ML20012A080
| ML20012A080 | |
| Person / Time | |
|---|---|
| Site: | 05000605 |
| Issue date: | 02/28/1990 |
| From: | Scaletti D Office of Nuclear Reactor Regulation |
| To: | Marriott P GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 9003080256 | |
| Download: ML20012A080 (5) | |
Text
s.
February 28, 1990 I
Docket No. STN 50-605 Patrick W. Marriott, Manager Licensing & Consulting Services GE Nuclear Energy General Electric Company 175 Curtner Avenue San Jose, California 95125
Dear Mr. Marriott:
SUBJECT:
ABWR MEETING RELATED TO CONTROL ROOM DESIGN AND SEISMIC FRAGILITY ANALYSES This letter is to notify you of the meetings scheduled with your staff on March 6-7, 1990 to discuss the ABWR control room design relative to the Chapter-18 review, and to the human factors assumptions used in the ABWR PRA.
On the second day of the meetings, parallel discussion will be held with your staff relative to the treatment of component fragilities in the ABWR PRA analysis.
The proposed agenda is enclosed.
The NRC staff will be represented by the following individuals:
R. Eckenrode and R. Correia, Human Factors Assessment Branch, NRR; J. Wachtel, and E.
Chelliah, RES; J. O'hara, R. Youngblood, W.
Luckas, and C.
Hsu, BNL; M. Ravindra, BNL consultant; and myself.
If you have any questions regarding this meeting, please call ne at (301) 492-1104.
Sin e ely, Dino C.
Scaletti, Project Manager Standardization and Life Extension Project Directorate Division of Reactor Projects-III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As-stated TDocket7 File?
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Regan H. Vandermolen
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R. Eckenrode J. Murphy PDSL Reading R. Correia M.
Cunningham J. Wachtel C. Miller E. Chelliah PDSLO7we*
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February 28, 1990
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Docket No. STN 50-605 l
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Patrick W. Marriott, Manager Licensing & Consulting Services GE Nuclear Energy General Electric Company 175 Curtner Avenue San Jose, California 95125 i
Dear Mr. Marriott:
SUBJECT:
ABWR MEETING RELATED TO CONTROL ROOM DESIGN AND SEISMIC FRAGILITY ANALYSES f
This letter is to notify you of the meetings scheduled with your-staff on March 6-7, 1990 to discuss the ABWR control room design relative to the Chapter 18 review, and to the human factors assumptions used in the ABWR PRA.
On the second day of the meetings, parallel discussion will be held with your staff j
relative to the treatment of component fragilities in the ABWR PRA analysis.
The proposed agenda is enclosed.
The NRC staff will be represented by the following individuals:
R. Eckenrode and R. Correia, Human Factors Assessment Branch, NRR;,J. Wachtel, and E. Chelliah, RES; J. O'hara, R. Youngblood, W. Luckas, and C. Hsu, BNL; M. Ravindra, BNL consultant; and
+
myself.
If you have any questions regarding this meeting, please call me at (301) 492-1104.
Sincerely, C
Dino C.
Scaletti, Project Manager Stalidardization and Life Extension Project Directorate i
Division of Reactor Projects-III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated
- +, - -.
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NRC STAFF /GE PRA AND CONTROL ROOM DESIGN MEETING MARCH 6-7, 1990 MARCH 6:
8:30-NOON
- Purpose NRC
- Overview of K6/7 Control Room Design GE
- Overview of Human Factors Involvement in ABWR Certification GE i
IPM - SPM
- Differences between ABWR Human Factors and EPRI ALWR Requirements Document GE
- Systems Analysis Documentation GE
- Control Room and Remote Shutdown Panels Design Documentation GE MARCH 7:
8:30 - NOON
- operations Analysis Documentation GE
- Human Factors Evaluation Documentation GE
- Design, Development and Evaluation Tools GE
- Risk Analysis Documentation of Human Involvement GE 1PM - SPM
- Proposed Expansion of ABWR SSAR Chapter 18 GE
- Develop Level of Detail Closure Plan GE/NRC
- Close SEISMIC FRAGILITY ANALNSIS MARCH 7:
t 8:30AM GE/NRC
- Seismic Fragility Analysis (Critical Equipment only)
- Use of Seismic Functions for Reference Sites
- Sequence Frequency Estimates (Including Method of Quantification)
- Impact on Seismic Events on Containment and Consequence Analyses
- System Reliability Analyses *
- Accident Sequence Analyses *
- Containment Event Tree Analyses *
- Containment Response Analyses *
- Consequence Analyses and Risk Integration *
- Emphasis on Clarification only
i ADDITIONAL HUMAN FACTORS DISCUSSION TOPICS MARCH 6-7, 1990 t
- 1. HUMAN FACTORS ENGINEERING PROGRAM PLAN
- 2. RISK ANALYSIS DOCUMENTATION FOR HUMAN INVOLVEMENT
- Methodology and results of the PRA performed; and discussion of how it was applied to advanced control room operations.
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- Identification of human factors safety issues associated with tnis design, how these issues were identified and how i
they were resolved.
- Identification of operator performance requirements during abnormal and emergency events.
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- Description of how the design supports error reduction and error tolerance.
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- Description of how the advances in technology affected this PRA.
- 3. SYSTEMS ANALYSIS DOCUMENTATION
- Operator requirements analysis.
- Function analysis and allocation of function optimization rationale.
- Task analysis.
4.
CONTROL ROOM (CR) AND REMOTE SHUTDOWN PANELS (RSP) DESIGN DOCUMENTATION i
- Results of studies that resulted in hardware and software selection, particularly for those aspects of the CR and RSP employing new technology.
- CR and RSP floor plans panel layouts and drawings, and photographs.
- Operator-software interface design (display / control) with sample displays and controls.
- Identification of human factors guidelines and standards e
used in the design process, and a discussion of any determinations that such guidelines and standards were not applicable.
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- Comparison of the CR and RSP design for the ABWR with i
those of other advanced CR and RSP with which General Electric has been involved (e.g. NUCLENET, GESSAR).
- 5. OPERATIONS ANALYSIS DOCUMENTATION
- Relevant normal, abnormal and emergency operating procedures for the scenarios being evaluated.
- Description of expert systems and decision aids used.
- Staffing requirements and operations philosophy.
- Training and qualifications requirements.
- Results of comparisons of operators' tasks between current and proposed BWR designs.
- 6. HUMAN FACTORS EVALUATION DOCUMENTATION i
- Human factors evaluation criteria (e.g. NUREG-0700) for CR and RSP elements such as: environment, panel layout, egronomics, AWS, process computer, communications, labels, controls, display design.
- Human factors evaluation of new MMI technology reflecting strong reliance on human-computer interfaces.
- Human factors evaluation of new approaches to operations, such as the use of a " workstation" concept for control room design.
- Human performance studies using walk-throughs, mock-ups, laboratory studies, simulators, etc.
- Results of verification studies to demonstrate compidance to operator needs and requirements.
7.
DESIGN, DEVELOPMENT, AND EVALUATION TOOLS
- Description of simulators, static or dynamic mock-ups, and t
l any other tools in use or planned, for the performance of studies and analyses of the type described above.
.