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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

slide3

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

Cattenom Belleville

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

slide4

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)
slide5

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

slide6

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)

slide7

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

slide8

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 …).
slide9

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
slide10

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
slide12

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)
slide19
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
slide27
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

slide28
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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