Pakistan s HWR Activities

Transcription

1 14 th Meeting of the Technical Working Group on Advanced Technologies of Heavy Water Reactors (TWG-HWR) Vienna, Austria June 2013 Pakistan s HWR Activities by Shahid Saghir, Senior Manager (Technical) Karachi Nuclear Power Plant

2 National Status on Nuclear Energy One 137 MWe PHWR is in operation since 1972 Two 325 MWe PWR plants in operation Two 340 MWe PWR plants under construction Target of 8800 MWe capacity through NPPs till 2030

3 Pakistan s Energy Mix 100% Others 0.3% 3.3% Others 80% 60% 40% Hydro Nuclear Gas 32.0% 3.0% 28.9% 16.2% 13.4% 21.4% 5.1% Hydro Nuclear Gas Oil 20% Oil 35.6% 40.6% Coal 0% 0.1% Pakistan-2010/11 World-2009 * Others include imported electricity for Pakistan and geothermal, wind, solar etc for the world.

4 KANUPP Introduction OWNER: Pakistan Atomic Energy Commission (PAEC) DESIGNER Canadian General Electric (CGE) LOCATION: 30 KM West of Karachi on Arabian Sea Coast REACTOR TYPE: PHWR (CANDU) COMMERCIAL OPERATION: 1972 RATED THERMAL POWER: 433 MWth GROSS ELECTRIC POWER: 137 MW NET ELECTRIC POWER: 125 MW CURRENT LICENSING POWER: 98 MW MODERATOR: Heavy Water (D2O) COOLANT: Heavy Water (D2O) CALANDRIA: Stainless Steel FUEL CHANNEL: Zr-Ni 2.5% FUEL SHEATH: Natural Uranium (UO2) FUEL SHEATH: ZircAlloy 4 RE-FUELLING SEQUENCE ON-Power TURBINE-GENERATOR Non Reheat, Tandem Compound

5 Efforts for Self Reliance Indigenous Fuel Fabrication Development of Spare Parts Development of Fuel Management Programme Computer Hardware/Software Development In-Service Inspection Programme Manpower Development Programme

6 Major Projects Three Projects initiated in the late 80 s and early 90 s to combat Ageing/obsolescence for safe/reliable operation 1. Safe Operation of KANUPP (SOK) 2. Technological Up-Gradation Project (TUP) 3. Balancing, Modernization and Rehabilitation (BMR)

7 Major Activities of SOK Major Projects 1. Fuel Channel Integrity Assessment 2. Installation of Emergency Boiler Feed Water System 3. Updating of KANUPP Final Safety Analysis Report 4. Probabilistic Safety Assessment (PSA) - Level 1

8 Major Activities of TUP Major Projects Computer Replacement C&I Replacement Safety Parameters Display System Critical Parameters Display System Electrical Back-fitting Nuclear Instrumentation Replacement Up-gradation of T/G Machine Monitoring System Plant Communication System Improvements Replacement of Plant Radiation Monitoring Equipment Extension of Switchyard

9 Major Activities of BMR Major Projects Replacement of Steam Condenser Tubes Replacement of Chillers Replacement of Service Air Compressors Installation of a new Fire Alarm System Replacement of Oil Circuit Breaker

10 PLANT LIFE EXTENSION (PLEX) KANUPP is first CANDU plant for PLEX Nuclear Regulatory Requirement PNRA pointed out 17+7 safety issues This lead to 53 major safety related activities

11 Major Safety Up-Grades Improving LACA Handling Capability Forced Emergency Injection System Redundant Emergency Injection System Emergency D 2 O addition facility Automatic Boiler Crash Cool Down System Protection of Active Drainage Sump Environmental Qualification

12 PAEC Response Post Fukushima Actions PAEC Corporate Office initiated re-assessment of the safety of KANUPP and CHASHMA NPPs In view of Stress-Test, targeted action plan called Fukushima Response Action Plan (FRAP) issued for KANUPP by Corporate Office on 22 June 2011 PAEC Corporate Office conducted 03 reviews of FRAP (Oct 2011, June 2012 and Feb 2013) Quarterly progress on FRAP is being sent to Corporate Office

13 Post Fukushima Actions Areas of Safety Concern External Natural Hazards Make-Shift AC Power DC Power Capacity Fire Protection and Control Emergency Core Cooling Hydrogen Hazard Containment Integrity Spent Fuel Cooling EOPs, SAMGs (On-Site Actions) Emergency Preparedness (Off-site Actions)

14 Post Fukushima Actions Strategy Enhancement in Defense-in-Depth Use of Simple Technology Easy to implement No / minimum change in existing logic (s) Indigenous efforts (analyses, engineering & implementation) Cost effective

15 Seismic Retrofits / Anchoring ( 0.2g) Strengthening of Wall above DG3 bus bar Strengthening of Wall near DG3 bus in Dist. Room Reinforcement of Cable Trays Anchoring of DGs Local Panel

16 Flooding Protection ( 3 ft) Wall Sliding Gate Flap Gate

17 Post Fukushima Actions Enhancing Defence in Depth for Prolong SBO Enhancement of Emergency Power Sources Installation of to 100 kva DGs for continuous charge of 24V DC and 220V AC UPS systems Shifting of station emergency lighting power supply from 230V DC system to 220V AC UPS for its prolonged availability Emergency Cooling Provision through Diesel Driven Pump Containment Integrity under Severe Conditions

18 Enhancement of Emergency Power Sources To charge battery bank, PLC for monitoring & signally, operating ECC Valves & emergency lighting Using extra capacity of FIJW-DGs to operate limited essential loads To provide power to essential buses (as a last resort) 17/40 Bowser for fuel transfer

19 Emergency Cooling Provisions PW-TK1 (2000 IG) BFW-TK1 (27740 IG) RFW-TK2 (20000 IG) DMW-TK1 (20000 IG) FW Ring Flexible Hose Gravity Feed Line Boilers ~06 days Core Cooling ~01 day Dousing Spray Diesel Driven Pumps Vault Cooling ~05+05 days Spent Fuel Bay SEA WATER

20 CONTAINMENT Penetration (Aliquate 336) (Alkaline solution (Thiosulphate) Vent Tank STACK Containment Integrity Water Storage Tank Feed through pump or gravity Concrete Shielding Orifice Passive Rupture Disk Active 6 3 MD7 MD9 3 MD8 MD10 To Stack To Dryer Diesel Driven Recirculation Pump Passive Filtered Containment Venting System Drain Valve

21 Hydrogen Hazard Post Fukushima Actions Conservative analysis carried out to determine the number and location of PARs IAEA Steering Committee (SC) approved the safety case for procurement of PARs. Budgetary prize from CANDU Energy received Procurement of hydrogen monitoring equipment is under way

22 Thank You!