licensing and safety issues for small and medium- sized ... 2/ms presentations… · jaitapur...

Dr. A. Ramakrishna, AERB and Shri Jose Joseph, BARC INDIA

Licensing and Safety Issues for Small and Medium-

sized Reactors (SMRs)

29 July – 2 August 2013

IAEA Headquarters, Vienna, Austria

Nuclear Regulation for SMR in India – Current

Perspectives

National Nuclear Power Programme

Organisational Structure for Atomic Energy

Development and Deployment of SMRs in INDIA

Nuclear Regulation – Role of Atomic Energy Regulatory Board

Licensing Process for SMRs

Review Experiences for SMRs

Pre-licensing Design Safety Review of AHWR

Current Perspectives for Licensing Approach for New NPPs

New Provisions in light of Fukushima Accident

General expectations for the Dialogue Forum

Contents

INPRO Dialogue Forum on Licensing and Safety Issues for SMRs

2

Atomic Energy Commission (AEC) lays down the policies for National

Nuclear Power Programme.

Department of Atomic Energy executes the policies by engaging in

Research, Technology Development, Commercial Operations in the

areas of Nuclear Energy, related high technologies and basic research

in Nuclear Sciences.

Bhabha Atomic Research Centre – Frontline Multidisciplinary Research

Centre and strong technical support organisation.

Atomic Energy Regulatory Board is National regulatory body to frame

safety policies, lay down safety standards and requirements with

powers for enforcement.

National Nuclear Power Programme


3

Organizational Structure for Atomic

Energy in India


4

Development and Deployment of SMRs

in India (1/3)

BWRs

• 2 x 160 MWe 320 MWe

PHWRs

• 1 x 100 MWe 100 MWe

• 1 x 200 MWe 200 MWe

• 14 x220 MWe 3080 MWe

• 2 x 540 MWe 1080 MWe

-----Total----

• 20 Units 4780 MWe

NPPs in operation:


5

Development and Deployment of SMRs

in India (2/3)

Government accorded approval for additional new NPPs (PHWR-

700 MWe & LWRs-1000 MWe or above)

Siting evaluation completed / in progress

Kudankulam (Tamil Nadu) : 1000 MWe, VVER

Jaitapur (Maharashtra) : 1650 MWe, EPR

Gorakhpur (Haryana) : 700 MWe, PHWR

New sites identified for :

PHWRs 700 MWe - Inland Sites - Madhya Pradesh,

Rajashthan, Karnataka

LWRs 1000 MWe & above-

Chhayamithi Virdi, Gujrat - West coast

Kovvada, Andhra Pradesh - East coast

INPRO Dialogue Forum on Licensing and Safety Issues for SMRs 6

Development and Deployment

of SMRs in India (3/3)

NPPs under Construction/Commissioning

• Kundankulam – 1 & 2 (1000 MWe, VVER) • Unit – 1 under commissioning.

• Unit – 2 Construction nearing completion.

• Prototype Fast Breeder Reactor (500 MWe, PFBR) at Kalpakkam – Advanced state of construction

• Kakrapar – 3 & 4 & Rajasthan – 7 & 8 (700 MWe, PHWR) • Construction started


Nuclear Regulation - Role of AERB

Safety Review and Issue of License/Authorisation to Nuclear and Radiation Facilities

Ensure compliance with the stipulated requirements by the nuclear and radiation facilities

Licensing of Key Operating Personnel

Regulatory Inspections

Review of Emergency Preparedness

Development of Safety Documents

Safety Research

Public Information


Licensing Process for SMRs

Governing Document “Regulation of Nuclear and Radiation Facilities

”(AERB-SC-G)”

Major Stages of Consent : Siting, Construction, Commissioning ,

Operation , Decommissioning

Clearances can be issued in Sub-stages

Multi-tier review process

AERB Guide on Consenting Process for NPPs and Research

Reactors, “AERB/SG/NPP&RR/G-1” provides following details on

Contents and Format of safety documents such as Site Evaluation

Report, Safety Analysis Report, Lead-Time for documents, Review

areas for each stage of consent, Method for review and assessment,

Application-Formats for various consents (AERB/SG/G-7)


Madras Atomic Power Station (2 220 MWe)

1970-80

1980-90

STANDARDISATION

1990 onwards

COMMERCIALISATION

RAPP-3&4 KAIGA-3&4

KGS-1&2 RAPP-5&6 RAPS-1&2

MAPS-1&2

NAPS-1&2

KAPS-1&2

Independent

Review Committees

Systematic Design

review by

Regulatory

Body

Licensing based on

ARB/SG/G-1

Review Experiences for SMRs (1/2)

(220 MWe PHWRs)


1995 onwards

ECONOMY OF

SCALES

TAPS-3&4, 500 MWe PHWR

KKNPP-1&2, 1000 MWe VVER

• Evolved Design

• Extensive design

safety review

• Extensive use of

mock-ups for

complex design

structures

• Design of foreign origin

• Review based on PSAR in

RG1.70 format

• Input from Rostechnadzor (RTN)

review

• Review of first-of-a-kind safety

systems

PFBR, 500 MWe FBR

2000 onwards

EXPANSION OF POWER

PROGRAM

2000 onwards

DEMONSTRATION OF 2ND STAGE

PROGRAM

• Review of new design

• Safety criteria

document

• Extensive R&D, Test

of prototype

components

• OEF from FBTR

Review Experiences for SMRs (2/2)

(Different Technologies)

KAPP-3&4, 700 MWe PHWR


Pre-licensing Design Safety Review of

Advanced Heavy Water Reactor (1/2)

The design of AHWR is unique and objective to develop the

fuel cycle technologies of thorium utilization for power

production and sustenance of technologies developed for

PHWRs. It is a 300MWe boiling light water cooled, heavy

water moderated, vertical pressure tube type reactor designed

to produce most of its power from thorium.


Pre-licensing Design Safety Review of Advance

Heavy Water Reactor (2/2)

Important Features:

Advanced coolant channel design features with easily

replaceable pressure tubes.

Reactor physics design tuned for the use of thorium based fuel

with negative void coefficient of reactivity.

Passive systems for core heat removal (under both normal and

shutdown conditions), containment cooling and isolation.

Direct injection of ECCS water into fuel bundle.

Advanced accumulator with fluidic device.

Availability of large inventory of water in the overhead pool inside

containment.

No exclusion zone

Associated Desalination Plant


Approach of AERB for New NPPs (1/2)

• Imported Reactors considered after clearance by their

respective regulator body and adherence to AERB regulatory

processes.

• Design of foreign origin should be licensable in the country of

its origin.

• Review to be based on AERB codes & guides to the extent

applicable.

• In areas not covered by AERB documents, IAEA safety

standards, international/ foreign standards as acceptable to

AERB are considered.

• For advanced or innovative designs, safety criteria to be

established in consultation with TSO and designer.


Approach of AERB for New NPPs (2/2)

• Industry codes and standards other than those normally

used in India may require special assessment and

comparison exercises

• Different safety approaches/philosophies can be accepted

with adequate justification.

• Internationally available information including review

reports of other regulators and safety assessments would

be taken as supportive information but will not substitute

review by AERB.

• Lessons learnt from Fukushima to be addressed

adequately


15

New Provisions in light of Fukushima

Accident

• For a multi unit/multi facility site, consequences due to external events shall be assessed .

• Consequential effects due to incidences in one facility/unit on other facilities/units shall be considered.

• Emergency preparedness program to include accidents in multiple facilities, possible isolation.

• Continuous monitoring and periodic assessment of hazards including assessment of natural and human induced events

• Need for additional safety margins beyond the parameters considered for design basis events.


General expectations for the Dialogue

Forum

As SMRs are based on advanced and innovative concepts, SMR Forum should address R&D activities related to:

• Reactor Physics,

• Probabilistic risk analyses,

• High temperature and radiation effects on fuels and materials and

• High efficiency power conversion systems.

Regulations for New Concept Reactors

Economic Viability and Competition with large reactors


Thank you
