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AzSPU Procedure for Management of Radioactive Materials & Radiation Generators

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 Roles and responsibilities of emergency response personnel (i.e. who will put the plan

into effect).

 Details of the equipment to be used (i.e. the „emergency kit‟).

The ERP may be a stand-alone document, or it may be part of the radiation procedures.

5.2.3.9 Classified / Category A Personnel

Where work requires Classified / Category A Personnel (persons likely to receive an effective

dose in excess of 6 mSv per year, or an equivalent dose that exceeds three-tenths of any

relevant dose limit

- see definitions Appendix A), the contractor must provide suitable

people. The contractor will provide a suitable radiation dose monitoring system for such

people and ensure adequate medical surveillance.

The above will be applied retrospectively in the case of contractors already carrying out work

with ionising radiation on AzSPU managed sites.

5.2.4 Completion of Contractor’s Checklist by AzSPU Site RPS

Prior to any work with ionising radiation being carried out for the fist time on an AzSPU

managed site, the Site RPS will carry out an audit of the contractor, using the Contractors

Checklist (Appendix M).

The aims of the Checklist are to enable the Site RPS to verify that the Contractor‟s personnel:

 have the necessary Special Permit for the work;

 have the necessary details regarding radioactive materials;

 have the necessary equipment for restricting exposures;

 have suitable and sufficient radiation monitoring instruments for monitoring radiation

levels in the workplace and in the event of an accident, and that the instruments have been

tested;

 have copies of the radiation procedures/local rules;

 have sufficient RPOs to cover the scope of work;

 have suitable personal dose meters;

 have copies of their Emergency Response Plan and that any kit identified in the ERP is

available and in good order;

 have suitable arrangements for accounting for any radioactive materials.

The information that the contractor is required to have could include decay charts, wipe-test

certificates, authorisations, registrations and calibration certificates.

In the event that a Contractor does not meet the criteria set down in the Contractors Checklist

then the Site RPS will notify the Site Manager / OIM. The OIM will decide whether or not to

allow the work to go ahead and record his decision on the Contractor‟s Checklist.

A permit will not be issued for work with ionising radiation unless the Contractor‟s Checklist

has been completed and been signed by the Site RPS and the Contractor‟ representative and if

necessary the Site Manager / OIM.

5.2.5 General Arrangements for Managing Contractor Sources on Site

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5.2.5.1 Storage of Radioactive Substances

The basic principles to be applied in the case of storing radioactive substances are to ensure

that there is adequate security and that the materials are stored such that persons in the

vicinity are not exposed to significant levels of radiation. The materials should also be stored

such that there is unlikely to be any damage to the containment system that could lead to a

release of radioactive substances into the work area.

All contractor radioactive substances must therefore be stored to prevent unauthorised access

to those substances. Any small easily transportable container or package that contains

radioactive substances must be kept locked and in a dedicated storage area that is accessible

only to the contractor, the AzSPU Site RPS and the Site Manager / OIM.

The storage area must provide protection from the effects of the weather. In the case of

radioactive substances that are transported to site in secure overpacks, that can not be easily

transported by an individual or individuals, then it is acceptable to store the substances in

these overpacks provided rainwater could not accumulate in or on the container.

Source containers must be stored so that the dose rate at the boundary of the storage area does

not exceed 7.5µSv/h. Any area in which the whole body dose rate does exceed 7.5 µSv/h

must be designated as a Controlled Area and barriered.

Sources must not be stored with explosives or pyrophoric material. The Site RPS should use

his judgement as to the extent that each should be separated, taking into account the

protection afforded by the transport containers and the quantity of explosives present.

5.2.5.2 Source Records

Each time radioactive substances are brought onto an AzSPU managed site, the Site RPS

must record the details of the radioactive substances in the Site Mobile Source Movement

a radioactive substance is either transported off the site or installed in plant equipment e.g.

nucleonic gauges.

Occasionally there is a requirement for small radioactive marker sources to be fixed down

hole (e.g. Cobalt-60 sources). Once these sources have been fixed down hole the Source

Movement Register should be updated with details of the particular well and the depth at

which the source was installed. Details of the source and its location should then be added to

the Site Inaccessible Source Register (Appendix O).

The same arrangements should be made for well logging sources that are stuck down hole and

are deemed irretrievable.

5.3

General Work Instructions for Working with Ionising Radiation

The following general instructions should be followed for all work with ionising radiation

carried out by Contractors. Instructions specific to the nature of the work are also given in

Section 5.4 Work Instructions for Site Radiography, Section 5.5 Work Instructions for Well

Logging, and Section 5.6 Work Instructions for Storage and Use of Pip Tags, and Section 5.7

Work Instructions for Nucleonic Devices.

 The contractor will have procedures for the safe use of the sources available on Site. A

risk assessment must be available for the operation.

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

The contractor will appoint one or more of his employees on the Site as the RPO. The

contractor‟s RPO will co-ordinate with the AzSPU RPS in all aspects of the work

involving ionising radiation. He will provide his procedures and registrations to the

AzSPU RPS.



Work with ionising radiation comes within the Permit to Work System (ISSOW). An

appropriate permit must be raised prior to work starting.



The AzSPU Site RPS must complete the Contractors Checklist (Appendix M) to confirm

that all of the contractor arrangements are satisfactory before work commences.



Contractor sources must be recorded as mobile sources in the Mobile Source Register

(Appendix N).



Announcements of impending radiation work will be given over the Site public address

system as part of the PTW requirements, at

30 and 15 minutes before the work

commences. The announcement will give the location and duration of the work.



A Controlled Area will be designated for the duration of the work and will include areas

above and below the work site if necessary.



In general only the contractor‟s personnel will work within the Controlled Area.



There must be at least two individuals in the contractor‟s team and at least one of them

must be an RPO.



The dose rate at the boundary of the Controlled Area must not exceed

7.5 µSv/h.



Mobile barriers or bunting tape will be erected around the Controlled Area.



Warning signs will be erected around the Controlled Area indicating the radiation hazard

e.g. “Controlled Area. External Radiation Risk. No Entry”.



The Contractor must provide calibrated monitors appropriate to each type of radiation

used e.g. gamma and neutron.



An announcement will also be made when the work is completed.



All sources must be returned to the radioactive substance store when not in use.

NB: Instructions for contractors involving incidents with ionizing radiation are included

within the AzSPU Radiation Contingency Plan (AzSPU-HSSE-DOC-00086-2).

5.4

Work Instructions for Site Radiography

Radiography is used on AzSPU Sites to verify the integrity of welds, corrosion studies and

other NDT investigations.

The radioactive sources that are most commonly used in industrial radiography are listed

below with corresponding details of the maximum activity of source that should be used on

any AzSPU Managed Site.

Maximum source activities for general radiography use are:

Source

Maximum Activity

Iridium - 192

1000 GBq

Ytterbium - 169

5000 GBq

Selenium - 75

2000 GBq

Cobalt - 60

Each job must be discussed

with the RPA

In addition to the General Work Instructions for Working with Ionising Radiation (Section

5.3), the following specific instructions are applicable:

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

In the case of industrial radiography carried out onshore, all work with transportable

items will be carried out in a dedicated radiography enclosure, unless the risks associated

with the transport of the item to be inspected or resulting from the delay in transporting

the item, outweigh the risks of carrying out site radiography.



Where a contractor proposes to use either a cobalt-60 source (which is a high energy

gamma source), or a source with an activity higher than listed in the table above for that

type of source, the RPA must be consulted prior to the work commencing.



The RPA must also be consulted where the contractor proposes to use a source type that

is not listed, including X-ray equipment.



If the work piece to be tested is portable, it should be taken to a dedicated area for

radiography.



The area used for radiography on Site must be described in Site-Specific Instructions for

that Site. If the work piece is not portable, radiography must take place with the area

down-manned as far as possible.



If possible, the work should be carried out when other people are not around, for example,

at night or at meal breaks.



Flashing amber warning lights will be erected at all entrances to the Controlled Area.



A flashing red warning light will be situated adjacent to the source exposure position

while an exposure is underway.



Warning signs will be erected around the Controlled Area indicating the radiation hazard

e.g.

“Controlled Area. External Radiation Risk. No Entry” and will include an

explanation of the meaning of the warning lights e.g. “Amber Light: Radiation Imminent”

and “Red Light: Radiation Exposure Underway”



The Controlled Area must be thoroughly searched prior to any exposure.



A horn or whistle must be sounded just before exposure. The significance of this warning

must be indicated to the work force.



The Contractor must provide two suitably calibrated radiation dose rate monitors.



The Contractor must ensure that the source is back in its container at the end of the

operation by checking with a suitable meter.



An announcement will also be made when the work is completed.



All sources must be returned to the radioactive substance store when not in use.

NB: Specific instructions for contractors involving incidents with radiography sources

are included within the AzSPU Radiation Contingency Plan (AzSPU-HSSE-DOC-00086-

2).

5.5

Work Instructions for Well Logging

Well logging is used extensively on AzSPU Installations to obtain petrophysical, geological

and directional data.

The radioactive sources most commonly used in well logging tools are:

Source

Maximum Activity

Caesium-137

Up to 60 GBq

Americium-241/Beryllium

Up to 600 GBq

Additionally, some logging tools generate Pulsed Neutrons and incorporate around 60 GBq of

hydrogen-3 (also called Tritium).

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In addition to the General Work Instructions for Working with Ionising Radiation (Section

5.3), the following specific instructions are applicable:

 On occasion it may be necessary for workers who are not part of the logging crew to

work within the Controlled Area e.g. a driller working in the dog-house during

logging operations. In this instance the contractor will provide a written system of

work for such individuals and make an assessment of the individual‟s radiation

exposure. Details of the exposure will be passed to the Site RPS to record in a

Radiation Exposure Log (Appendix E).

 Before any sources are run down hole, it must be ensured that there is free access for

the logging equipment to prevent it from becoming trapped.

 The contractor must ensure that the logging tool is free from sand, clay or other dirt

before the source(s) is installed in the tool.

 Remote controlled devices (e.g. handling tools) must be used when removing sources

from shields and inserting into the down-hole tool.

 The Contractor must ensure that the source or sources have been loaded into the

down-hole tool prior to leaving the drill floor by carrying out radiation monitoring in

the area.

 When the source or sources are returned the logging engineer will carry out another

radiation survey to ensure that the sources have been correctly loaded into the

storage/transport containers.

 The above precautions also hold if a logging while drilling source is loaded and

removed from the tool. On these occasions, the Controlled Area may go down

through several decks as the sources are run into the well.

NB: Specific instructions for contractors involving well logging radioactive source

incidents are included within the AzSPU Radiation Contingency Plan (AzSPU-HSSE-

DOC-00086-2).

5.6

Work Instructions for the Storage and Use of Pip Tags

Pip tags, or depth correlation subs, are small sources that are inserted into the casing or tubing

string at a known point. The string is then installed in the well. The pip tag then acts as a

reference point for subsequent well logging.

Pip tags are usually Cobalt-60 sources. There are requirements over the control, storage,

disposal and notification of loss of the sources. Whenever possible the source should be

loaded into the collar or pup joint before transportation to the Site or rig.

In addition to the General Work Instructions for Working with Ionising Radiation (Section

5.3), the following specific instructions are applicable:

On receipt of the pip tag sources offshore they must immediately be taken to the source store

and placed inside. The well logging contractor must have his own source store. If the pip tag

is already installed in a collar or sub, it cannot be stored in the source store. The dose rate at

the surface of the collar or sub will be measured. An assessment of the external radiation risk

associated with the use and handling of the collar or sub must be carried out. If this risk

assessment indicates potential exposure to any member of the workforce in excess of 1mSv

per year, a supervised area must be established. If the dose rate exceeds 7.5μSv/h, a

controlled area with a barrier must be set up at the 7.5μSv/h contour. Signs giving warning of

the controlled or supervised area must be displayed in suitable positions indicating the nature

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of the radiation sources and the risks arising from such sources. Details of the sources will be

entered on the form in Appendix N Mobile Source Register.

If the source has to be loaded into the collar or pup joint on the Site/rig, it must not be touched

by the fingers but handled using tweezers or tongs.

It is unlikely that a controlled area will be merited for pip tag work, but it is good practice to

provide a supervised area when handling pip tags and to barrier and mark that area.

The area must be prepared before use to aid source recovery if dropped. Whenever possible, a

tray (with a soft cover on) should be placed beneath the source loading area during the

operation.

All sources must be returned to the store when not in use and the keys returned to the OIM.

Where milling operations are likely to mutilate or destroy a pip tag located down a well, this

information must be immediately relayed to the AzSPU RP SPA and the RPA.

When the pip tag is installed in the well, the entry in the Mobile Source Register must be

closed out, with the well no. in which the pip tag has been installed. It must then be entered

in Appendix O Inaccessible Source Register. The position of any pip tags must be marked in

the well file. Although not required by legislation it is also good practice to have their

presence marked on the wellhead.

5.7

Work Instructions for Nucleonic Devices

Radioactive sources can be installed as part of nucleonic instrumentation for:

 Monitoring and/or controlling density of fluid flowing through pipelines;

 Monitoring and/or controlling liquid levels in vessels;

 Detecting interface between fluids of different densities such as water, oil and gas in

vessels.

Nucleonic devices incorporate sealed sources of radioactive material that emit penetrating

gamma radiation. The varying absorption of the emitted radiation by the medium under

investigation and the subsequent detection of the attenuated radiation provides the basis of the

measurement techniques.

In the case of level or density gauges the sources are usually housed in heavily shielded,

secure steel and lead containers that are mounted onto vessels or pipes.

Some interface measuring / detecting devices are mounted with the source or a string of

sources located inside a vessel in a dip pipe, with an external housing into which the source(s)

can be withdrawn and shielded. The detector is also mounted external to the vessel.

For the above nucleonic devices, the type and activity of the source is determined by a

number of process parameters including vessel wall thickness and distance from source to

detector. Most nucleonic devices incorporate caesium-137 sources, but cobalt-60 is also used

in some situations due to the higher penetrating power of the gamma rays emitted.

Density profiling instruments (the „Profiler‟), used for density measurements through the

depth of a vessel, use an array of americium 241 sources, which may extend to a few metres

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in length. The sources are contained within a source rod housed in a titanium dip pipe. The

device also incorporates an array of detectors in close proximity to the sources; there are no

detectors external to the vessel. Due to the low energy of the gamma radiation emitted from

americium-241, it is not normally possible to measure a dose rate on the outside of a vessel

fitted with a profiler.

5.7.1 Management Arrangements

Site Management have the ultimate responsibility for ensuring that installed nucleonic devices

are used in compliance with this procedure. This responsibility cannot be delegated to

employees, workers, the radiation protection supervisor (RPS), the RPA, the AzSPU RP SPA,

or anyone else.

All persons who may be affected by the content of these procedures should be made aware of

the relevant details. Site management will enable a free flow of radiation protection and

safety related matters between workers and management.

5.7.2 Critical Examination on Installation

Sections 5.2 and 5.3 must be applied in the case of Contractor‟s installing nucleonic devices.

In addition, the following requirements also apply:

A critical examination will be carried out when a nucleonic device is either installed for the

first time, or when any work is carried out on the device that could affect the safety aspects of

the device. It is the responsibility of the Contractor installing the device to carry out the

critical examination.

A site RPS will be present at the time of the Critical Examination to confirm the checks

carried out by the installer and he will complete the Critical Examination Checklist (Appendix

H). The RPS should ensure that the installer includes a check on the surface dose rate and the

dose rate at 1m and records the results in the Critical Examination Report.

Once the RPS is satisfied that a gauge has been installed satisfactorily, he will countersign the

Contractor‟s check-sheet to confirm that the checks have been carried out and that he agrees

with the results.

The site RPS will also sign the relevant documentation to formally accept the transfer of

ownership of the radioactive source(s) from the Contractor. The RPS will retain copies of the

source transfer document, the Contractor‟s Critical Examination Report and his own Critical

Examination Checklist. These will be retained in the Site Radiation Records.

5.7.3 Controlled and Supervised Areas

Controlled areas:

Controlled areas will be designated in accordance with the Radiation Protection Programme

requirements (see Section 5.1.1).

In most situations it should be possible for the Company installing the nucleonic devices to

ensure at the planning stage that the conditions requiring a designation of a Controlled Area

will not be created.

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In the event that a Controlled Area is required, the site RPS will contact the AzSPU RP SPA

and RPA for further advice.

In addition, the dose rate at 1 m from a nucleonic device must not exceed 3 Sv/h and the

dose rate on the surface of the device must not exceed 100 Sv/h.

During vessel entry operations, it will be necessary to designate a Temporary Controlled Area

to allow access to the inside of the vessel, see Section 5.7.9.

Supervised Areas:

A Supervised Area will be designated around each installed nucleonic device to within 1

metre of the source housing and the detector.

Supervised Area signs are not required. Access to Supervised Areas will not normally need

to be restricted.

5.7.4 Site Register of Installed Sources

The Site Manager is responsible for ensuring that an up to date Site Register of Installed

Sources is kept; on a day-to-day basis this will be maintained by the RPS. The Register will

be updated each time a new source(s) is installed on site or whenever a source(s) is removed

from site, even temporarily. The Register forms part of the Site Radiation Records and is a

controlled and auditable record. The Register must contain the following information for

each source:

 Type of source (e.g. caesium-137);

 Source serial number (or other unique identification mark);

 Date of receipt (i.e. the date that the source was installed and ownership transferred);

 Activity of the source at the date of receipt or previously recorded date (manufacture);

 Current location of each source;

 For sources transferred from site, the date of transfer and the destination.

Additionally, a Site Map of Radioactive Source Locations, including source storage areas,

will be compiled and maintained by the RPS. This will be shared with the ERT.

5.7.5 Source Accounting

An RPS or an Authorised Person will account for each installed radioactive source on a

monthly basis. The purpose of the accounting check is to confirm that the source has not

been stolen or tampered with. A visual check on the actual source would incur unnecessary

exposure to the individual involved. Instead, the check will be carried out to confirm visually

that the source holder is in place and padlocked and that the source holder and/or padlock

have not been tampered with. For devices that are normally inaccessible, this check can be

confirmed using binoculars.

The source accounting checks will be recorded on the Radioactive Source Accountancy,

Monitoring and Safety Checks record form (Appendix I).

An inventory of radioactive sources for each site must be sent to MENR, MES and Ministry

of Health before 15 December each year. The Permitting and Regulatory Affairs Adviser will

be responsible for this, working with the AzSPU RP SPA.

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5.7.6 Radiation Monitoring

The purpose of carrying out radiation monitoring is to demonstrate that radiation levels have

not changed significantly and that the area designation has not changed.

The monitoring should demonstrate that the dose rates that are accessible do not exceed 3

Sv/h at 1 m from the source housing and 100 Sv/h on the surface. In addition, the dose rate

at 30 cm from the source housing, detector or the surface of the vessel on which the nucleonic

device is installed should not exceed 7.5 Sv/h and 75 Sv/h for hand or forearm access.

Radiation monitoring will be carried out around each installed source or nucleonic gauging

device once a month, at the same time as the Source Accounting Check. Either the RPS or an

Authorised Person using a suitable dose rate meter that has been tested within the last 12

months will carry out the check.

The radiation monitoring results will be recorded on the Radioactive Source Accountancy,

Monitoring and Safety Checks Records Form (Appendix I) - the status of the shutter (i.e. open

or closed) at the time of the measurements will be recorded.

5.7.6.1 Nucleonic Level Alarms

The dose rate will be measured on the source housing, at 30 cm from the housing and the

detector and at 1 m from the source housing.

5.7.6.2 Interface Gauges

The source(s) is normally installed in a dip pipe inside the vessel, so the dose rate should be

measured at 30 cm from the surface of the vessel, or the next nearest accessible point. The

dose rate should also be measured at the detector.

5.7.6.3 Profiler Gauges

The sources are installed in a dip pipe inside the vessel. The americium-241 sources used in

the Profiler gauge emit low energy gamma rays, which do not have enough energy to

penetrate the vessel walls. It will not normally be possible to measure a dose rate outside the

vessel. A check should be carried out to ensure that there are no elevated dose rates around

the vessel or the device.

5.7.7 Maintenance and Safety Checks

5.7.7.1 Maintenance

Nucleonic gauges can be affected by the environment in which they are used, which may

result in the radiation safety and protection of the gauge being adversely affected, for

example, shielding may be degraded, shutters may stick, warning notices may become

illegible, etc. It is therefore important that gauges are included in a routine maintenance

schedule. Persons carrying out the maintenance work need to be aware of the radiation

hazards and be appropriately trained.

5.7.7.2 Safety Checks

The RPS or Authorised Person will carry out the following routine safety checks at the same

time as the source accountancy and radiation monitoring checks:

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 Inspect the general condition of the nucleonic device for wear, corrosion etc. and to

confirm that it is securely mounted.

 Check that the padlock on the source holder is still in place and is in good condition.

 Check that the source detail plate and warning sign on the nucleonic device and the

warning signs on the vessel are still in place and in good condition.

 Check the condition of the shutter mechanism ensuring that the shutter has not been

padlocked in the “OPEN” position and that the status of the shutter is clearly visible.

At least once a year, the operation of gauge shutters should be tested and sources installed in

dip pipes should be isolated and de-isolated to ensure the continued safe operation of the

devices; this should be carried out by the RPS or an Authorised Person, with the permission

of the Control Room.

The results of these checks will be recorded on the Radioactive Source Accountancy,

Monitoring and Safety Checks Record Form (Appendix I).

5.7.8 Leakage Testing

When a new radioactive source is purchased it should be supplied with a certificate

confirming that it is free from contamination. Sealed sources used in nucleonic gauging

devices must thereafter be tested for leakage at least once in every 24 months, or annually in

the case of sources that are older than

15 years. Gauges that are used under harsh

environmental conditions (e.g. high temperature, corrosive chemicals, and high levels of

vibration) may need to be checked more frequently.

The purpose of the leakage test is to confirm that the source capsule is intact and that there is

no leakage of radioactive material. Given that a direct test of the source capsule would cause

a significant exposure to the person carrying out the test, an indirect method will be used

instead. This involves wiping the external surface of any part of the gauge where leakage

could reasonably be detected e.g. at the source holder / shutter mechanism.

The Site RPS or an Authorised Person who has received the appropriate training will carry

out the test. Alternatively, the test may be carried out by the RPA during the annual audit.

The procedure for carrying out a leak test is given in Appendix J. Wipes should be sent to the

AzSPU approved laboratory for analysis.

The certificate issued by the laboratory will require the signature of the person doing the wipe

test to confirm that the swab was taken in accordance with the procedure.

Where the wipe test is carried out by the RPA, the certificate will be signed by the RPA.

Copies of the leak test certificates will be maintained in the Site Radiation Records for a

period of at least two years.

5.7.9 Entry to Vessels Fitted with Nucleonic Devices

During routine operating conditions it is not normally possible to access the internals of a

vessel on which a nucleonic(s) is installed. However, during shutdown or maintenance

activities, vessel entry may be required.

Prior to vessel entry, a Site RPS will isolate any sources that are installed on the vessel. This

must only be carried out with the permission of the Area Authority. The isolation procedures

for sources installed in dip pipes and for the Profiler sources are given in Appendices J and K,

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respectively. In the case of level and density gauges, the sources can be isolated by simply

closing the shutter on the source housing / container. The shutter should then be locked in the

“SHUT” or “CLOSED” position using a padlock. The padlock key will be kept by the RPS

until the source needs to be de-isolated.

The RPS is responsible for ensuring that the isolation procedure has been carried out and for

reinstatement and signing the work permit and/or isolation control certificate as appropriate.

5.7.9.1 Temporary Controlled Area

The inside of the vessel is normally designated as a Controlled Area due to the potential for

exposure to significant dose rates.

At the first opening of the man-way into the vessel, the RPS will confirm that the source(s)

have been isolated by monitoring inside the vessel with an intrinsically safe dose rate meter.

Provided there are no dose rates in excess of 7.5µSv/h, work can commence and the area can

be de-designated. It is not necessary to record the dose to the RPS in this instance. If the

dose rate is in excess of 7.5µSv/h, the RPS will withdraw and check that the source isolation

procedure has been carried out correctly. It should be noted that an exposed source, or

sources, would give rise to dose rates substantially in excess of 7.5µSv/h.

5.7.9.2 Naturally Occurring Radioactive Material (NORM)

If there is reason to suspect the presence of naturally occurring radioactive material in the

vessel then a check must be carried out before entry to the vessel is permitted. If NORM is

detected the AzSPU Procedure for Management of NORM (AzSPU-DOC-HSSE-00097-2)

must be followed and a task based risk assessment carried out. It should be noted that NORM

deposits could influence the dose rate measurement made above. A Controlled Area must be

designated for entry to a vessel containing NORM.

5.7.10 Precautions for Vessels Incorporating Nucleonic Interface Gauges

During normal operations, the source is retained in a dip pipe inside the vessel and the fluids

inside the vessel provide adequate shielding. If the liquid level inside the vessel falls, or is

lowered, it is possible that radiation dose rates outside the vessel will increase; the dose rate

that is likely to be present in the event of the loss of liquid level would be around 50 µSv/h.

In this event, the Control Room Operator will instruct an Authorised Person or RPS to retract

the source(s) into the shielded container and to lock the device in the “SHUT” position. The

RPS will retain the key and will ensure that the source is not exposed until the fluid level has

increased to the normal level.

For operational reasons it may occasionally be necessary to operate the gauge with the source

exposed above the liquid level. In these circumstances the RPS must measure the radiation

dose rate outside the vessel. If the dose rate exceeds 7.5 Sv/h then a Controlled Area should

be designated and signs and barriers should be put in place.

5.7.11 Removal of an Installed Nucleonic Device

Under no circumstances may a radioactive source be removed from its shielded

container.

Prior to removing an installed nucleonic device, the AzSPU RP SPA and the RPA must be

consulted and a task risk assessment must be carried out.

Control Tier:

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If it is necessary to remove the device from the vessel, either temporarily or permanently, the

RPO must ensure that the appropriate source isolation has been carried out and confirm this

by checking with a dose rate meter. The container may then be moved to an appropriate

storage location.

If the nucleonic device is refitted, the RPS will remove the padlock and open the shutter. The

RPS will then monitor the area and confirm that the readings are consistent with those made

during the critical examination. If they are not then the source(s) must be isolated, the area

monitored and the AzSPU RP SPA and the RPA contacted.

5.7.12 Temporary Storage of Nucleonic Devices

To ensure the safety and security of the sources, a temporary storage facility should:

 provide adequate shielding;

 be physically secure (e.g. locked when not in use);

 not be used as a general storage area for other goods;

 be fire proof and not contain other hazardous materials (e.g. flammable liquids and

explosive materials);

 be dry;

 be appropriately labelled (e.g. radiation trefoil and warning notices with the legend

“RADIOACTIVE” in English, Azerbaijani and Russian).

When nucleonic devices are placed into temporary storage, a daily accounting check should

be carried out by a RPS; and the Site Register of Installed Sources amended to reflect the

change of location.

5.7.13 Source Disposal

As soon as a nucleonic device becomes redundant, i.e. when there is no foreseeable use for

the device, arrangements should be made for its disposal and the AzSPU RP SPA and the

RPA should be informed. The means of disposal will normally be return of the device to the

supplier. The entire nucleonic device should be removed, in preference to just the source(s).

However, if this is not practicable for operational reasons and only the source(s) is removed,

then all warning signs should be removed from the device and a tag should be attached which

indicates that the radioactive source has been removed.

The supplier should be contacted to arrange for personnel to decommission the device. This

will require Sections 5.2 and 5.3 to be followed. Additionally, the AzSPU RP SPA and

Permitting and Regulatory Affairs should be notified of the planned disposal and the intended

change to the inventory of sources.

It must be ensured that the Contractor has the necessary Special Permit to carry out the work

and any other permissions and export licences required to dispose of the source(s). It should

also be ensured that the Contractor has made arrangements for onward shipping and where

necessary, temporary storage.

On completion of the work the Site Register of Installed Sources must be updated to reflect

the change in the source inventory and the source transfer documents should be added to the

Site Radiation Records.

At no time should a BP employee remove a radioactive source from a nucleonic device.

Control Tier:

2-AzSPU

Revision Date: October 04, 2010

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Key Documents/Tools/References

This procedure shall, where appropriate, be used in conjunction with the following AzSPU

procedures:

Document Number

Title of Procedure

AzSPU-HSSE-DOC-00097-2

AzSPU Procedure for the Management of NORM

AzSPU-HSSE-DOC-00086-2

AzSPU Radiation Contingency Plan

AzSPU-HSSE-DOC-00115-2

AzSPU Procedure for Transportation of Radioactive

Materials.

AzSPU-HSSE-DOC-00083-2

AzSPU Procedure for The Import / Export of Radioactive

Materials and Sources of Ionising Radiation

AzSPU-HSSE-DOC-00025-2

AzSPU HSSE Document Management Procedure

AzSPU-HSSE-DOC-00021-2

AzSPU HSSE Definitions

AzSPU-HSSE-DOC-00002-2

AzSPU SSOW Procedure for Control of Work

AzSPU-HSSE-DOC-00011-2

AzSPU Procedure for Deviations

AzSPU-HSSE-DOC-00060-2

AzSPU Procedure for Permit to Work

AzSPU-HSSE-DOC-00054-2

AzSPU Incident Reporting and Investigation Procedure

AzSPU-HSSE-DOC-00072-2

AzSPU Review/Revision Process for HSE Tier 2 Procedures

- Terms of Reference (ToR)

AzSPU-HSSE-DOC-00063-2

AzSPU SSOW Procedure for Task Risk Assessment

Revision/Review Log

Revision Date

Authority

Custodian

Revision Details

20 October 2004

Alan McNulty

Abbas Islamov

Initial Issue

07 November 2008

Alan McNulty

Adalat Mammadov

Note: the next review/revision date is

extended to

01.03

2009 due to

rescheduling

05 December 2008

Yuliy Zaytsev

Adalat Mammadov

Authority position/name has changed to

reflect org changes in HSE&TD as of

December 1st 2008

24 June 2009

Yuliy Zaytsev

Adalat Mamedov

Next revision date extended to 15 July

(Safety &

(Central Safety TL)

2009 due to rescheduling

Compliance

Manager)

31 July 2009

Yuliy Zaytsev

Niyaz Mamedov

Document substantially reworked with

(Safety &

(HSE

input from AzSPU‟s Radiation

Compliance

Systems/CoW

Protection Advisor and expanded to

Manager)

Advisor)

include the following:

 AzSPU Ionising Radiation Policy.

 Radiation Protection Programme.

 Management of contractors working

with ionising radiation.

 Work instructions for site

radiography, well logging, pip tags

and nucleonic devices.

Control Tier:

2-AzSPU

Revision Date: October 04, 2010

Document No: AzSPU-HSSE-DOC-00058-2

Print Date: 2/1/2011

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7^th October, 2009

Yuliy Zaytsev

Idrak Nazarov

Information regarding naturally

(Safety &

(HSE MS Team

occurring radioactive materials (NORM)

Compliance

Leader)

has been removed from this procedure

Manager)

and incorporated into a separate AzSPU

Procedure for Management of NORM

(AzSPU-HSSE-DOC-00097-2).

Information regarding transportation of

radioactive sources has been removed

from this procedure and incorporated

into a separate AzSPU Procedure for

Transportation of Radioactive Materials

(AzSPU-HSSE-DOC-00115-2).

31st July 2010

Yuliy Zaytsev

Idrak Nazarov

Thorough revision require additional

(Safety &

(HSE MS Team

consultation with AzSPU RPA, hence

Compliance

Leader)

the document review requires to be

Manager)

extended

04th October 2010

Yuliy Zaytsev

John Elliott

Sub-paragraph 5.1.3.1 Monitoring of

(Safety &

(Senior HSE

Workers 3rd and 4th statement lines are

Compliance

Advisor)

updated

Manager)

Appendix A added new abbreviations

Appendix B updated contact details

information

Control Tier:

2-AzSPU

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AzSPU Procedure for Management of Radioactive Materials & Radiation Generators

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Appendix A - Definitions & Abbreviations

Term

Definition

Absorbed Dose

Quantity of energy imparted by ionising radiation to unit mass of

matter such as tissue. Unit gray, Symbol Gy. Replaced the rad as unit

of absorbed dose.

1 Gy = 1 joule per kilogram.

1 Gy = 100 rads.

Activity

Measure of an amount of a radionuclide. Describes the rate at which

transformations occur in it. Unit becquerel. Symbol Bq. 1 Bq = 1

disintegration per second.

ALARP

As Low As Reasonably Practicable. Means taking every reasonable

effort to maintain exposures as far below the dose limits as is

achievable, while taking into consideration the trouble, time and

money needed to control it.

ALT

Azerbaijan Leadership Team

Alpha Radiation

Positively charged particulate radiation comprising 2 protons and 2

neutrons, emitted from some radioactive materials during radioactive

decay. It has low penetrating power and short range

(a few

centimetres in air). Not considered an external hazard but materials

that emit alpha radiation represent a significant internal hazard.

AzSPU

Azerbaijan Strategic Performance Unit

Becquerel

See Activity.

Beta Radiation

Negatively charged particulate radiation identical to an electron that is

emitted from some radioactive materials during radioactive decay.

Exposure to a large amount of beta radiation from external sources

may cause skin burns. Beta radiation is also presents an internal

radiation hazard. Thin sheets of low-density materials such as

aluminium or plastic may stop beta particles.

CAM

Contract Accountable Manager

Classified

/ Category

A Classified / Category A person is one who is likely to receive an

Person

effective dose in excess of 6 mSv per year, or an equivalent dose that

exceeds three-tenths of any relevant dose limit. A Classified

Category A person should be informed if he/she is so designated.

Classified / Category A persons should be over 18 years old and have

a health record certified by doctor confirming they are fit for the job.

Contamination

The contamination by any radioactive substance of any surface

(including the surface of the body or clothing) or any part of absorbent

objects or materials or the contamination of liquids or gases by any

radioactive substance.

Controlled Area

A controlled area is an area in which specific protective measures or

safety provisions are or could be required for:

 controlling normal exposures or preventing the spread of

contamination during normal working conditions; and

Control Tier:

2-AzSPU

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 preventing or limiting the extent of potential exposures.

cps

Counts per second

CTM

Compliance Task Manager

Curie

Former unit of Activity with symbol Ci. Replaced by the S.I. unit the

Becquerel. 1 Ci = 3.7 x 10¹⁰ Bq or 37 GBq.

DC&I

Drilling, Completions and Interventions

Decay

The process of spontaneous transformation of a radionuclide. The

decrease in activity of a radioactive substance.

Designated Area

Designated Areas include Controlled and Supervised Areas.

Disposal

In relation to radioactive waste, dispersal or emplacement in any

medium without the intention of retrieval.

Dose

General term for a dose quantity such as absorbed dose, equivalent

dose, and effective dose.

Dose Limit

Dose Limit in relation to persons of a specified class is the limit on

effective dose or equivalent dose in relation to a person of that class.

Dose Rate

Dose Rate, in relation to a place, is the rate at which a person or part

of a person would receive a dose of ionising radiation from external

radiation if he were at that place.

Effective Dose

The quantity obtained by multiplying the dose equivalents to various

tissues and organs by the tissue weighting factor appropriate to each

and summing the products. Unit sievert, symbol Sv. Frequently

abbreviated to dose.

ERP

Emergency Response Plan - Document describing the actions to be

taken in the event of a radiation incident or emergency, the purpose of

which is to restrict any exposure that arises from an accident both to

the employees themselves and to others, including emergency services

personnel, who may be affected by it. Also called Contingency Plan.

ERT

Emergency Response Team

Equivalent Dose

The quantity obtained by multiplying the absorbed dose by a

weighting factor to allow for the different effectiveness of the various

ionising radiations in causing harm to tissue. Unit sievert, symbol Sv.

Replaced the unit rem. 1 Sv = 100 rems.

External Radiation

External radiation, in relation to a person, is the ionising radiation

coming from outside the body of that person.

GBq

Gigabecquerel (10⁹ Bq)

Gray

S.I. unit of Absorbed Dose. Symbol Gy.

Half Life

The time taken for the number of atoms in a radioactive material to

decay to half the original value.

HSE

Health, safety and environment

IAEA

International Atomic Energy Agency

Internal Radiation

Internal radiation, in relation to a person, is the ionising radiation

Control Tier:

2-AzSPU

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coming from inside the body of that person.

Ionisation

The process by which an atom or molecule acquires or loses an

electric charge. The production of ions.

Ionising Radiation

Radiation capable of causing ionisation either directly or indirectly

e.g. alpha and beta particles, neutrons, gamma rays and X-rays.

ISSOW

Integrated Safe System of Work

Site-Specific Instructions

Working procedures specific to a site where work with ionising

radiation is carried out. These may or may not include an Emergency

Response Plan.

LSA

Low Specific Activity. Term derived from transport legislation to

describe material with low specific activity that could include NORM.

MENR

Ministry of Ecology and Natural Resources

MES

Ministry of Emergency Situations

MPPU

Major Projects Performance Unit

Non-ionising radiation

Radiation that does not produce ionisation in matter. Examples are

ultraviolet radiation, light, infrared radiation, and radio frequency

radiation.

NORM

Naturally Occurring Radioactive Material. In the oil and gas industry

this is material that originates from reservoir rock that is associated

with production, maintenance and decommissioning activities.

Presents a risk to health and work with NORM and disposal of NORM

waste must be carried out in accordance with the applicable legislation

or standards.

OIM

Offshore Installation Manager

Overexposure

Any exposure of a person to ionising radiation to the extent that the

dose received by that person causes a dose limit relevant to that person

to be exceeded or causes a proportion of a dose limit relevant to any

employee to be exceeded.

PPE

Personal protective equipment

PSCM

Procurement and Supply Chain Management

PTW

Permit to Work

Performance Unit

PUL

Performance Unit Leader

rad

Former unit of absorbed dose. Replaced by the gray (Gy).

1 rad = 0.01 Gy.

Radiation

Energy in the form of waves or particles originating from radioactive

materials or radiation generating equipment.

Radiation accident

Accident where immediate action would be required to prevent or

reduce the exposure to ionising radiation of employees or any other

persons.

RPA

Radiation Protection Adviser / Qualified Expert - Person or body

Control Tier:

2-AzSPU

Revision Date: October 04, 2010

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appointed to give advice on radiation protection and compliance

matters.

RPO

Radiation Protection Officer - All third party contractors are required

to appoint a RPO to supervise their work.

RPS

Radiation Protection Supervisor - Person appointed to be responsible

for day-to-day supervision of work with ionising radiation and to

ensure that the radiation procedures and local rules are followed.

RP SPA

Radiation Protection Single Point Accountability

Radioactive

Exhibiting radioactivity.

Radioactive Waste

Material for which no further use is foreseen that contains or is

contaminated with radionuclides at concentrations greater than levels

set by the regulatory bodies.

Radioactivity

The phenomenon whereby atoms undergo spontaneous random

disintegration, usually accompanied by the emission of radiation.

Radionuclide

A species of radioactive atom.

Rem

Former unit of Equivalent Dose. Replaced by the S.I. unit the sieverts

(Sv).

RPA

Radiation Protection Advisor

SCSSIMP

State Committee for the Supervision of Safe Industrial and Mining

Practices.

Sealed Source

Radiation source containing a radioactive material and constructed to

ISO standards to prevent under normal conditions of use, dispersion of

the radioactive material into the environment.

Sievert

The S.I unit of both equivalent dose and effective dose. The symbol is

Sv. Sub multiples are milli Sieverts (mSv) and micro Sieverts (µSv).

One millisievert is one thousandth of one sievert and one micro sievert

is one thousandth on one millisievert.

SME

Subject Matter Expert

Source

ionising

Radioactive substance or device emitting or capable of emitting

radiation

ionising radiation

SPU

Strategic Performance Unit

Safety Series

Supervised Area

Any area not already designated as a controlled area but where

occupational exposure conditions need to be kept under review even

though specific protection measures and safety provisions are not

normally needed.

Unsealed

Radioactive

Radioactive material not in the form of a sealed source, e.g. gas,

Materials

liquids or solid powder.

Vice President

Written System of Work

A written method of work that permits non-classified workers who to

enter a controlled area.

Control Tier:

2-AzSPU

Revision Date: October 04, 2010

Document No: AzSPU-HSSE-DOC-00058-2

Print Date: 2/1/2011

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X-rays

Penetrating electromagnetic radiation similar in nature to gamma

radiation but generated by electrical equipment.

Appendix B - Qualified Expert / Radiation Protection Adviser Contact

Details

AzSPU has appointed Tracerco Radiation Protection Advisory Services as their Radiation

Protection Adviser (RPA) (which is equivalent to the term Qualified Expert used by the IAEA

and the EC).

The first point of contact is Donald Urquhart, who is based in the Tracerco office in

Aberdeen, UK. However, all of the RPAs who are based either in the Aberdeen office, or the

Tracerco Billingham office, are able to advise on any issues affecting BP.

Contact details:

Aberdeen

Telephone

RPAs

+44(0) 01224 650658 (direct)

Donald Urquhart

donald.urquhart@matthey.com

+44(0) 07875 384225 (mobile)

+44(0) 1224 650652 (direct)

Graham Wales

graham.wales@matthey.com

+44(0) 7764836669 (mobile)

+44(0) 1224 650653 (direct)

Bill Good

bill.good@matthey.com

+44(0) 7801662320 (mobile)

Billingham

Telephone

RPAs

+44(0) 1642375462 (direct)

Andrew Smith

andrew.smith@matthey.com

+44(0) 7764290567 (mobile)

+44(0) 1642375463 (direct)

Nick Hutchison

nick.hutchinson@matthey.com

+44(0) 7919091388 (mobile)

+44(0) 1642375461 (direct)

Paul Warren

paul.warren@matthey.com

+44(0) 7889828968 (mobile)

Emergency Contact Details:

If none of the above can be contacted outside normal hours then call

+44(0) 1642 375500 and ask to speak to the duty RPA.

Postal Addresses

Aberdeen

Billingham

Office

Tracerco

Tracerco Technology Centre,

Chattan Mews Office

Pavilion 10, The Moat,

18 Chattan Place

Belasis Hall Technology Park

Aberdeen

Billingham, Cleveland,

AB10 6RD

TS23 4AZ,

United Kingdom

Control Tier:

2-AzSPU

Revision Date: October 04, 2010

Document No: AzSPU-HSSE-DOC-00058-2

Print Date: 2/1/2011

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Appendix C - Controlled Area Handover Certificate

Controlled Area Handover Certificate

The work described below is to be carried out in a AzSPU Controlled Area. This

document is a formal record that responsibility for the Controlled Area is handed over

to the Contractor named below and that the Contractor agrees to accept

responsibility for ensuring compliance with any applicable legislation and local

rules/radiation procedures.

Installation:

Contractor:

Work Location:

Description of Work:

Commencement:

Date:

Time:

Completion:

Date:

Time:

Signed:

Contractor RPO

Print:

Date:

Signed:

AzSPU RPS

Print:

Date:

Control Tier:

2-AzSPU

Revision Date: October 04, 2010

Document No: AzSPU-HSSE-DOC-00058-2

Print Date: 2/1/2011

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Appendix F - Radiation Monitoring

Introduction

The aim of this procedure is to give guidance on the proper use of radiation monitoring

instruments and the correct interpretation of results.

The radiation detection and measuring instruments are divided into two categories i.e.

contamination monitors and dose rate monitors.

Contamination monitors are used to detect and measure surface contamination i.e.

radioactivity on a surface or in a material. The monitors can be used to detect natural

radioactivity in materials i.e. Naturally Occurring Radioactive Material (NORM).

Dose rate monitors are used to measure the gamma dose rate arising from a source of

radioactive material or a radiation generator. The material may be in the form of a sealed

radioactive source such as a radiography source or a nucleonic source. Dose rates can also

sometimes be measured from NORM with a high specific activity and generally where there

are significant quantities of NORM, e.g. in a separator vessel or near bundles of contaminated

pipe/tubing.

Personnel

Only personnel who have received appropriate training may carry out radiation monitoring.

Appropriate training will include attendance at a RPS course, a NORM Awareness course, or

on the job training by the RPS. A record of on the job training will be kept by the Site RPS in

the Site Radiation Files or referenced therein.

Contamination Monitors

Contamination monitors typically incorporate a ratemeter and a detector. The detector type

determines the type of radiations that can be measured. The most common types of detectors

used to detect and measure NORM contamination are end window Geiger Mueller detectors

and scintillation detectors.

Monitors that use end window Geiger Mueller detectors are suitable for measuring alpha and

beta radiation, but are also sensitive to gamma radiation. Monitors that include probes with

Geiger Mueller detectors include the Tracerco T201 Monitor and Mini Monitor Series 900

rate meters with EP15 and EL probes.

Scintillation detectors are designed to detect specific types of radiation. Some detectors are

suitable for measuring only gamma radiation e.g. a Mini 900 Series Monitor with a 5.44A, or

44B probe. Other detectors are suitable for measuring alpha, beta or, in the case of a NE

PCM 5/1 ratemeter with DP2 probe, alpha and beta radiation.

It should be noted that the only monitor in common use that is intrinsically safe is the

Tracerco 201.

All of these instruments register in counts per second (cps). Unless done by the monitor,

calibration data is required to convert counts per second into Becquerels per square centimetre

(Bq/cm²) surface contamination. The conversion factor for particular radionuclides is found

on the instrument test certificate and sometimes on the instrument body.

The T201 is also calibrated in Bq/cm²for selected radionuclides such as Radium-222 and

Lead-210, both in the wet and dry state. The monitor can be set to provide a direct readout in

Bq/cm² for a selected radionuclide, while the analogue display reads c.p.s.

Checking a contamination monitor against a test disc

After each time a monitor is calibrated/tested, the RPS will check the response of the monitor

to the test disc and record the result in the Contamination Monitoring Log. If subsequent

checks against the test source deviate by 20% or more from this baseline value then the

monitor should be sent for retest.

Pre-use Checks and Function Tests

Prior to carrying out any measurements, the following checks must be carried out:

 Prior to switching on, check the zero setting (analogue displays only) i.e. ensure the

needle sits on 0.

 For instruments with a H.V. setting, check that the setting corresponds to the setting on

the test certificate.

 Check the meter and probe (especially the detector) for signs of damage

 Ensure the instrument is in calibration i.e. it has been tested in the last 12 months and

there is a valid test certificate

 Where applicable, ensure that the rate meter and probe combination is as stated on the test

certificate

 Switch to the „battery check‟ setting (the T201 performs a self check) and leave for 20s. If

the needle starts to drop back then replace the battery following the manufacturers

instructions.

 Remove any protective caps from the detector and check the response to a test source is

within

20% of the value after retest and record the result on the Contamination

Monitoring Log in the Procedures for Work with NORM.

Contamination Monitoring

 Carry out and record a backg2round check. This should be carried out away from sources

of radiation and should normally be no more than a few c.p.s.

 Angle the detector face as close as possible to the surface being checked.

 Hold the face of the detector approximately 2mm away from the surface, taking care not

to contaminate the detector by touching the surface.

 Move the probe slowly e.g. 25mm/second, across the surface taking care not to damage

the window of the detector on any sharp objects.

 To determine whether a monitor is detecting contamination on an external or internal

surface of an item, the plastic cap should be placed on the detector. If the reading

decreases, then there is external contamination present. If there is no cap available then

another suitable absorber could be used e.g. a piece of plastic, a few mm thick.

NORM contamination is considered to be present where there is a sustainable rise above

the instrument's normal backg2round.

General Points on Use

 Keep the monitor clean particularly the probe face, where deposits of contaminated

material may increase the monitor's normal backg2round. Take great care when

attempting to clean the face of a probe.

 Renew batteries before the indicator falls into the „low battery‟ area

 With detachable probes, ensure the connection is tight and the cable cannot be kinked or

caught in obstructions.

 Contamination monitors that are not intrinsically safe should not be used in an area where

recently broken containment has taken place. If a risk of flammable material is present, a

sample of the contaminant should be removed from the vessel and measured outside the

area of risk.

Dose Rate Monitoring

Dose rate monitors are generally used to measure gamma dose rate. Neutron monitors are also

used where neutron sources or neutron generators are used.

The dose rate is the rate at which a dose of radiation is received over a given amount of time.

The unit of dose is the Sievert (Sv), however, as this is a very large dose, dose rate meters

usually measure micro Sieverts (Sv) or milli Sieverts (mSv). The unit of dose rate is

therefore usually expressed in micro Sieverts per hour (Sv/h) or milli Sieverts per hour

(mSv/h).

Typical dose rate meters include the Gammatrol PRI-190 or the Tracerco T202, which

measure gamma radiation dose rate, both of which are intrinsically safe.

Pre-use Checks and Function Tests

 Prior to switching on, check the zero setting (monitors with analogue displays only) i.e.

ensure the needle sits on 0.

 Check the monitor for signs of damage

 Check the battery (self test carried out by the Gammatrol and T202)

 Ensure the instrument is in calibration i.e. it has been tested in the last 12 months and

there is a valid test certificate

Dose rate monitoring

 Switch on, away from sources of radiation if possible

 If applicable, select the lowest (i.e. most sensitive) range, which is usually 0-10 µSv/h

 Carry out a measurement with the front of the monitor pointed at the source of radiation

 Move the monitor around slowly to observe any increase or decrease in measurement

 Change the range if necessary

 Record the result

General Points on Use

 Renew batteries before the indicator falls into the „low battery‟ area

 Measurements of dose rate around nucleonic devices should be made at approximately 30

cm from the nucleonic, the detector or from vessel walls; this measurement indicates the

„whole body dose rate‟.

 Measurement of dose rate at closer than 30 cm is generally an indication of the dose rate

for extremities e.g. hands and forearms.

Appendix H - Critical Examination Checklist

The following checklist will be completed by the Site RPS prior to accepting handover of

responsibility for a nucleonic gauge from the Contractor installing the gauge.

Checklist

Yes

Is the gauging device securely mounted?

Is the source housing mounted such that it is not possible to get access to the

primary radiation beam?

Does the source housing contain a radiation trefoil sign?

Is there a source detail plate fixed to the source housing?

Does the source detail plate contain details of source type (i.e. radionuclide),

source activity and serial number?

Do the source serial number and activity details match those in the Contractors

source documentation?

Where appropriate, is the source holder secure and padlocked in place?

Where appropriate, does the shutter mechanism operate satisfactorily?

Is the shutter status (i.e. „open‟ or „closed‟) clearly indicated?

With the source(s) exposed, are accessible dose rates less than 7.5 Sv/h for

whole body exposure (i.e. at 30 cm from source container, the vessel and the

detector) and less than 75 Sv/h for exposure to hands, forearms or feet? Also,

is the dose rate at the surface of the source housing less than 100 Sv/h and

less than 3 Sv/h at 1 m (Ref. [7], Clauses 2.5 and 4.5)

For vessel-mounted (as opposed to pipe-mounted) devices, are radiation-

warning signs posted at all entrance points to the vessel?

Is a Leakage Test Certificate available for the source(s) and has the source(s)

been tested in the last two years?

Comments

Checks carried out by:

Name:

…………………………..

Signature:

…………………………..

Date:

…………………………..

Completed forms should be field in the Site Radiation Records

Appendix I - Radioactive Source Accountancy, Monitoring and Safety Checks

Source Type:

Location:

Activity:

Use:

Serial No.:

Instrument I.D.:

Max. Dose

Shutter

Rate (Sv/h)¹

Condition of

Warning

Date

Open /

Comments

Signed

Gauge⁴

signs⁵

Housing²

Detector²

Closed³

NOTES

Measurements should only be carried out by person(s) who have received appropriate training; this is not necessarily the RPS.

If a measurement cannot be made at the housing or detector, then record the location that the measurement is made under “Comments”.

The status of the shutter when measurements are made should be recorded i.e. either open or closed. Alternatively, if the source (or sources) is located in a dip pipe then

record whether it is retracted or not.

Check for signs of wear and tear or damage: if maintenance is required then record this under “Comments”.

Check warning signs on the gauge and on the vessel entry points. This should include a check on the source detail plaque and on the shutter status indication.

Appendix J - Leakage Test Method

The RPS, or an Authorised Person who has received appropriate training, will carry out the

test. Alternatively, the test may be carried out by the Radiation Protection Adviser (RPA)

during the annual audit.

The leakage test does not require direct access to the source. At no time will the source or

source holder be removed from the source container.

Kit required

 Swabs and tubes supplied by Tracerco (N.B: As an alternative to the Tracerco swab, a

small piece of cotton wool and a re-sealable bag may be used).

 Small container of water or isopropyl alcohol e.g. 100ml.

 Re-sealable bag.

 Pen.

 Disposable gloves.

 Contamination monitor.

 Radiation dose rate monitor.

Procedure

Carry out radiation dose rate measurements around the source housing to ensure that whole

body dose rates are less 7.5 µSv/h and extremity (hands, feet and forearms) dose rates are less

than 75 µSv/h.

Put on the gloves and then moisten a swab with water. Wipe the moistened swab over all

areas that could reasonably be expected to reveal any leakage of the source i.e. at the shutter

mechanism and where the source holder is fitted into the source container.

For interface gauges, the rear cap should be removed and a wipe made where the wire or

source rod passes through the shutter mechanism. (The same wipe can be used). For Profiler

gauges a wipe should be made where the source control handle fits into the gauge.

The swab should then be placed into the small plastic tube and the tube sealed. The tube

should then be placed in the plastic bag. The bag should then be sealed and the contents

should be checked for gross contamination using the contamination monitor on the c.p.s

setting.

Assuming no contamination is found (if contamination is found, follow the procedures

overleaf) the gloves may be removed. The bag should be marked with the following details:

 Date.

 Radionuclide.

 Identification of the source or sources (in the case of a Profiler gauge the gauge number

may be used as an identifier).

The „Request For Analysis Form‟ and the „Request for Leak test Analysis Form‟ on the

Tracerco website (http://www.tracerco.com/products-rpa-radiochemicalanalysis.htm ) should

be completed and the forms and wipes sent to the Tracerco laboratory:

Chris Pollin / Karen Waterman, Tracerco (Pavilion 10), PO Box, Belasis Technology Park,

Billingham, Cleveland, TS23 1LB, UK.

Procedure in the event of contamination being detected

 Do not panic. Assume that the person performing the leak test may be contaminated,

although this is highly unlikely.

 Summon help to inform the RPS immediately.

 The RPS should initiate the contingency plans for leaking source (see AzSPU Radiation

Contingency Plan, AzSPU-HSSE-DOC-00086-2).

 Seal the wipe within another bag to minimise the risk of spreading any contamination.

Appendix K - Procedure for Isolating and De-isolating Sources in Dip-

pipes

Isolation and De-isolation kit

4mm Allen (Hex Head) Key

Retaining Padlock, Pin or Wire (to pass through 3/16" holes in source capsule and

containment plate)

C Padlock for shutter mechanism (usually small D4)

D Radiation Dose Rate Monitor.

Radioactive Source Isolation Procedure

1. Remove the rear cover by unscrewing the four Allen (Hex Head) screws; retain the

screws.

2. Pull the end of the extension rod/cable

(which will be ill be visible in centre of

containment plate) to its full extent

(NOTE: rod/cable will be at vessel operating

temperature

- wear gloves). The source capsule cannot be withdrawn past the

containment plate.

3. Close the shutter by pushing in or turning to "CLOSED" position. Padlock shutter

mechanism shut at this point using item C (above).

3/16" dia. holes in source capsule and retaining lug on containment plate should be

aligned. Place item B (above) through these holes.

5. Unscrew extension rod/cable from source capsule and retain for future use.

6. Replace the rear cover using the 4 Allen (Hex Head) screws.

7. Use the Radiation monitor to observe radiation levels both at the source head and

detector. No radiation should be detected at the detector after the source has been

retracted into the source head.

8. Add notice to shielded container indicating source isolation.

Note! All padlock keys and extension rods/cables should be kept in a secure or controlled

system. Extension rods should be labelled to identify the gauge that they have been removed

from.

De-isolation Procedure

DO NOT UNLOCK OR OTHERWISE ADJUST THE CONTAINER SHUTTER

MECHANISM BEFORE STEP 5 BELOW.

1. Remove the rear cover by unscrewing the four Allen (Hex Head) screws; retain the

screws.

The end of the radioactive source connector will be in view. It will probably be locked

using a small padlock (item B) to a small locking tab attached to the capsule containment

plate. If a lock is not used, the capsule may be loosely wired to the locking tab. DO NOT

remove the padlock or fixing wire yet.

A rigid extension rod or flexible cable assembly is used to correctly position the source

capsule at the end of the internal dip-pipe in the vessel. This rod/cable will have been

removed when the source was isolated; it should be labelled to identify the gauge to

which it fits. Attach this rod or cable assembly to the threaded rear of the source

connector, making sure that it is tightly screwed into position. It is quite safe to touch the

end of the source connector.

Unlock and remove the padlock or fixing wire attaching the source connector to the

containment plate.

Unlock and remove the padlock (item C) holding the shutter mechanism in the SHUT

position. Pull or rotate the shutter mechanism to the „OPEN‟ position (the method of

opening the shutter depends on the shielded container type). This removes an internal

shield (item 2) within the shielded container and allows passage of the source capsule into

the vessel dip-pipe. The shutter may be wired (NOT locked) in the open position to

prevent accidental closure.

Push the extension rod/cable gently so that the source capsule enters the vessel dip-pipe.

Ensure that the source assembly does not catch any internal edges within the dip-pipe.

Move the source assembly gently back and forth if this happens so that any internal

obstructions are bypassed. When in the correct position, the source capsule should touch

the end of the internal dip-pipe and cannot be pushed further into the dip-pipe (a slight

flexing will be encountered if flexible cables are used. The assembly should reach a

"rest" position with the source capsule at the end of the dip-pipe). Once in position,

approximately 50mm of extension rod should protrude at the rear of the shielded

container.

Replace the rear cover using the 4 Allen (Hex Head) screws. The back cap will ensure

that the entire assembly is held securely in the correct operating position. Extension

rods/cables are cut to length at commissioning to ensure this.

Add notice to shielded container indicating source condition (de-isolated).

Appendix L - Procedure for Isolating and De-isolating Profiler Sources

Isolation and de-isolation kit

 Padlock and key

 Soft Fastening e.g. tie wrap

Isolation Procedure

1. Push down on the lever on the neck of the profiler to the indicated „closed‟ position. This

action brings the sources behind a shield, thereby reducing the surface dose rate on the

internal dip pipe.

2. Insert a padlock in the hole provided and lock it.

Comments

Complete closure must be confirmed on vessel entry by the use of an appropriate radiation

monitor

This padlock and key will be securely retained

Appendix M - Contractors Checklist for Contractors Using Radioactive

Materials on AzSPU Sites

Site Name:

Contractor:

Contractor Address:

Contractor’s RPA:

Contractor’s Site RPO (RPS):

Nature of work:

Source type:

Serial No.:

Activity:

Source Storage Location:

Checklist

Yes

N/A

Is the transport container in good condition?

Is the container labelled properly?

Do the measured dose rates correspond to the transport labels?

Does the Contractor have a valid Special Permit for work with this type

of radiation and is it available?

Are there sufficient RPOs for the work?

Do they have adequate dosimetry?

Are there Radiation Procedures and / or Local Rules available?

Are Emergency Response Plans available?

Is the equipment listed in the emergency kit available and operating?

Are suitable and sufficient Controlled Area signs available?

Are sufficient barrier materials available?

Are radiation-monitoring instruments appropriate to each type of

radiation to be used available?

 Gamma Dose Rate Meter (x 2 for radiography)

 Neutron Dose Rate Meter

 Contamination Meter

Are the instruments functioning?

Are test certificates available for the meters?

Checklist

Yes

N/A

Does the Contractor have documentation with details of the source(s)

Are there current leak test certificates available for all sources?

Does the Contractor have a source movement / accounting record?

Signed AzSPU RPS

Print:

Date:

If the answer to any of the above is “No” then the OIM should be notified and alternative

arrangements must be made that provide the same level of control or safety. The OIM will

decide whether or not to allow the work to go ahead and record his decision below, noting

any alternative arrangements that have been made. The AzSPU Radiation Protection (RP)

SPA and the Radiation Protection Adviser (RPA) should be contacted for advice if necessary.

OIM Comments:

Signed AzSPU (OIM):

Print:

Date:

Appendix P

References



Azerbaijan Republic Law on Public Radiation Safety No 4231Q as of January 30,

1997



International Atomic Energy Agency in Safety Series 115, Radiation Protection

Convention, 1960



Resolution No.

134 On approval of the Rules on Form and Completion of

Radiological-Hygienic Passports of Territories, Enterprises and Organisations and the

Rules of Recordation and Control Over Individual Ray Doses, August 25, 1999



The Cabinet Of Ministers Of The Azerbaijan Republic Decision No. 10 Baku City,

27 January 2000 On Approval of the Rules for Carriage of Dangerous Goods by Road



Law of the Azerbaijan Republic, № 913-IГ. On joining the European

Agreement (30 September 1957 )on the International Carriage of Dangerous

Goods by Road (ADR) and the Protocol on signing it



Cabinet of Ministers of the Azerbaijan Republic Resolution No 75 On

approving the Regulations for transportation of hazardous goods by maritime

transport



International Air Transport Association technical Instructions for the

Transport of Dangerous Goods by Air (IATA), 2009



International Maritime Dangerous Goods Code (IMDG), 2009 (with the

amendment of 34-08)

AzSPU Procedure for Transportation of Radioactive Materials

Page 1 of 24

AzSPU Procedure for Transportation of

Radioactive Materials

AzSPU-HSSE-DOC-00115-2

Authority:

Yuliy Zaytsev (AzSPU

Custodian:

Hazardous Materials TA

Safety & Compliance

Manager)

Scope:

AzSPU

Document

AzSPU HSSE MS Document

Administrator:

Coordinator

Issue Date:

7^th October, 2009

Issuing Dept:

AzSPU HSSE

Revision Date:

1^st July, 2010

Control Tier:

Next Review

7^th October, 2010

Date:

Control Tier: 2

Revision Date: 1 July, 2010

Document Number: AZSPU-HSSE-DOC-00115-2

Print Date: 2/1/2011

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AzSPU Procedure for Transportation of Radioactive Materials

Page 2 of 24

TABLE OF CONTENTS

PURPOSE/SCOPE

DEFINITIONS

GENERAL REQUIREMENTS

KEY RESPONSIBILITIES

PROCEDURE / PROCESS

5.1 TRANSPORTATION OF RADIOACTIVE SOURCES

5.1.1 Transportation of Radioactive Sources Offshore

5.1.2 Transportation of Radioactive Sources Onshore

5.2 TRANSPORTATION OF NORM CONTAMINATED EQUIPMENT / WASTE

5.3 TRANSPORTATION OF NORM CONTAMINATED SAMPLES

5.4 TRAINING

5.5 PERMITTING / LICENSING REQUIREMENTS

6. KEY DOCUMENTS/TOOLS/REFERENCES

APPENDIX A - REQUIREMENTS FOR CATEGORISING, PACKING, MARKING, AND LABELLING

RADIOACTIVE MATERIALS FOR TRANSPORTATION

APPENDIX B - DANGEROUS GOODS DECLARATION FORM - COMPLETED FOR NORM

CONTAMINATED EQUIPMENT / WASTE (SEE RED TEXT)

APPENDIX C - RADIATION PROTECTION ADVISER / QUALIFIED EXPERT (RPA) CONTACT

DETAILS

Control Tier: 2

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AzSPU Procedure for Transportation of Radioactive Materials

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PURPOSE/SCOPE

The intent of this procedure is to ensure a systematic approach to the transportation of

radioactive material

(to and from onshore and offshore AzSPU facilities) and to provide

requirements for permitting, packaging, labeling, documentation, and chain of custody.

Radioactive material encompasses radioactive sources, NORM contaminated equipment, NORM

waste (e.g. LSA scale), and NORM samples.

This controlled procedure applies to AzSPU Operations PUs and Projects engaged in the drilling,

production, and/or transportation of oil and gas (including support activities), and construction

activities when working with radioactive materials in Azerbaijan. Contractors working on

AzSPU owned or operated sites/installations are also required to align with this procedure.

This procedure does not replace, not should it conflict with, the AzSPU Procedure for

Management of Radioactive Materials and Radiation Generators (AzSPU-HSSE-DOC-00058-2).

Any form of deviation from this procedure, including but not limited to site-specific instructions,

shall be requested and authorised in accordance with the AzSPU Deviations Procedure (AZSPU-

HSSE-DOC-00011-2).

Revision of this procedure and the operational controls detailed therein will be in accordance

with the AzSPU HSSE Document Management Procedure (AzSPU-HSSE-DOC-00025-2).

DEFINITIONS

A full glossary of terms related to radiation and radioactive materials is provided in Appendix A

of the AzSPU Procedure for Management of Radioactive Materials and Radiation Generators

(AzSPU-HSSE-DOC-00058-2).

Additional definitions specific to this procedure are included here:

Consignee

A person or organisation that receives a consignment.

Consignor

A person or organisation that prepares a consignment for transport.

Fixed

Contamination other than „non-fixed contamination‟ (see definition

Contamination

below).

Low toxicity alpha

Natural uranium; depleted uranium; natural thorium; uranium-235 or

emitters

uranium-238; thorium-232; thorium-228 and thorium-230 when

contained in ores or physical and chemical concentrates; or alpha

emitters with a half-life of less than 10 days.

Non-fixed

Contamination that can be removed from a surface during routine

contamination

conditions of transport.

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AzSPU Procedure for Transportation of Radioactive Materials

Page 4 of 24

Overpack

An enclosure such as a box or bag which is used by a single consignor

to facilitate as a handling unit a consignment of one or more packages

for convenience of handling, stowage and carriage.

Package

The packaging with its radioactive contents as presented for transport.

Packaging

The assembly of components necessary to enclose the radioactive

contents completely, which may consist of one or more receptacles,

absorbent materials, spacing structures, radiation shielding etc. The

packaging may be a box, drum or similar receptacle, or may also be a

freight container, tank or intermediate bulk container.

Radioactive material

Any material containing radionuclides where both the activity

concentration and the total activity in the consignment exceed specified

values (see Table 1).

Special form

Either an indispersible solid radioactive material, or a sealed capsule

radioactive material

containing radioactive material.

Specific activity

The specific activity of a radionuclide shall mean the activity per unit

mass of that nuclide. The specific activity of a material shall mean the

activity per unit mass of the material in which the radionuclides are

essentially uniformly distributed.

Transport Index

The Transport Index assigned to a package, overpack or freight

container, or to unpackaged LSA-I or SCO-I, shall mean a number that

is used to provide control over radiation exposure. The number has no

units and is derived by dividing the dose rate, measured in µSv/h, at 1 m

from a package by 10.

GENERAL REQUIREMENTS

General requirements pertaining to radiation safety are detailed in Section 3.1 of the AzSPU

Procedure for Management of Radioactive Materials and Radiation Generators (AzSPU-HSSE-

DOC-00058-2).

In addition the following legislation is also considered applicable to this procedure:

International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive

Material, IAEA Safety Standards Series No. TS-R-1.

Road transport: Decree of the Cabinet of Ministers of the Azerbaijan Republic No. 10, 27

January 2007, On Approval of the Rules for Carriage of Dangerous Goods by Road. The decree

implements most of the provisions of the European Agreement on the Carriage of Dangerous

Goods by Road (ADR).

Sea transport: Current edition of the International Maritime Dangerous Goods Code (IMDG

Code).

Control Tier: 2

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AzSPU Procedure for Transportation of Radioactive Materials

Page 6 of 24

Radioactive Material & Exemptions:

The transport legislation defines radioactive material as that which exceeds a specified activity

concentration and total activity. Examples of exemption levels for some commonly encountered

radioactive materials are provided in Table 1.

Table 1: Radionuclide Exemption Levels

Activity concentration for an

Activity limit for an exempt

Radionuclide

exempt material (Bq/g)

consignment (Bq)

Americium-241

10,000

Bromine-82

1,000,000

Caesium-137

10,000

Carbon-14

10,000

10,000,000

Cobalt-60

100,000

Hydrogen-3

1,000,000

1,000,000,000

Iridium-192

10,000

Lead-210

10,000

Polonium-210

10,000

Radium-226

10,000

Radium-228

100,000

Material that does not exceed the activity concentrations in Table 1 can be classed as

Exempt and can be transported in accordance with AzSPU’s existing transportation

practices.

NB: NORM materials encountered in the oil and gas industry are frequently found to be Exempt

from the transport legislation. However, the activity concentration of a radioactive material can

only be determined by analysis of the material at a suitable laboratory.

KEY RESPONSIBILITIES

A full description of the responsibilities with regard to radiation protection is provided in Section

4 of the AzSPU Procedure for Management of Radioactive Materials and Radiation Generators

(AzSPU-HSSE-DOC-00058-2). A summary of key responsibilities directly applicable to this

procedure are provided below:

Site Manager / OIM

The Site Manager / OIM is accountable for providing authorization for dispatch of radioactive

sources to their site / facility.

Control Tier: 2

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AzSPU Procedure for Transportation of Radioactive Materials

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Supply Base / HSE Personnel

Responsible for ensuring that:

 Trucks and drivers arriving at the Supply Base are in compliance with legislative

requirements, prior to allowing entry.

 Shipping containers are intact and fit for purpose, and that labeling, placarding, and

documentation are in accordance with applicable legislation (see Appendix A).

 Radioactive sources are transported together with all accompanying documentation and

monitoring equipment (i.e. the load must not be split between vessels).

Deck Forman

Responsible for ensuring the safe lifting of radioactive sources onboard the Installation and

informing / consulting with contractor, or site RPS, about the placement and location of the

sources.

Site Radiation Protection Supervisor (RPS)

With respect to the transportation of contractor owned radioactive sources the RPS is responsible

for:

 Inspecting packages or containers containing radioactive sources, ensuring that they are

undamaged, and that the surface dose rate and Transport Index are correct

(in

collaboration with the contractor RPO).

 For identifying designated storage areas for radioactive sources and establishing

controlled / supervised areas (if required).

 Maintaining Site Radiation Records

(completing Contractor Checklist, Site Mobile

 Reviewing contractor‟s arrangements for accounting for radioactive sources.

With respect to the transportation of AzSPU owned NORM contaminated equipment / waste the

RPS is responsible for:

 Ensuring that the contaminated equipment / waste is categorized, packed, marked and

labeled appropriately (see Appendix A), and that the Dangerous Goods Declaration is

completed (see Appendix B).

 For collecting samples of NORM, monitoring their contamination levels, preparing them

for transportation, and arranging for them to be couriered to the Tracerco laboratory.

 Contacting the AzSPU RP SPA for advice on cleaning / disposal of contaminated

equipment / waste, prior to it being shipped from the facility.

AzSPU Radiation Protection Single Point Accountability (AzSPU RP SPA)

Responsible for maintaining a proper communication flow between the AzSPU RPA (UK based)

and the Site Radiation Protection Supervisors (RPSs).

Control Tier: 2

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AzSPU Procedure for Transportation of Radioactive Materials

Page 9 of 24

AzSPU Radiation Protection Advisor (RPA)

AzSPU retains by contract and appointment a RPA to provide the AzSPU with expert advice on

radiation safety and compliance matters. The RPA reports to the AzSPU Safety & Compliance

Manager and works directly with the AzSPU RP SPA.

In terms of this procedure, the RPA will be consulted with respect to the following:

 Cleaning / disposal options for NORM contaminated equipment / waste, based on the

results of sampling and analysis.

 Provision of instructions to drivers regarding accidents and emergencies (where AzSPU

is the consigner).

Contractors

All third party contractors transporting radioactive materials to / from AzSPU sites are required

to work in accordance with this procedure, and in compliance with applicable national and

international legislation.

PROCEDURE / PROCESS

5.1

TRANSPORTATION OF RADIOACTIVE SOURCES

5.1.1 Transportation of Radioactive Sources to / from Offshore Facilities

Before a Contractor brings a radioactive source onto an offshore facility, he will notify the OIM,

the site RPS, the Supply Base, and the sponsoring department representative at least 24 hours

prior to dispatch. The following information will be provided:

 Number, type and size of sources.

 Name of vessel/transport company.

 Dispatch date and time and estimated time of arrival.

 Type and ID number of transport container.

 Transport Index.

The OIM is responsible for providing authorization for dispatch.

The contractor will ensure that the radioactive substances are categorized, packed, marked and

labeled appropriately (see Appendix A). The contractor will also complete and sign a Dangerous

Goods Declaration.

The contractor will also provide test certificates for packages used for shipping of radioactive

materials when requested by a site RPS.

Once authorization has been obtained from the OIM the contractor delivers the radioactive

source to the Supply Base.

Control Tier: 2

Revision Date: 1 July, 2010

Document Number: AZSPU-HSSE-DOC-00115-2

Print Date: 2/1/2011

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AzSPU Procedure for Transportation of Radioactive Materials

Page 10 of 24

Supply Base Operations/HSE personnel will check that the transport arrangements are in

compliance with applicable legislation for transportation of radioactive sources (see Section 5.5).

Trucks or drivers not in compliance with legislative requirements will not be allowed to enter the

site.

Once sources are accepted onto the site Ops/HSE personnel will check if the shipping container

is intact and fit for purpose, and that labeling, placarding, and documentation are in accordance

with applicable legislation (see Appendix A).

Any shipping containers carrying radioactive source(s) will be loaded to the Supply Vessel as a

last item before dispatch and secured with deck straps for transit. The shipping manifest is

completed by the Supply Base Materials / Logistics Coordinator.

It should be noted that radioactive source(s) must always be transported offshore together with

all accompanying documentation and monitoring equipment. Splitting of equipment onto

different vessels has the potential to result in business value loss (as the work cannot be carried

out on the facility until all equipment and documentation received) and unsafe operations (e.g.

lack of radiation monitoring equipment in case of incident with radioactive source on vessel).

Upon arrival offshore, the Deck Foreman will place the radioactive source container into a

designated storage area previously agreed between the site RPS and contractor RPO. Where such

arrangements have not been previously agreed, the Deck Foreman will contact the site RPS or

contractor RPO before unloading the source container from the vessel.

The site RPS and contractor RPO will inspect packages or containers containing radioactive

material and ensure they are undamaged, and that the surface dose rate and Transport Index are

correct, i.e. as described on the transport documents and the package labels. Any anomalies will

be addressed by the contractor RPO. A controlled area / supervised area will be set up around the

source, if required (see Section 5.1.1 of the AzSPU Procedure for Management of Radioactive

Materials and Radiation Generators (AzSPU-HSSE-DOC-00058-2)).

Where a contractor does not accompany his radioactive source to site, the contractor will

endeavour to have an RPO on the site prior to the source arriving. By prior arrangement and

agreement, the site RPS may receive sources on behalf of the contractor. The site RPS will then

carry out the checks described above.

The site RPS will complete the Contractor Checklist (Appendix M of the AzSPU Procedure for

Management of Radioactive Materials & Radiation Generators (AzSPU-HSSE-DOC-00058-2))

prior to starting any on-site work with the radioactive source.

The site RPS will also update and maintain the Site Mobile Source Register (Appendix N of the

AzSPU Procedure for Management of Radioactive Materials & Radiation Generators (AzSPU-

HSSE-DOC-00058-2)) in order to record radioactive sources arriving on site and those leaving.

Contractors must carry out and record an accounting check for radioactive materials on a daily

basis. The contractor is responsible for ensuring that that these checks are carried out and the

Control Tier: 2

Revision Date: 1 July, 2010

Document Number: AZSPU-HSSE-DOC-00115-2

Print Date: 2/1/2011

PAPER COPIES ARE UNCONTROLLED. THIS COPY VALID ONLY AT THE TIME OF PRINTING. THE

CONTROLLED VERSION OF THIS DOCUMENT CAN BE FOUND AT

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AzSPU Procedure for Transportation of Radioactive Materials

Page 11 of 24

results recorded. The site RPS will review the contractor‟s arrangements for accounting for

radioactive substances on a regular basis, although the results of the RPS‟s checks do not need to

be recorded.

If the radioactive source is installed on the facility (e.g. installation of a nucleonic device) a

Critical Examination Checklist

(Appendix H of the AzSPU Procedure for Management of

Radioactive Materials & Radiation Generators (AzSPU-HSSE-DOC-00058-2)) will be completed

by the site RPS prior to AzSPU accepting responsibility for the device.

On completion of the scope of work, and prior to leaving the site, the contractor will ensure that

his sources are categorized, packed, marked and labeled appropriately (see Appendix A) and that

a Dangerous Goods Declaration has been completed. The Platform Materials

/ Logistics

Coordinator will complete the shipping manifest, using the contractor‟s Dangerous Goods

Declaration and with the assistance of the contractor RPO (if required).

In the event that the contractor leaves the site prior to dispatch of their radioactive source there

must be a formal handover of responsibility for the source between the contractor and the site

RPS and the contractor must present their completed documentation for transport. The site RPS

is then responsible for the security and accounting of the source. Radioactive sources must not be

left on site unless these, or suitable alternative arrangements have been made.

Prior to shipping the radioactive source the Platform Materials / Logistics Coordinator will

ensure that 24 hours notification has been sent to Supply Base and to the contractor.

The Supply Base liaises with the contractor to enable the contractor to have transport available to

collect the source at an appropriate time. The source is then transported on to the contractor‟s

premises.

As a general rule, sources used offshore will normally be back loaded if they will be redundant

for 7 days or more.

NB: Sources can be transported between offshore facilities but the same documentation that

would be required to send the sources onshore must be completed.

5.1.2 Transportation of Radioactive Sources to / from Onshore Facilities

The requirements outlined above for offshore transportation of radioactive sources also apply to

transportation of radioactive sources to AzSPU‟s onshore facilities. In this case, however,

radioactive sources are delivered directly from contractor owned storage facilities to AzSPU

facilities (without passing through the Supply Base). The contractor will notify the Site Manager,

site RPS, and the sponsoring department representative at least 24 hours prior to dispatch. The

Site Manager is responsible for providing authorization for dispatch.

The contractor will ensure that the radioactive substances are categorized, packed, marked and

labeled appropriately (see Appendix A). The contractor will also complete and sign a Dangerous

Goods Declaration.

Control Tier: 2

Revision Date: 1 July, 2010

Document Number: AZSPU-HSSE-DOC-00115-2

Print Date: 2/1/2011

PAPER COPIES ARE UNCONTROLLED. THIS COPY VALID ONLY AT THE TIME OF PRINTING. THE

CONTROLLED VERSION OF THIS DOCUMENT CAN BE FOUND AT

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AzSPU Procedure for Transportation of Radioactive Materials

Page 12 of 24

The contractor will also provide test certificates for packages used for shipping of radioactive

materials when requested by a site RPS.

On arrival at the facility, the radioactive source container will be placed in a designated area

previously agreed between the site RPS and contractor RPO. The site RPS and contractor RPO

will then inspect the packages, or containers containing radioactive material, and ensure they are

undamaged, and that the surface dose rate and Transport Index are correct, i.e. as described on

the transport documents and the package labels. Any anomalies will be addressed by the

contractor RPO.

Sources that are used onshore may be stored onsite temporarily, without being placed in a store

area, provided they are accompanied at all times.

The site RPS will be responsible for completing the Contractor Checklist prior to work with the

radioactive source, for updating and maintaining the Site Mobile Register, and for completing the

Critical Examination Checklist if radioactive sources are installed on the facility.

Contractors must carry out and record an accounting check for radioactive materials on a daily

basis. The contractor is responsible for ensuring that that these checks are carried out and the

results recorded. The Site RPS should review the contractor‟s arrangements for accounting for

radioactive substances on a regular basis, although the results of the RPS‟s checks do not need to

be recorded.

On completion of the scope of work, and prior to leaving the site, the contractor will ensure that

his sources are categorized, packed, marked and labeled appropriately (see Appendix A) and that

a Dangerous Goods Declaration is completed.

As a general rule, mobile sources are not stored at AzSPU onshore facilities. They are returned to

the contractor‟s storage facilities at the end of the work day.

5.2

TRANSPORTATION OF NORM CONTAMINATED EQUIPMENT / WASTE

In terms of NORM contaminated equipment and waste it is the site RPS‟s responsibility to

ensure that the radioactive substances are categorized, packed, marked and labeled appropriately

(see Appendix A). The site RPS will also complete and sign a Dangerous Goods Declaration

(Appendix B contains a Dangerous Goods Declaration Form already completed with the correct

UN number, proper shipping name, radionuclide information, activity, form, hazard category and

package classification for NORM contaminated equipment / waste - see red text).

Generally, NORM contaminated equipment will not be transported from site until sampling and

analysis has been carried out and advice received from the RPA. An exception to this would be

contaminated equipment impeding operations due to lack of deck space, etc.

The IMDG Code and ADR allow surface contaminated objects to be transported unpackaged

under the following conditions:

Control Tier: 2

Revision Date: 1 July, 2010

Document Number: AZSPU-HSSE-DOC-00115-2

Print Date: 2/1/2011

PAPER COPIES ARE UNCONTROLLED. THIS COPY VALID ONLY AT THE TIME OF PRINTING. THE

CONTROLLED VERSION OF THIS DOCUMENT CAN BE FOUND AT

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AzSPU Procedure for Transportation of Radioactive Materials

Page 13 of 24

 If under routine conditions of transport there will be no escape of radioactive contents or

loss of shielding - this can be achieved by fitting end caps to tubulars / drill pipe; sealing

open ends of valves, pumps, etc with flange protectors or heavy duty polythene; or

wrapping the entire item in heavy-duty polythene, as appropriate. Any externally

contaminated items must be wrapped in heavy-duty polythene.

 For accessible surfaces the non-fixed contamination must not exceed 4 Bq/cm² and the

fixed contamination 40 k Bq/cm².

 For inaccessible surfaces the non-fixed plus the fixed contamination must not exceed 40

k Bq/cm². Measures must be taken to ensure that the radioactive material from

inaccessible surfaces is not released into the conveyance or vehicle, again this can be

achieved through the use of end caps, flange protectors, polythene wrapping, etc.

Prior to contaminated equipment / waste being shipped from the site, the RPS should contact the

AzSPU Radiation Protection SPA in order to determine the facility to be used for cleaning /

disposal; the SPA will liaise with the RPA. For offshore facilities, the Platform Materials /

Logistics Coordinator will ensure that 24 hours notification has been sent to the Supply Base

prior to shipping.

Further instructions for the storage and handling of NORM contaminated equipment and wastes

are provided in the AzSPU Procedure for Management of NORM (AzSPU-HSSE-DOC-00097-

2).

5.3

TRANSPORTATION OF NORM CONTAMINATED SAMPLES

The activity concentration of radioactive material can only be determined by analysis at a

suitable laboratory. NORM samples may be in the form of solids such as sand, sludge, scale and

wax, liquids such as produced water, and samples of gas.

Due to the nature of NORM it is not always possible to know the type or quantity of radioactive

material that is present in a sample, however, certain assumptions can be made based on past

experience.

Solid samples can be transported as Exempt (i.e. not radioactive) provided the sample weights do

not exceed those stated below:



1-4 samples - maximum weight per sample 50g.



5-8 samples - maximum weight per sample 25g.

The values above are based on a conservative assumption that the specific activity could be up to

50 Bq/g. The RPS must monitor the samples to ensure that this specific activity is not exceeded.

Provided the contamination level of the material does not exceed 30 counts per second, the above

conditions apply.

Exempt samples can be couriered to the Tracerco Laboratory in Billingham (address in Appendix

C) in the same way as any other parcel, as long as there is nothing else in the sample that would

require it to be transported in accordance with the dangerous goods legislation.

Control Tier: 2

Revision Date: 1 July, 2010

Document Number: AZSPU-HSSE-DOC-00115-2

Print Date: 2/1/2011

PAPER COPIES ARE UNCONTROLLED. THIS COPY VALID ONLY AT THE TIME OF PRINTING. THE

CONTROLLED VERSION OF THIS DOCUMENT CAN BE FOUND AT

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Military reference books and manuals (2009-2023, Volume 4) - page 31