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Pakistan ANSN Links
Pakistan

Instruction

Welcome to the Pakistan web site for the Asian Nuclear Safety Network (ANSN).

The objective of the ANSN project is to pool and share existing and new technical knowledge and practical experience to further improve the safety of nuclear installations in Asia.

The ANSN computer network is operated in a coordinated yet decentralised manner with 8 ANSN National Centres in China, Indonesia, Japan, Korea, Malaysia, the Philippines, Thailand and Vietnam. The web site associated to each National Centre provides access to important nuclear safety knowledge and serves as a portal to other ANSN sites.

ANSN is operated in the Framework of the Extra budgetary Programme on the Safety of Nuclear Installations in the South East Asia, Pacific and Far East Countries.

Relevant Documents

Legal Documents

  • PNRA Ordinance 2001
  • Regulations on Radiation Protection (PAK/904)
  • Regulations for the Licensing of Radiation Facilities other than Nuclear Installations (PAK/908)
  • Regulations for Licensing of Nuclear Installation(s) in Pakistan (PAK/909 Rev 0)
  • Regulations on the safety of Nuclear Power Plants-Quality Assurance (PAK/912 Rev 1)
  • Regulations on the safety of Nuclear Power Plants-Operation (PAK/913)
  • Regulations on Radioactive Waste Management (PAK/915)
  • Pakistan Nuclear Safety & Radiation Protection (PNSRP) Regulations 1990

    Training Course Top of page

    1. PNRA Basic Training Course on PSA Techniques, 14-20 April 2004, Islamabad

  • Accident Sequence
  • Boolean Models
  • Fault Tree Elements
  • Human Reliability Analysis
  • Initiating Event Analysis
  • Introduction to Risk Analysis Techniques
  • PROBLEMS
  • PSA Quatification
  • Reliability Data Acquisition
  • Reliability Data Summary
  • STAGES-FAULT TREE
  • System Analysis

    2. National Training Course on ProbabilisticSafety Assessment, 02-06 May, 2005, Islamabad

  • ASME Standard RA-S-2002
  • Data Analysis I
  • Data Analysis II
  • Event Sequence Analysis
  • Event Sequence Model Workshop
  • Human Reliability Analysis Methods
  • Initiating Events Grouping
  • Initiating Events Selection
  • Loss of Ventilation
  • Pre-Initiator Human Errors
  • Post-Initiator Human Errors (without SLIM-ASEP examples)
  • PSA Extensions
  • PSA Review Techniques and Experience
  • PSA Regulators
  • Quantification, Uncertainty, Sensitivity
  • Risk informed Regulation
  • Success Criteria and Time Windows
  • System Analysis I
  • System Analysis II
  • Treatment of Dependencies

    3. Presentation at the Workshop on Emergency Operating Procedures (EOPs) Severe Accident Management Guidelines (SAMGs), 23-26 Feb, 2004, Islamabad.

  • IAEA Guidance Documents for Deterministic Safety Analysis
  • Applicable Approaches For Computational Analyses Of Transients And Accidents And Ensuring Safety Margins In Design And Licensing
  • General Approach to Licensing Analysis of Groups of Postulated Initiating Events, Including Analysis of ATWS
  • Consideration of Beyond Design Basis Accidents and Severe Accidents and Their Analyses in SAR's According to the IAEA Safety Guide
  • Overview of the IAEA Approach and Documents in The Area of Severe Accident Analysis and Accident Management
  • Regulatory Guidance on Review of Beyond Design Basis and Severe Accidents Within the Framework of Licensing
  • Licensing Process and Licensing Documentation for Russian NPPs
  • Russian Regulatory Requirements and Design Practices in WWER Accident Analysis
  • Russian Regulations on Severe Accident Consideration for Existing and New Reactors
  • Status in Development of EOP and SAMG for Russian NPPs
  • Acceptance Criteria for Severe Accidents
  • Accident Sequences EOP-SAMG
  • Exit and Entry Conditions
  • Role of Regulatory Body
  • Scope of EOPs and SAMGs
  • Strategy Report EOP-SAMG
  • Technical Basis and Background
  • IAEA Guidance Documents for Probabilistic Safety Analysis
  • Current Approach towards Format and Content of SARs in View of IAEA Safety Standards
  • Format and Content of SARs With Regards to Requirements of NS-R-1 & NS-R-2
  • Comparison of IAEA Approach and US NRC Reg.Guide 1.70 Keeping in View of the Current IAEA Safety Standards
  • Consideration of Human Factor Engineering in Safety Analysis Reports
  • Approach towards Performing Confirmatory Analysis/Audits/Calculations/Review of Safety Analyses Performed by Licensee in SAR

    • Pakistan Nuclear Regulatory Authority (PNRA)

    Pakistan Atomic Energy Commission (PAEC)

    Pakistan Contacts

    We always appreciate your feedback. Whether you have comments about the content, if you have suggestions on how to improve ANSN or if you have encountered any technical problems we would like to hear from you.

    Queries on the content of the ANSN site as a whole are to be made to

    Mr. Muhammad Masood
    E-Mail: masood@ins.pnra.org

    Mr. Zaheer Ayub Baig
    E-Mail: zabaig@ins.pnra.org

    Mr. Shahid Mallick
    E-Mail: shahid.mallick@ins.pnra.org