Regulation & Safety Requirements

7/28/2019 Regulation & Safety Requirements

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EDF / SEPTEN1

Regulation and

Safety requirements

for civil structures

Pierre.Pierre.lazzarinilazzarini@@edfedf..frfr


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EDF / SEPTEN2

Regulation and safety requirementsfor civil worksRegulation and safety requirementsfor civil works

1. Regulation : Laws / decrees / standards / codes

The regulation in France

A quick look at US and UK

2. Safety requirements

General considerations about civil works

Safety requirements for civil works in EPR


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EDF / SEPTEN3

1. Regulation

The regulation in France

A look at UK & US situationA look at UK & US situation


4/41EDF / SEPTEN4

General architecture of regulationGeneral architecture of regulation

Laws

Decrees,departmentalordersASNdecisions

RFSfundamentalsafetyrulesASN guidesTechnicalDirectives

DesignandConstruction codesStandards

Internaltechnicalrules

legislative

field

Regulatory

field

Standardisation

field

Parliament

Executive

power

Industry

General applicationCompulsory

Technically specificPossible deviations


5/41EDF / SEPTEN5

Laws and decreesLaws and decrees

TSN LAW (J une 16th 2006)

} TSN = Transparency and Security in Nuclear field

} TSN Law unifies previous laws and decrees

} Completed by several decrees which provide for application details


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} Create ASN :

y Independent regulatory authority

y With a large power :

y Technical and regulatory decisions

y Control of nuclear facilities

y Public information

y Management of emergency situations

y Technical enquiries

y Advices and recommendations to the Government

y Licensing of nuclear facilities


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} Security in Nuclear field is defined as :

1. Nuclear safety

2. Radioprotection

3. Prevention, mitigation of malicious acts

4. Organisation of public safety in case of accident

} Protected stakes :

1. Public safety

2. Public health

3. Public healthiness

4. Nature and environment protection

Civil Eng. Concerned

Civil Eng. Concerned


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EDF / SEPTEN8

Laws and decreesconcerning Civ. Eng

.

Laws and decreesconcerning Civ. Eng.

RTGE Decree (Dec. 31th 1999)

} RTGE = Environmental General Technical Regulation

} Prevention and mitigation of non-nuclear environmental impacts

1. Noise and vibrations

2. Atmospheric pollution prevention

3. Prevention of water pollution

4. Waste management

5. Fire risks

6. Nuclear risks


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EDF / SEPTEN9

Laws and decreesconcerning Civ. Eng

.

Laws and decreesconcerning Civ. Eng.

Regulation about working conditions and protection of workers health

} Radio protection

} Fire protection and fire escape routes

} Etc

Quality Decree (1984)

} Related to Quality Assurance in Nuclear activities

Others .


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EDF / SEPTEN10

RFS and ASN guidesRFS and ASN guides

RFS & ASN Guides

} RFS = Fundamental Safety Rule. The latest ones are named "Guides"

} Issued by ASN

What are they ?

} Dedicated to a specific technical field

} Fix safety objectives

}

Define technically acceptable practice} Reflect the state of knowledge at the date of issue Possible

evolutions

}

Possibility of deviations : with adequate justification that safetyobjectives are met


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EDF / SEPTEN11


RFS & ASN Guides concerning Civ. Eng.

} RFS I.2.a. Aircraft crash risks (August 1980).} RFS I.2.b. Turbine missile risks (Agust1980).

} RFS I.2.d. Risks in connection with industrial environment and transportways (May 1982).

} RFS I.2.e. external flooding risk (April 1984).

} RFS I.3.b. Seismic instrumentation (J une 1984).

} RFS I.3.c.Geological and geotechnical surveys (August 1985).

} RFS IV.l.a. Classification of mechanical components, electrical systems,civil structures and buildings (December 1984).


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EDF / SEPTEN12


RFS & ASN Guides concerning Civ. Eng.

} RFS-V.2.b. General design and construction code for civil works (rf.:code RCC-G), (J uly 1981).

} RFS-V.2.f Fire protection (rf.: code RCC-I), (December 1982).

}

RFS-V.2.g. Seismic calculations of civil works (December 1985).} RFS-V.2.h. General design and construction code for civil works (rf.:

code RCC-G), (J une 1986).

} RFS-V.2.j.Fire protection (November 1988).

} RFS 2001-01 : Seismic ground motion (May 2001)

} ASN Guide 2-01 : Seismic calculations of civil works (2002)

D i & t tiDesign & construction


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EDF / SEPTEN13

Design & constructioncodesDesign & constructioncodes

Requested by French authorities at the beginning of the nuclearprogram:

} Formalization of technical rules specifications applicable to design andconstruction of PWR in France

Written by EDF in cooperation of independent experts

Objectives

} Facilitate the technical instructions with ASN

}

Simplify the contractual technical relation between EDF and contractors,} A set of documents representing the technical French practice

(exportation China, Korea, South Africa)

}

Some of them approved by ASN through RFS

Design & constructionDesign & construction


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EDF / SEPTEN14

Design & constructioncodesDesign & constructioncodes

List of codes connected to Civil engineering and construction

} RCC-G (1981) = Design and Construction Code Civil structures CPY - 900MW PWR

} RCC-G (1985) = Design and Construction Code Civil structures

P4 P'4 N4 1300 / 1450 MW PWR

} ETC-C = EPR Technical Code Civil structures

} RCC-I (1987) = Design and Construction Code Fire protection N4

} ETC-F = EPR Technical Code Fire protection


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EDF / SEPTEN15

A quick look at US and UK situationA quick look at US and UK situation

In the US

}A comprehensive set of codes, guides and standards :

y ACI codes 349 and 359 (civil engineering)

y ASME code

In the UK

}Only general documents

y SAPs : Safety Assessment Principles

y Safety case based on ALARP approach

}The designer, or the Nuclear Utility, can chose its codes and standards,but must prove that the design complies with SAPs,


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EDF / SEPTEN16

2. Safety requirementsfor civil structures

./ General considerations on civil worksfunctions

./ EPR case study


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EDF / SEPTEN17



./ General considerations on civil worksfunctions

i f i il i f


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EDF / SEPTEN18

Functions of civil structures in Nuc. safetyFunctions of civil structures in Nuc. safety

Bearing and protectionof safety related and

safeguard systems

Reactivity control

Bearing and protectionof safety related and

safeguard systems

Power dissipation

Fuel casing1st barrier

Primary Circuit / Reactor vessel

2nd barrier

Containment wall

3rd barrier

Bearing and protection

of safety related and

safeguard systems

Radioprotection

radioactivity confinment

3 barriersSafety functions

Nuclear Fuel

Fuel Casing

Reactor Vessel

Containment Wall


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EDF / SEPTEN19

Main requirements for Civil Struc.Main requirements for Civil Struc.

Main requirements related to Safety Functions

}Stability

}Equipment bearing

}Tightness

}Containment


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EDF / SEPTEN20

Main requirements for Civil StrucMain requirements for Civil Struc

Stability

}Lowest level of requirement = No collapse

Objective not met Objective met


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EDF / SEPTEN21


Equipment bearing

The civil structures must bear the maincomponents even during and after accidentalsituations.

Limitation of deformation and cracking

i i f Ci il S


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EDF / SEPTEN22


Tightness (liquids)

}Pools Tanks etc

}Generally obtained bya steel liner

}Sometimes :limitation of cracking

and composite liner

Fuel Building

Spent fuel Pool



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EDF / SEPTEN23


Nuclear Fuel

Fuel Casing

Reactor Vessel

Containment Wall

Containment (gaz tightness)Obtained by :

Steel liner

Concrete pre-stressing(drastic reduction of cracking)

containment wall

Limitation of cracking low pressure

Dynamic containment / ventilation depression

M i i t f Ci il StM i i t f Ci il St


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EDF / SEPTEN24


Criteria severity v/s Requirements severity

Requirements

Criteriaseverity

Stability

Equipment bearing

Liquid tightness

Containment

Oth i tOth i t


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EDF / SEPTEN25

Other requirementsOther requirements

Mechanical protection

Biological protection

}For workers and equipments

Fire protection}Trains segregation


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EDF / SEPTEN26

2. Safety requirementsfor civil structures

./ EPR case study

EPR B ildiEPR Buildings


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EDF / SEPTEN27

EPR BuildingsEPR Buildings

1 . Reactor B.2. Fuel B.

3. Safeguard B.4. Diesel B.5. Nuclear auxiliaries B.6. Waste treatment B.7. Turbine hall

Design assumptions for safetyDesign assumptions for safety


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EDF / SEPTEN28

Design assumptions for safetyassesment

g p yassesment

Categories of operating conditions taken into account for design :

}Referenced operating conditions : PCC1 to PCC4

}Multiple failure operating conditions (RRC-A) and severe accidentconditions (RRC-B)

} Internal hazards

}External hazards

}Conditions taken into account as defence in-depth / design margins :LOCA 2A, LOCA + Earthquake



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EDF / SEPTEN29

g p yassesment

g p yassesment

Referenced operating conditions

}Normal operating conditions = 6 reactor states / PCC1 category

y

Facility lifespan (60 years)

y Ambient conditions (temperature, pressure, irradiation)

y Periodic tests

y Normal climatic conditions

} Incidental & accidental transients = PCC2 to PCC4 categories

y Ambient conditions (temperature, pressure, irradiation)



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EDF / SEPTEN30

g p yassesment

g p yassesment

Operating conditions with multiple failure (RRC-A) and severeaccidents (RRC-B)

}RRC-A conditions are less severe than PCC4 accidental transients Not taken into account

}RRC-B conditions / Severe accidents

y Ambient conditions (Temp. Pressure, Irradiation) + pressure margin

y Hydrogen combustion / deflagration

Internal hazards

y High energy pipes break

y Internal flooding

y Internal missiles & load fall

yFire



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EDF / SEPTEN31

g p yassesment

g p yassesment

External hazards

}Design basis earthquake (DE) & inspection earthquake (or Safe shutdownearthquake / SSE)

}Aircraft crash (APC)

}External explosion

}External flooding & underground water raise

}Exceptional meteorological conditions

Defence in-depth / design margins}LOCA-2A

}LOCA + earthquake

Safety RequirementsSafety Requirements


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EDF / SEPTEN32

Safety RequirementsSafety Requirements

Safety requirements are defined as the list of functional criteria thatmust be guaranteed in each scenario considered in the safetyassessment.

The functional criteria depend of :

}The scenario / situation,

}The element of structure(containment wall pool aircraft shield simple wall )

Standard criteria

Overview of safety requirements in following tables

S = serviceability (stability / component bearing) T = tightness

R = Resistance C = Containment

Safety requirementsSafety requirements


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EDF / SEPTEN33

y qReactor building

y qReactor building

Situations & categoriesInternal

containment

internal

structures

external

containment

/ ACS

foundation

slabACS

containment

linerPenetrations IRWST pool

N Normal situations Sc Sc / Sc / C + Sm C + Sm T

E1 PCC-2 situations Sc Sc / Sc / C + Sm C + Sm T

E2 Inspection earthquake (SSE) Sc Sc Sc Sc Sc C + Sm C + Sm T

E3 Snow & wind / / Sc / Sc / / /

E4 Exceptional temperatures / / Sc / Sc / / /

E5 Underground water / / / T / / / /

E6 Periodic tests Sc / Sc + C Sc / C + Sc C + Sc /

A1 Earthquake (DE) Rc Rc Rc Rc Rc C C T

A2 APC / / Rc Rc Rc / / /

A3 Explosion / Fire / / Rc / Rc / / /

A4 High energy pipe break Rc Rc Rc / / C Rm /

A5 PCC-3/4 - RRC-A Rc Rc / / / C C T

A6 RRC-B Rc Rc C Rc / C C /

A7 LOCA-2A Rc / / Rc / C C /

A8 LOCA + Earthquake Rc / / Rc / C / /

S = serviceability T = tightness R = Resistance C = ContainmentIndex c = concrete Index m = metal

Safety requirementsSafety requirements


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EDF / SEPTEN34

y qNuclear Island & Pumping station

y qNuclear Island & Pumping station

Situations & categories HK / HL2-3 HL1-4 HNPumping

stationHL / RIS HD

N Normal situations Sc (T) Sc Sc / T Sc / Sc

E1 PCC-2 situations Sc (T) Sc Sc / T / Sc /

E2 Inspection earthquake (SSE) Sc (T) Sc Sc / T Sc Sc Sc

E3 Snow & wind / Sc Sc Sc / Sc

E4 Exceptional temperatures / Sc Sc Sc / Sc

E5 Underground water / / Sc / T Sc / Sc

A1 Earthquake (DE) Rc (T) Rc Rc / T Rc Rc Rc

A2 APC / / / Rc Rc Rc

A3 Explosion / Fire / Rc Rc / T Rc / Rc

A4 High energy pipe break / / / / / /

A5 PCC-3/4 - RRC-A Rc / C (T) Rc / C T / Rc / C /

A6 RRC-B / / / / / /

S = serviceability T = tightness R = Resistance C = Containment

Index c = concrete Index m = metalHK = fuel B. HL = Safeguard B. HN = Nuclear auxiliary B HD = Diesel B.

Load combinations 1/2Load combinations 1/2


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EDF / SEPTEN35


N SituationsPermanent

loadsprestressing

variable

loads

(construction

& operation

External

temperature

Other loads

(climatic,

water temp,

inspectionearthquake)

Internal External

1 Construction X X X X X

2 Normal operation X X X X

3

Normal oper. +

climatic loads X X X X X

4Inspection

earthquakeX X X X

5 Underground water X NC X X

6 Except. water temp. X NC X X

7Except. climatic

loadsX NC X X X

8 Tests X X X

Accidental actions

Normal

situations

Exceptional

situations

Permanent actions Variable actions



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EDF / SEPTEN36


N SituationsPermanent

loadsprestressing

variable

loads

(construction

& operation

External

temperature

Other loads

(climatic,

water temp,

inspection

earthquake)

Internal External

9 LOCA X X X

10 LOCA 2B (0.55 MPA) X X X X

11 LOCA 2B (0.65 MPA) X X X X

12High energy pipe

failureX X X X X

13 Internal missile X X X X

14Accidental water

temp.X NC X X

15 Design earthquake X X X X X

16 APC X X X X X

17 External explosion X X X X X

18 Flooding X X X X X X

19LOCA +

D.earthquakeX X X X X X

20D.Earthquake + clim.

Loads

X NC X X

Accidental actions

Accidental

situations

Permanent actions Variable actions

From safety requirements to ETC-CFrom safety requirements to ETC-C


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EDF / SEPTEN37

From safety requirements to ETC CFrom safety requirements to ETC C

ETC-C as a design code

}ETC-C part 1 provides for :

y Detailed load combinations, with safety factors to be applied to the loads

y Criteria on material consistent with safety functional criteria :

admissible strains and stresses, maximum deformation , crack openinglimitation etc

with adequate safety factors.

ETC-C will be presented in a future session.


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EDF / SEPTEN38



./ How the safety requirements impactthe design

2 examples of EPR specificities

Reactor building containmentReactor building containment


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EDF / SEPTEN39

Reactor building containmentReactor building containment

Inner prestressed containment wall

With steel liner

Designed for severe accident :P = 0.65 MPa abs.Temp = 170C

Outer reinforced containment wall( partly ACS)

Depression and leakage controlin between

Aircraft crash protectionAircraft crash protection


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EDF / SEPTEN40

Aircraft crash protectionAircraft crash protection

Aircraft shield Fuel building

Safety trains segregation

Protected buildings

Non-protected buildings


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EDF / SEPTEN41

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Regulation & Safety Requirements

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