ML20086M664

From kanterella
Jump to navigation Jump to search
Forwards Functional Description of Safety Parameter Display Sys,Per Generic Ltr 82-33 Re Compliance W/Suppl 1 to NUREG-0737.Encl Also Provides Results of Review of Verification & Validation Plan Recommendations
ML20086M664
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/10/1984
From: Geier J
ILLINOIS POWER CO.
To: Schwencer A
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, U-0695, U-695, NUDOCS 8402170001
Download: ML20086M664 (42)
v • d • e


Text

. .. ..

f o

  • U- 0695 0210.6-L L30-84 (02-10)L ILLINDIS h0WER COMPANY February 10, 1984 CLINTON POE:R STATION. P.J. BOX 678. CLINTON, IL'INotS 61727 Docket No. 50-461 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Clinton Power Station Unit 1 Safety Parameter Display System (SPDS)

NUREG-0737, Supplement #1

Dear Mr. Schwencer:

NRC Generic Letter 82-33, Supplement 1 ro NUREG-0737, provides clarification of NRC requirements related to SPDS, among other Emergency Pesponse Capability initiatives. In a letter, dated April 13, 1983, Illinois Power Company's (IP) Emergency Response Capability Implementation Plan (ERCIP) was provided to the Staff as required by Generic Letter 82-33. IP Letter U-0676, dated October 28, 1983, provided you with the SPDS Pre-implementation Package. This package consisted of documentation related to the SPDS Verification & Validation (V6V) Plan, the SPDS Safety Analysis Report, the SPDS Parameter Set Validation Report, and the results of various aspects of Human Factors Evaluations of the SPDS.

IP has evaluated the recommendations contained within the independent V&V reviews (i.e. the SPDS Parameter Set. Validation Report on the Human Factors Review of SPDS) and the review of Human Factors performed by an interdisciplinary IP review team. As a result of these evaluations and additional design engineering work the attached documentation, entitled "Clinton Power Station Unit 1 Safety Parameter Display System Functional Description", is provided.

This information has been provided to accomplish the following:

1. Fulfill IP's commitment to provide'the results of our review of the V&V and Human Factors-recommendations, as noted in our SPDS Pre-implementation Package (U-0676). Section 3.2 of the SPDS Functional Description addresses the Human Factors aspects of SPDS. Section 3.4 of the SPDS Functional Description provides a revised SPDS Safety Analysis Report.

4

e -t U 0695 0210.6-L L30-84 (02-10 )L February 10,1984 2.. . Provide the Staff with the details of the Clinton SPDS design needed for your review of CPS' compliance with NUREG-0737 Supplement #1 (Section 4). IP committed to provide this information in telecons with G. A. Harrison (NRC Clinton Licensing Project Manager) and R. A. Kendall' (NRC ICSB reviewer) on January 13 and February 3 respectively. As noted during these discussions with the Staff, IP has requested an expedited review of this information. IP is ready to procure hardware / software to implement the SPDS and NRC concurrence with our proposed design is requested before proceeding.

During these recent telephone conversations with R. A. Kendall, some concerns of the NRC Staff were expressed related to the proposed isolation of the computer from safety system signal transmitters. Since a vendor to supply these isolation devices has not yet been authorized, we cannot resolve those concerns at this time. Efforts are underway however, to obtain information concerning the digital / analog signal isolation devices and IP will provide it in Itarch 1984.

Illinois Power representatives would be pleased to meet with your Staff concerning any aspect of SPDS at your convenience.

Sincerely yours.

  • F J. D. ier Manager Nuclear Station Engineering GEW/ lam Attachment ec: G. A. Harrison, NRC Clinton Licensing Project Manager R. A. Kendall, NRC/ICSB J. Joyce, NRC/ICSB NRC Residen: Office Illinois Departmen; of Nuclear Safety I

l i

1

l 1

l CLINTON POWER STATION UNIT #1 SAFETY PARAMETER DISPLAY SYSTEM FUNCTIONAL DESCRIPTION

m TABLE OF CONTENTS 1.0 Safety Parameter Display System Functional Description 1.1 General j 1.2 Purpose 2.0 Implementation of SPDS 2.1 General Operational Specification 2.1.1 Concice.Disolay .

2.1.2 General Availability 2.1.3 Normal Oldration 2.1.4 Personnel Requirements 2.1.5 Location-2.1.6 Reliability 2.2 Human Factors Design' Specification 2.2.1 Human Factors Shandard 2.2.2 Control Room' Access

2.2.3 Display Compatibility 2.2.4 Display Access 2.2.5 Display Format Simplicity 1 2.2.6 Pattern and Coding Techniques 2.2.7 Audible Alarm

'2.2.8 Simplified Human-machine Interface 2.3 SPDS Availability 2.3.1 Reactor Above Cold Shutdown i

2.3.2 Reactor In Cold Shutdown ,

2.4 SPDS Parameters-(see Appendix 4) 2.4.1 Reactivity l Control 2.4.2 Reactor Core Cooling and' Heat Removal From The Primary System 2.4.3 Reactor Coolant System Integrity 2.4.4 -Radioactivity Control 2.4.5 Containment Conditions

. r -

, # g. ,.--

4y .w, --- -, ,c v-

^ ,

.- . x 2.$ 'SPDS. Display Characteristics 2.6.1 Data Validation 2.6. 2 ~ . Data Updates 2 . 6'. 3 - Magnitudes and Trends o 2.6.4 Safety' System Isolation 3.0 Implementation

-3.1 New Instrumentation 3.2 Input Point? Assignment

-3.3. Software Changes 3.4 HUCLENET Changes 4.0 Appendices 4 .1'. ~ Appendix 1 - SPDS SS Display 4.2 ' Appendix.2 - Alarm l Initiated Display 4.3' Appendix-3.- ARM /PRM Status' Grid' 4.4 Appendix 4 - Point Description Chart

- 5 '. 0 References

-ii -

v f' l M

1.0 Safety Parameter Display System Functional Description 1.1 General The Safety Parameter Display System (SPDS) is being implemented as a part of the Display Control and Performance Monitoring Systems (DCS/PMS) currently installed in the Main Control Room. The PMS/DCS is the plant process computer system.The Number 5 CRT in the NUCLENET (Principal Plant Console) has been designated as the SPDS Display. Figure 2 shows the the location of the NUCLENET console, Panel P680, and Figure 3 shows the layout of the console and the location of CRT 5.

The CPS SPDS is not seirmically qualified nor Class lE powered equipment.

The purpose of the SPDS is to assist control room personnel in evaluating the safety status of the plant. The SPDS is to provide a continuous indication of plant parameters or derived variables represent-ative of the safety status of the plant. The primary function of the SPDS is to aid the operator in the rapid detection of abnormal operating cc4ditions.

Implementation of the SPDS Display will be accomplished by installing of a permanent display in the DCS and a temporary Alarm Initiated (AID) Display which will be automatically displayed on all nine NUCLENET DCS displays when an alarm of and AID parameter occurs. Radioactivity control information is available on a separate display.

Information from Chapter 6 and Chapter 15 of the Clinton Power Station Final Safety Analysis Report divides potential accident or transient events into eight individual categories. These FSAR categories are as follows:

Decrease in core coolant temperature.

Reactivity and power distribution anomalies.

Anticipated transients without scram.

Increase in reactor pressure.

Decrease in reactor core coolant flow rate.

Decrease in reactor coolant inventory.

Increase in reactor coolant inventory.

Radioactivity release from a subsystem or component.

These categories of events have been considered in the selection of the SPDS parameters. Each of these categories can be associated with an SPDS parameter group listed in Section 2.4. The detailed basis for the SPDS parameter selection is fully described in the CPS SPDS Parameter Set Validation Report (Reference m . _

_ ;; r .

5.27). This report was submitted to the NRC via IP letter U-0676 dated October 28, 1983 (along with the References 5.25,-5.26, 5.28 and 5.291 Reports).

_ 'The Safety Parameter Display System (SPDS) is being implemented within the scope of Reg. Guide

.1.97 as many.of the parameters associated with 1.97

aro also essential to SPDS. Reg Guide 1.97 design and

~ installation is proceeding under separate design control (Reference 5.24). It will be assumed for this document that Reg Guide 1,.97 parameters are already an integral part of the Display Control and Performance Monitoring System- (DCS/PMS) . Input point listings in this document will.be complete, but only those points not identified for Reg Guide 1.97 will be designated "new" SPDS parameters.

1.2 Purpose The purpose of this document is to describe how the SPDS at Clinton Power Station (CPS) will-be implemented with new'and existing hardware and software. The intent is to provide _the information necessary for detailed hardware and software design.

2.0 Implementation of SPDS 2.1 General Operational ~ Specifications 2.1.1 Concise Display The SPDS displays are, by the NUREG-0737 Supplement #1 definition, concise displays of critical plant parameters. Section 2.4 specifies parameters to be displayed and documents the basis.for that selection.

One cathode ray tube (CRT) currently available on the Display Control System (DCS) will be dedicated to display the majority of information concerning plant- ,

critical safety parameterc (grouped as '

described'in Section 2.4). The SPDS'CRT

~

will be the number 5 CRT in the Principal Plant 'C >nsole (PPC) or NUCIENET. : Appendix ,

1 specifies the graphics and associated  !

parameters for the SPDS Permanent Display j Format. Appendix 2 specifies the Alarm Initiated Display (AID) which is the lower portion of the_SPDS Display Format.

One CRT is also available in the Main Control Room'for display of information'from the Area-and Process Radiation Monitoring (ARM /PRM) system. Appendix-3 specifies the graphics and parameters-for the ARM /PRM System'(Status Grid Display).

2.1.2 General Availability The SPDS will be capable of being displayed during all operating modes of the plant.

The Area and Process Radiation Monitoring System is dedicated to the monitoring of radiation throughout the plant. The Status Grid display is the primary ARM /PRM display. The operator may select other displays, but the system will automatically return to Status Grid display after a uen minute time-out. The Status Grid provides information concerning radioactivity levels throughout the plant with specific numberic identification for each of the radiation monitors.

All the plant critical Safety Parameters will be monitored on the displays. The SPDS display will provide for reactivity control, reactor core cooling and heat removal from the primary system, reactor coolant system integrity, and containment conditions. Radioactivity control information will be available frem the ARM /PRM system.

2.1.3 Normal Operation

- The parameter information available from the SPDS displays will be an integral part of the operating procedures used by control room personnel during normal operation as well as during all classes of emergencies.

2.1.4 Personnel Requirements The SPDS display in the NUCLENET is centrally located and requires no operator interaction except that already designed into the NUCLENET. No additional Main Control Room personnel are required for monitoring SPDS.

The ARM /PRM display is loca'ad in panel P864 in the Main Control Roob. 'It requires no~ operator interaction to provide overall plant radioactivity release information. Alarm acknowledgement and response are included in Control Room Operator training.

2 ~.115 Location l

The SPDS display (CRT 5) is located in the NUCLENET console and is an integral part of the control room equipment. This CRT will be dedicated to SPDS Display. The SPDS Display will be available for call by the operator on any other NUCLENET display. The ARM /PRM is an integral part of control room equipment in Panel P864.

The location of the SPDS and ARM /PRM Displays is such that the control room operators will have unrestricted physical access.

2.1.6 Reliability The SPDS Display will meet the criteria for reliability and availability specified in the DCS Design Specification (GE Drawing 22A4098 , Section 4.1.3).

Display infornation provided by calculated contacts, calculated variables or transformed variables will have the reliability of the Performance Monitoring System (PMS). Appendix 4, column " CAL VAR" specifically identifies these points.

The-ARM /PRM will meet-the criteria established for that system in Section 2.3 of this specification.

2.2 Human Factors-Design Specification 2.2.1 Human Factors Standard

~ The Emergency-Response Program Review Team, comprised of Illinois Power Company personnel and a recognized Human Factors expert, will conduct reviews of the SPDS display as required by NUREG-0737 using the guidance of NUREG-0835 and NUREG-0700 (See Reference 5.25).

2.2.2 Control Room Access The SPDS Display will be located in the NUCLENET Panel P680. The' ARM /PRM display is'iocated in panel.P864 adjacent to the Standby Information Panel,'P678, in the Main Control Room. These panels are integral parts of the control room design

(See Figure
2). The operator's visual access to other control room equipment will not be obstructed.

a.

. o 2.2.3 Display Compatibility The SPDS Display CRT will be interchangeable with other control room DCS CRTs. The-Main Control Room ARM /PRM CRT will be

interchangeable with other ARM /PRM CRTs.

2.2.4 Display Access l

The SPDS Display, with the exception of the Alarm Initiated Display (AID) portion, will be available on any Performance ,

Monitoring System (PMS) CRT. The AID is a i transient display of parameters that duplicate or support permanently-displayed SPDS parameter values.

The Spectral Analysis and Record-Keeping System will receive input from the '

ARM /PRM. Terminals for this system will be provided in both the EOF and TSC which will display radiation information needed

, for the performance of offsite dose I

calculations.

2.2.5 Display Format Simplicity

[

The SPDS Display will consist of a permanently displayed portion and a portion displayed only when one of the parameters is in an alarm state (see Appendices 1 and 2). The display will consist of horizontal bar graphs for dynamic display of data, with quantitative information displayed adjacent to each bar graph. Trend information will be represented by a rate of change with a negative number indicating a decreasing value. Containment Isolation will be represented by a line of letters indicating I(inboard) or O(outboard) isolation for each of the 11 isolation groups. Successful isolation is indicated by a green' letter. The Alarm Initiated Display will be a simple list of 12 parameters with alarm conditions indicated in red. The AID'will only appear in the bottom 12 lines of the display area when an alarm occurs on any one of the parameters. 'The AID will appear on all active DCS CRTs.

i ;*J i

The. ARM /PRM Status Grid display will be an

.- . outline drawing of the Fuel, Containment,

= Auxiliary, Turbine, Control, and'Radwaste abuildings (see Appendix 3). Monitors will

._be-indicated by the presence of the respective . unit number (s) within'the

~ ; building outline. Red will be used to

? indicate a high radiation alarm. Yellow will-indicate an alert or trend alarm (radiation' increasing at a rate exceeding preselected limits).

2.2.6- d

-Pattern.and Co'ing Techniques Alarm points and conditions will,-in-

- general be indicated by the color red, with' normal or.non-alarm conditions indicated in green for digital values, and yellowzfor analog values and-bar' graphs. -

-Cyan will be.used for: alphanumeric labels,

. borders,qand the nondynamic portion of the

. background.--White will be.used to denote low confidence data (see.Section 2.6.1).

The:symbology and color convention used in

-the-SPDS display will be consistent with thatlused in all DCS CRT displays throughout the control room.

Display alarm setpoints will be the same for allidisplays except for1the AID indication of; reactor wide range water

- level. 1The reactor. water level wide

~

~

range parameter will alarm at 1evel 4 and ,

~ level 7:to provide the operator with

-warnings of; potential hazards. The AID portion of reactor. water' level' indication will alarm at reactor SCRAM water levels 3 and 8.

On the-SPDS1 Display bar graphs, alarm set "

points-will-be-indicated by a red grid; line. .The dynamic bar will-in general change from yellow to red when-theEset.

. point is exceeded. Some. parameters have only -low level: alarm: limits. These are l indicated.in theJappendices and"will:be red,-changing-to_ yellow, whenLthe.setpoint is exceeded.

SPDS Display. text will change.from green-to' red _whenever'the-display alarm set

-point"is exceeded. :On'the-ARM /PRM, monitor unit numbers will-be:normally displayedJintgreen and'will, change to

'.[

? -

~

- 6 '-

~

^

. . . , , , , n y, -,

yellow to indicate an alert or trend alarm, and red to indicate high radiation levels.

2.2.7 Audible Alarm All alarms will annunciate audibly in the control room. For the SPDS Display this will be accomplished through the distinct alarm feature described in Section 4.4.1.1.5 of GE Drawing 22A4099, the PMS Design Specification. For ARM /PRM an audible alarm will occur for all system status changes.

2.2.8 Simplified Human-machine Interface Monitoring 90 fixed and up to 42 portable radiation monitoring devices, as well as providing reliable information to an operator on plant safety status on one display, would result in an unacceptably cluttered' display. Therefore, the SPDS will consist of both the SPDS Display and the ARM /PRM display.

Human interaction with the systems will be kept to a minimum and will be consistent with the normal operator interaction with the DCS/PMS displays. For either SPDS display, acknowledgement of alarms will consist of no more than one pushbutton for response in each system.

2.3 SPDS Availability -

The SPDS design availability will be consistent with that specified for DCS/PMS.

2.4 SPDS Parameter Groups and Associated Selection Bases 2.4.1 . Reactivity Control Above the source range, once a stable period has been established, changes in neutron flux can be used to determine the reactivity of the core. Control-rod insertion provides secondary information about reactivity control and the ability to support a' scram is determined by the Scram Discharge Volume (SDV) level.

The Average Power: Range Monitor (APRM) channels monitor power during normal operation and indirectly-indicate if negative reactivity has been inserted upon

receiving a Reactor Protection System (RPS) trip by displaying decreasing power.

The APRM display will be a percentage of full poWar indication.

The Source Range Monitors (SRMs) provide neutron flux indication during reactor startup/ shutdown or low flux level operation. The SRMs allow the operator to confirm long term net negative reactivity by observation of power at steady source levels. This ensures safe shutdown and the ability to detect potential restart events. SRM information will be presented as Counts per Second with rate information provided_as period (time for power change by a factor of e) in seconds.

Scram Discharge Volume water level is of

' interest to an operator during non-shutdown. While neutron flux is the actual indicator of reactivity, it is prudent for an operator to be alerted whenever the ability to insert control rods may be jeopardized. An indication of l SDVs A and B level, in gallons, has been l provided on the Alarm Initiated Display portion of the SPDS Display.

2.4.2 Reactor Core Cooling and Heat Removal From The Primary System The primary indication of the ability to remove heat from the reactor vessel is the amount of water in the vessel, whatever the source. Directly related to the removal of heat is the flow of water within the vessel and the pressure of the vessel.

Reactor Wide Range water level, in inches, and Reactor Steam, Feed, and Total Core Flow, in millions of pounds per hour, are

_provided as a permanent part of the SPDS Display. Because of its importance, Reactor Water Level is also provided as a single value in the Alarm Initiated Display _ portion of the SPDS Display.

2:.4.3 , Reactor Coolant System Integrity During normal plant operations, core coolant is monitored via Reactor Feed Flow and. Total Core. Flow. Monitoring 3these-flows 1will provide reactor coolant

' system integrity indication. Excess' flow 1

. ,. - . ~ . - . . ~ . . .. - . - .

l in'the Drywellifloor drain sump is an early indication of' minor cracks or other ,

unidentified-leakage paths. Reactor and

,. Drywell PressuresLare provided as

' indicators of larger reactor coolant leaks.

Wide Range Reactor Pressure and Narrow Range Drywell~ Pressure, in pounds per square-inch gauge, will'be a permanent.

part of the SPDS Display.

-Drywell Floor Drain Sump Flow, in gallons per minute,,will be a permanent;part of the SPDS~ Display.- Because this flow is

, the most sensitive indicator of leakage,

.its maximum allowed value is a standard l technical specification basis for l .. shutdown,~and it will also be displayed
on'the Alarm-Initiated Display portion of the SPDS Display..

2.4.4. Radioactivity. Control I

il Forty-six' fixed digital Area Radiation Monitors (ARMS) are located throughout the

. plant to monitor gamma-dose rate. ; Twelve portable ARMS are available for connection

.to other ports'in the plant. Fourteen fixed - digital Constant Air Monitors (CAMS)

measure airborne radioactivity within the
. station, with ten portable CAMS available.

'One. Process Radiation Monitor (PRM) samples the common' station HVAC exhaust.

(with one in standby) , one monitors the F

' Standby Gas Treatment ~ System (SGTS) (with one in standby) , one each is included in Pre- and Post-Treatment Air _ Ejector

.off-gas' (with one in standby: for ' Post' - -

Treatment)', and-one-is included in'the

= Liquid Radwaste Effluent discharge. Six-PRMs monitor..various liquid streams to detect intersystem leakage'of heat exchangers.1

'There-are also 16 safety related'PRMs,

[. with control functions to initiate'SGTS, and secure HVAC ducts on Containment Building Exhaust,. Containment Building

- Fuel' Transfer. Vent Plenum,. Fuel Building

' Exhaust, or Main' Control' Room air' intake.

f-1 .

d

.,tsc w+q*r+iya 1 M m -e +g tv My,yq vg rug-e ym t-py- pdMe*=ge-*1-p,r? >-

Status of all 90 of the permanent monitors

and up to.22 portable monitors connected to the system communication ports will be provided on the ARM /PRM Status Grid. The following conditions will be indicated by color changes of the monitor unit number

light blue communications fail red high alarm yellow alert / trend alarm dark blue not initialized white calibration /

check source maintenance flush local control green normal / alarm off 2.4.5 Containment Conditions In addition ~to those parameters already specified, it is essential the operator be aware of containment pressure and the status of containment isolation in order to ascertain conditions within containment. Additional information that is useful to the operator includes drywell temperature, containment temperature, and containment hydrogen concentration.

Containment pressure, in pounds per. square inch gauge, will be a permanent part of the SPDS Display.

Containment Isolation, both inboard (I) and outboard (O) , for each of the 11 containment isolation groups specified in CPS Procedure No. lON4001.02S', AUTOMATIC ISOLATION will be indicated as a single character (I or O) for each group, with green indicating isolation has occurred and red indicating a failure to isolate e.t least one valve'in the group.

, containment isolation will be a permanent part of the SPDS Display.

l Average: suppression pool temp, in degrees l Farenheit,. will be a-permanent part'of the l SPDS Display.and indicated on the AID.

The Alarm Initiated Display portion of the SPDS Display will providef drywell and.

containment temperatures ~in degrees' l I Fahrenheit; suppression pool level in 1

-feet;-containment and drywell pressures in- j 1

,, - , s, ,

c. .

, pounds'per square inch gauge; and containment-hydrogen concentration expressed as a percentage.

To indicate steam relief valve (SRV) status', the alarm initiated display will include a composite SRV status which will display an alarm if any one of 16 SRV's is

. open or has opened. This SRV status information will be provided by signals from the SRV Acoustic Monitoring System.

2.5 -Emergency Operations Facility and Technical Support Center-A Performance ~ Monitoring System CRT and associated.

controls, similar to those available on the control room supervisor's console,-will be installed in the-

, Emergency Operations Facility -(EOF) and the Technical i' Support Center (TSC). These CRTs will be capable of calling up any,DCS/PMS display, including the SPDS Display, except that the Alarm Initiated Dislay will-not be available in the EOF or TSC. A standard feature of PMS is that an operator, including the.

. supervisor, may call up'for review the current status of any point, including calculated variable and transformed variable points. This allows the TSC and EOF access to all AID information available to the DCS/PMS even though not specifically' intended for EOF /TSC.

Section 2.2.4 describes how' radioactivity control information is provided in the EOF and TSC.-

2.6 SPDS Display Characteristics 2.6.1 Data validation Data validation is defined.to be an equipment or prodedure.to obtain increased assurance that parameter values displayed on the SPDS display ~ represent the true.

, value~of the parameter. Validation can-be-1 accomplished in a number of different ways:

(1):by referring to hard-wired' indicators and records which display the'same.

information present'ed on the display.

.All Reg. Guide l.97fparameters-used in the-SPDS display'will be also displayed.on recorders and indicators in the control' room.

f -

-11 z'

(2) by referring to hard-wired indicators and recorders which display related information which can be used to confirm or challenge the displayed information.

(3) the presence or absence of alarms and status indications can also be useful in validating the displayed information.

1 (4) range checks of the inputs by the computer system will detect and flag gross instrumentation failures such as ,

shorts, open-circuits and censing l element failures.

(5) cross checking of redundant computer inputs of the same parameter.

(6) cross checking of related parameters which confirm or challenge the parameter being validated.

Real-time data validation is a feature of DCS/PMS. Details of the validation are described in Section 3.2 of GE Drawing 22A7767, DCS Product Specification and an identical section is included in the draft PMS Product Specification. A general outline of data validation to be performed on SPDS Display signals from DCS/PMS is provided below:

Analog Signals Hardware checking Offset correction Gain compensation Digital Filtering Reasonable Limit Check Data Compression Calibration Correction Drift Testing Conversion to Engineering Units Digital Signals Input status change Group failure Change of state For invalid signals, the last good value will be substituted and displayed in white to indicate a low confidence.

d A real-time comparison of redundant signals for'drywell pressure will be performed.

A regular, schedule (per Technical Specifications) of sensor-calibration and alarm checks'will be performed on ARM /PRM

-monitors to ensure the validity of radiation monitoring information.

The DCS/PMS and ARM /PRM software will ,

provide the operator the on-line capability for verifying alarm setpoints._ Changes to alarm setpoints in DCS/PMS require reinitialization of the system. The loss of display during reinitialization'will not exceed 2 minutes. ARM /PRM setpoint changes will be made with no loss of display availability.

2.6.2 Data Updates DCS will have a-response time, from sensing of a significant change to updating the associated display,-that is within the bandwidth of the instrumentation loops themselves.

Calculated variables and transformed variables will'be updated at a pre-selected rate of from 2 to 10 seconds.

The update rate will be. selected based upon human factors' considerations.

Signals in this category are:

APRM Power 4 SRM Neutron Flux Reactor _ Wide Range Water Level Reactor Total Steam Flow Reactor Total Core Flow Drywell Pressure Narrow' Range-Containment Temperature Drywell Temperature 1

Suppression' Pool Terperature Average Containment ~ Isolation Valve Status

'All Rate of Change Information The ARM /PRM system uses an " interrupt" system to allow each' monitor to' notify the processor whenever an alarm condition =or i

status change occurs. :The time lag.from c sensing an excessive'radiationelevel or ratento displayfof'the~ alarm indication will be no more than'one'(1) second.

5 -

=

, _ , . _ ~ -- _ . - - - - - ,

O

  • 2.6.3 Magnitudes and Trends All analog SPDS parameters on the permanent portion of the SPDS Display will be represented in three forms.

Quantitatively as a digital representation in engineering units, qualitatively as a dynamic bar graph, and as a transformed variable providing rate of change (trend) information. The formula for calculation of the rate of change is specified in Section 3.3.5 of GE Drawing 22A7761, PMS Product Specification.

Radiation monitor trend information will be presented on the Status Grid of ARM /PRM as a change in color (to yellow). The Control Room operator may call up displays that specify the time period over which the radiation is detected as well as the type of radiation detected (e.g., gamma, high range noble gases, beta particulate, radioiodine).

As a backup, in addition to the trend information available in the Main Control Room Radiation Protection (RP) personnal will provide procedures to ensure the ARM /PRM operator in the RP Office notifies the Control Room Operator of radiation level trend alarms.

2.6.4 Safety System Isolation All SPDS Display process input signals, which are safety related, will be connected to the DCS/PMS process interface using isolation devices.

All Safety related radiation monitoring devices will be connected to the ARM /PRM interface using isolation devices.

3.0 Implementation 3.1 New Instrumentation The Point Description Chart, Appendix 4, lists all variables needed for SPDS implementation. Point Identifications (ids) are indicated for those variables-already available in the computer (PMS or DCS). "Later" in the Point ID column indicates a variable not currently implemented. Those points identified as "Later" and not identified as Reg. Guide 1.97 are being implemented solely to support SPDS.

For those points solely in support of SPDS, an "X" in

. o the " CAL VAR" column indicates a'psuedo point derived in the PMS or DCS software from other external points.

New instrumentation must be developed for any point identified as later that.does not have an X in either the "1.97" or the " CAL-VAR" column.

3.2 Input Point Assignment-3.2.1 1RFBA301 (Drywell Floor Drain Sump Flow) will be moved from the BOP computer to DCS.

3.2.2 The -following signa 3 s will be required as direct inputs to DCS:

Reactor Total Feed Flow Drywell Floor Drain Sump Flow Suppression Pool Level Containment Pressure Containment Hydrogen Concentration 3.2.3 SRV points will be monitored by acoustic monitor system inputs.

3.3 Software Changes The AID program software must be modified to incorporate the SPDS parameters.

3.4 NUCLSNET Changes The utilization of CRT #5 for SPDS will require re-engraving system select switch label plates for all NUCLENET CRTs. The fifth position on the upper switch will be relabelled from "CRD" to "SPDS/CRD", the sixth from "NMS" to "NMS/CRD".- The eighth posi'; ion of the lower switch will be relabelled from "H" to "S".

'In order to implement an audible alarm, appropriate wiring and devices willLbe added to the lighted annunciator described in Section 4.4.1.1.5 of GE Drawing 22A4099. The audible alarm will be distinguished from other_ control room audible alarms.

3.5 Integrated Plant Operating Activity Matrix

~

In order to irplement-the redesignation of the same selection switch positionffor all CRTs, it is-necessary to delete one Feedwater Display and move ~one Turbine System Display.

'Since all information on.the 3H, "Feedwater System Data -Emergency Shutdown" display is duplicated on other. displays,_the 3H display.will be deleted. The Plant. Operating Activity Matrix, Fig 1, indicates the

. o 3E display is the automatic display for Emergency Shutdown. The SE display will be renamed "Feedwater System Data - Emergency Shutdown."

8A is currently a spare display designation. The 8H display will be redesignated 8A.

4.0 Appendices 4.1 Appendix 1 - S9DS SS Display 4.2 Appendix 2 - Alarm Initiated Display 4.3 Appendix 3 - ARM /PRM Status Grid 4.4 Appendix 4 - Point Description Chart 5.0 References 5.1 NUREG-0696 Functional Criteria for Emergency Response Facilities 5.2 NUREG-0700 Guidelines fo? Control Room Design Reviews 5.3 NUREG-0737 Clarification of TMI Action Plan Requirements 5.4 NUREG-0835' Human Factors Acceptance Criteria for the Safety Parameter Display System (Draft Report for Comment) 5.5 Supplement 1 to NUREG-0737 Requirements for Emergency Response Capability (Generic Letter No. 82-33) 5.6 GE Drawing 22A4098 Display Control System Design Specification 5.7 GE Drawing 22A4099 Performance Monitoring System (NUCLENET) Design Specification 5.8 GE Drawing 22A7767 Display Control System Product Specification 5.9 GE Drawing 22A7761 (Draft) Performance Monitoring System Product Specification 5.10 Regulatory Guide 1.97, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident. (Revision 3) 5.11 Eberline Radiation Monitoring Erstem for Illinois Power Corporation, CPS Unit 1, Volume 1 5.12 Clinton Power Station Specifications K-2928 Radiation Monitoring Equipment 5.13 Clinton Power Station. Safety. Parameter Display System Requirements: Document ~rev. 0 5.14: . CPS No. 0AP1038.01S, CONTROL.OF. TECHNICAL SPECIFICATIONS i

! 5.'15 CPS'No. 0AP1204.01S,. LICENSED OPERATOR' TRAINING

5.16 -CPS No. ORP7400.00N~, PROCESS RADIATION MONITORING

- SYSTEM MANUAL; .

5.17- CPS.No. ORP7400.03N,.O'PERATION 0F CENTRAL CONTROL i

TERMINAL CRT' 5.18. CPS No.;10N4001.02S, AUTOMATIC ISOLATION 5.19 G.E. DWNG 287A4061 Rev 1 PCS~I/O List 5.20 G.E. DWNG 287A5583AC Rev 3 PMS I/O List

[ G.E. DWNG 287A5591AC Rev 2 DCSLI/O List

~

5.21

5.22- G.E.-DWNGL22A7892 Rev 1 DCS Display Data f

i 5.23 S & L Intter SLCN-089 of August.11,-1978; Enclosure 1; i- Display Control System (DCS)- Performance Monitoring-

{ System-(PMS)1 Computer Input List, Rev.'l.1

-5.24 Letter, Illinois Power Co. to NhC'; "Clinton-Power 3 Station Compliance Report . Regulatory Guide 1.97";

dated. September 9, 1983.

-5.25 "Clinton Power: Station Verificationa And Validation.

Plan-for-Safety. Parameter Display System.", dated-October. 19,-1983.

4 5.26 " Illinois Power Company SafetyTParameter Di7 play System' Safety Analysis Report" r 5.27 "Clinton Power Station Safety Parameter Display System

!. Parameter Set Validation: Report" i

' 5. 28. " Human' Factors Review:of the~ Safety Parameter Display System" 5.29' "SPDS-V&V Team Report on'the Human-Factors Review of

.the Safety l Parameter Display System"~

i.

4 4

2 1

,a,_ . .. .x_,..._. _. #. ,_ , .- . . . . . . - _ - - , ,

9 8 f

FIGURES

PLANT OPERATING ACTIVITY FORMAf MATRIX Integrated Plant DCS CRT Operating Assigned Activity to Sys. SPDS Group 1 2 3 4 5 6 7 8 9 COLD STARTUP 1C 2A 3C 4A 5S 6S 7A 8B 9A ACIIIEVE CRITICALITY 1C 2A 3C 4A 5S 6S 7A 8B 9A GRM/IRM OVERLAP 1C 2A 3C 4A SS 6S 7A 8B 9A HEATUP/COOLDN IC 2A 3C 4A SS 6S 7B 8B 9A IRM/APRM OVERLAP IJ 2J 3E 4A 5S 6S 7B 8D 9B HOT STARTUP/ RESTART 1C 2A 3C 4A SS 6S 7F 8B 9B HOT STANDBY 1C 2A 3C 4B SS 6S 7F 8B 9B POWER VARIATION (10-30%) 15 2J 3E 4A SS 6S 7F 8C 9B

=

POWER VARIATION (30-10%) IJ 2J 3D 4J 5S 6S 7F 8C 9B NO" MAL SHUTDOWN PREP 1C 2J 3J 4J SS 6S 7F BC 9B EMERG. SHUTDOWN IC 2A 3E 4A SS 6S 7F 8B 9B EOP SUPPORT IS 2S 3S 4A SS 6S 7F 8S 9S COLD RESTART 1C 2A 3C 4A SS .65 7A 8B 9B TURB ROLL / SYNC 1C 2J 3C 4A SS 6S 7B 8C 9B BASE LOAD SURVEILLANCE lJ 2J 3J 4J SS 6S 7J 8J 9J FIGURE 1

M I;eut/ Proc. rad. mon. -AIP Cont &Pon

$:VACContr. hSSS Proc. In.s t . Trans. Test ilVAC Cntrl Rod Test 2,0P !!iscel. 1eak Det. GSSS Ternp.  !!1scel . BOP NSPS Jet Pump Instr. Leak Det, tSIV Leak Contr. Area / Proc. Rad Plt. Equip. Temp BOP Ann -

Recirc. Flow Cont. Atmos.!!onit. Fire Prot. Plt.Elec.Mtr Swyd Cont.

\ Action 0ff. Gas ,

.{

s .

  1. 'T r.\ ,

,m i

g-

.; or . ; ,

/ .. ..

,,,, :.u, y m,,, u,y .n. ,,,,

_./.; /

. o ,

,,, , : r ,,y< ~,,,a.

, s,,,. .,p.

a, ,,;,- i,,;

r 7a. u

[<

o.nu.,,0

p. eng,,Yy,

. . . , .p. .m.y nc , .

,,,, .,,.u_.ns. ,3,,,e, ou m,,r~.!.,.,.n.. .

2,..

in~t

,,0.

~* u. n %o- ,,,,p3

, , . . - .u.

nn. . ,<~ g,,,

u ,,no n aozon9

.o , -~~

... .,,o

-c an> "",,

.:~

.o i...e

/

< i w .

l . . .

A A. ., 2h

.A. .-, L. /' ' ,

'o ';- b. = b!y I E u = c I  :. ..a

y. w A v6) cc 7,e: no,. c
  • .. u r. , < . . .

~. g .,el::r.ly-.-

r

'"a E,q. j ,l W

,a 6 l Ei

..o. . . . . . r A. .,Y, l,a-- a . .7,3 e - -

E e- ' -

a ejrc

.... .... r 4.u. .-

n. . -.-eku u .... m; z. s' r... = _

,,_ tlca ju 1-n n,.,:,7 A

ae or e

.,1 ,; --

,.,, ,. ...... < . ,,,..  :,.. , . , e. r.. ~3 a =- y e g , ' . y, , .g,

. . 's 2 +.

na m. 'S. .

raos niw ,g,,

uo isoi h

. u l.o.z n, . ..

a;- ,

l 3i . l n o .

or s Sg* ce e .

,6,,

. . a g  : e.. .

g a- g,g g,g

. . . M, =+..

s. 3 es c ot a ,es.- s. - .n.ooc. 6 6ao A

. gr g

,,o. l N . 02 . ,",, " '

I

% o j?,*,; t-F t **

$ O, 1 - (t% #

7 '

A ".,g) o, . ,,...

.u ..,,

.3 4_

y " 8 ....

n s

't C rool *.' -

      • c' a' t.o. t 96-p C").-

'/ ,

.og.. . r /. DE D

-.y.-

nn N

u . ress . 5*

rst *- e. he

.l [ rses ]g 4 N

g;-

g .02 N A gg g [i rt g8 .g* gg i 3' / 'b S' . #

Peas 2 Q,,

_p --- ..

e~, g .dj._,_ < s.e. y

.)~. ; _ .-. .

fECT: n

.... c. , ,

m, om , .... . - . m i m rn mm m_ J lf i  ! /o ,

[  ! / / / /

.... ... .. . i 2.,. i 1 ,.i.. .

.i........ .i". .. .. . p J. , .' -

.g  ;' '/ -

ag. r~---]< .f r y,,

u IV ARM /F$4 PA GLno 1  !

,",'a I

,, a su.

i r --

/

ra ir t

ji.ua c.c a. .-

= .. i.n --- . uf .. .

.C l sa ')

/

o' . ,:, ./ - . ., o n . ~  :,

?.Sy . . . . .

me

~

el61 *,

~ s- 5' o.

w r.

e' .- j' .v 1

k 6,

/

ns. su' 'pg e. era;c oiloa _. - ,, w tr - I a

[/-

f ,

_D

  • c. .!'_*! . .N is 0 =;= N D

'/,j .

i

,/ /' / / e.

/

' (/

't

  • o.iu! .. n ,.o.

."? "

cui u

$"o' L) oi----

t.c Z~E

-ura . no. ,m A /

/ / > ,I [ '. / -/ / , *:*

--- T- ,

a - -

u

_ c R.e e

/

$ $/

8' * .

- t- .

. -t "- o c 9 f

o. c a c

, , ' , ., . ~ c

. ,,, n

,. . ~ . = _.

q- ro,m,1 f 2:. run *

..u r

~ j f7 i . _ _/l7, 'l .

..2. . , . . ,w n., oc r . . . . .

-x. ~ . . a..

,n, s.o n. rc \

.. . . o, e

_.. . s s . b o

...a..  :;

,, c u.

m.

. ia .

a .

'. e n- -

/ a

! = t o ' c ', e ' . , , '*

t .,

/

/,i '

/,

,- == a a u 2' : . g.,

a ?. ..I 7

o 3 .

= .

0 !: .oz .o*,oag,' m ! os =on os;on ,

-m7 3 /g ,/

w. n e r+i uno I
  • Er-Ae N e,so ~

~.7*.

uns m n 'r / -7 I

~;T, . ,7G.T. Ih'*e!. eer'iTa .. e ir 5

,ii tH.o J'

TT , 'l rre .i ia p i. eris U i se' . L, f6is77 'UPN 5 r er n it.e8 il P l. c ,oh. x

~

'r -

c e e l. e Vrsi e.A'n.ev.oslT a go.pn nm )poulrm >ge.]ra. )lcoi> K e > cos)(onpmyeosco ai ipo po.)i s .ge.) tro

, mp o pal,(N) ,

e Mg) sg,N ) ipDOlf4)pNHik. DQl M)p p N , N*..

hq) p , _ (M)fDOpH}gM 00, en..

oe) 04 NSPS DCS Inter. ' Proces. Rad. Cont. Air. Font.

Ne ut /p roc . Ra.l .!!ont Rod Drive BOP ttiscel. S t m..;,v lnfo icia Consol 'ECCS Seismic  !!SIV Leak RFP Turb.

- g "- . . ( en L' -W"" "

Rod Action ilVAC Cntrl. Leak Det. RFP Turb.

Ann. BOP Miscel. FW & Recire. Stm Bypass FIGURE 2

SPPS PERMADEMT AMD "4 IDS [ ,,,,, \

DisPLhy. ., k u a

%.~

,sy'h' ,,

Nu. as ..

u a. .. '*ly,

c,

a '*+,,

's# - 1 - //

I v#7, g ..co ...

,... wi.o.. 'x q.,,

'v'*b.e j

p//

,,gl,,

  • t ?~'a0 s,

y%'.

== 's

/ 'f #

i lf i

,; ~

v

+

~ ~'

_,:::r:,-.

f.jl'.'j . : #

s-

/}/ C, \ T' 4

/ '

/ ///," s s

a$\ ,~ ~ \r j,, j bf"' .

  • s l f aj ']

'*:/ ,

N Y//

  • ' l;.','

I L .. .u. .u o. ...

FIGURE 3 Main Control Console

u-

@ I J

1 f

)

APPENDIX 1

-'SPDS SS DISPLAY l

l l

t. - - - - - _ _ _ . _ _ _ -

I l

. . - . ........ ............................ 4.........a.........t.......... . .

8 M E I 9 1 I t 9 i ! E I f f 1 J n 1 n . 4

. .nF (.M.

e t bWM_] .t.,,,

.. .,. .i.

W er

[! C @..lg.

l 4 I t f f f f f 9 t ' f

. . . .i 1 I

a f

.I I I Q7

@ [ . T..9.P.i {

=

w mm .t . . E ,.

...... e. .e. r.

=

b l .,

7 C.X e Et,f C.l.

. ( EAR) a e i

  • i

< i i i i

. .i .a .T .h1r w H .

e i s s > . . . , . ,

...... .T.. w .u. . e.

o. _ a.
  • ^

.. R 7. STCA.*. .c' nW '

."..c..." '

.4 w %,

. , , , , , , . ,,,,,. .. o

-,fu..n e

.e. ,f .u..e. .

  • m .o.x CeEn, .CLn,W. ' * *

.w . w . L W. e r e n . . . . . >. .

7 a e r i e i v v .

.m.a..c / yc.

. . . . . . . .i ., e . .i . . . w . .e .c ,, H R t . . . 1 .=.

14 TCT CORE FLOW '

F%wl :t :t . :t  :::t . : 14

- e

=

1L

.* D. N

. DD'*CCf IF .c

. .

  • C. = w I, hto re si f

1.-

i a

, . .D ..C.? C_

g .

.-1

  • T

.. mm t.....,

......, eca IC

. . n,

  • o

-- i

.e 19 DW FLOOR DRAIN .

l: : : : GPM in 20 SUMO P "W ' NN " ....

."..," r_.o . ..w e ^,

  • 9 m.

t I 8*,*.

.O.'".)

. U E b$ E8.h.C

. .GwO Q $ $F.' C.

. 8.hJ.[

s ) l t

t t

. .i f

.I

{Q .f _Q

-w MSNGi .. . , . ., .. . .,.. .cc.TG a

ty . S. g N E OO .I

  • Q w6$ $r r .Q.(.(. . M Q .f Mg W.4l f f I i 9 1 I .

f . I E ff w.

Q U

i

.'".L . PO = f."t f 7.'C.M.C f

.t,.,."...,.

. . . u".

. N .w

. C.C C. _'"'

    • r , -

.m. .r

  • ) Q ff1.M.e I^ TM ptdM.C.D4 s*.I" l 6, 4 - ' '

' ' ' ' ' ' ' l

. ww 4. e . . . . D.C 7. C. .S '.

90 WhM ..., .. 5

-. . + . C. Qi tnC .C Q C..C .. :

. . . ... . ,. .CC 1*C ." 0 w =s

.1 , **t..

  • 1 **

79 1 9 Av E A Q Q > .

  • . M.

. - w = i 7, w . .t vo i . .e i. .*

  • n ^

'."w* l.'.kl.M

. 4iT .T C ntwWn I w .i U

  • 1 n.

6 .T U ' .T U' ,

.T

^

U T n .T n

w 1 s T

. U .T s * * *

.w

7. 4 7 4

w -

  • W *W ww

.w i h vw Y *7 we .

T.C.

w *C

. N,

. D.

l 4I [. [' s Te I N

4 &. e v

4'w 4 w~'

44 44 45 45-46 4:

47 .47 4e - sve.,

  • ~ *

. . . . . ..............m..........w.. . . . . . ...*4.........a.........w. . . . . . . . . ~ . . .

CD

. r.N. C, ec .M.,.w. T C D'L., M'k.-

r w

SS DISPLAY (SPDS) Ears FLO. DIR PID LOWER UPPER ALM VALUE NO. ENDPT ENDPT PT FORMAT COMMENTS (EU) 1 H (Later) 0 120 108  % XXX% APRM 6

2 H (Later) 0 10 1C CPS X.XEX SRM

+40 3 H (Later) -160 +60 *+32 in -XXX Rx Level Wide Range ,

4 H (later) 0 12.5 4.2 Mlb/hr XX.X Rx Total Steam Flow 5 H (Later) 0 12.5 Mlb/hr XX.X Rx Total Feed Flow 6 H B33NA001 0 12.5 M1b/hr XX.X Total Core Flow 7 H C34DA011 0 1200 1045 psig XXXX Rx Pressare (WR) 8 H 1RFBA301 0 50 gpm XX.X DW Floor Drain Sump 10 Plow 9 H (Later) 0 5 2 psig X.X DW Press (NR) 10 H VR-BAiO1 0 75 9 psig XX.X Containment Press 11 H (Later) 0 300 90 'F XXX.X Suppression Pool Temp,

  • low alarm point 1-2

a .

SS SPDS DISPLAY Value FLD. PID VALUE NO. FORMAT COMMENTS 12 (Later) XXX Rate of change / min of field #1 13 (Later) -XXX Period in sec.

14 (Later) -XXX Rate of change / min of field #3 15 (Later) XX.X Rate of change / min of field #4 16 (Later) XX.X Rate of change / min of field #5 17 (Later) XX.X Rate of change / min of field #6 18 (Later) XXXX Rate of change / min of field #7 19 (Later) XX.X Rate of change / min of field #8 20 (Later) X.X Rate of change / min of field #9 21 __

(Later) XX.X Rate of change / min of field #10 22 (Later) XXX.X Rate of change / min of field #11 1-3

1 SS SPDS DISPLAY Text Strings FLD. PID CONTACT NO. STATUS FOR TEXT See Note #8 GRN COMMENTS 23 (Later) 1 I Group 1 inboard 24 (Later) 1 O Group 1 outboard 25 (Later) 1 I Group 2 inboard 26 (Later) 1 O Group 2 outboard 27 (Later) 1 I Group 3 inboard ,

28 (Later) 1 0 Group 3 outboard 29 (Later) 1 I Group 4 inboard 30 (Later) 1 O Group 4 outbosrd 31 B33DC011 1 I Group 5 inboard ,

32 B33DC012 1 O Group 5 outboard 33 (Later) 1 I Group 6 inboard 34 (Later) 1 O Group 6 outboard 35 1RIBC807 1 I Group 7 inboard 36 1RIBC806 1 O Group 7 outboard 37 (Later) 1 I Group 8 inboard 38 (Later) 1 O Group 8 outboard 39 (Later) 1 I Group 9 inboard 40 (Later) 1 O Group 9 cutboard 41 (Later) 1 I Group 10 inboard 42 (Later) 1 0 _

Group 10 outboard 43 (Lat er) 1 I Group 11 inboard 44 (Later) 1 O Group 11 outboard 1

1-4

I I

l APPENDIX 2 I ALARM INITIATED DISPLAY i

i f

1 1

I

, , + , a v ,,- s - , ,r---,- --.- , -, -. .- - -

i e * ,

.........:........ 2........ 3........ 4........ 5........ 6........ 7..

1 1 2 2 3 3 4 4 5 5 5 6 7 7 9 9 9 9 10 10 11 11 go *o 13 13 14 14 15 15 16 16 17 17 18 18 19 19 20 20 21 21 02 . 22 23 23 24 24 25 25 26 26 27 27 28 28 29 2?

3C 30 31 31 32 32 33 33 34 34 35 35 36 36 37 RX WTR LEVEL -xxx.x IN SUPP POOL LVL xx.x FT 37 38 38 39 DW PRESS xx.x PSIG SUPP POOL TEMP xxx.x F 3?

40 40 41 DW TEMP xxx.x F CNNT PRESS xx.x PSIG 41 42 42 43 SRV STATUS (OPEN/ CLOS"L) CNMT TEMP xxx.x F 43 44 44 45 DW FL SUMP FLOL: xx.x GPM CNMT H2 CONC xxx.x % 45 46 46 47 SDV A LEVEL xx GAL SDV B LEVEL xx GAL 47 48 48

........ 1........ 2........ 3........ 4........ 5........ 6........ 7..

ALARM INITIATED DISPLAY 2-1 l

..-.y...._. . .- -. - .. , . . . . , , ,. , c.. . --

e ALARM INITIATED DISPLAY (AID) Values FLD. PID VALUE LOWER ALARM UPPER ALARM NO. FORMAT LIMIT (EU) LIMIT (EU) COMMENTS 1 (Later) -XXX.X IN +10 +55 Rx Water Level (WR) 2 (Later) XX.X psi 1.5psig DW Press ,

3 (Later) XXX.X *F 150*F DW Temp 4 1RFBA301 XX.X gpm 10 gpm DW Floor Sump Flow 5 C11DA009 XX.X gal 18 gal SDV A LEVEL 6 (Later) XX.X ft 18.9 ft 19.4 ft Supp Pool Level 8 VR-BA201 XX.X psi 1.5 psig Cnmt Press 9 (Later) XXX.X *F 120 *F Cnmt Temp 10 (Later) XXZ.X % 2% Cnmt H, Conc 11,,_C11DA010 XX gal _

18 gal SDV B Level 12 (Later) XXX.X*F 90*F SUPP "OOL T""P 2-2

ALARM INITIATED DISPLAY (Text)

FLD. PID CONT TEXT COLOR NO. STAT CHANGE CHANGE COMMENTS 7 (Later) (Later) CLOSED GREEN SRV (OPEN/ CLOSED)

(Later) OPEN RED 2-3

9

  • APPENDIX 3 AREA AND PROCESS RADIATION MONITORING SYSTEM STATUS GRID e * , - , -

STATUS GRID CLINTCN FCwER STATION UNIT I Day xxx TIME xx xx:xx

" FUEL SLOG ~CCNTalNMENT aux TURBIT.E ELOG UNASC-NC' c

3 1 2 31 32 33 34 35 81 91 93 94 96 238 5 G S2 96 9910C 237 7 8 9 45 83 '01102 103

~ 10 5 50 i l

85 til 112 11 5 245 253 55 57 53 59 l 14 5 le its 20 56 62 53 64 65 S7 i 67 12 3 25: 252 i 2E 29 30 95 '77 79 239 80 90 '35 14C CCN TACT. SLOG . RA0 WASTE SLOG I

!al 14 4 17 3 175

-- r e ,-

  • ,*.p.

l t

56 120148 240 15 6 18 8

"..-.Urun Y :t. t- .w COL 0sCODES l 199 200 NORM UN-t.s. T STNO-SY : Alt 223 '.i A:NT Mi-ALM 229 236 aLTALM AL ARM ACKN0wtEDGE MON. = :

'asi.E C: at a vs l l02 00c 156 002 2^.3 033 111 052 045 l 3-1

= _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . = - 0

  1. . 4e 8 i

l l

l

)

l 1

i 1

?

I i

APPENDIX 4-POINT DESCRIPTION CHART I

I i

I i

l I

1 1

4 I

J

/

^

. i. .

POINT DESCRIPTION CHART The Point Description Chart lists all points used for the SPDS Display. The chart also indicates whether the signal is already provided in DCS/PMS and what type of input (analog or digital).

The " Point ID" Column lists all points used and gives the PID for a kncwn signal identified for computer.use. . If no signal has been identified in the computer "Later" is entered in this column.

The "SPDS" column indicates those points used for the SPDS or AID display and specifies the display and field. If a PID is used to develop a displayed parameter but not itself displayed, an "X" is entered in this column.

, The "1.97" column indicates, by an "X", all points which will be f implemented as a result of Reg. Guide 1.97 implementation.

The "DCS/PMS" column indicates by an "X" all points already implemented in DCS/PMS.

l The " CAL VAa", " DIG" and "ANG" columns indicate, by an "X", whether a l

point is a result of a calculation or transformation of actual input signals (CAL VAR) or is a digital (DIG) or analog (ANG) signal.

The Point Description column gives a brief description of the point.

I 1

i i

____._________.___.______.______.____.._--__..___--._._b

POINT DESCRIPTION CHART Point DCS CAL ID SPDS 1.97 PMS VAR Dig .Ang Point Description Later SS-1 X X APRM A,B,C,D E.U Later SS-2 X X SRM, A,B,C,D E.U.

Later SS-3 X X Rx Wtr Lvl. E.U.

AID-1 Later SS-4 X X X . Total Steam flow Later SS-5 X X X Total feed flow GE. Point But No'ID yet.

B33NA001 SS-6 X X X Total Core flow C34DA011 SS-7 X X Rx Press (WR)

VR-BA201 SS-10 X X Cnmt Press AID-8

-Later SS-12 X X APRM rate of change Later SS-13 X X -SRM E.U.. Average rate of change Later SS-14 X -X Rate of change for R:t Lvl (WR)

Later SS-15 X X. Rate of change for Rx Steam Later SS-16 X X Rate of change for Rx Feed Flow SS-17 Later X X Rate of change core' flow Later SS-18 X X Rate of change for Iuc Press - (WR)

Later SS-19 X ;X Rate of change for DW

{ ~

Floor Drn Sump Flow Later SS-20 X X Rate'of. change DW Press Later; SS-21 X X Rate of-change Cnmt-Press

'Later SS-22 X-  :- X - fRate of' change Supp Pool

^ Temp j

e ..

  • POINT DESCRIPTION CHART Point DCS CAL ID SPDS 1.97 PMS VAR Dig Ang Point Description C11DA009 AID-5 X X SDV Lvl A C11DA010 AID-11 X X SDV Lvl B Later AID-6 X Suppression Pool Lvl Later AID-10 X Cnmt H 2 Conc 1RFBA301 SS-8 X X DW Floow Drn Sump Flow AID-4 l

i Later AID-7 X SRV Composite Status Later AID-9 X X Cnmt Temp Later AID-3 X X DW Temp Later 5S-11 X Supp Pool Temp Avg AID-12 B21DA008 SS-9, X DW Press A (Display)-(NR)

AID 2 X B21DA009 SS-9 X X DW Press B (Check AID-2 Value) - (NR)

Later SS-23 X X Group 1 inboard Isol Var Truth table Later SS-24 X X Group 1 outboard Isol Var Truth Table Later SS-25 X X Group 2 inboard Isol Var Truth Table Later SS-26 X X Group 2 outboard Isol Var I Truth Table Later 5S-27 X X Group 3 inboard Isol Var f Truth Table

).

l Later SS-28 X X Group 3 outboard Isol Var Truth Table Later SS-29 X X Group 4 inboard Isol Var Truth Table

. __ _ _ _ _ . _m_ .. .

POINT DESCRIPTION CIIART Point DCS CAL ID SPDS 1.97 PMS VAR Dig Ang Point Description Later SS-30 X X Group 4 outboard Isol Var Truth Table B33DC011 SS-31 X X Group 5 inboard Isol Var 1B33-F019 B33DC012 SS-32 X X Group 5 outboard Isol Var.

1B33-F020 Later SS-33 X X Group 6 inboard Var Truth Table Later SS-34 X X Group 6 outboard Isol Var Truth Table

1RIBC907 5S-35 X X Group 7 inboard Isol Var lE51-F078 1RIBC806 SS-36 X X Group 7 outboard Isol Var lE51-5077 J

Later SS-37 X X Group 8 inboard.Isol Var Truth Table Later SS-38 X X Group 8 outboard Isol Var Truth Table Later SS-39 X X Group 9-inboard Isol-Var Truth Table Later SS-40 X X Group 9 outboard Isol. Var Truth Table Later SS-41 X _X ' Group 10 inboard Isol Var Truth Table .

Later SS-42 X. X Group 10 outboard Isol Var Truth Table Later SS-43 X' X- Group 11 inboard Isol Var

Truth Table

- Later SS-44 X X Group-11 outboard Isol' Var Truth Table 4

s

- - . r- y- -

vvy - , y .t y v- e e e- m +- = *

  • e 4
Retrieved from "https://kanterella.com/w/index.php?title=ML20086M664&oldid=2733789"