Radioactive Waste Management and Environmental Surveillance at KANUPP Khawaja Ghulam Qasim Sr. Manager (KANUPP)
PAEC Nuclear Power Program K-1 C-1 C-2 C-3 C-4 K-2/K-3 1972 2000 2011 Sep.2016 2017 2021 KANUPP-1 CHASNUPP-1 CHASNUPP-2 CHASNUPP-3 CHASNUPP-4 KCPP 137 MW 325 MW 330 MW 340 MW 340 MW 1100 MW each PHWR PWR PWR PWR PWR ACP1000 Canada China China China China China 2 of 25
KANUPP- General Design Features OWNER: Pakistan Atomic Energy Commission (PAEC) DESIGNER Canadian General Electric (CGE) LOCATION: 17 Km West of Karachi Harbor on Arabian Sea Coast REACTOR TYPE: PHWR (CANDU) COMMERCIAL OPERATION: 1972 RATED THERMAL POWER: 433 MWth GROSS ELECTRIC POWER: 137 MWe NET ELECTRIC POWER: 125 MWe CURRENT LICENSING POWER: 98 MWe MODERATOR: Heavy Water (D2O) COOLANT: Heavy Water (D2O) CALANDRIA: Stainless Steel FUEL CHANNEL: Zr-Nb 2.5% FUEL : Natural Uranium (UO2) FUEL SHEATH: ZircAlloy 4 RE-FUELLING SEQUENCE ON-Power 3 of 25
Surrounding of KANUPP 4 of 4 25
National Policy on Radioactive Waste Management Commitment: The Govt. of Pakistan (GoP) is committed to: Protect human health and environment now and in the future. Avoid imposing an undue burden on future generations. Management of ownerless waste and orphan sources. Abide all international agreements to which Pakistan is a signatory. Minimization: The production of radioactive waste must be kept to the minimum practicable level. Polluter pays principle: Every generator of radioactive waste shall be responsible for safe and secure management of radioactive waste and shall pay for its safe disposal. Import/Export: Radioactive waste shall not be imported/exported unless or otherwise approved by the regulator, PNRA Safe Disposal: Pakistan Atomic Energy Commission (PAEC) shall be responsible for safe and secure disposal of all radioactive waste including Disused Sealed Radioactive Sources (DSRS). 5 5 of 25
Radioactive Waste Management at Nuclear Power Plants in Pakistan
Basic Features of Radioactive Waste Management at NPP Waste Minimization Ensure integrity of Fuel. Filters and Ion-Exchange Columns are used. Decontamination and Reuse/recycle. Allows Decay. Volume Reduction Evaporation. Incineration. Compaction of Soft Waste. Dilution of Active Liquid. Immobilization (Cementization) Packaging and Record Keeping. Interim Storage. Monitoring. 7 of 25
Radioactive Waste Management Solid Waste Segregation. Soft Waste compacted in Drums. Contaminated Hard Waste stored in Trenches. (RCC Pit 10 X 10 X 10 covered with slab). Waste stored in Radioactive Waste Storage Area. o Radiation Monitoring. o Physically Secured. End State: Four Drums Grouted altogether LILW Segregation Compaction in MS Drums 04 MS Drums in One Concrete Container (Grouting) Interim Storage 8 of 25
Radioactive Waste Management Spent Resin At KANUPP, the resin is stored in steel tanks and kept in above ground/underground concrete vaults. At CHASNUPP, the resin after conditioning/solidification are stored at site. End State: Four Cementized MS Drums, Grouted altogether LILW Solidify with Cement in MS Drum 04 MS Drums in One Concrete Container (Grouting) Interim Storage 9 of 25
Radioactive Waste Management Liquid Effluent Holdup Tank to facilitate decay of short lived fission products. At KANUPP Dilution with inactive plant effluent water. Discharged to sea in monitored and controlled manner such that the concentration at point of discharge is less than the Daily Emission Limit of βɣ activity in liquid effluent. At CHASNUPP Evaporates and Concentrated effluent is cementized. 10 of 25
Radioactive Waste Management KANUPP : Dilution CHASNUPP Radioactive Liquid Effluent Management 11 of 25
Management of Radioactive Effluent Gaseous Effluent Filtered before release to Environment. Alarm in Control Room if Release Rate > 10 % of Daily Emission limit. Released from Stack. The effluents yearly releases remained below 1 % of the Allowable Release Limits. 12 of 25
Management of Spent Fuel Spent Fuel Spent Fuel are stored underwater at the NPPs. At KANUPP the storage capacity was completed in 2010. Capacity has been enhanced by placing 24 trays per stack. (Initial design 18 trays per stack). Two stacks each of 24 Trays are placed in a Rack provides seismic qualification upto 0.2g Atleast 10 yrs. cooled spent fuel will be shifted from wet storage to Dry Storage. Dry Storage facility at KANUPP is expected to be started in 2017. End State: Concrete Cask. SNF Water Filled Storage Pool ~ 10 years cooling Concrete Cask Dry Storage Facility 13 of 25
Monitoring and Environmental Surveillance at KANUPP Site
Monitoring of Wastes Before Release to Environment at KANUPP Liquid Effluent On-line Gamma Monitoring Beta, Gamma activity at Lab. Tritium Analysis at Lab. Gaseous Effluent Iodine-131 Noble Gases Air Particulate Gamma Dose Rate Tritium Estimated Dose to critical group of Public due to Releases ~ 0.01 msv/yr. (This is about only 1% of the regulatory limit) 15 of 25
Environmental Radiological Surveillance Program A program has been prepared which is duly endorsed by Regulator. This includes: Ambient Dose Rate Monitoring. Environmental Sampling and Analysis. Air-borne Activity monitoring. On-Line Environmental Gamma Radiation Monitoring Tritium Concentration in water Monitoring. 16 of 25
Ambient Dose Rate Monitoring 15 Thermo-luminescent Dosimeters (TLDs) are installed 5 TLDs at plant periphery 10 TLDs in Karachi city Data remains in the range of 0.08-0.10 µsv/hr, which is normal background dose rate. 6 continuously operating air samplers are installed in City. Portable Air Sampling. On-line Environmental Gamma Radiation Monitoring Only naturally occurring radionuclides found like K-40. 17 of 25
Environmental Sampling and Monitoring Environmental samples are collected 5km and 10km from plant, twice a year. Soil Milk Grass Water Sea Water Fish sample, near to liquid discharge conduit. Sediment. WHO Safe Food Limit for Cs-137 : 1000 Bq/kg. Radioactivity in Samples remained below Minimum Detectable Activity or few times measured less than 2 Bq/Kg. 18 of 25
Tritium (H-3) Activity Monitoring Water samples are collected from Underground Water (well) Sea WHO Drinking Water limit for H-3 : 10,000 Bq/l. Tritium H-3 concentration in samples remained below 7 Bq/l 19 of 25
Dose Constraints Site Facility in Operation Facility under Construction Per Facility Dose Constraint Per Site KANUPP 01 02 0.3 Will be set later on CHASNUPP 02 02 0.26 Under discussion with regulator 20 of 25
Management of Conventional (Non-Active) Emissions COx, SOx, NOx, halogen gases and particulates are not produced in significant quantity as compared with conventional power plants. A small portion of chemical non-active effluent is released to the environment in the form of liquid. The ph and temperature monitoring of non-active effluent is performed before discharge. The ph value of 6 9 is maintained before discharge of effluent. The temperature difference of less than 3 C is maintained between intake and discharge. 21 of 25
Management of Conventional (Non-Active) Emissions The COD / BOD5 monitoring results (at discharge point and at various points in the sea) shows that they are well within National Environment Quality (NEQ) Standard. S. No. Parameters NEQS limits (mg/l) Monitoring Results (mg/l) 1 BOD5 200 20-31 2 COD 400 70-92 22 of 25
UR1 Controllability of environmental stressors: User Requirement. Criteria Radiation Exposure to Public Radiation Exposure to Non-human species Indicators (IN) and Acceptance Limits (AL) KANUPP DATA Remarks Dose to the public 7x10-3 msv Canadian Standards Dose constraint Yes Only 2.3% of the Dose Constraint Dose to the reference biota species Lower than international recommendations Not evaluated --- Environmental Sample analysis results are available which can be compared with BCGs using RESRAD. Impact of chemicals and other nonradiation environmental stressors Levels of chemical and other stressors Lower than National Environmental Safety Standard Levels Not evaluated as per INPRO recommendations. Although Nonactive emissions compared with National Environment Quality Standard (NEQ) limits 23 of 25
UR3 Optimization of the measures to reduce environmental impact: UR2 Reduction of Total environmental impact of emitted radioactivity User Req. Criteria Radiation Exposure Radiation Exposure to the Public Optimization of the measures to reduce environment al impact Indicators (IN) and Acceptance Limits (AL) Total radiotoxicity R T is lower than radiotoxicity of stressors emitted to the environment from current NES delivering similar energy products. measures to reduce environmental impact of the NES Measures are optimised KANUPP DATA R T = 2.16 man- Sv/GWa (Average of 2012-2014 only for KANUPP) Not compared Radioactive materials released to the environment by implementing ALARA Principle Yes Remarks The value is relatively higher due to release of T 3 from PHWR and low generation of power at KANUPP. Radiological Impact on the Environment assessed during 2 nd Periodic Safety Review OF KANUPP. Same reviewed by the regulator and concluded that the ALARA Principle is adequately implemented. 24 of 25
Thank You for your Kind Attention! 25