Wednesday, 4 March 2015

HEALTH PHYSICS
RADIATION: Particles emitted by unstable nuclei during spontaneous transformation into stable nuclei is called radiation. Three types of radiations are emitted.
1. ALPHA  (α )
2. BETA   (β)
3. GAMMA  (γ)
RADIOACTIVITY: The spontaneous transformation of unstable nuclei into stable nuclei with emission of fast moving particles is called radioactivity
ACTIVITY: The activity ‘A’ of a radioactive element is the number of transformations taking place in unit time and is expressed in transformation per second ( tps). The unit of activity is Becquerel(Bq).  1 Bq = 1 tps
The old unit of activity is Curie (Ci). 1 Ci = 3.7 x 1010 Bq.
EXPOSURE: In general terms, it refers to the amount of radiation reaching a material. It refers to the amount of ionization produced in air by ionizing radiation. Unit of Exposure is roentgen(R). 1R = 2.58 x 10-4 Coulombs/Kg of air.
 Exposure of 1 roentgen is frequently considered approx. equivalent to an absorbed dose of 1 rad (radiation absorbed dose).
ABSORBED DOSE: Energy absorbed per unit mass of a substance to which it is exposed. SI unit is joule/kg and it is termed as Gray (Gy). The earlier unit is rad. 1 Gy = 100 rad. 1 Gy = 1 J/kg.
DOSE LIMIT:
Category
Annual effective Dose limit (mSv)
Annual equivalent Dose limit (mSv)
For consecutive five yrs (mSv)
Life time effective Dose limit (Sv)
Lens of eye
Skin
Extremities
Radiation worker
30
150
500
500
100
1
Apprentices & Trainees
6
50
150
150
--
--
Temporary worker
15
75
250
250
--
--
Member of Public
1
15
50
--
--
--

For Pregnant woman, 1 mSv effective dose to the embryo/fetus for remainder of pregnancy



EXTERNAL EXPOSURE CONTROL:
External exposure control can be achieved by:
A.      TIME: Dose (mSv) = Dose rate (mSv/hr) x time(hr). By reducing the time spent in radioactive areas.
B.      DISTANCE: I1D12 = I2D22. (Where I1 -> Intensity of radiation at a distance d1, & I2 -> Intensity of radiation at a distance d2. )Radiation field at a point is inversely proportional to the square of the distance between the point & source.
C.      SHIELDING: Introducing shielding material in between the source and the target can reduce the intensity of gamma radiation.
DOSE MEASUREMENT:
1.      DIRECT READING DOSIMETER(DRD): (FOR DAY TO DAY EXPOSURE)
It works on the principle of gold leaf electroscope. It consists of two electrodes, one is a fixed metal wire and the other is metal coated quartz fiber spring. Initially, the electrodes are charged to around 200V, externally by touching the charging pin to a battery. Both the electrodes will then be positively charged and the electrostatic repulsive force existing between them will drive the movable fibre away from the fined wire. When radiation falls on DRD for a time, ionization of air (app. 2cm3 volume) i.e filled in cavity (chamber) take place and this ionization discharges the movable fibre to lower voltage. The difference in voltage gives a measure of the total amount of radiation which fell on the chamber during irradiation.
Range of DRD:
0 – 200 mR
0 – 500 mR
0 – 1000 mR
0 – 5 R(5000 mR)
2.      THERMO LUMINESCENT DOSIMETERS(TLD): Issued every month and processed after completion of month material. CaSO4(Calcium Sulphate deposited in Dysprosium)
3.      ZONING:
In order to restrict spread of contamination to various areas and also to confine contamination, entire plant area is divided into 4 zones.

1.     WHITE ZONE: This zone will be free from contamination at all times and will contain no radioactive equipment. (Ex. Control room building, all offices, canteen etc)

2.   GREEN ZONE: This zone should not normally become contaminated and will not contain any radioactive equipment. With movement of person from amber zone some contamination may spread into this area. To prevent spread of contamination to white areas, contamination in green areas will be cleared as soon as it is detected. (Ex. All corridors, Lobby, Make up areas, solution make up & pumping areas, Change room). External radiation field less than 0.25 mR/hr. Air borne contamination = 0.1 DAC.

3.     AMBER ZONE: This zone includes the service areas for entire equipment and materials that are potential sources of contamination. Hence this zone is likely to get contaminated at times. Work procedures shall be planned to keep contamination localized and loose contamination shall be cleaned up whenever it occurs. (Ex. All access galleries, Sampling gallery etc. External radiation field less than 1 mR/hr. Air borne contamination = 1 DAC.

4.  RED ZONE:  This zone contains sources of contamination and also radioactive equipment. (Ex. Dissolver cell, all cells, Hot cell storage area, Pu enclosure A & B in Pu lab, all LEWA pumps located at 1st south side, 2nd north & south side.
A person moving from a higher zone to a lower should always check fro contamination at each inter zonal monitors.

4.      CONTAMINATION: Unit -> Bq/cm3.
§  Contamination is the presence of a radioactive substance in or on a material or on the human body or on any other place where they are undesirable or could lead to unwanted exposures.
§   Contamination which can be removed by simple means, is called loose contamination.
§  Contamination which requires either mechanical or chemical methods for removal, is called fixed contamination.
§   
5.      DECONTAMINATION: It is the process of removal of contamination from any surface or material.
§  Personal Decontamination:
1.      First find out the precise location of contamination.
2.      Special emphasis should be placed on the location of any hot spots on the individual.
§  Decontamination methods:
1.      Flush the location with water
2.      Wash with liquid soap/detergent for 2-3 minutes.
3.      Check for contamination. If contamination persists then
4.      Use compelling agent like EDTA(Ethylene diamante tetra acetic acid) solution.
5.      Check for contamination. If contamination persists then use mild organic acid like citric acid.
6.      Check for contamination. If contamination persists then refer to medical officer.

6.      ANNUAL LIMIT OF INTAKE(ALI): It is the quantity of radionuclide that, when taken in a year by the by the reference man, would result in a committed effective dose not exceeding the annual dose limit of 20 mSv of occupational exposure.

7.      DERIVED AIR CONCENTRATION (DAC): It is that concentration of a radionuclide in air (Bq/m3) which when breathed by reference person for working year of 2000 hrs under the condition of light activity (no any heavy work) which would result in intake of one ALI. The breathing rate for light activity is 1.2 m3/hr.
1.2m3/hr x 2000 hr = 2400 m3.
                   ALI
DAC =  --------------- 2400 m3.
                 2400
If a person works in one DAC environment for one hour, the dose received is 1mrem(1 mR). 1DAC-hr = 1mrem
For Pu-239 : 1 DAC = 0.26 Bq/m3
For Sr-90; 1DAC = 110 Bq/m3.

8.      SOLID WASTE CATEGORIES:
Category I       ->         < 200 mR/hr
Category II      ->         200 – 2000  mR/hr
Category III     ->         2000 mR/hr(2R/hr) – 50 R/hr
Category IV     ->         > 50 R/hr.

RADIATION EMERGENCY CLASSIFICATION
1.      Personal Emergency
2.      Emergency Alert
3.      Plant Emergency
4.      Site Emergency
5.      Off Site Emergency
EMERGENCY ALARM
1.      STAY IN: Off side: Short Intermittent Siren. 5 sec. on, 5 sec, off up to 2 minutes External Hazards. After 1.6 Km  Safe shutdown, normal route, assembly area
2.      EVACUATION: Inside plant. Long Intermittent Siren. 15 sec on, 5 sec off up to 2 minutes. Internal Hazards (Criticality). Safe shutdown, normal route, assembly area. Avoid affected area, shortest route, assembly area
3.      ALL CLEAR : Continuous Uninterrupted Siren for the period of 2 minutes.
·         If the gamma radiation field at 1 meter & above the ground at any Off site location exceeds 1mR/hr then Off site emergency is declared.
·         RESPIRATORY PROTECTIVE EQUIPMENTS:
PF = Protection Factor
= Inhalation(contamination) without protection
   Inhalation(contamination) with protection
MASKS
·         Half Face Mask: 1 to 10 DAC
·         Full Mask: 10 to 50 DAC
·         FAL (Fresh Air Line) half face: 50 to 1000 DAC (20 psi)
·         FAL (Fresh Air Line) full face: 1000 to 2000 DAC (20 psi)
·         Self Contain Breathing: 200 to 1000 DAC
·         Positive pressure self contained breathing apparatus kit (SCBA) = 2000 to 10000 DAC
DOSE ALLOWED
1.      Monthly : 200 mR
2.      Quarterly: 1.5 R/15 mSV
3.      Yearly: 2 R (20 mSv) averaged over period of 5 block(successive) yrs or 30 mSv for single year
4.      Life time: 1 Sv
DOSE AUTHORISATION
Up to 200 mR -> no authorization
200 mR to 400 mR -> Section Superintendent
Up to 1500 mR -> Plant Superintendent
Ø  In ROP, different area monitors such as AGM(area gamma monitor), SGM(Special purpose gamma monitor), WGM(wide range gamma monitor), LGM(low range gamma monitors), CAM( continuous air monitor) such as AMA(air monitor alpha) and AMB(air monitor beta) are placed in all access gallery, sampling gallery, all Labs & other areas of plant.
Ø  WGMs are placed in one Pu Lab (WGM-1) off gas heap room & near deep bed filters.
Ø  SGMs are placed in PCW, Steam trap area and Hold up tank area
Ø  LGM are placed near TLD rack area near Pu storage and Control Lab.
Ø  AGMs & CAMs are placed in all access galleries, sampling galleries, all Labs, cell top area etc.

Monitor
Alarm Level
Range
AGM
5mR/hr
0 – 100 mR/hr
LGM
50 mR.hr

SGM
2 mR/hr
0 – 100 mR/hr
WGM(off gas HEPA room)
20 mR/hr

WGM(deep bed filter)
1 R/hr

AMA
360 cpm

AMB
2400 cpm



Ø  STACK MONITORS – 2 UNITS. Each unit contain 3 monitors

SN
MONITOR
ALARM LEVEL
1
AMA
1200 cpm
2
AMB
9000 cpm
3
AMKr
2000 cps

Ø  CRITICALLITY  ALARM SYSTEM(CAS)
PREFRE – II                                                                  PREFRE - I
CAS-1 : CELL – 3    Display is kept at 2nd,/N/Corridor             CAS-1 : CELL – 3
CAS-2: CELL – 4            Display is kept at 2nd,/N/Corridor                  CAS-2: Pu Lab
CAS-3: Pu LAB                                                             CAS-3: Pu store
CAS-4: Pu STORE
CAS AT NMSF Pu STORE IS COMMON TO BOTH

Ø  ALARM INDICATION OF CAS
-          Dose rate : 4 R/hr then it will give alarm
-          Dose : 3 mRad in 500 mille sec then it will give alarm

PLANT EMERGENCY PROCEDURE
TYPE ‘A’ EMERGENCY: Minor accidents, Power failure, Ventilation failure etc
TYPE ‘B’ EMERGENCY: Heavy Fire,  Spillage of radioactive solutions and Explosion. 
SRVO ( SAFETY RELATED UNUSUAL OCCURANCE)
SERVILLANCE
To ensure, the trouble free availability of the equipment during the plant operations and to define its frequency.
1.      STACK MONITORS
2.      CONTAMINATION MONITORS
3.      CRABES
4.      D,G, SETS
5.      P.A SYSTEM
6.      DIESEL/OIL RELATED PUMPS.

MONITORS
1.      Plain Monitor/Single hand monitor/Alcin: Contamination of Alpha (10 cm range)
2.      Gamma Area Monitor: 2mr/hr
3.      Pu in air monitor(aerosol monitor): 1DAC/1Bq/m3.
4.      CRITICALITY Monitor: 4R/hr or 3mr/inch<500 milli sec.
5.      Alcin: Alpha ventilation monitor
6.      DRD: Direct reading dosimeter
7.      TLD: Thermo Luminous Dosimeter
8.      Neutron Badge: Neutron counting
HALF LIFE LIMIT
Uranium Oxide – 14 days
Biological: PuO2 – 50 years
Radiological: U238 =7 x 109 yrs
                        Pu239 = 24360 yrs

CLASSIFICATION OF FIRE
A.      Carbon contain fuel ie wood, paper, cotton etc
B.      Petroleum products ie Petrol, Diesel, kerosene
C.      Glass & chemical
D.     Combustible metal. Pu, U
E.      Electrical fire.
FIRE EXTINGUISHERS
SN
Fire/Extinguisher
Color code
Class of fire
1
SODA ACID
BLUE
B & C
2
CO2. (Carbon Di Oxide)
YELLOW
A,B, C & E
3
DCP (Dry Chemical Powder)
BLACK
D
4
HALLON
NO COLOR
D & E
5
FOAM
BROWN
B
6
WATER SPRINKLER/HOSE
RED
A



ABBRAVIATIONS

PREFRE
Power Reactor Fuel Reprocessing Plat

AWTF
Additional Waste Tank Form
AFFF
Advance Fuel Fabrication Facility

CFS
Centralized Fire Station
ROP
Revamping Of PREFRE

DRP
Driven Reading Process
WIP
West Immobilization Plant

EMC
Estate Management Cell
WMD
Waste Management Division

FRLS
Fire Retardant Lower Smoke
TWMF
Tarapur Waste Management Facility

GSO
General Services Organization
TRAP
Tarapur Radwaste Augmentation Plant

NMSF
Nuclear Material Storage Facility
AFR       
Away From Reactor

PLC
Programmable Logic Controller
AWSS
Augmented Water Storage Supply

SFSF
Spent Fuel Storage Facility
SF6
Sulphar Hexa Floride

ASSR
Aluminum Conductor Steel Rainforced
SSSF
Solid Storage Surveillance Facility

PILCA
Paper Insulated Lead Covered Armored
VFD
Variable Frequency Drive

HRPVC
High Rapchering Poly vinyl Chloride
WTA
Waste Tank Annex

APFCR
Automatic Power Factor Control Relay
WTF
Waste Tank Form

FRLS
Fire Retardant Low Smoke Cable
XLPE
Cross Link Polly Ethylene

ABCB
Air Blast Circuit Breaker
MOCB
Minimum Oil Circuit Breaker

VCB
Vacuum Circuit Breaker
ACB
Air Circuit Breaker

BOCB
Bulk Oil Circuit Breaker
ESL
Environmental  Survey Laboratory

AVS
Advance Verification System













--------**********---------

No comments:

Post a Comment