NEA News 2005 - No. 23.1 - Nuclear Energy Agency

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NEA News 2005 - No. 23.1 - Nuclear Energy Agency
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                     NEA News                       2005 – No. 23.1

          In this issue:

          Nuclear regulatory decision
          making
          An analysis of uranium
          exploration and price

          Lessons drawn from recent NPP
          operating experience
          Management of uncertainty in
          safety cases and the role of risk

          Safety of the nuclear fuel cycle
          News briefs

                          N U C L E A R • E N E R G Y • A G E N C Y
NEA News 2005 - No. 23.1 - Nuclear Energy Agency
NEA News                                     2005
                                                                                               No. 23.1

NEA News is published twice yearly in
English and French by the OECD Nuclear
Energy Agency. The opinions expressed
herein are those of the contributors
alone and do not necessarily reflect
                                              Contents
the views of the Organisation or of
its member countries. The material in
NEA News may be freely used provided
the source is acknowledged.
  All correspondence should be
addressed to:                                 Facts and opinions
The Editor, NEA News
OECD Nuclear Energy Agency
12, boulevard des Îles
92130 Issy-les-Moulineaux                     Nuclear regulatory decision making          4
France
Tel.: +33 (0) 1 45 24 10 10
Fax: +33 (0)1 45 24 11 10                     An analysis of uranium exploration
   The OECD Nuclear Energy Agency             and price                                   8
(NEA) is an intergovernmental orga-
nisation established in 1958. Its pri-
mary objective is to assist its member
countries in maintaining and further
developing, through international co-         NEA updates
operation, the scientific, technological
and legal bases required for a safe,
environmentally friendly and econom-          Lessons drawn from recent NPP operating
ical use of nuclear energy for peaceful
purposes. It is a non-partisan, unbi-         experience                                  10
ased source of information, data and
analyses, drawing on one of the best
international networks of technical           Management of uncertainty in safety cases
experts. The NEA has 28 member coun-
tries: Australia, Austria, Belgium,
Canada, the Czech Republic, Denmark,
                                              and the role of risk                        14
Finland, France, Germany, Greece,
Hungary, Iceland, Ireland, Italy, Japan,
Korea, Luxembourg, Mexico, the
                                              Safety of the nuclear fuel cycle            18
Netherlands, Norway, Portugal, the
Slovak Republic, Spain, Sweden,
Switzerland, Turkey, the United
Kingdom and the United States.
The European Commission takes part
in the work of the NEA. A co-operation
                                              News briefs
agreement is in force with the Interna-
tional Atomic Energy Agency.
   For more information about the NEA,
                                              The Generation IV International Forum
see:
              www.nea.fr
                                              enters a new phase                          20
             Editorial board:
              Gail H. Marcus
             Karen Daifuku
                                              Nuclear power for the 21st century          21
           Cynthia Gannon-Picot

         Production/photo research:
            Solange Quarmeau
                                              Projected costs of generating electricity   24
             Annette Meunier
          Design/layout/graphics:
            Annette Meunier                   Third phase of the TDB Project              26
            Andrée Pham Van

Cover page: Yellow cake being filtered
                                              New publications                            27
(P. Lesage, AREVA, France), refined yellow
cake (NEI, United States), fuel rods at the
Eole experimental reactor (P. Stroppa, CEA,
France), pipe failure at Mihama Unit 3
(JNES, Japan), site characterisation for
geological disposal (Posiva Oy, Finland).
NEA News 2005 - No. 23.1 - Nuclear Energy Agency
Ministers take a close look
    at nuclear energy

    Nuclear energy was the focus of considerable attention in this spring’s international
    agenda. At the international conference on Nuclear Power for the 21st Century held
    in Paris in March, 74 countries and 10 international organisations were represented.
    In May, nuclear energy was also debated at the Meeting of the International Energy
    Agency (IEA) Governing Board at Ministerial Level, the OECD Forum on Fuelling the
    Future: Security, Stability, Development, and at the Meeting of the OECD Council at
    Ministerial Level, held back-to-back with the OECD Forum.

       At the Nuclear Power for the 21 st Century conference, opinions about nuclear
    energy were largely, though not exclusively, positive. Many Delegates tended to consider
    that nuclear energy can, under the right conditions, be part of a response to the
    challenge of meeting expanding energy demand, ensuring the security of energy supply,
    while addressing climate change. An overview of the main themes covered during the
    conference is provided in the news brief on page 21.

        In the other meetings, the focus was less on nuclear energy and more on energy issues
    all-around. At the OECD Forum, the general sentiment was that urgent action was
    required in the energy sectors of both developed and developing countries. Ministers
    at the Meeting of the IEA Governing Board at Ministerial Level stressed that energy
    security remained their core mission, and described their vision of energy security as
    greater global availability of reliable, affordable, clean energy. At the Meeting of the
    OECD Council at Ministerial Level, on 3-4 May, Ministers underlined that sufficient
    supply of clean and affordable energy is crucial for economic and social development.
    They further considered that investment in energy technology and infrastructure must

2                                                                        Editorial, NEA News 2005 – No. 23.1
NEA News 2005 - No. 23.1 - Nuclear Energy Agency
be directed towards sustainable, efficient technology with less negative climate impact.
          During a joint meeting held between the Delegates attending the Meeting of the OECD
          Council at Ministerial Level (MCM) and the Meeting of the IEA Governing Board at
          Ministerial Level, participants discussed how governments can improve the framework
          conditions to ensure timely investment in energy infrastructure that meets the tests
          of security of supply, economic efficiency, environmental sensitivity and affordability.

             The messages from these high-level gatherings seem clear, and I firmly believe that
          we cannot afford to underestimate the importance of meeting the energy challenges
          before us. Our economies depend upon it, as do our health and well-being. Meeting
          growing energy demands must be done with due consideration for preserving the
          environment. To succeed, a full range of approaches – starting with energy conservation
          measures, but also including cleaner energy sources, greater use of renewables and
          appropriate environmental-preservation agreements and incentives – will be necessary.

                                                            Luis E. Echávarri
                                                          NEA Director-General

Editorial, NEA News 2005 – No. 23.1                                                                  3
NEA News 2005 - No. 23.1 - Nuclear Energy Agency
Nuclear regulatory
    decision making
                                              B. Kaufer, T. Murley *

    Nuclear safety regulators are continuously faced with making                            regulator’s decision-making
    a wide variety of decisions. Some of these may be made on                               process. In light of these
                                                                                            insights, the NEA Committee on
    the regulator’s own initiative, for example a regulation on
                                                                                            Nuclear Regulatory Activities
    new reporting requirements, but the large majority of                                   (CNRA) judged that it was an
    decisions are made in response to stimuli from outside the                              appropriate time to examine
    organisation. A new CNRA report 1 has found that in all                                 the broad issue of regulatory
    decision-making scenarios, whether difficult or straight-                               decision making. That judge-
    forward, the nuclear regulator will benefit from a structured                           ment was the basis for deciding
                                                                                            to prepare a report providing
    decision-making framework.                                                              an international consensus on
                                                                                            the integrated decision-making
                                                                                            process. To pursue this objec-
                                                                                            tive, an expert group was
                                                                                            formed with senior-level regu-
    N   uclear power programmes
        in OECD countries have
    matured over their four
                                                and insights from operating
                                                experience, especially from the
                                                accidents at Three Mile Island
                                                                                            lators.

    decades of commercial oper-                 and Chernobyl; in the consid-
    ation; this maturation has                  eration of human factor and
    brought many improvements in                organisational impacts upon
    safety through backfits in tech-            nuclear safety; and in an
    nology as well as programmes                increased emphasis on quality
    and improvements in opera-                  management systems.
    tional performance of nuclear                  It has been recognised for
    power plants generally. In par-             some years that the nature of
    allel with these changes in                 the relationship between the
    nuclear plants’ performance,                regulatory body and the oper-
    safety regulation of nuclear                ator can influence the opera-
    power plants has matured,                   tor’s safety culture at a plant,
    most notably in the use of new              either positively or nega-
    safety analysis methods such as             tively.2,3 An important factor
    probabilistic safety analysis               affecting the relationship
    (PSA); in the regulatory                    between the regulator and the
    responses to new information                operator is the nature of the               Types of regulatory
                                                                                            decisions
                                                                                               Perhaps the bulk of the deci-
                                                                                            sion cases that come before a
                                                                                            regulator are straightforward
    * Mr. Barry Kaufer (email: barry.kaufer@oecd.org) works in the NEA Nuclear              issues, but that does not mean
    Safety Division. Dr. Thomas E. Murley (email: temurley@erols.com) is a former
    Director of the Office of Nuclear Reactor Regulation at the United States Nuclear       that they are unimportant or
    Regulatory Commission and is a consultant to the NEA.                                   that the regulator does not

4                                                                                       Facts and opinions, NEA News 2005 – No. 23.1
NEA News 2005 - No. 23.1 - Nuclear Energy Agency
need to consider them care-                  fundamental distinction in             ments to satisfy the opera-
fully. Rather, it simply means               roles between the operator             tional needs of the plant
that there are substantial prece-            and regulator. A regulator’s           operator?
dents of case histories and ade-             decisions must be grounded in          This questioning is not
quate time for the regulator to              the nation’s laws and the regu-     meant to suggest that the reg-
define the issues clearly, to                lations and standards that          ulator should allow itself to
analyse alternative actions and              implement those laws. But           become paralysed by concerns
to involve the appropriate                   even further, the regulatory        that a decision may not turn
stakeholders. In other words,                body should promote safety by       out well. Rather, it is a
for such issues there is ample               setting a good example in its       reminder that the regulatory
opportunity for the regulator                own performance.                    body should assure itself that
to implement its deliberative,                  When approaching regula-         it has approached the decision
structured decision-making                   tory decisions several basic        following its procedures in a
process.                                     principles can be applied such      structured manner, has consid-
   Some of these decision                    as assessing safety significance,   ered all relevant input, has
issues will be more challenging              gathering sufficient information    used sound safety principles
for the regulator. They are fre-             to make an informed decision,       and has not appeared to be
quently characterised by unex-               seeking input from outside          unduly pressured in making
pected circumstances, lack of                stakeholders, maintaining con-      the decision.
complete information, uncer-                 sistency in decisions, and most
tain or contradictory informa-               importantly, acting as a com-       Criteria for regulatory
tion, disagreement among the                 petent, professional, independ-     decisions
safety experts, a real or per-               ent body that makes regulatory
ceived urgency to make a                     decisions on the basis of pro-          Current, comprehensive and
decision, an incomplete under-               tecting safety, security and the    clear regulations are essential
standing of the consequences                 environment.                        for a good decision-making
of a decision, or all of the                                                     process, but these cannot cover
                                                In making a decision on a
above. Adding to these difficul-                                                 all the aspects of the issues that
                                             difficult issue, the regulator
ties is often the concern in the                                                 a regulator will face. There will
                                             will have to consider how the
mind of the regulator that its                                                   always be questions of com-
                                             decision will appear in retro-
decision-making actions may                                                      pleteness, differing interpre-
                                             spect if it turns out to be
have profound effects not only                                                   tations and unexpected situ-
                                             wrong or not to have the
on public safety but on the                                                      ations. For these reasons a reg-
                                             desired outcome. In difficult
public’s perception and confi-                                                   ulatory body will usually be
                                             cases there will frequently be
dence in the regulatory body                                                     guided by broad criteria that
                                             pressure on the regulator from
itself.                                                                          form the foundation of its
                                             many sources, so the regula-
   Whether a decision issue is                                                   safety philosophy.
                                             tory body should ask itself
straightforward or difficult, a              some questions before render-           One of these criteria is the
nuclear regulator will benefit               ing a final decision:               level of safety and environmen-
by having a structured decision-                                                 tal protection to be required by
                                             ● Is there a clear safety basis
making framework and by                                                          the regulator. There are vari-
                                                for the decision?
having experience in follow-                                                     ous statements on the basic
                                             ● Is there a clear legal basis      level of protection criterion in
ing its procedures.
                                                for the decision?                OECD countries, but they all
                                             ● Were normal procedures fol-       acknowledge that it is not pos-
Basic principles for
                                                lowed?                           sible to achieve zero risk in
regulatory decision making
                                             ● Were all stakeholder views        nuclear activities. Some of the
   A fundamental tenet of                       considered?                      criteria for the basic level of
nuclear safety is that the oper-                                                 protection in OECD countries
                                             ● Was there due diligence
ator has the responsibility for                                                  are:
                                                used in gathering the neces-
safely operating its nuclear                                                     ● no unreasonable risk,
                                                sary information?
power plant(s). It is the
                                             ● Is the decision consistent        ● adequate protection of pub-
nuclear regulator’s responsi-
                                                with earlier precedents?             lic health and safety,
bility to oversee the operator’s
activities in order to ensure                ● Has the regulator ensured         ● risk as low as reasonably

that the plant is operated                      that the decision was not            practicable,
safely. Nothing the regulator                   made prematurely, bypass-        ● safety as high as reasonably

does should ever diminish that                  ing some regulatory require-         achievable,

Nuclear regulatory decision making, NEA News 2005 – No. 23.1                                                          5
NEA News 2005 - No. 23.1 - Nuclear Energy Agency
C. Cieutat, La Médiathèque EDF, France
         Miklos Beregnyei, PAKS NPP, Hungary

                                                                                                                             AECL, Canada
                                               Some of the criteria for the basic level of protection in OECD countries include adequate protection of public
                                                  health and safety, risk as low as reasonably practicable, and safety as high as reasonably achievable.

    ●   risk limited by use of best                                                      the health and safety of people                    earliest days of commercial
        technologies at acceptable                                                       living near nuclear power                          nuclear power, regulators have
        economic costs.                                                                  plants. In order to be more                        embraced defence in depth to
       A related question is what                                                        useful in practical decision                       require multiple layers of pro-
    criterion should be used for                                                         making, the health goals are                       tection to prevent accidents
    the level of assurance that the                                                      often supplemented by numer-                       and to mitigate their conse-
    required safety criteria are met?                                                    ical goals for core damage fre-                    quences. The use of defence-
    Here again, there are various                                                        quency (CDF) and large, early                      in-depth principles and safety
    formulations of the criterion                                                        radioactive release frequency                      margins have been, and con-
                                                                                         (LERF). Clearly the use of                         tinue to be, effective ways to
    for the level of assurance in
                                                                                         these latter safety goals                          account for uncertainties in
    OECD countries, but they all
                                                                                         requires the production and                        equipment and human per-
    recognise that absolute assur-
                                                                                         maintenance of high-quality,                       formance. As more operating
    ance cannot be achieved. Most
                                                                                         plant-specific PSAs as well as                     experience and improved
    countries have some variation
                                                                                         operator and regulatory staffs                     safety analysis methods give
    of a “reasonable assurance”
                                                                                         proficient in PSA methodology.                     us a deeper understanding of
    criterion.
                                                                                         Although the promulgation                          nuclear plant safety, safety
       These criteria are seen to be                                                     and use of quantitative safety                     margins and their uncertain-
    qualitative aspirational criteria                                                    goals is fairly common among                       ties, it may be possible to
    rather than quantitative safety                                                      OECD regulatory bodies, these                      reduce overly conservative
    requirements that must be met.                                                       criteria are generally regarded                    margins or to add margins
    In practice, they are what                                                           as not appropriate for use as                      where needed.
    some may call “revealed stan-                                                        the sole basis for making regu-
    dards”. That is, the sum of per-                                                     latory decisions. Instead, the
    haps hundreds of case history                                                        quantitative safety goals are
                                                                                                                                            Elements of the regulatory
    decisions and case law over                                                          best used as guidelines by the                     decision-making process
    several years will yield a work-                                                     regulator to supplement other                         The basic principles and cri-
    ing definition of what these                                                         regulatory criteria.                               teria for regulatory decision
    criteria mean.                                                                          A fundamental principle for                     making should be embodied in
       Beyond these qualitative                                                          safety regulators is the practice                  a practical, integrated frame-
    aspirational criteria a regula-                                                      of conservative decision mak-                      work that regulators can use in
    tory body may adopt quantita-                                                        ing. This is exemplified by the                    their daily activities. The frame-
    tive safety goals – for example,                                                     traditional defence-in-depth                       work need not be rigid but
    numerical goals for protecting                                                       safety philosophy. Since the                       must be consistent with national

6                                                                                                                              Facts and opinions, NEA News 2005 – No. 23.1
laws, customs, international                 system, similar to its planning    Conclusion
treaties, regulations and the                and budgeting processes, tak-
                                                                                   There is no guide or hand-
internal policies of the regula-             ing into account the national
                                                                                book that will tell a regulator
tor. The basic elements of an                laws, customs and internal
                                                                                how to make a proper deci-
integrated framework are to                  policies of the regulator. In
                                                                                sion, especially for difficult
(a) clearly define the issue,                this way the decision-making
                                                                                cases where the issues may be
(b) assess the safety signifi-               process will over time become
                                                                                contentious and the circum-
cance, (c) determine the laws,               part of the culture of the regu-
                                                                                stances unique. That is the
regulations or criteria to be                latory body’s organisation.
                                                                                value of having a decision-
applied, (d) collect the rele-                  The integrated decision-        making framework to fall back
vant information and data,                   making framework will cover        on. Beyond that, the regulator
(e) judge the expertise and the              the great majority of decisions    will have to rely on its experi-
resources needed, (f) agree on               faced by a regulatory body.        ence and good judgment, keep-
the analyses to be performed,                But every regulator will           ing in mind that safety, and, to
(g) assign priority to the issue             encounter special situations       some degree at least, the credi-
among the other tasks of the                 that are unique in some aspect     bility of the regulatory body
agency, (h) make a well-                     or that do not fit neatly into     may be at stake in the regula-
informed decision, and finally               the framework outlined above.      tory decision and the way it is
(i) write a clear decision and               The CNRA report on Nuclear         made. ■
its basis, and publish the deci-             Regulatory Decision Making
sion when needed.                            provides advice on how best
    The elements above are                   to approach a number of these
not meant to be followed in                  types of situations, notably:
sequential order; in fact, sev-              decision making in the face of
eral of them can be conducted                uncertainties, handling safety
in parallel and some could                   culture issues, facing differing
even be omitted in certain sit-              opinions, considering informa-
uations. The rigour and depth                tion from safety advisory bod-
with which the elements are                  ies and using risk information
followed should generally be                 in regulatory decisions.
proportionate to the safety and
regulatory significance of the               Communicating regulatory
issue being considered.
                                             decisions
    The regulator’s responsi-
bility does not end with the                    In any discussion of the
decision and its publication.                basic principles and criteria
Clearly, there are follow-up                 that a safety regulatory body
actions a regulator should take              should consider when making
to ensure that its decision is               a decision that can affect a
implemented. Likewise, the                   wide range of stakeholders, it
decision and its basis must be               is necessary to keep in mind
stored in the regulatory body’s              how those stakeholders might
established document control                 view the decision and its
system. This will enable effec-              rationale. In this regard, it is
tive follow-up actions and will              important for the regulatory
facilitate retrieval of the infor-           body to consider how its deci-
                                             sions are communicated to its      Notes
mation to assist in future deci-
sion making.                                 stakeholders.                      1. The CNRA booklet on Nuclear
                                                For many of the difficult          Regulatory Decision Making was
                                                                                   published this spring and is available
Implementing the elements                    issues facing the regulator, the      on the NEA website at www.nea.fr
                                             outside party most directly           and upon request from the NEA
of the decision-making                                                             Secretariat. Its contents formed the
                                             affected will be the plant oper-
process                                                                            basis for this article.
                                             ator. In some complex or con-
   The regulatory body can use               tentious cases, the regulator      2. NEA (1999), The Role of the Nuclear
                                                                                   Regulator in Promoting and Evaluat-
the elements above to develop                may want to explain the writ-         ing Safety Culture, OECD/NEA, Paris.
a regulatory decision-making                 ten decision in a meeting with
                                                                                3. NEA (2000), Regulatory Response
framework and to integrate it                the operator, perhaps in a            Strategies for Safety Culture Prob-
into its overall management                  meeting open to the public.           lems, OECD/NEA, Paris.

Nuclear regulatory decision making, NEA News 2005 – No. 23.1                                                                7
An analysis of uranium
    exploration and price
                                                  R. Price *

    The primary production of uranium has been less than reactor                       Yet, despite the significance
    requirements since the mid-1980s and secondary sources                          of this increase in relative terms,
    have had to make up the difference. By 2002, world uranium                      this price rise remains relatively
                                                                                    modest at this point when com-
    production provided only about 54% of world reactor                             pared with the historic peaks
    requirements. This dependence on secondary supplies is                          of the 1970s or even the short-
    projected to continue into the near future. Over the longer                     lived peak in the mid-1990s,
    term, however, primary production will need to expand.                          especially when viewed in
                                                                                    constant terms (see Figure 1).
                                                                                       Will this increase in market

    O   ne result of the abundance
        of secondary sources has
    been a consistently depressed
                                         price of uranium. Since the
                                         beginning of 2001, the price
                                         of uranium has rebounded
                                                                                    price result in the increased
                                                                                    exploration needed to support
                                                                                    new production capability? To
    market price for uranium over        from lows not seen since the               answer this question, a review
    the past several decades. These      early-1970s, and had almost                of the data collected over the
    low market prices led to the         doubled by July 2004.1                     past 40 years was conducted to
    curtailment of exploration and
    the closing and/or consolida-
    tion of many uranium produc-
    tion companies and production
    centres. Consequently, during          Figure 1. World exploration and uranium price, in 2003 US dollars
    this time the level of uranium                                   (1970-2002)
    exploration has been at low
    levels and mainly oriented           2003 USD Uranium price                                 World exploration 2003 USD
    towards development.                                                                                            1.4x109
                                         100
       Yet, after 2020, when sec-
    ondary sources of uranium                                                                                      1.2x109
    are expected to decline in avail-     80
    ability, reactor requirements will                                                                             1x109
    have to be increasingly met by
                                          60                                                                        8x108
    primary production. To meet
    this increasing demand, pri-
    mary production capability will                                                                                6x108
                                          40
    need to increase significantly.
    As a first step, new exploration                                                                               4x108
    will be needed to provide the         20
    increased resource base neces-                                                                                 2x108
    sary to support this expansion.
    A barrier to new exploration           0                                                                       0
    has been the low price for             1970       1975        1980     1985      1990       1995       2000
    uranium.                                                                 Year
       Over the past several years,
    though, there has been a sig-        * Mr. Robert Rush Price (e-mail: robert-rush.price@oecd.org) works in the NEA
    nificant increase in the market      Nuclear Development Division.

8                                                                              Facts and opinions, NEA News 2005 – No. 23.1
attempt to determine whether                      Figure 2. World exploration expenditures versus uranium price
exploration could be expected                                        (2003 USD, 1970-2002)
to respond to this price recov-                 2003 USD Exploration expenditures
ery, and in what time frame
                                                1.6x109
increased exploration could be                                  World exploration with 1-year lag v U price (1970-2002)
expected to result.
                                                1.4x109       A = -6.13745 x 107    t = -1.177267
   Data on uranium exploration
                                                              B = 1.437 x 107       t = 15.96424
was taken from the OECD/                                      R = 0.94588
                                                1.2x109
NEA series of publications
entitled Uranium Resources,
Production and Demand                             1x109
(known as the Red Book). The
data there represent the total                    8x108
amount of money spent on
exploration within a given                        6x108
country regardless of whether
the source was domestic or                        4x108
foreign. Data on the price of
uranium was taken from                            2x108
NUEXCO/TradeTech and was
the annual average of the end-                        0
of-month unrestricted
exchange values (without pre-                             0           20           40           60           80           100
miums).2                                                                      Uranium price, 2003 USD/lb U3O8

   A look at Figure 1 indicates a
possible correlation between                 indeed following as predicted,                   vide the resource base
price and exploration and                    but press reports are providing                  required to build new or
further points to a time lag                 circumstantial, anecdotal evi-                   expand existing production
between a change in uranium                  dence that exploration activity                  capability. An analysis of his-
price and changes in explora-                is already picking up in                         torical information indicates
tion expenditures. For world                 Australia, Canada and the                        that past price increases have
expenditures, the best correla-              United States, thus leading to                   resulted in increased explo-
tion was observed with a one-                the conclusion that data will                    ration. Recent price increases
year delay (see Figure 2).                   likely show an increasing                        can therefore be expected to
   The improvement in correla-               trend.                                           begin the increased exploration
tion when a time delay is                       Analysis using surface drill-                 needed to support the expan-
introduced corresponds logi-                 ing data, a more direct meas-                    sion of uranium production
cally to the delays as the influ-            ure of exploration activity, was                 capability. ■
ence of the uranium price                    also conducted to see if this
change works its way through                 would lead to a better predic-
the decision-making process in                                                                Notes
                                             tor. Adequate data on surface
the exploration companies, as                drilling was available for                       1. TradeTec, LLC (from www.uranium.
well as the time needed to ini-                                                                  info/index.html).
                                             Australia, Canada and the
tiate field studies once a deci-                                                              2. Total exploration expenditure
                                             United States for the period                        includes exploration and devel-
sion has been reached. The                   1975-2002. When plotted, how-                       opment expenditures. Exploration
results suggest that exploration             ever, the results were similar                      includes the costs of all types of
is a competitive and open sec-                                                                   surveys, including: surface and
                                             and showed no improvements                          underground drilling, logging, test
tor of the uranium industry,                 over the results provided in                        mining and other costs related to the
sensitive to uranium price, and              Figure 2.                                           search for new deposits or exten-
                                                                                                 sions to known deposits. Prior to
aggressively responds to mar-                   With reactor requirements to                     1989 world data does not include
ket signals.                                 be increasingly met by primary                      the countries associated with the
                                                                                                 former Soviet Union and certain
   The results indicate that                 production in the coming                            other non-western countries, e.g.
even relatively modest price                 years, it is necessary to ensure                    China and Mongolia, and so
increases are followed by                    that sufficient new discoveries                     represents only a sample of world
                                                                                                 activity and not the entire popu-
increases in exploration                     of uranium are made to enable                       lation. The inflation index used to
expenditures. Data for 2004                  the expansion of production                         convert to constant 2003 dollars was
exploration expenditures is                  capability as secondary sources                     the Producer Price Index. Historical
                                                                                                 values of this index were obtained
not yet available to verify                  decline. Increased exploration                      from http://www.jsc.nasa.gov/bu2/
whether market behaviour is                  activity will be needed to pro-                     inflation/ppi/inflatePPI.html.

An analysis of uranium exploration and price, NEA News 2005 – No. 23.1                                                                   9
Lessons drawn from recent
     NPP operating experience
                                                          P. Pyy *

     C  ountries need timely feed-
        back from international
     nuclear power plant (NPP)
                                                            WGOE
                                                                                    All three of these areas illus-
                                                                                    trate the continuing need to
                                                                                    institute an appropriate and
     operating experience in order              The NEA Working Group on            timely corrective action pro-
     to manage the safety of their              Operating Experience (WGOE)         gramme both by the utilities
     installations effectively. One             has an important task to            and the regulators in order to
     way to obtain this type of                 refine and report messages          avoid recurrence.
                                                from international nuclear
     information is through the
                                                power plant operating experi-
     annual technical notes about                                                   Electrical disturbances
                                                ence to NEA member coun-
     lessons drawn from recent
                                                tries. This is done via                Several electrical events,
     nuclear power plant operat-                reporting to the NEA Com-
     ing experience prepared by                                                     both plant-centered and in
                                                mittee on the Safety of
     the NEA Working Group on                                                       the off-site grid, have been
                                                Nuclear Installations (CSNI)
     Operating Experience (WGOE).                                                   reported in recent interna-
                                                and the NEA Committee on
     This article is based on the               Nuclear Regulatory Activities
                                                                                    tional operating experience.
     technical note for events                  (CNRA). Apart from technical        The previous technical note
     experienced in 2003-4 1 (the               notes, the WGOE issues              [NEA/CSNI/R(2004)4] reported
     third in the series 2).                    technical reports about             the August 2003 massive grid
        The WGOE technical notes                selected topics dealing with        disturbance in the United
     are based on the issues                    the analysis of nuclear oper-       States, which propagated into
     reported in the joint NEA/                 ating experience, including         parts of Canada, and more
                                                risk insights where relevant.       information has recently been
     IAEA Incident Reporting
                                                The group also seeks to             presented. For example, the
     System (IRS) and, in some
                                                advance practices to collect        Pickering station, which con-
     cases, the NEA joint safety                and analyse operating experi-
     projects dealing with operat-                                                  sists of eight units, experi-
                                                ence in member countries.
     ing experience data collection                                                 enced a total loss of off-site
     and analysis. The safety issues                                                power and natural circulation
     identified in the technical notes                                              secured the plant cooling for a
     are generic in nature and, con-                                                number of hours. The event
     sequently, useful to decision                                                  revealed deficiencies in a num-
                                              Recent safety issues
     makers. However, it is also                                                    ber of safety systems, includ-
                                              emerging from the Incident            ing emergency service water,
     suggested that national regula-
                                              Reporting System                      firewater, standby diesel gener-
     tory bodies, technical support
     organisations and nuclear oper-             Recent events of safety sig-       ators, and the licensing basis
     ators put them in national con-          nificance reported to the IRS         for these and other systems.
     text to see if they are relevant         include erosion-corrosion of          Corrective actions, including
     to the safety of the nuclear             piping, electrical disturbances,      changes in plant design and
     power plants (NPPs) in their             and foreign material intrusion        operation, are currently being
     countries.                               into the primary coolant system.      taken.
                                                                                       Furthermore, in June 2004
                                                                                    there was a loss of off-site
                                                                                    power at the Palo Verde NPP
     * Dr. Pekka Pyy (e-mail: pekka.pyy@oecd.org) works in the NEA Nuclear Safety   in the United States involving
     Division.                                                                      a complete loss of 5 500 MWe

10                                                                                  NEA updates, NEA News 2005 – No. 23.1
cladding was likely caused by
                                   IRS                                                     pieces of the gasket that went
                                                                                           through them.
  The Incident Reporting System (IRS) is the only international
  reporting system for regulators and governmental organi-                                     Another foreign material
  sations which provides an assessment of safety-significant                               intrusion event was experi-
  nuclear power plant events, as well as detailed information                              enced at the Fessenheim facil-
  on analyses of the root causes and lessons learnt from the                               ity in France. A human action
  safety perspective. The IRS is operated by a joint IAEA and                              on a valve alignment in the
  NEA secretariat. A guideline for IRS reporting has been in use                           chemical and volume control
  since June 1998. The system, based on quarterly CD distri-                               system (CVCS), combined with
  bution, is now in use in 31 countries. In 2005, it is planned
                                                                                           a design modification, resulted
  to make trial use of the web-based IRS. Periodic reports on
  Nuclear Power Plant Operating Experience (the “Blue Book”)
                                                                                           in intrusion of demineralised
  have been published for the periods 1996-1999 and 1999-                                  resins into the primary coolant
  2002. The next Blue Book for 2002-2005 is planned for                                    system. This led to the contam-
  spring 2006, in conjunction with the International Conference                            ination and exposure of work-
  on Future Uses of Operating Experience scheduled to take                                 ers, obstruction of the sampling
  place in Germany.                                                                        system, and a six-month out-
                                                                                           age of the facility for cleanup
                                                                                           and repair. The nuclear safety
                                                                                           consequences included inop-
                                                                                           erability of a number of con-
                                                                                           trol rods, blockage of injection
                                                                                           to reactor coolant pump seals,
                                                                                           and increased potential for
of generating capacity on the               Foreign material intrusion                     failure of high-pressure injec-
grid, including more than                   into the primary system                        tion pumps due to bearing
3 700 MWe from the three                                                                   failure.
                                               There have recently been
units at Palo Verde. The cause                                                                 Although foreign material
                                            two significant events involving
was traced to a single failure                                                             intrusion is a recurring con-
                                            foreign material intrusion. At
of protective circuitry at an                                                              cern, these two events were
                                            the Tihange plant in Belgium, a
off-site substation. In general,                                                           particularly significant. The
                                            severely damaged spiral-wound
the station responded accord-                                                              first one led to a fuel failure
                                            metallic gasket was found in a
ing to design, although one                                                                and the second one to safety
                                            safety injection system check
emergency diesel generator                                                                 system impairments and a
                                            valve, and a fuel failure was
failed to start. It was observed                                                           long outage.
                                            observed some months later.
that the transmission company
                                            The fuel anti-debris devices
operators had not analysed a
                                            were unable to catch some                      Erosion-corrosion of piping
situation involving the simulta-
                                            portions of the gasket, and the                   As regards piping, a signifi-
neous loss of all three units.              mechanical damage of the fuel
The event was considered risk-                                                             cant event occurred at the
significant and the corrective                                                             Mihama plant in Japan that
actions included improvements                               New and severely damaged       involved the failure of a con-
in the off-site grid components.                           gaskets at the Tihange plant.   densate water pipe in the tur-
                                                                                           bine hall. The event resulted
   These loss of off-site power
                                                                                           in severe injuries to plant per-
events had common messages:
                                                                                           sonnel, including five fatali-
1) the operating utilities may
                                                                                           ties. Some of the main
have inadequately analysed
                                                                                           features of the event are:
grid disturbances; 2) there is a
need to review operating pro-                                                              ● The ruptured portion of the

cedures, communication plans,                                                                 piping should have been
equipment and the licensing                                                                   inspected according to plant
basis for a widespread and                                                                    guidelines. However, it had
long loss of off-site power                                                                   not been inspected since
event, and 3) there may be                                                                    the plant start-up in 1976.
frailties in the interconnected                                                            ● An unauthorised residual
                                            AVN, Belgium

grids when large concurrent                                                                   life evaluation rule was
trips of generating capabilities                                                              applied by the plant oper-
occur.                                                                                        ating organisation.

Lessons drawn from recent NPP operating experience, NEA News 2005 – No. 23.1                                                  11
●  The quality management            removal in reduced inventory        the fact that both the licensee
        system of the operating           conditions during outages.          and the contractor organisa-
        organisation was not suffi-       More than 50 such events have       tions may experience loss of
        cient to check the con-           occurred over the past 25 years.    competence via outsourcing.
        tracted work.                     Several types of regulatory cor-    Small utilities and regulatory
     ● The secondary piping               rective action approaches have      bodies dealing with large and
        inspection had been within        been used, ranging from infor-      sometimes multinational con-
        the scope of the utility’s        mation notices, advisories and      tractor organisations seem to
        self-imposed inspections.         suggestions, to formal and          be most vulnerable to this.
                                          binding decisions by the regu-         Member countries gave sev-
        A number of precursor
     events have taken place at           latory authorities. In 1988, the    eral presentations about events
     similar plants, for example in       US NRC issued a generic letter      involving contracted work,
     Japan and in the United States       with non-binding suggestions        including a brief interruption in
     (e.g. at Surry in 1986), and         on means for reducing the           decay heat removal due to
     many of them may be found            number of occurrences. A            maintenance during an outage,
     in the IRS database. As a cor-       notable effect was observed,        a plant start-up before some
     rective action, improvements         but events continue to occur,       scheduled contracted work
                                          even in 2004. By contrast, for      could be completed, and manu-
     in inspection practices of both
                                          instance, France and Korea          facturing deficiencies in the
     the operator and the regulator
                                          issued binding requirements         component cooling water sys-
     are being considered and/or
                                          that seem to have stopped the       tem heat exchangers.
     already applied. For instance,
     since 1 October 2003 this pre-       recurrence there. In France, an        Ideas on how to avoid
     viously self-imposed inspection      automatic makeup function           problems with contracted
     is now legally required, and         was provided; a detailed work       work and to improve the situ-
     the Japanese regulatory agency       schedule and necessary condi-       ation were presented. There
     NISA (Nuclear and Industrial         tions were required prior to        was agreement that the licens-
     Safety Agency) reviews second-       mid-loop entry; and a vortex        ees must be able to exercise
     ary wall thickness inspection        detection device was installed.     contractor supervision in all
     by the utilities. In addition, the   In Korea, there were require-       circumstances. However,
     Japanese Society of Mechanical       ments for better training of        some events indicate a grow-
     Engineers is preparing a pip-        staff, better level instruments,    ing problem of detecting sub-
     ing thickness management             revision of residual heat           standard performance. In addi-
     standard, and NISA has recently      removal pump procedures,            tion, the licensees need to
     issued guidelines for the ins-       review of critical level calcula-   qualify the contractors, but the
     pection and management of            tions and revised technical         procedures for this may not be
                                          specifications.                     adequate or even exist in the
     pipe and wall thinning.
                                             The WGOE is currently inves-     light of recent experience.
                                          tigating whether a similar study    Furthermore, matters such as
     Recent safety issues                                                     training on nuclear-specific
                                          on the risk-significant issue of
     emerging from other WGOE             loss of heat sink or loss of        requirements must be
     work                                 service water to safety-related     addressed by the licensee.
        Other work carried out by         equipment should be initiated.         Contracting and subcontract-
     the WGOE has highlighted                                                 ing may, if not handled ade-
     additional safety issues includ-                                         quately, lead to losing a long-
                                          Events involving
     ing recurring events, events                                             term safety focus. Core compe-
                                          contractors                         tencies must always be kept
     involving the use of and per-
                                              The theme chosen for the        in-house in order to remain
     formance of contractors, and
                                          WGOE in-depth discussion at         an intelligent customer. This
     the origins of common-cause
                                          its annual meeting in 2004 was      includes, independently of
     failures (CCFs).
                                          the influence of contractor         the domain, the ability to
                                          (and subcontractor) work on         qualify contractors, oversight
     Recurring events                     the evolution of events. There      of training of contracted per-
        The WGOE has continued            is an increasing use of contrac-    sonnel, supervision and
     to study recurring events (it        tors and subcontractors in the      approval of contracted work,
     previously issued two reports        nuclear industry, although out-     and most importantly, continu-
     on the topic). The latest theme      sourcing is not new. Concerns       ing involvement in the mainte-
     concerns corrective actions          about the use of contractors        nance of safety-focused
     against PWR loss of decay heat       have increased lately due to        thinking.

12                                                                            NEA updates, NEA News 2005 – No. 23.1
well-known, but information
                                  ICDE                                           does not always seem to reach
                                                                                 end-users and/or corrective
  The International Common-cause Data Exchange (ICDE) proj-
  ect was initiated in August 1994. The countries participating                  action programmes are not
  in the third agreement phase of ICDE are: Canada (CNSC),                       always rigorously imple-
  Finland (STUK), France (IRSN), Germany (GRS), Japan                            mented. More needs to be
  (NUPEC/JNES), Republic of Korea (KAERI), Spain (CSN),                          done internationally to share
  Sweden (SKI), Switzerland (HSK), United Kingdom (NII) and                      experience on safety issues
  the United States (NRC). The objective of the ICDE project is                  and their solutions, and to
  to draw qualitative and quantitative insights from interna-                    make sure that the information
  tional operating experience data to help avoid common-cause
                                                                                 reaches the end-users at the
  failures or to mitigate their consequences. The ICDE data
  include both those events reported to regulatory bodies and                    NPPs.
  those based on additional analysis of proprietary nuclear                         The main findings that oper-
  power plant databases. The main findings of the project are                    ation and maintenance domi-
  reported publicly.                                                             nate as causes for common-
                                                                                 cause failures, and a number
                                                                                 of recent events dealing with
                                                                                 the increased role of contrac-
                                                                                 tors and subcontractors, show
                                                                                 that the utilities and regulators
Common-cause failures                       prevented with adequate prac-        may need to enhance over-
of batteries                                tices and surveillance of the        sight of the organisational
   The International Common-                circuit continuity.                  arrangements, competence and
cause Data Exchange (ICDE)                     Generally, the main areas         safety culture of the licensees
project has exchanged infor-                for improvement to prevent           to ensure the safe operation
mation on common-cause fail-                common-cause failures at NPPs        and maintenance of NPPs.
ures (CCFs) for more than ten               are, according to the project           Finally, an operating experi-
years. The project’s most                   findings: 1) scrutinizing existing   ence reporting and analysis pro-
recent report, issued in late               operation, maintenance and           gramme is a prerequisite to
2003, was about batteries.3                 testing procedures for deficien-     successful safety management
                                            cies creating the potential for      and is stipulated in the Conven-
   Deficiencies in design were                                                   tion on Nuclear Safety. In addi-
                                            CCF of redundant systems,
involved in about half of all the                                                tion to this, many problem
                                            2) ensuring comprehensive
events. Of those, more than                                                      areas also require a review of
                                            work control, 3) comprehen-
90% occurred during battery                 sively prescribing the testing       operating experience on lower
manufacture, e.g. inadequate                steps required in the requalifi-     levels than plant events and
selection of component materi-              cation of components or sys-         combining this review with
als for the plates, in the elec-            tems after maintenance, repair       other analyses – such as PSA,
trolyte, in separators, in cells,           or backfitting work, and             organisational and task analy-
or in terminal connections, and             4) intensifying training, intro-     ses, materials analyses and
less than 10% occurred during               ducing ergonomically better          thermal hydraulic calculations
the plant specification or modi-            designs and introducing more         – to find permanent solutions.
fication process, e.g. calculation                                               Such a cross-disciplinary
                                            key locks. These findings
errors in the capacity definition.                                               approach challenges the
                                            apply to all component types
Deficiencies in maintenance                                                      nuclear safety community to
                                            which have been analysed in
and testing were involved in                                                     progress to the new era of
                                            the ICDE project.
less than half of the events. Of                                                 safety management. ■
these, approximately half were
due to physical failures in the             Concluding remarks
battery subcomponents, nearly                  Almost all of the significant     Notes
30% were due to electrical fail-            events reported recently in
                                                                                 1. “Lessons Drawn From Recent Nuclear
ures, some 20% due to direct                international meetings have             Power Plant Operating Experience”,
human actions, and one event                occurred earlier in one form            NEA/CSNI/R(2005)4.
was due to premature ageing                 or another. Similarly, most of       2. The first two WGOE technical notes
caused by lack of mainte-                   the topics highlighted in the           are referenced as NEA/CSNI/R(2002)
                                                                                    24 and NEA/CSNI/R(2004)4.
nance. The data suggests that               2001-2 and 2002-3 technical
                                                                                 3. “ICDE Project Report: Collection and
the majority of maintenance                 notes are still valid. Counter-         Analysis of Common-cause Failures
and testing events could be                 actions are in many cases               of Batteries”, NEA/CSNI/R(2003)19.

Lessons drawn from recent NPP operating experience, NEA News 2005 – No. 23.1                                               13
Management of uncertainty
     in safety cases and the role
     of risk
          B. Dverstorp, A. Van Luik, H. Umeki, S. Voinis, R. Wilmot *

     D  eep geological repositories
        aim to protect humans and
     the environment from the haz-
                                                 current level of technical
                                                 understanding established
                                                 through uncertainty analysis.
                                                                                             be described in the safety case
                                                                                             at each stage.
                                                                                                There is a clear consensus
     ards associated with long-lived             A safety case 1 is a key input              among all national programmes
     radioactive waste over time-                to support the decision to                  on the importance of managing
     scales often up to several thou-            move to the next stage in                   uncertainties in a safety case.
     sand or even a million years.               repository development. A                   Managing uncertainties and
     Radioactive waste management                key output of the safety case               establishing levels of confi-
     thus involves a unique consid-              is the identification of uncer-             dence can be approached in
     eration of the evolution of the             tainties that have the potential            different ways. This requires a
     waste and engineered barriers,              to undermine safety. The con-               clear classification of the uncer-
     and the interactions between                nection therefore needs to be               tainties since a large range of
     these components and geologi-               made between key uncertain-                 uncertainties are to be han-
     cal barriers over very long                 ties that have been identified              dled. Various classifications of
     periods of time. Over long                  and the specific measures or                uncertainty exist – such as
                                                 actions that will be taken to               epistemic uncertainties, uncer-
     enough timescales, however,
                                                 address them, especially with               tainties due to natural variabil-
     even the most stable engi-
                                                 regard to the R&D programme,                ity, and randomness – and the
     neered materials and geolog-
                                                 in order to eventually arrive at            concept of uncertainty classifi-
     ical environments are subject
                                                 a safety case that is adequate              cation is both widely used and
     to perturbing events and
                                                 for licensing. Explicit treatment           judged as necessary for per-
     changes that are subject to                 of uncertainties is thus an                 forming uncertainty analyses.
     uncertainties. The uncertainties            essential part of building confi-           One part of the overall uncer-
     associated with the evolution               dence in the safety case. Con-              tainty management process is
     of the disposal system have to              fidence in the safety case is               the evaluation of quantifiable
     be appropriately considered                 supported by a reliable safety              uncertainties in a quantitative
     and managed throughout a                    assessment with a clear state-              assessment of system perform-
     repository development pro-                 ment on data quality, clear jus-            ance. However, since not all
     gramme.                                     tifications of assumptions and              uncertainties can be quantified,
        At each stage of a stepwise              discussion of the sensitivities of          the use of other elements of
     development programme, deci-                the system performance to                   information making up a safety
     sions should be based on                    uncertainties. The uncertainties            case, such as complementary,
     appropriate levels of confi-                and the potential for reducing              qualitative lines of evidence,
     dence about the achievability               them in subsequent develop-                 will also contribute to the
     of long-term safety, with the               ment phases should therefore                uncertainty management

     * Dr. Björn Dverstorp, of the Swedish Institute for Radiation Protection (SSI), was the Chair of the workshop on Management
     of Uncertainty in Safety Cases and the Role of Risk. Dr. Abe Van Luik, of the US Department of Energy (US DOE) was Chair of
     the NEA Integration Group for the Safety Case (IGSC) from 2000 to 2004. Dr. Hiroyuki Umeki, of the Japan Nuclear Cycle
     Development Institute (JNC) has been Chair of the IGSC since the end of 2004. Ms. Sylvie Voinis, of the NEA Secretariat, is in
     charge of the IGSC Scientific Secretariat. Dr. Roger Wilmot is from Galson Sciences.

14                                                                                            NEA updates, NEA News 2005 – No. 23.1
process (NEA, 2004). Uncer-                  how uncertainties should be                     be confidence in the analy-
tainty management consists of                treated in a safety case:                       sis of performance and asso-
understanding the potential                  ● The safety case informs                       ciated uncertainties.
implications of uncertainties,                  decisions at each stage of a
and in some cases planning to                   step-by-step decision-making               The 2004 workshop on
minimise these potential effects                process. There is therefore a
through the site selection                                                                 the management of
                                                trend towards safety cases
process and design adapta-                                                                 uncertainty
                                                providing a statement on
tions. Other issues, including                  why there is confidence in                    To build upon the lessons
policy, social context, availabil-              the results presented, and                 learnt from the earlier activities
ity of resources and decision-                  on the sufficiency of the                  and workshops and to provide
making timetables, also affect                  safety case for the decision               a forum for a focused discus-
choices.                                        at hand. With that perspec-                sion on the handling of uncer-
   The presentation of a safety                 tive, such a statement                     tainty and risk, the Integration
case will place most emphasis                   should acknowledge the                     Group for the Safety Case
on the evaluation and argu-                     existing uncertainties, their              (IGSC) decided to organise a
mentation of the expected                       significance at the present                workshop on the Management
performance of a waste man-                     stage of assessment, and the               of Uncertainty in Safety Cases
agement facility. However,                      future steps required to                   and the Role of Risk. The work-
making the case for the                         reduce uncertainty.                        shop was held in Stockholm
expected performance requires                ● Uncertainties should be
                                                                                           on 2-4 February 2004 and
an illustration of performance                  recognised as an inevitable                hosted by the Swedish Institute
in its uncertainty context while                aspect of radioactive waste                for Radiation Protection (SSI).
taking into account the current                 management systems, and                    The overall aim of the work-
stage of system development.                    these uncertainties will                   shop was to create a platform
                                                increase with the timescale                in order to better understand
                                                considered.                                different approaches to manag-
Previous NEA activities
                                                                                           ing uncertainty in post-closure
on uncertainty issues                        ● Uncertainties should be
                                                                                           safety cases and regulatory
                                                treated explicitly, and a sys-             approaches in different
   One of the earliest NEA
                                                tematic approach will aid                  national waste management
activities on uncertainty issues
                                                understanding.                             programmes. The aims of the
was a meeting in Seattle in
1987 at which the importance                 ● A combination of deter-                     workshop were:
of treating uncertainties in                    ministic and probabilistic                 ● to identify common elements
assessments of post-closure                     approaches may be appro-                      in different approaches to
performance of disposal facili-                 priate. Decision making is                    managing uncertainty;
ties was highlighted. This early                not based on a numerical
                                                                                           ● to discuss different approaches
recognition of the issue was                    value for uncertainty, and
                                                there is a need to clarify the                to setting regulatory standards
developed through a series of                                                                 for regulatory review;
NEA meetings and workshops                      role of each approach in the
                                                safety case.                               ● to     facilitate information
in subsequent years. The
Probabilistic Safety Analysis                ● A range of scenarios needs
                                                                                              exchange and to promote
Group (PSAG) played an                          to be considered in order to                  discussion on different techni-
important role in encouraging                   explore uncertainties. The                    cal approaches to the manage-
debate of different approaches,                 issue of human intrusion has                  ment and characterisation of
and also organised a series of                  a special place within the                    uncertainty and on the role of
                                                scenarios considered.                         risk;
code inter-comparison exer-
cises (NEA, 1997a). Other key                                                              ● to explore the merits of alter-
                                             ● A range of arguments is
activities include initiatives by                                                             native approaches to risk-
                                                important in treating uncer-
the Integrated Performance                                                                    informed decision making;
                                                tainties and developing a
Assessment Group (IPAG)                                                                       and
                                                safety case. In particular a
(NEA, 1997b, 2002a); work-                      mixture of quantitative and                ● to identify the potential for fur-
shops on confidence building                    qualitative arguments will                    ther developments of methods
(NEA, 1999) and the handling                    engender confidence in                        or strategies to support the
of timescales (NEA, 2002b);                     both the provider and the                     management of uncertainties.
and the ongoing development                     reviewer. Overall, the safety                 The NEA prepared a synthe-
of the Safety Case Brochure                     case can best fulfil the                   sis of the workshop, which was
(NEA, 2004).                                    requirements of decision                   published in proceedings (NEA,
   These activities have led to                 making by including a state-               2005). The main findings may
some broad conclusions about                    ment on why there should                   be summarised as follows.

Management of uncertainty in safety cases and the role of risk, NEA News 2005 – No. 23.1                                          15
What is risk?                       analysis”, refers to the meth-      the importance of treating
        Diversity definitions are        ods used in the field of both       uncertainty whatever the regu-
     sometimes adopted for terms         nuclear and non-nuclear indus-      latory end-point. Although
     such as “risk”. The word “risk”     try, to identify potential          expectations regarding the
     could be interpreted as having      sources of danger and rank          evaluation and presentation of
     different meanings for different    them in terms of importance.        uncertainties do vary depend-
                                            The following additional         ing on the end-point used,
                                         definitions were suggested:         there are similar expectations
                                                                             regarding the use of support-
                                         ● risk-based approach: “regu-
                                                                             ing arguments, transparency
                                            latory decision making
                                                                             and traceability, justification of
                                            solely based on the numeri-
                                                                             assumptions and other qualita-
                                            cal results of a risk assess-
                                                                             tive aspects of treating uncer-
                                            ment”;
                                                                             tainties, whether the end-point
                                         ● risk-informed approach:
                                                                             is dose or risk.
                                            “risk insights considered
                                                                                Regulators see interactions
                                            with other factors”;
                                                                             with implementers ahead of
                                         ● deterministic approach: “the
                                                                             the licensing process as an
                                            use of fixed values in mod-      opportunity to identify critical
                                            elling for characterisation of   issues, to resolve differences in
                                            uncertainty”;                    approach and to reduce the
                                         ● probabilistic approach:           resources and time required for
                                            “characterisation of uncer-      review of a license application.
     end-users (nuclear power               tainty with probabilistic dis-   Overall, regulatory expecta-
     plants, waste management               tribution functions as input     tions are for safety cases that
     organisations...), and a set of        to modelling”;                   are risk-informed rather than
     characteristics for which alter-    ● risk: “consequence times          risk-based.
     native approaches or view-             probability of occurrence”.
     points exist: objectivist/realist                                       Assessment of uncertainty
                                            A general observation from
     (regards risks as real) vs. con-                                        and risk
                                         the workshop discussions was
     structionist (regards risk as a
                                         that differences in the interpre-      All assessments must address
     mental construct); quantitative
                                         tation of key terms and con-        the components of the risk
     vs. qualitative; and different
                                         cepts may hamper a good             triplet: What can happen?
     mathematical formulations [e.g.
                                         discussion and understanding        What are the consequences?
     probability times consequence;
                                         of the national regulatory and      and What is the likelihood?
     expected (negative) utility; and
                                         assessment approaches. Hence,       Approaches differ in the extent
     open formulations]. For techni-
                                         it was concluded that clear def-    to which probabilities are
     cal experts, “risk” often means
                                         initions, when making a safety      assigned explicitly (e.g., as
     the product of probability and
                                         case, are key to a successful       probability density functions)
     consequence. In public discus-
                                         dialogue with various stake-        or implicitly (e.g., through the
     sion risk may mean only the
                                         holders.                            selection of likely and less
     probability (of a negative con-
     sequence), although the con-                                            likely scenarios). The explicit
     sequences may be of most            Regulatory approaches               use of probabilities to charac-
     interest to the public. Both           There is no simple distinc-      terise uncertainty is not
     “constructed” (perceived) risk      tion to be made between regu-       restricted to calculations of
     and “realist” risk do matter and    lations with risk or dose           risk. Overall, there is a role for
     the public may be concerned         criteria. In particular, regula-    deterministic and probabilistic
     about both. As an example, in       tions requiring the calculation     calculations in both risk- and
     Andra’s usage, “risk” is defined    of dose for the normal or           non-risk-oriented assessments.
     as the characterisation of a        expected evolution may                 A key difference between
     potential danger in terms of        require an assessment of risk       the alternative approaches to
     both probability and impor-         for less likely scenarios. Also,    the treatment of uncertainty is
     tance. The product of both is       regulatory guidance requiring       the extent to which uncertain-
     rarely considered. Therefore,       the calculation of risk for natu-   ties are aggregated or disaggre-
     such expressions as “the prob-      ral events and processes may        gated. Disaggregated analyses
     ability of a risk” or “the impor-   not require an assessment of        are of value for developing
     tance of a risk” refer to two       probabilities for human intru-      detailed system understanding
     independent variables. “Risk”,      sion scenarios. Regulators have     and providing information for
     in such expressions as “risk        similar expectations regarding      design choices and research

16                                                                           NEA updates, NEA News 2005 – No. 23.1
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