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Download Docsity.com - Collection of Academic Documents and more Slides Chinese Language in PDF only on Docsity! ABR! Le 2 SH CHASHMA NUCLEAR POWER PLANT PROJECT UNIT-2 el ERAS Title CONTROL ROD CONTROL SYSTEM MANUAL The copyright of this document is the property of SNERDI, unauthorized disclosure to any third party or duplication is not permitted. é, ASFA A LAER TILT DEP, ARAN OYE HL BLE BLS SB = 77 NEL al LA, EME LES GE Index No. Compiled by SHANGHAINUCLEAR ENGINEERING RESEARCH AND [Fy DESIGN INSTITUTE Confidential Z ‘® PC /2 17CCR 001 $040 45 GN 5 iit Bo | 2005.11] CEC 4 a\ %& Detailed Design Gyn | A | 2003.11] PRE SE SIPF ABA IE WR | EMA | KAS eK e@ wm ih W Hk HE Rev. Date Status | Reviewed by | Modification Observations | Approved by PLS AakeS S.C. 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PC2-03-12-03-06 RARE hee 8 Oe HOLD 1. LIFT COIL ON 2.5.6. COIL ON 3. M.G. COIL OFF 4, LIFT COIL OFF 5. M.G. COIL ON 6. S.S. COM OFF 3 docsity.com Bros PC2-03-12-03-06 EL MES RATA Rev, B C613 HOLD 1. $6. COIL ON 2. M.G. COIL OFF 3. LIFT COW. ON a MG. COL ON 5. S.G. COIL GFF 6. LIFT COIL GFF ® docsity.com SERS Hi 2 Se aA PC2-03-12-03-06 Rey. B C6-16 RA “OUT” CYCLE ARAKAE STATIONARY GRIPPER COIL | 33 420} rays | | MOVABLE GRIPPER COIL | J 03 52 98 126 © COUNTS 128 it Blip 128 COUNTS "IN" CYCLE RABE LEFT COIL Bey ak STATIONARY GRIPPER COIL po 67 103 3 qeonemll | MOVABLE GRIPPER COIL. 1 12 a3 22 63 0 COUNTS seein 128 COUNTS Fig, 6.2.3 Aaah CRDM COIL E: TRIC TIMING DIAGRAM docsity.com temIS tl) LAR 2 SHA CHASHMA NUCLEAR POWER PLANT PROJECT UNIT-2 tee PERE ARAB Title CONTROL ROD CONTROL SYSTEM MANUAL BIR RED Hse ip An ee RU Li LISI Byun SHANGHAI NUCLEAR ENGINEERING RESEARCH AND DESIGN INSTITUTE 2 oe i>. eas i ELT FAT ME Index No. Compiled by EI&C Dept. 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FA x et web Checked by a AR . f Reviewed by Gong Yi Soy ¥ aSfaat Ren he en os thee Approved by TPR. é Yof RAE S ARDS 203-12-03- $.C, No. Internal No. PC2-03-12-03-01 docsity.com PCa 03-01 CONTROL ROD CONTROL SYSTEM MANUAL Rev. Bo EI~1 1 Summary 1.1 General This manual states the function, design bases, system description and conirol bases of the control red control system(CCR), which includes trip breaker cabinets. Only one set of CCR system equipement is provided for the plant. 1.2 Contents Chapter Title Reference Revisio n 1 Summary PC217CCRO01S04045GN B Ll General 1.2 Contents 13 Updated revision Function PC217CCRO02804045GN B 21 General function 22 Safety function 3 General design PC217CCRO02804045GN B 3.1 Design bases and criteria 3.2 Equipment design 3.3 Choice of material-construction 4 Description of System and | PC217CCR002S04045GN B Equipment 4.1 Description 4.2 Characteristics 43 Layout 5 Operating Parameters PC217CCRO02804045GN B 5.1 Normal operation | 5.2 Particular steady operation 53 Particular transient operation 5.4 Startup and normal shutdown 5.5 | Other operations 5.6 Control principles : docsity.com PC2-03-12-03-02 CONTROL ROD CONTROL SYSTEM MANUAL Rev. B_E2-1 2 Function 2.1 General function Core reactivity and neutron flux are controlled by combining the effects of a soluble chemical poison (boric acid) dissolved in the reactor coolant with the action of control rod cluster assemblies (RCCA) made of neutron absorbers. The Control Rod Control System (CCR) is used to withdraw and insert the RCCAs. Core axial power distribution varies with insertion of RCCAs. If this core axial power is imbalance, it would be detrimental to optimum utilization of fuel. In order to minimize core flux asymmetry, control rod shall be operated in a pre-programmed sequence. The arrangement of control rod drive mechanisms have also been determined and fixed for the same purpose. A negative reactivity margin is provided by the shutdown banks which are fully withdrawn position from the core during normal operation. Manual control of the neutron flux distribution is provided by moving the shutdown bank Al or A2. Trip breakers are controlled by the reactor protection system. When receiving the trip signals from the reactor protection system, trip breakers are opened. Then the power supplies to CRDMs are lost, all the control rods drop into the core by gravity. Control rod control system consists of: a. Equipment for RCCA operation: ® control rod drive mechanisms (CRDM), ® electronic control equipment for CRDM, ® main control room equipment for manual operation of control rods and monitoring of movement. b. Equipment for rod position monitoring: (refer to “control rod position indication system manual” ) © rod position detector, @ rod position measuring and processing equipment. @ = main control room monitoring equipment. c. trip breaker cabinets. 2.2 Safety fimction 2.2.1 Reactor trip docsity.com Bu = CONTROL ROD CONTROL SYSTEM MANUAL When a reactor trip is demanded by the reactor protection system (CRP), the power supply to the CRDMs is interrupted through the trip breakers. Loss of power, all RCCAs, whether initially in testing or in operating, shall drop into the core very quickly by gravity, ie. within about 2 seconds. The rod dropping into the core will absorb a large amount of neutron immediately to choke off the nuclear reactions and making the core subcritical. 2.2.2 System safety requirements The quantity of rod banks, the quantity of RCCAs per bank and the initial insertion of the control rods are determined by following way as to ensure compliance with the safety criteria, ie.: The core is kept subcritical following a reactor trip by a predetermined amount known as the negative reactivity margin. The value of this margin is determined by accident analysis report. An acceptable power distribution of neutron flux is maintained during power plant operation. The positive reactivity rate and positive reactivity due to a rod ejection accident are limited. 2.2.3. Dropped RCCAs-stuck RCCA. The control rod position indicating system particularly can display the individual measured rod position in the main contro] room. The operator is able to discern abnormal configurations of RCCs, Le.: misaligned RCCAs, stuck RCCAs, dropped RCCAs. 2.2.4 Realignment In normal operation all RCCAs in a bank are operated together. If misaligned RCCAs or stuck RCCAs or dropped RCCAs occur, the local neutron flux variations would be produced. The operator can use realignment operating and return the cluster to correct position. docsity.com  CONTROL ROD CONTROL SYSTEM MANUAL 3 General Design 3.1 Design bases and criteria 3.1.1 Design bases Tn the automatic mode the Control Rod Control System receives the “rod speed + rod direction” signals from the reactor power control system (CRC), or by manual control modes regulates the power so as to satisfy the necessary power of the turbine. The rods are divided into two functional categories. These categories are contro! rods and shutdown rods. The reactor power is controlled by combining the effects of chemical compensate with rod control. Both the shutdown rods and the control rods are used to shutdown reactor. The Control Red Control System has the function that the shutdown rods can be operated manually. During the reactor is started-up, first the shutdown rods are withdrawn manually and they are always in the fully withdrawn position during the normal operation. Then the control rods are withdrawn in predetermined programmed sequence. The Control Rod Control System allows that the control rods can be operated in manual mode or automatic mode. With the two modes, the control rods are operated in predetermined programmed sequence. That sequence is stipulated that movement order is reversible, i.e. the order of the insertion is opposite to the withdrawal. In the manual operation, the rod stepping rate for withdrawal or insertion can be preset, but it is fixed in movement. In the automatic mode, rod stepping rate which is varied and direction are determined by output of the reactor power control system. Trip breakers must be complied with single failure criteria. They have enough redundancy to ensure that trip function can’t be lost because of failure of singie trip breaker. Trip breakers can be tested by the operator manually in the main control room during the normal operation of the reactor. Note that every time only one trip breaker can be test. After the first trip breaker is reset, the another can be test. 3.1.2 Design criteria 3.1.2.1 Control rod control system © Safety criteria HAF102-91 docsity.com  CONTROL ROD CONTROL SYSTEM MANUAL, Rew. PC2~03-12-03-02 BE2-6 6.3 Zoning Yes 6.4 Protection against sabotage Yes 3.2 Equipment Design 3.2.1 CRDMs 37RCCAs are provided 21 for the control rods and 16 for shutdown rods. Each RCCA is attached to a grooved drive shaft, distance between the grooved pitches is 10 mm, which therefore represents the smallest possible RCCA movement. CRDM consists of 3 electromagnetic coils located on the outside of the pressure housing, each energizing one movable pole located inside the pressure housing. These mechanisms are therefore perfectly leak tight. (Figure 3.2.1) The first pole operates a stationary gripper latch, which grips a groove on the drive shaft. The second pole operates a movable gripper latch, which grips another groove on the drive shaft. The third pole actuates the entire movable gripper latch assembly and transfers it one step. Energization of the third coil lifts the RCCA one step, while the third coil lost power, the movable gripper Jatch will drop one step by gravity and spring, Appropriate sequential energization of these three coil moves the RCCAs via the drive shaft (withdrawal or insertion). 3.2.2. CRDM operation 3.2.2.1 Arrangement of RCCA in banks and groups In order to preclude flux imbalance, two or three or four clusters are moved simultancously. They are positioned symmetrically in the core in a form of a bank or a group. The RCCA in core center is assigned into control rod bank T4. a, Shutdown banks The 16 shutdown RCCAs are divided into 2 banks: Al: 2 groups of 4 RCCAs, AIGI1 and A1G2. A2: 2 groups of 4 RCCAs, A2G1 and A2G2. - b. Control banks The 21 control RCCAs are divided into 4 banks: T1: 2 groups of 4 RCCAs,T1G1 and T1G2. T2: 2 groups of 2 RCCAs, T2G1 and T2G2. docsity.com PC2-03- 12-03-02 CONTROL ROD CONTROL SYSTEM MANUAL Rev. B E2-7 T3: 2 groups of 2 RCCAs, T3G1 and T3G2. T4: 1 group of 3 RCCA for T4G1 and 1 group of 2 RCCAs for T4G2. 3.2.2.2 CRDM selection and operating principles Rod banks may be operated in two modes: a: individual, b: overlapping. During normal reactor operation the shutdown banks are operated in individual mode. Control banks are operated in overlapping mode. Shutdown banks are manually operated in individual mode at a preset speed. The direction of travel is set by the operator. Control banks are operated in overlapping automatically or manually. Manual operation is controlled from the main control room. The operator chooses the direction but the speed is preset. In automatic operation the speed and the direction are determined by the reactor power control system. The travel speed of shutdown banks and control banks varies between from 6 steps to 60 steps per minute. The maximum speed and minimum speed are determined respectively according to the requirements of the nuclear power plant transient state safety analysis and operating. Bank movement sequences The upward bank movement sequence is as follows: Upward movement of shutdown banks: Al, A2. Upward movement of contro] banks: T1, T2, T3, T4. The downward bank movement sequence is as follows: downward movement of control banks: T4, T3, T2, T1. downward movement of shutdown banks: A2, Al. Rod operation rules: RCCAs in the same group are operated simultaneously, Jn any bank, operation of groups is offset by half a cycle, i.e. group 1 and group 2 operate alternately (except in realignment mode). The cycle is the time interval between two steps of the rod movement, i.c. the time interval from the beginning of one moving step to the beginning of the next step, it docsity.com  PC2-03-12-03-02 CONTROL ROD CONTROL SYSTEM MANUAL Rev. B E2-§ depends on the rod speed. Ability to stop RCCAs movement at any time implies that the two groups may be misaligned, but there is only a difference of one step between them at best. Reversal of direction is programmed such that the last ceased motion group will be now the first to move in the new direction. Two control banks are operated simultaneously in overlap region. The control bank withdrawals are programmed such that when T1 bank reaches a preset position, T2 bank begins to move out simultaneously with T1 bank. When T1 bank reaches the top of the core, it stops, T2 bank continues to move. When T2 bank reaches a preset position, T3 begins to move out, and so on. This withdrawal sequence continues until the unit reaches the desired power level. The control bank insertion sequence is the opposite with the withdrawal sequence. (Figure 3.2.2) Overlap occurs in the upper or the lower section of the core. There is no overlap in the middle section of the core, only one bank is moving. Overlap between successive control banks is adjustable from 0 to 140 steps, with an accuracy of +1 step. Overlap setpoints can be preset. The overlap setpoints: $1-210 S3-190 Ss-190 S2-70 82-90 S6-90 The advantage of overlapping operation is that it moves simultaneously 2 rod groups in the bottom half of the core and in the top half. This provides mote ideal differential reactivity equivalent of control rods wherever they are situated in the core, There is a special equipment (the rod position realignment device) in the main control room, it allows one or more RCCAs in a bank to be separated and operated alone. In order to prevent sticking, the RCCAs are never fully inserted. As soon as the reactor trip breakers are closed, the RCCAs will be lifted to the baseline elevation. 3.2.2.3. CRDM coil a. CRDM coil operation The same type of coil in the group is energized simultaneously. Any RCCA can be controlled individually by opening the lift coil circuits of the other docsity.com  c2-08- CONTROL ROD CONTROL SYSTEM MANUAL Rev. 12-03-02 B E2~i1 ambient conditions. The coil power supply is direct current with a ripple of 150Hz. The 260V three-phase busbar is rectified through a three-phase haif-wave thyristor circuit to each coil. The current is regulated by adjusting the firing time of each thyristor. Three independent current regulation systems are provided since there are three separate coils in each CRDM. 3.2.5 Trip breaker There are four pairs of trip breakers (two of each pair) which are divided into four channels of Al, A2, B1, B2. The four channels are corresponding to Al, A2, B1, B2 channel of the reactor protection system separately and controlled by the reactor protection system. Eight trip breakers are installed in four cabinets separately, which are configured to 2/4 general voting logic. They are connected with M-G set. When two or more than two pairs of trip breakers are actuated by the signal from the reactor protection system, latches are released due to loss of power supplies to the coils, all the shutdown rods and control rods drop into the core by gravity. (Fig. 3.2.5) Each trip breaker has two coils: shunt coil and undervoltage coil, which are controlled by the reactor protection system. The undervoltage coils and the shunt coils are simultaneously actuated by the same relay actuation module in case of protection system actuation, and each relay actuation module actuates two relays. One relay for the undervoltage coil and another one for the shunt coil. The control circuits of trip breakers are supplied by 220V DC sytem (EDH). To avoid the common mode failure, the specification of two breakers of each channel must be the same, but they must be different type or be produced by different manufactories. Different channel of trip breaker cabinets must be physically separated and electric isolated. Layout of the external cables must be separated. 3.2.6 Interlock of control red control system 3.2.6.1 Interlock of rod stopping Important interlock signals as follows: C-1: 1/2 neutron flux (intermediate range) above setpoint. Block automatic and manual control rod withdrawal. (from CRP) C-2: 2/4 neutron flux (power range) above setpoint. Block automatic and manual docsity.com Pr PC2-03-12-03-02 CONTROL ROD CONTROL SYSTEM MANUAL Rev. B 2-12 control red withdrawal. (from CRP) C-3: 2/4 overtemperature AT above setpoint. Block automatic and manual control rod withdrawal. (from CRP) C-4: 2/4 overpower AT above setpoint. Block automatic and manual control rod withdrawal. (from CRP) C-5: 1/1 main steam pressure after control valve below setpoint. Block automatic control rod withdrawal, (from CRP) C-11: 1/1 bank T4 control rod position above setpoint. Block automatic control rod withdrawal]. (from CRD C-12: 2/4 negative change rate of nuclear power above setpoint. Block automatic control rod withdrawal. (from CRP) C-15: 1/1 bank T4 control rod position lower then “low-low" setpoint. Block automatic control rod insertion. (from CRD (Figure 3.2.6) 3.2.6.2 Rod position interlock Before shutdown rods are withdrawn to the top of the core, withdrawal of control reds in overlap mode is forbidden. Control rods are stopped when they reach the position of 5 steps from the bottom of the core in overlap mode. Before control rod bank T1 reach the position of 5 steps (low insertion limit), insertion of shutdown rods manually is forbidden. 3.3. Choice of material - construction Following componets are used for control equipment: Programmable Logic Controller (PLC); CMOS (Complementary Metal Oxide Semiconductor) integrated circuit. Silicon controlled rectified componet. docsity.com  CONTROL ROD CONTROL SYSTEM MANUAL PC2-03-12-03-001 Rev. A E2-13 seh SNS NIN NI NN NF NP INNS PRESSURIZED REACTOR COOLANT $ X be / \ / lV LEFT COIL ABLE GRIPPTR LATCH ARH Bang STATIONARY GRIPPER COIL een STATIBNARY GRIFPER LATLE ARE docsity.com  Bac| ; | Pe2-08 ca CONTROL ROD CONTROL SYSTEM MANUAL . Rev. J CON Lid RuuM oe Eo Eat Fat a AUTOMATIC MANUAL CONTROL RMD CONTROL ROD 2a) Ti SPEED SPEED [ & MANUAL CONTROL ROD INSERTIUN cms Fa MANUAL CONTREL ROD WITHDRAWAL SMATIC-MANUAL j co SELECTOR ! ' TION CONTROL ROG WITHDRAWAL docsity.com PC2--03- CONTROL ROD CONTROL SYSTEM MANUAL Rev. 4 Description of system and Equipment 4.1 Description 4.1.1 General The control rod control system comprises two main parts: a. Rod control part. b. Rod position indication part. (refer to “contro! rod position indication system manual” ) 4.1.1.1 Control red control system cabinet a. Control logic cabinet Its function is to generate the necessary signals to step the rods during startup, continuous operation, and shutdown of the nuclear power plant. It receives command signals from the main control room and the reactor power contro] system (CRC). In response to these signals, it selects the CRDMs to be driven and send command signals to the assigned power cabinet to drive control rods. The cycler which determines rod stepping frequency should be designed so that after receiving a motion demand signal, it should cause the rods to step within the time Tespouse requirements. The control logic cabinet is capable of supervising the operation of a maximum configuration of four contro! banks and two shutdown banks. In addition to supervising the operation, the control logic cabinet has fault monitoring circuit to monitor the internal fault within it, and receive monitoring signals from each of its associated power cabinet. When a fault condition is detected, necessary action is taken to prevent unsafe operation going on or dropping of control rod into the core. b. Power cabinet A power cabinet comprises two separate power equipment units. Each power equipment unit is associated with a CRDM. Each power equipment unit consists of: @ = Three three-phase, half-wave, phase-controlled thyristor bridges They are used to control and regulate current to the connected CRDM coils, the first bridge is used to supply the stationary gripper coil, the second bridge used to supply the movable gripper coil, and the third bridge used to supply the lift coil. @ = Thyristor bridge control circuit 12-03-02 BL OE2-17 docsity.com [Bar| PC2-03+12-03-02 CONTROL ROD CONTROL SYSTEM MANUAL Rev. B E2-18 It is the interface between the logic part and the power part. It converts logic signals into analog setpoints so that the bridge can supply the required current to the coil (Fig 4.1.1). A group comprises of 2~4 cluster of rods, their CRDMs are controlled by 1~2 power cabinets. Because the whole group shall move together, there is a time sequence assignment module in the power cabinet for one group. The function of the time sequence assignment module is to provide current time sequence signals to three coils of CRDMs of group. After the time sequence assignment module has received the start pulse in terms of group from logic cabinet, cycle begins according to the predetermined program, and signals are sent to all the thyristor control circuit of this group. The cycle of the time sequence assignment module is 780ms. Based on the direction signal of withdrawal or insertion from logic cabinet, there are two kinds of program produced in the time sequence assignment module: withdrawal time sequence and insertion time sequence. ce. DC. hold cabinet A failure in the power cabinet may require replacement of a card, fuse, or other component. To avoid the possibility of dropping rods during maintenance, there is a switch in the power cabinet used to energize stationary gripper coil from a separate 125VDC and 7OVDC power supply. The 125VDC power supply is used to assure latching of the stationary gripper and the 70VDC power supply is used to hold the gripper without overheating the coil. The 125VDC and 70VDC power supplies are generated by the DC. hold cabinet. Power of the DC. hold cabinet is taken from the reactor trip breakers. Each power supply consists of a three-phase transformer (Y/A) and a full wave, three- phase rectifier unit. d. Control supply distribution cabinet It provides the redundant control source supplies to the control logic and power cabinets. The 220V is supplied by the AC. instrumentation power supply system (channel C). The 150V is from M-G set. e. 260V AC. power distribution cabinet This three-phase power is supplied by the M-G set and distributed to each of 19 power docsity.com  CONTROL ROD CONTROL SYSTEM MANUAL Rev. BE2-21 cabinet and power cabinet. ERP: CRDM Power Supply System. Provide 260V AC three phases power supply to the power cabinet and DC. hold cabinet through the reactor trip breakers. CPC: Plant Computer system. Control rod contro! system transmits following signals to the plant computer system; Rod speed, direction and alarm signals. CRP: Reactor Protection System. Provide interlock signals used to inhibit rod movement (C1,C2,C3,C4,C5,C12). Emergency reactor trip signal is sent to the trip breakers. CRI: Control Rod Position Indicating System. Receive demanded rod position signal. Provide interlock signals used to inhibit rod movement (C11,C15). CRC: Reactor Power Control System. Signals are transmitted to the control system to be used for rod travel speed control and direction selection. (Figure 4.1.2) CMC: Main control room. All kinds of control switches and status indicators and test switches of trip breakers are instalied on the control board in the main control room. 4.2 Characteristics 4.2.1 Drive shaft The travel step, i.e. the distance between two grooves, is 10 mm. Total travel is 280 steps. 4.2.2. CRDM The maximum design speed is 60 steps per minute. The maximum design load is 1471.5 N. (excluding the weight of the drive shaft) Cycle for up or down one step requires at least 780 ms. During a cycle, the sequence of current values in the movable gripper coil is low current, high current, zero current, high current, low current. The sequence of current values in the stationary gripper coil is zero current, high current, zero current. The sequence of current values in the lift coil is zero current, high current, low current, zero current. when not transferring the drive-shaft, only the movable gripper coil is energized, with low current. In the hot state, the average voltage at energized coil terminal is approximately docsity.com  CONTROL ROD CONTROL SYSTEM MANUAL Rev. B PC2-03-12- 100VDC to 120VDC. 4.2.3 Position detector and rod position indication equipment Refer to control rod position indication system manual. 4.2.4 Control red control system cabinets Travel speed of RCCA varies between 6 steps per minute and 60 steps per minute with a tolerance of +2 steps. Input voltage: 220VAC_ 1%. Input voltage: 260VAC : no. Coil current values are allowed to be set. Tolerance of coil current is 5%. The time response of the control rods before it begins to drop following the arrival of a trip signal at the trip breakers is 0.3 second. The time iag between actual rod move and demanded rod move is one second during the rods are in automatic control. No single failure in equipment shall cause the banks to move in other than the prescribed sequence. The equipment design shall be such that with a single failure, stmultaneous withdrawal of more than two banks of control or shutdown rods is not possible. 43 Layout 4.3.1 Layout of electrical equipment 4.3.1.1 Main control room Controls: a. Bank selector, b. In - Hold - Out Level, c. Test Bank Selector, d. Lift Coil Disconnect Switches, e. Startup Pushbutton, f. Alarm Reset Pushbutton, g. +1 Pushbuttons, h. -1 Pushbuttons, i. Realignment Mode Selector, j. Trip Breaker switches. docsity.com Bin PC2-03- CONTROL ROD CONTROL SYSTEM MANUAL Rey. 12-03-02 B E2-23 Status lights: a. Out Light, b. in Light, c. Manual Light, d. Automatic Light e. Test Light f. Interlock signal status Lights. (C1, C2, C3, C4, C5, C11, C12, C16) Indicators: a, Rod Speed Indicator, b. Demand Position displayer, c. Realignment Step Counter. Annunciators: a. Rod Control Urgent Failure, b. Rod Control Non-Urgent Failure. 4.3.1.2 Rod control room The control rod contro! system equipment is installed in the rod contro! room, which includes: a. Two control logic cabinets, b. one control power supply distribution cabinet, c. Nineteen power cabinets, d. Two 260V AC. power supply distribution cabinets, e, one DC. bold cabinet, £. 1" Generator distribution cabinet, g. 2* Generator distribution cabinet, h. MG Set control cabinet, 1. Ay trip breaker cabinet, j. A> trip breaker cabinet, k. By trip breaker cabinet, 1. Bo trip breaker cabinet, mi. Test cabinet. The equipment is exposed to the following ambient conditions: Ambient temperature <30°C in normal operation. docsity.com iS sy CONTROL ROD CONTROL SYSTEM MANUAL TESTING CABINET 4 cur Laser BLES He REACTIR BREAKERS INTERLOCK -aBuV os, ~ ; { Mh 7; WL freed 2o2oF = 40zer. IAG an an z . , SORA 7 4 - | ERP | | sev a ' a M | H{G)- To er a BURNER RE CRP ied | Conventional L [ 2e0v | Sei a Ld % _ _| reactor TRIP eenv Ac Etaa/ ie NORMAL STRARTUP/TRIP SULMHE DC HOLE c ROD DORP TIME MEASUREMENT ae PC2-03:-12-03 B E2-26 Rev. Bik SPEED.DIRECTION ALARM ce POWER CABINETS i, POWER SUPPLY DISTRIBUTICN CAB! e6oV L-L I5SGV i-N cao — | geo] | | CONTROL SUFPLY e20V AC | DISTRIBUTICN CABINE Fig 4.1.2 CCR AE] Ee fil CONTROL ROO BLOCK SIGNALS PaSITIDN i ETECTORS ; docsity.com PC2-03-12-03-02 CONTROL ROD CONTROL SYSTEM MANUAL Rev. B E2-27 4 i : ane i cence pee Aq-1 Aw-3 Ai-s Ai-7 9 Ai-3 Awa i — “4 At-2 Ai-4 8 z Pine | 2-3 Ta-3 . : ~ A2Gi AQ-1 Aa-5 A2-7 A2-3 2-2) 5 : 4 oo : A2— : L A2G2 42-2 Aza A2-6 Al-8 5 ji 1-8 T 4-3 | i : - . Area! Aga -~ T7161 fi-+ Tie3 T1-5 77-7 & : i i ik i b i { 4 i $ : Tis : o : _ 4 _ i G ~ 74+1G2 Fi-2 Ti-4a 7 T 7 80 Qn4 |T3-3 ra T 3-1 I 2-2 0 G pi? Tia | me _ t i 5 Ai-5 -3 : 8 Aina - 1261 Fo-1 72-3 : f2-— g T 1-6 T 4-4; T 3-4 Ti ~ F2G2 ¥2-2 T 2-4 1 Ag 3-7 Tar a > 10 A2-6 A2-7 - 7361 F351 7 33 T3—- 14 7 i-7 T 2-1 T 1-8 ; ' L 73G2 F3-2 Ts-4 5 _ 12 -|- - J rp T4G1 4-1 74-3 74-5 13 mo 3 + | - ooeeebee eee e L 7 4G2 f4-2 7 4-4 Y Ae 27 CONTROL ROD LAYOUT CIAGRAM docsity.com PC2-03- CONTROL ROD CONTROL SYSTEM MANUAL Rev. 12-03-0 02 B B2-28 5 Operating Parameters 5.1 Normal operation Control rod banks are operated automatically from 15% to 100% reactor rated power. 5.2 Particular steady operation When turbine load is less then 15% rated power, select switch of control rod banks will be changed from auto into manual by operator, control rod banks will be operated manually. 5.3 Particular transient operation 5.3.1 System internal failure 5.3.1.1 Acontrol bank cannot be moved If the failed bank responds to manual control only, manual control mode is used until the fault has been removed. After fault climination, automatic operation can again be used. 5.3.1.2 Acontrol bank inserts continuously Controls are switched to manual mode: a. First case: if the RCCAs respond to manual controls, equilibrium condition can be reestablished after inserting several steps. Allow failure examination while maintaining equilibrium condition. If the RCCAs do not respond to manual controls, The plant operation procedures shall be followed. b. Second case: If RCCAs insertion continues, the reactor is tripped. 5.3.1.3 A control bank withdraws continuously If the interlock is not actuated, the reactor will be tripped because of over nuclear power. 5.3.1.4 Acluster or several clusters drop a. If several clusters have dropped: a reactor trip may be triggered by high nuclear flux change rate depending on the power level and the location of the dropped clusters, b. If only one cluster has dropped: manual controls are used and power is reduced, then dropping cluster is aligned to correct position. 5.3.1.5 RCCA misalignment Controls are switched to manual mode and the correct operation of rod position displayer is checked. docsity.com