The irsn s reactor safety division and its contribution to the reactor safety assessment
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The IRSN’s Reactor Safety Division and its Contribution to the Reactor Safety Assessment. Giovanni Bruna - Jean-Luc Chambon (IRSN / DSR) 2010 November, 26. Current French Reactor Development Strategy. 900 MWe Series CP0 6 units. 900 MWe Series CP1 18 units. French NPP’s Fleet.

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The irsn s reactor safety division and its contribution to the reactor safety assessment

The IRSN’s Reactor Safety Divisionand its Contribution to the Reactor Safety Assessment

Giovanni Bruna - Jean-Luc Chambon (IRSN / DSR)2010 November, 26


The irsn s reactor safety division and its contribution to the reactor safety assessment

Current French Reactor Development Strategy


The irsn s reactor safety division and its contribution to the reactor safety assessment

900 MWe Series

CP0

6 units

900 MWe Series

CP1

18 units

French NPP’s Fleet

1450 MWe Series

N4

4 units

99

98

97

96

95

Chooz BCivaux

94

900 MWe Series

CP2

10 units

1300 MWe Series

P4 & P’4

8 + 12

93

92

91

90

89

CattenomBelleville

Nogent, PenlyGolfech

88

87

86

85

84

PaluelSt AlbanFlamanville

83

St LaurentChinonCruas

82

81

80

79

Tricastin, GravelinesDampierre, Blayais

78

77

76

Bugey

Fessenheim

75

74

73

72

71

1970


The irsn s reactor safety division and its contribution to the reactor safety assessment

Research Reactors and Mock-up Experiment Facilities

  • Reactors for material irradiation :

    • OSIRIS (70 MW), RJH (100 MW)

  • Reactors for fundamental Research :

    • ORPHEE (14 MW), RHF (58,3 MW)

  • Reactors dedicated to safety studies :

    • CABRI (14 MW), PHEBUS (38 MW)

  • Reactors Physics Mock-ups :

    • EOLE (10 kW), ISIS (700 kW), MINERVE (100 W), MASURCA (5 kW)


The irsn s reactor safety division and its contribution to the reactor safety assessment

Reactor Safety Demonstration

  • Radiological targets and protection against radiation

  • Safety principles

    • Defence in depth

    • 3 barriers

    • Safety functions

  • Design concept

    • Deterministic analysis

      • Postulated initiating events

      • Plant conditions category (PCC) used for design

      • Risk reduction category (RRC) used to complete the design

    • Probabilistic analysis

    • Internal and external hazards analysis

Excluded

Accounted for


The irsn s reactor safety division and its contribution to the reactor safety assessment

DBA ACCIDENTS

PROTECTION

INCIDENTS

CONTROL

OPERATION

BDBA ACCIDENTS

SEVERE ACCIDENTS

MITIGATION

Reactor Safety Demonstration : Defense in Depth

During the whole Plant Life (From Construction to Decommissioning)


The irsn s reactor safety division and its contribution to the reactor safety assessment

RISK

FORBIDDEN

RANGE

  • Control of nuclear chain- reaction(Reactivity – Criticality)

  • Fuel and Core-cooling-down (Coolability)

  • Confinement

  • of radioactive contaminants

ALLOWED

RANGE

LIKELYHOOD

SAFETY FUNCTIONS

BARRIERS

Reactor Safety Demonstration : Principles

SAFETY APPROACH AND TOOLS


The irsn s reactor safety division and its contribution to the reactor safety assessment

Safety Assessment 1/2

  • The major aim of the Safety Assessment of Nuclear Power Plants is the evaluation (and when possible, the quantification) of all potential risks, including those originated by either voluntary changes in design and operation (refurbishment, fuel loading) or involuntary ones (ageing, degradation of materials and fuel …).


The irsn s reactor safety division and its contribution to the reactor safety assessment

Safety Assessment 2/2

  • To achieve such an ambitious objective it is worth to:

  • - Identifying all the potential risk-sources through suitable probabilistic approaches (PSA),

  • - Understanding the physical phenomena generating such risks,

  • - Mastering the component and system design and operating features and their failure modes;

  • That is done, accounting for

    • The capitalization and increase of knowledge through operating experience, studies and R&D,

    • The change in the rules

    • The evolution of the socio-economical context


  • The irsn s reactor safety division and its contribution to the reactor safety assessment

    • DSR : 7 Services

    • Safety of Operating Power Reactors,

    • Safety of Experimental and Future Reactors,

    • Fuel, Core Design, Control & Operation, Plant Simulator (SIPA),

    • Materials, Components Equipment & I&C,

    • Severe Accidents,

    • Aggressions & Hazards, & International Affairs,

    • Human and Organizational Factors.

    SIPA Team

    & Int. Aff.

    Coordination

    DSR

    > 250 people

    • IRSN : 6 Divisions

    • - Reactor Safety Division (DSR),

    • Cycle and Transport Safety Div.,

    • Armament safety Division,

    • R&D (S.A. oriented) Division,

    • Environment Protection Div.,

    • Man Protection Division

    Secretariat

    Administration

    And Finance

    Technical

    Divisions

    IRSN

    > 1500 people


    Dsr reactor safety division

    Two main activities, for reactors and plants in France and abroad:

    Expertise and Studies in Reactor Safety for

    Power Reactors

    Research Reactors and Mock-up Experiment Facilities

    Research and Development activities in fields such as:

    Probabilistic Safety Analysis (PSA levels 1 & 2),

    Accident Modeling (LOCA, RIA, SGTR …),

    Human factors,

    Fuel,

    Materials and Components …

    DSR - Reactor Safety Division


    The irsn s reactor safety division and its contribution to the reactor safety assessment

    CONSTRUCTION, TESTS

    SHUTDOWN

    DESIGN

    OPERATION

    DISMANTLING

    DSR - Reactor Safety Division

    • Safety Assessment

      • Internal events (breaks, loss of grid, …)

      • Internal and external hazards

      • Probabilistic Safety Analysis

      • Severe Accidents

    • Reactor control and operation

    • Main skills

      • Reactor, Core & Fuel Physics and Fuel Management

      • Materials

      • Systems

      • Containment and reactor vessel Structures (concrete, component supports, …)

      • Ageing of reactor Components (Vessel, cables …)


    Dsr reactor safety division1

    Martial Jorel

    Giovanni Bruna, Jean Couturier, Pascal Quentin, Jean-Luc Chambon

    Two multi-functional Services

    Five specialists’ Services

    About 300 people including :

    -250 IRSN’s

    -50 externals (students, subsidiary workers)

    DSR - Reactor Safety Division


    Dsr reactor safety division2

    Five Specialists’ Services

    SAMS : Mechanics, electricity and electrical network, devices, cables and structures, (50)

    SESPRI : Design, control systems, Probabilistic Safety Analysis, external and internal aggressions (45)

    ST3C : Process (neutronics, thermal-hydraulics), fuel, reactor operation, SIPA (plant simulator) (45)

    SAGR : Major accident and radioactive releases (35)

    SEFH : Human factors / organizations (15)

    DSR - Reactor Safety Division


    Dsr reactor safety division3

    Two multi-functional Services

    Licensing

    Reactor operation

    Safety examination and re-examinations

    SEREP : Service for PWR Safety Evaluation (50)

    SEGRE : Service for the Safety Evaluation of Gas-Cooled, Fast and Experimental Reactors (25)

    DSR - Reactor Safety Division


    Dsr reactor safety division4

    Global overview in France on :

    EDF current Plants

    Research reactors and Mock-up Experiment facilities

    New Reactors (EPR, RJH, …)

    Consistent Approach to Reactor Safety

    Tight relationship among major topics

    Exploitation of operating experience both in normal and incidental conditions

    Synergy among

    Expertise

    Studies

    Research and Development

    DSR - Reactor Safety Division


    Follow up of french plant operation

    Permanently monitoring and assessing of the safety of each reactor.

    Making an annual global assessment of the development of the in-service safety level of the EDF reactors to detect trends and deviations

    an increase in unanticipated events and operating difficulties

    IRSN has developed tools, based on the utilization of the information contained in the significant events reports provided by the operator.

    RECUPERARE software

    Follow-up of French plant operation


    Sipa a pwr plant simulator

    SIPA : a PWR Plant-Simulator

    • A high-performance tool in support for safety

    • Capable of representing the behaviour of a PWR in all situations

    • Integrates description of fluid circuits, I&C, protection systems, electric power, containment…

    • User-friendly interface

    • Teaching display station

    • First operation in 1992 (with EDF), presently under renovation (with AREVA NP)


    The irsn s reactor safety division and its contribution to the reactor safety assessment

    for TRAINING

    Target : AuSN - IRSN – CEA

    From newcomers to experts

    (More than 400 participants since 2000)

    Training Objectives:

    - Understanding PWR Design and Operation Principles

    Mastering Physical Situation both in Normal Operation, Incidental & Accidental Conditions

    Presently / 9 One-Week Courses per Year

    for STUDIES

    VALIDATION of computation Tool for Crisis

    PREPARATION of National Crisis Exercises

    ASSESSMENT of Operation Procedures

    STUDY of Accidental Sequences

    SUPPORT to the PSA

    STUDIES of Accidental Transients and Non-Conformities

    PWR Plant-Simulator : a Precious Tool


    Assistance to east european safety authorities

    1990 : beginning of cooperationwithEasterneurope in the field of nuclearsafety

    The French ReactorSafety Division started to support Easternnuclearsafetyauthorities

    as a TSO withinRiskaudit

    through participation to IAEA activities

    Safetyanalysis of WWER plants

    Safety Recommandations

    Modernisation programs

    Review of improvementmeasures

    Assistance to East European safety authorities


    Dsr activity in the frame of safety analysis of vvers

    Safetyanalysis

    Consultancy services funded by European Commission

    Riskaudit reports

    IAEA (missions, meetings, training, …)

    Safety issues and theirranking for WWER-440 model 213, 1000 model 320

    Modernisation programs

    Russia, Bulgaria, Ukraine, Armenia, CzechRepublic

    Assesment of modernisation programs

    IAEA reviews (Kozloduy, Rovno, Temelin)

    Riskauditprojects

    Rovno 1,2,3 + Balakovo + Khmelnitski 2 / Rovno 4 + Kalinin 3

    DSR activity in the frame of safety analysis of VVERs


    Examples of riskaudit recommendations wwer 1000

    Report n°366 on modernisation status of K2/R4

    Items 19121/13111/13611 : to resolve the problems of boron dilution before start-up (studies, instructions, measurements)

    Item 30211 : elaboration of symtom based accidental procedures after installation of the Safety Parameter Display System

    Item 12111 : to implement one solution against cold overpressure (ECCS or pressurizer valves)

    Item 13411 : to modernize the pressurizer safety valves

    Item 24411 : to implement additional diesel generator

    Examples of Riskaudit recommendations WWER 1000


    Dsr efforts

    Various areas :

    review of safetyanalysis reports

    assessment of physicalstudies

    analysis of modifications

    PSA guidance and review

    Averageinvolvment :

    At least 5 assistance projectsat the same time

    About ten experts fromReactorSafety Division

    DSR efforts


    Current dsr assistance to eastern countries

    In progress :

    Russia : review of safetyimprovements

    Ukraine : analysis of modernisation programs, licensing of new plants, PSA guidance

    Arménie : review of safety upgrades

    New type of support :

    TACIS replaced by INSC

    « technical support projects »  « soft assistance projects »

    Consultancy services directlyfunded by East Europeansafetyauthorities

    Current DSR assistance to Eastern countries


    Irsn dsr services to foreign countries

    The Belene Project

    2-VVER 1000 NPPs are to be built on the BELENE site in Bulgaria

    GEN-3+ generation, designed for 60 years of operation

    Provided with

    A core catcher, as part of the third barrier,

    An advanced control system supplied by AREVA,

    Fully redundant Safety Active – Passive Protection Systems.

    IRSN/DSR services to foreign countries


    The belene project

    Agreement signed between Riskaudit (IRSN-GRS) and BNRA, the Bulgarian Nuclear Regulatory Authority

    Aimed at Assessing the BELENE’s ISAR (Intermediate Safety Analysis Report)

    One-year work : November 2008 to November 2009

    Several phases :

    Assessment of the ISAR in compliance with

    international guide-lines (IAEA),

    Bulgarian requirements

    best European safety practices

    In-depth analysis,

    Issuance of a Final Synthesis Report

    The BELENE Project


    The irsn s reactor safety division and its contribution to the reactor safety assessment

    Conclusions

    The Reviewers has provided BNRA with recommendations (more than 250), classified in class 1 “must do”, class 2 “should do” and class 3 “nice to have”.

    No substantial design flaws have been identified and no major issues are found as missing.

    However, the ISAR should be significantly improved before issuing the construction permit.

    In conclusion, RISKAUDIT asked for elaboration of a revised version of the ISAR

    The BELENE Project


    The irsn s reactor safety division and its contribution to the reactor safety assessment

    After release of the revised version of the ISAR (Belene ISAR REV2), RISKAUDIT has been asked by BNRA, through a new contract (Phase 2):

    To verify whether and how the RISKAUDIT’s Recommendations have been addressed and fulfilled,

    To provide assessment for the new material included in the Belene ISAR REV2 (about 1 000 more pages).

    The new contract (Mid 2010 – mid 2011) includes an expertise phase and an in-depth analysis phase as well

    The expertise phase is planned ending on November 30, 2010 with issuance of a Technical Report

    The in-depth analysis phase is planned January to June 2011

    The BELENE Project


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