
22    beneficial to this whole process, and that there is a
23    stronger tie with fundamental measurements and observations
24    than maybe you're taking credit for.
25              MR. LEWIS:  In the package performance study,
.                                                                44
 1    again, we'll only look at spent fuel truck and rail
 2    packages.  In this case, we will focus on the accident
 3    portion of the risks, not the incident-free risks.
 4              And what we intend to do is, as the reexamination
 5    was built as a logical followon to the 0170 project, the
 6    package performance study is the logical followon to the
 7    Modal Study component of that.
 8              And people say -- people have called this Modal
 9    Study II, including myself, call it Modal Study II.  We're
10    not redoing the Modal Study, because we don't believe that
11    anything is inherently wrong with the original Modal Study.
12              What we are doing is, we're building upon that,
13    and we're building upon the 2000 reexamination study as an
14    additional tool to make the safety case.
15              The goal of the package performance study will be
16    to assess severe accident cask performance and fuel
17    performance.  We may look at the behavior of the fuel inside
18    the casks in greater detail than we have in some of the
19    previous studies.
20              Of course, that would have to assume that the cask
21    already has a leak path due to the accident.
22              One of the major points of this scoping phase that
23    Sandia is currently contracted to do is to consider the need
24    for and benefits of physical testing, whether it be partial
25    scale or whether it be full scale, and not only physical
.                                                                45
 1    testing at the hypothetical accident conditions in Part 71,
 2    the 30-foot drop and so on, but physical testing beyond that
 3    realm into the 90 mph collision, say, to see that our risk
 4    codes and estimates in that realm are representative. 
 5    Therefore, we could determine the risk significance or
 6    insignificance in that very severe accident realm in greater
 7    detail.
 8              And we are, as I mentioned, using an enhanced
 9    public participatory approach, which is the subject of a
10    slide in a second, so I will get to that.
11              But where we are today, we have a contract with
12    Sandia Labs to do --
13              MR. LEVENSON:  Excuse me.  On the previous slide,
14    I've got the question of -- are the packages by which the
15    vitrified Defense wastes will be shipped from Savannah River
16    to Yucca Mountain, if that's where they go, are those
17    licensed shipping containers, by NRC?
18              MR. LEWIS:  Yes, they will be certified by the NRC
19    because the Nuclear Waste Policy Act requires all high level
20    waste --
21              MR. LEVENSON:  So it isn't only spent fuel? 
22    That's my question, where do those casks fit into this
23    picture?
24              Your slide says spent fuel only.
25              MR. LEWIS:  Well, we focused on spent fuel because
.                                                                46
 1    it's the larger component of the risk of the shipment in an
 2    accident.
 3              MR. LEVENSON:  But you also have a responsibility
 4    for those.  Part of what we're trying to do is sort out
 5    who's responsible for what.
 6              MR. LEWIS:  We would certify any high level waste
 7    package that would be going to Yucca Mountain.  That's my
 8    reading of the Nuclear Waste Policy Act.
 9              Sandia is working, and as we speak, they're
10    working on the scoping study phase.  We've gone out to the
11    public and collected public comments on the package
12    performance study.
13              We made up a bunch of issues, and got roundtable
14    of experts and kind of did a brainstorming, all-day
15    roundtable session to find out what could be and what maybe
16    should be done.
17              The second part of the scoping study is to do a
18    literature review and determine what tests have been done in
19    the U.S. and worldwide, because there are some tests in
20    England and Japan, I understand, that have also been done on
21    spent fuel cask performance against the IAEA standard.
22              Of course, there is a lot more experience in
23    shipping spent fuel internationally than in the U.S., and
24    the international standards are essentially the same as the
25    U.S. standards for Type B spent fuel type packages.
.                                                                47
 1              And the product of this first phase is going to be
 2    the Issues and Issues Resolution Options Report, which is
 3    due to NRC at the end of next month.  It will take us a
 4    month or maybe a month and a half to turn it around and give
 5    it out to the public.
 6              Our intent is to share that Issues Report with the
 7    public.  This issues report is akin to a proposal for
 8    followon research.  It's kind of a joint proposals from NRC
 9    to the public and from Sandia to NRC.
10              And it will describe the approach by which we plan
11    to proceed for the next phases.  We currently do not have
12    any contract for anything beyond this scoping study phase.
13              MR. LEVENSON:  I have one other -- sorry, going
14    back -- clarification question on what's in your scope. 
15    Does NRC license the casks that are used to ship spent fuel
16    back to this country from overseas reactors?
17              MR. LEWIS:  We issue a revalidation of a foreign
18    competent authority certificate through a request from the
19    DOT, which is kind of yes.
20              I mean, we do look at the casks, any import/export
21    casks for spent fuel.
22              DOT wanted to add something.
23              MR. BOYLE:  Yes, both.  If they are domestic,
24    there are certain casks that are manufactured in the U.S.
25    that are licensed by the NRC first, then revalidated by the
.                                                                48
 1    Department of Transportation, which then are shipped
 2    overseas to retrieve the research reactor fuel.
 3              There are also foreign packages that get foreign
 4    certification first, are sent to the Department of
 5    Transportation.  We ask for the NRC's review and
 6    recommendation before we issue a license, so there are both
 7    types used for that research reactor shipment.
 8              MR. LEVENSON:  Thank you.
 9              MR. LEWIS:  Thanks, Rick.  Like I said, we are
10    using for the package performance study, this intense public
11    involvement process, not only in describing how we're
12    proceeding with the study, but designing the study itself.
13              We have a website established which has study
14    information on it, and a forum for interactive communication
15    on the project.
16              We have held workshops last year.  At these
17    workshops, we had DOE, DOT, the nuclear industry and the
18    transportation industry, all collected at a roundtable, as
19    well as others like the International Atomic Energy
20    Commission came to one of them.
21              As I said, we had this session where we presented
22    some ideas and Sandia presented some ideas, and we just kind
23    of brainstormed on what should be done.
24              We held some public outreach meetings in Nevada. 
25    We had a workshop in Nevada, like I just described, and we
.                                                                49
 1    also had some more traditional public meetings in Nevada,
 2    kind of town hall type meetings in the December timeframe.
 3              We have a study mailing list which we haven't used
 4    much because we don't have any products yet, but we do have
 5    this mailing list we're compiling.
 6              We have planned for additional workshops, once we
 7    get this first phase product, the issues report.  We're
 8    going to go out to the public and present it in workshops
 9    this summer.
10              At those same workshops, we'll also present the
11    results of the reexamination study that will be published
12    this month, and hopefully between this month and the public
13    meetings, we can let the public have a chance to digest it,
14    as well as get the public consumable brochure, the plain
15    language version out in time for those meetings as well.
16              And so that's all I had, and unless you have
17    questions, I'll turn it back over to Wayne for the summary.
18              MR. HODGES:  In summary, we think the reactor
19    licensees will have more options for dry cask storage
20    available.  There should be four dual-purpose casks
21    available by the end of this calendar year.
22              We have established rules of engagement and
23    schedules for review, and as a consequence, the FSPO staff
24    has met all schedules.
25              We have introduced a stability and predictability
.                                                                50
 1    to the review process.
 2              There are areas for improvement, both in the
 3    process, procedural improvements such as amendment process,
 4    and for resolution of technical issues such as for high
 5    burn-up fuel and burn-up credit.
 6              We're actively engaged with both the industry and
 7    the public in discussing the issues related to spent fuel
 8    storage decommissioning and transportation.
 9              As far as the transportation studies themselves,
10    we're positioning ourselves to be better prepared to address
11    questions on the large shipment campaign when it does come,
12    and we're actively seeking public participation as we go
13    along.
14              That concludes the presentation, and we're open
15    for questions.
16              MR. LEVENSON:  Yes, for clarification on this last
17    point, there is a large shipment campaign.  I'm just trying
18    to sort out who is responsible for what.
19              It's clear that the NRC licenses the shipping
20    container.  You say that you review routes; you earlier
21    mentioned that.
22              But exactly what is your responsibility in the
23    overall transportation picture, other than licensing the
24    casks?
25              MR. BOYLE:  You might want to let my presentation
.                                                                51
 1    go first.
 2              MR. LEWIS:  You might want to hear from DOT, but
 3    our responsibilities are specified in Section 180 of the
 4    Nuclear Waste Policy Act, and they are limited to certifying
 5    the packages for high level wastes that go to Yucca
 6    Mountain, and DOE must also use our advanced notification
 7    procedures in shipments to Yucca Mountain.
 8              DOE has the responsibility to do training along
 9    the route.  That particular paragraph of the Act doesn't
10    mention anything about NRC's role there.
11              MR. LEVENSON:  What is covered under what you call
12    physical protection that you said you were responsible for? 
13    Are those guards?  What does physical protection mean?
14              MR. LEWIS:  Physical protection is the term we use
15    when we talk about our 10 CFR Part 73, which is prevention
16    of theft of the material, as well as that provision also has
17    the safeguards rules in there.
18              Our requirements involved armed escorts through
19    cities, immobilization devices in the truck, yes, constant
20    communication capabilities, and one that's slipped my mind
21    -- oh, safe havens be identified along the routes and things
22    of that nature.  It's not safety; it's our safeguards aspect
23    of the Agency's role.
24              MR. LEVENSON:  Oh, so it's safeguards, not safety.
25              MR. HODGES:  Safeguards.
.                                                                52
 1              DR. GARRICK:  Wayne, NRC has just finished risk
 2    assessment, spent fuel pool risk assessment.
 3              Has there been anything -- I haven't -- I have
 4    just barely glanced at that, but has there been anything in
 5    that study that has been of any help to your studies?
 6              I'm thinking primarily of any special work that
 7    was done to quantify the source term and the integrity of
 8    the fuel and what have you.
 9              Is this providing you with any additional source
10    material that enhances the quality or reduces the
11    uncertainty of some of your analyses?
12              MR. HODGES:  I haven't personally even looked at
13    that one yet, but some of the staff may have.
14              DR. GARRICK:  Okay.
15              MR. HODGES:  But I'm not aware of anything at this
16    point.  We are having some work done in the Office of
17    Research now to help out with the study that we're starting
18    on risk in dry cask storage.  And that should be done soon.
19              DR. GARRICK:  Well, the other thought I had there
20    is that I don't know how far you're pushing the
21    risk-informed methods.  But I would have thought that on
22    that particular study, they would have pushed them pretty
23    far.
24              And it's possible that there would be some.
25              MR. HODGES:  Yes, but it's a different set of
.                                                                53
 1    issues that you deal with.  Our failures tend to be things
 2    like cladding creep over a number of years as opposed to the
 3    kinds of things you might have in a pool, and so it's a
 4    different kind of a technical issue.
 5              DR. GARRICK:  Yes.  One final question:  Have you
 6    attempted to characterize the importance of what one might
 7    call the accident risk versus the routine risk or the acute
 8    risk versus the chronic risk?
 9              There are a lot of people that believe that there
10    are very important tradeoffs with respect to those two,
11    especially if you don't get too hung up on the collective
12    dose angle.
13              MR. HODGES:  Right, and I think the Modal Study
14    and this more recent study would tend to show that the
15    normal risks are larger than the transportation and the
16    accident risk.
17              DR. GARRICK:  Yes, yes.  I think it's important
18    for --
19              MR. HODGES:  Both of them being small.
20              DR. GARRICK:  For some sort of information to be
21    put out there that allows people to trade off between the
22    two and appreciate the fact that there is a tradeoff.  The
23    whole waste field seems to be suffering from the syndrome of
24    compromising the operating risks in order to reduce what is
25    believed to be, but a highly uncertain accident risk, highly
.                                                                54
 1    uncertain in terms of timing, and highly uncertain in terms
 2    of consequence.
 3              MR. HODGES:  Some of the work is being done by the
 4    Office of Research for this dry cask storage PRA, and it is
 5    aimed at trying to get best estimates on, one, the
 6    likelihood that one of the casks will leak at all, for
 7    example; and, two, if it does leak, looking at leakage
 8    fractions and release rates and things of that nature.
 9              DR. GARRICK:  The other thing that's important, it
10    seems to me, to keep in mind, at least in the short term --
11    I'm not talking about thousands of years timeframes -- is
12    the recovery angle.
13              One of the little known facts of reactor risk
14    assessment is the high dependence upon accident recovery to
15    keep the risk low.  And you don't really see a great deal of
16    emphasis on recovery scenarios with respect to the analysis
17    of transportation risks.
18              And yet the opportunities there are probably much
19    greater than what you would find in a reactor case.  And the
20    risk is greatly affected in reactor risk assessments by
21    recovery, accident management activities.
22              MR. HODGES:  Right, right.
23              DR. HORNBERGER:  I'm interested in when you
24    certify, the certification process for a new cask.  What
25    kind of testing data are required and what kind of analyses
.                                                                55
 1    are required?  I know you can't give it to me in great
 2    detail, but can you give me a little bit of a mental
 3    picture, at least?
 4              MR. HODGES:  Why don't you start?
 5              MR. LEWIS:  In our certifications, we do accept
 6    analysis, testing, comparison, or combinations of those in
 7    determining whether or not they pass the four hypothetical
 8    accident tests, and the normal condition test as well.
 9              The spent fuel casks typically will use analysis,
10    and if -- they will have an impact limiter on them as well. 
11    Often the impact limiter is tested, but the cask itself is
12    done with analysis.
13              That's my understanding, that that's the typical
14    approach.  That's not to say that somebody couldn't come in
15    with a scale model and test it.
16              MR. HODGES:  It really also depends upon the kind
17    of testing you're talking about.  With fire testing, for
18    example, the regulations allow explicitly to either do
19    analysis or by test, and for something the size of a spent
20    fuel package, it's not very practical to stick it in an oven
21    and do a test, and so it's generally done by analysis.
22              For smaller shipment or transportation packages,
23    it's a mixture.  Some are done by analysis, some are done by
24    tests.
25              Whenever there are new materials that are
.                                                                56
 1    introduced, for example, for neutron shielding, we would
 2    require testing for those materials, looking at things like
 3    the distribution of the boron and how it changes as it
 4    ages.
 5              So there are tests that have been required, but a
 6    lot of the stuff is done by analysis.
 7              DR. HORNBERGER:  That's good, thanks.
 8              MR. WYMER:  The only thing that occurs to me is
 9    that the doses from a cask are so strongly dependent on the
10    cooling time of the fuel before it goes into a cask, that it
11    seems to me that you're not adequately or realistically
12    taking advantage of that wide variation.
13              You could have a whole series of cask types graded
14    to cooling, but it seems to me that you're not really
15    capitalizing on that.
16              MR. HODGES:  That's really by choice of the vendor
17    when they come in with their design.  We don't preclude them
18    from doing that.
19              And in fact, it has been proposed that for some of
20    the high burn-up fuel, they may actually need to do some of
21    that, but it's generally cheaper if you can live with it, to
22    analyze for a kind of uniformity there.
23              MR. WYMER:  I see.  I have just one last question
24    on clarification of responsibility.  NRC licenses the WIPP
25    shipping containers.
.                                                                57
 1              You also have a role in the safeguarding of those
 2    shipments similar to spent fuel?
 3              MR. LEWIS:  No, I don't think we get involved with
 4    that.  We did certify the TRUPAC package, though.
 5              MR. LEVENSON:  Okay.  I want to thank you very
 6    much.
 7              MR. HODGES:  Rick Boyle will come and talk about
 8    DOT activities.
 9              MR. LEVENSON:  Thank you.  I also want to thank
10    you for finishing up five minutes early.
11              MR. BOYLE:  I want to thank you for offering me
12    the opportunity to come speak to you today.  My name is Rick
13    Boyle and I am with the Department of Transportation --
14    rather than run through the litany of abbreviations that
15    would follow, I think as I give you an overview of the
16    Department you will figure out exactly where I sit and it
17    will make more sense to you than just giving you a bunch of
18    initials.
19              I was asked to come in to give you an overview of
20    the Department of Transportation, primarily focusing on
21    hazardous material or radioactive material transport and who
22    is involved, which parts of the Department are involved, and
23    then give you a brief overview of the Department of
24    Transportation and the NRC's relationships.  If I have
25    oversimplified I was told I had about 10 or 15 minutes
.                                                                58
 1    because they didn't expect to finish early so they said keep
 2    it brief and if they have more questions they certainly are
 3    not afraid to ask, so interrupt me at any time you would
 4    like to.
 5              I could have put an org chart up that would show
 6    the Office of the Secretary and the six Associate
 7    Secretaries he has, and the Inspector General, but rather
 8    than that I dropped right to the bottom of his organization
 9    chart, which lists the 10 DOT operating administrations. 
10    Even that, when you get into hazardous material, is a little
11    bit large so we will jump right down to who is involved with
12    hazardous material administrations.  We will also get into a
13    little more pictures.
14              As you can see, this is a little bit idealistic. 
15    RSPA stands for Research and Special Programs Administration
16    and that is where I work.  One branch within that
17    administration is the Office of Hazardous Material Safety. 
18    Now I see everyone is writing "Research and Special Programs
19    Administration, Hazardous Material Safety" -- the technical
20    office houses the Radioactive Material Transport Branch and
21    that is the branch that I head up.
22              This is a little bit idealistic and hopefully this
23    is the way the Department is going, I believe it should be
24    going, is that the Research and Special Programs
25    Administration, by housing the Hazardous Material Office,
.                                                                59
 1    will coordinate the entire Department's hazardous materials
 2    efforts.  I think you can easily see that administrations
 3    such as the FAA, the Coast Guard, Federal Rail, and Federal
 4    Highway are much larger than the Research and Special
 5    Programs Administration, so I think you can understand the
 6    politics of the situation, that the small, minor funded
 7    agencies usually do not drive the whole process, so that is
 8    where this is a bit idealistic but they do defer to us to
 9    develop all of hazardous material regulations, which the
10    radioactive material regulations are part of it.
11              To give you name for the pictures that we see, the
12    train of course is the Federal Railroad Administration and
13    our counterparts are in the Office of Safety Enforcement,
14    and they had a Hazardous Material Branch and then something
15    we'll touch on later but I think was very important, the
16    other offices in that safety deal with track, making sure
17    that the tracks are safe, making sure that the railcars are
18    safe and then a special branch is for -- I think they call
19    it Method of Power.  I would call it the Loco Section -- the
20    locomotives to make sure they are safe, so they have four
21    branches.
22              The airplane you see on the top right is for the
23    Federal Aviation Administration.  Our counterparts are in
24    the Civil Aviation Security and Intelligence Section,
25    certainly a misnomer like Defense Intelligence.  Our
.                                                                60
 1    counterparts are definitely in the Dangerous Goods and Cargo
 2    Security Section.
 3              The cruise ship you see is really a Coast Guard
 4    cutter, but I couldn't find a better picture, and we work
 5    with the Marine Safety and Environmental Protection Group
 6    and then that is what you would see in our organization
 7    chart reflects the Coast Guard at Headquarters.  We also get
 8    many calls from the individual ports representing the
 9    captains of the ports and what is going on out in the field,
10    so they are much broader than you would really see at
11    Headquarters, where more of the other administrations are
12    more what is at Headquarters.
13              Lastly, the truck represents the Federal Highway
14    Administration and their Motor Carrier and Highway Safety
15    Office.  I am sure you are following around here Congressman
16    Wolf from Virginia has been working with the Department of
17    Transportation and that office will be split out separately. 
18    I personally believe he was correct in saying that somebody
19    that is overseeing safety should not be in the same group
20    that is promoting trucking, so you would look to see our
21    organization change and see a Motor Carrier and Highway
22    Safety Office formed.  It has already formed but all the
23    positions are TBA since it hasn't finally come through, I
24    think, the budget process, so I left them under Federal
25    Highway.
.                                                                61
 1              Radioactive Material Transport in the Federal
 2    Government -- a little bit of the who does what to whom, the
 3    regulatory role, which I will define more as I go through
 4    the memorandum of understanding between the two agencies. 
 5    The regulatory role falls within the Department of
 6    Transportation and the NRC and something I knew you would be
 7    interested in, somehow I thought I would throw in the
 8    Department of Energy, who is the primary shipper of most of
 9    the spent fuel and certainly would be the shipper were Yucca
10    Mountain to open.
11              We have a little bit different role or probably a
12    very different role than the NRC has with the Department of
13    Energy.  We treat them as a person.  They are subject to the
14    regulations of the Department of Transportation and that is
15    listed in our regulations in Part 107.3, which is where we
16    define what we mean as "person." Rather than just read it to
17    you -- it is kind of dry, regulatory text -- I can provide a
18    copy to the administration or administrators here and you
19    can see where that comes in and that one of the subparts is
20    also that any Federal agency is also subjected to our
21    regulations, so I will just pull that out.  It is a little
22    bit dry legalese, but I will leave it with you.
23              The one exception to that policy, which is in
24    173.7 of our regulations, which I will also leave -- it says
25    if they are making a shipment for national security, they
.                                                                62
 1    can be excepted from our shipments.  Those are SST shipments
 2    and those would not be spent fuel or their waste products. 
 3    Those are not national security, and there is a whole list
 4    of special provisions they have to take to sign off
 5    paperwork beforehand that that is what they are doing, to
 6    have armed escorts along with it.
 7              My understanding is that was the issue when they
 8    just took the MOX fuel pins up to Canada is they were
 9    bringing it in SSTs and when it got to the Canadian border
10    those SSTs were not allowed to go into Canada, that I don't
11    think the Canadians liked the armed guards or anything else,
12    therefore the shipment was picked up by helicopter and taken
13    the rest of the way to Chalk River.
14              The great dividing line, which I also did bring
15    more copies of so I can leave them for four or five members
16    as well as one for the copy -- I think you will be
17    interested in the memorandum of understanding between the
18    Department of Transportation and the NRC.  That truly
19    defines the who is responsible for what and fortunately for
20    my office, which is very small, most of it is you are
21    talking about spent fuel transport and certainly if you are
22    talking about transportation domestically above a Type A
23    quantity most of those responsibilities fall to the NRC,
24    even though you can see our column is a little bit longer
25    than the NRC's as far as the MOU is given.
.                                                                63
 1              Our responsibility is we serve as the competent
 2    authority.  That means the IAEA safety standards -- we are
 3    the lead agency in the United States but in my recollection
 4    we haven't been over there where we haven't had an NRC
 5    representative right beside us because the regulations do
 6    form the basis for both Title 10 and Title 49 of the Code of
 7    Federal Regulations.
 8              One of the biggest projects we have taken on to
 9    bring into the next revision cycle, which is in 2003 for the
10    IAEA, is a more risk-informed basis.  We have been working
11    to have actual proposals submitted which are instead of --
12    usually it is little more than here is the problem and they
13    do a very brief problem statement, here are the regulations
14    that are affected and what they should be changed to.
15              Working with your staff from the SFPO we have
16    developed a little lengthier format that says you have to
17    give a little more justification and provided guidance to
18    say you do have to look at cost.  You do of course look at
19    safety first, but then there is cost, and there is dose, and
20    there are a lot more factors to consider other than your
21    particular country has a problem with a set of the
22    regulations.  We have also switched to a two-year -- I think
23    it is more of a never-ending rule cycle -- rather than the
24    10-year process where there is a bigger push, because you
25    weren't going to have a chance for another decade to push a
.                                                                64
 1    lot of ideas in.
 2              I think switching to a two-year cycle, which is in
 3    line with the way the UN does it and the Modal organizations
 4    do it, would better suit the review and the development of
 5    risk-informed documentation because you didn't feel if I
 6    don't get it in today, I will have to wait 10 years, so I
 7    think those have been some big changes internationally that
 8    will benefit the way the regs are developed.
 9              Classification -- that would mean defining what we
10    mean by radioactive material and we switched from, we used
11    to call it a below regulatory concern limit, to radionuclide
12    specific exemption values for the regulations, as well as
13    conveyance limits, and that would determine when, as we
14    know, everything is radioactive but to what point you would
15    have to be covered by the radioactive material transport
16    regulations.
17              The dividing line -- you will see Type A materials
18    on our side of the chart, Type B materials on your side of
19    the chart.  It is the same limit.  When you reach that
20    threshold you become the property of the NRC and their
21    packaging requirements.  Below Type A standards are ours. 
22    Low specific activity materials, surface contaminated object
23    material, non-fissile excepted, UF-6 are also DOT's
24    responsibility.  Hazard communications are shipping papers,
25    labels, marking, emergency response phone numbers, the
.                                                                65
 1    emergency response guide book, things of that nature that go
 2    along with the shipment are our responsibility.
 3              Radiological controls, which would be the surface
 4    contamination allowed on packages, radiation levels for
 5    routine transport, and we do have employee training
 6    requirements which I think are minimal.  Their are
 7    function-specific to the job that you perform and you also
 8    are required to have an awareness of what is the hazard you
 9    are transporting, and I think you have to remember for us we
10    have nine hazard classes from flammables and compressed
11    gases, poisons, all the way through radioactive material, so
12    just an awareness of what you are carrying and if you have
13    more than one hazard to know not only is it radioactive, you
14    may have a flammable hazard or it could be a compressed gas
15    or it could be corrosive, so you have to be aware of all the
16    hazards, not just the radioactive, and then we do have
17    emergency response training or emergency awareness training
18    I think is a better term, to say if there is an accident at
19    your facility or with one of your shipments you would know
20    what to do or some general advice to give people.
21              We do have many Modal requirements, but I am going
22    to get to those later because they aren't part of the MOU.
23              Briefly I think the previous presentation with Rob
24    and Wayne went over the NRC responsibilities very well.  The
25    technical support for competent authority -- they come to
.                                                                66
 1    all the meetings with us.  The dividing line is if it is a
 2    domestic package the NRC will certify it and go through the
 3    entire revision process and then we will take second action
 4    to authorize it for import and export purposes.  If it is a
 5    foreign design it comes to us first and when it is for
 6    fissile material it is sent over to this office with a
 7    request for review and recommendation, and when that review
 8    is granted then they would get the approval for import and
 9    export for foreign packages being used in the U.S.
10              The same would be true for most Type B packages
11    and that -- it is written in.  I think you have to
12    understand it is written in the MOU that we do not have to
13    follow that.  That is I think I would say a good practice. 
14    I think we ran into trouble a little over five years ago
15    with not sending enough things to the NRC for their review
16    and where there were more and more foreign packages.  I
17    think we have really changed that and it has put a lot of
18    burden because fortunately because of the MOU we don't have
19    to pay the NRC so those are done gratis and we really
20    appreciate that, but it does put a burden on their time.
21              Safeguard standards were covered.  Quality
22    assurance -- we do reference yours.  Inspection and
23    enforcement -- I can get into the small role that we have
24    later, but you primarily do package fabrication and use,
25    your physical security and you also enforce DOT regulations
.                                                                67
 1    on your licensees.
 2              MR. LEVENSON:  Let me ask one question for
 3    clarification.
 4              MR. BOYLE:  Certainly.
 5              MR. LEVENSON:  On materials I don't know whether I
 6    misunderstood or whether you didn't intend to have it come
 7    out that way, but I interpreted what you said to mean if it
 8    was Type B materials the container, what have you, had to
 9    meet NRC requirements only.  It didn't necessarily have to
10    meet DOT requirements -- that there was a division of
11    responsibility here, that if it is Type A materials, it is
12    DOT requirements.  If it is Type B materials, it is NRC
13    requirements.
14              MR. BOYLE:  I certainly misspoke there if that is
15    what I said, that there are baseline packaging standards for
16    all packages containing hazardous material and those are
17    found in our regulations in 173.24, then there are baseline
18    standards for packaging for radioactive materials that are
19    found in 173.410 and these are all building, these are all
20    cumulative.  You follow those, then you would first hit your
21    Type A standards, which are in our regulations in 173.465
22    and then you would drop out to the NRC Type B, so they would
23    all be cumulative until you get into LSA, SCO which are
24    excepted out from some of them as well as the excepted
25    packages would be dropped out of some of them, but it is
.                                                                68
 1    cumulative into the NRC packaging standards.
 2              DR. GARRICK:  Before you take that off, Rick, I
 3    can't help but comment on this.  As I think back on some of
 4    the public meetings we have had and the training that we
 5    have had in risk communication and I look at that list.  I
 6    can just hear the public looking at that list and saying,
 7    well, really, all I want to know is who is responsible for
 8    safety, and trying to figure out what this really says.
 9              How would you answer a John Q. Public question
10    that says, okay, I don't understand all of these terms and
11    what have you.  What I want to know as a person living on a
12    highway through which all kinds of materials transport who
13    is responsible for the safety of those transports?
14              How would you handle that?  How would you answer
15    that?
16              MR. BOYLE:  First, I want to say the training that
17    we require is of only carriers to train their own people or
18    shippers to train their own people.  We do not require them
19    to go out to their community and say I am running a
20    radiopharmacy here and these would be the risks to your
21    community, so we don't do that as a fixed facility is not
22    required to go out and train the community.
23              As far as that is, I think we would have to go
24    back and as we have participated at the NRC meetings is use
25    the same modal studies and risk studies you are using as
.                                                                69
 1    well as we may pull some international studies together or
 2    our own studies to say the regulations provide for the safe
 3    transport of radioactive material.
 4              My experience is that doesn't always cover it
 5    because one of the things you can't define is what "safe"
 6    means.  What I feel is safe transport certainly is different
 7    than what somebody that maybe lives right along the highway
 8    or lives in a different part of the country would think.
 9              My familiarity with the regulations also is quite
10    different than everyone else.  We have had to in the past
11    drop back to the same type of public outreaches that's been
12    done through the NRC.  We try to do quarterly outreach
13    meetings for hazardous material as a whole, which somebody
14    from the Radioactive Materials Branch goes out.
15              Those are held regionally throughout the country
16    just trying to explain the regulations and what they mean
17    and how they are implemented.
18              DR. GARRICK:  I know, and that is a real problem,
19    because we have heard a considerable amount of emotional
20    rhetoric about transportation and who is responsible for
21    transportation safety and that there's a variety of agencies
22    involved and there is a great need, it seems, speaking of
23    simple English, for some simple English explanations to
24    people who view this as a major issue.
25              In fact, I would say that in some instances that
.                                                                70
 1    we are dealing with they view it as the major issue -- how
 2    to assure the public that there is accountability and
 3    responsibility for the safe transport of these things, but
 4    the public is definitely struggling with who is accountable.
 5    We don't need to dwell on that anymore --
 6              MR. BOYLE:  It is a hard point, and I think a lot
 7    comes down --
 8              DR. GARRICK:  And I don't think you get there by
 9    just listing these kinds of things.
10              MR. BOYLE:  Correct.  I think a lot does come down
11    more to the shipper than it does to the regulator to explain
12    that role because our standards are always seen as the
13    minimum, which are certainly far exceeded in many cases and
14    if you would look at the larger campaigns, be it a pharmacy
15    or anything else, a lot of it is your perceived risk is.
16    Somebody gets their pharmaceuticals, the tend to think that
17    those are less risk and the shipments proceed without much
18    thought.
19              You get to larger reactor components, which is one
20    of the things we are working on is their going to waste
21    repositories.  You raise a little more concern, and we had
22    seen the utilities holding a lot more public outreach than
23    they had in the past, and if you would look at some of the
24    larger DOE shipments now, the work that they do to explain
25    to everybody along the route and to train more people.  It
.                                                                71
 1    has fallen more as the shipper responsibility to -- I don't
 2    have the right words for that.
 3              MR. LEVENSON:  Just to follow up on that for one
 4    minute, from what you have said the shipper
 5    responsibility -- I'll put some words in your mouth maybe --
 6    would you say that any responsibility not on this list for
 7    potential shipments to Yucca Mountain would therefore all be
 8    DOE's responsibility?
 9              MR. BOYLE:  No, I wouldn't say that that is an all
10    inclusive list.  I would have to throw the book at you and
11    say here is the all-inclusive list and follow this, and it
12    certainly would be more requirements and much more detailed
13    requirements than five or six bullets on a page.
14              MR. LEVENSON:  But you have defined the things you
15    are trying to cope with, which is to sort out -- I mean if
16    we can't sort out who is responsible --
17              MR. BOYLE:  Right.
18              MR. LEVENSON:  -- how can the public sort out who
19    is responsible?
20              MR. BOYLE:  These would be the basic -- that is
21    the starting point.  I am sure if we went around the room
22    and brainstormed we may come up with three or four more
23    bullets for each chart, but each bullet may refer to a whole
24    section of the regulations and our book is tabbed so you can
25    see the whole -- the table of what properties we are looking
.                                                                72
 1    at as well as all the shipping papers and everything else,
 2    so there's whole sections of regulation on each portion,
 3    each bullet that is shown.
 4              MR. LEVENSON:  But that is --
 5              MR. BOYLE:  That is a basic and as I said it is
 6    rather dated but it is the only one we have is in the 1979
 7    Federal Register copy that said this is what the MOU between
 8    the two agencies is.  I think it would be helpful if
 9    you're -- I didn't realize that is what you were looking
10    for.  I just coincidentally brought it along with me to look
11    at who is responsible for what.
12              You are ahead of me.
13              MR. LEWIS:  Thank you.
14              MR. BOYLE:  The Modal responsibilities throw one
15    more little quirk of who is responsible for what routing.  I
16    think the only routing we can really be concerned with as
17    far as who is responsible for it within DOT is the highway
18    routing.
19              Certainly, the rail routings, those are private
20    railroads and the Department cannot come in and tell them,
21    you may not use this.
22              The highway routing is primarily uses the
23    interstate highways system, beltways wherever possible.  If
24    you vary from that, you justify it, get it approved by the
25    states, and use highways as much as possible.
.                                                                73
 1              The inspection and enforcement role, we do leave
 2    it to the -- it's a combination at the Department that we
 3    have enforcement in the Research and Special Programs
 4    Administration to look at the packaging efforts.
 5              But once it is, if you will, on the road, or
 6    carrier, the conveyance, that would be the responsibility of
 7    the modes.  We certainly inspect the locomotives, as we
 8    said, or the train or the rail cars.  That's the federal
 9    highway and we don't inspect the track bed; that's the --
10    those were both the federal rail -- highway, we don't check
11    the roads and bridges.  That would be the Federal Highway.
12              We don't inspect the trucks; that would be motor
13    carriers safety, so those types of responsibilities are at
14    the modes where the packages themselves, we would inspect
15    them up to the Type A, and once you exceed the Type A, as
16    the previous presentation said, the NRC would look at those.
17              I believe, for NRC licensees, they'd also look at
18    their Type A and below standards as well, as they have the
19    right to enforce Title 49, so upon their licensees, they
20    would.
21              Then, finally, there are additional operator
22    training requirements.  I'm sure everyone is familiar with
23    commercial drivers licenses.  And you'd have a hazardous
24    materials stamp to show you'd been trained for commercial
25    vehicles as well as for hazardous materials.  That would be
.                                                                74
 1    what we're talking about there.
 2              MR. LEVENSON:  Excuse me, before you leave that
 3    slide, routing, what's the interface or what is the role
 4    between DOT and the states in the area of routing?  My
 5    understanding is that the states have a rather major role in
 6    that for highways.
 7              MR. BOYLE:  I'm not from Federal Highways, so I
 8    can't really speak too much to the exact role and who can
 9    preempt whom.  My understanding is that Federal Highway's
10    position is that you're to use interstate highways, and the
11    states are to designate the approved routes that they have.
12              Certainly, you're going to have to work between
13    the states, because if one state says I want to use this
14    highway and it's much farther north than the other state
15    wants to, you're going to have to work out how you go state
16    to state.
17              You know, you have to select the state -- the
18    major interstates and what your alternates are.  But I don't
19    believe that the Department of Transportation dictates that
20    it has to be one or the other.  I'll say they offer an
21    opportunity to mediate such disputes, but I think you're
22    correct that it's between the states to determine what the
23    route, state-to-state, is, as well as Indian tribes as well.
24              MR. LEVENSON:  Among the states, there are over
25    500 laws that have some effect on routing.
.                                                                75
 1              MR. BOYLE:  And probably more since the time that
 2    article was written there.  There will be even more; they
 3    just keep growing.
 4              Just some of the current activities, as I said,
 5    and you saw a previous slide on it:  We have a large program
 6    for the adoption of the current IAEA regulations which were
 7    issued at the very end of 1996, and are to go into effect at
 8    the end of this year.
 9              They will go into effect, if you're transporting
10    by air, if you're transporting internationally, or if you're
11    transporting by water.  Your surface mode, which is
12    primarily the U.S. and Canada, both the two countries are
13    delayed in implementing them, so we'll stick with our Title
14    49, your Title 10, the Canadian regulations, or the older
15    versions of what they call Safety Series 6 instead of ST-1.
16              The revision of the IAEA regulations, as we said,
17    the 2003 revision kicks off in September of this year. 
18    We're in the process now of taking the comments that we've
19    received on ST-1.  We're not doing the -- we're doing an
20    old-fashioned rulemaking, if you will.
21              We went out for an Advance Notice of Proposed
22    Rulemaking which closes in June of this year.  We're taking
23    those comments and trying to, wherever we can, change the
24    regulations to address those comments.
25              We also went out last week with a call for papers
.                                                                76
 1    or change proposals, if you will, so we'll wrap that effort
 2    up by mid-May for a September kickoff to the entire process,
 3    which should lead to a new white book, Safety Series 6. 
 4    Actually, they have a whole other number that's coming out
 5    for the 2003, and that will come out then.
 6              Current events, in quotes:  I think you're all
 7    familiar with all the legislation that's been going on,
 8    Senate votes and the like.  We have a very small office, and
 9    very few people know about radioactive material in that
10    office, so we get to do a lot of the question and answer for
11    all those programs.
12              So I guess I could have said that's Congressional,
13    but if it's states or anything else, we do all the current
14    event answers, questions, and everything else.
15              Program coordination and outreach:  We've had a
16    series of public meetings, as I said, quarterly, just to
17    explain the regulations.  We've been participating at the
18    NRC's studies when they have their public meetings.  We try
19    to do public meetings around whenever we go overseas and
20    give regulatory reviews or changes to that.  Those try to go
21    out, as well as just as you have here, if you will, an open
22    door policy where applicants and industry can come in, as
23    well as the public can come in.
24              If I can skip down to package case work, we're
25    seeing more of that in what we're calling our special cases. 
.                                                                77
 1    We're seeing large reactor components, primarily steam
 2    generators that are being shipped to Barnwell.
 3              The public is much more interested in that than
 4    our previous efforts, so we're seeing more outreach and more
 5    interest in those, and running those special cases.
 6              But our other case work is the international
 7    revalidations as the competent authority, which is
 8    Import/Export, and we see quite a bit of those.
 9              Our case work -- we don't do the Type A and below
10    packages as the NRC does.  those are done on an enforcement
11    case basis.  Since they are self-certified, we would go out
12    and verify your records and your QA and your documentation,
13    so that work is also done at the Department.
14              Again, that's all I had as an overview, and kind
15    of decide who's responsible for what, but I am free to
16    answer any questions.  If you'd like me to come back in a
17    couple months when you have another meeting, with more
18    detailed information, I'd be happy to do that.
19              Again, I just appreciate the opportunity for being
20    invited to come out and talk to you.
21              MR. LEVENSON:  John, do you have any questions?
22              DR. GARRICK:  No, I don't think so; thank you.
23              MR. LEVENSON:  George?
24              [No response.]
25              MR. LEVENSON:  Ray?
.                                                                78
 1              MR. WYMER:  It's too much for me.
 2              MR. LEVENSON:  I have one more:  I don't like to
 3    repeat rumors I've heard, but for the casks that come from
 4    overseas, the accusation has been made that it's okay that
 5    spent fuel can be shipped from anywhere in the world to one
 6    of the U.S. sites, but that same cask cannot be used to ship
 7    it from one U.S. site to another, the same fuel; is that
 8    true?
 9              MR. BOYLE:  I don't believe so.  If I can review
10    the two types of casks, if the NRC, if it's a domestic
11    design, the NRC is going to approve it.
12              MR. LEVENSON:  If it's a domestic -- no, it's a
13    foreign design.
14              MR. BOYLE:  A foreign design is going to come into
15    my office first.
16              MR. LEVENSON:  Right.
17              MR. BOYLE:  And we're going to get the same --
18    well, we're going to ask for the safety analysis report, and
19    it's certainly going to be in a different format than the
20    NRC is used to seeing, since they don't have to follow
21    internationally -- doesn't have to follow the NRC
22    guidelines.
23              MR. LEVENSON:  I understand that.
24              MR. BOYLE:  But if you get a safety analysis
25    report, it's going to be sent to the NRC for their review
.                                                                79
 1    and recommendation.  Once we receive that, we're going to
 2    approve it for use into, out of, or through this country.
 3              So as far as the package being approved for it, I
 4    believe that that's true.
 5              MR. LEVENSON:  But into or out of or through does
 6    not cover from one place in this country to another place in
 7    this country.
 8              MR. BOYLE:  I'm not familiar, and this is not my
 9    specialty, to get export licenses as, can you export?
10              MR. LEVENSON:  If I have an export license, if it
11    comes from overseas to Idaho, for instance, and subsequently
12    the same cask cannot be used, I have been told, to ship it
13    from Idaho to Savannah River.
14              MR. BOYLE:  That's correct, that you get an
15    import/export, if you will, permit, and that does not allow
16    you to use it domestically, and that comes from -- I have my
17    own opinions.  Probably the NRC could better explain.  When
18    they give us a review and recommendation, that is not
19    equivalent to getting a full transport certificate, and they
20    could explain the differences between the two reviews and
21    what they're really doing.
22              I know I can't license domestic use.
23              MR. LEVENSON:  For somebody in the public, it's
24    hard to explain that it's safe to ship this cask halfway
25    around the world, halfway across the U.S., but it's not safe
.                                                                80
 1    to ship it the other half way.
 2              MR. BOYLE:  I think that that's an unfair
 3    characterization to say it's unsafe.  I think the truth of
 4    the matter is that nobody has asked to do it domestically;
 5    that in my opinion, the casks you're talking about, there is
 6    no reason that the couldn't be used from Idaho to Savannah
 7    River, except nobody has asked, nobody has come in and made
 8    the application to the NRC and gone through the -- if I can,
 9    and I know I'm outnumbered here -- the expensive review. 
10    You do have to pay for --
11              MR. LEVENSON:  I think you just answered the
12    question as to why it requires a completely new set of
13    reviews and licensing; it economically isn't worth it. 
14    Okay.
15              Any other questions?
16              MR. BOYLE:  I just have one.  Who should I turn
17    the paperwork over to?  They can do with it what they will. 
18    Thank you for your time.
19              MR. LEVENSON:  Thank you.  Do we have a
20    representative from EDLOW?
21              MS. OWENS:  Yes, I'm here.
22              MR. LEVENSON:  Are you Janice Owens?
23              MS. OWENS:  Yes, I am.
24              MR. LEVENSON:  Good.  The floor is yours.
25              MS. OWENS:  Hello, my name is Janice Owens, and
.                                                                81
 1    I'm with EDLOW International Company, and with me is Keith
 2    Brown.  He is a former DOE contractor, and he's now working
 3    with EDLOW on our foreign research reactor spent fuel
 4    shipments into the United States.
 5              I would like to begin my remarks by asking a few
 6    questions to emphasize what I believe are some of the key
 7    issues.
 8              First, did you know that according to IAEA data,
 9    that on an international basis, over the last 25 years, more
10    than 88,000 tons of commercial reactor spent fuel has been
11    shipped either by sea, road, rail, away from the reactors
12    where it was generated?
13              Do you realize that some form of spent fuel is
14    being transported on a routine basis in the United States?
15              While the general public has been led to believe
16    otherwise, that spent fuel is rarely moved, this simply is
17    not the case.  I believe that it's important to recognize
18    that the world is already engaged in a substantial amount of
19    spent fuel transportation, and there is quite a bit of
20    international cooperation to make this possible.
21              So what's the big deal about shipping spent fuel? 
22    The big deal is that it's being done all the time and very
23    safely.
24              I'd like to tell you a little bit about my company
25    and our views on shipping spent fuel, if you haven't gotten
.                                                                82
 1    an idea of where I'm going.  Then I will provide you with
 2    the description of some of the key planning considerations
 3    in arranging a spent fuel shipment.
 4              And I will finish by briefly describing the
 5    international regulatory framework, although I think you've
 6    had a very good presentation on that framework already.
 7              EDLOW International Company's primary business
 8    expertise is arranging for all types of international
 9    nuclear materials shipments, not just spent fuel.
10              Our business is very interesting and unique, and
11    we interact regularly with people all over the world in all
12    facets of the nuclear fuel cycle.
13              We have offices in Washington and Australia, the
14    United Kingdom, and in Russia.
15              Sam Edlow, the founder of our company, was an
16    early pioneer in spent fuel transport.  He built the first
17    spent fuel cask and arranged for the first shipment of
18    research reactor spent fuel back to the United States in
19    1963.
20              My message is simple:  We have the ability in the
21    United States right now to make arrangements and begin
22    moving commercial spent fuel.  As Keith and my colleagues in
23    Washington can tell you, we are currently arranging for
24    foreign research reactor shipments to the United States on
25    the order of three to four campaigns a year, serving up to
.                                                                83
 1    as many as 12 reactors.
 2              So I ask you, what is the problem about shipping
 3    spent fuel?  Is it the lack of a stable, effective,
 4    international regulatory framework?  Is it the lack of
 5    cooperation among international organizations to coordinate
 6    and establish standards for public protection?
 7              Is it the lack of a stable, effective domestic
 8    national regulatory framework?  Is it the design and
 9    licensing of transport casks?  Is it the performance of the
10    cask in accident conditions?
11              Is it threats of sabotage and terrorism?  What is
12    it, exactly?
13              Well, if you ask me, I'd say the problem is, we're
14    not transporting enough of our commercial spent fuel in the
15    United States.  Experience has shown that the technical
16    issues associated with spent fuel transport are not the
17    problem; the technical issues are not causing the delays and
18    the consolidation of spent fuel at fewer sites.
19              The safety record for 40 years of spent fuel
20    transport is nothing short of exemplary.  I have every
21    reason to believe that this record can and will be
22    maintained and strengthened in the future.
23              So what is the big deal?  I think it's fair to say
24    that, based on our experience to date, the political and
25    public acceptance issues are truly the most difficult issues
.                                                                84
 1    to deal with.
 2              As we all know, in the United States and in other
 3    countries, there is widespread concern about the safety of
 4    spent fuel shipments, and the possibility of a severe
 5    accident.
 6              Some knowledgeable parties seem to imply that it
 7    will only be acceptable to begin shipping spent fuel when
 8    the repository is licensed for operation in the United
 9    States.
10              Other use the term, "mobile chernobyl" when
11    talking about spent fuel shipments to evoke images of great
12    disaster comparable to an atomic bomb explosion.
13              So, in the United States and in other countries as
14    well, sensationalism is a fact of life, and any mistake is
15    going to become a media event.
16              Are people wrong to be concerned about spent fuel
17    shipments?  No, certainly not.  Concern and scrutiny are
18    constructive parts of the oversight process, and
19    particularly if such activities serve to enhance the safety
20    of these shipments.
21              It would be helpful, of course, for more people to
22    understand how rigorous the protective measures are.  The
23    stellar safety record of the nuclear transport industry is
24    not just a fluke; it's a product of a well-established
25    regulatory regime that has served the public for more than
.                                                                85
 1    40 years.
 2              I must admit, if you've not guessed it by now,
 3    that I'm one of those who favor moving spent fuel to a
 4    centralized interim storage facility prior to disposal. 
 5    Without it, instead of reducing the number of sites where
 6    spent fuel is stored, we're looking at having somewhere
 7    close to 75 interim storage facilities throughout the United
 8    States.
 9              As has been explained earlier today, we have 15
10    independent spent fuel storage installations, ISFSIs,
11    operating in 13 different states in the United States.
12              Twenty additional ISFSIs are planned in 14
13    additional states.
14              Now, in terms of planning spent fuel shipments,
15    all of the key parameters must be identified and considered. 
16    Of course, the most important question to address is where
17    is the spent fuel going?
18              Answering this question in the United States has
19    been the big challenge.  It means addressing the daunting
20    series of public and political acceptance hurdles.
21              In my experience with foreign research reactor
22    spent fuel, once the environmental review process is
23    completed and the court challenges are resolved, we have
24    found that everything tends to fall into place very rapidly
25    thereafter.
.                                                                86
 1              So once the political will is mustered to decide
 2    to ship spent fuel, I believe it is bound to proceed.
 3              In the preparation and planning phase, the
 4    questions that one asks oneself are, is the shipment part of
 5    a larger campaign, or will it be a one-time unique
 6    arrangement?  We've had experience with both arrangements.
 7              How much spent fuel is to be transported?  Is it
 8    too much for one shipment; that is, one physical shipment,
 9    or will it involve several shipments?
10              What modes of transport are necessary and can be
11    utilized, given the location and the ultimate destination of
12    the spent fuel?
13              Typically, a shipment of the foreign research
14    reactors' spent fuel will involve all modes of transport: 
15    Sea, road, rail, and we've even done some shipments by air.
16              What is the total radioactivity level of the
17    material?  What is the condition of the fuel?  Is it
18    damaged?  Is it in a pool?
19              Most likely, our experience has been that, yes, it
20    is coming from a pool, but more and more in the future, I
21    suspect we'll be looking at dry storage.
22              What is the schedule that needs to be met?  When
23    must the spent fuel be picked up at the reactor and when
24    must it arrive at its destination?
25              Are there weather considerations or other major
.                                                                87
 1    contingencies or factors to consider in selecting the
 2    routes, equipment, and shipping mode?
 3              What are the liability insurance needs, and how is
 4    responsibility shared among the parties involved in the
 5    shipment?
 6              What kind of transport casks are needed?  Are they
 7    available?  Are they approved by all of the various
 8    regulatory authorities involved in an international
 9    shipment?
10              Are they single-purpose or dual-purpose?  If
11    they're single-purpose transport casks, which we routinely
12    use, arrangements have to be made for their return.
13              What is the weight of the cask, and how much spent
14    fuel does it carry?  With respect to weight, does the
15    reactor have the crane capacity to lift it?  Does it meet
16    heavy-haul rail and road restrictions or are special
17    arrangements necessary?
18              What are the emergency response plans for each leg
19    of the shipment?
20              What are the physical security requirements?  Is
21    an escort required?  Is the communications tracking system
22    in place?  Is it acceptable?  What notifications must be
23    made prior to the shipment?  To whom?  When?  And how?
24              Answering all of the questions involves the
25    preparation of a transportation plan.  This is an iterative
.                                                                88
 1    process requiring extensive interaction among all the
 2    parties involved, the owner of the spent fuel, the shipper,
 3    the regulatory authorities in all of the countries through
 4    which the spent fuel will be shipped, and the recipient of
 5    the spent fuel.
 6              The transport plan is likely to be changed several
 7    times.  Importantly, however, I think it's very clear that
 8    the regulatory framework for international spent fuel
 9    shipments has evolved over many years and continues to
10    evolve in a generally constructive manner to meet new
11    challenges or address unforeseen issues.
12              Numerous spent fuel shipments have been made and
13    are still being made all over the world.  Although there
14    have been some transport accidents, none has resulted in a
15    serious radioactive release.
16              Nevertheless, there will continue to be intense
17    public scrutiny of all spent fuel shipments.  As others have
18    indicated, the IAEA regulations for the safe transport of
19    radioactive material has served as the basic guidelines to
20    promote safe transport of spent fuel worldwide.
21              These regulations establish the fundamental
22    standards for the safety of the industry.  The regulations
23    are not legally binding, but may be adopted by IAEA member
24    states for use in their national regulations with respect to
25    their own activities.
.                                                                89
 1              Because the regulations have been widely adopted
 2    all over the world and applied, a very high level of safety
 3    has ensued.
 4              The IAEA has also long been involved in the
 5    development of non-binding international standards for
 6    physical protection.  The first publication, entitled
 7    Recommendations for the Physical Protection of Nuclear
 8    Materials, was issued in 1972.  It has been periodically
 9    revised and updated since then, with the fourth and latest
10    version conducted in 1988 and published in 1999.
11              There is, of course, also an International
12    Physical Security Convention governing nuclear materials in
13    international transport.  It's up to each nation to decide
14    how physical protection requirements are fulfilled, however,
15    there is a dynamic international dialogue underway in this
16    area of physical protection, and many in the U.S., in
17    particular, believe further initiatives are needed to get
18    all nations to upgrade their physical protection standards.
19              For international organizations the International
20    Maritime Organization incorporate the IAEA regulatory
21    standards.  For sea shipments, for example, the IMO adopts
22    in whole the IAEA safety series.  It also sets forth its own
23    requirements for establishing three classes or categories of
24    ships for transporting spent fuel.  The ships must meet to
25    varying degrees certain requirements for stability in the
.                                                                90
 1    event of damage -- fire protection, temperature control of
 2    cargo spaces, structural considerations, cargo securing
 3    arrangements, electrical supplies, radiological protection
 4    of equipment, management training, shipboard emergency plans
 5    and notification in the event of an incident involving the
 6    nuclear materials.
 7              I hope the message is clear that shipping spent
 8    fuel requires advance planning and application of the
 9    rigorous protection standards.
10              The international and national regulatory
11    frameworks have required the industry to meet very strict
12    safety standards and they have been very effective in
13    promoting public health and safety.  In summary, from a
14    so-called technical perspective my colleagues and I continue
15    to have high confidence that the nuclear industry can move
16    spent fuel, high level waste and any sensitive nuclear
17    materials globally without adverse effects on the public
18    safety or environment.
19              If there is a clear political will, a mandate, to
20    move the materials and continue adherence to the strict
21    regulatory standards and criteria including those of
22    physical security, then the industry will be ready, able,
23    and willing to respond and to meet the challenges.
24              While I am optimistic about our industry's ability
25    to ship spent fuel, that does not mean there aren't
.                                                                91
 1    challenges that need to be overcome.
 2              First, the location of the centralized interim
 3    storage facility must be established.  The public must be
 4    convinced that the shipments will be conducted safely.  In
 5    the U.S. we have quite a bit of work to do on transportation
 6    planning and preparation.  I am optimistic that the studies
 7    that are now underway by the NRC that we have heard about
 8    today will help resolve some of the outstanding questions
 9    and will get the process moving.
10              I think the pressures are increasing to establish
11    centralized interim storage.  I don't think that pressure is
12    going to diminish, and I think the planning will have to
13    begin soon to engage in any major transportation campaign in
14    the United States.
15              I would be happy to answer any questions and Keith
16    here can help with specific questions on our foreign
17    research reactor spent fuel shipment.
18              MR. LEVENSON:  Okay, thank you.  You have
19    identified a large range of topics and a large range of
20    things that have to be done.  Our previous speakers
21    identified that certain things were the responsibility of
22    the shipper.  Could you briefly summarize from that big list
23    of things that have to be done that you covered what you
24    consider the primary responsibility of the shipper?
25              MS. OWENS:  The primary responsibility of the
.                                                                92
 1    shipper is to develop the transportation plan -- that is,
 2    according to the regulations that have been promulgated by
 3    all of the agencies.  There are guidelines on what types of
 4    equipment can be used, how the equipment can be used, and
 5    there are regulations that govern the selections of the
 6    routes that can be used.
 7              This, too, is an iterative process and it requires
 8    a great deal of interaction with the states and we have been
 9    involved in the planning of our shipments.  It has taken
10    quite an effort to interact with the states and to agree on
11    the acceptable routes.
12              MR. LEVENSON:  You are implying that your
13    responsibility is basically limited to conforming to
14    regulations?  Identify yourself.
15              MR. BOYLE:  Thank you.  I am Rick Boyle with the
16    Department of Transportation.
17              The first thing I think I want to comment, EDLOW
18    is not the shipper of research reactor fuel, nor would they
19    be the shipper of any high level waste that were to go to
20    any repository.  They are an agent or a broker that would
21    work between the owner, in this case the Department of
22    Energy and research reactor, owns the fuel and is the
23    shipper.  They contract out to various companies to arrange
24    the transport or broker the transport so in this case EDLOW
25    is neither the shipper or the carrier or the receiver of the
.                                                                93
 1    material, so the question you are getting at -- what is the
 2    shipper's responsibility -- would be better addressed to the
 3    Department of Energy.
 4              MR. LEVENSON:  Okay, thank you.
 5              DR. GARRICK:  That sort of brings us to a question
 6    that Janice asked at the opening, having to do with who is
 7    in charge here.  I think that my observation of the anxiety
 8    of the public about transportation is a very simple one. 
 9    That is, they are frustrated by not getting a clean answer
10    on who is accountable -- single point accountability is what
11    they are looking for and they don't get it.
12              They get multiple agency responsibility.  They get
13    carrier responsibilities and lists of items and things as we
14    have seen here this afternoon, but they don't get the
15    satisfaction evidently that they are looking for as to who
16    is in charge.  Of course, if you look at specific cases like
17    the shipment of transuranic waste to the WIPP facility, the
18    states play a critical role in there, so there is another
19    player, so if you ask me what the problem is, the problem is
20    one of resolution of accountability.
21              In a time when we are preaching the gospel of
22    taking a total systems approach and a total integrated risk
23    assessment, being able to pinpoint responsibility and
24    accountability is extremely important to that, and I think
25    that is what is causing a great deal of frustration among
.                                                                94
 1    the citizenry, and speaking of citizenry, we have Amy
 2    Shollenberger, who wants to make a comment, and I will ask
 3    her to introduce herself and her affiliation, but I would
 4    like to give her a chance while we are in the middle of this
 5    discussion to make her comment.
 6              MS. SHOLLENBERGER:  First of all, thank you,
 7    Chairman, for the opportunity to speak.  My name is Amy
 8    Shollenberger and I am a Senior Policy Analyst with Public
 9    Citizen's Critical Mass Energy Project.  Public Citizen is a
10    consumer and Government watchdog organization founded in
11    1971 by Ralph Nader, who I am sure you have all heard of.
12              The Critical Mass Energy Project deals
13    particularly with energy issues and we follow this issue, I
14    follow this issue particularly of Yucca Mountain high level
15    waste nuclear waste transportation.
16              I just have a few comments, most of them geared
17    specifically to the most recent discussion happening but a
18    few that will go back to this morning's session as well,
19    which was not on the record.
20              First of all, I find it ironic just seeing who you
21    have invited to speak at your meeting to you to give you the
22    information that you are looking for.  I am always
23    encouraged by Chairman Garrick's attempts to bring in the
24    public's concerns to your meetings and I am continually
25    grateful that he tries to keep that in the forefront and the
.                                                                95
 1    focus of your discussions.  However, I have noticed that at
 2    lease in all the meetings that I have attended you have
 3    never actually asked a member of the public to come in and
 4    speak to you the way you ask EDLOW Incorporator or the
 5    Department of Transportation of the Department of Energy to
 6    speak to you and to raise the concerns and the questions
 7    that happen.
 8              Now I am aware that you do have workshops and
 9    roundtables.  I have participated in those, as has EDLOW and
10    the Department of Transportation and Department of Energy. 
11    However, I think that if you really want to get a clear
12    picture it might be good to bring that discussion into a
13    more formal place, into your meetings, so that is just the
14    first thing that I would like to say.
15              Related to that is it is interesting to me to have
16    a company like EDLOW come in to give you the information
17    about how safe nuclear waste transportation is.  I feel that
18    there's somewhat of a conflict of interests there, because
19    of course as the Department of Transportation pointed out,
20    they are not the shipper of waste.  The Department of Energy
21    is the shipper of Waste, and they will own the waste that is
22    being shipped, but it says in the Nuclear Waste Policy Act
23    that the waste will actually be transported by a private
24    company which will bid on it, and of course the more
25    opportunity that EDLOW has to assure you that their waste
.                                                                96
 1    shipping is safe and all of the associated public relations
 2    that goes with that, the more likely it is that they may get
 3    the contract or that the waste will be shipped in the first
 4    place, so I would just like to point that out, that that is
 5    definitely something that the public is concerned about.
 6              Also I would like to comment on something that Ms.
 7    Owens said earlier about all of the shipping campaigns that
 8    have happened in the past and I would encourage you to ask
 9    the question of what is the average distance of any one of
10    those transports.  The records that I have looked at that
11    list out all of the nuclear waste transportation shipments
12    often include shipping waste from a spent fuel pool to a dry
13    cask storage area, which could be 100 yards, okay?  -- so
14    you can say you shipped 200,000 shipments but if they are
15    all at 100 yards, when you look at that on a bigger
16    perspective of shipping waste from Maine to Nevada it is a
17    much different story.
18              I have seen pictures of the Calvert Cliffs
19    shipments going from the spent fuel pools to the dry cask
20    storage area where they have armed guards all around the
21    trucks and they are walking really slowly and the roads are
22    all closed off, and that is a lot different than shipping
23    waste along Route 80, so I would just like to encourage you
24    to keep that question in the front of your mind as well.
25              Also, I would like to go to the question of
.                                                                97
 1    accountability.  Again I really appreciate Chairman
 2    Garrick's insistence on bringing that up because that is a
 3    big concern of the public and it is true that we do want
 4    single point accountability, and what is interesting is I
 5    don't know if you all had a chance to watch the debates when
 6    S. 1287 was being voted on in both the Senate and the House
 7    recently but Mr. Markey from Massachusetts gave some
 8    interesting comments about liability and what is interesting
 9    to me is that -- the truth is that the taxpayer is really
10    the one that is accountable for the shipment because in fact
11    the Department of Energy will own the waste.  It will be the
12    shipper.  It will be liable for any accident.  The
13    Department of Energy is funded by taxes, so again an
14    accident happens in a community, who is liable for cleaning
15    it up?  The Department of Energy.  Who pays for the
16    Department of Energy's ability to clean up the accident? 
17    The taxpayer.  So it is a double burden to whoever is
18    affected by any kind of an accident.
19              The shippers are not liable and Mr. Markey pointed
20    that out pretty eloquently and I would encourage all of you
21    to look at the Congressional Record for his statements.
22              Also, related to that is -- I asked this earlier
23    in the day, but I would like to say it on the record as
24    well.  I am interested in how the "take title" provisions
25    would be -- would affect liability, and I know that at the
.                                                                98
 1    last minute when S. 1287 was getting voted on in the Senate
 2    they took the "take title" provisions as far as taking title
 3    to the waste onsite, so currently even if S. 1287 is signed
 4    into law by the President, DOE will not be allowed to take
 5    title to the waste onsite.  It will only be able to take
 6    title to the waste when it will be shipped.
 7              However, there is a strong push for that, both by
 8    the Administration and by several members of Congress, and
 9    it seems like it would be an important question to ask --
10    what happens when DOE owns the waste as opposed to the
11    licensees.
12              Also, as far as shipping is concerned, I think the
13    question that Mr. Levenson brought up about the preemption
14    of state laws and who sets the routes is a very important
15    question, and I think it is one that was not adequately
16    answered nor I am not sure that it ever will be adequately
17    answered in the public's viewpoint.
18              Anytime I have ever been in a meeting where it has
19    been asked, well, who is responsible for saying which routes
20    will be chosen and who is responsible for making sure that
21    the routes that are chosen are safe, there is a big circle
22    that goes between DOT and NRC and DOE and it is never quite
23    clear to the public who is responsible for that.
24              Several states have put in alternate shipping
25    plans that can be approved by DOT.  However, it seems to me
.                                                                99
 1    that there is a pre-emption of DOT regulations over state
 2    plans and so if the DOT does not approve the state plan,
 3    then the state plan does not go into effect, and I think it
 4    is really important to make it clear to the public who gets
 5    to pick the routes and why they are picked and what the
 6    implications of which routes are picked are.
 7              Just one more point I would like to make -- oh,
 8    two more points, excuse me.  As far as interim storage goes,
 9    I would just like to point out that it is not only the
10    public that is against interim storage.  The Administration
11    is opposed to interim storage as well, and so I don't really
12    think it is fair to characterize that as only, you know,
13    crazy people out in the public opposed to interim storage. 
14    The truth is that the Administration has taken a strong
15    stance against interim storage including Secretary
16    Richardson and others in the Administration, and it is
17    really important to recognize that it is not a bunch of
18    crazy people opposed to that.
19              That interim storage provision was taken out of S.
20    1287 because the President showed that he was opposed to it
21    and when Mr. Murkowski was trying to make the bill palatable
22    to the President they removed interim storage and they put
23    in a provision called "Backup Storage" which only allows
24    temporary storage at the site after a license is granted by
25    NRC.
.                                                               100
 1              Finally, I would just like to make one final
 2    point.  That goes back to the Modal Study question that you
 3    were discussing earlier.  I participated in the roundtable. 
 4    I believe that Mr. Boyle was there as well, and Mr. Edlow
 5    himself was in the meeting as well, on the performance
 6    package scoping study, and at that time, if I understood it
 7    correctly, it was explained that those tests that were
 8    conducted in the 1970s were actually not used as the basis
 9    for modeling in the 1987 Modal Study and that is one of the
10    reasons that they are re-looking at the package performance
11    study -- if I understand it correctly.  In fact, Lawrence
12    Livermore did the 1987 study, not Sandia, so it was two
13    different groups that did the two different studies.
14              Sandia at the meeting said that they definitely
15    wanted to look at whether tests should be the basis of the
16    analysis for the new studies, so I just wanted to also point
17    that out, that it is not necessarily true that the tests
18    were used in the modelling for the 1987 study.
19              Thank you.
20              DR. GARRICK:  Thanks, Amy.
21              MS. OWENS:  Could I respond?  On one of the
22    questions or one of the points that you raised, Amy, the
23    amount of miles -- I don't have the data with me here right
24    now, but it is on the order of hundreds of millions of
25    miles.  There have been several shipments from Japan all the
.                                                               101
 1    way to Europe, spent fuel shipments, so it is not trivial. 
 2    It is not a trivial amount of miles.
 3              With respect to interim storage, I would like to
 4    point out that we already have more than 75 interim storage
 5    sites in the United States and even though the
 6    Administration may oppose it, I believe that it makes sense
 7    to begin slowly, to move spent fuel into centralize it in a
 8    single -- at fewer locations than where it is located now.
 9              MS. SHOLLENBERGER:  Were the shipments from Japan
10    to Europe by truck or rail or by boat or plane?
11              MS. OWENS:  A combination.
12              MS. SHOLLENBERGER:  That is my point.
13              MS. OWENS:  Yes --
14              DR. GARRICK:  If you are going to talk, you have
15    to use the microphone.
16              Any comments from the committee members?  Let me
17    just turn it back to you, Milt, to wrap up?
18              MR. LEVENSON:  Do you have any comments, John?
19              [Laughter.]
20              DR. GARRICK:  Lots of them.  The only overriding
21    comment that I have is that speaking of the taxpayers, the
22    taxpayers are paying a terrible price for decisions that are
23    being made in the name of the high risk of transportation,
24    not only in the shipment of nuclear materials but in the
25    shipment of all kinds of hazardous materials.
.                                                               102
 1              As I have said before, maybe the classic example
 2    of the response to the fear of transporting hazardous
 3    materials is in connection with the Army's Chemical
 4    Demilitarization Program, where rather than utilizing
 5    centralized disposal facilities for destroying the chemical
 6    weapons, the decision was made on the basis of a very
 7    shallow risk assessment that is full of holes to, rather
 8    than centralize the destruction of these weapons, to build a
 9    $500 million to billion plant at each of the storage
10    locations in the United States, and again, who is paying for
11    this?  The taxpayer.  It was a decision that was made on the
12    basis of very limited information.
13              I see that whole attitude being repeated with
14    respect to transportation in the disposal of or the
15    destruction of hazardous materials over and over again, and
16    yet on the other hand we keep hearing and we keep being told
17    that the risk of such transportation is extremely small, so
18    something doesn't hang together, and here we are with the
19    nuclear, about to perhaps make the same stupid mistake, and
20    again who is stupid here?  The taxpayer will have to be
21    accused of being so because they are tolerating it.
22              I think that we need to really be careful about
23    what we do in the name of safety and risk assessment, and
24    have to be on our toes to make sure that that information is
25    indeed getting in the right place and that the decisions
.                                                               103
 1    that are being made have the benefit of such information.
 2              I don't think that is happening very effectively
 3    and that is why it concerns me when I hear presentation
 4    after presentation about transportation of nuclear materials
 5    and do not see a tying together of all of the supporting
 6    evidence of the risk associated with the transport of
 7    nuclear materials, and so -- any what we have heard here
 8    today just continues in my mind that legacy.
 9              MR. LEVENSON:  George, any comments?
10              DR. HORNBERGER:  No.
11              MR. LEVENSON:  Ray?
12              DR. WYMER:  I just have one sort of small
13    observation.  I am certain that it is true that there's been
14    many, many miles of transportation of high level waste of
15    various kinds around the world, but there is also something
16    I haven't heard much discussion of, which I guess I would
17    refer to as an intensity factor, by which I mean that if you
18    have a central repository then from all parts of the
19    country.  They focus there and as they get near there they
20    tend to all run down the same road, and small though the
21    frequency of accidents may be, the likelihood of them
22    happening at all increases as you focus, as you intensify. 
23    I have not heard much discussion of that, and I don't think
24    that is particularly very important in a real sense.  I
25    think it is in the sense of having accidents.  I think it is
.                                                               104
 1    important for the public perception point that people out
 2    there in Nevada are really concerned about that focusing
 3    effect.  You don't get much discussion about that. Just an
 4    observation.
 5              MR. LEVENSON:  Amy, this is partly in response to
 6    your comment.  I don't know what the data is on
 7    internationally.  NRC two years ago in NUREG-0725 did
 8    publish a survey of fuel shipment and by and large, by a
 9    factor of three or four, the quantity of fuel was shipped at
10    the range of 200 to 400 miles rather than just a few hundred
11    yards and a lot of it is shipments of up to 600 or 700
12    miles.  That is all tabulated there, and I have no idea how
13    this relates to foreign data, but at least in the U.S. it
14    doesn't look like they are mostly short shipments.
15              One other comment.  I will bring your history up
16    to date, because I am not sure -- Sam may have done the
17    first commercial shipping cask, but the first shipments of
18    spent fuel were done in 1944 and they were flown by air from
19    Hanford to Oak Ridge, and while it wasn't high burnup fuel,
20    it was only cooled two days.  I know that because I arranged
21    it, so this shipping of spent fuel including by air goes
22    back quite a ways.
23              Other comments?  I want to thank you.
24              MS. OWENS:  Thank you very much for the
25    opportunity.
.                                                               105
 1              DR. GARRICK:  Thank you.  We are only ten minutes
 2    off our agenda?  That is excellent.  All right, unless
 3    there's further comment or discussion, I think we will take
 4    a break, and I guess for the meeting following we don't need
 5    to have a record -- we don't need to have it on the record,
 6    so we will adjourn.
 7              [Whereupon, at 4:10 p.m., the recorded portion of
 8    the meeting was recessed, to reconven Tuesday, March 28,
 9    2000, at 8:30 a.m..]
10

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