IAEA
In GSR Part2 2016 “Leadership and Management for Safety” The IAEA define :
“1.7 The requirements established in this Safety Requirements publication are intended for use in the following ways:
(a) By the registrant or licensee, for establishing and sustaining leadership and management on the part of organizations and managers responsible for facilities and activities5 that give rise to radiation risks6 ;
(b) By the registrant or licensee, to specify to a vendor or supplier of products and equipment, or a contractor for services, and to any other relevant organization, any requirements that must be met by the vendor’s or supplier’s management system**;
(c) By the regulatory body, as part of the basis for the regulation of facilities and activities;
(d) By the regulatory body and other relevant governmental organizations, as a basis for meeting their responsibilities for arrangements7 in relation to leadership and management, in conjunction with the requirements established ….”
“Notes:
5 ‘Facilities’ includes: nuclear facilities; irradiation installations; some mining and raw material processing facilities such as uranium mines; radioactive waste management facilities; and any other places where radioactive material is produced, processed, used, handled, stored or disposed of — or where radiation generators are installed — on such a scale that consideration of protection and safety is required. ‘Activities’ includes: the production, use, import and export of radiation sources for industrial, research and medical purposes; the transport of radioactive material; the decommissioning of facilities; radioactive waste management activities such as the discharge of effluents; and some aspects of the remediation of sites affected by residues from past activities.
6 The term ‘radiation risks’ is defined as:
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Detrimental health effects of exposure to radiation (including the likelihood of such effects occurring);
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Any other safety related risks (including those to the environment) that might arise as a direct consequence of:
● Exposure to radiation;
● The presence of radioactive material (including radioactive waste) or its release to the environment;
● A loss of control over a nuclear reactor core, nuclear chain reaction, radioactive source or any other source of radiation
7 ‘Arrangements’ in this context means an integrated set of infrastructural elements necessary to provide the capability for performing a specified function or task. Such elements may include authorities and responsibilities, organization, coordination, personnel, plans, procedures, facilities, equipment, training and contracts.”
** but in Requirement 11: Management of the supply chain IAEA state:
“The organization shall put in place arrangements with vendors, contractors and suppliers for specifying, monitoring and managing the supply to it of items, products and services that may influence safety.”
4.34. The organization shall have a clear understanding and knowledge of the product or service being supplied12. The organization shall itself retain the competence to specify the scope and standard of a required product or service, and subsequently to assess whether the product or service supplied meets the applicable safety requirements.
4.35. The management system shall include arrangements for qualification, selection, evaluation, procurement, and oversight of the supply chain.
4.36. The organization shall make arrangements for ensuring that suppliers of items, products and services important to safety adhere to safety requirements and meet the organization’s expectations of safe conduct in their delivery.”
“Notes:
11 The supply chain, described as ‘suppliers’, typically includes: designers, vendors, manufacturers and constructors, employers, contractors, subcontractors, and consigners and carriers who supply safety related items. The supply chain can also include other parts of the organization and parent organizations.
12 The capability of the organization to have a clear understanding and knowledge of the product or service to be supplied is sometimes termed an ‘informed customer’ capability.”
IAEA recognise that “Other international standards or national standards8 may be used in addition to the requirements of this Safety Requirements publication.”
“Notes:
8 International standards are, for example, those of the International Organization for Standardization or the European Foundation for Quality Management; national standards are, for example, British standards on Occupational Health and Safety Management or the Nuclear Quality Assurance standards of the United States of America”
IAEA Guidance
The IAEA have not yet published guidance to go with GSR Part 2.
The latest information as at 20 May 2018 was that a Document preparation Profile (DPP) was being put to the standards Committees to allow development of the guidance.
DS513 Proposed Title: Leadership, Management and Culture for Safety
Proposed Action: Revision and merger of two Safety Guides, Application of the Management System for Facilities and Activities IAEA Safety Standards Series No. GS-G-3.1 (2006) and the Management System for Nuclear Installations IAEA Safety Standards Series No. GS-G-3.5 (2009), into one new Safety Guide with additional content, to support Leadership and Management for Safety, IAEA Safety Standards Series No. GSR Part 2 (2016).
A technical meeting is proposed for later in 2018, with a draft for comment Q2 2020 and target publication date of Q4-2022
Over the last few years several workshops and course discussions have identified that there is general confusion around the world in the terminology and questionably different approaches between Management Systems, Quality Assurance and Quality Control. At the end of 2016, IAEA set up a small consultants group to start drafting a TECDOC on QA/QC Activities in Nuclear Power Plants: Lessons Learned and Good Practices.
This TECDOC is primarily intended for non-quality personnel e.g. top / senior management, who determine the business objectives and policies but need to understand the role quality has in delivering those objectives, policies and particularly products (Structures, Systems and Components SSCs) which form Nuclear Power Plants; although also being a prompt for specialists who have to explain the requirements of quality in nuclear safety and manage the activities required to assure safety.
The draft was well underway at the end of 2017 but IAEA issues have meant that no further work has been done upto May 2018.
Update as of 06/08/2018
DS 513 [Leadership, Management and Culture for Safety (revision and merging of GS-G-3.1 and GS-G-3.5)]
At the June Nuclear Safety Standards Committee (NUSSC) meeting Helen Rycroft the project officer made a presentation on intent and programme.
Target audience are the Operating Organizations for facilities and activities, Regulatory bodies, TSOs and government organizations.
• Major themes are
– Management for safety, including graded approach and IMS;
– Leadership for safety;
– Culture for safety;
– The assessment, measurement, assessment and improvement approaches.
DS 513 would supersede / combine the current GS-G-3.1 and GS-G-3.5
The proposal is to establish core or fundamental aspects of Management, Leadership
and Culture for safety which can be applied in a graded approach and with the support of an IMS.
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Chap 1 – Guide on Generic requirements of GSR part 2
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Chap 2 – Leadership and Culture for safety Requits 1, 2, 12
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Chap 3 – Management for safety Requits 3-11
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Chap 4 – Measurement Assessment and Improvement Requits 13, 14
Drafting of DS 513 is scheduled for Summer 2018 – Autumn 2019 with member state consultation / commenting Winter 2019 / Spring 2020 DPP shows target publication Winter 2022.
At the June 2018 NUSSC meeting “participants advised the Secretariat to look how it could interface with other standards organisations such as ISO”.
Document Preparation Profile (DPP) Version 3 Dated 06/06/2018 can be seen at:
DS514 - Draft Safety Guide: Qualification of Items Important to Safety in Nuclear Installations
This is a new safety guide to meet specific safety requirements in SSR 2/1, 2/2, SSR-3, SSR-4 and GSR Part 4
Equipment in scope
̶ Electrical, instrumentation and controls, electromechanical, active
mechanical equipment
̶ Installation features associated with this equipment (e.g. connectors,
penetrations, seals, mounting equipment)
̶ Materials of construction which could affect the performance of this
equipment including containment wall paint and piping insulation
Equipment out of scope
– Piping, structures and other passive components because their
qualification (safety status) is achieved directly by design, construction,
inspection and testing according to applicable codes
Seeking approval of the drafting proposal by Committee on Safety Standards in Nov 2018.
If approved would then need development / drafting etc which could be 3-5 years