GOVERNMENT OF INDIA

ATOMIC ENERGY REGULATORY BOARDATOMIC ENERGY REGULATORY BOARDANNUAL REPORT 2013-14

ATOMIC ENERGY REGULATORY BOARD

The Atomic Energy Regulatory Board (AERB) was constituted on November 15, 1983 by the President of India by exercising the powers conferred by Section 27 of the Atomic Energy Act, 1962 (33 of 1962) to carry out certain regulatory and safety functions under the Act. The regulatory authority of AERB is derived from the rules and notifications promulgated under the Atomic Energy Act, 1962 and the Environment Protection Act, 1986.The mission of the Board is to ensure that the use of ionizing radiation and nuclear energy in India does not cause undue risk to health of people and the environment. Currently, the Board consists of Chairman AERB, Chairman SARCOP (Ex officio), four Members from outside and a Secretary.

AERB carries out its functions through highly qualified work force and specialist committees under the guidance of the Board. Apex level committees include Safety Review Committee for Operating Plants (SARCOP), the Safety Review Committee for Applications of Radiation (SARCAR), Advisory Committees for Project Safety Review (ACPSRs), Advisory Committee on Radiological Safety (ACRS), Advisory Committee on Industrial and Fire Safety (ACIFS), Advisory Committee on Occupational Health (ACOH), Advisory Committee on Security (ACS) and Advisory Committee on Nuclear Safety (ACNS). The ACPSRs recommend to AERB issuance of authorizations at different stages of projects of the Department of Atomic Energy (DAE), after reviewing the submissions made by the project authorities based on the recommendations of the associated Project Design Safety Committees.

SARCOP carries out safety surveillance and enforces safety stipulations in the operating units of the DAE. SARCAR recommends measures to enforce radiation safety in medical, industrial and research institutions, which use radiation and radioactive sources. AERB receives advice on development of safety codes and guides and on generic nuclear, radiation and industrial safety issues from ACNS, ACRS, ACIFS and ACSDFCF. ACOH advises AERB on occupational health safety matters. The administrative and regulatory mechanisms in place ensure multi-tier review of all safety matters by experts in the relevant fields available nationwide. These experts come from reputed academic institutions, R&D organizations, industries and Governmental Agencies.

AERB has a Safety Research Institute (SRI) at Kalpakkam, which carries out research in various safety related topics and organizes seminars, workshops and discussion meetings periodically.

AERB has seven technical divisions. Chairman, Vice-Chairman and Directors / Heads of Divisions and Director, SRI constitute the Executive Committee, which meets periodically and takes decisions on important matters related to the functioning of the organization. AERB enforces the following Rules issued under the Atomic Energy Act, 1962:

• Atomic Energy (Radiation Protection) Rules, 2004.

• Atomic Energy (Working of the Mines, Minerals and Handling of Prescribed Substance) Rules, 1984.

• Atomic Energy (Safe Disposal of Radioactive Wastes) Rules, 1987.

• Atomic Energy (Factories) Rules, 1996.

GOVERNMENT OF INDIA

ANNUAL REPORT2013-2014

ATOMIC ENERGY REGULATORY BOARDNIYAMAK BHAVAN, ANUSHAKTI NAGAR

MUMBAI-400 094

Website: www.aerb.gov.in

FUNCTIONS OF THE

ATOMIC ENERGY REGULATORY BOARD

• Develop safety policies in nuclear, radiation and industrial safety areas for facilities under its purview.

• Develop Safety Codes, Guides and Standards for siting, design, construction, commissioning, operation and decommissioning of different types of nuclear and radiation facilities.

• Grant consents for siting, construction, commissioning, operation and decommissioning, after an appropriate safety review and assessment, for nuclear and radiation facilities.

• Ensure compliance with the regulatory requirements prescribed by AERB during all stages of consenting through a system of review and assessment, regulatory inspection and enforcement.

• Prescribe the acceptance limits of radiation exposure to occupational workers and members of the public and acceptable limits of environmental releases of radioactive substances.

• Review the emergency preparedness plans for nuclear and radiation facilities and during transport of large radioactive sources, irradiated fuel and fissile material.

• Review the training program, qualifications and licensing policies for personnel of nuclear and radiation facilities and prescribe the syllabi for training of personnel in safety aspects at all levels.

• Take such steps as necessary to keep the public informed on major issues of radiological safety significance.

• Promote research and development efforts in the areas of safety.

• Maintain liaison with statutory bodies in the country as well as abroad regarding safety matters.

• Review the nuclear and industrial safety aspects in nuclear facilities under its purview.

• Review the safety related nuclear security aspects in nuclear facilities under its purview.

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CONTENTS Page NoHIGHLIGHTS OF AERB ACTTIVITIES AT A GLANCECOMPOSITION OF THE BOARDORGANISATION CHART OF AERB

CHAPTER1 SUMMARY 3

CHAPTER 2 SAFETY SURVEILLANCE OF NUCLEAR FACILITIES 152.1 NUCLEAR POWER PROJECTS2.1.1 Project Safety Review 152.1.2 Consents/Clearances/Permissions Issued 192.1.3 Regulatory Inspections of Projects 192.2 NUCLEAR POWER PLANTS AND RESEARCH REACTORS 212.2.1 Safety Status of Operating Plants 212.2.2 Consents / Clearances / Permissions Issued 222.2.3 Operating Plants Safety Review 22 2.2.4 Regulatory Inspections 282.2.5 Licensing of Operating Staff 302.2.6 Significant Events 312.3 NUCLEAR FUEL CYCLE AND OTHER RELATED INDUSTRIAL FACILITIES 322.3.1 Operating Plants/Project Safety Review 322.3.2 Consents/Clearances/Permissions Issued 352.3.3 Regulatory Inspections 362.3.4 Compliance status of RI recommendations of fuel cycle and DAE Accelerator units and 37

their resolution (2012-13)2.3.5 Licensing of Plant Personnel 382.3.6 Significant Events 382.4 R&D UNITS AND OTHER FACILITIES 382.4.1 Variable Energy Cyclotron Centre (VECC) 382.4.2 Raja Ramanna Centre for Advanced Technology (RRCAT) 392.4.3 Electronics Corporation of India Limited (ECIL) 39

CHAPTER 3 REGULATION OF FACILITIES USING RADIOACTIVE SOURCES IN INDUSTRY, 41 MEDICINE, AGRICULTURE AND RESEARCH

3.1 INTRODUCTION 413.2 REGULATORY PROCESS 443.2.1 Issuance of Consents 443.2.2 Safety Committees for Radiation Facilities 463.2.3 Approval of Radiological Safety Officers 473.3 REGULATORY INSPECTIONS 473.4 UNUSUAL OCCURRENCES AND ENFORCEMENT ACTIONS 483.5 AWARENESS PROGRAMS 49

CHAPTER 4 INDUSTRIAL SAFETY 534.1 LICENSES ISSUED UNDER THE FACTORIES ACT, 1948/ ATOMIC ENERGY 53

(RADIATIONPROTECTION) RULES, 20044.2 REGULATORY INSPECTIONS AND SAFETY REVIEW 534.3 OCCUPATIONAL SAFETY STATISTICS 544.4 FATAL ACCIDENTS 584.5 PROMOTION OF INDUSTRIAL SAFETY 594.5.1 Industrial & Fire Safety Awards 594.5.2 Environmental Protection Awards 604.6 OCCUPATIONAL HEALTH 604.6.1 Advisory Committee on Occupational Health 60

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CHAPTER 5 ENVIRONMENTAL SAFETY AND OCCUPATIONAL EXPOSURES 615.1 ENVIRONMENTAL SAFETY 615.2 OCCUPATIONAL EXPOSURES 65

CHAPTER 6 EMERGENCY PREPAREDNESS 69

CHAPTER 7 SAFETY DOCUMENTS 717.1 NEW SAFETY DOCUMENTS PUBLISHED 717.2 SAFETY DOCUMENTS TRANSLATED AND PUBLISHED IN HINDI 717.3 SAFETY DOCUMENTS UNDER DEVELOPMENT 727.4 REVIEW OF IAEA DRAFT DOCUMENTS 727.4.1 IAEA Draft Documents 727.4.2 IAEA Draft Document Profile (DPPs) 72

CHAPTER 8 SAFETY REVIEW AND STUDIES 758.1.1 SEVERE ACCIDENT ANALYSIS FOR VERIFICATION OF

SAMG FEATURES OF VVER-1000 USING ASTEC 8.1.2 Severe Accident Analysis for PHWRs 758.1.3 Simulation of thermo mechanical behavior of coolant channels in PHWR 758.2 HYDROGEN DISTRIBUTION & MITIGATION STUDIES 768. 2.1 Hydrogen Distribution Analysis for TAPS 3&4 (540MWe PHWR) 768.2.2 Sump Evaporation Model Development 768.2.3 Containment Thermal Hydraulic Analysis of a typical VVER-1000 for Extended SBO 768.2.4 Short-term Containment System Response Studies 778.2.5 Numerical Studies on Hydrogen Mitigation using Passive Autocatalytic Recombiners (PAR) 778.2.6 OECD/NEA HYMERES Project 778.2.7 Oecd/Nea Hymeres Project 778.3 THERMAL HYDRAULICS STUDIES 778.3.1 Pre-test and Post-test Analysis of Primary Natural Circulation (NC) Test for VVER-1000 778.3.2 Extended SBO Analysis for VVER-1000MWe using SCDAP/RELAP5 788.3.3 Extended SBO Analysis for 540 MWe PHWR with RELAP5/MOD3.4 788.3.4 Enhancement of Capability of In-House Containment Thermal Hydraulics Code 78

(THYCON) for Reactor Safety Studies8.4 EXPERIMENTAL STUDIES 78 8.4.1 Experimental study on transient Critical Heat Flux (CHF) in horizontal channels 788.4.2 Experimental and theoretical studies on shield design optimization of 78

Iron-Polyethylene system for Am-Be neutron source8.4.3 High Temperature Material property Evaluation 798.5 INTERNATIONAL COLLABORATIVE SAFETY ANALYSIS EXERCISES 798.5.1 IAEA ICSP on HWR moderator sub-cooling requirement to demonstrate backup heat sink 79

capabilities of moderator during accidents8.6 PROBABILISTIC SAFETY ANALYSIS 798.6.1 Probabilistic Structural Analysis of Typical Reactor Pressure Vessel 798.6.2 External flood PSA for PFBR 808.7 REACTOR PHYSICS STUDIES 808.7.1 Development of multipoint kinetics model for RELAP5 808.7.2 Pre-test Transient Analysis of KKNPP Core Commissioning Experiments using TRIKIN Code 808.7.3 Criticality Safety Assessment of FRFCF Dissolver 808.7.4 External coupling of Monte Carlo neutronics and ORIGEN codes for fuel depletion analysis 808.7.5 Analyses of reactivity initiated transients (RIT) in VVER-1000 reactor using TRIKIN code 808.7.6 Analysis of fuel loading scheme and first approach to criticality of PFBR 818.7.7 Reactivity Load Estimation for Silicon carbide coating on PHWR Fuel cladding 818.8 FIRE SAFETY STUDIES 818.8.1 Fire Modeling and Heat Flux Evaluation During Multiple Cable Fire 81

Scenario using CFD Approach8.8.2 Compartment Fire Test Facility (CFTF) and numerical Simulation 81

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8.9 STRUCTURAL SEISMIC ANALYSIS AND CORE MATERIAL STUDIES 818.9.1 Evaluation of thermal stratification induced stress in pipe and their impact on fatigue design 818.9.2 Seismic Capacity Assessment of AHX of PFBR using R6 Method 818.9.3 Evaluation of ultimate load capacity (ULC) of inner containment structure of KKNPP-1&2 828.9.4 Seismic safety of NPP structures under beyond design basis earthquakes 828.10 RADIOLOGICAL ASSESSMENT STUDIES 828.10.1 Development of in-house Gaussian plume model for atmospheric dispersion modeling 828.11 ENVIRONMENTAL SAFETY STUDIES 838.11.1 Nuclear Emergency Management Information System (NEMIS) 838.11.2 Environmental Assessment of Kudankulam Nuclear Plant site, Tirunelveli District, 83

Tamilnadu using Satellite Remote Sensing and Geographical Information System (GIS8.11.3 Mapping of Sea Surface Temperature (SST)Measurement around MAPS 848.11.4 Environmental Assessment of Combined Outfall Channel for the 84

PFBR-MAPS on the Marine Environment8.11.5 Prediction of Water Table Fluctuations in Response to Precipitation 858.12 PROCESS SAFETY ANALYSIS STUDIES 858.12.1 Recovery of uranium (VI) from dilute aqueous solutions using liquid membrane 858.12.2 Consequence Analysis of Hazardous Chemical releases 858.13 SAFETY REVIEW 858.13.1 Review of Proposals on Hydrogen Generation and Mitigation 858.13.2 PSA for PHWR Plants 858.13.3 Project Design Safety Committee (PDSC) –KAPP 700 MWe 858.13.4 KK Commissioning 858.13.5 Fukushima Experience Feedback in Documents8.13.6 Task Force for preparation of the State of the Art Report on R&D for 86

Severe Accident Assessment in PHWR (TF-PHWR-SOAR-SAA)8.13.7 Review of Extended SBO 868.13.8 Safety Studies for Fuel Pins, Cladding Tube and PT & CTs of PHWRs 868.14 AERB FUNDED SAFETY RESEARCH PROGAMME 86

CHAPTER 9 PUBLIC INFORMATION 899.1 INTERACTION WITH MEDIA 899.1.1 AERB press conference on December 13, 2013 899.1.2 Articles and Interviews Published in Different Magazines 899.2 PRESS RELEASES 899.3 AERB NEWSLETTER 899.4 ANNUAL REPORT 899.5 AERB BULLETIN 899.6 WEBSITE MANAGEMENT 909.6.1 AERB Website Launched 909.6.2 Development & Implementation of e-Licensing Of Radiation Applications (eLORA) 909.7 PARLIAMENTARY QUESTIONS 909.8 RIGHT TO INFORMATION ACT-2005 90

CHAPTER 10 INTERNATIONAL CO-OPERATION 9110.1 CNS MEETING AT IAEA DURING MARCH 2014 9110.2 INTERNATIONAL PEER REVIEW 9110.2.1 India decides to host IRRS Mission 9110.2.2 IRRS Reviewer Training 9210.3 VVER REGULATORS FORUM 9210.4 IAEA WORKSHOP ON IRS, RCA AND CA 9210.5 AERB’s ACTIVITIES AS AN MDEP MEMBER 9310.6 STRENGHTHENING NUCLEAR SAFETY 93 10.6.1 General Conference of IAEA 9310.6.2 Technical Working Group on Nuclear Power Infrastructure 93

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10.6.3 Activities related with INES 9310.6.4 ASEM Seminar in Nuclear Safety 9410.6.5 Korea- India Nuclear Energy Co-operation Forum 9410.6.6 International Workshop hosted by CANSAS 9410.6.7 Fuel Cycle Facilities 9410.6.8 Radiation Safety 9410.6.9 Faculty Member in IAEA Expert Mission 9410.7 NUCLEAR SECURITY 9410.7.1 Nuclear Security Guidance Committee 9410.8 CONTRIBUTION IN PREPARATION OF IAEA STANDARDS 9510.9 TRANSPARENCY AND REGULATORY COMMUNICATION 9510.9.1 Meeting of WG on Effectiveness and Transparency 9510.9.2 Activities related to Public Communication 9510.10 INTERNATIONAL AGREEMENT 95

CHAPTER 11 QUALITY MANAGEMENT SYSTEM (ISO 9001: 2008) 9711.1 QUALITY MANAGEMENT SYSTEM (QMS) OF AERB 97

CHAPTER 12 HUMAN RESOURCE DEVELOPMENTS 9912.1 MANPOWER AUGMENTATION 9912.2 IMPLEMENTATION OF PERSONS WITH DISABILITIES ACT, 1995 AND

IMPLEMENTATION / WELFARE OF RESERVATION POLICY FOR SCHEDULED CASTES/TRIBES/OBC 99

12.3 TRAINING 9912.3.1 AERB Orientation Course for Regulatory Processes (OCRP- 2014) 9912.3.2 One Year Training Programme for Stipendiary Trainees 10012.3.3 Orientation Course on Environmental Impact Assessment (EIA) of 100

Nuclear Fuel Cycle Facilities12.3.4 Other Training Activities 10112.4 REFRESHER COURSE 10112.5 AERB TECHNICAL TALKS 10112.6 AERB COLLOQUIA 10212.7 KNOWLEDGE MANAGEMENT 10212.8 DEVELOPMENT OF OFFICE AUTOMATION SOFTWARE 10212.9 IT INFRASTRUCTURE RELATED ACTIVITIES 10212.10 RETIREMENTS ON SUPERANNUATION 102

CHAPTER 13 SAFETY PROMOTIONAL ACTIVITIES 10313.1 DAE SAFETY AND OCCUPATIONAL HEALTH PROFESSIONALS MEET 10313.2 IAEA WORKSHOP ON INCIDENT REPORTING SYSTEM (IRS), ROOT CAUSE 103

ANALYSIS (RCA) AND CORRECTIVE ACTIONS (CA)13.3 THEME MEETING ON ‘REVISED CRITERIA FOR USE IN PREPAREDNESS 104

AND RESPONSE TO NUCLEAR OR RADIOLOGICAL EMERGENCIES’ (AERB/SG/EP-5)

13.4 THEME MEETING ON ‘EQUIPMENT QUALIFICATION (EQ) 105 OF OPERATING NPPS’

13.5 DISCUSSION MEET ON “PHWR SAFETY R&D WITH FOCUS ON SEVERE 105 ACCIDENTS”

13.6 INTERNATIONAL WORKSHOP ON NEW HORIZONS IN NUCLEAR REACTOR 106 THERMAL HYDRAULICS AND SAFETY

13.7 DISCUSSION MEET ON ENGINEERING OF FOUNDATIONS FOR 107 NPP STRUCTURES IN ALLUVIAL SOILS

13.8 DISCUSSION MEET ON ASSESSMENT OF STRUCTURE UNDER 107 IMPACT AND BLAST LOADS

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CHAPTER 14 OFFICIAL LANGUAGE IMPLEMENTATION 10914.1 PUBLICATIONS IN HINDI 109 14.2 PROMOTIONAL ACTIVITIES FOR HINDI IMPLEMENTATION 10914.3 HINDI TALKS/WORKSHOPS 10914.4 HINDI COMPETITIONS 110

CHAPTER 15 ACHIEVEMENTS 11115.1 ACHIEVEMENT OF PH. D 11115.2 HIGHER QUALIFICATION 11115.3 AERB AWARDS 111

CHAPTER 16 TECHNICAL INTERATION WITH EXTERNAL AGENCIES 11516.1 INTERACTION WITH OTHER AGENCIES 11516.1.1 Atomic Energy Regulatory Board signs Memorandum of Understanding 116

with Anna University, Chennai for Research Collaboration16.1.2 Bureau of Indian Standards (BIS) 11616.1.3 National Disaster Management Authority (NDMA) 11616.1.4 Representation in Ministry of Environment and Forests 11616.2 PROJECT GUIDANCE 11616.2.1 Guidance provided by IPSD 11616.2.2 Guidance provided by SRI 11616.2.3 Guidance provided by NSAD, AERB 116

CHAPTER 17 AERB WELFARE ACTIVITIES 11717.1 AERB STAFF CLUB ACTIVITIES 11717.2 DAE SPORTS AND CULTURAL MEET-2013 11717.3 INTERNATIONAL WOMEN’S DAY CELEBRATION 118

CHAPTER 18 DEPUTATIONS ABROAD 119

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INDEX TO TABLESTable No. Title Page No

2.1 Meetings of Safety Review Committees of Nuclear Power Projects and Nuclear Fuel 15 Cycle Facilities during year 2013-14

2.2 Categorization of RI Observations 20

2.3a Regulatory Inspection recommendations of Nuclear Projects in 2013-14 with Status of resolution 21

2.3b Status of resolution of RI recommendations of Nuclear Projects for the Year-2012-13 21

2.4 Meetings of Safety Committees 21

2.4a Categorization of Recommendations made During Scheduled Regulatory Inspections 28 (April 2013 to March 2014)

2.4b Status of resolution of RI recommendations (Category-I, II & III) of Operating NPPs 30 for the previous year (Year-2012-13)

2.5 Licensing of Operating Staff 30

2.6 INES Rating of Significant Events in NPPs during the last five years 31

2.7 Meetings of Safety Review Committees of Fuel Cycle Facilities 32

2.8a Categorization of Deficiencies Observed During Scheduled Regulatory Inspections of 37 Fuel Cycle Facilities and DAE accelerator units (April 2013 to March 2014)

2.8b Status of resolution of RI recommendations (Category-I, II & III) of Fuel Cycle Facilities 38 and DAE accelerator units for the Year-2013-14

4.1 Comparison of Incidence Rates of DAE Units with Equivalent Non-DAE Industries 57

5.1 Radiation Doses Received by Workers in NPPs (2013) 66

5.2 Radiation Doses Received by Workers in Front End Fuel Cycle Facilities 67

5.3 Radiation Doses Received by Workers in Medical, Industrial and Research Institutions (2013) 68

6.1 Site and Off-site emergency Exercises conducted in 2013 69

8.1 New Research Projects Approved 87

8.2 Research Projects Renewed 87

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INDEX TO FIGURESFigure Title Page No No.

2.1 INES Rating of Significant Events in NPPs during the year 2013 31

2.2 System-wise Classification of SERs in NPPs during the year 2013 31

4.1 Distribution of Reportable Injuries in DAE units in 2013 55

4.2 Distribution of Man-days Loss in DAE Units in 2013 55

4.3 Injury Index in DAE Units in 2013 56

4.4 Frequency Rates in DAE Units in 2013 56

4.5 Year wise comparison of Injury Index in DAE Units 56

4.6 Distribution of Injuries due to Unsafe Acts in DAE Units-2013 57

4.7 Distribution of Injuries due to Unsafe Conditions in DAE Units- 2013 57

4.8 Distribution of Injuries with respect to Type of Accidents causing Injuries in DAE units-2013 58

5.1a Liquid waste Discharges from NPPs (Tritium) 61

5.1b Liquid waste Discharges from NPPs (Gross Beta) 62

5.1c Gaseous waste Discharges from NPPs (Tritium) 62

5.1d Gaseous waste Discharges from NPPs (Argon-41) 63

5.1e Gaseous waste Discharges from NPPs (Fission product Noble Gas) 63

5.1f Gaseous waste Discharges from NPPs (Iodine-131) 64

5.2a Public Dose at 1.6 Km Distance for NPPs (AERB prescribed Annual Limit is 1000 micro-sievert) 64

5.2b Total Effective Dose in Different Zones during the year-2013 65 (AERB prescribed Annual Limit is 1000 micro-sievert)

5.3 Collective Dose (Person-Sv) at NPPs 66

5.4 Collective Dose ( Person-Sv) at FCFs 67

8.1.1 Primary pressure during SBO 75

8.1.2 Primary pressure during MSLB 75

8.2.1 Containment Pressure 76

8.2.2 Ternary Diagram for Case 2 76

8.3.1 Hot leg temperature 77

8.3.2 Cold leg temperature 78

8.9.1 FE model of the structure 82

8.9.2 Pushover curve of the structure 82

8.11.1 Sector-wise information given in the NEMIS for Kalpakkam site 83

8.11.2 Morphological changes along northern end of the canal due to the 84 construction of engineered discharge canal

9.1 RTI queries replied during the last 7 years 90

12.1 Year wise Manpower Augmentation in AERB 99

Highlights of AERB Activities at a Glance

During the year, Atomic Energy Regulatory Board continued its regulatory safety oversight on Indian operating nuclear power plants (20 units), nuclear power projects (6 units under construction and 1 unit under commissioning), several fuel cycle facilities, research units and large numbers of radiation facilities spread over the country.

All operating nuclear power plants and fuel cycle facilities under AERB’s purview operated safely during the year; radioactive discharges as well as doses to occupational workers were well within prescribed limits.

Significant progress was achieved in the commissioning of Unit 1 of Kudankulam Nuclear Power Plant (KK-NPP). AERB granted clearance for First Approach to Criticality of KK-NPP Unit 1 on July 4, 2013 and Unit achieved first criticality at 2305 hrs on July 13, 2013. Subsequently, various low power physics tests were conducted to establish nuclear characteristics, efficiency of reactor control & protection and associated safety systems. All the test results were reviewed and based on satisfactory review, clearance was given on August 14, 2013 to raise reactor power up to 50% Full Power (FP) & synchronize unit.

The reactor power was raised gradually in steps and unit was synchronized successfully with grid on October 22, 2013 at ~150 MWe. Various tests were conducted during power operation at 40% FP and 50% FP. Based on satisfactory review of test results and plant performance; clearance was given on January 24, 2014 to raise power up to 75% FP. Subsequently, reactor power was raised up to 75% FP and various tests were conducted as per approved procedure. Prototype Fast Breeder Reactor (PFBR) project is in the advanced stage of construction with civil construction, erection of equipment and components nearing completion. Majority of the equipment below roof slab and inside Main Vessel have been erected. Commissioning review related to pre operational activities is in progress.

AERB continued the detailed design safety review of the indigenously designed 700 MWe Pressurized Heavy Water Reactors, Rajasthan Atomic Power Project (RAPP-7&8) and Kakrapar Atomic Power Project (KAPP-3&4), being constructed in Rajasthan and Gujarat respectively. Review is in progress towards granting clearance for the last sub-stage of construction i.e. Major Equipment Erection at KAPP-3&4. For RAPP-7&8, construction of safety and non-safety buildings is in progress.

AERB continued to monitor the progress of safety enhancements at operating NPPs post Fukushima accident.. After detailed review of the mandated documents, license for operation of NAPS and KGS-3&4 were renewed for another 5 years. Pending implementation of the safety measures/upgrades identified post Fukushima, AERB extended the license for operation of MAPS-1&2 and TAPS-1&2 up to June 30, 2014 and December 31, 2014 respectively. The licenses for operation of TAPS-3&4 and RAPS-3&4 were extended up to August 31, 2016 and October 31, 2017 respectively. AERB has issued license for operation to COmpact Reprocessing of Advanced fuels in Lead cell (CORAL) facility of IGCAR. AERB has also granted permission for regular operation of Resin Fixation Facility (RFF) at TAPS-1&2.

For fuel cycle facilities, AERB continued to exercise its regulatory oversight over the operating uranium mines and mills, thorium mines and mills, fuel fabrication facilities and also the heavy water plants. Exhaustive review and assessment were carried out for various projects which are under different stages of consenting. After ensuring the regulatory requirements, AERB issued clearances for many of these ongoing projects. Commissioning of Tummalapalle mill was achieved during the year 2013-14. License for enhancing the uranium ore production capacity of Turamdih mine from 550 to 1000 TPD was issued. Consent for commissioning of Monazite Processing Plant (MoPP) at IREL OSCOM to produce Uranium, Throium and Rare Earths, consent for commissioning and operation of New Oxide Chlorination Facility at NFC, Hyderabad were issued.

With regard to radiation facilities, the consenting process takes cognizance of the diverse facilities in huge numbers with varying hazard potential. As a part of its e-Governance initiative, AERB has undertaken a project for developing a web-based Information and Communication Technology application called “e-Licensing of Radiation Applications (e-LORA)”. e-LORA portal began functioning on May 3, 2013, with its first module as radiation professional registration. Subsequently e-LORA was made operational for the Radiotherapy and Diagnostic Radiology modules.

AERB continued to pursue safety studies and research activities on important areas of nuclear, industrial and radiation safety to enable independent assessment and facilitate regulatory decisions during the licensing process. AERB promoted safety research activities relevant to regulatory issues at other academic institutes as well.

Towards improving technical co-operation with other international regulatory bodies in the field of nuclear and radiation safety, AERB signed a bilateral arrangement with the United State Nuclear Regulatory Commission (USNRC) on October 9, 2013 for the exchange of technical information and cooperation in nuclear safety matters. India has decided to host the Integrated Regulatory Review Service (IRRS) of IAEA and invited IAEA to review the activities of AERB in respect of the regulatory system and activities related to safety of Nuclear Power Plants in India. AERB has been augmenting its trained manpower by 5% increase during the year in view of the increasing regulatory requirements due to expansion of the Indian nuclear power programme and increasing number of radiation facilities in the country.

Shri S. S. BajajCHAIRMAN, AERB

Shri S. DuraisamyVice Chairman, AERB &

Chairman, SARCOP

Prof. Harsh GuptaMember,

National Disaster Management Authority New Delhi

Prof. Devang V. KhakharDirector

Indian Institute of Technology, Bombay

Dr. G. K. RathProfessor and Head,

Department of Oncology AIIMS, New Delhi

Shri R. BhattacharyaSecretary

Director, Information and Technical Services Division & Director, Industrial Plants Safety Division, AERB.

Dr. K. V. RaghavanDistinguished Professor,

INAE Indian Institute of Chemical Technology Hyderabad

MEMBERS

1

COMPOSITION OF THE BOARD

ORGANISATION CHART OF AERB

ATOMIC ENERGY REGULATORY BOARD

Safety Review Committee for Operating Plants

(SARCOP)

Project Safety Review Committees

AdvisoryCommittees

Safety Research Institute(SRI), Kalpakkam

Safety Review Committee for Application of Radiation

(SARCAR)

Operating Plants Safety Division (OPSD)

Nuclear Projects Safety Division (NPSD)

Industrial Plants Safety Division (IPSD)

Siting & Structural Engineering Division (SSED)

Radiological Safety Division (RSD)

Nuclear Safety Analysis Division (NSAD)

Information & Technical Services Division (ITSD)

Administration Division

Accounts Division

2

AERB continued to carry out the principal mandate of ensuring safety in all facilities and activities involving nuclear energy and ionizing radiation. AERB has been providing regulatory safety supervision of the nuclear power plants (20 operating, 6 under construction and 1 under commissioning), front and back end fuel cycle facilities, research facilities under its purview and radiation facilities which are using ionizing radiation sources in industry, medicine, agriculture & research. There has been no major safety related event in any of the nuclear and radiation facilities during the year.

AERB carried out its functions with the support of its secretariat and specialist committees under the guidance of the Board. The Board met two times during the financial year (2013-14): on May 27, 2013 and August 28, 2013 at AERB, Mumbai.

AERB Board Meeting in Progress (L to R: Shri R. Bhattacharya, Secretary, AERB, Shri S. Duraisamy, Vice Chairman, AERB,

Shri S. S. Bajaj, Chairman, AERB, Dr. K.V. Raghavan, IICT-Hyderabad, Prof. Harsh Gupta, NDMA, New Delhi, Prof. Devang V.Khakhar IIT-Bombay, Dr. G. K. Rath, AIIMS, New Delhi)

Safety Review of Nuclear Power Projects and Backend Facilities

The well-established practice of multi-tier review process was followed for safety review during various stages of projects namely siting, construction, commissioning and operational stage in all the Nuclear Power Projects (NPP) and Back End Fuel Cycle Facilities. The highlights of project safety reviews conducted during financial year 2013-14 are as follows:

Presently, seven NPPs are under various stages of construction and commissioning. Safety review towards commissioning of Kudankulam Nuclear Power Project KKNPP-1&2 was in progress AERB granted Clearance for First Approach to Criticality (FAC) of KKNPP Unit -1 on July 4, 2013 and Unit achieved first criticality at 2305 hrs on July 13, 2013.

3

CHAPTER 1

SUMMARY

4

Subsequently, various low power physics tests were conducted. Based on satisfactory review of test results, Clearance was given to raise reactor power up to 50% Full Power (FP) & synchronize unit with electrical power grid. The reactor power was raised gradually in steps and unit was synchronized successfully with grid on October 22, 2013. Various tests were conducted during power operation up to 40% FP. Based on satisfactory review of plant performance data and various test results, concurrence was given to raise power from 40 to 50% FP. After power raise, remaining tests were conducted and results were found satisfactory. Based on satisfactory review of test results, clearance was given on January 24, 2014 to raise reactor power up to 75% FP. Subsequently, reactor power was raised to 75% FP and various tests were conducted as per approved procedure.

Safety review of pre-commissioning activities on various systems in KKNPP-2 was in progress. After getting concurrence from AERB, structural integrity test & Integrated Leak Rate Test

(ILRT) for containment was taken up. Civil construction, erection of equipment and components were in progress for indigenously designed 500 MWe sodium cooled Prototype Fast Breeder Reactor (PFBR). Majority of the equipment below roof slab and inside Main Vessel have been erected. Commissioning review related to pre operational activities was in progress. Civil construction work for 700 MWe indigenously designed Pressurized Heavy Water Reactor (PHWR) was in progress for the twin units Kakrapar Atomic Power Project (KAPP)-3&4 and Rajasthan Atomic Power Project (RAPP)-7&8 projects. Review was in progress towards granting clearance for the last sub-stage of construction i.e. Major Equipment Erection at KAPP-3&4. For RAPP-7&8, clearance for second stage of construction i.e. First Pour of Concrete (FPC) was earlier granted in the year 2011. Construction of safety and non-safety buildings was in progress.

Kudankulam NPP Units - 1 & 2

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Safety review towards Clearance for Site Excavation for KKNPP-3&4 was in progress. Presently infrastructure development works were in progress at the site.

Four units of indigenously designed PHWR, each of 700 MWe are planned to be set up at Gorakhpur, Haryana. NPCIL application with relevant submissions for siting consent is under review by Site Evaluation Committee of AERB.

NPCIL has proposed to install progressively 6 units of Evolutionary Pressurized Reactor (EPR), each of 1650 MWe capacity, at Jaitapur Site on the western coast of Maharashtra. NPCIL application seeking siting consent for Jaitapur Nuclear Power Project (JNPP) - 1 to 6 was under review with Site Evaluation Committee (SEC) of AERB.

Safety review of indigenously designed back end fuel cycle facilities namely, Demonstration Fast Reactor Fuel Reprocessing Plant (DFRP) and Fast Reactor Fuel Cycle Facility (FRFCF) was in progress. AERB granted clearance for construction of FRFCF on September 12, 2013.

Safety Review of Operating NPPs and Research Reactors

All operating nuclear power plants and research reactors under AERB’s purview operated safely during the year.

Subsequent to the accident at Fukushima NPPs, Japan due to earthquake followed by tsunami on March 11, 2011, both AERB and NPCIL had independently carried out safety assessment of Indian NPPs. The details of these assessments were brought out in the annual reports

of AERB for the years 2011-12 and 2012-13. Based on these reviews, a number of measures/safety upgrades were identified for strengthening the safety of nuclear power plants. These measures were categorized into short term, medium term and long term, with respect to time frame for implementation. AERB is closely monitoring the progress of safety enhancements at operating NPPs. Many of the measures have been implemented and actions are in advance stages for the implementation of remaining measures in time bound manner. The status on implementation of upgrades is given in Chapter 2.

AERB has carried out detailed review of the mandated 10-yearly Periodic Safety Review (PSR) report submitted by Narora Atomic Power station (NAPS) and Application for Renewal of License (ARL) for operation submitted by Kaiga Generating Station (KGS)-3&4. The operational and safety performance of these plants were satisfactory during the reporting period. Based on the satisfactory review, license for operation of these plants have been renewed for another 5 years.

Pending implementation of the safety measures/upgrades identified post Fukushima, AERB had earlier extended the license for operation of MAPS-1&2, RAPS-3&4, TAPS-1&2 and TAPS-3&4 for a limited period rather than for the full 5-year term. The applications for extension of license for operation of these plants were reviewed. Based on the review, license for operation of MAPS-1&2 and TAPS-1&2 was extended again for shorter durations upto June 30, 2014 and December 31, 2014 respectively. The license for operation of TAPS-3&4 and RAPS-3&4 was extended upto

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August 31, 2016 and October 31, 2017 respectively. AERB reviewed Periodic Safety Review (PSR) report of Fast Breeder Test Reactor (FBTR). Pending resolution of some identified issues including safety upgrades identified post Fukushima accident, AERB granted permission for operation of FBTR for limited period. Subsequently, FBTR has submitted progress report on resolution of the pending issues identified during PSR. Based on the satisfactory PSR and action plan submitted for resolution of identified issues & implementation of necessary upgrades, AERB issued the license for operation to FBTR for 5 years.

On recommendation of SARCOP, an application seeking license for operation in line with the requirements specified by AERB was submitted by CORAL (Compact Reprocessing of Advanced fuels in Lead cell), IGCAR. Based on satisfactory review of the application, AERB has issued license for operation to CORAL facility of IGCAR. AERB has also granted permission for regular operation of Resin Fixation Facility (RFF) at TAPS-1&2. During the reporting period, a total of 33 significant events were reported from operating NPPs. Out of these, 1 event was rated at level 1 (anomaly) on International Nuclear Events Scale (INES). Remaining 32 significant events were rated at level 0 (deviations below scale) on INES.

During the period from April 2013 to March 2014, a total of 47 inspections were carried out in the operating NPPs and research facilities, out of which 26 were scheduled inspections and

21 were special inspections. Special inspections included unannounced inspections of NPPs & research facilities and inspections during biennial shutdown of NPPs to monitor the compliance to the radiation protection aspects, inspection carried out to check site emergency preparedness aspects etc.

The radioactive releases from NPPs were within the limits of technical specifications for operation approved by AERB. Effective dose to public around all NPP sites was far less than the annual limit of 1 mSv (1000 micro-Sievert) prescribed by AERB. The individual radiation dose among occupational workers during the year 2013 was well below the prescribed limit of 30 mSv/yr, with maximum individual radiation dose as 15.79 mSv/yr.

In the year 2013, Off-Site Emergency Exercise (OSEE) was conducted at all NPP sites except KKNPP where it was conducted in the year 2012. Site Emergency Exercise (SEE) was conducted at all NPP sites. AERB officials carried out special regulatory inspections on emergency preparedness aspects and participated in OSEE as observers.

India is signatory of IAEA convention on ‘Early Notification of Nuclear Accidents and Assistance in case of Nuclear Accident of Radiological Emergency’. AERB officials participated in Emergency Exercises Conducted by IAEA. Safety Review of Nuclear Fuel Cycle Facilities, R&D and Other Facilities

The Nuclear Fuel Cycle and Research & Development (R&D) facilities namely atomic

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minerals exploration units of Atomic Minerals Directorate for Exploration and Research (AMD), mines & uranium ore processing mills of Uranium Corporation of India Ltd. (UCIL), thorium mining, mineral separation plants & mills of Indian Rare Earths Ltd. (IREL), Nuclear Fuel Complex (NFC) at Hyderabad, Zirconium Complex (ZC) at Pazhayakayal, Heavy Water Plants (HWP), diversified projects of Heavy Water Board, radiological safety surveillance on the industries handling Naturally Occurring Radioactive Materials (NORMs), R&D units at Variable Energy Cyclotron Centre (VECC), Raja Ramanna Centre For Advanced Technology (RRCAT) and industrial units at Electronics Corporation of India Limited (ECIL) operated safely during the year.

Safety review of projects & operating plants of these units were carried out with respect to both radiological & industrial safety aspects.

All the uranium mines and mills of UCIL operated safely. Commissioning of Tummalapalle mill, which is one of the major milestones in the front-end fuel cycle facilities with alkaline leaching of ore for the first time was achieved during the year. AERB granted license for enhancing the uranium ore production capacity of Turamdih mine from 550 to 1000 TPD.

Rare Earths Division and Mineral separation plants of IREL operated safely. AERB continued to monitor the activities of IREL with special focus on long-term management of thorium oxalate and recovery of uranium. AERB granted consent for commissioning of Monazite Processing Plant (MoPP) at IREL

OSCOM to produce Uranium, Throium and Rare Earths.

The Nuclear Fuel Complex at Hyderabad and Zirconium Complex at Pazhayakayal operated safely.Pending implementation of some of the AERB recommendations, AERB had earlier extended the licence for operation of NFC, Hyderabad for a limited period instead of 5 years duration Based on satisfactory resolution of the safety issues, the license for operation of NFC, Hyderabad was further renewed for the remaining period by AERB.

Application seeking consent for commissioning and operation of New Oxide Chlorination Facility at NFC, Hyderabad was reviewed by AERB. Based on the detailed review and compliance of recommendations, consent for commissioning and operation of New Oxide Chlorination Facility at NFC, Hyderabad was issued by AERB. The application for siting of a new project of 500 TPA PHWR fuel fabrication facility and 65 TPA of Zircaloy Fabrication Facility at Rawatbhata, Kota was submitted by NFC, which is under review by AERB. Safety review of Heavy Water Plants at Kota, Manuguru, Hazira and Thal engaged in production of heavy water continued. All these plants operated safely during the year. HWP-Kota completed its in-depth inspections of equipment/piping during the major turnaround. The inspection results indicated satisfactory safety margins in the critical equipment/piping.

The production of Heavy

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Water at HWP Baroda, Tuticorin and Talcher continued to remain suspended due to non-availability of feedstock from the connected fertilizer plants, however they are engaged in production of organic solvents and other diversified activities. AERB granted consent for commissioning and operation of 2000-Ampere sodium test cell at HWP-Baroda.

HWP Manuguru is also engaged in diversified activities besides heavy water production. Consent for siting and construction of O18 plant at HWP - Manuguru was granted. Authorization for operation of Boron Enrichment Plant (BEP) at HWP - Manuguru was extended for a period of 2 years by AERB.

AERB continued its radiological safety surveillance on facilities handling Beach Sand Minerals and other Naturally Occurring Radioactive Materials. The operational & project safety reviews of R & D units at VECC, RRCAT and industrial units at ECIL continued. AERB granted consent for commissioning of 5 MeV Linear Accelerator at Industrial & Medical Accelerator building and consent for siting and construction of 1 PW (Peta Watt) laser system at RRCAT, Indore. Consent was also granted by AERB for operation of thermal battery division at ECIL, Hyderabad based on the satisfactory resolution of the safety issues.

Industrial Safety AERB is responsible for administration of the Factories Act, 1948 and the Atomic Energy (Factories) Rules, 1996 in all the units of DAE under its purview. AERB deals with the

industrial and fire safety aspects during stage-wise consenting process, inspections and document development. AERB also focuses on the construction safety aspects of nuclear projects by carrying out special monthly inspections of nuclear power projects and quarterly inspection of other nuclear facilities under construction. The fire safety aspects of the nuclear facilities are verified by checking the compliance with the requirements of AERB Safety Standard on ‘Fire Protection Systems for Nuclear Facilities’ and periodic review of Fire Hazard Analysis of the facilities.

For nuclear fuel cycle facilities, R&D units and other facilities, a total of 135 regulatory inspections were conducted during the year with respect to radiological, industrial and fire safety aspects. Apart from the regulatory inspections of nuclear power projects, operating nuclear power plants, operating nuclear fuel cycle facilities, R & D and other facilities on yearly & half yearly basis, additional 43 industrial safety focused monthly inspections at construction sites of nuclear power projects, 4 quarterly inspections of nuclear fuel cycle facilities construction sites, 6 special regulatory inspections and 2 security inspections were carried out. There were 4 fatalities during the financial year 2013-14. These were due to electrocution at KKNPP-1&2, fall of object during handling at KAPP-3&4, fall from height each at RAPP-7&8 and UCIL-Turamdih & Jaduguda mills. These accidents were investigated and reviewed by AERB in various committees before resuming further work and recommendations to prevent

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recurrence of such incidents were disseminated to all DAE units.

Safety Review of Radiation Facilities AERB carried out safety review of various facilities using radiation sources and issued 2075 consents (license, authorization and registration) for operation, 105 type approvals, 1105 approval of radiation safety officers for different practices and 2390 permissions for procurement of radioactive sources (imported & indigenously manufactured). During this period, AERB has carried out safety review of proton therapy facility which is a new modality in Radiotherapy.

AERB carried out regulatory inspections of 711 different radiation facilities, which is higher than last year. The Directorate of Radiation Safety and Radiation Safety Agency in Kerala and Mizoram have also carried out a substantial number of inspections. AERB investigated 4 unusual occurrences related to loss/ misplacement of radiation sources.

Towards streamlining the regulation of X-ray based diagnostic radiology practice; AERB has focused on a) building of infrastructure b) Optimising requirements to utilities c) Spreading of awareness.

AERB has accredited four laboratories involved in measurement of radioactivity contents in commodities, environs, packaged drinking water, etc. and laboratories involved in the calibration of radiation survey meters & pocket dosimeters subject to fulfillment of requirements in the AERB document titled “Accreditation

of Laboratories for Measurement of Radionuclide Content in Commodities, 2003”. AERB has investigated certain incidents of radioactive contamination (due to Co-60) in the stainless steel (SS)/brass in items exported to various countries from India. Though the source of this contamination is not clear, AERB has initiated various actions such as co-ordination with other Ministries/Governmental agencies, international co-ordination with respect to radioactive contamination in the scrap material, organised public awareness programmes on brass/steel contamination with emphasis on the need for installation of portal monitors at import points. AERB has signed a MoU with National Institute of Secondary Steel Technology (NISST) to disseminate information on steel contamination, amongst stake holders like recycling industries.

e-Governance Initiatives As a part of its e-Governance initiative, AERB has undertaken a project for developing a web-based Information and Communication Technology application called “e-Licensing of Radiation Applications (e-LORA)” envisaging automation of the regulatory processes for various Radiation Facilities located across the country with the objective to enhance the efficiency and transparency in the regulatory processes. e-LORA portal began functioning on May 3, 2013, with its first module as radiation professional registration. Subsequently e-LORA was made operational for the Radiotherapy and Diagnostic Radiology modules. For the Diagnostic radiology facilities, as of March 31,

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2014, the new utilities could obtain Registration for operation of their equipment; the existing utilities could declare their equipment and for those who already have obtained a valid license record the x-ray equipment, all through e-LORA. Thus, as on March 31, 2014, around 228 “Registrations” were issued through e-LORA, around 2562 equipment were declared.

Safety Document Preparation AERB develops safety documents, which include Safety Codes (SC), Safety Guides (SG), Safety Manuals (SM) and Technical Documents (TD) for nuclear and radiation facilities such as siting, design, operation and quality assurance of nuclear power plants, radiation protection and radioactive waste management of nuclear and radiation facilities.

During the year, 3 new safety documents were published, 5 were under development and 17 documents were translated into Hindi. As of now, AERB developed 144 regulatory safety documents for nuclear and radiation facilities including industrial safety.

International Cooperation

AERB recognizes international cooperation as a measure for enhancing effectiveness of regulatory system and harmonizing international regulatory practices and accords due importance to the same During the period, AERB took several initiatives to enhance its contribution towards harmonization of international regulatory practices and methodologies and continued

its participation in various international forums.

AERB organized a IAEA workshop at Mumbai during November 4-8, 2013 with wide participation from utilities and technical support system in addition to AERB officials. The participants were introduced to the concepts and methodologies associated with International Reporting System (IRS) for operating experience, Root Cause Analysis (RCA) and Corrective Actions (CA) techniques. The importance of systematic and in-depth root cause analysis was emphasized.

The 20th annual meeting of the VVER Regulators Forum was hosted by AERB in India during December 11 - 13, 2013. This Forum consists of the nuclear regulators of countries operating reactors of Russian VVER design and aims at sharing the operating experience and harmonizing the regulatory practices followed for VVERs. Participating members shared the operating experience of VVERs in their countries which helped all the members learn from the incidents discussed. The members got an opportunity to visit the KKNPP site, where one unit was under commissioning and the other unit was under construction.

AERB continued to participate in the meetings and discussions at IAEA on the various issues related to NPPs. AERB also actively contributes to the different Working groups of Nuclear Energy Agency (NEA) and Multinational Design Evaluation Programme (MDEP).

The 6th review meeting of the Convention on Nuclear Safety (CNS) was held at IAEA, Vienna

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during March 24-April 4, 2014, in which the Indian delegation led by Chairman, AERB. Mr. S.S. Bajaj presented its national report covering the safety aspects on design, construction, commissioning and operation of Indian NPPs, status on challenges and planned measures identified during the earlier review meetings, apart from commitment of planned measures and challenges for future. Post Fukushima safety enhancements in Indian NPPs and followup of their implementation were appreciated during the review meeting of CNS. AERB signed a bilateral arrangement with the United State Nuclear Regulatory Commission (USNRC) on October 9, 2013 for the exchange of technical information and cooperation in nuclear safety matters. The bilateral meetings between AERB and USNRC were taking place earlier also under the technical cooperation program. This formal agreement signed now will further strengthen the

Participants of VVER Forum Meeting held in Kanyakumari, Tamil Nadu, India(Shri S. S. Bajaj, Chairman, AERB is present along with foreign participants from

VVER Forum and other senior AERB officials)

technical cooperation between the two countries. AERB has also similar arrangements with other international regulatory bodies of France, Russia, Romania and Ukraine.

Integrated Regulatory Review Service (IRRS) of IAEA

It has been decided to get the indian nuclear regulatory system peer reviewed by international experts through IRRS of IAEA. In this regard, a request has been made to IAEA and peer review mission is expected during March 2015. The peer review under IRRS is carried out by an international team comprising senior regulators with broad knowldge of the regulation of nuclear and radiation safety from different countries and extensive experience in specialized areas. AERB has taken steps for self assessment as input for the peer review. A preparatory meeting will be held in octomber, 2014 for further interaction between AERB and IAEA officials.

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Research & Development (R&D) and Safety Studies

In the area of R&D and safety studies towards regulatory support, important studies like reactor physics involving KK-NPP startup and low power physics experiments, severe accident studies, Hydrogen distribution and containment safety studies, thermal hydraulic safety studies, fire safety studies, structural and seismic analysis, radiological assessment studies, environmental safety studies, etc. were carried out.

AERB continued to promote and fund several research projects on reactor safety, radiation safety, front end and back end fuel cycle safety related problems and industrial safety at various reputed universities and academic institutions under the Committee for Safety Research Programme (CSRP).

Human Resource Development

AERB has augmented the technical manpower substantially by inducting postgraduates through AERB Graduate Fellowship Scheme (AGFS) at IIT-Bombay and IIT-Madras, and through training schools of BARC, IGCAR, and NFC. The manpower in AERB has increased from 310 (251 scientific & technical and 59 supporting staff) to 326 (264 scientific & technical and 62 supporting staff) during April 2013 to March 2014.

AERB continued to trainits staff by organizing various training programmes, workshops, on the job training at sites etc. Orientation Course for Regulatory Processes for Safety Research Institute (OCRP-2014) was conducted for the scientists/engineers newly inducted in AERB and nominated scientific staff from technical divisions of AERB. AERB has provided guidance to young engineering students to share its expertise distribution in containment, Hydraulic transients in an Adiabatic closed loop system, development & application of Probalistic Safety Analysis methodologies for estimating risk in nuclear systems, Hazards and Operability (HAZOP) studies, during summer internships of engineering students from various reputed academic institutions.

AERB Awards

AERB has awarded some of its officials under various categories for outstanding achievements to promote excellence in the regulatory activities. AERB award scheme comprised 8 individual awards in addition to group achievement awards. Awards for the year 2012-13 were distributed during the Annual Day Celebrations of AERB held on November 23, 2013.

AERB Bulletin

AERB continued its initiatives to publish popular

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versions of annual report, in an understandable and public friendly format “AERB BULLETIN” in different regional languages, to enhance transparency and openness and reach out to larger public more effectively. The bulletin presents information contained in the Annual Report and was published in English and Hindi, Marathi and Tamil.

Press Conference

A press briefing was arranged on Dec.13, 2013 in Kanyakumari, which was addressed by Shri S.S. Bajaj, Chairman AERB. The other senior

AERB officials present during the press briefing included Shri S. Duraisamy, Vice Chairman AERB; Shri R. Bhattacharya, Secretary AERB; Shri K.J. Vakharwala, Director NPSD and Shri P.R. Krishnamurthy, Director OPSD. Chairman AERB briefed the media about the VVER Forum and its establishment in 1993 by the regulators of 11 countries operating the nuclear power plants of Russian VVER design. He informed the media that the main aim of this Forum was to harmonize the regulatory practices and sharing experiences of VVER reactors.

Shri S. S. Bajaj, Chairman, AERB addressing the Press Conference at Kanyakumari, Tamil Nadu, India

(L to R: Shri P. R. Krishnamurthy, Director, OPSD, Shri S. Duraisamy, Vice-Chairman, AERB, Shri S. S. Bajaj, Chairman, AERB, Shri R. Bhattacharya, Secretary AERB & Director, IPSD and ITSD,

Shri K. J. Vakharwala, Director, NPSD)

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CHAPTER 2

SAFETY SURVEILLANCE OF NUCLEAR FACILITIES

2.1 NUCLEAR POWER PROJECTS

2.1.1 Project Safety Review

The well-established practice of multi-tier review process was followed for safety review during various stages of projects namely siting, construction, commissioning and pre-operational stage in all the Nuclear Power Projects (NPP) and Back End Fuel Cycle Facilities. The first tier review is carried by Site Evaluation Committee (SEC), Project Design Safety Committee (PDSC), Civil Engineering Safety Committee (CESC) and associated Specialist Groups (SGs)/ Task Forces (TFs)/ Working Groups (WGs). In the case of KKNPP-1&2, SGs carried out the first-tier design safety review. For commissioning phase of these Units, additional Specialists Groups have carried out in-depth safety review of various commissioning procedures and performance of various systems and commissioning reports. Apart from the above, various In-House Review Groups (IHRGs) conducted detail technical reviews of all the submissions and provided comments before review by respective safety committees/SGs/WGs.

The second-tier review is performed by respective Advisory Committee for Project Safety Review (ACPSR), which includes members from Academic Institutes, Experts retired from DAE units, specialist members from the Ministry of Environment & Forests, Central Boilers Board, Central Electricity Authority and members from AERB, BARC, IGCAR and NPCIL.

The third-tier review is carried out by the Board of AERB.

The safety review process is supplemented by periodic Regulatory Inspections (RI) as per the established practice. Compliance with the requirements recommended by the safety committees and those specified in various codes, standards and guides of AERB are verified during periodic RI. Safety significant observations from RI are reviewed in safety committee and are considered before giving clearance for subsequent stages.

Table 2.1 lists the number of meetings held by first and second tier safety committees during the year 2013-14. In addition, a large number of meetings of SGs, TFs and WGs constituted by SEC/ PDSC/ CESC/ ACPSR/ AERB were held for in-depth review of specific aspects of the projects.

Table 2.1: Meetings of Safety Review Committees of Nuclear Power Projects and Fuel Cycle Facilities during the year 2013-14

Project Safety Committee Number of Meetings

ACPSR - LWR-1 17ACPSR - LWR-2 NilACPSR ( PHWR/PFBR) 2ACPSR - FRFCF 1PDSC (KAPP-3,4 & RAPP-7,8) 11PDSC (KKNPP 3&4) NilPDSC (PFBR) 3PDSC (DFRP) NilPDSC (IFSB) ** NilPDSC (FRFCF) 1SEC (JNPP) 3SEC (GHAVP) 2CESC 7

** Process of taking over of safety review of IFSB by SARCOP is in progress.

The status of safety review of various projects and some salient observations/ recommendations made during the review are given in the subsequent paragraphs.

(1) Kudankulam Nuclear Power Project (KKNPP) – 1&2

KKNPP-1:

AERB granted Clearance for First Approach to Criticality (FAC) of KKNPP Unit -1 on July 4, 2013. Unit-1 achieved first criticality on July 13, 2013 at 2305 hrs. Subsequently, various low power physics tests were conducted to establish nuclear characteristics, efficiency of reactor control & protection and associated safety systems. All the test results were reviewed in SGs/ACPSR-LWR-1. Based on satisfactory review of the test results, Clearance was given on August 14, 2013 to raise reactor power up to 50% Full Power (FP) & synchronize unit with grid.

The reactor power was raised gradually in steps and unit was synchronized successfully with grid on October 22, 2013 at ~150 MWe. Initially, various tests were conducted during power operation up to 40% FP. Based on satisfactory review of plant performance data

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and various test results by ACPSR, concurrence was given to raise power from 40 to 50% FP. After power raise, remaining tests namely power failure, turbine trip tests, natural circulation test and reactor physics related tests etc were conducted and results were found satisfactory. As part of the next stage of commissioning, NPCIL application along with test results & plant performance report were reviewed and clearance was given on January 24, 2014 to raise Reactor Power up to 75% FP. Subsequently, Reactor power was raised up to 75% FP and various tests were conducted as per approved procedure. AERB Observer Teams (AOTs) were deputed regularly to KKNPP Site for physical verification of various compliances and witness the various tests. The reports sent by AOT were reviewed in-house as well as in SGs/ACPSR for necessary follow up.

Turbine Generator Unit in KKNPP-1

KKNPP-2:

Pre-commissioning activities were under progress. After getting concurrence from AERB, structural integrity test & ILRT for containment was done. AERB observers were posted at site. Detailed reports of results for the containment related tests are to be submitted by NPCIL for review by AERB committees.

Some of the salient observations/recommendations made during safety review of KKNPP-1 are given below:

a) Containment box-up logic test was satisfactorily conducted. While normalizing the system after test, two valves of containment isolation system did not open. The deficiency was rectified and valves were re-tested and found to be operating satisfactory.

b) One of the ventilation system fans got damaged due to failure of tack weld of an additional stainless component attached to counter-weight of discharge damper. Corrective action was done by stitch welding. Indication was also made

available in main control room for fan/damper. The same was reviewed and found acceptable.

c) As part of Phase-B commissioning activity, Natural Circulation test was done at 2% and 5% full power. Primary Natural Circulation (NC) Test demonstrated the plant capability to cool the core by NC in primary without aid of forced coolant flow .The test results were reviewed and found satisfactory.

d) During one of the reactor trip event, it was

observed that all the Atmosphere Steam Dump (BRU-A) valves opened in cool down mode resulting in primary system cooling at a rate higher than 60°C/hr. Modifications were made in BRU-A interlock such that valves will start closing whenever cool down rate exceeds 60°C/hr. This logic change and implementation was reviewed and found acceptable.

e) Reactor tripped on Emergency Protection (EP) actuation on apparent high Linear Heat Generating Rate (LHGR) values due to non-correction of related coefficients while stabilising reactor power to ~50% FP. The uncorrected coefficients were resulting in high calculated LHGR values than actual expected values, leading to reactor trip. The coefficients were corrected, after which LHGR readings reduced to acceptable values. Subsequently, the reactor performance at 50% FP was stable and no LHGR trip occurred.

f) During performance test of Condenser Steam Dump system, feedback from positioned sensor mechanism (LVDTs) to dump valves controller were found fluctuating. Subsequently, feedback signal to the controller was changed from LVDT to control oil pressure of valve and performance of dump valve was found satisfactory during subsequent testing.

g) During testing of Passive Heat Removal

System (PHRS), outlet dampers were observed to be oscillating. A passive mechanism was introduced to latch-in the dampers once it opens. The modification was reviewed and found satisfactory.

h) Based on post Fukushima safety assessment, various activities related to safety enhancement were reviewed periodically. All short-term plans have been implemented at KKNPP Site before First Approach to Criticality. Preliminary analyses results for the items related to long-term action plan were under review.

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(2) Prototype Fast Breeder Reactor (PFBR)

The last phase of construction i.e. major equipment erection was at the advance stage of completion. Majority of the equipment below roof slab and inside Main Vessel have been erected and the reactor top is closed. Control and Safety Rod Drive Mechanisms & Diverse Safety Rod Drive Mechanisms have been erected. Reactor vault biological shield cooling system testing was completed. All the Intermediate Heat Exchangers have been erected. Works related to the primary and secondary sodium circuits and fuel handling systems are nearing completion. Both the primary sodium pumps are erected inside Main Vessel. Pre-commissioning activities were in progress. Some of the salient observations/recommendations made during the safety review are given below:

a) Analysis on the effect on Safety Grade Decay Heat Removal (SGDHR) performance due to the proximity of DG chimney to the Air Heat exchanger (AHX) of the SGDHR was reviewed. It was noted that there was no adverse effect on the heat removal capacity of SGDHR loop when DGs are in service.

b) Performance tests of primary sodium pumps at various speeds have been carried out at manufacturer shop. The test report was reviewed and it was found that the performance of the pump was meeting the design specification. Even though the vibration of pump was very low during the testing, it was recommended to measure the vibration readings at various temperatures and speeds during the integrated test of primary sodium pump and ensure that it is well within limits.

PFBR Caisson Top View

PFBR Overall Site View

c) Tests were carried out for seismic qualification of CSRDM with control and safety rod in water. The test results were reviewed and it was found that the overall performance during and after

the test was acceptable, the stresses were within allowable limits for OBE and SSE and the control rod drop time was within acceptable limits.

d) Implementation of the recommendations of the committee for review of design in the light of Fukushima event was in progress. Compliance to the recommendations is being reviewed

e) In situ concreting of Large Rotating Plug (LRP), Small Rotating Plug (SRP) & Roof Slab (RS) with heavy density concrete had been completed. It was noted that adequate care had been taken to ensure that the temperature of the concrete mix during this process were within limits.

(3) Kakrapar Atomic Power Project (KAPP-3&4) and Rajasthan Atomic Power Project (RAPP-7&8)

Detailed safety review of the indigenously designed 700 MWe PHWRs was in progress. The design of RAPP-7&8 is similar to KAPP-3&4, except for site specific changes.

Civil construction activities related to safety and non-safety buildings were in progress at KAPP 3&4. Major equipment like Calandria, End shield, Diesel Generator (DG), safety related pumps, heat exchangers etc have been received at Site. NPCIL Application for Major Equipment Erection was under review.

Civil construction activities of safety and non-safety buildings were in progress at RAPP-7&8. Major equipment like Calandria, Diesel Generators, safety related pumps etc have been received at Site.

Some of the salient observations/recommendations made during the safety review are given below:

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700 MWe End Shield received at KAPP-3, 4 Site

700 MWe Calandria Vault at RAPP-7 Site

a) Certain changes carried out in plant layout were

reviewed and found acceptable. For example, Induced Draft Cooling Tower (IDCT) basin water inventory volume, which is the Ultimate Heat Sink for KAPP-3,4 units, was marginally increased. DG chimney was shifted to ground supported independent structure. Also turbine position was slightly changed in the turbine building.

b) Implementation of the recommendations of the

committee for review of design in the light of Fukushima event was in progress. Compliance to the recommendations is being reviewed.

c) Experiments have been conducted to establish the performance of Passive Decay Heat Removal System (PDHRS) and results of the same were reviewed. For further experiment, review was in

progress.

d) Results of Containment Spray System (CSS)

mock up tests regarding spray coverage and droplet size measurement were reviewed. NPCIL will carry out analysis taking cognizance of these test results to check the efficacy of CSS for heat and iodine removal in containment during accident conditions. Additional experiments are being conducted at IIT Bombay for determining

capability of CSS for Iodine removal and pressure reduction in containment building.

e) Mock up tests were done to demonstrate

constructability of Fuel Transfer room using super heavy concrete (SHC) in KAPP-3&4 and RAPP-7&8. The results were reviewed for shielding adequacy and constructability aspect. Construction of FT Room was completed in KAPP-3&4 and was in progress in RAPP-7&8.

(4) Kudankulam Nuclear Power Project (KK NPP) - 3 to 6

Infrastructure development related activities at KKNPP 3&4 was in progress. Safety review of Preliminary Safety Analysis Report and submissions related to Excavation Clearance stage i.e. site-specific data, layout, geotechnical data, design basis ground motion, tsunami hazard assessment etc were in progress. The validity of the environmental clearance has been extended up to 22-09-2018 by Ministry of Environment and Forests (MoEF).

(5) Jaitapur Nuclear Power Project (JNPP) Six units of Evolutionary Pressurized Reactor (EPR), each of 1650 MWe are planned to be set up at Jaitapur Site on the western coast of Maharashtra. NPCIL Application and relevant submissions for Siting Consent for JNPP- 1 to 6 were under review in Site Evaluation Committee.

(6) Demonstration Fast Reactor Fuel Reprocessing Plant (DFRP)

DFRP is being set up at IGCAR Kalpakkam to reprocess the spent fuel from FBTR on regular basis and PFBR fuel on experimental basis. It consists of two facilities namely Head End Facility (HEF) and Process Plant Facility (PPF). Construction of PPF and erection of most of the major equipment have been completed and construction of HEF is nearing completion. Safety review related to pre-commissioning activities was in progress.

(7) Interim Fuel Storage Building (IFSB)

Subsequent to completion of safety review, AERB has given the clearance for regular operation of IFSB i.e. receipt, assembly and storage of PFBR fuel pins/ subassemblies. Further operational safety review was in progress.

(8) Fast Reactor Fuel Reprocessing Facility (FRFCF)

An integrated facility called Fast Reactor Fuel

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Reprocessing Facility (FRFCF) is being constructed at IGCAR Kalpakkam. The facility will be used for recycling the fuel from PFBR, including fuel fabrication & assembly, reprocessing and waste management. After detailed review of safety aspects, construction clearance of FRFCF was issued on September 12, 2013.

Some of the salient observations/recommendations made during the safety review are given below:

a) The Stacks are designed for keeping releases within limits in case of design basis events. IGCAR was asked to submit analysis report to ascertain margin considering credible Beyond Design Basis Event (BDBE).

b) As per recommendation by AERB, the Design Basis Flood Level (DBFL) of DG building and its auxiliary system have been revised to be in line with the other safety related buildings of FRFCF. It was noted that the design change does not affect any of the surrounding buildings of FRFCF.

c) Vitrified wastes are generally stored in tested and qualified canisters. However, IGCAR was asked to prepare a procedure for handling an event of an unlikely failure of canister and submit the same for review.

(9) Indigenously Designed 700 MWe PHWR NPPs – Gorakhpur, Haryana

Four units of PHWR, each of 700 MWe, are planned to be set up at Gorakhpur, Haryana. Application and relevant submissions for Siting Consent are under review in Site Evaluation Committee.

(10) Advanced Pressurized Water Reactor

(AP 1000) Project

For the proposed AP-1000 Reactors to be setup in India, General Technical Information on overall design and operational safety requirements of the proposed reactors is being reviewed.

2.1.2 Consents /Clearances /Permiss ions /Concurrence Issued

(1) Kudankulam Nuclear Power Project - 1&2

(KKNPP-1&2) KKNPP-1

• Concurrence for Installation and In-Situ Testing of Double Check Valve (DCV) of KKNPP-1 (April 20 and 29, 2013).

• Clearance for First Approach to Criticality and Phase-B Low Power Physics Experiments (July 4, 2013)

• Permission for First Approach to Criticality (July 11, 2013)

• Concurrence for Phase-B Low Power Physics Experiments (July, 14, 2013)

• Clearance for Raising Reactor Power up to 50% FP & Synchronization of Generator (August 14, 2013).

• Concurrence for Reactor Power Raise from 40 to 50 % FP (November 23, 2013).

• Clearance to raise Reactor Power up to 75% FP (January 24, 2014).

KKNPP-2

• Concurrence to conduct Containment test (January 18, 2014).

(2) Fast Reactor Fuel Reprocessing Facility (FRFCF):

• Clearance for Construction of FRFCF (September

12, 2013).

(3) Rajasthan Atomic Power Project (RAPP- 7&8)

• Permission for construction of Fuel Transfer Room using Super Heavy Concrete (July 31, 2013).

2.1.3 Regulatory Inspections of Projects

Regulatory Inspections (RI) of the Nuclear Power Projects were carried out as a safety audit measure to ensure compliance with the AERB safety requirements and stipulations. Emphasis was given on aspects related to Project Management, Quality Assurance, Equipment Storage & Preservation, Fabrication and Erection of major safety related components, Documentation, Commissioning activities, Radiological Monitoring and Emergency Preparedness. In addition compliance to previous RI recommendations was checked during every inspection. Observations made during the Regulatory Inspections of Nuclear Projects are broadly categorized adopting the graded approach for resolution of issues. Safety related RI observations were discussed in respective safety committees. Category I & II observations from these inspections were appropriately considered for enforcement measures and granting of the regulatory consents. Category III & IV issues are related to shortcoming noticed

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during construction and commissioning and are treated for quick resolution as per project schedule. Additionally, Category IV issues which are related mainly to procedural inadequacy are corrected by project management on priority for implementation. Compliance received within

one month for all such issues are verified during subsequent RI. Category V issues are mostly related to good housekeeping and most of the observations are complied during RI itself. Categories of RI observations are given in Table 2.2.

Table 2.2: Categorization of Regulatory Inspection Observations

Category Particulars

Category I • Violation of AERB safety directives and/or ACPSR/PDSC/CESC Stipulations/ Recommendations,

• Non-compliance with the Requirements of AERB Codes/Standards/Rules and other consent stipulations

• Deviations from Technical Specifications for Operation and Safety Report requirements during commissioning stage.

Category II • Deficiencies and degradations in systems/ structures/ components and deficiencies in preservation/ construction procedures/ practices /QA of safety and safety related systems

• Deficiencies in procedures and compliance with PSI requirements• Major Inadequacies and non-compliance in Emergency Preparedness during

construction / commissioning • Deficiencies in important procedures to meet Technical Specification for operation

requirements during commissioning stage• Observation/Recommendation requiring safety Review.

Category III • Shortcomings noticed in the design of safety, safety related and safety support systems, during construction / commissioning phase, including generic design deficiencies.

• Deficiencies in implementation of design, and/or lack of design provisions related to safety, safety related and safety support system.

Category IV Procedural inadequacies and non-compliance during construction/ commissioning:• Organizational• Managerial• Training & Qualification• Emergency Preparedness• QA of Non - Safety Related Systems

Category V General Observations/Deficiencies regarding• Housekeeping and• Good Practices

Compliance / response to RI observations / recommendations were required to be submitted by utilities within stipulated time period from the date of issuance of RI report. Safety related RI observations/recommendations were discussed in respective safety committees along with utility responses. Before granting of particular stage/sub stage consent, resolutions of all relevant RI observations / recommendations for the respective projects were considered.

Total 23 RIs of nuclear projects including one special RI of KAPP-3.4 were carried out during the year 2013-14. Total number of RIs and numbers of recommendations (categorywise) and their current resolution status are brought out in Tables 2.3 a.

Updated current resolution status of recommendations (category wise) of the RIs carried out for various projects during year 2012-13 is also brought out in Table 2.3 b.

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2.2 NUCLEAR POWER PLANTS AND RESEARCH REACTORS

2.2.1 Safety Status of Operating Plants

AERB carried out safety review and monitoring of operating NPPs and Research Reactors following three tier review process. The SARCOP (Safety Review Committee for Operating Plants), which is the apex committee for safety review of operating plants, held 14 meetings during the year 2013-14. Unit Safety Committees (USC) / standing committees established under SARCOP met a number of times to review safety related issues of individual plants or subject in detail. Number of meetings conducted by various safety committees / standing committees during the year 2013-14 is given in Table 2.4.

Table 2.3a: RI recommendations of Nuclear Projects in 2013-14 with Status of resolution

Project No. of RI Number of RecommendationsNumber of Recommendations resolved as on March 31, 2014

Cat. I Cat. II Cat. III Total Cat. I Cat. II Cat. III TotalKKNPP-1&2 4 0 10 45 55 0 1 18 19KKNPP-3&4 2 0 0 0 0 0 0 0 0KAPP-3&4 5 0 14 60 74 0 8 36 44RAPP-7&8 4 0 10 42 52 0 3 11 14PFBR 4 0 8 88 96 0 0 22 22DFRP 2 0 1 11 12 0 0 0 0FRFCF 2 0 0 3 3 0 0 0 0Total 23 0 43 249 292 0 12 87 99

Table 2.3b: Status of resolution of RI recommendations of Nuclear Projects for the Year 2012-13

Project No. of RI Number of RecommendationsNumber of Recommendations resolved as on March 31, 2014

Cat. I Cat. II Cat. III Total Cat. I Cat. II Cat. III TotalKKNPP-1&2 4 0 8 51 59 0 7 47 54PFBR 4 1 7 73 81 0 5 46 51KAPP-3&4 4 0 24 52 76 0 20 44 64RAPP-7&8 4 0 10 33 43 0 9 24 33KKNPP-3&4 2 0 1 0 1 0 1 0 1DFRP 2 0 0 9 9 0 0 0 0FRFCF 2 0 0 0 0 0 0 0 0Total 22 1 50 218 269 0 42 161 203

Table 2.4: Meetings of Safety CommitteesName of the Safety Committee No. of meetingsSARCOP 14TAPS-1&2 Safety Committee 13TAPS-3&4 Safety Committee 09RAPS-MAPS Safety Committee (RMSC) 09NAPS-KAPS Safety Committee (NKSC) 12KGS 1 to 4 and RAPS 3 to 6 Safety Committee (KRSC) 13IGCAR Safety Committee 9SARCOP Standing Committee – Reactor Physics (SC-RP) 7SARCOP Standing Committee on Control, Instrumentation & Computer based systems (SCCI&CS)

4

Expert Group on Coolant Channels 3CESCOP 2

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2.2.2 Consents / Clearances / Permissions Issued

During the year, a number of applications from the utilities were reviewed and several authorizations / clearances / permissions were issued. Important among these are:

• Extension of License for Operation of TAPS-1&2 up to December 31, 2014.

• Renewal of License for Operation of TAPS-3&4 up to August 31, 2016.

• Renewal of license for operation of RAPS-3&4 up to October 31, 2017.

• Renewal of License for Operation of NAPS up to June 30, 2018.

• Renewal of license for operation of KGS-3&4 up to April 30, 2018

• Issue of License for Operation to FBTR up to June 30, 2018.

• Issue of License for Operation to CORAL facility at IGCAR for one year i.e up to December 31, 2014.

• Permission for regular operation of Resin Fixation Facility (RFF) at TAPS-1&2

2.2.3 Operating Plants Safety Review

The safety status of individual NPPs and research reactors is described below:

(i) General

Safety assessment of operating Nuclear Power Plants (NPPs) in the wake of accidents at Fukushima Daiichi NPPs

Subsequent to the accident at Fukushima NPPs, Japan due to earthquake and tsunami on March 11, 2011, both AERB and NPCIL had independently carried out safety assessment of Indian NPP s. The details of these assessments were brought out in the annual reports of AERB for the year 2011-12 and 2012-13. Based on these reviews, a number of measures were identified for strengthening the safety of nuclear power plants. These measures were categorised into short term, medium term and long term, with respect to time frame for implementation. AERB is closely monitoring the progress of safety enhancements at operating NPPs. The status of implementation of identified upgrades is as follows:

Short term measures

• Enhancing the reliability of cooling throughexternal hook-up points

External hook up points have been provided at all stations for injecting water to important systems and equipment viz. steam generators, primary heat transport system, emergency core cooling system,

end shield, calandria, calandria vault, and spent fuel storage bay, during extended accident conditions, if required.

• Additionalemergencylightingbackedupbysolar cells:

Solar powered emergency lighting has been installed at MAPS and KGS-3&4. Pending the implementation of this provision at other stations, the battery backed up emergency lighting has been augmented.

• ReviewandrevisionofEmergencyOperatingProcedures

The review and revision of emergency operating procedures related to external events and SBO has been completed at all NPPs. The procedures are further updated as and when additional strengthening measures are implemented.

• Training andMock-up exercise of operatingpersonnel.

The training & mock-up exercises of operating personnel have been completed at all stations.

Medium term measures

• Introductionofseismictripwhereitdoesnotexist:

The provision of automatic trip of reactor during seismic event exists in the original design of NAPS-1&2 and KAPS-1&2. Post Fukushima, AERB has reviewed and approved NPCIL proposal for implementation of this provision in all other operating NPPs. Subsequently, the provision has been implemented in both the units of MAPS and KGS-3&4. At other stations, scheme is expected to be implemented the end of year 2014.

• Strengthening of back-up power supply (aircooled mobile/fixed DG at higher elevation):

Air cooled DGs have been installed at MAPS to provide back-up power to essential loads during extended SBO. Also, air cooled DG of 200 kVA is arrived at KGS site. DGs for other sites are under procurement. Pending the procurement and commissioning of these DGs, mobile air cooled DGs of similar / lower capacity have been arranged on temporary basis at all sites.

• Strengthening provision for monitoring ofcritical parameter under prolonged loss of power:

All stations have identified the critical parameters that are required to be monitored during extended loss of power failure. Portable monitors have been made available in control room at all NPPs to monitor

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these parameters from the identified location in control equipment room. A detailed procedure in this regard is also available at all stations. The power supply from the air cooled DGs can also be utilised for monitoring essential plant parameters. As an additional measure, six nos. of 850 VA capacity UPS have been installed at MAPS and four 650 VA UPS are being procured for TAPS-3&4 for monitoring essential parameters during extended SBO.

• Provisionofdieseldrivenpumpsfortransferof water from deaerator storage tank to steam generators:

It was decided to make provision for makeup of steam generators from deaerator storage tank during emergency at all NPPs. The status of this upgrade at various stations is as follows:

At RAPS-2, an additional emergency boiler feed pumps has been installed at higher elevation. This pump can be operated by power from air cooled flood DGs (DG-5 or DG-6), located at higher elevation.

At MAPS, the emergency boiler feed pump located above the review basis flood level can be used for transferring water from deaerator to steam generators. This pump can be operated by supplying power from 200 kVA air-cooled DGs. In addition, water in deaerator storage tank can be transferred to steam generators by gravity also.

At RAPS-3 to 6 and KGS-1 to 4 deaerator water can be transferred to SG by gravity.

The installation of diesel driven fire water pump for transferring water from deaerator storage tank to steam generator is pending for NAPS, KAPS and TAPS-3&4.

• Additionalmobilepumpsandfiretenders:

The adequacy of existing pumps and fire tenders has been reviewed by all NPPs. Based on this review, additional fire tenders are under procurement for NAPS and MAPS.

• Steps for augmentation of onsite waterstorage, wherever required:

The availability of water in seismically qualified tanks has been reviewed for each NPP. Review indicated that sufficient water is available in onsite seismically qualified structures/tanks for meeting the emergency need at KGS-1 to 4 & RAPS-3 to 6. Based on this review NPCIL has decided to build seismically qualified water pools at MAPS, NAPS, KAPS and TAPS-3&4 and strengthened the existing storage tanks at RAPS-1&2 to meet the seismic qualification.

Long term measures

• Enhancing Severe Accident Managementprogramme:

Preventive measures that are required to be taken under severe accident condition such as hook up provisions have been implemented at all stations. NPCIL had prepared interim severe accident management guidelines for usage of these provisions. The analysis of other severe accident sequences and the provisions required for handling severe accidents are also completed and NPCIL has submitted final SAM guidelines to AERB. The plant specific guidelines will be prepared based on these generic guidelines.

• Strengthening hydrogen managementprovisions:

NPCIL has submitted an analysis on hydrogen generation under accidental conditions and requirement of Passive Auto-catalytic Recombiners (PAR) for hydrogen management for all operating PHWRs. These analysis reports are under review by expert committees constituted by AERB. The requirements for installation of PARs for management of hydrogen during severe accidents will be worked out based on these reviews.

• Provisionforventingofcontainment:

NPCIL has submitted a conceptual design note on hardened venting system for primary containment of NPPs. However, the details of various components and design of systems are awaited. NPCIL has conducted experiments to test the performance of the components that are to be used in containment hardened venting system. NPCIL has also submitted Design Basis Report (DBR) for containment venting system for TAPS-1&2 which is under review by safety committee.

• CreationofanemergencysupportfacilityatNPP sites:

AERB constituted an Advisory Committee for developing the guidelines for creation of an on-site emergency support facility. The Committee has submitted its report. The report has been accepted by SARCOP. NPCIL has been asked to submit site specific proposal for creation of emergency support facility, in-line with the guidelines recommended by this Advisory Group.

(ii) TAPS-1&2 and TAPS-3&4

TAPS-1&2 and TAPS-3&4 operated safely during the year.

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Extension of license for operation of TAPS-1&2

The license for operation of TAPS-1&2 was