REGDOC 2 3 3 Periodic Safety Reviews

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Operating Performance Periodic Safety Reviews,Regulatory Document REGDOC 2 3 3. Canadian Nuclear Safety Commission CNSC 2015,PWGSC catalogue number CC172 120 2015E PDF. ISBN 978 1 100 25942 0, Extracts from this document may be reproduced for individual use without permission provided the. source is fully acknowledged However reproduction in whole or in part for purposes of resale or. redistribution requires prior written permission from the Canadian Nuclear Safety Commission. galement publi en fran ais sous le titre Bilans p riodiques de la s ret. Document availability, This document can be viewed on the CNSC website at nuclearsafety gc ca To request a copy of the. document in English or French please contact,Canadian Nuclear Safety Commission.
280 Slater Street,P O Box 1046 Station B,Ottawa Ontario K1P 5S9. Tel 613 995 5894 or 1 800 668 5284 in Canada only,Facsimile 613 995 5086. Email info cnsc ccsn gc ca,Website nuclearsafety gc ca. Facebook facebook com CanadianNuclearSafetyCommission. YouTube youtube com cnscccsn,Publishing history,April 2015 Version 1 0. April 2015 REGDOC 2 3 3 Periodic Safety Reviews, This regulatory document is part of the CNSC s operating performance series of regulatory documents.
which also covers commissioning construction and severe accident management The full list of. regulatory document series is included at the end of this document and can also be found on the CNSC s. Regulatory document REGDOC 2 3 3 Periodic Safety Reviews sets out the CNSC s requirements for the. conduct of a periodic safety review PSR for a nuclear power plant NPP It is consistent with the. International Atomic Energy Agency s Safety Standards Series Specific Safety Guide No SSG 25. Periodic Safety Review for Nuclear Power Plants 1 REGDOC 2 3 3 supersedes RD 360 Life Extension. of Nuclear Power Plants published in February 2008. A PSR involves an assessment of the current state of the plant and its performance to determine the extent. to which it conforms to applicable modern codes standards and practices and to identify any factors that. would limit safe long term operation, Operating experience in Canada and around the world new knowledge from research and development. activities and advances in technology are taken into account This enables the determination of. reasonable and practical improvements that should be made to structures systems and components and to. existing programs to ensure the safety of the facility to a level approaching that of modern nuclear power. plants and to ensure continued safe operation A PSR is a rigorous safety assessment that is. complementary to and does not replace routine and non routine regulatory reviews inspections. mid term reports event reporting and investigations or other CNSC compliance and verification. activities, Conduct of a PSR is intended to be a requirement that can be aligned with licence renewals and form part. of the licensing basis for a regulated facility or activity within the scope of this document It is intended. for inclusion in licences either as part of the conditions and safety and control measures in a licence or as. part of the safety and control measures to be described in a licence application and the documents needed. to support that application, For existing nuclear power plants the requirements contained in this document do not apply unless they. have been included in whole or in part in the licence or licensing basis. An applicant or licensee may put forward a case to demonstrate that the intent of a requirement is. addressed by other means and demonstrated with supportable evidence. The requirements and guidance in this document are consistent with modern national and international. practices addressing issues and elements that control and enhance nuclear safety. Guidance contained in this document exists to inform the applicant to elaborate further on requirements. or to provide direction to licensees and applicants on how to meet requirements It also provides more. information about how CNSC staff evaluate specific problems or data during their review of licence. applications Licensees are expected to review and consider guidance should they choose not to follow it. they should explain how their chosen alternate approach meets regulatory requirements. A graded approach commensurate with risk may be defined and used when applying the requirements. and guidance contained in this regulatory document The use of a graded approach is not a relaxation of. requirements With a graded approach the application of requirements is commensurate with the risks. and particular characteristics of the facility or activity. April 2015 REGDOC 2 3 3 Periodic Safety Reviews, Important note Where referenced in a licence either directly or indirectly such as through licensee. referenced documents this document is part of the licensing basis for a regulated facility or activity. The licensing basis sets the boundary conditions for acceptable performance at a regulated facility or. activity and establishes the basis for the CNSC s compliance program for that regulated facility or. Where this document is part of the licensing basis the word shall is used to express a requirement to. be satisfied by the licensee or licence applicant Should is used to express guidance or that which is. advised May is used to express an option or that which is advised or permissible within the limits of. this regulatory document Can is used to express possibility or capability. Nothing contained in this document is to be construed as relieving any licensee from any other. pertinent requirements It is the licensee s responsibility to identify and comply with all applicable. regulations and licence conditions,April 2015 REGDOC 2 3 3 Periodic Safety Reviews.
Table of Contents,1 Introduction 1,1 1 Purpose 1,1 2 Scope 1. 1 3 Relevant regulations 1,1 4 National and international standards 2. 2 General Requirements 2,3 Periodic Safety Review Basis Document 3. 3 1 Current licensing basis 3, 3 2 Proposed operating strategy of the nuclear power plant 3. 3 3 Scope of the periodic safety review 4, 3 4 Methodology for the performance of the periodic safety review 5.
3 5 Applicable modern codes standards and practices 5. 3 6 Methodology for the identification dispositioning and tracking of gaps 6. 3 7 Methodology for the global assessment 6,3 8 Periodic safety review governance 7. 4 Performance of the Periodic Safety Review 7,4 1 Safety factor reports 7. 5 Global Assessment Report 8,6 Integrated Implementation Plan 9. Appendix A Safety Factor for Radiation Protection 10. A 1 Objective 10,A 2 Scope and tasks 10,A 3 Methodology 10. A 3 1 Review of the reactor design features for radiation protection 11. A 3 2 Review of radiation protection equipment and instrumentation for radiation. monitoring 11, A 3 3 Review of radiation protection aspects for nuclear emergencies 11.
A 3 4 Review of radiation protection related to operating experience 11. Appendix B CNSC Safety and Control Areas 12,April 2015 REGDOC 2 3 3 Periodic Safety Reviews. Glossary 13,References 15,Additional Information 16. April 2015 REGDOC 2 3 3 Periodic Safety Reviews,Periodic Safety Reviews. 1 Introduction, REGDOC 2 3 3 Periodic Safety Reviews sets out the CNSC s requirements for the conduct of a. periodic safety review PSR A PSR is a comprehensive evaluation of the design condition and. operation of a nuclear power plant NPP plant It is an effective way to obtain an overall view of. actual plant safety and the quality of the safety documentation and to determine reasonable and. practical improvements to ensure safety until the next PSR or where appropriate until the end of. commercial operation, PSRs have been effective in achieving improvements in safety Adopting PSRs in support of licence.
renewal will ensure the continued improvement of NPP safety Past experience with life extension. projects gives the CNSC and the Canadian nuclear industry a large degree of familiarity with the. PSR process As such the application of a PSR in Canada represents an evolution of a current. practice as opposed to the adoption of a new one,1 1 Purpose. This regulatory document sets out the CNSC s requirements for the conduct of a PSR Guidance is. also provided on how these requirements may be met. This document is intended for nuclear power plants However it can be used by other nuclear. facilities applying a graded approach,1 3 Relevant regulations. The following provisions of the Nuclear Safety and Control Act NSCA and regulations made under. the NSCA that are relevant to this regulatory document. 1 Subsection 24 4 of the NSCA states that No licence shall be issued renewed amended or. replaced and no authorization to transfer one given unless in the opinion of the Commission. the applicant a is qualified to carry on the activity that the licence will authorize the licensee to. carry on and b will in carrying on that activity make adequate provision for the protection of. the environment the health and safety of persons and the maintenance of national security and. measures required to implement international obligations to which Canada has agreed. 2 Subsection 24 5 of the NSCA states that A licence may contain any term or condition that the. Commission considers necessary for the purposes of this Act. 3 Section 3 of the General Nuclear Safety and Control Regulations states the general licence. application requirements, 4 Paragraphs 12 1 c f and i of the General Nuclear Safety and Control Regulations state that. Every licensee shall, c take all reasonable precautions to protect the environment and the health and safety of. persons and to maintain security of nuclear facilities and of nuclear substances. f take all reasonable precautions to control the release of radioactive nuclear substances or. hazardous substances within the site of the licensed activity and into the environment as a result. of the licensed activity, i take all necessary measures to facilitate Canada s compliance with any applicable safeguards.
April 2015 REGDOC 2 3 3 Periodic Safety Reviews, 5 Sections 3 and 6 of the Class I Nuclear Facilities Regulations state the general licence. application requirements specific to Class I nuclear facilities and the information required to. apply for a Class I nuclear facility operating licence. 1 4 National and international standards, Key principles and elements used in developing this regulatory document are consistent with. national and international standards guides and practices In particular this regulatory document is. consistent with the International Atomic Energy Agency s IAEA Safety Standards Series Specific. Safety Guide No SSG 25 Periodic Safety Review for Nuclear Power Plants SSG 25 1. 2 General Requirements, The licensee shall conduct a PSR in accordance with this regulatory document for the period until. the next PSR or if applicable until the end of commercial operation of the plant The PSR shall be. conducted according to the following four phases,1 preparation of a PSR basis document. 2 conduct of the safety factors reviews and identification of findings. 3 analysis of the findings and their integral impact on the NPP s safety global assessment. 4 preparation of a plan of safety improvements integrated implementation plan. The objectives of a PSR are to determine, 1 the extent to which the facility conforms to modern codes standards and practices.
2 the extent to which the licensing basis remains valid for the next licensing period. 3 the adequacy and effectiveness of the programs and the structures systems and components. SSCs in place to ensure plant safety until the next PSR or where appropriate until the end of. commercial operation, 4 the improvements to be implemented to resolve any gaps identified in the review and timelines. for their implementation, The PSR approach is outlined in SSG 25 The complex process of conducting a PSR can be. facilitated by subdividing it into tasks that are identified as safety factors These safety factors are. intended to cover all aspects that are important to the safety of an operating nuclear power plant The. terms safety factor and safety factor reports are an adoption of the SSG 25 terms with the. addition of a safety factor for radiation protection Safety factor reports are discussed further in. sections 3 and 4, The licensee first prepares the PSR basis document which defines the scope and methodology for the. PSR This is then used to conduct the review prepare the safety factor reports and the global. assessment report The results of the PSR are used to establish the corrective actions and safety. improvements to be included in the integrated implementation plan. The documentation submitted to the CNSC includes,1 PSR basis document. 2 reports on the review of each safety factor safety factor reports. 3 global assessment report GAR,4 integrated implementation plan IIP.
April 2015 REGDOC 2 3 3 Periodic Safety Reviews, In accordance with SSG 25 and international practice 10 years is considered an appropriate interval. between PSRs to identify any factors that would limit the NPP s continued safe operation and. determine the extent to which it conforms to applicable modern codes standards and practices The. next PSR interval may deviate from 10 years when it includes the end of commercial operatio. 978 1 100 25942 0 Extracts from this document may be reproduced for individual use without permission provided the source is fully acknowledged

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