ML20206H626
| ML20206H626 | |
| Person / Time | |
|---|---|
| Issue date: | 04/20/1986 |
| From: | Beltracchi L NRC |
| To: | |
| Shared Package | |
| ML20206H509 | List: |
| References | |
| NUDOCS 8606260233 | |
| Download: ML20206H626 (10) | |
Text
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International Topical Mtg on Aduances in Human Factors in Nuclear Power Systems o 4/20-23/86, Knoxville, Tennessee THE HEAT ENGINE CYCLE, THE HEAT REMOVAL CYCLE, AND ERGONOMICS OF THE CONTROL ROOM DISPLAYS LEO BELTRACCHI U.S. NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555 The views and opinions expressed herein are the author's personal ones and they are not to be interpreted as Nuclear Regulatory Commission criteria, requirements, nor guidelines.
The heat engine cycle is the basic power cycle in a nuclear power plant. In Light Water Reactors, this cycle is defined in terms of the process functions and in terms of the systems, which control and contain the process. Energy transfer from the heat source, the reactor, to the turbine generator, which produces electrical energy, to the condenser, and then ultimately to the environment, is defined in terms of the thermodynamic properties of the coolant water. The heat engine cycle is expressed in terms of these thermodynamic properties of water to form an iconic display of the cycle and of the systems that control it.
The heat removal cycle is the basic cycle in a nuclear power plant which best describes the function of the Engineered Safeguard Systems.
During abnormal transients and accidents, the Engineered Safeguard Systems remove afterheat from the core to prevent a meltdown of the fuel and the release of radiation. The heat removed from the core is ultimately transferred to the environment and the cycle is defined in terms of the thermodynamic properties of the coolant water. The heat removal cycle is expressed in terms of these thermodynamic properties of water to form an iconic display of the cycle and of the systems that control it.
The physical 1ccation of process data and system data within existing control rooms make it difficult for operators to evaluate functions within the cycles described above. Generally, these data are spread over many control boards. Because of the physical distance among the various displays of process variables, it is difficult for an operator to make a physical comparisen of related variables within the heat engine cycle / heat removal cycle. However, a walkdown of the contal board does allow the operator to evaluate and monitor each individual system on the board.
The heat engine cycle provides a structure for integrating process data into a clear, easily recognized image of the process. The image of the process is called an iconic. The thermodynamic properties of 4
the coolant water, as determined directly or calculated from measured
- pro. cess variables, are used to define key points in the iconic. These points are then connected in a logical manner to synthesize the cycle in the process. . Details on how this is done for the processes within the primary coolant system and the steam generators were presented in 8606260233 860619 PDR MISC 8606260147 PDR ,
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ppscs-H'Y a previous paper <. Furthermore, addi ional background and details are presented in draft technical papers ({) This talk discusses and illustrates the ergonomics of an integrated display, which will allow operators to monitor the heat engine cycle during normal operation of the plant, and the heat removal cycle during emergency operation of the plant. A computer-based iconic display is discussed as an overview to monitor these cycles. Specific emphasis is placed upon the process variables and process functions within each cycle, and the action of control systems and engineered safeguard systems within each cycle. This talk contains examples of display format for the heat engine cycle and the heat removal cycle for a pressurized water reactor. The display formats in this talk were developed on a Tektronix 4115B Display System. Color is a major f actor used to code inf ormation within the display formats. Black and white copies of these display formats are inadequate to convey the color coded information. Furthermore, a color photograph of the image on the display screen does not reproduce the image exactly; some details and sharpness are lost. Also, as costs to publish color is high, only a list of the illustrations (Kodak 35mm slides, color) used in the talk follow:
- 1. Design Steps i Goals Functions Systems Process ,
- 2. Goals Contain Radiation -
Maintain Coolant Mass Inventories Sustain Heat Removal Cycle, Source To Sink
- 3. Temperature - Entropy Diagram of Water Subcooled Liquid Water Two - Phase Region, Liquid and Vapor Superheated Steam ,
I
- 4. Heat Engine Cycle, Pressurized Water Reactor l 1
Pressurizer, at Quality Water Heated in Re, actor Core Rankine Cycle, Secondary Coolant Water
- 5. Shape Codes For:
Subcooled Water , Water Levels: Pressurizer Steam Generators Condenser Hotwell _z -
2 1
- 6. Color Codes Cyan - Subcooled Liquid Phase Water White - Two Phase Water, Liquid and Vapor Gray - Containment SI:ructure t
Red - Alerts
- 7. PWR Heat Engine Cycle, Shape and Color Coded
! Process Iconic: Pressure Bar, Pressurizer
- Temperature Rise of Core Coolant Water l Heat Transfer, Primary to Secondary Coolant I
Boiling in Steam Genarators
, Steam Expansion and Turbine Work Condensation of Steam in Condenser Heatup of Feedwater System:
Condenser Cooling Water System
- 8. GINNA Steam Generator Tube Rupture (SGTR) 01/25/82, 09:25:00 AM, 100% Power i
Process Iconic: i Heat Source (Reactor) to Steam Generators
- 9. GINNA-SGTR (-
01/25/82,'09:28:00 AM, after initial rupture but pre-trip. l Process Iconic:
~
I Heat Source to Steam Generators Radiation Detected , 1 ! ! 10. GINNA SGTR 01/25/82, 09:28:35 AM, post trip, min RCS pressure l Process Iconic: Heat Source to Steam Generators
- 11. GINNA SGTR j 01/25/82, 09:35:00 AM, natural circulation in primary loop
- . Process Iconic:
Heat Source to Steam Generators
- 12. Heat Removal Cycle, Post Reactor Trip
_3- _ _ - . _ - . . _ _ ~ ._. ._ . . _ __
u .: - - - . :. .-.......-. . . s Process Iconic: Heat Source to Heat Sink Systems: , Condenser Cooling Water System Auxilary Feedwater System Accumulators Upper Head Injection System , Safety Injection System Charging System
- 13. Heat Removal Cycle. LOCA Process Iconic:
Core ccolant water removing reactor's afterheat Systems: Residual Heat Removal System Containment Spray System
- 14. Heat Removal Cycle, 1500 F Reactor Steam Illustration of cycle and systems CONCLUSIONS Based on the material contained in the illustrations, the conclusionn ,
are:
+ measured process variables may be used to form a process iconic.
The heat engine cycle serves as the strucuture to form the iconic ,
+ the status of prccess functions may be evaluated from the process iconic,
+ the impact of interactions between plant systems and the plant process may be monitored from one display format,
+ pattern recognition by a human may be used to distinguish normal versus abnormal operation from the process iconic.
A user need not be an expert on entropy to interpret the displayed pattern,
+ color may be used to code measured process variables into information,
+ shape codes for subcooled water and water levels may be used to human factor (at the expense of thermodynamic l
- db *
-- ~ ~
i 9 characteristics) the display of these variables,
+ one display format may be used to monitor normal and abnormal plant operations. The one display format does not contain sufficient data to support all types of ,
I momitoring tasks performed by control room operators. REFERENCES
- 1. L. Beltracchi, "A Process / Engineered Safeguards Iconic Display,"
Symposium on NewTechnologies in Nuclear Power Plant Instrumentation and Control, November 28-30, 1984.
- 2. L. Beltracchi, " Comments on the Design of Control Rooms for Nuclear Power Plant," draft of a technical paper submitted for publication.
- 3. L. Beltracchi, " Iconic Displays f or Boiling Water Reactors,"
draft of a technical paper submitted for publication.
% **f t
- JI- _ _ . _ ._ _ _ _ _ _ _ _ _ _ _ -
International Topical Mtg on Advances in Human Factors in Nuclear Power Systems, 4/20-23/86, Knoxville, Tennessee THE HEAT ENGINE CYCLE, THE HEAT REMOVAL CYCLE, AND ERGONOMICS OF THE CONTROL ROOM DISPLAYS LEO BELTRACCHI U.S. NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555 The views and opinions expressed herein are the author's personal ones and they are not to be interpreted as Nuclear Regulatory Commission criteria, requirements, nor guidelines. The heat engine cycle is the basic power cycle in a nuclear power plant. In Light Water Reactors, this cycle is defined in terms of the process functions and in terms of the systems, which control and contain the process. Energy transfer from the heat source, the reactor, to the turbine generator, which produces electrical energy, to the condenser, and then ultimately to the environment, is defined in terms of the thermodynamic properties of the coolant water. The heat engine cycle is expressed in terms of these thermodynamic properties of water to form an iconic display of the cycle and of the systems that control it. The heat removal cycle is the basic cycle in a nuclear power plant which best describes the function of the Engineered Safeguard Systems. During abnormal transients and accidents, the Engineered Safeguard Systems remove afterheat from the core to prevent a meltdown of the fuel and the release of radiation. The heat removed from the core is ultimately transferred to the environment and the cycle is defined in terms of the thermodynamic properties of the coolant water. The heat removal cycle is expressed in terms of these thermodynamic properties of water to form an iconic display of the cycle and of the systems that control it. The physical location of process data and system data within existing control rooms make it difficult for operators to evaluate functions within the cycles described above. Generally, these data are spread over many control boards. Because of the physical distance among the various displays of process variables, it is difficult for an operator to make a physical comparison of related variables within the heat engine cycle / heat removal cycle. However, a walkdown of the contal board does allow the operator to evaluate and monitor each individual system on the board. The heat engine cycle provides a structure for integrating process data into a clear, easily recognized image of the process. The image of the process is called an iconic. The thermodynamic properties of the coolant water, as determined directly or calculated from measured process variables, are used to define key points in the iconic. These points are then connected in a logical manner to synthesize the cycle in the process. Details on how this is done for the processes within the primary coolant system and the steam generators were presented in
-L-
Sv$ a previous paper f. Furthermore, addi ional background and details are presented in draft technical papers ({}}) This talk discusses and illustrates the ergonomics of an integrated ' i display, which will allow operators to monitor the heat engine cycle during normal operation of the plant, and the heat removal cycle during emergency operation of the plant. A computer-based iconic display is discussed as an overview to monitor these cycles. Specific emphasis is placed upon the process variables and process functions within each cycle, and the action of control systems and engineered safeguard systems within each cycle. This talk contains examples of display format for the heat engine cycle and the heat removal cycle for a pressurized water reactor. The display formats in this talk were developed on a Tektronix 4115B Display System. Color is a major factor used to code information within the display formats. Black and white copies of these display formats are inadequate to convey the color coded information. Furthermore, a color photograph of the image on the display screen does not reproduce the image exactlyl some details and sharpness are lost. Also, as costs to publish color is high, only a list of the illustrations (Kodak 35mm slides, color) used in the talk follow:
- 1. Design Steps Goals Functions Systems Process
- 2. Goals Contain Radi ation --
Maintain Coolant Mass Inventories Sustain Heat Removal Cycle, Source To Sink
- 3. Temperature - Entropy Diagram of Water Subcooled Liquid Water Two - Phase Region, Liquid and Vapor Superheated Steam
- 4. Heat Engine Cycle, Pressurized Water Reactor l 1
Pressurizer, at Quality l Water Heated in Re, actor Core Rankine Cycle, Secondary Coolant Water
- 5. Shape Codes For:
Subcooled Water Water. Levels: Pressuri z er Steam Generators Condenser Hotwell c52 -
l
- 6. Color Codes Cyan - Subcooled Liquid Phase Water ,
White - Two Phase Water, Liquid and Vapor Gray - Containment Structure Red - Alerts -
- 7. PWR Heat Engine Cycle, Shape and Color Coded Process Iconic:
Pressure Bar, Pressurizer Temperature Rise of Core Coolant Water Heat Transfer, Primary to Secondary Coolant Boiling in Steam Genarators . Steam Expansion and Turbine Work Condensation of Steam in Condenser ' Heatup of Feedwater
,s System:
Condenser Cooling Water System
- 8. GINNA Steam Generator Tube Rupture (SGTR) 01/25/82, 09:25:00 AM,~100% Power Process Iconic:
Heat Source (Reactor) to Steam Generators '
- 9. GINNA-SGTR --
01/25/82,'09:28:00 AM, after initial rupture but pre-trip.' Process Iconic: _ Heat Source to Steam Generators Radiation Detected ,\
- 10. GINNA SGTR 01/25/82, 09:28:35 AM, post trip, min RCS pressure Process Iconic:
Heat Source to Steam Generators
- 11. GINNA GGTR 01/25/82, 09:35:00 AM, natural circulation in primary loop
_ Process Iconic: Heat Source to Steam Ganerators
- 12. Heat Rem val Cycle, Post Reactor Trip
- +
e - ; , 3- ,J ";
l Process Iconic: Heat Source to Heat Sink Systems: , Condenser Cooling Water System Auxilary Feedwater System Accumulators Upper Head Injection System Safety Injection System Charging System
- 13. Heat Removal Cycle. LOCA Process' Iconic:
Core ccolant water removing reactor's afterheat Systems: Residual Heat Removal System Containment Spray System
- 14. Heat Removal Cycle, 1500 F Reactor Steam Illustration of cycle and systems CONCLUSIONS Based on the material contained in the illustrations, the conclusionI ,
are:
+ measured process variables may be used to form a process iconic.
The heat engine cycle serves as the strucuture to form the iconic ,
+ the status of process functions may be evaluated from the process iconic,
+ the impact of interactions between plant systems and the plant process may.be monitored from one display format,
+ pattern recognition by a human may be used to distinguish normal versus abnormal operation from the process iconic.
A user need not be an expert on entropy to interpret the displayed pattern, l
+ color may be used to code measured process variables l into information, I + shape codes for subcooled water and water levels may be used l to human factor (at the expense of thermodynamic w
characteristics) the display of these variables,
+ one display format may be used to monitor normal and abnormal plant operations. The one display format does not contain sufficient data to support all types of ,
momitoring tasks performed by control room operators. REFERENCES
- 1. L. Beltracchi, "A Process / Engineered Safeguards Iconic Display,"
Symposium on NewTechnologies in Nuclear Power' Plant Instrumentation and Control, November 28-30, 1984.
- 2. L. Beltracchi, " Comments on the Design of Control Rooms for Nuclear Power Plant," draft of a technical paper submitted for publication.
- 3. L. Beltracchi, " Iconic Displays for Boiling Water Reactors,"
draft of a technical paper submitted for publication.
,, C-9 l
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