Transcript Ростовская АЭС, блок №1
1000 900 800 700 600 500 400 300 200 100 0 0 1 882 0 0 2 832 VVER-1000/440 RBMK-1000 782 532 40 40 3 210 4 160 5 384 6 384 384 384 7 8 2
Programme for increasing power output at operating NPP units of Rosenergoatom Concern Investment programme of Rosenergoatom Concern for the period of 2007-2010
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REA orders: of 10.04.2007, No. 331 of 21.05.2007, No. 496 NPP orders Subprogrammes for lines of activities Work programmes and time schedules 3
I II III IY Y YI YI I YIII IX X XI XI I I II III IY Improvements in engineering design of reactor facility, demonstration of safety and changes in SAR and OD Y YI YI I YIII IX X XI XI I I II Environmental impact analysis Changes in license terms Changes in license terms Pilot operation at Nnom 4
Modification of engineering designs of the reactor facility and NPP with definition of requirements for upgrading of process monitoring and control equipment;
Development of modifications to SAR to prove safe operation of nuclear power units at increased power;
PSA updating for comprehensive assessment of design safety levels associated with operation at increased power;
Analysis of environmental impacts resulting from operation at increased power, and development of compensatory measures.
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(CDF, 1/yr.) 1,20E-04 1,00E-04 8,00E-05 6,00E-05 4,00E-05 2,00E-05 5,00E-19 -2,00E-05 4,40E-05 2BAL International requirements for CDF 4,44E-05 3KLN 5,52E-05 1RST 1,88E-05 1,22E-05 1KUR 2LEN 6
Upgrading of CPS / IMCPS equipment Instrumentation upgrading to improve the accuracy of measuring process parameters Upgrading of in-core instrumentation, power restriction devices, and interlocks Upgrading of the flow-through part in the first stage of the HPC rotor Generator upgrading (introduction of a system for monitoring vibrations in the working components of the generator) 7
Exciter side Group 1 Turbine side Group 2 Stator core Group 3 Tables Vibration monitoring system of TG-3 Arrangement of vibration sensors Vibration data Group 1. Exciter side Location Pressure ring Vertical diameter Pressure ring Horizontal diameter Spacer ring Vertical diameter Spacer ring Horizontal diameter Pressure header Busbar connectors against slots 17, 19 Busbar connectors against slots 17, 19 Busbar connectors against slots 37, 47 Busbar connectors against slots 37, 47 Phase lead C4 connection bus Phase lead C5 connection bus Phase lead C6 connection bus Zero lead 1C1 connection bus Zero lead 2C1 connection bus Zero lead 2C3 connection bus Measurement direction Radial Axial Radial Axial Radial Axial Radial Axial Radial Axial Radial Radial Radial Radial Radial Axial Radial Axial Radial Axial Radial Axial Radial Axial Radial Axial Show all Hide all 8
Monitoring of core neutronics Checking of thermal hydraulic characteristics Separation testing of SGs and DSs Thermal monitoring of the generator and its systems Confirmation of conveyance capacity of condensate and feedwater lines Fuel cladding leak tests Load variation tests RCP trip tests Tests with one TG trip (for VVER-440 and RBMK) Checking of the reactor power constraints Checking of the electronic system of hydraulics regulation for stability 9
Instrumentation systems of power units showed trouble-free performance;
The neutronic characteristics and thermal parameters of reactor facilities in the process of power increase are consistent with the design data and stay within the permissible limits;
The performance of automatic power regulators, power restricting devices, pressure regulators, IMCPS and other systems for regulating and monitoring the reactor facility equipment parameters, is consistent with the design;
The capacity of the condensate and feedwater lines was confirmed during reactor operation at an increased power level;
Vibrations in the end areas of the generator, in TG bearing supports and in the main steam and feedwater lines showed practically no variations in the process of power increase;
No radioactive releases into the ventilation stack were observed.
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Maximum permissible Тin 1 – Т in 11
Maximum permissible
Т 2 – ΔТ 12
1,6 1,55 1,5 1,45 1,4 1,35 1,3 1,25 1,2 1,15 0 Kv Kv (add) (for zone 6) Kq Kq (add) 50 100 150 200 250 300 350 Т eff. day 13
1,0E-02 1,0E-03 1,0E-04 1,0E-05 1,0E-06 1,0E-07
Удельная суммарная активность изотопов йода в теплоносителе первого контура энергоблока 2 Total specific activity of iodine nuclides in primary coolant of Unit 2
4500 4000 3500 3000 2500 2000 1500 1000 500 0
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Fuel integrity parameters and environmental impact during Balakovo-2 operation at 104% power Parameter Power level 100 % Nnom.
104 % Nnom.
Operating limits Specific activity of iodine nuclides in primary coolant ∑А I normalised to the design flow rate of the water treatment system SVO-2, Ci/kg I-131 activity normalised to the design flow rate of SVO-2, Ci/kg 2.64∙10 3.0∙10 -6 -8 2.86∙10 3.2∙10 -6 -8 1.0∙10 -3 Steam generator leaks
SG 1-4 none none 4 kg/h No increase in radioactive releases into ventilation stack was observed during pilot operation at the power level of 104 %;
No increase in natural gamma background was recorded by the automatic radiation monitoring system in the control and surveillance areas.
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For VVER-1000, tests were performed at power levels of 100%, 102%, and 104%:
Steam moisture content at SG outlet did not exceed the specified level of 0.2%.
For VVER-440, tests were performed at power levels of 90%, 100%, 104%, and 107%:
Steam moisture content at SG outlet did not exceed the specifies level of 0.25%.
For RBMK-1000, tests were performed at power levels of 100%, 101%, 102%, 103%, 104%, and 105%:
Steam moisture content at DS outlet did not exceed the specified level of 0.1%.
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With the original louvred arrangement of the separation system, the specified moisture content (0.2%) was reached when the boiler water level rose to +70 mm from Hnom.
With the separation system upgraded to use a punctured sheet, the specified moisture content (0.2%) was reached when the boiler water level rose to +150 mm from Нnom 17
Operating algorithms of the automatic power regulators, power restricting devices, pressure regulators and IMCPS are consistent with the design;
Operating algorithms of interlocks geared to pressure in the primary / forced recirculation circuit are consistent with the design;
Operating algorithms of SG and DS makeup and level regulators are consistent with the design;
Primary and secondary circuit parameters can be regulated during transients without reaching the setpoints for actuation of emergency and preventive protection devices;
Vents to the atmosphere (BRU-A) did not open during the tests.
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Balakovo-2 (pilot unit) Volgodonsk-1 (pilot unit) Balakovo- 3 Balakovo-4 Balakovo-1 Kalinin-1 Kalinin-2 Kalinin-3 Kola-4 (pilot unit) R&D, upgrading R&D, upgrading 104% R&D (E), upgrading R&D (E), upgrading R&D (E), upgrading 104% 104% 104% R&D, upgrading R&D (E), upgrading R&D (E), upgrading R&D, upgrading Kola-3 R&D (E) – extension of R&D results from pilot power units R&D (E), upgrading 104% 104% 104% 104% 107% 107% 19
Kursk-1 (pilot) Kursk- 2 Leningrad-2 Leningrad-3 Kursk-3 Leningrad-4 Kursk-4 Smolensk-1 Smolensk-2 Smolensk-3 2006 2007 R&D, upgrading 2008 2009 105% 2010 2011 R&D (E), upgrading R&D (E), upgrading R&D, upgrading 105% 105% 105% R&D, upgrading 105% R&D, upgrading R&D, upgrading R&D, upgrading R&D (E), upgrading R&D (E), upgrading 105% 105% 105% 2012 2013 105% 105% 20
Balakovo-2, 3, 4 and Rostov-1 – to continue pilot operation at the power level of 104% Nnom; Balakovo-1 – to obtain a permit for pilot operation at 104% Nnom; Kalinin-1, 2, 3 – to carry out tests at 104% power after planned outage of 2010 and to obtain a permit for pilot operation at increased power for Units 2 and 3; Kola-3,4 – to obtain a permit for pilot operation at 107% Nnom; Kursk-1 – to continue pilot operation at 105% Nnom; Kursk-3, Leningrad-3 – to carry out tests at 105% Nnom; Kursk-2 and Leningrad-2 – to obtain a permit for pilot operation at 105% Nnom.
The expected output growth in 2010 due to increased power of plants will be in the order of 2.0 billion kW*h.
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OJSC Gidropress, RRC Kurchatov Institute and OJSC VNIIAES carried out research to assess the scope for increasing the power of VVER-1000 reactors.
Research objectives:
To assess the scope for increasing reactor power subject to the condition of meeting all safety requirements with conservative restrictions removed;
To assess the economic expediency of upgrading VVER-1000 plants so as to provide the greatest possible power increase subject to the condition of safety assurance.
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It is impossible to prove the dynamic stability in some transients with the use of the existing software products.
It is impossible to improve the accuracy of thermal power monitoring for changeover to measurement of local core parameters without upgrading in-core instrumentation.
It is necessary to consider the influence of heat transfer intensifiers in computational validation of adopted criteria.
It is necessary to verify the service life of the reactor vessel and core enclosure.
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Kurchatov Institute and Gidropress have proposed some methods for reducing conservatism in the existing procedures for proving safe operation of VVER-1000:
Calculation of the CHF margin;
Allowance for coolant mixing across the FA section;
Calculation of engineering safety factors;
Selection of governing conditions and initiating events for safety analyses.
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R&D is required for:
assessing and predicting the state of critical reactor facility components :
reactor vessel (due to higher fluence);
enclosure (due to temperature- and radiation-induced swelling);
developing and validating procedures for justification of SG upgrades Enclosure Core Reactor vessel 25
Stationary and emergency operating conditions of VVER 1000 cores were verified by neutronic calculations;
The performance of VVER-1000 protection systems was analysed and shown to be adequate in terms of safety under conditions of power increase;
Safety maintenance at 110% of nominal power was shown to be basically feasible;
It was proved necessary to requalify Normal Operation with load shedding from 110% to 30% as an Operational Occurrence on account of the reduced margin to opening or due to direct opening of vents to the atmosphere (BRU-A).
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Upgrading was found necessary for:
Steam generators (steam separation system);
Basic electrical components (generator, KAG-24, current carrying wires);
Power unit turbine and regulation systems.
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Efficiency indicators Without replacing the generator (to 107% Nnom) With the generator replaced (to 110% Nnom) Investment costs in prices of 2008, million roubles
825.0
Power increment, MW
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Unit cost of additional power, $/1kW Note: The cost of 1 kW of installed capacity for new build is $2000 per 1 kW Pay-off period (from the moment first benefits are gained), years
916 4.5
Both upgrading options are economically sound.
1 725.0
60 958 9
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Stages in the work for increasing VVER-1000 power to 110%
Making a decision to increase power to 110%. Licensing and implementation.
110% Tests at the power level of 107% Preparation of documents for tests. Licensing Upgrading of monitoring, control and protection systems Upgrading of turbine and regulation systems Generator upgrading (or replacement) Justification of SG upgrading, design and development of the upgrading procedure. Installation and development of test programmes.
Safety case for power increase to 110%. Updating of the reactor facility and core designs. Updating of the SAR.
Feasibility analysis and development of the work programme.
- completed 104% 29
Reactor facility safety case, reactor facility design modification, updating of SAR and OD for 110% power R&D, upgrading justification, designing, licensing, and upgrading of the basic equipment Ordering, manufacture and upgrading of I&C systems Environmental impact analysis Development of test documentation 30
Strong points
Specific costs of 1 additional kW are roughly a factor of 2.5 less than with construction of a new VVER-1000 unit; Upgrades are made during planned outages. Weak points
The degree of original conservatism in ensuring safe operation is decreased; The planned outage time is increased due to upgrades.
Benefits
Successful implementation of the project will allow extending this experience to other operating VVER-1000 units; The results obtained in increasing power of operating plants will be used in design of new plants.
Threats
The equipment and services will be more expensive.
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The results of tests and the experience of running power units at increased power levels confirmed the feasibility of stable and safe operation of VVER-1000 units at 104%, of VVERs-440 at 107% and of RBMKs at 105% Nnom;
It was found to be possible and expedient to raise the power of VVER-1000 plants step by step from the nominal level (reference unit 4 of Balakovo NPP) to 110% with the additional benefit of extending such experience to other operating VVER-1000 units and of using it in design of new NPPs.
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THANK YOU FOR YOUR ATTENTION!
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