ML20207E240
| ML20207E240 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/22/1986 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20207E236 | List: |
| References | |
| NUDOCS 8701020120 | |
| Download: ML20207E240 (169) | |
Text
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TABLE OF CONTENTS g-: TITLE
.SgCTION PAGE jf. - Pre face - iii 1.0 Introduction' 1
}y 1.1 -objective 1 "q>4~ , 1.2; ' Discussion 1 f'Yp 1.3 Reference Documents 2 52.0, . System Overview' 4 - p-
'< 12.1~ SPDS Hardware Configuration 4 2.2- . Basis for SPDS Parameter Selection 8 c4 2.3 SPDS Software 9 UV 2.4 SPDS Displays 10 i$ '. 3.01 Systes. Usage by Control Room 24 sq. Personnel and Plant Procedures p
3.1 Integration of SPDS and Operating Procedures 24
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13.2 . Training 24 _\v j- 3.3 System Reliability 24 4.0- ~ Verification, Validation and Quality 25 Assurance s' Design, Manufacturing and Installation 25
. 4.1' -
i- , ,,.y 4.2' Verification and Validation Plan 25 a . s.
- ~s - APPENDICES SUBJECT
+p-M' Computer CRT Graphic Display Design Guidelines
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A Of B Verification and Validation Plan C SPDS Displays and Keyboards D Critical Safety Functions Status Tree Logic
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-- 'E List of Acronyms oO
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. TABLES TITLE PAGE
=2.4-1 STP SPDS Parameters 12 2.4 Display Presentation, Normal 18 Mid Level Displays 2.4 Display Presentation, Critical 21
'Mid Level Displays FIGURES- TITLE PAGE 2.1-1 Control Room CRT Layout 5 l 2.1-2 Hardware Configuration 6 2.4-1 Normal Safety Parameter Display 16
'2.4-2 . Critical Safety Parameter Display 17 a
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PREFACE
' Thei system performing the functions of the Safety Parameter Display System (SPDS)- Jat - the South Texas ' Project (STP) is integrated into the Emergency 1 Response Facilities Data acquisition and Display System (ERFDADS). The SPDS at
-STP provides concise, reliable, pertinent data to control room personnel overseeing the.~ plant- during normal and emergency operations. The system m -monitors plant process data input from field sensors, organizes it, applies it to a hierarchy. of displays and presents it to the operators via ' color monitors in the ' Control Room (CR), -Technical. Support Center (TSC) and Emergency Operations Center (EOC).
This Safety' Analysis Report is provided in accordance with the guidance contain-ed in NUREG-0696 and the requirements of NUREG-0737 Supplement 1, and supple-L meats'the.information previously provided in STP FSAR-Section 7.5.7 and Appendix
- 75. -
The methodology implemented in developing the 'SPDS displays is in accordance with NUREG-0696 and the Control Room Design Review programs addressed in the STP Control-Room Design Review (CRDR) Reports,.and NUREG-0700. This methodology is
'also reflected in the design of the Westinghouse Qualified Display Processing System (QDPS) displays.
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1.0 INTRODUCTION
~ 1.1 Objective The objective of this Safety Analysis Report is to present the basis that was used to develop and implement the SPDS as well as to provide both a functional and system design ~ description. The SPDS provides a display of plant parameters from which.the plant safety status may be quickly assessed during both normal and emergency operating conditions. The primary function of the SPDS is to help operating personnel in the control room make rapid assessments of plant safety status. The SPDS has been designed in accordance. with NUREG-0696, NUREG-0737 Supplement 1 and NUREG-0700.
1.2 Discussion-An analysis was conducted to identify the appropriate variables and establish
'the design basis and qualification criteria for instrumentation employed by the
- control room operator during and following an accident. The results of this analysis are summarized in STP FSAR Appendix 7B. Further, the variables needed by the operators to rapidly assess plant status during normal and emergency conditions have been identified. Most of these variables are also Regulatory Guide 1.97 variables; however, the primary reason for selection as SPDS variables was usefulness in assessing plant status.
['N For the purposes of this document the following meanings are used: t ! v (1) normal / abnormal plant operating conditions - reactor trip breakers closed (2) emergency plant operating conditions - reactor trip breakers open
-The detailed implementation of displays has been developed through the design of the Qualified Display Processing System (QDPS) and in conjunction with the Control Room Design Review program, which addresses NUREG-0700.
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1.3 Reference Documents
!NUREG-0588- '_' Environmental Qualification of Safety Related Equipment" NUREG-0654 " Criteria for Preparation and Evaluation of Radiological Emergency
-Response Plans and Preparedness in Support of Nuclear Power Plants" NUREG-0696. " Functional Criteria for Emergency Response Facilities" NUREG-0700 " Guidelines for Control Room Design Review" NUREG-0737 " Clarification of TMI Action Plan" NUREG-0737. " Requirements for Emergency Response Supplement 1 Capabilities"
'NUREG-0800 " Human Factors Review Guidelines for Section 18.2 SPDS"
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' () NUREG-0814' " Methodology for Evaluation Emergency Responsg Facilities" of Contents of Applications; Technical 10CFR50.34 Information" 10CFR50.49L " Environment Qualification of Electric Equipment Important to Safety for Nuclear i
Power Plants." IEEE 323-1974 " Standard for Qualifying class 1E Equipment for Nuclear Power Generating Stations" l IEEE 344-1975 " Recommended Practices for Seismic Qualification of Class 1E Equipment l for Nuclear Power Generating l-Stations" ANSI N45.2 " Quality Assurance Program Requirements for Nuclear Power Plants" L NSAC/39 " Verification and Validation for l Safety Parameter Display System" STP FSAR Section 7.5.7 and Appendix 7B W1/A505/z 2 12/22/86 i l._. , _ , . , , . _ _ _ - , , _ _ _ - _ _ - . - , , _ , _
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1.3 Ref-:rence Documents (Cont'd)
' Letter -Mr.'M.-R. Wisenburg, HL&P to ST-HL-AE-1790 Mr. Vincent S. Noonan, NRC; " Test Report dated 10/31/86 for Class 1E Isolators"
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.STP Control Room CRDR Criteria Report, including revisions Design Review I
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'2.0 SYSTEM OVERVIEW:
'2.1 SPDS Hardware Configuration The Dtwo ~ power plant units at the -South Texas Project are independent, fetand-alone units.- Each unit has.its own SPDS and independent Technical Support I Center (TSC); a ' single . Emergency ~0perations Center-(EOC) is provided for both
- plants. - The SPDS'provides displays of plant parameters in the control room, TSC and IOC.
The SPDS equipment configuration in the main control . room is illustrated in Figure 2.1-1. The SPDS displays in the control room are conveniently located to
.the : control room operating. crew. The location and size of the displays meet
~ human ~ factors guidelines and the intent of appropriate display readability
;; guidelines stated in NUEEG-0700.
The'two control room consoles have three 13 inch color ~ graphic displays, with a
- full function keyboard 'for each console. Mounted ' on the control panels are three additional 19 -inch color graphic displays with function keypads.
.The display locations were chosen to provide convenient and readily accessible information to the plant operators to aid in assessing the safety status of the plant - during -- normal /abnorisal and emergency" operating conditions. Display locations ' on the operator's consoles facilitate monitoring of the plant, using p -the SPDS, by' supervisory personnel.
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- h 2.1.1 Hardware glements
.The hardware components of the SPDS are divided into four major groups, as depicted on Figure 2.1-2.
2.1.1.1' Isolation System This system provides electrical isolation and physical separation between Class 1E instrumentation and the non-Clan IE SPDS. 2.1.1.2 Data Acquisition System This system gathers sensor data, converts this information to digital format, converts to engineering units, determines and applies data quality tags, and transmits data to the central processing units. 2.1.1.3 Central Processing Units (CPUs) The two host CPUs receive digitized data, process and store it and transmit it to the Man-Machine Interface System. 2.1.1.4 Man-Machine Interface System This system provides for the display of SPDS processed data to the plant opera- , tors and responds to demands for display of data. W1/A505/z 4 12/22/86
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PERIPHERALS (MANMACHI!TE
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KEYBOARDS j PRINTERS SPDS System Hardware Configuration Figure 2.1-2 Wl/A505/z 6 12/22/86
X i V M : Displays ~ were designed to ' provide concise information to the plant operators.
~ Display l locations were optimized with the panel layout to provide convenient and readily accessible information to plant operators in the areas of the control room where response equipment is controlled, in order to aid in assessing the normal / abnormal and emergency operating conditions. Display locations or. the operator's consoles facilitate monitoring of the plant via the SPDS by
-supervisory personnel.
2.1.2. Data Flow From Sensor to Display Data is initially scanned by multiplexers in the data acquisition system (DAS). Non-Class 1E process and control data is wired directly to the multiplexer
-inputs while Class 1E process and control data is processed through qualified
- isolation devices before being input to the multiplexers. The DAS also receives input data via the data links from the Radiation Monitoring System (RMS) and the Qualified Display Processing System (QDPS). The multiplexers collect the data and'make it available to two redundant DAS CPUs via fiber optic cables. The CPUs organize the data and transmit it to redundant host CPUs via high speed
' data links. The host CPUs also receive data from the meteorological monitoring system and transmit data to the Plant Computer System.
The two redundant host CPUs perform identical functions, with one designated as primary and the other as backup. Similarly the two redundant DAS CPUs perform identical ~ functions. Capability exists within the system to automatically fail over to the backup CPU, upon detection of a system failure. An Uninterruptible Power - Supply (UPS) is provided to support system power requirements. The V integrated hardware system as designed provides an availability of 99%. After the collected data reaches the host CPUs, it resides in the system data-base. Here the data is acted upon by the operating system software and applica-tions software to provide to plant operating personnel SPDS displays which are comprehensive and functional. These displays have been integrated into the Emergency Operating Procedures and are designed to meet the intent of NUREG-0696 and NUREG-0737 Supplement 1. 2.1.3 Isciation System
'The isolation ' devices for the SPDS provide isolation between the Class 1E instrumentation and the non-Class LE SPDS. The SPDS isolators have been qualified to the requirements of Regulatory Guide 1.75. This qualification includes environmental qualification per the requirements of IEEE 323-1974 and seismic qualification to the requirements of IEEE 344-1975. In addition, the L isolation devices have been tested to 'the maximum credible fault as required by
[ NUREG-0737 Supplement 1. It has been demonstrated that there are no plant safety concerns which result from the existing SPDS input configuration. (Refer to Houston Lighting and Power Company letter to Mr. Vincent Noonan, NRC, ST-HL-AE-1790, dated 10/31/86, for additional detailed information regarding isolator qualification and testing.) I 1 I W1/A505/z 7 12/22/86
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- 2'.2 3 asis ~for SPDS Parameter Selection Thel principal' purpose and function of the STP SPDS are . to aid the control room
. personnel' . during normal and emergency conditions in determining the safety statua of the - plant and whether- conditions warrant' corrective actions. To
' fulfil 1~ this purpose,. the STP SPDS provides a concise display of critical plant
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Evariables to the control room operators to aid ' them in rapidly evaluating the safety ' status of the plant. The STP SPDS will be operable during normal operations as well as during abnormal and emergency' conditions, and will provide continuous display of these critical variables. This~ design basis establishes the key and preferred backup variables displayed via . the SPDS. The design basis recognizes the variables essential to the
- control' room staff from normal operating conditions up to the time other emer-ger.cy response facilities are manned, as well as the information essential to the control. room staff in subsequently controlling the plant and proceeding to safe shutdown conditions.
The selection of variables for post-accident plant - status determination was integrated with implementation of the Westinghouse Owners Group (WOG) Emergency Response Guidelines (ERGS) in ' accordance with the guidance on integration of emergency response capability elements outlined in NUREG-0737 Supplement 1. This integration was accomplished by performing a task analysis based upon the WOG ERGS to identify those variables necessary for impismentation of the guide-lines. The Optimal Recovery Guidelines (ORGs) were reviewed to determine those
'7 q variables necessary t o. (a) perform diagnosis, (b) take preplanned manually N . controlled actions and (c) take actions necessary to reach and maintain a controlled condition.- The Critical Safety Function (CSF) Status Trees were reviewed to determine those variables necessary for the operator to determine if a Functional Restoration Guideline (FRG) should be implemented. Furthermore, the' ' FRCs ~were reviewed to determine those variables necessary to assess the process of accomplishing or maintaining CSFs, i.e., Suberiticality, Reactor Core Cooling, Heat Sink Maintenance, ' Reactor Coolant System Integrity, Containment Environment, and RCS Inventory.
Utilisatio'n of this task analysis process ensures that the plant information utilized by the plant operators during emergency conditions to implement the STP Emergency Operating Procedures (EOPs) is obtained from specially designed and qualified instrumentation as defined in this design basis. The selection of variables for normal / abnormal operation plant status determina-tion was performed in a similar fashion. The same safety functions were identi-fied as important during normal / abnormal operation; the plant parameters deemed most appropriate for determining the safety function status were selected by
- engineering and operations personnel for use on the normal safety function displays.
The results of the Control Room Design Review and the STP implementation of RG 1.97 Revision 2 have been used in conjunction with the variables identified as l SPDS variables to develop SPDS displays that are human factored, function oriented, and integrated with the plant design and operating procedures. i l W1/A505/z 8 12/22/86 I
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'd -2.3 SPDS Software 1 l
The process and control : data which is continuously collected from the plant l
. sensors lis converted to engineering units and its data quality is determined by the DAg-software. After being sent to the host CPUs, the data is acted upon by a E set / of. algorithms which format the data into the SPDS displays. A very
'important Tpart of the SPDS is the methodology or algorithms in which a group of qplantL data values is associated within an algorithm to .previde a meaningful
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m ' displaycwhich defines a -deviation from a safe operating condition. The SPDS algorithme generally consist of the following sections: 2.3.1-Quality 1 Tagging'and Validation (DAS CPUs) The sensor data coming into the SPDS is initially tested for the sensor point
- being in or . out . of scan and the incoming data being within the calibrated operating range. - An operability self-test of each SPDS input circuit card is also conducted every scan cycle. As a result of these initial tests, a quality tag is assigned to each parameter. 6 The validation portion of the algorithm compares each incoming signal with like signals of similar range measuring the same plant parameter. If the signals deviate significantly, the parameter measured is tagged invalid (bad) or poor, depending on the extent of deviation. The validation information is retained for'use in algorithms and is displayed to the operator.
9 2.3.2 Processing of Parameters G The validated signals are processed (i.e. averaged, high select, low select) to generate- a " representative. value" of the measured parameter. This
" representative value" is then used to drive analog displays on the mid level normal and critical function display pages.
2.3.3 Comparison with Predetermined Safe Value The 1 representative values are then compared with a predetermined safe value , based upon operating mode and/or a measured plant parameter. The resultant is then normalized and combined with other parameters to generate a bar length value for the composite parameter to identify deviations from the predetermined
- safe value.
2.3.4 Bar Length and Color Determination The bar lengths for the mid level displays are calculated by the software based upon the identified plant operating mode and the alarm limits associated with the identified mode. When a parameter changes to a value exceeding an alarm limit, the color of the bar changes as a function of the alarm limit reached. The bar. lengths for the top level normal safety function display are calculated by the software using the results of the comparison of the normal mid level parameters to the predetermined safe values. The color of each bar changes as a function of the highest alarm level reached on its associated mid level parameter set. W1/A505/z 9 12/22/86 !
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'"y The.har lengths.for.the top level critical safety function display are calcu- !
Isted using- the' results of the comparison of the critical aid level parameters to the predetermined safe values. The color of each bar remains pink, unless
- all input ' parameters are bad, regardless of parameter values or alarm limits reached. If all inputs are bad, a full length, dark blue bar will be displayed.
2.3.5 Safety Status Indicators During normal / abnormal plant operation .(reactor trip breakers closed), each safety function backup page displays the status of each of .the normal safety functions in the lower lef t-hand corner in the form of six safety status indi-cators, one for each normal safety function. The color of each safety status indicator . is the same as ' and reflects the same status as the corresponding bar on the top level normal safety function display. During emergency modes of operation (reactor trip breakers oped), each safety function' backup page displays the status of the critical safety functions in the lower lef t-hand corner in the form of six safety status indicators, one for each critical safety function. The color of each safety status indicator is determined according to the critical safety function status tree logic as des-cribed in the STP Emergency Operating Procedures (EOP) and developed by the Westinghouse Owners Group .for the Emergency Response Guidelines. (Refer to
;; Appendix D.)
The 'six safety status indicators are also shown below the corresponding safety
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l' . function bar on each top level display, with colors determined the same as for the indicators on the mid level displays. 2.4 SPDS Displays 2.4.1 SPDS Display Overview The Safety Parameter Display System provides a display of plant parameters from which the safety status of operation may be assessed both during normal / abnormal operation and emergency conditions. The primary function of the SPDS is to help operating personnel in the control room make quick assessments of plant safety status. The SPDS displays are designed in accordance with NUREG-0696 and NUREG-0700. The SPDS displays have been designed to meet these requirements during normal / abnormal and emergency operating modes with due consideration to the human factors guidelines. Human factors review of the SPDS displays is performed as part of the STP Control Room Design Review (CRDR). The STP CRDR Criteria Report guidelines specific to CRT displays (Appendix Q) are included in the Computer CRT Graphic Display Guidelines provided as Appendix A to this report. 2.4.2 Top Level Display The SPDS displays are dynamic real time displays which indicate the status of the plant. A single primary display format is displayed for normal / abnormal operation and another for emergency operation, from which plant safety status can be inferred.
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The primary displays are composed of a number of parameters and derived vari-ables giving.an overall systems status. The plant safety functions identified in . NUREG-0696, as modified by the Westinghouse Owners Group (WOG) Esergency Response Guidelines, are included in the top level SPDS display for emergency operation. The normal operation safety function display addresses the same safety. functions; however parameters applicable to normal / abnormal operation are lused in the display. The plant safety functions presented in the two top level displays include the following:
- 1. Subcriticality
- 2. Core Cooling
-3. Heat Sink
- 4. Integrity
- 5. Containment
- 6. Inventory Each of these plant safety functions is composed of mid level variables. A unique set of variables used in the mid level displays is included for each plant mode of operation (normal / abnormal and emergency conditions).
2.4.2.1 Mid Level Variables Assurance that each safety function is being maintained requires the monitoring of numerous plant variables. Those variables, identified as mid level safety parameters, have been selected for use in monitoring the status of each safety
,bp] -t function. The variables associated with emergency operation are considered eritical safety function variables and those associated with normal / abnormal plant operation are identified as normal safety function variables.
The mid level parameters associated with safety functions during normal / abnormal operation and safety functions during emergency operation are identified in
-Table 2.4-1.
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Table 2.4-1
- / \- STP SPDS Parameters t . ,vj.
Sj fEty Function ' Normal Safety Function Critical Safety Function (Pre Reactor Trip) (Post Reactor Trip) Suberiticality Source Range Neutron Flux Neutron Flux - Extended Range (Upper and Startup Rate Range) Intermediate Range Neutron Neutron Flux - Extended Range (Lower Flux and Startup Rate Range) Power Range Neutron Flux Neutron Flux - Extended Range - Startup Rate
-Core Cooling Max Tcold (Wide Range) Reactor Vessel Water Level - Upper Head
** hot (Wide Range) Reactor Vessel Water Level - Plenum Average Temperature (Narrow Subcooling Margin Range) Core Exit Temperature Delta Temperature (Narrow
. , , Range)
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( Total RHR Flow ,
-H rt Sink Steam Generator Level Steam Generator Level (Narrow Range)
(Narrow Range) Steam Generator Pressure Steam Flow / Feed Flow Total Aux. Feedwater Flow Differential Aux. Feedwater Loop Flow Steam Generator PORV Status Steam Generator Safety Relief Valve Status Steam Generator Blowdown Radiation Level Condenser VacAum Pump Exhaust Radiation Level Max Main Steamline Radiation Level W1/A505/z 12 12/22/86 _ _ _ _ _ , . , _ _ , _ . _ _ . _ _ _ _ _ _ . ~ _ _ ~ . . _ . . , . _
Tr Table'2.4-1 (Cont'd) i if
*- mitegrity- Pressuriser Pressure T eold in each Loop (Wide Range)
Pressuriser PORY Status T cold Drop (in last hour) Pressurizer Safety Relief RCS Pressure Valve Status- RCS Pressure and Temperature versus Plant i RCS Pressure Operational Limits Display Reactor Vessel Head Vent RCS Pressure and Temperature versus COMS Valve Status Limits Display Reactor Containment Building Atmosphere Radiation Level (Noble Gas and Particulate) ECoitainment Atmosphere Radiation Level Water Level (Wide Range) Plant Vent Radiation Level Hydrogen Concentration-Pressure (Normal Range) High Range Radiation Level Temperature Pressure (Normal Range and Extended Isolation Status / Operability Range) Ci .
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Inventory Pressurizer Level Reactor Vessel Water Level - Upper Head VCT Level Reactor Vessel Water Level - Plenum . Charging Flow , Pressurizer Level Letdown Flow Seal Injection Flow Critical Safety Functions: as defined in the WOG ERGS and the STP E0Ps. W1/A505/z 13 12/22/86
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'2.4.2.21 Display Presentation The , top level normal , safety function display is designed to show the relative ,
value Lof- each ofthe six normal safety functions -during normal / abnormal plant
) operation.. 1Each ~~ safety function uvalue is shown as a vertical bar. The
, magnitude .~of each bar represents the degree of deviation from normal, and the
' color of .the bar changes as a function of alarm limits recched. The normalized
' displays identify normal, warning, and alara levels of operation by changing the color from green to yellow to magenta respectively. The top level normal safety
' function . display also has six ' safety - status indicators, one for each normal safety : function. The color of each status ; indicator is the same as its respective safety function bar.
The top level critical safety function display is designed to show the relative
.value of each of the six critical safety functions following a reactor trip.
Each < safety function vs.lue is shown as a vertical bar. The magnitude of each bar represents.the degree of deviation from normal, and the color of each bar is pink. If all : input parameters are bad, a full length dark blue bar will be displayed. The normalised ' displays identify normal, warning, and alarm levels of operation. The top level critical safety function display has six safety status indicators, one for each critical safety function. The color of each status indicator is determined through the logic of the critical safety function status-trees as described in the STP Emergency Operating Procedures (EOP) and developed by the Westinghouse owners Group (WOG) for the Emergency Response Guidelines (ERGS). M The top level L normal and critical safety function display bars represent the deviation of up to- fifteen aid level parameters. In order to effectively present this'informatfor',-the deviation from normal of each aid level parameter is normalised to a prescribed scale. The displayed top level deviation is the largest of these normalised parameters. lThe top. level displays for normal and critical safety functions are shown in Figure 2.4-1 and 2.4-2 respectively, and in Appendix C. 2.4.2.3 Validation-Validation of each top level safety function bar depends on the validation of its' constituent aid level parameters. The top level safety function bar vali-dation algoritha does not use an invalid mid level parameter. If all mid level parameters for a top level safety function bar are invalid, a full length bar having the invalid designation is displayed. Data which has been rejected analytically during algorithm processing for the mid level parameters is so marked and is treated as invalid in both top level and mid level displays and in any subsequent calculations and displays. 2.4. 2.4 Algorithms A generalized method of computing the top level safety function bar deflection as a function of mid level parameters is used. The result is presented as a unitiess number presented within the normal, warning or alarm areas of the
' display.
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(' , V)~ ~ 2.4.3 Mid Level Displays The mid level displays are backup displays, one for each safety function, and present a graphical representation of the parametric values associated with that safety function. The information displayed on the normal and critical mid level displays is shown in Tables - 2.4-2 and 2.4-3 respectively. The mid level dis- _ plays for normal / abnormal and emergency operating conditions are shown in Appendix C. '
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O Figure 2.4-2 Wl/A505/z ,,
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Table 2.4-2 Display _ Presentation Normal Mid Level Displays Normal Subcriticality 0 Source Range Neutron Flux Display 30 min trend of flux from 1 to 10 CPS and Startup Rate and startup rate from -0.5 to +5.0 DPM.
~II Intermediate Range Neutron Display 30 min trend of flux from 10 to 10 3 Flux and Startup Rate amp and startup rate from -0.5 to +5.0 DPM.
Power Range Neutron Flux Display 30 min trend of flux in each quadrant from 0 to 120 percent. Normal Core Cooling Maximum T Id ('lide Range) Display 30 min trend of highest loop T cold jm (wide range) from 0 to 700 degrees F. I \ ( ,/ Maximum Thot (Wide Range) Display 30 min trend of highest loop T gg (wide range) from 0 to 700 degrees F. Average Temperature (Narrow Display 30 min trend of overall average Rango) temperature between 530 and 630 degrees F. Delta Temperature (Narrow Display 30 min trend of differential Range) temperature in each of four loops from 0 to 140 degrees F. Total RHR Flow Display bar graph of total RHR flow from 0 to 12,000 GPM. Normal Heat Sink Steam Generator Level Display 30 min trend of narrow range water level (Narrow Range) for each steam generator from 0 to 100 percent. W1/A505/z 18 12/22/86
pr ( , . [ ,, Q.
>' . Table 2.4-2.(Cont'd)
- Steam Flow /Ieed E Flow Display 30 min trend of steam
- Differentia 1> flow /feedwater flow ' differential for each f steam generator from -1000 to +1000 KLB/HR.
' Steam Geogator . PORY Display status (open/ closed) of each SG PORV.
Status Steam Generator Safety Display status (open/ closed) of the SG safety
~
" Relief Valve ~ Status .
_ relief valves. (Shows open if any valve is open.) Steam Generator Blowdown Display 30 min trend of. maximum SG blowdown Rad'istion Level radiation level from 10 ~0 to 10 uCi/cc. Condenser Vacuum Pump Display radiation level in condenser vacuum Rahaust Radiation Level pump exhaust from 3.4x10 -7 to 2.0x105 uci/ce. Main Steamline' Display the highest radioactivity level y, , Radiation Level of the main steamline monitors and identify O-g . SG being displayed. Range from 1.4x10 -2 to 6 1.4x10 uCi/cc
' Normal Intearity Pressuriser Pressure Display bar graph of pressurizer pressure from 0 to 3000 PSIG.
Pressuriser PORY Status Display status (open/ closed) of the pressuriser PORVs. (Shows open if either valve is open.) Pressuriser Safety Relief Display status (open/ closed) of the Valve Status pressurizer safety relief valves. (Shows open if any valve is open.) RCS Pressure Display 30 min trend of RCS pressure from 0 to 3000 PSIG. Reactor Vessel Head Vent Display status (open/ closed) of the reactor Valve Status vessel head vent valves. (Shows open if either throttling valve is open.) W1/A505/ 19 12/22/86
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' Table 2.4-2 (Cont'd)
RCB Atmosphere ~ Display 30 min trend of RCB atmosphere
' Radiation Level radiation level (noble gas and particulate) from 10 ~11 to 10-3uci/cc.
Normal Containment Noble Gas Effluent Display'30 min trend of containment Radiation Level. atmosphere and plant vent noble gas radiation
~7 level fran 10 to 10-2uci/cc.
Pressure and Temperature Display 30 min trend of containment pressure from -5 to +20 PSIG and temperature i from 70 to 120 degrees F. Isolation Status / Display the presence of containment phase A Operability isolation signal or containment vent
-- isolation signal and "INOP" if any valve
( ,j receiving signals is inoperable. Normal RCS Inventory Pressuriser/VCT Level Display 30 min trend of pressurizer and VCT water levels from 0 to 100%. Charging Flow / Letdown Display 30 min trend of charging flow, Flow / Seal Injection Flow seal injection total flow and letdown flow from 0 to 500 CPM.
\
W1/A505/z 20 12/22/86
i+ 4
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v Table 2.4-3 Display Presentation Critical Mid Level Displays
> .Suberiticality
' Neutron Flux - Extended Range Display 5 min trend of extended range neutron (Upper Range) flux (upper range) from 10 ~0 to 200 percent, log scale.
% Power / Linear Scale Display bar graph of percent of full power from 1 to 10 percent.
Neutron Flux- Extended Range Display bar graph and value of extended range (Lower Range) neutron flux (lower range) from 10 -1 to 10 $ CPS, log acale. Neutron Flux - Extended Range Display bar graph and value of extended range 7- m - - Startup Rate neutron flux startup rate from -0.5 to 2.0 () DPM. Core Cooling Resctor Vessel Water Level Display bar graph and values of upper head and plenum water levels from 0 to 100% with sensor locations indicated. Subcooling Margin Display bar graph and value of subcooling margin from 200 degrees F subcooled to 50 degrees F superheat. Core Exit Temperature Display bar graph and value of maximum temperature (5th hottest thermocouple) from 500 to 1500 degrees F. Heat Sink Steam Generator Level Display bar graph and value of each steam (Narrow Range) generator water level (narrow range) from 0 to 100%. W1/A505/s 21 12/22/86
{.;
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y ; f' 7- Table 2.4-3 (Cont'd)
'Steae Generator Pressure Display bar graph and value of each steam generator pressure from 0 to 1400 PSIG.
' Aux Feedwater Loop Flow Display value of each auxiliary feedwater loop flow from 0 to 700 GPH.
Total Aux Feedwater Flow Display bar graph of total auxiliary feedwater flow from 0 to 2800 GPM. Intearity Tcold (Wide Range) Display bar graph and value of each wide range cold leg loop temperature from 0 to 700 degrees F. T eoid Drop (Last Hour) Display bar graph and value of largest cold leg temperature drop in last 60 minutes from 0 to 200 degrees F. n RCS Pressure and Display of RCS pressure from 0 to 3000 PSIC
) Temperature versus PSIG and auctioneered low wide range cold Plant Operational leg temperature from 0 to 400 degrees F, Limits with plant operational limits displayed. Also display value of RCS pressure.
RCS Pressure and Display of RCS pressure from 500 to 800 PSIG Temperature versus CONS and minimum RCS temperature from 0 to 400 Limits degrees F, with cold overpressure (COMS) limits displayed. Containment Water Level (Wide Range) Display bar graph and value of water level Train A from 0 to 75 inchess Train B from 0 to 81 inches; Train C from 0 to 87 inches. O W1/A505/ 22 12/22/86
l
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Table 2.4-3 (Cont'd) Hydrogen Concentration Display bar graph and value of hydrogen concentration from 0 to 10 percent
' Radiation Level Display bar graph and value of containment 8
high range radiation level from 10 to 10 R/HR, log scale. Pressure (Normal and Display bar graph and value of normal range Extended Range) pressure from -5 to 65 PSIG and extended range pressure from 0 to 180 PSIG. Inventory Reactor Vessel Water Level Display bar graph and values of upper head and plenum water levels from 0 - 100% with sensor locations indicated. Pressurizer Level Display bar graph and value of pressurizer fs water level from 0 to 100%. L) - I W1/A505/ 23 12/22/86 i
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LR 3.0 System. Usage by Control Room Personnel and Plant Procedures 1%' ;;h ,m.
, af.3.1 Integration of SPDS and Operating Procedures
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9 . - 1 The SPDS, it, used by control room personnel for monitoring plant status during boti neraal/ abnormal and energency plant operations. Separate sets of displays are"provided for.these differing conditions. The plant operators are encouraged through training -to une the displays, with the selection of particular displays
'left;.t'o their discretion. The flexibility built into the system allows selec-tion / of different displays on each CRT based on the individual operator's O m 'p'referenc'e.
B 'i;he ' normal o safety function displays contain a, selection of normal operating N parameters which present a broad basis for determining plant safety status based lon the six safety functions.' The critical safety function displays contain the emergency operating parameters required? En. assess plant safety status using the CSF status trees. Those i% displays previded to aid in the accomplishment of specific tasks are referenced within the text = of ' the F.nergency Operating Procedures. This relieves the operator . from the need to recall which display to select during an already stressful situation. 3.2 Training g/
)m .The SPDS vando'r has provided training and necessary material to the South Texas j <
t Project traini~ng department to provide ongoing training to operations personnel. SPDS trainin'g will be integrated into the operator training program provided by the training i department. JQ Tho' HDS' will be installed into the plant simulator to enhance the operator S int,Irface with the system during training for all modes of operation. g 3.'3,8ystem Retir.bility
% reliability analysis of the SPDS has been performed and demonstrated that the system provides a better than 99% availability. A 30 day operational availabi-lity demonstration will be conducted to validate the reliability analysis. The system reliability is enhanced by implementation of redundant DAS CPUs, ' ' redundant host.CPUs, and an Uninterruptible Power Supply (UPS). In addition, the UPS AC supply bus is backed-up with diesel generator power.
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.W1/A505/z 24 12/22/86
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( \ .. 4.0 VERIFICATION,' VALIDATION AND QUALITY ASSURANCE 4.1 Design, Manufacturing and Installation ' '. l-The SPDS design, development, and installation were independently verified by Jqualified. personnel other than the original designers, developers. and installers.' This independent verification and validation .was required to provide assurance that a highly reliable and available system was implemented. For those1 portions of the SPDS that' interface with~ safety system signals and other Class 1E systems, a full 10CFR50 Appendix B Quality; Assurance program was implemented and applied to the design, engineering, procurement, manufacturing, testing, and installation of the applicable system components. In the STP SPDS, Class IE sensor connections and Class -1E isolation devices are fully qualified to meet.10CFR50 Appendix B requirements. Verification 'and validation of the installed SPDS has been conducted by the startup group during the pre-operational test phase as defined in the Verifi-cation and Validation Plan (refer to Appendix B). 4.2 Verification and Validation Plan The Verification and _ Validation (V&V) Prograin standardized in NSAC/39 "Verifi-
. cation and Validation for Safety Parameter Display System" was used by the SPDS fM - vendor in developing the specific V&V plan for the STP SPDS. A copy of the plan
.]. is submitted as Appendix B to this report.
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APPENDIX A [.-
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f COMPUTER CRT GRAPHIC DISPLAY DESIGN GUIDELINES i
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's' APPENDIX A COMPUTER CRT GRAPHIC DISPLAY DESIGN GUIDELINES l t TABLE OF CONTENTS ~
SECTION TITLE PAGE INTRODUCTION A-il A.1 - CRT DISPLAY CHARACTERISTICS A-1 A.2 SYMBOLS AND CHARACTERS A-3 A.3. '
.0PE.tATOR-DISPLAY RELATIONSHIP A-5
'A.4 DATA PRESENTATION FORMAT A-7 A.5 SCREEN LAYOUT ~AND STRUCTURING A-10 p
~ A.6 ~ MESSAGES A-12 A.7- GRAPHIC CODING AND HIGHLIGHTING A-13 7-g A-16
- V_. - A.8 MULTIPLE-PAGE CONSIDERATIONS
, A.9' DISPLAY DESIGN STANDARDS FOR SPECIFIC COMPUTER SYSTEMS A-17 A.10 STANDARD SYMBOLS FOR COMPUTER GRAPHIC DISPLAYS - A-34 , s O A-i 8482c/0325c
+
4
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I
'~C INTRODUCTION This appendix describes the criteria followed in developing and implementing
' the South Texas Project (STP) computer CRT displays. Sections A.1 through A.8 of this criteria refer to NUREG-0700 guidelines and the STP Control Room
- Design Review (CRDR). Criteria Report (Appendix Q) used to develop the STP CRT
~ displays. Sections A.9 and A.10 describe the criteria used for the design of the CRT graphic displays in the Plant Computer (PC) System and in the Emergency Response Facilities Data Acquisition and Display System (ERFDADS).
/
A U l A-li I 8482c/0325c
. .,---. _ . . - - ~ . - - - - - - - . - - .- - ---...-- - -- .....- -. . - . . . - - . _ . . .-
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A.1 CRT DISPLAY CHARACTERISTICS l
'(Ref. NUREG-0700, Sec. 6.7.2.1)
' Most contemporary process computer systems include one or more CRTs. These CRTs comprise the' principal interface between computer output and control room operators. It is therefore'important that the characteristics of the CRT displays. optimize the information transfer from the computer to the operator.
.The quality'of the displayed image must be consistent with operator needs.
The following criteria shall be used to ensure image quality: A.. Readability - All characters, both alphanumeric and graphic, shall be easily readable by the operator under all control room lighting conditions.
.B. Reflected Glare - CRT screens shall be installed to minimize or eliminate glare at-normal operator viewing angles.
<g
\s_ , C. Screen Luminance
- 1. -Ambient illumination shall contribute no more than 25 percent to screen luminance.
~ 2. When the CRT employs dark characters on a light background, the screen background luminance shall be between 23 foot-Lamberte (minimum) and 46 foot-Lamberts (preferred).
- 3. When the CRT employs light characters on a dark background,
.the character luminance shall be between 23 foot-Lamberts (minimum) and 46 foot-Lamberts (preferred).
D. Luminance Contrast Contrast between the characters and the background shall be 15:1
-s (minimum) and 20:1 (preferred).
l - 8482c/0325c A-1
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. Geometric Distortion - No point on the CRT viewing area shall be
'.c E.
-displaced _by more than 5 percent of the picture height from its correct position.
F. Resolution 1.- Alphanumeric ~CRTs shall have a minimum of 20 resolution elements per inch.
- 2. CRTs for displaying complex symbols and graphic detail
-shall have a minimum'of 100 resolution elements per inch.
+ 3. Complex symbols which must be distinguished from other complex shapes shall have a minimum of 10 resolution elements for the longest dimensions of the symbol.
- ~s 4 Alphanumeric characters shall have a minimum of 10
-/ i As _,) resolution. elements per character height.
G.. Regeneration Rate The regeneration rate for a particular CRT display shall be above the critical frequency at fusion so that the occurrence of
~
' disturbing flicker is not perceptible.
'H. CRT Display Controls
- 1. Brightness, concrast and color shall be adjustable by the
-operator.
- 2. Adjustment controls shall conform to the appropriate criteria for Controls in Section 6.2 of the CRDR Criteria Report.
v. 8482c/0325c A-2 (- I . - - _ . _ . . . _ _.____ _ .__._ _ _ .._ _.. _ _ , _ , _ _ _ _ _ _ , , , , _ , , _ , _ ___
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[L 9 /E A.21 SYMBOLS AND~ CHARACTERS
'(Ref. NUREG-0700,- Sec. 6.7.2.2)
~ Visual angles are the vertical angles subtended at the eye by a viewed object, symbol, or character. This angle, expressed in minutes of arc, decreases in proport'ionLto the operator's distance fron'the CRT. This distance varies considerably because of.the operator's movement'within the control room. The human eye can distinguish symbols and characters at visual angles of 5 minutes of arc-under' ideal conditions.- However, because operational environments are
'not ideal, more stringent criteria than the above have been applied.
Following is s list of such criteria for CRT symbol / character variables: A. Symbol' Size - Complex symbols that must be distinguished shall ,
. subtend a visual angle of at least 20 minutes of arc.
B._ Alphanumeric Character Size
~ l, '\ '
As ,/ 1. . Alphanumeric characters shall subtend a visual angle of not less than 12 minutes of are for the required viewing distance.
- 2. . Alphanumeric characters shall be upper-case letters.
C. Character Width-to-Height Ratio - The width-to-height ratio for alphanumeric characters shall be between 3:5 and 1:1. D. Stroke Width-to-Character Height Ratio - Stroke width-to-character height ratio shall be between 3:5 and 1:10.
-E. Graphics - Graphic lines shall contain a minimum of 50 resolution elements per inch to ensure the illusion of continuity among these elements.
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. s/- 8482c/0325c A-3
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' F. Character and Symbol Separation z't >
- 1. Horizantal separation between characters or symbols shall
-be~between 10 percent and 65 percent of the symbol height.
, 2.' Separation shall not'be less than 25 percent of character or symbol height when any of the following degraded conditions are present:
- a. Character or symbol width is less than 85 percent of height
- b. Character or symbol luminance is less than 12 foot-Lamberts
- c. Luminance contrast is less than 88 percent
;m
_,) d. CRT screen location is greater than 35* to either side of the operator's straight-ahead line-of-sight
- e. Visual angle subtended by symbol height is less than 15 minutes of are
- f. Visual angle subtended by character height is less than 12 minutes of are
. G. Character Style (Font)
- 1. Simple character fonts shall be used (no serifs, variable stroke widths, slanting, etc.). ,
- 2. When dot-matrix characters are used, 7x9 dot matrix shall be used in preference to 5x7 dot-matrix.
'N 8482c/0325c A-4
m: . i Q1 :. Jr
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'--/' 3. Character styles such as Lincoln / Mitre or Leroy shall be
-used.
,, A.3 ' OPERATOR - DISPLAY RELATIONSHIP
.(Ref. NUREG-0700, Section_6.7.2.3)
CRTs may.be either (1) fixed position mounted in a -seated operator console,
-(2) fixed position mounted in a vertical standup panel, or (3) rotetable or moveable mounted on a stand or desktop. The following criteria will be ;k considered regardless of the type of CRT. installation and applied as nccessary:
JA. Viewing distance shall be at least 18 inches.
> B. 'The minimum angle betwean the operator's actual line-of-sight (as measured from the operator's normal work location) and the plane of the display screen shall be 45' or greater in either the horizontal or vertical direction.
7-~ N~- C. Screen Location, Seated Operators
- 1. CRT displays requiring frequent or centinuous monitoring, g or which display critical (e.g. alarm) information, shall
" 1be located within the following limits as measured from the normal operator work station:
- a. Horizontal Limits - Not more than 35' to either side of the operator's straight-ahead LOS.
- b. Vertical Limits - Not more than 20' above and 40*
below the operator's horizontal LOS. i
'{ n 8482c/0325c A-5
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- 2. ' CRTs not requiring frequest or continuous monitoring, and which do not display critical (e.g. alarm) information, !
shall be located within the following limits as measured from norac1 work stations permitting full head and eye i
. rotation:
.a. Horizontal Limits - Not more than 95* to either side of the operator's straight-ahead LOS.
- b. Vertical Limits - Not more than 70* above and 90*
below the operator's h'orizontal LOS. D. Screen Location, Standing Operators 1.- CRT displays requiring frequent or continuous monitoring, or which display critical (e.g. alarm) information, shall
.be located within the following limits as measured from I -~s\
\_/
s normal operator work locations in the control room:
- a. Horizontal Limits - Not more than 35* to either side of the operator's straight-ahead LOS.
- b. Vertical Limits - Not more than 35* above and 25' .
below the operator's horizontal LOS. 2 CRTs not requiring frequent or continuous monitoring, and which do not display critical (e.g. alarm) information, shall be located within the following limits as measured from normal work locations in the control room permitting full head and eye rotation:
- a. Horizontal Limits - Not more than 95* to either side of the operator's straight-ahead LOS.
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U 8482c/0325c A-6 m _ _ __. _ _ _ _.__ _.__. . . _ . _ _ _ . _ _ _ . __.
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- b. Vertical Limits - Not more than 85* above and 90' below the operator's horizontal LOS.
E. When CRTs are mounted in consoles, the console configuration, dimensions, and type of use shall conform to the criteria that apply to work station design. These criteria are given in the CRDR Criteria Report, Appendix A. F. All-data and messages shall be within the unobstructed view of an operator at the normal work station. A.4 DATA PRESENTATION FORMAT (Ref. NUREG-0700, Section 6.7.2.4) The format used in presenting CRT data shall correspond to the following criteria: 7x.
~\,,) .s A. Usability of Data
- 1. Data shall be presented in a readily usable format.
2.- Operators shall not be required to transpose, compute, interpolate, or mentally translate displayed data into other numerical units or bases. B. Illustratic r shall be used whenever possible to supplement text. C. Character Grouping 1.. Characters shall be grouped in blocks of three to four when five or more digits and/or non-text alphanumeries are displayed and no natural organization exist s.
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8482c/0325c A-7
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S/ 2. . Groups shall be separated by a minimum of one blank
. character space.'
D. : Elements in a data field shall.be displayed in logical order (e.g.-chronological).
.E. Presentations of Identical Data
.l. . Data shall.be presented in the way the information will be used by the operator.
- 2. Witnin the limits of (1) above, identical data in dif ferent presentations shall be displayed in a consistent, standardized manner.
F. Menu Designators
,m jg_, : 1.- Numbers shall normally be used as designators when listing selectable items. If the listing of selectable items contains numbers, alphabetic characters should be used to prevent confusion.
- 2. Numerical designators shall start with the number "1" or "101" (not zero).
- 3. If used, alphabetic designators shall start with the letter "A".
G. Lists
- l. Lists shall be vertically aligned and left-justified.
- 2. Indentation shall be used for subclassifications.
N 8482c/0325c A-8 f
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7 s.
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' 0' M ' H. Tables and Graphs - Quantitative data to be scanned and compared
' shall be presented.in either tabular or graphic form.
l I.. Hyphenation - Hyphenation will be minimized.
~
J. 'Al'ignment .
. 1. - When presented in' tabular form,~ alphanumeric data shall be left-justified.-
2.. When presented in tabular. form, numeric data shall be right-justified with decimal points aligned. K.- Periods shall be placed after item selection designators and at
. the end of a-sentence.
<%\ L.. The following standa'rdized fields will be used:
. (Q 1.. Telephone Number: (914) 555-1212
- 2. . Time: HH:MM:SS, HH:MM, MM:SS:(.S)
- 3. Date: DD:MMM:YY M. ' Data Group Labeling
- 1. Descriptive titles shall be used for each individual data group or message.
- 2. Unique characteristics of the content of the data group or message shall be reflected in the selection of labels.
.N.- Labels shall be located in a consistent manner either above or to the left of the data group or message they describe.
8482c/0325c A-9
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'-- 0.. Labels shall be horizontally '(not vertically) oriented.
P.. Label Highlighting
'l.: f Labels shall be highlighted or otherwise accentuated to facilitate operator scanning and recognition.
j
.2. [Thetechnique'usedtohighlightlabelsshallbeeasily Ldistinguished from that used to highlight emergency and other critical messages.
Q. 'When presenting a list of operator options, the label shall reflect the question or choices being posed to the operator. A.5 SCREEN LAYOUT AND STRUCTURING: q L(Ref. NUREG-0700, Section 6.7.2.5)
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'( ,) Screen layouts and data structure presented on CRTs shall minimize the probability of operator error. The following criteria shall be used to achieve this goal:
-A.- ' Displayed data shall be organized in a logical, consistent manner, and shall reflect some obvious and inherent quality of
- the data groups (e.g. hierarchical, sequential, or mimic).
Plant system displays (P&ID type) shall emulate the main control panels. Where the main control panels do not indicate an obvious directional structure, the layout shall be from left to right and top to bottom. B. Consistent physical locations shall be used for specific data groups. C. Organization and separation of information subgroups shall be made apparent through the use of blank spaces, lines, or some v
\ other form of visible demarcation.
8482c/0325c A-10
- )*
D. Lists of options shall be organized according to the probability jf of selection of each item (high selection probability items fpresented first). E. Non-option-lists of equal probability options shall be presented in alphabetical or numerical order. F.- At least one bir7k line shall be used to separate paragraphs in continuous text. G. A't least one blank space shall be used to separate selection designators from text designators. H. When multiple pages are used to present data, each page shall display its page number and shall provide an indication of any additional pages in its group which contain data. s,/ I. Items contained in a numbered list and described on " continued" P pages shall be numbered relative to the first number on the first page of the list. J. Operator instructions shall precede the list of options where possible, or shpil be provided on the list of menu options to facilitate operator interface. K. Urgant messages requiring immediate operator response shall be:
- 1. Highlighted to attract attention.
, 2. Displayed in the same location.
L. In systems where selection is made by use of a cursor, formats shall be organized to minimize positioning movements of the cursor.
- 1. "(_- . f'^~)%
8482c/0325c A-11
-ee.-___ l M. The amount of information-bearing activated screen area shall ! not exceed 25% of the total screen area (excluding demarcation lines used to separate data groups).
, K. Trend plot scales shall be consistent with the intended functional use of the data.
A.6 MESSAGES (Ref. NU2EG-0700, Section 6.7.2.6) Messages (whether prompts, error messages, or systems feedback) shall conform to the following criteria: A. Messages shall be concise and provide the information required to complete a specific action or decision sequence. B. Information contained in messages shall be necessary, complete, I and readily usable. x , C. Prompts shall be used when the operator may need direction or guidance to initiate or complete an action or sequence of actions. D. Prompts shall contain clear and specific cues and instructions which are relevant to the action to be taken. E. Directions shall be in the sequence to be used by the operator. F. Error messages shall be included for any erroneous or invalid input. G. Error messages shall contain instructions regarding required corrective action.
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8482c/0325c A-12
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i A H. Capability shall be provided for individual error correction }l without affecting adjacent valid entries. ff _ I. Feedback messages shall convey system status changes to the j operator.
-= _
J. When a displayed item is selected as an option or input to a $w system, the item shall be highlighted, or otherwise positively E identified, to indicate acknowledgement by the systen. i K. When execution.of system functions requires the operator to ; stand by, such as when the computer is searching for requested ff data, periodic feedback shall be provided the operator to indicate normal system operation and the reason for delay. _= L L. When a process or sequence is completed by the system, positive j s indication shall be provided concerning the outcome of the Q d @ process and requirements for subsequent operator actions. :q 3_ M. System diagnostic, error and response messages may be displayed j either at the top or the bottom of the CRT screen. The CRT j location of these nersages shall be consistent within each computer display system. $ 4 1 A.7 GRAPHIC CODING AND HIGHLIGHTING ? (Ref. NUREG-0700, Section 6.7.2.7) Z The following criteria shall be applied: ? 3 a A. Highlighting shall be used to attract attention to displayed data that are important to actions and decisions. a - 3 7" B. Consistent Approach
- 1. Highlighting methods shall be consistent among applications.
f I 5 5-8482c/0325c A-13 j 2 5
I [, 1 l 6 2 Highlighting methods shall be different for normal and j. abnormal conditions. C.- When contrast enhancement is used for highlighting, not more than two (preferable) brightness levels shall be used in a single presentation. D. Blinking of a symbol or message shall be used for ar.orgency (or other critical) conditions only. E. Blink Rates
- 1. No more than two blink rates shall be used.
- 2. For a single blink rate, the rate shall be 2-3 blinks per second with a minimum of 50 maec "on" time between blinks.
- 3. When two blink rates are used, the fast blink shall approximate four per second and the slow rate shall approximate one per second, the on/off ratio shall approximate 50%, and the higher rate shall apply to the most critical infornation.
F. Image reversal (e.g., dark characters on a light background) shall be used primarily for dense data fields, such as a word or phrase in a paragraph of text, or a set of characters in a table of data. G. Graphic coding (e.g., boxes, symbols, underlining) shall be used to present standard qualitative information or to draw attention to a particular portion of the display. H. Graphic codes shall have the'same meaning in all applications.
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8482c/0325c A-14
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k^ ' -I. When geometric shape (symbol) coding is used, the symbols shall
' vary widely in shape.
, 9. .
-J.. Number of Symbols-
=. i 1. The number of display symbols used for coding shall not exceed ~the operator's ability to discriminate among them.
This will range from 6-20 symbols per display depending on the display conditions (screen fill). 2 .' Other highlighting and graphic techniques (e.g., color) shall be used as needed to display different states or - qualities of a basic symbol. K. 'Use of Color
.,f-A The following criteria shall be applied to the use of color for a\j CRT display presentations:
T
~
.l. CRT colors shall be consistent in use and meaning with all other color codes in the control room.
- 2. Once colors are assigned a specific use or meaning, no other color shall be used for the same purpose.
L. Color Meanings - Where possible, color meanings shall equate with the commonly understood meanings of those colors. Following are the specific meanings for three colors - red, green, and yellow / amber. However other meanings of these colors which are commonly understood for control room use are also acceptable. 1; O 3-i V 8482c/0325c A-15 a
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Red - Unsafe, danger, immediate-action required, critical parameter value out of tolerance.
- 2. _ Green - Safe, no action required, parameter value within tolerance.-
- 3. Yellow / amber - Hazard, potentially unsafe, caution, attention, parameter value marginal.
See Section A.9 for other color meanings. M.. Red-Green Combinations 1.. Whenever possible, red and green colors shall not be used in combination. s 2 Use of red symbols on a green background shall be avoided. V.
.A.8 MULTIPLE-PAGE CONSIDERATIONS (Ref. NUREG-0700, Section 6.7.2.8)
When it-is necessary to include multiple pages, or when scrolling, panning, and zooming of a single page is anticipated, the following criteria will be
. applied:
A. All data relevant to a specific operator entry shall be displayed on a single page, and requirements for operator memory shall be minimized. B. Location References
- 1. When scrolling or panning is required, location references shall be provided in the viewable portion of the f rame.
O O 8482c/0325c A-16
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- 2. Sectional coordinates shall be'used when large schematics
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must be panned or magnified. t
=C. -Afcapa'bility shall exist for controlling the amount, format, and complexity of information displayed by'the system.
(D. .If the message is a variable option list, common elements shall
- maintain their physical relationship to other recurring elements.
A.9_ DISPLAY DESIGN STANDARDS FOR SPECIFIC COMPUTER SYSTEMS The following criteria shall be used for the design of the graphic displays in
.the Plant Computer and the ERFDADS:
A.- Standard-abbreviations for display labeling shall be in accordance with'the STP CRDR Criteria Report, Appendix L.
,n B._ Symbol Definition
- 1. Symbols used in CRT graphic ~ displays shall be in accordance with Section A.10, 2 Symbol' shape shall be consistent with the standards in Section A.10; symbol size may vary depending on the specific display requirements.
- 3. Bar charts and/or digital displays shall be used for variable analog parameters. The specific application shall be on a case-by-case basis. The nominal width for bars shall be 1/4-inch.
s 8482c/0325c A-17
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mw y ~g [ l10 i. , vAq- 4,. : Symbol Behavior a .' Valve status shall be a red-outlined symbol for an open valve,' and.a sol!1 green shaded symbol for a
- 4. - closad valve. .(In addition, for the Plant Computer only, an operator-entered state of valve open shall be represented as an outlined cymbol in the cyan-dim ;
condition, and an operator-entered state of valve
' closed shall.be represented as a solid-shaded symbol in the cyan-dia condition). Valves not monitored by
, .the computer system but shown on a graphic shall be
' cyan-outlined symbol- for a normally open valve and a
' - ' ' solid-cyan shaded symbol.for a normally closed valve.
~
'b. For dynamic equipment, status shall be a red-outlined symbol for equipment running, a solid green shaded W J- . symbol for equipment not running, and a solid magenta x_, . shaded symbol for an equipment trip condition. On initiation of an equipment-related alarm, the symbol for equipment running shall change to magenta-outlined. Reset of the alarm condition shall cause the symbol to return to the run status condition.
In addition, a three character designator (OFF, RUN, TPP) inside the symbol shall be used to supplement the color representation. The color of the character
. designator shall be green for OFF, red for RUN, and magenta for TRP.
- c. Digital parameters and bar chart parameters shall be dynamic and updated at scan ratcs appropriate for
< their intended use and the process being monitored.
- p d. Dynamic textual information shall be color-coded in i .
accordance with Paragraph A.9-C. , _8482c/0325c A-18
i i J. e.. Flow lines and electrical lines shall be static in behavior. f.. Valves and equipment monitored in accordance with Regulatory Guide (RG) 1.47 (Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems) shall be shown with the descriptor "INOP", color-coded white, when in a bypass / inoperable condition.
- g. For static equipment such as condensers, deaerators, heaters, etc., the symbol shall be changed to magenta-outlined when an associated parameter is in the alarm condition (acknowledged).
- h. Dynamic behavior (i.e., color change) for bar charts
,r 'T in the alarm state shall be for the whole bar.
k-
- 1. Bar charts shall be oriented vertically for pressure, temperature, and level parameters. They shall be oriented horizontally for flow parameters. Where alarm setpoints are shown for plant variables, they shall be indicated by a tic mark located on the side of the bar chart.
'j. Bar charts shall be located to the left of the scale for vertical displays and above the scale for horizontal displays.
- k. Units labels may be located above or adjacent to scales.
8482c/0325c A-19
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Color! Coding
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The following colors shall be used for STP CRT graphic displays: Colo'r- Use Black- o Eackground Black.(Reverse). o J138 kV power line Bl'ue (Dark) o. Numeric and bar chart values for' acknowledged signal which is out of range, a signal determined
' bad by quality checking algorithms, or a signal manually removed from scan by the operator, o Numeric and bar chart values for signals which
-c have been removed from scan (Plant Computer).
o . Valve status digital input points which have been removed from scan. o 25 kV power line Blue (Dark-Blink) o Numeric values and bar chart quality characters State for unacknowledged signal which is out of range (Plant Computer). Cyan (Lt. Blue) o Labels, units, textual information, tic marks and scales of bar charts and trend graphs. o Bar charts and numeric values for analog points which have been operator-entered (Plant Computer).
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8482c/0325c A-20
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' ^/ - Color Use
/ Cyan (Lt'. Blue) 'o Valve and pump symbols whose digital status has been operator-entered (Plant Computer).
o Static symbols o Flow-lines o 345 kV power line o Normal state for equipment symbols such as tanks, heat exchangers, condensers, steam generators. White o Status words for intermediate states f-~ , o- Bypassed / Inoperable status indication (RG 1.47) d, 9) - o Bar charts and numeric values for analog points which have been operator-entered (ERFDADS). o Event-type alarm messages (ERFDADS). o Bar charts and numeric values for analog points which have been removed from alarm limit checking (Plant Computer) o 480 V Power Line Green o Safe operating status (if not defined by any other status) o Off, not in operation (pump, turbine) () o Valve closed, not open 8482c/0325c A-21
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- Color' Use t
=o Electrical breaker open (de energized) o Bar charts and numeric values within alarm limits F
o , Red. o Unsafe operating status attained o On, in operation (pump, turbine) o Valve open, not closed o Electrical breaker closed (energized) Yellow .o Approaching unsafe condition f -i o Bar charts and numeric values whose alert set-k,) point has been exceeded - condition acknowledged. o Setpoint tic mark on bar chart displays o 4.16 kV power line Yellow (Blink) o Alert state - unacknowledged (numeric values, bar chart displays on ERFDADS, and bar chart quality character on Plant Computer) Orange o 13.8 kV power line o Unsafe operating status imminent Magenta o Bar chart and numeric values whose alarm set point has been exceeded - condition acknowledged. ( o Dynamic equipment symbols in the tripped state. 8482c/0325c A-22
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Color Use o Equipment symbols with related alarms - condition acknowledged.
-Magenta (Reverse) o Alarm messages set by digital inputs.
~ Magenta (Blink) o Alarm state - unacknowledged (numeric values, bar chart displays on ERFDADS, and bar chart quality character on Plant Computer)
J o Equipment symbols with related alarms unacknowledged. Pink o Safety Function Parameter deviation bars on SPDS top level Critical Safety Function display t r~5i (ERFDADS).
\)
D. Point Quality Coding The values of process points, calculated points, and program constants have associated with them a quality function which is one of four states: good, suspect, poor, or bad. When a value whose quality is not good is displayed on the CRT (numeric or bar chart representation), the quality of that point is denoted by adding a one letter suffix after the value. The letter S is used for " Suspect", P for " Poor", and B for " Bad". Numeric values with " Good" quality have no suffix, and bars in the Plant Computer will display the letter G.
- l. Bad quality is assigned when a point is removed from scan, the sensor input is deterained to be out of range, or the quality checking algorithm determines the point to be bad.
- 2. Poor quality is assigned via the quality checking I algorithm.
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-3. ~ Suspect quality.is assigned,when a value is manually
- entered or the quality checking algorithm determines the i
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, . point to be suspect.
m t y[' y~ 4 . Good. quality-is assigned when the point is not one of the.
;;3 -conditions above.
s.$i e S, J[dd}7'- '5.. Supplemental' color coding is applicable to items 1-4 above
.. n 4- n W (See Section A.9-C).
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6.- -In the Plant Computer System, a bad point has its value set g] . __ to a string of X's followed by the B suffix. tr,b '
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V < -E. ' Alarm / Annunciation Features s sw cy v ..a a M .; .-'* 1. Functional Requirements W. .Me - 4 4 ,, N U M
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h.x [A_,/f? ;g a. Alert.the operator to'the fact that a system or
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.E process deviation exists.
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- b. -Inform the operator about the nature of the deviation r.
and the urgency of any needed action. f;k!)lL. __ t ,
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#? E -c. Guide the operator's initial response to the deviation.
, !d. Confirm whether the operator's response corrected the
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- e. Assist.the operators in monitoring the plant, but not
[h . encourage undue reliance. Quantitative and status a ^
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information shall be provided by other means, w Minimize nuisance alarms, without suppressing i- f. J+ _ necessary valid alarms. n !; 1 k
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N L2. -Annunciation Functions The following~are the specific-functions and features ' required of the computer-driven annunciation plan. n . X,,
. :a. Auditory Alert - The computer display systems shall provide outputs to drive the plant annunciation system when any specified alarm point is activated in the computer display systems.'..One output per alarm group is required and each output shall be an open contact whichclosesmomentarilE(50msecmin.)onalarm activation.
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-- s. b. Visual-Alarm - Visual alarm information shall be b ,) . presented to the operator via - computer-driven alarm and graphic display devices. The information shall i indicate the nature of the deviation. Refer to Paragraphs 3.a.1 and 3.b below for specific requirements.
- c. Operator Response Capability - Controls for operator response to annunciation functions shall be conveniently located. The following control functions are required:
^
- 1) Alarm Acknowledge - Controls shall be provided to n acknowledge visual alarms. Acknowledgement shall Y
!. turn off the flashing alarm symbols / messages and cause them to continue with a steady display until reset. fd 8482c/0325c A-25 L
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- 2) -Alarm Reset - Controls'shall be provided to reset F
s alarms af ter they have returned' to normal. - The
-controls shall remove the visual alarm display
. flag, indicating clearance.
1
- d. . Ring Back - When a previously abnormal condition l returns to normal it shall be accompanied by flashing
- of the' visual indication to provide feedback on the corrective action. The flashing shall terminate after
.the alarm is reset.
+
3.
, b', 1 - e.. Transient Alarm Detection - An alarm shall remain "E' ' . displayed until acknowledged and reset by the operator even if it has already returned to normal. This will
-allow deviations to be detected which are only momentarily in the alarm-state. Further verification Eb of transient alarms shall be available on the printed alarm log.
p (,~/ L . t,y . f. Alarm List Paging - Computer-based alarm lists shall
- g. ,
tunne the capability to display sequential pages of the w
> alarm list by depression of no more than a single A.-
pushbutton.
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g.R 3. Computer Driven Alarm Displays
- a. Plant Computer - Dedicated Alarm CRT Displays
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- 1) , When a point goes into alarm, the alarm CRT display shall show a line for that point. The text shall be color-coded magenta (Reverse Video) and contain the following information:
is [k- h 75, ' ,-y 7-~ 4_.< . l848 c/0325c A-26 m
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- , o: Time of alarm
;A_,[{ o Point ID o Point description o 1 Deviation or alarm type (e.g., Alert, Alarm, Bypass, etc.)
o Current value status (Analog Points) o Alarm limit /setpoint (Analog' Points) o Engineering Units for the point (Analog Points only)
>The text showing the alarm state shall blink until acknowledged, at which time it shall change
~
to steady-state magenta. The first alarm message is written on the first ,. line (top) of page 1. Each successive alarm . message shall be written on the first line, displacing the older alarm messages downward on (e x/~ s.
). the page. When page 1 is full, then the oldest alarm on page 1 (bottom line) shall be displaced g to the first line (top).on page 2. This sequence continues until all pages are full.
When an alarm point returns to normal, a return-to-normal message, blinking in green, will 4 be written in place of the alarm message. The ALARM ACK pushbutton will clear the blinking return-to-normal message from the screen, leaving a blank line. The display heading for alarm CRTs shall include the following: o Current time and date I l l r (s_l) - i ! 8482c/0325c A-27 l
,_ _ . . - - _ , , . . _ . . , . , _ _ . - _ _ , . . . . . . . . _ . - _ , _ . . . . , , . . - . . . _ - , , . , . _ , ~ . _ _ . . . . . , , , . _ . . ._4_ _ , _ , . _ . - - . , . . . _ _ _
in G;; bfL . : M-1 l
._f3 o ~ Alarm page currently displayed o . Alarm pages with points currently in alarm
.(acknowledged and unacknowledged) o' Overflow message field y . Paging through the alarm displays shall be available via a dedicated pushbutton. Access to
-a specific alarm page identified by number in the
. display heading, shall be available using the cursor / execute pushbuttons.
- 2) Alarm CRT Utilization o Discrete inputs which are re-transmitted from the plant annunciator first-out windows l
shall not be directed to any alarm CRT.
" w)':[ m ... They shall be output to the alarm typer only, for time-tagging.
o Discrete inputs which are single inputs to the plant annunciator and are re-transmitted to the plant computer shall not be directed r to any alarm CRT. They shall be output to the alarm typer only, for time-tagging. o Discrete inputs to multiple input windows in the plant annunciator which are re-transmitted to the plant computer shall be assigned to an alarm CRT. I-
%.)
l ' l L 8482c/0325c A-28 l 1
m s ~ D
~
s 9D _ .fx ,n,
. , h .3) ' Alarm CRT Assignment a ul' i{}{; ? o Alarm CRT No. 1, which is located on ZCP-004 shall be used to display alarms associated ;
Oie 'with' control' boards-ZCP-001 through
' 'ZCP-005. Alarm CRT No. 2, which is located on ZCP-008 shall be used to display alarms associated with control boards ZCP-006 thrcugh ZCP-010. Alarm CRT No. 3 is located
' l~ . in the operators console (ZCC-020). o Multiple input alarms which are-re-transmitted from the plant annunciator shall be assigned to the alarm CRT associated with the control board on which that annunciator lampbox is located. 1]%} . o ' Alarm conditions for which the operator can
-U- ~
take corrective action at the control board shall be assigned to the alarm CRT associated with that control board.
~
o All other alarms shall be assigned to Alarm CRT No. 3.
- b. ERFDADS - Dedicated Alarm CRT Displays 5
When a point goes into alarm, the alarm CRT shall show a line for that point, color coded as follows: Magenta for Level 1 Alarm (High) Yellow for Level 2 Alarm (Alert) + White for Level 3 Alarm (Event) O
, 8482c/0325c A-29
e
$' w
, >~
The alarm line will display: l
\
~ au
~
\
o Time of Alarm 'l { o Point I.D.- l l
- o. Point Description I o- . Deviation or Alarm Type (e.g., High, Lo-Lo,
. INOP, etc.)
o' Current Value Status o Alarm Limit /Setpoint o Engineering Units for the Point (Analog Point Only) The text showing the alarm state shall blink until
~ acknowledged either by operator or automatically.
-depending on the zone assignment (see paragraph 3.c below), at which time it shall change into steady-state.
,/~w
! E
The first alarm massage is written on the first line (top) of page 1 of the zone to which that alarm belongs. Each successive alarm message of that zone shall be written on the first line, displacing the older alarm messages downward on the page. When page 1 is full, then the oldest alarm on page 1 (bottom line) shall be displaced to the first line (top) on page 2. This sequence shall continue until all pages of the zone are full. The alarms displayed on the alarm Summary Screen shall be in reverse chronological e
order. When an alarm point returns to normal, a return to normal message will be written in place of the alarm message. This will be in fast blink mode and when acknowledged, will change into a slow blink mode and (I upon hitting the reset key, this message will disappear. 8482c/0325c A-30
.. . _ . _ . ~.- _._._- , _ . . , _ . . _ - - _ _ _ _ _ - _ . . _ _ _ - _ . _ . . . _ _ _ . _ _ . _ _ . _ _ _ . .. . _ ,
'n c'- 'The: display heading for alarm CRTs shall include the 1 following:
o Current time and date
- o. Alarm zone and page number currently -
if displayetd. o A message "More alarms on next page" if there are more alarms on the next page of that zone, or '"End of ASD for zone",if there are no more alarms in that zone. Paging through the alarm displays shall be available through page plus and page minus keys. Page right and page left keys shall allow accessing the next zone number or previous zone number, respectively.
- c. ERFDADS Computer - Alarm Zones - The alarm points in 4
). ERFDADS shall be assigned to one of eleven zones. A zone designation consists of two characters; the first one shall indicate the group and the second character shall represent the CRT and/or alarm horn location.
- 1) The " Priority" alarms shall be assigned to group 1. These contain the following alarms:
a) Individual points associated with multiple input windows in the plant annunciator, b) QDPS Priority 2 alarms which include: o Emergency Core Cooling System Sumps o Shutdown Margin Monitor o Steam Generator Water Level Compensation System, Temperature
'[
' Averaging System, Qualified Control System, and Qualified Display Processing System Failure.
8482c/0325c A-31
er .r
~
c$$Nt qu l D-These alarms are printed.on the alarm typer
. and do not need to be acknowledged within ERFDADS. After a preset time, these alarms
'are acknowledged automatically by the-computer.
.The~" Normal" alarms shall be assigned to
~
2) t group 2. These contain the following alarms: o -Database generated alarms that do not appear on any other alarm device. f o All QDPS alarms (priority three) except y those listed in paragraph 3.c.1 above. o Meteorological System alarms
~;m .
( ) These alarms are printed on the alarm typer and
~~
must be manually acknowledged within ERFDADS.
- 3) The " Historical" alarms shall be assigned to group 3. These contain the following alarms:
o ESF status monitoring alarms o Alarms which have dedicated windows in the annunciator o Database generated alarms which appear on other alarm devices. These alarms are printed on the alarm typer and do not require manual acknowledgement within ERFDADS. O O 8432c/0325c A-32
r ;
~
l t iC1 _ _,/ 4) The second character of the alarm zone shall
. determine the location of the CRT where the alarm '
- will normally appear, and the horn where the
. alarm will sound.
2- CRT located in Main Control Panel ZCP-002
;g / 4 CRT located in Main Control Panel ZCP-004 5 C2T located in Main Control Panel ZCP-005 C CRT located in Operator's Console A CRT located in' Auxiliary Shutdown Panel The Group-3 alarms shall be displayed on the CRT located in the Operator's console.
The assignment of alarm zones for group 2 alarms will require the operator to acknowledge and silence the alarm condition from a specific p fs
! ) keyboard location. For example, alarms in zone 8 v
can only be acknowledged from the function keyboard associated with Main Control Panel ZCP-005, t Q o 8482c/0325c A-33 l
i
., m
- ! )
'w/
-A.10- STANDARD SYMBOLS FOR COMPUTER GRAPHIC DISPLAYS The following symbols shall be used on computer graph displays:
A. The reactor vessel elevation outline used as a level reference for the core elevation: i
% /
I rh A,/ )
\ /
B. Reactor core map outline: I I _J L. O, 7 I I I 8482c/0325c A-34
Z
,D . .
- v. . Steam generator:
C.
\- / .
U D. Pressurized vessels: A ,/ ( 3 L J 9 Vertical Horizontal l i O 8482c/0325c A-35
s E. Heat exchanger: F. Feedwater heater: h
)
O l C. E'esting or cooling coils: l l l O 8482c/0325c A-36
. - - - . _ . - - - - . . - . . - , . - . . - . ~ . _ _ ..
s H. Double flow turbine:
/ \ ,
I. Single flow turbine: O J. Generator: I i 8482c/0325c A-37 _ _ _ _ _ , _ . _ . _ . _ . _ ~ . _ . . . _ _ _ _ _ _ _ . _ _ _ _ . _ . ~ _ _ _ _ - . _ _ _ _ _ _ __
's K. Generator auxiliaries:
L. Filter: F O M. Centrifugal pump: u 1 l l l O 8482c/0325c A-38
( .: V N. Positive displacement pump: P. Vertical pump: RU O es Q. Reactor coolant pumps i l memu 65 i O 8482c/0325c A-39
fm
\
v) R. Fan: tun C3 S. Valves: 2-way 4-way Relief T. Screen: 0 0 0 8482c/0325e A-40
-- - - _ _ . - . . - - - - - - - - - . .... ... - . . . - . . . . - ~
f3 i )
\d U. Damper:
V. Circuit breaker: M d O W. Transformer: WW AAAA l l l O 8482c/0325c A-41 i
= .
^6 ~t i
t APPENDIX B
~
VERIFICATION AND VALIDATION PIAN l 1 l I i l i I l l 1 L 8482c/0325c
e . N . . VERIFICATION AND VALIDATION PLAN
- ~ FOR BECHTEL ENERGY CORPORATION AGENT FOR HOUSTON LIGHTING AND POWER CORPORATION EMERGENCY RESPONSE FACILITY
, DATA ACQUISITION AND DISPLAY SYSTEM BID REQUEST NO. 14926-4331/8331 PREPARED BY ENERGY INCORPORAT:D P.O. BOX 736 IDAHO FALLS, IDAHO 83402 E
(
/IA:. N1 FYl u~ unhy y 4W C4yl)Y -
V8V COMMITTEE CHAIRMAN El STP PROJECT MANAGER NOTE: ALL REVISIONS ARE FLAGGED WITH THE SYMBOL b IN THE RIGHT MA WHERE N IS THE NUMBER OF THE REVISION. Rev. 0 - Issued for Use - 6/11/83 Rev.1 - Incorporated Client Coments - 8/15/84 Rev. 2 - Incorporated Ci tent Coments - 1/18/85 khr M 8/0:g' lj'f// /
//8,,lW
%\i Illb/64 Rev. 3 - Incorporated Program Changes - 11/24/86 'M Y^ '"
205-3 -- STP-201 [@' {E()c.!A.20d
. , q 'y01.Yn m ute O Air __ . := _ _ _ . __
m i a .. - :c - i i 7 c4 o 1 . L /. TA8LE OF CONTENTS ~ -
.' ~
SECTION TITLE , PAGE -
~
1.0 -0VERVIEW............................................................ 1 2.0 V4V PROGRAM REQUIREMENTS............................................ 7
. :2.1 Program Contro1................................................ 7
?
. -2.1.1 Organization............................................
7 2.1.2 Sc he du l e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 2.1.3 Documentation, Files, Distribution, and Approval .. ...... 8
-2.1.4 Work Control and Work Breakdown Structure. . . . . . . . . . . . . . 13 l gjg 2.2 Appl icabl e Codes and Sta ndards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 2.3 - Di sposi ti on of Resul ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 3.0 VERIFICATION AND VALIDATION (V4V) PROGRAM ELEMENTS................. 16
-3.1 System Requi rements Rev1 ew. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16
,m
( ') 3.1.1 Approach and 0bjectives................................ 16
\"' 3.1.2 Res pon s i b i l i ti e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 3.1.3 Resol ution of De ficiencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 3.1.4 System Requi rements Revi ew Documentation . . . . . . . . . . . . . . . 18 3.2 Des i gn Rev i ew . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 3.2.1 Approach and Objecti ves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 3.2.2 Responsibilities....................................... 20 3.2.3 Resol u ti on of Defici encies. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 3.2.4 Desi gn Revi ew Documentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 3.3 Va l i da ti on Te s ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . . . 21 3.3.1 Approach and Objectives................................ 21 3.3.2 Responsibilities....................................... 22 3.3.3 Resolution of Deficiencies. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 3.3.4 Val i dati on Test Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 3.3.5 Unit-Specific Validation Test Reports.................. 24 2h STP-201 Page i of fii 205-3 ...
D 9
l
, ~ . -
.- "TA8LEOFCONTiRTS(Continued) l
, ~
SkCTION -
~
~ TITLE --
PAGE 3.4 Fi el d Ve ri fic a tion Tes ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4 3.4.1 Approach and Objectives................................ 24 3.4.2 Res pons i b ( 1 1 ti e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5 3.4.3 Resol ution of Defici enci es. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25
'3.4.4 Fiel d Veri fication Test Procedure. . . . . . . . . . . . . . . . . . . . . . 26 3.4.5 Unit-Specific Field Verification Test Reports. .... .. . .. 26 A 3.5 V4V Summa ry Repo rt. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 7 3.5.1 Overview of V4V Plan, Documentation, and Ac t i v i ti es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 3.5.2 Phase 1 System Requirements Revi ew. . . . . . . . . . . . . . . . . . . . . 28 3.5.3 Phase 1 Design Review.................................. 28 3.5.4 V al i da ti on Tests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 lbh 3.5.5 Fi el d Veri fic atio n Tes ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 .<~.
(, \ 3.5.6 Summa ry and Concl us io ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 y ,) 4.0 A C R0 NY MS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3 ljji i r O .. . .
~
STP-201 Page 11 of 111 205-3
m-5 -g. ., N t .
'~
LIST OF FIGURES
' FIGURE: TITLE , PAGE 1-1 Phase 1 V4V Pl an El ements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1-2 Phase 2 Unit-Speci fic V4V Plan Elements. . . . . . . . . . . . . . . . . . . . . . . . 4 1-3 Phase 2 Uni t-Speci fic V4V Pl an El ements . . . . . . . . . . . . . . . . . . . . . . . . 5 3-1 Example of Compl i ance Matri x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 d 3 3-2 Design Review Checklist....................................... 31 3-3 Design Review Report.......................................... 33 3-4 Desi gn Review Reconcil i ati on Report. . . . . . . . . . . . . . . . . . . . . . . . . . . 36
~.3-5 Sof tware Speci ficati on Revi ew. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38 3-6 So f twa re De s i gn Re v 1 ew . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 9 3-7 Software Program Review....................................... 40 3-8 Software Acceptance Test Review............................... 41 3-9 Sof tware Revi ew Report, Continuation Page. . . . . . . . . . . . . . . . . . . . . 42
., (tjm)
\ .
STP-201 Page 111 of 111 l 205-3 e---ww W +w e- r we v -
m 1 _j 1.0 OVERVIEW -- -
~~
The 5outh Texas Project (STP) Emergency Response Facility Data Acquisition and Display System (ERFDADS) verification and validation plan (STP V8V plan) is a program to provide the high reliability required by NUREG 0696 for emergency response facilities. It provides a fully independent Vav program along the guidelines of NSAC-39 for the STP ERFDADS. This V8V pro-gram will meet, as minimum requirements, the guidelines of EPRI Document
)lSAC-39, " Verification and Validation for Safety Parameter Display Systems" with the exception that the buyer has agreed to perform all verification and validation activities for the field verification tests. These require-
- ments will apply to both software and hardware.
Verification in this sense is a combination of activities with emphasis on review of requirements and design documentation. The requirements review is intended to ensure that the right functions are being correctly and com-pletely addressed. The design review ensures that the system design cor- []- rectly fulfills the requirements. J Yalidation refers to the testing of the completed system to determine compliance to the various requirements. A validation test is an integral part of the STP V8V plan and will be conducted on the fully integrated system. It should be noted that Energy Incorporated (EI), through its normal course of doing business, employs all the elements of a good V8V program. These Q normal "in-process" VAV activities are governed by the following documents: lg (1) EI's Quality Assurance Manual (QAM), (2) E!'s Engineering Procedures Manual (EPM), (3) E!'s Engineering Standards Manual (ESM), (4) EI's Software Procedures Manual (SPM), STP-201 Page 1 of 43 2_05-3
~
.. l
! ~
V~ m ~(5) the F.I STP project Program Requirements' Document (PRD), and
' 's . ' (4) the project-specific-addenda to EI's QualitF~ Assurance Manual lThus, norme1 "in-process" V8V tasks include second level reviews, formal ld !
design reviews, documentation, inspections, and testing, performed by the ! software and hardware functional organizations. A portion of the indepen- ld
..dont V4V committee task, as defined for the EI STP project, is to ensure that both the software and hardware functional organizations perform these ;
"in-process" V4V functions in accordance with the above documents. I Section 2.0 of this document describes in detail the requirements to imple- ,
ment the STP V8V plan. Certain of these requirements, such as those relat-ing to schedules, controls, and/or facilities, are of a project nature; f.e., they are required in order to successfully implement the independent V4V plan itself. Others relate to documentation required in order to pro-f) vide the technical basis for conducting reviews, formulating test plans, and providing auditability. . Section 3.0 treats each of the major elements of the STP V4V plan indi-vidually, defining in each instance the methodology, objectives, and responsibilities of both the independent V4Y committee and the STP system - designers and integrators. The system designers and integrators are members of the hardware and software functional organizations who perform the "in-process" V8V. The STP VSV plan is divided into two phases: Phase i 1 consists of plan elements which apply to both units and Phase 2 consists of unit-specific plan elements. Figure 1-1 shows the relationship among the major elements for the Phase 1 portion of the V8V plan and Figures 1-2 [
' and 1-3 show the relationships among the major elements for the unit-specific portions of the V4V plan. Note, the Phase 1 portion is intended to apply equally to both units. Particular attention is given to both the manner in which deficiencies are resolved and how they are recorded. Each element of the VSV program will be documented in the V8V Summary Report.
~
STP-201 Page 2 of 43 i 205-3 T ean
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REPORT WILL INCLUDE BOTH UNITS 4 4 EluYER TO PERFORM ALL V & V ACTIVITIES FOR FIELD VERIFsCATION/ SITE DEMONSTRATION TESTS i I 8 FIGURE l-2 PHASE 2 UNIT-SPECIFIC V SV PLAN ELEMENT
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SUMMARY
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) REPORT i e m, 6
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REPORT WILL INCLUDE SOTH UNITS ,
*
- BUYER TO PERFORM ALL V S V ACTIVITIES FOR FIELD VERIFICATION / SITE DEMONSTRATION TESTS h FIGURE 1-3 PHASE 2 UNIT-SPECIFIC VSV PLAN ELEMENT 4
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t-i M The V8V' Summary Report will contain both the Phase 1 and the Phase-2 or b , J ~ ' icitt-specific elements of.the program.- See Section 3.5 for addi.tional
~~ ..de't'eils regarding t% V8V Summary Report.
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~2 .0 V4V' PROGRAM REQUIREiENTS i
... . .. s
)TherequirementsfortheV8Vprogramcontrol;codesandistandards,and ' -
disposhion of results for tlk V4V effort are described in the following , , sections. s t 2.1 Program Control
.This section . defines and describes the V8V committee's. organization, sched- j
-ule of work, controls, and other requirements which will be observed to assure an orderly execution of the V8V program.
t
' 2.1.1' Organization The V8V committee will be managed through EI's Systems Engineering Depart-ment. This department operates within EI's Systems Group. The EI V8V' committee chairman is Mr. Claire M. Moser.
x
- (d
\
Mr. Moser is responsible for seeing that the V8V program is complete is done within budget and on schedule, and that sound technfcal direction is pursued. The STP project office will ettablish and maintair an STP V8V file for disposition of all V8V materials related to the STP hroject. The V8V committee's primary technical contributions will be made by senior staff members who are independent of software and hardware design. Mr. Moser will assign personnel for V8V committee activities concerning soft-ware and hardware verification and for validation testfng. ' Each member ld assigned to this team will have a demonstrated performance record in roles of this type. Mr. Moser does not assign personnel for the normal "in-pro-cess" V8V activities. These normal "in-process" V8V activities are defined in Section 1.0 of this plan and are the responsibility of the STP system designers and integrators (the hardware and software functional ld organizations). O ~ '
~
~
l STP-201
~
Page 7 of 43 l 205-3
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2.1.2 Schedule m 4[ - ' SNc'e
'- thi elements of ' Ells V8V effort folio), in a natural way, the STP '
,F
, > project's completion of its tasks, the V8V committee's schedule of work lb y.g - will be heavily dependent on the STP project schedule. These elements are l
'
- described in Section 3.0.
i I i 3 > l A software requirements review will be performed upon completion of the l 0' . System Software Specification document and a hardware requirements review i will be performed upon completion of the System Functional Description document. Additionally, hardware and software design document reviews and 1
- ', audits will be performed subsequent to completion of the hardware and
-software designs. Validation testing and ~ evaluation will be performed ,
; concurrent with the Factory Demonstration Test for each unit. The buyer
- has agreed to perform all VSV activities for the field verification tests g h3n for both. units.
u gy.,s _( i Following validation testing, resolution of all system deficiencies, and
-J shipping of the entire system, an overall V8V summary report will be pre-f parEdfortheSTP. This report will s'ummarize the V8V activities for the V8V elements that are common to both units and then summarize them for the unit-specific elements of the V&V program. This report is the final V8V Summary Report.
A 2.1.3 Documentation, Files, Distribution, and Approvals The EI STP Project Requirements Document (PRD) identifies Diree categories of documentt for the STP ERFDADS project. These include EI-generated
. project support submittals, client submittals, and vendor submittals. ,
- Various types of submittals include contract documents, correspondence, ;
Y engineering and analysis reports, procedures, specifications, drawings,
" quality records, design calculations and reports, and vendor manuals. ld i
l O .
; STP-201 - Page 8 of 43 l
205-3 . __ M W
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,m
'd- The following documentsiill be' maintained by the project office. Software
~ ~
' Specification, Software Specification Review Report, Sof tware-Design Docu- _
~
ments, Software Design Review Reports, Program (Code-Walkthrough) Review Reports, and the client's specifications, Mdterial Requisitions,_.and Sup-plier Deviation Disposition Requests. All sof tware documents are either
~
maintained as controlled documents by the project office or by EI's docu-ment control center. The project office is responsible for establishing and maintaining document files,' for the above documents, and project files j
. in accordance with Section 4.0 of the Engineering Standards Manual. Docu-ments maintained by the project office are shown as "0RG" in the column
" Project File" in Appendix D of the PRD. The Software Librarian will con-
. trol certain software items (magnetic tape, source listings, and associated control records) in accordance with Section 6.0 of the $PM. The EI docu-ment control center will maintain control of all other documents that require control of preparation, review, approval, distribution, and d revision.
.o (v 3 2.1.3.1 Preparation, Review, and Approvals Document preparation will be in accordance with the requirements of the STP specifications, EI QAM and addendum, the ESM, the EPM, and the SPM, as ;
modified by the PRD. Document numbers for El procedures, drawings, wire i lists, and manuals are assigned by the El Document Control Center. l STP specific documents will be numbered consistently with the Work Break- { l down Structure as specified in the PRD. All vendor documentation will be s l* [ ' numbered as per vendor specification and not assigned a separate EI sequence number. Required reviews and approvals are specified in Appendix C of the PRD. All documents not listed in Appendix C of the PRD will be j reviewed in accordance with the applicable sections of the EI Engineering Procedures Manual (EPM), the EI ESM, the EI QAM and addendum, the EI SPM, and the STP specifications. l
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STP-201
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V) t 2.1.3.2 Receipt and Recording - =-
.All project-related documentation shall be submitted to the El project -
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control coordinafdr for recording. The project-control coordinator = will log the receipt of all formal and informal project documentation. If the document is to be controlled by the El document control center, see Appen-
' dix D of the PRD, the project control coordinator will log receipt of the 3 document and forward same to the El document control center for recording,
. distribution, filing, and revision control. If the document is to be controlled by the project office, the project control coordinator will log receipt of the document and place the document under project office docu-
, ment control. If the document is to be controlled by the Software Librar-ian, the project control coordinator will log receipt of the document and forward the same to the STP Software Librarian for control in accordance with Section 6.0 of the SPM. Additionally, a Client Submittal Log and a Vendor Submittal Log will be used to record pertinent project information received from the client and vendor, respectively. ESM Sections 4.8.4 and
/s.D 4.8.5 provide instructions in the use of these logs. Examples of these
')- logs are presented in the PRD, Appendix E, Exhibits 1 and 2.
2.1.3'.3 Transsittals All transmittals of controlled documents to the client shall be authorized and approved by the Project Manager through use of a Document Transmittal Record (DTR) (see PRD, Appendix E, Exhibit 3) and as instructed on the
-distribution list in Appendix D of the PRD. Clients will be requested to sign and return DTRS. Note, the distribution list for all' controlled documents will be prepared prior to the distribution of the document.
2.1.3.4 Control and Filing Engineering documents, as specifled in Appendix 0 of the PRD, will be controlled by the El document control center in accordance with Section 6.0 of EI's QAM, as amended by the project-specific QA addendum, Section 4.0 of EI's ESM, and the PRD. Controlled software documents will either be _ ~ STP-201 Page 10 of 43
. 205-3 h
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' controlled by project document control or by the El document control center
'in accordance with EI's QM4 Section 6.0 as amended by the proje_ct-specific ,
' _.' ..QA' ' addendum, Section 4.0 of EI'
- cS4, and the PRD. 'Certain sof tware docu- l l 1 ments such as magnetic tape, source-listings, and associated control _ . ;
records will be controlled by the 5oftware Librarian in accordance with Section 6.0 of the SP'4. In general, the project control coordinator will establish and maintain the project document controls, for the software i under project maintenance, in accordance with Sections 4.1, 4.2, 4.3, 4.4,
,4.5, 4.6, 4.8, and 4.9 of the ESM. Distribution of the STP specifications, Material Requisitions (Mts), Supplier Deviation Disposition Requests (SDDRs), and revisions to the STP specifications will be controlled by the
, project office and will be logged and distributed in accordance with Sections 7.2 and 7.5 of the PRD. The project office (project document control) will maintain a document control log for all documents controlled by the project office. An example of this log is presented in the PRD, Appendix E, Exhibit 4.
The project office wilk maintain a working file of all project documents g
'" and correspondence. Signout forms shall be used by anyone desiring to use the documents. EI will maintain its files for the project for a period of five years after completion of contract, after which they will be archived or sent to the Buyer at the Buyer's written request. These files, contain-ing drawings, plans, specifications, books, records, and miscellaneous documents, will be available for Buyer inspection at EI corporate headquarters.
2.1.3.5 Distribution A distribution list will be prepared by the project office prior to the release of any controlled document from any document control center. All documents controlled by the El document control center will be distrib-uted to the parties specified on the standard distribution list contained j in Appendix 3 of the PRD and the distribution list prepared at the time the document is distributed. L.) _ - -
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M STP-201 - Page 11 of 43 1 205-3 - - t Wen-
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['d All documents controlled by the ' project document control center will'be ! '
, ' ' Yistributed to the parties.specified on the standard distribution list
- contained in Appendix D of the PRD and the distribution list prepared at '
the time ~ the document is distributed. The project office will distribute l all client documents that require distribution control, such as the STP l
. specifications, MRs,1 and SDDRs. The EI document control center and the project office will-not distribute a controlled software document until all
- the following criteria are met:
(1)'. appropriate. software review and reconciliation reports are received, (2) appropriate approval signatures are obtained on the document, and (3) the document transmittal is approved by the project manager. A transmittal log, maintained by the project control coordinator, serves as a record of all document transmittals, both controlled and uncontrolled. g An example Document Transmittal Log is included in Appendix E of the PRD. The number of copies transmitted to meet project milestone objectives will
'be mutually agreed to by the EI and STP project managers. Project task records as defined in the STP specifications shall be transferred to
' Bechtel at the completion of the task.
2.1.3.6 Document Revisions Revisions to controlled hardware documents will be in accordance with Section 6.5 of EI's QAM and addendum and Sections 4.5.2, 4.5.3, and 4.5.4 of EI's ESM. Revisions to controlled software documents will be in accor-dance with Section 6.5 of EI's QAM; Sections 4.5.2, 4.5.3, and 4.5.4 of l EI's ESM; and Section 6.0 of the SPM as amended by the PRD. Preparation, l review, approval, receipt, recording, control, and distribution of all l revisions will be in accordance with paragraphs 2.1.3, 2.1.3.1, 2.1.3.2, ! 2.1.3.3, 2.1.3.4, and 2.1.3.5 above. Revised documents shall be reviewed l i r and approved in the same manner as the original. l
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~2.1.3.f Correspondence IndeTand Documents to STP f.A correspondence numbering system, sequential from the beginning of the -
project,' will be used. Thesjitemis: -
-ST-ZY-YB-XXX where XXX is the sequential correspondence number, 001, 002, etc.
The V8V chaiman will provide the EI STP project office with all V8V docu- ; mentation in accordance with Appendices A and B of Specification
'.9Z559ZS1048. The El STP project office w' ill transmit these documents to: i Technical Documents Center lb -
Bechtel Energy Corporation P.O. Box 2166
. , , 5400 Westheimer: lb
) Houston, TX 77252-2166 Information copies of correspondence will be sent to:
Mr. Francisco Gonzalez Bechtel Energy Corporation P.O. Box 2166 5400 Westheimer b Houston, TX 77252-2166 , 2.1.4 Work Control and Work Breakdown Structure EI's organization of its V&V work is accomplished through the work break-down structure (WBS). The WBS forms the basis for downward extension of the V8V effort to the actual work activities. The EI project office has generated a WBS numbering system (see PRD Section 7.1). Under this system, the project engineers prepare Work Package Authorizations (WPAs) dividing /N\ tasks into individual subtasks. The WPAs are an internal working document STP-201 Page 13 of 43 3 205 ^
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and in conjunction with the WBS ' form the basi [ for cost control and project
~ ' ' ' . - . .. .
tracking. _ A The WBS is input into the Track-50 scheduling program. Track-50 is a l
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management aid for tracing critical path items, and periodic input from f
-project engineers is used by the PM to compare the project status against
-the. schedule.
, Key steps employed in the project planning and control system are (1) ~ identifying all required activities,
~. (2) preparing a' detailed schedule correlating activities, (3). identifying critical or controlling activities, and (4) monitoring major project milestones.
l Problems and concerns will be tracked with a weekly review of the project. 2.2 Applicable Codes and Standards
. Applicable codes, standards, and documents for the STP ERFDADS project are listed in Section 2 of STP Specification No. 9Z559ZS1048, Section 2.2 of 4Z559ZS1049, Section 2 of 4A479ES1018, Section 7.0 of 4A479ES1025, and Section 9.0 of 4A479ES1027. Additional codes and standards EI will comply with during the performance of the project are Nuclear Regulatory Commission 10CFR Part 50, Appendix 8: Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants; Nuclear Regulatory Comission 10CFR Part 21: Reporting of Defects and Concompliance; Nuclear Regulatory Comission 10CFR Part 50.49: Environmental Quali-fication of Electrical Equipment Important to Safety for Nuclear Power s Plants;
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I STP=201 Page 14 of 13 i 205-3 _ _
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Nuclear Regulatory Consission 10CFR Part 50," Append x R: Fire Protec-tion Program for Operating-Nuclear Power Plants; _ Nuclear RegulatAry Counission R.G. 75, 1974: Physical ' Independence of Electrical Systems; Al:SI C37.20: IEEE Standard for Switchgear Assemblies including Metal-Enclosed Bus;- ANSI C37.90-1978:- Relay and Relay Systems Associated With Electric Pom r Apparatus;
~.
NEMA'ICS-1976-1: . Industrial Control and Systems; NEMA ICS-1976-2: Industrial Control Devices, Controllers, and Assemblies; e f3 NEMA ICS-1976-3: Industrial Control Systems; d
\ /i NEMA ICS-1976-4: Terminal Blocks of Industrial Use; NEMA ICS-1976-5: Resistance Welding; and ~
NEMA ICS-1976-6: Enclosures for Industrial Controls and Systems. The above list is not necessarily complete nor do all parts of the. listed codes and standards necessarily apply to the STP V8V plan. A 2.3 Disposition of Results The results of reviews and tests and their disposition are discussed, for each phase of the plan, in Section 3.0. i I O - STP-201 Page 15 of 43 _205-3 l L
. . . . . . . . . _ - . - . . _ . . _ . . _ . . _ _ _ . _ - _ . . . - . . - _ . , . _ _ _ . _ _ _ , . _ _ . . - ~ - _ _ _ _ _ _ . , _ . _ _ _ _ _ . . - . _ _ . _ _ _
l (d p 3.0" TERIFICATION AND' VALIDATION (V8V) PROGRAM ELEMENTS
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'The major V8Vwlements of this plan are (1) Phase 1-system requi[rements
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.'revient -(2)L Phase 1 design; document reviews and audits, (3) unit-specific h validation tests, and (4) a V8V summary report. Note, the buyer has agreed to perform-all V8V activities for the field verification tests. The remainder of Section 3.0 will address each of these components in detail, discussing what is to be accomplished in each case, who will perform the
~
. tasks, and how each step will be conducted.
3.1 System Requirements Review The system requirements review is a key element of the verification and
-validation plan. A clear statement of the requirements is necessary in order to determine whether the correct problem is being solved and whether subsequent design reviews are correctly addressing the statement of the problem.~ Moreover, it is the system requirements agains'; which validation
) test results must be measured. . There will be one system requirements review. This review will apply to both units.
Note, the system requirements review, as defined for the STP project, includes a review of the System Software Specification, the System Functional Desc-f ption Documents, the Project Requirements Document, and L the STP Specifications. 3.1.1' Approach and Objectives ! The system requirements review will be performed to evaluate the require-ments with respect to a number of criteria. These criteria include (1) correctness, (2) completeness, (3) consistency, (4) feasibility, and (5) testability.
. The correctness and completeness criteria are applied to the requirements to determine if the correct problem is being solved. When requirements are I being reviewed for correctness, they are to be reviewed with respect to l being necessary as well as sufficient.
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STP-201 _ 205-3
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's f A-spot check of the requirements for consistency toward applicable stan- -
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,' dards and regulations will be conducted. . _
.The requirements will be reviewed for feasibility and testability to deter _
eine a reasonable and meaningful set of acceptability and test criteria. Emphasis will be placed on review of the stated requirements with respect
. to how well they lend themselves to testing against measurable test cri-teria. Requirements which are not easily tested against objective criteria or witn repeatable results will be ide,ntified.
The specific requirements shall be identified by references to the specific
", sections in the System Software Specification and the System Functional Description document and the STP . Specifications. Traceability of require-
.ments through subsequent documentation and later phases of the V8V program is thus begun via the software and hardware compliance matrices. Q Along with a thorough examination of the requirements as stated in the 1( STP/EI contract documentation, the review will produce an independently
\"~/
documented definition of the system itself via the software and hardware compliance matrices. An example of this matrix is presented in Figure 3-1. d 3.1.2 Responsibilities The EI STP project office, via the "in-process" V8V software and hardware functional organizations, has the responsibility for performing and docu-A menting the system requirements review.and correcting any deficiencies identified by both the "in-process" V8V personnel and the V8V committee. The EI STP project office, via the software and hardware functional organi- A zations, should respond, in writing, to all V8V committee findings. The V8V committee has the responsibility to ensure that these reviews are perfomed in accordance with the documents listed in Section 1.0 and to l perform spot check reviews of their own. . / l
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STP-201 Page 17 of 43 205-3
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3 -- 3.1.3 Resolution of Deficiencies - = - l
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M Deff'ciencies may be resolved by modification of the _ system's requirements d documentatiin or by providing supplementary. documentation addressing the
~
particular requirements issues involved.
~ 3.1.4 _ System Requirements Review Documentatio.
.A summary of the system requirements review, as documented by the EI STP project office, will be included in the V&V Summary Report. The V&V Q -
Summary Report, with regard to the system requirements review, will
, describe the review approach and verify the requirements with respect to the' criteria of Section 3.1.1. g 3.2 Design Review The design review will be performed as a normal part of EI's "in-process"
.(N V8V. program to verify that the hardware and software designs correctly address the system requirements. Traceability of the various design features to particular requirements is emphasized, as is the completeness of _ the design with respect to requirements. The review process also exam-ines design with respect to logical quality, sufficient detail, and testing implications. This design review will apply equally to both units.
3.2.1' Approach and Objectives A number of documents will be used to perform the design re' view. Included are the documents listed in Section 1.0 of this plan, the System Functional Description, Analysis and Design Reports, System Softdare Specification, detailed design documents relating to hardware and software, and any other supplemental documents which may provide design information. Traceabili ty
- of design features to the various specific requirements recorded in the requirements review is provided. All such requirements will be thus iden-tified in terms of associated design information.
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- STP-201 ~Page 18 of 43 205-3 l
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, , One phase of the ' review will be to perform independent evaluations of the hardware and software design. The hardwate design review will address the following design features and considerations:
(1) hardware architecture; (2) input and output interfaces; (3) hardware availability and redundancy; (4) equipment locations and environmental requirements; (5) signal types and rates, testing approach; (6) hardware integration including communications, subsystem integra-tion, and testing approach; and
\
,- m l (7) human factors considerations.
The software design review will address the following design considerations: (1) software structure, i.e., distribution of functions into subsys-tem packages; (2) data structure definition; , (3) interfaces, including interfaces among subsystems and input /out-put interfaces; (4) system and executive control; (5) consistency between preliminary or top-level design and detailed design; O U . Page 19 of 43 STP-201 205-3 _ ..
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.(6) ~ p'e'rformance analys'is;
_, ~ (7 )' human factors considerations; ind_
.(8) association of design features to requirements.
i At the the conclusion of the independent hardware and sof tware reviews, an
- integrated review process will ensure that the total system design is com-
~
. pletely descrit trd i and adequately referenced to requirements. . Figures 3-2 through 3-9 present typical checklists and reports used by the hardware and g
. software functional . organizations during the design review process.
~.
3.2.2 Responsibilities The El STP project office, via the "in-process" software and hardware V8V personnel, will perform the hardware an'd software design reviews in accor-dance with the documents listed in Section 1.0 of this plan and provide the
.p- IVSV comittee with the results of these reviews. The EI STP project g- ' office will also have the responsibility for documenting the design reviews and correcting any deficiencies identified during the review process.
The responsibility of the V&V committee is to ensure that these design reviews are conducted in accordance with the documents listed in Section 1.0 of this plan, to ensure that generic design reviews are conducted for both hardware and software, and to verify that the system requirements are indeed being met by the design. The V8V committee findings will be reported to the project office. The EI STP project office, via the soft-ware and hardware functional organizations, should respond, in writing, to A all V&V committee findings. , 3.2.3 Resolution of Deficiencies Deficiencies may be resolved by revision of design documentation, issuance of additional documentation, or written clarification by the El STP project d office.
.m W O ees
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- STP-201 Page 20 of 43 j205-3
g . f \. V 3.2 k Design Revtuw Documentation
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~$A summary of the hardware-and software design reviews, as documented by the
-. ' EI STP project office, will be included fri the V8V Sunnary Report. b 3.3 Validation Tests The validation or Factory Demonstration Test (FDT) will be conducted after the system hardware and software are fully integrated. There are two distinct subactivities: (1) test procedure development and (2) test execu- g tion. Note, the same test procedure will be applicable to both units while
~ ' the actual tests are unit specific.
-3.3.1 Approach and Objectives
' The objective of the test is to demonstrate and document the compliance of the integrated system to the requirements. The El STP project office will
.h provide a validation test procedure to the V8V committee for review and to
,{
}. . assist in the audit of the unit-specific validation tests. The El STP test g procedure will contain all the important aspects of the test plan contained in Section 4. of NSAC-39 and . include test requirements, test philosophy, test specifications, test environment, detailed test descriptions, test procedures, and test evaluation approach. The final validation test proce-dure will be referenced in the VaY Sumary Report. The test audit will include assurance that the test execution follows the procedures and that the test records are maintained accurately and in detail.
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~STP-20I Page 21 of 43 -
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( }.- ~ Nd 3.3.2. Responsibilities The El STP .prohch office will prepare a validation test procedure in - g _ accordance with.the test plan contained in Section 4. of NSAC-39, including _ test requirements, philosophy, environment, specifications, descriptions, and procedures, with the objective of demonstrating that the completed system meets all system requirements. The procedures will be defined func-tionally in a manner which will allow tracking of test results to system
. requirements'. The El STP project office will be respo7sible for detailed step-by-step descriptions for performing the unit-specific tests within the framewort of the test procedure. The V&V committee will review the test
. ' procedure for completeness per Section 3.3.4 below. b A V8V committee representative will audit the execution of the validation portion of the TDT tests and be responsible for assuring that the valida-tion tests are conducted in accordance with the procedures. The El STP project office will provide the personnel for conducting the tests. The assigned test personnel will have sufficient systems knowledge to ensure
~ -- - the test steps are conducted in a clear and repeatable manner. The EI STP project office will be responsible for establishing and maintaining the ld test environment,'as well as supplying all test equipment, special test software, and special test data files which may be required. The V8V connittee will audit the validation test reports prepared by the El STP project office. The V8V committee will be responsible for verification of acceptable performance in accordance with acceptance criteria previously d
specified and agreed upon. . i Following completion of all validation testing, the V&V committee will prepare a sunsary of the unit-specific validation test. This summary will be finalized upon resolution of identified deficiencies and the completion of required retesting and be included in the VSV Summary Report.
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STP-201 Page 22 of 43 205-3
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-3.3.3 1 Resolution of DeficieVicies -
. ~ The disliiosition of deficiencies and approach to test case-repeats and sign-
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3 _ offs will be agreed-to by the client and the EI STP-project office and
~.' defined in the test procedure. Provisions will be made for resolution of minor ' deficiencies during or immediately after the performance of a test,
'in which case documentation attached to the procedure would describe the nature of the correction or allowance and contain approval signatures of
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. both' the client and the El STP project office representatives. If, during lg testing,' procedural errors are identified, they would be handled in accor-
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dance with the instructions contained in the test procedures. ld
. Provisions will be made to retest sections of test cases which fail. It is anticipated these provisions will include criteria to detennine when the entire test case must be rerun and when only selected sections of a test case need be repeated. These criteria will be specifically defined in the r test specifications portion of the test procedure. Provisions will also be ld made to handle major test failures or repeated test failures, as identified in the test procedure.
The procedures will contain a final sign-off portion to be signed by the designated client and EI STP project office representatives after suc- g cessful completion of all portions of the test and resolution of all discrepancies. 3.3.4' Validation Test Procedure d The validation test procedure will include all the important aspects of the
- NSAC-39 test plan, including test requirements, test philosophy, test envi-b f' ronment, test specifications, detailed test descriptions, test procedures, I- _and test evaluation approach.
In general, the validation test procedure should contain the following ld sections: (1) introduction, (2) prerequisites, (3) system description and , test requirements, (4) test environment specifications, (5) test equipment
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STP-201 Page 23 of 43 205-3
- and software, (6) general test specifications, (7) individual test case specifications, and (8) test procedures. - _
3
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3.3.5 Unit-Specific Validation Test Reports The EI STP project office will prepare and compile the validation test ld reports subsequent to completion of the unit-specific validation tests. These reports will summarize each test and include an attachment containing
^
. relevant hard copy test results.
3.4 Field Verification Tests The objective of this activity is to verify that the validated system was properly installed. That is, the purpose of the field verification test is not to validate the system but to verify its proper installation. The field verification consists of verifying that each input is correctly connected and that the signal range is consistent with the design. Note, ( ') the same field verification test procedure will be applicable to both units while the actual tests are considered as unit specific. The field verifi-d cation test is identical i:o the Site Demonstration Test (SDT). 3.4.1 Approach and Objectives The objective of the field verification test is to demonstrate and document ld the installed systems compliance with system requirements as validated by the validation test. The EI STP project office will provide a field verification test procedure and the VaV committee will review the field verification test procedure. The test procedure shall contain test speci-fications, environmental specifications, detailed test procedures, and acceptance criteria. A The EI STP project office will provide personnel to assist the buyer in conducting the field verification test. The buyer has agreed to perform all verification and validation activities for the field verification b p tests. Therefore, the VAV committee's responsibilities, relative to the I STP-201 Page 24 of 43 205-3 e
~-
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-# field verification tests, end af'ter the review of the field verification-A
' , [ ' test procedures.. _.
3.4.2 ResponsibTlities - The EI STP project office shall identify test purpose, philosophy, and prerequisites and shall prepare a field verification test procedure with ld the objective of demonstrating that the installed system meets all system
.requiremen ts. The procedures will be defined in a manner which will allow tracking of test results to system requirements. The El STP project office shall be responsible for detailed step-by-step descriptions for performing
".the test within the framework of the test procedure. The V8V committee will review the test procedure for completeness per Section 3.4.4 below.
The EI STP project office will provide personnel to assist the buyer in conducting the field verification test. The test personnel assigned must have experience in the testing of real-time computer systems and sufficient systems knowledge to ensure that the test steps are conducted in a clear ( ') and repeatable manner, g The buyer is responsible for performing all verification and validation activities for the field verification tests as required by NSAC-39 and paragraph 3.2.9.0 of Specification 9Z559ZS1048, Revision 4. EI's V8V responsibilities, relative to the field verification tests, end with the review of the field verification test procedure and resolution of all review coments. , 3.4.3 Resolution of Deficiencies The disposition of deficiencies and approach to test case repeats and sign-offs will be agreed on by the buyer and El STP project and defined in the test procedure. Provisions will be made for resolution of minor deficien-b cies during or immediately after the performance of a test case, in which case documentation attached to the procedure would describe the nature of '(
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STP-201 Page 25 of 43 205-3 _ . .
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e the correction or a11 hance and contain approval signatures of the desig-
, ,nated buyer and the EI.-STP project office representatives. If, during
~ ~
lg
. testing, procedural errors are identified, they would be handled .tii the
~' -
~
~~-
' same manner. _
Provision's will be made to retest sections of test cases which fail. It is anticipated that these provisions will include criteria to determine when
- the entire test case must be rerun and when only selected sections of a
. test case need be. repeated. These criteria will be specifically defined in ,
- the test specifications portion .of the test plan. Provisions will also be made to handle mejor test failures or repeated test failures, as identified
. in the test plan.
The-procedures will contain a final sign-off portion to be signed by the designated buyer and the E! STP project representatives after successful ld
. completion of all portions of the test and resolution of all discrepancies.
^
.b v 3.4.4 Field Verification Test Procedure D3 The field verification test procedure will include sections describing test ld specifications and procedures. The philosophy and test environment will be identified along with specifications for the particular test cases.
In general, the field verification test procedure will contain the follow- lg ing sections: (1) introduction, (2) prerequisites, (3) test requirements, (4) test environment specifications, (5) test equipment and software, and , (6) test procedures. g 4 3.4.5 Unit-Specific Field Verification Test Reports The EI STP project office and the buyer will jointly prepare and compile Q the unit-specific field verification test reports subsequent to completion of the unit-specific field verification tests. These test reports will summarize each test and include an attachment containing all relevant hard copy test results. In general, these reports will contain the following O -
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STP-201 Page 26 nf 43 205-3 t -- ----T -^r--wt--%--t- ' w wr---se--ww--*. - - - e.------=-,,----,,m----n---me--wwwm--wwe----we--- -
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'v sections: (1) introduction; (2) list of reference documents; (3) indi-
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,' 'vidual' test case-analysis; (4) overall sumaryrincluding capabilities ~
' su$essfully demonstrated and deficiencies; and (5) reconnendations.
A
- 3.5 V8V Summary Report The verification and validation sunnary report will be prepared by the V8V
~ committee after the field verification test procedures have been reviewed,
; all review findings have been resolved, and the system has been shipped to g the buyer. This report will be based on the activities of both the "in-process" V8V and the V8V committee.
The V8V Summary Report will sunnarize the V8V activities over the life of the project. The V8V sunnary report will contain a section applicable to both units and a separate unit-specific section for each unit. The general content for this report will be as follows: ld (b (1) overview of V8V plan, documentation, and activities; (2) Phase 1 systems requirements review; (3) Phase 1 design review; (4) validation test: (a) Phase 1 validation test procedure review, , ld (b) validation test for Unit No. 1, and (c) validation test for Unit No. 2; (5) field verification test procedure review; and ld (6) summary and conclusions. l . I i p - STP-701 Page 27 of 43 205-3 _ _ . l ._ - l
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- ' 3.5.1 Overview of V8V Plan, Documentation, and Activities -
d Thit El STP "in-prccess" VaY'and the independent V8V programs will be' sum- -- marized in the overview section. The--overview will also list the Var
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documentation used to implement the V8V plan or generated as a result of the V8V activities. 3.5.2 Pt'ase 1 System Requirements Review This section will summarize the objectives, activities, and results of the systems requirements review. It will sunniarize the deficiencies identified
- and the manner in which they were resolved and list the reference material germane to the requirements review.
3.5.3 Phase 1 Design Review The design review section will contain the same type of information as the [) previous section. Both the hardware and sof tware reviews will be included in the discussion. Reference material relevant to the design review phase will be listed.' 3.5.4 Validation Tests The Phase 1 validation test procedura review will be summarized and a summary of the test execution and the test report for each unit will be presented. Haar deficiencies identified during the unit-specific tests will be discussed, including the manner in which they were ' resolved. References relative to each validation test will be itemized. 3.5.5 Field Verification Tests This section will contain information sunnarizing the Phase 1 field verifi-cation test procedure review. The report will discuss the resolution of major deficiencies and will itemize applicable reference documentation. O . .. .- STP-201 Page 23 of 43 205-3
% _,-y. --.w.- - _3,7, ,,,,w-, .ye,.e-- m,
N# _ - E5.6 Sunnary and Conclusions This section will present an overall sunnary of te STP V8V project. The
~
c6n~clusions will address the qualitf of each system, each system's trace-ability, and each system's auditability. A software and hardware compli-ance matrix will be included to serve as a " road map" to the traceability b of the various requirements issues. The system auditability discussion will address the role of the various document references listed in the
.- overview section and thus serve as a starting point for any future study of the plant emergency response capability documentation trail.
bo i
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STP-201 Page 29 of 43 205-3 . l.
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SOFTWARE COMPLIANCE MATRIX
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ZS1048 - . FDT
- Reference Paraphrased Specification ' Section - o
. 1.1.*1 Scope to supply an ERFDADS for PWR.
.1.2.1 Support three facilities: CR, TSC, EOF.
~~
- 1.2.3
- SPDS functional capability:
(a) display critical plant variables rapidly,
- .(b) continuous display representing plant
' safety status, (c). detect abnormal operating conditions, (d) aid determination of cause of abnormal conditions,
, (e) monitor corrective actions, (f) group parameters for display, (g) provide simple display formats, (h) display and validate in real time, and (1) provide parameter trend displays.
g v 1.2.5- Three thousand i 20', inputs.
-3.2.7.A FDT philosophy.
3.2.7.B Compliance matrix. 3.2.7.C External data link simulation for test purposes. 3.2.7.0 Compliance matrix, specificity test requirement. 3.2.7.E Order of functions to be tested. 3.2.7.F Retest procedure. 3.2.10.2.8 Source and nbject copies on tape. 3.2.10.2. Source listings. C,D 3.2.10.2.F System memory utilization. ! Figure 3-1. Example of Compliance Matrix STP-201 Page 30 of 43 205-3 .__. P-WTr
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SHtET t OF 2 EMASY CORP 0AATED DEsasse RtytEW CHemtuST pedNT see. 00CuesENT No.
. Fifts A TEE 311 CAL RETIEN OF TM DESIGN WITE RESPECT TO TIIE FOLLOUING IIITIALS*
REEIGIRBENTS. AS AFFLICABLE LEAR BEIN CONDUCTED.
.- 1. RASIC FUIICTIONS OF EACE STROCTtiAE. SYSTDt; AalD CtatPOWElff
- 2. PERFOWIAIICE REQUIREMENIS SUCE AS CAFACITT. RATDC. SYSTDI OITTFttf.
- 3. CODES. STAISARDS. Aan RECULATORT REQUIREMElftS INCLUDDG THE AFFLICASLE ISSUE A15/04 ADDEISA.
A. DESIGE C0tBITIDMS SUCK AS PRESSURE. TDEFERATURE. FLtTID CitDfISTRY. A30 VOLTACE. 3.' LOADS SUCR AS SEISMIC. WDD. TEIRMAL AaB DTIIAIIIC.
- 6. ENTIROISENTAL COISITIONS ANTICDATED DURDIG STORAGE. CONSTRITCTION.
AIS OPERATICW SUCE AS PRESSURE. TDIFERATURE. MatIDITT. CORROSIVDESS SITE ELETATICII. W!Ie DIRECTICII. NUCLEAR RADIATION. ELECTROIIACNETIC
,[r} RADIATICII. AIS DURATION OF EIFOSURE.
\j . F. INTERFAG REIGIRBIENTS DCLIIDDG DEFINITION OF THE FUNCTIONAL AND PETSICAL INTERFACES DTOLVING STRUCTURES. SYSTDtS AND CONFottDT3.
- 8. MATERIAL REElITIREIENTS DICLUDIIRC SUG ITDtB AS COMPATIBILITT. ELECTRICAL INSUIATICII PROPERTIES. FROTECTIVE COAfDG. AND CORROSIOlt RESISTANCE.
J 9. MECMAllICAL RElUIREMElrTS SUCE AS VISRATICII. STRESS. SEOCE. AND REACTION FORCES.
- 10. 56 REQUIRBIDTS COTERDIC SUCE ITDes AS EtitTIP! TENT FOU::DATIONS J D FIFE SUFFORTS.
- 11. IlrDRAULIC REQUIRBElifS SUG AS PUMP NET POSITITE SUCTICII READS (NPSE).
ar ttuaame r yRESSURE DAOPS. Aag arrmaanr r FIrID VELOCITIES.
- 12. CIttISTRY REQUttatElrTS SITG AS Pref 1SIONS FOR SAMPLDC AND LDtITATIONS ON WATO CIDEISTRT.
L3. ELECTRICAL REQIf!RattfTS SU G AS SOURCE OF FOWER. VOLTACE. 3ACEWAY 18QUIRDEDif3. ELECTRICAL INSUIATICII. AllD 2RJTOR REQUIRDIENTS. . 14 IATOUT Als ARRAIIGEMDrt REQUIRDtDrfS.
- 13. OPUATI0llAL REQtTIRDIENTS UNEEE VARIOUS CONDITIONS. SUC5 AS Ft. ANT STARTUF
.301 DIAL PLA:IT OPERATICIt. Pt.Aarf SuuTDOWN. FIAltf OfERCDCT OPERATION.
l SPECIAL OR INFREQEitif 0FDATICII. AND SYSTDt Aste0NfAL OR DfERCDICT ! 0FERATI006. I
- 16. I3STRtDttfTATI0tl AND COIITROL REQUIRDIOTS INCIrDING INDICATING INSTRU-MENTS. CONTROLS AND AIARMS REQUIRED FOR OPERATION. TESTI:C. AND PAINTEMANCE. OTHER REQUIRDtENTS SUCII AS T31 TTFE OF INST 2tCIENT. INSTALLED SFARES. RANGE 0F MF.ASURDtENT AalD LOCATI0tt OF DDICATION SUOULD ALSO SE
! 13CLUDED. l I
*DITIAL THOSE ITD!S RI71EVED. MARE N/A AS AFFLICARLE i rents E-cas 4Ev.0.a/so i
figure 3-2~
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.- STP-201 Page 31 of 43 1- --
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, Design and Analysis Control Rev. 1 I \- -\ ;- -\/
i 1 0E34800 flentlF CHECMUST (COIITt91UTECO PaedecT me. occuales? no. i Titta j DITIALS l
- 17. ACCESS AIS ADIIINISTRATITE CONTROL REQUIRElsart$ TOR FIAarf SECURITY. I
- 18. REDutmAIICT. DITERSITT. Ale SEFARATICII REQUIRDIENTS OF STRUCTURES.
- SYSTDS. AIS CIEWONENTS.
, 19. FAILURE EFFECTS REQUIRMIENTS OF STRUCTURES. SYSTIME. AND CCHF0ttElfr5 INCLUDDG A DEFINITION OF TEOSE ETUrtS AND ACCIDurTS WRIG THET MUST SE DESIGNED 10 WITESTAND.
- 20. TEST " ' . v*
INCLUDING D.FIAart TESTS AND TIIE CONDITI0IES UllDER WEIG TEET WILL SE PERFONIED. .
- 21. ACCESSIBILITT. MADITEMalICE. REFAIR. AND IIISDTICE INSFECTI0ll REQUIREMENTS FOR TEE FIAllT DCLUDDIC TEE COIGITICIES UNDER WEICH TRESE WLLL SE PERFONIED.
- 22. F m unet REQUIRainffS AIS LIMITATICIIS DICLUDDC TEE QUALIFICATION AaB IRalBER OF F-user AyAgtAggg y0R FIalIT OPERATICII. MAINTEllA31CE.
A TESTDC. AND DISFECTICII: AND PErJtISSISLE PERSONIIEL RADIATICN
./ EIFOSURES FOR SPECIFIED LEIAS A31D COISITIONS.
U 23. TRAIISFORTASILITT REQUIREMDITS SUG AS SIZE AND SHIFFDC WEIGHT. LDEITATIONS.1.C.C. REGUIATICIts.
- 26. FIRE FROTICTICII OR RESISTA3BCE REQUIRDIENTS.
- 25. RANDLDC, STORACE. AaB SEIFFDC REQUIREMDTS.
I6. OTEER REQUIRDIENTS TO PRETCrf UllDUE RISE TO TIE REALTE AND SAFETT OF TEE FUSLIC.
- 27. MATmAr.n. FROCESSES. FART AND IQUIPIElrF SUITABLE TOR AFFLICATION
- 28. SAFETT REQUIREMElfts FOR FREYDrTING PERSOINfEL IIIJURT INCLUDING SUG ITDIS AS RADIATICII EAZARDS. RESTRICTING TEE USE OF DAaIGIBOUS MATERIALS.
ESCAPE FROTISICIIS FRGt DCIOSURES. AND GROUNDDG OF ELECIRICAL SYSTEMS. conuests. dEviggum av DaTE Fomas E-o23 AEM0.4/so ( ( . Figu re_. 3-2 _(Con ' t)
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- STP-201 -
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- Page 36 of 43 ll . STP-201 l
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SOFTWARE PROCEDURES MANUAL ENERGY INCORPORATED g/ ' COMPUTER SYSTEMS & ANALYSIS DIVISION SECij0N. & TITLE PAGE 8 OF 18 REVISION 1 7.0 FORMS - -
~~-~
DATE 5/7/82 SOFTWARE REVIEW REPORT No. SPECIFICATION REVIEW
,h ENERGY INCORPORATED SHEET _ OF _
- w COMPUTER SYSTEMS & ANALYSIS OlvlSION PART 1 CF 4 FROJECT: SUBSYSTENM00ULE:
CLIENT: CONTRACT NO.. SFECIFICATICN APPROVED: DATE: ORGNIIZATICN/ TITLE: , ATTENDEES CMAIPPAM: CATE: CRGANIZATICN/ TITLE: / NAME ORGANIZATION MAME CRGANIZATION LJ CHECX LIST ITE*S ITN SAT /U'ISAT
- 1. 0verview Section Reflects Task Requirements
- 2. References Adequate for Task j
- 3. Specifications Como11es with Clients Requirements
- 4. Startup and Error Conditions Complete -
- 5. Soecial Considerations Defined in Detail ,
1
- 5. I 1.
S. AC ION ITEMS
*TD CESC'4fPT!CN NAST CATE 1.
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Figure 3-5 STP-201 Page 38 of 43
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. SOFTWARE PROCEDURES MANUAL ~~
ENERGY INCORPORATED ( ' COMPUTER SYSTEMS & ANALYSlS DIVISION PAGE 9 OF 18
~'SECTION 8 TITLE 7.0 FORMS REVISION 1 DATE 5/7/82 SOFTWARE REVIEW REPORT m-DESIGN REVIEW
. ENERGY INCORPORATED SH EET _0F Jem ' COMPUTER SYSTEMS & ANALYSIS DIVISION PART 2 oF 4 PROJECT: SUBSYSTEhMODULE:
CLIENT: CCNTRACT NO.: OESIGN APPROVED: CATE: CRGMIIZATICM/ TITLE: , ATTENDEES CHAIRMAN: CATE: ORGANIZAT!cN/ TITLE:
/m MAME ORGANIZATION - NAME 09GANIZATION
( u CHECX LIST ITEMS ITEM SAT /UNSAT
- 1. Overview Section Reflects Task Design
- 2. Flow Of agrams Represent Design
- 3. Pseudocode is Adequate for Task Functions
- 4. Data Structures Completely Defined
- 3. Design Meets Specifications
- 6. Test Design Covers Task Functions
- 7. Installation Procedures Ccmolete 8.
ACTION ITE585 TEM CEICMIPfict: NAME OATE 1. 2.
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Figure 3-6 STP-201 Page 39 of 43 l
SOFTWARE PROCEDURES MANUAL ! l ENERGY INCORPORATED 1
^ # '
PAGE 10 OF 18 G COMPUTER SYSTEMS & ANALY. SIS DIVISION __
-SECTION- 8 TITLE REVISION 1 7.0 FORMS - _
DATE 5/7/82 l SOFTWARE REVIEW REPORT No. PROGRAM REVIEW SHEET _ OF _ h ENERGY INCORPORATED eImm m COMPUTER SYSTEMS & ANALYSIS OlVISION PART 3 0F 4
~
PROJECT: SUBSYSTEM / MODULE: CLIENT: CONTRACT NO.:
. CODING APPROVED: CATE:
CRGMIZATION/ TITLE: ATTENDEES CHAIRFAN: DATE: CRGANIZATICN/ TITLE: NAME ORGANII.tTION NAME ORGANIZATION A I G'I CHECX LIST ITEMS ITEM SAT /UNSAT
- 1. Code Follows Design
- 2. Code is Well Structured
- 3. Code Contains Prologue
- 4. Code is Well Coseented
- 5. Prograssing Standards Met
- 6. Program /Stannary Sheet Complete 7.
S. AC* ION ITEMS
!*EM DESCRIPTION .IA!T CATE 1.
z. 3. li", tn'. figure 3-7 STP-201_. Page 40 of 43 O e. m q-e - - - , .
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SOFTWARE PROCEDURES MANUAL - l ENERGY INCORPORATED ' i) COMPUTER SYSTEMS & ANALYSIS DIVISION __ PAGE 11 OF 18 - A_/ ___ SECTION & TITLE REVISION 1 l 7.0 FORNs - DATE 5/7/82 ow m SOFTWARE REVIEW REPORT m. ACCEPTANCE TEST REVIEW ENERGY INCORPORATED SH EET _ 0F ,,,, e-w COMPUTER SYSTEMS & ANALYSIS DIVISION PART 4 OF 4 PROJECT: SUBSYSTEH/ MODULE: CLIENT: CO C M No.: TESTING APPROVED: DATE: ORGANIZATION / TITLE: ATTENDEES CHAIRMAN: DATE: ORGANIZATICN/ TITLE: NAME ORGANIZATION MAME ORGANIZATION C'y
'Qj CHECX LIST ITOG SAT /UNSAT
[ TEM
- 1. Code Performs as Designed
- 2. All Test Procedure Steps Completed Satisfactorily
- 3. Test Case Documented
- 4. Test Results Doctsnented S.
6. l' 7. 3. ACTION ITEMS CEScat# TION NAME CATE
!TCe 1.
2. 3. O ' 7[v"i $1 Figure 3-8 STP-201 Page 41 of 43 yn, wy-- , - , ,
SOFTWARE PROCEDURES MANUAL ENERGY ~lNCORPORATED PAGE 12 op 18 [ CO,MRUIER SYSTEMS & ANALYSIS DIVISION
' SECTlON .8 TITLE REVISION 1 7.0 F0PM --
DATE 5/7/82 - NO. - SOFTWARE REVIEW REPORT : CONTINUATION PAGE I ENERGYINCORPORATED SHEET _OF l
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vi 'CU c Figure 3-9 - l Page_42 of 43 STP-201 v ,t--w--- -y------m y - , - - . , - - . - .,.,w, -- -cy- ,-w,, . -,, , , , -, - . - w---,,- - - . - y , --,m.,c --g - - - - - - - -
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4.0 ACRONYMS i ,
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1.: ANSI - American-National Standards.. Institute
. 2. CFR - Code of Federal- Regulations -
l
' 3. CR - Control Room
- 4. ' DTR .- Document Transmittal Record ;
- 5. EI - Energy Incorporated i 6.- EOF ~- Emergency Operations Facility l
- 7. - EPM - Engineering Procedures Manual ,!
< 8. ERFDADS - Emergency Response Facility Data Acquisition and Display l System
- 9. ESM - Engineering Standards Manual
- 10. - FDT - Factory Demonstration Test
- 11. IEEE. - Institute of Electrical and Electronic Engineers d ,
- 12. MRs '- Material Requisitions
- 13. NEMA National Electrical Manufacturers Association
- 14. NSAC - Nuclear Safety Analysis Center 1 15. NUREG - Nuclear Utility Regulations
- 16. PRD - Project Requirements Document l
- 17. ' PWR - Pressurized Water Reactor
' 18. QA - Quality Assurance
'19. QAM - Quality Assurance Manual
- 20. SDDR - Supplier Deviation Disposition Request
-'21. .SDT - Site Demonstration Test
- 22. SPM - Software Procedures Manual
- 23. STP - South Texas Project ,
- 24. :TSC - Technical Support Center
- 25. V8V - Verification and Validation
- 26. W85 - Work Breakdown Structure
- 27. WPA - Work Package Authorization 1
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STP-201 Page 43 of 43 205-3 --
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APPENDIX C SPDS DISPLAYS AND KEYBOARDS
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.,_s APPENDIX 0
., )- SPDS DISPLAYS AND KEYBOARDS TABLE OF CONTENTS TITLE' PAGE Displays. C-1 Top Level Normal Safety Function (Top-N)~ C-2
. Top Level Critical- Safety Function (Top-C) C-4 0, Normal Suberiticality (NSF-S) C-6
- Normal Core Cooling (NSF-C) C-8
. Normal Heat Sink (NSF-H) C-10 Normal RCS Integrity (NSF-P) C-12
~
i s j. ' Normal Containment Status (NSF-Z) C-14 Normal RCS Inventory (NSF-I) C-16 Critical Subcriticality (CSF-S) C-18 Critical Core Cooling (CSF-C) C-20 Critical Heat Sink (CSF-H) C-22 Critical Integrity (CSF-P) C-24 Critical Containment (CSF-Z) C-27
. Critical Inventory (CSF-I) C-29 Keyboards C-31 C-1 8561c/0328c
p-
', APPENDIX C v.
is. _j SPDS DISPLAYS AND KEYBOARDS a LIST OF FIGURES FIGURE NO. TITLE PAGE C.1 Top Level Normal Safety Function (Top-N) C-3
@ C.2 Top Level Critical Safety Function (Top-C) C-5 C.3 Normal Suberiticality.(MSF-S) C-7 C.4- Normal Core Cooling (NSF-C) C-9 C.5_ . Normal Heat Sink (NSF-H) C-11
.C.6 Norinal RCS Integrity (NSF-P) C-13
.- C.7 Normal Containment Status (NSF-Z) C-15
~. l' C.8' Normal RCS Inventory (NSF-I) C-17 C.9 Critical Suberiticality (CSF-S) C-19 C.10 Critical Core Cooling (CSF-C) C-21
'C.11 Critical Heat Sink (CSF-H) C-23 C.12 Critical Integrity (CSF-P) C-26 C.13 Critical Containment (CSF-Z) C-28 C.14 Critical Inventory (CSF-I) C-30 C.15 Function Keypad Layout C-32 C.16 Full Keyboard Layout C-33 l
l A
\_) C-il 8561c/0328c l
l
'r : , ..l' DISPLAYS I
The Safety Parameter. Display System (SPDS) displays have a similar layout.
-The; top left box of each display contains the display mnemonic, the display number, Land the South Texas Project unit number. The top middle box of each display contains the display name. The top right box of each display contains the date, time, and the plant operational mode.
The middle section of the SPDS displays contains the various parameters. These are displayed in a variety of formats, including digital values, analog-style bars, trend graphs, and status messages. The bottom lef t section of the SPDS displays, with the exception of the top
,s level Normal Safety Function and Critical Safety Function displays, contains
! \
(,,/ the status boxes for the Normal Safety Functions (NSF) or Critical Safety Functions (CSF). The computer selects the N3F or CSF boxes based on the position of the reactor trip breakers. The NSF boxes are displayed if the reactor trip breakers are closed. The CSF boxes are displayed if the reactor trip breakers are open. The center bottom section of the displays is reserved for the system point detail function. The bottom right section displays the SPDS computer " health" status via an alpha / color-cued indicator. l L E 1 i l l l [ 8561c/0328c C-1 L
W E
.. TOP LEVEL NORMAL SAFETY FUNCTION (TOP-N) o u -
- The top..' level Normal Safety Function display, or TOP-N, is shown on Figure C.1;.it contains the six NSF status bars, as' described in Section 12.4.2.2. .It also contains the six NSF status boxes and displays the position lof 'the Train R and Train S reactor trip breakers. In addition, the bottos
=section of the graphic display contains several status messages. These messages are: "SI" for safety injection actuation initiation, "CNTMr ISOL" 1
for containment Phase A isolation actuation, "CVI" for containment ventilation isolation' actuation, "STM LINE ISOL" for steam line isolation actuation, "LOOPWR" for loss of offsite power, "FHB HI RAD" for high radiation, detected
- by the spent fuel pool exhaust radiation monitors, in the Fuel Handling Building, "AMSAC" for the Anticipated Transient Without Scram (ATWS)
Mitigation System Actuation Circuitry activation, "AFW" for Auxiliary (,g f.~
/ 'Feedwater actuation, "FW ISOL" for feedwater isolation, " AUTO RECIRC" for automatic recirculation mode entered (suction of SI and containment spray l
. pumps switched from RWST to containment sumps), "EAB HI RAD" for high radiation detected by the Control Room / Electric Auxiliary Building intake radiation monitors, "CS" for containment spray actuation, and "RX TRP" for reactor trip actuation.
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'The top level Critical Safety Function display, or TOP-C, is shown on Figare C.2; it contains the six CSF status bars as described in Section
'2.4.2.2. It also contains the six safety function status boxes and displays the position of the Train R and Train S reactor trip breakers. The bottom portion.is used to display the same status messages as displayed in TOP-N.
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p . - - - - NORMAL SUBCRITICALITY (NSF-S) 7 s The NSF Subcriticality status display is shown on Figure C.3; it contains the following features. The upper section gives a thirty minute trend chart for the four power range neutron flux detectors. . In addition, vertical bars representing the current value of each channel appear to the right of the t rends. Surrounding this trend chart, in the approximate location of the detectors around the reactor, are the current values for the four power range channels, along with the current values for the two intermediate range detectors, and the current values for the two source range detectors. All of these values are presented in digital format. The lower lef t box on the display gives the intermediate range neutron flux trend graph. The trend graph displays a thirty minute time history of the gm ( ) intermediate range startup rate and the intermediate range flux. Values shown v in this area reflect averages of the two intermediate range neutron flux detectors. A vertical bar to the left represents the current value of the intermediate range startup rate (SUR). The bar to the right of the trend graph represents the current value of the latermediate range flux. The lower right box gives the source range neutron flux trend graph. The trend graph displays a thirty minute time history of the source range flux and source range startup rate. Values shown in this area reflect averages of the two source range neutron flux detectors. A vertical bar to the left is the current value of the source range startup rate. A bar to the right of the trend graph represents the current value of the source range flux. O V 8561c/0328c C-6
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NORMAL CORE COOLING (NSF-C) i s - The NSF Core Cooling status display is shown on Figure C.4; it contains the following features.- The top center trend graph displays a thirty minute time history and the current value bar of the Reactor Coolant System average temperature, calculated from the four loop average temperatures (narrow range). The top lef t trend graph displays the thirty minute time history and the current value bar of the maximum cold leg temperature (Tcold), selected from the four wide range loop cold leg temperatures. The top right trend graph displays the thirty minute time history and the current value bar of the maximum hot leg temperature (Thot), selected from the four wide range loop hot leg temperatures. j-- 3 A v
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The bottom lef t section of the display shows a horizontal bar of the current value of total Residual Heat Removal (RHR) flow. The bottom center of the display contains a trend graph with the thirty minute time history and the current value bars of the four loop differential temperatures (delta T), calculated from the four loop narrow range cold leg temperatures and the four
' loop narrow range hot leg temperatures. Alarm limits for overpressure delta T and the overtemperature delta T are shown on this trend graph display.
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The NSF Heat Sink status display is shown on Figure C.5; it contains the following features. The left portion of the display is dominated by a graphic representation of a steam generator. The top trend graph, within the steam generator graphic, contains a thirty minute time history and the current value bars of the four steam generator narrow range water levels. Each displayed SG narrow range water level is calculated from the four narrow range water level channels for that steam generator. The bottom trend graph contains a thirty minute trend graph and the current value of the maximum SG blowdown radioactivity level, selected from the four SG blowdown radiation monitors. The top center section of the display shows the status of each steam generator's power operated relief valve (PORV) and each steam generator's safety relief valves. Below that information is the maximum main steamline radioactivity level, selected from the four main steamline radiation monitors, and the steam generator associated with that reading. Directly below the steamline radioactivity level reading is the condenser vacuum pump exhaust radioactivity level. The bottom right section of the display contains a trend graph which shows the thirty minute time history of the four steam generator steam flow /feedwater flow differentials and a current value bar of the maximum steam flow /feedwater flow differential signal, selected from the four steam generators. Each of these differential signals is calculated using the three feedwater flow signals and two steam flow signals for each steam generator. O) L 8561c/0328c C-10
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si? NORMAL RCS INTCCRITY (NSF-P)
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The NSF Reactor Coolant System (RCS) Integrity status display is shown on Figure C.63 it contains the following features. The top left section has a graphic representation of the pressuriser. Inside this figure is a bar that represents .the current value of pressurizer pressure, calculated from the four pressuriser pressure signals. To the left of this figure is the present status of the pressuriser power operated relief valves and pressurizer safety valves. The bottom left section of the display is a graphic representation of the , reactor vessel. A thirty minute time history and a current value bar of reactor. coolant system pressure are displayed. The values are calculated from
.three reactor coolant system pressure channels. Alarm limits, calculated from D. -( ) reactor coolant system temperature, are displayed to the right of the current value bar. - These limits are the cold overpressure mitigation setpoints. To the left of the reactor vessel' graphic representation is the status of the reactor vessel head vent throttle valves.
The right section of the display is a trend graph of the radiation detectors used for reactor coolant pressure boundary leak detection. Thirty minute time history and current value bars of the Reactor Containment Building (RCB) atmosphere monitor noble gas and particulate detector readings are displayed. 8561c/0328e C-12
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C NORMAL CONTAINMENT STATUS (NSF-Z) p T ) v The NSF Containment Status display is shown on Figure C.7; it contains the following' features. The left portion is a trend graph, displaying a thirty minute-time history and a current value bar of the RCB atmosphere monitor - noble gas detector. In addition, to provide the operator with information relating to total' gaseous radioactivity releases from the plant, a thirty
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The right portion of the display is a trend graph of containment pressure and temperature. A thirty minute time history and a current value bar of
- containment temperature are displayed. In addition, a thirty minute time
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The NSF, Reactor Coolant System Inventory display is shown on Figure C.8; it contains,the following features. To the left are the thirty minute time
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- water level, calculated from the two VCT level channels.
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P k T CalTICAL SUBCRITICALITY (CSF-S) b 7 The CSF Suberiticality display is shown on Figure C.9; it contains a graphic E representation of the reactor vessel. To the left are displayed a five minute = time history and a current value logarithmic bar for the extended range m
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neutron flux (upper range) . Above the trend is the current value of the upper e L range flux displayed in numeric format. A linearized representation in bar E k format for this same reading is displayed in the top center section of the E P display. The lower center section of the display contains a logarithmic
~
y current value bar for the extended range neutron flux (lower range). Above E - this bar is the current numeric value. The right portion of the display 5 displays the current numeric value and current value bar of the extended range V startup rate. The values used on this display are all calculated using the b output from the two post-accident qualified extended range neutron flux = [ detectors. w n E r t b W e F M 5 5 5 F b a 5 b b [ 8561c/0328c C-18 ->
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u_/ The CSF Core Cooling display is shown on Figure C.10; it contains a graphic representation of.the side view of the reactor vessel on the left side of the
-display. ' Major structural features are shown on this representation. The top portion of the reactor graphic contains a current value bar and numeric reading for reactor vessel upper head water level. The center portion of the reactoe graphic contains the current value bar and numeric reading for the reactor vessel plenum water level. The bottom portion of the graphic shows a message-" LVL BELOW BOTTOM SENSOR" when the water level is below the last sensor on the probes. These values are calculated usir.g the signals from the two reactor vessel water level probes, each of which has sensors in the upper head and plenua regions of the vessel.
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( ,/ The upper right hand portion of the display gives the Reactor Coolant System subcooling numeric reading and current value bar. A message displaying the appropriate condition, either "SUBC00 LING" or "SUPERHEAT", appears slightly below and to the left of the numeric reading. The value of the subcooling is
' calculated using steam tables, the thres wide range reactor coolant systen pressure channels, and the auctioneered-high quadrant average core exit thermocouple temperature readings.
The lower right hand section of the display contains the numeric value and current value bar of the fif th highest thermocouple reading, selected from the valid core exit thermocouple readings. 8561c/0328c C-20
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Y ^? Yh j.[. bh @ f' k .f??5 ~- ., b' e> eagga g kyr y gyk:QW q'.q" m 'x ~ ' p~ A - O : - j$ MS9%gF@ M FM)8 Y# $ ' EI M . A h%y }.l. llp m A" ' ->= 5 ' r= ' Figure C 1 CRITICAL HEAT SINK (CSF-H) s ; } , qj .The CSF-Heat Sink display is shown on Figure C.11; it contains a graphic representation of a steam generator on the left section of the display. At the top of the steam generator graphic cre shown the four numeric readings of SG narrow range water level. These values are each calculated from the four narrow-range readings for that steam generator. Below the numeric readings are current--value bars for these same readings. The upper right portion of the display presents the numeric readings and current value bars for the four steam generator steam line pressure readings. Each of these values is calculated from the four pressure channels for that steam generator. (s_ ,/ The lower portion of the display shows auxiliary feedwater flow readings. A horizontal bar of total auxiliary feedwater flow is showti. To the right of ~ this bar are the four individual auxiliary feedwater flow numeric readings. These values are added and displayed as the total reading for the horizontal bar and the nume-ic total reading, displayed directly below the individual readings. ( %./ 8561c/0328c C-22 l l ~' . j E 7 % +- > Q O Ojq. ;. g :- > + x. - a . . _..:t L.G... . N: - '2%w "l ?, f.O . j k' ({_5.% ;M.,; f..,-' p?. f [j [.y l. O [ O ' O .. O l \c Q f . ..?: ')u . .' yll. -- *o-. y, ;3 .. it. . . ' L ~; ; .. :-{k-. $ ? :'. 6 ; ; 1' m. . m a m.Y m . -- m .i : # >4 ? J. 7,'
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' '~ ~ ' .f f f( may w M., M A e sos m~ : *MA% .l [ ,. f 5{ffff;n w g o HN. b#4 $0F $ . F'qme C 1 m F. s . CRITICAL INTEGRITY (CSF-P) . :-c .!l '\ q,i ?The CSF ' Integrity display is shown on Figure C.12; it has the following features.- fThe upper left section contains numeric readings and current valu.e hers ~ for the four RCS loop wide range cold leg temperature readings (Teold). ' The lower left section of the display shows the calculated largest drop in . temperature, as measured by the four loop wide range cold leg ~ . temperature detectors, over the preceeding-sixty minutes. In addition, the associated. loop is displayed. 1. k . The upper right portion' of the display contains a plot of reactor coolant ' system' pressure versus reactor coolant system cold leg temperature. The plant . operational limits are shown on this curve 'along with the current values of pressure and temperature. Reactor coolant system pressure is displayed in ; ./~i .It is calculated from the three wide ' ( ,) numeric form to the left of the plot. range reactor coolant system pressure signals. The reactor coolant system cold leg temperature is displayed in numeric fore below the plot. It is calculated by selecting the lowest'of the four wide range cold leg temperature readings. pr L 4 The lower right portion of the display is a plot very similar to the plot in [ the upper right.- This display is also a plot of reactor coolant system L [ pressure versus reactor coolant system temperature. The plant cold L overpressure limit curve and tha current pressure and temperature values are ~ shown on the plot. To the left of the plot is the numeric reading for the current value of reactor coolant system pressure, calculated from the two l (" k b E l 8561c/0328c C-24 reactor coolant' system pressure signals used for cold overpressure (3 fs ] ' protection. Below the plot is the reactor coolant system temperature, icalculat'ed by selecting the lowest reading of the four wide range cold leg . loop temperatures and the four= wide range hot leg temperatures. O J I ( -8561c/0328c C-25 l + 1 1 . - - - , - . . . - , - . - - , , . . - . - . - - - _ . . _ . , . . , . _ . . . - - . . - , . - . - - , . , . . - - - - - - - . . - - , - _ _ _ ,n,,- - f 1 l l 'N . . M = f @$@$Q. 3&~ &R[&.,h; O. f M ' &f'n W l A&' I c * $ k: r) i' .l;4 (.W. .;r .F.* Ws:.;X ;' .h.h ;;.7.fW .,Q%yo.j.k (
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/ l / " Y h Figure C 1:- ~ CRITICAL INVENTORY (CSF-I) 7- . L{ ) %/. The CSF Inventory display is shown on Figure C.14; it has a graphic representation of the reactor vessel in the left portion of the display. _ Major. structural features of the reactor vessel are shown. The upper portion of _the reactor vessel graphic contains the current value bar and numeric reading of the reactor vessel upper head water level. The middle portion ..contains the current value bar and numeric reading for the reactor vessel plenum water level. . A message "LVL BELOW BOTTOM SENSOR" appears in the lower portion of the graphic when the reactor vessel level is below the last sensor on-the probes.. These values are all calculated using the signals from the two reactor vessel water level probes, each of which has sensors in the upper head .and plenum regions of the vessel. ij._ . ( ). - The - right ' side of the display is a graphic representation of the pressurizer. A numeric value and current value bar for pressurizer water level are displayed. This value is calculated from the four pressurizer water level channels. , N- / l l 8561c/0328c C-29 i f gur=Q . ' ,'Pq ' T - d M ' q. . i* D gb
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, b Figure C.16 FULL SIZE ASCll KEYBOARD C-33 4 APPENDIX D CRITICAL SAFETY FUNCTIONS STATUS TREE LOGIC c. s + 4 O 8591c/0331c + _ , ' '.~
- I ,
-Q APPENDIX D -CRITICAL SAFETY FUNCTIONS STATUS TREE LOGIC l LIST OF FIGURES FIGURE NO. TITLE-D-1 Subcriticality Safety Function Status Tree D-2' Core Cooling Safety Function Status Tree D-3 Heat Sink Safety Function Status Tree D-4 Integrity Safety Function Status Tree D-5 Containment Safety Function Status Tree .D-6 Inventory Safety Function Status Tree () l r I l l: D-i 8591c/0331c s' s, \.j SUBCR!TICALITY SAFETY FUNCTION STATUS TREE RM l E N Extended Range NO T N Nucles' Power oss han 5% YES Orange Yellow Extended Range NO SUR More NO SUR Zero Neg Than fN or Neg. -0.2 DPM YES YES I CSF SAT Extended Range NO Power Less Than SE - 6% YES Yellow I NO SUR Zero I or Neg. YES NOTE: All Values are l Typical. See Set l - Green Point Documentation CSF SAT for Actual Values O- Figure D-1 ORG.F7(SFST 3) / % w/ CORE COOLING SAFETY FUNCTION STATUS TREE Red E N Core Exit NO T N TCs Less Than E 1200*F R YES Orange Core Exit NO TCs Less Than 730*F YES '~) . A Yellow RVWL NO Plenum Greater Than 20% YES I Yellow RCS Subcooling NO Greater Than or Equal to 31 *F* YES i I Green
- Normal Containment Value CSF SAT NOTE: All Values are Typical. See Set O Point Documentation for Actual Values Figure D-2 oRG. F7 (SFST 4)
m .; ') . xv. HEAT SINK SAFETY FUNCTION STATUS TREE Total Feedwater NO Red Flow to SGs Greater Than 580 GPM YES E Yellow N N/R Level in at . NO Pressure in all NO T 4 Least One SG SGs Less than Greater Than 6%* YES - 1325 psig YES NO Yellow ' b( D N/R Level in all SGs Less Than 87% YES 1 l Pressure in all NO Yellow i SGs Less Than ! 1285 psig YES Yellow i N/R Level in all NO j SGs Greater Than 6%* YES Green
- Normal Containment Value CSF SAT NOTE: All Values are I Typical. See Set Point Documentation for Actual Values Figure D-3 l
l ORG.F7(SFST 2) I o /*9'- ; d.-) INTEGRITY SAFETY FUNCTION STATUS TREE All RbS Pressure NO Red See Plant Cold Leg Temperature Operatonal Points to the Right Limits Graph of Umit A . YES Orange I I All RCS Cold Leg NO Temperatures Greater Than 242*F YES Yellow All RCS Cold Leg NO (,, [~'^)i Temperatures Greater Than 272*F CSF y Temperature NO YES O" SAT y =) . Decrease in All RCS E Cold Legs <100*F in Last 60 Minutes YES R NO Orange - All RCS Cold Leg Temperatures Greater Than 242*F YES See Cold Overpressure ! yeitow limits Graph RCS Pressure NO [ Less Than Cold Overpressure Limit YES l 1 l l l CSF Green RCS Temperature NO SAT ( Greater Than 350*F CSF YES SAT l
- NOTE
- All Va ues are l Typical. See Set Figure D-4
! Point Documentation for Actual Values ORG.F7(SFST 1) l 'w )\ CONTAINMENT SAFETY FUNCTION STATUS TREE l l E N Contanment NO T N Pressure Less g Than 56.5 psig YES Orange Containment NO Pressure Less Than 20.0 psig YES .[Ag \ Orange Containment NO Water Level Less Than 68 inches YES Yellow Containment High NO NOTE: All Values are Range Radiation Typical. See Set LessThan 500 R'HR YES Point Documentation for Actual Values - Green CSF SAT ( Figure D-5 ORG.F7(SFST 5) .~ . ! } INVENTORY SAFETY FUNCTION STATUS TREE Yellow RVWL NO Indicates 100% Upper Head YES I Yellow E N Pressurizer NO T N Level Less , g Than 92% YES [')1 q - Yellow Pressurizer NO Level Greater Than 17% YES Yellow
- RVWL NO i i Indicates 100%
l Upper Head YES NOTE: All Values are Typical. See Set CSF SAT Point Documentation for Actual Values O \ Figure D-6 ORG.F7 (SFST 6) i ._. ._ .,. - . - . ~ - . -. .. - - . . ._ _ _ . .. . - _ _ . I I I l i h 5 l l i APPENDIX E LIST OF ACRONYMS 1 I i i t ! I O ; l' i l i i I i i t i I r i i l 1 LIST OF ACRONYMS d j Acronym ' Definition .v-AC . Alternating Current ACK Acknowledge AFW Auxiliary Feed Water 'AHSAC- >ATWS Mitigation System Actuation Circuitry ' ANSI. -American National Standards Institute ASD Alarm Summary Display 'ATUS Anticipated Transient Without Scram AUTO Automatic C. Core Cooling / Critical .CFR' Code of Federal Regulations CNTMT Containment COMS Cold Overpressure Mitigation System -CPS Counts Per Second CPU Central Processing Unit ' CR ' Control Room . ,. g CRDR Control Room Design Review )_ ~ CRT: Cathode Ray Tube CS- Containment Spray CSF. Critical Safety Function 'DAS' Data Acquisition System DPM Decades Per Minutes EAR Electrical Auxiliary Building -EOC Emergency Operations Center EOP Emergency Operating Procedure ERFDADS- Emergency Response Facilities Data Acquisition and Display System - ERG Emergency Response Guidelines ESF- Engineerc. Safety Features FHB Fuel Handling Building , FRG Functional Restoration Guideline FSAR Final Safety Analysis Report , GPM Gallons Per Minute m ( 6 i-E-1 8616c/0331c ,_. _ _ . - _ , _ - _ _ _ _ _ _ - ~ . _ , _ . _ , _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ -_ _ _ _ _ - - - ~ ' p i. QY ,0 W . LIST OF ACRONYMS );,,lAcronya' Definition -H Heat Sink HLP. . Houston Lighting and Power JI ' Inventory .;p.. w M iIEEE Institute of Electrical and Electronic Engineers S y Y -: INOP Inoperable ISOL . Isolation 'kV Kilo-Volt -LOOPWR- Loss of Offsite Power LOS; Line Of Sight N Normal .A N/R . Narrow Range _ r.. NRC Nuclear Regulatory Commission NSAC Nuclear Safety Analysis Center NSF Normal Safety Function OPG~ Optimal Recovery Guidelines P - Integrity \,j. - 'P41D -Piping And Instrumentation Diagram . . P'CY Plant Computer. . s,. .
- PORY Power Operated Relief Valve PSIG'
.h. Pound Per Square Inch Guage ,QDPS. Qualified Display Processing System R/HR Roentgen per Hour y RAD Radiation RCB Reactor Containment Building ,, :4RCS Reactor Coolant System RECIRC Recirculation RG Regulatory Guide RHR' Residual Heat Removal -RMS Radiation Monitoring System RVWL Reactor Vessel Water Level j .RWST Refueling Water Storage Tank
- RX Reactor
. S Suberiticality l ' y. 1[D) i E-2 8616c/0331c f p-- r . LIST OF ACRONYMS ., Acronym Definition SAT Satisfied SG Steam Generator SI Safety Injection SPDS Safety Parameter Display System STM Steam STP South Texas Project SUR Startup Rate Thermocouple l T/C .TRP Trip TSC Technical Support Center UPS Uninteruptible Power Supply .V Volt V&V Verification And Validation VCT Volume Control Tank W/R Wide Range n . WOG Westinghouse Owners Group 1 Z Containment ^ S i % ,) E-3 8616c/0331c . , . . ,,}}