The Local Rules for the Protection of Persons Exposed to Ionising Radiations are enforced by the RPO and RPSs on campus in order to comply with SI 30; all users of ionising radiation must adhere to the rules.

1. Introduction

1.1 Under the Licence from the EPA Office of Radiological Protection the University is obliged to draw up local rules to regulate the acquisition, use and disposal of sources of ionising radiation. The following rules are designed to meet this requirement and to foster the highest standards of safety and care. Detailed rules applicable to a range of relevant situations found in the University are included.
1.2 The provisions of these rules are subordinate to the rules and guidelines of the EPA Office of Radiological Protection.
Copies of the current licence are on display in each relevant department.

2. Administrative Organisation

2.1 The University of Galway Committee on Radiation Safety has been established to administer and advise on all matters relating to radiation safety in all areas of the University. This does not include UHG.
2.2 The Committee includes:
(a) Representatives from all departments where regular use is made of significant amounts of radioisotopes or generators of ionising radiation;
(b) A representative from the Buildings Office;
(c) A Medical Advisor (see 2.5).
2.3 The Committee will mediate on behalf of the University with the EPA Office of Radiological Protection on all matters concerning Radiological Safety.
2.4 The Committee will be responsible for seeing that safe practices are established and maintained, and will issue regulations to that effect (e.g. these rules). It will report to the Academic Council and the Governing Body at regular intervals.
2.5 To assist the Committee, a University Radiological Protection Officer, a Medical Advisor and Departmental Radiation Supervisors will be appointed by the Committee.

3. Duties of Radiation Protection Officer

3.1 He or she will act as executive officer and secretary of the Committee on Radiation Safety. He or she will, therefore, be an ex-officio member of the Committee and should attend all its meetings.
3.2 The primary duty of the University Radiation Protection Officer is, with the Committee on Radiation Safety, and in co-operation with the Departmental Radiation Supervisors, to ensure that these agreed Local Rules for the Protection of Persons Exposed to Ionising Radiations are followed.
3.3 It is a duty of the Radiation Protection Officer to attend such courses on Radiation Protection etc. as are necessary for him or her to undertake the responsibilities and exercise the duties as laid out in this section.
3.4 On becoming acquainted with any deviation from good practice he or she must take appropriate action as follows:

  • Stop the work resulting in the abuse and issue any necessary instructions to the person in charge.
  • Report the matter to the Committee on Radiation Safety.
  • If necessary, directly advise the relevant University Officer on action to be taken.

3.5 He or she must classify the areas which are set aside for work with sources of ionising radiation.
3.6 He or she will ensure that Departmental Radiation Supervisors and, where necessary, individual workers, receive any special training in radiological protection necessary to their work.
3.7 He or she will supervise the drafting of specialised rules by Departmental Radiation Supervisors.
3.8 He or she will monitor the receipt and distribution of radiation protection film and thermoluminescent badges and will maintain all dosage records, as well as record of accidents etc. and these will be kept for a period of not less than 30 years.
3.9 He or she will record the ordering and reception of all radioactive materials.
3.10 He or she will control the disposal of all relevant materials (or control their storage in a safe place pending disposal) and will keep or oblige to be kept, full records of all such transactions. This includes the disposal of equipment containing radioactive material.
3.11 He or she will ensure that monitoring equipment is available to all relevant laboratories and that it is regularly maintained and calibrated.
3.12 He or she will advise the relevant bodies when decision related to the future use of radiation sources in the University are being taken.
3.13 He or she will mediate (as executive officer of the Committee on Radiation Safety) with relevant authorities outside the University (e.g. the EPA Office of Radiological Protection) and must report any accident or incident having a bearing on radiological safety to the RPII.
3.14 He or she must advise heads of department on the appointment of Departmental Radiation Supervisors and seek the approval of the EPA Office of Radiological Protection for their appointment.

4. Duties of Departmental Radiation Supervisors

4.1 The efficient operation of proper safety regulations depends largely on the diligence of the Departmental Radiation Supervisors. They are responsible for day-to-day matters of radiological safety within their own departments.

4.2 They must ensure that each person in their respective departments carrying out work involving exposure to ionising radiation is acquainted with the hazards and the precautions necessary.

4.3 They must keep a register of all radiation sources in their respective departments together with periodic contamination or leakage checks (monitor surveys, swab tests).

4.4 They must keep an account of the use of unsealed sources - see Section 9.

4.5 They must keep records and perform swipe tests on all sealed sources

4.6 They must make available copies of all records to the University Radiological Protection Officer.

5. Essential Names and Telephone Numbers

Radiation Safety Contacts

For further information or enquiries on matters regarding radiation protection, see site page Radiation Safety Committee

6. Control of Protective Measures

6.1 Any person, section or department proposing to undertake work with ionising radiation must inform the Committee on Radiation Safety IN ADVANCE through the University Radiological Protection Officer. Any change in personnel or in the nature of the work must similarly be notified IN ADVANCE. This procedure is to avoid delay because administrative arrangements (including extension or modification of the Licence from the EPA Office of Radiological Protection) may have to be made.
6.2 If a department where relevant work is to be carried out does not already possess a Departmental Radiation Supervisor the head of department must nominate one.
6.3 Special areas must be set aside for work with apparatus emitting ionising radiation, with unsealed sources and with sealed sources. The Radiological Protection Officer must classify these areas and suitable warning notices displayed at the boundaries of such areas.
6.4 Working areas containing irradiation apparatus or sealed radioisotope sources will classify as follows:
(a) "Controlled Areas", where annual doses obtained by personnel might exceed three-tenths of the maximum dose limits allowed for Category A persons (see section 7.9) or any person working in the area liable to receive an equivalent dose greater than 6 mSv in a period of 12 months.
(b) "Supervised Areas", where it is most unlikely that the annual exposure will exceed three-tenths of the same dose limits or any person working in the area liable to receive an equivalent dose greater than 1mSv in a period of 12 months.
6.5 Laboratories handling unsealed radioactive substances may be classified as High, Medium or Low Risk Laboratories depending on their design. The quantity of radioactive substances, which may be handled, shall be limited in accordance with paragraphs 34 to 40 of ICRP 25 (Annals of the ICRP Vol. l. No. 2, l977 Pergamon Press). There will be a further class of supervised area suitable only for very low-level tracer work (See Section 9).

6.6 With the prior approval of the University Radiological Protection Officer, work with very small amounts of certain radioactive tracers (other than alpha-emitters) may be carried out in unclassified areas. In such circumstances the normal procedures for any mildly toxic substances must be observed.

6.7 Storage of Radioactive substances must be such that the dose rate at all accessible outside surfaces of the store does not exceed 0.l millirems (0.00l mSv) per hour. The store itself and all individual containers must be clearly identified with details and warning signs.
6.8 Transport of licensed items outside the department for which they have been ordered and into which they have been received must not be done without due caution and without prior notification of the University Radiological Protection Officer.

7. Personnel Supervision

7.1 No person may be allowed to handle radioactive material or to carry out work with ionising radiations until adequate instructions has been received by that person. To indicate that they have been made familiar with the precautions necessary, they must complete the relevant form.
7.2 An exposed worker who is liable to receive an effective dose greater than 6 mSv in a period of 12 months or an equivalent dose greater than three-tenths of the dose limits for the lens of the eye, or, as the case may be, the skin, hands, forearms, feet and ankles specified in Section 7.9 (Dose Limits for Exposed Workers) shall be classified as a Category A person and shall be subject to a routine medical examination and an annual review.
7.3 According to S.I. No. 125, an exposed worker who is not classified as a Category A worker shall be classified as a Category B person.
7.4 No person under l8 years of age shall be permitted to take part in work, which might result in his being classified as a Category A or B person.
7.5 As soon as a pregnant employees informs her employer of her condition, her employer should provide a level of protection for the child to be born which is comparable with that for members of the public. The dose limit for pregnant employees is 1 mSv for the remainder of the pregnancy. In the event of a pregnancy the woman should be taken off work involving radioisotopes.
7.6 Both Category A and Category B persons shall be subject to individual dose assessment by means of film badges. These will be issued and returned for analysis by the Departmental Radiation Supervisors, who will forward the doses recorded to the Radiological Protection Officer.
7.7 Any person who suspects that he has received an unusually large dose of radiation, or that he may have ingested or inhaled or had on his skin an appreciable amount of a radiochemical, must report the matter at once to his/her Departmental Radiation Supervisor who must take appropriate action and inform the University Radiological Protection Officer (the importance of immediate reporting is emphasised also in Section 3.l3).
7.8 Any spillage of a significant (> 5 uCi, >l85 kBq) amount of a Radio-chemical must also be reported (see 7.7).
7.9 No person must receive an exposure to Ionising Radiation in the course of their work in excess of the following annual dose limits:-

Dose Limits for Exposed Workers

1. The limit on effective dose for an exposed worker shall be 20mSv in a period of 12 months.
2. Without prejudice to subparagraph (1) -
(a) the limit on equivalent dose for the lens of the eye of such a worker shall be 150 mSv in a period of 12 months.
(b) the limit on equivalent dose for the skin of such a worker shall be 500 mSv in a period of 12 months; this limit shall apply to the dose averaged over any area of 1cm sq, regardless of the area exposed.
(c) the limit on equivalent dose for the hands, forearms, feet and ankles of such a worker shall be 500 mSv in a period of 12 months.
3. As soon as a pregnant exposed worker informs the undertaking of her condition, the equivalent dose to the child to be born shall be limited to 1 mSv for the remainder of the pregnancy.
Exposed workers must be over 18 years of age

Dose Limits for Apprentices and Students

1. The dose limits for an apprentice or student aged 18 years or over who, in the course of his or her studies, is obliged to use sources shall be the same as the dose limits for an exposed worker specified above.
2. The limit of effective dose for an apprentice or student aged 16 years or more but less than 18 years who, in the course of his or her studies, is obliged to use sources shall be 6 mSv in a period of 12 months.
3. Without prejudice to subparagraph (2) -
(a) the limit on equivalent dose for the lens of the eye of an apprentice or student referred to in that subparagraph shall be 50 mSv in a period of 12 months.
(b) the limit on equivalent dose for the skin of such an apprentice or student shall be 150 mSv in a period of 12 months; this limit shall apply to the dose averaged over any area of 1 cm sq., regardless of the area exposed.
(c) the limit on equivalent dose for the hands, forearms, feet and ankles of such an apprentice or student shall be 150 mSv in a period of 12 months.
(d) the dose limits for an apprentice or student to whom subparagraphs (1) and (2) do not apply shall be the same as the dose limits for members of the public i.e. 1mSv.

7.10 All doses to organs of the body should be kept within the limits described in S.I. 125 (See Licensing and Legislation for further information).
7.11 Dose limits for undergraduate students who must use sources, in laboratory practicals are one-tenth of the limits specified above for Category A persons and each single exposure shall not exceed one hundredth of these limits.
7.12Most importantly, and not withstanding the dose limits specified above, all exposures of persons to ionising radiations must be kept as low as reasonably achievable.

8. Emergency Procedures

8.1 General procedures for immediate execution in the event of an emergency are given below. Special emergency procedures relevant to particular laboratories will, if necessary, be displayed on site.
8.2 At the conclusion of an emergency the Department Radiation Supervisor, in conjunction with the University Radiological Protection Officer, must make a written report to the Committee on Radiation Safety together with recommendations for avoiding a recurrence. In accordance with Section 3.l3, the University Radiological Protection Officer, must make a written report to the Committee on Radiation Safety together with recommendations for avoiding a recurrence. In accordance with Section 3.l3, the University Radiological Protection Officer must report any accident or incident having a bearing on radiological safety to the EPA Office of Radiological Protection. This must be done as soon as possible but in any case not later than 48 hours from the time of the occurrence.

8.3 Radiation Accidents Involving Personal Injury


1. Severe Injury accompanied by Radioactive Contamination

  • The treatment of serious injuries must take precedence over decontamination and containment of contamination.
  • Immediate medical assistance can be obtained from Medical Advisor (or the Radiologist on emergency call) at the UCHG, or at home (see essential contact numbers). Call ambulance. Give (written) information regarding the nature and approximate amount of the radioactive contaminant and, if possible, telephone to the Accident and Emergency Department, UCHG, so that they are prepared to receive the injured.
  • If a LARGE SPILL (0.l mCi, 3.7 MBq) is involved, proceed as in 8.4 below.
  • Inform the Departmental Radiation Supervisor and the University Radiological Protection Officer.

 
2. Minor Injury accompanied by Radioactive Contamination

  • Render First Aid, thoroughly washing any contaminated sites, and monitor for residual contamination.
  • Inform the Departmental Radiation Supervisor and the Radiation Protection Officer.
  • If neither is available or there is any doubt concerning the treatment of the injury, proceed as in 8.3.1 above..

3. Over-Exposure to External Radiation

  • If the accident occurred with a high intensity beam it is imperative that the radiation beam be shut off or the casualty moved from the radiation field before any other action is taken. If medical attention is urgently required, proceed as in 8.3.1 above.
  • Inform the Departmental Radiation Supervisor and the University Radiological Protection Officer.

8.4 Radiation Accidents Not Involving Immediate Personal Injury
· Large Spills of Radioactive Material (>0.1 mCi, >3.7 MBq)

  • Warn personnel and evacuate the laboratory
  • Decontaminate personnel
  • Turn off all laboratory services except lighting, but including ventilation if appropriate.
  • Close all doors and windows.
  • Inform the Departmental Radiation Supervisor and the College Radiological Protection Officer.

· Over-Exposure to External radiation

  • Inform the Departmental Radiation Supervisor and the University Radiological Protection Officer.

8.5 Radiation Accidents Involving Fire

  • In the event of fire, follow the University Instructions in Case of Fire and state that radioactivity or radiation is involved.

8.6 Flood

  • Remove all radiochemicals from the path of the water.
  • Stop the source of the water, if necessary call the buildings office. Stop any flow of water out of the suite. If the water is running near electrical outlets isolate the laboratory electrically, if necessary call the buildings office. Protect sensitive equipment with plastic sheeting.
  • Inform the suite manager, Departmental RPS and University RPO immediately.

8.7 Action to be taken in the Event of a Source of Ionising Radiation becoming Lost or Stolen.

  • Inform the Departmental Radiation Supervisor and the University Radiological Protection Officer.
  • In the event of neither of the above being available, the Gardai and the EPA Office of Radiological Protection must be immediately informed.

9. Rules for Persons working with Unsealed Radioisotpes

9.1 Scope
9.1.1 These rules apply to all work with unsealed radioisotopes but are particularly designed for research work and teaching being carried out in the Departments of Biochemistry, Chemistry, Micro- biology and Physiology. Equivalent projects when carried out in the Departments of Anatomy, Experimental Medicine or Oceanography has also been taken into account.
9.1.2 The radioisotopes used unsealed at NUI,Galway include the following, classified according to their radiotoxicity.       

Low toxicity

Medium toxicity

Tritium

Carbon - 14

 

Iodine - 125

 

Phosphorus - 32

                                                  
9.1.3      These rules are graded to cover three types of situation:
(a) Tracer Laboratories, where laboratory design and facilities are not such as to allow classification as a Low Risk Laboratory. The maximum amounts of labelled compounds that may be used are listed here.

Procedure

Low toxicity radioisotopes

Medium toxicity radioisotopes

Simple storage

3.7 GBq (100 mCi)

37 MBq (1 mCi)

Very simple wet operation

370 MBq (10 mCi)

3.7 MBq (0.1 mCi)

Normal chemical operation

37 MBq (1 mCi)

370 kBq (0.01 mCi)

Complex wet operation

3.7 MBq (0.1 mCi)

37 kBq (0.001 mCi)

Volatile or dry,  dusty components

370 kBq (0.01 mCi)

3.7 kBq (0.0001 mCi)

This table was derived from ICRP 25, paragraphs 34‑40 by dividing all amounts for a Low Risk Laboratory by 10.
The following laboratories are classified as Tracer Laboratories:


Department          Area             Room Description

Biochemistry          All of 203       Research suite, Upper Corrib Wing

(b) Low Risk Laboratories, where facilities etc. are adequate and suitable amounts of isotopes may be used. The maximum amounts of labelled compounds that may be used are listed here.


Procedure

Low toxicity radioisotopes

Medium toxicity radioisotopes

Simple storage

37 GBq (1000 mCi)

370 MBq (10 mCi)

Very simple wet operation

3.7 GBq (100 mCi)

37 MBq (1 mCi)

Normal chemical operation

370 MBq (10 mCi)

3.7 MBq (0.1 mCi)

Complex wet operation

37 MBq (1 mCi)

370 kBq (0.01 mCi)

Volatile or dry, dusty components

3.7 MBq (0.1 mCi)

37 kBq (0.001 mCi)

This table was derived from ICRP 25, paragraphs 34‑40.
The following laboratories are classified as Low Risk Laboratories:


Department          Area             Room Description

Biochemistry          All of 138       Sequencing Area for CMBG

(c) Medium Risk Laboratories, where facilities etc. are adequate and procedures such as radio-iodinations with Iodine-125 or manipulations with larger amounts of Phosphorous-32 may be carried out.  
The following laboratories are classified as Medium Risk Laboratories:


Department          Area            

Biochemistry          All of Radiochemical suite       

9.1.4 All these types of laboratories are classified as supervised areas and must be indicated by standard design radiation warning signs as supplied by the Radiological Protection Officer. No work involving breaking the above limits may be carried out and reclassification of a laboratory can only considered after application in writing to the Radiological Protection Officer.
9.1.5 All persons intending to perform work with unsealed radioisotopes must first be instructed in the handling and usage of radioactive materials and in radiological safety. They must carefully read the Univeristy Local Rules for the Protection of Persons Exposed to Ionising Radiations. Together with the Departmental Radiation Supervisor they must complete the relevant form.


9.2 General regulations


9.2.1 All work with unsealed radioactive material must be segregated from other work and, where possible, carried out in a laboratory reserved for this work alone. The room or area used must be suitable and must have the prior approval of the Radiological Protection Officer.
9.2.2 Entry to such an area should be restricted to authorised personnel and radiation warning signs must be prominently displayed.
9.2.3 On completion of any operation in which radioactive materials are handled the personnel involved should wash their hands thoroughly. In the event of a spillage, it is necessary to monitor the face and other exposed portions of the body, in addition to the hands. In addition, any equipment used that is in general use in the department should be carefully monitored to ensure that it has not been even slightly contaminated.
9.2.4 All working surfaces and the floor of the supervised area must be regularly and systematically monitored for contamination. Direct monitoring, using a suitable ratemeter should be carried out where feasible. Indirect monitoring using wipes or swabs must be used as required. This involves wiping the suspect area with a tissue or filter paper, transferring the wipe or swab to a scintillation vial (+ scintillation cocktail) and counting as usual.
9.2.5 Working procedures must be designed to minimise the spread of contamination from the working area, not only in the interest of the safety of personnel but also to prevent interference with measurements of radioactivity. For this reason, all dispensing of concentrated stock solutions (7.4 MBq/ml; 0.2 mCi/ml) and especially dry, solid radioactive substances, and all procedures involving the production of radioactive spray, vapour, dust or gas must be carried out in an efficient fume-cupboard or glove box.
9.2.6 Eating, drinking, smoking or the application of cosmetics in the designated area is prohibited.
9.2.7 Pipetting of radioactive material by mouth is prohibited - use samplers, bulb or safety pipettes.
9.2.8 Protective clothing (e.g. white coat buttoned up) must be worn at all times in the radioactive working area and should be reserved for this purpose alone. This rule should be applied even at low levels of activity due to the risk of contaminating other work.
9.2.9 To avoid the spread of contamination in the event of a breakage or spill, all work with greater than tracer concentrations (0.2 mCi/ml; 7.4 MBq/ml) should be carried out over large drip-trays lined with absorbent disposable paper.
9.2.10 All containers of radioactive materials must be clearly labelled.
9.2.11 For each lot of labelled material received, a new radiochemical use and disposal form should be started, and kept up to date as the material is used (Forms available on this site)
9.2.12 All accidents, involving radioisotopes, even if trivial, must be reported immediately to the Departmental Radiation Supervisor.


9.3 Handling and disposal of radioactive waste


9.3.1 Records must be maintained of the ways in which radioisotopes are used and disposed of. No disposals may be carried out except by permission of the Departmental Supervisor acting in consultation with the University Radiation Protection Officer. A safe storage place is a place designated as such by the Radiological Protection Officer.
9.3.2 The contents of liquid scintillation vials and other contaminated organic solvents should be transferred to the clearly labelled winchester bottles or suitable drums and must be incinerated according to the regulations laid down by the Radiological Protection Officer.
9.3.3 Low activity aqueous waste must be stored in labelled bottles and must be disposed of according to the regulations laid down. This will normally be by flushing through a special designated sink after dilution to an approved level.
9.3.4 Solid contaminated waste (e.g. plastic vials, tissues, syringes, etc.) should be collected and stored in suitably labelled double-layer plastic refuse bags. These will be disposed of in accordance with the regulations laid down. This will preferably be by burning in an approved incinerator. Any bag containing greater than l-2 mCi (37-74 MBq) should be labelled with its estimated content.
9.3.5 The waste contaminated by Iodine-125 will be classified and disposed of as follows:
(a) Radiochemical Centre vials containing unused Iodine-125. After checking that the tops are tightly screwed down, each year's supply will be collected in a suitable container. This will be clearly labelled with date and estimated content of Iodine-125 and stored in a safe place until it may be safely disposed of.
(b) "High" level liquid waste consisting of unreacted Iodine-125 etc., about (2 x 10-5 Ci/ml, 370-740 kBq/ml initially) will be collected and stored labelled with date, in a safe place until it may be clearly disposed of.
(c) Solid waste consisting of plastic counting tubes, contaminated tissues, etc., will be collected and stored, clearly labelled with date in double layer plastic sacks about (10-5 Ci/kg, initially) in a safe place until it may be safely disposed of.
(d) Low-level liquid waste (10 nCi/ml; 370 Bq/ml) will be stored in clearly labelled drums until it may be safely disposed of.
9.3.6 Waste contaminated by other radioisotopes will be disposed of as determined by the Radiological Protection officer. For shorter half-life isotopes this will normally involve storage until the activity is negligible.
9.3.7 In all cases the labels on radioactive waste must be sealed in plastic to ensure legibility throughout its storage lifetime. Details of such labels can be obtained from the Radiological Protection Officer.


9. 4 Radiochemical Suite, Dept. of Biochemistry - Supplementary rules
9.4.1 Services include a fume cupboard designed for radiochemical use, a wash-up sink, and all normal laboratory services. The floor surface is non-absorbent and the walls and ceiling are treated with non-absorbent paint.
9.4.2 Access to the suite is restricted to those having work to do in the suite.
9.4.3 All manipulations with free iodine-125 and other materials giving off radioactive vapours of dust must be carried out in the fume cupboard.
9.4.4 Whenever possible, work must be carried out over a tray lined with absorbent disposable material to provide containment in the event of spillage.
9.4.5 Levels of contamination in the laboratory, which would present little or no health hazard, could seriously affect the reliability of the sensitive assays which are carried out there. In order to maintain the level of contamination at a minimum the following procedures must be carried out:
(a) All bench surfaces must be washed down at regular intervals.
(b) The floor must be mopped at regular intervals and fully cleaned and waxed at 2-3 month intervals.
(c) A dust-absorbent foot mat should be provided at the entrance and renewed when necessary. When any contamination is found, the area concerned must be thoroughly washed and rechecked. Isolated areas of stubborn contamination must be brought to the notice of the Departmental Radiation Supervisor who will take any necessary action.
9.4.6 Laboratory coats (buttoned up) must be worn by all personnel in the suite at all times.
9.4.7 Regular users of the laboratory should have separate white coats for use there, which are taken off before leaving. Hands should be washed and monitored before each break from work in the suite.



9.5 Precautions for Radio-Iodinations


9.5.l Iodine is a volatile material, and, therefore, the major hazard in working with Iodine-125 is that radioactive vapour may be inhaled and, therefore all iodinations must be carried out in a suitable, efficient fume cupboard. In addition, the direct dose of radiation to the body or hands may be excessive if precautions are not taken. However, if sensible precautions are taken the iodinator need never obtain a significant dose of radiation.
9.5.2 Record forms (Available on this website) must always be fully written up.
9.5.3 The iodine vial should be kept behind lead at all times other than when being used or transported. So also should the fraction-collector rack holding the separated reactants.
9.5.4 The iodine vial must be first opened only under the following conditions:
(a) Wrapped in tissue (to be monitored before disposal);
(b) While wearing two pairs of disposable gloves; and
(c) Well inside fume cupboard, with door at minimum convenient height.
9.5.5 The work should be arranged so that the hands and body are kept the maximum practical distance from the high specific activity material. Column chromatography with amounts greater than 0.l mCi (3.7 MBq) of iodinated material should be done in the fume cupboard, and the glass door kept down when access is not needed.
9.5.6 All personnel involved with iodinations must wear radiation monitoring film badges. A Digital dosimeter should be worn by the principal iodinator in which case a record taken of the dose detected should be taken.
9.5.7 The contamination checks detailed on the record form must be carried out before and after the iodination. Between these checks the laboratory should be regarded as contaminated. Therefore, access must be restricted and over-shoes must be worn.
9.5.8 Contamination checks may be done with the orange coloured Berthold LB1210 Monitor, the MiniMonitor+5.42 scintillation probe or by taking wipes for counting in the automatic Gamma Counter or a Liquid Scintillation Counter.
The taking and counting of wipes: This method is the only way in which surface contamination by tritium can be measured with present equipment; for 14C contamination it is an excellent method; and for 125I it promises greater sensitivity to very low-level soluble contamination than the 5-42 probe. The routine method is to wet a small piece of tissue, wipe the area of interest, insert the tissue in a counting tube or a liquid scintillation vial with cocktail, and count. For more precise measurements a small measured area is carefully swabbed with the tissue. The assumption of counting efficiencies of 33% for 125I (in the autogamma counter), 20% for 3H and 67% for 14C (in the Packard 3330 counter) will give realistic estimates of the degree of contamination provided one also makes the assumption that only about 10% of the removable contamination is transferred to the tissue.

10. Rules for working with Sealed Sources

10.1 All sealed sources must be kept in a secure environment.
10.2 All sealed sources must swipe tested for leaks every year. It is the duty of the each Departmental Radiation Supervisor to perform these checks and to keep records of each test. The swipe tests must be performed using a designated counter which has had a recent calibration certificate.
10.3 If the sealed source is moved from its secure environment this must be logged in a sign out book giving the details of where the source will be kept, the date when it was removed and replaced as well as the signature of the person responsible.
10.4 In the case of moving boxes of sources these must be individually checked and signed in and out. The contents of the box should be checked before and after movement.
10.5 When the sealed source is no longer required it must be given to the University RPO who will make arrangements for the permanent storage or disposal of the source.

11. General

11.1 The above regulations are only intended to give a broad outline of procedures to be followed. Included in separate appendices are detailed rules concerning the work in various laboratories, as well as regulations governing approved methods of waste management etc. All regulations will be kept under review by the Committee on Radiation Safety which will consider any proposed changes.

12. Interim rules/Radiochemical suite rules

12.1 Anybody entering the suite must sign the log giving his or her name, date, time in and time out. You should also indicate which isotope has been used. Anyone who is found in the suite and has not signed the book, for whatever reason and for any period of time, will in the first instance been warned and in the second banned from using the suite.
12.2 Swabs should be taken prior to starting work and when leaving. If the suite is found to be contaminated then the person who used it last will in the first instance be warned and in the second banned from using the suite. By not taking a swab you become responsible for all previous contamination. A separate book is provided to record the results of swabs.
12.3 White coats and dosemeters must be worn at all times. All users of the radiochemical suite must have had instruction in radiological safety.
12.4 All glassware should be cleaned and put away after use.
12.5 The two fridges must only contain the isotopes specified on the outside of the fridge. The book attached to each fridge should be used to note the material that is being stored in the fridge. Any material which is found in the fridge which is not in the book will be disposed of immediately without any checks.
12.6 In the event of an emergency the rules posted in the suite must be followed.