mo99 facl oper tn 0329 b: dose assessment - … · mo99_facl_oper_tn_0329_b: dose assessment ......

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Mo99_FACL_OPER_TN_0329_B: Dose Assessment

Revision: B Effective Date: 25/05/2016

Approved by: ANM Program Director Custodian: ANM Project Quality Co-ordinator

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ANM MO99 PROJECT

Mo99_FACL_OPER_TN_0329_B: Dose Assessment

May 2016

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Mo99_FACL_OPER_TN_0329_B: Dose Assessment Page 1 of 27


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Revision Details Print name, date and initial each box

Rev. Letter

Description of Revision Prepared Reviewed Approved Agreed

A Initial Issue

B Updated to address SAC comments

Notes: 1. Revision shall be verified in accordance with the Quality Plan for the project.

2. Revision to be agreed by the relevant Client.

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Table of Contents

1. Purpose .................................................................................................................................................... 3 2. Scope ....................................................................................................................................................... 3 3. Method ..................................................................................................................................................... 3

3.1. Task Identification .............................................................................................................................. 3 3.2. Dose Rates ........................................................................................................................................ 3 3.3. Individual and Collective Doses ......................................................................................................... 4

4. Results ..................................................................................................................................................... 5 5. Conclusion............................................................................................................................................... 6 6. Definitions................................................................................................................................................ 6 7. Records .................................................................................................................................................... 7 8. References ............................................................................................................................................... 7 Appendix A: Operations Staff Annual Dose Assessment ..................................................................... 8 Appendix B: Maintenance Annual Dose Assessment .......................................................................... 10 Appendix C: Health Physics Annual Dose Assessment ...................................................................... 15 Appendix D: Dispatch and Packaging Annual Dose Assessment ...................................................... 20 Appendix E: Waste Operations Annual Dose Assessment ................................................................. 21 Appendix F: Contractors Annual Dose Assessment ........................................................................... 22 Appendix G: Drivers Annual Dose Assessment ................................................................................... 24 Appendix H: QC Annual Dose Assessment .......................................................................................... 25 Appendix I: ANM Mo99 Ground Floor ...................................................................................................... 26 Appendix J: ANM Mo99 Basement ........................................................................................................ 27

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1. Purpose The purpose of this document is to report the results of the radiation dose assessment for workers at the ANM Mo99 facility. This radiation dose assessment is based on the detailed design of the facility. This dose assessment will be reviewed and updated accordingly during the construction, cold commissioning and hot commissioning as the operating and maintenance strategies are further refined for the ANM Mo99 facility.

2. Scope The scope of the radiation dose assessment presented in this document is for Operations workers performing routine operations, Maintenance workers performing routine maintenance and anticipated breakdown maintenance; Health Physics (HP) support workers; Quality Control (QC) workers, Dispatch and Packaging workers, Drivers, Waste Operations workers and Contractors.

This document describes the process followed and assumptions made in calculating the radiation doses for each of the worker groups listed above.

This document does not include dose assessments for long term maintenance activities. Long term maintenance activities will be subject to separate safety assessments with submissions to the Safety Assessment Committee (SAC) for approval, prior to the work being performed.

3. Method The Dose Assessment was made according to the following steps.

1. Identification of all tasks performed for routine operations and worker numbers.

2. Calculation of dose rates workers are exposed to during tasks for routine operations.

3. Estimate of times taken to perform tasks.

4. Calculation of doses to workers performing tasks during routine operations.

3.1. Task Identification

A working group was formed consisting of members from Radiation Protection Services (RPS), Systems Safety and Reliability (SS&R), current B54 Mo-99 operations and representatives from the ANM Mo-99 project team and the ANM Mo99 client.

Initial meetings were held between 20th and 29

th of January 2014 with members from the working

group which identified and recorded the following information.

Task performed,

Group performing the task,

Location where the task is performed,

Frequency of the task,

Number of people required to perform the task,

The time estimated to perform the task and

The number of staff proposed for each work group.

Further meetings were held on 29th May and 17

th July 2015, further refining the above, using

completed detailed design information.

3.2. Dose Rates

Wherever possible, modelling was performed to obtain results which actually reflect the geometry of the exposure situation, taking into account contributions from all significant source terms. This has resulted in dose rates being calculated for anticipated worker positions while performing tasks which are more likely to be encountered during the operation of the ANM Mo99 facility.

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Where dose rate modelling is not available, a conservative approach was taken for dose rates used for this dose assessment and are based on the following criteria:

Shielding design objective and contact dose rates, and,

Conservative general area dose rates based on operational experience from similar activities at ANSTO.

The doses calculated for these tasks are considered to be bounding.

Separate dose assessments had previously been performed for a number of tasks and work groups from the current Mo-99 operations. These tasks are the loading of the B(U) container and QC operations. The doses calculated from these assessments have been used in place of a dose rate and time calculation.

The dose assessment for the drivers is only the dose attributable to loading and delivering Mo99 manufactured at the ANM Mo99 facility. It assumes that all Mo99 produced is for export and is also considered conservative. This dose does not include exposures from the transport of other radiopharmaceuticals.

3.3. Individual and Collective Doses

The method used to estimate the average individual and collective dose to workers was as follows.

Each workgroup was considered separately.

For each work group, the annual dose per task was calculated by multiplying the dose rate, time taken, number of people required and the annual frequency together.

For each workgroup, the annual collective dose was calculated by summing the annual task doses.

For each work group, the average individual dose was calculated by dividing the annual collective dose for the work group by the proposed number of workers within that work group.

Note that there is no average individual dose calculation for the contractor group, as there are a range of different contractors, and the number of individuals from each firm cannot be established at this time. A collective dose for contractors has been included instead.

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4. Results A summary of the annual dose assessment results is displayed in Table 1.

Table 1

Routine Maintenance 2268 756

Breakdown Maintenance 1157 386

TOTAL 3425 1142

Routine Operations 393 197

Routine Maintenance 1015 508

Breakdown Maintenance 159 79

TOTAL 1567 783

Routine Operations 34

Routine Maintenance 738.05

Breakdown Maintenance 1.2

TOTAL 773.25

**The annual collective dose for the drivers is the exposure due to ANM operations only.

It assumes that all Mo99 is export product, is transported by ANSTO, and does not take into account the

delivery of other radiopharmaceuticals manufactured by ANSTO.

Average Individual

Annual Dose (µSv)Task Sub-Type

23Routine Operations 19225 836

Contractors

Worker Group

Maintenance

Annual Collective

Dose (person µSv)

Number of

Workers in Group

3

Dispatch and

Packaging

Waste Operations

4

2Routine Operations



Operations

Health Physics

Quality Control

1721

1452

2

12

726

**Drivers Routine Operations 3156 4 789

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5. Conclusion The results of this dose assessment is intended as a guide for the potential exposures workers are expected to receive for the routine operations of the ANM Mo-99 facility. This dose assessment is considered to be the upper bounding case for exposures workers could receive.

Actual doses to workers are expected to be lower during routine operations as some conservative assumptions have been made for these calculations. Some of these conservative assumptions are:

Conservative general area dose rates based on operational experience from similar activities at ANSTO,

Shielding design objective and contact dose rates used for some exposure calculations,

Times taken to perform tasks,

The doses to the Operations, Maintenance, Dispatch and Packaging, Health Physics, Waste Operations and QC worker groups indicate that expected average individual doses are below ANSTO’s ALARA objective of 2mSv/yr. Any further dose reductions are not considered justified from an economic perspective. Further dose reductions over the life of the plant would not be achievable through the justifiable monetary amount determined through cost-benefit analysis in the ALARA process.

The dose assessment for the drivers is only the dose attributable to loading and delivering Mo99 manufactured at the ANM Mo99 facility. It assumes that all Mo99 produced is for export and this result is also considered conservative and bounding. This dose does not include exposures from the transport of other radiopharmaceuticals.

For the 2009 to 2014 period, the maximum individual dose ranged between 3.44mSv and 5.01mSv for ANSTO Health Drivers. The average individual dose for this same period ranged between 2.68mSv and 3.46mSv. These dose results are due to the loading and delivery of all ANSTO Health produced radiopharmaceuticals. It is anticipated that the driver doses could potentially increase by an average of 0.79mSv/yr during ANM Mo99 operations, should the same number of delivery drivers be used. The ANM project is committed to further investigate increasing the amount of shielding currently installed in the delivery vans, to further reduce exposures to drivers. This will be confirmed by the Operational Readiness team prior to operation.

All anticipated exposures at the ANM Mo99 facility are well below ANSTO’s annual dose constraint of 15mSv/yr and the annual regulatory limit of 20mSv/yr.

The dose assessment described in this document will be reviewed and updated accordingly during the construction, cold commissioning and hot commissioning as the operating and maintenance strategies are further refined for the ANM Mo99 facility.

6. Definitions

Term Definition

ANM ANSTO Nuclear Medicine

Mo-99 Molybdenum 99

SAC Safety Assessment Committee

QC Quality Control

RPS Radiation Protection Services

HP Health Physics

SUF Spent Uranium Filter

B(U) Type ‘B’ Transport Package

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7. Records A paper copy is kept on: File number: ADM100421

Electronic records are kept in:

P:\eng_capex_projects\Molybdenum 3000 Facility\04 Regulatory\ARPANSA Submissions\05 Regulation 54s\Dose Assessment\2015 revision\

N:\Divisions\safety\projects\op0036\RP Project Support\ANM Mo99\

8. References Alam, M. Mills, B. 2015. ANM Mo99 Source Terms and Geometry of Sources for the Shielding

Basis of Hot Cells, Waste System and Facility Design - Mo99_FACL_CELL_TN_0154G. : ANSTO, 2015.

Jones, W. Barton, R. 2014. Safety Review of the Basement Shielding in the ANM Mo99 Facility – ANSTO/T/TN/2013-22 rev 1. : ANSTO, 2014.

Penny, C. 2014. Safety Review of the Concrete Hot Cell Shielding in the ANM Mo99 Facility – ANSTO/T/TN/2013-27 rev 1. : ANSTO, 2014.

Jones, W. Penny, C. 2014. Safety Review of the Lead Hot Cell Shielding in the ANM Mo99 Facility – ANSTO/T/TN/2013-26 rev 1. : ANSTO, 2014.

Penny, C. 2015. Safety Review of the ANM Mo99 Facility Liquid Waste System Shielding– ANSTO/T/TN/2013-23 rev 1. : ANSTO, 2015.

Jones, W. Penny, C. 2014. Safety Review of the Ground Floor Shielding in the ANM Mo99 Facility – ANSTO/T/TN/2014-17 rev 0. : ANSTO, 2014.

Jones, W. Penny, C. 2015. Safety Review of Flasks, Doors and other Shielding in the ANM Mo99 Facility – ANSTO/T/TN/2015-06 rev 0. : ANSTO, 2015.

WATPAC Construction. AECOM. Graham Bell Bowman Architects. ANSTO ANM Mo99 - Floor Plan – Basement Level – MO99_FACL_ARCH_ED_2310 rev F. : ANSTO, 2014.

WATPAC Construction. AECOM. Graham Bell Bowman Architects. ANSTO ANM Mo99 - Floor Plan – Ground Level – MO99_FACL_ARCH_ED_2311 rev G. : ANSTO, 2014.

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Appendix A: Operations Staff Annual Dose Assessment

Type Task Area Frequency (per year)

# workers for task

time required (hrs)

dose rate (µSv/hr)

dose rate comments

total dose per

year (µSv)

OPS Change over valve Pump room B007 1 1 0.5 4.4 4.4µSv/h @ 1m with

side wall of gas delay tanks

2.2

OPS Cell face operations

during production run

Cell Face 0024

Dissolver Cell Face 1 1 2162 1.85

1.85µSv/h @ 0.5m, cell face

manipulator operations

3999.7

Purification Cell Face

1 1 822.5 0.6



493.5

Evaporation Cell Face

1 1 470 0.1



47.0

Dispensing Cell Face

1 1 235 0.1



23.5

Packaging Cell Face

1 1 705 0.1



70.5

Room 0024 away from cell face

1 1 3290 0.25

Cell face operator not at cell face.

Position assumed at rear of room 0024 with average dose rate of 0.25µSv/h

822.5

OPS

All other cell face operations (such as

operator input during flask/movements)

Cell Face 0024 1 2 2162 0.25

other two operators, during a

batch run in dissolver

1081.0

OPS Remove and Replace

product dispenser equipment

Dispensing Hotcell

0.3 1 8 0.5 Ambient dose rate in the front of cell

1.2

0.3 2 0.5 3

Dose rate to the PADIRAC operator in the rear of cells, following decay of the equipment in

the waste cells

0.9

OPS General routine

operations at rear cell area

Rear of cells

1 2 132 3 Average dose rate 0.5m from rear of

cells - dissolver 792.0

1 2 264 0.5 Average dose rate 0.5m from rear of cells - other cells

264.0

1 2 1320 1 Average dose rate 2.0m from rear of

cells - dissolver 2640.0

1 2 6204 0.5 Average dose rate

at 2m rear of cells - other cells

6204.0

OPS SUF cup movements in

PADIRAC Rear of cells 75 2 0.1 8

8 µSv/h @ 1m on the side of the

PADIRAC 120.0

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OPS

Target flask movements (inc. tie

down and drive from OPAL)

Rear of cells 450 1 0.1 5 Contact dose rate

with flask 225.0

Rear of cells 450 1 0.5 0.5 Dose rate at 1m 112.5

OPS Transfer of retention

sample to storage cabinet

Rear of cells 48 2 0.25 1 Average dose rate 2.0m from rear of

cells 24.0

OPS Decontaminate hotcell

equipment Active

maintenance- 26 330 1 0.1 10

10µSv/h ambient dose rate during

decontamination of equipment

330.0

OPS Service and clean

hotcell process tanks Active

maintenance- 26 6 1 2 10

10µSv/h ambient dose rate at

operator 120.0

OPS Clean process flasks Active



operator 480.0

OPS Rebuild Evaporation

equipment Active



operator 40.0

OPS Rebuild Bursting Discs Active



operator 120.0

OPS Rebuild in-cell

peristaltic pumps Active



operator 120.0

OPS Service air-ejectors Active



operator 10.0

OPS Service dispensing

equipment Active

maintenance- 26 0.3 1 3 10


operator 9.0

OPS Service hot cell DPTE

doors Active

maintenance- 26 10 1 0.5 10


operator 50.0

OPS Rebuild Hydrogen

Converters Active



operator 70.0

OPS Service Vacuum

Pumps Active



operator 20.0

OPS Clean PADIRAC

containers Active

maintenance- 26 48 1 0.5 10


operator 240.0

OPS SS &EW testing Active

maintenance- 26 48 1 1 0.5

General ambient dose rate

24.0

OPS Sample Cell operations

Sample cell 0036 12 1 1 1.7 Contact dose rate from liquid waste

sample cell 20.4

OPS SyMo transfer Sample cell 0036 4 1 0.5 1.7 Contact dose rate from liquid waste

sample cell 3.4

OPS Feeding containers

thru to despatch Container

handling 0043 330 1 1 0.5

General ambient dose rate

165.0

OPS Placement of items Blue waste 0035 48 1 1 10 10µSv/h @ contact 480.0

Total Collective

Dose Ops 19225

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Appendix B: Maintenance Annual Dose Assessment


# workers for task

time required (hrs)

dose rate (µSv/hr)

dose rate comments

total dose per

year (uSv)

RM Radiation monitor

calibration (2 In-cell, 1 room)

Sample cell 0036 1 1 0.5 0.5 Dose rate @ 0.5m

from front of liquid waste sample cell

0.3

RM 10 pressure sensors

for calibration / change out

Sample cell 0036 1 1 5 0.5 Dose rate @ 0.5m


2.5

RM Vacuum pump maintenance



1.0

RM

Liquid level gauge system maintenance (demister, pressure sensors, silica trap)



1.0

RM Valve acutator

maintenance (46) Sample cell 0036 2 1 0.5 0.8

Dose rate @ 0.5m from top of liquid waste sample cell

0.8

RM Sample Cell

maintenance Sample cell 0036 1 1 1 0.5

Dose rate @ 0.5m from front of liquid waste sample cell

0.5

RM Pulsair system maintenance



0.5

RM Decayed part

movement (for decontamination)


cells 48.0

RM Ball valve

maintenance Rear of cells 0.3 1 0.5 3

Dose rate at 0.5m from dissolver hot

cell roof. 0.5

RM Service Padirac Door

and table system Rear of cells 96 1 0.5 3

Dose rate at 0.5m from rear of

dissolver hot cell. 144.0

RM Calibrate Instruments (sampling, DP's, dose

monitors) Rear of cells 1 1 8 1

Average dose rate 2.0m from rear of

cells 8.0

RM Change cell lighting Rear of cells 0.5 1 8 5 Dose rate at contact

with rear of dissolver hot cell.

20.0

RM Service Padirac Flasks

(e.g. door rollers) Rear of cells 12 1 1 1


cells 12.0

RM Floor access hatch Rear of cells 2 1 0.5 1 Average dose rate 2.0m from rear of

cells 1.0

RM Rad monitor

calibration in change areas

Changeroom (0010, 0020, 0037, 0042 &

0045)

1 1 2.5 0.5 General ambient

back ground 1.3

RM Calibrate instruments Cell exchange

M1015 1 1 16 2.5

Dose rate 1.0m from top of

dissolver hot cell 40.0

RM Service pumps (10) Cell exchange

M1015 2 1 2 2.5



RM Hot water baths Cell exchange

M1015 1 1 3 2.5



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RM

routine maintenance (roller door, DB, FH, radiation monitor

calibrations, instrument

calibrations)

Truck Airlock B001

1 2 8 0.5 Dose rate 1.0m

from carbon column wall

8.0

RM

Changing carbon filters (8- but only 4

changed each 5 years) and HEPA's (2, with

one changed)

Active Vent Filter Rooms- B004 &

B005 0.2 1 8 10.6

Dose rate 10.6µSv/h 2m from B004/B005

dividing wall 17.0

RM Testing of Hepa filters

(2)- smoke filter integrity etc


B005 0.5 2 4 10.6


dividing wall 42.4

RM Pressure Transmitters

changeover (for calibration)

Carbon column area- B006

3 2 0.5 2

Dose rate is sum of 0.5m DR from

Carbon Column Wall B006 (0.14µSv/h) and 2.5m DR from Gas Delay Tanks

B012 (1.86µSv/h) in the Access Corridor

B013.

6.0

RM Replace Vacuum Pump Pump room B007 4 1 1 4.4 4.4µSv/h @1m from B012 dividing wall

17.6

RM Replace Demister Pump room B007 2 1 0.5 4.4 4.4µSv/h @1m from B012 dividing wall

4.4

RM Replace Solenoid

Valve Pump room B007 2 2 0.5 4.4

4.4µSv/h @1m from B012 dividing wall

8.8

RM Replace flow switch Pump room B007 1 2 0.5 4.4 4.4µSv/h @1m from B012 dividing wall

4.4

RM

Calibrate Instruments (2 flow swithces, 3

level sensors, area rad monitor)

Pump room B007 1 2 8 4.4 4.4µSv/h @1m from B012 dividing wall

70.4

RM Radiation detector &

pump maintenance (2) Corridor B013 2 1 1 2




B013.

4.0

RM RH and Temp sensor

maintenance (3) Corridor B013 3 1 0.5 2




B013.

3.0

RM Calibration of

instruments (P & T sensors- 12)

Corridor B013 1 2 6 2




B013.

24.0

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RM Change Tank Outlet

Valve (168) Corridor B013 1 2 1 8.73




B013.

17.5

RM Change Tank Inlet

Valve (168) Corridor B013 1 2 1 8.73




B013.

17.5

RM Calibrating Pressure

Transmitter (84) Corridor B013 84 1 1 8.73




B013.

733.3

RM Change of SIAM filters

(2) Pump & Tank Room B015

0.2 2 2 50

50µSv/hr design objective used. This area is not normally

occupied and if work is to take place

in B015, ILLW and LLLW inventories

will be cleared and flushed repeatedly until a sufficiently low dose rate is

achieved.

40.0

RM

Calibrations (2 SIAM Rad Monitors, diff

pressure transmitter, temp transmitter, Area monitor, air

sampler)

Pump & Tank Room B015

1 1 8 50





achieved.

400.0

RM Calibrating Hydrogen

transmitter, Pump & Tank Room B015

2 1 2 50





achieved.

200.0

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RM Calibration- Holding

tank pressure indicator


1 1 4 50





achieved.

200.0

RM Change out the

check/pressure relief valve (15)


1 1 2.5 50





achieved.

125.0

RM Safety shower testing 52 1 0.5 1 <1µSv/h ambient

dose rate 26.0

2268

BM Maintenance of

motorised valves- 6


B005 0.2 2 4 10.6


dividing wall 17.0

BM Change solenoids

(336) Corridor B013 3 2 0.5 8.73




B013.

26.2

BM Change Pressure Transmitter (84)

Corridor B013 0.5 2 0.5 8.73




B013.

4.4

BM Change PT (Pressure

Transmitter) electronics

Corridor B013 3 1 2 8.73




B013.

52.4

BM Change

solenoids/actuators Pump & Tank Room B015

1 1 0.5 50





achieved.

25.0

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BM Replacement of

manips (MT200's)

Front of cells 12 2 1 10 At operator position 240.0

Front of cells 12 2 0.15 200 Near penetration 720.0

BM Replacement of other

manips Front of cells 12 2 1 3 3µSv/h @ contact 72.0

1157

Total Collective

Dose Maintenance 3425

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Appendix C: Health Physics Annual Dose Assessment


# workers for task

time required (hrs)

dose rate (µSv/hr)

dose rate comments

total dose per

year (uSv)

OPS / HP

Routine Surveys and clearances

Rear of cells 48 1 2 1 Average dose rate 2.0m from rear of

cells 96

OPS / HP


Front of cells 48 1 2 0.5 Average general

Ambient dose rate 48

OPS / HP


General facility 48 1 2 0.5 Average general


OPS / HP

Front of Cells general Front of cells 1 1 400 0.5 Average general


OPS / HP

Change over valve Pump Room B007 1 1 0.2 4.4 4.4µSv/h @1m from

B012 dividing wall 0.88

OPS / HP

Remove and Replace product dispenser

equip Dispensing Hotcell 0.3 1 1 0.5

0.5µSv/h @ contact with rear of cell

0.15

393

RM / HP

Sample Cell maintenance

Sample cell 0036 1 1 1 5

Dose rate 0.5m from valve

enclosure and valve handles

5

RM / HP

Crane maintenance (monthly)


cells 6

RM / HP

Ball valve maintenance

Rear of cells 0.3 1 0.25 3.5 Dose rate at 0.5m from dissolver hot

cell roof. 0.2625

RM / HP



one changed)


B005 0.2 1 4 10.6


dividing wall 8.48

RM / HP

Testing of Hepa filters (2)- smoke filter

integrity etc


B005 0.5 1 2 10.6


dividing wall 10.6

RM / HP

Doors- Chain block & pulley inspection

Outside B004 & B005

1 1 0.5 39 38.96µSv/h @ contact with wall/door.

19.5

RM / HP

Pressure Transmitters changeover (for

calibration)


3 1 0.25 2


Carbon Column Wall B006

(0.14µSv/h) and 2.5m DR from Gas Delay Tanks B012 (1.86µSv/h) in the

Access Corridor B013.

1.5

RM / HP

Cooling coils maintenance (1)


1 1 0.5 2





1

RM / HP

Monorail, crane & chain block

inspections (4)


1 1 0.25 12.45 Dose rate at 0.5m 3.1

RM / HP

Replace Vacuum Pump

Pump Room B007 4 1 1 4.4 4.4µSv/h @1m from


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RM / HP

Replace Demister Pump Room B007 2 1 0.5 4.4 4.4µSv/h @1m from


RM / HP

Replace Solenoid Valve

Pump Room B007 2 1 0.5 4.4 4.4µSv/h @1m from


RM / HP

Replace flow switch Pump Room B007 1 1 0.5 4.4 4.4µSv/h @1m from


RM / HP

Calibrate Instruments (2 flow swithces, 3

level sensors, area rad monitor)

Pump Room B007 1 1 0.5 4.4 4.4µSv/h @1m from


RM / HP

Radiation detector & pump maintenance (2)

Corridor B013 2 1 0.5 2





2

RM / HP

RH and Temp sensor maintenance (3)

Corridor B013 3 1 0.25 2





1.5

RM / HP

Calibration of instruments (P & T

sensors- 12) Corridor B013 1 1 3 2





6

RM / HP

Change Tank Outlet Valve (168)

Corridor B013 1 1 0.5 8.73



(0.03µSv/h) and 0.5m DR from Gas Delay Tanks B012 (8.7µSv/h) in the Access Corridor

B013.

4.365

RM / HP

Change Tank Inlet Valve (168)

Corridor B013 1 1 0.5 8.73




B013.

4.365

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RM / HP

Calibrating Pressure Transmitter (84)

Corridor B013 84 1 0.5 8.73




B013.

366.66

RM / HP

Change of SIAM filters (2)


0.2 1 1 50


occupied and if work is to take

place in B015, ILLW and LLLW

inventories will be cleared and flushed repeatedly until a

sufficiently low dose rate is achieved.

10

RM / HP

Calibrations (2 SIAM Rad Monitors, diff

pressure transmitter, temp transmitter, Area monitor, air

sampler)


1 1 4 50






200

RM / HP

Calibrating Hydrogen transmitter,


2 1 1 50






100

RM / HP

Calibration- Holding tank pressure

indicator


1 1 2 50






100

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RM / HP

Change out the check/pressure relief

valve (15)


1 1 1.25 50






62.5

RM / HP

Inspection of crane rails


1 1 0.25 50






12.5

RM / HP

Safety shower testing 52 1 1 1 <1µSv/h ambient

dose rate 52

RM / HP

Calibrating fire detectors (too all basement rooms)

All Basement Rooms

1 1 2 3.5




B013.

7

1015

BM / HP

Maintenance of motorised valves- 6


B005 0.2 1 2 10.6


dividing wall 4.24

BM / HP

Change solenoids (336)

Corridor B013 3 1 0.25 8.73




B013.

6.5475

BM / HP

Change Pressure Transmitter (84)

Corridor B013 0.5 1 0.25 8.73




B013.

1.09125

BM / HP

Change PT (Pressure Transmitter) electronics

B013 Corridor 3 1 1 8.73




B013.

26.19

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BM / HP

Change solenoids/actuators


1 1 0.25 50






12.5

BM / HP

Replacement of manips (MT200's)

Front of cells 12 1 0.75 10 Dose rate at HP

position 90

BM / HP

Replacement of other manips

Front of cells 12 1 0.5 3 Dose rate at HP

position 18

BM / HP

Swipe access testing & maintenance

Exit doors in corridor

0.1 1 0.5 3.5




B013.

0.175

159

Total Collective

Dose HP 1567

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Appendix D: Dispatch and Packaging Annual Dose Assessment


# workers for task

time required (hrs)

dose rate (µSv/hr)

dose rate comments

total dose per

year (uSv)

OPS Smear Test

Cell face area and Dispatch and

Packaging. 765 1

Dose based on assessment of

packing B(U) in IHB. 765 x 9 =

6885µSv/yr

6885

OPS Move trolley to leak

test area

OPS Perform leak test

OPS Transfer to despatch

OPS assemble final

container

OPS lid tensioning

OPS transport index and

final smear test

Total Collective Dose Dispatch and

Packaging 6885

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UNCLASSIFIED

Appendix E: Waste Operations Annual Dose Assessment


# workers for task

time required (hrs)

dose rate (µSv/hr)

dose rate comments

total dose per

year (uSv)

OPS Taking SUF flask off

truck Truck Airlock

B001 52 2 0.5 0.5

Dose rate 1.0m from carbon column

wall 26

OPS flask onto waste cell, transfer of SUF cups

into flask

Ground floor cell area- rear of cells

52 2 0.5 2 0.5m dose rate with rear of ILSW hot cell

104

Ground floor cell area- front of cells

52 2 0.5 1.5 0.5m dose rate with

front of ILSW hot cell

78

OPS SUF flask onto truck -

contact period Truck Airlock

B001 52 2 0.1 25 15 weeks decay 260

OPS SUF flask onto truck Truck Airlock

B001 52 2 0.5 0.5


wall 26

OPS Taking Retievable

waste flask flask off truck

Truck Airlock B001

72.8 2 0.5 0.5 Dose rate 1.0m

from carbon column wall

36.4

OPS flask onto waste cell,

transfer of retrievable waste into flask

Ground floor cell area- rear of cells

72.8 2 0.5 1 General ambient rear of cells dose

rate 72.8

OPS Ground floor cell

area- front of cells 72.8 2 0.5 0.50

General ambient front of LLSW cells

dose rate. 36.4

OPS Retrievable waste flask onto truck -

contact period

Truck Airlock B001

4 2 0.1 67 AG Columns 53.6

OPS Retrievable waste flask onto truck -

contact period

Truck Airlock B001

68.8 2 0.1 50 All other waste 688

OPS Retrievable waste

flask onto truck Truck Airlock

B001 72.8 2 0.5 0.5


wall 36.4

RM



one changed)


B005 0.2 2 8 10.6


dividing wall 33.92

Total Collective Dose Waste Ops

1452

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Appendix F: Contractors Annual Dose Assessment


# workers for task

time required (hrs)

dose rate (µSv/hr)

dose rate comments

total dose per

year (uSv)

Ops Crane maintenance

(yearly) Rear of cells 1 2 5 1


cells 10

Ops Girder trolley servicing Active

maintenance- 26 1 2 0.5 10 10 @ contact 10

Ops Powered conveyor

inspection & maintenance

Container handling 0043

2 2 3 1 3 @ contact 12

Ops Crane inspection Container

handling 0043 4 1 0.5 1 3 @ contact 2

34

RM Calibrating fire

detectors (too all basement rooms)

All basement rooms

1 2 4 3.5




B013.

28

RM Inspection of crane

rails Pump & Tank Room B015

12 2 0.5 50





achieved.

600

RM Cooling coils

maintenance (1) Carbon column

area- B006 1 2 1 2




B013.

4

RM Monorail, crane &

chain block inspections (4)


1 2 0.5 12.45 Dose rate at 0.5m 12.45

RM Doors- Chain block &

pulley inspection Outside B004 &

B005 1 2 1 8.8

Contact DR with AVS room door

17.6

RM Crane maintenance

(monthly) Rear of cells 11 2 1 1


cells 22

RM SS / EW testing Rear of cells 48 2 0.5 1 Average dose rate 2.0m from rear of

cells 48

RM High bay light changes Rear of cells 0.5 2 2 1 Average dose rate 2.0m from rear of

cells 2

RM Fire detection system Rear of cells 1 2 1 1 Average dose rate 2.0m from rear of

cells 2

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UNCLASSIFIED

RM Scissor lift servicing Rear of cells 1 2 1 1 Average dose rate 2.0m from rear of

cells 2

738.05

BM Swipe access testing &

maintenance Exit doors in

corridor 0.1 2 1 6

DR down centre of Corridor B013

1.2

1.2

Total Collective

Dose Contractors 773.25

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Appendix G: Drivers Annual Dose Assessment A conservative approach was taken and it was assumed that the total yield from all Mo99 production was to be export Mo99.

In order to estimate the increase in exposure to drivers from the loading and delivery of export Mo99 from the ANM Mo99 Facility, first an exposure per activity delivered ratio was calculated based on 2014 export Mo99 activity delivered and driver EPD dosimetry data.

The total weekly yield from the ANM Mo99 Facility is taken as 3000Ci/week, 6 day calibration. This was extrapolated to an annual yield by multiplying by 52 weeks/year.

To estimate the total collective exposure to the drivers for the delivery of export Mo99 from the ANM Mo99 Facility, the ANM Mo99 annual yield was divided by the exposure per activity delivered ratio.

B54 Exposure (µSv)

Activity Delivered (TBq)

Activity per unit exposure (TBq/µSv)

19 157.648 8.30

ANM (6 day Cal) Annual, Calibrated Activity (TBq)

Annual, Yield Activity (TBq)

Annual Collective Dose (µSv)

5772.00 26189.01 3156

Annual Collective Dose (µSv) 3156

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Appendix H: QC Annual Dose Assessment In order to estimate the annual collective dose for ANM QC workers, an extrapolation of the average of the 2014 and 2015 annual collective doses, due to the increase in QC work and total activity handled, was performed. For the 2014 and 2015 calendar years, the average annual collective dose for the Mo99 QC group was 4.85man mSv. This exposure is due to QC performing analysis 4 times per week with an initial QC sample size of 5GBq. Total activity handled per week is 20GBq. Production at ANM will be a maximum of 10 runs per week with QC performing analysis a maximum of 8 times per week as 2 production runs will be combined when samples are sent to QC. The maximum sample size that will be sent to ANM QC will be 2.7 GBq. Total activity handled per week will be 21.6GBq. In order to estimate the potential exposure to the the QC group during the operation of ANM, the following assumptions were made:

A 100% increase in the collective dose for QC analysts from the increase in number of runs from 4 to 8.

An additional 8% increase on current collective dose for QC analysts due to the increase in total activity handled from 20GBq to 21.6GBq.

The expected maximum annual collective dose for the QC worker group is calculated to be 10.1mSv. The ANM project has indicated that 12 workers will make up the QC work group. This results in an average annual individual dose of 842µSv. This value is considered very conservative as it does not take into account any potential dose reductions due to improvements which are being implemented in the B2 QC lab.

UNCLASSIFIED



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Appendix I: ANM Mo99 Ground Floor

UNCLASSIFIED



UNCLASSIFIED

Appendix J: ANM Mo99 Basement

End of Document

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