Overview of documents related to the disposal of DSRS via the BDC Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria

Content Why the IAEA borehole disposal concept (BDC) was developed. The benefits and sustainability of the solution will be elaborated for your understanding. Where to look for information on the BDC.

Why the Borehole Disposal Concept (BDC) Current concept (BDC) conceived at a meeting of the 1AFRA Waste Management Project Coordinators in 1995 in South Africa. Difficult to provide the required level of control for DSRS in their countries. The IAEA provides the secretariat for the AFRA projects and they were approached to fund the development of the concept. 1AFRA – African Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology.

Long term storage NOT sustainable Developing countries have more important priorities than looking after disused sealed radioactive sources. Political turmoil and economic hardship in many parts of the world exasperate lack of control. Lack of knowledge and skills among operators and regulators. Knowledge management often not carried out. Conditioning for the long term not affordable and not often done. (e.g. stainless steel drums). Long term storage without long term thinking leads to corrosion, contamination, accidents and more!!!

Development of the Borehole Disposal Concept – Necsa Involvement 1995 – AFRA Project Coordinators meeting 1996 – 1Necsa proposal to the IAEA 1998 – Phase 1 complete – description 2000 – Phase 2 complete – 1st safety assessment 2004 – Phase 3 complete – detailed evaluation 2005 – International Peer Review 1South African Nuclear Energy Corporation Ltd (Necsa)

IAEA contribution Funded all the Necsa work from 1TCF Studied the concept through the 2ISAM 3CRP Developed a Safety view through a TECDOC 1368 and Safety Guide SSG-1 Funded a generic post closure safety assessment – completed 2003 Currently publishing a report on the generic safety assessment. Produced technical manual TECDOC 1644. 1Technical Cooperation Fund (TCF). 2Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities (ISAM). 3Coordinated Research Project (CRP)

Requirements Safety Standard There are 26 detailed requirements for disposal in Document SSR-5 including requirements for :- Responsibilities of government, the Regulator and Operator. Passive means for the safety. Understanding of the disposal facility and confidence in safety. Multiple safety functions. Containment of radioactive waste. Isolation of radioactive waste. Surveillance and control of passive safety features. Etc. Detailed review of these requirements will be addressed in another lecture

Borehole disposal Specific landfill disposal Near surface disposal Safety Requirements apply to all types of disposal and disposal facilities Specific landfill disposal Near surface disposal Disposal of intermediate level waste Geological disposal Borehole disposal Safety Guides provide comprehensive guidance on and international best practices for meeting the requirements in respect of different types of disposal facility.

Key Published IAEA Documents Many unpublished reports including Necsa documents

Some of the Necsa reports The complete list of Necsa reports can be found in IAEA-TECDOC-1644

Some of the Necsa reports I GEA-1620 development philosophy The document provides a useful summary of all the BDF project documents. The key components of the philosophy are: The approach will be ‘pragmatic’; The relevant safety requirements will be met; Operational safety will be ALARA. GEA-1621 requirements for the borehole disposal facility This is an overview of the BDF as a long term management solution for disused SRS. The text discusses, evaluates and documents a wide range of policy, regulatory, engineering, logistical and scientific issues related to setting defensible and achievable requirements for safe implementation of the BDF.

Some of the Necsa reports II GEA-1622 borehole disposal facility: generic site selection and characterization This document provides guidelines for site selection and site characterization for a borehole disposal facility so that, in conjunction with the engineered barriers, the facility will provide radiological protection that complies with international standards. GEA-1623 design for the borehole disposal facility This document provides a clear description of the generic or reference design and how the facility would be operated. It provides detailed information on most aspects of the design and operation.

Some of the Necsa reports III GEA-1626 road map and procedures to implement the BDF This document contains an implementation process (road map) for the BDF and procedures for many of the associated activities such as site selection and characterization, borehole construction, container manufacture, and source conditioning and containerization. GEA-1627 practical demonstration and qualification This document provides a description of the various trials and demonstration tests that were carried out. It contains useful information and photographs that help to explain some of the procedures and the choice of materials.

Some of the Necsa reports IV GEA-1628 techno-economic study This document, referred to in the overview but not technical manual, derives an estimate of the likely cost of the BDF. GEA-1633 prospective hazard assessment of a borehole disposal facility This document describes operational activities so as to demonstrate that the doses to operators of the facility can be controlled to within acceptable limits. The estimates for some activities are compared with actual dose measurements that were taken during previous missions where radium sources were pre-conditioned.

Some of the Necsa reports V GEA-1632 generic HAZOP for borehole disposal of spent radioactive sources This document is likely to be useful to the RPO. It presents an analysis of potential hazards associated with the BDF. Various types of deviation (e.g. ventilation failures, monitoring instrument failures, welding failures, power supply failures, etc.) are listed along with their important characteristics i.e.: Causes; Consequences; Ranking of consequences; Protecting or mitigating features; Actions (including recovery to a normal situation).

Some of the Necsa reports VI GEA-1641 practical demonstration of the borehole disposal facility This report briefly describes Necsa’s intentions with respect to demonstrating the BDF. It is largely of historical interest and is not referred to in this technical manual. GEA-1643 generic waste acceptance criteria for the borehole disposal facility This document presents generic waste acceptance criteria (WAC) for the BDF, which may be used to help define site specific WAC. It provides guidelines with regard to the acceptability of materials other than those used in the generic design and associated safety assessment. The document specifically excludes SHARS and neutron sources however.

Some of the Necsa reports VII GEA-1714 waste acceptance criteria for the borehole disposal facility This document presents generic (but detailed) waste acceptance criteria for the borehole disposal facility. It includes tables of limiting activity levels for individual waste packages based on their heat output and doses arising from operation of the conditioning unit and portable hot cell.

Some of the Necsa reports VIII BDF-006-NTW NNR review of borehole disposal investigation This document presents a review of the BDF by the South African nuclear regulator (NNR). The review aims to compare Necsa’s proposals for the BDF with international best practice. The document concludes that “The studies conducted by Necsa, including the generic safety assessment, demonstrated compliance with regulatory requirements, based on international standards”. The document is likely to be helpful to other regulatory bodies. BDF-007-NTW guidance document on the borehole disposal facility (previously published as lg-1043, licensing guide: borehole disposal facility safety case) This presents comprehensive regulatory body guidance to the implementer of a borehole disposal with respect to compliance with regulatory criteria and, specifically, with respect to the preparation of the safety case. The document is likely to be helpful to other regulatory bodies.

Some of the Necsa reports IX QRS-1128A-6 v2 generic post-closure safety assessment (GSA) This document is a comprehensive generic post-closure safety assessment for the BDF Calculations are performed for three lithological environments (arenaceous, argillaceous and crystalline) that, along with other variables, serve as a proxy for a range of hydrogeological and geochemical conditions. The container corrosion rates are based on localized corrosion of stainless steel. QRS-1128C-1 v2 (F-GSA) This document presents further calculations on post-closure safety and should be read in conjunction with the GSA. The effect of a wider range of corrosion rates is explored but the lowest rates used are still significantly higher than those applicable to uniform corrosion.

Implementation of the borehole disposal technology Documentation on borehole disposal technology IAEA documentation package for governmental authorities and decision-makers  Flyer (published) for regulators, developers, operators, etc.  Technical Manual (in draft)  Safety Assessment Template (TBD)

Implementation of the borehole disposal technology Safety documentation on borehole disposal technology IAEA Safety Standards Series SSR-5 Disposal of Radioactive Waste. Safety Requirements SSG-1 Safety Guide on disposal of radioactive waste in borehole facilities IAEA TECDOC series TECDOC-1355 Security of Radioactive Sources (2003) TECDOC-1368 Safety considerations in the disposal of DSRS in borehole facilities (2003)

Implementation of the borehole disposal technology Technical documentation on management of DSRS IAEA TECDOC series TECDOC-804 Methods to identify and locate DSRS (1995) TECDOC-776 Reference design for a centralized waste processing and storage facility (1994) TECDOC-886 Conditioning and interim storage of spent radium sources (1996) TECDOC-1145 Handling, conditioning and storage of DSRS (2000)

Implementation of the borehole disposal technology Technical documentation on management of DSRS IAEA TECDOC series TECDOC-1205 Management for the prevention of accidents from DSRS (2001) TECDOC-1301 Management of spent high activity sources (2002) TECDOC-1357 Management of long-lived DSRS (2003) TECDOC 1368 Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities (2003) TECDOC 1644 Borehole Disposal (2011)

Implementation of the borehole disposal technology Technical documentation on management of disused sealed radioactive sources (cont’d) IAEA TECDOC series TECDOC-804 Categorization of Radioactive Sources (2003) IAEA Technical Report Series Under preparation - Handling, conditioning and storing DSRS (will supersede TECDOCs-886, 1145, 1301 & 1357) TRS-376 Quality Assurance for radioactive waste packages (1995) TRS 436 Disposal Options for Disused Radioactive Sources (2005) IAEA Working Material Practice oriented training on quality management of RW (2002)

How much would borehole disposal cost? Necsa study for Category 3 to 5 sources estimated 2004 costs at US$407 500 in South Africa. Recent estimates push this up to ≈US$700 000. If one includes the deployment of the Mobile Hot Cell another ≈US$350 000 should be added. NOTE: Costs are dependant on inventory and conditions in a country

The Concept

Objective of IAEA/Necsa Disposal Concept The technology to be used in the borehole concept is such that each country possessing DSRS will be able to safely implement the concept for its own wastes. The concept will meet all safety standards as laid down in the IAEA documents. The concept must be economically feasible to implement, taking into consideration the financial situation in some of these African countries. The concept should preferably be applicable for both short- and longer-lived radionuclides, such as 226Ra and 241Am.

A Simple Water Drill

The Concept - Filling the Borehole

A single disposal container (van Blerk, 2011) DSRS inside the small capsule which is in turn inside the containment barrier of cement. The disposal container is made of 316L stainless steel. The area surrounding the container is filled up with backfill material which is inside the casing. Grout is pumped into the outside space between the casing and the rock.

Concept Detail (van Blerk, 2000)

The Disposal Package + Capsules Container Container Lid Backfill Capsules

Capsule sizes Two capsule sizes are proposed in the original concept. They are the same sizes as those used in radium conditioning operations. This will be altered for the high activity sources.

Dimensions of the capsule, containment barrier and container Length (mm) Inside Diameter (mm) Outside Diameter (mm) Thickness1 (mm) Capsule S 110 15.26 20.80 2.77 L 121 40.24 47.60 3.68 Containment Barrier (cement) 186 102.30 40.75 171 47.6 27.35 Stainless Steel Container S, L 250 114.30 6.00 1 As used here thickness refers to the wall thickness of the capsule and disposal containers as well as the thickness of the containment barrier. S=small capsule, L=large capsule Ref: van Blerk 2011

Typical dimensions of the borehole The borehole has a nominal depth of 100 metres that will vary depending on the site conditions. The disposal zone should be below 30 metres which is the level accepted for maximum intrusion depth. The outside diameter of the borehole is 260mm. The outside diameter of the casing is 160mm (≈6 inches). The inside diameter of the casing is 145.34 mm giving a wall thickness of 7.33 mm. Note: The recommended casing is high-density polyethylene (HDPE)

Emplacement Lifting Equipment “Grabber” Grout outside container

Down the hole Equipment Cement is placed around the container inside the hole by means of a hopper that delivers the correct amount of cement to cover the disposal container. The lowering equipment “Grabber” has a positive clamping mechanism, which will clamp on to the lifting ring and will only release as soon as pressure is applied to the lifting equipment. Grabber Hopper

Options for conditioning High Activity Sources Option 1 to condition in a Mobile Hot Cell over the borehole. Option 2 to condition before the borehole is available in a Hot Cell and then dispose of containers using the Mobile Hot Cell Lower Activity Sources Option 1 to condition in facility next to the borehole and dispose directly out of this facility. Option 2 to condition before borehole is available and then dispose of containers using the Transfer Cask.

Transfer Flask In the event that the sources are conditioned away from the borehole, a transfer flask can be used for transporting waste packages to the disposal facility. The transfer flask is fitted with a gate at the bottom, which can be opened during the disposal process. There will be a minimum lead thickness of 100 mm to provide shielding during the transferring process. Used for lower category sources (Cat 3 to 5).

Conditioning at the borehole (Cat 3-5) Ref: van Blerk , 2011

Conditioning for disposal The successful radium operations used as a model for conditioning for disposal of lower activity sources. Difference being the welding of the disposal container which will need different welding equipment. Can be done in mobile facility such as an ISO transport container. Procedures need to be developed.

Conditioning high activity sources High specific activity means large shielding requirements such as found in a Hot Cell. Remote handling necessary including remote welding equipment. Hot Cell must be big enough to fit large self shielded irradiators and teletherapy heads. Disposing at borehole site implies large shielding requirement such as found in the Mobile Hot Cell.

Typical operation for radium

Radium Conditioning Continued

Conditioning facility and completed hole

Conceptual High Activity Disposal Mobile Hot Cell Borehole

Safety Assessment

Long Term Safety “With a suitable combination of inventory, near-field design and geological environment, the borehole disposal concept is capable of providing a safe solution for the disposal of both long-lived and short-lived radionuclides”. Quote from International Peer Review 2005

International Peer Review (2005) Safe, economic, practical and permanent means of disposing DSRS. Applicable to a wide range of DSRS. Appropriate steel and backfill selected. High activity sources still to be included. No full scale demonstration done. All procedures addressed in Necsa documents.

How much would borehole disposal cost? Necsa study for Category 3 to 5 sources estimated 2004 costs at US$407 500 in South Africa. Recent estimates push this up to ≈US$700 000. If one includes the deployment of the Mobile Hot Cell another ≈US$350 000 should be added. NOTE: Costs are dependant on inventory and conditions in a country

Decommissioning and Disposal Costs in 2008 Dollars Data Obtained from Cost-Benefit Analysis for Potential Alternative Technologies for Category 1 and 2 Radioactive Sources Report produced by ICF Incorporated, L.L.C. on August 31, 2009 Blood Irradiation Cs-137 Irradiators Co-60 Irradiators Device Decommissioning and Disposal $110K - $125K for recovery and disposala depending on the location (2009 USD) $165K - $180K for recovery and disposalb depending on the location (2009 USD) Recycling No information available at this time Storage a. Recovery costs are the averaged proposed costs from 4 vendors and 13 Cs-137 devices from a recent procurement. b. Recovery costs are the averaged proposed costs from 4 vendors and 6 Co-60 devices from a recent procurement

Benefits of Implementing BDC Reduce long term financial liability to zero. Risk of malicious use of sources reduced to zero. Shifting the burden of care to future generations is prevented. Sustainability of the solution is assured where resources are limited. Safety and Security of DSRS management is significantly improved. Cheaper solution than waiting for shallow land or deep geological disposal options to become available.

Thank you!

Self Assessment Why is long term storage of DSRS not sustainable in developing countries? Choose from the selection of options. Developing countries have more important priorities than looking after disused sealed radioactive sources. Political turmoil and economic hardship in many parts of the world exasperate lack of control. Lack of knowledge and skills among operators and regulators. Knowledge management often not carried out. Conditioning for the long term not affordable and not often done.

Self Assessment What is the backfill around the capsule within the disposal container? Choose one of the following. Bentonite Copper Cement Lead Is borehole disposal expensive compared to traditional shallow land disposal of sources? Much more expensive About the same Considerably cheaper

Self Assessment Name some of the benefits of disposing of DSRS? Reduce long term financial liability to zero. Risk of malicious use of sources reduced to zero. Shifting the burden of care to future generations is prevented. Sustainability of the solution is assured where resources are limited. Safety and Security of DSRS management is significantly improved. Cheaper than other disposal options.