Control room for nuclear power plant

1. A reactor control interface comprising:

a home screen video display unit (VDU) configured to display:

blocks representing functional components of a nuclear power plant including at least (i) blocks representing functional components of a normal heat sinking path of the nuclear power plant and (ii) blocks representing functional components of at least one remedial heat sinking path of the nuclear power plant, and

connecting arrows of a first type that connect blocks that are providing a current heat sinking path, wherein directions of the connecting arrows of the first type represent the direction of heat flow along the current heat sinking path, and the connecting arrows of a first type are only displayed when the current heat sinking path is operational.

2. The reactor control interface of claim 1 wherein connecting arrows of the first type do not connect blocks that are not providing the current heat sinking path.

3. The reactor control interface of claim 2 wherein the home screen VDU is further configured to display connecting arrows of a second type visually distinguishable from the first type, the arrows of the second type connecting blocks.

4. The reactor control interface of claim 2 wherein the VDU is configured to update the displayed connecting arrows of the first type in response to the nuclear power plant switching from the normal heat sinking path to a remedial heat sinking path.

5. The reactor control interface of claim 1 wherein the blocks representing functional components of the normal heat sinking path include a block representing a reactor coolant system, a block representing a turbine, and a block representing a condenser.

6. The reactor control interface of claim 2 wherein the blocks representing functional components of the normal heat sinking path further include a block representing a steam system for conveying steam to the turbine.

7. The reactor control interface of claim 6 wherein the blocks representing functional components of the normal heat sinking path further include a block representing a feed water system for conveying feed water to a steam generator.

8. The reactor control interface of claim 1 wherein the VDU is configured to apply a first highlighting format to a block responsive to the functional component represented by that block transitioning to an abnormal condition that is the root cause of the nuclear power plant entering an abnormal operating condition.

9. The reactor control interface of claim 8 wherein the VDU is configured to apply a highlighting format different from the first highlighting format to a block responsive to the functional component represented by that block performing an intended remedial operation in response to the nuclear power plant entering the abnormal operating condition.

10. The reactor control interface of claim 7 wherein the VDU is configured to apply a highlighting format different from the first highlighting format to a block responsive to the functional component represented by that block transitioning to an abnormal condition that is not the root cause of the nuclear power plant entering an abnormal operating condition.

11. The reactor control interface of claim 1 wherein:

the VDU is configured to apply a highlighting format to a block responsive to the functional component represented by the block transitioning to an abnormal condition,

the applied highlighting format identifying that the functional component represented by the block is in an abnormal condition;

the applied highlighting format not identifying the abnormal condition.

12. The reactor control interface of claim 1 further comprising: a mimic VDU configured to display a mimic of a selected functional component responsive to a user input to the home screen VDU selecting a block displayed on the home screen VDU that represents the selected functional component.

13. The reactor control interface of claim 12 further comprising:

a procedures VDU configured to display a stored procedure.

14. The reactor control interface of claim 13 further comprising:

an electronic data processing device configured to execute the displayed stored procedure.

15. The reactor control interface of claim 14 wherein the electronic data processing device does not execute a step of the displayed stored procedure until a user input is received at the mimic VDU identifying a component that executes the step.

16. The reactor control interface of claim 13 further comprising:

a multi-trend VDU configured to display trends of one or more measured nuclear power plant parameters.

17. The reactor control interface of claim 16 wherein the multi-trend VDU displays a central window and peripheral windows surrounding the central window, wherein each peripheral window displays a trend dedicated to that peripheral window and the central window displays an enlarged view of one of the peripheral windows selected by user input to the multi-trend VDU.

18. The reactor control interface of claim 16 further comprising:

an alarms VDU configured to display a list of alarms generated by the nuclear power plant.

19. The reactor control interface of claim 18 further comprising:

an additional VDU;

wherein a group of safety VDUs includes the home screen VDU, the mimic VDU, the procedures VDU, the multi-trend VDU, and the alarms VDU but does not include the additional VDU; and

wherein responsive to a malfunctioning safety VDU, the displays of the safety VDUs that continue to function shift to free up one safety VDU to display content previously displayed on the malfunctioning safety VDU and a display that is removed from the group of safety VDUs by the shift is displayed on the additional VDU.

20. The reactor control interface of claim 1 further comprising:

an alarms VDU configured to display a left-hand window and a right-hand window with (1) a list of alarms generated by the nuclear power plant in chronological or reverse chronological order in one window (2) a list of alarms generated by the nuclear power plant in a user-selectable order in the other window.

21. The reactor control interface of claim 1 further comprising:

an alarms VDU configured to display a left-hand window and a right-hand window with (1) a list of alarms generated by the nuclear power plant in chronological or reverse chronological order in one window (2) a list of alarms ordered by priority in the other window.

22. The reactor control interface of claim 1 comprising a plurality of VDUs including the home screen VDUs, the number of VDUs being eight or less.