The Radioactive Waste Quality Assurance Programme in Qatar

The article that decides whether anything else can be proved

Part Five of the Regulation has asked for a great deal by the time it reaches Article 94. Waste must be generated at the lowest practical level, classified as soon as it is generated, segregated at the bench, discharged only within authorised limits, stored in a room with twelve features, and disposed of only on an application that meets acceptance criteria. Article 94 is the article that asks how any of that would be demonstrated to somebody who was not there.

That is why it is placed where it is. A duty that cannot be evidenced is a duty that cannot be inspected, and Article 85 has already given the Ministry the right to inspect all records of radioactive material or waste and to obtain copies of them. Article 94 turns the practice into a documented system, and item 4 of Article 82 had already made establishing and applying such a programme one of the six responsibilities of the licensee. Article 94 is that duty expanded, with a submission point, a verification mechanism and a list of contents.

One practical warning before the detail. The phrase quality assurance invites a facility to reach for whatever management system it already holds and rename a folder. Article 94 does not ask for a management system in the abstract; it asks for a programme that covers all aspects of radioactive waste management, the facilities, the activities and the waste, and it then lists eight specific things its documents must contain. A general certificate on a wall satisfies none of the eight.

Article 94: submitted for endorsement, as part of the licence application

Article 94 is headed quality assurance and it opens with the submission. The licensee must submit a quality assurance programme to the Council for endorsement, as part of the licence application, covering all aspects of radioactive waste management, the facilities, the activities and the waste, and this programme must be proportionate to the size of the operations.

Four elements of that sentence do separate work, and each one answers a question a facility actually asks. The programme is submitted, so it leaves the building. It is submitted for endorsement, so the authority either endorses it or does not - a programme written and filed internally has not met the article. It is submitted as part of the licence application, which fixes the timing: this belongs with the application under Article 83, which itself has to be made thirty days before the work starts. And it must be proportionate to the size of the operations.

Proportionality is the element most often misread, and it is misread in both directions. A small clinic reads it as permission to have nothing, and a large operator reads it as a demand for a document nobody will finish. Neither follows. Proportionate to the size of the operations scales the depth of the programme, not its coverage: the article still requires it to cover all aspects of waste management, the facilities, the activities and the waste. A single-isotope nuclear medicine unit can satisfy Article 94 with a short, exact document. What it cannot do is leave one of the eight contents out because it is small.

The independent checks, and why they are not the officer's own review

The second paragraph of Article 94 adds a verification duty that is easy to read past. The effectiveness of the quality assurance programme must be verified by independent checks, to ensure that radioactive waste management activities are carried out so as to meet the requirements necessary to protect human health and the environment.

Three words carry the weight. Effectiveness, not existence: the check is whether the programme works, not whether it has been written. Independent, a word the Regulation attaches to the waste management officer in Article 84. Whether it is used of the radiation protection officer elsewhere in the instrument is a question for the text of those articles, and this explanation does not rest an argument on it. And checks in the plural, which reads as a recurring activity rather than a single exercise at the licensing stage.

The Regulation does not define independent here, and this explanation will not supply a binding definition for a word the instrument left open. What the Institute reads the word as guarding against is the circularity of a programme checked by the person who runs it: if the waste management officer writes the procedures, applies them, and then audits his own application of them, the check has no information in it that the officer did not already have. In the Institute's view - and this is our reading, not the text - what a facility should settle with the Ministry is who performs the checks, how often, and to whom the findings go. Those three points are what make the difference between a check and a formality.

Note also what the paragraph makes the checks measure against. Not the programme's own procedures, but the requirements necessary to protect human health and the environment. So a check that reports full compliance with internal procedures, where those procedures are themselves inadequate, has answered the wrong question. A test to the same effect appears at the head of Article 93, in slightly different words, where storage is forbidden except in the manner that achieves the protection of human health and the environment.

The eight required contents, and the two usually missing

The third paragraph lists what the quality assurance documents must contain. The eight items are reproduced in the table below as the article states them. Read together they describe a file that answers four different questions: what waste exists and where, what the facility physically is, what was measured, and what has left.

Item 1 is the inventory, and it is the item with the most inside it. The documents must contain the inventory of radioactive waste, including its origin and location, its physical and chemical characteristics, and the record of radioactive waste for disposal discharged from the facility in accordance with what it has been licensed for. Four of those five elements are routinely present in some form. The one that is usually absent is origin: a store whose containers say what is in them but not which procedure or department generated them cannot support the minimisation duty in Article 86, because nobody can see where the volume comes from.

Item 2 asks for site plans, engineering drawings, and the specifications and description of the operations. This is the item small facilities skip, on the reasonable-sounding ground that the store is a room and the room is obvious. It is not obvious to a responder or an inspector, and it is the document that makes the twelve features of Article 93 checkable: the water-impermeable floor covering with containment edges and slight slopes to a central liquid collection area and slopes, the ventilation, the partitions and the boundaries that have to be clearly shown are all features of a drawing before they are features of a room.

Items 4 and 5 are a pair and they are the second thing usually missing. The documents must contain the methods of environmental evaluation and safety evaluation and the means of calculating them, and then separately the results of those evaluations. The method and the result are two of the eight contents, not one. A file that holds a conclusion without the method cannot be checked by anybody, which defeats the independent checks in the paragraph above; and a method with no result has not been applied. Item 1 of Article 82 had already required the evaluations themselves - this is the article that says the calculation steps have to be kept.

One measurement point belongs with items 4 and 6, and it is the Institute's observation rather than a provision of the article. A monitoring result that says not detected means less than some value, not zero, and it carries no information unless the detection limit achieved is recorded with it. It follows that a programme whose detection limit sits above the discharge limit cannot demonstrate compliance however often it is run - which is the practical content of the words sufficient detail and accuracy in item 2 of Article 90. Record the detection limit beside every result, and state it in the method under item 4.

Item 7 looks administrative and is the quiet backbone of the file. Determining the identification numbers of radioactive waste packages is what lets every other record point at a specific object. Without package numbers, the inventory in item 1, the performance log required by item 9 of Article 93, the annual report under Article 96 and the acceptance criteria referred to in Article 91 are four lists that cannot be reconciled with each other. With them, a single number ties the container to its origin, its measurement, its store entry date and its departure. If a facility fixes one item from this article first, this is the one that makes the others possible.

Item 8 closes the loop: data on the waste that has been disposed of and the place of its discharge. Together with the disposal route in Article 91 and the annual report in Article 96, this is what turns a store into a system with an exit. It is also the item that will be read first if a container is ever asked after.

Building the file in an order that works

A facility that has none of this and reads the list top to bottom usually starts at item 1 and stalls, because a full inventory is the largest single task on the list and the one that depends on everything else. The order the Institute recommends in a documentation review is different, and it is our recommendation rather than anything the article prescribes: the article lists contents and does not set a sequence.

Start with item 7, the package identification numbers, because every other record needs something to point at. Then item 2, the plans and drawings, because they are a one-off piece of work that makes the storage requirements of Article 93 checkable. Then items 4 and 5 as a pair, method then result, because item 1 of Article 82 required the evaluations anyway and the independent checks cannot proceed without the method. Then item 1, the inventory, which by this point has numbers to hang on and locations to refer to. Items 3 and 8 then accumulate on their own as the system runs, provided somebody has decided where they are written. Item 6 does not. The results of environmental impact monitoring and the discharge and emission rates are the only measured quantities on the list, and no data exist for them until a monitoring programme has been designed: which nuclides, in which medium, at which points, how often, by what method, and to what detection limit. Item 2 of Article 90 already requires that the monitoring and recording be in sufficient detail and accuracy to demonstrate compliance, which is a design duty before it is a record-keeping one.

Questions this article gets asked

How the Institute can help

Article 94 produces two findings in nearly every documentation review we carry out, and they are the same two. The first is a programme that exists internally but was never submitted for endorsement with the licence application, which is what the article asks for. The second is a file that holds the results of the safety and environmental evaluations with no record of the methods and the working, so items 4 and 5 are half satisfied and the independent checks have nothing to examine.

Radiation Protection Officer training that covers the waste chapter and the quality assurance duties, advisory support in drafting the programme for submission under Article 94 and in setting up a package numbering scheme that the inventory and the performance log of Article 93 can both use, help in structuring the evaluation files so that method and result are separable as items 4 and 5 require, and a documentation review that maps what you hold against the eight items one by one and writes the gaps so they can be put in front of the Ministry with a plan. The environmental and safety evaluations themselves, where they need measurement of activity or concentration, draw on specialist partners; the Institute does not carry out laboratory analysis, instrument calibration or equipment testing.

Scope of what the Institute does: training and consulting. Field radiation surveys are carried out through specialist partners. The Institute does not carry out laboratory analysis, instrument calibration or equipment testing.

A note on the authority named in the text. The Regulation says the Council, meaning the Supreme Council for the Environment and Natural Reserves. That body no longer exists. Competence today sits with the Ministry of Environment and Climate Change, and the unit concerned is named in the organisational decisions as the Radiation Protection Department. The word Council is kept where this explanation renders what the instrument itself says, because that is the instrument's own word; in the Institute's own advice it is written as the Ministry. Read Council as the Ministry throughout.

This explanation is published for awareness by the radiation protection team at ALDuha Institute for Training and Environmental Consulting. The English text is an explanation, not a certified translation: the Arabic text published in the Official Gazette governs in case of any difference, and the official Arabic wording of every article discussed here is quoted in full on the Arabic version of this article. This explanation is introductory. It is not a legal opinion, it does not replace the conditions of your own licence, and it does not replace review by the regulator. Last updated 4 October 2026.