ML19209C867
| ML19209C867 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/09/1977 |
| From: | Farmer W NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Constable G, Ming Li, Milhoan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation, NRC OFFICE OF STANDARDS DEVELOPMENT |
| Shared Package | |
| ML19209C834 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7910180398 | |
| Download: ML19209C867 (8) | |
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liAY 9 1977
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0Qh0 Those on Attached List u
Gentleman:
Subject:
Advanced Ituclear Control Room Rman Engineering Review The minutes of a meeting bet:seen ORNL and NRC to discuss a proposed future program in humn engineering are enclosed. The fortWng 02XL proposal will be brought before the Cocarittee in June or July.
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yc Original Signed by William S. Far:er William 5. Farmer, Chairman du: nan Engineering Review Group (Division of Reactor Safety Research)
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Enclosure Date and Place: April 12, 1977 Phillips Bldg., Bethe.sda, MD Purcose:
Discuss Proposed Human Engineering Assessment of Advanced Nuclear Control Rooms Attendees:
T. Ippolito, DSS L. Oakes, ORNL F. Rosa, 00R
A Human Engineering Assessment of Advanced Nuclear Control Rooms was proposed for consideration at the above meeting. The attached program outline was used as a starting point for the discussion. ORNL would perform the study.
It was agreed that:
1.
ORNL will review the attached program scope and submit in June 1977 a program outline and 189 reflecting their review and subsequent NRC comments.
2.
ORNL will further discuss the licensing issues in this topic with DSS and DOR to better identify related needs.
3.
There was general agreement that the study should start with an information gathering and state-of-the-art assessment.
Subsequent tasks in the attach-ment might be changed to reflect a greater hardware interest.
4 The study should be directed to a review of the human engineering design as it relates to safety system operation.
However, in reviewing cperator performance relative to safety systems,.the total plant operating work load has to be considered.
5.
The ORNL proposal should be submitted by June to allow for subsequent discussions with DSS, 00R and the Human Engineering Review Group. These could necessitate several iterations.
6.
The study, if approved, would start in FY 1978.
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Human Engineering Assessment of Advanced Nuclear Control Rooms Ba c kereunc Advanced control center designs employing CRT displays driven by computers are being proposed by the reactor vendors for the next generation of nuclear plants. These control centers appear to offer the operator increased access te control functions and improved diagnostic capability. They therefore should help plant operators in responding to the demands of routine and emer-gency operating situations.
Standardized advanced control room designs have been discussed by the ver. dors at recent technical meetings. Typical examples are the General Electric NUCLENET (Ref.1) and the Combustion Engineering Advanced Control Room Design (Ref. 2). The vendors state they have considered the operator controls inter-face in the design of the control room. A paper by Combustion Engineering entitled " Effective CRT Display Creation for Power Plant Applications" discusses the hurran engineering considerations which went into their advanced control room center design.
A need exists for a human engineering assessment of these advanced control room designs to provide criteria and guidance for licensee reviews in the future.
Data is available from the process industry on the design of CRTs, panel board layouts, etc. and similar geometric choices. However, a thorough study has not
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been made of the operator-controls interface in nuclear designs to determine whether the operator can respond to safety cccurrences in a timely fashion.
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2 Other issues such as how much information can the operator remember, etc.
should be assessed.
Work S:cce A study of the operator-controls interface in advanced control center design is proposed. The study would consist of four tasks.
Task 1: Review of Proposed Advanced Control Center Designs.
In this phase, visits would be made to CE, GE, y and B&W to obtain information on their proposed designs, discuss the design and observe the mockups'available.
In addition, visits would be made to a selected number of chemical process plants== ploying a high degree of automation in conjunction with CRT displays.
During the latter visits, discussions would be held with the operators in order to identify the human factor attributes and deficiencies. A selected number of visits would also be made to fossile power stations employing CRTs and automation.
The results of these visits, discussions and a literature review would be put together in a state-of-the-art report at the end of this phase.
Emphasis would be placed on identifying the significant human factors involved and noting criteria and guidelines for safe operation.
Task 2: Task and Failure Mode Analysis Using the Information Obtained From Phase 1.
A typical advanced nuclear control room would be selected for a human task and failure mode analysis. Operational 86:
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sequences at several levels of stress such as startup, turbine trip, malfunctioning makeup water. pump, LOCA, etc. would be time analyzed to trace the steps an operator would be expected to perform and identify whether he could accomplish the tasks expected.
Task 3: Human Factors Criteria. An assessment would be made of the human engineering desired in the advanced control room displays.
Examples of areas to be considered are:
a) How should safety system status be displayed? Dedicated CRTs, multiplexing, etc.
b) How should malfunctions be identified? Hard wired lights with audible backup, blinking lights on CRT graphics, color changes on CRT graphics?
c) Will the operator be expected to respond more quickly to alpha numeric tabulations on CRTs or data associated with graphics?
d) If multiplexing is used, what is the maximum respons e time?
e) Should features of the safety system be displayed on the CRTs and be backed up by analog continuous displays?
f) How much time is required to diagnose the cause of a failure using CRTs?
g) Should trend displays or tolerance displays be used?
h) Where should the safety system CRT be located?
i) Should color and/or blink be specified for coding safety system displays?
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The output from this phase of the study would be a report assess;ng the human factors considerations in advanced control room design.
Design criteria would be developed and listed.
This report should provide the technical basis for preparing guides and standards.
Task 4: Reconnendations. The final task would be a report summarizing the observations and recomendations of the study. The need for further studies if required and/or research requirements would be identified.
Schedule This program would begin at the start of FY 1978. The initial contract effort would be the detailed planning of the program and resource allocation. The Task 1 survey and Task 2 analysis would be expected to be completed by the end of the third quarter of the fiscal year. The third task on human factors would be expected to be complete in the first quarter of FY 79 and a final report should be submitted to NRC during the second quarter of FY 79.
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w References 1.
J. N. Shukla and R. H. Wong, "Nucienet Control Complex," IEEE, Control Room Desion Proceedinos,1975.
2.
J. E. Mp rs and J. W. Veirs, "An Advanced Control Center Design for Nuclear Power Plants," American Power Conference, April 1975.
3.
M. M. Danchak, " Effective CRT Display Creation for Power Plant Applica-tions," ISA, May 1975.
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