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RP SURVEILLANCE AND CONTROL PROGRAMME FOR THE MANAGEMENT

OF DSRS AT THE CENTRALISED WASTE MANAGEMENT FACILITIES AT

CNESTEN IN MOROCCO

NLM-SUR-00082 Date: 2014-09-05

Nuclear Liabilities Management Necsa P.O. Box 582 Pretoria, 0001

South Africa

Prepared by: R Swart

Document No. NLM-SUR-00082

Rev. No. 00

Department/Section: CNESTEN

Title: RP SURVEILLANCE AND CONTROL PROGRAMME FOR THE MANAGEMENT OF DSRS AT THE CENTRALISED WASTE MANAGEMENT FACILITIES AT CNESTEN IN MOROCCO

Authorization

NAME SIGNED DATE

PREPARED R SWART

ACCEPTED L HORDIJK

APPROVED GR LIEBENBERG

Distribution list:

NO. NAME NO. NAME NO. NAME

1 IAEA 29

2 30

3 31

4 32

5 33

6 34

7 35

8 36

9 37

10 38

11 39

12 40

13 41

14 42

This document is the property of NECSA and shall not be used, reproduced, transmitted or disclosed without prior written permission.

Doc. No.: NLM-SUR-00082

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RP SURVEILLANCE AND CONTROL PROGRAMME FOR THE MANAGEMENT OF DSRS AT THE CENTRALISED WASTE MANAGEMENT FACILITIES AT CNESTEN IN MOROCCO

Revisions This document has been revised according to the following schedule:

Revision Date Approved Nature of Revision Prepared by

00 See title page First Issue R Swart



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Contents: No. Description Page

1.0 PURPOSE 6

2.0 SCOPE 6

3.0 DEFINITIONS AND ABBREVIATIONS 6

3.1 DEFINITIONS: 6

3.2 ABBREVIATIONS: 6

4.0 REFERENCES 7

5.0 GENERAL RESPONSIBILITIES 7

6.0 RPO DUTIES 7

7.0 SOURCE TERM/ INVENTORY DURING NORMAL OPERATIONS 8

8.0 RADIOLOGICAL SURVEILLANCE 14

8.1 RADIOLOGICAL AREA CLASSIFICATION 14

8.2 DEMARCATION AND SIGNPOSTING 14

8.3 ACCESS / EGRESS 14

8.4 WORKPLACE SURVEILLANCE 15

9.0 SOURCE ACCEPTANCE RADIOLOGICAL SURVEILLANCE 17

9.1 PERSONAL PROTECTIVE EQUIPMENT (PPE) 17

9.2 RECEIVING OF SOURCES FROM USER FACILITIES 18

9.3 OFF LOADING 19

9.4 DETAIL CHECKING AND ASSESSMENT 19

9.5 REGISTRATION OF SOURCE CONTAINERS/UNITS ON THE STS 19

9.6 POSITIONING OF SOURCE CONTAINERS/UNITS INSIDE THE SOURCE STORE 20

9.7 SMOKE DETECTORS CONTROL 20

9.8 CONFISCATED/ORPHAN SOURCES 20

9.9 IMMOBILIZED OR CONDITIONED SOURCES 21

10.0 PERSONNEL MONITORING 21

10.1 RADIATION DOSIMETRY 22

10.2 ALARA REQUIREMENTS 22

11.0 INSTRUMENTATION 22

12.0 REMOVAL OF MATERIAL AND EQUIPMENT 23

13.0 TRANSPORT OF DISUSED SEALED RADIOACTIVE SOURCES 23

14.0 WASTE MANAGEMENT 23

14.1 SOLID AND COMPRESSIBLE WASTE 24

14.2 LIQUID WASTE 24



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15.0 RECORDS 24

List of Tables

Table 1: Abbreviations ..................................................................................................................................... 6 Table 2: References .......................................................................................................................................... 7 Table 3: Basic Nuclides .................................................................................................................................... 9 Table 4: Area Classifications ......................................................................................................................... 14 Table 5: Workplace Surveillance .................................................................................................................. 15 Table 6: Actions in the Event of Exceedance ............................................................................................. 16 Table 7: Action Levels for Exceedance of Routine Dose Rate Measurements ...................................... 16 Table 8: Area Monitoring Programme.......................................................................................................... 17 Table 9: Personnel Monitoring Requirements ............................................................................................ 21 Table 10: TLD and Neutron film badge limits for 8 week wearing periods ........................................... 22 Table 11: Instrumentation ............................................................................................................................. 23 Table 12: CNESTEN Records ......................................................................................................................... 24



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1.0 PURPOSE

The purpose of this section is to describe Radiological Protection surveillance and control measures for the National Centre of Nuclear Energy, Science and Techniques (CNESTEN) DSRS Centralised Waste Treatment and Storage Facilities situated at the Nuclear Studies Centre of Maamora near Rabat in Morocco. The programme is compiled taking cognizance of the safety case for the management of DSRS in Morocco [1].

2.0 SCOPE

This section covers specific RP surveillance and control measures that apply to the Central Waste Treatment and Storage Facilities for the management of DSRS. The scope of this RP programme does not address the surveillance and control requirements for the treatment activities of other waste streams although most of the requirements of this programme will also satisfy some of the RP surveillance and control requirements for other waste management activities in the Waste Treatment Facility.

3.0 DEFINITIONS AND ABBREVIATIONS

3.1 DEFINITIONS:

Occupationally Exposed Workers (OEW):

Workers who are or may be occupationally exposed to hazards encountered in a hazardous area e.g. Radiation workers

Sealed Radioactive Source:

Radioactive material that is (a) permanently sealed in a capsule or (b) closely bounded and in a solid form. The capsule or material of a sealed source shall be strong enough to maintain leak tightness under conditions of use and wear for which the source was designed.

3.2 ABBREVIATIONS:

Table 1: Abbreviations ALARA As Low As Reasonably Achievable

CENM Nuclear Studies Centre of Maamora

CNESTEN National Centre of Nuclear Energy, Science and Techniques

CNRP National Centre of Radiation Protection

EPD Electronic Personal Dosimeter

FS Facility Supervisor

NCR Non Conformance Report

OEP Occupationally Exposed Personnel



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PPC Personal Protective Clothing

PPE Personal Protective Equipment

RP Radiation Protection

RPE Respiratory Protective Equipment

RPO Radiation Protection Officer

STS Source Tracking System

TLD Thermo Luminescent Dosimeter

4.0 REFERENCES

Table 2: References

[1] NLM-REP-14/191 Draft Safety Case for the Management of DSRS in

Morocco.

[2] GSR Part 3 IAEA, Radiation Protection and Safety of Radiation

Sources: International Basic Safety Standards - 2014

[3] SSR-6 IAEA. Regulations for the Safe Transport of Radioactive Material; Specific Safety Requirements No. SSR-6; 2012 Edition

5.0 GENERAL RESPONSIBILITIES

The Facility Supervisor and the RPO are responsible for the following:

- The implementation of this document - Ensuring that personnel or any other person who visits the Waste Treatment and Storage

Facilities, adhere to any and all requirements as prescribed in this document.

6.0 RPO DUTIES

- Perform specific induction prior to entry to the respective facilities - Implementation of this programme. - Registering OEPs. - Arrange training for OEPs. - Train OEPs on RP requirements. - Complete access control registers. - Evaluate dose history of person’s accessing the area - Monitor persons on exit. - Check portable contamination and radiation monitors used at regular intervals. - Train special persons on the use of RPE if required. - Issue visitors with letter indicating their dose due to visit to the facility.



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- Assess worker dose. - Perform routine workplace monitoring. - Make arrangements for personnel monitoring. - Invigilate radiological tasks. - Evaluate data and results, and reporting it in monthly and quarterly RP reports. - Monitor, for clearance or transfer, material and equipment taken out from the facility. - Communicate non-conformances with the Facility Supervisor. - Inspection of signage for correct position and fading or legibility. - Participate in event and NCR investigations. - Source acceptance radiological surveillance - Source conditioning radiological surveillance - Source storage radiological surveillance - Supervise Ad-hoc radiological tasks

7.0 SOURCE TERM/ INVENTORY DURING NORMAL OPERATIONS

All sources received will be registered in accordance with a suitable Source Tracking System. The Source Tracking System should provide details about the source’s nuclide characteristics, manufacture, radiation hazard categories, source form and security categories etc. Disused High Activity Sources will be received, but the sources must be in its safe closed position inside their original working shields in accordance with the facility Waste Acceptance Criteria. The ambient and contact dose rate should be within the radiological classification limits. The following table presents an extract from the IAEA Decommissioning of small medical, industrial and research facilities (Technical Reports series No 414), for basic nuclides that are commonly used in industry and which may be accepted by CNESTEN.



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Table 3: Basic Nuclides



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8.0 RADIOLOGICAL SURVEILLANCE

8.1 RADIOLOGICAL AREA CLASSIFICATION

The waste treatment and storage facilities are classified in accordance with Requirement 24 of [2]. The radiological area classifications for normal operations are set out as follows:

Table 4: Area Classifications

RADIOLOGICAL AREA CLASSIFICATION*

CONTAMINATION RADIATION

AREA Uncontrolled Supervised Controlled Uncontrolled Supervised Controlled

DSRS Treatment Facility (Operational areas)

X X

Storage Facility

X X

Conditioning Area in Treatment Facility (Temporary Classified Area)

X X

* The radiological area classification status shall be revised, should routine surveys show a change in

conditions.

8.2 DEMARCATION AND SIGNPOSTING

The respective classified area’s as mentioned in Table 4 above, except for the temporary classified area which is part of the DSRS Treatment Facility, is delineated by means of walls and doors. The DSRS Storage Facility is a separate building. A temporary classified area will be demarcated by means of a barrier that will be put in place for the duration of the temporary classification. a) All entrances leading to the classified areas, including temporary classified areas shall be

signposted at the barrier or entrance. b) At the exits from the area leading to an uncontrolled area, a sign indicating that personnel are

entering an uncontrolled area shall be displayed.

8.3 ACCESS / EGRESS

a) Only authorized radiation workers familiar with operational activities and the radiological

control measures for the Waste Treatment Facility and Storage Facility has unrestricted access to the facility.

b) Visitors shall be approved by the Facility Supervisor and must be accompanied by the RPO.



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c) All doors leading to the classified areas shall be locked at all times and are opened only under control of the waste treatment facility or waste storage facility personnel for access of services. The vehicle entrance leading into the waste treatment facility and the waste storage facility can only remain open when under constant supervision the facility personnel or the security officer.

d) Visitor’s access is subject to the approval by the Facility Supervisor. e) Keys of all lockable doors and gates of the facility are under direct control of the Facility

Supervisor or any person as delegated by him.

8.4 WORKPLACE SURVEILLANCE

Workplace monitoring will be performed in the central waste treatment facility and the waste storage facility as required also in Requirement 24 of [2].

8.4.1 Routine Workplace Surveillance Schedule

Table 5: Workplace Surveillance

SURVEILLANCE (Routine)

FREQUENCY AMOUNT POSITION

SURFACE CONTAMINATION

(SWIPES)

Monthly 3 In Storage Facility Monthly 5 Treatment Facility Monthly 3 Change House

NEUTRON MEASUREMENT Monthly 2 Storage Facility

NEUTRON MEASUREMENT Monthly 2 Treatment Facility

DOSE RATES: GAMMA RADIATION

Monthly 2 Storage room Monthly 4 Treatment Facility

Six-monthly 3 Offices ground floor Six-monthly 4 Offices and laboratories first floor Six-monthly 4 Outside on walls of Storage Facility

8.4.2 Surface Contamination Monitoring

a) Routine swipe samples are being taken on fixed positions in the respective areas. b) Swipes will be counted for alpha and beta/gamma contamination. c) Whenever it is suspected that removable contamination may be present, swipe sampling

shall be used to verify the presence of contamination. d) Ad hoc swipes shall be taken during non-routine operations, whenever there is an incident

or when it is considered necessary by the RPO for investigation purposes. e) The routine intervention levels for smearable surface contamination are set as the upper

bound of the radiological classification criteria for the area. The criteria and actions in case of exceedance are indicated in Table 6 below.



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Table 6: Actions in the Event of Exceedance

Actions in event of exceedance

Area Contamination Limits (Bq/cm2)

Exceedance per surveillance-zone average less than

Exceedance per surveillance-zone average in excess of intervention

Recurring events

Uncontrolled Supervised Controlled

Alpha Beta Clean up and re-survey

1. Temporary re-classification of area 2. Investigation and root cause analysis.

1. Investigation and root cause analysis 2. Permanently change area classification and controls

0.04 0.4 4.0

0.4 4.0 40

8.4.3 Routine Radiation Surveys

a) Routine radiation surveys will be performed on fixed positions in the respective classified

and non-classified areas. b) Radiation surveys shall be conducted using a calibrated dose rate meter. c) Neutron measurements (if neutron DSRS are present) will be conducted using a neutron

monitor. The intervention levels for routine radiation surveys are set as upper bound of the radiological criteria for the area.

d) Ad hoc radiation surveys shall be conducted during non- routine operations or considered necessary by the RPO during an incident or intervention.

e) The criteria and actions in the case of exceedance are indicated in Table 7 below. The criteria are based on 2000 hours per annum work year.

Table 7: Action Levels for Exceedance of Routine Dose Rate Measurements

Actions in event of exceedance

Intervention Levels Exceedance per surveillance-zone average less than

Exceedance per surveillance-zone average in excess of intervention

Recurring events

Uncontrolled Supervised Controlled

< 0.5 µSv/h 0.5 – 2.5 µSv/h 2.5µSv/h to 10

µSv/h

Remove source of radiation

1. Shield source 2. Temporary re-classification of area 3. Investigation and root cause analysis.

1. Investigation and root cause analysis 2. Permanently change area classification



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8.4.4 Continuous External Radiation Monitoring

The following continuous monitoring programme will be followed for areas except the Storage Facility. Table 8: Area Monitoring Programme Monitoring Position Type of Monitoring Number Monitoring Period

Treatment facility TLD 3 2 monthly Offices ground floor TLD 2 2 monthly

Offices and laboratories first floor

TLD 2 2 monthly

Outside Storage Facility (fixed points at 2 m height

around facility)

TLD 4 2 monthly

8.4.5 Environmental Monitoring

Although no environmental exposures are expected during the normal operational activities inside the Waste Treatment Facility and Waste Storage Facility, some confirmatory environmental monitoring will be performed. The following routine and ad-hoc monitoring will be performed: TLDs will be placed on the security fence around the Waste Storage Facility as described in

Table 8 above. The liquids that are collected in the effluent tanks will be sampled and analysed in a

laboratory before the release thereof into the environment. The analysis should be performed for the typical nuclides handled and present in the facility. It is once again noted here that not only DSRS will be handled in the Waste Treatment Facility. The release criteria for any effluent from this building therefore have to take into consideration also the other possible nuclides present and treated.

9.0 SOURCE ACCEPTANCE RADIOLOGICAL SURVEILLANCE

9.1 PERSONAL PROTECTIVE EQUIPMENT (PPE)

a) Before conducting any work on sources containers/ units, the RPO and the operators shall

ensure that the correct personal protective equipment and dosimetry (dosimetry is described in Section 10.1) is used. The PPE requirements will include the following:

- Safety shoes - Extremity TLD’s if needed - Neutron film badge if neutron sources are to be handled. - PVC gloves to take swipe samples - Leather gloves to handle source containers. - Overcoat



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b) Note: Additional protective clothing and equipment to be used such as Respiratory Protective Equipment etc. can be prescribed by the RPO depending on the task that has to be performed.

c) All PPE, PPC and RPE will be monitored for contamination after any activity involving open sources or leaking sources.

d) All protective equipment, damaged in a manner that decreases its protective ability, shall be discarded.

9.2 RECEIVING OF SOURCES FROM USER FACILITIES

The following activities will be undertaken upon receiving of any sources (from external or internal clients) before the sources are unloaded from the vehicle. - Source containers/ units shall be received at the receiving bay at the large door that

provides access to the Waste Storage Facility. - The source containers/units will remain on the transport vehicle until all confirmatory checks

have been completed. - The provided documentation is evaluated to ensure that all applicable information has been

provided. - Before handling the unit the RPO shall perform a contamination survey on the vehicle. - The RPO shall take contact dose rate measurements and a swipe sample on the outside

container of the source to check for possible removable contamination. - If the contact dose rate is above the prescribed limit, the source will be placed inside a shielded

container or shielded to conform to the requirements of Controlled Area Radiation Criteria, and stored accordingly.

- If the radiation measurements conform to the specified criteria a swipe will be taken on the source/holder to cover as large an area as possible (500 cm2 if possible). The swipe will be measured by means of a portable contamination monitor. Sources will only be accepted for storage if no removable contamination is indicated (Measurement on swipe taken to be done in a low background area).

- In the event that removable contamination is found to be present on the source container, the container is to be sealed in plastic/or drummed and taken to the decontamination bay for decontamination purposes. The prescribed removable contamination limits on the outside of the container are 0.04 Bq/cm2 (alpha) and 0.4 Bq/cm2 (beta/gamma).

- Remove the source from the vehicle and check the vehicle for any loose contamination. - All these measurements shall be recorded on surveillance forms and kept as records. - Any non-compliance shall be reported immediately to the facility manager and handled in

accordance with the CNESTEN Quality Assurance system. - Confirm that the unit number or description complies with the identification provided on the

documentation. - If no information on the type of source is available, perform a characterization of the source

using a gamma spectrometer. It is in any event good practice to verify the isotope for every source that is received as a final verification of the documentation.



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9.3 OFF LOADING

a) Only after the RPO confirmed that the source units are acceptable, these could be handled

and offloaded. b) If the source containers/units are not heavy, place them on a trolley. If the source

containers/units are heavy, use a forklift/jack trolley to move them to the reception area of the source store to be registered on the STS.

c) The facility personnel will sign a source acceptance form at this stage and will either hand it over to the driver or will forward it to the previous source owner. A copy will be kept as part of the information documentation of the source.

9.4 DETAIL CHECKING AND ASSESSMENT

a) Confirm that the serial numbers on the source containers/ units correspond with the numbers

on the paper work. Record the source container/ unit on a logbook. b) Conduct detail assessment and inspection on the source container/unit to ensure that there are

no leaks etc. and record this on the logbook. c) Weigh the source containers/units on the scale and record the weight on the logbook. The

weight is important in order to ensure that it can be stored on the shelves provided for storage. d) If the source container/unit is without a serial number, they must be uniquely identified by a

sticker with the following information:

- Unique number (to be allocated by CNESTEN) - Nuclide - Origin - Activity (present day) - Dose Rate on contact - Date of Receipt - Weight

9.5 REGISTRATION OF SOURCE CONTAINERS/UNITS ON THE STS

a) Register the source containers/units on the STS in with the following information:

- Source container unit identification number - Unit weight - Container type - Source location in storage room - Contact dose rate - Contamination levels

b) After registering the sources/unit, the data pack for each source/unit/quote shall be kept as

QA records.



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9.6 POSITIONING OF SOURCE CONTAINERS/UNITS INSIDE THE SOURCE STORE

a) Use the STS to determine the source position in the source store and generate a source

transfer permit. b) Move the containers/units to the racks or identified demarcated floor spaces/areas as

defined on the transfer permit. A sign which indicates the maximum weight that the racks can carry will be placed conspicuously on the racks.

c) Confirm on the STS that the source was moved to the defined position

9.7 SMOKE DETECTORS CONTROL

a) Decommissioned smoke detectors shall be controlled separately and not registered on the

STS. b) A register shall be kept of all the smoke detectors received, indicating:

- Source no (if available) - Last user - Date received - Activity - Status (whole unit/stripped)

c) Complete smoke detectors shall be accumulated in a drum. d) Stripped sources shall be kept in another separate container. e) Sources shall be removed from the units on a campaigned basis, thus where all the units

received to date are opened and the actual source removed from the unit. This activity shall be done in accordance with a radiological work permit.

9.8 CONFISCATED/ORPHAN SOURCES

The following special conditions will apply for source containers/units which were confiscated or orphan sources which were recovered: - These sources will be brought to the CNESTEN Waste Management Facility with no

information although a submittal form from the regulator should accompany the source. - Register the DSRS and mark as described as in Section 9.5a) above. - The regulator (The National Centre of Nuclear Energy, Science and Techniques CNRP)

should indicate whether the source can be regarded for eventual conditioning/disposal, or keeping it in storage area until a decision has been made on the future of the source.

- These sources/units indicated as to be stored will be kept in the separate storage area inside the Storage Facility.

- A separate list of these sources shall be kept. - Once every two years a list of these sources/units shall be sent to the regulator (CNRP)

requesting them to indicate if any of these could be reclassified for conditioning and disposal.

- Should CNRP decide that there are sources that could be reclassified for conditioning/disposal; they will send a reply indicating the sources that can be conditioned.



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- These reclassified sources must then be handled and registered on the STS the same way as any other source being received in the store.

9.9 IMMOBILIZED OR CONDITIONED SOURCES

In some instances sources that have already been immobilized in concrete or have been conditioned in lead or concrete shields will be brought to the CNESTEN Waste Storage facility. In such instances the following process will be followed before source acceptance. - Waste packages (drums, shields etc.) shall be received at the large door that provides access

to the Storage Facility. - The waste packages will remain on the transport vehicle until all confirmatory checks have

been completed. - The provided documentation is evaluated to ensure that all applicable information has been

provided. This information must include data on all the sources in the packages that have been conditioned and/or immobilized and brought in for storage.

- Before handling the waste package the RPO shall perform a contamination survey on the vehicle.

- The RPO shall take contact dose rate measurements and a swipe sample on the outside container of the waste package to check for possible removable contamination.

- Only after the RPO confirmed that the waste packages are acceptable, these could be handled and offloaded.

- The waste package number will be registered on the STS and not each individual source in that waste package.

- The facility personnel will sign a source acceptance form at this stage and will either hand it over to the driver or will forward it to the previous source owner. A copy will be kept as part of the information documentation of the source.

10.0 PERSONNEL MONITORING

Personnel involved in the acceptance and handling of the source/s is classified and registered as radiation workers. The Personnel Monitoring Programme shall be implemented as prescribed in Table 9 below. Table 9: Personnel Monitoring Requirements

Type Frequency

Medical

Prior to commencement of employment Yearly examination

At termination of employment TLD’s (personnel) e.g. Two-monthly wearing period

Electronic Pocket Dosimeters (EPDs) To be worn during all DSRS related activities Neutron Film Badge e.g. Two-monthly wearing period

Radiation Worker Training Every two years



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10.1 RADIATION DOSIMETRY

a) All personnel working in radiation areas shall be issued with a TLD and Neutron Film Batch. b) Personnel working in the source store are issued with an extremity TLD (Extremity TLD’s) c) Persons working in the source store shall be issued with an EPD and their daily doses shall

be recorded by the RPO. d) Personnel dosimetry results shall be reported on, in the monthly radiation protection report. e) In the case of exceedance of the investigation dosimetry levels on the TLD’s, Neutron Film

Badge and Extremity TLD’s, it will be reported and investigated. f) The prescribed limits for TLD’s and Neutron Film Badges are described in Table 10 below.

Table 10: TLD and Neutron film badge limits for 8 week wearing periods

Type of dosimeter Wearing period Whole body Skin

TLD 8- weeks 2 mSv 20 mSv Neutron film badge 8- weeks 2 mSv 20 mSv Extremity TLD 8 weeks N/A 20 mSv

10.2 ALARA REQUIREMENTS

a) Although the Safety Assessment performed for the management of DSRS at the CNESTEN

Waste Management Facilities [1] indicated low levels of occupational exposure, an ALARA programme shall nonetheless be implemented in order to strive for a continuous reduction in exposures to workers at the CNESTEN Radioactive Waste Management Facilities.

b) For special or ad hoc tasks with the projected individual dose of more than 1 mSv or extremity skin dose of 10 mSv or a collective dose of more than 10 mSv, a formal ALARA review should be conducted.

c) For any ad-hoc radiological tasks or tasks where a procedure does not exist or procedures which do not prescribe radiological protection requirements the RPO will determine the RP requirements.

11.0 INSTRUMENTATION

The instruments and techniques used for radiological surveillance, operation procedures and routine test and calibration requirements are specified in the table below.



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Table 11: Instrumentation

Instruments Operation Procedure

Routine test and calibration requirements if/when the instrument is in use

Port

able

Co

ntam

inat

ion

mon

itor

To b

e dr

afte

d − Calibration validity (≤14 months) − Response checks – once daily before use − Background checks – once daily before use − Visual checks – once daily before use − Update record sheet per instrument

Port

able

ra

diat

ion

mon

itor

− Calibration validity (≤14 months) − Response checks – once daily before use − Visual checks – once daily before use − Update record sheet per instrument

12.0 REMOVAL OF MATERIAL AND EQUIPMENT

Any material or equipment used in the CNESTEN Waste Treatment or Storage Facility shall be monitored and cleared prior to removal from the facility. Contamination and radiation clearance and transfer levels will adhere to the criteria specified in [2]. The prescribed removable contamination limits on the outside of material /equipment are 0.04 Bq/cm2 (alpha) and 0.4 Bq/cm2 (beta/gamma)

13.0 TRANSPORT OF DISUSED SEALED RADIOACTIVE SOURCES

Transport if DSRS shall be done according with the IAEA Regulations for the Safe Transport of Radioactive Material [3].

14.0 WASTE MANAGEMENT

The CNESTEN Radioactive Waste Management Facilities do not only handle DSRS but also other waste streams generated from the research reactor on site as well as from other research and development programmes. The waste treated and secondary waste generated during the treatment processes at the Waste Treatment Facility can be solid waste, compressible waste, liquid waste and gaseous emissions.

This RP programme shall not address the waste treatment requirements for the other CNESTEN radioactive waste streams but rather only the potential secondary waste generated by the DSRS waste treatment activities.



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14.1 SOLID AND COMPRESSIBLE WASTE

a) Compressible waste is expected to be only waste such as potentially contaminated gloves,

overshoes and paper towels. b) Solid waste will be monitored for surface contamination c) If waste is within the clearance levels as stipulated in [2] the waste shall be unconditionally

cleared and disposed of as general waste. d) If waste is above the clearance levels, the waste shall be disposed of as radioactive waste in

radioactive waste containers in accordance with the relevant WAR. e) The waste shall be temporarily stored in the area in 160ℓ red drums.

14.2 LIQUID WASTE

a) No liquid waste, except for floor wash water, is expected to be generated during normal

DSRS management activities at CNESTEN. b) Should there be a need to decontaminate the area all liquid waste generated will be

disposed of in the effluent management system. c) No liquid waste will be released to the environment without having been sampled and

analysed to ensure that the liquid effluent conforms to release criteria.

15.0 RECORDS

The following records shall be kept.

Table 12: CNESTEN Records

TITLE RETENTION

PERIOD ARCHIVE PERIOD

BY WHOM

Access control register

Completed forms to be submitted to CNESTEN QA

monthly

50 Years, after the closure of the facility CNESTEN QA

Visitor Dose Records Completed forms to be

submitted to CNESTEN QA monthly

50 Years, after the closure of the facility CNESTEN QA

Monthly, Quarterly and Annual reports 3 years Lifetime of facility RPO

Quarterly inspection of waste containers

Lifetime of facility Summary of data as part of conceptual decommissioning

strategy 30 Years

CNESTEN QA

Radiation survey data record sheet

4 years Summary of data as part of conceptual decommissioning

strategy 30 Years

CNESTEN QA

Contamination survey data record sheet

4 years Summary of data as part of conceptual decommissioning

strategy 30 Years

CNESTEN QA



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TITLE RETENTION

PERIOD ARCHIVE PERIOD

BY WHOM

Smears sampling survey results

3 years Lifetime of facility CNESTEN QA

Copy of transfer cards 3 years Lifetime of facility CNESTEN QA Radiation monitor daily checklist 3 years Lifetime of facility CNESTEN QA Contamination monitor daily checklist 3 years Lifetime of facility RPO

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