ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events

Session 55 Abstracts
4) PROGRESS IN INTERNATIONAL COOPERATION ON REGULATORY OF LEGACY MANAGEMENT:
EXPERIENCE IN NORWEGIAN COOPERATION PROGRAMMES (wP-59399)
Malgorzata Sneve, Norwegian Radiation Protection Authority (Norway)
This paper describes the Norwegian Radiation Protection Authoritys (NRPA) experience in regulatory cooperation projects in
Russia, with special focus on legacy issues. These legacies include many different kinds of objects and activities: obsolete large
waste sources, such as those used in radioisotope thermoelectric generators; remediation of former military sites used for storage
of spent nuclear fuel and radioactive waste; and wastes from uranium mining and ore processing. The objectives of these bi-lateral
cooperation programmes are to promote effective and efficient regulatory supervision, taking into account international recommendations
and good practice in other countries. Specific projects in the program address specific challenges which require practical
local interpretation of ICRP recommendations, the IAEA Basic Safety Standards and other IAEA requirements and guidance
documents. In some cases, new regulatory documentation has been required, as well as new regulatory procedures. In the long term,
the program is intended to lead to an enhanced and enduring safety culture. The positive experience in Russia has encouraged the
Norwegian government to extend the regulatory collaboration programme to countries in central Asia, using experience gained with
Russian regulatory authorities as well as support from Russian Technical Support Organisations. The programmes are evolving into
a regional regulatory support group. Noting this experience, the paper includes suggestions and ideas for how such regional groups
can be effective in addressing common radiation safety objectives while addressing local differences in technical, geographical,
economic and cultural matters in each country...
5) METHODOLOGICAL AND PRACTICAL BASES OF PROVIDING INFORMATION SUPPORT TO
ACTIVITIES ON ENVIRONMENTAL REMEDIATION OF THE SPENT NUCLEAR FUEL AND
RADIOACTIVE WASTE TEMPORARY STORAGE FACILITY IN GREMIKHA (wP-59375)
Dmitry Stepennov, Anatoly P. Varnavin, NRC Kurchatov Institute; Anatoly A. Zakharchev, Rosatom;
Lucien Pillette-Cousin, AREVA TA (Russia/France)
Remediation of a spent nuclear fuel (SNF) and radioactive waste (RW) temporary storage facility is a multifaceted process that
includes a number of stages, such as development of a remediation programme, performance of comprehensive engineering and
radiological survey, development of a remediation design, removal of SNF and RW up to the site cleanup. At any stage of the remediation,
making of justified decisions is ensured by availability and completeness of associated information. Huge amount of information
has to be managed. Therefore an information analysis system (IAS) was developed by the National Research Centre «Kurchatov
Institute» within the framework of the project for environmental remediation of the SNF and RW temporary storage facility
in Gremikha with financial and technical support provided by France (CEA) and the Russian Federation (Rosatom). The IAS
accumulates all information about the project: technical and radiological characteristics of objects/facilities, cartographic information,
documentation, data on the project participants, technologies and equipment involved. The IAS architecture includes the following
functional subsystems: data management, data analytical processing, project management, geoinformation, 3D modeling,
and public information. The IAS allows developers and performers of environmental remediation of the SNF and RW temporary
storage facility in Gremikha to fulfill tasks arising at all stages of the work. The IAS operating experience can be transferred for
use during surveys and remediation of any radiation hazardous facilities.
SESSION 55 — SAFETY AND SECURITY RELATED TO ENVIRONMENTAL
AND NUCLEAR MATERIALS MANAGEMENT (5.11)
1) REMOTE RADIATION AND VISUAL SURVEYS OF THE HOT CELL WASTE VAULT
AND SPENT FUEL TRANSFER ROUTE AT KAZAKHSTANS BN-350 REACTOR (wP-59101)
David Wells, Nuvia Limited, Dorchester,United Kingdom, Collin Knight, Idaho National Laboratory;
Alexander Klepikov, Nuclear Technology Safety Center; Igor Yakovlev, CRT&TD MAEC-Kazatomprom LLP;
Evgeniy Tur, National Nuclear Center of the Republic of Kazakhstan; Andrew Herrick, Nuvia Limited (USA/Kazakhatan/UK)
Kazakhstans BN-350 fast reactor was shut down in 1999 and is in the process of being decommissioned in preparation for Safestore.
A key achievement during 2010 was the removal of the known inventory of spent nuclear fuel (SNF) from the reactor to offsite
secure storage. As a complementary activity, surveys of areas of the fuel discharge route where it was considered possible for
fuel pins or fuel residues to have collected over many years of operation were also arranged to confirm that no significant amounts
of fuel of remained at the plant.
This paper reports on the remote radiation and visual (video and still photograph) surveys undertaken on the following areas
of the spent fuel route:
• The waste storage repository or vault underneath the Post-Irradiation Examination Hot Cell in which non-destructive and
destructive examination of irradiated fuels was undertaken throughout the operating life of the reactor.
• The fuel transfer and washing cells within which irradiated fuel sub-assemblies were processed and residual sodium
coolant removed.
• The fuel storage ponds.
Man access to several areas (particularly the waste vault) was not possible due to very high radiation levels from stored ??active
wastes or residual contamination and in these cases specially engineered remote camera and detector deployment systems
were developed and used. In other areas, such as the ponds, limited man access was possible under prepared and controlled conditions.
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