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Development of NPP Safety Regulations in Pakistan ” Application Set

Development of NPP Safety Regulations in Pakistan ” Application Set. CONTENTS. PNRA regulatory approach Development process of PNRA regulations and regulatory guides Applicability and use of IAEA safety standards and standards from other countries

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Development of NPP Safety Regulations in Pakistan ” Application Set

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  1. Development of NPP Safety Regulations in Pakistan”Application Set

  2. CONTENTS • PNRA regulatory approach • Development process of PNRA regulations and regulatory guides • Applicability and use of IAEA safety standards and standards from other countries • Prioritization for development of safety regulations • Involvement of interested parties • Use of external technical support

  3. PNRA REGULATORY APPROACH • Following its establishment in 2001, as an independent regulatory body, PNRA developed its regulatory framework by adapting/adopting the IAEA safety standards as national regulations. • PNRA linked regulations to IAEA safety guides and USNRC regulatory guides which further link down to industrial codes and standards with specific acceptance criteria. • PNRA offers full flexibility to the licensee to meet the objectives specified in PNRA regulations. • The licensee defines a list of codes and standards which is agreed upon by PNRA and become basis for a specific authorization. • PNRA regulations are on the whole performance based but also include some prescriptive requirements based on NRC regulations and regulatory guides.

  4. MODEL OF PNRA REGULATORY FRAMEWORK In the form of LAW Ordinance Administrative Administrative Regulations defines regulatory processes i.e. Licensing process, review and Assessment process, enforcement etc. Regulations Technical Technical Regulations covers technical aspects i.e. Design requirements, operating requirements, QA requirements, Siting details, etc. Connected to Industrial Codes and Standards Regulatory Guides Connected to Needs to be approved by PNRA IEEE ASME RCC

  5. SPECIFIC EXAMPLE • PNRA regulations PAK/911 require the licensee to perform probabilistic safety analysis of the plant in order meet the following safety targets: • CDF shall be less than 10-5 per reactor year, • Frequency for radioactivity release shall be less than 10-6 per reactor year. • Although PNRA provides specific acceptance criteria in terms PSA targets/goals, licensee has the flexibility to adopt any methodology to conduct the PSA to meet these goals. • The licensee proposed methodology of conducting full power PSA as per recommendations of IAEA SG 50-P-4 which was accepted and applied during the licensing process. • In this way PNRA approach provided performance objective as well as prescriptive detail. • The regulatory approach is, therefore, mixed i.e. largely performance based complemented by prescriptive approach.

  6. DEVELOPMENT PROCESS OF PNRA REGULATIONS PNRA REGULATORY FRAMEWORK • The pyramid depicts the regulatory framework of PNRA. • At the highest level is the PNRA Ordinance. • Second tier in the regulatory pyramid are PNRA Regulations. Compliance with the PNRA Regulations is mandatory for the licensees. • Third level consists of regulatory guides, which are non-mandatory and provide acceptable methods for meeting the requirements of regulations.

  7. DEVELOPMENT PROCESS OF PNRA REGULATIONS • Each set of regulations undergoes extensive internal review at different levels within the organization and the opinions of all stakeholders, including licensees, the government, and the general public, is actively sought and incorporated. • The entire process of developing a regulation, depicted in the flow chart below takes around 3 years.

  8. DEVELOPMENT PROCESS OF PNRA REGULATIONS Step-1 (Development of a Document Preparation profile (DPP)) • Any of the Directorates of PNRA may identify the need for the development of Regulations with the submission of a Document Preparation Profile (DPP). • The need for development of new regulations or revision of existing regulations may arise from any of the following: • Obligations of the PNRA Ordinance. • Obligations of international conventions. • Feedback of regulatory/licensing experience. • International practice and experience. • DPP is reviewed by Policy and Procedures Directorate (PPD) of PNRA and sent for obtaining approval of Director Generals of PNRA.

  9. DEVELOPMENT PROCESS OF PNRA REGULATIONS Step-2 (Preparation of Draft-1) • After the approval of DPP, PPD requests the originating Directorate to submit draft-1 of the Regulations within a period of three months. Step-3 (Review by PPD) • PPD reviews Draft-1 to check the correctness of the technical information and its legality under the existing regulatory framework on the basis of the relevant documents • PPD generates Draft-2 of the Regulations on the basis of its in consultation with the originating Directorate. Step-4 (Internal Review within PNRA) • Draft-2 is reviewed by all technical Directorates within PNRA. Finalized comments are incorporated by PPD to generate Draft-3 of Regulations.

  10. DEVELOPMENT PROCESS OF PNRA REGULATIONS Step-5 (Review by Taskforce) • Internal Task force is formulated for detailed clause-by-clause review of Draft-3. • The taskforce generally comprises of the following personnel: • Representatives of PPD, • Representatives of originating Directorate. • Two to three relevant technical professionals as subject specialists. • The comments offered by the task force are incorporated by PPD resulting in Draft-4.

  11. DEVELOPMENT PROCESS OF PNRA REGULATIONS Step-6 (Review by All Director Generals) • Draft-4 is circulated among all DGs for comments. • Comments by the DGs are incorporated by PPD in consultation with the originating Directorate resulting in Draft-5. Step-7 (Review by Stakeholders) • Draft-5 is sent to the relevant licensees and placed on the web page for information of all the stakeholders. • The comments received from the licensees and other stakeholders are incorporated after conducting meetings with the licensees resulting in Draft-6.

  12. DEVELOPMENT PROCESS OF PNRA REGULATIONS Step-8 (Review by Authority part time Members) • Draft-6 is circulated among part time Members of the Authority. • The comments offered by part time members are evaluated by PPD and incorporated to formulate Draft-7. Step-9 (Approval by Authority) • Draft-7 is sent to the Secretary of Authority for presenting it in the Authority’s meeting for final approval. Step-10 (Gazette Notification) • After approval of Draft-7 of the Regulations by the Authority, PPD carries out the process of its notification in the official gazette of Pakistan

  13. DEVELOPMENT PROCESS OF PNRA REGULATIONS The regulatory guides are developed with the view to facilitate the licensee in understanding the requirements of national regulations and provide guidance for their implementation that is non-mandatory. The following guides have been developed by PNRA. • Format and Contents of Application for Modifications in Technical Specifications and Operating Policies and Principles of NPP. • Format and Content of Application for Design Modification in a NPP. • Probabilistic Safety Assessment of Nuclear Power Plant-Level 1. • Dosage and Distribution of Potassium Iodide Tablets (A Thyroid Blocking Agent) In Radiation Emergencies. • Transport of Radioactive Material by road in Pakistan. • Guidance for the Users of I-131 in Nuclear Medicine Centers

  14. APPLICABILITY AND USE OF IAEA SAFETY STANDARDS • In exercise of the powers conferred by section 16(2)(a) of the PNRA Ordinance, PNRA may adopt or adapt such Regulations for nuclear safety and radiation protection as, in its opinion, may be necessary. • So far PNRA has adopted the IAEA Fundamental Safety Principles (SF-1) and IAEA regulations on transport of radioactive material (TSR-1, 2003) and rest of the regulations are generally based on adaptation of IAEA Safety Standards • PNRA since its inception gained tremendous benefit from the use of IAEA safety standards. • Owing to performance based and objective oriented approach of IAEA Safety Standards these provide flexibility in application

  15. APPLICABILITY AND USE OF IAEA SAFETY STANDARDS Nuclear Safety • PNRA regulations for the safety of nuclear power plants design (PAK/911) are based on IAEA safety requirements NS-R-1 (2000) with some additional requirements. • Currently PAK/911 is undergoing revision process mainly on the basis of IAEA SSR 2/1 “Safety of Nuclear Power Plants: Design”, 2016 and lessons learned from Fukushima accident. • Regulations for Safety of NPP operation (PAK/913) are based on IAEA safety requirements NS-R-2 (2000) with some additional requirements. • Planned revision is in progress mainly on the basis of IAEA SSR 2/2 “Safety of Nuclear Power Plants: Operation”, 2016 and Fukushima experience. • Regulations on the Safety of Nuclear Installations- Site Evaluation (PAK/910) is mainly based on IAEA NS-R-3 (2003) with some additional requirements.

  16. APPLICABILITY AND USE OF IAEA SAFETY STANDARDS Nuclear Safety • Regulations on the Safety of Nuclear Installations- Site Evaluation (PAK/910) is mainly based on IAEA NS-R-3 (2003) with some additional requirements. • These requirements are from USNRC regulations related to criteria for determination of exclusion area, low population zone and population centred distances. • Quality Assurance regulations (PAK/912) are also based upon IAEA 50-C-Q (1996). • Regulations on “Safety of Nuclear Research Reactor Operation (PAK/923)”, are based on IAEA NS-R-4 with the additional requirements on criteria for the licensing of reactor operating personnel.

  17. APPLICABILITY AND USE OF IAEA SAFETY STANDARDS Radiation Safety and Emergency Preparedness • PNRA regulations on Radiation Protection (PAK/904) are mainly based upon IAEA Safety Series No. 115, Basic Safety Standards (BSS) of 1996 which is currently being revised mainly on the basis of GSR Part 3. • PNRA regulations for Management of a Nuclear or Radiological Emergency (PAK/914), published in 2008, were mainly based on IAEA GS-R-2 are being currently revised on the basis of GSR Part 7. • The implementation of these requirements is regularly verified by PNRA before and after commencement of operation of facilities. • Pakistan has categorized facilities/activities in five hazard categories according to IAEA recommendations and emergency preparedness arrangements are made on the basis of assessment of hazards. • The regulatory guides (e.g. GS-G-2.1, 50-SG-06, 50-SG-G6 etc.) are used for evaluation of emergency preparedness and response arrangements at facilities.

  18. APPLICABILITY AND USE OF IAEA SAFETY STANDARDS Radioactive Waste, Transport Safety and Decommissioning • PNRA regulations on Radioactive Waste Management (PAK/915) are mainly based on WS-R-2. • Under these regulations, PNRA is also developing a regulatory guide for the management of Radioactive Waste from Medicine, Industry, Agriculture, Research and education on the basis of WS-G-2.7. • PNRA adopted TS-R-1 (2003 edition) as national regulations for ensuring safe transport of radioactive material in Pakistan which is currently being planned to be revised mainly on the basis of SSR-6 (2016). • The regulations on decommissioning under development are generally based on WS-R-5 and GSR Part-6.

  19. APPLICABILITY AND USE OF IAEA SAFETY STANDARDS Physical Protection and Nuclear Security PNRA is developing regulations entitled “Physical Protection of Nuclear Material and Nuclear Facilities” which are mainly based upon the latest revision of INFCIRC/225. In future, PNRA is planning to develop guidance documents using IAEA nuclear security implementing guides. Implementation of Management System at PNRA Integrated Management system mainly based on IAEA GS-R-3 is being implemented in the organization In this regard, a management system manual has been established on the basis of GS-R-3 and the IAEA safety guide GS-G-3.1 “Application of the Management System for Facilities and Activities”.

  20. APPLICABILITY OF STANDARDS OF OTHER STATE’S INCLUDING VENDOR • Design and safety criteria are mainly based on USNRC10 CFR 50, RGs and industrial standards such as ASME, ACI, IEEE etc. • Safety analysis reports (SARs) are submitted by the licensee according to NRC Regulatory Guide 1.70 and reviewed by using the NUREG-0800 (SRP). • However, the design of the plant and safety analysis reports areensured to conform to the IAEA Safety Standards • In case of the use of Chinese industrial standards the applicant had to demonstrate its equivalence with relevant US standard • In establishing design requirements, PNRA adopted IAEA NS-R-1 of 2000 complemented by some requirements from 10CFR 50 of NRC. • Since the Chinese regulatory body (NNSA) also adopted IAEA safety standards, the vendor country had no real difficulty in getting authorization of the design

  21. PRIORITIZATION FOR DEVELOPMENT OF SAFETY REGULATIONS • Following the establishment of PNRA, the first task was to develop requirements for granting different authorizations to C-2 during its licensing process. • Priority was assigned on need basis during the contract negotiations of C-2 and the regulations for the licensing of nuclear power plants were issued in 2001. • Afterwards, detail technical requirements for C-2 design were required and consequently the regulations for the safety of NPP design (PAK/911) were issued. • These regulations was issued based on the IAEA safety standard on design (NS-R-1), the licensing experience of C-1 and NRC regulations • PNRA developed its third regulations on nuclear power plant Quality Assurance- PAK/912 on need basis for the review of the application for the construction license of C-2 based on IAEA 50-C-QA.

  22. PRIORITIZATION FOR DEVELOPMENT OF SAFETY REGULATIONS • The regulatory review of the application for the construction licence of C-2 was reviewed against PNRA regulations on Safety of NPP Design (PAK/911) and regulations on Safety of NPP Quality Assurance (PAK/912) along with applicable USNRC regulations/guides and IAEA safety standards. • Format and Content of safety analysis report was agreed to be followed as per the USNRC regulatory guide RG 1.70. • PNRA uses standard review plan (SRP) of USNRC to review the safety analysis reports. • Most of the following regulations were also issued on need basis e.g. the regulations on licensing fee (PAK/900), regulations for licensing of NPP safety class equipment manufacturing (PAK/907) and Enforcement Regulations.

  23. INVOLVEMENT OF INTERESTED PARTIES IN DEVELOPING SAFETY REGULATIONS • PNRA gives prime importance to involve all the stakeholders in the development process of safety regulations • During the development process, the draft regulations are sent to the relevant licensees and other interested parties for comments • The draft is also placed on website for information of general public for a period of four months • Comments received are evaluated and discussed with stakeholders by organizing meetings with stakeholders for acquiring consensus • Comments received from the public are also evaluated and incorporated as far as practicable • The finalized draft is then sent to the part time external Members of the authority for reviewwhich represent different fields and are also represented by the licensee

  24. USE OF EXTERNAL TECHNICAL SUPPORT IN DEVELOPING SAFETY REGULATIONS • Most of regulations of PNRA are generally based on IAEA safety standards, • The process for development of safety regulations have not been so stringent. • As such, the involvement of External Technical support in drafting or review of safety regulations was not considered. • However, the regulations were reviewed by TSO formed within PNRA which is functionally and financially independent. • In some cases, the TSO was requested to conduct independent analysis of certain safety criteria before their inclusion or adaptation in safety regulations. • Through establishment of internal TSO PNRA achieved the objective of self reliance and independent capability in different technical areas • The process ensured obtaining an independent input throughout the development process of safety regulations

  25. THANK YOU

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