ML20204G070
| ML20204G070 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 07/29/1986 |
| From: | Long S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8608070060 | |
| Download: ML20204G070 (13) | |
Text
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8 '"e' Ao UNITED STATES NUCLEAR REGULATORY COMMISSION Y $ )n,E W ASHINGTON, D. C. 20555
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, , ** JUL e y gy Dacket No.: 50-601 APPL.ICANT: Westinghouse Electric Corporation FACII.ITY: RrSAR-SP/90
SUBJECT:
St'MMARY OF MEETING PEl.D ON JUI.Y 8,1986, TO DISCUSS THE FORMAT AND CONTENT FOR SUBMISSION OF MODUI.E 15 The meeting was requested by Westinghouse to discuss the nature of the
. information to be provided on the design and design process for the SP/90 control room and related instrumentation. The agenda for the meeting is provided as Attachment 1. A list of those attending the meeting is included as Attachment 2.
,- Discussion: .
e The control room design process, including human factors topics, are included under Chapter 18 in the standard safety analysis report format. Westinghouse staff presented a verbal summary of their organization for the materials to be provided in this section.
NRC staff noted that the materials described for Section 18.8 no longer included the remote shutdown panel (RSDP) or the Technical Support Center (TSC). Westinghouse agreed that the design of the RSDP would be treated as an extension of the control room design process, and that the control room interfaces with the TSC would also be included , but not the actual design of the TSC.
NRC staff also noted that the summary for Section 18.3.7 did not mention the relevant regulatory guide on " work space environment". Westinghouse was urged to explicitly address compliance with and deviations from applicable regulatory guides whenever possible to facilitate NRC review.
Because the initial control room design process already incorporates the elements specified in NUREG-0700, the material in Section 18.6, " Control Room Design Review," will describe how these elements are reflected by the other parts of Chapter 18. The NRC staff still believes that a control room design review process will be necessary to identify' human engineering discrepancies (FEDsl and provide for their correction or formal acceptance.
Under Section 18.4, " Control Room Design Validation", Westinghouse intends te extend the verification and validation plan which was reviewed by NRC for RESAR 414. Special emphasis will be placed on " man-in-the-loop" testing.
Westinghouse requested an additional meeting with NRC staff in late August to further discuss " man-in-the-loop" testing.
8608070060 860729 PDR ADOCK 05000601 A PDR
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The instrumentation and control aspects of the control room are included in Chapter 7 of the standard safety analysis report format. Westinghouse staff presented a verbal summary of the materials from Chapter 7 that will be included in Module 15.
The extensive use of multiplexed fiber optics for transmission of data and control signals will have a major effect on the logic of control panel design and the mechanisms for switching to the remote shutdown panel. In addition to the fiber optic systems, some hard wired actuation circuits will be provided in the control room for actuation of engineered safety features. The NRC requested that the hard wired circuits be explicitly identified. The NRC staff expressed some concern that the use of fiber optics for control of plant systems is new and as yet unproven in the nuclear industry. It will require a
. large effort for verification of the adequacy of the control systems with respect to NRC reouirements.
The subject of software maintenance and security was discussed, also. The NRC requested that Westinghouse specify where and how this will be addressed in
,- the Module. .
e The NRC staff found the approached described by Westinghouse to be generally satisfactory, and requested that Westinghouse submit a revised table of contents for Module 15 that reflects the meeting discussions.
Di m x. 4V -r Steven M. l.ong, Project Manager PWR Project Directorate #5 Division of PWR I.icensing-A
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y Docket No. STN 50-601 (WAPWR) RESAR-SP/90 i
Mr. E. P. Rahe, Jr., Manager Nuclear Safety Department Westinghouse Electric Corporation Water Reactor Divisions, Box 355 Pittsburgh, PA 15230 Dr. Rober Bari Brookhaven National I.aboratory Building 130 Upton, NY 11973 i
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ATTENDEES NAME AFFILIATION Steve long NRC Pro.iect Manager James R. Easter W Nuclear Technology W. G. Kennedy NRC/NRR/DHFT M. H. Shannon W Nuclear Terminology Systems Div.
W. M. Schively W Nuclear Safety (cpl.)
. J. E. Knight NRC EICSB Section leader Pete Morris W NID, Nuc. Safety, I&C 1.icensing Med Elzftawby ACRS/NRC
'r S. N. Saba NRC/NRR/EICSB Reviewer J. Brian Reid W Plant I&C Systems John Carrera W NTD/ Man-Machine F.D.
James Jay Cox W Plant I&C Systems Sy Weiss EICSB
r HEVISED JULY 8th AGENDA
.. ;- . 10:30 AM - 10: 45 am -- Introduction and Mode of Operation 1
M. H. Shannon Manager, Construction Plant Licensing 10: 45 am - 11 : 30 am -- Wal k-through of Chapter 18 Section Summary J. R. Easter -
Man-Machine Functional Design 11:30 am - 12:00 am -- NRC Feedback / Group Discussion 12:00 am - 1:00 om -- Lunch at Bethseda Licensing Office 1:00 om - 1:45 om -- Walk-through of Chapter 7 Section Summary I J. J. Co::
Plant Instrumentation & Control Systems 1:45 cm - 2:15 cm -- NRC Feedback / Group Discussion p 2:15 om - 2:45 cm -- W L NRC Commitments / Meeting Wrap-up n
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. To: StevIn M. Long, Projact Minager PWR Proj2ct Dirgetorcta C5 Division of PWR Licensing-A I
From: William M. Schivley i
W Nuclear Safety-Construction Plant Licensing Monroeville Energy Center Bay 410 Mail Stop 4-08 Phone: 412-374-5106 ~
D to: July 2, 1986
Subject:
Meeting agenda and Chapter summaries for scheduled July 8, 1986 meeting on RESAR-SP/90 PDA Module 15, " Control Room / Human Factors", to be held in Westinghouse Bethseda Licensing Office.
Wnstinghouse
Participants:
M. H. Shannon W. M. Schivley J. P. Carrera J. R. Easter P. J. Morris J. J. Cox l Attached for your early perusal is the Chapter 7 and Chapter
, 18 summaries which will be used for our discussion of
_ RESAR-SP/90 PDA Module 15.
b a The following agenda will be used for the scheduled W/NRC July Oth meeting to discuss the format of RESAR-SP/90 PDA Module 15:
9:00 am - 9:15 am -- Introduction and Mode of Operation
- M. H. Shannon Manager, Construction Plant Licensing 9:15 em -
10:00 am - Walk-through of Chapter 18 Section Summary J. R. Easter Man-Machine Functional Design 10:00 am - 10:30 am -- NRC Feedbac t:/ Group Discussion 10:30 am - 11:15 am -- Walk-through of Chapter 7 Section Summary J. J. Cox Plant Instrumentation b Control Systems 1.LL15 am - 11:45_amm -- NRC Feedback / Group Discussion 11:45 am - 12:15 om -- W & NRC Commitments / Meeting Wrap-up l
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. 18.3 Control Room Desian
/' 18.3.1 Overview 18.3.2 Information System This section describes the creation of the Display Task Descriptions from the results of the Cognitive Task Analysis described in Section 18.2.4, above. These Display Task Descriptions describe in detail the operator tasks, usually mental, that the display in question must support. These Task Descriptions are later used as the basis for a review of the display as part of the Verification and Validation process for the control room. Examples of these Task Descriptions and examples of the displays that are created from these will be included in this PDA application.
18.3.3 Alarm System This section will describe the design processes and fundamental bases that will be used in designing a modern alarm system.
. Detailed examples of the process, bases and results will be included.
p 18.3.4 Control System s
This section will describe the design processes and fundamental bases that will be used in laying out the controls portion of the control board. Examples of the process, bases and results will ,
be included.
18.3.5 Panel Layout Thi.s section will describe the design processes and fundamental bases that will be used in integrating (physically and from the cognitive aspects of operator performance) the alarms, the displays, and the controls into a complete work station design.
Examples of this integration will be included.
18.3.6 Room Layout This section will describe the design processes and fundamental bases that will be used in integrating the control room work stations (both physically and from the cognitive aspects of control room crew performance) to achieve a synergistic design that supports team work among members of the control room crew.
18.3.7 Work Space environment This section will discuss the process, and design principles and standards used to establish such things as: the location, level and color of lighting; allowable noise levels; intra-crew comminication; and the choice of room colors and decor. Those aspects of the overall room design which limit superfluous visitors and which contribute to the overall sense of purpose will also be discussed.
18.3.8. Process Computers (This will be addressed in Chapter 7 of Module 15).
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1 ,8 . 4 Control Room Design Validation
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This section will describe the design processes and fundamental bases that will be used in verifying and validating the control room design. Special emphasis will be placed on the development of a plan for man-in-the-loop testing.
18.5 Post-TMI Reauirements This section will describe how the post-TMI requirements for such systems as SPDS, Reg. Guides 1.97 and 1.47, etc. will be integrated into the control room design 18.6 Control Room Decian Revi ew This section will describe how the elements of the NUREG-0700 Control Room Design Review have been included in the design process for the control room.
18.7 Qgerator Trainino 5
This section will describe the process that Westinghouse plans to p use in conjunction with the utility and A/E in developing a '
s training program for control room operators.
18.8 Locations Outside Control Room This section will describe the process that Westinghouse plans to' use in conjunction with the utility and A/E to ensure that the control room design supports and interfaces well with these outside resources.
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r RESAR-SP/90 CONTROL ROOM / HUMAN FACTORS ENGINEERING j ,
- PROPOSED MODIFICATION TO CHAPTER 7 FOR INCLUSION OF MAIN CONTROL ROOM AND REMOTE SHUTDOWN PANEL IN MODULE 15 7.8-----MAIN CONTROL ROOM This section describes the Main Control Room in the context of the Instrumentation and Control Systems that feed into the
. Main Control Room. Interfaces are mentioned which support the Main Control Board Alarms, Displays, and Control Switches. Figure 7.8-1 entitled "ILC Architecture" is used for the basis of presentation. It also identifies the fact that this section is based on typical or planned implementations and that final decisions will be made as a result of the processes described in Chapter 18.
. 7.8.1-----MAIN CONTROL ROOM LAYOUT This section describes the circular shape of the Main Control Board, the placement of the Supervisory Console, free standing " diagnostic system" panels, and addresses miscellaneous panels desired by the utility. Figure 7.8.1-2, r entitled " Main Control Room Layout" is used for the basis of presentation.
7.8.2-----MAIN CONTROL BOARD This section presents a general description of the Main Control Board, circular section dimensions, and a side view.
The typical locations of the Alarms, Displays, and Control Switches'are also shown. Figure 7.8.2-1 entitled " Main Control Board (Front and Side Views)" graphically present this information.
7.8.2.1-----TYPICAL MAIN COtJTROL BOARD LAYOUT This section presents a general description of the layout of the Main Control Board with respect to systems and functions. Figure 7.8.2.1-1 entitled " Main Control Board Layout" physically shows this typical layout.
7.8.2.2-----MAIN CONTROL BOARD INTERFACES TO ILC SYSTEM This section presents a general discussion of the electrical interfaces surrounding the implementation of the IOC equipment, e.a., multiplexing, redundancy within systems, and the use of individual dedicated wires as required. Also discussed is how the reduction in the quantity of cables into the Main Control Board afffects the cable spreading room.
7.8.2.2.1-----ALARM SYSTEM This section presents a general description of the Alarm System. Figure 7.8.2.2.1-1 entitled " Alarm System Architecture" is used as the basis for this discussion.
g, -7. 8. 2. 2. 2-----DISPLAY SYSTEM This section presents a general description of the three types of data displays which are found in the Main Control Room, i.e.,
Accident Monitoring (Reg. Guide 1.97) Displays, Operational Displays, and Plant Computer driven displays. Figure. 7.8.2.2.2-1 entitled " Display System Architecture" is used as a basis for thi s di scussi on.
7.8.2.2.2.1-----ACCIDENT MONITORING (REG. GUIDE 1.97) DISPLAYS This section describes how the equipment which supports the Accident Monitoring Displays meets the equipment requirements of Reg. Guide 1.97. The above Figure 7.8.2.2.2-1 is used for this description.
7.8.2.2.2.2-----OPERATIONAL DISPLAYS This section describes the equipment which supports the Operational Displays during normal operation and uses part of the Accident Monitoring Display equipment. The above Figure 7.8.2.2.2-1 is used for this description.
f 7.8.2.2.2.3-----PLANT COMPUTER DRIVEN DISPLAYS This section covers the equipment on the Main Control Board that interfaces with the Plant Computer.
7.8.2.2.3-----CONTROL SWITCHES This section addresses the two types of Control Switches, i.e.,
multiplex'ed and hardwired. Figure 7.8.2.2.3-1 entitled " Control Switch Interfaces" is used as the basis for this presentation.
7.8.2.2.3.1-----MULTIPLEXED CONTROL SWITCHES This section covers the two types of multiplexed switches. One is connected through multiplexers to Integrated Logic Cabinets, and the other is connected through a multiplexer to the Integrated Control Cabinet. Reference is made to Figure 7.8.2.2.3-1.
7.8.2.2.3.1.1-----CONNECTIONS TO THE LOGIC BUS This section addresses the Off-On Control Switches which are connected to the Integrated Logic Cabinets via 1E and non-1E multiplexers, via a logic bus. Reference is made to Figure 7.8.2.2.3-1, 7.8.2.2.3.1.2-----CONNECTIONS TO THE PROCESS BUS This section addresses the Auto-Manual Controls which are connected to the Integrated Control Cabinet via a process bus.
Reference is made to Figure 7.8.2.2.3-1.
CHAPTER 7
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7.8.2.2.3.2-----HARDWIRED CONTROL SWITCHES This section addresses those Control Switches on the Main Control Board which are directly connected to a destination cabinet, rather than being multiplexed. Ex2mples will be given such as the Manual Reactor Trip, Safety System Manual Actuation, etc.
7.8.3-----SUPERVISORY CONSOLE #
This section will describe that the Supervisory Console and the devices it contains for viewing the Accident Monitoring (Reg.
Guide 1.97) Displays, Alarms, and Displays driven by the Plant Computer.
7.8.4-----REMOTE SHUTDOWN PANEL This section will cover that the Remote 7hutdown Panel which contains plasma flat panel devices f or d; splaying Reg. Guide 1.97 Data Displays (no meters) and Control Switches similar to those on the Main Control Board. It will be noted that non-optical links (i . e. , wires) will be used to connect these multiplexed signals to their respective Integrated Logic Cabinets. The .
'e Remote Shutdown Panel does not have an Alarm System since the 8
operator is consciously controlling the safety plant components.
7.0.5-----MAIN CONTROL BOARD DESIGN IMPLEMENTATION PROCESS This section will describe the process of using a multidisiplined team to design the Main Control Board. Mention will be made of using a static full size mockup, and prototypes for the Main o
Control B'ard structure, Alarm System, Display System, and Control Switches. Figure 7.8.5-1 entitled "One Section From Main Control Board Mockup" will be used to show typical results expected after the team has completed the design.
7.8.6-----CONFORMANCE TO REGULATORY GUIDES This section identifies the various Regulatory Guides to which the Main Control Room /Mair. Control Board / Remote Shutdown Panel will conform.
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The instrumentation and control aspects of the control room are included in Chapter 7 of the standard safety analysis report format. Westinghouse staff presented a verbal sunnary of the materials from Chapter 7 that will be included in Module 15.
The extensive use of multiplexed fiber optics for transmission of data and control signals will have a major effect on the logic of control panel design and the mechanisms for switching to the remote shutdown panel. In addition to the fiber optic systems, some hard wired actuation circuits will be provided in the control room for actuation of engineered safety features. The NRC requested that the hard wired circuits be explicitly identified. The NRC staff expressed some concern that the use of fiber optics for control of plant systems is new and as yet unproven in the nuclear industry. It will require a large effort for verification of the adequacy of the control systems with respect to NRC requirements.
The subject of software maintenance and security was discussed, also. The NRC requested that Westinghouse specify where and how this will be addressed in the Module.
The NRC staff found the approached described by Westinghouse to be generally satisfactory, and requested that Westinghouse submit a revised table of contents for Module 15 that reflects the meeting discussions.
W Steven ,l.ong, Project Manager PWR Project Directorate #5 Division of PWR I.icensing-A 0FC PD#5 : : : : : :
___________g____:.___________:____________:____________.____________.______
NAME :St.ong:es : : : : : :
DATE : 7/zf/86 : : : : : : )
0FFICIAI. RECORD COPY l
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o k Meeting Summary Distribution
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-(Docket 6'rlentral; File'. NRC Participants NRC PDR local PDR S. Long PD#5 Reading File W. G. Kennedy J. Partlow J. E. Knight V. Noonan Med Elzftawby Project Manager S. Long S. N. Saba OELD Sy Weiss E. Jordan B. Grimes ACRS (10)
M. Rushbrook cc: Licensee and Plant Service list 1
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