The document discusses various legal instruments and guidelines for emergency preparedness in India relating to nuclear and radiation facilities. It describes the roles and responsibilities of the Atomic Energy Regulatory Board (AERB) in regulating such facilities. The AERB has established various safety codes, guides, and rules like the Atomic Energy Act, Radiation Protection Rules, and criteria for emergency planning. It also discusses emergency preparedness and response plans at different facility and government levels along with concepts like categorization of facilities, declaration of on-site and off-site emergencies, and operational intervention levels to guide emergency response actions.

1. LEGAL INSTRUMENTS FOR EMERGENCY
PREPAREDNESS
Delivered at TOT course to NDRF on “Mobile Radiation Detection Systems MRDS and Response to Radiation Emergencies”
at Arokkonam/ Jan.19, 2017
Dr.R.M.Nehru,
Officer-in-Charge,
Southern Regional Regulatory Centre,
Atomic Energy Regulatory Board
Anupuram, Kalpakkam-603127
Tamil Nadu
nehru@aerb.gov.in

2. Outline…..
1. Introduction
2. Application of Nuclear Energy &
Radiation
3. Role of AERB & Legal Instruments for Emergency Preparedness
4. Typical doses received by workers in medical, industrial and
research institutions
5. Summary

3. Non-Ionizing
( cannot Ionize matter)
Radiation
Ionizing
( can Ionize matter)
Directly Ionizing
Radiation (charged
particles)
Indirectly Ionizing
Radiation
( Neutral Particles)
What are Radiation Detectors?
INTRODUCTION

5. 21 operational NPPs // 5 are under construction

6. Atomic Energy Regulatory Board
Nuclear Reactor Consists Of-------
Fuel - Each fuel rod of Zircaloy contains stacks of
uranium dioxide pellets. Zircaloy (2 or 4) is an alloy of
zirconium used as fuel clad.
Moderator - Used to slow down the neutrons to
thermal energies. Sometimes the same material is
used as a coolant. Typical moderator includes water,
heavy water, and graphite.
Coolant - Used to remove the heat from the fuel rods
directly if the moderator and coolant are the same
material. In cases where a separate moderator is
used, coolant tubes are routed through the
moderator, removing heat from fuel rods.
Control Rods - Used to regulate the distribution of
power in the reactor while the reactor is operating.
The most important function is to insert to shutdown
or stop the nuclear fission process when required.
Supporting Structure - Used to keep the fuel rigid either
horizontally or vertically, depending on the specific design.
Also is used to direct a uniform, or optimum, flow
distribution through the reactor.
Vessel-either horizontal or vertical - Used to hold the
fuel, moderator, coolant, and supporting structure.
BWR

7. Atomic Energy Regulatory Board
BWR, PWR, PHWR & LMFBR – Major Design Features
Reactor Types
Thermal Reactors Fast Reactors
Major
systems/
components
BWR PWR PHWR LMFBR
Reactor
Vessel
Pressure Vessel Pressure Vessel Pressure Tubes Pool type (Low Pressure)
Moderator H2O H2O D2O Not Applicable
Fuel Enriched-U Enriched-U Natural-U Plutonium-U
Coolant H20 H2O D2O Liquid.Sodium
Heat Transport
System
Direct Cycle, Boiling
occurs in Reactor Vessel
Primary (H2O) and
Secondary (H2O) Circuit
Primary (D2O) and Secondary
(H2O) Circuit
Primary(Na), Secondary (Na)
& Tertiary (H2O)Circuit

8. Atomic Energy Regulatory Board
How a NPP Works?How a NPP Works?

9. Application of Radiation
Radiography Nuclear Medicine
Diagnostic
Teletherapy Brachytherapy
Radiotherapy Nuclear Medicine
Therapy
Radiation in Medicine
Industrial
Radiography
Irradiators Nucleonic
Gauges
Consumer
Products
Radiation in Industry
Medical Industry Agriculture University
Radiation in Research

11. Radiology

12. Radiography & Fluoroscopy equipmentTypical doses of the order of
0.2 mGy to 10 mGy
Radiography Fluoroscopy
X-ray unit

13. C-Arm
Used in Operation Theaters
Typical dose
range : 1 mGy -20 mGy

14. Mammography Typical doses of the order of
3 mGy to 7 mGy

15. Computed Tomography
Typical doses of the order of
7 mGy to 10 mGy

16. Interventional Radiology
Typical Effective dose range : 10
mSv-70 mSv
Typical Skin Doses of the
order of 1 Gy to 20 Gy

17. Other Applications
• Dental X-ray (1 mGy-8 mGy)
• Orthopantomography/CBCT
• Bone Densitometry (~0.1 mGy)

18. Nuclear Medicine

20. POSITRON EMISSION TOMOGRAPHY

21. Radiation Therapy

22. Tele = “distance”

23. Brachy = “Short”
•Co-60 /Cs-137 in
needles/tubes
•Ir-192 in Wires/ Pellet
(commonly used)
•Co-60 in pellet(s)/ I-125
in Seeds

24. Research applications

30. Industrial applications
Radiographic Testing is widely used in the;
1. Aerospace industries
2. Military defence
3. Offshore industries
4. Marine industries
5. Power-gen industries
6. Petrochem industries
7. Waste Management
8. Automotive industries
9. Manufacturing industries
10.Transport industries
Radiographic testing is a non-
destructive testing of components and assemblies that is
based on differential absorption of penetrating radiation-
either electromagnetic radiation of very short wave-
lengths or particulate radiation by the part or test piece
being tested
Reference: http://www.twggroup.in/radiographic-testing.html
http://slideplayer.com/slide/4865849/

31. Reference:
http://www.slideshare.net/ravrak/intro-to-radiography-12ndt
Reference: http://www.twggroup.in/radiographic-testing.html

32. Courtesy: IAEA
Typical maximum source activities:
5.5 TBq (150 Ci) of 192Ir;
2.9 TBq (80 Ci) of 75Se;
740 GBq (20 Ci) of 169Yb;
370 GBq (10 Ci) of 60Co;
370 GBq (10 Ci) of 137Cs.
Typical GAMMA RADIOGRAPHY PROJECTORS /CAMERAS

33. Research- Gamma Irradiation Chamber
Radiation Symbol

42. Safety codes and standards are formulated on the basis of nationally and
internationally accepted safety criteria for design, construction and operation of
specific equipment, structures, systems and components of nuclear and radiation
facilities.
Safety codes establish the objectives and set minimum requirements that shall
be fulfilled to provide adequate assurance for safety.
Safety guides elaborate various requirements and furnish approaches for their
implementation.
Safety manuals deal with specific topics and contain detailed scientific,
technical information on the subject.
These documents are prepared by experts in the relevant fields and are
extensively reviewed by advisory committees of the Board before they are
published. The documents are revised when necessary, in the light of experience
and feedback from users as well as new developments in the field.
Regulatory Documents

43. ATOMIC ENERGY ACT 1962 NO. 33 OF 1962 [15th September, 1962] AFTER
AMENDMENTS NO. 59 of 1986 [23rd December, 1986] NO. 29 OF 1987 [8th
September, 1987]

44. Section 14. Control over production and
use of atomic energy
Section 16. Control over radioactive
substances
Section 17. Special Provisions as to
safety
Section 23. Administration of factories
Act, 1948
Section 24. Offences and Penalties
Section 27. Delegation of Powers
3.
Section 3
General Powers of the Central Government
Subject to the provisions of this Act, the Central Government shall have power -
(a) to produce, develop, use and dispose
of atomic energy either by itself or
through any authority or Corporation
established by it or a Government
company and carry out research into
any matters connected therewith;
(b) to manufacture or otherwise produce
any prescribed or radioactive
substance and any articles which in
its opinion are, or are likely to be,
required for, or in connection with, the
production, development or use of
atomic energy or such research as
aforesaid and to dispose of such
described or radioactive substance or
any articles manufactured or
otherwise produced;
ATOMIC ENERGY ACT 1962 NO. 33 OF 1962 [15th September,
1962]
Section 30. Power to make rules

46. Atomic Energy (Radiation Protection) Rules, 2004…..

47. Atomic Energy (Radiation Protection) Rules, 2004…..

48. Atomic Energy (Radiation Protection) Rules, 2004…..

49. Atomic Energy (Radiation Protection) Rules, 2004…..

50. Atomic Energy (Radiation Protection) Rules, 2004…..

51. Atomic Energy (Radiation Protection) Rules, 2004…..

53. http://www.aerb.gov.in

55. ROLE OF THE REGULATORY BODY WITH RESPECT TO EMERGENCY RESPONSE AND
PREPAREDNESS AT NUCLEAR AND RADIATION FACILITIES
AERB SAFETY GUIDE NO. AERB/SG/G-5

56. 2. TYPES OF EMERGENCIES AND BASIC RESPONSIBILITIES
AERB SAFETY GUIDE NO. AERB/SG/G-5

57. 3. ORGANISATIONAL ASPECTS - INTERFACES
AERB SAFETY GUIDE NO. AERB/SG/G-5

58. AERB SAFETY GUIDE NO. AERB/SG/G-5

59. AERB/NPP/SC/O (Rev. 1)
NUCLEAR POWER PLANT OPERATION

60. AERB/NPP/SC/O (Rev. 1)

61. AERB SAFETY GUIDE NO.AERB/SG/O-6
PREPAREDNESS OF THE OPERATING ORGANISATION FOR
HANDLING EMERGENCIES AT NUCLEAR POWER PLANTS

62. AERB SAFETY GUIDE NO.AERB/SG/O-6
PREPAREDNESS OF THE OPERATING ORGANISATION FOR
HANDLING EMERGENCIES AT NUCLEAR POWER PLANTS

63. AERBSAFETYGUIDENO.AERB/SG/O-6
PREPAREDNESSOFTHEOPERATING
ORGANISATIONFORHANDLINGEMERGENCIESAT
NUCLEARPOWERPLANTS

64. AERB SAFETY GUIDE NO.AERB/SG/O-6

65. AERB SAFETY GUIDE NO.AERB/SG/O-6

66. SITE EMERGENCY
AERB SAFETY GUIDE NO.AERB/SG/O-6

67. AERB SAFETY GUIDE NO.AERB/SG/O-6

68. AERB SAFETY GUIDE NO.AERB/SG/O-6
OFF-SITE EMERGENCY

69. AERB SAFETY GUIDE NO.AERB/SG/O-6

70. Action Flow Diagram for Site / Off-site Emergencies
Abnormal Plant
Conditions
SED Activates
Emergency Control
Centre
Shift Charge Engineer Alerts Site
Emergency Director
SED Reviews Radiation Levels at
the Site
Site Emergency Committee members Informed
of Plant / Radiation Status & SEC Convened by
SED
Site Emergency Declaration
by SED
Survey of Off-site Radiation
Levels
Increase in Off
–Site Radiation
Levels
SED Informs Off-site
Authorities (OED)
Off-site Emergency
Declaration by OED
Off-site Emergencies
Actions Continued
Fall in Off-site
Radiation Level
Below ERL
Termination of Off-site
Emergency by OED
Site Emergency Actions
Continued
Recovery of Normal
plant Status &
Normal Radiation
Termination of Site Emergency
by SED
Increase in
Radiation Levels
Within the Site
Atomic Energy Regulatory Board, India

71. Incident site
Declaration of Emergency by SED /
OED of site
Incident site
Declaration of Emergency by SED /
OED of site
State Level
State Emergency Response
Committee
State Level
State Emergency Response
Committee
Incident site/ERCC
Emergency Response
Co-ordination Committee
Incident site/ERCC
Emergency Response
Co-ordination Committee
DAE Level
DAE-Emergency control Room/Crisis Management
Group remains
Activated till emergency is terminated.
DAE Level
DAE-Emergency control Room/Crisis Management
Group remains
Activated till emergency is terminated.
National Level
National Crisis Management Committee (NCMC) /
NCMC Control room at Delhi is activated and convened
National Level
National Crisis Management Committee (NCMC) /
NCMC Control room at Delhi is activated and convened
Communication during Off Site Emergency
Atomic Energy Regulatory Board, India

72. AERB SAFETY GUIDE NO.AERB/SG/O-6
PREPAREDNESS OF THE OPERATING ORGANISATION
FOR HANDLING EMERGENCIES AT NUCLEAR POWER
PLANTS

73. CRITERIA FOR PLANNING, PREPAREDNESS AND RESPONSE
FOR NUCLEAR OR RADIOLOGICAL EMERGENCY
AERB SAFETY GUIDELINES NO. AERB/NRF/SG/EP-5
(Rev. 1)

74. CRITERIA FOR PLANNING, PREPAREDNESS AND RESPONSE
FOR NUCLEAR OR RADIOLOGICAL EMERGENCY
AERB SAFETY GUIDELINES NO. AERB/NRF/SG/EP-5
(Rev. 1)

75. CRITERIA FOR PLANNING, PREPAREDNESS AND RESPONSE
FOR NUCLEAR OR RADIOLOGICAL EMERGENCY
AERB SAFETY GUIDELINES NO. AERB/NRF/SG/EP-5
(Rev. 1)

76. CRITERIA FOR PLANNING, PREPAREDNESS AND RESPONSE
FOR NUCLEAR OR RADIOLOGICAL EMERGENCY
AERB SAFETY GUIDELINES NO. AERB/NRF/SG/EP-5
(Rev. 1)

77. CRITERIA FOR PLANNING, PREPAREDNESS AND RESPONSE
FOR NUCLEAR OR RADIOLOGICAL EMERGENCY
AERB SAFETY GUIDELINES NO. AERB/NRF/SG/EP-5
(Rev. 1)

78. CRITERIA FOR PLANNING, PREPAREDNESS AND RESPONSE
FOR NUCLEAR OR RADIOLOGICAL EMERGENCY
AERB SAFETY GUIDELINES NO. AERB/NRF/SG/EP-5 (Rev. 1)
TABLE11:CATEGORISATIONOFNUCLEARANDRADIATIONFACILITIESBASED
ON
HAZARDPOTENTIAL

79. CRITERIA FOR PLANNING, PREPAREDNESS AND RESPONSE
FOR NUCLEAR OR RADIOLOGICAL EMERGENCY
AERB SAFETY GUIDELINES NO. AERB/NRF/SG/EP-5 (Rev. 1)
TABLE11:CATEGORISATIONOFNUCLEARANDRADIATIONFACILITIESBASED
ON
HAZARDPOTENTIAL

80. CRITERIAFORPLANNING,PREPAREDNESSANDRESPONSE
FORNUCLEARORRADIOLOGICALEMERGENCY
AERBSAFETYGUIDELINESNO.AERB/NRF/SG/EP-5(Rev.1)

81. CRITERIA FOR PLANNING, PREPAREDNESS AND RESPONSE
FOR NUCLEAR OR RADIOLOGICAL EMERGENCY
AERB SAFETY GUIDELINES NO. AERB/NRF/SG/EP-5 (Rev. 1)

82. SUGGESTED RADIUS OF THE INNER CORDONED AREA (SAFETY
PERIMETER) IN A RADIOLOGICAL EMERGENCY
Situation Initial inner cordoned area (safety
perimeter)
Initial determination — Outside
Unshielded or damaged potentially dangerous source 30 m radius around the source
Major spill from a potentially dangerous source 100 m radius around the source
Fire, explosion or fumes involving a dangerous source 300 m radius
Suspected bomb (possible radiological dispersal
device), exploded or unexploded
400 m radius or more to protect
against an explosion
Conventional (non-nuclear) explosion or a fire
involving a nuclear weapon (no nuclear yield)
1000 m radius
Initial determination — Inside a building
Damage, loss of shielding or spill involving a
potentially dangerous source
Affected and adjacent areas (including floors
above and below)
Fire or other event involving a potentially dangerous
source that can spread radioactive material
throughout the building (e.g. through the ventilation
system)
Entire building and appropriate outside distance
as indicated above
Data extracted from AERB SAFETY GUIDELINES NO. AERB/NRF/SG/EP-5 (Rev. 1)

83. OPERATIONAL INTERVENTION LEVELS (OILs) IN RADIOLOGICAL
EMERGENCIES BASED ON AMBIENT DOSE RATE MEASUREMENTS
FROM GAMMA-EMITTING RADIONUCLIDES
Major exposure conditions OIL Main actions
External radiation from a point
source
100 μSv/h Isolate the area
Recommend evacuation of cordoned
area
Control access and egress
External radiation from ground
contamination
over a small area
100 μSv/h Isolate the area
Recommend evacuation of cordoned
area
Control access and egress
External radiation from ground
contamination over a wide area
1 mSv/h Recommend evacuation or substantial
shelter
External radiation from air
contamination with an unknown
radionuclide(s)
1 μSv/h Isolate the area (if possible)
Recommend evacuation of cordoned
area or
downwind in case of open area
Data extracted from IAEA-TECDOC-1162

84. International Obligations
India is a signatory to
• The Convention on Assistance in the Case of a Nuclear Accident or
Radiological Emergency (‘Assistance Convention’).
• Convention on Early Notification of a Nuclear Accident
• The Crisis Management Group (CMG) is the nodal agency under
both these conventions for keeping contact with the Incident and
Emergency Centre (IEC) of IAEA.

86. Response to Radiological Emergency
Radiological Incident : Information From Public / Media
/ Police/ Hospitals etc.
Mobilize Resources :
• NDMA
• CMG
• AERB
• DAE ERCs (28)
• SDMA / DDMA
• MHA/NEC
Coordinate Actions Through :
• District authorities
• NDRF
• SDRF / DDRF
• Other Resources
Atomic Energy Regulatory Board, India
After Information
DC/DM to take Full Charge of the situation
Initiate actions
DC /DM AERB CMG NDMA

87. NDRF
Arrival of DC/DM(IC)
Technical
Support
Police, SDRF,
Transport etc
NDMA MHA/NECCMG (DAE) AERB
•Inform NCMC
•Coordinate at national Level
in Consultation with AERB,
DAE & MHA
•Move NDRF
Activate ERC/
Installation and
NDRF Bn for
Monitoring
• Monitoring
• Supervision
• Advice
•Activate state Govt.
-Police Support
- Transport Facility
• Arrange for Medical
Support, Air Lifting (if
required)
• Inform NCMC
AFFECTED SITE
Monitor the Area & cordoning-off
Start Rescue and Relief Operation
Provide Technical
Support from
BARC/NPCIL/
BRIT
Atomic Energy Regulatory Board, India
DC/DM to Co-ordinate (under guidance)
• Recovery & Disposal of Source
• Rescue & Relief
• Large Scale DC and Rehabilitation

88. Emergency Planning and Preparedness
 Lay down the Criteria for Emergency Response.
 Review Off-site Emergency Preparedness Plan.
 Ensure emergency facilities, equipments and resources are available with response
organisations by periodic RI.
 Ensure periodic emergency exercises are conducted
 Post observers during the emergency exercises.
 Ensure conduct of off-site emergency exercise prior to first criticality
 Approve any modification of emergency plan or procedure.
 Review and update emergency preparedness plans during the PSR
Atomic Energy Regulatory Board, India
Nuclear and Radiological Emergencies – Role of AERB

89. During Actual Emergency Situation
 Obtain information of actions taken by the District Authorities and the operating
organisation.
 Review and assess the emergency situation
 Inform public concerning the emergency situations.
 If required, intervene and issue directions to mitigate the consequences of the
accident.
Atomic Energy Regulatory Board, India

90. Post Emergency Situation
 Review and advise follow up actions to minimize exposures from radioactive
contamination.
 Lay down criteria for re-entry into plant areas and affected places.
 Review and authorise actions as necessary for recovery, resumption of operations
or decommissioning of the concerned plant.
 Conduct an overall assessment of the events that led to the emergency, response
actions taken during the emergency and post-emergency consequences and action
plans.
Atomic Energy Regulatory Board, India

91. During Emergency Situation in Other Country
 Obtain information regarding progression of events and radiological releases.
 Get inputs on environmental monitoring in India from responsible organisations
(BARC, CMG, NDMA)
 Review and assess the impact of emergency in India ( environment, imports, arrival
of air crafts and passengers etc ).
 Inform public regarding accident progression and impact if any on environment in
India.
 Advise Indian citizen though appropriate channel.
Atomic Energy Regulatory Board, India

92. Ref: http://www.slideshare.net/Tunoo/rad-safety-at-hospitals-v-07-25jun2010-peternyan
RADIATION ACCIDENTS

93. Avoidable radiation exposure arising from, for example:
Accidents or incidents to be reported
REPORT
x-ray equipment
component failure
during interventional
radiology, inappropriate
or improper monitoring
of fluoroscopy and other
imaging
poorly maintained x-ray
equipment
non-compliant x-ray
equipment

94. ACCIDENT
Failure to use survey
meter
Equipment failure
Safety procedures not
followed
Regulatory control lacking
or inadequate
Lack of safety program
Inadequate or lack of
training
Typical Causes of
Radiological Accidents...

95. Reference: AERB Annual Report 2014/2015
Typical doses received by workers in medical, industrial and
research institutions

97. SUMMARY
1. The use of ionizing radiation and nuclear energy continue to benefit
the society in several ways.
2. Safety systems in Radiation and industrial and research facilities are
well-maintained and regulated.
3. Radiation hazards to environment is negligible when compared to
other sources.
4. Relevant Legal and Regulatory instruments are in place to
address the radiological emergency situations.

98. THANKING……..THANKING……..
Organizers of this Course (Dr.S.Murali &
NDRF Team members),
and
AERB
&
YOU !!
Also to….