NEA News 2005 - No. 23.1 - Nuclear Energy Agency
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Cov-NEA News 23 1 1/07/05 14:56 Page 1 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 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).
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
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
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
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
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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