IAEA-TECDOC-922 XA Performance analysis

Transcription

1 IAEA-TECDOC-922 XA Performance analysis

2 The IAEA does not normally maintain stocks of reports in this series. However, microfiche copies

3 The originating Section of this publication in the IAEA was: Nuclear Power Engineering Section International Atomic Energy Agency Wagramerstrasse 5 P.O.

4 FOREWORD

5 EDITORIAL NOTE In preparing this publication for press, staff of the IAEA have made up the pages from the original manuscript(s). The views expressed do not necessarily reflect those of the governments of the nominating Member States or of the nominating organizations. Throughout the text names of Member States are retained as they were when the text was compiled. The use of particular designations of countries or territories does not imply any judgement by

6 CONTENTS SUMMARY...

7 7. THE DETERMINANTS OF OPERATING PERFORMANCE Explanatory factors...

8 SUMMARY The WWER-440/230 was the first commercial model of the Soviet WWER design of nuclear power plant. A total of 16 plants of this design were constructed, installed in Russia, the former Czechoslovakia, Bulgaria, Armenia

9 that

10 These two factors meant that highly qualified personnel could be attracted and retained for all important tasks

11

12 under management control because they

13 More generally, the work should have relevance to any countries that possess or hope to launch nuclear power programmes. There is still wide variability in the success with which nuclear power programmes are carried through and uncertainty as to why this variability arises. This work may help to reduce this uncertainty by identifying skills and functions that are of key importance, and features of institutional structures that have proved effective

14 2. ENERGY CO-OPERATION IN THE EASTERN EUROPEAN COUNTRIES ( ) This chapter is intended to highlight the energy resources context and the development of the nuclear area in the former Soviet Union and eastern European countries. The final objective is to outline the general background that, along with the information of the following chapters should complete

15 multinational basis, a programme that fully integrated all of its allies. The CMEA member States pursued this policy with varying degrees

16 TABLE 2.1. ELECTRICITY PRODUCTION

17

18 Sl««4*l l S F

19 Poland: two WWER-440 were under construction at the Zarnowiec station and more two units were envisaged for the same site; a second site, Kujawy, had already been selected

20

21 TABLE 3.1. MAIN CHARACTERISTICS OF THE WWER-440/230 COUNTRY SITE UNIT NUMBER CONSTRUCTION START COMMERCIAL OPERATION SHUTDOWN RUSSIA NOVOVORONEZH KOLA ARMENIA* GERMANY GREIFSWALD** SLOVAK REPUBLIC BOHUNICE BULGARIA KOZLODUY Both reactors were closed following

22 nuclear power plants should

23 because they adopted

24 TABLE 3.3. MAIN CHARACTERISTICS

25 The first "demonstration unit", 100 MW(e), was built in 1958 at the Siberian Nuclear Power Station 5 at Troitsk. Five other reactors of the same type went into operation, at the same site, in the period The fuel cycle of these dual purpose reactors was prevalently oriented to plutonium production for military purposes. were The two reactors -100 and 200 MW(e) respectively - built at Beloyarsk Nuclear Power Station

26 The earliest studies in this field date from A series of research reactors (namely BR-1 - Bystryi Reactor - and BR-2 in 1955, BR-5 in 1959) led to the construction of a first prototype, the

27

28 the WWER-440 design towards that "production oriented layout", that may have contributed to the good operating performance of the first generation of reactors. This concentrated structure

29 problems for plants or in any way affected plant performance. Indeed, Soviet fuel cycle facilities were able

30 Power Safety (Gosatomenergonadzor) 8

31

32 K) Manager (Site Director) Deputy Manager on economics Deputy Manager on security Economic services Deputy Chief Engineer

33 The Deputy Chief Engineer of units 3 and 4 heads the shift operations department, which carries out all operational activities. Five of seven available shift teams are allocated to supporting the

34 5.3. SAFETY POLICY

35 annual reviews of plant operating disturbances are produced, including analysis of causes and recommendations for prevention of such disturbances in future, such reviews being sent to all plant departments; annual reports

36

37 TABLE 6.1. SAMPLE DESCRIPTION Sample Description all WWER-440/230 all WWER-440/213 all WWER-1000 all world PWR, excluding WWER all world

38 The

39 TABLE 6.3. ENERGY AVAILABILITY FACTORS AND YEARLY STANDARD DEVIATION. Sample 1 - WWER-440/230 Bulgaria Russian Federation Kozloduy 1 Kozloduy 2 Kozloduy 3 Kozloduy Slovak Republic

40 6.4. IMPACT OF EXTERNAL EVENTS Table 6.5 shows that the main impact of external events has been in the most recent period, , when planned unavailability

41 TABLE 6.6. WWER-440/230 LIST OF OUTAGES LONGER THAN THREE MONTHS Reactor Kozloduy 1 Kozloduy 2 Kozloduy

42 6.6. CAUSES

43 TABLE 6.9. OUTAGES ANALYSIS

44 TABLE FREQUENCY OF FORCED OUTAGES FOR PWRS TO WWER-440/230 2 WWER-440/213 3 WWER PWR excluding WWER 5 PWR <600 MW(e) 6 Sample of 2 loops US 7 Sample of 4 loops US Rate 1987 No. of Units Rate 1988 No. of Units

45 Scram rate The world

46 Volume

47

48 8. Size

49 may allow valuable resources

50 of the IAEA Incident Reporting System in which some countries participated from the mid-1980s, the plants were not completely open to international scrutiny for safety until Given that

51 Standardisation Standardisation

52 5. A Disciplined and skilled workforce

53 6. Technological prestige This effect relates to the status of these plants as commercial pioneers of a new prestigious technology.

54 particularly with the Paks plant in Hungary. But it may be that, perhaps because of its small generating capacity, the WWER-440/230 is simply a relatively undemanding design which would tend

55 APPENDIX ENERGY CO-OPERATION DEVELOPMENT

56 technical assistance, should have been supplied by the former Soviet Union. The prototype should have been finished

57 technology. In 1967, construction of the first two units of the unified model WWER-440/230 (Novovoronezh 3 and 4) was started. In 1965, the former Soviet Union and the former GDR agreed on the construction of two WWER-440/230 plants in Greifswald (also known as Nord or Bruno Leuschner). One year later, an agreement with Bulgaria

58 (previously Technopromexport) and each counterpart separately. Afterwards Interatomenergo had to become responsible for supplying equipment - or if it was the case the whole plant 13.

59 In , the construction of the two Loviisa reactors started in Finland. Representatives of a unique mixture of Soviet design, American (Westinghouse) containment and German (Siemens) instrumentation and control systems, they can be considered as the precursors of the second (and may be also of the third) WWER generation. Second generation (WWER-440/213) reactors were built later on at Kola (3 and 4) and Rovno (1 and 2) in the former USSR, Bohunice (3 and 4) and Dukovany

60 continue to be a major CMEA supplier of nuclear equipment, 16 eventually including the WWER-1000 (Reisinger, p. 58); in that period, the first unit of this kind was still under construction at Novo Voronezh. As the states were working out an effective division of labour in the nuclear power industry, agreements

61 Energy sector

62 Fox, L.J., "Soviet Policy BIBLIOGRAPHY

63 ANNEXA GENERAL PLANT DESCRIPTION OF THE REFERENCE UNTT WWER-440/ CORE CHARACTERISTICS, REACTIVITY CONTROL, PRIMARY CIRCUIT 1.1. Core Characteristics 1. Fuel material:

64 OS C*. 1 REACTOR VESSEL 2 PRIMARY ISOLATION VALVE

65 2. PRIMARYCIRCUIT SUPPORT SYSTEMS

66 2.2. Make up System General Description Low power feed-in system

67 2.3. Intermediate Cooling System for Main Circulating Pumps General Description Cooling system

68 2.4. Intermediate Cooling System for Rod Driving Mechanism Cooling General Description Closed cooling system

69 3. EMERGENCY CORE COOLING, PRESSURE CONFINEMENT AND SPRAY SYSTEM As previously mentioned

70 Mam components Number of loops: Number

71 Mam Components Number of pressure reducing stations: Capacity (t/h): Inlet steam pressure range (kg/cm 2 ): Process (technological) condenser Type: straight-tube heat exchanger After-cooler Type: straight-tube heat exchanger Long-term cooler Type: straight-tube heat exchanger Cooling pumps Number: Type: KRZ-200/50012 Rated volume flow (m 3 /h): Shutoff or rated head (m of H,O): 2 (one for each unit) 60 <47 Capacity (t/h): 53.0 Capacity (t/h): 53.0 Capacity (t/h): ELECTRICAL SUPPLIES General Description Electrical Supplies

72 6. INSTRUMENTATION AND CONTROL General Description The Instrumentation and Control (I&C) consists of three plains: the sensor plain, logic plain and control plain. The sensor plain is wired up in one train and three channels. The construction of I&C alters from one-train to two-train-system with crossing from the sensor plain to the logic plain. These two trains

73 TABLE

74 TABLE

75

76 Stage inlet steam pressure (kg/cm 2 ): Stage inlet steam enthalpy (kcal/kg): Outlet pressure (kg/cm 2 ): Outlet pressure enthalpy (kcal/kg): Number of condensers: Type: Materials tubes: shell: Automatic cleaning system: Material: Number

77 Pumps Characteristics Number

78 ANNEXB FORMER USSR 1. HISTORICAL REVIEW, POLICY AND ENERGY CONTEXT

79 oo o POLITBÜRO SECRETARIAT (ENERGY) COUNCIL

80 Acting as advisory committees to the Council of Ministers there have been :

81 c. The USSR Ministry of Heavy Power and Transport Machine Building: responsible

82 poor economic convenience of such a choice. To outrun that reason, since the early stages an intensive effort

83 uranium prospection, to bring the enormous Atommash Works, for serial production of reactor vessels and other components under pressure,

84 1.3. Energy resource The USSR had at its disposal probably almost all the resources needed to assure the country's economic development. Cod

85 A great effort

86 FYP ( ) about MW(e) were installed,

87 TABLE 3 - TRANSMISSION LINES EXTENSION (1000 km) KV YEAR 1500 (cc) 1150 (ca) (*) 2, (*) initial estimate The Central Supervisory Control system of the electric power industry has to ensure not only an uninterrupted supply

88 TABLE

89 BIBLIOGRAPHY Lavrencic,D., "L 1 energíanucleareneipaesi del COMECON", NotiziarioCNEN, anno 23, n.3,1977. Dienes,

90 ANNEX C FORMER CZECH AND SLOVAK FEDERAL REPUBLIC

91 in the agriculture, it is necessary to consider the needs of the industrial fertilizers not only as the whole quantity but also as to the assortment and quality. The main reasons given for the nuclear continuing programme are that nuclear energy is environmentally clean, safe, economic

92

93

94 General Manager SEP Headquarters Bratislava Nuclear Power Plants Headquarters Qualified workers training centres - SOU-e Tmava

95

96 2.2. Manufactures

97 at the site. Fire brigade consists of about 70 men. Fire prevention section consists of 5 persons. The scheme

98 3. DESCRIPTION OF NPP ORGANIZATION, MANAGEMENT AND POLICY 3.1. Plant Operation Structure Original plant organization structure (see Figure 6) was created according to the CSFR practices and as it was used for the first NPP with the HWGCR reactor. For WWER 440/230 it had to

99 Plant manager office 102 jurists control security computer center personnel secretary control development systems Department economic

100 (foremen, technicians). Training

101

102 Confinement systems: improvement of confinement tightness; obtaining a subatomospheric pressure in the confinement within the required time period after beginning of small LOCA; protection

103 Steam generators, pressuriser

104 ANNEXD BULGARIA

105 The primary resources limits, the growth of the electricity demand, and the world's scale of the nuclear power plant development, were the background of the nuclear power strategy during the period Bulgaria

106 or million

107 TABLE 5 - ELECTRICITY IMPORTS/EXPORTS (bn kwh) IMPORTS EXPORTS TABLE 6 - ELECTRICITY PRODUCTION (GW(e).h) Nuclear Thermal Hydro Total Nuclear Share

108 TABLE 7 - ELECTRICITY CAPACITY Nuclear Capacity (MW(e)) ,224 1,224 1,633 1,632 1,632 1,632 1,632 2,585 2,585 2,585 Total Capacity (MW(e)) 6,169 7,060 7,210 7,082 7,518 7,993 8,197 9,059 9,499 9,633 9,798 10,243 10,243 10,743 11,309 11,113 Share

109 feedback measures. Contracts with outer organizations and research institutes are signed on some problems, which

110 2.4. Public Acceptance During the last years, the public concern about the nuclear power plant's operation is studied, discussed and paid greater attention by the media and the government. In the country exist some individual

111 3.2. Management Politics (Planning, Staff Organization, Training, Leading and Controlling, Research and Development) Planning:

112 maintenance schedule (PPM). It includes prophylactic, current and main repair of all main and supplementary equipment

113 the required core subcriticality with shut down reactor in cold condition. Calculations have been carried

114 ANNEXE OTHER PERFORMANCE INDICATORS 1. KOZLODUY NUCLEAR POWER PLANTS (UNITS 1, 2, 3 AND 4) 1.1. Number

115 1.4. Thermal Performance and Self Consumption Table 2 - Adjusted Actúa] Gross Heat Rate (kj/kw.h) Unit Design gross heat rate (kj/kw.h)= Unit Unit Unit Table 3 - Thermal Performance Note: Thermal performance Unit Unit Unit Unit

116 Table

117 1.7. Core Average Burnup

118 1.9. Fuel Reliability Table 8 - Iodine 131 and Iodine 134 Activity (in microcurie per gram) Unit 1-13] S S I

119 1.10. Purification Rate Constant Table

120 2. BOHUNICE NUCLEAR POWER PLANTS (UNITS

121 2.5 Collective Radiation Exposure (unit exposure based

122 Table

123 Table 18 - Average Bumup of Replaced Part of Fuel (Discharged Portion) (MW.d/kg U) Unit

124 "Aerosols

125 -,13l /106

126 3. KOLA NUCLEAR POWER PLANT (UNITS

127 3.3. Time

128 Table 24 - Self Consumption (MW(e)) Unit Unit Collective Radiation Exposure Table 25 - Collective Radiation Exposure S SO SE 19S ~j/-i^» ^O.' 19S Unit 1 ri -^T"i O Ci O SO. 39 E EE E4.E 151

129 3.6. Volume of Low and medium Level of Solid Radioactive Waste Table 26 - Volume of Low and Medium Level of Solid Radioactive Waste (8 mcu/sec.) JL '"SÍ

130 Table 28 - Volume of High Level Solid Radioactive Waste (>260mCu/sec ) W Unit 1 U n i t 2 D" W <i i Sí S missing " II IÍ! It II It " ' II " il 11 p " missing _ u D 4,6 4,3 5,34 0,3 0,75 0,32 1,3 0,5 1,03 5,42 4,34 /i. se 1 i«-. Table 29 - Volume of Radioactive S S1 198E Sa

131 3.7. Core Average Burnup

132 3.9. Fuel Reliability Table 32 - Parameters of Reliability of Fuel (Rated Activity x 10-5, Cu/I) Year Before

133 'X' CO OJ Xi CO CO en CO O O O O O O O O O e co -J cr, i_n.e to ru M. m 03 vi cr, en ja to ru *-* ru ^ o'u O O O O O '"' O' O O

134 1S O Ol OE O3 O 4 05 O6 07 OS IE 01 OS O6 07 OS OS- 10 li 12 Ol OE 03 O OS IE Ol OE O3 O4 O5 O6 07 OS O9 1O 11 IE 0,36 O,36 O,31 0,27 0,36 0,5E 0,55 0,61 5,7 5,4 O f\ *-r

135 3.10. Purification Rate Constant Table 33 - Parameters of purification of Coolant of 1 s circuit Year Month A Unit S O OS «- J. -. IE 01 ' OS OS OS O9 10 i i ,' ~7

136 193; Í 1936 OS io 1Í IE Ol OE OS 09 IO 11 IE Ol OE OT- OS OS IE 01 OS O7 03 OS IE Ol OE O6 O7 OS 09 IO 11 IE - 0,1 0,1 0,1 0,1 0,1 0,1 0,1 o-;i 0,1-0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1 0,1-0,1 0,1 0,1 0, ,1 0,09 O.1O + 0,1 + 0,O9+ - o,os 0,05

137 19SS 19S9 199O O4 05 O6 O7 OS IE 01 OE OS Í1 IE -01 OE O OS O IE Ol OE O5 O6 O7 OS 09 1O 11 IE 0,1O - 0,10 O,09+ 0,09 0,09 0,1O 0,09+ O,09 0,1 0,1 + 0,1 0,1 0,1 0,1 + 0,1 0,09 0,10 0, 09 0,1 0,1 0,1 0,1 0,1 0,1-0,1 O.1 + 0,1 + 0,07 0,1 0,1 0,1 0,1 0,1 0,1 _ 0,1 0,1 0,1 0,1 1 GO 100 loo loo 1OO 10O 1OO 1OO 1OO 1OO 1OO 10O OO 1OO ioo 1OO 100 IOO ÍOO 96 IOO IOO 100 1OO 100 IOO IOO IOO 1OO 100 0,10+ 0,10+ 0,10 0,10 0,10 0,10 O,O5 0,05 0,10 O,O9+ 0,O9 0,1O O.lO-s- 0,10 0,10 O,1O O,1O 0, , 0,1 + O,O6+ O,O6+ O,O9+ O,10 0,10 0,1 0,1 0,10 0,1 0,1 0,1 0,1 0,10 IOO IOO SE unstable 96,SE unstable IOO OO 100 IOO 1OO 1OO 100 unstable Note: - Planned maintenance

138 4. NOVOVORONEZH NUCLEAR POWER PLANTS (UNITS 3 AND 4) 4.1. Number

139 4.3. Time of Reactor Critical (i.e. annual hours that the reactor was critical) Table

140 Table

141 4.6. Volume

142

143

144 Table

145 5.5. Collective Radiation Exposure (unit exposure based on TLD or film badge) Table 43 - Collective Radiation Exposure (man Sv) for all Units ysar

146 5.6. Volume of Low and Medium Level of Solid Radioactive Waste Table 44 - Solid Radioactive Wastes (Low and Medium Level 0 ) in m 3 year 1974 wasre I9S ) C

147 5.7. Core Average Burnup

148 Table 46 - Fuel Burn-up of the Unloaded Fuel (MW.d/kg uranium) year i unit l uniü 2! i j 1975

149 5.9. Fuel Reliability Table

150 Table

151 Table 49 - Reliability of the Nuclear Fuel - Unit 3 refuelling cycle 4/73-5/79

152 Table

153 Table 51 - Stack Exhaust for Twin Unit I (Units 1 and 2, one vent stack for both) year aerosoles * ' (MBq) i noble gases (TBq) loaine (MEq; S8S S C S8! 407 l 388! & c SS

154 Table 52 - Stack Exhaust for Twin Unit I (Units 3 and 4, one vent stack for both) year ?

155 ANNEX F THE IAEA POWER REACTOR INFORMATION SYSTEM (PRIS) Virtually every publication, paper

156 performance factors

157 ENERGY CO-OPERATION ANNEX G

158 160 F/g. 1. Former CMEA Member Countries, 1993

159 The organizational structure of the CMEA comprised the Session (yearly or twice yearly meetings of Prime Ministers), the Executive Committee, established in 1962 (several yearly meetings of Deputy Prime Ministers), the Standing Commissions, which were established

160 COUNCIL SESSION EXECUTIVE COMMITTEE COMMITTEE ON CO-OPERATION IN PLANNING COMMITTEE

161 In 1960, at the XIII CMEA Session, a fourth Commission, the Standing Commission for Peaceful Use of Atomic Energy was established. This was based in Moscow and was in charge of organising scientific

162 INTERSTATE ECONOMIC ORGANIZATIONS MIR dispatcher INTERELEKTRO International Bank for Economic Co-operation International Investment Bank CMEA SECRETARIAT INTERNATIONAL RESEARCH ORGANIZATIONS DUBNA INTERNATIONAL ECONOMIC ORGANIZATIONS Interatominstrument Interatomenergo Fig. 3. CMEA Organizations 164

163 Czibolya, CONTRIBUTORS TO DRAFTING AND REVIEW

164 Regneil, B. Sturm,