India s HWR Activities S.G.Ghadge Executive Director (Reactor Safety & Analysis) Nuclear Power Corporation of India Limited

Transcription

1 India s HWR Activities S.G.Ghadge Executive Director (Reactor Safety & Analysis) Nuclear Power Corporation of India Limited 13 th Meeting of the Technical Working Group on Advanced Technologies for HWRs (TWG-HWR) June 18-20, 2012

2 1. National Status on HWR and related R&D (1 of 3) Operating Units TAPS-1 BWR 160 MWe TAPS-2 BWR 160 MWe 320 MWe RAPS-1 PHWR 100 MWe RAPS-2 PHWR 200 MWe MAPS-1 PHWR 220 MWe MAPS-2 PHWR 220 MWe NAPS-1 PHWR 220 MWe Total Installed Capacity 4780 MWe Units under construction/ commissioning NAPS-2 PHWR 220 MWe KAPS-1 PHWR 220 MWe KAPS-2 PHWR 220 MWe KAIGA-2 PHWR 220 MWe RAPS-3 PHWR 220 MWe KAIGA-1 PHWR 220 MWe RAPS-4 PHWR 220 MWe 4460 MWe KK-1 PWR 1000 MWe KK-2 PWR 1000 MWe KAPP-3 PHWR 700 MWe KAPP-4 PHWR 700 MWe RAPP-7 PHWR 700 MWe RAPP-8 PHWR 700 MWe 2000 MWe 2800 MWe TAPS-4 PHWR 540 MWe TAPS-3 PHWR 540 MWe KAIGA-3 PHWR 220 MWe RAPS-5 PHWR 220 MWe RAPS-6 PHWR 220 MWe KAIGA-4 PHWR 220 MWe

3 1. National Status on HWR and related R&D (2 of 3)

4 1. National Status on HWR and related R&D (3 of 3) Emphasis on R&D Bhabha Atomic Research Centre NPCIL R&D (Technology Development) NPCIL R&D (Electronic Systems) NPCIL R&D Centre at TAPS Educational institutes and research labs

5 2. New Technologies applied to operating HWRs (1 of 2) Retrofittings in operating HWRs En-masse coolant channel and feeder replacement High pressure accumulators in emergency core cooling system Supplementary control room Dedicated instrument air for essential loads Segregation and rerouting of power and control cables for safety related loads Installation of additional diesel generator (above revised flood level) Up gradation of fire protection system Calandria vault dew point monitoring system Replacement of MG sets with static UPS in Class II power supply system Symptom based event handling scheme (for feedback)

6 2. New Technologies applied to operating HWRs (2 of 2) Retrofitting planned for operating HWRs Augmentation of on site power and water supplies Severe accident management features Inclusions in new design Partial boiling in heat transport system Interleaving of primary coolant system feeders Passive decay heat removal system Enhanced mixing of containment areas Containment spray system Metal lined containment Severe accident mitigation provisions

7 3. Post Fukushima Actions (1 of 3) Feed back to operating and under construction NPPs Stress test carried out for all NPPs this indicated that margins exist over designed seismic and flood levels : cliff edge evaluated Need identified to incorporate automatic reactor trip in all NPPs for seismic event strengthen provisions for beyond design basis accidents addition of water for core/fuel cooling and spent fuel cooling have means for augmentation of on site water supplies have smaller DG sets for charging batteries and running small capacity pumps incorporate provisions for containment safety formalize and implement severe accident management guidelines

8 3. Post Fukushima Actions (2 of 3) Feed back to operating and under construction NPPs (continued) The envisaged safety enhancements are being implemented with regulatory review and concurrence Augmenting power supplies and on site water sources provision of diesel operated pumps, mobile pumping units, mobile DG sets, augmented flood protection The modifications are planned in such a way that actions can be taken from outside plant buildings to supply cooling water to core, auxiliary and support systems, and spent fuel pools All preventive and mitigating measures are qualified for maximum anticipated flood and earthquake at NPP site. Early tsunami warning system is made available at all coastal NPPs Automatic reactor trip on sensing seismic event is under implementation at all NPPs (exists at two stations)

9 3. Post Fukushima Actions (3 of 3) Feed back to operating and under construction NPPs (continued) Document made available to all NPPs giving guidelines for utilizing systems incorporated to handle beyond design basis accidents and completion of comprehensive SAMG document is accelerated Emergency drills, in addition to regular practice carried out at all NPPs involving central and state authorities Implementing containment safety measures Passive hydrogen recombiners Filtered containment venting Completing implementation of all the recommended safety enhancements (both preventive and mitigating) at all NPPs progressively in their respective biennial shutdowns. Augmenting facilities and capabilities of on-site emergency control centre at all NPPs Implementing SAMGs at all NPPs and providing necessary training to operating personnel

10 4. Proposals for future IAEA activities (1 of 3) OSART mission planned for RAPS-3&4 (October-November 2012) CRPs/TMs identified in Consultants Meeting on Applying Lessons Learned from Fukushima Accident to Water Cooled Reactor (WCR) Technology Development (23-26 April 2012) may be pursued CRP CRP Damaged core cooling, including in vessel retention options analytical basis code comparisons possible experimental back-up determination of calandria as a barrier with calandria vault heat sink maintained (for PHWRs) Equipment survivability /hardened instrumentation for severe accident conditions harmonization of methodology for survivability assessment possible experimental back-up R&D for equipment development PHWRs PHWRs

11 4. Proposals for future IAEA activities (2 of 3) CRP CRP Containment safety provisions (Cooling, PARs, containment venting) International collaborative efforts for collection and analysis of Fukushima accident PHWRs BWRs CRP Hydrogen free cladding material development PHWRs TM Guidelines for SAMGs without instrumentation PHWRs TM Design and features of off site emergency response centre / technical support centre TM International information exchange actions for accident management PHWRs PHWRs TM Systematic approach to reduce risk PHWRs

12 4. Proposals for future IAEA activities (3 of 3) Proposal for new CRP Topic Expected Outcome Approach Fire hazard Analysis of Nuclear Power Plants Comparison of analysis methodologies and techniques and Benchmarking/Validation of code(s) Coordinated Research Project (CRP)

13 Thank you for your attention