8.0 instrumentation & control · 2012-12-05 · 1. state the purposes of the following: a....
TRANSCRIPT
8.0 Instrumentation & Control
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Objectives
1. State the purposes of the following:
a. Safety Information and Control Systemb. Process Information and Control Systemc. Protection System
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c. Protection Systemd. Process Automation Systeme. Diverse Actuation System
2. Describe the major differences between the I&C design of the US-EPR and those of currently operating PWRs.
CRDCS – Control Rod Drive Control Sys.DAS – Diverse Actuation SystemMCR - Main Control RoomPACS – Priority & Actuator Control SystemPAS – Process Automation SystemPICS – Process Information & Control SystemPS – Protection SystemRCSLS – Reactor Control, Surveillance, &
Limitation SystemRSS – Remote Shutdown StationSAS – Safety Automation SystemSCDS – Signal Conditioning & Distribution SystemSICS – Safety Information & Control SystemTG I&C – Turbine-Generator Instr. & Control 3
Figure 8-1I&C Architecture
Human-Machine Interface (HMI): Safety Information & Control System
Controls & indications for:
• Mitigation of AOOs & accidents (manual reactor trips & ESF actuations)
• Reaching & maintaining safe shutdown
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shutdown• Mitigation of severe accidents• Display of PAM variables
• Implemented with dedicated, hardwired equipment
• Powered from EUPS (safety) & 12UPS (nonsafety)
HMI:Process Information & Control System
• Equipment for monitoring & control of process systems during normal ops
• Workstations in MCR, RSS • Data connections to RCSLS (core
control), PAS (plant control)
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• Implemented with industrial I&C platform
• Powered from 12UPS
Automation Systems:
Protection System
• Auto reactor trips & ESF actuations
• TELEPERM XS platform• 4 divisions in safeguard
buildings • Powered from EUPS
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Safety Automation System
• Performs auto & manual grouped safety-related control functions
• TELEPERM XS platform• 4 divisions in SCI buildings • Powered from EUPS
APU - Acquisition & Processing Unit
ALU - Actuation & Logic Unit
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Figure 8-4 Typical Reactor Trip Actuation
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Figure 8-5 ManualReactor Trip
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Figure 8-3 Safety-Related Reactor Trip Devices
Table 8-2
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Table 8-2 (cont’d)
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12Figure 8-6 Typical ESF Actuation
Table 8-4
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Table 8-4 (cont’d)Table 8-4 (cont’d)
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Table 8-4 (cont’d)
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Table 8-4 (cont’d)
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Automation System:Priority & Actuator Control System
• Prioritizes actuation signals from different I&C systems
• Interfaces with actuation devices & actuated equipment via (mostly) hardwired connections
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• Implemented with priority & communication modules (1 set per actuator)
• 4 divisions in SCI buildings• Powered from EUPS (safety)
& 12UPS (nonsafety)
18Figure 8-2 Priority & Actuator Control System
Automation System:Signal Conditioning & Distribution System
• Performs signal conditioning & distribution of signals from sensors, black boxes
• Receives hardwired inputs & sends hardwired signal outputs to various systems
• Implemented with TELEPERM XS signal conditioning & distribution equipment
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g q p(diverse from TELEPERM XS digital function processors)
• 4 divisions in SCI buildings• Powered from EUPS (safety) & 12UPS
(nonsafety)
Automation System:Reactor Control, Surveillance, & Limitation System
• Performs reactivity-related control & limitation functions
• Provides orders to CRDCS for rod motion, to PAS for boration or dilution
• Implemented with TELEPERM XS l tf 4 di i i i f d
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platform, 4 divisions in safeguard buildings
• Powered from 12UPS
Core Control• RCSLS implements automation-level
I&C functions:
– Tavg control using rod motion– Tavg control adjusting boron concentration
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– Neutron flux control– Axial offset control
• Control Rod Drive Control System (CRDCS) provides interface to CRDM coils (controls currents).
25%, 587
35%, 587
60%, 594 100%, 594
585
590
595
600T
EM
PE
RA
TU
RE
(F
)
Fig. 8-7 RCS Temperature Program
100% values:
• Th ~ 625°F
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0%, 578
570
575
580
0% 20% 40% 60% 80% 100%
POWER LEVEL (% OF RATED THERMAL POWER)
AV
ER
AG
E R
C T • Tavg ~ 594°F
• Tc ~ 563°F
• ΔT ~ 62°F
Fig. 8-8Rod Speed Control
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Automation System:Process Automation System
• Nonsafety-related automation & control system for plant
• Redundant control units acquire hardwired inputs from various sources
• Outputs sent directly to nonsafetyactuators or to PACS
I l t d ith i d t i l
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• Implemented with industrial, commercial-grade digital I&C platform
• 4 divisions for most functions, 2 trains for others in various buildings
• Powered from various nonsafetysources
Plant Control• RCS Pressure Control: Controls PZR
heaters & spray
• Pressurizer Level Control: Modulates CVCS letdown
• Steam Generator Level Control: Maintains
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• Steam Generator Level Control: Maintains SG levels by modulating MFW control valves
• Main Steam Pressure Control: Modulates turbine bypass valves to provide main steam overpressure control
Diverse Performance of Safety Functions
• SICS: Manual reactor trip; initiation of system-level safety functions via DAS
• DAS: Executes manual functions from SICS & auto functions to mitigate ATWS, software CCF of PS– Reactor trips
ESF t ti
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– ESF actuations– Display of post-accident monitoring variables
• PACS: Supports execution of auto & manual functions to mitigate ATWS, software CCF of PS; diverse in operation from the PS
• SCDS: Outputs are hardwired & sent independently to each system
Diverse Actuation System Functions
• Acquires sensor info from SCDS & executes logic for several reactor trip & ESF actuation functions
• For trips, DAS outputs go to breaker shunt trip coils (PS affects undervoltage coils), control
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( g ),units of CRDCS to interrupt power to CRDM coils
• For ESF actuations, DAS outputs go directly to PACS (bypassing PS & SAS)
• Designed so that DAS should not interfere with PS; PS should actuate first
Automation System:Diverse Actuation System
• Nonsafety-related system for mitigating AOO or accident concurrent with common-cause PS failure
• Hardwired inputs & ouputs• Hardwired interface with SICS for
receipt of manual system-level d
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commands
• Implemented with something other than microprocessor-based technology
• 4 divisions in safeguard buildings• Powered from 12UPS
DAS Protection Functions• Reactor Trips
– High neutron flux
– Low RCS flow (2 loops)
– Low-low RCS flow (1 l )
• ESF Actuations– SIS actuation
– EFWS actuation
– Main steam isolation
– Containment isolation
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loop)
– High PZR pressure
– Low hot leg pressure
– Low SG pressure
– High SG level
– Low SG level
– Turbine trip on reactor trip
– MFW isolation
– Opening of containment H2 mixing dampers
– Starting of SBODGs