Post Fukushima Operational Safety Upgrades in Nuclear Power Plants of Pakistan; A Regulatory Perspective
Description
Full text: The accident at Fukushima Daiichi NPP in japan which occurred on March 11, 2011 was one of the most catastrophic events in the history of NPP operation which spans over half a century. The event resulted in core meltdown in multiple-units accompanied by significant radiological and environmental consequences. The aftermath somewhat hampered the prospects of otherwise rapidly growing nuclear industry necessitated by rising energy demand and depletion of fossil fuel reserves. Initiated by WENRA stress tests, the event led to a worldwide quest by the nuclear industry to re-assess safety of operating nuclear power plants on the basis of lessons learnt from Fukushima accident so as to recuperate public perception. In Pakistan, there are three nuclear power plants in operation with a total installed capacity of around 800 MWe. Among these, Karachi Nuclear Power Plant (KAN UPP) is a pressurized heavy water CANDU type reactor which completed its design life in 2002 and has been re-licensed after implementing various safety upgrades to operate till December, 2016.C- 1 and C-2 are two loop(325 and 330 MWe gross electrical output each) pressurized water reactors which started commercial operation in 2000 and 2011 respectively. Two more similar units C-3 and C-4 are under construction and are expected to start commercial operation in 2016 and 2017 respectively. Following Fukushima accident, Pakistan Nuclear Regulatory Authority {PNRA}, an independent regulatory body authorized to supervise and oversee safety of nuclear installations issued directives to its licensees to conduct targeted reassessment of existing safety margins in order to identify and rectify vulnerabilities in the areas of extreme natural hazards, extended loss of electrical power, emergency preparedness and response, severe accident management and safety culture. Post Fukushima assessments of each nuclear installation were conducted under the Fukushima Response Action Plan {FRAP)and the issues identified during the assessments were addressed in the form of activities to be undertaken as short term, medium term and long term actions. This paper describes the post Fukushima upgrades identified and so far implemented to improve the operational safety of NPPs in Pakistan, the challenges being faced from the view point of regulator. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-152118-7
- Imprint Title
- International Conference on Operational Safety. Proceedings of an International Conference
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series (CD-ROM)
- Journal Page Range
- p. 183
- ISSN
- 1991-2374
Conference
- Title
- International Conference on Operational Safety
- Dates
- 23-26 Jun 2015
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49059844
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; ENERGY DEMAND; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; HAZARDS; KANUPP REACTOR; MECHANICAL TESTS; MELTDOWN; NUCLEAR INDUSTRY; NUCLEAR POWER PLANTS; OPERATING LICENSES; PAKISTANI ORGANIZATIONS; PWR TYPE REACTORS; SAFETY CULTURE; SAFETY MARGINS; STATION BLACKOUT; STRESS ANALYSIS; VULNERABILITY
- Descriptors DEC
- ACCIDENTS; ATTITUDES; BEYOND-DESIGN-BASIS ACCIDENTS; CANDU TYPE REACTORS; DEMAND; ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INDUSTRY; LICENSES; MANAGEMENT; MATERIALS TESTING; NATIONAL ORGANIZATIONS; NATURAL URANIUM REACTORS; NUCLEAR FACILITIES; PHWR TYPE REACTORS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR SITES; REACTORS; SEVERE ACCIDENTS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Abstract only
- Secondary number(s)
- STI/PUB--1826; IAEA-CN--227