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License Renewal at Paks NPP
Project Technical Tasks
Sándor RÁTKAI, LR project technical head, PAKS NPP
Telephone: 75/508576, fax: 75/507036
E-mail address: ratkai@npp.hu
1st Hungarian-Ukrainian Joint Conference on
„Safety-Reliability and Risk of Engineering Plants and Components”
Miskolc, Bay Z. Institute; 11th April, 2006.
Why can we speak about LR?
World tendency
Feasible in the sense of safety and technical aspects
Good business
Decision of the owner
Society support
Political support
Existing regulation
Why to extend the operational lifetime?
Hungarian electricity supply - present situation and
perspectives
– Environmental aspects: Kyoto obligations – it is
possible only if nuclear is considered
– Security of supply – considering available sources and
reliable markets to control the import dependence
– Competitiveness of the economy – reliable and cheap
electric energy is required
Hungarian electricity production
Today: Well Diversity of the
balanced system ensured
system, the according to
Kyoto targets •sources
could be met coal •technologies
Nuclear
39%
24,8%
•import market
10% system
capacity reserve
exists
oil, gas
34,7% Total domestic consumption
2004: 41 118 GWh
water Total domestic production
0,6% 2004: 33 708 GWh
Needs for new capacities
12 000
11 000
10 000
new plants
9 000 import
8 000 renewables
peak demand
7 000
6 000
hydrocarbon
5 000
4 000
3 000
coal
2 000
1 000 nuclear
0
2005 2010 2015 2020
Construction of 6000 MW capacity is needed between 2005 and 2020
(to replace the old capacities and cover the increasing needs).
Domestic market - 2004
12000 20
GWh
11111.83 sold GWh Ft/kWh
av. price Ft/kWh 18
10000
16
14
8000
12
6000 10
8.5
Largest, cheapest 8
4000
domestic producer! 6
4
2000
2
0 0
Termelő
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Source: www.eh.gov.hu
A
Renewable production in 2004: 884 GWh state support: 16.495 MFt 5,95 Ft/kWh
Regulation
Activities for the sake of LR -- LTO
Environmental Licensing
1
NEW
Nuclear Licensing 4. Issue of the
Authority license
7. Authority revew
(Making of LR application report)
review
5.
2. 3.
2 LR „program” making
Demonstration
of commitment
Technical tasks
6.
License application
document
1.
Feasibility study 1 2 IMPLEMENTATION
1. Operation due to LAR
Project Plan 2. Reconstruction, upgrad
1. TLAAs 2010.
2000.
2. Ageing
2011. 2012.
2008.
2002.
2009. 1. unit
REVIEW OF THE PROJECT TASKS
No. Tasks of the project
1. Determination of the scope of the license renewal and
methodology
2. Overall review of the current ageing management
practise
3. Solving the currently known unresolved issues
( from feasibility study)
4. Time Limited Ageing Assessment (TLAA)
5. Other TLAA tasks
6. Currently known ageing management measures
7. Introduction of the new maintenance rules: evaluation,
methodological task, development of programs
8. Finalisation of the programs for equipment qualification
+ methodology development
9. Condition maintaining activities (making reconstruction
plans)
10. Elaboration of the measures derived from the
comprehensive review of the current ageing management
programs
11. Activities to obtain the nuclear safety licence-in-principle
12. PR activities
13. Implementation of the reconstruction and investment
plan
14. Finalisation of the EQ (deficiencies)
15. Fulfilment of the new maintenance rules (effectiveness)
Integrated Plant
Assessment
(Review of the AMP)
SCOPEING + SCREENING of LR
1. Separately managed components:
• Reactor pressure vessel
• Reactor cover
• Reactor inner components
• Pressurizer
• Steam generator
Scoping: Safety Class 1-3
• Main circulation pump
• Main gate valve Screening: Long lived, passive
•………….
2. Review units and commodity groups:
Safety class Type of component Working medium Type of Material
SC 1 Housing of valves Primary water Austenic
SC 2 Housing of pumps (boric acid) Ferrite
SC 3 Piping Duna water ….
4T, which Vessels Steam
failure Heat exchangers ….
threatens Acid/alkali
safety ….
Integrated Plant Assessment
• Review includes: assessment of the SSCs aged
status in context with assessment of
effectiveness of existing AMP
• Review is extended also to plant programmes
in general, i.e. ISI, T, maintenance practice
(ASME BPVC sections XI,V)
• Items not included into the scope of LTO are
covered by PLiM
• Action items: improvement or new programmes
if needed
• Review the condition of the equipments
Review and assessment of the AMP
• To demonstrate for the extended operational
lifetime that:
– The safety and ageing analysis remain valid and could be
projected to the end of intended operational lifetime;
– The effects of ageing on the intended function(s) will be
adequately managed;
– There is a procedure to deal with unexpected ageing
mechanisms that can surface later in the years.
• In many cases, the plants existing ageing
management programmes can be credited as
acceptable programmes for LTO. For the remaining
cases, either the plants existing programme can be
augmented to satisfy the attributes listed above or
new programmes should be initiated.
TLAA Review
Time Limited Ageing Analysis
TLAA are defined as those licensee calculations
and analyses (qualifications) that satisfy the
following:
– Involve systems, structures, and components within the
scope of license renewal;
– Consider the effects of ageing;
– Involve time-limited assumptions defined by the current
operating term, for example, 30 years;
– Were determined to be relevant in making a safety
determination;
– Involve conclusions or provide the basis for
conclusions related to the capability of the system,
structure, and component to perform its intended
functions; and
PROJECT TASKS-- TLAAs
1. Embrittlement of Reactor Pressure Vessel
• PTS
• p-T curves (normal operation & pressure test)
2. Strength + Fatigue calculations /check of the design/
• benchmark tasks (tank, piping, flange)*
• load catalog
• strength calculations fatigue calculations (ASME BPVC 2001.)
• thermal stratification
3. Stability of indications (crack growth )
4. Extension of Environmental Qualifications (I&C)
5. Other TLAAs
• cranes
• (review of operational limits) ----- preparation of the list
Remark:
* Also for PTS
OTHER PROJECT TASKS
1. Civil Structures
• Examination of soil stability (preparation of soil model--sinking);
• Examination of SC 2 structures due to high temperature ( check
of >70 °C environments);
• penetration, examination of machine foundation, liners;
2. Introduction of Maintenance Rule
• Guidelines for establishment of monitoring of maintenance goals
(deterministic and risk based) (all of specialty);
• Benchmark (High pressure safety injunction system);
3. Configuration management programs (Programs for reconstruction
short, medium, long terms)
4. I & C program modification
5. Making of Final Environmental Usage Report
PROJECT ORGANIZATION
RELATED ACTIVITIES: PROJECT Project Supervisory
HUMAN PROGRAM, MANAGEMENT Board
PUBLIC RELATIONS
Project administration
LR PROJECT TEAM
In-house team
PROJECT PLANNING,
team SCHEDULING,
CO-ORDINATION,
Power Uprating CONTRACTING,
DOCUMENTATION, QA
FSAR upgrading
Scientific committees:
Reactor, Mechanical Eq.,
Civil structures, ISI,
Water chemistry
Thanks for your attention!
PTS analyses
1. HAEA guideline (Analyses of RPV due to PTS events, No.:
3.17);
2. Scope of PTS transients (10-5/év);
3. Termo hydraulic analyses (transient pressure, temperature);
4. Calculation of neutron fluent at RPV;
5. Calculation of allowable Tk (critical transient temperature)
value (fracture mechanics);
6. Evaluation RPV embrittlement;
7. Determination of the lifetime of RPV;
8. Determination of technical and administrative measures for
50 (60) years of RPV lifetime;
9. Summary of PTS results for FSAR;
10. Summary (PR document);
Deadline: End of 2007
Scope of the calculations
Scope: Safety Category 1&2 systems
1. Equipments in the main coolant system (Class 1):
• Reactor + reactor internals
• Pressurizer & MCP & MIV
• Steam Generator
• Main coolant piping
1. Class 2 systems:
• Piping
• Heat Exchangers
• Pumps
• Tanks
• Valves
Main Passive/Active
VVER 440/213 Components
MCP shaft/A
Steam Generator/P MCP pump/A
MCP housing/P
MGV shaft./A
MGV motor/A
MGV housing/P
CR drive/A
CR drive housing/P
Primary
piping/P
REACTOR/P PRESSURIZER/P
pressure vessel
heater patron /P
Cable/P
Check of the design against ASME BPVC code
requirements for selected SSCs
Tasks:
1. Strengths calculations (& embrittlement) (ASME I, III, XI);
2. Review of overpressure protection ;
3. Fatigue calculations (50+10 years, power up rating: 108%,
thermal stratifications);
4. Determination of fatigue monitoring places and
parameters;
5. Summary document for FSAR
Deadline: Mid of 2007.
Political support
On 21th November, 2005 the Hungarian Parliament has approved a
resolution (votes with 339 Yes, 4 No, 8 Abstention):
1) To initiate activities of preparing for establishment of radioactive
waste repository for low and medium level of radioactive waste,
2) Extension of the operational life time of PAKS NPP
The resolution reads as follows:
“Under Act CXVI of 1996 on Atomic Energy, Article 7, Section (2) the Parliament
approves, preliminarily and in principle to initiate activities of preparing for the
establishment of a radioactive waste repository for low and medium level waste in the
administrative area of Bátaapáti, in the region of Bátaapáti (Üveghuta), in a territory
which was previously qualified suitable from geological point of view.
The Parliament takes note of the information on the extension of the
operational life-time of Paks Nuclear Power Plant, as a solution necessary for
the long-time and safe provision of the country with electric energy.”
