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IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA1 /16
GB ConsultingFRENCH NUCLEAR PLANT LIFE MANAGEMENT STRATEGY----------------------------------------------------------------
REACTOR PRESSURE VESSEL ASSESSMENTAND
STEAM GENERATORS LIFE MANAGEMENT STRATEGY
.
Georges BEZDIKIAN
CONTENT� REACTOR PRESSURE VESSEL PLIM � STEAM GENERATORS STRATEGY
SGpressurizer
SG
vessel head
elbows primary pump
confinement containment
SG
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA2 /16
GB ConsultingNUCLEAR PLANTS LIFE MANAGEMENT
INTRODUCTIONNUCLEAR PLANTS LIFE MANAGEMENT
INTRODUCTION
The capability of nuclear electricity generation by French Utility’s (EDF Electricité de France) is 80% of global generation, 58 PWR units are in
operation, 34 units three-loop, 20 units four-loop (1300MWe) and 4 units four-loop (1450MWe).
� The Status of Nuclear Plants Life Management is depending of the following objectives :� To maintain current operating performances (safety, availability, costs, security,
environment) in the long term, and possibly improve on some aspects ;� wherever possible, to operate the units throughout their design lifetime, in other
words 40 years, and after 40 years ;� To consolidate Mormal and Exceptionnal Maintenance and long term
Prediction.The Nuclear Plants Life Management Policy will take intoaccount the category of the components and structure ; and strategic choices in relation with prediction of AgingManagement
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA3 /16
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PWR in FRANCE.GRAVELINES
6 units NOGENT-sur-SEINE
2 unitsDAMPIERRE4 units
CHOOZ2 unitsCATTENOM4 units
FESSENHEIM2 unitsBELLEVILLE2 unitsLE BUGEY4 units
SAINT-ALBAN2 unitsCRUAS4 units
TRICASTIN4 units
1300 MW unit (20)900 MW unit (34) 1450 MW unit (2)
PENLY2 units
FLAMANVILLE2 units
PALUEL4 units
GOLFECH2 units
LE BLAYAIS4 units
CIVAUX2 units
CHINON4 units
SAINT-LAURENT2 units
REACTOR PRESSURE VESSEL LIFE MANAGEMENT AT FRENCH PWR PLANTS
.PARIS
(4)
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA4 /16
GB ConsultingREACTOR PRESSURE VESSEL INTEGRITY ASSESSMENT
The lifetime of a nuclear power plant may be affected by three main factors :� normal wear of its components and systems - called aging - that depends
particularly on their age, operating conditions and maintenance conditions applied to them ;
� the safety level, that must consistently comply with the safety requirements applicable to the power stations at all times, and which could change as a function of new regulations ;
� competitiveness, which must remain satisfactory compared with the competitiveness of other production means.
The general strategy is based on the following two points :� the ten-year safety reassessment process for each ten years period PSR,� the implementation of two structured programmes in order to make sure that all
technical and industrial actions necessary to achieve a lifetime of at least 40 years are actually implemented .
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA5 /16
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NeutronCore zone
PTS Integrity Analysis Calculation Safety Injection Fluid
Reactor coolant fluid
Defect
Cladding
Defect postulatedCore zoneInspected
Neutron Action on Vessel Walland Degradation mode underirradiation
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA6 /16
GB ConsultingEVALUATION APPROACHES CARRIED OUT
SPECIFIC VESSEL by VESSEL EVALUATION
Initial RTNDT
RTNDTvalues comparison
Margins ofcode criteria forin operation units
Chemical compositionparameters for each vessel
Thermal-hydraulic & Mechanical Analysis
Fluence reduce -15 %irradiation during operating lifetime
RTNDT ofeach vessel
RTNDT 30 years40 years50 years
Size of defect postulated at themaximum fluence situation
or Results of in service inspection
Results of transients analysesand most severe transient
A
B
+
Results of irradiationsurveillance program
∆ RTNDT during operating lifetime
prediction Formula
.
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA7 /16
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Fluence initial properties of steel
T(x,t) and σ (x,t) distribution
Stress intensity factor KCP -computation at crack tipsToughness K1C -computation at crack tips
Margin factor KCP / K Ic
BRITTLE DUCTILEToughness
Initialtransition temperature
Temperature of the vessel steel
Defect
Cladding
Defect0
100
200
300
400
0 500 1500 2000timeflu
id tem
perat
ure
Transient
Assessment of RPV integrity : fluence calculations at EDF
Level A = 2nd category of situation => Sc =2level C = 3rd category of situation => Sc = 1.6Level D = 4th category of situation => Sc = 1.2
KCP = KI plastic correction
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA8 /16
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FIGURE 3 : PROJECTIONS DE FLUENCE A 40 ANS
0
1
2
3
4
5
6
7
8
0 5 10 15 20 25 30 35 40années
Flue
nce
en 1
019 n/
cm2
fluence deconception
fluenceréactualisée à15 ansprojection defluence - 20 %
projection defluence - 40 %
projection defluence -15%
Fluence –Basic Design
Fluence –updated 15 years
Years
Years
The actual fluence for 40 years lifetime (considering the reduction of fluence) is :• 3 loop Reactors : 6.5 x 1019 n/cm2• 4 - Loop RPV (1300 MWe) fluence at 40 years lifetime : 4.65 x 1019 n/cm2
of
of
of
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA9 /16
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Capsule V
Capsule Y
CP1 – CP2 Series Plants
Capsule Z
Capsule U
Capsule W
Capsule X
Capsule Capsule Capsule Capsule1 (u) 2 (V) 3 (Z) 4 (Y)
4 7 9 14
11.2 19.5 28.0 40
Extension of the RPV irradiation surveillance : introduction ofreserve irradiation capsules in theFrench plants since 1999 for allreactors.Two reserve capsules W and X in place of capsules U and Z afterremoving from reactor thesecapsules U and Z.
Time ofDurationin vessel(years)
Equivalenttime ofirradiation of Vessel(Years)
RTNDT VALUES - RPV SURVEILLANCE PROGRAMME RTNDT VALUES - RPV SURVEILLANCE PROGRAMME
RTNDT = 82 °C ->CP0 unitsRTNDT = 73°C -> CP1/CP 2 units.RTNDT = 82 °C ->CP0 unitsRTNDT = 73°C -> CP1/CP 2 units.
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA10/16
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CORE ZONE INSPECTION
VPM
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA11/16
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The global Life Management strategy and Maintenance Program of Steam Generators are in relation with:
� The importance of the inspection Programme� The on-going actions during NPPs time in operation normal and current
Maintenance � To anticipate the exceptional maintenance � To anticipate to order the strategic components
Classification of plants with SG Replacement strategyPERIODIC INSPECTIONS OF STEAM GENERATOR
– Technical SG End of Life – SG Plugging Rate max: 12,5 or 15%– Planning schedule in function of intervention on Plants (industrial
capability, Availability of reserve of SG spare parts) – Connection with SGR and 10-years outages
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA12/16
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� Group 1Units with SG affected by dégradations and SGR is will be carry out in futur (date of SGR estimated)
� Group 2Units with SG lifetime evaluation iswith incertainties (evolution of dégradations is unknown, treat onSGR Planed with 3rd 10-years outage
� Group 3Units with SG Lifetime = Plant lifetime
GROUP 1DAMPIERRE 2, DAMPIERRE 4GRAVELINES 3BUGEY 2, BUGEY 3, BUGEY 4FESSENHEIM 2BLAYAIS 1
GROUP 2CHINON B1, CHINON B2BLAYAIS 2, BLAYAIS 3, BLAYAIS 4
GROUP 3 900 Mwe : 21 unitsCRUAS 1-2-3-4GRAVELINES 5 – 6CHINON B3 – B4
• Units with SG replaced in past• 1300 MWe: all 20 units• 1450 MWe : all 4 units
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA13/16
GB ConsultingSYNTHESIS of DURATION FRENCH SGR
DAM10
50
100
150
200
250
BUG5
DURÉ
ES en
JOUR
S
GRA1 SLB1 DAM3 GRA2 TRI2 TRI1 GRA4
Heures en zone
Durée de l'arrêt (jours)
Durée du RGV (jours)TRI3 FES1
140000
120000
100000
80000
60000
40000
20000
HEUR
ES en
ZONE
0
176600dont environ 10000 de RCVSG In 2 Parts
SG In 2 Parts
RPV Inspection Core Zone VPM
SGR Duration
Outage total Duration
Total hours in controled zone
10 000 hours on CVCSTOTAL
D U R A T I O NI N Z O N E
DURATION
IN
DAYS
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA14/16
GB ConsultingPLANNING OF SG REPLACEMENT
GRA4TRI1TRI2
GRA2
SLB1DA3
GRA1BUG5
DAM1
1990199119921993199419951996199719981999200020012002Réalisées
TRI3FES1
DAM2BUG4
SLB2
2003200420052006200720082009DAM4, GRA3, ... ?
TRI4
A venir
SGR Carried out
2003 2004 2005
SLB2TRI4
DAM2
Futur SGR 2007 2008 2009 2010 20112006 2012
BUG 4CHB1, DAM4, BLA1,
IAEA 2nd Symposium on PLIM 15-18 October 2007 – Shanghai CHINA15/16
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~ 20 m
320 tons in weight
Example SGR One Piece Monobloc
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CONCLUSION
The importance of Criteria combined with periodic inspection and in relation with:� The global Maintenance program and strategy
Specific Maintenance and Inspection for RPV and for Steam Generator
� The monitoring to enrich the feedback experience and database collectedon Steam Generator and RPV
� To anticipate the exceptional maintenance Mainly for SGR
� To anticipate to order the strategic componentsare very important for Plant Life Mnagement Strategy
All of actions engaged and applied on 58 NPPs taking into account thelarge informations capitalised in database from the feedback experienceinformations , current Maintenance and exceptionnal maintenance give to the french utility the good approaches to the long term life
Management