ML20237D343
| ML20237D343 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 12/11/1987 |
| From: | Kenyon T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19302D206 | List: |
| References | |
| NUDOCS 8712230207 | |
| Download: ML20237D343 (4) | |
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UNITED STATES o,,
NUCLEAR REGULATORY COMMISSION o
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December 11, 1987 Docket No. 50-601 APPLICANT: Westinghouse Electric Corporation FACILITY:
RESAR SP/90
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS THE WESTINGHOUSE ADVANCED CONTROL ROOM DESIGN On November 19, 1987, representatives of the NRC and Westinghouse met at the Westinghouse Energy Complex in Monroeville, Pennsylvania to discuss the engineering and human factors design aspects of the Westinghouse Advanced Control Room (ACR) that will be utilized in the RESAR SP/90 facility design. is a list of attendees. Enclosure 2 is a proprietary copy of the slides used during the presentation.
In its opening remarks, the' applicant indicated that the design of the ACR has been evolving over the last 5 years and will continue to evolve. When an ACR is ordered by a utility, the final design would be locked in place for that-particular order. Westinghouse indicated that the staff would be viewing a _
" snapshot" of where the design is today.
Westinghouse began its presentation with a discussion of the basis for the information provided in Module 15 " Control Room / Human Factors Engineering."
The applicant's goal has been to reduce the propensity for operator error by presenting appropriate control information conveniently and clearly.
The applicant is developing a system that will sort vital information from incidental information, and present that vital information to the operator in order for the individual to make an informed decision as to appropriate actions to take during an abnormal or emergency occurrence. Alarm systems are being analyzed to determine the appropriate number of alarms that should be presented to an operator during such an abnormal or emergency occurrence.
During the course of the meeting, the staff observed the applicant's mockups of the alann system, their mockup of the advanced control room, and their main control board and I & C prototype.
At the exit meeting, the staff indicated they could see that Westinghouse has put a lot of thought and work into the ACR design, and that the approach the applicant is taking should overcome many of the shortcomings of current designs. The staff stated that it agreed with Westinghouse that there was no need to try to finalize the design of the ACR to support the PDA. However, the staff further indicated that it appeared that documentation of the design Q22gggj{ h p
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December 11 1987 0 and analytical processes that were used in making certain choices during the i
development of the system would be necessary to support the FDA.
In addition, I
the staff indicated that additional information describing the criteria used in the development of the ACR (a description of the task analysis, the functional decomposition standards being utilized) process, and the conventions, guidelines, and may be required to support the PDA.
The staff indicated it would re-review Module 15, and notify Westinghouse if additional information was required.
original signed by Thomas J. Kenyon, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects
Enclosure:
As stated DISTRIBUTION:
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and analytical processes that were used in making certain choices during the development of the system would be necessary to support the FDA.
In addition, the staff indicated that additional information describing the criteria used in the development of the ACR (a description of the task analysis, the I
functional decomposition process, and the conventions, guidelines, and standards being utilized) may be required to support the PDA. The staff 1
indicated it would re-review Module 15, and notify Westinghouse if additional information was required.
i Thomas J. Kenyon, Project lianager Standardization and Non-Power Reactor Project Directorate l
Division of Reactor Projects III, IV, V and Special Projects 1
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Enclosure:
As stated 1
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ENCLOSURE 1
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W/NRC Meeting to Tour Control Room / It<C Facili ti cs November 19, 1987 1
1 Attendee Sion-vo i
i Name Affiliation Functional Group / Branch j
Thomas Kenyon NRC/PDSNP SP/90 Project Manager George Lapinsky NRC/HFAD Human Factors Reviewer j.
1 Leo Beltracchi NPC/RHFB/RES Human Factors-Research 1
Mike Shannon W-NTSD Licensing Pat Trayers W-NTSD Licensino t.
Barb Gongeware E-NTSD Licensing David Woods W-R8cD Human Sciences Bill Elm W-NTSD Man-Machine Punctional Design Jim Easter M-NTSD Man-Machi ? Functional Design Glenn Elias W-R 6< D Human Sciences Jim Cox W-NTSD ITTC/ Plant IS<C Systems Other Participants Bi-i an Mc Intyre W-NTSD Product Licensing Theo van de Venne W-NTSD APWR Development Engineering John Carrera W-NTSD Man-Machine Functional Decian David Turner W-NTSD P1 ant 18<C Systems Brian Reid W-NTSD Plant IS<C Systems
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