ML19337A430: Difference between revisions

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hk /          b A7 g              UNITED STATES OF AMERICA
hk /          b A7 g              UNITED STATES OF AMERICA p      NUCLEAR REGULATORY COMMISSION N    -
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BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of                          )
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of                          )
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                                                                  -
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OUTLINE The purposes and objectives of this testimony are to respond to Sholly Contention 15 and ANGRY Contt ntion V(C),
OUTLINE The purposes and objectives of this testimony are to respond to Sholly Contention 15 and ANGRY Contt ntion V(C),
which contend that the TMI-l Control Room should be evaluated and modified in a manner which assures that the operator-process interface is such that the operators cart exercise adequate control over the reactor. This testimony describes the original TMI-l control room design process, the successful
which contend that the TMI-l Control Room should be evaluated and modified in a manner which assures that the operator-process interface is such that the operators cart exercise adequate control over the reactor. This testimony describes the original TMI-l control room design process, the successful experience of operators controlling TMI-l over five years through n"merous transients and trips, and the human factors review that has been performed on TMI-1. Although the human factors review has identified improvements that can be made to the operator-process interface, the review also showed that the present control room design has substantial strengtas. Thus TMI-l can be opr. rated safely with the current control room design and conf.'iguration, i
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experience of operators controlling TMI-l over five years through n"merous transients and trips, and the human factors review that has been performed on TMI-1. Although the human factors review has identified improvements that can be made to the operator-process interface, the review also showed that the present control room design has substantial strengtas. Thus TMI-l can be opr. rated safely with the current control room design and conf.'iguration, i
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INDEX INTRODUCTION ................................................ 1 RESPONSE TO SHOLLY CONTENTION NO. 15 ...... ................. 2 RESPONSE TO ANGRY CONTENTION NO. V(C) ...................... 17 1
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INDEX INTRODUCTION ................................................ 1 RESPONSE TO SHOLLY CONTENTION NO. 15 ...... ................. 2 RESPONSE TO ANGRY CONTENTION NO. V(C) ...................... 17
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  .
INTRODUCTION This testimon-                by Mr. Patrick S. Walsh, GPU Plant Analysis Manager, Mr. William E.                          Meek, Manager of Engineering, Gilbert Associates, Inc., Mr. Herbert Estrada, Jr., of MPR Associates, Dr. Julien M. Christensen of SSSV, Inc., and Dr.
INTRODUCTION This testimon-                by Mr. Patrick S. Walsh, GPU Plant Analysis Manager, Mr. William E.                          Meek, Manager of Engineering, Gilbert Associates, Inc., Mr. Herbert Estrada, Jr., of MPR Associates, Dr. Julien M. Christensen of SSSV, Inc., and Dr.
Thomas B.              Sheridan, Professor of Engineering and Applied Psychology at the Massachusetts Institute of Technology, is aadc== sed to the following contentions:
Thomas B.              Sheridan, Professor of Engineering and Applied Psychology at the Massachusetts Institute of Technology, is aadc== sed to the following contentions:
SHOLLY CONTENTION NO. 15 It is contended that the design of the Unit 1 Control
SHOLLY CONTENTION NO. 15 It is contended that the design of the Unit 1 Control
               .toom, instrumentation, and controls is such that operators cannot maintain system variables and systems within prescribed operating ranges during feedwater transients and LOCA 's.                It is further contended that this violates the provisions of GDC 13 regarding instrumentation and controls.                It is contended that in view of the numerous operating difficulties encountered with Unit 2, and the similarities in design and construction between' Units 1 and 2, a thorough human factors engineering review of Unit l's Control Rcom is called for in order to provide                                    i
               .toom, instrumentation, and controls is such that operators cannot maintain system variables and systems within prescribed operating ranges during feedwater transients and LOCA 's.                It is further contended that this violates the provisions of GDC 13 regarding instrumentation and controls.                It is contended that in view of the numerous operating difficulties encountered with Unit 2, and the similarities in design and construction between' Units 1 and 2, a thorough human factors engineering review of Unit l's Control Rcom is called for in order to provide                                    i assurance that the operator-instrumentation interface is such that the operators can exercise adequate control over                          -
                                                                                                    '
assurance that the operator-instrumentation interface is such that the operators can exercise adequate control over                          -
the reactor and prevent off-site consequences from anticipated operational occurrences and postulated accidents.                It is further contended that in order to assure maximum protection for the public health and safety, the human factors engineering review and any necessary changes recommended as a result of this review must be completed prior to restart.
the reactor and prevent off-site consequences from anticipated operational occurrences and postulated accidents.                It is further contended that in order to assure maximum protection for the public health and safety, the human factors engineering review and any necessary changes recommended as a result of this review must be completed prior to restart.
ANGRY CONTENTION NO. V(C)
ANGRY CONTENTION NO. V(C)
The NRC Order fails to require as conditions for restart the following modifications in the design of the TMI-1 reactor without which there can be no reasonable assurance that TMI-l can be operated without endangering the public health and safety:
The NRC Order fails to require as conditions for restart the following modifications in the design of the TMI-1 reactor without which there can be no reasonable assurance that TMI-l can be operated without endangering the public health and safety:
                                                                                                .
wiwm rme---              -  --            *m -
wiwm rme---              -  --            *m -


                                                                                          ._
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(C)  Performance of an analysis of and implementation of modifications in the design and layout of the TMI-l control room as recommended in NUREG 0560.
(C)  Performance of an analysis of and implementation of modifications in the design and layout of the TMI-l control room as recommended in NUREG 0560.
RESPONSE TO SHOLLY CONTENTION NO. 15 l
RESPONSE TO SHOLLY CONTENTION NO. 15 l
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of positiv.e indication of valve closure, is r.ddressed in Licensee's testimony on Valves and Valve Testing in response to UCS Contentions 5 and 6.      A second example, positive indication of inadequate core cooling, is addressed in Licensee's testi-i mony on Detection of Inadequate Core Cooling in response to UCS Contention No. 7, ANGRY Contention V(B) and Sholly Contention No. 6(b).
of positiv.e indication of valve closure, is r.ddressed in Licensee's testimony on Valves and Valve Testing in response to UCS Contentions 5 and 6.      A second example, positive indication of inadequate core cooling, is addressed in Licensee's testi-i mony on Detection of Inadequate Core Cooling in response to UCS Contention No. 7, ANGRY Contention V(B) and Sholly Contention No. 6(b).
The third example citea in the statement of basis asserts that the inability of the operator to view an increasing trend on the fuel handling building exhaust monitors at 18 minutes inte the accident affected tha operators' ability te control the sequence of events.
The third example citea in the statement of basis asserts that the inability of the operator to view an increasing trend on the fuel handling building exhaust monitors at 18 minutes inte the accident affected tha operators' ability te control the sequence of events.
This assertion is not valid.      The
This assertion is not valid.      The monitor detected an increase of approximately 20%, stabilized at this reading, and then decreased slowly for several hours.
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monitor detected an increase of approximately 20%, stabilized at this reading, and then decreased slowly for several hours.
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The important 'information the operator needed to know, however, was that a primary system relief valve was open. It is unlikely that the operators would have deduced thac che increased reading was caused by a leak in the waste gas system, which is connected to a header that vents the Reactor Coolant Drain Tank (RCDT), which was receiving a larger than normal volume of water from a stuck open relief valve. In fact, operator interviews indicate that the operators believed the conditions in the RCDT were due to the initial lifting of the relief valve at the onset of the transient. In any case, the high alarm setpoint for the monitors was not reached until after 0700, and the system design relies principally upon monitor alarms to alert the operator to sudden increases, and upon periodic logging of' readings to detect slower trends. It should algo be noted that in the TMI-l control Room these recorders are located in a more visible location (higher on the back panel) than they are in the TMI-2 Control Room.
The important 'information the operator needed to know, however, was that a primary system relief valve was open. It is unlikely that the operators would have deduced thac che increased reading was caused by a leak in the waste gas system, which is connected to a header that vents the Reactor Coolant Drain Tank (RCDT), which was receiving a larger than normal volume of water from a stuck open relief valve. In fact, operator interviews indicate that the operators believed the conditions in the RCDT were due to the initial lifting of the relief valve at the onset of the transient. In any case, the high alarm setpoint for the monitors was not reached until after 0700, and the system design relies principally upon monitor alarms to alert the operator to sudden increases, and upon periodic logging of' readings to detect slower trends. It should algo be noted that in the TMI-l control Room these recorders are located in a more visible location (higher on the back panel) than they are in the TMI-2 Control Room.
l BY WITNESSES WALSH, ESTRADA, CHRISTENSEN AND SHERIDAN:                            '
l BY WITNESSES WALSH, ESTRADA, CHRISTENSEN AND SHERIDAN:                            '
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Mr. Sholly's statement of basis for his Contention No. 15 :
Mr. Sholly's statement of basis for his Contention No. 15 :
I also cites a study performed by the Electric Power Research Institute (EPRI Report #NP309) of human factors engineering in nuclear power plant control rooms. Mr. Sholly stated that many                      :
I also cites a study performed by the Electric Power Research Institute (EPRI Report #NP309) of human factors engineering in nuclear power plant control rooms. Mr. Sholly stated that many                      :
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the review described below of the TMI-l Control Room are based on the same generally accepted control design standards utilized in the cited EPRI report.
the review described below of the TMI-l Control Room are based on the same generally accepted control design standards utilized in the cited EPRI report.
BY WITNESS WALSH:
BY WITNESS WALSH:
There are four major elements in the body of Sholly Contention No. 15 itself.                The remair. der of this response to the contention is organized to address each of these elements.
There are four major elements in the body of Sholly Contention No. 15 itself.                The remair. der of this response to the contention is organized to address each of these elements.
                                    .'.,
The contention asserts that the design of the Unit 1 Control Room instrumentation and controls is such that opera-tors cannot maintain system variables and systems within prescribed operating ranges during feedwater transients and LOCA's.
The contention asserts that the design of the Unit 1 Control Room instrumentation and controls is such that opera-tors cannot maintain system variables and systems within prescribed operating ranges during feedwater transients and LOCA's.
I do not agree with this assertion.                            TMI Unit 1 operated at power for over 30,000 hours during the five years 1974-1979.
I do not agree with this assertion.                            TMI Unit 1 operated at power for over 30,000 hours during the five years 1974-1979.
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The capability of the control systems and the operators to maintain control of the plant during transient conditions was tested during the startup test program in 1974. These tests 1
The capability of the control systems and the operators to maintain control of the plant during transient conditions was tested during the startup test program in 1974. These tests 1
measure the ability of the feedwater system as well as the entire plant to respond to transient conditions. The tests include load changes at design ramp rates at 40, 76 and 100%
measure the ability of the feedwater system as well as the entire plant to respond to transient conditions. The tests include load changes at design ramp rates at 40, 76 and 100%
power, tripping of a main feedwater pump at 100% power and
power, tripping of a main feedwater pump at 100% power and l
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turbine trit at 76%, as well as reactor trip tests. During all l
turbine trit at 76%, as well as reactor trip tests. During all l
these tests the operators were able to control the plant and        l return it to a stable steady state condition without violating safety limits and with plant instrumentation remaining in the indicating range.
these tests the operators were able to control the plant and        l return it to a stable steady state condition without violating safety limits and with plant instrumentation remaining in the indicating range.
Curing five years of operation TMI-l ecperienced 17 reactor trip transients. Three of these were intentionally initiated for test purposes and ten were experienced during the startup test phase over the first tb ee months of operation.
Curing five years of operation TMI-l ecperienced 17 reactor trip transients. Three of these were intentionally initiated for test purposes and ten were experienced during the startup test phase over the first tb ee months of operation.
Only two reactor trips can be directly attributed to upsets in the feedwater system. One occurred on June 20, 1974, fifteen
Only two reactor trips can be directly attributed to upsets in the feedwater system. One occurred on June 20, 1974, fifteen days after initial criticality, at 18% power during a transient      i caused by a turbine bypass valve malfunction that was com-          -
                                                                        !
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days after initial criticality, at 18% power during a transient      i
,
caused by a turbine bypass valve malfunction that was com-          -
plicated by an overfeed condition. The other trip occurred on July 13, 1974, at 15% power, when a clogged suction strainer caused a condensate booster pump to trip. During both of these transients the operators returned the plant to a stable shutdown condition and system instrumentation remained within the indicating range.
plicated by an overfeed condition. The other trip occurred on July 13, 1974, at 15% power, when a clogged suction strainer caused a condensate booster pump to trip. During both of these transients the operators returned the plant to a stable shutdown condition and system instrumentation remained within the indicating range.
BY WITNESSES WALSH, MEEK AND ESTRADA:
BY WITNESSES WALSH, MEEK AND ESTRADA:
It should also be noted that TMI-l differs significantly from TMI-2 with respect to control room design and arrangement.
It should also be noted that TMI-l differs significantly from TMI-2 with respect to control room design and arrangement.
These differences are discussed further below in Section 3.
These differences are discussed further below in Section 3.
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BY WITNESSES NALSH, ESTRADA, CHRISTENSEN AND SHERIDAN:
BY WITNESSES NALSH, ESTRADA, CHRISTENSEN AND SHERIDAN:
Nevertheless, Licensee has undertaken a thorough review of the Unit 1 Control Room arrangement and the controls and displays therein. This review was performed by a team made up of:
Nevertheless, Licensee has undertaken a thorough review of the Unit 1 Control Room arrangement and the controls and displays therein. This review was performed by a team made up of:
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A. Guidelines and objectives were developed whereby the specifics of the control and display designs could be eval-uated. These guidelines are based on generally accepted military and industrial standards for control design.              MIL-STD-1472B, which was used in the NRC study of the TMI-2 Control Room, was also used as a source for the guidelines that were developed for this Unit 1 Control Room review.
A. Guidelines and objectives were developed whereby the specifics of the control and display designs could be eval-uated. These guidelines are based on generally accepted military and industrial standards for control design.              MIL-STD-1472B, which was used in the NRC study of the TMI-2 Control Room, was also used as a source for the guidelines that were developed for this Unit 1 Control Room review.
1 B. A full-scale control room mock-up was constructed to allow evaluations as described in C and D below.              Panel fronts were reproduced by utilizing a combination of photographic and photocopy enlargements of a gridwork of high quality photo-graphs.
1 B. A full-scale control room mock-up was constructed to allow evaluations as described in C and D below.              Panel fronts were reproduced by utilizing a combination of photographic and photocopy enlargements of a gridwork of high quality photo-graphs.
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C. Key operational and emergency procedures were walked-through to develop a clear understanding of how, when, by whom and in what way displays, controls and means of communications in the Control Room are used and what changes, if any, would be        i desirable. Cualified TMI operating personnel performed the simulated operations, with the evaluations being performed by          i the review team mentioned previously.                                  l l        Operating procedures that were walked-through include i
C. Key operational and emergency procedures were walked-through to develop a clear understanding of how, when, by whom and in what way displays, controls and means of communications in the Control Room are used and what changes, if any, would be        i desirable. Cualified TMI operating personnel performed the simulated operations, with the evaluations being performed by          i
                                                                          !
the review team mentioned previously.                                  l
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l        Operating procedures that were walked-through include i
plant heatup and startup (including operation at power),                i shutdown and cooldown, and refueling.                                    I Emergency procedures that were walked-through include reactor trips from a variety of causes, turbine trips with and without reactor trips, a variety of losses of feedwater flow and other upsets in the feed system, a spectrum of losses of reactor coolant with a variety of postulated causes, and a spectrum of steam system leaks.
plant heatup and startup (including operation at power),                i shutdown and cooldown, and refueling.                                    I Emergency procedures that were walked-through include reactor trips from a variety of causes, turbine trips with and without reactor trips, a variety of losses of feedwater flow and other upsets in the feed system, a spectrum of losses of reactor coolant with a variety of postulated causes, and a spectrum of steam system leaks.
D. Displays and controls on the principal panels and consoles were individually reviewed, separately from the walk-throughs.      The object of this review was to ensure that items such as scale divisions, selections of units and legend readability, all of which might not be picked up in the walk-throughs , were ev alua ted .
D. Displays and controls on the principal panels and consoles were individually reviewed, separately from the walk-throughs.      The object of this review was to ensure that items such as scale divisions, selections of units and legend readability, all of which might not be picked up in the walk-throughs , were ev alua ted .
E. A review of alarm systems was performed to evaluate the usefulness of the information presented to the operator in both normal and off-normal situations, and to develop, as              -
E. A review of alarm systems was performed to evaluate the usefulness of the information presented to the operator in both normal and off-normal situations, and to develop, as              -
warranted, improvements in the way that alarm information is presented.
warranted, improvements in the way that alarm information is presented.
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F. The environmental conditions in the control room were surveyed to evaluate whether they adequately support the operators and equipment therein. The conditions include, among others:  temperature, humidity, normal and emergency lighting, noise, kitchen and bathroom facilities, and arrangement of equipment and facilities.
F. The environmental conditions in the control room were surveyed to evaluate whether they adequately support the operators and equipment therein. The conditions include, among others:  temperature, humidity, normal and emergency lighting, noise, kitchen and bathroom facilities, and arrangement of equipment and facilities.
The review has concluded that while improvements can be made, the present Control Room arrangement and the controls and displays therein have a number of significant strengths:
The review has concluded that while improvements can be made, the present Control Room arrangement and the controls and displays therein have a number of significant strengths:
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(1)  Auxiliary operators are present in sufficient numbers and stations to provide effective operational support for both normal and off-normal evolutions.
(1)  Auxiliary operators are present in sufficient numbers and stations to provide effective operational support for both normal and off-normal evolutions.
(2)  Control room operators are present in sufficient numbers to man consoles effectively in both normal and off-normal evolutions.
(2)  Control room operators are present in sufficient numbers to man consoles effectively in both normal and off-normal evolutions.
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o    The control and display hardware, particularly I
o    The control and display hardware, particularly I
pushbuttons, switches, meters and controllers, have proven to have satisfactory reliability.
pushbuttons, switches, meters and controllers, have proven to have satisfactory reliability.
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o    The main alarm panels are essentially " dark" ( usually less than five are lit) when the plant is operating normally at power, and thereby enhance the ability of the operator to recognize an off-normal condition.
o    The main alarm panels are essentially " dark" ( usually less than five are lit) when the plant is operating normally at power, and thereby enhance the ability of the operator to recognize an off-normal condition.
As should be expected of a detailed engineering study, the review of the Unit 1 Control Room has uncovered a number of areas where the Control Room design can be enhanced. While    it is our opinion that TMI-1 can be safely operated with the Control Room as it presently exists, we are proceeding to make improvements to the TMI-1 Control Room design where we can clearly demonstrate that human factor aspects will indeed be enhanced.
As should be expected of a detailed engineering study, the review of the Unit 1 Control Room has uncovered a number of areas where the Control Room design can be enhanced. While    it is our opinion that TMI-1 can be safely operated with the Control Room as it presently exists, we are proceeding to make improvements to the TMI-1 Control Room design where we can clearly demonstrate that human factor aspects will indeed be enhanced.
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  .
Based on ' recommendations of the study the following modifications are being evaluated:
Based on ' recommendations of the study the following modifications are being evaluated:
(A). Outlines of controls and indicators to indicate functional relationships are being evaluated.      Replacement and reg roupin: of labels to provide better visibility are being evaluated. Larger lettering and consistent color combinations are being evaluated. Selected indicators are being evaluated for replacement of scale faces to provide easier readability and consistent scale markings and divisions.
(A). Outlines of controls and indicators to indicate functional relationships are being evaluated.      Replacement and reg roupin: of labels to provide better visibility are being evaluated. Larger lettering and consistent color combinations are being evaluated. Selected indicators are being evaluated for replacement of scale faces to provide easier readability and consistent scale markings and divisions.
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(D). The annunciator panels are being evaluated for several combinations of annunciator window arrangement and alarm suppression and prioritization strategies.
(D). The annunciator panels are being evaluated for several combinations of annunciator window arrangement and alarm suppression and prioritization strategies.
In the process of designing each of these modifications, as well as all other modifications being made to the control room, full size facsimiles of the proposed arrangements are being placed on the control panel mockup and evaluated by the review team described above, using operating and emergency procedures.
In the process of designing each of these modifications, as well as all other modifications being made to the control room, full size facsimiles of the proposed arrangements are being placed on the control panel mockup and evaluated by the review team described above, using operating and emergency procedures.
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Certain of the improvements in the control 2 and displays will enhance the ability of the control room operators to react to the transients of concern in the contention, specifically feedwater transients and loss-of-coolant accidents (reactor system leaks). In addition, modifications to the controls and displays made as a result of lessons learned from the TMI-2 accident will also improve the operator's ability to assimilate int'ormation and act on it in such transients. The improvements planned which will most directly enhance the operator's response in loss-of-feed and LOCA situations include:
  .
Certain of the improvements in the control 2 and displays will enhance the ability of the control room operators to react to the transients of concern in the contention, specifically feedwater transients and loss-of-coolant accidents (reactor system leaks). In addition, modifications to the controls and displays made as a result of lessons learned from the TMI-2 accident will also improve the operator's ability to assimilate int'ormation and act on it in such transients. The improvements
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planned which will most directly enhance the operator's response in loss-of-feed and LOCA situations include:
o    The emergency feedwater system will have mimic arrangement of the controls and displays of EFW clearly ~ indicating the flow path from water sources through the pumps and major valves to the steam generators.
o    The emergency feedwater system will have mimic arrangement of the controls and displays of EFW clearly ~ indicating the flow path from water sources through the pumps and major valves to the steam generators.
o Instrumentation measuring the flow of emergency feedwater to each steam generator has been added with the displays integrated into the above described mimic .
o Instrumentation measuring the flow of emergency feedwater to each steam generator has been added with the displays integrated into the above described mimic .
o    Primary relief valres will have accelerometers attached to each valve as well as downstream flow measuring devices with indicators located on the main control boards.
o    Primary relief valres will have accelerometers attached to each valve as well as downstream flow measuring devices with indicators located on the main control boards.
o The reactor building sump will have wide range level instrumentation installed with indicators in the Control Room.
o The reactor building sump will have wide range level instrumentation installed with indicators in the Control Room.
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o    An unambiguous indicator of the margin to saturation
o    An unambiguous indicator of the margin to saturation
,                for both reactor hot legs will be installed in the I
,                for both reactor hot legs will be installed in the I
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o    The Engineered Safeguards Features Actuation System status panel in the Control Room will be modified to have more readable labels and brighter lights on the status indicators, improving the operators' ability to note abnormal status after system actuation.
o    The Engineered Safeguards Features Actuation System status panel in the Control Room will be modified to have more readable labels and brighter lights on the status indicators, improving the operators' ability to note abnormal status after system actuation.
BY WITNESSES WALSH, MEEK AND ES"iK]A :
BY WITNESSES WALSH, MEEK AND ES"iK]A :
: 2. The contention states that the design of the TMI-l Control Room violates the provisions of General Design
: 2. The contention states that the design of the TMI-l Control Room violates the provisions of General Design Criterion 13 of Appendix A to 10 CFR Part 50, which . states:
'
Criterion 13 of Appendix A to 10 CFR Part 50, which . states:
                              .
Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for 3
Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for 3
   ;
   ;
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controls shall be provided to maintain these variables and systems within prescribed operating ranges.
controls shall be provided to maintain these variables and systems within prescribed operating ranges.
Clearly, the instrumentation and control of any power plant should meet the intent of this criterion (although, at the time TMI-1 was designed the criterion did not exist in its present form) .
Clearly, the instrumentation and control of any power plant should meet the intent of this criterion (although, at the time TMI-1 was designed the criterion did not exist in its present form) .
The instrumentation and control of TMI-l meet the criterion. This statement is based on the fact that the
The instrumentation and control of TMI-l meet the criterion. This statement is based on the fact that the design process included a careful review of the instrumentation and controls by both the designers and operators to insure that adequate instrumentation was available for normal and emergency operation.
 
_  ._ _ _ _ _ _    .-
.
design process included a careful review of the instrumentation and controls by both the designers and operators to insure that adequate instrumentation was available for normal and emergency operation.
As with other technologies, improvements can and should be made to instrumentation and control systems as the technology develops.
As with other technologies, improvements can and should be made to instrumentation and control systems as the technology develops.
As a result of Licensee's review of the Control Room design and lessons learned from the TMI-2 accident, a number of ,
As a result of Licensee's review of the Control Room design and lessons learned from the TMI-2 accident, a number of ,
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o    Relocation of controls operated during the first few minutes after a reactor trip and revision of proce-dures, which assure that operators will be able to remain at their normal station facing the control console in the short term following reactor and turbine trips. This enables the operator to concen-trate on the response of key process variables and maintain them within prescribed limits.
o    Relocation of controls operated during the first few minutes after a reactor trip and revision of proce-dures, which assure that operators will be able to remain at their normal station facing the control console in the short term following reactor and turbine trips. This enables the operator to concen-trate on the response of key process variables and maintain them within prescribed limits.
o Improved labels of meters, pushbuttons, switches, and controllers with larger letters, less use of abbre-viations, and a consistent color convention to improve readability.
o Improved labels of meters, pushbuttons, switches, and controllers with larger letters, less use of abbre-viations, and a consistent color convention to improve readability.
o    Addition of outlines and labels to emphasize the functional groupings of controls and displays.        For ex ample , the feedwater system controls will have
o    Addition of outlines and labels to emphasize the functional groupings of controls and displays.        For ex ample , the feedwater system controls will have 9
 
i
9 i
      -
                                                                             \
                                                                             \
l
l
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o      Provision of an automatic reset feature for High Pressure Injection actuation logic circuit on increasing pressure. This will free the Control Room operator from the manual function and allow closer monitoring of the process during transients in which pressure recovers.
o      Provision of an automatic reset feature for High Pressure Injection actuation logic circuit on increasing pressure. This will free the Control Room operator from the manual function and allow closer monitoring of the process during transients in which pressure recovers.
: 3. The contention recommends that, in view of the numerous operating difficulties encountered with TMI-2, and the similarities in design and construction between TMI-l and TMI-2, a thorough human factors engineering review of the TMI-1 Control Room be made, in order to provide assurance that the operator-instrumentation interface is such that the operators can exercise adequate control over the reactor and prevent off-site consequences from anticipated operational occurrences and postulated accidents.
: 3. The contention recommends that, in view of the numerous operating difficulties encountered with TMI-2, and the similarities in design and construction between TMI-l and TMI-2, a thorough human factors engineering review of the TMI-1 Control Room be made, in order to provide assurance that the operator-instrumentation interface is such that the operators can exercise adequate control over the reactor and prevent off-site consequences from anticipated operational occurrences and postulated accidents.
Licensee concurs with the desirability of performing a thorough review of the THI-1 Control Room design and is doing so, as has been previously stated. It is important to bear in mind , however , that the operator-process interface was consid-ered in the design of the TMI-l Control Room. Specifically,
Licensee concurs with the desirability of performing a thorough review of the THI-1 Control Room design and is doing so, as has been previously stated. It is important to bear in mind , however , that the operator-process interface was consid-ered in the design of the TMI-l Control Room. Specifically, i
,
i i
i i
i I .
I .
t
t


during the design phase of TMI-1, physical mockups of the control boards were constracted and paper facsimiles of controls e,nd displays were used to determine the location of these devices on the panels. Simulated operations were per formed . Final decis' ions on component locations were made in conference among design engineers and Metropolitan Edison operating personnel.      This procedure resulted in physical arrangements which, in general, are logical and promote ease of operation.
during the design phase of TMI-1, physical mockups of the control boards were constracted and paper facsimiles of controls e,nd displays were used to determine the location of these devices on the panels. Simulated operations were per formed . Final decis' ions on component locations were made in conference among design engineers and Metropolitan Edison operating personnel.      This procedure resulted in physical arrangements which, in general, are logical and promote ease of operation.
                            .
There are also significant differences between the TMI-1 and TMI-2 Control Rooms in the arrangement of the cone.rols and in the physical dimensions. The following table compares some of these features.
There are also significant differences between the TMI-1 and TMI-2 Control Rooms in the arrangement of the cone.rols and in the physical dimensions. The following table compares some of these features.
TMI-l          TMI-2 Overall Control Room Size            58' X 40'      75' X 56' Operating Area Size 39' X 25'      42' X 36' Linear Feet of Control Boards            107'          168' Total Number of Annunciators              660          1020 BY WITNESSES WALSH, ESTRADA, CHRISTENSEN AND SHERIDAN:
TMI-l          TMI-2 Overall Control Room Size            58' X 40'      75' X 56' Operating Area Size 39' X 25'      42' X 36' Linear Feet of Control Boards            107'          168' Total Number of Annunciators              660          1020 BY WITNESSES WALSH, ESTRADA, CHRISTENSEN AND SHERIDAN:
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of control room arrangement enhances operator response during          I transient conditions.      The arrangement of panels in the two control rooms also differs.      Panels containing Reactor Coolant l
of control room arrangement enhances operator response during          I transient conditions.      The arrangement of panels in the two control rooms also differs.      Panels containing Reactor Coolant l
Drain Tank parameters and alarms, Reactor Building temperature recorders and Reactor Building high temperature and high
Drain Tank parameters and alarms, Reactor Building temperature recorders and Reactor Building high temperature and high
                          *
                                    .


  .
pressure alarms are not visible in the Unit 2 Control Room from the operating area. On Unit 1 these panels are located in the operating area and the indicators and alarms are visible to the operators.                                                        '
pressure alarms are not visible in the Unit 2 Control Room from the operating area. On Unit 1 these panels are located in the operating area and the indicators and alarms are visible to the operators.                                                        '
: 4. The contention asserts that TMI-l startup should be delayed until the modifications identified by the human factors review of the Control Room design have been implemented.
: 4. The contention asserts that TMI-l startup should be delayed until the modifications identified by the human factors review of the Control Room design have been implemented.
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: c. Operators have been trained to use the improvements.
: c. Operators have been trained to use the improvements.
We do not consider such improvements to be a necessary prerequisite to startup. In the present schedule appropriate relabeling and functional demarcation of the main control boards are the first modifications that will be completed.      The expected completion date is in early 1981.      The other modifica-tions identified thus far will proceed through the steps identified above.
We do not consider such improvements to be a necessary prerequisite to startup. In the present schedule appropriate relabeling and functional demarcation of the main control boards are the first modifications that will be completed.      The expected completion date is in early 1981.      The other modifica-tions identified thus far will proceed through the steps identified above.
                                                                      .


                    ,                          -_
The review that was described above in Section 1 is not considered to be a "one time" process that is now essentially complete. Further changes to the Control Room will be reviewed using the methods and criteria developed in this review. By this method the human factors aspects of the control room design can be maintained.
The review that was described above in Section 1 is not considered to be a "one time" process that is now essentially complete. Further changes to the Control Room will be reviewed using the methods and criteria developed in this review. By this method the human factors aspects of the control room design can be maintained.
RESPONSE TO ANGRY CONTENTION NO. V(C)
RESPONSE TO ANGRY CONTENTION NO. V(C)
BY WITNESSES WALSH AND ESTRADA:
BY WITNESSES WALSH AND ESTRADA:
This contention asserts that NRC has not provided reason-able assurance of public health and safety since it has not required that analysir, of the design and layout of the Control Room, in accordance with NUREG 0600 be performed and that nodifications resulting therefrom be implemented. Apparently, the basic thrust of this contention is the desire for a human factors review of the control Room. Our position regarding a human factors review and the Lmplementation of panel improve-ments generated by that review is described in the testimony above in response to Sholly Contention No.15.
This contention asserts that NRC has not provided reason-able assurance of public health and safety since it has not required that analysir, of the design and layout of the Control Room, in accordance with NUREG 0600 be performed and that nodifications resulting therefrom be implemented. Apparently, the basic thrust of this contention is the desire for a human factors review of the control Room. Our position regarding a human factors review and the Lmplementation of panel improve-ments generated by that review is described in the testimony above in response to Sholly Contention No.15.
                                                                    ,


_ ___              _ _ _ --
. .
PATRICK S. WALSE Business Address:  GPU Service Corporation 100 Interpace Parkway Parsippany, New Jersey  07054 Education:        B.S., Chemical Engineering, Illinois Institute of Technology, 1969.
PATRICK S. WALSE Business Address:  GPU Service Corporation 100 Interpace Parkway Parsippany, New Jersey  07054 Education:        B.S., Chemical Engineering, Illinois Institute of Technology, 1969.
M.S.E., Nuclear Engineering, Catholic University of America, 1978.
M.S.E., Nuclear Engineering, Catholic University of America, 1978.
Line 281: Line 197:
Officer, U.S. Navy, 1970 to 1974.      Held positions of Nuclear Submarine Engineering Department Division Officer and Nuclear Prototype Instructor and Training Officer.
Officer, U.S. Navy, 1970 to 1974.      Held positions of Nuclear Submarine Engineering Department Division Officer and Nuclear Prototype Instructor and Training Officer.
Professional Affiliations:    Registered Professional Engineer , New Je rsey.
Professional Affiliations:    Registered Professional Engineer , New Je rsey.
      .


_  _  _ __      _ _ - .            _ _ _ _ _
WILLIAM E. MEEK Business Address:      Gilbert Associates, Inc.
WILLIAM E. MEEK Business Address:      Gilbert Associates, Inc.
525 Lancaster Avenue Reading, Pennsylvania              19603 Education:            B.S.M.E., Mississippi State University, 1957. Postgraduate Study in Mechanical Engineering, Rutgers University,1963.
525 Lancaster Avenue Reading, Pennsylvania              19603 Education:            B.S.M.E., Mississippi State University, 1957. Postgraduate Study in Mechanical Engineering, Rutgers University,1963.
Line 297: Line 211:
Senior Proj ect Engineer, Gilbert Associa tes, Inc. , 1971 to 1973.
Senior Proj ect Engineer, Gilbert Associa tes, Inc. , 1971 to 1973.
Responsible for coordination and direction of mechanical, nuclear, building service, and chemical design personnel and associated drafting groups for Florida Power Corporation's Crystal River Nuclear Unit 4.            Developed conceptual plant designs for 2000 and 3000 MWt high temperature gas            '
Responsible for coordination and direction of mechanical, nuclear, building service, and chemical design personnel and associated drafting groups for Florida Power Corporation's Crystal River Nuclear Unit 4.            Developed conceptual plant designs for 2000 and 3000 MWt high temperature gas            '
                                                                          .
cooled reactors for General Atomic Corporation, San Diego, California.
cooled reactors for General Atomic Corporation, San Diego, California.
Mechanical Engineer, Gilbert Associates, Inc., 1967 to 1971.                Involved in design engineering and equipment specifications for mechanical equipment, instruments and controls for Metropolitan Edison Company's Three Mile Island Nuclear Station, Unit 1;
Mechanical Engineer, Gilbert Associates, Inc., 1967 to 1971.                Involved in design engineering and equipment specifications for mechanical equipment, instruments and controls for Metropolitan Edison Company's Three Mile Island Nuclear Station, Unit 1;
                                            ,


_ _ _ _ _ _  __      _            _
t l
,
Florida Power Corporation's Crystal River Nuclear Station, Unit 3; and South Carolina's Electric & Gas Company's V.C.
t
  .
l Florida Power Corporation's Crystal River Nuclear Station, Unit 3; and South Carolina's Electric & Gas Company's V.C.
Summer Nuclear Station, Unit 1.
Summer Nuclear Station, Unit 1.
Station Mechanical Engineer, Mississippi Power & Light Company, 1963 to 1967.
Station Mechanical Engineer, Mississippi Power & Light Company, 1963 to 1967.
Line 321: Line 230:
I
I
_2_
_2_
                                              .


_ __ _
. .
Industry Committee - American Power Conference.
Industry Committee - American Power Conference.
Atomic Industrial Forum - Subcommittee on Operations, 'Ihree Mile Island Lessons Learned Task Force.
Atomic Industrial Forum - Subcommittee on Operations, 'Ihree Mile Island Lessons Learned Task Force.
Registered Professional Engineer, Mississippi, Pennsylvania and Florida.
Registered Professional Engineer, Mississippi, Pennsylvania and Florida.
                                                                    .
G l
G l
l
l
    . . _ . - _ -
                                            .      .__


  .
JULIEN M. CHRISTENSEN Business Address:  SSSV, Inc.
JULIEN M. CHRISTENSEN Business Address:  SSSV, Inc.
2600 Far Hills Avenue Dayton, Ohio    45419 Education:        B.S., Accounting, University of Illionois, 1940.
2600 Far Hills Avenue Dayton, Ohio    45419 Education:        B.S., Accounting, University of Illionois, 1940.
Line 341: Line 243:
Professor, Department of Industrial Engineering and Operations Research. Wayne State University, 1977 to 1978. Research
Professor, Department of Industrial Engineering and Operations Research. Wayne State University, 1977 to 1978. Research
;
;
'
and teaching, primarily in areas of human factors (ergonomics), safety and envi-ronmental studies and systems.
and teaching, primarily in areas of human factors (ergonomics), safety and envi-ronmental studies and systems.
Professor and Chairman, Department of Industrial Engineering and Operations Research, College of Engineering , Wayne State University, 1974 to 1977.
Professor and Chairman, Department of Industrial Engineering and Operations Research, College of Engineering , Wayne State University, 1974 to 1977.
Line 348: Line 249:
decision-making, safety and physical anthropology. Personnel included a wide range of skills such as experimental psychology, mathematics , physics , statis-    '
decision-making, safety and physical anthropology. Personnel included a wide range of skills such as experimental psychology, mathematics , physics , statis-    '
tics, engineering, physiolgy and anthropol-l                    Ogy.
tics, engineering, physiolgy and anthropol-l                    Ogy.
Research Scientist through Branch Chief
Research Scientist through Branch Chief Aerospace Medical Research Laboratory,
                .
Aerospace Medical Research Laboratory,


  .
Wright-Patterson Air Force Base,1946 to 1956. Research and applications in experimental psychology and human factors engineering. Research on visual perception with simple and complex stimuli, effects of high brightnesses on visual functions, visual form field expansion, methods of activity analysis, workplace layout, navigation plotter design, weightlessness, and systems. Applications work included contributions to specifications, standards and handbooks and direct application of human engineering principles of numerous aircraf t and command / control communication centers.
Wright-Patterson Air Force Base,1946 to 1956. Research and applications in experimental psychology and human factors engineering. Research on visual perception with simple and complex stimuli, effects of high brightnesses on visual functions, visual form field expansion, methods of activity analysis, workplace layout, navigation plotter design, weightlessness, and systems. Applications work included contributions to specifications, standards and handbooks and direct application of human engineering principles of numerous aircraf t and command / control communication centers.
United States Air Force, 1943 to 1946.
United States Air Force, 1943 to 1946.
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Visiting Lecturer, Air Force Institute of Technology (AFIT) for more than 10 years.
Visiting Lecturer, Air Force Institute of Technology (AFIT) for more than 10 years.
Lecturer and technical adviser to Instituto Technologico y de Estudios Su Monterey, Mexico (one year). periores, Lecturer, American Psychological Association / National Science Foundation Visiting Scientist Program (four years) .
Lecturer and technical adviser to Instituto Technologico y de Estudios Su Monterey, Mexico (one year). periores, Lecturer, American Psychological Association / National Science Foundation Visiting Scientist Program (four years) .
                                        '
l t
l t


  .
f Cadat Lecturer at numerous other uni-versities, high schools, societies, etc. A representative sampling includes: Purdue University, Indiana University, Miami University, University of Cincinnati, The University of Michigan, Southern Illinois University; Tau Beta Pi, IEEE, AIIE, ASME, Dayton Engineer's Club.
f Cadat Lecturer at numerous other uni-versities, high schools, societies, etc. A representative sampling includes: Purdue University, Indiana University, Miami University, University of Cincinnati, The University of Michigan, Southern Illinois University; Tau Beta Pi, IEEE, AIIE, ASME, Dayton Engineer's Club.
Honors and Professional Affiliations:  American Men and Women of Science, Who's Who Among Authors and Journalists, Community Leaders and Noteworthy Americans, Men of Achievement, Notable Americans.
Honors and Professional Affiliations:  American Men and Women of Science, Who's Who Among Authors and Journalists, Community Leaders and Noteworthy Americans, Men of Achievement, Notable Americans.
Line 381: Line 277:
Consultant:  National Bureau of Standards (NBS); National Institute for Occupational Safety and Health (NIOSH); Air Forces Office of Scientific Re'dearch; Air Forces  ;
Consultant:  National Bureau of Standards (NBS); National Institute for Occupational Safety and Health (NIOSH); Air Forces Office of Scientific Re'dearch; Air Forces  ;
{
{
Human Resources Laboratory; U.S. Army Human
Human Resources Laboratory; U.S. Army Human 1
 
Engineering Laboratory; Standard Oil of New Jersey; United Air Lines; Ford Motor Co.; &  1
_ _ _ _
    .
1 Engineering Laboratory; Standard Oil of New Jersey; United Air Lines; Ford Motor Co.; &  1
                                                               )
                                                               )
others.
others.
Line 410: Line 303:


1
1
                                              .
.                                              1 Consultant to the National Academy of Sciences Working Group cn Role of Man in    l Space Research. Mr. R. W. Porter , Vice l
.                                              1 Consultant to the National Academy of Sciences Working Group cn Role of Man in    l Space Research. Mr. R. W. Porter , Vice l
President, General Electric Company,        !
President, General Electric Company,        !
Line 424: Line 316:
for numerous systems, including B-47, B-50, B-52, B-66, B-70, C-97, C-131, KC-135, Lcng Range Interceptor (LRI), and A/N CPS 6-B, developed procedures for the effective inclusion and integration of human engi-    l neering data during the development cycle of Air Force Systems.
for numerous systems, including B-47, B-50, B-52, B-66, B-70, C-97, C-131, KC-135, Lcng Range Interceptor (LRI), and A/N CPS 6-B, developed procedures for the effective inclusion and integration of human engi-    l neering data during the development cycle of Air Force Systems.
Editor and co-author of Combat Navigatory Proficiency Test for Strategic Air Command.
Editor and co-author of Combat Navigatory Proficiency Test for Strategic Air Command.
                                              ,
l (Test used to select lead crew navigators    I for European theatre in World War II) .
l (Test used to select lead crew navigators    I for European theatre in World War II) .
During World War II, deeeloped with Dr. M.
During World War II, deeeloped with Dr. M.
J. Warrick first battery of tests for
J. Warrick first battery of tests for selection and classification of pilots, bombardiers and navigators.
 
_  _ _ - - _ _ _
  .
selection and classification of pilots,
,
bombardiers and navigators.
Aerospace Medical Association.
Aerospace Medical Association.
American Association for the Advancement of Science.
American Association for the Advancement of Science.
Line 450: Line 335:
                   " Psychological Factors Involved in the Design of Air Navigation Plotters".
                   " Psychological Factors Involved in the Design of Air Navigation Plotters".
Memorandum Report No. TSEAA-694-ID, Eq. Air Materiel Command, Wright-Patterson Air Force Base, Ohio, October 1946. ATI 105 688. Also appears in Psychological Research on Equipment Design, AAF Aviation
Memorandum Report No. TSEAA-694-ID, Eq. Air Materiel Command, Wright-Patterson Air Force Base, Ohio, October 1946. ATI 105 688. Also appears in Psychological Research on Equipment Design, AAF Aviation
_    _                    _ - .


_ -  . _ .                --. - -_--                            .
l i
                                                                          -            . . . . _ _ _      -      _ -- - -
J j                              Psychology Program Research Report 19,
l
    .
i J
j                              Psychology Program Research Report 19,
;                              Chapter 5, Paul M. Fitts, Editor, 1947.
;                              Chapter 5, Paul M. Fitts, Editor, 1947.
                               " Aerial Analysis of Navigator Duties with Special Reference to Equipment Design and Workplace Layout.                        I. Development of Technique ," Memorandum Report No.
                               " Aerial Analysis of Navigator Duties with Special Reference to Equipment Design and Workplace Layout.                        I. Development of Technique ," Memorandum Report No.
Line 468: Line 348:
MCRE XD-6 94 -IP , Hg. Air Materiel Command, Wright-Patterson AFB, Ohio , October 1948.
MCRE XD-6 94 -IP , Hg. Air Materiel Command, Wright-Patterson AFB, Ohio , October 1948.
ATI 42 468.
ATI 42 468.
                               "The Sampling Method of Activity Analysis and Its Application to the Problem of Aircraft Crew Requirements," Scientific
                               "The Sampling Method of Activity Analysis and Its Application to the Problem of Aircraft Crew Requirements," Scientific Methods for Use in the Investigation of Flight Crew Requirements, Flight Safety Foundation, Woods Hole, Massachusetts,                                                          ,
  .
Methods for Use in the Investigation of Flight Crew Requirements, Flight Safety Foundation, Woods Hole, Massachusetts,                                                          ,
1948.
1948.
                               " Human Engineering of the AMCPS-6B System,"
                               " Human Engineering of the AMCPS-6B System,"
Line 477: Line 355:
'                            "The Sampling Technique for Use in Activity Analysis," Personnel Psychology, Volume 3, No. 3 Autumn, 1950.
'                            "The Sampling Technique for Use in Activity Analysis," Personnel Psychology, Volume 3, No. 3 Autumn, 1950.
Quantitative Instrument Reading as a l
Quantitative Instrument Reading as a l
'
Function of Dial Design, Exposure Time, Preparatory Fixation, and Practice.                              WADC Technical Report No. 52-116, Wright Air Development Center, Wright-Patterson AFB, Chio, September 1952. AD 101.
Function of Dial Design, Exposure Time, Preparatory Fixation, and Practice.                              WADC Technical Report No. 52-116, Wright Air Development Center, Wright-Patterson AFB, Chio, September 1952. AD 101.
Reports of Research in the Field of Engineering Psychology. WADC Technical Report 53-75, Wright Air Development Center, Wright-Patterson AFB, Ohio, April 1953.                    AD 6991.
Reports of Research in the Field of Engineering Psychology. WADC Technical Report 53-75, Wright Air Development Center, Wright-Patterson AFB, Ohio, April 1953.                    AD 6991.
_
                  ., _ _ _ _      _ _ - _ - . - - _ .          _ _ _ _          _ . _              ._ _ _    _ _ _


                            . _ _ _      . - _ _ _ _ _ _ _ _ _ _      ___
.
   "The Effect of Selected Visual Training Procedures on the Visual Form Field."                          WADC Technical Report 54-239, Wright Air Development Center, Wright-Patterson AFB, Ohio, April 1955.      AD 76 423.
   "The Effect of Selected Visual Training Procedures on the Visual Form Field."                          WADC Technical Report 54-239, Wright Air Development Center, Wright-Patterson AFB, Ohio, April 1955.      AD 76 423.
   "The Importance of Certain Dial Design Variables in Quantitative Instrument Reading."      WADC Technical Report 55-376, Wright Air Development Center, Wright-Patterson AFB, Chio, October 1955.
   "The Importance of Certain Dial Design Variables in Quantitative Instrument Reading."      WADC Technical Report 55-376, Wright Air Development Center, Wright-Patterson AFB, Chio, October 1955.
Line 500: Line 373:
(one of several contributors).
(one of several contributors).
i
i
                                                                          !
                          -


__
       .                                                        l l
       .                                                        l l
             "The Use of Space to Study Man."      Psi Chi Quarterly, University of Dayton, Autumn, 1963.
             "The Use of Space to Study Man."      Psi Chi Quarterly, University of Dayton, Autumn, 1963.
Line 513: Line 383:
           " Human Engineering:      Past, Present, Future."    Bio-environmental Symposium, Aerospace Medical Division, Brooks Air                1 Force Base, Texas, October 1964.
           " Human Engineering:      Past, Present, Future."    Bio-environmental Symposium, Aerospace Medical Division, Brooks Air                1 Force Base, Texas, October 1964.
l
l
           " Performance Capabilities of Man on . Earth
           " Performance Capabilities of Man on . Earth and In Space:    A Study in Continuity."            1 American Astronautical Society, Advances in the Astronautical Sciences, 20, 1965.
,
and In Space:    A Study in Continuity."            1 American Astronautical Society, Advances in the Astronautical Sciences, 20, 1965.
( Also catalogued as AMRL-TR-66-211. )
( Also catalogued as AMRL-TR-66-211. )
           "Individ uals and Us." (Presidential Address for the Human Factors Society.)
           "Individ uals and Us." (Presidential Address for the Human Factors Society.)
Line 521: Line 389:
( Also catalogued as AMRL-TR-65-221. )
( Also catalogued as AMRL-TR-65-221. )
(With Miller, J.W., Fa r r , M. J., Beach, L.R., and Katchmar , L.T. ) " Contributions of Engineerlag Psychology to Military Systems." Chapter 12 in Uhlander, J.E.
(With Miller, J.W., Fa r r , M. J., Beach, L.R., and Katchmar , L.T. ) " Contributions of Engineerlag Psychology to Military Systems." Chapter 12 in Uhlander, J.E.
(Ed.) Psychological Research in National Defense Today, TR-S-1, U.S. Army Behavioral
(Ed.) Psychological Research in National Defense Today, TR-S-1, U.S. Army Behavioral l
                                                                ,
Sciences Research Laboratory, Arlington,              l Virginia, 1967.
l Sciences Research Laboratory, Arlington,              l Virginia, 1967.
j (With Mills, R.C.)      "What does the Cperator do in Complex Systems?" Human Factors, 9,
j (With Mills, R.C.)      "What does the Cperator do in Complex Systems?" Human Factors, 9,
_g_
_g_
!
  , . .  .                      --      _-          --    - _ ,


.
(4), 1967.    (Also catalogued as AMRL-TR-67-100.) In Chiles, W.D. (Ed.),
(4), 1967.    (Also catalogued as AMRL-TR-67-100.) In Chiles, W.D. (Ed.),
Assessment of Complex Operator Performance, AMRL TR-67-239 Aerospace Medical Research Laboratories, Wright-Patterson Air Force Base, Ohio August 1967.
Assessment of Complex Operator Performance, AMRL TR-67-239 Aerospace Medical Research Laboratories, Wright-Patterson Air Force Base, Ohio August 1967.
Line 542: Line 406:
     " Overview of Aerospace Medical Research Laboratory Human Engineering Program."
     " Overview of Aerospace Medical Research Laboratory Human Engineering Program."
Proceedings of the " Psychology in the Air Force" Sympo sium , USAF Academy, Colorado, March-April 1970.    (Also catalogued as AMRL TR-70-64.)
Proceedings of the " Psychology in the Air Force" Sympo sium , USAF Academy, Colorado, March-April 1970.    (Also catalogued as AMRL TR-70-64.)
  -
     "An Evaluation of Some Common Methods of Activity Analysis."    Proceedings of the NATO Advanced Study Institute cn Human Factors / Ergonomics:    Research Methods ,
     "An Evaluation of Some Common Methods of Activity Analysis."    Proceedings of the NATO Advanced Study Institute cn Human Factors / Ergonomics:    Research Methods ,
Bellagio, Italy, September 1971.
Bellagio, Italy, September 1971.
Line 548: Line 411:
Applied Ergonomics, 1972.
Applied Ergonomics, 1972.
l
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                                                  .


                                                    - _ _
  .
       " Human Factors Engineering in the United States Air Force." Proceedings of the NATO Research Study Group on Human Engineering /Anthropotechnic Soesterberg, The Netherlands, June 1973.
       " Human Factors Engineering in the United States Air Force." Proceedings of the NATO Research Study Group on Human Engineering /Anthropotechnic Soesterberg, The Netherlands, June 1973.
       " Ergonomics--Where Have We Been and Where Are We Going?"    Ergonomics, 19, No . 3, May 1976.
       " Ergonomics--Where Have We Been and Where Are We Going?"    Ergonomics, 19, No . 3, May 1976.
Line 563: Line 423:
Honeywell Report IR-1, Air Forces Materials Lab., Wright-Patterson Air Force Base, Ohio, February, 1980.
Honeywell Report IR-1, Air Forces Materials Lab., Wright-Patterson Air Force Base, Ohio, February, 1980.
     " Human Factors in Hazard / Risk Evaluation."        l Proceedings of the Symposium on Human Factors and Industrial Design in Consumer            i Products. Tufts University, Medford, Mass., May, 1980.
     " Human Factors in Hazard / Risk Evaluation."        l Proceedings of the Symposium on Human Factors and Industrial Design in Consumer            i Products. Tufts University, Medford, Mass., May, 1980.
                                                  '
i
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_ __
__
THOMAS B. SHERIDAN Business Address:  Massachusetts Institute of Technology Room 1-110 77 Massachusetts Avenue Cambridge, Massachusetts    02139            .
THOMAS B. SHERIDAN Business Address:  Massachusetts Institute of Technology Room 1-110 77 Massachusetts Avenue Cambridge, Massachusetts    02139            .
Education:        B.S., Purdue University, 1951.      M.S.,
Education:        B.S., Purdue University, 1951.      M.S.,
University of California, Los Angeles, 1954. Sc.D., Systems Engineering and Psychology, Massachusetts Institute of Technology, 1959.                          -
University of California, Los Angeles, 1954. Sc.D., Systems Engineering and Psychology, Massachusetts Institute of Technology, 1959.                          -
    '
Experience:        Professor of Mechanical Engineering and Professor of Engineering and Applied Psychology, Massachusetts Institute of Technology, 1970 to present.      Responsible for the Man-Machine Systems Laboratory; developed interdepartmental graduate degree program in Technology and Policy; teaches a graduate course in man-machine systems and the core Seminars in Technology and Policy; has taught control, design and other engineering subjects. Has conducted research on mathematical models of human operator and socio-economic systems; on man-computer interaction in piloting aircraft and in supervising undersea and industrial robotic systems; and on computer
Experience:        Professor of Mechanical Engineering and Professor of Engineering and Applied Psychology, Massachusetts Institute of Technology, 1970 to present.      Responsible for the Man-Machine Systems Laboratory; developed interdepartmental graduate degree program in Technology and Policy; teaches a graduate course in man-machine systems and the core Seminars in Technology and Policy;
* has taught control, design and other engineering subjects. Has conducted research on mathematical models of human operator and socio-economic systems; on man-computer interaction in piloting aircraft and in supervising undersea and industrial robotic systems; and on computer
'                        graphic technology for information searching and group decision-making.
'                        graphic technology for information searching and group decision-making.
Associate Professor, Massachusetts Insti-        i
Associate Professor, Massachusetts Insti-        i tute of Technology, 1964 to 1970.                I Assistant Professor, Massachusetts Insti-tute of Technology, 1959 to 1964.
                                                                          ,
tute of Technology, 1964 to 1970.                I Assistant Professor, Massachusetts Insti-tute of Technology, 1959 to 1964.
Instructor, Massachusetts Institute of Technology, 1956 to 1959.
Instructor, Massachusetts Institute of Technology, 1956 to 1959.
Research Assistant, Massachusetts Institute of Technology, 1954 to 1956.
Research Assistant, Massachusetts Institute of Technology, 1954 to 1956.
                      .
Served as visiting r~aculty member at the        i University of California at Berkeley, Stanford University and the Technical University of Delft, Netherlands.
Served as visiting r~aculty member at the        i
                                                                          '
University of California at Berkeley, Stanford University and the Technical University of Delft, Netherlands.
                                                           ;
                                                           ;


_ _ _ _ _ ___  _ _ _ _
l Honors and Professional Affiliations:  1977 Recipient of the human Factors Society's Paul M. Fritts Award for contri-butions to education. IEEE Systems Man and Cybernetics Society (past President). IEEE Committee on Technology Forecasting and Assessment (past Chairman). Formerly                        '
  .
l Honors and
'
Professional Affiliations:  1977 Recipient of the human Factors Society's Paul M. Fritts Award for contri-butions to education. IEEE Systems Man and
!
'
Cybernetics Society (past President). IEEE Committee on Technology Forecasting and Assessment (past Chairman). Formerly                        '
Editor, IEEE Transactions on Man-Machine
Editor, IEEE Transactions on Man-Machine
_ Systems. Fellow, Human Factors Society.
_ Systems. Fellow, Human Factors Society.
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Sheridan, T.B., "Com section in Science , puters Reviewand and Man,"
Sheridan, T.B., "Com section in Science , puters Reviewand and Man,"
Preview        a published jointly by Childrens Press, Chicago, and Natl. College of Education, 4                Evanston, Illinois, 1964.
Preview        a published jointly by Childrens Press, Chicago, and Natl. College of Education, 4                Evanston, Illinois, 1964.
_.


.
Sheridan, T.B., " Man-Machine Systems," 1967 McGraw Hill Yearbook of Sc).ence and Technology, McGraw Hill, N.Y., pp. 66-74.
Sheridan, T.B., " Man-Machine Systems," 1967 McGraw Hill Yearbook of Sc).ence and Technology, McGraw Hill, N.Y., pp. 66-74.
Sheridan, T.B.,  " Vehicle Handling:
Sheridan, T.B.,  " Vehicle Handling:
Line 627: Line 468:
Sheridan, T.B., and Ferrell, W.R., " Remote Manipulative Control with Transmission Delay," IEEE Transactions, P.T.G. Human
Sheridan, T.B., and Ferrell, W.R., " Remote Manipulative Control with Transmission Delay," IEEE Transactions, P.T.G. Human
   , Factors in Electronics, March 1963.
   , Factors in Electronics, March 1963.
__
j      -
j      -
i Sheridan, T.B., Paynter, H.M., and Coons, S.A., "Some Novel Display Techniques for Driving Simulation," IEEE Trans. on Human
i Sheridan, T.B., Paynter, H.M., and Coons, S.A., "Some Novel Display Techniques for Driving Simulation," IEEE Trans. on Human Factors in Electronics, Vol. HFE-5,    n.l.,
,
Factors in Electronics, Vol. HFE-5,    n.l.,
,
Sept. 1964.
Sept. 1964.
Zeigler, B.P., and Sheridan, T.B., " Human Use of Short Term Memory in Processing Information on a Console," IEEE Trans. on Human Factors in Electronics, Sept.      1965.
Zeigler, B.P., and Sheridan, T.B., " Human Use of Short Term Memory in Processing Information on a Console," IEEE Trans. on Human Factors in Electronics, Sept.      1965.
Sheridan, T.B.,    "Three Models of Preview Control," IEEE Trans, on Human Factors in Electronics, June 1966.
Sheridan, T.B.,    "Three Models of Preview Control," IEEE Trans, on Human Factors in Electronics, June 1966.
Knowles, W.B.,  and Sheridan  T.B.,  "The
Knowles, W.B.,  and Sheridan  T.B.,  "The
           ' Feel' of Rotary Controls: Friction and
           ' Feel' of Rotary Controls: Friction and Inertia," Human Factors, June 1966, pp.
  '
Inertia," Human Factors, June 1966, pp.
209-215.
209-215.
Ferrell, W.R., and Sheridan, T.B., " Super-visory Control of Remote Manipulation,"
Ferrell, W.R., and Sheridan, T.B., " Super-visory Control of Remote Manipulation,"
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Sheridan, T.B., and Roland, R.D., "A Normative-Model for Control of Vehicle Trajectory in an Emergency Maneuver,"
Sheridan, T.B., and Roland, R.D., "A Normative-Model for Control of Vehicle Trajectory in an Emergency Maneuver,"
Highway Research Record, No. 195, 1967, pp.
Highway Research Record, No. 195, 1967, pp.
83-97.                                                    i
83-97.                                                    i Vickers, W.H. and Sheridan, T.B., "A Dynamic Model of an Agonist-Antagonist Muscle Pair," paper 38 in Proc. 4th Annual NASA-Univ. Conf. on Manual Control, March 1968 (NASA SP in press), also published in IEEE Trans. on Man-Machine Systems, March 1968.
                                                                  '
Vickers, W.H. and Sheridan, T.B., "A Dynamic Model of an Agonist-Antagonist Muscle Pair," paper 38 in Proc. 4th Annual NASA-Univ. Conf. on Manual Control, March 1968 (NASA SP in press), also published in IEEE Trans. on Man-Machine Systems, March 1968.
Sheridan, T.B.,    "What's a Man Machine?",
Sheridan, T.B.,    "What's a Man Machine?",
editorial in IEEE Trans. on Man-Machine Systems, Vol . MMS-9, No. 1, March 1968.
editorial in IEEE Trans. on Man-Machine Systems, Vol . MMS-9, No. 1, March 1968.
Sheridan, T.B., " Big Brother as Driver:
Sheridan, T.B., " Big Brother as Driver:
l New Demands and Problems for the Man at the Wheel," Human Factors, 1970, 17(1), pp.                  i 95-101.                                                  t
l New Demands and Problems for the Man at the Wheel," Human Factors, 1970, 17(1), pp.                  i 95-101.                                                  t
                                                                  '
                          --                        -                              . _ .


          .
  .
(
(
I
I
                                                    !
:    Sheridan, T.B., "On How Often the              l Supervisor Should Sample," Proc. IEEE Intl.
:    Sheridan, T.B., "On How Often the              l Supervisor Should Sample," Proc. IEEE Intl.
Symposium on Man-Machine Systems, Cambridge, England, Sept. 1969, also in IEEE Trans. Systems, Science and cybernetics, SSC-6 No. 2, April, 1970, pp.
Symposium on Man-Machine Systems, Cambridge, England, Sept. 1969, also in IEEE Trans. Systems, Science and cybernetics, SSC-6 No. 2, April, 1970, pp.
Line 675: Line 502:
Human Operator Alertness," Proceedings of        j the National Specialists Meeting in            '
Human Operator Alertness," Proceedings of        j the National Specialists Meeting in            '
Guidance of Aero-Space Vehicles, Institute of Aeronautical Sciences, New York, 1960.
Guidance of Aero-Space Vehicles, Institute of Aeronautical Sciences, New York, 1960.
reprinted as Sheridan, T.B., " Alertness Measurement of the Human Operator of a Continuous Control      l
reprinted as Sheridan, T.B., " Alertness Measurement of the Human Operator of a Continuous Control      l System, Automatic Centrol, March 1961.
                                                    !
System, Automatic Centrol, March 1961.
Sheridan, T.B., "The Human Response Equation," M.I.T. Technology Review,  May, 1962.
Sheridan, T.B., "The Human Response Equation," M.I.T. Technology Review,  May, 1962.
l
l i
                                                !
                                                  .
i


  .          _                      _          _ _
l i
l
I i
                                                    '
l Sheridan, T.B.,  " Engineering Analysis of Canc Information Acquisition," in Linsner, J.W., ed. , Proceedings of the Mobility Research Conference, (M.I.T., 1961), Amer.
i I
i l
Sheridan, T.B.,  " Engineering Analysis of Canc Information Acquisition," in Linsner, J.W., ed. , Proceedings of the Mobility Research Conference, (M.I.T., 1961), Amer.
Foundation for the Blind, New York, May 1962.
Foundation for the Blind, New York, May 1962.
Mickunas, J., and Sheridan, T.B., "Use of an Obstacle Course in Evaluating Mobility of the Blind," Amer. Found. Blind, Res.
Mickunas, J., and Sheridan, T.B., "Use of an Obstacle Course in Evaluating Mobility of the Blind," Amer. Found. Blind, Res.
Line 701: Line 520:
and Kreifeldt, J.G., " Control Models of Creatures Which Look Ahead," Proc. 5th Natl. Symp. on Human Factors in 1
and Kreifeldt, J.G., " Control Models of Creatures Which Look Ahead," Proc. 5th Natl. Symp. on Human Factors in 1
Electronics, IEEE, May 1964.
Electronics, IEEE, May 1964.
                                                    !
Sheridan, T.B., Fabis, B.F., and Roland, R.D., " Preview Control Behavior and Optimal Control Norms," Proc. Second Annual NASA-University Conference on Manual            )
Sheridan, T.B., Fabis, B.F., and Roland, R.D., " Preview Control Behavior and Optimal Control Norms," Proc. Second Annual NASA-University Conference on Manual            )
Control, NASA SP-128, pp. 293-310.
Control, NASA SP-128, pp. 293-310.
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l l
l l
i
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Sheridan , T.B. , " Human Decision Making in High Speed Transportation," IEEE Intl.
Sheridan , T.B. , " Human Decision Making in High Speed Transportation," IEEE Intl.
Line 725: Line 542:
Sheridan, T.B., Ferrell, W.R.,
Sheridan, T.B., Ferrell, W.R.,
D.E., " Human Control of Remote  and Whitney, Computer Manipulators," IEEE NEREM Record , Vol. 10, 1968, pp. 198-199.
D.E., " Human Control of Remote  and Whitney, Computer Manipulators," IEEE NEREM Record , Vol. 10, 1968, pp. 198-199.
.
Sheridan, T.B., Ferrell, W.R.,
Sheridan, T.B., Ferrell, W.R.,
D.E.,                              and Whitney,
D.E.,                              and Whitney,
Line 734: Line 550:
483-494.
483-494.
Sheridan, T.B.,    " Supervisory control of Computer Manipulators" in Advances in External Control of Human Extremities, Yugoslav Comm. for Elec. and Automation, Belgrade, 1970, pp. 353-364.
Sheridan, T.B.,    " Supervisory control of Computer Manipulators" in Advances in External Control of Human Extremities, Yugoslav Comm. for Elec. and Automation, Belgrade, 1970, pp. 353-364.
.
    .
Sheridan, T.B.,  " Citizen Feedback:  New Technology for Social Choice," in MIT Technology Review, Jan. 1971, pp. 47!51.
Sheridan, T.B.,  " Citizen Feedback:  New Technology for Social Choice," in MIT Technology Review, Jan. 1971, pp. 47!51.
Rouse, W.B., and Sheridan,    T.B., "Supervis-ory Sampling and Control:    Sources of Suboptimality in a Tracking Task" in Proc.
Rouse, W.B., and Sheridan,    T.B., "Supervis-ory Sampling and Control:    Sources of Suboptimality in a Tracking Task" in Proc.
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                                                         ;
                                                         ;
Sheridan, T.B.,
Sheridan, T.B.,
                         "Several Roles of Man as a
                         "Several Roles of Man as a Supervisor of Robots", Proc. 6th Congress International Federation of Automatic Control,  M.I.T.,  Cambridge, Mass., Aug.
                                                      '
Supervisor of Robots", Proc. 6th Congress International Federation of Automatic Control,  M.I.T.,  Cambridge, Mass., Aug.
1975.
1975.
i l
i l
  .


    -  .        .-      _ - _              _. .  -    -      _ - - -    .    ..-  _
,
            .
!
Sheridan, T.B.,      "On Interf acing Models ar.d              I Decision Makers", IEEE Proc. International                    !
Sheridan, T.B.,      "On Interf acing Models ar.d              I Decision Makers", IEEE Proc. International                    !
Conference on Cybernetics and Society, Saa                    l Francisco, Sept. 1975.                                          l Sheridan, T.B.,      "On the Human Supervision                ;
Conference on Cybernetics and Society, Saa                    l Francisco, Sept. 1975.                                          l Sheridan, T.B.,      "On the Human Supervision                ;
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;
;
Industrial Robots, University of Nottingham, U.K., March 1976.
Industrial Robots, University of Nottingham, U.K., March 1976.
1
1 Sheridan, T.B.,      " Production Control Task Allocation to Man vs. Computer" Proc. 1976 Joint Automatic Control Conference, Purdue                      l University, July 1976.
                                                                                                  !
!
Sheridan, T.B.,      " Production Control Task Allocation to Man vs. Computer" Proc. 1976 Joint Automatic Control Conference, Purdue                      l University, July 1976.
Sheridan, T.B.,      and Johannsen,    G., Editors, Monitoring Behavior and Supervisory Control, Flenum Press, 1976.                                    '
Sheridan, T.B.,      and Johannsen,    G., Editors, Monitoring Behavior and Supervisory Control, Flenum Press, 1976.                                    '
.
Kiguchi, T., and Sheridan, T.B.,
* Kiguchi, T., and Sheridan, T.B.,
l                                " Selecting Measures of Plant Information:
l                                " Selecting Measures of Plant Information:
Some Criteria Based on Information and
Some Criteria Based on Information and Decision Theory," Proc. 1976 Intl.
'
Decision Theory," Proc. 1976 Intl.
Symposium on Systems, Man and Cybernetics, IEEE/SMC, M Lhington, D.C.
Symposium on Systems, Man and Cybernetics, IEEE/SMC, M Lhington, D.C.
Sherjian, T.B.,      and Sicherman,    A.,
Sherjian, T.B.,      and Sicherman,    A.,
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                                 " Supervision of Dynamic Decision Making in
                                 " Supervision of Dynamic Decision Making in
           '                    Multi-Task Monitoring and Control," 13th Annual Conference on Manual Control, M.I.T., June 15-17, 1977.                                        ,
           '                    Multi-Task Monitoring and Control," 13th Annual Conference on Manual Control, M.I.T., June 15-17, 1977.                                        ,
                                                                                                  !
Palgi, A.,      and Sheridan T.B., " Nutrition Slide Show with Audience Participation," J.                      '
Palgi, A.,      and Sheridan T.B., " Nutrition Slide Show with Audience Participation," J.                      '
                                                                                                  ,
Nutrition Education, Vol. 9, No. 3, July-Sept. 1977, pp. 123-126.
Nutrition Education, Vol. 9, No. 3, July-Sept. 1977, pp. 123-126.
i
i
                                               -g_
                                               -g_
                                                                            .
  , _ .        -    - -.            -
_  _ _    _  , - -


                                            .
  *
                                                          !
Burke, T.E., Sheridan, T.B., et al.,
Burke, T.E., Sheridan, T.B., et al.,
       " Integrating Technology Assessment
       " Integrating Technology Assessment Techniques," Eighth Annual Pittsburuh Conf.
,
Techniques," Eighth Annual Pittsburuh Conf.
on Modeling and Simulation, April 1977.
on Modeling and Simulation, April 1977.
Sheridan, T.B., and Mann, R.W.,      " Design of Control Devices for People with Severe            -
Sheridan, T.B., and Mann, R.W.,      " Design of Control Devices for People with Severe            -
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Sheridan, T.B.,    "The Changing Role of the Pilot from Manual Controller to Computer Supervisor," Proc. Symp, on Man-System Interface: Advances in Workload Study, Air Line Pilots Assn., July 31 and Aug. 1, 1978, pp. 132-143.
Sheridan, T.B.,    "The Changing Role of the Pilot from Manual Controller to Computer Supervisor," Proc. Symp, on Man-System Interface: Advances in Workload Study, Air Line Pilots Assn., July 31 and Aug. 1, 1978, pp. 132-143.
Sheridan, T.B.,    and Tulga,  M.K.,  "A Model for Dynamic Allocation of Human Attention Among Multiple Tasks," Proc. Intl. Conf. on Cybernetics and Society, Tokyo, Japan, Nov.          l 3-7, 1978, pp. 1112-1117, IEEE 78-CH-1306-0-SMC.                                    !
Sheridan, T.B.,    and Tulga,  M.K.,  "A Model for Dynamic Allocation of Human Attention Among Multiple Tasks," Proc. Intl. Conf. on Cybernetics and Society, Tokyo, Japan, Nov.          l 3-7, 1978, pp. 1112-1117, IEEE 78-CH-1306-0-SMC.                                    !
                                                          !
Sheridan, T.B., Verplank, W.L.,
Sheridan, T.B., Verplank, W.L.,
T.L., " Human / Computer Control ofand    Brooks, Undersea Teleoperators," Proc. Intl. Conf. on Cybernetics and Society, Tokyo, Japan, Nov.
T.L., " Human / Computer Control ofand    Brooks, Undersea Teleoperators," Proc. Intl. Conf. on Cybernetics and Society, Tokyo, Japan, Nov.
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Tulga, M.K. and Sheridan, T.B., " Dynamic Decisions and Work Load in Multi-Task Supervisory Control,"_IEEE Trans. Systems Man and Cybernetics, May 1980, pp. 217-231.
Tulga, M.K. and Sheridan, T.B., " Dynamic Decisions and Work Load in Multi-Task Supervisory Control,"_IEEE Trans. Systems Man and Cybernetics, May 1980, pp. 217-231.
Sheridan,    T.B.,  " Mental Workload, What is it, Why Bother With It?", Human Factors Society Bulletin, 1980.
Sheridan,    T.B.,  " Mental Workload, What is it, Why Bother With It?", Human Factors Society Bulletin, 1980.
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HERBERT ESTRADA, JR.
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l HERBERT ESTRADA, JR.
Business Address:  MPR Associates, Inc.                              !
Business Address:  MPR Associates, Inc.                              !
1140 Connecticut Avenue, N. W.                  l Washington, D. C. 20036 Education:        B.S. in Electrical Engineering University of Pennsylvania, 1951 (With Distinction).
1140 Connecticut Avenue, N. W.                  l Washington, D. C. 20036 Education:        B.S. in Electrical Engineering University of Pennsylvania, 1951 (With Distinction).
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: 3. Development of check and alignment procedures, and definitive troubleshooting data, for on-line verification of the operation of automatic combustion and feedwater control systems. These procedures have been designed for use by semi-skilled personnel and have been successfully applied.
: 3. Development of check and alignment procedures, and definitive troubleshooting data, for on-line verification of the operation of automatic combustion and feedwater control systems. These procedures have been designed for use by semi-skilled personnel and have been successfully applied.
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: 4. Analysis of steam power plant operations under cyclic load conditions, for the purpose of developing revised operating procedures and systems to accommodate cycling service.            '
: 4. Analysis of steam power plant operations under cyclic load conditions, for the purpose of developing revised operating procedures and systems to accommodate cycling service.            '
i Chief of the Nuclear Systems Engineering Section, Allison Division of the General Motors Corporation, 1963 to 1964.
i Chief of the Nuclear Systems Engineering Section, Allison Division of the General Motors Corporation, 1963 to 1964.
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Bettis Atomic Power Laboratory of Westinghouse Electric Corporation,1951 to 1963. Responsibilities included :
Bettis Atomic Power Laboratory of Westinghouse Electric Corporation,1951 to 1963. Responsibilities included :
Supervisor of Advanced Surface Ship Control Engineering; Chief Test Engineer for acceptance testing of Bettis-designed reactors for nuclear submarines at Portsmouth Naval Shipyard; Lead Engineer for nuclear plant analysis of Skate Class Nuclear Submarines; Designer of power range instrumentation and reactor protection
Supervisor of Advanced Surface Ship Control Engineering; Chief Test Engineer for acceptance testing of Bettis-designed reactors for nuclear submarines at Portsmouth Naval Shipyard; Lead Engineer for nuclear plant analysis of Skate Class Nuclear Submarines; Designer of power range instrumentation and reactor protection
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                                 -systems and hardware for USS Nautilus.
                                 -systems and hardware for USS Nautilus.
Honors:              Bettis Distinguished Service Award - April 1962, for outstanding contributions in engineering for submarine nuclear power plants and for technical guidance and effective coordination in the shipyard
Honors:              Bettis Distinguished Service Award - April 1962, for outstanding contributions in engineering for submarine nuclear power plants and for technical guidance and effective coordination in the shipyard installation of propulsion systems in three classes of nuclear submarines.
                            -
installation of propulsion systems in three classes of nuclear submarines.
Most Meritorious Patent Disclosure Award (with two others), Bettis Atomic Power        i Laboratory - 1963.
Most Meritorious Patent Disclosure Award (with two others), Bettis Atomic Power        i Laboratory - 1963.
                                                                                !
l Publications:
l Publications:
Author of numerous technical papers and reports, published and proprietary, on the following subjects:
Author of numerous technical papers and reports, published and proprietary, on the following subjects:
Measurement of the dynamic responses and characteristics of nuclear power plants.                                      t
Measurement of the dynamic responses and characteristics of nuclear power plants.                                      t 1
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Transient behavior and control design for nuclear and  ;
Transient behavior and control design for nuclear and  ;
fossil-fired steam generators.
fossil-fired steam generators.
                                                                    !
1 Generalized computer codes for calculating nuclear and  I fossil steam plant responses to normal and upset condi-tions.
1 Generalized computer codes for calculating nuclear and  I fossil steam plant responses to normal and upset condi-tions.
Theory of operation and accuracy of flow measurement    !
Theory of operation and accuracy of flow measurement    !
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alignment and troubleshooting of control systems.
alignment and troubleshooting of control systems.
Holder of several patents, in addition to numerous patent disclosures, relating to power plant systems and controls.    ;
Holder of several patents, in addition to numerous patent disclosures, relating to power plant systems and controls.    ;
:
                                                                    .
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Revision as of 14:35, 31 January 2020

Testimony in Response to Sholly Contention 15 & Antinuclear Group Representing York Contention V(C) Re Control Room design-human Factors Engineering.Improvements Can Be Made. Prof Qualifications Encl.Related Correspondence
ML19337A430
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 09/15/1980
From: Jason Christensen, Estrada H, Meek W, Sheridan T, Walsh P
METROPOLITAN EDISON CO.
To:
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ML19332B231 List:
References
ISSUANCES-SP, NUDOCS 8009260417
Download: ML19337A430 (49)


Text

__ __ ____ _. -. . __ _ _

t cI /tb DTED COnagEENCR Di g

w SEp 0%*"*c

_ LIC 9/15/80 Q

hk / b A7 g UNITED STATES OF AMERICA p NUCLEAR REGULATORY COMMISSION N -

BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

METROPOLITAN EDISON COMPANY ) Docket No. 50-289 1

) (Restart)

(Three Mile Island Nuclear ) i Station, Unit No. 1) ) l l

l LICENSEE'S TESTIMONY OF PATRICK S. WALSH, WILLIAM E. .iEEK, HERBERT ESTRADA, JR.,

JULIEN M. CHRISTENSEN AND THOMAS B. SHERIDAN IN RESPONSE TO SHOLLY CONTENTION NO. 15 AND ANGRY CONTENTION NO. V(C)

(CONTROL ROOM DESIGN-HUMAN FACTORS ENGINEERING) l l

/

S0093 1

4

OUTLINE The purposes and objectives of this testimony are to respond to Sholly Contention 15 and ANGRY Contt ntion V(C),

which contend that the TMI-l Control Room should be evaluated and modified in a manner which assures that the operator-process interface is such that the operators cart exercise adequate control over the reactor. This testimony describes the original TMI-l control room design process, the successful experience of operators controlling TMI-l over five years through n"merous transients and trips, and the human factors review that has been performed on TMI-1. Although the human factors review has identified improvements that can be made to the operator-process interface, the review also showed that the present control room design has substantial strengtas. Thus TMI-l can be opr. rated safely with the current control room design and conf.'iguration, i

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INDEX INTRODUCTION ................................................ 1 RESPONSE TO SHOLLY CONTENTION NO. 15 ...... ................. 2 RESPONSE TO ANGRY CONTENTION NO. V(C) ...................... 17 1

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INTRODUCTION This testimon- by Mr. Patrick S. Walsh, GPU Plant Analysis Manager, Mr. William E. Meek, Manager of Engineering, Gilbert Associates, Inc., Mr. Herbert Estrada, Jr., of MPR Associates, Dr. Julien M. Christensen of SSSV, Inc., and Dr.

Thomas B. Sheridan, Professor of Engineering and Applied Psychology at the Massachusetts Institute of Technology, is aadc== sed to the following contentions:

SHOLLY CONTENTION NO. 15 It is contended that the design of the Unit 1 Control

.toom, instrumentation, and controls is such that operators cannot maintain system variables and systems within prescribed operating ranges during feedwater transients and LOCA 's. It is further contended that this violates the provisions of GDC 13 regarding instrumentation and controls. It is contended that in view of the numerous operating difficulties encountered with Unit 2, and the similarities in design and construction between' Units 1 and 2, a thorough human factors engineering review of Unit l's Control Rcom is called for in order to provide i assurance that the operator-instrumentation interface is such that the operators can exercise adequate control over -

the reactor and prevent off-site consequences from anticipated operational occurrences and postulated accidents. It is further contended that in order to assure maximum protection for the public health and safety, the human factors engineering review and any necessary changes recommended as a result of this review must be completed prior to restart.

ANGRY CONTENTION NO. V(C)

The NRC Order fails to require as conditions for restart the following modifications in the design of the TMI-1 reactor without which there can be no reasonable assurance that TMI-l can be operated without endangering the public health and safety:

wiwm rme--- - -- *m -

(C) Performance of an analysis of and implementation of modifications in the design and layout of the TMI-l control room as recommended in NUREG 0560.

RESPONSE TO SHOLLY CONTENTION NO. 15 l

BY WITNESS WALSH:

Mr. Sholly has described the bases of his Contention No.

15 (See Appendix to Board First Special Prehearing Conference Order, recember 18, 1979.) This statement of basis includes three examples of TMI-2 control room design inadequacies which purportedly impacted the operators' ability to control the

, sequence of events during the accident. One example, the lack I

of positiv.e indication of valve closure, is r.ddressed in Licensee's testimony on Valves and Valve Testing in response to UCS Contentions 5 and 6. A second example, positive indication of inadequate core cooling, is addressed in Licensee's testi-i mony on Detection of Inadequate Core Cooling in response to UCS Contention No. 7, ANGRY Contention V(B) and Sholly Contention No. 6(b).

The third example citea in the statement of basis asserts that the inability of the operator to view an increasing trend on the fuel handling building exhaust monitors at 18 minutes inte the accident affected tha operators' ability te control the sequence of events.

This assertion is not valid. The monitor detected an increase of approximately 20%, stabilized at this reading, and then decreased slowly for several hours.

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The important 'information the operator needed to know, however, was that a primary system relief valve was open. It is unlikely that the operators would have deduced thac che increased reading was caused by a leak in the waste gas system, which is connected to a header that vents the Reactor Coolant Drain Tank (RCDT), which was receiving a larger than normal volume of water from a stuck open relief valve. In fact, operator interviews indicate that the operators believed the conditions in the RCDT were due to the initial lifting of the relief valve at the onset of the transient. In any case, the high alarm setpoint for the monitors was not reached until after 0700, and the system design relies principally upon monitor alarms to alert the operator to sudden increases, and upon periodic logging of' readings to detect slower trends. It should algo be noted that in the TMI-l control Room these recorders are located in a more visible location (higher on the back panel) than they are in the TMI-2 Control Room.

l BY WITNESSES WALSH, ESTRADA, CHRISTENSEN AND SHERIDAN: '

l 1

Mr. Sholly's statement of basis for his Contention No. 15 :

I also cites a study performed by the Electric Power Research Institute (EPRI Report #NP309) of human factors engineering in nuclear power plant control rooms. Mr. Sholly stated that many  :

of the concerns discussed in the EPRI report are present at I TMI-l and should be addressed in a human factors engineering reyiew of its control room. In fact, the guidelines used in l

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the review described below of the TMI-l Control Room are based on the same generally accepted control design standards utilized in the cited EPRI report.

BY WITNESS WALSH:

There are four major elements in the body of Sholly Contention No. 15 itself. The remair. der of this response to the contention is organized to address each of these elements.

The contention asserts that the design of the Unit 1 Control Room instrumentation and controls is such that opera-tors cannot maintain system variables and systems within prescribed operating ranges during feedwater transients and LOCA's.

I do not agree with this assertion. TMI Unit 1 operated at power for over 30,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> during the five years 1974-1979.

It had few operational upsets during this period. A number of feedwater transients did occur during which plant control systems maintained system variables and the systems themselves within prescribed operating ranges.

The capability of the control systems and the operators to maintain control of the plant during transient conditions was tested during the startup test program in 1974. These tests 1

measure the ability of the feedwater system as well as the entire plant to respond to transient conditions. The tests include load changes at design ramp rates at 40, 76 and 100%

power, tripping of a main feedwater pump at 100% power and l

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turbine trit at 76%, as well as reactor trip tests. During all l

these tests the operators were able to control the plant and l return it to a stable steady state condition without violating safety limits and with plant instrumentation remaining in the indicating range.

Curing five years of operation TMI-l ecperienced 17 reactor trip transients. Three of these were intentionally initiated for test purposes and ten were experienced during the startup test phase over the first tb ee months of operation.

Only two reactor trips can be directly attributed to upsets in the feedwater system. One occurred on June 20, 1974, fifteen days after initial criticality, at 18% power during a transient i caused by a turbine bypass valve malfunction that was com- -

plicated by an overfeed condition. The other trip occurred on July 13, 1974, at 15% power, when a clogged suction strainer caused a condensate booster pump to trip. During both of these transients the operators returned the plant to a stable shutdown condition and system instrumentation remained within the indicating range.

BY WITNESSES WALSH, MEEK AND ESTRADA:

It should also be noted that TMI-l differs significantly from TMI-2 with respect to control room design and arrangement.

These differences are discussed further below in Section 3.

BY WITNESSES NALSH, ESTRADA, CHRISTENSEN AND SHERIDAN:

Nevertheless, Licensee has undertaken a thorough review of the Unit 1 Control Room arrangement and the controls and displays therein. This review was performed by a team made up of:

( i) Members of the GPU engineering staff; (ii) TMI Unit 1 operating personnel; and (iii) Engineers from MPR Associates, Inc., a firm with a broad background in the design and operation of power plants; (iv) Dr. J. M. Christensen; and (v) Dr. T. B. She r id an .

The review included the following elements:  !

A. Guidelines and objectives were developed whereby the specifics of the control and display designs could be eval-uated. These guidelines are based on generally accepted military and industrial standards for control design. MIL-STD-1472B, which was used in the NRC study of the TMI-2 Control Room, was also used as a source for the guidelines that were developed for this Unit 1 Control Room review.

1 B. A full-scale control room mock-up was constructed to allow evaluations as described in C and D below. Panel fronts were reproduced by utilizing a combination of photographic and photocopy enlargements of a gridwork of high quality photo-graphs.

C. Key operational and emergency procedures were walked-through to develop a clear understanding of how, when, by whom and in what way displays, controls and means of communications in the Control Room are used and what changes, if any, would be i desirable. Cualified TMI operating personnel performed the simulated operations, with the evaluations being performed by i the review team mentioned previously. l l Operating procedures that were walked-through include i

plant heatup and startup (including operation at power), i shutdown and cooldown, and refueling. I Emergency procedures that were walked-through include reactor trips from a variety of causes, turbine trips with and without reactor trips, a variety of losses of feedwater flow and other upsets in the feed system, a spectrum of losses of reactor coolant with a variety of postulated causes, and a spectrum of steam system leaks.

D. Displays and controls on the principal panels and consoles were individually reviewed, separately from the walk-throughs. The object of this review was to ensure that items such as scale divisions, selections of units and legend readability, all of which might not be picked up in the walk-throughs , were ev alua ted .

E. A review of alarm systems was performed to evaluate the usefulness of the information presented to the operator in both normal and off-normal situations, and to develop, as -

warranted, improvements in the way that alarm information is presented.

F. The environmental conditions in the control room were surveyed to evaluate whether they adequately support the operators and equipment therein. The conditions include, among others: temperature, humidity, normal and emergency lighting, noise, kitchen and bathroom facilities, and arrangement of equipment and facilities.

The review has concluded that while improvements can be made, the present Control Room arrangement and the controls and displays therein have a number of significant strengths:

o The majority of controls and displays are arranged in logical groups (except where regulatory requirements, most notably separation, require otherwise).

o The console and panel are generally uncluttered as compared to other control rooms familiar to the review team.

o The division of operational responsibilities between operators in the Control Room and auxiliary operators in machinery spaces is workable, more specifically:

(1) Auxiliary operators are present in sufficient numbers and stations to provide effective operational support for both normal and off-normal evolutions.

(2) Control room operators are present in sufficient numbers to man consoles effectively in both normal and off-normal evolutions.

o The control and display hardware, particularly I

pushbuttons, switches, meters and controllers, have proven to have satisfactory reliability.

o The displays associated with use of a particular control are usually both visible and recognizable from the station where the operator uses that Control.

o The alarm annunciators (for the display of irdica-tions of off-normal conditions) for specific systems are generally located above the console section where the controls and analog displays associated with that system are located.

o The main alarm panels are essentially " dark" ( usually less than five are lit) when the plant is operating normally at power, and thereby enhance the ability of the operator to recognize an off-normal condition.

As should be expected of a detailed engineering study, the review of the Unit 1 Control Room has uncovered a number of areas where the Control Room design can be enhanced. While it is our opinion that TMI-1 can be safely operated with the Control Room as it presently exists, we are proceeding to make improvements to the TMI-1 Control Room design where we can clearly demonstrate that human factor aspects will indeed be enhanced.

Based on ' recommendations of the study the following modifications are being evaluated:

(A). Outlines of controls and indicators to indicate functional relationships are being evaluated. Replacement and reg roupin: of labels to provide better visibility are being evaluated. Larger lettering and consistent color combinations are being evaluated. Selected indicators are being evaluated for replacement of scale faces to provide easier readability and consistent scale markings and divisions.

(B). The arrangement of emergency feedwater controls and indicators is being evaluated to accommodate system additions, and to include a flow mimic.

(C). An altered arrangement of Engineered Safegua';ds

~

Features System pane 1 is being evaluated with regard to improved readability for the operator, particularly for rapid verification of system status after actuation.

(D). The annunciator panels are being evaluated for several combinations of annunciator window arrangement and alarm suppression and prioritization strategies.

In the process of designing each of these modifications, as well as all other modifications being made to the control room, full size facsimiles of the proposed arrangements are being placed on the control panel mockup and evaluated by the review team described above, using operating and emergency procedures.

I l-

Certain of the improvements in the control 2 and displays will enhance the ability of the control room operators to react to the transients of concern in the contention, specifically feedwater transients and loss-of-coolant accidents (reactor system leaks). In addition, modifications to the controls and displays made as a result of lessons learned from the TMI-2 accident will also improve the operator's ability to assimilate int'ormation and act on it in such transients. The improvements planned which will most directly enhance the operator's response in loss-of-feed and LOCA situations include:

o The emergency feedwater system will have mimic arrangement of the controls and displays of EFW clearly ~ indicating the flow path from water sources through the pumps and major valves to the steam generators.

o Instrumentation measuring the flow of emergency feedwater to each steam generator has been added with the displays integrated into the above described mimic .

o Primary relief valres will have accelerometers attached to each valve as well as downstream flow measuring devices with indicators located on the main control boards.

o The reactor building sump will have wide range level instrumentation installed with indicators in the Control Room.

o An unambiguous indicator of the margin to saturation

, for both reactor hot legs will be installed in the I

Control Room.

o The Engineered Safeguards Features Actuation System status panel in the Control Room will be modified to have more readable labels and brighter lights on the status indicators, improving the operators' ability to note abnormal status after system actuation.

BY WITNESSES WALSH, MEEK AND ES"iK]A :

2. The contention states that the design of the TMI-l Control Room violates the provisions of General Design Criterion 13 of Appendix A to 10 CFR Part 50, which . states:

Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for 3

anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems. Appropriate -

controls shall be provided to maintain these variables and systems within prescribed operating ranges.

Clearly, the instrumentation and control of any power plant should meet the intent of this criterion (although, at the time TMI-1 was designed the criterion did not exist in its present form) .

The instrumentation and control of TMI-l meet the criterion. This statement is based on the fact that the design process included a careful review of the instrumentation and controls by both the designers and operators to insure that adequate instrumentation was available for normal and emergency operation.

As with other technologies, improvements can and should be made to instrumentation and control systems as the technology develops.

As a result of Licensee's review of the Control Room design and lessons learned from the TMI-2 accident, a number of ,

potential improvements to the design have been identified in addition to the improvements cited above in Section 1. These include:

o Relocation of controls operated during the first few minutes after a reactor trip and revision of proce-dures, which assure that operators will be able to remain at their normal station facing the control console in the short term following reactor and turbine trips. This enables the operator to concen-trate on the response of key process variables and maintain them within prescribed limits.

o Improved labels of meters, pushbuttons, switches, and controllers with larger letters, less use of abbre-viations, and a consistent color convention to improve readability.

o Addition of outlines and labels to emphasize the functional groupings of controls and displays. For ex ample , the feedwater system controls will have 9

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outlines which include feed pump suction and dis-i charge valves, steam inlet valves, pump speed control, discharge flow and AC and DC lube oil pumps.

These outlines are labeled to clearly differentiate between the A and B pumps and other controls on the console.

o Provision of an automatic reset feature for High Pressure Injection actuation logic circuit on increasing pressure. This will free the Control Room operator from the manual function and allow closer monitoring of the process during transients in which pressure recovers.

3. The contention recommends that, in view of the numerous operating difficulties encountered with TMI-2, and the similarities in design and construction between TMI-l and TMI-2, a thorough human factors engineering review of the TMI-1 Control Room be made, in order to provide assurance that the operator-instrumentation interface is such that the operators can exercise adequate control over the reactor and prevent off-site consequences from anticipated operational occurrences and postulated accidents.

Licensee concurs with the desirability of performing a thorough review of the THI-1 Control Room design and is doing so, as has been previously stated. It is important to bear in mind , however , that the operator-process interface was consid-ered in the design of the TMI-l Control Room. Specifically, i

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during the design phase of TMI-1, physical mockups of the control boards were constracted and paper facsimiles of controls e,nd displays were used to determine the location of these devices on the panels. Simulated operations were per formed . Final decis' ions on component locations were made in conference among design engineers and Metropolitan Edison operating personnel. This procedure resulted in physical arrangements which, in general, are logical and promote ease of operation.

There are also significant differences between the TMI-1 and TMI-2 Control Rooms in the arrangement of the cone.rols and in the physical dimensions. The following table compares some of these features.

TMI-l TMI-2 Overall Control Room Size 58' X 40' 75' X 56' Operating Area Size 39' X 25' 42' X 36' Linear Feet of Control Boards 107' 168' Total Number of Annunciators 660 1020 BY WITNESSES WALSH, ESTRADA, CHRISTENSEN AND SHERIDAN:

The TMI-l Control Room review noted that this compactness l

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of control room arrangement enhances operator response during I transient conditions. The arrangement of panels in the two control rooms also differs. Panels containing Reactor Coolant l

Drain Tank parameters and alarms, Reactor Building temperature recorders and Reactor Building high temperature and high

pressure alarms are not visible in the Unit 2 Control Room from the operating area. On Unit 1 these panels are located in the operating area and the indicators and alarms are visible to the operators. '

4. The contention asserts that TMI-l startup should be delayed until the modifications identified by the human factors review of the Control Room design have been implemented.

As we have stated, we will perform those modifications which can be clearly shown to bring about an enhancement in overall human factors aspects of the plant and which can be implemented with proven hardware. This is not to say that all changes which will ultimately be made to the TMI-l Control Room will be performed prior to startup. We intend to proceed in a careful and methodical manner and will not modify the system until:

a. It is clear an improvement will result,
b. Proven hardware is available, and
c. Operators have been trained to use the improvements.

We do not consider such improvements to be a necessary prerequisite to startup. In the present schedule appropriate relabeling and functional demarcation of the main control boards are the first modifications that will be completed. The expected completion date is in early 1981. The other modifica-tions identified thus far will proceed through the steps identified above.

The review that was described above in Section 1 is not considered to be a "one time" process that is now essentially complete. Further changes to the Control Room will be reviewed using the methods and criteria developed in this review. By this method the human factors aspects of the control room design can be maintained.

RESPONSE TO ANGRY CONTENTION NO. V(C)

BY WITNESSES WALSH AND ESTRADA:

This contention asserts that NRC has not provided reason-able assurance of public health and safety since it has not required that analysir, of the design and layout of the Control Room, in accordance with NUREG 0600 be performed and that nodifications resulting therefrom be implemented. Apparently, the basic thrust of this contention is the desire for a human factors review of the control Room. Our position regarding a human factors review and the Lmplementation of panel improve-ments generated by that review is described in the testimony above in response to Sholly Contention No.15.

PATRICK S. WALSE Business Address: GPU Service Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 Education: B.S., Chemical Engineering, Illinois Institute of Technology, 1969.

M.S.E., Nuclear Engineering, Catholic University of America, 1978.

U.S. Navy Nuclear Training Program, 1969 to 1970.

Excerience: Plant Analysis Manager, GPU Service Corporation, 1979 to present. Responsible for conducting evaluations of operating experience and technical performance of all GPU system nuclear generating stations.

Senior Engineer, Nuclear Analysis Section, GPU Service Corporation, 1978 to 1979.

Responsible for performing nuclear fuel thermal-hydraulic analyses and fuel performance analyses. .

Senior Engineer, Nuclear Fuel Management Unit, Baltimore Gas and Electric Company, 1976 to 1978. Responsibilities included the performance of fuel management analyses; evaluation of safety analyses required for license amendments; and, supervision of, and preparation of proce-dures for, core refueling, new and ir-radiated fuel inspection and spent fuel shipment.

Engineer, Startup Test Group, Baltimore Gas and Electric Company, 1974 to 1976.

Responsible for procedure preparation and supervision of hot functional, low power physics and power escalation testing of mechanical and instrumentation systems.

Officer, U.S. Navy, 1970 to 1974. Held positions of Nuclear Submarine Engineering Department Division Officer and Nuclear Prototype Instructor and Training Officer.

Professional Affiliations: Registered Professional Engineer , New Je rsey.

WILLIAM E. MEEK Business Address: Gilbert Associates, Inc.

525 Lancaster Avenue Reading, Pennsylvania 19603 Education: B.S.M.E., Mississippi State University, 1957. Postgraduate Study in Mechanical Engineering, Rutgers University,1963.

Experience:

Manager of Engineering, Power Division, Gilbert Associates , Inc. , 1977 to Present.

Responsible for technical and administra-tive direction of engineers and other design personnel involved in the design of power plant facilities.

Manager of Mechanical Engineering l i

Department and Chief Mechanical Engineer ,

Gilbert Associates, Inc., 1973 to 1977.

Responsible for technical and administra- .

l tive direction of design engineers and technicians performing mechanical design on fossil and nuclear projects. Other )

responsibilities included: review and approval of mechanical specifications; chairman of System Design Review Committees.

Senior Proj ect Engineer, Gilbert Associa tes, Inc. , 1971 to 1973.

Responsible for coordination and direction of mechanical, nuclear, building service, and chemical design personnel and associated drafting groups for Florida Power Corporation's Crystal River Nuclear Unit 4. Developed conceptual plant designs for 2000 and 3000 MWt high temperature gas '

cooled reactors for General Atomic Corporation, San Diego, California.

Mechanical Engineer, Gilbert Associates, Inc., 1967 to 1971. Involved in design engineering and equipment specifications for mechanical equipment, instruments and controls for Metropolitan Edison Company's Three Mile Island Nuclear Station, Unit 1;

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Florida Power Corporation's Crystal River Nuclear Station, Unit 3; and South Carolina's Electric & Gas Company's V.C.

Summer Nuclear Station, Unit 1.

Station Mechanical Engineer, Mississippi Power & Light Company, 1963 to 1967.

Responsible for design review, contruction supervision, plant startup, maintenance coordination and operator training for Baxter Wilson Unit 1, fossil plant. Plant engineer and relief shift supervisor on several other units and involved in general plant engineering including plant modifica-tions, problem diagnosis, results engi-neering and water chemistry control.

Site Activation Engineer, General Dynamics Corporation, 1961 to 1963. Involved in construction, equipment installation, checkout, design modification, startup, and crew training for hardened launch facil-ities for intercontinental ballistic missiles.

Ordnance officer, Guided Missile Maintenance Unit, U.S. Army,1958 to 1961.

Also assistant to contracting officer at Bell Telephone Labs, administering . )

development contract for anti-missile '

defense system.

Assistant Engineer, United Gas Pipeline Company, 1957 to 1958. Involved in gas pipeline construction, route selection and survey, metering, and regulator station design.

Professional Affiliations: American Society of Mechanical Engineers. >

l EPRI Steam Generator's Owner's Group Architect - Engineer Advisory Committee.

EEI Prime Movers Architect - Engineer Advisory Committee. ,

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Industry Committee - American Power Conference.

Atomic Industrial Forum - Subcommittee on Operations, 'Ihree Mile Island Lessons Learned Task Force.

Registered Professional Engineer, Mississippi, Pennsylvania and Florida.

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JULIEN M. CHRISTENSEN Business Address: SSSV, Inc.

2600 Far Hills Avenue Dayton, Ohio 45419 Education: B.S., Accounting, University of Illionois, 1940.

M.A., Experimental Psycholoqy, Chio State University, 1952.

Ph.D., Experimental Psychology, Ohio State University, 1959. 1 Experience: Director, Human Factors Division, Stevens, Scheidler, Stevens, vossler, Inc.,1978 to present. Consulting and applied research in areas of human factors, products liability / products safety and systems.

Professor, Department of Industrial Engineering and Operations Research. Wayne State University, 1977 to 1978. Research

and teaching, primarily in areas of human factors (ergonomics), safety and envi-ronmental studies and systems.

Professor and Chairman, Department of Industrial Engineering and Operations Research, College of Engineering , Wayne State University, 1974 to 1977.

Director, Human Engineering Division Aerospace Medical Research Laboratory, Wright-Patterson Air Force Base, 1956 to 1974. Planned and managed major interdis-ciplinary human factors research and development program of the Air Force.

Programs included visual perception and displays , controls and control dynamics, effects of environmental factors (including weightlessness and partial gravity), human performance modeling, maintainability, human reliability, information processing ,

decision-making, safety and physical anthropology. Personnel included a wide range of skills such as experimental psychology, mathematics , physics , statis- '

tics, engineering, physiolgy and anthropol-l Ogy.

Research Scientist through Branch Chief Aerospace Medical Research Laboratory,

Wright-Patterson Air Force Base,1946 to 1956. Research and applications in experimental psychology and human factors engineering. Research on visual perception with simple and complex stimuli, effects of high brightnesses on visual functions, visual form field expansion, methods of activity analysis, workplace layout, navigation plotter design, weightlessness, and systems. Applications work included contributions to specifications, standards and handbooks and direct application of human engineering principles of numerous aircraf t and command / control communication centers.

United States Air Force, 1943 to 1946.

Rank: Captain (Rated Navigator and Radar Observer). Staff of Air Force Navigation Instructor's School. Construction and validation of academic and in-flight measures of proficiency in navigation.

Statistical Clerk and Personnel Technician United States Air Force Training Command, 1941 to 1943. Development and validation of tests for selection and classification of pilots, bombardiers and navigators.

Development of academic and in-flight criteria for navigation.

Adj unct Professor, Wright State University, University of Dayton, Wittenburg University, and Sinclair University.

Visiting Lecturer, The University of

, Michigan's College of Engineering Summer Conferences, annually since 1960.

Visiting Lecturer, Air Force Institute of Technology (AFIT) for more than 10 years.

Lecturer and technical adviser to Instituto Technologico y de Estudios Su Monterey, Mexico (one year). periores, Lecturer, American Psychological Association / National Science Foundation Visiting Scientist Program (four years) .

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f Cadat Lecturer at numerous other uni-versities, high schools, societies, etc. A representative sampling includes: Purdue University, Indiana University, Miami University, University of Cincinnati, The University of Michigan, Southern Illinois University; Tau Beta Pi, IEEE, AIIE, ASME, Dayton Engineer's Club.

Honors and Professional Affiliations: American Men and Women of Science, Who's Who Among Authors and Journalists, Community Leaders and Noteworthy Americans, Men of Achievement, Notable Americans.

Fellow, Human Factors Society,1970.

The Franklin V. Taylor Award (American Psychological Association), 1969.

Honorary Faculty Member, Defense Weapon l Systems Management Center,1969.

Fellow, American Psychological Association.

Air Force Association Citation of Honor, 1966.

Air Force Decoration for Exceptional Civilian Service,1966.

Diplomate, American Board of Forensic Psychology. Listed in Forensic Service i Directory (1979).

National Science Foundation Fellow,1957.

Julien M. Christensen Award ( Annual award given by the Human Factors Association of Canada for the best student paper) .

Designed Air Force B-2 Navigation Plotter (Standard for over 25 years) .

Consultant: National Bureau of Standards (NBS); National Institute for Occupational Safety and Health (NIOSH); Air Forces Office of Scientific Re'dearch; Air Forces  ;

{

Human Resources Laboratory; U.S. Army Human 1

Engineering Laboratory; Standard Oil of New Jersey; United Air Lines; Ford Motor Co.; & 1

)

others.

Chairman, SAE Human Factycs Committee.

Chairman, NASA Behavior / Technology Committee Space Lab II and Orbital Flight Test Program (Evaluation of proposals for experiments in Space Lab I) .

Member , NAS-NRC Vision Committee Working Group on Evaluation of Air Force Simulation Prog r am . (1976).

Member, Board of Governors, American Society for Safety Research (1975-1979).

Member, U.S. Army Human Factors Research &

Development Review Board (1975).

Chairman, Human Factors Committee, Society of Automotive Engineers (1975-1977).

Member, Executive. Committee, SAE Automobile Body Activity.

Member, U.S.A. Technical Advisory Group for ISO /TC-159 (Ergonomics) (1975-present).

I Co-chairman of NATC Advanced Study Institute on Human Factors / Ergonomics:

Research Methods, Bellagio , Ital y ,

September (1971).

General Chairman, National Safety Council Industrial Safety Performance Measurement Symposium, Chicago, Illinois (1970 ) .

Consultant to the National Safety Council

- on industrial and traffic safety (1968-1975).

Editorial Board, The Journal of Systems Eng ineering (1969).

Editorial Board, Journal of Safety Research (1969).

Manned Orbiting Laboratory (MOL) Evaluation Group (1965).

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. 1 Consultant to the National Academy of Sciences Working Group cn Role of Man in l Space Research. Mr. R. W. Porter , Vice l

President, General Electric Company,  !

Chairman (1965). 1 Consultant to the National AJademy of Sciences Working Group on Medicine and ,

Physiology, Dr. Loren Carlson, Chairman {

(1965). j Co-inventor with Dr. C. L. X: aft of "Soloon" (acronym for solar balloon), 1965.

Chairman of the Human Performance Scientific Advisory Committee for the Manned Orbiting Laboratory (MOL) program (1964).

Chairman of NASA /DOD Committee of Crew Performance; Technical Advisor to General Charles Roadman, Chief of Bioastronautics for NASA.

Editor and contributor to the iniM.ial Crew Porformance Plan for Gemini and' Apollo for NASA.

Chairman of Air Force Systems Command Behaviorial Sciences Advisory Panel.

Member of Air Force Systems Command Medical Safety and Human Engineering Committee.

Advisor to , or member of, mock-up boards, l review boards, and source selection boards '

for numerous systems, including B-47, B-50, B-52, B-66, B-70, C-97, C-131, KC-135, Lcng Range Interceptor (LRI), and A/N CPS 6-B, developed procedures for the effective inclusion and integration of human engi- l neering data during the development cycle of Air Force Systems.

Editor and co-author of Combat Navigatory Proficiency Test for Strategic Air Command.

l (Test used to select lead crew navigators I for European theatre in World War II) .

During World War II, deeeloped with Dr. M.

J. Warrick first battery of tests for selection and classification of pilots, bombardiers and navigators.

Aerospace Medical Association.

American Association for the Advancement of Science.

American Psychological Association, Division of Military Psychology.

Society of Engineering Psychologists.

Human Factors Association (Canada) .

Human Factors Society (Past President) .

International Ergonomics Research Society.

Society of Logistics Engineers.

Systems Safety Society.

American Society of Safety Engineers.

Licensed Psychologist, Ohio.

Publications: Representative publications include:

" Summary Report: Bombardier-Navigator Selection and Classification," Division, Army Air Corps Technical Training Command, Tulsa, Oklahoma, May 1942.

"A Study of Errors in Log Book Computations in Navigation School," Analysis of Duties of Aircrew Personnel Bulletin No. 20, Psychology Section, Office of The Surgeon, Headquarters, AAF, May 1943.

" Psychological Factors Involved in the Design of Air Navigation Plotters".

Memorandum Report No. TSEAA-694-ID, Eq. Air Materiel Command, Wright-Patterson Air Force Base, Ohio, October 1946. ATI 105 688. Also appears in Psychological Research on Equipment Design, AAF Aviation

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J j Psychology Program Research Report 19,

Chapter 5, Paul M. Fitts, Editor, 1947.

" Aerial Analysis of Navigator Duties with Special Reference to Equipment Design and Workplace Layout. I. Development of Technique ," Memorandum Report No.

TSEAA-694- 15, Hg. Air Materiel Command, Wright-Patterson AFB, Chio, September 1947.

ATI 125 06.

" Psychological Research on Navigator .

Training," AAF Aviation Psychology Program Research Report 10, L. F. Carter, Editor, i

1947. (Contributor to several chapters) .

"The Effect of the Staircase on Dial Reading Accuracy," Memorandum Report No.

MCRE XD-6 94 -IP , Hg. Air Materiel Command, Wright-Patterson AFB, Ohio , October 1948.

ATI 42 468.

"The Sampling Method of Activity Analysis and Its Application to the Problem of Aircraft Crew Requirements," Scientific Methods for Use in the Investigation of Flight Crew Requirements, Flight Safety Foundation, Woods Hole, Massachusetts, ,

1948.

" Human Engineering of the AMCPS-6B System,"

AMC Memorandum Report MCREXD-694-18C, Hg.

Air Materiel Command, Wright-Patterson AFB, Ohio, March 1949.

' "The Sampling Technique for Use in Activity Analysis," Personnel Psychology, Volume 3, No. 3 Autumn, 1950.

Quantitative Instrument Reading as a l

Function of Dial Design, Exposure Time, Preparatory Fixation, and Practice. WADC Technical Report No.52-116, Wright Air Development Center, Wright-Patterson AFB, Chio, September 1952. AD 101.

Reports of Research in the Field of Engineering Psychology. WADC Technical Report 53-75, Wright Air Development Center, Wright-Patterson AFB, Ohio, April 1953. AD 6991.

"The Effect of Selected Visual Training Procedures on the Visual Form Field." WADC Technical Report 54-239, Wright Air Development Center, Wright-Patterson AFB, Ohio, April 1955. AD 76 423.

"The Importance of Certain Dial Design Variables in Quantitative Instrument Reading." WADC Technical Report 55-376, Wright Air Development Center, Wright-Patterson AFB, Chio, October 1955.

AD 97 492.

" Engineering for the Human." Proceedings of the First International Symposium on Military Psychology, National Academy of Sciences National Research Council, 894, Washing ton, D.C. , 1961.

" Trends in Human Factors." Human Factors ,

1, No. 1, September 1958.

"The Importance of Selected Design Variables in Cuantitative Instrument Re ad.ing . " Dissertation for the Degree of Doctor of Philosophy. The Ohio State University, Columbus, Ohio; 1959.

" Training in Engineering Psychology." The American Psychologist, 16, No. 4, April 1961. (One of eight contributors) .

"The Role of Man in Automated Systems."

Working Group XIII (Brig. General Don Flickinger , Chairman) of NATO Long-Range Scientific Planning Committee (Theodor von Karman , Chairman) , CincSouth, Naples, Italy, 1961. (One of several contribu-tors).

"The Evolution of the Systems Approach in Human Factors Engineering." Human Factors, 4, No. 1, February 1962.

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"Of Men and Machines." (Thirty minute l film. Part of the Focus on Behavior series sponsored by the National Educational Television and Radio Center), August 1963.

(one of several contributors).

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"The Use of Space to Study Man." Psi Chi Quarterly, University of Dayton, Autumn, 1963.

"The Emerging Role of Engineering Psycholog y. " (Presidential Address for Society of Engineering Psychologists, 1963). AMRL Technical Report 64-88, Aerospace Medical Research Laboratories, Wright-Patterson AFB, Ohio, September 1964.

Also appears as Chapter 2 in Howell, W.C.

and Goldstein, I . L. " Engineering Psychology: Current Perspectives in Research," New York:

Appleton-Century-Crofts, 1971.

"The Measurement of General Performacce in Military Space Systems." Transactio:ss of the Ninth Annual Symposium on Ballistic t Missiles and Space Technology, Space Systems Division and Ballistics Systems Division, Los Angeles, August, 1964. )

" Human Engineering: Past, Present, Future." Bio-environmental Symposium, Aerospace Medical Division, Brooks Air 1 Force Base, Texas, October 1964.

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" Performance Capabilities of Man on . Earth and In Space: A Study in Continuity." 1 American Astronautical Society, Advances in the Astronautical Sciences, 20, 1965.

( Also catalogued as AMRL-TR-66-211. )

"Individ uals and Us." (Presidential Address for the Human Factors Society.)

Human Factors , 8, No. 1, February 1966.

( Also catalogued as AMRL-TR-65-221. )

(With Miller, J.W., Fa r r , M. J., Beach, L.R., and Katchmar , L.T. ) " Contributions of Engineerlag Psychology to Military Systems." Chapter 12 in Uhlander, J.E.

(Ed.) Psychological Research in National Defense Today, TR-S-1, U.S. Army Behavioral l

Sciences Research Laboratory, Arlington, l Virginia, 1967.

j (With Mills, R.C.) "What does the Cperator do in Complex Systems?" Human Factors, 9,

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(4), 1967. (Also catalogued as AMRL-TR-67-100.) In Chiles, W.D. (Ed.),

Assessment of Complex Operator Performance, AMRL TR-67-239 Aerospace Medical Research Laboratories, Wright-Patterson Air Force Base, Ohio August 1967.

" An Overview of Human Factors Engineering."

National Safety Congress Transactions, Industrial Safety, 12, pp. 37-48, 1967.

" Overview of Human Factors Engineering."

Proceedings of the 39th Annual Eastern Regional Safety Convention and Exposition, New York, New York, April 1969.

" Human. Factors Considerations in Design for Safety." Proceedings of Safety Conference, University of Maryland, American Society of Safety Engineers August 1969.

" Human Factors Engineering Considerations in Systems Development." Proceedings of the Fifth DRG Seminar on Design of Equipment for Effective Utilization.

Mondello (Palermo, Italy) 21-23 September 1969. Also appears as a chapter in Singleton, W.T., Fox J.G. and Whitfield , D.

" Measurement of Man at Work: An Appraisal of Physiological and Psychological Criteria in Man-Machine Systems," London: Taylor and Francis, Ltd., 1969. (Catalogued also as AMRL Technical Report 69-82. AD 727 l 365).

" Overview of Aerospace Medical Research Laboratory Human Engineering Program."

Proceedings of the " Psychology in the Air Force" Sympo sium , USAF Academy, Colorado, March-April 1970. (Also catalogued as AMRL TR-70-64.)

"An Evaluation of Some Common Methods of Activity Analysis." Proceedings of the NATO Advanced Study Institute cn Human Factors / Ergonomics: Research Methods ,

Bellagio, Italy, September 1971.

"What Are They Doing?" ( An Evaluation of Some Common Methods of Activity Analysis),

Applied Ergonomics, 1972.

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" Human Factors Engineering in the United States Air Force." Proceedings of the NATO Research Study Group on Human Engineering /Anthropotechnic Soesterberg, The Netherlands, June 1973.

" Ergonomics--Where Have We Been and Where Are We Going?" Ergonomics, 19, No . 3, May 1976.

" Ergonomics and Engineering." Proceedings of the Ninth Annual Meeting of the Human Factors Association of Canada, University of Waterloo, Ontario, Canada, 1976.

" Status, Effectiveness and Future of Human Engineering," Introductory Chapter in Kraiss, K.F. and Moraal, J., Introduction to Human Engineering, Cologne: Verlay TVV, Rhe inland , 1976.

" Human Factors in Consumer Product Design."

Proceedings of the Consumer Products Technical Interest Group, Human Factors Society, Santa Monica, California, May 1977.

" Human Factors Considerations in Designing i for Product Safety." Proceedings of the Engineering Foundation Conference on Product Liability, New York, New York, June 1977.

Human Factors Engineering--Tools and Directions for the Future, (Invited address, Sesquicentennial Celebration, University of Toronto, Canada, 1977) (to be bound and published by the University of Toronto).

(One of several authors) " Human Factors Affecting Integrated Computer-Aided Manufacturing (ICAM) Implementation."

Honeywell Report IR-1, Air Forces Materials Lab., Wright-Patterson Air Force Base, Ohio, February, 1980.

" Human Factors in Hazard / Risk Evaluation." l Proceedings of the Symposium on Human Factors and Industrial Design in Consumer i Products. Tufts University, Medford, Mass., May, 1980.

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THOMAS B. SHERIDAN Business Address: Massachusetts Institute of Technology Room 1-110 77 Massachusetts Avenue Cambridge, Massachusetts 02139 .

Education: B.S., Purdue University, 1951. M.S.,

University of California, Los Angeles, 1954. Sc.D., Systems Engineering and Psychology, Massachusetts Institute of Technology, 1959. -

Experience: Professor of Mechanical Engineering and Professor of Engineering and Applied Psychology, Massachusetts Institute of Technology, 1970 to present. Responsible for the Man-Machine Systems Laboratory; developed interdepartmental graduate degree program in Technology and Policy; teaches a graduate course in man-machine systems and the core Seminars in Technology and Policy; has taught control, design and other engineering subjects. Has conducted research on mathematical models of human operator and socio-economic systems; on man-computer interaction in piloting aircraft and in supervising undersea and industrial robotic systems; and on computer

' graphic technology for information searching and group decision-making.

Associate Professor, Massachusetts Insti- i tute of Technology, 1964 to 1970. I Assistant Professor, Massachusetts Insti-tute of Technology, 1959 to 1964.

Instructor, Massachusetts Institute of Technology, 1956 to 1959.

Research Assistant, Massachusetts Institute of Technology, 1954 to 1956.

Served as visiting r~aculty member at the i University of California at Berkeley, Stanford University and the Technical University of Delft, Netherlands.

l Honors and Professional Affiliations: 1977 Recipient of the human Factors Society's Paul M. Fritts Award for contri-butions to education. IEEE Systems Man and Cybernetics Society (past President). IEEE Committee on Technology Forecasting and Assessment (past Chairman). Formerly '

Editor, IEEE Transactions on Man-Machine

_ Systems. Fellow, Human Factors Society.

National Institutes of Health, Study Sections on Accident Prevention and Injury Control. NASA Life Sciences Advisory Com-mittee. NASA Study Group on Robotics.

U.S. 2ongress OTA Task Fr. ,e on Appropriate Technology. NSF Automation Research Council. NSF Advisory Committee on Applied Physical, Mathematical and Biological Sciences.

Publications: Sheridan, T.B., and Ferrell, W. R.,

Man-Machine Systems: Information, Control and Decision Models of Human Performance, M.I.T. Press, Cambridge, Ma., 1974.

Sheridan, T.B., "The Human Operator in Control Instrumentation," a chapter in R.H.

MacMillan, ed., Progresc in Control Engineering, Heywood and Co., Ltd., London, 1962.

Dupress, J.K., and Sheridan, T.B., " Sensory Supplementation, An Introduction," chapter in Degan, Bennett, Spiegel, eds., Human Factors in Modern Technology," McGraw-Hill, New York, 1963.

Sheridan, T.B., Merel, M.G., Kreifeldt, J.G., and Ferrell, W.R.,

"Some Predictive Characteristics of the Human Controller,"

Progress in Astronautics and Aeronautics, Vol. 13, Academic Press Inc., New York, 1964.

Sheridan, T.B., "Com section in Science , puters Reviewand and Man,"

Preview a published jointly by Childrens Press, Chicago, and Natl. College of Education, 4 Evanston, Illinois, 1964.

Sheridan, T.B., " Man-Machine Systems," 1967 McGraw Hill Yearbook of Sc).ence and Technology, McGraw Hill, N.Y., pp. 66-74.

Sheridan, T.B., " Vehicle Handling:

Mathematical Characteristics of the Driver" from Soc. Auto. Engrs, Progress in Technology, Vol. 13: Highway Vehicle Safety, 1968, pp. 268-276.

Sheridan, T.B., Articles en " Man Machine Systems" (pp. 105-109) and " Human Factors Engineering" (pp. 573-577) in 1970 McGraw Hill Science Encyclopedia.

Sheridan, T.B., " Optimum Allocation of Personal Presence," Chapter IV (Vol. II) of Progress in Cybernetics (edited by J. Rose)

Gordan and Breach, New York, pp. 803-811, also in IEEE Trans. Systems Science and Cybernetics, Vol. SSC-6, No. 2, April 1970, pp. 140-145.

Sheridan, T.B., "Teleoperators and Remote Control," " Supervisory control of Teleoperators," " Externally Powered Limb Prostheses," Chapters in R.K. Bernstat and K.P. Gartner, Displays and Controls, Swets and Zeitlinger, Amsterdam, 1972.

Sheridan, T.B., " Technology for Group Dialog and Social Choice," Chapter 12 (pp.

223-236) in de Sola Pool, Ithiel, ed.,

Talking Back: Citizen Feedback and Cable Technology, M.I.T. Press, Cambridge, Ma.

1973.

Weissenberger, S., and Sheridan, T.B.,

" Dynamics of Human Operator Control Systems Using Tactile Feedback," J. Basic Engr.,

June 1962.

Sheridan, T.B., and Ferrell, W.R., " Remote Manipulative Control with Transmission Delay," IEEE Transactions, P.T.G. Human

, Factors in Electronics, March 1963.

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i Sheridan, T.B., Paynter, H.M., and Coons, S.A., "Some Novel Display Techniques for Driving Simulation," IEEE Trans. on Human Factors in Electronics, Vol. HFE-5, n.l.,

Sept. 1964.

Zeigler, B.P., and Sheridan, T.B., " Human Use of Short Term Memory in Processing Information on a Console," IEEE Trans. on Human Factors in Electronics, Sept. 1965.

Sheridan, T.B., "Three Models of Preview Control," IEEE Trans, on Human Factors in Electronics, June 1966.

Knowles, W.B., and Sheridan T.B., "The

' Feel' of Rotary Controls: Friction and Inertia," Human Factors, June 1966, pp.

209-215.

Ferrell, W.R., and Sheridan, T.B., " Super-visory Control of Remote Manipulation,"

IEEE Spectrum, Vol. 4, No. 10, Oct. 1967, pp. 81-88.

Sheridan, T.B., and Roland, R.D., "A Normative-Model for Control of Vehicle Trajectory in an Emergency Maneuver,"

Highway Research Record, No. 195, 1967, pp.

83-97. i Vickers, W.H. and Sheridan, T.B., "A Dynamic Model of an Agonist-Antagonist Muscle Pair," paper 38 in Proc. 4th Annual NASA-Univ. Conf. on Manual Control, March 1968 (NASA SP in press), also published in IEEE Trans. on Man-Machine Systems, March 1968.

Sheridan, T.B., "What's a Man Machine?",

editorial in IEEE Trans. on Man-Machine Systems, Vol . MMS-9, No. 1, March 1968.

Sheridan, T.B., " Big Brother as Driver:

l New Demands and Problems for the Man at the Wheel," Human Factors, 1970, 17(1), pp. i 95-101. t

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Sheridan, T.B., "On How Often the l Supervisor Should Sample," Proc. IEEE Intl.

Symposium on Man-Machine Systems, Cambridge, England, Sept. 1969, also in IEEE Trans. Systems, Science and cybernetics, SSC-6 No. 2, April, 1970, pp.

l 140-145. i Murphy, R.L.H. Jr., Fitzpatrick, T.B.,

Haynes, H.A., Bird, K.T. and Sheridan, T.B., " Accuracy of Dermatological Diagnosis i

by Television," Archives of Dermatology, June 1972, Vol. 105, pp. 833-835.

Hardin, P.A., Whitney, D.E., and Sheridan, T.B., "And Tree" Computer Data Structures for Supervisory Control of Manipulation, Proc. 1972 Intl. Conf. on Cybernetics and Society, IEEE/SMC (172-CHO-547-8-SMC), Oct.

1972, Washington, D.C.

Sheridan, T.B., " Experimental Analysis of Time-Variation of the Human Operator's Transfer Function," Proc. of the First International Congress of the International Federation of Automatic Control (Moscow),

Butterworths, London, 1960.

Sheridan, T.B., " Human Operator's Time-varying Transfer Function in the Study of Perception and Fatigue," Proceedings of the Symposium on Recent Mechanical Engineers, Institute of Mach. Engrs.,

London, 1960.

l Sheridan, T.B., "In Flight Measurement of l

Human Operator Alertness," Proceedings of j the National Specialists Meeting in '

Guidance of Aero-Space Vehicles, Institute of Aeronautical Sciences, New York, 1960.

reprinted as Sheridan, T.B., " Alertness Measurement of the Human Operator of a Continuous Control l System, Automatic Centrol, March 1961.

Sheridan, T.B., "The Human Response Equation," M.I.T. Technology Review, May, 1962.

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l Sheridan, T.B., " Engineering Analysis of Canc Information Acquisition," in Linsner, J.W., ed. , Proceedings of the Mobility Research Conference, (M.I.T., 1961), Amer.

Foundation for the Blind, New York, May 1962.

Mickunas, J., and Sheridan, T.B., "Use of an Obstacle Course in Evaluating Mobility of the Blind," Amer. Found. Blind, Res.

Bul., No. 3, New York, August 1963.

DeFazio, T.L., and Sheridan T.B.,

" Vibration Analysis of the Cane," Amer.

Found. Blind Res. Bul., No. 3, New York August 1963.

Sheridan, T.B., " Techniques of Information Generation: the Cane," Proceedings of the International Congress on Technology and Blindness, Amer. Found. Blind, New York, 1963.

Sheridan, T.B., "On Precognition and Plan-ning Ahead in Manual Control," Proc. 4th Natl. Symp. on Human Factors in Electronics, IEEE, May 1963.

Sheridan , T.B. , Johnson, W.M., Bell, A.C.,

and Kreifeldt, J.G., " Control Models of Creatures Which Look Ahead," Proc. 5th Natl. Symp. on Human Factors in 1

Electronics, IEEE, May 1964.

Sheridan, T.B., Fabis, B.F., and Roland, R.D., " Preview Control Behavior and Optimal Control Norms," Proc. Second Annual NASA-University Conference on Manual )

Control, NASA SP-128, pp. 293-310.

Sheridan, T.B., " Preview Control and Super-visory Dynamics in Man-Machine Systems,"

Tri-National Symposium on Man-Machine Interactions NATO /MWDDEA, Paris, France, Sept. 1966.

Ferrell, W.R., and Sheridan, T.B.,

" Supervisory Control of Remote Manipulation," IEEE NEREM Record, 1966, pp.

16, 17.

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Sheridan , T.B. , " Human Decision Making in High Speed Transportation," IEEE Intl.

Convention Digest, March 1967, pp. 482-483.

Sheridan, T.B., and Ferrell, W.R., " Super-visory Control of Manipulation," Proc. 3rd Annual NASA-University Conference on Manual Control, NASA SP-144, 1967, pp. 315-323.

Sheridan, T.B., Ferrell, W.R., Krafchick, Jr., and Strickler, T.G., " Tactile Sensing for Remote Palpation and Manipulation in Telediagnosis," Proc._20th Annual Conf. on Engr.. in Medicine and Biology, Nov. 1967, pp. 23.

i Nevins, J.L., Johnson, I.S., and Sheridan, T.B., " Man / Machine Allocation in the Apollo Guidance, Navigation and Control System,"

Proc. Inst. of Navigation National Space <

Meeting on Simplified Manned Guidance, Feb.

1968, pp.71-118.

Whitney, D.E., and Sheridan, T.B., " State Space Models of Remote Manipulation Tasks,"

Proc. 4th Annual NASA-Univ. Conf. on Manual Control, March 1968 (NAS7 SP in press).

Sheridan, T.B., Ferrell, W.R.,

D.E., " Human Control of Remote and Whitney, Computer Manipulators," IEEE NEREM Record , Vol. 10, 1968, pp. 198-199.

Sheridan, T.B., Ferrell, W.R.,

D.E., and Whitney,

" Human Control of Remote Computer Manipulators," paper presented at Fall Joint Computer Conference, San Francisco, 1968.

Sheridan, T.B., and Ferrell, W.R.,

" Human Control of Remote Computer Manipulators,"

Proc. Intl. Joint Conference of Artificial Intelligence, Washington, May 1969, pp.

483-494.

Sheridan, T.B., " Supervisory control of Computer Manipulators" in Advances in External Control of Human Extremities, Yugoslav Comm. for Elec. and Automation, Belgrade, 1970, pp. 353-364.

Sheridan, T.B., " Citizen Feedback: New Technology for Social Choice," in MIT Technology Review, Jan. 1971, pp. 47!51.

Rouse, W.B., and Sheridan, T.B., "Supervis-ory Sampling and Control: Sources of Suboptimality in a Tracking Task" in Proc.

1971 NASA- University Conference on Manual Control, U. Southern California, Los i Angeles, June 1971.

Sheridan, T.B., " Technology for Group l Dialogue and Social Choice," Fall Joint  :

Computer Conference, Las Vegas, Nevada, November 1971, AFIPS Conference  !

Proceedings, Vol. 39, pp. 327-336.

Sheridan, T.B., "Cn Modeling Performance of Open-Loop Mechanisms," Proceedings of 1st I CISM-IFTCM Symp. on Theory and Practice of l Robots and Manipulators, Udine, Italy, Sept. 1973.-

Sheridan, T.B.,

"The Several Roles of Man as a Supervisor of Robots" in Proc. 1974 International Conf. on Systems, Man and Cybernetics, IEEE 74-CHO-908-4-SMC, pp.

453-457.

Sheridan, T.B., " Community Dialog Technology", Proceedings of the IEEE:

Special Issue on Social Systems, Vol. 63, No. 3, March 1975, pp. 463-474.

Sheridan, T.B., " Technology for Citizen Participation in Planning," NRC Transportation Research Record, 1975.

Rouse, W.B., and Sheridan, T.B., " Computer Aided Group Decision-Making: Theory and Practice," Proc. 1974 Intl. Conf. on Systems, Man and Cybernetics, IEEE 74-CHO-908-4-SMC. Also published in Technological Forecasting and Social Change, 7, 113-126. (1975).

Sheridan, T.B.,

"Several Roles of Man as a Supervisor of Robots", Proc. 6th Congress International Federation of Automatic Control, M.I.T., Cambridge, Mass., Aug.

1975.

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Sheridan, T.B., "On Interf acing Models ar.d I Decision Makers", IEEE Proc. International  !

Conference on Cybernetics and Society, Saa l Francisco, Sept. 1975. l Sheridan, T.B., "On the Human Supervision  ;

of. Industrial Robots", Paper A4 in Third  ;

Conference on Industrial Robot Technology i and 6th International Symposium on i

Industrial Robots, University of Nottingham, U.K., March 1976.

1 Sheridan, T.B., " Production Control Task Allocation to Man vs. Computer" Proc. 1976 Joint Automatic Control Conference, Purdue l University, July 1976.

Sheridan, T.B., and Johannsen, G., Editors, Monitoring Behavior and Supervisory Control, Flenum Press, 1976. '

Kiguchi, T., and Sheridan, T.B.,

l " Selecting Measures of Plant Information:

Some Criteria Based on Information and Decision Theory," Proc. 1976 Intl.

Symposium on Systems, Man and Cybernetics, IEEE/SMC, M Lhington, D.C.

Sherjian, T.B., and Sicherman, A.,

"Est'.mation of a Group's Multi-Attribute Util.ii function in Real Time by Anonymous Voting," IEEE Transactions Systems, Man and Cybernetics, Vol. SMC 7, No. 5, May 1977.

Sheridan, T.B., Supervisory Control of Manipulators for Undersea Applications, 1977 Intl. Conf. Cybernetics and Society, IEEE/SMC.

Tulga, M.K. and Sheridan, T.B.,

" Supervision of Dynamic Decision Making in

' Multi-Task Monitoring and Control," 13th Annual Conference on Manual Control, M.I.T., June 15-17, 1977. ,

Palgi, A., and Sheridan T.B., " Nutrition Slide Show with Audience Participation," J. '

Nutrition Education, Vol. 9, No. 3, July-Sept. 1977, pp. 123-126.

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Burke, T.E., Sheridan, T.B., et al.,

" Integrating Technology Assessment Techniques," Eighth Annual Pittsburuh Conf.

on Modeling and Simulation, April 1977.

Sheridan, T.B., and Mann, R.W., " Design of Control Devices for People with Severe -

Motor Impairment," Human Factors, Vol.

20(3), June 1978, pp. 321-338.

Sheridan, T.B., "The Changing Role of the Pilot from Manual Controller to Computer Supervisor," Proc. Symp, on Man-System Interface: Advances in Workload Study, Air Line Pilots Assn., July 31 and Aug. 1, 1978, pp. 132-143.

Sheridan, T.B., and Tulga, M.K., "A Model for Dynamic Allocation of Human Attention Among Multiple Tasks," Proc. Intl. Conf. on Cybernetics and Society, Tokyo, Japan, Nov. l 3-7, 1978, pp. 1112-1117, IEEE 78-CH-1306-0-SMC.  !

Sheridan, T.B., Verplank, W.L.,

T.L., " Human / Computer Control ofand Brooks, Undersea Teleoperators," Proc. Intl. Conf. on Cybernetics and Society, Tokyo, Japan, Nov.

3-7, 1978, IEEE 78-CH-1306-0-SMC, pp.

969-978.

Kiguchi, T., and Sheridan, T.B., " Selection Measures of Plant Information with Application to Nuclear Reactors," IEEE Trans. Systems Man and Cybernetics, to be published April 1979.

Sheridan , T.B. , " Human Error in Nuclear Power Plants," Technology Review, Feb.

1980, pp. 22-33.

Tulga, M.K. and Sheridan, T.B., " Dynamic Decisions and Work Load in Multi-Task Supervisory Control,"_IEEE Trans. Systems Man and Cybernetics, May 1980, pp. 217-231.

Sheridan, T.B., " Mental Workload, What is it, Why Bother With It?", Human Factors Society Bulletin, 1980.

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~"/ Sheridan, T.B., " Understanding Human Error

/ and Aiding Human Diagnostic Behavior in

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' Nuclear Power Plants," in Rasmussen, J. and Rouse, W.B. Human Detection and Diagnosis of System Failures, (Proc. of NATO Symposium, Aug. 4-8), Plenum Press, to be published 1980.

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HERBERT ESTRADA, JR.

Business Address: MPR Associates, Inc.  !

1140 Connecticut Avenue, N. W. l Washington, D. C. 20036 Education: B.S. in Electrical Engineering University of Pennsylvania, 1951 (With Distinction).

Graduate Courses in Physics and Mathematics, University of Pittsburgh, l 1952-1953.

Experience: MPR Associates ,1964-present. Responsible for technical coordination and direction of projects including design, analysis, 4 testing and operation of nuclear and fossil-fueled fueled power systems, hydraulic, pneumatic and electronic control systems, electrical systems, and fluid systems. Some specific projects include:

1. Design, analysis, instaliation, and

, testing of propulsion plant instrumentation and controls, to replace controls and instrumentation of questionable reliability and excessive complexity, for a class of five U.S. Navy (fossil fuel / steam powered) assault ships. This work included : analysis of manning skills and levels required for effective performance of operations manually, under both emergency and normal conditions; and, arrangement of controls, displays, valves, and the hardware for the effective performance of required tasks.

2. Design, analysis, and evaluation of instrumentation systems for power plants and experimental facilities.
3. Development of check and alignment procedures, and definitive troubleshooting data, for on-line verification of the operation of automatic combustion and feedwater control systems. These procedures have been designed for use by semi-skilled personnel and have been successfully applied.

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4. Analysis of steam power plant operations under cyclic load conditions, for the purpose of developing revised operating procedures and systems to accommodate cycling service. '

i Chief of the Nuclear Systems Engineering Section, Allison Division of the General Motors Corporation, 1963 to 1964.

Responsible for engineering and operations research activities on chemical systems for several energy conversion development projects.

Bettis Atomic Power Laboratory of Westinghouse Electric Corporation,1951 to 1963. Responsibilities included :

Supervisor of Advanced Surface Ship Control Engineering; Chief Test Engineer for acceptance testing of Bettis-designed reactors for nuclear submarines at Portsmouth Naval Shipyard; Lead Engineer for nuclear plant analysis of Skate Class Nuclear Submarines; Designer of power range instrumentation and reactor protection

-systems and hardware for USS Nautilus.

Honors: Bettis Distinguished Service Award - April 1962, for outstanding contributions in engineering for submarine nuclear power plants and for technical guidance and effective coordination in the shipyard installation of propulsion systems in three classes of nuclear submarines.

Most Meritorious Patent Disclosure Award (with two others), Bettis Atomic Power i Laboratory - 1963.

l Publications:

Author of numerous technical papers and reports, published and proprietary, on the following subjects:

Measurement of the dynamic responses and characteristics of nuclear power plants. t 1

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Transient behavior and control design for nuclear and  ;

fossil-fired steam generators.

1 Generalized computer codes for calculating nuclear and I fossil steam plant responses to normal and upset condi-tions.

Theory of operation and accuracy of flow measurement  !

systems.

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Descriptions and procedures on the theory, checkout ,

alignment and troubleshooting of control systems.

Holder of several patents, in addition to numerous patent disclosures, relating to power plant systems and controls.  ;

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