at Region Östergötland and Linköping University

Radiation Safety Guidelines

at Region Östergötland

and Linköping University: for laboratory work with

Local Authorization

SAMS, Radiation Protection

2010-12-16, rev3 2016-06-22

This document is available in four versions:

• Web based in Swedish www.liu.se/insidan/miljo/laboratoriesakerhetshandboken/stralskydd?l=sv

• Web based in English www.liu.se/insidan/miljo/laboratoriesakerhetshandboken/stralskydd?l=en

• Electronic document (pdf) in Swedish • Electronic document (pdf) in English (this version)

If discrepancies would occur, the web based Swedish version is valid.

Radiation Safety Guidelines at Region Östergötland and Linköping University

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Table of contents Radiation Protection Organization Radiation protection 3 Local authorization 4 Categorization of staff and premises 6 Education and training 7 Radiation protection audit 8 Radiation and its Risks Different types of [ionizing] radiation 11 Biological and medical effects 12 Radiation doses 13 Personal dosimetry 15 External irradiation 16 Internal irradiation 17 Radiation protection instrument 18 Radiation Protection in Practice Radiation protection recommendations 21 Work practices 22 Routines for monitoring of contamination 23 Measures in case of contamination 24 Handling of radioactive sources 25 Internal transportation 26 Cleaning of premises 27 Waste Management Waste management 31 Liquid radioactive waste 32 Solid waste management 33 Airborne radioactivity 34 Contact Information 35 Appendices Appendix 1 Activity limits for waste disposal 37 Appendix 2 ALImin values 39 Appendix 3 The Local radiation safety guidelines 41


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Radiation Protection Organization


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Radiation protection Radiation work is regulated, apart from the Work Environment Act, by special legislation, the Radiation Protection Act (SFS 1988:220) and Radiation Safety Authority (SSM) regulations. They specify the overall requirements of radiation protection organization, authorization, justification, competence / training and quality assurance, which is a prerequisite for good Radiation Safety culture and practice.

The Radiation Safety Handbook and its main document, the Radiation Safety Guidelines at Region Östergötland and Linköping University, provide the support documents for radiation protection managers and staff working with ionizing radiation for the implementation of radiation safety regulations.

For those laboratories that hold a Local Authorization, their contact person has to ensure that a full copy of the Radiation Safety Handbook, together with local appendices is available in the laboratory. See Appendix 3 The Local Radiation Safety Handbook.

The Radiation Safety Handbook is available, together with additional material, at the website (Laboratory Safety Manual1)

Radiation Protection Organization The primary responsibility for radiation protection of staff, patients, animals and the environment rests, according to the law (SFS 1988:220), with the Principal office within the University, and the Region for activities in the county. The operational responsibility for radiation protection activities has been delegated to department heads, “prefekter” (LiU) and business managers, “verksamhetschefer” (Region). Laboratories are expected to have the resources and authority required for the operation and the radiation safety.

1 http://www.liu.se/insidan/miljo/laboratoriesakerhetshandboken/stralskydd?l=en


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Local authorization For operations at Region Östergötland, SSM has issued licenses for the collection of radiological work, one that applies to nuclear medicine and laboratory work with radionuclides, one for radiation therapy, and one for diagnostic radiology. Similarly, SSM issued an aggregated license for LiU for the use of radionuclides and x-ray equipment (up to 200 kV) for scientific purposes and teaching.

For the individual department's / institution's work with radionuclides and x-ray equipment it is required to apply for an annual Local Authorization, assessed and issued by the Region's and LiU's radiation protection officer. This assumes that the individual Section / Dept. total activity does not exceed 1 GBq (Class B) or 10 GBq (Class C and D), see below. Working with higher amounts of activity in class B-D requires special license directly from SSM via the Radiation Protection Officer. If planning for work with radioactivity of class A, the Radiation Protection Officer shall be contacted for evaluation of conditions to comply with the restrictive radiation protection requirements.

Local Authorization can only be granted if the conditions in SSM's regulations are met, SSM FS 2008:28 (unsealed sources), SSM FS 2008:27 (accelerators, and sealed sources), SSM FS 2008:25 (radiography), SSM FS 2008: 14 (lasers). Both the license application and the application for Local Authorization shall be submitted to the Radiation Protection Officer. The application shall on request be submitted annually. For new or modified activities you are requested to apply in advance at any time during the year.

The application shall be signed by the head of the department and contact person for radiation protection issues.

Classification of radionuclides Radionuclides are categorized into four classes with regard to risks for internal contamination. The classes in order of decreasing radio toxicity ("harmfulness") are named A, B, C and D. See also Appendix 2 regarding ALImin values.

Class A: e.g. 210Pb, 210Po, 226Ra, 230Th, 239Pu, 241Am, 244Cm, 252Cf Class B: e.g. 22Na, 36Cl, 54Mn, 60Co, 89Sr, 90Sr, 110mAg, 125I, 131I, 134Cs, 137Cs, 152Eu, 154Eu, 192Ir, 224Ra. Class C: e.g. 14C, 18F, 24Na, 32P, 33P, 35S, 51Cr, 55Fe, 57Co, 63Ni, 65Zn, 75Se, 90Y, 99Mo, 111In, 123I, 198Au,

203Hg Class D: e.g. 3H, 11C, 99mTc, 133Xe, 232Th, Th (nat), 238U, U (nat)


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From a risk perspective, the handling of radionuclides is graded in three different classes.

Work type I: Work with a risk of internal exposure by inhalation. This includes the handling of radioactive material in gaseous or powder form and the processing of solid radioactive material.

Work type II: Work with a risk of external and internal exposure, but where the risk of internal exposure by inhalation is small. This includes the handling of radioactive solutions in chemical analysis, synthesis, labeling, manufacturing of products and animal experiments.

Work type III: Work with minor risk of external or internal irradiation. This includes simple handling of radioactive solutions, such as withdrawals from stock solutions.

Table 1 Limits of activity per job according to toxicity class and type of

work.

Work type: MBq of radionuclide of toxicity class:

B C D

I 1 10 100

II 10 100 1000

III 100 1000 10000

If these limits are exceeded, separate license from SSM is required.


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Categorization of staff and premises (SSM FS 2008:51) Employees in work with ionizing radiation are subsumed into either category A or B. If it is determined that the employee's annual effective dose will not exceed 6 mSv, but might exceed 1 mSv in a year, is the category will be B. Otherwise, when the annual dose might exceed 6 mSv, the category will be A. This will be assessed by the Head of department in consultation with the radiation protection officer. The classification should be documented in the local Radiation Safety Handbook.

For category A workers continuous monitoring of individual doses is mandatory (see personal dosimetry) as well as medical surveillance.

Premises where there is a significant risk of internal or external exposure and / or contamination which may result in staff doses (annual effective doses) >6 mSv are designated as controlled area, for which specific requirements for signage, access and written work rules. Other facilities where work with ionizing radiation is performed is designated as protected areas, which also requires signage and work rules, but is less rigorous. Radiation Protection Division will help radiation protection manager with this classification and information about the requirements to meet.

Medical surveillance of workers (SSM FS 2008:51) Special medical examination is mandatory for workers in Category A. The purpose of the examination is to assess whether the employee would be at particular risk of harm from exposure to ionizing radiation during radiological work. However, the medical examination cannot show whether the work is undertaken satisfactorily according to radiation safety. The medical examination shall be made at the introduction to the work and then every three years. The employers are responsible for the initiative for the initial investigation. The employee is called on to the upcoming examinations by occupational health services. Intermediate years, special health declaration is submitted to the examining doctor upon request.


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Education and training (SSM FS 2008:28, § 7, 2008:27, § 6)

All participants in work activities involving ionizing radiation have to undergo adequate education and training in radiation safety before starting work. The local radiation safety manager will determine, in consultation with the Radiation Protection Section, of what is proper level of training. The staff shall be familiar with the Radiation Safety Guidelines at Region Östergötland and Linköping University and of the local work routines. Any laboratory must organize a local introduction in radiation safety practices. Everyone who participates in work activities involving ionizing radiation has an individual responsibility to comply with these rules.

Radiation Protection Division holds an annual radiation safety course (12+4 h) as well as a refresher course (4 h) which is advertised on the Web and via the local contacts. Other acquired radiation physics courses may be sufficient. The date and extent of, radiation safety training must be recorded in the local radiation safety handbook for each worker.

Refresher training should be repeated at least every ten years.


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Radiation Protection Audit (SSM FS 2008:28, §3, §6, 2008:27, §3, §8) Radiation Protection Division annually book audits at the laboratories that have or will apply for Local Authorization. Present at the visit should, in addition to radiation protection section and laboratory contact person, be persons responsible for the methods used. The laboratory itself can initiate an audit of radiation protection when changing premises, increasing their operations etc. The purpose of the visit is to exchange experiences, review the local radiation safety manual and to jointly ensure that good radiation protection conditions prevail. A checklist is followed and an action list is established. Feedback is performed within the agreed time.

Radiation Protection Division writes a protocol during the audit, which then is stored in the local radiation safety manual, and also shared to the local radiation protection manager and head of department / operations manager.

Radiation and its Risks


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Different types of [ionizing] radiation From a radiation protection standpoint, it is important to know what type of radiation that is at hand, because it will affect the radiation shielding methodology and the biological effect of the different radiation types. There are mainly four radiation types:

Alpha radiation (α): emitted during radioactive decay. The particles contain two protons and two neutrons, have a short range (a few cm in air, up to 0.1 mm in tissue), but are very energetic. Causes no radiation problems at external exposures, but may pose radiation problems for internal contamination by alpha emitters (via inhalation / ingestion).

Beta radiation (β) emitted during radioactive decay. The particles consist of an electron, are limited in range, from a few mm to 10 m in air, depending on energy. Beta radiation may cause erythema, at irradiation of unprotected skin and cataracts in the eye lens by prolonged exposure of the eyes. Beta radiation can cause radiation problems at internal contamination (via inhalation / ingestion).

Gamma radiation (γ): emitted during radioactive decay. The radiation consists of electromagnetic waves, have in principle infinite range but the fluence decreases with depth in matter, the denser the substance, the faster the decline. For this reason we use a high-Z material e.g. lead in radiation protection shielding.

X-rays: radiation produced in accelerators and x-ray machines. The radiation consists of electromagnetic waves with the same characteristics as gamma rays.

Neutrons (n): released by nuclear fission, and in some reactions between ionizing radiation and atomic nuclei. Uncharged particle, often with high energy. Decreases with depth in the matter, most effectively in light hydrogen-rich materials, e.g. water.

Note that during radioactive decay, combinations of several radiation types may occur.

Description of appropriate shielding for radionuclides and radiation types are found in the datasheet of the Radiation Safety Handbook appendices.


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Biological and medical effects Irradiation of biological tissues at low to moderate doses causes cell killing, however at a level which normally does not obstruct the functions of the tissue / organ. In addition, the radiation may cause damage to the genome, which can cause changes in DNA code. Damages of DNA induced either directly by ionization of atoms or molecules in the DNA chain or via formation of reactive free radicals that may cause DNA lesions. Such a defect can disable cell division, and the cell is thus eliminated, or can be an initiator of the formation of a cancer cell.

There is a distinction between acute and late effects of ionizing radiation. Late effects are cell defects that are manifested several years after initiation, resulting in cancer of some type. Late effects can occur even at relatively low levels of exposure. Acute effects appear when the radiation dose (effective dose, see below) is of the order of 1 Sv or more. If the internal organs are exposed at these doses it may result in organ failure, which can be lethal. At very high doses (about 100 Sv) symptoms appear within a few minutes and if vital organs are exposed it will be lethal within a few hours. For lower doses, the effects may appear after several days or up to several weeks. Normally, a whole‐body dose greater than 4‐5 Sv leads to death within a few weeks, but adequate medical treatment can prolong the survival. No human has survived a whole‐body dose of 10 Sv or more.

When working with ionizing radiation in Sweden, it is extremely rare with exposures at levels that induce lethal acute radiation effects, and at Linköping University and Region Östergötland, it has never occurred. At a few occasions, the staff at LiU received acute radiation injury of the skin (small areas) following accidental exposure of the extremities. However, no long term medical effect has been registered.


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Radiation doses

Activity The SI unit of activity is becquerel, symbol Bq. 1 Bq equals one nuclear transformation (disintegration) per second. Becquerel supersedes the former unit of activity, Curie, symbol Ci.

1 GBq = 0.027 Ci = 27 mCi, 1 Ci = 37 GBq 1 MBq = 0.027 mCi = 27 μCi, 1 mCi = 37 MBq 1 Bq = 2.7 10-11 Ci = 1 disintegration / s, 1 μCi = 37 kBq

Dose Units (SSM FS 2008:51, appendix) The SI unit of absorbed dose is gray, symbol Gy. 1 Gy is equal to one joule absorbed radiation energy per kg (J/kg). Different types of ionizing radiation (α, β, γ, x-rays, n) result in different degrees of harm in biological tissue. Therefore, in radiation protection, the quantity equivalent dose (denoted HT) is used, which is equal to the absorbed dose (D) in a tissue/organ T, multiplied by a quality factor (wR), which takes into account the biological harmfulness of the radiation type. When there are multiple radiation types simultaneously the equivalent dose is summed according to:

Equivalent dose: HT = Σ DT,R wR, where wR is the quality factor for radiation type.

Effective dose (E): finally, to assess and compare the risks related to irradiation of different organs, a quantity called effective dose (E) is introduced. The effective dose is the sum of the equivalent doses in all tissues / organs from external and internal exposure, multiplied by a weighting factor for each tissue/organ at risk of developing [lethal] cancer. The weight factor is 0.12 for each of the most radiosensitive organs; breasts, lungs, stomach, red bone marrow, colon, 0.04 for the bladder, esophagus, liver, thyroid, and 0.01 for bone surfaces, brain, skin, salivary glands.

Effective dose: E = ΣHT wT, where wT is the weight factor for each of the tissues/organs.

The unit of equivalent dose and effective dose is sievert, symbol Sv. Sievert is a large unit, in the context of radiation protection we often use millisieverts (mSv, 1 mSv = 0.001 Sv).

Remarks: • quality factor, wR

= 1 for x-ray, γ, electrons and β-particles = 20 for α-particles = 2.5 - 20 for neutrons (energy dependent)

• for gamma and beta radiation is 1 Gy in a tissue/organ = 1 Sv equivalent dose • Radiation instruments calibrated in the superseded unit roentgen(R) should be changed to SI

units. • For approximation; 1 R ≈ 10 mSv

Old units: 1 rad = 0.01 Gy 1 rem = 0.01 Sv


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Dose limits The following dose limits apply for external and internal exposure (SSM FS 2008:51):

Maximum admitted radiation dose (effective dose) for radiation workers over age 18, whole body irradiation, is 100 mSv per five years, maximum 50 mSv in a single year. The corresponding dose limit for a single year for students / apprentices between 16 and 18 years of age is 6 mSv / year. For pregnant women, a dose limit of 1 mSv to the fetus apply for the whole pregnancy period. In addition, the following maximum dose equivalents apply:

• skin, hands and feet: 500 mSv / year • eye (lens): 150 mSv/year

Weight factors, wT, for organs, giving the relative risk of lethal radiation induced cancer in an organ. The sum of factors = 1.


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Personal dosimetry (SSM FS 2008:51)

Radiation Protection Division is approved by the Swedish Radiation Safety Authority for dosimetry service for the measurement of personal dose equivalent Hp(10) which is used to estimate the effective dose, see Radiation doses and limits. Personal dose measurements are conducted with electronic Direct Ion Storage (DIS) dosimeters and with thermoluminescence dosimeters(TLD).

For category A workers (see Categorization of staff and premises), continuous measurements of personal dose is mandatory. Radiation Protection Division provides and evaluates these dosimeters, and reports monthly doses to the Swedish Radiation Safety Authority.

For category B workers there is no legal requirement for continuous dose measurement, as long as measurements or experience can show that the radiation doses will always be expected to be lower than the threshold for category A. If measurements are desired, the radiation protection section provides, after consultation with the radiation protection officer, dosimeters including workers in category B, evaluated quarterly.

New staff eligible for monitoring of personal doses shall promptly notify their personal data and the type of duties to the contact person who will then forward the information to the Radiation Protection Section.

Radiation Protection Division also administers the measurement of finger and eye doses, and environmental measurements for evaluation of radiation protection of the premises.

When working with open radioactive sources dose burden from internal contamination shall also be evaluated, this is normally done by monitoring of excretion of the radionuclide in the urine. With knowledge of the excretion one can assess the internal contamination and thus make an estimation of the dose. Sampling and analysis shall be carried out on regular basis, but also in cases of suspected contamination events. The Radiation Protection Division manages urine analysis and dose estimations.

When working with iodine isotopes corresponding dose estimations of internal contamination can also be made by external spectrometric measurement of the thyroid, provided by the Radiation protection section.


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External irradiation The factors that determine the radiation risks on external radiation are:

• Activity and radionuclide / radiation type

• External radiation shields, shield thickness, material and position will determine the reduction of radiation intensity. Suitable materials depend on radiation type and appropriate thickness is determined by the energy (see Annex Radionuclide info).

• Distance from the radiation source, the radiation intensity decreases rapidly with distance, doubling the distance reduces the radiation intensity to 1/4 (inverse square law). Therefore, work at the largest possible distance from the source, and use distance tools (pliers, forceps) when the source is not sufficiently shielded.

• Residence times in the radiation field; a doubling of the time gives a doubling of the absorbed dose. Therefore, work quickly and methodically.


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Internal irradiation The factors that determine the radiation risks of internal irradiation are:

• Radionuclide; amount of activity, physical half-life, radiation type, chemical form.

• The body's metabolism of this radionuclide, which is reflected in the so-called biological half-life.

• Intake: oral / inhalation.

For internal irradiation, the following applies (SSM FS 2008:51) For radiation doses caused by radioactive substances inside the body, the same annual limits for effective dose apply as those stated for external exposure. Effective doses due to intake of radioactive material are limited by the quantity ALI (Annual Limits on Intake). ALI is the limit of annual intake of radioactive substances to persons engaged in radiation work. The limit is set according to the annual limit for radiological personnel, 20 mSv, or where applicable, the limit on equivalent dose for a single organ (500 mSv). There are different ALI values for ingestion respectively inhalation. ALImin refers to the lowest of these values for each radionuclide. ALImin-values for the most common radionuclides are found in Appendix 2 ALImin values.


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Radiation protection instruments (SSM FS 2008:28. §24, 2008:27, §15) Appropriate radiation protection instruments shall be available in the laboratory, for monitoring of radiation levels in the laboratory, but also for contamination control. Typically, for external beta radiation, GM tube with thin entrance windows is used and for external gamma radiation GM tube or scintillating NaI (Tl) crystal is used. Feel free to contact Radiation Protection Section for advice before purchasing. Radiation Protection Division offers regular opportunities for quality control and calibration of radiation protection instruments. The laboratory must have local procedures for performance testing of its radiation protection instruments. Function checks should be made in conjunction with each measurement. Quality control using a calibration source shall be made at most three years intervals. Calibration should be considered if the instrument falls outside the tolerances. Calibration results and control measures shall be documented in the local radiation safety manual.

When working with radionuclides that emit beta radiation with low energy, e.g.3H, 14C, typical radiation protection instruments are not designed to register such beta radiation. Contamination control can instead be made by using liquid scintillation counters / beta counters for quantification of the smears. If the lab does not have access to such a detector, examine the possibilities to measure at another lab, otherwise the measurements can be made at the Radiation Protection Section.

Radiation Protection in Practice


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Radiation protection recommendations

The main principles of Radiation protection: 1. Justification: Any activity by ionizing radiation and radioactive substances must carry

a net benefit.

2. Optimization/ALARA: All doses should be kept as low as is practically possible.

3. Individual protection: No individual may be exposed to inappropriately high dose of radiation.

The following rules apply generally: • Participants in radiological work shall be at least 16 years of age (min 18 years for

employees and 16 years for students and apprentices).

• Individual doses must be kept below the maximum permissible radiation dose, and being kept as low as is reasonably possible.

• Any unnecessary exposure should be avoided.

• Pregnant women who work with ionizing radiation have the right to reassignment.

Dose limits • The easily accessible parts of the laboratory, where staff is staying temporarily, the

dose rates must not exceed 20 μSv/h.

• In areas where radiological staff stay for longer periods, the dose rates must not exceed 2 μSv/h.

Note: The above dose rates do not include background radiation.


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Work practices

(SSM FS 2008:28 § 19-23)

Carry out your work using the following principles:

1. Separate the work with radioactivity as far as possible from other operations.

2. Keep the lab clean and free from unnecessary equipment.

3. Use as far as possible shielding between source and body, and use remote tools.

4. Use lab coat and liquid absorbent paper with plastic underside for bench cover.

5. Protective gloves made of plastic or rubber should always be worn when handling open radioactive sources, and be changed regularly. Used protective gloves should be treated as radioactive waste. Always wash your hands after ending working.

6. Safety goggles should be worn when working with any open beta-emitting substances, and

with solutions/samples with high energy beta emitters (e.g. P-32, P-33, Sr-90) and in general if there is a risk of splashing.

7. Prevent hand-to-mouth spread by careful hand hygiene and by not eating, put on lip balm,

etc. in the laboratory.

8. When working with syringes, use syringe shielding.

9. The work should be performed in a fume hood, and especially if there is a risk of airborne radioactivity.

10. If you are assigned a dosimeter, wear your body dosimeter or ring dosimeter throughout the

work process. Wear dosimeters under a lab coat and gloves to prevent contamination of the dosimeter.

11. Minimize waste by using minimal activity. Dispose waste according to given rules, see the

Waste management sections.

12. Check for contamination of hands, clothes and shoes, and work tables, benches and tools with appropriate radiation protection instruments after finished work. Clean regularly and inform cleaning staff of the laboratory cleaning rules.

13. Do not work with unprotected wounds on hands or arms.

14. Exercise the procedures without the radioactive substance to minimize the time of exposure.


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Routines for monitoring of contamination (SSM FS 2008:28 §22)

The laboratory should have a routine that after each work shift inspect work areas, tools and clothing with appropriate radiation protection instruments (γ‐emitters, and β‐emitter with medium to high energy) or smears (β‐emitters, low energy, for example. 3H, 14C, 35S) measured in the liquid scintillator/β‐counter. In addition, contamination control should be performed immediately after suspicion of contamination. At least once every third month documented contamination check shall be performed.

Contact the Radiation Protection Section if personal contamination (skin/clothing) exceed three times the background level and other contamination (after decontamination) exceeds ten times the background level.

In cases where there is a probable risk of internal contamination, personnel monitoring is performed by measurement of urine samples (or in the case of iodine isotopes thyroid measurement). The Radiation protection section provides for analysis of urine samples.


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Measures in case of contamination

Measures to major contamination / personal contamination 1. If spills of radioactive iodine (especially ionic form) or significant contamination of other

radionuclide (> 1 ALImin), use great caution, immediate contact the radiation protection section for assistance with decontamination. Initiate actions as shown below.

2. Stop immediately ongoing operations. Turn off any apparatus. 3. Other staff, unless they are suspected to be contaminated, shall leave the laboratory as soon

as possible. 4. Personal decontamination should begin as soon as possible. 5. Try to immediately verify suspected skin contamination by direct measurement or wipe test. 6. Wash contaminated skin with soap and luke warm water. This may require repeated

washings to remove the activity completely. Do not reduce the skin's protective function by hard scrubbing or harsh solvents.

7. Let contaminated wounds bleed a while if possible. Rinse the wound thoroughly with clean water.

8. Seal off the room. Put notice on the door of the event. 9. Leave any contaminated clothing and shoes in the laboratory. 10. Inform all staff at the laboratory. 11. Decontamination of premises and equipment are carried out according to the instructions

from the Radiation Protection Section. 12. Document accurately what happened. Register and report the injury. The dose assessment is

attached to the personal report made according to organization's procedures. In cases of ingestion (oral / inhalation) of radionuclides to the staff, the Radiation protection section makes internal dose assessment.

13. All incidents and mishaps shall be reported to the Radiation Protection Section.

Measures to minor contamination without personal contamination

1. Mark the area where the spillage of active material occurred. Inform the personnel. 2. Wear gloves and shoe covers and wipe up spilled liquid with absorbent paper. 3. Wash contaminated surfaces with mild detergent. Wipe with absorbent paper. 4. Check with radiation instruments or wipe test that cleaning paid off, otherwise repeat the

wash. 5. Surfaces where, after cleaning, the surface activity is greater than 40 Bq/cm2, shall be

covered with suitable protective material, plastic or wood. 6. If decontamination is not satisfactory or if in doubts about cleaning procedure, please

consult the Radiation Protection Section. 7. Take measures to prevent recurrence. 8. Document the contamination event.


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Handling of radioactive sources

Purchasing procedures Deliveries of all radionuclides to laboratories at US and HU shall be made via the Radionuklidcentralen, RNC. Enter, therefore, always shipping address as: Godsmottagningen University Hospital, RNC plan 08 f.v.b. DEPT./CLINIC Attn: Contact person 581 85 Linköping

Radiation Protection Section alerts addressee or local radiation protection manager by phone or e‐mail when delivery can be picked‐up from the RNC. Radiation Protection Section administers the keys to the RNC. RNC is on level 08 of the main block, US. Follow the signs from the elevator hall A. Deliveries arriving to US when the goods reception is closed are managed by the emergency department (akutmottagningen) that has instructions to forward it to the RNC.

Laboratories at Campus Valla shall have procedures so that deliveries are made safely. Information on the radionuclide, activity, supplier and batch number shall be notified the Radiation Protection Section.

All suppliers of radioactive material require a copy of the aggregate license. Copies are obtained from the Radiation Protection Section. The amount of activity is limited, however, according to the Local Authorization. Prior to purchase of fixed / sealed sources contact must be made to the Radiation Protection Section.

Activity register (SSM FS 2008:28, § 9, 13, § 29, § 36) Radiation Protection Section registers the received radionuclides. Locally, the laboratory shall hold a register of current activities, including fixed/sealed sources.

Storage (SSM FS 2008:28, § 30‐34)

• Radioactive materials should be stored out of reach for unauthorized persons. • Radioactive materials shall be stored fireproof. • Containers with radioactive materials shall always be labeled with the radiation alert symbol.

o When the amount of activity exceeds one waste limit or 1 MBq, radionuclide (s), activity, date and signature should be stated.

• Gamma emitters with an activity above 1 MBq shall be kept in lead containers or behind lead shielding. Beta emitters are kept in plastic containers.

• Around containers or small shielded storage rooms containing radioactive material, the dose rate should be kept below 20 μSv/h at 5 cm from the container surface or the radiation protection area.

• In rooms where personnel regularly reside, the dose rate should be kept below 2 μSv/h. • Storage areas of radioactive materials should have signs displaying storage location for

radioactive material, the person responsible and the radionuclides contained in the storage. Radiation Protection Section provide signs.

• Volatile radioactive materials should be stored in well ventilated areas, e.g. in ventilated chemical cabinets or poison cupboards.


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Internal transportation (SSM FS 2008:28, §35) Internal transport of radioactive materials must be safe so that the risk of radioactive material stolen or lost is minimal. The laboratory shall have procedures for:

• Transport routes (to / from the RNC, waste storage or IFM waste room)• Monitoring (continuous transport, radioactive material shall not be left unattended during

transport),• Packaging (sealed suitable transport vessels) that is labeled (radioactive, nuclide, contact

person).

In case of an incident during transport, location should be marked to minimize dispersion. Follow decontamination routine and inform the radiation protection section. When transportation is made by an external agent (non‐laboratory personnel), the scope of the contract and contact procedures should be documented.


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Cleaning of premises (SSM 2008:28, §9 p.14) Local cleaning instructions shall be provided and the cleaning staff should be informed of these and associated risks. Cleaning instructions should be posted clearly on the premises. Room specific cleaning equipment should be considered where unsealed sources are present. Contact details must be documented.


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Waste management


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Waste management (SSM FS 2010:2) Radioactive waste delivered to Radionuklidcentralen (RNC), U.S. (Level 08, elevator A) or at the IFM's chemical waste store (B: 525), must be marked with a complete waste label, see pictures below. The Radiation Protection Section provides waste labels and keys to the RNC. The rules for solid and liquid waste apply in accordance to the following sections.

Waste regulations are formulated only with regard to radiation risks. Other criteria for the waste, as toxicity, fire hazard, risk of infection etc. must also be assessed and may cause the waste not be disposed of locally, regardless of the amount of radioactivity.

Radioactive waste that does not meet the rules for temporary deposition at the RNC or at IFM's chemical storage room awaiting decay for disposal, shall remain at the laboratory until agreement on the appropriate disposal method is made with the Radiation Protection Section. This is especially important for solid/sealed sources.

Radioactive waste must be documented. Templates of the waste documentation are available on Radiation Protection Manual website.

Waste Plan (SSM FS 2010:2) The local radiation safety manual shall include a waste management plan describing the radioactive waste generated in operations, including emissions and disposal of the wastes. This management plan must be updated before new radionuclides or new methods are taken in use.


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Liquid radioactive waste (SSM FS 2010:2) Liquid waste disposals to the sewer system must be soluble in water. Total disposal per month and laboratory may not exceed ten times the activity listed in Annex to the Radiation Protection Act (SFS 1988:220), see also Appendix 1. Disposable emissions per occasion shall be less than 1 times the activity. Flush thoroughly with water so that no activity remains in the trap. Scintillation fluid must not be poured down the sink. Discharges of liquid radioactive waste should be kept to one designated sink per laboratory. The sink must have a visible sign indicating where liquid radioactive waste may be flushed out, see picture below. The laboratory must, at the invitation of the Radiation Protection Section, provide an estimate of the annual released activity. Liquid wastes that are not soluble in water, nor containing hazardous chemicals, nor biological or infectious waste can be disposed of as solid waste. It should be packed in tightly closed containers with absorbent material equivalent to twice the solute volume. A maximum of 2 liters of fluid per waste container is allowed.

Exceptions (SSM FS 2010:2, § 9) Urine and feces from patients treated with radionuclides, in connection with examination or treatment, may be flushed down the toilet without regard to the maximum allowable emission activity.

Airborne radionuclide emissions (SSM FS 2010:2, § 5‐6) The regulating authority (SSM) request the organizations to assess and document airborne activity released to the environment. Assessments of the dose to the public are required. This can apply to work with open sources/solutions that are able to become airborne, e.g. by heating of the samples, and diffusion through the ventilation system. The Radiation Protection Section assists in the assessments.


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Solid radioactive waste (SSM FS 2010:2, §10‐14) Solid radioactive waste is divided into the following groups:

1. Sealed sources.2. Solid radioactive waste, contaminated materials (protective gloves, swabs, cover papers

etc.).3. Sealed containers with liquid radioactive waste.4. Mixed Waste. Radioactive waste with additional environmental impacts, such as infectious,

biological or chemical. Even radioactive waste having a low flash‐point

Solid waste can be deposited at the municipal waste facility, provided: 1. Sealed sources have an activity less than 50 kBq.2. The waste is packed securely in special waste boxes with inner plastic bag.3. The waste may contain a maximum of 2 liters of fluid and should contain the absorbent

material corresponding to the double absorbency.4. Activity per container may not exceed the limit values set out in annex to the radiation Act

(SFS 1988: 220), see Appendix 1, and divested activity per month from the laboratory not exceeding ten times the activity levels.

5. Surface dose rate on carton may not exceed 5 μSv/h.6. Waste carton equipped with completely filled white label RADIOACTIVE WASTE, see picture

below. (Labels received from the radiation section).7. Each tag has a unique number and content should be documented in the laboratory. When

the waste is disposed of, radiation protection division reports and then the package isdeleted from the list. Canceled labels should be reported to the radiation protection division.

8. If two or more radionuclides are added in the same waste cardboard, it must not be themaximum quantity of each radionuclide. Packaging must be 1 ≤ Σ Ai/Li where Ai is the activityof radionuclide i and Li is the corresponding exemption limit.

Cutting/pungent, biological and contaminated wastes are treated as individual hazardous waste if the conditions above are met.

Cutting/sharps are e.g. needles or non‐stick protection, suture needles, knife blade, acupuncture needles, needles with fixed needles etc. If the half‐life is shorter than 10 hours treated cutting/pungent as merely cutting/pungent.

Biowaste, as parts of tissue from animals or humans.

Contaminated waste as the needles used on humans. The following can be treated as conventional waste: contaminated waste that has been converted to non‐contaminated, i.e. autoclaved, disinfected accordingly waste from, for example, microbiological laboratory work.

Wastes with low flash point (< 60 °C) can be deposited at the RNC, but it is important that it be clearly marked on the waste label.

Wastes with scintillation fluid can be added in the waste boxes of absorbent material corresponding to double the volume of liquid. Maximum allowed packed 2 liters liquid per waste cardboard.

The solid radioactive waste is shipped to US the area down to the RNC by laboratories and local practices. Radiation Protection Division ensures that task — and surface dose rate above are met and forwards it to the waste facility as well as documenting.

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Wastes that do not meet the above criteria For radioactive waste which cannot be disposed of according to the rules above, and that cannot be deposited of locally at the laboratory, the radiation protection division shall be contacted. At Radionuklidcentralen, US, waste destined for disposal in municipal waste facility but that exceeds the activity limits, can be deposited in the waiting decay. This waste is noticeable and is documented in the same way, but with a yellow label. In the case of sealed sources (e.g. calibration sources, sources in equipment) shall be disposed for recycling or disposal be discussion with radiation protection section of the possibilities for coordination in order to reduce costs.


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Contact information Radiation protection officer Håkan Pettersson Office tel: 010‐103 17 52 (pager 1752) Cell: 0733‐795873 [email protected] fax: 010‐103 28 95 Radiation Protection Engineer Magnus Gårdestig Office tel: 010‐103 17 75 (pager 1775) [email protected] [email protected] Physicist Marie Carlsson Office tel: 010‐103 9666 (pager 9666) [email protected] Radiation Protection Section Radiation Physics Department O‐huset entrance 34, floor 08 University Hospital 581 85 Linköping Radionuclide central (RNC), floor 08, elevator A, Main building, University Hospital Arrivals and registration of radionuclides delivered to US and HU and waste management. Please state the following delivery address: Godsmottagningen Universitetssjukhuset, RNC floor 08 Forwarded to Dept. X Attn. Contact person 581 85 LINKÖPING Swedish Radiation Safety Authority tel: 08‐799 40 00 171 16 Stockholm (Regulator of ionizing radiation) Swedish Radiation Safety Authority contact at Region Östergötland and Linköping University Radiation Protection Officer Håkan Pettersson tel: 010‐103 17 52 Web: lisa.lio.se/stralskydd (internal) www.liu.se/insidan/miljo/laboratoriesakerhetshandboken/stralskydd Stralsakerhetsmyndigheten.se

http://lisa.lio.se/stralskydd

http://www.liu.se/insidan/miljo/laboratoriesakerhetshandboken/stralskydd

http://www.stralsakerhetsmyndigheten.se/


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Appendix 1 Activity limits for waste disposal

SSMFS 2010:2 (i) Activity limits for solid waste per nuclide and waste container for transport and

destruction at waste disposal site (Gärstadverket). When mixing several radionuclides in the same container limits are calculated with the equation below.

(ii) Activity limits per radionuclide and occasion when disposal of liquid water soluble radioactive waste by flushing in designated sink in the laboratory. Ten times this activity limit is allowed to be flushed per month and per laboratory.

Nuclide

Activity

[MBq]

Nuclide

Activity

[MBq]

3H 1000 99Mo 1

11C 1 99mTc 10

14C 10 111In 1

18F 1 123I 10

22Na 1 125I 1

32P 0.1 131I 1

33P 100 134Cs 0.01

35S 100 137Cs 0.01

36Cl 1 153Sm 1

45Ca 10 152Eu 1

51Cr 10 154Eu 1

89Sr 1 192Ir 0.01

90Sr 0.01 203Hg 0.1

90Y 0.1 201Tl 1

When mixing several radionuclides in the same waste container limits are calculated by

Σ Ak/Lk ≤ 1,

where Ak is the activity for radionuclide k, and L

k is the limit from the table above for radionuclide k.

Strålskyddsregler vid Region Östergötland och Linköpings universitet: Laboratorieverksamhet med Lokalt Medgivande

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Appendix 2 ALImin values ALImin

values for occurring compounds with nuclides below. 1 ALI corresponds to 20 mSv annual effective dose. Calculated from ICRP 1191

Nuclide

ALImin

[MBq]

Tox. Class

3H(HTO) 1100 D 3H (org) 480 D 14C 37 C 18F 410 C 32P 8 C 33P 80 C 35S oorg 15 C 35S org. 25 C 36Cl 3 B 45Ca 7 B 51Cr 530 C 89Sr 2.5 B 90Sr 0.1 B 90Y 7.5 C 99Mo 17 C 99mTc 690 D 111In 65 C 123I 95 C 125I 1.3 B 131I 1.8 B 134Cs 1 B 137Cs 1.5 B 153Sm 27 152Eu 0.5 B 192Ir 3 B 203Hg 9 C 201Tl 210 C

1 ICRP, 2012. Compendium of Dose Coefficients based on ICRP Publication 60. ICRP Publication 119. Ann. ICRP 41(Suppl.)

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Appendix 3 The Local radiation safety guidelines The local Radiation Safety Guidelines constitute a radiation protection quality manual for the Laboratory having a Local Authorization at The Region Östergötland and Linköping University.

The local radiation protection manager is responsible for compilation and revision of the local Radiation Safety Guidelines. The operative parts with record keeping etc. should be made available for the employees.

A printed copy of Radiation Safety Guidelines at Region Östergötland and Linköping University: for laboratory work with local authorization, method manuals and data sheets should be made ready available at the laboratory. The local Radiation Safety Guidelines is reviewed in connection to the annual radiation protection audit.

Appendices to the local Radiation safety handbook. Templates for these documents are available at the website1

Document Notes Radiation Safety Guidelines at Region Östergötland and Linköping University

Copy of the Local Authorization Given by the RP section Local Authorization p.4 Print copy of the Radiation Safety Guidelines at Region Östergötland and Linköping University

Available as pdf at the Radiation Safety Handbook website2

Local information on radionuclides E.g. data sheets from the manufacturer

Register of current possession Where applicable, withdrawal from stock solutions

Activity register p. 25

Storage routines Location of signed storage cabinets Storage p. 25 Local method documentation Register of educated personnel (name, course, date, refresh date) p. 7 Local courses, method competence Contamination measurements Where applicable, routines, log p. 23 Internal dose measurements Where applicable, routines, log p. 17 Instrument checks Where applicable, routines, log, report p. 18 Local purchase routines Where applicable p. 25 Local transport routines Where applicable p. 26 Local waste management Where applicable p. 31ff Local cleaning routines Where applicable p. 27 Local instructions for protective gear Where applicable p. 22 Categorization of staff and premises Decision from prefect/head of dept. p. 6 External dose measurements Where applicable s. 15 Data sheets for radionuclides Radiation protection audit Protocol from the last audit p. 8 Contact information Local Radiation protection organization p. 3 Waste management plan Local p. 31

1 www.liu.se/insidan/miljo/laboratoriesakerhetshandboken/stralskydd 2 www.liu.se/insidan/miljo/laboratoriesakerhetshandboken/stralskydd/blanketter

http://www.liu.se/insidan/miljo/laboratoriesakerhetshandboken/stralskydd

http://www.liu.se/insidan/miljo/laboratoriesakerhetshandboken/stralskydd/blanketter

at Region Östergötland and Linköping University

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