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Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 LICENSING PROCESS FOR BELENE NPP: CURRENT STATUS AND NEXT STEPS Tinko Ganchev Head of Department.

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Presentation on theme: "Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 LICENSING PROCESS FOR BELENE NPP: CURRENT STATUS AND NEXT STEPS Tinko Ganchev Head of Department."— Presentation transcript:

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2 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 LICENSING PROCESS FOR BELENE NPP: CURRENT STATUS AND NEXT STEPS Tinko Ganchev Head of Department Bulgarian Nuclear Regulatory Agency

3 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 2 Content of the presentation 1.Introduction 2. Legal requirements on licensing and safety assessment 3. Regulatory review of Belene NPP TD, ISAR and PSA 4. Additional analyses and discussions of selected safety issues

4 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 3 1. Introduction

5 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 4 Main Advantages of AES-92 Design- Generation III LWR Provision of a “core catcher” for severe accident cases, leading to a core melting and reactor pressure vessel breach Provision of a “core catcher” for severe accident cases, leading to a core melting and reactor pressure vessel breach Long design operation life time: 60 provisional years of operation Long design operation life time: 60 provisional years of operation Substantial reduction of core damage frequency : ~10 -7 /y Substantial reduction of core damage frequency : ~10 -7 /y

6 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 5 Main Advantages of AES-92 Design- Generation III LWR Two individual completely independent reactivity control systems Two individual completely independent reactivity control systems Redundancy for all safety functions provided by the use of both active and passive safety systems Redundancy for all safety functions provided by the use of both active and passive safety systems Use of a special double containment, designed to withstand a large range of internal and external events Use of a special double containment, designed to withstand a large range of internal and external events

7 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 6 2. Legal requirements 2. Legal requirements on licensing and safety assessment

8 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 7 Legislation applied to licensing new nuclear facility Primary legislationPrimary legislation –EU legislation, Conventions, Constitution of the Republic of Bulgaria –Act of the Safe Use of Nuclear Energy (Nuclear Act) –Energy Act –Environment Protection Act –Act on the Territorial Structure Secondary legislationSecondary legislation - 22 regulations for the application of the Nuclear Act - 22 regulations for the application of the Nuclear Act

9 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 8 Nuclear Act: Types of Authorisations °permit for site selection °order for approval of the selected site °permit for design °order for approval of the technical design °permit for construction °permit for commissioning °licence for operation °licence for decommissioning

10 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 9 Main NRA regulations applied during licensing Regulation for the procedure for issuing licenses and permits for safe use of nuclear energy (2004)Regulation for the procedure for issuing licenses and permits for safe use of nuclear energy (2004) Regulation on ensuring the safety of nuclear power plants (2004)Regulation on ensuring the safety of nuclear power plants (2004) Regulation on basic norms of radiation protection (2004)Regulation on basic norms of radiation protection (2004) Other relevant regulations issued under the Nuclear ActOther relevant regulations issued under the Nuclear Act

11 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 10 Regulation on Ensuring the Safety of NPPs Design limits and safety assessment Design limits and safety assessment Acceptance criteria for the barriers;Acceptance criteria for the barriers; Radiological and other technical acceptance criteriaRadiological and other technical acceptance criteria Frequency of a large radioactive release into the environment that requires undertaking of immediate protective measures for the population shall not exceed 1E-6 events per NPP per year.Frequency of a large radioactive release into the environment that requires undertaking of immediate protective measures for the population shall not exceed 1E-6 events per NPP per year.

12 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 11 Regulation on Ensuring the Safety of NPPs: Safety Analysis and Assessment Safety Analysis and Assessment Plant safety shall be analyzed using deterministic and probabilistic methods to verify and confirm the established design basis and the effectiveness of defense in depth arrangementPlant safety shall be analyzed using deterministic and probabilistic methods to verify and confirm the established design basis and the effectiveness of defense in depth arrangement Postulated initiating events (PIEs) shall be also analyzedPostulated initiating events (PIEs) shall be also analyzed Computer codes, analytical methods and plant models to be used in the safety analysis shall be verified and validated, uncertainty of the results shall be quantifiedComputer codes, analytical methods and plant models to be used in the safety analysis shall be verified and validated, uncertainty of the results shall be quantified

13 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 12 Safety Margins and Uncertainty Safety Margins and Uncertainty

14 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 13 Probabilistic Safety Criteria of European Utilities (EUR): Probabilistic Safety Criteria of European Utilities (EUR): more restrictive than the criteria of the IAEA more restrictive than the criteria of the IAEA EUR Probabilistic Safety Targets: EUR Probabilistic Safety Targets: - Core damage frequency: CDF<1 E-5 - Core damage frequency: CDF<1 E-5 - Frequency of release>limited impact (LI): 1 E-6 - Frequency of release>limited impact (LI): 1 E-6 - Early or large release frequency (ELRF): 1 E-7 - Early or large release frequency (ELRF): 1 E-7 IAEA Probabilistic Safety Targets for future plants (INSAG 3, 1999) - CDF: 1E-5 per reactor year - CDF: 1E-5 per reactor year - LRF: 1E-6 per reactor year - LRF: 1E-6 per reactor year Examples of international safety and reliability criteria

15 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 14 3. Regulatory review of TD, ISAR and PSA for Belene NPP

16 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 15 Current Licensing Status April 2008 Application for Design Approval Review and Assessment of Submitted Documentation

17 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 16 Main documents subject to assessment Technical Design (TD)Technical Design (TD) Interim Safety Ananalysis Report (ISAR)Interim Safety Ananalysis Report (ISAR) Probabilistic Safety Analysis (PSA)Probabilistic Safety Analysis (PSA) -Amount of the technical documents submitted: > 30 000 pages -Amount of the technical documents submitted: > 30 000 pages

18 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 17 Internal expert opinion Within the BNRA frames According to approved program - stages, experts, terms Review and assessment by consultants ISAR – Riskaudit International (GRS & IRSN) Chosen technical design solutions – EnproConsult Ltd. EnproConsult Ltd. PSA - IAEA in the frame of national TC project BNRA review and assessment process:

19 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 18 In-depth analyses of selected safety issues by Riskaudit In-depth analyses of selected safety issues by Riskaudit 1.Large Break Loss of Coolant Accident (LOCA) Study 2.Core-Catcher Features and Performance Investigation 3. Coupled ATHLET-COCOSYS analysis for a BDBA LOCA DN80 4. ATHLET BDBA analysis Small break DN80 and total loss of power for 24 hours 5. COCOSYS accident analyses for NPP Belene 6. Structure mechanical analyses of the containment behavior 7. Analysis of the resolution of the IAEA Safety Issues for WWER- 1000/V-320 Nuclear Power Plants for Belene NPP Review and assessment of the ISAR (Rev.0)

20 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 19 Total amount of experts’ report – 1000 pages There are no issues that could not be resolved Classification of the Review 2008-2009 Classification of the Review 2008-2009 recommendations : recommendations : Class 1 – essential for safety “Must do” Class 2 – having an effect on safety “Should do” Class 3 – without significant effect on safety “Nice to have” Results from the review of TD and ISAR (Rev. 0)

21 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 20 Review and assessment of the Technical Design EnproConsult Task: Review and assessment of chosen design solutions Geotechnical issues Primary circuit Hermetic construction Safety related I&C systems (including software) Control Systems Systems for management of severe accidents Reliability of chosen main structures Analysis of the fire risk and protection measures Analysis of the measures for ensuing seismic safety Measures for ensuring radiation protection

22 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 21 Review and assessment of TD and ISAR – Rev.2 New contracts with Riskaudit and EnproConsult signed in May – July 2010 Task 1: Review and assessment of the Revision 2 of TD and ISARTask 1: Review and assessment of the Revision 2 of TD and ISAR Task 2: Performance of part 2 of research oriented activities and generic oriented in-depth studies for selected safety issues and accident scenarios identified in the course of TD and ISAR review with a special focus on the novel passive safety systemsTask 2: Performance of part 2 of research oriented activities and generic oriented in-depth studies for selected safety issues and accident scenarios identified in the course of TD and ISAR review with a special focus on the novel passive safety systems

23 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 22 Review and Assessment of the PSA National TC project supported by the IAEA Assessment of PSA: –Preliminary Mission – February 2009 –IPSART Mission for assessment of PSA Rev. 0 - May 2009. Final Report - August 2009 –Follow-up IPSART Mission, PSA Rev. 2 - October 2010. Final Report - February 2011 Importance ranking of findings: - “HIGH” - “MEDIUM” - “LOW” - “N/A”

24 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 23 Review and Assessment of the PSA Conclusions of the PSA review: Large number of findings of the IPSART Mission has been resolved in the PSA Report Rev.2 Some of the PSA issues can only be resolved during the detailed design stage when the required details will be known and available

25 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 24 4. Additional analyses and discussions 4. Additional analyses and discussions of selected safety issues

26 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 25 BNRA internal review of consultants’ recommendations High level decision-making group has been created in the BNRA: Task: To review and assess all the recommendations made by the BNRA experts and by the consultants and to take a decision about their importance for the current licensing stage - approval of the design Task: To review and assess all the recommendations made by the BNRA experts and by the consultants and to take a decision about their importance for the current licensing stage - approval of the design Results: Class 1 recommendations (must be resolved before approval of the plant design): Results: Class 1 recommendations (must be resolved before approval of the plant design): RiskAudit – 83 RiskAudit – 83 EnproConsult – 31 EnproConsult – 31 Total – 114 Total – 114 List of missing Topical reports has been prepared

27 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 26 NRA internal review of consultants’ recommendations Further analyses and discussions needed: Further analyses and discussions needed: Novel passive safety systems: - Molten Core Retention System (“Core catcher”); - Molten Core Retention System (“Core catcher”); - Passive secondary Heat Removal System (PHRS); - Passive secondary Heat Removal System (PHRS); - Quick Boron Injection System (QBIS) - Quick Boron Injection System (QBIS) - Containment structure and PHRS - airplane crash impact - Containment structure and PHRS - airplane crash impact Dual use of some systems for normal operation Systems and components classification Submission of additional Topical reports

28 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 27 EU (ENSREG) “Stress tests” analysis of Belene NPP Stress test”: targeted reassessment of the safety margins of NPPs. “Stress test”: targeted reassessment of the safety margins of NPPs. Technical scope: a) Initiating events: earthquake; flooding; b) Consequence of loss of safety functions from any initiating event: loss of electric power, including station black out; loss of ultimate heat sink; combination of both; c) Severe accident management issues: loss of core cooling function; loss of the cooling function of the fuel storage pool; loss of containment integrity

29 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 28 EU (ENSREG) “Stress tests” analysis of Belene NPP Progress report Final report Licensee report August 15, 2011 October 31, 2011 National report September 15, 2011 December 31, 2011 The final National report will be subject to a peer review process The EC will present a progress report to the EU Council for the meeting scheduled on 9 th December 2011 and a consolidated report for the meeting scheduled for June 2012. Timeframe:

30 Bulatom Annual Forum, Bulgaria, Varna - Riviera, 2-4 June 2011 29 Next licensing steps Design approval order Construction permit Commissioning permit Operating License

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