Digital plant protection system

• US 6,049,578 A
• Filed: 04/30/1998
• Issued: 04/11/2000
• Est. Priority Date: 06/06/1997
• Status: Expired due to Term

• Current Assignee: Westinghouse Electric Company LLC (Brookfield Asset Management Incorporated)
• Original Assignee: Combustion Engineering Incorporated (ABB Limited)
• Inventors: Wilkosz, Stephen J., Senechal, Raymond R., King, Arthur G., Bransfield, Stephen G., Safryn, Frank J., Yanosy, Paul L., Zaccara, Donald D., Bryan, Robert E., Althenhein, Gary D., McCloskey, Glenn J.
• Primary Examiner(s): Jordan, Charles T.
• Assistant Examiner(s): KEITH, JACK W
• Application Number:
  US09/069,869
• Time in Patent Office: 712 Days
• Field of Search: 376/259, 376/215-218, 364/184-187, 371/36
• US Class Current: 376/215
• CPC Class Codes: G05B 9/03 with multiple-channel loop, i.e. redundant control systems
• CPC Class Codes: G21D 3/04 Safety arrangements emergency protection of reactor G21C9/00
• CPC Class Codes: Y02E 30/00 Energy generation of nuclear origin
• CPC Class Codes: Y02E 30/30 Nuclear fission reactors

Abstract

A digital plant protection system for use in nuclear power plants of the pressurized water type includes cross-connected sensed-parameter processing channels that provide a suitably conditioned digital value to a digital comparator that tests the conditional digital value against a predetermined value to determine whether or not the sensed parameter has been exceeded. A comparator is associated with each of the plural channels and receives a separate measurement of the sensed parameter for each channel. If a sensed-parameter is determined to be out-of-specification by 2 of 4 or more channels, a `trip` signal is generated to effect remedial action.

Claims

1. A digital plant protection system for use in nuclear power plants, comprising:

a plurality of substantially identical independent sensed-parameter processing channels, each of which accepts a digital value representative of a sensed-parameter;

a digital comparator associated with each sensed-parameter processing channel for (1) comparing said digital value of the sensed-parameter with a first predetermined digital value indicative of a pre-trip condition and generating a pre-trip output if said pre-trip condition is detected, and (2) further comparing said digital value of the sensed-parameter with a second predetermined digital value indicative of a trip condition and generating a trip output if said trip condition is detected; and

a coincidence logic processor associated with each said sensed-parameter processing channel for receiving said trip output from said digital comparator, each said coincidence logic processor being cross-connected to every sensed-parameter processing channel for receiving several trip outputs from digital comparators within each said channel, wherein said coincidence logic processor generates a trip signal for effecting remedial action upon receipt of trip outputs from at least two channels.

2. A digital plant protection system for use in nuclear power plants as in claim 1, wherein said first plurality is four.

3. A digital plant protection system for use in nuclear power plants as in claim 1, wherein each said comparator further includes a bistable processor.

4. A digital plant protection system for use in nuclear power plants as in claim 3, wherein said digital value is received by said bistable processor which effects said comparison of said digital value of the sensed-parameter with said predetermined digital value indicative of a pre-trip condition.

5. A digital plant protection system for use in nuclear power plants as in claim 4, wherein said bistable processor effects said further comparison of said digital value with said second predetermined digital value indicative of a trip condition and provides said trip output to said coincidence logic processor if said trip condition is detected.

6. A digital plant protection system for use in nuclear power plants as in claim 1, wherein said trip signal for effecting remedial action is received by a Digital Engineered Safety Features Actuation System.

7. A digital plant protection system for use in nuclear power plants as in claim 1, wherein said trip signal for effecting remedial action is received by reactor trip breakers.

8. A digital plant protection system for use in nuclear power plants as in claim 7, wherein said trip breakers are actuated using high energy relays which accommodate either 12 VDC or 24 VDC actuation outputs.

9. A digital plant protection system for use in nuclear power plants as in claim 6, wherein said trip signal for effecting remedial action is also received by reactor trip breakers.

10. A digital plant protection system for use in nuclear power plants as in claim 9, wherein said trip breakers are actuated using high energy relays which accommodate either 12 VDC or 24 VDC actuation outputs.

11. A digital plant protection system for use in nuclear power plants as in claim 10, wherein said trip signal is optically isolated from said trip breakers.

12. A digital plant protection system for use in nuclear power plants as in claim 6, wherein said trip signal is optically isolated from said Digital Engineered Safety Features Actuation System.

13. A digital plant protection system for use in nuclear power plants as in claim 1, wherein said channels are cross-connected using fiber optic data links.

14. A digital plant protection system for use in nuclear power plants as in claim 1, wherein each channel further includes a maintenance and test panel and an interface and test processor for communicating with an engineered safety features systems.

15. A digital plant protection system for use in nuclear power plants as in claim 14, wherein each said interface and test processor communicates with said engineered safety features system via fiber optic data links.

16. A digital plant protection system for use in nuclear power plants as in claim 14, wherein each said interface and test processor further includes quadport optical distributors that redirect fiber optic data upon a loss of power.

17. A digital plant protection system for use in nuclear power plants as in claim 16, wherein said optical distributors provide loop termination upon loss of power to protect fiber optic data line integrity.

18. A digital plant protection system for use in nuclear power plants as in claim 14, wherein each said interface and test processor may initiate testing of the coincidence logic processors within said channels.

19. A digital plant protection system for use in nuclear power plants as in claim 17, wherein each said interface and test processor further includes a separate I/O module and a separate programmable logic circuit.

20. A method for monitoring all safety related system parameters within a nuclear power plant, comprising:

cross-connecting a plurality of substantially identical independent processing channels;

within each said channel further comprising the steps of;

receiving a plurality of conditioned digital input signals representative of a sensed parameter;

comparing said digital input signals with a first pre-determined stored digital value indicative of a pre-trip condition;

generating and transmitting a pre-trip output to all said channels if said pre-trip condition is detected;

receiving pre-trip signals from all said channels if said pre-trip condition is detected;

comparing said digital input signals with a second pre-determined stored digital value indicative of a trip condition if said pre-trip output is received;

generating and transmitting a trip output to coincidence logic processors within each said channel if said trip condition is detected, wherein said coincidence logic processors generate a trip signal if said trip output is received from two or more channels; and

taking pre-determined corrective action if said trip signal is detected.

21. A method for monitoring all safety related system parameters within a nuclear power plant as in claim 20, wherein said step of receiving a plurality of conditioned digital input signals representative of a sensed parameter further includes the steps of:

receiving an analog signal representative of the sensed parameter; and

converting said analog signal to a digital signal representative of the sensed-parameter.

22. A method for monitoring all safety related system parameters within a nuclear power plant as in claim 21, wherein said step of taking pre-determined corrective action further includes the steps of:

providing said trip signal to reactor trip breakers; and

providing said trip signal to a Digital Engineered Safety Features Actuation System.

23. A digital plant protection system, comprising:

means for cross-connecting a plurality of substantially identical independent processing channels;

within each said channel further comprising;

means for receiving a plurality of conditioned digital input signals representative of a sensed parameter;

means for comparing said digital input signals with a first pre-determined stored digital value indicative of a pre-trip condition;

means for generating a pre-trip output to all said channels if said pre-trip condition is detected;

means for comparing said digital input signals with a second pre-determined stored digital value indicative of a trip condition;

means for generating a trip output to all said channels if said trip condition is detected;

means for receiving trip outputs from each said channel generating a trip output;

means for providing a trip signal if said trip output is received from two or more channels; and

means for taking pre-determined corrective action if said trip signal is detected.

24. A digital plant protection system as in claim 23, wherein said means for receiving a second plurality of conditioned digital input signals representative of a sensed parameter further includes:

means for receiving an analog signal representative of the sensed parameter; and

means for converting said analog signal to a digital signal representative of the sensed parameter.

25. A digital plant protection system as in claim 24, wherein said means for taking pre-determined corrective action further includes:

means for providing said trip signal to reactor trip breakers; and

means providing said trip signal to a Digital Engineered Safety Features Actuation System.

26. A digital plant protection system as in claim 25, wherein said means for cross-connecting and said means for receiving trip signals are each fiber optic data links.

27. A digital plant protection system for use in nuclear power plants, comprising:

a plurality of sensors each providing an analog output representative of a sensed-parameter, each said output received by an analog-to-digital converter for providing a digital value representative of said sensed-parameter;

four substantially identical independent sensed-parameter processing channels each of which accepts said digital value representative of said sensed-parameter;

a digital comparator associated with each said sensed-parameter processing channel for (1) comparing said digital value of said sensed-parameter with a first predetermined digital value indicative of a pre-trip condition and generating a pre-trip output to all four of said channels if said pre-trip condition is detected and (2) comparing said digital value of said sensed-parameter with a second predetermined digital value indicative of a trip condition and generating a trip output to all four of said channels if said trip condition is detected; and

a coincidence logic processor associated with each said sensed-parameter processing channel for receiving said trip output from said digital comparator, each said coincidence logic processor being cross-connected to every sensed-parameter processing channel for receiving separate trip outputs from digital comparators within each said channel, wherein said coincidence logic processor generates a trip signal for effecting remedial action upon receipt of two-out-of-four trip outputs from said digital comparators within each said channel, wherein said trip signal for effecting remedial action is received by a Digital Engineered Safety Features Actuation System and by reactor trip breaks.

28. A digital plant protection system for use in nuclear power plants, comprising:

a plurality of substantially identical independent sensed-parameter processing channels, each of which accepts a digital value representative of a sensed-parameter;

a digital comparator associated with each sensed-parameter processing channel for (1) comparing said digital value of the sensed-parameter with a first predetermined digital value indicative of a pre-trip condition and generating a pre-trip output if said pre-trip condition is detected, and (2) further comparing said digital value of the sensed-parameter with a second predetermined digital value indicative of a trip condition and generating a trip output if said trip condition is detected; and

a coincidence logic processor associated with each said sensed-parameter processing channel for receiving said trip output from said digital comparator, each said coincidence logic processor being cross-connected to every sensed-parameter processing channel for receiving several trip outputs from digital comparators within each said channel, wherein said coincidence logic processor generates a trip signal for effecting remedial action upon receipt of trip outputs from at least two channels, and wherein said trip signal for effecting remedial action is received by reactor trip breakers which are actuated using high energy relays which accommodate either 12 VDC or 24 VDC actuation outputs.

29. A digital plant protection system for use in nuclear power plants, comprising:

a plurality of substantially identical independent sensed-parameter processing channels, each of which accepts a digital value representative of a sensed-parameter;

a digital comparator associated with each sensed-parameter processing channel for (1) comparing said digital value of the sensed-parameter with a first predetermined digital value indicative of a pre-trip condition and generating a pre-trip output if said pre-trip condition is detected, and (2) further comparing said digital value of the sensed-parameter with a second predetermined digital value indicative of a trip condition and generating a trip output if said trip condition is detected; and

a coincidence logic processor associated with each said sensed-parameter processing channel for receiving said trip output from said digital comparator, each said coincidence logic processor being cross-connected to every sensed-parameter processing channel for receiving several trip outputs from digital comparators within each said channel, wherein said coincidence logic processor generates a trip signal for effecting remedial action upon receipt of trip outputs from at least two channels, and wherein said trip signal for effecting remedial action is received by a Digital Engineered Safety Features Actuation System and by reactor trip breakers, said reactor trip breakers being actuated using high energy relays which accommodate either 12 VDC or 24 VDC actuation outputs.

30. A digital plant protection system for use in nuclear power plants, comprising:

a plurality of substantially identical independent sensed-parameter processing channels, each of which accepts a digital value representative of a sensed-parameter;

a digital comparator associated with each sensed-parameter processing channel for (1) comparing said digital value of the sensed-parameter with a first predetermined digital value indicative of a pre-trip condition and generating a pre-trip output if said pre-trip condition is detected, and (2) further comparing said digital value of the sensed-parameter with a second predetermined digital value indicative of a trip condition and generating a trip output if said trip condition is detected;

a coincidence logic processor associated with each said sensed-parameter processing channel for receiving said trip output from said digital comparator, said coincidence logic processor cross-connected to every sensed-parameter processing channel for receiving several trip outputs from digital comparators within each said channel, wherein said coincidence logic processor generates a trip signal for effecting remedial action upon receipt of trip outputs from at least two channels; and

a maintenance and test panel and an interface and test processor associated with each channel for communicating with an engineered safety features system, wherein each said interface and test processor includes quadport optical distributors that redirect fiber optic data upon a loss of power.

31. A digital plant protection system for use in nuclear power plants, comprising:

a plurality of substantially identical independent sensed-parameter processing channels, each of which accepts a digital value representative of a sensed-parameter;

a digital comparator associated with each sensed-parameter processing channel for (1) comparing said digital value of the sensed-parameter with a first predetermined digital value indicative of a pre-trip condition and generating a pre-trip output if said pre-trip condition is detected, and (2) further comparing said digital value of the sensed-parameter with a second predetermined digital value indicative of a trip condition and generating a trip output if said trip condition is detected;

a coincidence logic processor associated with each said sensed-parameter processing channel for receiving said trip output from said digital comparator, each said coincidence logic processor being cross-connected to every sensed-parameter processing channel for receiving several trip outputs from digital comparators within each said channel, wherein said coincidence logic processor generates a trip signal for effecting remedial action upon receipt of trip outputs from at least two channels; and

a maintenance and test panel and an interface and test processor associated with each channel for communicating with an engineered safety features system, wherein each said interface and test processor includes quadport optical distributors that, upon loss of power, (1) redirect fiber optic data and (2) provide loop termination to protect fiber optic data line integrity.

32. A digital plant protection system for use in nuclear power plants, comprising:

a plurality of substantially identical independent sensed-parameter processing channels, each of which accepts a digital value representative of a sensed-parameter;

a digital comparator associated with each sensed-parameter processing channel for (1) comparing said digital value of the sensed-parameter with a first predetermined digital value indicative of a pre-trip condition and generating a pre-trip output if said pre-trip condition is detected, and (2) further comparing said digital value of the sensed-parameter with a second predetermined digital value indicative of a trip condition and generating a trip output if said trip condition is detected; and

a coincidence logic processor associated with each said sensed-parameter processing channel for receiving said trip output from said digital comparator, each said coincidence logic processor being cross-connected to every sensed-parameter processing channel for receiving several trip outputs from digital comparators within each said channel, wherein said coincidence logic processor generates a trip signal for effecting remedial action upon receipt of trip outputs from at least two channels; and

a maintenance and test panel and an interface and test processor associated with each channel for communicating with an engineered safety features systems, wherein each said interface and test processor includes quadport optical distributors that, upon loss of power, (1) redirect fiber optic data and (2) provide loop termination to protect fiber optic data line integrity, and wherein each said interface and test processor further includes a separate I/O module and a separate programmable logic circuit.