DS397 Saf Use Mod RRs with NUSSC comments 18-06-2010

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Storage9.10. If the irradiated equipment of the dismantled experiment, facility or system is to bestored on site, the volume and the characteristics including the measured or estimatedactivities of the materials to be stored should be evaluated and safe storage should bedemonstrated.10. SAFETY ASPECTS OF OUT-OF-REACTOR-CORE INSTALLATIONS10.1. The group of out-of-reactor core installations includes two categories: those whichutilize the radiation produced by the reactor but which are outside the reactor (biological)shielding (e.g. a neutron spectrometer), and those which are at or near the reactor and whichdo not utilize the radiation produced by the reactor, but which constitute a potential hazard(e.g. a cryostat for the generation of liquid nitrogen).10.2. Both groups should be subjected to the categorization process as described in paras3.7–3.25.10.3. For the out-of-reactor core installations which constitute a potential hazard in additiona “conventional” safety impact, analyses should be performed, identifying the potentialhazards and the safety provisions to be implemented to reduce the hazards to the extentpossible.10.4. In addition to the review by the reactor safety committee, if required, the safetyanalysis should be reviewed according to management system procedures by appropriatespecialists, e.g. in the field of occupational hazards, chemical hazards, electrical hazards, etc,10.5. The reactor manager should approve the proposal, including the safety analysis forimplementation. Based on its safety significance, (i.e. major, significant) the proposal shouldbe submitted to the reactor safety committee and to the regulatory body for review andapproval of the analysis, as appropriate.38
REFERENCES[1] EUROPEAN ATOMIC ENERGY COMMUNITY, FOOD AND AGRICULTUREORGANIZATION OF THE UNITED NATIONS, INTERNATIONAL ATOMICENERGY AGENCY, INTERNATIONAL LABOUR ORGANIZATION,INTERNATIONAL MARITIME ORGANIZATION, OECD NUCLEAR ENERGYAGENCY, PAN AMERICAN HEALTH ORGANIZATION, UNITED NATIONSENVIRONMENT PROGRAMME, WORLD HEALTH ORGANIZATION,Fundamental Safety Principles: Safety Fundamentals, IAEA Safety Standards SeriesNo. SF-1, IAEA, Vienna (2006).[2] INTERNATIONAL ATOMIC ENERGY AGENCY, Safety of Research Reactors,IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005).[3] INTERNATIONAL ATOMIC ENERGY AGENCY, The Use of a Graded Approach inthe Application of the Safety Requirements for Research Reactors, IAEA SafetyStandards Series, IAEA, Vienna (in preparation). [[DS 351]][4] INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Assessment of ResearchReactors and Preparation and Content of the Safety Analysis Report, IAEA SafetyStandards Series, IAEA, Vienna (in preparation). [[DS 396]][5] INTERNATIONAL ATOMIC ENERGY AGENCY, Review and Assessment ofNuclear Facilities by the Regulatory Body, IAEA Safety Standards Series No. GS-G-1.2, IAEA, Vienna (2002).[6] INTERNATIONAL ATOMIC ENERGY AGENCY, Commissioning of ResearchReactors, IAEA Safety Standards Series No. NS-G-4.1, IAEA, Vienna (2006).[7] INTERNATIONAL ATOMIC ENERGY AGENCY, Radiation Protection andRadioactive Waste Management in the Operation of Research Reactors, IAEA Safetyreport Series NS-G-4.6, IAEA, Vienna (2008).[8] INTERNATIONAL ATOMIC ENERGY AGENCY, IAEA Safety Glossary:Terminology Used In Nuclear Safety and Radiation Protection (2007 Edition), IAEA,Vienna (2007).39
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Page 7 and 8: 1. INTRODUCTIONBACKGROUND1.1. This
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DS397 Saf Use Mod RRs with NUSSC comments 18-06-2010

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