ML18051B018

Psar,Safety Parameter Display Sys.

ML18051B018
Person / Time
Site:	Palisades
Issue date:	07/31/1984
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18051B017	List: ML18051B016 ML18051B018
References
NUDOCS 8408070441
Download: ML18051B018 (201)

Text

ATTACHME.WT 2 Consumers* Power Company, Palis:ader;;- Plant . ,. . Docket 50..,...255 PRELIMINARY SAFETY ANALYSIS REPORT SAFETY PARAMETER DISPLAY SYSTEM

• July 31, 1984

• ( 8408070441 840731 PDR ADOCK 05000255 201 Pages F PDR

TABLE OF CONTENTS 1.0 Introduction 2.0 Accident Monitoring System Design 3.0 Critical Safety Functions 4.0 AMS Hierarchical Information Presentation 5.0 SPDS Display Parameters 5.1 Safety Function Status Check 5.2 Additional Alarms 6.0 Critical Function Monitor System 6.1 CFMS Alarm Algorithms 6.2 Equipment Status Displays 6.3 System Support Displays 6.4 Display Methodology 7.0 Historical Data Storage and Retrieval 7.1 Data Storage 7.2 Data Retrieval

• MI0784-0021A-RE03 i

TABLE OF CONTENTS

• 8.0 System Interfaces 8.1 8.2 Display Stations Printer 8.3 Programmer's Console 8.4 Annunciation Outputs 8.5 Hard Copy Trend Recorder Outputs 8.6 Data Link Inputs 8.7 Hardwired Inputs 9.0 Signal Validation 9.1 EPRI Signal Validation Program 10.0 Inadequate Core Cooling Instrumentation 11.0 Verification and Validation

. 11.1 SPDS Requirements Document 11.2 SPDS Requirements Review 11.3 Design Rev;i.ew 11.4 Validation 11.5 Field Verification Test

11. 6 Validation Report

11. 7 System Modifications 12.0 Human Factors Engineering

• MI0784-0021A-RE03 ii

TABLE OF CONTENTS 13.0 AMS Training 14.0 Standards, Codes and Guidelines 14.1 Code of Federal Regulations 14.2 Regulatory Guides 14.3 NUREGS 14.4 IEEE Standards 14.5 ANSI/ANS Standards 14.6 Nuclear Safety Analysis Center (NSAG). Guidance 14.7 EPRI Signal Validation Comiuittee 14.8 Combustion Engineering Documentation 14.9 Additional Industry Guidance 14.10 Alternative Industry SPDS Designs Appendix A - AMS Level 2 Displays Appendix B - AMS Level 3 Displays Appendix C - .AMS Input Data Base Appendix D - Procedure for Human Factors Review of Palisades Plant Safety Parameter Display System

• MI0784-0021A-RE03 iii

1 1.0 Introduction This report describes the Safety Parameter Display System (SPDS),

which is being developed for the Palisades Plant. The Palisades SPDS is one of two major subsystems of the Palisades Accident Monitoring System (AMS). The AMS consists of:

1. The Safety Parameter Display System (SPDS), and

2. The Critical Function Monitoring System (CFMS).

The Palisades AMS is shown in Figure 1. The SPDS provides Palisades Plant information in the control room, as well as other locations, such as the technical support center, the emergency operations facility, and the Consumers Power Company (CPCo) general offices. The AMS consists of computer generated displays of critical plant parameters that provide emergency response personnel with an aid in determining the safety status of the plant.

This document has been prepared as a written safety analysis describ-ing the basis of the SPDS design features. It describes the hardware, displays, and other features that relate to the safe operation of the Palisades Plant. Included are descriptions of the CFMS alar~ alogo-rithms, safety functions, parameter selection, integration with other Supplement 1 to NUREG 0737 initiatives, signal validation, historical data storage and retrieval, human factors, and system validation and

• verification.

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PALISADES ACCIDENT MONITORING SYSTEM r-----------------,

MAIN CONTROL ROOM  :

I I

~:

r-----+l-,1..

1 I

HDSR

. i CFMS VDU

~

SPDS KB I

I

" I KB I ISOLATED lE INPUTS------~

L ____ - ________ ...J CFMS/SPDS COMPUTER ISOLATED ICC INPUTS -----~

r---- ------------,

NON-lE CRITICAL--------l~I SPDS  : TECHNICAL SUPPORT CENTER  :

FUNCTION PARAMETER INPUTS CFMS

......f - - - - - - - - - -

...,1 (CFMS, SPDS, HDSR, TRENDS) I I I HDSR I VDU, KB, LINE PRINTER I DL TRENDS I I INPUTS FROM L---------------~

RADIOLOGICAL &

METEOROLOGICAL MASSI STORA~

COMPUTERS r---------------,

EMERGENCY OPERATIONS FACILITY  :

MODEMS I (CFMS, SPDS. HDSR, TRENDS) I I I L - - - - - - - P _ L_ _ _ _ _-t..,._I VDU, KB, LINE PRINTER I LEGEND L_______________ J SPDS SAFETY PARAMETER DISPLAY SYSTEM CFMS CRITICAL FUNCTION MONITORING SYSTEM HDSR HISTORICAL DATA STORAGE & RETRIEVAL r-- --------------,

DL DATA LINK 1 GENERAL OFFICE CONTROL CENTER I I I ICC INAD!=OUATE CORE COOLING PL (CFMS, SPDS, HDSR, TRENDS)  :

PL PHONE LINE VDU VISUAL DISPLAY UNIT 1 2VDU, 2KB I KB KEYBOARD I I L--------------~~

2

• 2.0 Accident Monitoring System Design The Accident Monitoring System (AMS) integrates the operations staff role, the Critical Safety Function philosophy, and computer technology to produce a plant monitoring, information processing, and information display system capable of aiding the Palisades operational staff in assessing the plant safety status. A block diagram of the AMS is shown in Figure 2. It performs much of the logic to help the operator determine if safety functions are jeopardized. The SPDS key safety parameters are displayed on a dedicated SPDS color CRT in the Palisades control room. The operator can call up additional detailed

• information from a hierarchy of secondary Critical Function Monitoring System (CFMS) displays on another color CRT located in the control room. The locations of the SPDS and the CFMS display CRTs are shown on Figure 3. The locations will be confirmed by the Detailed Control Room Design Review.

The CFMS provides a primary computerized safety function status check display of critical safety functions. Secondary CFMS displays help the operator diagnose and determine appropriate "success paths" so he can take control actions to ensure that safety functions are accomp-lished. In addition to the two control room color CRTs, the AMS is provided with color CRTs in three locations:

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• ACCIDENT MONITORING SYSTEM (AMS) BLOCK DIAGRAM SAFETY DEDICATED

- . PARAMETER DISPLAY

-- CONTROL ROOM

>-- CRT 1,

c USER INPUTS }-

~

CRITICAL FUNCTION DISPLAY ALGORITHM INPUT SENSOR

-- PROCESSING DISPLAY PLANT

~ CRT PLANT INPUTS

-- PROCESSING - PROCESSING INFORMATION DISPLAYS

~

USER STATIONS CONTROL ROOM TSC EOF GOCC

--. REAL TIME TRENDS DISPLAY h

HISTORICAL DATA

-- STORAGE &

RETRIEVAL

- LINE PRINTERS

FIGUR MAlN CONTROL PANELS

( SMM Diep lay) r:tl

~

i.:I 1-l E-i

~

11.

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0 0 1-l CONTROL CONSOLE r:tl E-i

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CFMS/SPDS Display C~T Display 1

Technical Support Cen tei- with SS/Shift Eng Office I TMI CFM/SPDS Die play I Modifications Panel PALISADES CONTROL ROOM .,,,.

3

• 1) A color CRT and keyboard are hardwired to the CFMS/SPDS computer in the Palisades Technical Support Center (TSC). Emergency response personnel and the plant technical staff use this CRT for both routine and emergency monitoring of the plant status. A line printer is available in the computer support module located near the turbine deck which can be used to obtain real-time trend data or graphs/listing from the data stored on the Historical Data Storage and Retrieval System (HDSR). On this CRT the user can select the SPDS display or any of the CFMS hierarchical displays as well as historical data and real-time trends.

2) Another color CRT and keyboard is linked by a phone line and modem to the CFMS/SPDS computer in the Palisades Emergency Operations Facility (EOF) located in South Haven. The user can select the SPDS display or any of the CFMS hierarchical displays as well as historical data and real-time trends at the EOF.

3) Two color CRTs and keyboards are linked by a phone line and modeum to the CFMS/SPDS computer at the Consumers Power Company General Office Control Center (GOCC) and the Reactor Engineering Depart-ment (RED) in Jackson. Here, the user can select the SPDS display, any of the CFMS hierarchical displays, historical data displays, or real-time trends.

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4

• In addition to the 6 color CRTs, the AMS consists of a single 32-bit Perkin-Elmer process minicomputer, I/O equipment, and a fully graphic system including 4 display generators. The AMS provides several plant information processing functions, including input processing, inte-grated plant information and display processing, critical function algorithms/safety parameter display, trending, and historical data storage and retrieval.

Process inputs utilized by the SPDS are provided from both Class IE and non-Class IE devices. Inputs from Class IE devices are provided through qualified located remote to the AMS computer. The in-plant sensors are connected to the AMS process computer I/O which scans the

• data and performs A/D conversions of analog inputs.

The AMS computer processor functions to scan the field inputs, converts inputs to engineering units, and performs signal validation and alarming of process variables. Validation of inputs assure that inputs are within expected ranges .

• MI0784-002IA-RE03

5 3.0 Critical Safety Functions The Palisades Accident Monitoring System utilizes the Safety-Level-Concept, an outgrowth of the Defense-in-Depth philosophy, which has been an integral part of the nuclear industry since its inception.

Out of this safety level concept has evolved the Critical Safety Function philosophy to help operators cope during.events that require knowledge-based behavior. Critical Safety Functions are a means of organizing plant data to aid the operator to maintain plant safety no matter what his/her primary mode of behavior is or what the abnormal event initiator may be.

Critical Safety Functions themselves are a group of actions that main-tain the safety of the nuclear plant by preventing core melt or minimizing radiation release to the general public. The concept is*

that a nuclear plant can be maintained in a safe and stable condition if a small number of critical safety functions are properly performed.

The critical safety functions that are utilized by Palisades Accident Monitoring System are described in Table I.

Using safety functions the operator observes the plant's state, through logic determines if safety functions are jeopardized, and, if so, determines appropriate "success paths" and takes control actions along these success paths to ensure the safety functions are accomp-lished. By monitoring key safety parameters associated with the safety functions on the SPDS display and taking action to control MI0784-0021A-RE03

6 TABLE I NO. SAFETY FUNCTION PURPOSE

1. Reactivity Control* Shut reactor down to reduce heat production.

2. Primary coolant system Maintain a coolant heat transfer inventory control. medium around the core.

3. Primary coolant system Maintain the appropriate heat pressure control. transfer properties of the coolant.

4. Reactor core heat removal. Transfer heat from core to a coolant.

5. Primary coolant system Transfer heat from core coolant heat removal. to a heat sink.

. 6. Containment pressure/ Maintain containment in proper temperature control. state to prevent dama_ge and

.radiation release.

7. Containment isolation. Maintain radioactive material within the containment.

8. Environmental control. Prevent radioactive releases to environment from sources outside containment.

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7 these parameters within prescribed limits, the operator can maintain the safety of the plant even if he is unfamiliar with the event at hand. The CFMS alarm algorithms provide real-time logical compu-tations of plant variables to identify which safety functions are in jeopardy. The CFMS provides a safety function status check by a "go" or "no-go" display of all critical safety functions on a single display page.

The "top down hierarchical" displays of the CFMS provide additional plant information to assist the operator to verify, analyze, and diagnose conditions of Critical Safety Function success paths. Each safety function success path represents the equipment, operator actions, and a set of' success criteria that will fulfill the safety function. Multiple success paths exist for each safety function because of the Defense-in-Depth philosophy of nuclear plant design.

The Critical Safety Function alarm algorithms of the CFMS are designed to assess the key plant safety parameters, filter the plant infor-mation, deduce the status of the safety function success criteria, and provide this information to the operator. The algorithms are functional (ie, system/operational) oriented and not event symptom oriented. Critical Safety Function alarm algorithms are discussed in Section 6.

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8

• 4.0 AMS Hierarchical Information Presentation Figure 4 illustrates the Accident Monitoring System display hierarchy.

The system has four levels of displays in the top down hierarchy.

These levels are important because of the physiological and psycho-logical capabilit~es and limitations of the operator.

The hierarchy is designed to allow the user to easily move through the information presented by the AMS and always be able to find the infor-mation which is required. The upper level (Level 0) is dedicated to the display of safety parameters. In the control room, one color CRT displays these safety parameters at all times. The operator cannot

• access any other level from this CRT which constitutes SPDS. A redundant color CRT in another location in the control room allows operators to access all of the displays of the AMS hierarchy including the SPDS display.

The second level (Level 1) of the AMS is used to present the user with an overview of the status of the plant and the AMS. This level contains the AMS Critical Function Monitor page which gives a safety function status check of the plant critical safety functions. This

.level also contains displays of the Current Alarm List. The Display Directory, the Computer Status List, and the Trend pages also appear on the second level of the hierarchy. The Critical Function Monitor Page of the CFMS can be accessed directly from the SPDS Level 0 display by keying Sector 1 on the page control module.

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Ba.

FIGURE 4 AMS HIERARCHY - BLOCK DIAGRAM ooo SAF£1""'f ?A~MEIJ,'

J)JS 1'L '4 'Y 0

l'/\LISJ\llf.S 1110 101 IOI\ lll!i DlllECTOllY CUIHll*T Al.MIM uur OF 111\llGE COMPUTER STATUS LIST LIST 244 255 HYIROllllllNTAL RADIOLOGICAL Alll flll COllTAINMlllT ISO VALVH TRENDS t-~-o1_j1--~121;,_l ")

SHUT. . . CllWtl TllEID llT I 1 TllEID RT Z r

9

• The third level (Level 2) of the hierarchy includes the major systems pages. These pages include the Core, Primary, Secondary, Containment and Environmental pages. These pages are presented in Appendix A. The fourth level (Level 3) of the hierarchy includes more detailed information about the major subsystems which make up the five major systems. (See Appendix C) The pages are arranged in closed loops which connect pages with related information. Figure 5 is a nodal diagram of the CFMS display hierarchy.

The AMS also incorporates a Historical Data Storage and Retrieval (HDSR) system. The HDSR system allows plant information to be record-ed, stored, recalled and displayed to the operator and support

• personnel. Retrieved information may be sent to the printer as logs or displayed on the AMS display screens as static graphs.

retrieval is performed directly from the AMS user stations.

All The HDSR include dialogue pages. These pages ~xhibit the dialogue between the computer and the operator when changing system parameters regarding trends, logs, graphs, system backup and disc protection for the HDSR.

There are also 6 other display pages in the HDSR. These are pages which exhibit the HDSR graphs; one for each CRT station. These pages are also in a closed loop. Figure 6 shows the HDSR hierarchy .

• MI0784-0021A-RE03

9a FIGURE 5

• AMS HIERARCHY - NODAL DIAGRAM CRITICAL fUNCTIONS MONITOR D I a p LA v "" I I RA n c Hy N 0 DA L D I A a ft AM SPDS OMPUTER STATUS G

9b FIGURE 6

• HDSR HIERARCHY - BLOCK DIAGRAM SYSTEM FUNCTION PAGE LEVEL 1 LEVEL 2 130 130 130 130 130

.* DISK TR~DS LOGS GRAPHS BACKUP PROTECTION 1.-

121*

TREND S!T J30 130 13Q TR EN CS

• - LOGS .GRAPHS

10 5.0 SPDS Display Parameters The Palisades Safety Parameter Display System is provided on a dedicated color CRT in the control room. The SPDS display is also available to other users on any of the other AMS color CRTs. The SPDS is designed to provide a concise display of key critical safety function plant variables in analog form to aid the control room operators in maintaining the safety status of the plant.

Using the safety function concept, a detailed Functions and Task Analysis of the Palisades plant is being conducted partly to determine the key parameters the operator would monitor to fulfill plant safety functions. The parameters selected are the primary analog variables that are used by the CFMS alarm algorithms to alert where Critical Safety Functions are in jeopardy based on a set of success criteria.

The analog parameters selected for the SPDS display have been grouped together to cover six of the eight critical safety functions identi-fied in Table I. Alarm setpoints are selected to match the alarm setpoints of the CFMS algorithms. These are based on plant instrumen-tation, plant technical specifications, or combinations of plant inputs that indicate loss of safety function control. Distinctive color coding is used on the display to alert an abnormal condition.

If a parameter is within its normal range and the safety function is not in jeopardy, the bar for that parameter on the display is cyan .

• MI0784-0021A-RE03

11

• However, if the parameter is out of its normal range for a given mode of operation it is displayed magentaAlso, if the safety function is in jeopardy the border surrounding that safety function becomes magenta in color matching the CFMS primary display.

Figure 7 shows the SPDS display of the present design. In addition to displaying the analog signal of the safety parameter, digital filters are used by the SPDS software to evaluate the rate-of-change of the parameter at any instant. The operator can also use the redundant color CRT in the control room to obtain real-time trend information for any of the parameters on the SPDS display using the trends feature of the AMS .

• The parameters selected for each safety function are discussed below:

a. Reactivity Control

1. Percent Power: Nuclear instrumentation signals are integrated in the AMS computer to provide a wide range power signal from

-4 10 to 115 percent.

Rate of Power Change: A rate of change of power in decades/

minute is digitally displayed .

• MI0784-0021A-RE03

FIGURE 7 SPDS DISPLAY *

• CORE REACTIVITY PCS INVENTORY PCS PRESSURE POWER (pct) 192.~ PZR LEVEL (pc~t'~---54......,.~ PZR PRESS (rsi;) 219~

11 e iiiililiilil_ _.1::J15 0 100 0 . .-=21:::J00

~ate:Q,90 dee/Min rate:-2,64 pct/Min rate:23.91 psi/Min CORE HEAT REMOVAL PCS HEAT REMOVAL CONTAINMENT TEMP/PRESS T-cold (deg F) 694.8 SGA LEVEL (pct) 52.5 CNMT TEMP (deg F) ?1. 0 I I I 459 759 9 119 40 220 rate:2.54 deg F/hr ~ate:-2.59 pct/Min rate:Q,09 deg F/Min T-hot (deg F) 614.9 SGB LEVEL (pct) 29.4 CNMT PRESS (~si~) 0.10 I I I I I 459 ?50 0 110 0 50

~ate:4.31 deg F/hr rate:-21.84 pct/Min rate:0.90 psi/Min T-ave (deg n 609.9 20.4 I I 450 ?50 110 rate:J,45 deg F/hr SCH (def F) 41.0 SGB FW (pct) 52.4 I I

-59 199 9 119

~ate:Q,56 deg F/Min rate:9,49 pct/Min CONTAINMENT ISOLATION ENVIRONMENTALS

~ 9?-20-1984 t:ti:j 11:4?:32

• NOTE: Completed design will have units and ranges consistent with control room instrumentation.

12

• b. Primary Coolant System Inventory Control

l. Pressurizer Level: Pressurizer level has been selected as the key parameter for PCS inventory control when the PCS is sub-cooled. It is also an important parameter for PCS pressure control.

c. Primary Coolant System Pressure Control

1. Pressurizer Pressure: Pressurizer pressure is used to monitor high or low pressure conditions against design limits and system setpoints. Pressurizer pressure is also used in conjunction with system temperatures to compute the subcooled margin parameter used in the core heat removal safety function.

d. Core Heat Removal

1. T-Cold: Cold leg temperature is monitored in conjunction with hot leg temperature to determine adequate core heat removal during forced circulation and natural circulation heat trans-fer modes.

This temperature is also used with PCS pressure to monitor plant status with respect to system NDT limits .

• MI0784-0021A-RE03

13 Cold leg temperature is used in conjunction with the nuclear instrumentation to determine adequate shutdown margin for reactivity control.

2. T-Hot: Hot leg temperature is monitored in conjunction with cold leg temperature to determine adequate core heat removal.

This temperature is combined with pressurizer pressure to compute minimum subcooled margin temperature. This is used both as an indication of loss of PCS pressure control and core heat removal control.

T-hot is combined with T-cold to compute the average PCS temperature to determine that adequate cooldown/heatup rates are being experienced.

3. T-Average: The average PCS temperature is calculated using the cold leg temperature and the lowest hot leg temperature.

The average temperature and the rate-of-change of*T-average are used to determine that adequate heat removal is being experienced.

The average temperature is also used in the shutdown mode to determine that reactivity control is not jeopardized. If T-average is decreasing and reactor power is increasing the reactivity control function will alarm.

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14

4. Subcooled Margin Temperature: Subcooled margin temperature is computed by subtracting the hottest hot leg temperature from the saturation temperature corresponding to the measured pressurizer pressure. It is used to indicate that core heat removal is adequate and that PCS pressure control is adequate.

e. Primary Coolant System Heat Removal:

1. Steam Generator-A Level: Adequate steam generator level is indicative of PCS heat removal for each steam generator. This safety function will alarm on a low steam generator level condition in either the A or B steam generator. The alarm is dependent on the mode of operation or PCS cooling equipment operating.

2. Steam Generator-B Level: Same as Steam Generator-A Level.

3. Steam Generator-A Feedwater Flowrate: The flowrate to the steam generator is also an indication of adequate PCS heat removal. During shutdown conditions, after a reactor trip, percent feedwater flowrate should approximately match the percent of decay heat as a function of time after trip for a stable PCS heat removal rate.

4. Steam Generator-B Feedwater Flowrate: Same as Steam Generator-A Feedwater Flowrate.

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15

• 5.1 Safety Function Status Check In the lower center of the SPDS screen is displayed the critical function matrix. This feature is displayed on all pages of the AMS hierarchy. When any critical safety function comes into an alarmed state, it will be immediately displayed on the critical function matrix, which is a representation of the Critical Functions Monitor page 102. Figure 8 shows the color scheme used by the critical function matrix which is a safety function status check for the operator. The alarm algorithms are discussed in Section 6.

The SPDS page is presented with the safety functions in the same relative matrix locations as the Critical Function Monitor page. In addition the borders of the SPDS safety function blocks are color coded to alarm in the same way as the Critical Function Monitor page.

On the SPDS display engineered safeguards alarms are located to the right side of the critical function monitor matrix. Normally, the engineered safeguards alarms will be invisible. However, they will be displayed in yellow upon an engineered safeguards signal being generated. The engineered safeguards systems which alarm are:

a. CIAS - Containment Isolation Actuation Signal

b. RAS - Recirculation Actuation Signal

c. SIAS - S~fety Injection Actuation Signal

d. CHP - Containment High Pressure

• e. CHR MI0784-0021A-RE03

- Containment High Radiation

15a FIGURE 8 CRITICAL FUNCTION MATRIX COLOR AND SHAPE CODES NO ALARM D GOOD QUALITY BLUE NO ALARM

[] FAILED INPUT YELLOW

• ~

ALARM FAILED INPUT MAGENTA I YELLOW ALARM GOOD QUALITY MAGENTA

~I 16

• Below the critical function matrix "time post trip" is displayed.

Also included on the display is the current date and time which is updated each 5 seconds.

5.2. Additional Alarms In addition to the continuous parameters displayed on the SPDS, additional static alarms are displayed. In the lower left hand corner of the safety function matrix the containment isolation function alarms when containment* isolation is required but not attained. The operator may refer to the critical function matrix of the CFMS to obtain information about which vaives/penetrations do not isolate during emergencies.

In the lower righ~ hand corner, high radiation alarms will be.dis-played in the environmental safety block when external radiation

- I levels exceed their setpoints. The operator may refer to the critical function matrix of the CFMS to determine which radiation levels are exceeded.

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17 6.0 Critical Function Monitor System By way of distinction, the CFMS contains all of the displays associated with levels 1, 2 and 3 of the AMS. The SPDS display is level 0. The Palisades CFMS includes:

a. 1 critical function monitoring page,

b. 26 operational display pages,

c. 3 alarm list pages,

d. Non-operational maintenance pages, and

e. A computer status list page.

The CFMS provides the following benefits during transients:

a. Processes information and performs critical function monitoring,

b. Concentrates information to aid problem diagnosis,

c. Aids in success path selection, and

d. Provides control action feedback to operators.

The Critical Safety Functions philosophy provides the basis for all information processing by the CFMS. The Critical Safety Functions philosophy is:

A nuclear power plant can be maintained in a safe and stable condition if a small set of

• MI0784-0021A-RE03 critical functions are accomplished.

18

• Critical Safety Functions have the following. characteristics:

a. If a critical safety function is not accomplished, reaching the target state (safe and stable) is highly unlikely.

b. Critical safety functions may relate to safety, availability and operation.

The Palisades CFMS utilizes a set of alarm algorithms to provide a safety function status check to the operator. These alarm algorithms are the basis for _the Critical Functions page of the CFMS (page 102).

A CFMS alarm algorithm is a mathematical representation of the logic an operator would use to monitor the status of a critical safety function. A unique CFMS algorithm has been designed for each critical safety function. Figure 9 shows the Critical Functions Monitor page of the CFMS.

6.1 CFMS Alarm Algorithms The CFMS alarm algorithms continuously monitor the safety status of the plant. The algorithms utilize time delays, filters, averages, highest and lowest values, etc., in the calculation of the status of critical safety functions. All inputs to the algorithms are quality checked. This quality check is reflected in the algorithm outputs.

Following is a description of each of the alarm algorithms:

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FIGURE CRITICAL FUNCTION MONITO PAGE l!l I ISHAUPAL8 11 I 1111111

_ AUG/ll/1182 a ~

t R I T I c f1Di L f U Ii C TI 0 Ii S. II ~1111 IJI 111 IJe 1111,'JJ ~

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• 5

• 5 ~ 5 8 5 I i _

E CORC REAOHVITY

- HI POST TRP OHTRTI

- YHCRHAL REAOT APD 1

pos INUCHTORY

- PZR LEVEL

- HI P2R LUL RATE

- 8UCNCM TANK LUL

- 8UENCM TAHK PAES i

,Of, ,RES5URE HI *** PREllUR<

Hl*T tEHP EXCEEDED Ptft PRESS RATE SU8-COOLEO HAAOIN I 2

- LOH .6

- RELIEF ULU DISCH PRl/IJO br Ii I 8 OO~E HEAT ~EHOUAL ros HEAT f'CHOUAL OHltT TCHP / PRCJ5 2

- LOH LOOP FLOM I - HI P05 HCAT LOADI 2 - OHHT LOW PRCi5

- HI HAX OT - 115 NOT COOLING - CHHT HIGH PREii

- SATURATION HARGIN 2 - IDD NOT COOLING - CWHt PREii CHA"QE '1 Ii- LOW POP LOAD

- LOOp/CDRE UOID - 5GS NOT COOLING I3 -

F 4,H COOLER&

CHHT HIGH TCHP ClllHl SPRAY FLOH 8 3 OHHT UOLATIOH Ii J

- 56 SYS UALUC5 Hi

- 8UCNCH TANK,N2

- CHHT 5UHP,ORH.UHT

~ HliC VALVES Hi

- CLH Mil RCUR THKi

CN~T PUR6£ FAH

'1 CHV I ROUllE11To1L I.5 Qeeefe ' ee r1 I 11 r1 11 I r1 I I I I 11 I 11 11 11 111 I I I I I 11 I I 11 I I I I I I I I I I 1 I

19

• 6.1.1 Core Reactivity Control Critical Function Objective:

Monitor the status of various core parameters to assure ability to maintain control of the nuclear process.

Definition of the Critical Function:

The core reactivity control function is an indication of the reactivity in the reactor core. The alarm logic is based on losing control of reactivity, ie., uncontrolled positive reactivity insertion rather than an absolute bound such as criticality.

The logic legs for Core Reactivity Control are:

1. Hi Post Trip Count Rate

2. Thermal Reactivity Addition 6.1.2 PCS Inventory Control Critical Function Objective Monitor the system's ability to keep the core covered with an effective cooling medium .

• MI0784-0021A-RE03

20

• Definition of the Critical Function:

The PCS inventory control function is comprised of that group of actions which serve to maintain control over either coolant volume or mass. The critical function inventory control involves the initial loss of ability to control the PCS coolant inventory.

The logic legs for PCS Inventory Control are:

1. Pressurizer Level

2. Quench Tank Level

3. Quench Tank Pressure

4. Relief Valve Discharge

5. Steam Generator Primary/Secondary LlP Low

6. Hi Pressurize Level Rate 6.1.3 PCS Pressure Control Critical Function Objective:

Monitor the ability of the pressurizer system to keep the reactor coolant pressure between its upper and lower bounds .

• MI0784-0021A-RE03

21

• Definition of the Critical Function:

The PCS pressure control critical function serves to maintain the reactor coolant system pressure in the range between the upper bound, which is the high pressure reactor trip setpoint, and the lower bound, which is the pressure required to maintain the reactor coolant sub-cooled. Alarms are activated by the CFMS when these bounds are exceeded or when the coolant system pressure control will not be able to prevent exceeding these bounds.

The logic legs for PCS Pressure Control are:

1. High Pressurizer Pressure

2. Minimum Pressurization Temperature Exceeded

3. Pressurizer Pressure Rate

4. Subcooled Margin 6.1.4 Core Heat Removal Control Critical Function Objective:

Monitor the transfer of heat from the reactor core to the primary coolant system .

• MI0784-0021A-RE03

22 Definition of the Critical Function:

The core heat removal function is the capability to transfer heat from the core to the primary *coolant and transport and the coolant away from the core by any of these methods:

A. Forced circulation by primary coolant pumps.

B. Forced circulation by the shutdown cooling system.

C. Natural circulation.

The loss of the core heat removal critical function will be indicated by excessive reactor coolant temperature conditions which signals the

• inability to transport the coolant away from the core or will be indicated by large voiding in the coolant system signaling the in-ability to transfer heat to the coolant.

The logic legs for Core Heat Removal Control are:

1. Saturation Margin

2. Low PCP Load

3. Loop/Core Void

4. Low Loop Flow

5. High Maximum b.T

• MI0784-0021A-RE03

23 6.1.5 PCS Heat Removal Control Critical Function Objective:

Monitor the transfer of the stored heat and the decay heat from the reactor coolant system.

Definition of the Critical Function:

The PCS heat removal critical function is to transfer the stored heat and the decay heat from the reactor to the heat sink outside the containment. These heat transfer mechanisms are:

• A. The primary coolant circulation in the primary system and the feedwater supply and the steam removal in the secondary side of the nuclear power plant.

The heat removal function also monitors the situation wherein steam flows from the reactor vessel to the steam generator. Also included is the case where non-condensible gases impede normal coolant system flows through the steam generator and reactor vessel.

B. The PCS heat removal function includes the circulation in the shutdown cooling system and the transfer of heat from the shutdown

• cooling system.

MI0784-0021A-RE03

24

• C. The CFMS also monitors the initial functioning of the ECCS and subsequent recovery from an incident. It includes the heat removal via the pressurizer relief valves and recirculation of coolant through the reactor containment sump.

The logic legs for PCS Heat Removal Control are:

1. SIS Not Cooling

2. SDC Not Cooling

3. Steam Generators Not Cooling 6.1.6 Containment Pressure/Temperature Control

• Critical Function Objective Monitor the system's ability to maintain containment pressure within design safety limits.

Definition of the Critical Function The containment pressure/temperature control function monitors contain-ment pressure and temperature and the effectiveness of those systems which maintain these pressures and temperatures. The bounds which are maintained are a result of safety limits designed to protect the containment integrity .

• MI0784-0021A-RE03

25

• The logic legs for Containment Temperature/Pressure Control are:

1. Fan Coolers Status

2. Containment Spray Flow

3. Containment Pressure Change

4. High Containment Pressure

5. Low Containment Pressure

6. Containment Temperature 6.1.6 Containment Isolation Critical Function Objective:

Monitor the valves in the piping paths which penetrate the containment structure. The position of those valves required to isolate the containment is monitored by this function.

Definition of the Critical Function:

The containment isolation control function is the monitoring of those valves necessary to the complete isolation of the containment structure. These valves are normally shut in response to the engineered aafeguard (ESG) signals generated in response to reactor safety safety functions. The ESG signals may be placed in three general categories:

• MI0784-0021A-RE03

26 A. Containment High Pressure (CHP).

B. Safety Injection Actuation Signal (SIAS).

C. Containment High Radiation (CHR).

The logic legs for Containment Isolation Control are:

1. Steam Generator Valves Not Shut

2. Quench Tank,, Nitrogen Valves Not Shut

3. Containment Sump,-Drain and Vent Valves Not Shut

4. Misc. Valves Not Shut

5. Clean Waste Receive Valves Not Shut

6. Containment Purge Fan Valves Not Shut 6.1.8 Environmental Critical Function Objective Monitor the status of various radiation monitors to assure that radiation is not being released to the environment.

Definition of the Critical Function:

The environmental safety function is an indication of radioactive releases and release rates for the purpose of alerting operating personnel that Emergency Implementing Procedures are required .

• MI0784-0021A-RE03

27

• The logic legs for the environmental safety function are:

1. High Off Gas Radiation

2. High Stack Radiation

3. High Failed Fuel Radiation

4. High Containment Radiation

5. High Steam Line Radiation

6. High Liquid Discharge Radiation These logic legs have not yet been incorporated within the CFMS. They are planned to be installed within the near future .

• 6.2 Equipment.Status Displays Following are the Level 2 and 3 page hierarchy for the equipment status/operational displays. Level 2 displays are designated by capital letters, and Level 3 displays are designated by numbers and indented.

A. Core

• Ml0784-0021A-RE03

28

• • B. Primary System 1.

2.

Safety Injection Pumps Safety Injection Tanks

3. Letdown/Charging

4. Boration/Dilution

5. Pressurizer

6. Shutdown Cooling C. Secondary System

1. Main Steam

2. Main Feedwater

3. Auxiliary Feedwater

• D. Containment System

1. Containment Cooling

2. Containment Spray

3. Containment Isolation E. Environmental

1. Meteorological

2. Radiological These operational displays are accessed either directly by page number or by sectoring from the Critical Function Monitor page. Following are functional descriptions of each display page .

• MI0784-0021A-RE03

29

• The Level 2 of the hierarchy contains five pages.

primary systems of the Palisades plant.

of the Level 2 displays.

These deal with Appendix A contains examples A. THE CORE - This page display is concerned with presenting infor-mation about the reactor core. The hot and cold leg temperatures, pressurizer pressure and level channels, excore detector outputs, and the eves system status including boron concentration.

B. THE PRIHARY SYSTEH - This page provides an overvi*ew of the primary coolant system including the primary coolant pumps, steam generators, pressurizer, core and charging system connections.

C. THE SECONDARY SYSTEM - This page provides information concerning the status* of the. steam generators, main condenser, condensate storage tank, main auxiliary feed pumps, and condensate pumps.

D. THE CONTAINMENT SYSTEM - This page displays the information relevant to the containment environment, containment spray opera_-

tion', contai.nment radiation monitors status, hydrogen concentra-tion and sump levels, radiation levels and some balance of plant equipment.

MI0784-0021A-RE03

30 E. THE ENVIRONMENTAL - This page displays the radiological and environmental status of the plant including containment radiation monitors, radioactive liquid levels~ and wind speed.and direction monitors.

Level 3 of the hierarchy associated with the Primary System contains six pages of information displays. These are:

1. SAFETY INJECTION PUMPS - This page displays information concerning the safety injection systems, their pumps, valves, SIRW tanks, pressures, and flows.

2. SAFETY INJECTION TANKS - This page presents the status of the safety injection tanks and their associated valves' positions.

3. LETDOWN/CHARGING ~ This page shows the status of the letdown and charging *systems. The pumps status as well as the condition of the volume control tank, boron concentration, and charging and letdown flows.

4. BORATION/DILUTION - The information displayed on this page is relevant to the boric acid tanks, their associated pumps and piping systems.

MI0784-0021A-RE03

31

• 5. PRESSURIZER - The information presented here is vital to the functions of PCS pressure and inventory. The summary of infor-mation presented here provides that data necessary to assess the condition of the plant's overall PCS pressure and inventory safety functions.

6. SHUTDOWN COOLING - Data presented here allows the operator to monitor the shutdown cooling system and to determine if there is a heatup or cooldown rate inappropriate to the plant's required condition. The display also shows the status of pumps, valves and heat exchangers .

• The lower level of hierarchy associated with the secondary system contains three pages of informational displays. They are as follows:

1. MAIN STEAM - This page presents information pertaining to the main steam system from the steam generators to the turbines. It covers data presenting main and auxiliary feed flows, relief valve positions, turbine sump radiation levels, as well as heatup and cooldown rates. (The pressurizer pressure and temperature are also shown.)

• MI0784-0021A-RE03

32

• 2. MAIN FEED - This system is presented in detail* because of the importance it bears on the core heat removal function. The system's main condenser, condensate pumps, feed pumps, and feed-water control valves status are displayed. The pressurizer pressure and temperature are also shown.

3. AUX FEED - The auxiliary feed system status as an alternate feedwater source during plant emergencies is required, thus the status of this system is invaluable to the plant operator. The auxiliary feed system is also.required for plant cooldown. This page displays the status of the condensate storage tank, auxiliary feed pumps, and associated important valves. The pressurizer pressure and temperature are also shown.

The lower level hierarchy associated with the conta'inment* system contains three pages of informational displays. They are as follows:

1. CONTAINMENT COOLERS - This page shows the layout of the contain-ment air cooler fans, and associated important valves. Also shown is the reactor building heater isolation valves.

2. CONTAINMENT SPRAYS - This page shows the layout of the containment spray cooling systems, including the containment spray pumps and spray coolers.

MI0784-0021A-RE03

33

• 3. CONTAINMENT ISOLATION - This page displays the valves needed to isolate the containment. The valves are presented in groups and close on CHP, CHR or SIS signal.

The lower level hierarchy associated with the environmental page contains two pages:

1. METEOROLOGICAL - This page display information data linked from the meteorological tower. The information includes wind speed and direction and the tower temperature.

2. RADIOLOGICAL - This page displays radiation monitors inside containment as well as liquid radiation monitors. Monitors in various locations are also displayed.

6.3 System Support Displays The Level 1 displays excluding the Critical Functions Monitor page constitute the CFMS System Support displays.

They include:

Display Directory - An alphanumeric display which lists the display page titles and page numbers. The Display Directory is arranged in a structured sequence that indicates the three hierarchical levels and

• the available sectors for each page.

MI0784-0021A-RE03 See Figure 10.

33a FIGURE 10 TYPICAL DISPLAY DIRECTORY PAGE ALIG/19/198'2 DISPLAY DIRECTORY 093e.:ese 1ee DISPLAY DIRECTORY 191 CURRENT ALARM LJST 19'2 CRITICAL F'UNCTIONS 1 E*3 OUT OF' RANGE LJST i E*'i 8AD DATA LIST 1 95 COMPUTER STATUS LJST 1 '29 TREND SET 1 1 '21 . TRE:ND SET '2

• '211' CORE 2'2'2 PRIMARY 3'21 SAF'ETY JH.JECTJOH PUMPS 3'2'2 SAF'ETY IH.JECTJOH TAHKS 3'23 LETDOHH/CHARGIHG 3"2'f BORATJON/DJLUTJOH 3"25 PRESSURIZER 3"26 SHUTDOMH COOL I HG

'233 SECONDARY 331 HAIH STE AH 33'2 MAIN F'EEO 333 AUX F'EED

34a FIGURE 11 TYPICAL CURRENT ALARM LIST PAGE SH ~ *..ir: .~ L :i J~tv*2i; *: ~! ~

CUF: RENT ALARM L I S T 101

~* ?'+i:. ! :;- 1 0?4'2:05 LOLO CCW HEAT EXCH ccw INLET PR 7'+ PT091S 3'21 SIZI O?"+'l:05 HI CONTAINMENT WR PRESS 1SIZISA 1O'+ PT1S05M '2 '+I.I 55 094'2: es HIHI CONTAINMENT SUMP HATER LEVEL '2 IZI l. Tt!l3S'2 '2 '+ i+

1'2 0?'+'2: 05 HIHI COLD LEG L.OOP '2B TEMPERATURE 56'+ TT01'2'2CB '211 555 O?i.+'2:05 HIHI COl.D L.EG l.OOP 1B TEMPERATURE 56'+ TTIZJ11'2CB '2 11 555 IZl9'+'2: es LOL.O STEAM GENERATOR t-see PR£SS i;99 Pi0i5'2 233 6013

---

~-----------------------------------------------

G9'+'2:G5 LOL.O STEAM GENERATOR E-59A PRESS '+99 PTG751 '233 iOS IZl9'+'2:G5 HI COHTAIHHENT BLDG DOME TEMP 199 TE1U5 '2 '+ '+

1513 091+'2: 05 HI QUENCH TANK T-73 PRESSURE 1'2 PTG1 U 3'25 10 OSi.+'2:05 LOL.O PZR HEATER TRANSF'ORHER AMPS 0 AIIZJ10'+ 3'25 160 0?"+'2: 05 LOL.O PZR HEATER TRANSF'ORHER AMPS ~9 AI010J 3'25 1SO 0?"+'2: 05' LOLO STM GEN F'E£0 PUMP ~-18 OISCH 599 PT0703 33'2 700 09"+'2: 05 LOLO STM GEN F'EEO PVMP P-1A DISCH 599 PT0701  :: 3 '2 700 09'+'2:05 HI CONTAINMENT MR PRESS 1S1'2A e PT191'2A '2 '+I.I 70 O?i.+'2:05 HIHI CO_LO l.EG LOOP 14 TEMPERA TL1RE SSI+ TT01'2'2CA '211 555 o;-+': 1!15' !1 IHI COLO LEG L)0P 14 TEHPERATURE:

1 561+ TTQ11'2CA '2 11

- . S55 o:o.+'2: OS LOLO PRIH~RY COOLANT LOOP 28 OP 31 OPTO 1'2'20 '2 2'2 s '2 091.12: es LOLO PRIMARY COOLANT LOOP 2A OP 31 OPTe1'2'2C '2 '2 '2 s '2

34b FIGURE 12 TYPICAL OUT OF RANGE LIST PAGE JAN/2S/19SJ OUT OF RANGE LIST 103 1122:"+5 1 F'AIL. HPSI HEADER A PRESSURE PTQJU :3'21 F'AIL. HPSI F'L.OH TO LOOP '2B F'TGJ1'+A 3'2'2 F'AIL LPSI F'LOH TO LOOP '2B . F'TGJ1JA J '2 '2 F'AIL CCH HEAT EXCH CCW INLET PR PTG9U J '21

~A. 9 I r l*UI. HIDE RANGE POWER NI eei; NI'3GI'+ 211 F'AIL AUX F'H CNTRL sa ESeB VLV ?J6 EPG?36 JJJ F'AIL CONTAINMENT HR PRESS 1895A PT1SG5A '2 '+ '+

F'AIL CONTAINMENT SUMP HATER L.EVEL LTGJ8'2 '2 '+ '+

F'AIL HPSI F'LOW TO LOOP 2A F'TeJ1'2A :n2 F'AIL L.PSI F'L.OW TO L.OOP '2A F'TGJ 11A 32'2 F'AIL. CONTAINMENT SPRAY HOR '2 F'LOH F'TGJG'2 3'+'2 F'AIL. HOT LtG LOOP '2 TEMPERATURE TT01'2'2HB '211 F'AIL COLO LE:G LO.OP '2B TE:HPE:RATURE: TTG1'2'2CB '211 F'A IL. COLO LEG LOOP 1B TE:MPE:RATURE TT011 "2CB '211 F'A?L. AUX F'W F'LOW TO STH GEN E-seA F'T0?J? 333 F'AIL. F'EED CNTRL VL.V STM GEN £-see tPe?eJ J'+J F'AIL STEAM GENERATOR £-see PRESS PTG?5'2 233

34 Current Alarm List (CAL) - An alphanumeric display lists parameter alarms in chronological order. As alarms clear they can be removed from the Current Alarm List. The information for each parameter displayed on the current alarm list includes:

Time of alarm arrival Severity of the alarm English descriptor of the parameter Current parameter value Violated setpoint Instrument tag no. (point I.D.)

Operational display page

• See Figure 11.

Out of Range List An alphanumeric display lists the out of range alarms in chronological order. The information for each out of range alarm message includes:

"FAIL" identifier English descriptor of the parameter Point ID Operational display page Figure 12 depicts the typical out of range list page.

MI0784-0021A-RE03

35 Alarm Transition Categorization Whenever a parameter fails out of range, the message is placed on the top line in blinking blue until acknowledged.

Bad Data List An alphanumeric display lists the bad data alarms in chronological order. The information for each bad data alarm message includes:

"BADD" identifier English descriptor of the parameter Point ID Operational display page Figure 13 depicts a typical bad data list.page.

Alarm Transition Categorization Whenever a parameter fails as bad data, the.message is placed on the top line in bl.inking blue until acknowledged.

6.4 Display Methodology The CFMS is an information display system and as such uses many

• standard display techniques including:

MI0784-0021A-RE03

35a FIGURE 13 TYPICAL BAD DATA LIST PAGE

]* I I I_I ,I) I) I _I) I I

- .. F,. I .;. l. l ,,.;o l I ' I I I I*'B A D l ... . . DATA LI s T II I " II I " II 111 II 111 II I1" I I , ,.

S S oi .S I G'tI 0_

&~: .. ::£e s i s 0 s ~ S 0 S G i O S E .. C1C1 HC1T LEG TEllP" LC11: 1 F- l ( llFc ) Tl 1 lX  : 1l E ;.C1C1 C:llllT !F Fo..:.Y .... F'f..ES! . P":;;l!1'lY  ::;. .. l --

c--

S .. c°C1 MLI).( F'll F.lllP C1J !C F f::E!.H F SE:1't > PT't7:! o!>  :; ~::.

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E .:.C*CI .:.*.*>: f'O Pl*llf* Ol!C f'Fo.E~!C,.l'tG> F'T't?l!>J l:!J E* .. C*C1 *:.H .. f:.u F\.lllP CIJSCH HC1Fo. FFo.ESS P'2 i: J:s

T: 1.:._

E .:.C*C1 1: llllT !Fr.. .:.*,* llC1. 1 F'LOlll'.,;,Tt nH  :-t"+ -

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- : *~* e... c*c* .;.1..1:.: F'll f'L*:*llFo.o;,TE TO SG'l f'T"+'?:*'.9 'l~ ~

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--- =- -*c* C t:ll T :F Fo.,.; *1' 1 Ff:. E.! .! Pl*~*~~  :::... l :s:

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E .. C°C1 C* 1L Cl LEu Ttllf 0: LC10f' t.:. I llFI > T11 I y *~ l I c*,..C1C. Hf:: J f UllF HC*Fo. 114 F'f\ESS ,.lOSr

_ ... -- . *1 ~:1

-  ;  : .. 1 E*C.C'I Hfl";iJ . COLC'I LEu ...

"'... F'LOlll'..:O TE f'Jll J"'~

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: :..:. ::~. : .,. !i l:j I I I 11 I I I 1'"1 I I I I I 11111 It 1111 I I I I I I I I 11111 I I I I I I I I I lri .:.ei 1 5 1'"1 I I I j=>I t+. 0

36

• Standard Color Codes Standard Symbol Shapes Standard Symbol Behavior Flow Directions Spatial Arrangement The following section describes these conventions. Specific applica-tion to the different types of displays is described in the succeeding sections.

6.4.1 Color Codes Color is used in the CFMS to classify information and assist the user in the search task.

Eight colors are used.

The colors are classified according to the information they present.

Background

Black - Background Color

• MI0784-0021A-RE03

37

• Information Blue - Non-Essential, Failed, Bad Data, Static Components Cyan - Essential Information, Normal Status Red - Active, On, Open, Energized Green - Passive, Off, Closed, De-energized White - Intermediate, Throttled Alarm

• Yellow - Caution Magenta - Danger 6.4.2 Standard Symbol Shapes Standard symbols shape codes indicate major components for the opera-tional displays and critical function status. Figure 14 displays typical component symbol shapes. These symbols are developed from:

1. Standard piping and instrumentation diagram symbols.

2. Operator input

3. Simplified physical depictions of function .

• MI0784-0021A-RE03

37a FIGURE 14 TYPICAL COMPONENT SYMBOL SHAPES REACTOR CORE PRESSURIZER RESERVOIR

• 0 TURBINE SPRAY STEAM GENERATOR VALVES VALVES TANK

~*

• TYPE OPEN e EJ e

CLOSED Al~ALOG -w-

-+i-NFO

~~I ~ *'

NFC TiiREE \JAY FAILED

~10 INFO.

• ~

38

• 6.4.3 Symbol Behavior A. Dynamic and Static Behavior Graphical symbols used on the CRT displays are either static or dynamic. All static symbols are shown in blue. Dynamic symbols change color and shape depending on plant conditions.

For dynamic symbols, the two shape and color codes are hollow and solid, red and green.

An active component is hollow and red; a passive component is solid and green .

Active behavior includes component on, valve open, and passive behavior includes component off, valve closed.

Figure 15 summarizes typical shape and color codes.

B. Valve Behavior Six shapes are used on the display to describe the status of a valve. Not all shapes will be used for any one valve .

• MI0784-0021A-RE03

38a FIGURE 15 TYPICAL SHAPE AND COLOR CODES C><l VALVE OPEN RED

~ VALVE CLOSED '3REEN NO ALARM

~ VALVE NFC RED D

GOOD QUALITY BLUE ~ VA.LVt NFO GREEN

~

NO ALARM D

VALVE THROTTLED WHITE F.W.ILEO INPUT YELLOW

~ VALVE NO INFO BLUE

~

ALARM F..:.ILE:::i INPUT MAGENTA I YELLOW ACTIVE STATE~HOL!..OW II ALARM PUMP ON RED GOOO QUAL!TY .

MAGENTA ACTIVE, ON. OPEN PASSIVE STATE- SOLlO PUMP OFF GREE.~

PASSIVE, OFF. CLCSEO

39 SHAPE COLOR STATUS Hollow Red Open Solid Green Closed Left Half Hollow Red Not fully Closed*

Left Half Hollow Green Not fully Open*

Left Half Hollow White Throttled Right Half Hollow Blue No Information or Failed (2 limit)

(Open contact state for 1 limit)

• NOTE: These two shapes are used only when one limit switch on the valve is available C. Critical function alarm matrix behaves with color and shape according to the following alarm and quality state combinations:

Alarm No Alarm Good Quality Magenta Blue Failed Input ~ Magenta Yellow

~ Yellow MI0784-0021A-RE03

40

• D. Words and Numerical Behavior Words and numerical values also have behaviors. A numerical value can appear as:

Cyan Normal Yellow Caution Magenta Danger All numerical values are shape coded by placing a symbol leading and trailing the value.

Normal xxxxxx No Leading or Trailing Symbol Unacknowledged Alarm Trailing*

Acknowledged Alarm Leading and Trailing MI0784-0021A-RE03

41

~- Bad Data or Out of Range

???????? Blue Question Marks E. ESG Status The engineered safeguards alarms are located at the lower left corner of CFMS displays. They will be to the right of the critical function monitor matrix. Normally they will be invisible and will be displayed in YELLOW upon an ESG signal being generated .

• The ESG Systems which alarm here are the:

1. CHP Contai.nment High Pressure

2. SIS Safety Injection Actuation S,ignal

3. CHR Containment High Radiation

4. CIAS Containment Isolation Actuation Signal

5. RAS Recirculation Actuation Signal F. Alarm Flashing and Acknowledge Flashing symbols and numeric values are used to attract the attention of the user to a point that has just gone into alarm and has not been acknowledged. These flashing alarms include symbols,

• numerical values, sector numbers.

MI0784-0021A-RE03

42

• Pressing the ACK button on the keyboard in the Control Room acknowledges the alarm and stops the flashing. Alarms cannot be acknowledged from any other station.

The Control Room ACK keys stop the flashing on all pages of all display stations.

The color of the parameter, symbol, or alarm is not affected by acknowledging an.alarm .

• MI0784-0021A-RE03

43

• 7.0 Historical Data Storage and Retrieval The Historical Data Storage and Retrieval System (HDSR) assists Palisades Personnel in the assessment of historical plant information.

The HDSR is used to record, store, recall, and display historical information as it is needed by plant personnel. The system is designated to respond to user's needs under a variety of situations.

The user is offered the choice of viewing historical date on color CRT displays as graphs or on computer printouts as logs. The graphical representation is based on a sectoring concept that provides a zoom-in enlargement of sections of the HDSR graphs.

The HDSR provides:

7.1 Data Storage

1. Data Data which are stored may be broken into 2 classes:

A. "Raw" data from I/O ch~ssis B. Calculated data from the AMS Selection of data and the number of inputs selected are determined by the plant AMS.

MI0784-0021A-RE03

44

• • 2. Memory Data are stored on disc for short term memory and on tape for long term. The transfer from disc to tape is performed by the operator.

3. Storage Initiation Storage may be initiated manually during normal operations and periods such as startup or shutdown. Storage is automatically initiated after reactor trips or periods of power or certain equipment failures .

• 4. Resolutions Data are stored at 2 resolutions:

A. High - not more than 2 seconds per point for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> B. Low - 1 minute per point for 2 weeks Data will be overwritten after it passes the 16 hour/2 week point on the disc. This data will be lost unless a back-up to tape has been performed.

5. Disc Protections

• MI0784-0021A-RE03

45

• Protections are in effect on data so that accidental erasure cannot occur. These protections are of two types:

A. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> pre-event protection.on high resolution data B Twelve hour post-event protection on high resolution data

6. Tape Back-up Magnetic tape back-ups for HDSR disk provide the means for permanent storage of plant data. Back-up for both high and low resolution data is possible. High resolution backs up date. for the previous 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Low resolution backs up data for the previous week.

7.2 Data Retrieval AMS data may be accessed from two areas:

A. Retrieval from disc.

The disc contains the latest 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> and 2 weeks of AMS data and may be directed to the AMS graphical display or line printer using the data recall commands. The output from the line printer provides time tagged blocks of data. The data are limit checked and annotated, converted to engineering units and are in user selected time increments.

MI0784-0021A-RE03

46

• B. Retrieval from tape.

Data that were recorded prior to sixteen hours are available via the AMS line printer. Data retrieval is accomplished by mounting the tape containing the time span desired onto the tape drive, dumping the tape to the AMS computer, and directing the output to the AMS line printer using data recall commands.

The five major functions of the HDSR are:

Trends Logs

• Graphs Tape Back Disc Protection Figure 6 depicts the HD$R hierarchy which is arranged in three levels by function. Movement through the hierarchy is done using the option item list. The user controls HDSR through the page control module. Each block of the HDSR hierarchy is a dialogue page that is interactive with the user. The dialogue page is designed in two parts:

1. The upper portion User information

• MI0784-0021A-RE03

47

• 2. The lower portion User entry box for requests and selection.

Figure 16 is a depiction of the display for the HDSR Level 1 dialogue page. Figure 17 shows a typical HDSR Level 2 dialogue display. All HDSR dialogue pages have instructions to exit the HDSR system and return to the AMS.

Trend Displays Two trend display pages provide graphical, time based trends. Each trend display page can trend four parameters. The graphical trend

• displays are dynamic; that is the top of the trend is the most recent parameter value.

graphical trends.

The trend displays are separate from the HDSR The HDSR graphical trend is a static graphic or a "snapshot" of historical data that is not continuously updated.

All four trends on a display page utilize the same time scale. Each trend display page may have a different time scale. All trend graphs can be area filled at one-half normal intensity. Alphanumeric annotation is provided on each trend page. This includes scales, axis and labels. Each trend is capable of displaying the previous 256 points and is continuously updated at a constant time increment .

• MI0784-0021A-RE03

16 SHA 1...'PAL 1 i:tPR/*20/ 198't USER ALOGUE C 198'+ CE 130 1039:25 SYSTEM FUNCTIONS LEVEL I MELCOHE TO THE CFHS DIALOGUE THIS DIALOGUE MILL ALLOW YOU TO PERrORH SYSTEH rUNCTIONS DIRECTLY rROH YOUR DISPLAY STATION.

PLEASE SELECT THE NUHBER or THE rUNCTION YOU WANT PERFORHED:

rUNCTIONS DESCRIPTION 1 TRENDS RECORDS CURRENT DATA WHICH IS GRAPHICALLY DISPLAYED ON TMO TREND PAGES.

"2 HDSR LOGS PRINTS LOGS or HISTORICAL DATA ON THE CFHS PRINTER.

3 HDSR GRAPHS REPRESENTS HISTORICAL DATA ON SIX HDSR DISPLAY PAGES. ONE or THE HDSR PAGES IS ASSIGNED TO THIS STATION. ONLY THAT PAGE H~Y BE CHANGED BY THIS STATION.

Ii HDSR BACKUP TRANSrERS HISTORICAL DATA rROH THE DISK TO TAPE roR PERHANENT STORAGE.

S HDSR DISK PROTECTS HISTORICAL DATA FROH BEING OVERWRITTEN PROTECT I OH AFTER A SIXTEEN HOUR LIHIT IS PASSED.

ENTER YOUR SELECT I ON ON THE KEYBOARD, FOLLOWED BY @ll4M EXIT USING ~ IOU ~ OR gjli 0 1111

)

• • APR/*20/ 198'1 10'10:25 FIGilli-7 U~.ER YA L0; lJ E T~'.£NDS LEUEL 2 130 TWO DIALOGUE PAGES ARE AVAILABLE FOR CHANGING TREND PARAHETERS:

LEVEL 2 SELECTS MHJCH TREND SET WILL CHANGE, l OR 2.

LEVEL 3 CHANGES POINT JDS, RANGES, BASELINES ANO TIHEBASE.

~----------

ITEH roRHAT CURRENT STATUS LIST 1 GO DIRECTLY TO TREND SET l l IBi . .,.

HIN l

• 2 TREND SET 2 l OR '2 2 IBi BASE HAX HIN BASE HAX HIN 3 BASE HAX HIN BASE HAX TIHEBASE IS SECOHO(S)

CHOOSE AN ITEH AND ENTER FOLLOWING THE APPROPRIATE FORMAT. NOTE ALL ENTRIES ARE ACCENTED IN WHITE.

EXIT USING ~ DUD !Ill OR gjji 0 ~ OR ITEH l

48 A typical trend page is depicted in Figure 18.

The trends are set up through the display station. The user enters the following information to set up the trends:

1. The page time scale

2. For each of the four graphs:

a. Point ID

b. Upper and lower engineering range limits (if not entered, default values of the maximum range are automatically selected)

c. Baseline value NOTE: All graphs are not required to be filled; ie., the user can trend from one to four trends per page.

The trend display pages are accessed by keying the TREND key.

The trend displays provide the following information:

1. English Descriptor - Describes the trend, usually in terms of the monitored process variable .

• MI0784-0021A-RE03

18 SHA 1...'F*t.L 1 AF*R/20i1981f TREND 1 120 1939:05 TIMEBASE: I SECONDS PRESSURIZER VAP PRESSURIZER SI PZR WIDE RANGE DIRTY WASTE ORN BASE: 559 BASE : '20'25 BASE: 119 BASE: 39 l 61f 3 DEG r '2099 PSIA 69 PCT 58 PCT 59 100 T

I "i=_~~

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'250 HIN: 599 HIN: '2000 .HIN: 100 HIN: '20 HAX: 600 HAX: *2esa HAX: I '2(~ HAX: If 9

49

2. Engineering Units.

3. Alarm Condition - If alarming, displayed in magenta.

4. Current numerical value.

5. Digital - Display current state.

6. Time Post Trip - Time elapsed since reactor trip.

7. Date and Time - Seconds figure updated in 5-second increments.

8. Scale - The engineering scale used in the present display.

9. Title and page number.

Logs are computer printouts of plant parameters that were stored via

• SR. Eight plant parameters may be printed on a log at one time.

~ogs dialogue Level 2 and 3 provides the options for selecting parameters, start and end times, time step and data resolution.

Graphs Graphs and trends have similarity in their setup. Four graphs are shown on a display page at a time. The left hand vertical axis presents the time scale. The minimum and maximum scale values are listed at the bottom of each bar chart. A baseline is selected by the user. The baseline is that line from which the graph is drawn.

MI0784-0021A-RE03

so

• 8.0 8.1 System Interfaces Display Stations The user display station is the primary man-machine interface. The display functions of the SPDS, the CFMS, and HDSR displays are accessed and presented by the user display stations.

In the control room the SPDS user display station is dedicated to the presentation of the SPDS display only and is strategically located so that it can be monitored easily by control room supervisory personnel.

During normal plant operations the SPDS display will be locked out form displaying CFMS or HDSR pages. A redundant display station in the control room will allow users to display the full capability of the AMS.

Each display station consists of:

1. a color CRT monitor

2. an alphanumeric keyboard

3. a page control module including function keys:

a. RESET - This key is used to compress the alarm lists .

• MI0784-0021A-RE03

51

b. PAGE - This key is used to tell the computer that the operator wants to look at the page whose number is entered immediately following the page key.

c. SECTOR (SECT) - This key is used to tell the computer that the operator wants to look at the sector whose number is entered immediately following the sector key.

d. EXECUTE (EXEC) - The execute key is used to tell the computer that the operator wants the page or sector keystrokes entered into the keyboard executed;

e. TREND - The trend key is used to tell the computer to display the trends entered previously by the computer operator from the computer system console.

f. FORWARD (FWD) - This key is used to tell the computer that the operator wants to move to the next page in sequence in the hierarchy.

g. BACKWARD (BACK) - This key function is the reverse of the forward key. It is used to move to the left or through decreasing page numbers on the display hierarchy diagram .

• MI0784-0021A-RE03

52

• h. ACKNOWLEDGE (ACK) - This key acknowledges alarms by suppress-ing any blink when pressed. Only the operator can acknowledge alarms.

i. HDSR - This key accesses the HDSR graphical page for the user display station.

j. HDSR SECTOR (HDSR SECT) - This key allows sectoring in the dialogue and HDSR graphs.

k. DIALOGUE (DIAL) - This key accesses the dialogue pages for trends and HDSR.

The page control module design is displayed in Figure 19.

Display stations are placed in the:

1. Control Room

2. TSC

3. EOF at South Haven

4. GOCC at Jackson MI0784-0021A-RE03

52a FIGURE 19 CONTROL PAGE MODULE RESET SELECTTRENO DISPLAY 0

• 9 NUMERIC KEYP:..O COM PR ESSES ALARM CJST ~ ,

I r-17s..:..

£;1.C:.C.-w7"e-S c..:t-IN.Al""i:> RESET TR ENO 7 8 9 I RETURN I SELECT PO.G~

~ PAGE iolO.S~ L1.l 5 6 I 2

.$i:l..~C. 'i'

., IQ. L.O i-' 'Ac. E c.U£ SELECT SECTOR SE\..H.T "40SR S ~c.T~.._

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EXECUTES COMMANC

'\_PAGE FORWARO

. PAGE BAC~WARO KEY SEQUENC;S; PAGE #~# EXEC si::cT # exec FWO BACK

53

• 8.2 Printer The printers printout HDSR log information. The printer is located in the computer support module at Palisades which is near the turbine deck.

8. 3 Programmer.' s Console The programmer's console is located in the computer support module.

It is used to maintain the system software and to coordinate hardware interface operation .

• 8.4 Annunciation Outputs The AMS has contact outputs for annunciation of alarms for the follow-ing conditions:

1. Critical function alarm

2. AMS failure alarm

3. AMS failed sensor alarm Annunciation shall be provided by other Palisades devices external to the AMS .

• MI0784-0021A-RE03

54

• 8.5 Hard Copy Trend Recorder Outputs The AMS has four analog outputs for external hard copy trend recorders (to be provided by others). The specific analog values are address-able through the programmer's console.

8.6 Data Link Inputs The AMS acquires inputs from the meteorological tower. The informa-tion is received with a modem.

8.7 Hardwired Inputs Analog and contact inputs are connected to the AMS central computer via termination cabinets .

• MI0784-0021A-RE03

55

• 9.0 Signal Validation To prevent misleading the operator, analog values displayed by the AMS are extensively validated in.real time prior to display. This valida-tion is achieved by comparing* redundant sensor readings and/or through other checks prior to display of the parameter to the operator. In the event that the computer is unable to ascertain a valid reading, the analog values on the display pages are filled with blue question marks, alarms are presented in yellow (caution), and bar charts turn yellow. These actions readily identify faulty data to the operator.

In addition to the color changes that occur, the signals that are

• invalid are placed on the Bad Data List page of the AMS.

Validation of SPDS analog inputs begin by performing limit checks on each input signal. This check assures that the input is within its eXpected operating range. Inputs found out of limits are flagged, alarmed and placed on the Bad Data List. Appendix C contains a copy of the Input Data Base for the Palisades CFMS (AMS). The limit checks and all data information are contained on this list. New data may be added to the data base by qualified personnel and old data may be removed .

• MI0784-0021A-RE03

56

• 9.1 EPRI Signal Validation Program Consumers Power Company is a member of the Utility Advisory Group for the EPRI PWR Signal Validation project (RP 2292-1). During 1985 EPRI will release signal validation algorithms developed by Babcock and Wilcox that utilize both physical redundancy and analytic redundancy for validation of selected PWR safety parameters. These algorithms may be incorporated in the AMS at a future date to enhance the current signal validation techniques .

• MI0784-0021A-RE03

57

• 10.0 Inadequate Core Cooling Instrumentation Inadequate core cooling (ICC) instrumentation, including a reactor vessel level monitor and core exit thermocouples will be installed in the Palisades plant during a future refueling outage. These ICC instruments will be Class lE. These Class lE signals will be data linked via qualified signal isolation devices to the AMS computer input processor.

The SPDS display will be modified to incorporate the ICC instrUmen-tation after the signal installation. It is expected that the reactor vessel level signal will replace the T-ave signal on the Core Heat Removal function display. The hottest core-exit thermocouple (validated) signal*will be used to compute the subcooling margin temperature in place of the hottest T-hot temperature signal now being used.

MI0784-0021A-RE03

58

• 11. 0 Verification and Validation To assure that a very high quality SPDS is implemented, a verification and validation (V&V) program is being conducted throughout the process of design, development, installation, and testing of the system.

Figure 20 is a flow chart detailing the V&V program. This section discusses the major types of design verification to be performed for the Palisades SPDS.

Verification and validation of the CFMS was performed by Combustion Engineering and CPCo during the design and installation phases of that portion of the AMS. The SPDS is treated as a separate system and is receiving a separate V&V program. However, additional V&V of the CFMS will occur because of the commonality of both hardware and software.

The CFMS was developed to all of the hardware and software standards for an SPDS and many of the functional requirements also.

11.1 SPDS Requirements Document The SPDS requirements document is being written to detail the functional specifications of the system and specify the CRT display.

The SPDS display is designed to utilize the CFMS inputs, signal validation, color codes, alarm features, and safety function considera-tions. Also, the SPDS display supports the Palisades Emergency Procedure Guidelines which are the basis for new function oriented

• emergency operating procedures.

MI0784-0021A-RE03

FIGURE 20 58a SPDS DESIGN FLOW CHART SPDS FUNCTIONAL SPECIFICATION I

• CONTROL SPECIFICATION I

SYSTEM REQUIREMENT REVIEW*

I I

TEST PLAN

- - ~ - - - -1 ARCHITECTURE I DOCUMENT I

HARDWARE*

CONFIGURATION I DESIGN REVIEW PRELIMINARY*

DESIGN REVIEWI I

DETAILED DESIGN I

l CRITICAL*

DESIGN REVIEW I

SYSTEM I

SOFTWARE INTEGRATION

- - l I

INTEGRATION I

VALIDATION*

TEST I

FIELD INSTALLATION I

I FIELD VALIDATION*

TEST I

I VALIDATION*

REPORT

• V&V Activity

59

• The specification details the regulatory requirements as well as the format, content, color and source of data for the displays.

details the operator interaction requirements.

It also When completed the specification will provide the software programmer with implementation requirements. This document is the foundation on which the completed SPDS will be designed, installed and accepted.

11.2 SPDS Requirements Review The SPDS requirements review will be conducted by a team of CPCo personnel to independently determine that the requirements will result in a possible and useable solution to the entire SPDS program. The requirements will be reviewed for correctness, completeness, consistency, understandability, feasibility, testability and trace-ability. The requirements review also provides the basis for develop-ing the SPDS validation test plant.

The results of the SPDS requirements review including identification of system deficiencies will be documented. Upon completion of the requirements review and resolution of deficiencies, the requirements document will become a controlled document so that future changes are traceable to an approved document.

MI0784-0021A-RE03

60 11.3 Design Review The objective of ,this activity is the verification of hardware and software design against the SPDS requirements. The specifications and the design will be reviewed to ensure that the system requirements decomposition into hardware and software is complete and that there are no ambiguities or deficiencies. The specifications and design descriptions are both contained in the SPDS Requirements Document.

This V&V activity will examine the software design in terms of its logical integrity, ability to satisfy the performance requirements, data manipulation and timing requirements. Other items to be considered are operator response, hardware interface design, data base design, control structures, task allocations, programming languages, and I/O structure.

The design review will address Architecture for both hardware and software Input/output interfaces System and executive control Operating sequences including initialization, startup, error detection, restart, etc.

Testability: Use of test equipment such as data tapes, simulations, etc.

MI0784-0021A-RE03

61 Timing analysis of sampling rates, response time, etc.

Availability Algorithm design and data verification Information flow including communication between hardware sub-systems, data management and signal conversion to engineering units.

Human factors engineering including consultation with operators to verify displays, and analysis of control room activity.

The results of the design verification activity will be documented with any deficiencies identified for resolution. A Design Verification Report will then be issued.

11.4 Validation A validation Test Plan for the SPDS will be developed by Consumers Power Company. The test plan will include:

Test requirements Test philosophy Te~t environment Test specifications Detailed test descriptions Test procedure Test evaluation approach

• MI0784-0021A-RE03

62

• Static and/or dynamic tests of all SPDS capabilities will be per-formed.

During validation testing there will be recording and analysis of test results for acceptability. Records will be kept during each validation test to insure that the test is identified and the inputs and outputs are achieved with sufficient detail so that the same test can be repeated by others and results confirmed.

The test results, analysis, and nonconformances to acceptability criteria will be documented in a Validation Test Report.

11.5 Field Verification Test A field verification will be performed to insure that the validated system was properly installed. An Installation Verification Test Plan will be prepared. The tests to be performed and any special test equipment will be defined in this plan.

Field verification will consist of documenting that each input signal is properly connected and that the signal range is consistent with design so that the information displayed is directly correlated with the sensor data. For each test, the inputs, outputs, and accept-ability criteria will be specified.

MI0784-0021A-RE03

63

• 11.6 Validation Report A final SPDS V&V report will be issued to summarize all of the V&V results for the program. This document will provide the foundations for dialogue with NRC when reviewing the adequacy of the SPDS validation effort. Traceability of the V&V activities throughout the project, identification and resolution of discrepancies and reference to detailed documentation will be provided.

11.7 System Modifications Modifications of the SPDS will be verified and validated using the same level of detail contained in the design V&V. Documentation of all modifications will be permanently maintained.

MI0784-0021A-RE03

64 12.0 Human Factors Engineering Detailed Human Factors Review procedures have been developed for both pre-installation and post-installation periods. Appendix D contains a copy of these procedures. The Human Factors Review will be documented and included as ~art of the V&V final report.

MI0784-0021A-RE03

65 13.0 AMS Training The Palisades Training Department has prepared an extensive course for the use of the AMS. This includes details concerning the design, philosophy, utilization, data base, alarm algorithms, CFMS, HDSR, etc.

Hands-on training is being given to all potential emergency response, operations, and technical personnel within the Company.

A mimic of the AMS is provided as part of the Palisades training simulator in Midland, Michigan. Operators will betrained in how to utilize the function oriented safety functions, the success paths, the success criteria, and the HDSR capabilities of the AMS. Also, their training will concentrate on being able to recover from emergency conditions when the AMS is not available .

• Ml0784-0021A-RE03

66

• 14.0 Standards, Codes and Guidelines The AMS design bases were established using the appropriate and applicable standards, codes and guidelines listed below.

14.1 Code of Federal REgulations (CFR) 10 CFR 50 Licensing and Production of Utilization Facilities -

Appendix A General Design Criteria (GDC)

1. GDC 19 - Control Room 10 CFR 50 Appendix E - Emergency Planning and Preparedness for Production and Utilization Facilities.

14.2 Regulatory Guides 1.97 Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident -

Revision 2, August 1980.

14.3 NUREGS NUREG 0696 Final Report

• "Functional Criteria for Emergency Response Facilities", February 1981 MI0784-0021A-RE03

67

• NUREG 0700 "Guidelines for Control Room Design Reviews", September 1981 NUREG 0737, Supplement 1 "Requirements for Emergency Response Capability", December 1982 NUREG 0801 Draft Report for Comment "Evaluation Criteria for Detailed Control Room Design Review",

October 1981 NUREG 0835 Final Report, Draft "Human Factors Review Guidelines for the Safety Parameter Display System", September 1983 NUREG 0899 "Guidelines for the Preparation of Emergency Operating Procedures",

August 1982 NUREG/CR-1994 "Techniques for Displaying Multivariate Data on Cathode Ray Tubes with Applications to Nuclear Process Control", April 1981

• MI0784-0021A-RE03

68 NUREG/CR-2496 "Human Engineering Design Considerations for Cathode Ray Tube-Generated Displays", April 1982 14.4 IEEE Standards P742/ANS 4.3.2 - "Criteria for the Application of Programmable Digital Computer Systems of Nuclear Power Generating Stations".

14.5 ANSI/ANS Standards ANSI/ANS 4.5 - 1980 - (American Nuclear Society sponsored) Criteria for Accident Monitoring Functions in Light-Water-Cooled Reactors ..

ANSI/ANS 4.6 - draft - Functional Criteria for On-Line Monitoring -

Transient Reconstruction in Light Water Reactors.

14.6 Nuclear Safety Analysis Center (NSAC) Guidance NSAC/8 "Nuclear Plant Safety .Parameter Evaluation by Event Tree Analysis",

October 1980 NSAC/10 "A Parameter Set for a Nuclear Plant Safety Console", November 1980 MI0784-0021A-RE03

69

• NSAC/34 "Design and Hardware Alternatives for a Safety Parameter Display System", May 1981 NSAC/38 "A Transient Library f9r Validating Safety Parameter Display Systems",

December 1982 NSAC/39 "Verification and Validation for Safety Parameter Display Systems",

December 1981 NSAC/40 "Accident Sequences for Design, Validation, and Training (SPDS)",

April 1982 NSAC/61 "Verification and VAlidation of the Yankee Plant Safety Parameter

• Display System", January 1984 14.7 EPRI Signal Validation Committee "EPRI Signal Validation Draft Interim Report with Functional Requirements", January 9, 1984 MI0784-0021A-RE03

70

• "EPRI Signal Validation Advisory Group Meeting Minutes",

February 24, 1984 14.8 Combustion Engineering Documentation CE Document 578-ICE-4503 Revision 01 "Functional Test Procedures for the Consumers Power Company Palisades Nuclear Generating Station Critical Function Monitoring System";

June 29, 1983 CE Document 578-ICE-1210 Revision 01 "Functional Design Speciffcation for the Critical Function Monitoring System for Consumers Power Company Palisades Plant", May 12, 1983 CE Document 2966-ICE-1212 Revision 02 Pages70-109 "CFMS Displays CEN-152 Revision 01 "Combustion Engineering Emergency Procedure Guidelines", November 1982

• MI0784-0021A-RE03

71

• CE Report "The Critical Safety Functions and Plant Operation", Nuclear Technology, Volume 55, December 1981 CE Report "The Application of the Safety Level Concept and Related Aviation and Aerospace Concepts to Light Water Reactors", ANS Summer Meeting, June 7-12, 1981 CE Report "The C-E Historical Data Storage and Retrieval System", 10th Annual Conference on Reliability, Availability, and Maintainability, May 25-27, 1983 .

CE Report "An Integrated Accident Monitoring System, A Computerized Aid to Improve the Overall Response to Abnormal Situations", International Meeting on Thermal Nuclear Reactor Safety, August 29 - September 2, 1982 CE Report "Operational Aids to Improve the Man-Machine Interaction in a Nuclear Power Plant", ANS Annual Meeting, June 8-10, 1980

• MI0784-0021A-RE03

72

• CE Report "The Operator's Role and Safety Functions", Workshop on Licensing and Technical Issues, March 9-12, 1980 CE Report "The Plant Designer's View of the Operator's Role in Nuclear Plant Safety", Fourth Symposium on Training of Nuclear Facility Personnel, April 27.-29, 1981 14.9 Additional Industry Guidance INPO 83-036 "Human Engineering Principles for Control Room Design Review", Nuclear Utility Task Action Committee (NUTAC), September 1983 "Guidelines for an Effective SPDS Implementation Program", Draft, Revision E, Nuclear Utility Task Action Committee (NUTAC),

November 1983 Northeast Utilities Letter NE-83-SAB-235 MS Kai (NE) to Distribution "Safety Parameter Display System", September 16, 1983 MS-84-21 "ACRS Subcommittee Meeting on Human Factors", Meeting Minutes Service for Evaluating Regulatory Changes, February 7, 1984 MI0784-0021A-RE03

73

• 14.10 Alternative Industry SPDS Designs AROS Corporation "Safety Parameter Display System", Presentation Summary, Draft Report QUADREX Corporation "Quadrex micro-SPDS Safety Parameter Display System for Nuclear Power Plants", Summary Proposal Pacific Gas and Electric Letter JD Shiffer (PG&E) to DG Eisenhut (NRC)

"PG&E Safety Parameter Display System Safety Analysis for Diablo Canyon", August 2, 1983 Scientific Systems Services Document 301389-0lOOB "Control-Spec for the Safety Parameter Display System for Midland Units 1 and 2", November 18, 1983 Scientific Systems Services Document 301389-0400A "Operator's Guide for the Safety Parameter Display System for Midland Units 1 and 2", February 10, 1984 MI0784-0021A-RE03

79 APPENDIX A

• AMS LEVEL 2 DISPLAYS .

• MI0784-0021A-RE03

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APPENDIX B AMS LEVEL 3 DISPLAYS MI0784-0021A-RE03

I

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APPENDIX C

• AMS INPUT DATA BASE MI0784-0021A-RE03

INPUT~ BASE FOR THE PALISADES CRITICAL FUNCTION MONITORING SYSTEM DESCRIPTION No. 578-ICE-1402, REVISION 00 Nuclear Power Systems COMBUSTION ENGINEERING,INC.

Windsor, Connecticut PREPARED BY

v.

• lJ a.uL

.......o<t-~~~...,..-~~~~~~~~~~~~~~~~-DATE Walsh (INFORMATION & DISPLAY SYSTEMS)

• REVIEWED BY_~

APPROVED BY

_______

• _2:_......_~_.,......_.....___.__-______DA~E ~ J~ (o '/

M. E. Hartnett (INFORMATION & DISPLAY SYSTEMS)

(1J.b\~ DATE

~

,_(,.'8 'f G* a;' Neuschaefer (Secti 1\'Manager,ADVANCED COMPIITER SYSTEMS)

This document is the property of Combustion Engineering, Inc. ( C-E), Windsor, Connecticut, and is to be used only for the purposes of the agreement with C-E pursuant to which it is furnished.

Issue Date 6/6/84

~~~--'"~~~~~

Description No. 578-ICE-1402 Rev 00 Page 1 of 47

~\

~ Q!. CONTENTS

• 1.0 Table of Contents Record of Revisions Purpose 2

3 4

2.0 Instructions for Use 4 3.0 Data Base Record Information 5 3.1 Information Common to All Data Base Records 5

3. 2 Analog Input Records 6 3.3 Contact (Digital) Input Records 7 3.4. Composed Analog Records S 3.5 Composed Digital Records 9 3.6 Calculated Analog Records 9 3.7 Calculated Digital Records 10 Appendix A 11 Description No. 578-ICE-1402 Rev 00 Page 2 of 47

APPQO- PAG:S cu: VAL S MOCIF!E:l E)'PLANATit;)~S

~evisions for Cesc. ~2?66-IC:-1402.

.Jc '5 3 2 v J'.I ~~D All CHN J1 1J-1-32 EVP ~JD 1,3,4, S+aff,Datas,"cards " to "records";

CHN 17, 24, 'FT0306' to "FT3QC6", , A" in P !O "s 45 2 P! O's added 02 1 c-1 s- 33 V JW CHN 1-3 St:iff,Dates, "cards" to "records",

revisions.

4-1C Purposg,secticn d"s,(1d),(2) 7,~,10 Alar~ states 11-2512!-3Q,or:i '!lodificatiors "and additions 32-45

~evisions for :lesc. =578-ICE-1402.

oc e-e-e4 VJ\ol CHN 1,3,4-10,14,qev#;Contract#;Revd;change "card" and 23,24,ze, "cards" to "record" :ind "records",

33,40,,1 sc~*s 595,59?,6C3,6C4,1SPAL, 20?AL1310AL,320AL1330AL,35?AL, 390AL,45PAL,5SOAL,126PAL,1620AL, 165PAL,166PAL1173PAL,1790AL1 1e1PAL Jescri~tion ~c. ~7~-!C~-14)2 ~ev IJO Pag~ 3 of 47

1.0 Purpose

• The Critical Funcion Monitoring System (CFMS) is used to present the user with a concise, integrated and understandable presentation of information which will assist him in assessing the_~afety status of the plant.

This document describes the signal types and field information for the point ID's in the I/O database.

Section 2.0 presents instructions on how to use this document to add, delete or modify a point. Section 3.0 defines which records are to be used with each point type (i.e., analog input, composed analog, etc.).

Section 3.1 describes information which is common to all database records.

Sections 3.2 through 3. 7 describe the information contained in each database field for the analog inputs, digital inputs, composed analog and digital points, and calculated analog and digital points.

Appendix A contains the listing of the current I/O database for Consumers Power Company Palisades Nuclear Generating Station.

2 .o Instructions for Use If it is desired to add/delete a point from the CFMS data base, or to modify an existing point, then the following must be done:

(l~) If adding a new point, look in section 3.0 to find the section which will indicate what information must be entered on wh'ich records, according to the point type. Also look at section 3.1 for important notes. Then put these records into the data base.

(lb) If deleting a point, then remove all records pertaining to that. point from the data base.

(le) If modifying a point, look in section 3.0 to find the section which will indicate which particular records must be modified in the data base. Also look at section 3.1 for important notes.

(ld) Edit the I/O database, PIODB.DAT/141, accordingly.

(2) Run CFM4:PALIM.F.* CSS/14l to read the data base and, from it, create the PIPOPUTP.FTN file, and the INTPOINT.FTN file *

• Description No. 578-ICE-1402 Rev 00 Page 4 of 47

2*.Q. Data Base Record Information

• 3.1 3.2 3.3 Information common to all data base records Analog input records:

Contact (Digital) input records:

A,B,C,D,I,N A~E,I,N 3.4 Composed analog records: A,D,N 3.5 Composed digital records: A,E,N 2.6 Calculated analog records: A 3.7 Calculated digital records: A,E 3 .1 Information Commn ~ All Data Base Records (1) All entries are left-justified, unless otherwise noted.

(2) When a finite number of values is given for a record entry, then those are the only legal values for the present CFMS *

• Description No. 578-ICE-1402 Rev 00 Page 5 of 47

1*1 Analog Input Records

'A R.ecord:*Col\ilml9 Entry*

l Record Name (A) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-41 English Description.of point.

43-48 Signal type ("ANA-I" for analog input).

64-67 CFM input list print item number.

77-79 Display page where point appears.

B Record: Columns Entry l Record Name (B) f 3 Current Revision Letter (A

• base cfms) s-12 Point ID 14-16 Sensor type ("VI", see sensor units) 18-20 Processing frequency (CFMS cycles I processing).*

22-24 Conversion curve (linear ("LIN") or square root ("SQR!'),

or logarithmic ("LOG")).

29-34 Sensor low value.

36-41 Sensor high value.

43-44 Sensor units (voltage ("V") or milliamps ("MA")).

46-51 Engineering units low value.

53-58 Engineering units high value.

60-65 Engineering units (GPM, PSIG, HP, etc~>**

67 Significant figures after decimal point for engineering units.

( 0 - -+<)0000 i - -+ooo.o 2 * -+oo.oo 3 ,. +o.000 4 - +.0000 5 * -+o.ooo+oo >

69-71 Exponential for low engineering value and for low and low-low alarm values.

73-75 Exponential for high engineering value and for high and high-high alarm values.

77-78 Incremental change limit in digital counts (def*05).

C Record: Columns Entry l Record Name (C) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-22 Sensor drift limit.

24-26 Smoothing coefficient.

28-33 Sensor out-of-range, low value.

35-40 *sensor out-of-range, high value.

D Record: Columns Entry l Record Name (D) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-21 Low-low alarm value, engineering units.

23-30 Low alarm value, engineering units. .

39-46 High alarm value, engineering units.

48-55 High-high alarm value, engineering units.

57-62 High deadband value, engineering units.

75-77 Alarm time delay, seconds (0-127) *

• Description No. 578-ICE-1402 Rev 00 Page 6 of 47

I Record: Columns Entry 1 - Record Name (I)

• 3 - Current Revision Letter (A

• base cfms) 5-12 Point ID 17-19 Multiplexor.

28-29 Module(RJ) 31-32 Channel on the module(RJ).

36-38 Module address.

68-71 Direct memory access.

N Record: Columns Entry 1

3 Record Name (N)

Current Revision Letter (A

• base cfms) i-5-12 Point ID 14-21 Low alarm cutout point ID.

23 Cutout point's cutout state (open contact (0) or closed contact (C)).

25-32 High alarm cutout point ID.

34 Cutout point's cutout state (open contact (0) or closed contact (C)).

Ii 3.3 Contact (Digital) Input Records ")

A Record: Columns Entry 1 Record Name (A) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-41 English Description of point.

43-48 Signal type ("CI" for contact input).

64-67 CFM input list print item number.

77-79 Dis_play page where point appears.

E Record: Columns Entry 1 Record Name (E) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-15 Alarm/Status state ("OP" or "CL" for open or closed contact).

OPEN

• 0 state, CLOSED

• l state.

17-19 Alarm/Status state condition ("ALM", "NOA").

21-28 Alarm/Status state message.

30-31 Alarm/Status state ("OP" or "CL" for open or closed contact).

OPEN

• 0 state, CLOSED

• l state.

33-35 Alarm/Status state condition ("ALM", "NOA").

37-44 Alarm/Status state message.

46-47 Processing frequency (CFMS cycles I processing).

75-77 Alarm time delay, seconds (0-127).

Description No. 578-ICE-1402 Rev 00 Page 7 of 47

., I Record: Columns 1 :

• 3 5-12 17-19 28-29 31-32 Entry Record Name (I)

Current Revision Letter (A

• base cfms)

Point ID Multiplexor.

Module(RJ)

Channel on the moduie(RJ).

36-38 Module address.

68-71 Direct memory access.

N Record: Columns Entry 1 Record Name (N) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 36-43 Alarm cutout point ID.

45 Cutout point's cutout state (open contact (0) or closed contact (C)).

3.4 Composed Analog Records A Record: Columns Entry l R..ecord Name (A) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-41 English Description of point.

43-48 Signal type ("KA" for composed analog).

64-67 CFM input list print item number.

77-79 Display page where point appears.

D Record: Columns Entry l Record Name (D) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-21 Low-low alarm value, engineering units.

23-30 Low alarm value, engineering units.

39-46 High alarm value, engineering units.

48-55 High-high alarm value, engineering units.

57-62 High deadband value, engineering units.

75-77 Alarm time delay, seconds (0-127).

N Record: Columns Entry l _ Record Name (N) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-21 Low alarm cutout point ID.

23 Cutout point's cutout state (open contact (0) or closed contact (C)).

25-32 High alarm cutout point ID.

34 Cutout point's cutout state (open contact (0) or closed contact (C)).

Description No. 578-ICE-1402 Rev 00 Page 8 of 47

3.5 Composed Digital Records A Record: Columns Entry 1 Record Name (A) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-41 English Description.of point.

43-48 Signal type ( "KD" for composed digital).

64-67 CFM input list print item number.

77-79 Display page where point appears.

E Record: Columns Entry 1 Record Name (E) 3 Current Revision Letter (A** base cfms) 5-12 Point ID 14-15 Alarm/Status state ("OP" or "CL" for open or closed contact).

OPEN

• 0 state, CLOSED

• 1 state.

17-19 Alarm/Status state condition ("ALM", "NOA").

21-28 Alarm/Status state message.

30-31 Alarm/Stat.us state ("OP" or "CL.. for open or closed contact).

OPEN

• 0 state, CLOSED

• 1 state.

33-35 Alarm/Status state condition ("ALM", "NOA").

37-44 Alarm/Status state message.

46-47 Processing frequency (CFMS cycles I processing).

75-77 Alarm time delay, seconds (0-127).

N Record: Columns Entry 1 Record Name (N) J 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-21 Low alarm cutout point ID.

23 Cutout point's cutout state (open contact (0) or closed contact (C)).

25-32 High alarm cutout point ID.

34 Cutout point's cutout state (open contact (0) or closed contact (C)).

3.6 Calculated Analog Records A Record: Columns. Entry 1

3 Record Name (A)

Current Revision Letter (A

• base cfms)

• I 5-12 Point ID 14-41 English Description of point.

43-48 Signal type ("CA" for calculated analog).

77-79 Display page where point appears *

• • Page 9 of 47 Description No. 578-ICE-1402 Rev 00

J.*l Calculated Di~ital Records

• A Record: Columns Entry l Record Name (A) 3 Current.Revision Letter (A* base cfms) s-12 Point ID 14-41 English Description-of point.

43-48 Signal type ("CD" for calculated digital).

77-79 Display page where point appears.

E Record:*. Co 1U11m;9 Entry 1 Record Name (E) 3 Current Revision Letter (A

• base cfms) 5-12 Point ID 14-15 Alarm/Status state ("OP" or "CL" for open or closed contact).

OPEN

• 0 state, CLOSED

• 1 state.

17-19 Alarm/Status state condition ("ALM", "NOA").

21-28 Alarm/Status state message.

30-31 Alarm/Status state ("OP" or "CL" for open or closed contact).

OPEN

• 0 state, CLOSED

• l state=

33-35 Alarm/Status state condition ("ALM", "NOA").

37-44 Alarm/Status state message.

46-47 Processing frequency (CFHS cycles I processing).

75-77 Alarm time delay, seconds (0-127).

I Description No. 578-ICE-1402 Rev 00 Page 10 of 47

APPENDIX A: PIODB Listing (Revision 00)

• A A AlCRREAC E A AlCRREAC A A A2RCSINV E . A A2RCSINV A A AJRCSPRS E A AJRCSPRS CORE REACl'IVITY CNTRL ALGO ALARM PCS INVENTORY.CONTROL ALGO ALARM

• PCS PRESSURE CONTROL ALGO ALARM NORMAL NORMAL NORMAL CD CD

• en 102 102 102 A A A4CRHEAT CORE HEAT REMOVAL ALGO CD 102 E A A4CRHEAT ALARM NORMAL A A A5P3 CNMT HIGH PRESSURE TRAIN A CI 0119 E A A5P3 OP NOA NORMAL CL ALM HI I A A5P3 4 16 0 076 240 N A A5P3 A A A5P6 CNMT HIGH PRESSURE TRAIN B CI 0120 E A A5P6 OP NOA NORMAL CL ALM HI I A A5P6 4 16 0 276 752 NA A5P6 A A A5R3 CNMT HIGH RADIATION TRAIN A CI 0121 E A A5R3 OP NOA NORMAL CL ALM HI I A A5R3 4 16 2 076 242 NA A5R3 A A A5R6 CNMT HIGH RADIATION TRAIN B CI 0122 E A A5R6 OP NOA NORMAL CL ALM HI I A A5R6 4 16 2 276 754 N A A5R6 A A A5RCSHT PCS HEAT REMOVAL CNTRL ALGO CD E A A5RCSHT ALARM NORMAL A A A6CNTISO CONT ISO ALGO CD E A A6CNTISO ALARM NORMAL A A A7CNMTPT CONT PRESS/TEMP CNTRL ALGO CD E A A7CNMTPT ALARM NORMAL A A A8RXTRIP REACTO~ TRIP ALGO KD E A A8RXTRn> OP ALM 'i'RIP CL NOA NORMAL N A A8RXTRIP

. A A AI0103 PZR HEATER TRANSFORMER AMPS ANA-I 0002 325 B A AI0103 VI . 1 LIN o.o 5.0 v 0 200 AMP 05 C A AI0103 o.o 5.0 D A AI0103 I A AI0103 1 1 2 101 134 N A AI0103 A A AI0104 PZR HEATER TRANSFORMER AMPS ANA-I 0003 325 B A AI0104 VI 1 LIN o.o 5.0 v 0 200 AMP 05 C A AI0104 o.o 5.0 D A AI0104 I A AI0104 1 1 3 101 135 N A AI0104 A B AI2401L CNMT H2 MON CI 0064 244 E B AI2401L OP NOA NORMAL CL ALM HIGH I A AI2401L 3 5 0 145 296 N A AI2401L A B AI2401R CNMT H2 MON CI 0064 244 E B AI2401R OP NOA NORMAL CL ALM HIGH

• I A AI2401R N A AI2401R 3

Description No. 578-ICE-1402 5 2 145 Rev 00

. 298 Page 11 of 4.7

A A AMTBll ACOUSTICAL MONITOR CH 1 CI 0016 325 E A AMTBll OP NOA CLOSED CL ALM OPEN I A AMTBll -4 15 2 075 234

• NA AMTBll A A AR.0203 B A AR.0203 C A AR.0203 D A AR0203 I A AR.0203 N A AR.0203 PCS BORON CONCENTRATION VI 1 LIN 1

o.o o.o 2 2 5.0 5.0 102 ANA-I v 0 2200*

2 PPM 0001 138 05 A A CFlBOT CF 1 MATRIX BOX BOTTOM CD 102 E A CFlBOT A A CFlTOP CF 1 MATRIX BOX TOP CD 102 E A CFlTOP A A CF2BOT CF 2 MATRIX BOX BOTTOM CD 102 E A CF2BOT A A CF2TOP CF 2 MATRIX BOX TOP CD 102 E A CF2TOP A A CF3BOT CF 3 MATRIX BOX BOTTOM CD 102 E A CF3BOT A A CF3TOP CF 3 MATRIX BOX TOP CD 102 E A CF3TOP A A CF4BOT CF 4 MATRIX BOX BOTTOM CD 102 E A CF4BOT A A CF4TOP CF 4 MATRIX BOX TOP CD 102 E A CF4TOP A A CF5BOT CF 5 MATRIX BOX BOTTOM .CD 102

• E A CF5BOT A A CF5TOP 102 CF 5 MATRIX BOX TOP CD E A CF5TOP A A CF6BOT CF 6 MATRIX BOX BOTTOM *CD 102 E A CF6BOT A A CF6TOP CF 6 MATRIX BOX TOP CD 102 E A CF6TOP A A CF7BOT CF 7 MATRIX BOX BOTTOM CD 102 I

E A CF7BOT A A CF7TOP CF 7 MATRIX BOX TOP CD 102 E A CF7TOP A A CFBBOT CF 8 MATRIX BOX BOTTOM CD 102 E A CFBBOT A A CFBTOP CF 8 MATRIX BOX TOP CD 102 E A CFBTOP A A CF9BOT CF 9 MATRIX BOX BOTTOM CD 102 E A CF9BOT A A CF9TOP CF 9 MATRIX BOX TOP CD 102 E A CF9TOP A A CURCPlA PRIMARY COOLANT PUMP A AMPS ANA-I 0004 222 B A CURCPlA VI 1 LIN o.o 5.0 v 0 800 AMP OS C A CURCPlA o.o 5.0 D A CURCPlA 500 700 5 I A CURCPlA 1 1 0 101 132 N A CURCPlA YSP50A c A A CURCPlB PRIMARY COOLANT PUMP B AMPS ANA-I 0005 222 B A CURCP lB VI 1 LIN o.o 5.0 v 0 800 AMP 05 C A CURCP lB o.o 5.0

• • D A CURCP lB 500 Description No. 578-ICE-1402 700 Rev 00 5

Page 12 of 47

I A CURCPlB  : 1 1 1 101 133 N A CURCPlB YSPSOB c A A CURCP2A PRIMARY COOLANT PUMP C AMPS ANA-I 0006 222 B A CURCP2A VI 1 LIN o.o 5.0 v o* 800 AMP 05 CA CURCP2A o.o 5.'0 D A CURCP2A 500 700 - 5 I A CURCP2A 2 0 2 120 194 NA CURCP2A YSP50C c A A CURCP2B PRIMARY COOLANT PUMP DAMPS ANA-I 0007 222 B A CURCP2B VI l LIN o.o 5.0 v 0 800 AMP 05 C A CURCP2B o.o 5.0 D A CURCP2B 500 700 5 I A CURCP2B 2 0' 3 120 195 N A CURCP2B YSP50D c A A DPT0112A PRIMARY COOLANT LOOP lA DP ANA-I 0008 222 B A DPT0112A VI 1 LIN 1.0 5.0 v -2 65 PSID 05 C A DPT0112A 1.0 5.0 D A DPT0112A I A DPT0112A 1 6 l 006 25 N A DPT0112A A A DPTO l l2B PRIMARY COOLANT LOOP lB DP ANA-I 0009 222 B A DPT0112B VI l LIN 1.0 s.o v -2 65 PSID 05 C A DPT0112B 1.0 5.0 D A DPT0112B I A DPT0112B 1 6 2 006 26 N A DPT0112B

• A A DPT0122C PRIMARY COOLANT LOOP 2A DP B A DPT0122C VI l C A DPT0122C D A DPT0122C I A DPT0122C N A DPT0122C l

LIN '1.0 1.0 s.o 5.0 6 3 006 ANA-I v -2 65 PSID.

00.10 27 222 05 A A DPT0122D PRIMARY COOLANT LOOP 2B DP ANA-I 0011 222 B A DPTO.l 22D VI l LIN 1.0 5.0 v -2 65 PSID 05 C A DPT0122D 1.0 5.0 D A DPT0122D I A DPT0122D 1 7 0 007 28 N A DPT0122D A A DTHTUP PCS HEAT UP RATE KA 0086 222 D A DTH'IDP N A DTHTUP A A EP0306 SDC CL~."PCS BYPASS VLV 3006 ANA-I 0283 326 B B EP0306 VI 1 LIN 1.0 5.0 v 100 0 PCT 05 I C A EP0306 1.0 5.0 D A EP0306 I A EP0306 2 5 0 125 212 N A EP0306 A A EP0701 FEED CNTRL VLV STM GEN E-50A ANA-I 0285 332 B A EP0701 VI 1 LIN 1.0 5.0 v 0 100 PCT 05 C A EP0701 .1.0 5.0 D A EP0701 I A EP0701 l 11 0 011 36 N A EP0701 A A EP0703 FEED CNTRL VLV STM GEN E-50B ANA-I 0286 332 B A EP070J VI l LIN 1.0 *5.0 v 0 100 PCT 05 C A EP0703 1.0 5.0 Description No. 578-ICE-1402 Rev. 00 Page 13 of 47

D A EP0703 I A EP0703 - 1 7 2 207 286 N A EP0703 A B EP0727 AUX FW CNTRL SG E50B VLV 727 ANA-I. 0395 333 B B EP0727 VI 1 LIN 1.0 5.0 v 100 0 PCT 05 C B EP0727 1.0 5.0 D B EP0727 I B EP0727 2 1 3 021 071 N B EP0727 A B EP0736A AUX FW CNTRL SG E50B VLV 736 ANA-I 0287 333 B. B EP0736A VI 1 LIN 1.0 5.0 v 100 0 PCT OS C B EP0736A 1.0 5.0 D B EP0736A I B EP0736A 2 00 1 220 4501 N B EP0736A A B EP0737A AUX FW CNTRL SG E50A VLV 737 ANA-I 0288 333 B B EP0737A VI 1 LIN 1.0 5.0 v 100 0 PCT OS C B EP0737A 1.0 5.0 D B EP0737A I B EP0737A 2 00 2 220 4502 N B EP0737 A I.

A B EP0749 AUX FW CNTRL SG E50A VLV 749 ANA-I 0396 333 B B EP0749 VI 1 LIN 1.0 5.0 v 100 0 PCT OS C B EP0749 1.0 5.0 D B EP0749 I B EP0749 N B EP0749 2 1 2 021 070 325 AAEP1057 PRESSURIZER SPRAY VALVE 1057 ANA-I 0289 B A EP1057 VI . 1 LIN 1.0 5.0 v 0 100 PCT 05 C A EP1057 1.0 5.0 DA EP1057 I A EP1057 1 . 2 0 102 136 N A EP1057 A A EP1059 PRESSURIZER SPRAY VALVE 1059 ANA-I 0290 32S B A EP1059 VI 1 LIN 1.0 5.0 v 0 100 . PCT OS C A EP1059 1.0 5.0 D A EP1059 I A EP1059 1 2 1 102 137 N A EP1059 A A EP2012 INTERMD LTDN CNTRL VLV 2012 ANA-I 0363 323 B A EP2012 VI l LIN 1.0 5.0 v 0 100 PCT OS C A EP2012 1.0 5.0 D A EP2012 I A EP2012 2 3 3 123 207 N A EP2012 A A EP2122 INTERMD LTDN CNTRL VLV 2122 ANA-I 0263 323 B A EP2122 VI 1 LIN 1.0 s.o v 0 100 PCT 05 C A EP2122 1.0 5.0 D A EP2122 I A EP2122 2 1 l 121 197 N A EP2122 A B EP3025 SOC P~S FLOW CNTRL VLV 3025 ANA-I 0300 326 B A EP3025 VI 1 LIN 1.0 5.0 v 0 100 PCT 05 c*A EP3025 1.0 5.0 D A EP3025 I A EP3025 2 5 l 125 213 Description No. 578-ICE-1402 Rev 00 Page 14 of 47

N A EP3025 A B FS0954 WES'!' SFGRD PMPS LO SEAL WTR CI 0018 321 E A PS0954 CL ALM ALARM OP NOA NORMAL I A FS0954 . 4 0 4 260 644 N A FS0954 A B FS0958 EAST SFGRD PMPS LO SEAL WTR.. ..CI 001.9 321 E A FS0958 CL ALM ALARM . OP NOA NORMAL I-I A FS0958 4 0 6 260 646 N A FS0958 A A FT0202 PRIMARY COOLANT LETDOWN FLOW ANA-I 0020 323 B A FT0202 VI l SQR 1.0 5.0 v 0 160 GPM 05

• c A FT0202 1.0 5.0 D A FT0202 30 133 2 I A FT0202 1 14 0 114 176 N A FT0202 A A FT0210A BORIC ACID MKUP PMW FLOW ANA-I 0087 324 B A FT0210A VI 1 SQR 1.0 5.0 v 0 200 GPM 05 C A FT0210A 1.0 5.0 D A FT0210A I A FT0210A l 17 0 117 188 N A FT0210A A A FT0212 CHARGING LINE FLOW ANA-I 0021 323 B A FT0212 VI l SQR 1.0 5.0 v 0 140 GPM 05 C A FT0212 r.o 5.0 D A FT0212 25 2 I A FT0212 l 14 l 114 177 N ~ FT0212 A A FT0301 CONTAINMENT SPRAY HDR l FLOW ANA-I 0022 342 B A FT0301 VI l SQR 1.0 5.0 v 0 3000 GPM 05 C A FT0301 1.0 5.0 D A FT0301 I A FT0301 1 13 2 013 46 N A FT0301 A A FT0302 CONTAINMENT SPRAY HDR 2 FLOW ANA-I 0023 342 B A FT0302 VI 1 SQR 1.0 5.0 v o. 3000 GPM 05 C A FT0302 1.0 5.0 D A FT0302 I A FT0302 1 14 2 214 306 N A FT0302 A A FT0306 LPSI-SHUT DOWN COOLING FLOW ANA-I 0024 326 B A FT0306 VI l SQR 1.0 5.o v 0 8000 GPM 05 C A FT0306 1.0 5.0 D A.FT0306 I A FT0306 1 14 2 114 178 N A FT0306 A B FT0307 LP SI FLOW TO LOOP lA . ANA-I 0025 322 B A FT0307 VI l SQR 1.0 5.0 v 0 2000 GPM 05 C A FT0307 1.0 5.0 D A FT0307 I A FT0307 1 13 3 013 47 N A FT0307 A A FT0308A HPSI FLOW TO LOOP lA ANA-I 0026 322 B A FT0308A VI 1 SQR 1.0 5.0 v 0 250 GPM 05 C A FT0308A

• 1.0 5.0 D A FT0308A I A FT0308A l 14 0 014 48 Description No. 578-ICE-1402 Rev 00 Page 15 of 47

N A PT0308A A A PT0309A - I.PSI FLOW TO LOOP lB ANA-I 0027 322 B A F1'0309A VI 1 SQll 1.0 s.o v 0 2000 GPM OS C A F1'0309A 1.0 s.o D A F1'0309A I A FT0309A 2 2 1 022 73 N A FT0309A A A PT0310A HPSI FLOW TO LOOP lB ANA-I 0028 322 B A PT0310A VI 1 SQR 1.0 s.o v 0 250 GPM OS C A FT0310A 1.0 s.o D A FT0310A I A FT0310A 2 2 2 022 74 N A FT0310A A A FT0311A LP SI FLOW TO LOOP 2A ANA-I 0029 322 B A FT0311A VI l SQR 1.0 s.o v 0 2000 GPM OS C A FT0311A 1.0 s.o D A PT0311A I A FT0311A 1 14 3 214 307 N A FT0311A A A FT0312A HP SI FLOW TO LOOP 2A ANA-I 0030 322 B A FT0312A VI l SQR 1.0 s.o v 0 250 GPM 05

• C A FT0312A 1.0 s.o D A PT0312A I A FT0312A 1 15 0 215 308 N A FT0312A A A FT0313A B A FT0313A HPSI FLOW TO LOOP 2B VI l SQR 1.0 s.o ANA-I v 0 250 GPM 0031 322 05

C A FT0313A 1.0 5.0 DA ~0313A I A FT.0313A 2 14 3 234 371 N A FT0313A A A FT0314A I.PSI FLOW TO LOOP 2B ANA-I 0032 322 B A FT0314A VI 1 SQR 1.0 5.0 v 0 2000 GPM OS C A FT0314A 1.0 5.0 D A FT0314A I A FT0314A 2 15 0 235 372 N A FT0314A A A FT0701 FEED FLOW TO STEAM GEN E-50A ANA-I 0033 332 B A FT0701 VI l SQR 1.0 s.o V. 0 6 . LB/HR 5 6 05 C A FT0701 1.0 5.0 D A FT0701 5.81 .05E6 I A FT0701 *1 7 l 007 29 N A FT0701 A A FT0702 STM FLOW FROM STM GEN E-50A ANA-I 0034 331 B A FT0702 vr* 1 SQR 1.0 5.0 v 0 6 LB/HR 5 6 05 C A FT0702 1.0 5.0 D A FT0702 5.81 .05E6 I A FT0702 l 7 2 007 30 N A FT0702 A A FT0703 FEED FLOW TO STEAM GEN E-50B ANA-I 0035 332 B A FT0703 VI 1 SQR 1.0 5.0 v 0 6 LB/HR 5 6 OS C A FT0703 1.0 s.o D A FT0703 5.81 .05E6 I A FT0703 1 6 1 206 281 N A FT0703 A A FT0704 S'l'M FLOW FROM S'l'M GEN E-SOB ANA-I 0036 331 Description No. 578-ICE-1402 Rev 00 Page 16 of 47

3 A FT071J4 VI *1 S~R 1.0 s.o v 0 6 L !! I HR -:.

J 6 05

... A FT0704 1.0 5.0

s. 81 .05E6 J A FT0704

! A FT0704 1 6 2 2*J 6 282 FT0704 -

FT07 27 A AUX FW FLOW TO ST~ GEN E-506 ANA-I 0393 333 i=T0727 A VI 1 SQR 1.0 5.0 v 0 . 450 GPM OS

-... 9 !=T 0727 A a FT07 27 A 250 1.0 s.a 5

J I 3 FT0727.\ 1 13 c 013 044

• ~ 9 FT0727A

.\ A FT07"36 AUX FW =Loiil TO STM G:N ~-503 AN A-I 0037 333 A i=T07 '36 VI 1 S~R 1.0 s.o v 0 450 GO,. 05

-3

... A FT07 '3t 1.0 s.o 5

J A FT07'36 250

• J 9 ?=T0736 A r:ro736 2 14 c 231. 3 68

~ .A FT 07 37 AUX FW r:LJW TO ST.,. GEN :-SCA ANA-I 0038 333 3 A FT0737 V! 1 SQR 1.0 5.0 v 0 450 GPM 05

...- A r:ro7 37 1.0 5. *J J A FT0737 2 so 5 I A FT0737 1 7 3 2a1 297 A FT07 37

.\

3 B FT0749A 9 FT0749A A Ult FW l=L~W TO ST~ GEN C:-50 A AN A-I VI- 1 SQR 1.0 s.o v a 450 GPM 0394 3;3 05 I

I

,..... 6 r:ro749A 1.0 s.o J 9 FT07 4<1 A 25C 5

.... 8 !=T0749A .1 13 1 013 045

!! FT07 49 A

"" =roa g3 c CAR 0 RANGE OIFF:RS S:::ROM B-CARO.CPCO Rl!QUEST a~ a; 0-2 275.

- ACTUAL RANG~

FT08~3 CNT A!R CLR s:Rv WTQ LK Ol!T ANA-I 003Q .3 41 3 B FTOS33 VI 1. LIN 1.0 5.0 v a 2332.3 GJ'M 05

... 3 =roe 33 1.0 4. 9 J 3 =roas; 7-5 r A =r:Je33 1 15 1 115 1 ~1

-~ A !=TOS33

.\ A K1 REACTOR TQI~ 3R:AKEQ 1 CI 0129 211

-! A !( 1 A I( 1 CL AL:-1 YSS 4 1 OP c

NOA NO 061 1 36

-4 ~ K1

~ A K2 R:A C'TO~ TIHO '3R:A:<E~ 2 CI 0130 *211 NO,A NO A K2 A K2 CL AL~

4 Y': S 1

O?

2 0~1 1!e

'J A 1(2

-~ A K3 ~:ACTOP TQil'. 3REAKER ~ t:I C325 211 CL AL!-11 Y: S 0 !) ~o A 'IC

- A K3

~

A K!

A ;{ 3 4 4 4 2 ~4 676

~ A K4 R:ACTOR T~IP 3R:At(EQ 4 CI 0326 211

- A I( 4 CL AL~ Y':S cc 'I 0 A '10

! A K4 4 4 6 2~4 61S

.. A 1(4

~ A KG A,.. ._,A A CNP' T GA"4~ ~ AL:IH I( 0 244

-N' A l<GA~~Al KGAMMAA QC ~OA ~O=iMAL CL AL"1! AL=RT KGAMMAH CNMT GAMMA HIGH KD 244 KGAMMAH OP NOA NORMAL CL ALM ALERT escriotion P~c. 57~-IC :-1402 ~ev ,:JO ?a;ie 1~ of 47

• NA KGAMMAH A A ICMS'IMA

• MAIN STEAM RELIEF ALERT KD 244

• E A ICMS'IMA OP -NOA NORMAL CL ALM ALERT N A 1CMS 'l'MA A A ICMS'lMH MAIN STEAM RELIEF HIGH KD 244 E A ICMS'lMH OP NOA NORMAL CL ALM ALERT _

N A 1CMS 'l'MH A A KPZRHTRS SUM OF PZR. HTR AMPS KA 32S D A KPZR.HTRS N A KPZRHTRS 160 200 I

_I A A KSGAPSDP SGA P/S DP KA 222 D A KSGAPSDP 1380.0 1S30.0 1.0 0 N A KSGAPSDP A A KSGBPSDP SGB P/S DP KA 222 D A KSGBPSDP 1380.0 1530.0 1.0 0 N A KSGBPSDP A A KXCHP CNMT HI PRESS SIG STATUS KD 211 E A KXCHP OP ALM ACTUATED CL NOA NORMAL N A KXCHP A A KXCHR CNMT HI RAD SIGNAL STATUS KD 0090 211 E A KXCHR OP ALM ACTUATED CL NOA NORMAL N A KXCHR A A KXCIAS CIAS STATUS KD 211 E A KXCIAS OP ALM ACTUATED CL NOA NORMAL N A KXCIAS A A KXSIAS E A KXSIAS SIAS SIGNAL STATUS OP ALM ACTUATED CL NOA NORMAL KD 211 ,

NA KXSIAS A A KXSRAS RECIRCULATION ACTUATION SIG KD 0091 211 E A KXSRAS OP ALM ACTUATED CL NOA NORMAL N A KXSRAS A A LT0102A PRESSURIZER LEVEL CHANNEL A ANA-I 0040 325 B B LT0102A VI l LIN 1.0 5.0 v 0 100 PCT OS C A LT0102A 1.0 s.o D B LT0102A 63.S 79.6 .1 I A LT0102A 1 7 3 007 31 N A LT0102A A A LT0103 PZR. WIDE RANGE LEVEL IND ANA-I 0093 325 B B LT0103 VI 1 LIN 1.0 s.o v 0 100 PCT OS C A LT0103 1.0 s.o D B LT0103 2.0 98.0 .l I A LT0103 2 6 0 126 216 N A LT0103 A A LT0206 BORIC ACID TANK T-S3B LEVEL ANA-I 0041 324 B B LT0206 VI 1 LIN 1.0 s.o v 0 100 PCT OS C A LT0206 1.0 s .o*

D B LT0206 2.4 l.O I A LT0206 1 15 2 115 182 N A LT0206 A A LT0208 BORIC ACID TANK T-53A LEVEL ANA-I 0042 324 B B LT0208 VI 1 LIN 1.0 s.o v 0 100 PCT 05 C A LT0208 1.0 s.o D B LT0208 2.4 1.0 I A LT0208 1 15 3 115 183 N A LT0208 A A LT0331 SIRW TANK LEVEL ANA-I 0043 321 Description* No. 578-ICE-1402 Rev 00 Page 18 of 47

B B LT0331 VI .1 LIN 1.0 5.0 v 0 100 PCT 05

... 5.0 C A LT0331 1.0 D B LT0331 90 99 .1 I A LT0331 1 15 1 215 309 N A LT0331 KXSIAS 0 KXSIAS 0 A A LT0365 SAFETY !NJ. TANK T-82A LEVEL .ANA-I 0046 322 B B LT0365 VI 1 . LIN 1.0 5.0 v 0 100 PCT 05 C A LT0365 1.0 5.0 D :& LT0365 55.2 55.8 58.1 s8.7- .* s I A LT0365 1 14 1 014 49 N A LT0365 A A LT0368 SAFETY INJ. TANK T-82B LEVEL ANA-I 0047 322 B B LT0368 VI 1 LIN 1.0 5.0 v 0 100 PCT 05 C A LT0368 1.0 5.0 D B LT0368 S5.2 SS.8 58.1 58.7 .5 I A LT0368 2 3 0 023 76 N A LT0368 A A LT0372 SAFETY INJ. TANK T-82C LEVEL ANA-I 0048 322 B B LT0372 VI 1 LIN 1.0 5.0 v 0 100 PCT OS C A LT0372 D B LT0372 55.2 55.8

. 1.0 5.0 58.1 sa.7 .5 I A LT0372 1 15 2 215 310 N A LT0372 A A LT0374 SAFETY INJ. TANK T-82D LEVEL ANA-I 0049 322 B B LT0374 VI 1 LIN 1.0 5.0 v 0 100 PCT 05 I C A LT0374 1.0 5.0 D B LT0374 5S.2 55."8 58.l 58.7 .5 I I A LT0374 2 15 1 235 373 N A LT0374 A A LT0382 CONTAINMENT S~ WATER LEVEL ANA-I 0045 244 B B LT0382 VI 1 LIN 1.0 5.0 v 0 50 PCT 05 C A LT0382 1.0 5.0 D B LT0382 9.5 28.6 .1 I A LT0382 .1 .16 0 216 312 N A LT0382 A A LT0446A CNMT FLOOR WAT.ER LEVEL ANA-I 0062 244 B B'LT0446A VI 1 LIN 1.0 5.0 v 0 100 PCT 05 *I C A LT0446A 1.0 5.0 D A LT0446A .I I A LT0446A 1 15 0 015 52 N A LT0446A A B LT0702 NARR RNGE LVL STM GEN E-50A ANA-I 0052 B B LT0702 VI 1 LIN 1.0 5.0 v 0 100 PCT 05 C A LT0702 1.0 5.0 D A LT0702 55 84.7 .5 I A LT0702 1 10 0 010 32 N A LT0702 A B LT0704 NARR RNGE LVL STM GEN E-50B ANA-I 0053 B B LT0704 VI 1 LIN l.o* 5.0 v 0 100 PCT 05 C A LT0704 1.0 5.0 D A LT0704 55 84.7 .5 I A LT0704 1 6 3 206 283 N A LT0704 A A LT0729 CONDENSER HOTWELL LEVEL ANA-I 0054 233 B B LT0729 VI 1 LIN 1.0 5.0 v 0 100 PCT 05 C A LT0729 1.0 5.0 Description No. 578-ICE-1402 Rev 00 Page 19 of 47

D B LT0729 19.3 58 81 1 I A LT0729 l 0 0 100 128

• N A LT0729 A B LT0751A B B LT0751A C A LT0751A D A LT0751A I A LT0751A N A LT0751A NARR RNGE LVL S'l'M GEN E-50A ANA-I VI 1 LIN 1

55 LO LO 10 3 5.0 5.0 010 84~7 v 0 100

• 5 Per 0094 35 332 05 I.

A B LT0752A NARR RNGE LVL S'l'M GEN E-SOB ANA-I 0055 332 B B LT0752A VI l LIN LO s.o v 0 100 PCT 05 r-C A LT0752A LO 5.0 D A LT0752.A 55 84.7 .5 I I A LT0752A 1 10 1 010 33 N A LT0752A A A LT1012 CLN WST RCVR INK T-64A LEVEL ANA-I 0057 244 B B LT1012 VI 1 LIN 1.0 5.0 v 0 100 Per 05

.C A LT1012 l.O 5.0 D A LT1012 ll 85 .5 I A LTl012 2 1 2 121 198 N A LTl012 A A LTlO 14 CLN WST RCVR TNK T-64B LEYEL ANA-I 0058 244 B A LTl014 VI 1 LIN 1.0 5.0 v 0 100 Per 05 C A LT1014 LO 5.0 D A LT1014 ll 85 .5 I A LTl014 2 1 3 121 199 N A LT1014 0059 244 A A LT1016 CLN WST RCVR INK T-64C LEVEL ANA-I '

B A LT1016 VI 1 LIN 1.0 5.0 v 0 100 Per 05 C A LT1016 l .O 5.0 D A LT1016 ll 85 .5 I A LT1016 2 2 0 122 200 N A LT1016 A A LT1018 CLN WST RCVR TNK T-640 LEVEL ANA-I 0060 244 B A LT1018 VI l LIN 1.0 5.0 v 0 100 PCT 05 C A LT1018 1.0 5.0 D A LT1018 ll 85 .5 I A LT1018 2 2 1 122 201 N A LT1018 A A LTlll5 DIR.TY WASTE ORN TI< T-60 WEST .ANA-I 0088 352 B A LTlll5 VI 1 LIN 1.0 5.0 v 0 100 Per OS C A LT1115 1.0 5.0 D A LTlllS - 27 .5 90 .5 I A LTlll5 2-. 2 2 122 202 N A LTlll5 A A LT1117 DIRTY WASTE ORN TI< T-60 EAST ANA-I 0089 352 B A LT1117 VI 1 LIN l.O 5.0 v o.o 100 PCT 05 C A LTl 117 1.0 5.0 D A LT1117 27 .5 90 .5 I A LTlll7 2 2 3 122 203 N A LTlll7 A A LT202l CNDNSATE STORAGE TANK LEVEL ANA-I 0061 233 B B LT2021 VI l LIN 1.0 5.0 v 0 100 PCT 05 C A LT2021 1.0 5.0 D B LT2021 50 98 1 I A LT2021 2 3 1 023 77 Description No. 578-ICE-1402 Rev 00 Page 20 of 47

N A LT2021 A A LTA0116

• QUENCH TANK T-73 LEVEL ANA-I 0063 325 B B LTA0116 VI 1 LIN 1.0 5.0 v 0 100 PCT 05 C A LTA0116 1.0 5.0 D B LTA0116 66.7 79.2 90.3 .5 I A LTA0116 1 16 0 116 184 N A LTA0116 A A LTC0205 VOLUME CONTROL TANK LEVEL ANA-I 0095 323 B A LTC0205 VI 1 LIN l.;0 5.0 v 0 100 PCT 05 C A LTC0205 1.0 5.0 D A LTC0205 7.9 64 82 94.4 .5 I A LTC0205 2 6 1 126 217 N A LTC0205 A A MDELT TOWER TEMPERATURE DIFFERENCE MAI 0096 351 B A MDELT VI 1 LIN 1.0 5.0 v 05 C A MDELT 1.0 5.0 D A MDELT G A MDELT MDL 001 N A MDELT A A MSGlO STANDARD DEV WIND DIR lOM MAI 0099 351 B A MSGlO VI 1 LIN 1.0 5.0 v 05 C A MSGlO 1.0 s.o D A MSGlO G A MSGlO MDL 004 N A MSGlO A A MSG60 STANDARD DEV WIND DIR 60M MAI 0098 351 B A MSG60 VI 1 LIN 1.0 5.0 v 05 C A MSG60 1.0 5.0 D A MSG60 G A MSG60 MDL 007 N A MSG60 A A MWDlO WIND DIRECTION lOM MAI 0100 351 B A MWDlO VI 1 LIN 1.0 5.0 v 05 C A MWDlO 1.0 5.0 D A MWDlO G A MWDlO MDL 003 N A MWDlO A A MWD60 WIND DIRECTION 60M MAI 0103 351 B A MWD60 VI 1 LIN 1.0 5.0 v 05 C A MWD60 1.0 5.0 D A MWD60 G A MWD60 MDL 006 N A MWD60 A A MWSlO WIND SPEED !OM MAI 0104 351 B A MWSlO VI 1 LIN 1.0 5.0 v 05 C A MWSlO 1.0 5.0 D A MWSlO G A MWSlO MDL 002 N A MWSlO A A MWS60 WIND SPEED 60M MAI 0105 351 B A MWS60 VI 1 LIN 1.0 5.0 v 05 C A MWS60 1.0 5.0 D A-MWS60 G A MWS60 MDL 005 N A MWS60 A A NIOOl STARTUP COUNT RATE X NI 001 ANA-I 0012 211 Description No. 578-ICE-1402 Rev 00 Page 21 of 47

B A NIOOl VI t LOG a.o 10.0 v 1 3 CNTS/S 5 0 5 05

• C A NIOOl D A NIOOl I A NIOOl N A NIOOl A A NI002 B A NI002 C A NI002 V! l 1

LOG a.a 1

o.o o.o 1

la.a 001 STARTUP COUNT RATE Y NI 002 ANA-I 10.0 10 .o v 1 3 0013 CNTS/S 5 0 s

s

Z.il OS D A NIOa2 I A NI002 l 1 0 201 260 N A NI002 A A NI003 WIDE RANGE POWER NI 003 ANA-I 0014 211 B B NI003 VI 1 LOG o.o 10.0 v l 1.25 PCT 5 -8 2 OS C A Nia03 o.o 10.0 0 A NI003 I A NI003 2 0 *O a2o 64 N A NI003 A A NI004 WIDE RANGE POWER NI 004 ANA-I 0015 211 B B NI004 VI 1 LOG o.o 10.0 v l 1.25 PCT 5 -d 2 OS C A NI004 o.o 10.0 0 A NI004 I A NI004 2 13 0 233 364 N A NI004 A A NI005 POWER RANGE SAFETY CHANNEL A ANA-I 0106 B A NI005 VI l LIN o.o 10 .o v 0 12S PCT OS C A NI005 o.o 10.0 0 A NI005 10 l 107 1 I A NIOOS 1 l 2 001 6 N A NIOOS A A NI006 POWER RANGE SAFETY CHANNEL B ANA- I 0114 B A NI006 VI 1 LIN o.o 10.0 v 0 125 PCT OS C A NI006 o.o 10.0 0 A NI006 101 107 1 I A NI006 l 1 1 201 261 N A NI006 A B PT0102A PRESSURIZER SI CHANNEL PRESS ANA-I 0066 325 B A PT0102A VI l LIN 1.0 s.o v 1500 2500 PSIA 05 C A PT0102A 1.0 s.o 0 A PT0102A 1850 1935 2185 2230 s I A PT0102A 1 10 2 010 34 N A PT0102A A A PT0103 PRESSURIZER WIDE RANGE PRESS ANA-I 0067 211 B A PT0103 VI 1 LIN 1.0 5.0 v 0 3000 PSIA OS C A PT0103 1.0 s.o D A PT0103 2500 27 so s I A PT0103 2 l 0 021 68 N A PT0103 A A PT0116 QUENCH*TANK T-73 PRESSURE ANA-I 0068 32S B A PT0116 VI 1 LIN l. 0 s.o v 0 25 PSIG OS C A PT0116 l.O s.o D A PT0116 10 .1 I A PT0116 1 16 l 116 18S N A PT0116 A A PT0202 INTERMED tJTDOWN CNTRL PRESS ANA-I 0069 323 B B PT0202 VI 1 LJl'I LO 5. *J v 0 700 PSIG OS C A PT0202 1.0 s.o

• DA PT0202 400 500 600 3 I A PT0202 - l 16 2 116 186 N A PT0202 A A _PT0205 VOLUME CNTRL TNK T-54 PRESS ANA-I 0070 323 B A PT0205 VI 1 LIN 1.0 5.0 v 0 100 PSIG 05 C A PT0205 1.0 5.0 D A PT0205 o.s 4 so 75 l I A PT0205 l 16 3 116 187 N A PT0205 A A PT0318 HPSI HEADER A PRESSURE ANA-I 0071 321 B A PT0318 VI l LIN 1.0 5.0 v 0 2000 PSIG 05 C A PT0318 1.0 5.0 D A PT0318 1600 5 I A PT0318 2. 15 2 235 374 N A PT0318 A A PT0363 SAFETY INJ. TANK T-82A PRESS ANA-I 0072 322 B A PT0363 VI 1 LIN 1.0 5.0 v 0 300 PSIG 05 C A PT0363 1.0 5.0 D A PT0363 200 205 225 250 1 I A PT0363 1 14 2 014 50 N A PT0363 A A PT0367' SAFETY INJ". TANK T-82B PRESS ANA-I 0073 322 B A PT0367 VI l LIN 1.0 5.0 v 0 300 PSIG 05 C A PT0367 1.0 5.0 D A PT0367 200 205 225 . 250 l I A PT0367 2 3 2 023 78 N A PT0367 A A PT0369 SAFETY INJ. TANK T-820 PRESS ANA-I 0074. 322 B A PT0369 VI 1 LIN 1.0 5.0 v 0 300 PSIG 05 C A PT0369 1.0 5.0 D A PT0369 200 205 225 250 1 I A PT0369 2 15 3 235 375 N A PT0369 A A PT0371 SAEETY INJ. TANK T-82C PRESS ANA-I 0075 322 BAPT0371 VI 1 LIN 1.0 5.0 v 0 300 PSIG 05 C A PT0371 1.0 5.0 D A PT0371 200 205 225 250 1 I A PT0371 l 15 3 215 311 N A PT0371 A A PT0375 HPSI HEADER B PRESSURE ANA-I 0076 321 B A PT0375 VI 1 LIN 1.0 5.0 v 0 2500 PSIG 05 C A PT0375 1.0 5.0 D A PT0375 I A PT0375 2 3 3 023 79 N A PT0375 A A PT0521 AUX *rw PUMP TURB S'l'M PRESS ANA-I ,0077 333 B A PT0521 VI l LIN 1.0 5.0 v 0 750 PSIG 05 C A PT0521 1.0 5.0 D A PT0521 40 200 300 1.5 I A PT0521 1 0 2 100 130 N A PT0521 YSAXFPB 0 A A PT0580 MAIN TURB STEAM INLET PRESS ANA-I 0125 331 B A PT0580 VI l LIN 1.0 5.0 v 0 1500 PSIG 05 C A PT0580 1.0 5.0 D A PT0580 I A PT0580 1 15 0 115 180 Description. No. 578-ICE-1402 Rev 00 Page 23 of 47

N A PT0580 A A PT0701 S'DLGEN PEED PUMP P-lB DISCH ANA-I 0056 332 B A PT070l VI l LIN 1.0 5.0 v 0 1200 PSIG 05 C A PT070l 1.0 5.0 D A PT070l 700 800 1 I A PT0701 1 0 1 100 129 N A PT0701 A A PT0703 S'l'M* GEN PEED PUMP P-lA DISCH ANA-I 0126 332 B A PT0703 VI 1 LIN 1.0 5.0 v 0 1200 PSIG 05 C A PT0703 1.0 5.0 D A PT0703 700 aoo l I A PT0703 l 14 3 114 179 N A PT0703 A B PT0750 SG AUX FEED PMP C DSCHG PR.ES ANA-I 0407 333 B B PT0750 VI 1 LIN 1.0 5.0 v 0 1600 PSIG 05 C B PT0750 1.0 s.o D B PT0750 I B PT0750 2 0 3 220 323 N B PT0750 A B PT0751B STEAM GENERATOR E-50A PRESS ANA-I 0078 233 B A PT0751B VI l LIN 1.0 5.0 v 0 1000 PSIA 05 C A PT0751B 1.0 5.0 D A PT0751B 600 650 1 I A PT0751B 1 7 0 207 284 N A PT0751B A B PT0752B STEAM GENERATOR E-508 PRESS ANA-I 0079 233 B A PT0752B VI 1 LIN l.O 5.0 v 0 1000 PSIA 05 C A PT0752B 1.0 5.0 D A PT0752B 600 650 1 I A PT0752B 1 7 1 207 285 N A PT0752B A A PT0763 CONDENSER VACUUM WIDE RANGE ANA-I 0080 332 B A PT0763 VI 1 LIN 1.0 5.0 v 0 30 INHGA 05 C A PT0763 1.0 5.0 D A PT0763.

I A PT0763 *1 6 2 106 154 N A PT0763 A A PT0789 SG AUX FEED PP DISC HDB. PR. ANA-I 0081 333 B A PT0789 VI l LIN 1.0 5.0 v 0 1600 PSIG 05 C A PT0789 1.0 s.o D A PT0789 I A PT0789 l 0 3 100 131 N A PT0789 A A PT0918 CCW HEA'.r. EXCH CCW INLET PR ANA-I 0082 323 B A PT0918 VI 1 LIN 1.0 s.o v 0 150 PSIG 05 C A PT0918 1.0 5.0 D A PT0918 80 100 l I A PT0918 2 14 l 234 369 N A PT0918 A A PT1119 WASTE GAS DECAY TANK l PRESS ANA-I 0319 B A PT1119 VI l LIN 1.0 5.0 v 0 120 PSIG 05 C A PT1119 1.0 5.0 D A PT1119 100 l I A PT1119 2 3 0 123. 204

• N A PT1119 AAPT1120 WASTE GAS DECAY TANK 2 PRESS ANA-I Description No. 578-ICE-1402 Rev 00 0320 Page 24 of 47

B A PT1120 VI .1 LIN 1.0 s.o v 0 120 PSIG 05 C A PT1120 1.0 5.0 D A PT1120 100 1 I A PT1120 2 3 1 123 205 N A PT1120 A A PT1121 WASTE GAS DECAY TANK 3 PRESS ANA-I 0321 B A PT1121 VI 1 . LIN 1.0 5.0 v 0 120 PSIG 05 C A PT1121 1.0 s.o

. D A PT1121 100 1 I A PT1121 2 3 2 123 206 N A PT1121 A A PT1160 WASTE GAS DECAY TANK 4 PRESS ANA-I 0322 B A PT1160 VI 1 LIN 1.0 s.o v 0 120 PSIG OS C A PT1160 1.0 s.o D A PT1160 100 l I A PT1160 2 4 1 124 209 N A PT1160 A A PT1161 WASTE GAS DECAY TANK 5 PRESS ANA-I 0323 B A PT1161 VI 1 LIN 1.0 s.o v 0 120 PSIG 05 C A PT1161 1.0 5.0 D A PT1161 100 l I A PT1161 2 4 2 124 210 N A PT1161 A A PT1162 WASTE GAS DECAY TANK 6 PRESS ANA-I 0324 B A PT1162 VI 1 LIN 1.0 s.o v 0 120 PSIG 05 C A PT1162 1.0 5.0 D A PT1162 100 1 I A PT1162 2 4 3 124 211 N A PT1162 A A PT1805A CONTAINMENT WR *PRESS 1805A ANA-I 0065 244 B A PT1805A VI l LIN 1.0 5.0 v 10 200 PSIA 05 C A PT1805A 1.0 s.o D A PT1805A 55 l I A PT1805A 1 16 l 216 313 N A PT1805A A A PT1812A CONTAINMENT WR PRESS 1812A ANA-I 0084 244 B A PT1812A VI 1 LIN l.O 5.0 v 10 200 PSIA 05 C A PT1812A 1.0 5.0 D A PT1812A 70 l I A PT1812A l 15 l 015 53 N A PT1812A A A PZLBE PRESS~IZER LEVEL BEST EST KA 0166 222 D A PZLBE N A PZLBE A A PZRBE PRESSURIZER PRESS BEST EST KA 0167 D A PZRBE N A PZRBE A A QlCRREAC CORE REACT CNTRL QUALITY CD E A QlCRREAC BAD QUAL GOOD A A Q2RCSINV PCS INVENTORY CNTRL QUALITY CD E A Q2RCSINV BAD QUAL GOOD A A Q3RCSPRS PCS PRESS CNTRL QUALITY CD E A Q3RCSPRS BAD QUAL GOOD

• A A Q4CRHEAT E A Q4CRHEAT A A Q5RCSHT CORE HEAT REMOVAL QUALITY BAD QUAL PCS HEAT REMOVAL CNTRL QUAL

• Description No. 578-ICE-1402 GOOD CD CD Rev 00 Page 25 of 47

E A QSRCSHT BAD QUAL GOOD A A Q6CHTISO CONT ISO QUALITY CD EA Q6CNTISO BAD QUAL GOOD A A Q7CNK'rPT CONT PUSS/TEMP CNTRL QUAL CD E A Q7CNM'l'PT BAD QUAL GOOD A A QSRXTllIP REACTOR Tl.IP QUALITY KD E A Q8RXTR.IP OP ALM-, BAD QUAL CL NOA GOOD NA Q8RXTRIP A B RE2321 CNMT GAMMA RADMON SYS CI 0381 244 E B RE2321 OP NOA NORMAL CL ALM HIGH I A R.E2321 3 5 4 145 300 N A R.E2321 A A R.E2321A CNMT GAMMA RADMON SYS ALERT CI 0384 . 244 E A RE2321A OP NOA NORMAL CL ALM ALERT I A R.E2321A 3 5 6 145 302 N .A RE2321A A B R.E2322 CNMT GAMMA RADMON SYS CI 0382 244 E B RE2322 OP NOA NORMAL CL ALM HIGH I A R.E2322 3 6 0 146 304 N A RE2322 A A RE2322A CNMT GAMMA RADMON SYS ALERT CI 0386 244 E A R.E2342A OP NOA NORMAL CL ALM ALERT I A RE2322A 3 6 2 146 306 N A R.E2322A A B RE2323* MS RAD RELIEF MON SYS CI 0383 244 E B R.E2323 OP NOA NORMAL CL ALM HIGH I A R.E2323 3 6 4 146 308 N A R.E2323 A A R.E2323A MS RAD RELIEF MON SYS ALERT CI 0388 244 E A RE2323A OP NOA NORMAL CL ALM ALERT I A RE2323A 3 6 6 146 310 N A RE2323A A B RE2324 MS RAD RELIEF MON SYS CI 0384 244 E B RE2324 OP NOA NORMAL CL ALM HIGH I A RE2324 3 7 0 147 312 N A RE2324 A A RE2324A MS RAD RELIEF MON SYS ALERT CI 0390 244 E A RE2324A OP NOA NORMAL CL ALM ALERT I A R.E2324A 3 7 2 147 314 N A R.E2324A A B RE2325 STACK EFFLU RAD MON CI 0385 244 E B RE2325 OP NOA NORMAL CL ALM HIGH I A RE2325 3-. 7 4 147 316 N A RE2325 A A RE2325A* STACK EFFLU RAD MON ALERT CI 0392 244 E A R.E2325A I A RE2325A OP NOA NORMAL 3

CL ALM ALERT

• 7 6 147 318 I I

I N A RE2325A A A RI0707 S'l'M GEN !LOWDOWN RAD MONITOR ANA-I 0218 352 B B RI0707* VI l LOG o.o s.o v l l

• CNTS/M 5 l 6 OS C A RI0707 o.o s.o D A RI0707 I A RI0707 l 13 3 113 175 N A RI0707

• A A RI0833 B B RI0833 SERVICE WATER RAD MONITOR VI l LOG Description No. 578-ICE-1402 o.o s.o ANA-I v

Rev 00 l l 0221 CNTS/M 5 l 6 352 OS Page 26 of 47

C A RI0833 o.o 5.0

• D A RI0833 I A RI0833 1 7 0 107 156 N A RI0833 A A RI0915 COMP COOLING RAD MONITOR ANA-I 0222 352 B B RI0915 VI l LIN o.o 5.0 ..v 0 l CNTS/M 5 6 r, 5 I.

C A RI0915 o.o 5.0 D A RI0915 I A RI0915 1 7 1 107 157 N A RI0915 A A RI1049 RAD WASTE DISCHG RAD MONITOR ANA-I 0239 352 B B RI1049 VI 1 LOG o.o 5.0 v 1 l CNTS/M 5 l 6 05 C A RI1049 o.o 5.0 D A RI1049 I A RI1049 1 7 2 107 158 N A RI1049 A A RI1323 MIXING BASIN RAD MONITOR ANA-I 0241 -6 352 1*

B B RI1323 VI 1 LIN o.o 5.0 v 0 l CNTS/M 5 6 05 C A RI1323 o.o 5.0 D A RI1323 I A RI1323 1 7 'l

.J 107 159 N A RI1323 A A RI1805 CN'l'MT ISO RAD MNTR 1805 ANA-I 0244 352 B B RI1805 VI 1 LIN o.o 5.0 v 1 l MR/HR 5 -1 7 05 C A RI1805 o.o 5.0 D A RI1805 22 I A RI18P5 1 5 2 005 N A RI1805 A A RI1806 CNTMT ISO RAD MNTR 1806 ANA-I 0284 352 B B RI1806 VI 1 LIN o.o 5.0 v 1 1 MR/HR 5 -1 7 05 C A RI1806 o.o 5.0 D A RI1806 I A RI1806 1 5 2 205 278 N A RI1806 A A RI1809 RADWASTE PLENUM RAD MONITOR ANA-I 0291 352 B B RI1809 VI l LIN o.o 5.0 v 0 l CNTS/M 5 6 05 C A RI1809 o.o 5.0 D A RI1809 I A RI1809 1 10 2 110 162 N A RI1809 A A RI1810 EAST ENGR SAFEGUARD RAD MNTR ANA-I 0292 352 B B RI1810 VI L. LIN o.o 5.0 v 0 l CNTS/M 5 6 OS C A RI1810 o.o 5.0 D A RI1810 I A RI1810 l 10 3 110 163 N A RI1810 A A RI1811 WEST ENGR SAFEGUARD RAD MNTR ANA-I 0293 352 B B RI1811 VI l LIN o.o 5.0 v 0 l CNTS/M 5 6 05 C A RI1811 o.o 5.0 D A RI1811 I A RI18ll 1 11 0 111 164 N A RI1811 A A RI1817 CONTAINMENT GAS RAD MONITOR ANA-I 0294 255 B B RI1817 VI l LIN o.o 5.0 v 0 1 CNTS/M 5 6 05 C A RI1817 o.o 5.0 D A RI1817 Description No. 578-ICE-1402 Rev 00 Page 27 of 47

.I A R.!1817 - 1 11 1 111 165 N A R.Il817 A A R.I2310 MAIN CNTRL R.OOM RAD MONITOR ANA-I 0295 255 B B R.12310 VI 1 LIN . o.o 5.0 v 1 1 MR./HR 5 -.1 7 05 C A R.12310 o.o 5.0 D A R.12310 I A R.12310 1 li 2 111 166 N A R.I2310 A A R.I2313 SPNT FUEL POOL ROOM RAD MNTR ANA-I 0296 352 B B R.12313 VI 1 LIN o.o 5.0 v 1 1 MR./HR 5 -1 7 05 1-C A RI2313 o.o 5.0 D A RI2313 I A R.12313 1 11 3 111 167 N A RI2313 A A R.12316 FUEL HANDLING AREA RAD MNTR.l ANA-I 0297 352 B B R.I2316 VI 1 LIN o.o 5.0 v 1 1 MR./HR 5 -1 7 05 C A R.12316 o.o 5.0 D A RI2316 I A RI2316 1 5 3 005 23 N A RI2316 A A RI2317 FUEL HANDLING AREA RAD MNTR.2 ANA-I . 0298 352 B B R.12317 VI 1 LIN o.o s.o v l l MR/HR .5 -1 7 05 C A RI2317 o.o 5.0 D A RI2317 I A RI2317 1 5 3 205 279 N A RI2317 A A R.12318 STACK GAS RAD MNTR INST A ANA-I 0299 255 o.o v 1 B B RI2318 VI 1 LOG 5.0 1 CNTS/M 5 1 6 05 C A RI2318 o.o 5.0 DA RI2318 I A RI2318 1 12 2 112 170 N A RI2318 A A RI2319 STACK GAS RAD MNTR INST B ANA-I 0301 255 B B RI2319 VI 1 LIN o.o 5.0 v 0 1 CNTS/M 5 6 05 C A RI2319 o.o 5.0 D A RI2319 I A RI2319 1 12 3 112 171 N A RI2319 A A RI5709 WASTE DEMINERALIZER RAD MON ANA-I 0302 352 B B RI5709 VI 1 LIN o.o 5.0 v 1 1 CNTS/M 5 -1 7 05 C A RI5709 o.o 5.0 D A RI5709 I A RI5709 1 13 0 113 172 N A RI5709 A A R.1571 ~ RADWASTE ADDITION VENT. MON ANA-I 0303 352 B B RI5711 VI 1 LOG o.o 5.0 v 1 1 CNTS/M 5 l 6 05 C A RI5711 o.o 5.0 D A RI5711 I A R.I571 l 1 13 1 113 173 NA RI5711 A B RIA0631 OFF GAS MONITORING ANA-I 0217 352 B B RIA0631 VI 1 LIN o.o 5.0 v 0 l C~TS/M 5 '6 05 C B RIA0631 o.o 5.0 D B RIA0631 I B RIA0631 1 13 2 113 174 N B RIA0631 Description-No. 578-ICE-1402 R.ev 00 Page. 28 of 47

A B RR0202B FAILED FUEL MONITOR ANA-I 0085 323 B B RR0202B VI l LIN o.o 5.0 v 0 l CNTS/M 5 6 05 C B RR0202B - o.o 5.0 D B RR0202B I B RR0202B l 6 3 106 155 N B RR0202B A A SIS7 SAFETY INJECTION ACT TRAIN A *er 0123 E A SIS7 OP NOA NORMAL CL ALM ACTUATED I A SIS7 4 17 0 077 248 N A SIS7 A A SISlO SAFETY INJECTION ACT TRAIN B CI 0124 E A SISlO OP NOA NORMAL CL ALM ACTUATED I A SISlO 4 14 4 274 740 N A SISlO A A TAVG AVERAGE TEMP HOT & COLD LEGS KA .0309 222 D A TAVG N A TAVG A A TCOLDAV AVERAGE COLD LEG TEMPERATURE KA 0310 D A TCOLDAV N A TCOLDAV A A TCOLDMIN LOWEST COLD LEG TEMPERATURE KA 0311 D A TCOLDMIN N A TCOLDMIN A A TE1815 CONTAINMENT BLDG DOME nlfi' ANA-I 0312 244 B A TE1815 VI l LIN 1.0 5.0 v 0 400 DEG F 05 C A TE1815 1.0 5.0 D A TE181S lSO 2SO I A TE181S 2 1 0 121 196 N A TE181S A A TESTl DIGITAL TEST POINT CI 0313 801 E A TESTl OP NOA NORMAL CL ALM ALARM I A TEST! 3 17 0 1S7 376 N A TESTl A A TEST2 DIGITAL TEST POINT CI 0314 801 E A TEST2 I A TEST2 3 17 2 157 378 N A TEST2 A A TEST3 ANALOG TEST POINT ANA-I 031S 801 B A TEST3 VI l LIN o.o 10.0 v o.o 10.0 PCT 0 C A TEST3 o.o 10.0 D A TEST3 3.0 s.o 7.0 8.0 I A TEST3 l 6 0 106 1S2 N A TEST3 A A TEST4 ANALOG TEST PO INT ANA-I 0316 801 B A TEST4 VI l LIN o.o 10.0 v o.o 10.0 PCT 0 C A TEST4 o.o 10.0 D A TEST4 3.0 s.o 7.0 8.0 I A TEST4 1 6 1 106 1S3 N A TEST4 A A TESTS DIGITAL POINT CI 801 E A TESTS I A TESTS 3 17 4 1S7 380 N A TESTS A A THOTAVG AVERAGE*TEMPERATURE HOT LEGS KA 0317 D A THOTAVG N A THOTAVG Description No. S78-ICE-1402 Rev 00 Page 29 of 47

A A THO'lMAX HIC~EST HOT LEG TEMPERAl'URE KA 0318 D A THO'lMAX . .

N A l'HO'IMAX A A TI0101 PRESSURIZER VAPOR TEMP ANA-I 0101 325 B A TIOlOl VI 1 LIN 1.0 5.0 v 0 700 DEG F 05 C A TIOlOl 1.0 5.0 D A TIOlOl 605 629 659 662.0 1 I A TIOlOl 1 17 l 117 189 N A TIOlOl A A TI0102 PZR WATER PHASE TEMPERATURE ANA-I 0102 325 B A TI0102 VI 1 LIN 1.0 5.0 v 0 700 DEG F 05 C A TI0102 1.0 5.0 D A TI0102 I A TI0102. 1 17 2 117 190 N A TI0102 A A TI0303 SHTDN Cl.NG HX PCS INLET TEMP ANA-I 0097 326 B A TI0303 VI 1 . LIN 1.0 5.0 v 0 400 DEG F 05 C A TI0303 1.0 5.0 D A TI0303 I A TI0303 1 3 2 103 142 N A TI0303 A A TIA0205 VOLUME CONTROL TANK TEMP ANA-I 0115 . 323 B A T!A0205 VI 1 LIN 1.0 5.0 v 50 200 DEG F 05 C A TIA0205 1.0 5.0 D A TIA0205 I A TIA0205 N A TIA0205 80 1

100 2 3 102 130 180 1 139 ,

A A TIA0328 SIRW TANK TEMPERATURE ANA-I 0116 321 B A TIA0328 VI 1 LIN 1.0 5.0 v 0 150 DEG F 05 C A TIA0328 1.0 5.0 D A TIA0328 40 45 110 l I A TIA0328 l 14 3 014 51 N A TIA0328 A A TIC020l REGEN HX OUTLET TEMPERATURE ANA-I 0117 323 B A_TIC0201 VI 1 LIN 1.0 5.0 v 0 600 DEG F 05 C A TIC0201 1.0 5.0 D A TIC0201 460 470 1 I A TIC0201 l 3 0 103 140 N A TIC0201 A A TT0112CA COLD LEG LOOP lA TEMPERATURE ANA-I 0107 222 B A TT0112CA VI 1 LIN 1.0 5.0 v 515 615 DEG F 05 C A TT0112CA 1.0 5.0 D A TT0112CA 538 555 1 I A TT0112CA 1 11 l 011 37 N A TT0112CA A A TT0112CB COLD LEG LOOP lB T>>!PERATUR.E ANA-I 0108 222 B A TT0112CB VI 1 LIN 1.0 5.0 v 515 615 DEG F 05 C A TT0112CB 1.0 5.0 D A TT0112CB 538 555 1 I A TT0112CB 1 10 0 210 288 N A TT0112CB A A TTOll2HA HOT LEG LOOP 1 TEMPERATURE ANA-I 0109 222 B A TT0112HA VI l LIN 1.0 5.0 v 515 615 DEG F 05 C A TT0112HA 1.0 5.0 D A TT0112HA 586 605 l I A TT0112HA 1 11 2 011 38 Description No. 578-ICE-1402 Rev 00 Page 30 of 47

NA TT0112HA A A TT0115

• COLD LEG LOOP l TEMPERATURE ANA-I B A TTOllS VI l LIN 1.0 5.0 v 0 600 DEG F 05 C A TT0115 1.0 5.0 D A TT0115 I A TT0115 2 5 0 025 084 N A TT0115 A A TT0122CA COLD LEG LOOP 2A TEMPERATURE ANA-I 0110 222 B A TT0122CA VI l LIN 1.0 5.0 v 515 615 DEG F 05 C A TT0122CA 1.0 5.0 D A TT0122CA 538 555 1 I A TT0122CA 1 11 3 011 39 N A TT0122CA A A TT0122CB COLD LEG LOOP 2B TEMPERATURE ANA-I 0111 222 B A TT0122CB VI l LIN 1.0 5.0 v 515 615 DEG F 05 C A TT0122CB 1.0. 5.0 D A TT0122CB 538 555 l I A TT0122CB l 10 l 210 289 N A TT0122CB A A TT0122HB HOT LEG LOOP 2 TEMPERATURE ANA-I 0112 222 B A TT0122HB VI l LIN 1.0 5.0 v 515 615 DEG F 05 C A TT0122HB 1.0 5.0 D A TT0122HB 586 605 l I A TT0122HB l 10 2 210 290 N A TT0122HB A A TT0125 COLD LEG LOOP 2 TEMPERATURE ANA-I B A TT0125 VI l LIN 1.() 5.0 v 0 600 DEG F 05 C A TT0125 1.0 5.0 D A TT0125 I A TT0125 1 2 0 220 .no N A TT0125 A A TT0351B SHTDN CLNG HX PCS OUTLT TEMP ANA-I 0113 326 B A TT0351B VI l LIN 1.0 5.0 v 0 400 DEG F 05 C A TT0351B 1.0 s.o D A TT0351B 40 45 325 350 1 I A TT0351B l 17 3 117 191 N A TT0351B A A TTC0203 LETDN HX PCS OUTLET TEMP ANA-I 0118 323 B A TTC0203 VI l LIN 1.0 5.0 v so 200 DEG F 05 C A TTC0203 1.0 5.0 D A TTC0203 70 95 175 200 l I A TTC0203 l- 3 l 103 141 N A TTC0203 A A VIA CNMT COOLER RECIRC FAN VlA CI 0162 341 E A VlA OP NOA ON CL NOA OFF I A VlA 3 17 6 257 638 N A VlA A A V2A CNMT COOLER RECIRC FAN V2A CI 0163 341 EA V2A OP NOA ON CL NOA OFF I A V2A 4 0 0 260 640 N AV2A A A V3A CNMT COOLER RECIRC FAN V3A CI 0164 341 EA V3A OP NOA ON CL NOA OFF

• I A V3A NA V3A A A V4A 4 0 2 260 CNMT COOLER RECIRC FAN V4A Description No. 578-ICE-1402 CI Rev 00 0165 642 341 Page 31 of 47

! A V4A OP SOA ON CL NOA OPP.

- 3 12 2 052 82 I A V4A NA V4A A A XACOUMON RELIEF VLV DISQl LEG CAL PT CD 102 E A XACOUMON ALARM NORMAL A A XALMBPDL CNMT .LOW PRES LEG lB CAL PT. _CD 102 E .A XALMBFDL .. ALARM NORMAL A A. XAPTRCR HI POST TllP CNTRT LEG CAL PT CD 102 E A XAPTRCR ALARM NORMAL A A XBOTEMPC BORON CONC LEG CAL PT 'CD 102 E A XBOTEMPC

• ALARM NORMAL A A XCNMPRST CNMT PRES CHANGE LEG CAL PT CD 102 E A XCNMPRST ALARM NORMAL A A XCNMT'IMP CNMT HIGH T!MP

• LEG CAL PT CD 102 E A XCNMT'IMP ALARM NORMAL A A XCNSMDRV CNMT SUMP,DRN,VNT LEG.CAL PT CD 102 E A XCNSMPRV ALARM NORMAL A*A XCNSPSTA CNMT SPRAY FLOW LEG CAL PT CD 102 E A XCNSPSTA ALARM NORMAL A A XCNTPGFN CNMT P UR.GE FAN LEG CAL PT CD 102 E A XCNTPGPN ALARM NORMAL AA XCWR.EACA THERMAL REACT ADD LEG CAL Pf CD 102 E A XCWR.EACA ALARM *NORMAL A A XCWR.TNKS CLN WST RCVR TNKS LEG CAL PT CD 102 E A XCWR.TNKS ALARM NORMAL A A XPANSTAT FAN COOLERS LEG CAL PT CD 102 E A XFANSTAT ALARM NORMAL A A XLLPFLW LOW LOOP FLOW LEG CAL PT CD 102 E A XLLPFLW ALARM NORMAL A A XLPSPRS LOW SG PRI/SEC DP LEG CAL PT CD 102 E A XLPSPRS ALARM NORMAL A A XLRCSHLD HI PCS HEAT LOAD LEG CAL PT CD 102 E A XLRCSHLD ALARM NORMAL A A XMAXDTMP HI MAX DT LEG CAL PT CD 102 E A XMAXDTMP ALARM NORMAL A A XMAXPPSR HI PZR PRESSURE LEG CAL PT CD 102 E A XMAXPPSR *ALARM NORMAL A A XMINPLvL LO PZR LEVEL LEG CAL PT CD 102 E A XMINPLVL ALARM NORMAL A A XMISCVLV MISC VALVES NS LEG CAL PT CD 102 E A XMISCVLV ALARM NORMAL A A XMPTTEMP MPT TEMP.EXCEEDED LEG CAL PTCD 102 E A XMPTTEMP ALARM NORMAL A A XPLVLRTE HI PZR LVL RAT'E LEG CAL PT CD 102 E A XPLVLRTE ALARM NORMAL A A XPPSRRTE PZR PRES RATE LEG CAL PT CD 102 E A XPPSRRTE ALARM NORMAL.

A A XQTNKLVL QUENCH TANK LVL LEG CAL PT CD 102 E A XQTNIC.LVL ALARM NORMAL A A XQTNKPSR QUENCH TANK PRES LEG CAL PT CD 102 E A XQTNKPSR ALARM NORMAL A A XQTNKSPN QUENCH TANK, N2 LEG CAL PT CD 102 E A XQTNKSPN . ALARM NORMAL A A XRCPSRUN LOW PCP LOAD LEG CAL PT CD 102 E A XRCPSRUN AI.It.RM NORMAL A A XRCTRTRP CNMT HIGH PRES LEG CAL PT CD 102 Description No. 578-ICE-1402 Rev 00 Page 32 of 47

E A XRCTRTRP AI.ABM NORMAL A .A XRVLVLHT LOOP/GORE VOID LEG CAL PT CD 102

• E A XRVLVLHT A A XSAXMARG E A XSATMARG A A XSDCLOSS E A XSDCLOSS A A XSGSSVLV E A XSGSSVLV AI.ABM NORMAL SAl'URATION MARGIN LEG CAL PT CD AI.ABM NORMAL SDC NOT COOLING.LEG CAL PT AI.ABM CD NORMAL ..

SG SYS VL.VES NS LEG CAL PT A.I.ABM NORMAL CD 102

. 102 102 A A XSISLOSS SIS NOT COOLING LEG CAL PT CD 102 E A XSISLOSS AI.ABM NORMAL

• A A XSRASl RECIRCULATION ACTUATION SIGA CI 0127 E A XSRASl OP ALM ACTUATED CL NOA NORMAL I A XSRASl 4 16 4 076 244 NA XSRASl A A XSRAS2 RECIRCULATION ACTUATION SIGB CI 0128 E A XSRAS2 OP ALM ACTUATED CL NOA NORMAL I A XSRAS2 4 16 6 076 246 N A XSRAS2 A A XS'IMGNLC SGS NOT COOLING LEG CAL PT CD 102 E A XS'IMGNLC AI.ABM NORMAL A A XSUBCOOL SUB COOLED MARGIN LEG CAL PT *CD 102 E A XSUBCOOL ALARM NORMAL A A YS421501 PROPORTIONAL HEATER #1 STAT CI 0131 325 E A YS421501 OP NOA OFF CL NOA ON I A YS421501 3 0 0 140 256 N A YS421501 A A YS421502 BACKUP HEATER GROUP #1 STAT CI 0132 325 E A YS421502 OP NOA OFF CL NOA ON I A YS421502 3 0 2 140 258 N A YS421502 A A YS421506 BACKUP HEATER GROUP li2 STAT CI 0133 325 E A YS421506 OP NOA OFF CL NOA ON

• I A YS421506 3 0 4 140 260 N A YS421506 A A YS421601 PROPORTIONAL HEATER #2 STAT CI 0134 325 E A YS421601 OP NOA OFF CL NOA ON I A YS421601 3 2 0 242 528 N A YS421601 A A YS421602 BACKUP HEATER GROUP #3 STAT CI 0135 325 E A YS421602 OP NOA OFF CL NOA ON I A YS421602 3 2 2 242 530 N A YS421602 A A YS421606 BACKUP HEATER GROUP #4 STAT CI 0136 . 325 E A YS421606 OP NOA OFF CL NOA ON I A YS421606 3 2 4 242 532 N A YS421606 A A YSAXFPA AUX FEEDWATER PUMP P8A STAT CI 0137 333 E A YSAXFPA OP NOA ON CL NOA OFF I A YSAXFPA 3 1 6 041 14 N A YSAXFPA A A YSAXFPB AUX FEEDWATER PUMP PSB STAT KD 0138 333 E A YSAXFPB OP NOA OFF CL NOA ON N A YSAXFPB A B YSAXFPC AUX FEEDWATER. PUMP PSC STAT* CI 0157 333

. E B YSAXFPC OP NOA ON CL NOA OFF Description No. 578-ICE-1402 Rev 00 Page 33 of 47

1 I B YS.AXFPC 4 12 6 272 726 N B YS.AXFPC

• A A YSCDP2A EA YSCDP2A I A YSCDP2A N A YSCDP2A A A YSCDP2B E A YSCDP2B I A YSCDP2B CONDENSAl'E PUMP P2A STATUS OP NOA ON 4

OP NOA ON 4

CL NOA OFF 0 0 160 CONDENSATE PUMP*P2B STATIJS CL NOA OFF 0 2 160 CI CI 0139 0140 384 386 332 332 N A YSCDP2B A A YSMFPlA HAIN FEED PUMP PlA STATUS CI 0141 332 E A YSMFPlA OP NOA PMP ON CL NOA PMP OFF I A YSMFPlA 4 5 0 265 680 N A YSMFPlA A A YSMFPlB HAIN FEED PUMP PlB STATUS CI 0142 332 E A YSMFPlB OP NOA PMP ON CL NOA PMP OFF I A YSMFPlB 4 5 2 265 682 N A YSMFPlB A A YSP50A PCP lA STATUS CI 0143 222 E A YSP50A OP NOA PMP ON CL NOA PMP OFF I A YSP50A 3 4 6 044 38 N-A YSP50A A A YSP50B PCP lB STATUS CI 0144 222 E A YSP50B OP NOA PMP ON CL NOA PMP OFF I A YSP50B 3 5 2 045 42 N A YSP50B A A YSP50C PCP 2A STATUS CI 0145 222 1 E A YSP50C OP NOA PMP ON CL NOA PMP OFF I A YSP50C 3 5 0 045 40 N A YSP50C A A YSP50D PCP 2B STATUS CI 0146 222 E A YSP50D OP NOA PMP ON CL NOA PMP OFF I A YSP50D 3 5 4 045 44 N A YSPSOD A A YSP54A CNMT SPRAY PUMP P54A STATIJS CI 0147 342 E* A YSP54A OP NOA PMP ON .CL NOA PMP OFF I A YSP54A 4 12 2 272 722 N A YSP54A A A YSP54B CNMT SPRAY PUMP P54B STATUS CI 0148 342 E A YSP54B OP NOA PMP ON CL NOA PMP OFF I A YSPS4B 4 13 0 073 216 N A YSP54B A A YSP54C CNMT SP.UY PUMP P54C STATUS CI 0149 342 E A YSP54C OP NOA PMP ON CL NOA PMP OFF I A YSP54C 4 13 2 073 218 N A YSP54C A A YSP55A CHARGING PUMP P55A STATUS CI 0150 323 E A :YSP55A OP NOA PMP ON CL NOA PMP OFF I A YSP55A 4 6 2 266 690 N A YSP55A A A YSP55B CHARGING PUMP P55B STATUS CI 0151. 323 E A YSP55B . OP NOA PMP ON CL NOA PMP OFF I A YSP55B 4 6 4 266 692 N A YSP55B A A YSP55C CHARGING PUMP P55C STATUS CI 0152 323 E A YSP55C OP NOA PMP ON CL NOA PMP OFF De~cription No. 578-ICE-1402 R.ev 00 Page 34 of *47

I A YSP55C - 4 4 6 064 166 N A YSP55C A A YSP56A BORIC ACID PUMP P56A STATUS CI 0153 324 E A YSP56A OP NOA PMP OFF CL NOA PMP ON I A YSP56A 4 13 2 273 730 N A YSP56A A A YSP56B BORIC ACID PUMP.* P56B STATUS CI 0154 324 E A YSP56B OP NOA PMP OFF CL NOA PMP ON I A YSP56B 4 5 0 065 168 N A YSP56B A A YSP66A HPSI PUMP P66A STATUS CI 0155 321 E A YSP66A OP NOA PMP ON CL NOA PMP OFF I A YSP66A 4 12 4 272 724 N A YSP66A A A YSP66B HPSI PUMP P66B STATUS CI 0156 321 E A YSP66B OP NOA PMP ON CL NOA PMP OFF I A YSP66B 4 13 4 073 220 N A YSP66B A A YSP67A I.PSI PUMP P67A STATUS CI 0158 321 E A YSP67A OP NOA PMP ON CL NOA PMP OFF I A YSP67A 4 12 0 272 720 N A YSP67A A A YSP67B I.PSI PUMP P67B STATUS CI 0159 321 E A YSP67B OP NOA PMP ON CL NOA PMP OFF I A YSP67B 4 13 6 073 222 N A YSP67B A A ZH0511 STEAM BYPASS TO CONDENSER CI 0327 331 E A ZH0511 OP NOA CLOSED CL NOA OPEN I A ZH0511 3 2 4 142 276 N A ZH0511 A A ZH0521 AUX FEED PUMP K8 S'l'M ISO VLV CI 0328 333 E A ZH0521 OP NOA NFO CL NOA OPEN I A ZH0521 3 1 4 041 12 N A ZH0521 A A ZH0522A AUX FEED PUMP KS S'l'M SUPPLY CI 0168 333 E A ZH0522A OP NOA NFO CL NOA OPEN I A ZH0522A 3 0 4 040 4 N A ZH0522A A A ZH0522B AUX FEED PUMP KS TURB TRIP CI 0169 333 E A ZH0522B OP NOA NFO CL NOA OPEN I A ZH0522B 3 0 2 040 002 N A ZH0522B A A ZH0569 HP TURB S'l'M INLET VALVE tll CI 0170 331 E A ZH0569 OP NOA NFC CL NOA CLOSED I A ZH0569 4 5 4 265 6S4 N A ZH0569 A A ZH0571 HP TURB STM INLET VALVE tl2 CI 0171 331 E A ZH0571 OP NOA NFC CL NOA CLOSED I A ZH0571 4 5 6 265 6S6 N A ZH0571 A A ZH0573 HP TURB STM INLET VALVE 113 CI 0172 331 E A ZH0573 OP NOA NFC CL NOA CLOSED I A ZH0573 4 15 0 275 744

• N A ZH0573 A A ZH0575 E A ZH0575 HP TURB S.TM INLET VALVE 114 OP NOA NFC Description No. 57S-ICE-l402 CL NOA CLOSED CI Rev 00 0173 331 Page 35 of 47

I A ZB0575 4 15 2 275 746 N A ZH0575 A A ZB0701 S'lM GEN E-50A FDWTR REG VLV CI 0174 343 E A ZH0701 OP NOA NFC CL NOA CLOSED I A ZH0701 4 0 2 060 130 N A ZH0701 . -

A A ZH0703 S'l'M GEN E-50B FDWTR REG VLV CI 0175 343 E A ZH0703 OP NOA NFC . CL NOA CLOSED I A ZH0703 4 0 4 060 132 N A ZH0703 A A ZH0824 CNMT FAN CLRS SW OUTLET VLV CI 0176 341 E A ZH0824 OP NOA NFO CL NOA OPEN I A ZH0824 3 11 o 051 72 N A ZH0824 A A ZB0847 CNMT FAN CLRS SW INLET VALVE CI 0177 341 E A ZH0847 .OP NOA NFO CL NOA OPEN I A ZH0847 3 11 2 051 74 N A ZH0847 A A ZH086l CNMT* FAN. CLR VHX-l SW OUTLET CI 0178 341 E A ZH0861 OP NOA NFO CL NOA OPEN I A ZH0861 3 16 0 256 624 N A ZH0861 A A ZH0862 CNMT FAN CLR VHX-1 SW INLET CI 0179 341 E A ZH0862 OP NOA NFO CL NOA OPEN I A ZH0862 3 16 2 256 626 N A ZH0862 A A ZH0864 CNMT FAN CLR VHX-2 SW OUTLET CI 0180 341 E A ZH0864 OP NOA NFO CL NOA OPEN I A ZH0864 3 16 4 256 628 N A ZH0864 A A ZH0865 CNMT FAN CLR VHX-2 SW INLET CI 0181 341 E A ZH0865 OP NOA NFO CL NOA OPEN I A ZH0865 3 16 6 256 630 N A ZH0865 A A ZH0867 CNMT FAN CLR VHX-4 SW OUTLET CI 0182 341 E A ZH0867 OP NOA NFO CL NOA OPEN I A ZH0867 3 11 4 051 76 N A ZH0867 A A ZH0869 CNMT FAN CLR VHX-4 SW INLET CI 0183 341 E A ZH0869 OP NOA NFO CL NOA OPEN I A ZH0869 3 11 6 051 78 N A ZH0869 - .

A A ZH0870 CNMT FAN CLR VHX-3 SW OUTLET CI 0184 341 E A ZH0870 OP NOA NFO CL NOA OPEN I A ZH0870 .3 17 0 257 632 N A ZH0870 A A ZH0873 CNMT FAN CLR VHX-3 SW INLET CI 0185 341 E A ZH0873 OP NOA NFO CL NOA OPEN I A ZH0873 3 17 2 257 634 N A ZH0873 A A ZH0937 SDC HX SW INLET ISO VLV 0937 CI . 0330 E A ZH0937 OP NOA NFO CL NOA OPEN I A ZH0937 3 17 4 257 636 N A ZH0937 A A ZH0938 SDC HX SW INLET ISO VLV 0938 CI 0331 E A ZH0938 OP NO.A NFO CL NOA OPEN Qescription No. 578-ICE-1402 Rev 00

• Page 36 of 47

I A ZH0938 . 3 12 0 052 80

• N A ZH0938 A A ZB1013 E A ZH1013 I A ZH1013 N A ZH1013 A A ZH1015 CLN WST RCVR TNK T-64A RECIR. CI OP NOA NFO 4

CL NOA OPEN 1 4 061 CLN WST RCVR TNK T-64B RECIR. CI 0332 0333 140 E A ZH1015 OP NOA NFO CL NOA OPEN I A ZH1015 4 l . 6 061 142 N A ZH1015 A A ZH1017 CLN WST CRVR TNK T-64C RECIR CI 0334 E A ZH1017 OP NOA NFO CL NOA OPEN I A ZH1017 4 2 0 062 144 N A ZH1017 A A ZH1019 .CLN WST RCVR TNK T-64D RECIR CI 0335 E A ZH1019 OP NOA NFO CL NOA OPEN I A ZH1019 4 2 2 062 146 N A ZH1019 A A ZH2002 LTDN ORIFIC BYP STP VLV 2002 CI 0186 323 E A ZH2002 OP NOA NFO CL NOA OPEN I A ZH2002 3 3 4 243 540 N A ZH2002 A A ZH2003 LTDN ORIFIC BYP STP VLV 2003 CI 0187 323 E A ZH2003 OP NOA NFO CL NOA OPEN I A ZH2003 3 3 6 243 542 N A ZH2003 A A ZH2004 LTDN ORIFIC BYP STP VLV 2004 CI 0188 323 E A ZH2004 OP NOA NFO CL NOA OPEN I A ZHi004 3 4 0 244 544 N A ZH2004 A A ZH2005 LTDN ORIFIC BYP STP VLV 2005 CI 0189 323 E A ZH2005 OP NOA NFO CL NOA OPEN I A ZH2005 3 4 2 244 546 N A ZH2005 A A ZH2087 VCT PMW TO CHG PMPS ISO.VLV CI 0190 323 E A ZH2087 OP NOA CLOSED CL NOA NFC I A ZH208-7 4 5 2 065 170 N A ZH2087 A B ZH2140 MAKEUP CONT BLND VLV BYP VLV CI 0336 324 E A ZH2140 OP NOA OPEN CL NOA NFO I A ZH2140 3 7 0 247 568 N A ZH2140 A A ZH2153 BORIC ACID CONTROL VALVE CI 0192 E A ZH2153 op* NOA CLOSED CL NOA NFC I A ZH2153 3 3 0 043 24 N A ZH2153 A A ZH2155 PMW MAKEUP CONTROL VALVE CI 0193 324 E A ZH2155 OP NOA NFO CL NOA OPEN I A ZH2155 3 3 2 043 26 N A ZH2155 A A ZH2160 SIRW PMW TO CHGING PUMPS VLV CI 0337 324 E A ZH2160 OP NOA C~OSED CL NOA NFC I A ZH2160 4 17 6 277 766 N A ZH2160 A A ZH2165 PMW TO BLENDER CNTLR ISO VLV CI .. 0338 324 E A ZH2165 OP NOA NFO CL NOA OPEN Descriotion No. 578-ICE-1402 Rev 00 Page 37 of 47

• I A ZB2165 - 3 11 4 151 332 N A ZR2165

• A A ZH2169 E A ZH2169 I A ZH2169 N A ZH2169 A A ZH2170 E A ZH2170 I A ZH2170 BA TANK T-58A GRAV FEED STOP CI OP NOA NFO 4

OP NOA NFO 4

CL NOA OPEN 5 4 065 CL NOA OPEN 5 6 065 BA TANK T-58B G"B.AV FEED STOP CI 0194 0195 172 174 324 324 N A ZH2170 A A ZH2191 PCP BLEEDOFF CONTROL VALVE CI 0196 E A ZH2191 OP NOA NFO CL NOA OPEN I A ZH2191 3 4 4 244 548 N A ZH2191 A A ZH3007 HPSI TO LOOP lA STP VLV 3007 CI 0339 322 E A ZH3007 OP NOA CLOSED CL NOA NFC I A ZH3007 4 10 0 070 192 N A ZH3007 A A ZH3008 I.PSI TO LOOP lA STP VLV 3008 CI 0340 322 E A ZH3008 OP NOA CLOSED CL NOA NFC I A ZH3008 4 10 2 070 194 N A ZH.3008 A A ZH3009 HPSI TO LOOP lB STP VLV 3009 CI 0341 322 E A ZH3009 OP NOA CLOSED CL NOA NFC I A ZH3009 4 10 4 070 196 N A ZH3009 A A ZH3010 I.PSI TO LOOP lB STP VLL 3010 CI 0379 322 1 E A ZH3010 OP NOA CLOSED CL NOA NFC I A ZH3010 4 12 6 072 214 N A ZH3010 A A ZH3011 HPSI TO LOOP 2A STP VLV 3011 CI 0380 322 E A ZH3011 OP NOA CLOSED CL NOA NFC I A ZH30ll 4 12 4 072 212 N A ZH3011 A A ZH3012 I.PSI TO LOOP *2A STP VLV 3012 CI 0342 322 E A ZH3012 OP NOA CLOSED CL NOA NFC I A ZH3012 4 7 2 267 698 N A ZH3012 A A ZH3013 HPSI TO LOOP 2B STP VLV 3013 CI 0343 322 E A ZH3013 OP NOA CLOSED CL NOA NFC I A ZH3013 4 10 6 070 198 N A ZH3013 A A ZH3014 I.PSI TO.~OOP 2B STP VLV 3014 CI 0344 322 E A ZH3014 OP NOA CLOSED CL NOA NFC I A ZH3014 4 7 6 267 702 N A ZH3014 A A ZH3027 SIRW TANK RECIRC VALVE 3027 CI - 0209 321 E A ZH3027 OP NOA NFO CL NOA OPEN I A ZH3027 3 7 0 047 56 N A ZH3027 A A ZH3031 SIRW TANK OUTLET VALVE 3031 CI 0197 321 E A ZH3031 OP NOA NFO CL NOA OPEN I A ZH3031 3 5 6 045 46 N A ZH3031 A A ZH3041 SI TANK T-82A OUTLET VALVE CI 0198 322 E A ZH3041 OP NOA CLOSED CL NOA NFC Description No. 578-ICE-1402 Rev 00 Page 38 of 47

I A ZH304l 3 6 0 046 48 N A ZH304l A A ZH3045 SI TANK T-82B OUTLET VALVE CI 0199 322 E A ZH.3045 OP NOA CLOSED CL NOA NFC I A ZH.3045 3 6 2 046 50 N A ZH.3045 A A ZH3049 SI TANK T-82C OUTLET VALVE CI 0200 322 E A ZH3049 OP NOA CLOSED CL NOA NFC I A ZH3049 3 10 4 250 580 N A ZH3049 A A ZH3052 SI TANK T-82D OUTLET VALVE CI 0201 322 E A ZH3052 OP NOA CLOSED. CL NOA NFC I A ZH3052 3 10 6 250 582 N A ZH3052 A A ZH3055 SDC HX PCS INLET STOP VALVE CI 0202 326 E A ZH3055 OP NOA NFO CL NOA OPEN I A ZH3055 3 4 6 244 550 N A ZH3055 A A ZH3056 SIRW TANK RECIRC VALVE 3056 CI 0203' 321 E A ZH3056 OP NOA NFO CL NOA OPEN I A ZH3056 3 12 0 252 592 N A ZH3056 A A ZH3057 SIRW TANK OUTLET VALVE 3057 CI 0204 321

• E A ZH3057 OP NOA NFO CL NOA OPEN I A ZH3057 3 11 2 251 586 N A ZH3057 A A ZH3062 ~UNDNT HPSI TO LOOP 2B VLV CI 0345 322 E A ZH3062 OP NOA CLOSED CL NOA NFC I A ZH3062 4 7 4 267 700 N A ZH3062 A A ZH3064 REDU~NT HPSI TO LOOP 2A VLV CI 0346 322 E A ZH3064 OP NOA CLOSED CL NOA NFC I A ZH3064 4 10 4 270 708 N A ZH3064 A A ZH3066

• REDUNDNT HPSI TO LOOP lB VLV CI 0347 322 E A ZH3066 OP NOA CLOSED CL NOA NFC I A ZH3066 4 10 0 270 704 N A ZH3066 A A ZH3068 REDUNDNT HPSI TO LOOP lA VLV CI 0348 322 E A ZH3068 OP NOA CLOSED CL NOA NFC I A ZH3068 4 10 2 270 706 N A ZH3068 A A ZH3212 SDC Hi~B INLET STOP VALVE CI 0205 326 E A ZH3212 OP NOA NFO CL NOA OPEN I A ZH3212 3 11 4 251 588 N A ZH3212 A A ZH3213 SDC HX-B OUTLET STOP VALVE CI 0206 326 E A ZH3213 OP NOA NFO CL NOA OPEN I A ZH3213 3 11 6 251 590 N A ZH3213 A A ZH3223 SDC HX-A INLET STOP VALVE CI 0207 326 E A ZH3223 OP NOA NFO CL NOA OPEN I A ZH3223 3 6 4 046 52 N A ZH3223 A A ZH3224 SDC HX-A OUTLET STOP VALVE CI 0208 326 E A ZH3224 OP NOA NFO CL NOA OPEN Description No. 578-ICE-1402 Rev 00 Page 39 of 47

I A ZR3224 3 6 6 046 54 N A ZH3224-

• A A ZL0155 E A ZL0155 I A ZL0155 N A ZL0155 A A ZL0501 E A ZL0501 I A ZL0501 PMW TO QUENCH TANK SPRAY VLV CI OP NOA NFC 3

CL NOA CLOSED 4 4 044 MAIN STEAM ISO VLV SG E-50B CI OP NOA NFC 3

.CL NOA CLOSED 0 2 240 0349 0211 36 514 325 331 N A ZL0501 A A ZL0510 MAIN STEAM ISO VLV SG E-50A CI 0212 331 E A ZL0510 OP NOA NFC CL NOA CLOSED I A ZL0510 3 0 6 040 6 N A ZL0510 A A ZL0511 MAIN STEAM BYP VLV TO COND CI 0351 331 E A ZL0511 OP NOA NFC CL NOA CLOSED I A ZL0511 3 2 6 142 278 NA ZL0511 A A ZL0594 REHEATER E-9A TEMP CNTRL VLV CI 0213 331 E A ZL0594 OP NOA NFC CL NOA CLOSED I A ZL0594 3 1 0 141 264 N A ZL0594 A A ZL0595 REHEATER E-9B TEMP CNTRL VLV CI 0214 331 E A ZL0595 OP NOA NFC CL NOA CLOSED I A ZL0595 N A ZL0595 A A ZL0596 E A ZL0596 3 l 2 141 REHEATER E-9C TEMP CNTRL VLV CI OP NOA NFC CL NOA CLOSED 0215 266 331 ,

I A ZL0596 3 1 4 141 268 N A ZL0596 A A ZL0597 REHEATER E-9D TEMP CNTRL VLV CI 0216 331 E A ZL0597 OP NOA NFC CL NOA CLOSED I A ZL0597 3 l 6 141 270 N A ZL0597 A A ZL0738 SG E50B TOP BLDN ISO VLV 738 CI 0219 332 E A ZL0738 OP NOA NFC CL NOA CLOSED I A ZL0738 3 13 6 053 94 N A ZL0738 A A ZL0739 SG E50A TOP BLDN ISO VLV 739 CI 0220 332 E A ZL0739 OP NOA NFC CL NOA CLOSED I A ZL0739 4 1 0 261 648 N A ZL0739 A B ZL0743 AUX FW _ISO VALVE TO SG B CI 0400 343 E B ZL0743 OP NOA NFC CL NOA CLOSED I B ZL0743 3 2 6 042 022 N B ZL0743 A B ZL0748 AUX FW ISO VALVE TO SG B CI 0405 343 E B ZL0748 OP NOA NFC CL NOA CLOSED I B ZL0748 4 6 0 266 688 N B ZL0748 A B ZL0753 AUX FW ISO VALVE TO SG A CI 0398 343 E B ZL0753 OP NOA NFC CL NOA CLOSED I B ZL0753 3 2 2 042 018 N B ZL0753 A B ZL0754 AUX FW ISO VALVE TO SG A CI 0403 343 E B ZL0754 OP NOA NFC CL NOA CLOSED Description No. 578-ICE-1402 Rev 00 Page 40 of 47

I B ZL0754 - 4 15 4 275 748 N B ZL0754 A B ZL0755 AUX FW ISO VALVE TO SG B CI 0399 343 E B ZL0755 OP NOA NFC CL NOA CLOSED I B ZL0755 3 2 4 042 020 N B ZL0755 A B ZL0759 AUX_ FW ISO VALVE TO SG A CI 0397 343 E B ZL0759 OP NOA NFC CL NOA CLOSED I B ZL0759 3 2 0 042 016 N B ZL0759 A B ZL0760 AUX FW ISO VALVE TO SG A CI 0404 343 E B ZL0760 OP NOA NFC CL NOA CLOSED I B ZL0760 4. 15 6 275 750 N B ZL0760 A A ZL0767 SG E50A BTM BLDN ISO VLV 767 CI 0223 332 E A ZL0767 OP NOA NFC CL NOA CLOSED I A ZL0767 4 1 2 261 650 N A ZL0767 A A ZL0768 SG ESOB BTM BLDN ISO VLV 768 CI 0224 332 E A ZL0768 OP NOA NFC CL NOA CLOSED

• 1 A z*to768 4 l 4 261 652 .

N A ZL0768 A A ZL0770 SG ESOB BTM BLDN ISO VLV 770 CI 0225 332 E A ZL0770 OP NOA NFC CL NOA CLOSED I A ZL0770 3 14 0 054 96 N A ZL0770 A A ZL0771 SG ESOA BTM BLDN ISO VLV 771 CI 0226 332 E A ZL0771 OP NOA NFC CL NOA CLOSED I A ZL0771 3 14 2 054 98 N A ZL0771 A A ZL0779 SG E50B ATMOS RELIEF VLV 779 CI 0227 233 E A ZL0779 OP NOA NFC CL NOA CLOSED I A ZL0?79 3 1 0 041 8 N A ZL0779 A A ZL0780 SG ESOB ATMOS RELIEF VLV 780 CI 0228 233 E A ZL0780 OP NOA*NFC CL NOA CLOSED I A ZL0780 3 0 4 240 516 N A ZL0780 A A ZL0781 SG ESOA ATMOS RELIEF VLV 781 CI 0229 233 E A ZL0781 OP NOA NFC CL NOA CLOSED I A ZL0781 3 1 2 041 10 N A ZL0781 A A ZL0782 SG ESOA ATMOS RELIEF VLV 782 CI 0230 233 E A ZL0782 OP NOA NFC CL NOA CLOSED I A ZL0782 3 0 6 240 518 N A ZL0782

. AB ZL0798 AUX*FW ISO VALVE TO SG B CI 0406 343 E B ZL0798 OP NOA NFC CL NOA CLOSED I B ZL0798 4 6 6 266 694 N B ZL0798 A A ZL0910 CCW SUPPLY TO CNMT STP VALVE CI 0352 343 E A ZL0910 OP NOA NFC CL NOA CLOSED I A ZL0910 3 16 6 056 118 N A ZL0910 A A ZL0911 CCW RTN FM CNMT STOP VLV 911 CI 0353 343 E A ZL0911 OP NOA NFC CL NOA CLOSED Description No. 578-ICE-1402 Rev 00 Page 41 of 47

I A ZL09ll 3 17 0 057 120 N A ZL09ll

• A A ZL0939 E A ZL0939 I A ZL0939 N A ZL0939 A A ZL0940 E A ZL0940 I A ZL0940 SHIELD CLNG SRGE TK FILL VLV CI OP NOA NFC 3

CL NOA CLOSED 17 2 057 ccw RTN FM CNMT STOP VLV .940 "er OP NOA NFC

• 4 CL NOA CLOSED 3 4 263 0354 0355 122 668 343 343 N A ZL0940 A A ZLlOOl PCS DRAIN TK T-74 RECIRC VLV CI 0231 343 E A ZL1001 OP NOA NFC CL NOA CLOSED I A ZL1001 3 14 4 054 100 N A ZL1001 A A ZL1002 PC ORN TK PMP suer VLV 1002 CI 0232 343 E A ZL1002 OP NOA NFC CL NOA CLOS ED I A ZL1002 3 14 6 054 102 N A ZL1002 A A ZL1004 CLEAN WST RCVR TKS ISO VALVE CI 0233 343 E A ZL1004 OP NOA NFC CL NOA CLOS ED I A ZL1004 3 15 0 055 104 N A ZL1004 A A ZL1007 PC ORAN TK PMP SUCT VLV 1007 CI 0234 343 E A ZL1007 OP NOA NFC CL NOA CLOSED I A ZL1007 4 1 6 261 654 N A ZL1007 A A ZL1014 CLN WST RCVR TK T-64B IN S'IP CI 0356 E A ZL1014 OP NOA NFC CL NOA CLOSED I A ZL1014 4 2 4 062 148 N A ZL1014 A A ZL1016 CLN WST RCVR TK T-64C IN STP CI 0357 E A ZL1016 OP NOA NFC CL NOA CLOSED I A ZL1016 4 2 6 062 150 N A ZL1016 A A ZL1018 CLN WST RCVR TK T-640 IN STP CI 0358 E A ZL1018 OP NOA NFC . CL NOA CLOSED I A ZL1018 N A ZL1018 4 3 0 063 152 .

A A ZL1036 CLN WST RCVR TKS PMP SUC1036 CI 0235 343 E A ZL1036 OP NOA NFC CL NOA CLOSED I A ZL1036 3 15 2 055 106 N A ZL1036 A A ZL1037 CLN WST RCVR TIC PMP DIS 1037 CI 0236 343 E A ZL1037 OP NOA NFC CL NOA CLOSED I A ZL1037 4 2 0 262 656 N A ZL1037 A A ZL1038 CLN WST*RCVR TICS PMP SUC1038 CI 0237 343 E A ZL1038 OP NOA NFC CL NOA CLOS ED I A ZL1038 4 2 2 262 658 N A ZL1038 A A ZL1042A PZR POR BLOCK VALVE 1042A CI 0238 325 E A ZL1042A OP NOA OPEN CL NOA NFO I A ZL1042A 4 6 0 066 176

. N A ZL1042A A A ZL1043A PZR POR BLOCK VALVE l043A CI 0240 325 E A ZL1043A OP NOA OPEN CL NOA NFO Description No. 578-ICE-1402 Rev 00 Page 42 of 47

.I A ZL1043A 4 6 2 066 178 N A ZL1043A.

A A ZL1044 CLN WST RCVR TK PMP SU Vl044 CI* 0242 343 E A ZL1044 OP NOA NFC CL NOA CLOSED I A ZL1044 3 15 4 055 108 N A ZL1044 A A ZL1045 CLN W~T RCVR TK-PMP SU Vl045-CI 0243 343 E A ZL1045 OP NOA NFC CL NOA CLOSED I A ZL1045 4 2 4 262 660 N A ZL1045 A A ZL1064 - CLN WST RECVER TK VENT 1064 CI 0245 343 E A ZL1064 OP NOA NFC CL NOA CLOSED I A ZL1064 3 15 6 055 110 N A ZL1064 A A ZL1065 CLN WST RECVER TK VENT 1065 CI 0246 343 E A ZL1065 OP NOA NFC CL NOA CLOSED I A ZL1065 4 2 6 262 662 N A ZL1065 A A ZLllOl WST GAS TK CNMT STOP V 1101 CI 0247 343 E A ZLllOl OP NOA NFC CL NOA CLOSED I A ZLllOl 3 16 0 056 112 N A ZLllOl A A Z.Lll02 WST GAS TK CNMT STOP V 1102 CI 0248 343 E A ZL1102 OP NOA NFC CL NOA CLOSED I A ZL1102 4 3 0 263 664 N A ZL1102 A A ZL1103 CNMT SUMP DRAINS ISO V 1103 CI 0249 342 E A ZL1103 OP NOA NFC CL NOA CLOSED I A ZLll03 3 16 2 056 114 N A ZL1103 A A ZL1104 CNMT SUMP DRAINS ISO V 1104 CI 0250 342 E A ZL1104 OP NOA NFC CL NOA CLOSED I A ZL1104 4 3 2 263 666 N A ZL1104 A A ZL1358 NITROGEN CNMT ISOLATION VLV CI 0251 343 E A ZL1358 OP NOA NFC CL NOA CLOSED I A ZL1358 3 16 4 056 116 N A ZL1358 A A ZL1501 CNMT BLDG STM RETRN VLV 1501 CI 0378 341 E A ZL1501 OP NOA NFC CL NOA CLOSED I A ZL1501 4 0 0 060 128 N A ZL1501 A A ZL1502 CNMT BLDG STM RETRN VLV 1502 CI 0359 341 E A ZL1502 OP NOA NFC CL NOA CLOSED I A ZL1502 4 4 0 . 264 672 N A ZL1502 A A ZL1503 CNMT BLDG STM SPPLY VLV 1503 CI '0360 341 E A ZL1503 OP NOA NFC CL NOA CLOSED I A ZL1503 3 17 4 057 124 N A ZL1503 A A ZL1813 AIR SPC PRGE FAN DAMPER 1813 CI 0361 343 E A ZL1813 OP NOA NFC CL NOA CLOSED I A ZL1813 4 4 2 264 674 N A ZL1813 A A ZL1814 AIR SPC PRGE FAN DAMPER 1814 CI 0362 343 E A ZL1814 OP NOA NFC CL NOA CLOSED Description. No. 578-ICE-1402 Rev 00 Page 43 of 47

I A ZL1814 3 17 6 057 126 N A ZL1814 A A ZL1910 PRI*SYS SAMPLNG ISO VLV 1910 CI 0252 ,343 E A ZL1910 OP NOA NP'<:! CL NOA CLOSED I A ZL1910 . 4 0 6 060 134 N A ZL1910 A A ZL1911 PRI SYS SAMPLNG ISO VLV 1911 CI 0253 343 E A ZL1911 OP NOA NFC CL NOA CLOSED I A ZL1911 4 3 6 263 670 N A ZL1911 A A ZL2009 PRI COOLNT LTDN ISO VLV 2009 CI 0254 323 E A ZL2009 OP NOA NFC CL NOA CLOSED I A ZL2009 3 3 6 043 30 N A ZL2009 A A ZL2014 BORONOMTR & FAILED FUEL DET CI 0255 323 E A ZL2014 OP NOA NFC CL NOA CLOSED I A ZL2014 3 5 0 245 552 N A ZL2014 A A ZL2023 PURIFIER ION EXCH VLV 2023 CI 0256 323 E B ZL2023 OP NOA ION EXCH CL NOA BYPASS I A ZL2023 3 5 2 245 554 N A .ZL2023 A A ZL2056 VOL CNT/RADWASTE SYS v 2056 CI 0257 323 E B ZL2056 OP NOA RAD WST CL NOA VCT I A ZL2056 3 5 4 245 556 N A ZL2056 A A ZL2083 E A ZL2083 PCP BLEEDOFF ISO VALVE 2083 CI OP NOA NFC CL NOA CLOSED 0258 343 ,

I A ZL2083 3 4 0 044 32 i N A ZL2083 A A ZL2111 CHARGING LINE STOP _VLV 2111 CI 0259 323 E A ZL2111 OP NOA NFC CL NOA CLOSED I A ZL2111 3 5 6 245 558 N A ZL2111 A A ZL2113 LOOP .lA CHG LIN ISO VLV 2113 CI 0260 323 E A ZL2113 OP NOA NFC CL NOA CLOSED I A ZL2113 3 6 0 246 560 N A ZL2113 A A ZL2115 LOOP 2A CHG LIN ISO VLV 2115 CI 0261 323 E A ZL2115 OP NOA NFC CL NOA CLOSED I A ZL2115 3 6 2 246 562 N A ZL2115 A A ZL2117 AUX SPRAY STOP VALVE 2117 CI 0262 222 E A ZL2117 OP NOA NFC-. CL NOA CLOSED I A ZL2117 3 6 4 246 564 N A ZL2117 A A ZL2140 PCS MA.KEUP BYPASS VALVE 2140 CI 0364 324 E A ZL2140 OP NOA CLOSED CL NOA NFC I A ZL2140 3 .7 2 247 570 N A ZL2140 A A ZL2153 CONCENTRATED BA TO BLEND VLV CI 0365 324 E A ZL2153 OP NOA CLOSED CL NOA OPEN I A ZL2153 3 3 2 143 282 N A ZL2153 A B ZL2165 PCS MAKEUP TO BA BLEND VALVE CI 0264 E A ZL2165 OP NOA CLOSED CL NOA OPEN

. Description No. 578-ICE-1402 Rev 00 Page 44 of 47

I A ZL2165 - 3 4 2 044 34 N A ZL2165

• A A ZL3001 E A ZL3001 I A ZL3001 N A ZL3001 A A ZL3002 E A ZL3002 I A ZL3002.

CONTAINMENT SPRAY VALVE 3001 Cl OP NOA NFC 3

CONTAINMENT SPRAY VALVE 3002. CI OP NOA NFC CL NOA CLOSED 7 2 047 CL NOA CLOSED 0265 0266 58 594 342 342 3 12 2 252 N A ZL3002 A A ZL3007 HPSI TO LOOP lA S'I:P VLV 3007 CI 0366 3ll E A ZL3007 OP NOA OPEN CL NOA NFO I A ZL3007 4 11 2 071 202 N A ZL3007 A A ZL3008 I.PSI TO LOOP lA S'I:P VLV 3008 Cl 0367 3ll E A ZL3008 OP NOA OPEN CL NOA NFO I A ZL3008 4 11 4 071 204 N A ZL3008 A A ZL3009 HPSI TO LOOP lB S'I:P VLV 3009 Cl 0368 3ll i'

E A ZL3009 OP NOA OPEN

. , ,.CL NOAO"NFO 206 I I A ZL3009 I.

.L.L 6 I .L N A ZL3009 A A ZL3010 I.PSI TO LOOP lB STP VLV 3010 Cl 0369 322 E A ZL3010 OP NOA OPEN CL NOA NFO I A ZL3010 4 12 0 072 208 N A ZL3010 A A ZL3011 HPSI. TO LOOP 2A S'I:P VLV 3011 CI 0370 322 E A ZL3011 OP NOA OPEN CL NOA NFO I A ZI.3011 4 11 0 071 200 N A ZI.3011 A A ZI.3012 I.PSI TO LOOP 2A STP VLV 3012 Cl 0371 322 E A ZI.3012 OP NOA OPEN CL NOA NFO I A ZI.3012 4 10 6 270 710 N A ZL3012 A A ZI.3013 HPSI TO LOOP 2B S'I:P VLV 3013 Cl 0372 322 E A ZL3013 OP NOA OPEN CL NOA NFO I A ZL3013 4 12 2 072 210 ..

N A ZI.3013 A A ZL3014 I.PSI TO LOOP 2B S'I:P VLV 3014 Cl 0373 3%2 E A ZL3014 OP NOA OPEN CL NOA NFO I A ZL3014 4 11 2 271 714 N A ZI.3014 A A Z.L3015 SDC RTN FROM LOOP 2 VLV 3015 Cl 0267 326 E A ZL3015 OP NOA OPEN CL NOA NFO I A ZL3015 4 6 4 066 180 N A ZL3015 A A ZL3016 SDC RTN FROM LOOP 2 VLV 3016 Cl 0268 326 E A ZL3016 OP NOA OPEN CL NOA NFO I A ZL3016 3 2 6 242 534 N A ZL3016 A A ZL3018 SI TANK TEST STOP VLV 3018 CI 0269 321 E A ZL3018 OP NOA NFC CL NOA CLOSED I A ZL3018 3 7 4 047 60 N A ZL3018 A A ZL3029 HPSl-SIRW TK RECIRC VLV 3029 Cl 0270 321 E A ZL3029 OP NOA NFC CL NOA CLOSED n.:.a,.. .,.of .,.,of,..., 'f,... c;"70-T("'l:'-1 b.n? 'Q.,.u nn 'PIH!'P 45 of 47

I A ZL3029 . 3 12 4 252 596

• N A ZL3029 A A ZL3030 E A ZL3030 I A ZL3030 N A ZL3030 A A ZL3036 E A ZL3036.

HPSI-SIRW TK R.ECIRC VLV 3030 CI OP NOA NFC 3

OP NOA NFC CL NOA CLOSED 7 6 047 SI TANK TEST STOP VALVE 3036 CI CL NOA CLOSED 0271 0272 62 321 321 I A ZL3036 3 12 6 252 598 N A ZL3036 A A ZL3037 HPSI PMP P66A DCH TO BPS HDR CI 0273 321 E A ZL3037 OP NOA NFC CL NOA CLOSED I A ZL3037 3 13 0 253 600 N A ZL3037 A A ZL3055 SDC HX INLET STOP VALVE 3055 CI 0274 326 E A ZL3055 OP NOA NFC CL NOA CLOSED I A ZL3055 3 6 6 246 566 N A ZL3055 A A ZL3059 HPSI PMP B&C DCH TO HPSI HDR CI 0275 321 E A ZL3059 OP NOA NFC CL NOA CLOS ED I A ZL3059 ':I

..J 10 0 050 64 N A ZL3059 A A ZL3062 R.EDUN HPSI TO LOOP 2B V 3062 CI 0374 .322 E A ZL3062 OP NOA OPEN CL NOA NFO I A ZL3062 4 11 0 271 712 N A ZL3062 A A ZL3064 REDUN HPSI TO LOOP 2A V 3064 CI 0375 .322 E A ZL3064 OP NOA OPEN CL NOA NFO ~

I A ZL3064 4 13 0 273 728 N A ZL3064 A A ZL3066 R.EDUN HPSI TO LOOP lB V 3066 CI 0376 322 E A ZL3066 OP NOA OPEN CL NOA NFO I A ZL3066 4 11 4 271 716 N A ZL3Q66 A A ZL3068 REDUN HPSI TO LOOP lA V 3068 CI 0377 .322 E A ZL3068 OP NOA OPEN CL NOA NFO I A ZL3068 4 11 6 271 718 N A ZL3068 A A ZL3070 SDC-HPSI R.ECIRC VALVE 3070 CI 0276 326 E A ZL3070 OP NOA NFC CL NOA CLOSED I A ZL3070 3 10 2 050 66 N A ZL3070 A A ZL3071 SDC-HPSI R.ECIRC VALVE 3071 CI 0277 326 E A ZL307l OP NOA NFC CL NOA CLOSED I A ZL307l 3 13 2 253 602 N A ZL3071 A A ZL3072 CHG PMPS-HPSI XCONN VLV 3072 CI 0278 321 E A ZL3072 OP NOA OPEN CL NOA NFO I A ZL3072 4 7 0 267 696 N A ZL3072 A A ZL3212 SDC CLR B INLET STP VLV 3212 CI 0279 326 E A ZL3212 OP NOA NFC CL NOA CLOSED I A ZL3212 3 13 4 253 604

. N A ZL3212 A A ZL3213 SDC CLR B OTLET STP VLV 3213 CI 0280 326 E A ZL3213 OP NOA NFC CL NOA CLOS ED Description No. 578-ICE-1402 Rev 00 Page 46 of 47

APPENDIX D

• PROCEDURE FOR HUMAN FACTORS REVIEW OF PALISADES PLANT SAFETY PARAMETER DISPLAY SYSTEM

• MI0784-0021A-RE03

• PROCEDURE FOR HUMAN FACTORS REVIEW OF PALISADES PLANT SAFETY PARAMETER DISPLAY SYSTEM PROCEDURE NO A-RE-84-4-NPS-l Procedure Prepared by NPS EE Section Date Procedure Reviewed and Approved by NPS EE Section Head Date Procedure Reviewed and Approved by QA - NOD Date

• RP0484-0202B-NS06-TP04

Procedure No A-RE-84-4-NPS-l Page No 2 of 9 Revision No DRAFT Date 5/1/84 TABLE OF CONTENTS Item 1.0 PURPOSE 3 2.0 SCOPE 3

3.0 REFERENCES

3 3.1 SOURCE DOCUMENTS 3 3.2 REFERENCE DOCUMENTS 3 4.0 DEFINITIONS 4 4.1 SAFETY PARAMETER DISPLAY SYSTEM 4 4.2 DEFINITIONS TO SUPPORT GUIDELINES 4 5.0 RESPONSIBILITIES 4 5.1 SPDS PROJECT ENGINEER 4 5.2 SPDS PLANT ENGINEER 4 5.3 SPDS HUMAN FACTORS REVIEWER 4 6.0 PREREQUISITES 4 6.1 PRE-SPDS INSTALLATION REVIEW PREREQUISITES 4 6.2 POST-SPDS INSTALLATION REVIEW PREREQUISITES 5 7.0 PROCEDURE 5 7.1 PRE-SPDS INSTALLATION REVIEW PROCEDpRE 6 7.2 POST-SPDS INSTALLATION REVIEW PROCEDURE 7 8.0 ACCEPTANCE CRITERIA 8 9.0 REVIEW SIGN-OFF 9 ATTACHMENT A - DEFINITIONS OF TERMS USED IN ATTACHMENT B REVIEW GUIDELINES ATTACHMENT B - REVIEW GUIDELINES ATTACHMENT C - PRE-SPDS INSTALLATION REVIEW DOCUMENTATION.SHEETS ATTACHMENT D - POST-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS ATTACHMENT E - PROCEDURAL CHANGE LOG RP0484-0202B-NSOG-TP04

Procedure No A-RE-84-4-NPS-l Page No 3 of 9 Revision No DRAFT Date 5/l/84 PROCEDURE FOR HUMAN FACTORS REVIEW OF PALISADES PLANT SAFETY PARAMETER DISPLAY SYSTEM 1.0 PURPOSE This procedure provides review guidelines and requires that they be used to evaluate the design of the Palisades Plant Safety Parameter Display System (SPDS) for incorporation of accepted human factors principles.

The guidelines used in this procedure have been extracted from Chapters 5 and 6 of NUREG-0835.

2.0 SCOPE This procedure applies only to that portion of the Palisades Plant Critical Functions Monitoring System which has been designated as the SPDS. The guidelines provided by this procedure focus upon the appropri-ateness and accuracy of the data displayed by the SPDS, the techniques and format used in the visual data displays, the effectiveness and convenience of the SPDS location, and the proficiency of the operator in utilizing the SPDS.

3.0 REFERENCES

3.1 SOURCE DOCUMENTS

a. NRC NUREG-0835, "Human Factors Review Guidelines for the Safety Parameter Display System Final Report," September 19, 1983.

3.2 REFERENCE DOCUMENTS a; NRC Generic Letter No 82-33, "Supplement 1 to NUREG-0737 -

Requirements for Emergency Response Capability,"

December 17, 1982.

b. NRC NUREG-0700, "Guidelines for Control Room Design Reviews,"

September 1981.

c. Nuclear Plant Support Department Procedure NPS-10, "Design Document Review," Revision 0, November 8, 1982.

d. Nuclear Activities Department Procedure NAD-01, "Preparation and Control of Administrative Procedures," Revision 1, June 28, 1983.

e. Nuclear Activities Department Procedure NAD-11, "Design Control Measures for Technical Support Activities," Revision 0, December 6, 1982.

f. Nuclear Operations Department Standard NODS-P08, "Control of Minor Modification," Revision 5, January 16, 1984.

RP0484-0202B-NS06-TP04

Procedure No A-RE-84-4-NPS-l Page No 4 of 9 Revision No DRAFT Date 5/1/84 4.0 DEFINITIONS 4.1 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) - A concise display of critical parameters to the control room operators to. aid them in rapidly and reliably determining the status of critical safety functions. Such determination is made when assessing whether abnormal conditions warrant corrective actions by operators to avoid a degraded core.

4.2 DEFINITIONS TO SUPPORT GUIDELINES - Other definitions are provided in Attachment A to support the review guidelines provided in Attachment B.

5.0 .RESPONSIBILITIES 5.1 SPDS PROJECT ENGINEER - An indiv~dual within the Reactor Engineering Department assigned the responsibility of completing the SPDS conceptual and detailed designs. Some of the duties of this engineer are to prepare the design documents identified in I.tem 6 .1. 2.

5.2 SPDS PLANT ENGINEER - An individual within the Palisades Plant Technical Department assigned the responsibility of coordinating and overseeing the performance of any onsite activities related to the SPDS project.

5.3 SPDS Human Factors Reviewer - An individual within the Nuclear Plant Support Department assigned the overall responsibility of reviewing the SPDS design to determine whether or not the design conforms to accepted human factor principles. This individual is assisted by a Licensed Operator or Shift Technical Advisor ;rom the Plant Operations Department as noted in Attachment C and D.

6.0 PREREQUISITES 6.1 PRE-SPDS INSTALLATION PREREQUISITES 6.1.l The SPDS Project Engineer has requested the human factors review of the SPDS in writing via an Action Item Record.

AIR No SPDS Project Engr Date RP0484-0202B-NS06-TP04

Procedure No A-RE-84-4-NPS-l Page No 5 of 9 Revision No DRAFT Date 5/1/84 6.1.2 The SPDS Project Engineer has transmitted to the SPDS Human Factors Reviewer the following design documents via Document Transmittal Form 3142:

a. The SPDS Requirement~sew D:cument.

> *sr

r s.: )

.-C::- §- Q;a:: l ; ; ~

b. A written safety analysis describing the basis on which the selected parameters for SPDS display are sufficient to assess the safety status of the plant for a wide range of events which includes the symptoms of severe accidents.

c. The SPDS Facility Change Design Input Checklist.

d. The SPDS Facility Change Engineering Analysis Work Sheet.

e. The SPDS Facility Change Design Document Checklist and Design Documents (eg, applicable drawings, instruction manuals, etc).

SPDS Project Engr Date 6.2 POST-SPDS INSTALLATION PREREQUISITES 6.2.1 The SPDS is installed and is fully operational.

SPDS Project Engr Date 7.0 PROCEDURE NOTE 1:

The human factors review of the SPDS is to be accomplished in two phases.

The first phase consists of reviewing the SPDS design prior to SPDS installation yet after the conceptual and detailed designs are completed.

During this phase, review will be conducted utilizing those guidelines for which an evaluation of SPDS design conforinance to accepted human factors principles is valid without requiring the SPDS to be installed and operational. The second phase of the review will consist of conducting such design conformance evaluations where SPDS installation and operability are required to ensure validity of the evaluations *

• RP0484-0202B-NS06-TP04

Procedure No A-RE-84-4-NPS-l Page No 6 of 9 Revision No DRAFT Date 5/1/64 NOTE 2:

If during the following procedures it is determined by the Human Factors Reviewer that a change to the procedure must be made to facilitate the review and such a change does not alter the intent of the procedure, such change can be made by the Human Factors Reviewer provided that: (1) the-change is documented in Attachment E, and (2) the change is technically reviewed by a competent engineer and the technical review is documented by technical reviewer sign-off as indicated in Attachment E.

7.1 PRE-SPDS INSTALLATION REVIEW PROCEDURE

7. 1.1 The Human Factors Reviewer (HFR) .shall ensure that all Section 6.1 Pre-SP.DS Installation Prerequisites are ful-filled.

HFR Date 7 *. 1. 2 For each guideline identified in Columns 1 and 2 of Attach-ment C, the .following shall be* performed: .

a *. The HFR shall determine if the guideline is applicable to the SPDS design and, if so, the HFR and either a Licensed

• Plant Operator (LPO) or a Plant Shift Technical Advisor (STA) as identified in Column 5 shall compare the design to the guideline to determine whether or not the design conforms to the intent of the guideline. The HFR shall document the result of such determination by entering a check mark appropriately in Column No 3. Similarly, if it is determined that the guideline does not apply to the SPDS, the HFR shall enter a check mark appropriately in Column No 3. *

b. The HFR shall provide in Column No 4 a written justifica-tion as to why: (1) the SPDS design.conforms to the intent of the guideline, (2) the SPDS design does not conform to the intent of the guideline, or (3) the guideline does not apply to the SPDS design.

c. As indicated in Column No 5, the HFR and either an LPO or an STA shall document the completion of the guideline review by entering a signature and date.

HFR Date

• RP0484-0202B-NS06-TP04

Procedure No A-RE-84-4-NPS-l Page No 7 of 9 Revision No DRAFT Date 5/1/84 7~1.3 The HFR shall forward to the SPDS Project Engineer via Transmittal Form 3142 the completed Attachment C Review Documentation Sheets. Should a discrepancy or discrepancies exist where the SPDS design does not conform to the intent of an applicable guideline, the HFR shall request on the trans-mittal form that the SPDS Project Engineer resolve such discrepancy.

HFR *Date 7.1.4 If in Step 7.1.3 discrepancy resolution was requested and such resolution was formulated in detail and planned for implementation, the HFR may be requested in writing by the SPDS Project Engineer to perform a subsequent human factors.

review of SPDS design against the guideline(s) associated with the discrepancies. the HFR shall perform the subsequent review using the applicable Attachment C Document Review Sheets in accordance with the steps in Section 7.1.2 as they apply. The HFR shall then forward to the SPDS Project Engineer the completed Attachment C Document Review Sheets via Transmittal Form 3142 *

• 7.2 HFR POST-SPDS INSTALLATION REVIEW PROCEDURE 7.2.1 The Human Factors Revie~er (HFR) shall ensure that the Date Section 6.2 Post-SPDS Installation Prerequisites are ful-filled.

HFR Date 7.2.2 For each guideline identified in Columns No 1 and No 2 of Attachment D, the following shall be performed:

a. The HFR shall determine if the guideline is applicable to the SPDS design and, if so, the HFR and either a Licensed Plant Operator (LPO) or a Plant Shift Technical Advisor (STA) as identified in Column No 5 shall compare the design to the guideline to determine whether or not the design conforms to the intent of the guideline. The HFR shall document the results of such determination by entering a check mark appropriately in Column No 3.

Similarly, if it is determined that the guideline does not apply to the SPDS, the HFR shall enter a check mark appropriately in Column No 3.

RP0484-0202B-NS06-TP04

Procedure No A-RE-84-4-NPS-l Page No 8 of 9 Revision No DRAFT Date 5/1/84

b. The HFR shall provide in Column No 4 a written justifica-tion as to why: (1) the SPDS design conforms to the intent of the guideline, (2) the SPDS design does not conform to the intent of the guideline, or (3) the guideline does not apply to the SPDS design.

c. As indicated in Column No 5, the HFR and either an LPO or an STA shall document the completion of the guideline.

review by entering a signature and date.

HFR Date 7.2.3 The HFR shall forward to the SPDS Project Engineer via Transmittal Form 3142 the completed Attachment D Review Documentation Sheets. Should a discrepancy or discrepancies exist where the SPDS design does not conform to the intent of an applicable guideline, the HFR shall request on the trans-mittal form that the SPDS Project Engineer resolve such discrepancy.

HFR Date 7.2.4 If in Step 7.2.3 discrepancy resolution was requested and such resolution was formulated in detail and planned for implementation, the HFR may be requested in writing by the SPDS Project Engineer to perform a subsequent human factors review of the SPDS design against the guideline(s) associated with the discrepancy(ies.) The HFR shall perform the subse-quent review using the applicable Attachment D Document Review Sheets in accordance with the steps in Section 7.2.2 as they apply. The HFR shall then forward to the SPDS Project Engineer the completed Attachment D Document Review Sheets via Transmittal Form 3142.

HFR Date

. 8.0 ACCEPTANCE CRITERIA 8.1 This .procedure is considered complete and the SPDS design is considered as conf 9rming to accepted human factors principles when it has been shown and documented by this review that the SPDS design meets the intent of all applicable Attachment B guidelines.

RP0484-0202B-NS06-TP04

Procedure No A-RE-84-4-NPS-l Page No 9 of 9 Revision No DRAFT Date 5/1/84 9.0 REVIEW SIGN-OFF 9.1 The above acceptance criteria is satisfied.

HFR Date SPDS Project Engr Date RP0484-0202B-NS06-TP04

Procedure No A-RE-84-4-NPS-l Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS. INSTALLATION REVIEW DOCUMENTATION SHEETS RP0484-0202B-NS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 1 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Colullln No 2 Column No 3 Column No 4

• Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 5.1.11 Conciseness of Display HFR 5 .1. 21 Critical Plant Variables HFR Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 2 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 5.1.31 Status of Variables HFR 5.1.34 Failure Recognition HFR Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 3 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs

5. 1. 42 Abnormal Condi-tion .Alert Cues HFR Date 5.2.21 Continuous*

. Display HFR Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 4 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 5.4.11 Display Format HFR Date 6.1.1 Critical Functions HFR Date

• Refer to Attachment B for the specific guideiines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Sheet 5 of 17 Revision No DRAFT Procedure No A-RE-84-4-NPS-1 Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Cohpnn No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6.1. 2 Primary and Secondary HFR Date Displays LPO/STA Date 6.1. 3 Primary and Secondary HFR Date Displays

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly. identify which.Section 6 guideline is being addressed in.each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-1 Sheet 6 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to,Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6 .1.4 Primary and Secondary HFR Date Displays

6. 1. 5 Hierarchical Displays HFR

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs ~ave been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Sheet 7 of 17 Revision No DRAFT Procedure No A-RE-84-4-NPS-l Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No l Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6.1.6 Hierarchical Displays HFR Date 6.1. 7 Element

• Identification HFR

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 8 of 17 Revision No DRAFT Date .5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No l ColuJRn No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs

6. 1. 8 Trend Data HFR Date 6.1.10 Time History Data HFR Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 9 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No J Column No 4 Column No 5 SPDS Desigri Brief Conforms to

. NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6.2.1.l Informational Relationships HFR Date LPOf STA 6.2.1.2 Scaling HFR Date LPO/STA Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 10 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No l Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline* Yes No NA Regarding Conformance Review Sign-Offs 6.2.1.3 Scaling HFR Date LPO/STA 6.2.2 Parameter Identification HFR Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify .which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

• Procedure No A-RE-84-4-NPS-1 Sheet 11 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6.2.3 Perceptual Aids HFR Date 6.2.3.1 Color HFR

• Refer to Attachment B for the specifit guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6. guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

• Procedure No A-RE-84-4-NPS-l Sheet 12 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline

• Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6.2.3.2 Symbols and Mimics HFR Date 6.2.3.3 Overlays HFR Date LPO/STA Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 13 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6.2.3.4 Blinking and Flashing HFR Date 6.2.4.1 Association Between Dis- HFR Date play Pattern &

Plant Status

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE~84-4-NPS-l Sheet 14 of 17 Revision No DRAFT Date 5/l/84 ATTACHMENT C

~RE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column NQ l Column No 2 Column No 3 - Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justific-ation for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6.2.4.2 Display Pattern HFR Date Distortion 6.2.4.3 Displayed Parameter HFR Date Deviation

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 15 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6.2.4.4 Top Level Dis-play Pages HFR Date 6.2.5 Status Set Points HFR

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

• Procedure No A-RE-84-4-NPS-1 Sheet 16 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Colu!1lll No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 5.4.21 Pattern and Coding HFR Date Techniques 5.5.11 Primary Display Format HFR LPO/STA Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Sheet 17 of 17 Revision No DRAFT Date 5/1/84 ATTACHMENT C PRE-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design, Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 5.5.12 Display Format Selection HFR Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section '6 of the attached guidelines, -the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06-TP04

Procedure No A-RE-84-4-NPS-l Revision No DRAFT Date 5/1/84 ATTACHMENT D.

POST-SPDS INSTALLATION REVIEW DOCUMENTATION SHEETS RP0484-0202B-NS06-TP04

l Procedure No A-RE-84-4-NPS-1 Sheet 1 of 6 Revision No DRAFT Date 5/1/84 ATTACHMENT D POST-INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No l Colulllil N9 2 Column lqo 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes . No NA Regarding Conformance Review Sign-Offs 5.1.32. Display Responsiveness HFR LPO/STA Date 5 .1. 33 Display Validation HFR Date LPO/STA Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06

Sheet 2 of 6 Revision No DRAFT Procedure No A-RE-84-4-NPS-l Date 5/1/84 ATTACHMENT D POST-INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 5 .1. 35 Functional Qualification HFR Program LPO/STA 5.1.41 Displayed Magni-tudes *and Trends HFR

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which.Section 6 guideline is being addressed in each evaluation.

RP04840202BNS.06

• Procedure No A-RE-84-4-NPS-l Sheet 3 of 6 Revision No DRAFT Date 5/1/84 ATTACHMENT D POST-INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identif icatfon Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Desigri Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 5.2.11 SPDS Location HFR Date 5.2.12 SPDS Location HFR Date LPO/STA Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06

• Procedure No A-RE-84-4-NPS-l Sheet 4 of 6 Revision No DRAFT Date 5/1/84 ATTACHMENT D POST-INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 5.2.13 SPDS System In-terference With HFR Date Operators LPO/STA Date 5.3.11 Compensatory Measures HFR Date LPO/STA Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06

Procedure No A-RE-84-4-NPS-l Sheet 5 of 6 Revision No DRAFT Date 5/1/84 ATTACHMENT D POST-INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline

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Column No l Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Descr'iption of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 5.3.12 Staffing HFR Date LPO/STA Date 5.4.22 SPDS Readability HFR Date LPO/STA Date

• Refer to Attachment B for *the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06

Procedure No A-RE-84-4-NPS-l Sheet 6 of 6 Revision No DRAFT Date 5/1/84 ATTACHMENT D POST-INSTALLATION REVIEW DOCUMENTATION SHEETS Guideline Identification Review of SPDS Design to Guideline Column No 1 Column No 2 Column No 3 Column No 4 Column No 5 SPDS Design Brief Conforms to NUREG-0835 Description of Guideline? Justification for Conclusion Guideline No* Guideline Yes No NA Regarding Conformance Review Sign-Offs 6.1. 9 Trend Date HFR Date 6.2.1.4 Scaling Factors HFR Date LPO/STA Date

• Refer to Attachment B for the specific guidelines.

NOTE: In Section 6 of the attached guidelines, the individual paragraphs have been numbered for purposes of this procedure to more clearly identify which Section 6 guideline is being addressed in each evaluation.

RP04840202BNS06

Procedure No A-RE-84-4-NPS-l Revision No DRAFT Date 5/1/84 ATTACHMENT E PROCEDURAL CHANGE LOG SiS!!-Offs Change Technical Number Change Description HFR/Date Reviewer/Date

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RP0484-0202B-NS06-TP04 l