The wastes generated at the nuclear power stations during their operation are of low  and intermediate radioactivity level. These wastes are appropriately treated,  concentrated and subjected to volume reduction. The concentrates are immobilized in  inert materials like cement, bitumen, polymers etc. and stored in specially constructed  structures (near surface disposal facilities) located at the site under monitoring. The  treated liquids and gases are diluted and discharged under continuous monitoring,  ensuring that the discharges are well within the stipulated limits set by Atomic Energy  Regulatory Board (AERB). The radioactivity level of the stored wastes reduces with  time and by the end of the plant life, falls to very low levels. The releases are also  monitored by AERB.

The volume of low and intermediate level wastes generated from the operating  nuclear power stations annually during the last 10 years was about 1.25 lakh cubic  meter (m3) and 130 cubic meter (m3) respectively. The projections of waste  generation for future would depend on the actual capacity additions and technologies  adopted.

During the recycling of spent nuclear fuel (SNF) small amount of liquid radioactive  wastes are generated which are classified as low, intermediate and high level as per  the safety guidelines of Atomic Energy Regulatory Board (AERB) and Bhabha  Atomic Research Centre Safety Council (BSC). Current strategy for their  management involves treatment of intermediate level waste to convert it to low and  high-level wastes followed by immobilization of high level waste to vitrified glass.  Total volume of vitrified waste generated by processing one metric ton of Pressurised  Heavy Water (PHWR) spent nuclear fuel is around 0.2 m³.

There has been no incident of release of radioactivity from Nuclear Waste  Management Facilities nor any incident/accident at the waste management  plants/interim storage Facilities during the said period.

Radioactive nuclear waste is systematically treated, conditioned, and monitored prior  to its disposal at designated storage locations. This is a continuous process, and there  is no backlog of conditioned waste awaiting disposal at interim storage facilities.

The low half life solid waste from nuclear facilities is disposed of in specially  constructed engineered structures in the Near Surface Disposal Facility within the  boundary of the facility. These disposal facilities are co-located near reactor/nuclear  facilities to avoid transportation of radioactive waste through the public domain. All the  Nuclear Power Plant (NPP) sites have Near Surface Disposal of Radioactive Solid  Waste (NSDF) at the site except Kudankulam Nuclear Power Plant (KKNPP), where  waste is stored in engineered modules within the facility.

The nuclear waste handling, treatment, storage and disposal are carried out as per the  well laid down procedures and guidelines stipulated by the AERB in accordance with  the Atomic Energy (Safe Disposal of Radioactive Wastes) Rules, 1987 and the requirements of AERB Safety Code on ‘Management of Radioactive Waste  (AERB/SC/RW)’. The adherence to these is verified through periodic inspection  conducted by AERB. The handling and disposal area is kept under surveillance by the  facility management. The environmental monitoring is carried out by Environmental  Survey Laboratories (ESLs) of BARC. The results do not indicate any buildup of  radioactivity in the environment and annual doses are well below AERB specified  limits.

Comprehensive safeguards and well-established procedures are implemented to  ensure the safe storage, handling, and disposal of nuclear waste. Waste management  practices are governed by stringent regulatory standards and are designed to protect  operating personnel, the public, and the environment. Radioactive waste is segregated  based on its activity level, treated using appropriate techniques such as chemical  decontamination, absorption, ion exchange/membrane separations and volume  reduction, and then conditioned into stable forms suitable for storage. Engineered  storage systems with multiple containment barriers, radiation shielding, and leak  detection mechanisms are employed to prevent any release of radioactivity. Waste  handling operations are conducted using remote or shielded systems, wherever  necessary, and under strict radiological surveillance. Regular monitoring, periodic  safety reviews, and adherence to approved waste disposal protocols ensure continued  safety throughout the lifecycle of waste management.

This information was given by Dr. Jitendra Singh, Union Minister of State (Independent Charge) for Science and Technology, Earth Sciences, MoS PMO, MoS Personnel, Public Grievances & Pensions, Department of Atomic Energy and Department of Space, in a written reply in the Lok Sabha today.

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NKR/PSM

(Release ID: 2147270)