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IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared for Wisconsin Public Service Corporation Prepared by EIGEN Engineering, Inc. San Jose, CA Reviewed by: A; I Ken V. Allen, P.E. Project Engineer "Joseph D. Doyel, O.E. Project Manager 8909060304 890901. PDR ADOCK 05000305 P PDC 3150 ALMADEN EXPRESSWAY. SUITE 233 * SAN JOSE, CALIFORNIA 95118 * (408) 978-8113 Allm-11

Transcript of Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR...

Page 1: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

IGEN NGINEERING, INC

KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT

WPS-1000-88-010, Rev. 1

October 6, 1988

Prepared for

Wisconsin Public Service Corporation

Prepared by

EIGEN Engineering, Inc. San Jose, CA

Reviewed by:

A; I

Ken V. Allen, P.E. Project Engineer

"Joseph D. Doyel, O.E. Project Manager

8909060304 890901. PDR ADOCK 05000305 P PDC

3150 ALMADEN EXPRESSWAY. SUITE 233 * SAN JOSE, CALIFORNIA 95118 * (408) 978-8113

Allm-11

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TABLE OF CONTENTS

1.0 INTRODUCTION . . . . . .* * * *

1.1 Purpose . . * * * * * 1.2 Design Review Methodology

2.0 CONCLUSIONS . . . . * *.***

3.0 SUMMARY OF REQUIREMENTS REVIEW

3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 3.10 3.11 3.12

* * * * * . ... 1

* . , . . . . .

* S 0 0 0 S * S

1 2

* * * * * * * . . 4

. . . . . . . . &

Display Content and Format * * Data Scan Intervals . . . * * * Scale Optimization * * * * Data Validation . * * . * SPDS Operability . * * * * Electrical Isolation . . . * * . Configuration Control . . . . . Reliability . . . . . . . . . . Location . * * * * * * .Procedures and Training . Human Factors . . . . .. System Operation and Maintenance

4.0 REFERENCES . . . . . . . . . . . . .

APPENDIX

APPENDIX

APPENDIX

APPENDIX

1

. . . . S . .

6

6 23 27 38 44 46 48 50 51 56 59 61

63

- Reference Documents

- Discrepancies

3

4

EIGEN ENGINEERING, INC.

- Instructions for the Verification of SPDS Composed Points

- Verification of SAS Documentation Checklists

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1.0 INTRODUCTION

1.1 Purpose

The Safety Parameter Display System (SPDS) is one of several emergency response facilities called for in NUREG 0696. NUREG 0737 specifies SPDS as a requirement for all operating nuclear power plants. NSAC 39 requires an independent Verification and Validation program as part of the implementation of the SPDS. The Kewaunee Nuclear Power Plant SPDS Verification and Validation Program Plan (Ref 4.1) describes a V&V program which addresses System Requirements, Design Review, Performance Validation, and Field Verification of the Kewaunee SPDS.

The purpose of this report is to document the results of the Design Review phase of the V&V program.

System Requirements have been identified and are included in the V&V Plan. Performance Validation and Field Verification will be accomplished during simulator Dynamic Testing and the Field Installation Audit.

Typically, the V&V of a computer system is an integral part of the specification, design, and installation phases of the project. This approach generally minimizes the impact of problem resolution since problems can be identified and corrected prior to the implementation of the system.

The Kewaunee SPDS is a plant-specific derivation of a generic PWR Safety Assessment System (SAS) provided to several operating PWRs. The generic SAS was modified by Wisconsin Public Service to; operate on the Honeywell 45000 plant process computer, and reconfigure the four loop generic design to a two loop plant specific design.

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The NRC post implementation audit report of January 1987 (Ref. 4.2) identified several areas of concern and concluded that the system did not meet the requirements of NUREG-0737, Supplement 1 (Ref. 4.3).

In January, 1988, Eigen Engineering was contracted to perform a Verification and Validation program on the Kewaunee SPDS.

Since the system was already installed and operational, and consisted of hardware and software components from suppliers having extensive industry experience, no attempt was made to validate the basic design of the system. Instead, the V&V program was concentrated on evaluating how well the final system configuration and performance met the system requirements.

1.2 Design Review Methodology

The objective of the design review was to ascertain that the implementation of system requirements into hardware and software is complete and without ambiguity.

As described in the V&V Program Plan, the design review began with identification of the task(s) necessary to evaluate the system with respect to each requirement, and a description of the documentation necessary to perform each evaluation.

A documentation related deficiency was encountered when the V&V team attempted to confirm actual data manipulation techniques such as engineering unit conversions and data validation algorithms.

Since no formal documentation was available to document how

each displayed variable was generated from raw input data and

how these variables would behave under different input

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conditions, Eigen Engineering obtained the SAS computer code listings and developed documentation, which identified;

- actual calculations performed on raw data to generate all displayed variables.

- logic governing the behavior of each display feature on the CRT screen (i.e. - alarm limits).

- all constants, and alarm limits used in display development.

This documentation was included in the Kewaunee SPDS Design Document Package (Ref. 4.4) which constitutes the complete basis for the V&V team's verification of all data manipulation and validation techniques employed by the Kewaunee SPDS. Attachment 1 to this report identifies all Kewaunee SPDS documents used during the review process.

Many of the attributes specified by the various requirements of the V&V program were reviewed at the same time. In order to consistently review these attributes, a checklist and a set of instructions was developed. The instructions are included in Attachment 3 and copies of the checklists are included in Attachment 4.

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2.0 CONCLUSIONS

During the course of the design review, the V&V team identified a total of 94 discrepancies (see Appendix 2).

Based on additional documentation received from WPS, 74 of these have been resolved and closed.

Of the remaining 20 discrepancies, most can be resolved by making minor revisions to existing system software or plant documentation.

The major system deficiencies appear to be

- lack of documentation verifying human factors evaluation of the plant specific modifications to the generic SAS. (discrepancy #14)

- lack of documentation demonstrating a high level of system reliability. (discrepancy #13)

- lack of data validation as defined in the Design Document Package. (discrepancy #46)

- two parameters (Intermediate Range and Source Range start up rate) were identified as providing the status of critical safety functions. Sensors providing this information are not currently connected to the system. (discrepancies 11 and #15)

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In general, the V&V team feels that the basic.concept of the Kewaunee SPDS is adequate and that with some additional effort the system will satisfy the requirements of Supplement 1 to NUREG 0737.

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3.0 SUMMARY OF REQUIREMENTS REVIEW

3.1 Display Content and Format

3.1.1 Requirement: This SPDS should -provide a predetermined minimum set of critical plant variables to help the control room operators evaluate plant safety. (NUREG 0800, Section 5.1.2.1)

A. Verification Task(s): Review Kewaunee Nuclear Power Plant (KNPP) Safety Analysis Report for Safety Parameter Display System (SPDS) and WPS letters providing additional information for the selection of the SPDS variable set.

Review SPDS design document package for the proper implementation of the variables.

B. Summary: Selection of the minimum SPDS parameter set was based on the parameters used to demonstrate the generic Safety Assessment System (SAS) at the Indian Point Unit 2 Nuclear Plant Simulator. The generic four loop parameter set was modified to a two loop configuration for Kewaunee and additional parameters (Hot Leg Temperatures, Auxiliary Feedwater Flow and Charging minus Letdown Flow) were added to the top level displays.

The Kewaunee parameter selection is discussed in detail in Section 3.1.2.

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C. Verification Reference(s):

SPDS Design Document Package (Ref. 211), Section 6.0.

Safety Analysis Report, (Ref. 11)

Letter (NRC-84-123) from D. C. Hintz to D. G. Eisenhut (Ref. 12)

Letter (NRC-85-84) from D. C. Hintz to D. G. Eisenhut (Ref. 210)

Quadrex Functional Design Specification, (Ref. 8) page IV-23 and Appendix A.

Lesson Plan T-STA-SP 2.13.4, (Ref. 218) Section IV, Handout #6 thru 12.

Letter (SASLOG-118) from J. B. Moritz (Quadrex) to SAS Distribution. (Ref. 74)

Video copies of Kewaunee displays dated Sept. 22, 1986 (Ref. 202)

D. Conclusion:

The SPDS parameter set satisfactorily meets the requirement of a predetermined minimum set of critical plant parameters.

This item is considered closed.

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3.1.2 Requirement: The minimum information to be provided should be sufficient to provide information to the plant operators about: reactivity control, reactor core cooling and heat removal, coolant system -integrity, radioactivity control, and containment conditions. (NUREG 0800, Section 5.5)

A. Verification Task(s): Verify that the SPDS critical parameters envelope / address the required Critical Safety Functions (CSF) and associated control functions have been included in the identification of the SPDS variable set. Review the resulting display formats to ensure that the minimum required information is displayed. Also review the method used to provide access to the above minimum information.

B. Summary: WPS letter NRC-84-123 provides a discussion of the parameters selected to monitor each of the Critical Safety Functions (CSF). The SPDS design document package presents the following safety function correlation:

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SAS CRITICAL SAFETY FUNCTIONS AND ASSOCIATEDMONITORED AND DISPLAYED PARAMETERS

CRITICAL SAFETY FUNCTION

Reactivity Control

Core Cooling & Primary System Heat Removal

Coolant System Integrity

DISPLAYED PARAMETER

Rx Power (SRIR,PR)

Rx Trip Status

Rx Vessel Level/Void Fraction

Przr Level Core Exit Temp. Cold Leg Temp. Rx Coolant Avg Temp.

*Rx Coolant Pump Status Subcooling

S/G Level S/G Pressure Aux. FW Flow S/G Steam Flow RHR System Flow RHR HX Inlet Temp.

RHR HX Outlet Temp.

Rx Coolant Sys Press.

Rx Coolant Avg Temp.

Cold Leg Temp. Rx Vessel Level Przr Level Cntmt Rad. Cntmt Press. Cntmt Sump Level S/G Blowdown Rad.

Condenser Air Ejector Rad.

MONITORED PARAMETER

(SR, IR & PR Monitor)

Rx Trip Status

Rx Vessel Level/ RCP Status Przr Level Core Exit Temp. Cold Leg Temp. Hot Leg Temp. & Cold Leg Temp.

*Rx Coolant Loop Flow

Core Exit Temp. & Coolant Press. S/G Level S/G Pressure Aux. FW Flow S/G Steam Flow RHR System Flow RHR HX Inlet Temp. RHR HX Outlet Temp.

Rx Coolant Loop Press & Pressurizer Press. Cold Leg Temp. & Hot Leg Temp.

Cold Leg Temp. Rx Vessel Level Przr Level Cntmt Rad. Cntmt Press. Cntmt Sump Level S/G Blowdown Rad.

Condenser Air Ejector Rad.

*indirectly indicated

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SAS CRITICAL SAFETY FUNCTIONS AND ASSOCIATEDMONITORED AND DISPLAYED PARAMETERS

CRITICAL SAFETY FUNCTION

Containment Conditions

Radioactivity Control

DISPLAYED PARAMETER

Cntmt Pressure Cntmt Sump Level Cntmt Radiation

Aux Bldg Vent Stack Rad Cntmt Radiation S/G Blowdown Rad.

Cond Air Ejector Rad.

MONITORED PARAMETER

Cntmt Pressure Cntmt Sump Level Cntmt Radiation

Aux Bldg Vent Stack Rad

Cntmt Radiation S/G Blowdown Rad. Cond Air Ejector Rad.

As described in the Design Document Package, the SPDS

will display either Reactor Vessel Level or Void

Fraction depending on Reactor Coolant Pump Status

(running or stopped). The parameter displayed (Level or Void Fraction) is therefore the method by which Coolant Pump status is indicated.

The KNPP Integrated Plant Emergency Operating Procedures (F-series) provide flow diagrams to direct operator

response to CSF alarms (except radioactivity control).

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211),

Section 6.0

Letter (NRC-84-123) from D.C. Hintz to D.G.

Eisenhut (Ref. 12)

Letter (NRC-85-84) from D. C. Hintz to D. G.

Eisenhut (Ref. 210)

Lesson Plan T-SLA-LP 2.13.4, (Ref. 218),

Section III, Handout #3.

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D. Conclusion: The parameters necessary to provide the necessary information about each critical safety function are available in

the SPDS.

3.1.3 Requirement: The display should contain the minimum set of indicators and data needed to assess the plant functions that are used to determine the plant's safety status. (NUREG 0800, Section 5.5.1.2)

A. Verification Task(s): Review KNPP IPEOP's to ensure that CSF EOP decision points are supported by the display features.

B. Summary: Discrepancy #11 results from CSF. EOP F-0.1 which requires a decision based on Intermediate Range startup rate below -0.2 DPM. This is a "Future" input and i's not connected at this time.

Discrepancy #15 results from CSF EOP F-0.1 which requires a decision based on source range startup rate. This parameter is not part of the SPDS parameter set.

Discrepancy #9 results from CSF EOP F-0.2 which requires a decision based on core subcooling being above or below 120 0F. The display range on both trend graphs showing this parameter is from 100oF subcooling to

50oF superheat.

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Discrepancy #8 results from CSF EOP F-0.2 which requires a decision based on a core exit temperature of 700 0 F. The Design Document Package shows the core exit thermocouples process range as -100 to

+100 0 F. This range is inadequate to support the EOP.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211), Section 6.0.

Safety Analysis Report, (Ref. 11)

Letter (NRC-84-123) from D. C. Hintz to D. G. Eisenhut (Ref. 12)

Letter (NRC-85-84) from D. C. Hintz to D. G. Eisenhut (Ref. 210)

Quadrex Functional Design Specification,

(Ref. 8) page IV-23 and Appendix A. Lesson Plan T-STA-SP 2.13.4, (Ref. 218)

Section IV, Handout #6 thru 12. Letter (SASLOG-118) from J. B. Moritz

(Quadrex) to SAS Distribution. (Ref. 74) Video copies of Kewaunee displays (Ref. 202)

D. Conclusion: This item is open pending

resolution of discrepancies 8, 9, 11 and 15.

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3.1.4 Requirement: The SPDS Oser is made aware of

important changes in critical safety related

variables when they occur. (NUREG 0800, Section

5.2.2.1)

A. Verification Task(s): Review SPDS

documentation for the operational

description of alarm capabilities, and the

method(s) used to alert users when

parameters have reached alarm limits.

B. Summary: The SPDS Design Document Package

describes the various alarm methods used for

bar graphs, numerical values and target

fills used on the top level displays and

associated trend graphs.

The SPDS consistently implements the color

red to indicate an alarm condition. On top

level displays, a red bar graph, target

fill, or box around a parameter value

indicates an alarm condition.

On 2nd level trend graphs, the displayed

numerical value of the alarming parameter

will turn red. The associated bar graph and

trend plot will remain unchanged.

Discrepancy #5 is used to document that

display alarms are controlled from two

different setpoint inputs. The Top level

display bar graph fill color is controlled

by setpoint values contained in the

Chromatics computer. Trend graph numerical

value color changes are controlled by

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setpoint values contained in the Honeywell computer. In most cases there are minor differences between the alarm values for the same parameter. This could result in ambiguous alarm indication for parameters displayed on both top level and 2nd level displays.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211). AIDS Executive SAS Software Module

(Ref. 134, page 6). SAS setpoint values (Ref. 140). Top Level.P Chrom Software Module

(Ref. 147, page 7).

D. Conclusion: This item will remain Open until discrepancy #5 is resolved.

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3.1.5 Requirement: For each plant modemof operation,

the display formats may either be automatically

displayed or manually selected. (NUREG 0800,

Section 5.5.1.2)

A. Verification Task(s): Verify that the

display screens can be used to track the

mode of plant operation.

B. Summary: The SPDS Design Document Package

discusses the following top level displays

which are manually selected to cover all

modes of plant operation:

1. Normal

2. Heatup/Cooldown

3. Cold Shutdown

The message area of the 2nd level trend

graphs also shows the operating mode based

on the most recent top level display

selected at the Chromatics console. The

trend graph mode indication will not change

until a different top level display is

selected at the console.

C. Verification Reference(s):

Lesson Plan T-SLA-LP 2.13.4, (Ref. 10), Section IV, Handout #2.

Quadrex Functional Specification, (Ref. 8)

page IV-2.

SPDS Design Document Package, (Ref. 211)

Section 4.1, 4.2 and 4.3.

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D. Conclusion: The manual selection of plant mode used by Kewaunee meets this requirement.

This item is considered closed.

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3.1.6 Requirement: The variables associated with each critical safety function should also be available for display and operator assessment (NUREG 0800, Section 5.0)

A. Verification Task(s): Verify that the entire SPDS parameter/variable set is available to the operator at all times.

B. Summary: The SPDS Design Document package contains a complete set of drawings for each computer point shown on the SPDS display screens. These drawings depict all of the information used to develop that point for display.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211), Appendix B.

D. Conclusion: The operator has access to the SPDS variables at various locations within the control room and on process computer displays, which would allow assessment of any questionable variable. This review item is closed.

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3.1.7 Requirement: There should be provisions in the display to indicate to the control room operator that a change in the mode of plant operation has occurred (NUREG 0800, Section 5.5.1.2)

A. Verification Task(s): Review displays to verify that plant modes are indicated.

B. Summary: The top level and 2nd level displays indicate the plant mode for Normal Operation, Heatup/Cooldown and Cold Shutdown conditions, based on the most recent selection of the top level display at each Chromatics console.

C. Verification Reference(s):

Video copies of Kewaunee displays (Ref.

202).

Lesson plan T-STA-LP 2.13.4, (Ref. 218),

Section IV.

SPDS Design Document Package (Ref. 211),

Section 3.5.

Quadrex Functional Specification, (Ref. 8),

pages IV-2 and IV-3.

D. Conclusion: This item is closed.

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3.1.8 Requirement: The display should be responsive to transient and accident sequences including symptoms of severe accidents. (NUREG 0800, Section 5.1.3.2)

A. Verification Tasks: Review FSAR Chapter 14 to assure that display data throughput and range are adequate for the transient times and ranges given in the FSAR.

Perform an SPDS "walk through" for simulator scenarios (Approx 3) to ensure that display data for the SPDS parameters aid the operator in responding to the transient being simulated.

B. A review of the FSAR shows three transient times of <10 seconds with a majority of the transients at 60 to over 1000 seconds under a variety of accident conditions. Each transient curve also defines a maximum value for that associated parameter.

The initial display callup time is approximately 4 seconds with updates approximately every 12 seconds. The 2nd level trend graphs display the previous 30 minutes of data with each point representing the average of 6 seconds of data.

With the exception of the Pressurizer Pressure, Nuclear Power and Delta T Average, transients (FSAR Figures 14.1-6 and 14.1-7) the 2nd level trend graphs will allow the operators to obtain information to aid in

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responding to the transient conditions. Due to the 12 second update time, it is possible for fast transient parameters to complete a transient between SPDS updates.

The "walk-through" verification will be conducted during the dynamic testing at the simulator.

C. Verification References: SPDS Design Document Package (Ref. 211),

Section 2.1, 4.4 and Appendix B. Kewaunee FSAR Chapter 14 (Ref. 212)

D. Conclusion: The faster transients (i.e.<l0 sec) could be over before the operators are aware of them. The update rate of the top level displays is not responsive to fast transient type data, however the trend graphs could give information to aid operators in responding to plant conditions.

This item remains open pending completion of the simulator walkthrough scenarios.

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3.2 Data Scan Intervals

3.2.1 Requirement: The displayed data should represent the current status of critical plant variables (NUREG 0800, Section 5.1.3.1)

A. Verification Task(s): Review documentation to identify the available scan interval capabilities of the system. Review the assigned scan (i.e. update) interval specified for each SPDS point, including intermediate calculational results, for reasonable application of the system capabilities with expected operator needs.

B. Summary: The Honeywell manual (5100293, Section 3) identifies the fastest available scan rate as once per second, with longer intervals extending into minutes.

The point drawings contained in the SPDS Design Document Package include the various scan rates for sensor inputs and the Honeywell intermediate points used to develop the information displayed on the SPDS screens.

As part of the overall V&V methodology for algorithm verification, both scan intervals and the computational order of computed values were reviewed. In general, all of the SPDS scan rate intervals are acceptable. Most points were in the 1 and 5 sec range with temperatures within the 15 to 60 second range. Some points indicate that they are

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scanned on demand (DMD) which can vary from 5 seconds to 60 seconds. Digital points are scanned every 0.25 seconds.

The Top level displays are updated approximately every 12 seconds and on the trend graphs each point is the average of 6 seconds of data.

C. Verification Reference(s): SPDS Design Document Package (Ref. 211),

Appendix B.

D. Conclusion: As discussed in section 3.1.8, the display update rate of 12 seconds appears to be restrictive for displaying current status under fast changing conditions.

The data scan rates for the individual points were acceptable.

This item will be reviewed during the dynamic testing to determine if the long display update rate is discernable to the operators.

This item will remain open until dynamic testing is completed, and discrepancy 94 is resolved.

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3.2.2 Requirement: The time -delay from when the sensor signal is sampled to when it is displayed should be consistent with other control room displays (NUREG 0800, Section 5.1.3.1)

A. Verification Task(s): Verify that the actual system performance is consistent with the design relative to CRT update interval.

B. Summary: The SPDS display information is processed by the same Honeywell process computer that controls the data shown on the other control room computer displays. The time delay for all displays, both SPDS and others, is consistent.

C. Verification Reference(s): Honeywell Block Diagram (Ref. 77).

D. Conclusion: Since the Honeywell computer process control display data for both the SPDS and other display CRT's, the time delay of data shown on both SPDS and other displays is consistent.

This review item is closed.

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3.2.3 Requirement: The sampling rate for each critical plant variable is such that there is no meaningful loss of the data presented to the operator (NUREG 0800, Section 5.1.3.1)

A. Verification Task(s): None

B. Summary: None.

C. Verification Reference(s): None.

D. Conclusion: This requirement is satisfactorily addressed in the preceding two sections and is therefore considered closed.

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3.3 Scale Optimization

3.3.1 Requirement: Each critical plant variable is

displayed with an accuracy sufficient for the control room operator to discriminate between conditions that impact the plant's safety status and normal operating conditions (NUREG 0800, Section 5.1.3.1)

A. Verification Task(s): Review all alarm limits for reasonableness with respect to the span of the point to be monitored.

B. Summary: The point drawings contained in the SPDS Design Document Package were

reviewed for all values or digital logic states used as a basis for an alarm

threshold.

The Top level bar graphs do not show a vertical scale, they only display limit

lines and a numerical value for each

parameter beneath its bar graph.

Discrepancy #6 resulted because the

instrumented range for Containment Pressure is -5 to 200 psig and the alarm setpoint is 1.0 psig. The ability to accurately

distinguish between normal and abnormal

conditions is inadequate.

Discrepancy #7 documents that the

Pressurizer level input is only from a wide

range sensor (0 - 100%). The SAS program

attempts to select between wide range and

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narrow range based on RCS temperature conditions, but will only be able to display wide level under all conditions.

Discrepancy #93 resulted from the SAS displays indicating 0-150 gpm for inputs of 0-100 and 0-110 gpm respectively.

C. Verification Reference(s):

SPDS Design Document Package, Appendix B (Ref. 211).

SAS setpoint values (Ref. 140) Chromatics Code Listing TOPLEVEL.P (Ref. 147).

D. Conclusion: Since the Top level bar graphs displays setpoint limit lines, these will aid the operator to see if a variable is approaching its alarm condition. The trend graphs can also be used by the operator to monitor variables of interest over a period of time to determine their changes.

This item will remain open until the discrepancies 6, 7 and 92 are resolved.

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3.3.2 Requirement: The displays should be capable of presenting magnitudes and trends of critical plant variables or derived parameters (NUREG 0800, Section 5.1.4.1)

A. Verification Task(s): Review the SPDS Design Document Package to determine

trending capabilities of the Chromatics Consoles. Review the critical parameter trend graphs to ensure that when associated CSF EOPs require that a variable be "maintained" relative to a specified value that the trending will support this

requirement.

Review the trending implementations for adequate scaling and resolution relative to CSF EOP demands.

B. Summary: The 2nd level trend graphs are

organized in the following functional

groupings.

GROUP NAME LABEL CONTENTS (TREND PARAMETERS)

Nuclear Instr. Power Range Power Intermediate Range Power Source Range Power

Contain LPR Containment Sump Level Containment Pressure Containment Radiation

RCS Reactor Coolant System (RCS) Pres Pressurizer Level Core Exit Temperature Subcooling

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GROUP NAME LABEL RCS TEMP WR

Containment HHT

RCS TEMP NR (NOTE: NR is just the WR with an expanded scale for easier reading)

Core Cooling

S/G Press

S/G NR Levels

S/G Feed &-Steam Flows

AFW Flows

Tank Levels

CONTENTS (TREND PARAMETERS) RCS Loop A Hot Leg Temperatures RCS Loop A Cold Leg Temperatures RCS Loop B Hot Leg Temperatures RCS Loop B Cold Leg Temperatures

Link Update Rate Humidity (Future) Temp (Future)

RCS Loop A Hot Leg Temperatures RCS Loop A Cold Let Temperatures RCS Loop B Hot Leg Temperatures RCS Loop B Cold Leg Temperatures

Reactor Vessel Level Core Exit Temperature Subcooling

Steam Generator A Pressure Steam Generator B Pressure

Steam Generator A Level Steam Generator B Level

Steam Generator A-FF Steam Generator A-SF Steam Generator B-FF Steam Generator B-SF

Auxiliary Feedwater Flow to S/G A Auxiliary Feedwater Flow to S/G B

Containment Sump Level RWSW (Future) Condensate Storage Tank (Future)

Radiation Monitors Containment Radiation Air Ejector Radiation Steam Generator Blowdown Stack Effluent Radiation

Radiation

RCS P VS. T

Charging Letdown

EIGEN ENGINEERING, INC.

RCS Pressure VS. RCS Average Temp

Charging Flow Letdown Flow

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The COLD SHUTDOWN top level display contains the following trend graph groupings;

SOURCE RANGE Source Range N31 output Source Range N32 output

RHR RHR flow RHR Hx Inlet Temperature RHR Hx Outlet Temperature

RCS RCS Pressure Core Exit Temperature Rx Cavity Level

C. Verification Reference(s): Lesson Plan T-SLA-LP 2.13.4, (Ref. 218) page

10 item IV.4.6, page 12 item IV.B.9 and Handout #3.

Video copies of Kewaunee displays (Ref. 202).

Quadrex Functional Specification, (Ref. 8) page IV-9 section E.

SPDS Design Document Package (Ref. 211), Section 4.4.

CSF EOP Procedures (Ref. 23 thru 28).

D. Conclusion: The trend graphs meet the requirement of presenting magitudes and trends of critical plant parameters.

This item is considered closed.

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3.3.3 Requirement: Trend data are displayed with sufficient resolution in time and magnitude to ensure that rapidly changing variables are accurately displayed. (NUREG 0800, Section 5.1.4.1)

A. Verification Task(s): Review SPDS Design Document Package to ensure that trend graphs are implemented for critical parameters. Review the trend graphs for adequate scaling and resolution relative to CSF EOP demands.

B. Summary: The cold shutdown Top level display contains trend graph that show the previous 2 hours of data for selected parameters.

The 2nd level displays all consist of trend graphs arranged by related parameters, except the RCS pressure and temperature envelope graph (DSP018). The trend graphs display the previous 30 minutes of data in 6 second increments for the variables contained on each trend graph as described in Section 3.3.2.

The trend graphs vertical scale for each variable is determined by the bar graph range for that variable shown on the same trend graph.

Discrepancy #2 was written because it can not be determined if the sensors being monitored for S/G Level (ANLO18 and ANLO14) are indeed "Narrow Range" measurements as

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indicated on trend graph (DSP017). The range shown on all documents is 0-100% which would indicate a full range measurement for

these parameters.

Discrepancy #3 resulted from an engineering unit difference for S/G Feedwater Flows (ANLO26 and 027), CSF EOP F-0.3 requires readings in gpm, and the trend graph (DSP006) displays units of lbs/hr(106 ),

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211), Sections 4.3 and 4.4 and Appendix B.

CSF Procedures (Ref. 23 and 28).

D. Conclusion: The time axis is satisfactory for the intended purpose of tracking "increasing" and "decreasing" parameters as required to follow EOP conditions.

This item will remain open until the discrepancies 2 and 3 are resolved.

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3.3.4 Requirement: Where graphic representations of variables are used, scaling should be chosen to. allow tracking of variables over a wide range of abnormal conditions. Therefore, displays for normal conditions should not fill the entire display area (NUREG 0800, Section 6.2.1)

A. Verification Task(s): Review CSF EOP and Reg. Guide 1.97 control ranges against the scales used in displays.

B. Summary: SPDS scaling meets the abnormal range conditions given in Regulatory Guide 1.97 with the exceptions of Core Exit Temp, Subcooling Margin', Containment Radiation, Hot Leg Temp, Cold Leg Temp Containment Temperature and RCS Pressure.

Except as noted earlier (Discrepancies 8, 9, 11 and 15) SPDS scaling is adequate with respect to the requirements of the CSF EOPs.

Discrepancy #10 resulted because the trend graph full scale range for RCS Pressure is 2500 psig. FSAR Figure 14.1-34, shows a range for this parameter in excess of 2700 psig. The existing range does not allow trending of data during abnormal conditions above 2500 psig.

C. Verification Reference(s):

Regulatory Guide 1.97, Rev. 2, December 1980 SPDS Design Document Package (Ref. 211),

Appendix B.

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D. Conclusion: The vertical axis scaling for trend graphs is generally satisfactory except as noted in Discrepancies 8, 9, 10, 11 and 15.

This item will remain open until discrepancies 8, 9, 10, 11 and 15 are resolved.

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3.3.5 Requirement: The SPDS should alert the control operator when a graphically represented variable is off scale. (NUREG 0800, Section 6.2.1)

A. Verification Task(s): Review SPDS Design Documentation Package to identify the capabilities available to inform the operator when a displayed point is off scale. Review the lesson plan to ensure that the operators are trained to recognize the implemented techniques.

B. Summary: The SAS SPDS screens will display "NORMAL" data as a white numerical value on the Top levels and trend graphs. For those points using multiple inputs to measure the same parameter, at least two of the multiple inputs must be within range for the numerical value to remain in Normal data condition. If only one input from the multiple group is within range, or if any point is more than 10% above or below the average value, an Alert condition is indicated by showing the numerical value of the data in yellow. For any point which has all inputs out of range, the word "FAIL" will appear in yellow in place of the numerical value..

The SPDS lesson plan also covers the material and explains the various conditions of data being presented.

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"Future" points which are not connected at this time show as "FAILO on their displays

at all times.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211),

Section 5.0.

Lesson Plan (Ref. 218), Section V and

handout #5.

D. Conclusion: The various methods of

informing the operator of failed or

questionable inputs is adequate to satisfy

the requirement.

This item is considered closed.

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3.4 Data Validation

3.4.1 Requirement: The displayed data should be validated on a "real timeu basis where practical (NUREG 0800, Section 5.1.3.3)

A. Verification Task(s): Review SPDS Design Document Package to verify that the SAS data validation techniques are implemented. Review the SPDS lesson plan for the inclusion of the data validation techniques implemented and for a discussion as to how an operator becomes aware that a point is invalid.

B. Summary: The Honeywell SEER program performs a High-Low limit test of all incoming sensors prior to passing data on to the SAS program.

All points processed by the SEER program including those for which SEER performs calculations (i.e. composed points), contain a data status flag in the data string received by the SAS program. For those inputs whose data flag is set for "novalue", the SAS program will not perform validation checks and will display the data as "FAIL".

For all SAS inputs, including composed

points, for which SEER has set the data flag to normal, the SAS program performs limit

tests against predefined engineering units for upper and lower range limits. Inputs

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that do not pass these tests will be displayed as "FAILI.

Where redundant input data is used by SAS to monitor a parameter, that data passing the range checks will be subject to further validation. When at least two or more inputs are valid, and when all valid inputs are within a 10% bandwidth of the average for that parameter, the data is displayed as normal. If only one input of the multiple group is available, or if any are outside the 10% bandwidth, the data is displayed as alert.

Discrepancy #46 resulted from the data, manipulation technique of letting SEER compose (i.e. average) data points from multiple sensors prior to sending data to the SAS data validation program.

The SPDS lesson plan discusses the data validation techniques and explains the

various conditions of data being displayed.

C. Verification Reference(s):

Letter (NRC-84-123) from D. C. Hintz to D. G. Eisenhut (Ref. 12) page 12.

Lesson plan T-SLA-LP 2.13.4, (Ref. 218), page 13 item V and Handout #5.

Quadrex Functional Specification, (Ref. 8),

Appendix B Section II.

SPDS Design Document Package (Ref. 211),

Section 5.0.

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D. Conclusion: SAS does not check.the validity of inputs calculated in the Honeywell SEER program and passed over as a single input, such as an average value of multiple sensors. Since the SEER program only checks that sensors are within range limits and sets a data status flag for the single point being sent to the SAS program, it is possible for data to be included in the single composed input which would be rejected by SAS data validation techniques if the multiple inputs were available to SAS.

This item will remain open until discrepancy #46 is resolved.

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3.4.2 Requirement: The displayed data should represent the correct status of critical plant variables.

(NUREG 0800, Section 5.1.3.1)

A. Verification Task(s): Review the algorithms

used to develop each of the displayed SPDS

points to ensure that the value displayed is

a correct representation.

B. Summary: Many of the attributes specified

by the various requirements of the V&V

program were reviewed at the same time,

although the other attributes are addressed

separately within this report.

Discrepancy #92 resulted from WPS response

to an earlier comment regarding coolant pump

status.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211),

Appendix B.

D. Conclusion: With the exception of Reactor

Coolant Pump status, the algorithms for the

individual data points will provide the

correct status of critical plant variables.

This item will remain open until discrepancy

#92 is resolved.

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3.4.3 Requirement: Validated, unvalidated, and invalid

data are identified and coded where practical.

(NUREG 0800, Section 5.1.3.3)

A. Verification Task(s): Review SPDS design

document package to ensure that the method

of presenting unvalidated and invalid data

is presented to the operators is

implemented.

B. Summary: The SPDS design document package

describes the following display methodology

for coding of validated and invalid data.

Condition

Data which passes all SAS validation tests

One input remaining from multiple inputs or has input more than 10% away from average value

Data which is rejected during the SAS validation tests or SEER range limits checks

Data which exceeds its AIDS setpoints

Data type

Normal

Alert

Fail

Abnormal

Method of display

White numerical value on all displays

Yellow numerical value on all displays

"FAIL" in yellow used in place of numerical value on All displays

Red numerical value on trend graph displays

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C. Verification Reference(s):

SPDS Design Document Package (Ref. 211),

Section 5.3.

Lesson plan T-SLA-LP 2.13.4, (Ref. 218) page

15 item V.D and Handout #5.

Quadrex functional specification, (Ref. 8),

page IV-3 and Appendix B page B-8.

D. Conclusion: The display methodogy used on

the Kewaunee displays meets this

requirement.

This item is considered closed.

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3.5 SPDS Operability

3.5.1 Requirement: The SPDS will continuously display

information from which the safety status of the

plant can be assessed. (NUREG 0800, Section 5.2)

A. Verification Task(s): Ensure that the

system provides for continuous display

capability and that the operators are aware

that SPDS shall be continuously displayed.

B. Summary: Although the lesson plan states

that the appropriate top level display

should always be displayed on one of the

Control Room SAS CRT's, no administrative

procedure was provided to document that a

top level display shall always be displayed

on one of the CRT's.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211),

Section 2.2.

Lesson plan T-SLA-LP 2.13.4, (Ref. 218),

page 7, item IV.A.3

D. Conclusion: The SPDS has two dedicated

consoles in the control room and one console

in the Technical Support Center (TSC) whose

only function is the display of SAS informa

tion which contain the SPDS parameters.

This item is open until discrepancy #89 is

resolved.

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3.5.2 Requirement: The operating crew should be provided

with the information and criteria they need to

perform an operability evaluation of the SPDS. In

addition, the crew must be able to easily recognize

a failed SPDS. (NUREG 0800, Section-5.1.3.4)

A. Verification Task(s): Review the SPDS lesson

plan for the identification of SPDS failure

criteria and the means of detection.

B. Summary: The link between the Honeywell

computer and the chromatics console is

continuously monitored and will activate a

message on all displays except cold shutdown if

it fails. The number "2" will also appear on

all trend graphs at the time the link failed.

If the Honeywell computer experiences a fail

ure, all data being displayed on the chromatics

consoles will show as "FAIL" in yellow.

These items are discussed in the lesson plan

for operator training.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211),

Section 3.5.

Lesson plan (Ref. 10), Section VII.

D. Conclusion: The plant operators are provided

with the operability information needed to

recognize a failed SPDS and are made aware of

these methods during training.

This review item is closed.

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3.6 Electrical Isolation

3.6.1 Requirement: The SPDS shall be suitably isolated

from electrical and electronic interference with equipment and sensors that are in use for the

safety systems. (NUREG 0800, Section 5.3)

A. Verification Task(s): None.

B. Summary: Test results are documented in the following reports: (1) WCAP-7819, Revision

1-A, "Test Report, Nuclear Instrumentation

System Isolation Amplifier," April 1975, (2)

WCAP-7685-A, "Test Report on Isolation

Amplifiers," May 1975, and (3) WCAP-7817,

"Seismic Testing of Electrical and Control

Equipment." The first two reports were.

reviewed and accepted by the NRC staff in

the following documents: (1) AEC letter, D.

B. Vassallo to R. Salvatori, WEC, September

3, 1974, (2) AEC letter, D. B. Vassallo to

R. Salvatori, WEC, June 6, 1973, and the

third report was accepted by: AEC memo R. R.

Maccery to R. C. DeYoung, August 22, 1974.

The seismic qualification testing is in

accordance with the seismic criteria that

was the basis for plant licensing.

Environmental testing was not included

because the amplifiers are located in the

mild environment of the relay room that is

located beneath the control room.

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Class lE electrical .isolation methodology

was found acceptable during an evaluation of

the Kewaunee DCRDR.

C. Verification Reference(s):

Post-Implementation Audit Report, (Ref. 1),

Safety Evaluation Report (enclosure 1 to

letter K5-87-72) (Ref. 2).

Power Plant Facilities Information System

Priority Information List (Ref. 215).

D. Conclusion: This item is closed.

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3.7 Configuration Control

3.7.1 Requirement: Major SPDS interfaces and

* performance characteristics (hardware and software) should be adequately documented to provide a basis for evaluating the acceptability of future system alterations/modifications.

(NSAC 39, Section 2)

A. Verification Task(s): Review SPDS

administrative controls to ensure that a configuration control system has been implemented to control the SPDS hardware and

software.

B. Summary: Administrative Control Directive

(ACD 1.9) specifies the requirements for

modifying the software on the process

computer systems. This directive would also apply to SAS and Chromatics software

programs.

Configuration control documents for SPDS

hardware interfaces and drawings were not

provided for review.

C. Verification Reference(s):

Administrative Control Directive, ACD 1.9, (Ref. 5)

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D. Conclusion: The existing Administrative Control Directive for software control does not contain any references that it also includes SAS and Chromatics software.

The hardware and drawing configuration

controls are not available for review.

This item will remain Open pending resolution of discrepancy #12.

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3.8 Reliability

3.8.1 Requirement: The SPDS reliability analysis shall be

reviewed for consistency with the overall

requirements and objectives defined herein.

Included will be the review of any maintainability

(i.e., repair) assumptions incorporated within that

analysis. (NSAC 39, Section 2).

A. Verification Task(s): Review the reliability

analysis for consistency with overall system

requirements. Review repair assumptions for

reasonableness.

B. Summary: Discrepancy #13 was written to

document that the reliability analysis and

repair assumptions have not been provided for

review.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211),

Section 2.2.

D. Conclusion: A reliability analysis of the SAS

is not available.for review. This item will

remain Open, pending resolution of discrepancy

#13.

EIGEN ENGINEERING, INC. 48 WPS-1000-88-010 REV. 1

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3.9 Location

3.9.1 Requirement: Critical plant variables for the

SPDS are presented on a single primary display

or on a group of displays at a single locations.

(NUREG 0800, Section 5.1.1.1)

A. Verification Task(s): Verify that the

critical parameters are displayed on a

single display.

B. Summary: As discussed in Sections 3.1.1,

3.1.2, 3.1.3 and 3.5.1, the critical plant

variables are grouped together and displayed

on the Top Level displays.

The SPDS displays are presented on two

dedicated SAS consoles located in the

control room and one console located in the

TSC.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211),

Section 2.2.

D. Conclusion: The use of SAS consoles

dedicated for the display of SPDS parameters

meet this requirement.

This item is closed.

EIGEN ENGINEERING, INC. 49 WPS-1000-88-010 REV. 1

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3.9.2 Requirement: The display should be located so that it is convenient to the control room operating crew and where control room operators who are responsible for avoiding degraded and damaged core events can observe the displays.

(NUREG 0800, Section 5.2.1.2)

A. Verification Task(s): Verify that the SPDS display(s) are readily accessible to the control room operators.

B. Summary: The two SAS control room consoles

are positioned adjacent to the plant process computer display monitors and are accessable to control room operators.

C. Verification Reference(s):

SPDS Design Documents Package (Ref. 211), Section 2.2.

Panel Numbering Arrangements in Control Poom (Ref. 93).

D. Conclusion: The location of the SAS consoles in the control room satisfies this

requirement.

This item is closed.

EIGEN ENGINEERING, INC. 50 WPS-1000-88-010 REV. 1

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3.9.3 Requirement: The SPDS should be readily

distinguished from other displays on the control

board. (NUREG 0800, Section 5.2.1.1)

A. Verification Task(s): Verify that the SPDS

displays are uniquely identified from other

CRT displays.

B. Summary: The SPDS is displayed on two

dedicated SAS consoles located in the

control room.

C. Verification Reference(s):

SPDS Design Documentation Package (Ref.

211), Section 2.2.

Panel Numbering Arrangements in Control Room

(Ref. 93).

D. Conclusion: The SPDS is readily

distinguished from other control room

displays.

This item is closed.

EIGEN ENGINEERING, INC. 51 WPS-1000-88-010 REV. 1

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3.9.4 Requirement: The SPDS displays should be

readily accessible to the following personnel,

but not necessarily simultaneously: Shift

Supervisor, Control Room Senior Reactor

Operator, Shift Technical Advisor,.and one

Reactor Operator. (NUREG 0800, Section 5.2.1.2)

A. Verification Task(s): Verify that SPDS is

accessible to the: shift supervisor,

control room senior operator, shift

technical advisor, and one reactor operator.

B. Summary: The two control room SAS consoles

are located adjacent to the process computer

monitors in a central location. An

additional SAS console is located in the

Technical Support Center (TSC). These

consoles are available to all control room

and TSC personnel when these areas are

manned.

C. Verification Reference(s):

SPDS Design Document Package (Ref. 211),

Section 2.2.

Panel Numbering Arrangement in Control Room

(Ref. 93).

General Arrangement Technical Support Center

(Ref. 94).

D. Conclusion: The SPDS displays are

accessable to the necessary personnel.

This item is closed.

EIGEN ENGINEERING, INC. 52 WPS-l000-88-010 REV. 1

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3.9.5 Requirement: The control room operating crew,

not personnel outside the control room, control

images displayed on the control room SPDS.

(NUREG 0800, Section 5.2.1.2)

A. Verification Task(s): Determine who has

control of displays on SPDS consoles.

B. Summary: Each SAS console is supplied with a dedicated keyboard which can request

display screens for that individual console only.

C. Verification Reference(s):

SPDS Design Documentation Package (Ref.

211), Section 2.2.

D. Conclusion: The control room operating crew

has control of the screens displayed on the

SAS consoles.

This item is closed.

EIGEN ENGINEERING, INC. 53 WPS-l000-88-010 REV. 1

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3.10 Procedures and Training

3.10.1 Requirement: Procedures which describe the

timely and correct safety assessment when SPDS

is and is not available, will be developed.

(NUREG 0800, Section 5.3.1)

A. Verification Task(s): Review Emergency

Operating Procedures to determine usage of

SPDS displays during their performance.

B. Summary: The function of the SAS is to

supply at a centralized location, information to aid plant operators during

both normal and abnormal plant conditions.

Current procedures and training do not

require that SAS be used for safety

assessment. (e.g. determination that plant

conditions warrant performance of an EOP).

C. Verification Reference(s).

Emergency Operating Procedures (Ref. 23 thru

73).

D. Conclusion: Additional procedures are not required since Safety Assessment (e.g.

determination that plant conditions warrant

performance of an EOP) is not dependent on

the availibility of the SAS.

This item is closed.

EIGEN ENGINEERING, INC. 54 WPS-l000-88-010 REV. 1

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3.10.2 Requirement: Control room operators should be

trained to respond to accident conditions both

with and without SPDS available. (NUREG 0800,

Section 5.3.1)

A. Verification Task(s): Review operator

training to determine usage of the SAS

during accident conditions.

B. Summary: Although a lesson plan which

describes the SAS parameters and functions

is in use, current operator training does

not include the use of the SAS during

accident conditions.

Training for operator response to accident

conditions without SPDS has been in effect

for several years.

C. Verification References:

Emergency Operating Procedures (Ref. 23

through 73).

Lesson plan (Ref. 218)

D. Conclusion: Operator response to accident

conditions using SPDS needs to be

incorporated into operator training.

This item is Open pending resolution of

discrepancy 90.

EIGEN ENGINEERING, INC. 55 WPS-1000-88-010 REV. 1

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3.10.3 Requirement: The control room operators

training program contains instruction and

training in the use of the SPDS in conjunction with operating procedures for normal, abnormal, and emergency operating conditions. -(NUREG

0800, Section 5.3.1.2)

A. Verification Task(s): Review operator training to verify instruction on usage of SPDS during normal, abnormal and emergency plant conditions.

B. Summary: As discussed in Section 3.10.2, current training is limited to a lesson plan describing SAS parameters and functions.

C. Verification Reference(s):

Lesson Plan (Ref. 218).

D. Conclusion: Operator training needs to be revised to include use of SAS during normal, abnormal and emergency operations.

This item is Open pending resolution of

discrepancy 91.

EIGEN ENGINEERING, INC. 56 WPS-l000-88-010 REV. 1

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3.11 Human Factors

3.11.1 Requirement: The SPDS design shall incorporate

accepted human factors engineering principles.

(NUREG 0800, Section 5.4.1) (NRC V&V-Audit

October, 1986)

A. Verification Task(s): Review available documentation for human factors reviews that have been performed for the SAS.

B. Summary: The Quadrex Functional

Specification states that the generic SAS design was evaluated against human factors design criteria.

SASLOG-33 specifies the industrial design and human factors guidelines and abbreviations used during development of the generic SAS.

SASLOG-102 describes the human factors considerations relative to generic SAS displays.

Modifications to the generic design during development of the plant specific system were to have been reviewed as part of the overall control room design review.

Discrepancy #14 was written since this report was not supplied for review.

EIGEN ENGINEERING, INC. 57 WPS-1000-88-010 REV. 1

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C. Verification Reference(s):

Quadrex functional specification (Ref. 8)

page 11-2.

Letter (NRC-83-169) from C. W. Giesler to D.

G. Eisenhut (Ref. 11), page A-2.

SPDS Design Document Package (Ref..211)

Section 3.0.

SASLOG-33, "Industrial Design/Human Factors

Guidelines and Abbreviations" (Ref. 221)

SASLOG-102, "SAS Displays Human Factors

Considerations" (Ref. 220)

D. Conclusion: Human factors engineering

principles were well implemented during the

development of the generic SAS design.

No information has been provided to verify

that modifications to the generic system

were evaluated against human factors design

criteria.

This item is open pending resolution of

discrepancy 14.

EIGEN ENGINEERING, INC. 58 WPS-l000-88-010 REV. 1

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3.12 System Operation and Maintenance

3.12.1 Requirement: No additional operating staff

other than the normal control room operating

crew should be needed to operate the-display

during normal and abnormal plant operation and

during display outages. (NUREG 0800, Section

5.3.1.2)

A. Verification Task(s): During the Dynamic

testing, verify that only the regular

operating crew is required to operate SPDS.

B. Summary: None

C. Verification Reference(s): None

D. Conclusion: This item will remain Open

until dynamic testing has been completed.

EIGEN ENGINEERING, INC. 59 WPS-1000-88-010 REV. 1

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3.12.2 Requirement: Vendor equipment documentation

shall be reviewed to verify implementation of

recommended periodic maintenance guidelines in

plant procedures. (NSAC 39, Section 2.0)

A. Verification Task(s): Review preventive

maintenance records during the field "walk

through".

B. Summary:

C. Verification Reference(s):

D. Conclusion:

This item will remain Open until the Field

Installation Audit has been completed.

EIGEN ENGINEERING, INC. 60 WPS-1000-88-010 REV. 1

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4.0 REFERENCES

1. Kewaunee Nuclear Power Plant Safety Parameter Display System Verification and Validation Plan, WPS-1000-99001, Rev. 0.

2. Post-Implementation Audit Report for Wisconsin Public Service Corporation's Kewaunee Nuclear Power Plant (SAIC-86/3000) dated January 30, 1987.

3. Requirements for Emergency Response Capability (Generic Letter 82-33), NUREG 0737, Supplement 1, dated 12/17/82.

4. Kewaunee Nuclear Power Plant SPDS Design Document Package (WPS-1000-88-009), Rev. 1 dated October 6, 1988.

EIGEN ENGINEERING, INC. 61 WPS-1000-88-010 REV. 1

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ATTACHMENT 1

Kewaunee SPDS Design Review

Reference Document List

Page 65: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

REF NUM

1

DOCUMENT TYPE

Report

Report

Screens

Spec

Procedure

Lesson Pin

Report

Spec

Letter

Lesson Pin

Letter

Letter

Letter

Report

Letter

ENTS PR D BY EIGEN ENGINEERING, INC.KEWAUNEE DOCUM

DOCUMENT NUMBER

SAIC-86/3000

K-87-72

51107909

ACD 1.9

77 Q

EIGEN-88-001

T-STA-LP 2.13.4

NRC-83-169

NRC-84-123

NRC-84-142

WCAP 7819

NRC-84-24

DOCUMENT TITLE

Post-Implementation Audit Rpt. for WPS Corporation's Kewaunee Nuclear Power Plant SPDS (SAIC Technical Evaluation Report)

Safety Evaluation Report for the Kewaunee Nuclear Power Plant SPDS (Enclosure 1)

Copies of Kewaunee Display Screens (19 Screens) (See Reference #202)

System Specification Section Nine WPS Kewaunee Nuclear Power Plant (Honeywell)

Software Maintenance Control

SAS For Operators (Lesson Plan)(Superseded by T-STA-LP 2.13.4)

Safety Assessment System Evaluation Program Report (Quadrex)

Functional Specification (Quadrex)

WPSC Comments on Draft V&V Plan and Requirements Matrix

Safety Assessment System (Non-Approved Copy)

Safety Analysis Report for Safety Parameter Display System

Additional Information on SPDS

Seismic Qualification of SPDS Isolation Amplifiers

Nuclear Instrumentation System Isolation Amplifier

Schedule for Safety Parameter Display System (SPDS) Implementation

Page Nr 10/06/1

1

REV/DATE

01-30-87

9-18-86

A/01-05-84

1/04-4-86

3-6-85/3-6-85

05-20-82

2 / 5-20-82

2/5/88

B / None

9/2/83

8/1/84

9/4/84

1A/4/75

2/3/84

2

3

4

5

6

7

8

9

10

11

12

13

14

15

DATE RECEIVED

01-18-88

01-18-88

2-25-88

01-18-88

01-18-88

01-18-88

01-18-88

01-18-88

2/8/88

2/8/88

2/8/88

2/8/88

2/8/88

2/8/88

2/8/88

Page 66: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

REF NUM

16

17

18

19

20

21

22

23

24

25

26

27

28

29

30

31

32

DOCUMENT TYPE

====mm

Letter

Letter

Letter

Letter

Report

Letter

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

NTS RE, BY EIGEN ENGINEERING, INC.KEWAUNEE DOCUME

DOCUMENT NUMBER

K-84-66

NRC-84-88

K-86-161

NRC-86-113

WCAP-7685-A

K-87-12

UG-0

F-0.1

F-0.2

F-0.3

F-0.4

F-0.5

F-0.6

E-0

ES-0.0

ES-0.1

ES-0.2

DOCUMENT TITLE

NRC Request for Additional Information on Safety Parameter Display System

Additional Information on SPDS

NRC Notice of Impending SPDS Audit

Additional Information on SPDS

Test Report on Isolation Amplifiers

NRC Safety Evaluation Report of SPDS

User's Guide for Integrated Plant Emergency Operating Procedures

Subcriticality

Core Cooling

Heat Sink

Integrity

Containment

Inventory

Reactor Trip or Safety Injection

Rediagnosis

Reactor Trip Response

Natural Circulation Cooldown

Page N1 10/06/'

REV/DATE

3/26/84

5/25/84

8/8/86

8/21/86

5/75 .

4/8/87

orig/10/13/87

A/4/1/85

B/4/1/86

B/4/1/86

B/4/1/86

A/4/1/85

B/4/1/86

B/4/1/86

A/4/1/86

C/3/10/87

C/8/11/87

DATE RECEIVED

2/8/88

2/8/88

2/8/88

2/8/88

2/8/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

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REF NUM

33

34

35

36

37

38

39

40

41

42

43

44

45

46

47

DOCUMENT TYPE

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

NTS RE, BY EIGEN ENGINEERING, INC.EEWAUNEE DOCUME

DOCUMENT NUMBER

ES-0.3

E-0 ORF

E-1

ES-1.1

ES-1.2

ES-1.3

E-1

E-2

E-3

ES-3.1

ES-3.2

ES-3.3

ECA-0.0

ECA-0.1

ECA-0.2

DOCUMENT TITLE

Natural Circulation Cooldown with Steam Void in Vessel

Quick Reference Foldout Section E-0

Loss of Reactor or Secondary Coolant

SI Termination

Post LOCA Cooldown and Depressurization

Transfer to Coldleg Recirculation

Quick Reference Foldout Section E-1

Faulted Steam Generator Isolation

Steam Generator Tube Rupture

Post-SGTR Cooldown Using Backfill

Post-SGTR Cooldown Using Blowdown

Post-SGTR Cooldown Using Steam Dump

Loss of All AC Power

Loss of All AC Power Recovery Without SI Required

Loss of All AC Power Recovery With SI Required

Page Nc 10/06/8,

3

DATE REV/DATE RECEIVED

B/8/11/87 2/15/88

B/4/1/86 2/15/88

B/4/1/86 2/15/88

C/8/11/87 2/15/88

D/8/11/87 2/15/88

B/6/9/87 2/15/88

B/4/1/86 2/15/88

A/4/1/86 2/15/88

C/3/10/87 2/15/88

B/8/11/87 2/15/88

C/8/11/87 2/15/88

C/8/11/87 2/15/88

C/3/10/87 2/15/88

B/4/1/86 2/15/88

B/4/1/86 2/15/88

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REF NUM

48

49

50

51

52

53

54

55

56

57

58

59

60

61

62

DOCUMENT TYPE

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

ENTS REC BY EIGEN ENGINEERING, INC.KEWAUNEE DOCUM

DOCUMENT NUMBER

ECA-1.1

ECA-1.2

ECA-2.1

ECA-2.0 ORF

ECA-3.1

ECA-3.2

ECA-3.3

ECA-3 ORF

FR-S.I

FR-S.2

FR-C.1

FR-C.2

FR-R.1

FR-H.2

FR-H.3

DOCUMENT TITLE

Loss of Emergency Coolant Recirculation

LOCA Outside Containment

Uncontrolled Depressurization of All Steam Generators

Quick Reference Foldout Section ECA-2

SGTR With Loss of Reactor Coolant-Subcooled Recovery Desired

SGTR With Loss of Reactor Coolant-Saturated Recovery Desired

SGTR Without Pressurizer Pressure Control

Quick Reference Foldout Section ECA-3

Response to Nuclear Power Generation/ATWS

Response to Loss of Core Shutdown

Response to Inadequate Core Cooling

Response to Degraded Core Cooling

Response to Loss of Secondary Beat Sink

Response to Steam Generator Overpressure

Response to Steam Generator High Level

Page Nc 10/06/8t

REV/DATE

B/8/11/ 87

A/8/11/87

C/8/11/87

B/4/1/86

E/8/11/87

D/8/11/87

C/8/11/87

B/4/1/86

B/4/1/86

A/10/19/85

B/4/1/86

B/4/1/86

C/4/1/86

B/4/1/86

B/4/1/86

DATE RECEIVED

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

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REF NUM

63

64

65

66

67

68

69

70

71

72

73

74

75

76

77

DOCUMENT TYPE

Procedures (EOP)

Procedures (EOP)

Procedures EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Procedures (EOP)

Letter

Memo

Memo

Block Diagram

ENTS BY EIGEN ENGINEERING, INC.KEWAUNEE DOCUM

DOCUMENT NUMBER

FR-H.4

PR-H.5

FR-P.1

FR-P.2

FR-Z.1

FR-Z.2

FR-Z.3

FR-I.1

FR-I.2

FR-I.3

FR-C.3

SASLOG-118 (I.D.2)

E3265

DOCUMENT TITLE

Response to Loss of Normal Steam Release Capabilities

Response to Steam Generator Low Level

Response to Imminent Pressurized Thermal Shock Condition

Response to Anticipated Pressurized Thermal Shock Condition

Response to High Containment Pressure

Response to Containment Flooding

Response to High Containment Radiation Level

Response to High Pressurizer Level

Response to Low Pressurizer Level

Response to Voids in Reactor Vessel

Response to Saturated Core Conditions

SPDS Parameters/Basis of Selection (Quadrex)

SAS Top Level Display Setpoints (Green Bay)

SAS Parameter Display Range (Green Bay)

Honeywell Computer System Block Diagram

Page Nc 10/06/6

5

REV/DATE

A/10/19/85

orig/4/l/85

B/4/1/86

A/10/19/85

B/4/1/86

A/10/19/85

A/4/1/86

A/4/1/86

A/4/1/86

B/4/1/86

A/10/19/82

5-9-832

2-1-84

7-31-84

C/

DATE RECEIVED

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/15/88

2/18/88

2/18/88

2/18/88

2/18/88

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REF NUM

78

79

80

81

82

83

84

85

86

87

88

89

90

91

92

93

DOCUMENT TYPE

Evaluation

Manual (Sect)

Procedure (I&C)

Procedure (I&C)

Procedure (Maint)

Procedure (Maint)

Procedure (Maint)

Procedure (Maint)

Procedure (Maint)

Procedure (Maint)

Procedure (Maint)

Procedure (Maint)

Procedure (Maint)

Procedure (Maint)

Procedure (Maint)

Drawing

ENTS REC BY EIGEN ENGINEERING, INC.KEWAUNEE DOCUM

DOCUMENT NUMBER

CCPUIPS-M

ICP 35.6

ICP 36.38

ICP 46A.01

ICP 46A.02

ICP 46A.04

ICP 46A.05

ICP 46A.06

ICP 46A.07

ICP 46A.08

ICP 46A.10

ICP 46A.11

ICP 46A.12

ICP 46A.13

237127A-E854

DOCUMENT TITLE

Objective of Data Validation

4500C Power Subsystem Mantenance (Honeywell)

CVCS-Reactor Coolant Pump IA Bearing Water Temp-Loop 132 ,

RC-Pressurizer Relief Tank Pressure Loop 440

CD-SAS Units 1, 2, and 3 Weekly Maintenance

CD-Honeywell Monthly Cleaning and Inspection

CD-Honeywell Power Supply Semi-Annual Check

Annual Flux Map A/D Converter Calibration

Honeywell Moving Head Disc 6 Month Preventive Maintenance

Honeywell Line Printer Semi-Annual Functional Check

Honeywell Mag Tape Annual Maintenance

Honeywell P.I.U. 6 Month Maintenance

Honeywell Floppy Disc Drive Yearly Maintenance

Honeywell Large Core Storage Maintenance

CD-Tektronix Video Copier Maintenance Monthly

Panel Numbering Arrangement in Control Room

Page No 10/06/8L

6

REV/DATE

None

3/83

E/7-8-86

G/11-17-87

4/9/85

A/9/3/86

B/9/3/86

3/24/87

C/9/3/86

B/9/3/86

A/9/17/86

A/10/1/86

A/9/3/86

1/21/86

AH/6/30/87

DATE RECEIVED

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

Page 71: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

REF NUM

94

95

96

97

98

99

100

101

102

103

104

105

DOCUMENT TYPE

Drawing

Drawing (Block Diag)

Drawing (Block Diag)

Drawing (Block Diag)

Drawing (Block Diag)

Drawing (Block Diag)

Drawing (Block Diag)

Drawing (Block Diag)

Drawing (Block Diag)

Drawing (Block Diag)

Drawing (Block Diag)

Drawing (Block Diag)

KEWAUNEE DOCUM

DOCUMENT NUMBER

237127A-A329

BD-01

BD-02

BD-03

BD-04

BD-05

BD-06

BD-07

BD-08

BD-09

BD-10

BD-11

ENTS RECRW BY EIGEN ENGINEERING, INC.

DOCUMENT TITLE

General Arrangement-Technical M/ Support Center, Basement and First Floor

Cover Sheet & Index 1/

Pressurizer Press 2P

Pressurizer Level IN

Delta T - Tavg IH

Delta T - Tavg (con't) 1J

Delta T - Tavg (con't) 1H)

Delta T - Tavg (con't) 1i

Tavg, Delta T, Rod Insertion Limit 1H)

Rod Control 1 R/

Steam Gen Level 1M/

Steam Dump 2J/

Page No 10/06/86

REV/DATE

6/13/86

2-75

/8-21-86

/12-26-86

/10-8-86*

/10-8-86

/10-8-86

'10-8-86

/11-2-79

10-20-80

3-27-87

9-12-84

DATE RECEIVED

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

Page 72: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

8

REF DOCUMENT NUM TYPE

106 Drawing (Block Diag)

107 Drawing (Block Diag)

108 Drawing (Block Diag)

109 Drawing (Block Diag)

110 Printout

Ill Printout

112 Printout

113 Printout

114 Printout

115 Printout

116 Block Diagram

117 Data Sheet

118 Data Sheet

119 Data Sheet

120 Data Sheet

KEWAUNEE DOCUMENTS RE'

DOCUMENT NUMBER

BD-12 Loop A

BD-13

BD-1 4

BD-15

Rpt.No.3 (HNW)

Rpt.No.4 (HNW)

Rpt.No.2 (HNW)

Rpt.No.3 (HNW)

SAS Code

Rpt.No.1 (HNW)

Handdrawn

DS No. 1

DS No. 2

DS No. 3

DS No. 4.

BY EIGEN ENGINEERING, INC.

DOCUMENT TITLE

Comp Steam/F.W. Flow

Loop B Comp Steam/F.W. Flow

Reactor Coolant Flow

Containment Pressure

Digital Input Report (D)

Composed Digital Inputs (L)

Composed Analog Report (G)

DTK,CVS and CVR Point Report (B&K)

SASP Parameter Display System Readin Module

Eigen Engineering (Analog Points) (A)

Basic Block Diagram (Honeywell CPUs)

Stm Gen A Stm Out F (Flow Correction Data Sheet)

Stm Gen B Stm Out F (Flow Correction Data Sheet)

Stm Gen A Feed-wtr In F (Flow Correction Data Sheet)

Stm Gen B Feed-wtr In F (Flow Correction Data Sheet)

REV/DATE

IN/3-27-87

2P/3-27-87

1H/9-12-84

2H/11-24-81

2-17-88

2-17-88

2-17-88

2-17-88

2/02-82

2-17-88

Page No 10/06/8

DATE RECEIVED

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

2/25/88

3/07/88

2/25/88

3/2/88

3/2/88

3/2/88

3/2/88

3/2/88

Page 73: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

REF NUM

121

122

123

124

125

126

127

128

129

130

131

132

133

134

135

136

137

138

Page No, 10/06/8L

NTS REC EIGEN ENGINEERING, INC.

DOCUMENT TYPE

Data Sheet

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Printout

Block Diagram

KEWAUNEE DOCUME

DOCUMENT NUMBER

DS No. 5

(mNW)

SAS Code

SAS Code

SAS Code

SAS Code

SAS Code

SAS Code

SAS Code

SAS Code

SAS Code

SAS Code

SAS Code

Handdrawn

DOCUMENT TITLE REV/DATE

Non Regener Ex Letdown Out F

Exp Factors List (CRV List)

PID Point List (SPC Point Lookup Table)

Chromatics/Honeywell Link Data 2/29/88 Sorted By Honeywell Point ID

Chromatics/Honeywell Link Data 2/29/88 Sorted By Array Word

Chromatics/Honeywell Link Data 2/29/88 Sorted by Link Byte

Chromatics/Honeywell Link Data 2/29/88 Sorted By Chromatis Word

Critical Safety Function Monitor 3-4-88

SASP Parameter Display Program - 3/5-12-82 Executive

SASP Parameter Display Program - 3/5-11-82 GAVDTY Module

SASP Parameter Display Program - 3/3-4-82 RATOCH Module

SASP Parameter Display Program - 5/5-8-82 PURSAS Module

SASP Parameter Display Program - 2/5-12-82 GSATEM module

AIDS Subsystem - AIDS Executive 3-3-88

AIDS Subsystem - Transfer Executive 3-3-88

AIDS Subsystem - PAPS Subroutine 3/5-3-82

AIDS Subsystem - SAPS Subroutine 5/5-3-82

SAS Data Interfaces (Software Modules)

DATE RECEIVED

3/2/88

3/2/88

3/2/88

3/2/88

3/2/88

3/2/88

3/2/88

3-7-88

3-7-88

3-7-88

3-7-88

3-7-88

3-7-88 3-7-88

3-7-88

3-7-88

3-7-88

3-7-88

3-7-88

Page 74: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

REF NUM

DOCUMENT TYPE

139 Curve

140

141

142

143

144

145

146

147

148

149

150

151

152

153

154

Printout (Reduced)

Printout

Block Diagram

Drawing

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

KEWAUNEE DOCUMENTS RE(

DOCUMENT NUMBER

RD11.1.1

SAS Code

Handdrawn

Handdrawn

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

BY EIGEN ENGINEERING, INC.

DOCUMENT TITLE REV/DATE

Kewaunee Reactor Coolant System Heatup and Cooldown Limitations.

SAS Setpoint Values

Flow Data Point List (P)

Incore TC Input Diagram

SAS Keyboard Layout

SASMAIN.P

SASDISP.P

JWLINK.C

TOPLEVEL.P

CHSBAR.C

TOPCOLDSD.P

DATAFIN.C

PMLINK.C

TEXTDISPLAY.P

TRENDGRAPH.P

TIMEDP.P

4-15-86

4-29-XX

1/8-25-83

1/8-24-83

1/3-85

1/7 27-83

0/7-25-83

0/3-6-82

4/8-87

1/3-23-85

0/3-6-82

0/

0/3-6-82

Page No 10/ 06/88 0

DATE RECEIVED

3/10/88

3/10/88

3/10/88

3/10/88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

.3-16-88

3-16-88

3-16-88

3-16-88

Page 75: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Page Noy 10/06/E,

KEWAUNEE DOCUMENTS RE( BY EIGEN ENGINEERING, INC.

DOCUMENT TYPE

=== ==========

155

156

157

158

159

160

161

162

163

164

165

166

167

168

169

DOCUMENT NUMBER

Chrom CodePrintout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom Code

DOCUMENT TITLE

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

REF NUM

TIMEUPDATE.P

TRDCOLKEY.P

ARROWBOLD.C

BACKGRD.C

CNRC.C

DISP.C

INITIALIZE.C

HVSCOL.C

LEDS.C

LOGO.C

SASERROR.C

SIMKEY.C

TEXTS.C

TRENDDP.C

TRENDBACK.C

REV/DATE

0/3-6-82

1/8-2-83

0/3-6-82

1/7-15-83

0/3-6-82

0/3-6-82

1/1-84

0/

0/

0/

0/3-6-82

1/7-3-83

0/3-6-82

0/3-6-82

0/3-6-82

DATE RECEIVED

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

Page 76: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

2

REF NUM

DOCUMENT TYPE

== = == = == === = =

KEWAUNEE DOCUMENTS

DOCUMENT NUMBER

BY EIGEN ENGINEERING, INC.

DOCUMENT TITLE REV/DATEDATE

RECEIVED================================= u======~======= ========

170

171

172

173

174

175

176

177

178

179

180

181

182

183

184

Page Nc. 10/06/8b

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Chromn

Chrom

Chrom

Chrom

Chrom

Chrom

Chrom

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

Code

UPDATE.C

VALMOD.C

VALDATE.C

VDSTXT.C

VECRECTAN.C

VTEXT.C

AIDSDISPLAY.P

BARDSPLAY.P

BAROUT.P

CLEARSCREEN.P

DATTIMECBR.P

DELAY.P

DSTCBR.P

DSTCHR2.P

DSTCHRTOP.P

0/3-6-82

2/11-85

2/3-12-84

1/8-24-83

0/3-6-82

0/3-6-82

1/7-15-83

0/3-6-82

1/8-24-83

0/3-6-82

0/3-6-82

0/

0/3-6-82

0/3-6-82

0/3-6-82

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88 3-16-88

Page 77: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

REF NUM

DOCUMENT TYPE

~= =m~~

KEWAUNEE DOCUMENTS RE

DOCUMENT NUMBER

= = == = == =

BY EIGEN ENGINEERING, INC.

DOCUMENT TITLE REV/DATEDATE

RECEIVED==================== ========== ==== m~=

185

186

187

188

189

190

191

192

193

194

195

196

197

198

199

200

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Printout

Printout

Printout (Reduced)

Printout (Reduced)

Printout (Reduced)

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Chrom Code

Rpt.No.2

Code

Code

Code

Page N' 10/06A

INITNORMAL.P

LIMITLINES.P

MONTHX.P

RECTANGLE.P

REDBOX.P

STAT12.TXT(VIEW)

SECBARGRAPH.P

SHIFT.P

TREND.C

GRAPH-LIB.C

BAKUP(floppy input prg).

TSTFLW, and VAR point Report (P)

CRV List (G)

SECICC.P

SECLOCA.P

SECLOSC.P

Chrom

Chrom

Chrom

0/

1/7-8-83

0/3-6-82

0/3-6-82

0/3-6-82

0/3-6-82

1/8-1-83

0/3-6-82

0/3-6-82

2-29-88

1/8-14-83

0/5-6-82

1/8-24-83

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

3-16-88

2/25/88

3/2/88

3-16-88

3-16-88

3-16-88

Page 78: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

REF NUM

201

202

203

204

205

206

207

208

209

210

211

212

213

214

215

216

217

DOCUMENT TYPE

Printout (Reduced)

Screens

Drawing

Drawing

Manual (Sect)

Manual (Sect)

Spec

Procedure (I&C)

Printout (Reduced)

Letter

Report

FSAR

Corr.Fact. (Handmade)

Memo

Printout

Printout

Memo

ENTS R BY EIGEN ENGINEERING, INC.KEWAUNEE DOCUM

DOCUMENT NUMBER

Chrom Code

237127A-E3416

237127A-E3417

51107909

WPS-K1-244

9285-ICE-35212

Request 000 & 001

NRC-85-84

WPS-l000-009

Chap. 14

JDD 88009

TRX:610

TRX:613

N/A

DOCUMENT TITLE

SECSGTR.P

Copies of Kewaunee Display Screens (9 screens) (see reference #3)

ICCMS Logic Diag. Train A

ICCMS Logic Diag. Train B

Sect 9, Redundant Measurements (Honeywell)

TDC 4500 Instructions (Honeywell)

Spec for ICCMS

Table 3.3.1.3-7A, Analog Input Ch A

KNPP/Honeywell PPFIS List

Status of Safety Parameter Display System

SPDS Design Document Package (Eigen)

Safety Analysis

Flow Correction Factors F-100OG-F007G

Doyel to Allen Re: Telecon with Chadek

Priority Information List From Power Plant Facilities Information System

Drawing Information List From Power Plant Facilities Information System

WPS V&V Comment Response

Page N; 10/06/b

14

REV/DATE

0/5-6-83

10-15-87

/2-5-86

/2-5-86

A/1-5-84

/10-77

5/11-10-85

1/

/8-1-84

4-26-85

0/4-19-88

3/7-1-85

None

5/3/88

4/25/88

4/25/88

DATE RECEIVED

3-16-88

1-18-88

4/11/88

4/11/88

4/11/88

4/11/88

4/11/88

4/11/88

4/11/88

2/8/88

N/A

4-25-88

4-23-88

5-3-88

5-9-88

5-9-88

8-3-88

Page 79: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

REF NUM

218

219

220

221

222

223

224

DOCUMENT TYPE

Lesson Plan

Drawing

Memo

Memo

Specificat ion

Memo

Report

NTS REI BY EIGEN ENGINEERING, INC.KEWAUNEE DOCUME

DOCUMENT NUMBER

T-STA-LP 2.13.4

E2021

SASLOG-102

SASLOG-33

9285-ICE-3073

WPS-1000

DOCUMENT TITLE

SAS Lesson Plan

Rad Monitoring Logic, Sh. 3 of 3

SAS Displays Human Factors Considerations

Industrial Design/Human Factors Guidelines & Abbreviations

Inadequate Core Cooling Monitoring System (ICE-273(80K5)/LRl)

Calc Sheets F100OG thru F1007G

SPDS Design Document Package

Page No; 10/06/8\

REV/DATE

B/4-21-88

G/

/5-17-82

/5-15-81

1/3-6-86

None

DATE RECEIVED

8-3-88

8-3-88

9-12-88

9-12-88

9-12-88

10-6-88

10-6-88

Page 80: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

ATTACHMENT 2

Discrepancies

Page 81: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

During the design review phase of the SPDS V&V program, the

following 94 discrepancies were identified. Based on

additional information received from WPS, 74 discrepancies

have been resolved and closed.

The remaining 20 discrepancies have been categorized as

follows:

o Category 1 - Discrepancies which will require

modifications to the SPDS hardware and/or software.

Discrepancies in this category include #'s 2, 3, 5, 6,

7, 8, 9, 10, 11, 15, 46 and 94.

o Category 2 - Discrepancies which will require

development or revision of station procedures or

documents. Discrepancies in this category include #'s

12, 13, 14, 89, 90, 91, 92 and 93.

EIGEN ENGINEERING, INC. WPS-1000-88-010 .. REV. 1

Page 82: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 1 Date: 3/18/88

Page 1 of 1

References: 1)

2)

3)

Read In Module - Source File (Ref 114/P9) Composed Analog Report, (Ref 112/P6-1) Analog Inputs, (Ref 115/P5-1)

Requirement #: N/A (ANLO54, ANLO55)

Subject: Error in readin module source code comments.

Problem Description: Source code descriptions for CON G,145 and CON G,146 reference composed analog points F8003G and F8004G. These points are not in the Composed Analog Report. The Analog Inputs printout list points F8003A and F8004A for AFW lA and lB flow.

Disposition:

Additional documentation received from WPS provided the required information. See Reference 217.

The Design Document Package has been revised (Ref. 224), and this discrepancy is closed.

Disposition Prepared by: V & V Review:

Disposition Verified Sigrif ture

EIGEN ENGINEERING, INC. 2.1

Jo / 4C / -e

/'0 /J$_/ 0

Date

WPS-1000-88-010 REV. 1

Page 83: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 2 Date: 3/29/88

Page 1 of 1

References: 1) Display 017 (S/G (NR) Level)

2) EOP F-0.3 Heat Sink

3) ANL 018 & 019 (S/G Level)

Requirement #: 3.3.3

Subject: Steam Generator level nomenclature ontrend graph

Problem Description: The trend graph and EOP both refer to

"Narrow Range" level. The range being displayed for this

point is 0-100% and no information has been provided to

verify that ANL 018 and ANL 019 are narrow range level

indications.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.2

/ /

/ /

/_ / Date

WPS-1000-88-010 REV. 1

Page 84: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 3 Date: 3-29-88

Page 1 of 1

References: 1) Display 006 (Feed Flow & Steam Flow) 2) CS? EOP F-0.3 Heat Sink 3) ANL 026 & 027 (S/G Feed Flow)

Requirement #: 3.3.3

Subject: Engineering unit requirement differences.

Problem Description: The CS? EOP has a requirement for total feedwater flow to SG's greater than 200 GPM. Trend graph display flows have units of lbs/hr(10 6 )

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.3

/

/ /

Date

WPS-1000-88-010 REV. 1

Page 85: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 4

References: 1) WPS Letter NRC-84-123

2)

3)

Requirement #: 3.1.1

Date: 4/29/88

Page 1 of 1

Subject: Minimum set of critical plant variables

Problem Description: Although listed in WPS letter NRC-84

123, Reactor Coolant Average Temperature is not displayed on

the SPDS. Tavg can (at best) be estimated using the

Pressure/Temperature 2nd level display.

Disposition: Cancelled. Reactor Coolant Average temperature

is provided in the message area of the normal operation and

heatup/cooldown top level displays.

Disposition Prepared by:

V & V Review:

Disposition Verified Si g nAtu r e

EIGEN ENGINEERING, INC.

_e / Ic) / 5- / 37~t

__QJ/ / Date

2.4 WPS-lOOO-88-010 REV. 1

Page 86: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 5 Date: 4/13/88

Page 1 of 1

References: 1) SPDS Design Document (Ref. 211)

2) GEN002, Sh 1 & 2 (Drawing)

3) AIDS Setpoint List (Ref. 140)

4) Chrom Setpoint (Ref. 147/P7)

Requirement #: 3.1.4

Sublect: Alarm limits

Problem Description: The top level display bar graph alarm

setpoints are contained in the Chromatics programs. The

associated 2nd level trend graph numerical value color is

controlled by the AIDS programs. The setpoint value for the

same parameter is not the same in the following cases.

AIDS Chrom ANL001 Hi - 2484 Hi - 2485

Low - 1816 Low - 1815 ANL002 Hi - 56 Hi - 57

Low - 18 Low -18 ANLO18 & 19 Hi -.65 Hi - 66

Low - 16 Low - 15 ANLO22 & 023 Hi - 1050 Hi - 1050

Low - 500.0 Low - 500 ANLO34 & 035 Hi - 553 Hi - 554

Low - 521 Low - 520

Disposition:

Disposition Prepared by: /

V & V Review: / /

Disposition Verified: / /

Signature Date

EIGEN ENGINEERING, INC. 2.5 WPS-1000-88-010 REV. 1

Page 87: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 6 Date: 4/18/88

Page 1 of I .

References: 1) AIDS Setpoint List (Ref. 140)

2) ANLOO8, Point Drawing (Ref. 211)

3)

Requirement #: 3.3.1

Subject: Containment Pressure Alarm Setpoint.

Problem Description: Containment Pressure is measured by the

average of two sensors with range of -5 to 200 psig. The

Containment Pressure Alarm is 1.0 psig. The accuracy of the

algorithm is inadequate for determining this low of an alarm.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.6

/ /

/ _/

_ / / _

Date

WPS-l000-88-010 REV. 1

Page 88: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 7

References: 1) ANL002 (Drawing)

2)

3)

Requirement #: 3.3.1

Date: 4/18/88

Page 1 of 1

Subject: Pressurizer level input range.

Problem Description: The only variable being monitored for this parameter is the wide range sensors. The SAS program attempts to select between wide range and narrow range based on Tave temperature conditions, but will only display wide level under all conditions.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

D / / /

/ / Date

EIGEN ENGINEERING, INC. 2.7 WPS-1000-88-010 REV. 1

Page 89: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 8

References: 1)

2)

3)

Date: 4/18/88

Page 1 of 1

V ANLQf4 (Drawing) DSP008 (Drawing)

Ref. 209/Pl7

Requirement #: 3.3.1

Subject: AVG Core Exit Temp Range.

Problem Description: The core exit thermocouple process ranges are shown in the Honeywell database as -100 to 1000F.

This range is inadequate to support CSF EOP F-0.2.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.8

/ /

/ /

_/ / Date

WPS-looo-88-010 REV. 1

Page 90: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 9 Date: 4/18/88

Page 1 of 1

References: 1)

2)

3)

CSF (F-0.2) (Ref. 24) DSPOO1, 008 and 010

ANL006 (Drawing)

Requirement #: 3.1.3

Subject: Inadequate subcooling temperature range.

Problem Description: The display range on both trend graphs is from 100 0 F subcooled to 50oF superheated. The adverse containment condition in the CSF EOP requires a decision based on 120OF subcooling. The SAS range is inadequate to support this decision.

Disposition:

Disposition Prepared by: V & V Review:

Disposition Verified:Signature

EIGEN ENGINEERING, INC. 2.9

/ /

/ / Date

WPS-1000-88-010 REV. 1

Page 91: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 10

References: 1)

2)

3)

Date: 4/22/88

Page 1 of 1

ANL001 (Drawing)

DSPOO8 (Drawing)

FSAR Chap 14 (Ref. 212)

Requirement #: 3.3.4

Subject: RCS pressure Trend graph range.

Problem Description: The RCS pressure trend graph range is

0-2500 psig. The instrument input range for this parameter

is 0-3000 psig. Under an abnormal condition that exceeds

2500 psig the trend graph will be at the top of its range and

will not be usable to follow this parameter. FSAR Chapter 14

Figure 14.1-34 requires a full scale range of over 2700 psia.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:Signature

/ /

_ _ /

_ / / Date

EIGEN ENGINEERING, INC. 2.10 WPS-l000-88-010 REV. 1

Page 92: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 11 Date: 4/22/88

Page 1 of 1

References: 1) ANL 058 (Drawing)

2) CSF F-0.1 (Ref. 23)

3)

Requirement #: 3.1.3

Subject: CSF EOP function is not connected.

Problem Description: CSF EOP F-0.1 requires the monitoring

of Intermediate Range startup rate. The inputs are shown as

"Future" points and are not connected.

Disposition:

Disposition Prepared

V & V Review:

Disposition Verified:Signature

EIGEN ENGINEERING, INC. 2.11

/ / _

/ _ / _

_ / _ / _

Date

WPS-1000-88-010 REV. 1

Page 93: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 12 Date: 4/22/88

Page 1 of 1

References: 1)

2)

3)

Requirement #: 3.7.1

Subject: Configuration Control not available.

Problem Description: The requirement to review documentation of major SPDS interfaces (hardware and software) can not be completed at this time since these documents for hardware and drawing control were not provided for review.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.12

/ / _

/ /

/ _/ _

Date

WPS-1000-88-010 REV. 1

Page 94: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 13 Date: 4/22/88

Page 1 of 1References: 1)

2)

3)

Requirement #: 3.8.1

Subject: Reliability analysis not available.

Problem Description: The requirement to review the reliability analysis and maintenance assumptions can not be completed at this time since these documents were not provided for review.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.13

/ D/

/ _/

/ _ / _

Date

WPS-1000-88-010 REV. 1

Page 95: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 14 Date: 4/22/88

Page 1 of 1References: 1)

2)

3)

Requirement #: 3.11.1

Subject: Human factors review documentation not available.

Problem Description: Although incorporation of human factors principles during generic SAS development has been verified, no information has been provided to verify that the modifications made to develop a plant specific system were reviewed by human factors qualified personnel.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

EIGEN ENGINEERING, INC.

Signature

2.14

/ / / /

/ / Date

WPS-1000-88-010 REV. 1

Page 96: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 15 Date: 4/29/88

Page 1 of 1

References: 1) CSF EOP F-0.1

2)

3)

Requirement #: 3.1.3

Subject: CSF EOP Decision Point.

Problem Description: CSF EOP F-0.1 requires a decision based

on Source Range startup rate. This parameter is not part of

the SPDS parameter set.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.15

/ _/

_/ __ /

/ _/ Date

WPS-1000-88-010

REV. 1

Page 97: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 16

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 001

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 21077

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: ,

V & V Review:

Disposition Verified: eZ fSignat re

EIGEN ENGINEERING, INC.

_6 /$/&Dat Date

2.16 WPS-l000-88-010 REV. 1

Page 98: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT.

Number: 17 Date: 5/2/88

Page 1 of 1

References: 1) ANL 009

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 24070 and 24071

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: / z4 V & V Review:

Disposition Verified f Signature

EIGEN ENGINEERING, INC.

_zn/ _ LE / F Da- te

Date

2.17 WPS-1000-88-010 REV. 1

Page 99: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 18

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 001

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 29012

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: V & V Review:

Disposition Verified Sinat i e

EIGEN ENGINEERING, INC. 2.18

/e8 / s-, a-i

Date

WPS-1000-88-010 REV. 1

Page 100: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 19

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page I of 1

References: 1) ANL 012

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 29004

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: V & V Review: J Disposition Verifiedakgep,

f Signavre

EIGEN ENGINEERING, INC. 2.19

S/

Y?

L/ /i~& Date

WPS-1000-88-010 REV. 1

Page 101: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 20 Date: 5/2/88

Page 1 of 1References: 1) ANL 013

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 29005

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: / &

V & V Review:

Disposition Verified (Signatdre

EIGEN ENGINEERING, INC.

/o?/ 3.S / Xf

Date

2.20 WPS-1000-88-010 REV. 1

Page 102: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 21 Date: 5/2/88

Page 1 of 1

References: 1) ANL 014

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 15045, 21094, 21095, 21096

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by:/ZV & V Review:

Disposition Verified: Signatilre

EIGEN ENGINEERING, INC.

S/ '5D/ t

Date

2.21 WPS-1000-88-010 REV. 1

Page 103: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 22

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 015

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 15046, 21097, 21098, 21099.

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: 4

V & V Review:

Disposition Verified: Signatire

EIGEN ENGINEERING, INC. 2.22

/4 / S / £..

Date

WPS-1000-88-010 REV. 1

Page 104: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 23 Date: 5/2/88

Page 1 of 1References: 1) ANL 020

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 23022

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: V & V Review:

Disposition Verified/Signat re

EIGEN ENGINEERING, INC. 2.23

6 - / J-d

Date

WPS-l000-88-010 REV. 1

Page 105: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 24

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 021

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 15118, 21075, 23021

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: / o

V & V Review:

Disposition Verified:I Signatore

/o /0J /

Date

EIGEN ENGINEERING, INC. 2.24 WPS-1000-88-010 REV. 1

Page 106: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 25 Date: 5/2/88

Page 1 of 1

References: 1) ANL 026

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 15043, 21094, 21095, 21096

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: /4 - zoo.,-

V & V Review:

Disposition Verified: A

Signature Date

EIGEN ENGINEERING, INC. 2.25 WPS-1000-88-010 REV. 1

Page 107: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 26 Date: 5/2/88

Page 1 of 1

References: 1) ANLO27

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 15044, 21097, 21098,

21099

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: 4 V & V Review:

Disposition Verified it C2 F Signaiure

EIGEN ENGINEERING, INC. 2.26

_6 /AL /

Date

WPS-1000-88-010 REV. 1

Page 108: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 27

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 030

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 15123

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by:

V & V Review: 7 Disposition Verified

signature

EIGEN ENGINEERING, INC. 2.27

I" / J~ / r (0o/5SJ/A

Date

WPS-l000-88-010 REV. 1

Page 109: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 28 Date: 5/2/88

Page 1 of 1

References: 1) ANL 031

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 15125

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified Signature

EIGEN ENGINEERING, INC. 2.28

_J _ 7 ?L / /o /j- /ts

_(i S L/& Date

WPS-1000-88-010 REV. 1

Page 110: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 29 Date: 5/2/88

Page 1 of 1

References: 1) ANL 034

2)

3)

Requirement #: 3.6.1

Subiect: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 15124

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared

V & V Review: L

ire

EIGEN ENGINEERING, INC. 2.29

/0 / D a

Date

WPS-l000-88-010 REV. 1

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Number: 30

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of I

References: 1). ANLO35

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 15126

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: V & V Review:

Disposition VerifiedSignat re

EIGEN ENGINEERING, INC. 2.30

Date

WPS-1000-88-010 REV. 1

Page 112: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 31

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 038

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 29010, 29007

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: / 1

V & V Review: =,z Disposition Verified

Signat re

EIGEN ENGINEERING, INC. 2.31

/0 / J /rr

Date

WPS-1000-88-010 REV. 1

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KEWAUNEE V&V DISCREPANCY REPORT ,

Number: 32 Date: 5/2/88

Page 1 of 1

References: 1) ANL 044

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 24068

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified S ign atire

EIGEN ENGINEERING, INC. 2.32

/o / s-/ 77?

/O -/ 94: Date

WPS-1000-88-010 REV. 1

Page 114: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 33 Date: 5/2/88

Page 1 of 1

References: 1) ANL 047

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 24040, 24062

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified. Signat re

EIGEN ENGINEERING, INC. 2.33

lo / J / 8

Date

WPS-l000-88-010 REV. 1

Page 115: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 34 Date: 5/2/88

Page 1 of 1

References: 1) ANL 054

2)

3)

Requirement #: 3.6.1

Subiect: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 48301

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: / rR V & V Review: Disposition Verified

Signature

EIGEN ENGINEERING, INC. 2.34

_ 5 /3/ $'

Date

WPS-1000-88-010 REV. 1

Page 116: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 35 Date: 5/2/88

Page 1 of 1

References: 1) ANL 055

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 48302

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: /

V & V Review:

Disposition Verified E E SignaGure

EIGEN ENGINEERING, INC. 2.35

/~ ~/ /

Date

WPS-1000-88-010 REV. 1

Page 117: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 36 Date: 5/2/88

Page 1 of 1

References: 1) ANL 058

2)

3)

Requirement #: 3.6.1

Subiect: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 4122802, 4122804

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review: 2

Disposition Verifiedi / .( Signat ure

EIGEN ENGINEERING, INC. 2.36

/ / 5- / de

a/teL/ Pr Date

WPS-1000-88-010 REV. 1

Page 118: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT,

Number: 37 Date: 5/2/88

Page 1 of 1

References: 1) ANL 059

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: NM41F, NM42F, NM43F,

NM44F

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: /&Z '

V & V Review:

Disposition Verified: I Signatdre

EIGEN ENGINEERING, INC.

/D /___

_ _/- d/ r

2/ / Date

2.37 WPS-1000-88-010 REV. 1

Page 119: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 38 Date: 5/2/88

Page 1 of 1

References: 1) ANL 060

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 4156401, 4156403

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by:

V & V Review: .

Disposition Verified/ Signatue

EIGEN ENGINEERING, INC. 2.38

__j' - / -F

0C / 5 /FRI Date

WPS-l000-88-010 REV. 1

Page 120: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 39

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 163

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 23030

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: J ZO,4

V & V Review:

Disposition Verified Signatude

EIGEN ENGINEERING, INC. 2.39

to / /77

Date

WPS-l000-88-010 REV. 1

Page 121: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 40 Date: 5/2/88

Page 1 of 1

References: 1) ANL 164

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 15122

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by

V & V Review:

Disposition Verified

EIGEN ENGINEERING, INC. 2.40

'0 / J$ / Eg

Date

WPS-1000-88-010 REV. 1

Page 122: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 41

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 165

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: 15121

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition VerifiedSignat re

EIGEN ENGINEERING, INC.

fo />2 ~k/ 'F

.1z/ D/ Date

2.41 WPS-1000-88-010 REV. 1

Page 123: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT,

Number: 42 Date: 5/2/88

Page 1 of 1

References: 1) IDIGO2

2)

3)

Requirement #: 3.6.1

Subiect: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 52/RTA, 52BYA, 52RTB, 52BYB

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by:/z V & V Revie*:

Disposition 1 erified* fSignatire.

EIGEN ENGINEERING, INC. 2.42

/3 / 5 / ff

Date

WPS-1000-88-010 REV. 1

Page 124: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 43 Date: 5/2/88

Page 1 of 1

References: 1) IDIGO4

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: need sensor identification.

Disposition:

Disposition Prepared by:

V & V Review:._

Disposition Verified Signafure

EIGEN ENGINEERING, INC. 2.43

/0 / pr / gk

Date

WPS-looo-88-010 REV. 1

Page 125: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 44

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) N8029G

2)

3)

Requirement #: 3.6.1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation requirements for the following sensors: 4156501

Disposition:

Additional documentation received from WPS provided the required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: V & V Review: , Disposition Verified

Signatitre'

EIGEN ENGINEERING, INC. 2.44

Date

WPS-1000-88-010 REV. 1

Page 126: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 45

References: 1) N8030G

2)

3)

Requirement #: 3.6.1

Date: 5/2/88

Page 1 of 1

Subject: Electrical Isolation

Problem Description: Unable to determine the isolation

requirements for the following sensors: NM32F

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 215.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verifie *:

EIGEN ENGINEERING,,INC. 2.45

&- / 7

_ 1/ / Date

WPS-1000-88-010 REV. 1

Page 127: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 46 Date: 5/2/88

Page 1 of 1

References: 1) SPDS Design Document (Ref. 211)

2)

3)

Requirement #: 3.4.1

Subject: Data Validation

Problem Description: Although the SAS data validation techniques are adequate, data manipulation in SEER (i.e.

averaging) results in a single input to SAS. This single input will not be subjected to SAS data validation.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.46

/ _/

_ /__ /

/ / Date

WPS-1000-88-010 REV. 1

Page 128: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 47

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 004

2)

3)

Requirement #: 3.2.1

Subject: Scan Intervals

Problem Description: Unable to review scan intervals until

the "DMD" is defined for point: Il001G to I1020G

Disposition: Per Ref. 214 the DMD time for these points is 5

seconds.

Disposition Prepared by:

V & V Review: .A e oa

Disposition Verified:( .' 0z Signafure

EIGEN ENGINEERING, INC. 2.47

/A0 / 5 /&,

10/ S / Date

WPS-1000-88-010 REV. 1

Page 129: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 48 Date: 5/2/88

Page 1 of 1

References: 1) ANL 005

2)

3)

Requirement #: 3.2.3

Subject: Scan Intervals

Problem Description: Unable to review scan intervals until

the "DMD" is defined for point: L8020G and L8021G

Disposition: Per Ref. 214 the DMD time for these points is 5

seconds.

Disposition Prepared by:

V & V Review:

Disposition Verified* I Signakure

EIGEN ENGINEERING, INC. 2.48

/c@ / 9"/ F'd

Date

WPS-lO00-88-010 REV. 1

Page 130: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 49 Date: 5/2/88

Page 1 of I

References: 1) ANL 006

2)

3)

Requirement #: 3.2.1

Subject: Scan Intervals

Problem Description: Unable to review scan intervals until

the "DMD" is defined for point: Ill00G

Disposition: Per Ref. 214 the DMD time for this point is 1

minute.

Disposition Prepared by:

V & V Review:

Disposition Verified Signaure

EIGEN ENGINEERING, INC. 2.49

_,u / 37 / I

/s s ir/F

Date

WPS-1000-88-010 REV. 1

Page 131: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 50

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 014

2)

3)

Requirement #: 3.2.1

Subject: Scan Intervals

Problem Description: Unable to review scan intervals until

the "DMD" is defined for point: P8021G

Disposition: Per Ref. 214 the DMD time for this point is 1

minute.

Disposition Prepared by: )6 e t

V & V Review:.

Disposition Verified signature Date

EIGEN ENGINEERING, INC. 2.50 WPS-1000-88-010 REV. 1

Page 132: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 51

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 015

2)

3)

Requirement #: 3.2.1

Subject: Scan Intervals

Problem Description: Unable to review scan intervals until

the "DMD" is defined for point: P8022G

Disposition: Per Ref. 214 the DMD time for this point is 1

minute.

Disposition Prepared by: / &A

V & V Review:

Disposition Verified Signatire

EIGEN ENGINEERING, INC. 2.51

_0/ 5 /~

Date

WPS-1000-88-010 REV. 1

Page 133: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 52

KEWAUNEE V&V DISCREPANCY REPORT,

Date: 5/2/88

Page 1 of 1

References: 1) ANL 026

2)

3)

Requirement #: 3.2.1

Subject: Scan Intervals

Problem Description: Unable to review scan intervals until

the "DMD" is defined for point: P8021G

Disposition: Per Ref. 214 the DMD time for these points are

1 minute.

Disposition Prepared by:

V & V Review:

Disposition Verified(e.i) Signat re

EIGEN ENGINEERING, INC. 2.52

// / - / 8t

Date

WPS-l000-88-010 REV. 1

Page 134: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 53 Date: 5/2/88

Page 1 of 1

References: 1) ANL 027

2)

3)

Requirement #: 3.2.1

Subject: Scan Intervals

Problem Description: Unable to review scan intervals until

the "DMD" is defined for point: P8022G

Disposition: Per Ref. 214 the DMD time for this point is 1

minute.

Disposition Prepared by: zm! t,

V & V Review:

Disposition Verified: SignatIe3

EIGEN ENGI NEERING, INC. 2.53

/ J // { Date

WPS-1000-88-010 REV. 1

Page 135: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 54

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) ANL 037

2)

3)

Requirement #: 3.2.1

Subject: Scan Intervals

Problem Description: Unable to review scan intervals until

the "DMD" is defined for point: L8022G, L8023G

Disposition: Per Ref. 214 the DMD time for these points is 5

seconds.

Disposition Prepared by: ZV

V & V Review:

Disposition Verified L 9 Signat re

EIGEN ENGINEERING, INC. 2.54

CQ/ -5- /S? Date

WPS-1000-88-010 REV. 1

Page 136: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 55

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

References: 1) IDIGO2

2)

3)

Requirement #: 3.2.1

Subiect: Scan Intervals

Problem Description: Unable to review scan intervals since

scan times for digital points is not given: Y0009L

Disposition: Per Ref. 214 the scan time is 0.25 seconds.

Disposition Prepar d by: )&

V & V Review:

Disposition Verified: Signatdre

EIGEN ENGINEERING, INC. 2.55

~ 5// / FF -/ :5_/ Prf Date

WPS-1000-88-010 REV. 1

Page 137: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Number: 56

References: 1)

KEWAUNEE V&V DISCREPANCY REPORT

Date: 5/2/88

Page 1 of 1

IDIGO4 Status: Closed

2)

3)

Requirement #: 3.2.1

Subject: Scan Intervals

Problem Description: Unable to review scan intervals since scan times for digital points is not given: XS002L

Disposition: Per Ref. 214 the scan time is 0.25 seconds.

Disposition Prepared by:

V & V Review:

Disposition Verified Signafure

EIGEN ENGINEERING, INC. 2.56

/0 /~/7 __{L/ 5 / g1F

Date

WPS-1000-88-010 REV. 1

Page 138: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 57 Date: 5/2/88

Page 1 of 1

References: 1) ANL 011

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 29012

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified Signabbure

EIGEN ENGINEERING, INC. 2.57

/0 /J7 /d' /0 / ,? E

Date

WPS-1000-88-010 REV. 1

Page 139: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number; 58 Date: 5/2/88

Page 1 of 1

References: 1) ANL 012

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 29004

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by:V & V Review: . Disposition Verified: ,

fSignatuqe '

EIGEN ENGINEERING, INC. 2.58

_ / J / if

Date

WPS-1000-88-010 REV. 1

Page 140: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 59 Date: 5/2/88

Page 1 of 1

References: 1) ANL 013

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs display range. The engineering units of the input ranges for the following sensors is required: 29005

Disposition:

Additional documentation received from WPS provided the required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared bX: t 2 V & V Review:

Disposition Verifie :, .I Signatlre

EIGEN ENGINEERING, INC. 2.59

/0 / 35 /

Date

WPS-1000-88-010 REV. 1

Page 141: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 60 Date: 5/2/88

Page 1 of 1

References: 1) ANL 014 and 015

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: need flow units for.

1438.297 inwc for 23001, 23005, 23002 and 23007

Disposition:

Additional documentation received from WPS provided the

required information. See References 217 and 223.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review: J Disposition Verified

Signature

EIGEN ENGINEERING, INC. 2.60

Id / -/ OF

Date

WPS-1000-88-010 REV. 1

Page 142: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 61 Date: 5/2/88

Page 1 of 1

References: 1) ANL 020

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs display range. The engineering units of the input ranges for the following sensors is required: 23022

Disposition:

Additional documentation received from WPS provided the required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: A'V

V & V Review: r Disposition Verified:(I -' '

Signature

EIGEN ENGINEERING, INC. 2.61

ao

Date

WPS-1000-88-010 REV. 1

Page 143: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 62 Date: 5/2/88

Page 1 of 1

References: 1) ANL 021

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 23021

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: Ad

V & V Review:

Disposition Verified

EIGEN ENGINEERING, INC. 2.62

/6A / 5YA/ /o / 3 /6hP

Date

WPS-1000-88-010 REV. 1

Page 144: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 63 Date: 5/2/88

Page 1 of 1

References: 1) ANL 026 and 027

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: need flow units for

368.5195 inwc for 23003, 23009, 23004 and 23011

Disposition:

Additional documentation received from WPS provided the

required information. See References 217 and 223.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: V & V Review: .

Disposition Verified T14' SignatEreN

EIGEN ENGINEERING, INC. 2.63

/0 / CD/X

_12/ /~ Date

WPS-l000-88-010 REV. 1

Page 145: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 64 Date:

Page 1 of 1

References: 1) ANL 037 & 005

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review since the

input is calculated by the ICCMS and is not given on the

drawing.

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review: .

Disposition Verifie :

EIGEN ENGINEERING, INC. 2.64

/0/ 52fgb

Date

WPS-1000-88-010 REV. 1

Page 146: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 65 Date: 5/2/88

Page 1 of 1

References: 1) ANL 038

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs display range. The engineering units of the input ranges for the following sensors is required: 29010 and 29007

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by: d664 V & V Review:

Disposition Verified: Signatilre

EIGEN ENGINEERING, INC. 2.65

Date

WPS-1000-88-010 REV. 1

Page 147: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 66 Date: 5/2/8,8

Page 1 of 1

References: 1) ANL 054

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 48301

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: ao/ V & V Review:

Disposition Verified t SSignat re

EIGEN ENGINEERING, INC. 2.66

Date

WPS-1000-88-010 REV. 1

Page 148: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 67 Date: 5/2/88

Page 1 of 1

References: 1) ANL 055

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 48302

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised .(Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review: ME

Disposition Verified SignaIre

EIGEN ENGINEERING, INC. 2.67

/4 / J~ / rt

Date

WPS-1000-88-010 REV. 1

Page 149: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 68 Date: 5/2/88

Page 1 of 1

References: 1) ANL 058 (Future)

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 4122802 and 4122804

(Future Points)

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review: ,

Disposition Verified Sig aEIre

EIGEN ENGINEERING, INC. 2.68

5 // /f

Date

WPS-1000-88-010 REV. 1

Page 150: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 69 Date: 5/2/88

Page 1 of 1

References: 1) ANL 060

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 4156401 and 4156403

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by

V & V Review:

Disposition Verified(.

EIGEN ENGINEERING, INC. 2.69

/4 / r / ASB2

Date

WPS-1000-88-010 REV. 1

Page 151: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 70 Date: 5/2/88

Page 1 of 1

References: 1) ANL 163

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 23030

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: _,

V & V Review:

Disposition Verifie Signat re

EIGEN ENGINEERING, INC.

/0 /s- /Jt

_Q/ - / 1t Date

2.70 WPS-1000-88-010 REV. 1

Page 152: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 71 Date: 5/2/88

Page 1 of 1

References: 1) IDIG15

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 23024, 23025, 23026,

23027, 23028, and 23029

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review: Z 1 Disposition Verified:

f Signattre

EIGEN ENGINEERING, INC.

Date

2.71 WPS-1000-88-010 REV. 1

Page 153: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT,

Number: 72 Date: 5/2/88

Page 1 of 1

References: 1) N8029G

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs

display range. The engineering units of the input ranges for

the following sensors is required: 4156501

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared

V & V Review: que

Disposition Verified

EIGEN ENGINEERING, INC.

/0 / / d

Date

2.72 WPS-1000-88-010 REV. 1

--- I

Page 154: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE.V&V DISCREPANCY REPORT

Number: 73 Date: 5/2/88

Page 1 of 1

References: 1) N8030G

2)

3)

Requirement #: 3.3.1

Subject: Input Ranges

Problem Description: Unable to complete review of input vs display range. The engineering units of the input ranges for the following sensors is required: NM32F

Disposition:

Additional documentation received from WPS provided the required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified Signa iur e

EIGEN ENGINEERING, INC.

//4 / P

Date

2.73 WPS-1000-88-010 REV. 1

Page 155: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 74 Date: 5/3/88

Page 1 of 1

References: 1) ANL 005

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 20.00000

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: 44:

V & V Review:

Disposition Verified I Signat re

EIGEN ENGINEERING, INC. 2.74

Date

WPS-1000-88-010 REV. 1

Page 156: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 75 Date: 5/3/88

Page 1 of 1

References: 1) ANL 011

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 1.00 and

2.30258

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:-,

V & V Review:

Disposition Verified Signakure

EIGEN ENGINEERING, INC.

_ Q/D_ /e Date

2.75 WPS-1000-88-010 REV. 1

Page 157: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 76 Date: 5/3/88

Page 1 of 1

References: 1) ANL 012

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 2.30258 and

10.0000

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition VerifiedSignaiure

EIGEN ENGINEERING, INC.

/ /J/Da JA/5 /71 Date

2.76 WPS-1000-88-010 REV. 1

Page 158: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT,

Number: 77 Date: 5/3/88

Page 1 of 1

References: 1) ANL 013

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 2.30258 and

10.0000

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified

EIGEN ENGINEERING, INC.,

i'd /Ja- /

Date

2.77 WPS-1000-88-010 REV. 1

Page 159: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 78

References: 1) ANL 020

2)

3)

Requirement #: 3.4.2

Date: 5/3/88

Page 1 of 1

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms since constants used do not have traceability to source data.

The following constants need to be verified: 1.000 and 55.000

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by.: wxolA_

V & V Review:

Disposition Verified Signakure

EIGEN ENGINEERING, INC. 2.78

./o /j4 / p

Date

WPS-1000-88-010 REV. 1

Page 160: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 79 Date: 5/3/88

Page 1 of 1

References: 1) ANL 021

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 1.0000 and

49.95019. The accuracy of the CRV coefficients for F9134G

can not be verified. The accuracy of FLW Base Temp, press,

and specific vol values for F0134F can not be verified.

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified

EIGEN ENGINEERING, INC. 2.79

/0/ 6S /, Date

WPS-1000-88-010 REV. 1

Page 161: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 80 Date: 5/3/88

Page 1 of 1

References: 1) ANL 026

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 230.7930. The

accuracy of the CRV coefficients for F9466G can not.be

verified. The accuracy of the FLW Base Temp, press and

specific volume values for F0466F and F0467F can not be

verified.

Disposition:

Additional documentation received from WPS provided the

required information. See References 217 and 223.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: 4

V & V Review:

Disposition Verified Signdture

EIGEN ENGINEERING, INC.

Date

2.80 WPS-1000-88-010 REV. 1

Page 162: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT ,

Number: 81 Date: 5/3/88

Page 1 of 1

References: 1) ANL 027

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 230.7930. The

accuracy of the CRV coefficients for F9476G can not be

verified. The accuracy of the FLW Base Temp, press and

specific volume values for F0476F and F0477F can not be

verified.

Disposition:

Additional documentation received from WPS provided the

required information. See References 217 and 223.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: /

V & V Review:

Disposition Verifie I Signatkre

EIGEN ENGINEERING, INC.

Date

2.81 WPS-1000-88-010 REV. 1

Page 163: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 82 Date: 5/3/88

Page 1 of 1

References: 1) ANL 037

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms since constants used do not have traceability to source data. The following constants need to be verified: 20.000

Disposition:

Additional documentation received from WPS provided the required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by:

V & V Review: 4 Disposition Verified

Sign ture

EIGEN ENGINEERING, INC. 2.82

/~'5, gd' L/ 5Z / L

Date

WPS-1000-88-010 REV. 1

Page 164: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

I

KEWAUNEE V&V DISCREPANCY REPORT

Number: 83 Date: 5/3/88

Page 1 of 1

References: 1) ANL 038

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 2.30258 and

10.000.

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by: V & V Review:

Disposition Verified & Signaure

EIGEN ENGINEERING? INC. 2.83

/V / fl / Jh't

Date

WPS-1000-88-010 REV. 1

Page 165: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 84 Date: 5/3/88

Page 1 of 1

References: 1) ANL 060

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 8.000, 5.000,

5.000 and 2.29998

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified Signat re

EIGEN ENGINEERING, INC. 2.84

/0 / 5/ ff

D t / Date

WPS-1000-88-010 REV. 1

Page 166: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 85 Date: 5/3/88

Page 1 of 1

References: 1) ANL 163

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms since constants used do not have traceability to source data. The following constants need to be verified: 1.000 and. 3000.000

Disposition:

Additional documentation received from WPS provided the required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified Signatfre

EIGEN ENGINEERING, INC. 2.85

/fI / y- 4/ 2y

Date

WPS-1000-88-010 REV. 1

Page 167: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 86 Date: 5/3/88

Page 1 of 1

References: 1) IDIGl5

2)

3)

Requirement 1: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 1.8000

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified

EIGEN ENGINEERING, INC. 2.86

y- / ks- / re _Q /5-/ ft

Date

WPS-1000-88-010 REV. 1

Page 168: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 87 Date: 5/3/88

Page 1 of 1

References: 1) N8029G

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 10.000, 6.000,

5.000, 1.000 and 2.29998

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified IF.Sigdature

EIGEN ENGINEERING, INC. 2.87

/d /_SC_/AL /0, ~g

Date

WPS-1000-88-010 REV. 1

Page 169: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 88 Date: 5/3/88

Page 1 of 1

References: 1) N8030G

2)

3)

Requirement #: 3.4.2

Subject: Algorithm constants

Problem Description: Unable to complete review of algorithms

since constants used do not have traceability to source data.

The following constants need to be verified: 10.000, 6.000,

5.000, 1.000 and 2.29998

Disposition:

Additional documentation received from WPS provided the

required information. See Reference 217.

The Design Document Package has been revised (Ref 224), and

this discrepancy is closed.

Disposition Prepared by:

V & V Review:

Disposition Verified SignaIre

EIGEN ENGINEERING, INC. 2.88

/o/ /

/J0Q / / W Date

WPS-1000-88-010 REV. 1

Page 170: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

KEWAUNEE V&V DISCREPANCY REPORT

Number: 89 Date: 5/3/88

Page 1 of 1

References: 1) SPDS Lesson Plan (Ref. 218)

2)

3)

Requirement #: 3.5.1

Subject: Continuous display of SPDS

Problem Description: Although the SPDS Lesson Plan states that the top level display should always be displayed on one of the Control Room SAS CRT's, there were no administrative procedures submitted for review to document this requirement.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.89

/ /

/ /

/ _/

Date

WPS-1000-88-010 REV. 1

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KEWAUNEE V&V DISCREPANCY REPORT

Number: 90 Date: 9/30/88

Page 1 of 1

References: 1) SAS Lesson Plan (Ref. 218)

2)

3)

Requirement #: 3.10.2

Subject: Procedures and Training

Problem Description: Operator training for response to accident conditions does not include available/unavailable SPDS.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

/ /

/ /

/ / DateSignature

EIGEN ENGINEERING, INC. 2.90 WPS-l000-88-010 REV. 1

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KEWAUNEE V&V DISCREPANCY REPORT,

Number: 91 Date: 9/30/88

Page 1 of 1

References: 1) SAS Lesson Plan (Ref. 218)

2)

3)

Requirement #: 3.10.3

Subject: Procedures and Training

Problem Description: Operator training does not include use

of SAS during normal, abnormal and emergency operations.

Disposition:

Disposition Prepared

V & V Review:

Disposition Verified:Signature

/ /

_ / /

_ / /

Date

EIGEN ENGINEERING, INC. 2.91 WPS-1000-88-010 REV. 1

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KEWAUNEE V&V DISCREPANCY REPORT

Number: 92 Date: 9/30/88

Page 1 of 1

References: 1) SPDS Lesson Plan (Ref. 211)

2) WPS V&V Comment Response (Ref. 217)

3)

Requirement #: 3.4.2

Subject: Accuracy of critical plant variables

Problem Description: Reference 211, (drawing WPS-1000-IDIGl5)

bases the status of the Reactor Coolant Pumps (Running/Off)

on Reactor Coolant Loop Flow relative to 20%.

Reference 217 (discrepancy 486) indicates that flow

transmitteRoutput of 1.8 volts is equivalent to 49.19%

reactor coolant flow.

This could be very misleading since during low power

operation, (i.e. flow <49.19%) the SAS will indicate that the

reactor coolant pumps are not running.

Disposition:

Disposition Prepared

V & V Review:

Disposition Verified:Signature

_ _/ /

_ / /

/ _/

Date

EIGEN ENGINEERING, INC. 2.92 WPS-1000-88-010 REV. 1

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KEWAUNEE V&V DISCREPANCY REPORT

Number: 93 Date: 10/4/88

Page 1 of 1

References: 1) SPDS Design Document (Ref 224) 2) WPS V&V Response (Ref 217 3) ANL 020 & 021

Requirement #: 3.3.1

Subject: Display Accuracy

Problem Description: Per reference 217, the ranges of charging and letdown flow are 0-110 and 0-100 gpm, respectively as shown in Ref 224 (drawing DSP015), the SAS indicates ranges of 0-150 gpm.

1. This could be misleading since SAS implies considerably more flow available than rated for these systems.

2. Per Ref 224 (drawing DSP002) CHG-LDN flow differential indicates ranges of 0 to + 150 gpm. The range of this parameter should be -100 to 110 gpm.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:

Signature

EIGEN ENGINEERING, INC. 2.93

/ /

/ /

/ __/ Date

WPS-1000-88-010 REV. 1

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KEWAUNEE V&V DISCREPANCY REPORT

Number: 94

References:

Date: 10/4/88

Page 1 of 1

1)

2)

3)

SPDS Design Document (Ref 224)

WPS V&V Response (Ref 217)

ANL 163

Requirement #: 3.2.1

Subject: Current status of critical plant variables

Problem Description: Per reference 217, the range of RHR flow

is 0-6000 gpm. Per reference 224 (drawing DSP003) the SAS

range for RHR flow is 0-4000 gpm. The SAS range is

inadequate for RHR flows between 4000 and 6000 gpm.

Disposition:

Disposition Prepared by:

V & V Review:

Disposition Verified:Signature

/ / / /

Date

EIGEN ENGINEERING, INC. 2.94 WPS-1000-88-010 REV. 1

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ATTACHMENT 3

Instructions For The Verification

of SPDS Composed Points

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Instructions for Verification of, SPDS Control Documentation

The attached checklist identifies the various software controlled attributes of each SPDS point displayed. These attributes, are to be reviewed and compared to other plant documentation (e.g. Instrument Index, Instrument Loop Diagrams, Emergency Operating Procedures, and etc.) and the SPDS design documentation (i.e. SPDS Design Document Package). The following descriptions are intended to provide uniform guidance in the execution and documentation of these comparisons.

1. TOP LEVEL

Verify whether this point appears on a top level display. Put in a Yes or No in the blank.

2. TREND

Verify whether this point is used on a 2nd trend display. If so, write in the name of the display in the blank. If not, write in "None".

3. SCALE

If this point is used for creating a trend display, put in the range of the trend in the blank; otherwise put in "N/A".

EIGEN ENGINEERING, INC. 3.1 WPS-looo-88-010 REV. 0

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4. SAS HI/LOW ALARM:

All numbers or digital logic states used as a comparison

for an'alarm threshold on a top level display are to be

considered "alarms". All alarms in an algorithm shall

be verified for proper implementation as specified in

the SPDS Design Document Package and where applicable

the appropriate CSF. All references utilized to confirm the alarms shall be listed.

5. EOP(CSF) ENTRY VALUE

The EOP entry condition is the first decision point

shown in the F series Emergency Operating Procedures.

Verify that the required variable range being displayed

will provide the operator necessary information to

perform this decision. List reference used to obtain

this value.

6. EOP (CSF) CONTROL VALUE

The EOP control conditions are decision points shown in

the F series EOP's. Verify that the required variable

range being displayed will provide the operator

necessary information to perform this decision. List

references used to obtain these values.

7. INPUT RANGE VERSUS I/O RANGE:

All analog / digital raw data inputs shall be reviewed

for proper range implementation in the point algorithm.

All analog inputs shall have a specified range and

digital inputs shall have a specified binary state (e.g.

open/closed, closed/open, closed/not closed, or on/off).

Only if all the ranges associated with the displayed

EIGEN ENGINEERING, INC. 3.2 WPS-lOOO-88-010 REV. 0

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parameter are correct, should the "Satisfactory" be

designated with a YES. Otherwise,-a discrepancy report

shall be initiated and recorded.

8. ALGORITHM:

The algorithm for all displayed points shall be reviewed

for a consistent integration of all of the above as

specified in the SPDS Display Functional Descriptions.

Also the algorithm shall be reviewed for mathematical

correctness and consistency of engineering units. All

numbers used within equations that are engineering unit

conversion constants or correction factors shall be

considered "Constants". The documentation that

establishes the constants shall be reviewed for adequate

traceability to source data, accuracy of the established

equation and corresponding display precision, and

properly documented signoffs. Only if the algorithm

associated with the displayed parameter is correct,

should "Satisfactory" be designated.

9. CALCULATION ORDER:

All algorithms for displayed points shall be reviewed to

ensure that each calculation within the algorithm uses

the latest available data. That is, each input to a

calculation shall be reviewed to verify that for a given

scan interval, all inputs are determined prior to

performing the calculation. Only if the calculation

order associated with the displayed parameter is

correct, should "Satisfactory" be designated.

Otherwise, a discrepancy report shall be initiated and

recorded.

EIGEN ENGINEERING, INC. 3.3 WPS-looo-88-010 REV. 0

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10. SCAN INTERVALS:

All displayed points, including data input points and intermediate calculations, shall be reviewed for reasonable and consistent update intervals so that the displayed point represents "real time" with respect to other control room instrumentation for the same variable, and is comparable with realistic variable rates of change. Only if the scan intervals associated

with the displayed parameter is correct, should "Satisfactory" be designated. Otherwise, a discrepancy report shall be initiated and recorded.

11. SAFETY RELATED ISOLATION:

All plant input sources for each displayed point shall be compared against the plant instrument index to.

determine if the sensing instrument is safety related. If found to be safety related, the appropriate loop / schematic diagrams shall be reviewed to ensure that an isolation device exists. Only if the isolation

associated with safety related inputs is correct, should "Satisfactory" be designated. Otherwise, a discrepancy

report shall be initiated and recorded.

Should a particular checklist item not pertain to a point, enter NA in the "Satisfactory" column. Upon completion of the checklist, the reviewer shall sign and date the form. A completed and signed form shall exist

for each displayed point.

EIGEN ENGINEERING, INC. 3.4 WPS-1000-88-010 REV. 0

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ATTACHMENT 4

Verification of SAS

Documentation Checklists

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Verification of SAS Documentation

SAS Point: Display Variable Name:

Number P r

Input Name: e-U,,e u Zge /sur5eea

Reqmnts : Variable displayed on:

3.1.1 : Top level: yf 3.3.2 3.3 2 Trend: /f) 60 /&/ %5 Apont Scale: O-- 25-OP5g 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

SAS alarm limits

Low: P9' _// A1/1/,2 Reference: /7 1V7

High: L vQ/:4 AebAl-/71 Reference: _7//___

EOP (CSF) entry value: A/ Ae EOP (CSF): _______

EOP (CSF) control values: _o__ps_ 3

7F0 F0, 3

Input range: /70o-20oo Satisf vs. Satisfactory: 41re/U,00voy x ,

T/O range: O-2$oops y

Algorithm: 15 S

3.2.2 : Calculation order: 4 7'i5

3.2.3 : Scan intervals:

J 3.6.1 * Safety related Isolation:

Prepared by: ,/ Reviewed by:

Date: 2 ff Date: -.2-1?-g-

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Verification of SAS Documentation

SAS Point: /41_11 _ Display Variable Name: Number

Input Name: VPSuXig' 4 , ew

Variable displayed on:

Top level: Yes Trend: 6o 6A,/15 On Scale: 0-/OZ,

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

/X t @rd - Reviewed by:

Date:

SAS alarm limits

Low: _ _ _ _Reference: c17 P7

High: 57 Reference: _ _7_ _ _

EOP (CSF) entry value: Z o EOP (CSF): C__*

EOP (CSF) control values: 32/c* , '-se'

Input range: ____o_ _

VS Satisfactory: Ye 5 I/O range: 0-_007__/

Algorithm:_ _SC4" /5 c ,C

Calculation order: _ __/ _

Scan intervals: _____S

Safety related Isolation: SW /S

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

F.za

a--2 - T

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Verification of SAS Documentation

SAS Point: &/N 3 Display Variable Name:

Number e

Input Name: -/ /e q,( / f

Variable displayed on:

Top level: Y'ts et'sdef q&

Trend: 0/O Scale: A 0 Ao e

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

Prepared by:

Date:

.44 7- av Reviewed by: 4

Date: __

SAS alarm limits

Low: _ /__ _ e Reference:

High: /AAe Reference:

EOP (CSF) entry value: /vo vl EOP ,(CS):

EOP (CSF) control values: 736-00')e

Input range: 50 -450 bFC F VS Satisfactory:SA s

I/O range: P/AJee- lt k

Algorithm: 5ef/7s

Calculation order: ____s __

Scan intervals: 54 1 /s

Safety related Isolation:

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

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Verification of SAS Documentation

SAS Point: /'/ L Display Variable Name:

Number / C E 7 o A1~Cokee rFrXLJ r-A

Input Name: /te Ey,/ e/e oeg -Cou /es

Reqmnts : Variable displayed on:

3.1.1 : Top level: e_5

3.3.2 3.3.3 Trend: _(;o__'s___

Scale: / _ _ _

3.1.4

3.3.5 : SAS alarm limits

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

Low: A^OAle Reference:

High: /VoIVe Reference:

EOP (CSF) entry value: Zh, oF EOP (CSF) F-2,

EOP (CSF) control values: 73CoF F-02.Z

--Zoo 700ooF

Input range: -/00 C~ leoOF VS Satisfactory: Use,'evc/ ',O

I/O range: 1afec ? A' OOFndv

Algorithm: 5# 5

3.2.2 : Calculation order: S_ __s

3.2.3 Scan intervals: 5

3.6.1 : Safety related Isolation: 54A's (Lc s

Prepared by: Reviewed by:

Date: __ Date: _

I~v /~;/3 2~ 4

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Verification of SAS Documentation

SAS Point: /____d _ Display Variable Name:

Number re,,44e lesse/ /eve/

Input Name: geAcA 4 e 11desse-/ /e-e/

Reqmnts : Variable displayed on:

3.1.1 : Top level: 'e (vo e')

3.3.2 (; Coe vOw 3.3.3 Trend: '_eav__

3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4-

b4( -re Z c/ s a( e

Scale: /-fo

SAS alarm limits

Low: A/vo-Ae Reference:

High: /Vo If _Reference:

EOP (CSF) entry value: /VeAer EOP (CSF):

EOP (CSF) control values: dPtZ ______

Input range: __ C VS Satisfactory:

I/O range: /ZeeJ d /ol

Algorithm: A 5

3.2.2 :Calculation order

3.2.3 Scan intervals:

3.6.1 : Safety related Isolation: 515i (54

Prepared by: 1 Reviewed by:

Date: 51 _Date:

-3-__[ _

I

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Verification of SAS Documentation

SAS Point: /_, W- Display Variable Name:

Number Co/ 4/l4,4 lel- A'w

Input Name: 51/6cco/v yety~g .

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

/ 3.2.3

3.6.1

Prepar ed by: ______Reviewed by: J-.r

Date: ,~/'Date: ______

(,ed g,-d 4)

K /~-~2 A?~ r--r-"&I

At ofe / 1!, 5J se C 0./ <Y,-r, Variable displayed on: e " At rue

Top level: Sve,ad c4,4lysi"e 5&//

Trend: KyXold/ Syst'ep, Scale: -/oo k o'f

SAS alarm limits

Low: -. /VOt/ 0 Reference: . - .

High: /V ^At _e Reference:

EOP (CSF) entry value: l.o-a'e EOP (CSF)

EOP (CSF) control values: 30 _ /_oo

Input range: '//e e ' -e e 4C AeWic/ 5417)FM VS Satisfactory: Z/5 eueWCwcy

I/O range: -/,0 -1o 5o F

Algorithm: _____/ __

Calculation order:

Scan intervals: / '

Safety related Isolation: SAhs7-s (Z2CS)

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Verification of SAS Documentation

SAS Point: AA/L &(/ Number

Fct e o.r /rO Y

Display Variable Name:

Input Name: // /

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

Reviewed by:

Date:

Variable displayed on:

Top level: * / FMVt Ce ft'ZcJ

Trend: (Or)_______7 Scale: 5o -/so aF

SAS alarm limits

Low: Al%/ e- Reference:

High: _ aIoAe Reference:

EOP (CSF) entry value: AIoAle EOP (CSF):

EOP .(CSF) control values: ,voA/C _

Input range: 20- 50-oo*, VS Satisfactory:

I/O range: 5o-/fD S

Algorithm:

Calculation order: ___fs

Scan intervals: _ ____5

Safety related Isolation: F ' "tfo-7

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

2-1

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Verification of SAS Documentation

SAS Point: 19A/Z. 9 Display Variable Name:

Number o0 d ,,. e / /2?ss

Input Name: ~%,v $9,~vA1 es-v / es-see,

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1,

:

Prepared by:

Date:

~, / i~4~'g

Reviewed by:

Date: X-2_-77

Variable .displayed on:

Top level: p4 V-, ( C ^a '^ EienWe(rT /)

Trend: ____,__mwU PR) Scale: -574 2o0 0 s

SAS alarm limits

Low: IV/Ae Reference: 4/ove

High: * Reference: /Vc /

EOP (CSF) entry value: ______y EOP (CSF): -'S

EOP (CSF) control values: ~ /7, y____

Input range: -5/ t foos/D VS Satisfactory: _/5c

I/O range: S 76. S a '/

Algorithm: 541s

Calculation order: SA _/

Scan intervals: AL7 5

Safety related Isolation:

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Verification of SAS Documentation

SAS Point: 1 Display Variable Name:

Number ;u eh a

Input Name:

Reqmnts : Variable displayed on:

3.1.1 Top level: pA4/ o 6 A no

3.3.2 :e//S: 3.3.3 Trend: 76I!1 v scale: 0-2-2

3.1.4 P0-.22 6et

3.3.5 : SAS alarm limits

: Low: __ Reference: Ne e

High:_ e__L Reference:

3.1.3 EOP (CSF) entry value: No-nI'e EOP (CSF):

3.5.1 : EOP (CSF) control values: 67-

Input range: 0-22 ee/

VS : I/O range: -,22

SAlgorithm: 5A-17s

Satisfactory:

3.2.2 : Calculation order:

3.2.3 Scan intervals: /75

3.6.1 : Safety related Isolation: _ _ __ _

Prepared by: Reviewed by:

Date: Date:

/0)/, __(___IV("___- r

3.2.1 3.3.1 3.3.4

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Verification of SAS Documentation

SAS Point: // Display Variable Name:

Number

Input Name: /

CVA, Oeelvo

Reqmnts

3.1.1 3 .3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

Prepared by:

Date:

4 Reviewed by:

Date: r-_-_t

: Variable displayed on:

* Top level: ( C

Trend: (W me4 T Scale: __

: SAS alarm limits

: Low: Iva__ __ Reference:

: High: I/V_ g 0___Reference:

* EOP (CSF) entry value: /VoAte EOP (CSF):

: EOP (CSF) control values: A/OvO __

Input range: / 2 77z/w a

VS Satisfactory: Co a g / / o

: I/O range: o Xs, s e .

Algorithm: Fdatde

Calculation order: _ _ _ _

Scan intervals: Fa

Safety related Isolation: fa/e As e

3.2.2

3.2.3

3.6.1

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Verification of SAS Documentation

SAS Point: _t/ _

NumberDisplay Variable Name:

Input Name:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

21 3.2.1 3.3.1 3.3.4

3.2.2

/ 3.2.3

3.6.1

Variable displayed on:

Top level: Ye5

Trend: e Scale: /-/oo 000 a

SAS alarm limits

Low: 1yo y/e Reference:

High: A/IA/e Reference:

EOP (CSF) entry value: /10Ae EOP (CSF):.

EOP (CSF) control values: 2 $ __S

Input range: e -r VS / Satisfactory:

I/O range://Oo ;//

Algorithm: I 5cep 7 v Jr 7

Calculation order: SA/5

Scan intervals:

Safety related Isolation:

Prepared by: . ,

Date:

Reviewed by: / P

Date: 57_-_3 __r&

49

a Alal ^t/. e y/

-1393

:

*

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Verification of SAS Documentation

SAS Point: AA/1 - Display Variable Name:

Number /9 Ile E-re c,14 oYkd

Input Name:Ag E~ec-/v~ i~d

Reqmnts : Variable displayed on:

3.1.1 : Top level: ePa a ec c^1/e 3.3.2 Sae 6

3.3.3 Trend: Ahines vzS cale: /0 -4 14

3.1.4

SAS alarm limits

Low: /VOA/e Reference:

High: /6 0 0 CPin Reference: /o /

EOP (CSF) entry value: AVo4e EOP (CSF): A1/4

EOP (CSF) control values: /_

/00/0 (a 1F

Input range: -4__s

VS Satisfactory: I/O range: /0 A /0 CP47

Algorithm:

3.2.2 Calculation order:

3.2.3 : Scan intervals: _:__4_h ___

3.6.1 Safety related Isolation: 4 14 fat - 5

Prepared by: A * Reviewed by:

Date: 3_ Date: 3 -8

Ad/~ft

L j~4 Tfo~-~

3.3.5

3.1.3 3.5.1

13.2.1 3.3.1 3.3.4

II

II

Page 194: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /A1 /3 Display Variable Name:

Number ~ ~~

Input Name:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

(I

3.2.2

.3.2.3

I 3.6.1

Variable displayed on:

Top level: Ae o( 44/ Ae Trend: 4^4 4k 4 si'4,c Scale: /0________

SAS alarm limits

Low: _V __/__ Reference:

High: £000 Of-4 Reference:

EOP (CSF) entry value: A1o /-e EOP (CSF):

EOP (CSF) control values: Ad_^__

Input range: CA VS .Satisfactory: 5/

I/O range: /o /O P S f

Algorithm: S0 ± og4s

Calculation order: 5

Scan intervals: 5A/5

Safety related Isolation: g1 & 5*9 5

Prepared by: -_

Date: 5

f'&'i /c,/~h9 (O41fr~ 9- L

Reviewed by:

Date: 37_ 3_-8_F

510 & awlk-1

Page 195: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /9 / Number

Display Variable Name:

Input Name:

Reqmnts

3.1.1 3.3.23.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3)3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Variable displayed on:

Top level: A10

Trend: _e ______ F / Scale: 0 - 0 (/0') / s//

SAS alarm limits

Low: A/oALe, Reference:

High: _l__A//e Reference:

EOP (CSF) entry value: 4/ow/e EOP (CSF):

EOP (CSF) control values: AvAe

Input range: 4 VS ) Satisfactory: .

I/O range: 0#7

Algorithm: 54/3 6K2/3)

Calculation order:

Scan intervals:

Safety related Isolation: t 54%s

Prepared by:

Date:

~2 / el/gs A

Reviewed by:

Date: __

d.3~8Iv

ioi~s/&i QQ e#zVk~ 9J~P

I)

9-I

.5 574-/9~ r-cto-

Page 196: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: AW /5 Display Variable Name: Number 4/6 8 5 F/

Input Name: /26 5

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

/ 3.2.3 AZ 3.6.1

Variable displayed on:

Top level: A10

Trend: Feec//l/wvy5/An F/k," Scale: 0- /

SAS alarm limits

Low: A/ove Reference:

High: /V_ _e Reference:

EOP (CSF) entry value: Alo -e EOP (CSF):_

EOP (CSF) control values: /ow 1ve

Input range: VS Satisfactory:

I/O range: 0-(/ /

Algorithm: 54/ (CeA.213)

Calculation order:

Scan intervals:

Safety related Isolation:

Prepared by:

Date: 5

K4/3 /o/gf AX5

Reviewed by: e

Date:

f

J - 3 r

Page 197: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: __/_ _/_ Display Variable Name: Number

Input Name:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date: Zz /1Reviewed by:

Date:

Variable displayed on:

Top level: Yes

Trend: S/ei C4 (ye)// scale: -/oo

SAS alarm limits

Low: /5_ _ _Reference: /97/P7

High: _UZ Reference: / -7/e7

EOP (CSF) entry value: '_2Z 'L5 ]EOP (CSF): F-&"*3

EOP (CSF) control values: F-067 03

Input range: 0-/10021 VS Satisfactory: CA nfe C0

I/O range: 0 _St t C

Algorithm: !54 /7

Calculation order: 5-14A45

Scan intervals: _ _ _

Safety related Isolation: 5AA'5

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

*

*

Page 198: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: AA 1/ Display Variable Name: Number

Input Name:

Variable displayed on:

Top level: eS

Trend: 54A66 4 l/eve/ Scale: O-/0o1

SAS al

Low:

High:

EOP (C

EOP (C

arm limits

__________o __ Reference: /V7 P7

6___ 'Reference: /Y7/e 7

SF) entry value: 7, D87 EOP (CSF): FA -3 SF) control values: <__7___ F-0s3

_____F-0,3

Input range: -/0oot_0 VS

I/O range: O/a'1

Algorithm: _4175

Calculation order;

Scan intervals: 543

Safety related Isolation: _ ___

Prepared by:

Date:

Reviewed by:

Date:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Satisfactory: PsclP CA

P -Z-81' 2 -8r

5~ / /W A le /4,/ ,, 1

Page 199: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /___O Display Variable Name:

Number

Input Name: ch' //M

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

113.2.1 3.3.1 3.3.4

3.2.2

3.2.3

f 3.6.1

Variable displayed on:

Top level: _1 _9

Trend: d/4,7 Z K7< ^ Scale:

SAS alarm limits

Low: __/_ 0 _V_ e Reference:

High: /Vo /e Reference:

EOP (CSF) entry value: /V0/ e EOP (CSF):_

EOP (CSF) control values: N/OA/ e

Input range: VS Satisfactory: IO /A

I/O range: 0-50 9LpPft

Algorithm: :reyry' - s

Calculation order:

Scan intervals: _ ___5

Safety related Isolation:

Prepared by:

Date:

,Ve / 01r

A ~//4-~ Reviewed by: C9 E&7

Date: 5_-_ 3-8 8

0 -/,5-0 6 ? w

Page 200: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /_ _ Display Variable Name: Number

//a,. /r,41z)

Input Name: //a vb( /0i"-

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

I 3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

/ 3.6.1

Variable displayed on:

Top level: A/o

Trend: C 0y),w Scale: O0'O 6kPA

SAS alarm limits

Low: A/pale Reference:

High: /vo e Reference:

EOP (CSF) entry value: ;VA/ve EOP (CSF):

EOP (CSF) control values: A/lw e

Input range: VS Satisfactory: P/ e 7c

I/O range: 6_-S_,_ n .tf or

Algorithm:

Calculation order: 5 SA

Scan intervals: /AJ5

Safety related Isolation:

Prepared by:

Date:

Reviewed by:

Date:

J -

Page 201: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: AI fl Display Variable Name:. Number

Input Name:

Variable displayed on:

Top level: Ye s

Trend: S4^ (w , es1 Scale: 0 -/11a/,s y

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Calculation order: 51f/S

Scan intervals:

Safety related Isolation: 5#71,

Prepared by:

Date: 3/ 2/ffReviewed by:

Date: _ -. 2-__ __

SAS alarm limits

Low: 5O0 P 7 Reference: /1Y7/'7

High: /050 PS F Reference: 17/j y

EOP (CSF) entry value: A/oa e EOP (CSF):

EOP (CSF) control values: __ _f5 _-0. *3

Input range: _-__you__,_

VS Satisfactory: le5 I/O range: V-/'oo ety

Algorithm: 17

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

/A.- /essd

Page 202: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

*SAS Point: 3/ &2 Display Variable Name: Number Y,6 P/tessude

Input Name:

: Variable displayed on:

Top level: _ _ _

Trend: S Af 7W KS cale: ____ S______

: SAS alarm limits

Low: 500 P', Reference: '7/o0

* High: /0oS7 Reference: /'f7/O7

: EOP (CSF) entry value: /_V_ _ EOP (CSF):

EOP (CSF) control values: P 3

: Input range: VS Satisfactory: . 5

I/O range: 0 -/ds5'

Algorithm: 6 5

Calculation order: 5/#

Scan intervals: 5-A5

Safety related Isolation: _5_ _7s

Prepared by:

Date: 3/ d'J2

Reviewed by:

Date: _ _ _ _ _

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

___

____

__

_

*

Page 203: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: _______

NumberDisplay Variable Name:

- 51! .lea/ "rxq 06

Input Name:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3 3.2.1 3.3.1 3.3.4

31

1 2/

3.2.2

3.2.3

3.6.1

: Variable displayed on:

: Top level: /Vo

Trend: f 5 Abdz. Scale: ____________

: SAS alarm limits

: Low: __/ __ e Reference:

: High: Al/c?_ve Reference:

: EOP (CSF) entry value: A/o e EOP (CSF):

EOP (CSF) control values: /701P fF .

: Input range: 5A17 VS Satisfactory:

: I/O range: ,-e (o s4

Algorithm:

: Calculation order:

: Scan intervals: 7 L4A-S

: Safety related Isolation: 64, Aei 5--24 5

Prepared by: st( ,

Date: f__

~?ef// S//~ K q^9

Reviewed by:

Date: _ _ _ _ _ _ _

5( Fe6 / F/&-'

d

Page 204: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: I;//&Z,7 Number

Display Variable Name:

5/e bc/ 47, A

Input Name: j s e2 leod Vews

Variable displayed on:

Top level: NO

Trend: ________/_ Scale: o-9 /1s/Ae(fo09

SAS alarm limits

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

*2.v-- / /3/e8 '(

lrvz111F

Reviewed by:

Date: __ rr5/31M

&f3-8

Low: /o _ e Reference:

High: A/erve Reference:

EOP (CSF) entry value: A{o^/- EOP (CSF):

EOP. (CSF) control values: '.2Olp/w1

Input range: VS Satisfactory: _ _ePc 3o

I/O range: q ) Si t .

Algorithm: & lye M.

Calculation order: S _

Scan intervals: gy t :3 - 5

Safety related Isolation: Pe1 ( 'L.

31

I I Al

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Page 205: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: A__.__

NumberDisplay Variable Name:

Input Name: I/l! ', L

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

1 3.6.1

Variable displayed on:

Top level:

Trend: 44 de &70 77l Scale: So- Ze / k-1/< /e A e (ir)71// 5 62- 6 o F

SAS alarm limits

Low: /__^ __ e- Reference:

High: A/a_ __ Reference:

EOP (CSF) entry value: A/o l/ EOP (CSF):

EOP (CSF) control values: /MoVa

Input range: 5-6529 b' F VS Satisfactory:

I/O range: 5o06Jo ,e1.

Algorithm: hm_5

Calculation order: _ _ _ _

Scan intervals:

Safety related Isolation: o;:__:____-_____r

i- A-/I;Prepared by:

Date: 2

Reviewed by: E =

Date: r-_z _-rr

-9

tq &Ie; q-,9

Page 206: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: / 31 Display Variable Name:

Number rem

I n put N am e: Zey Z1-,' 4,a g

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

21 3.6.1

Variable displayed on:

Top level: Ala

Trend: F'/e 2Ah4t 7 C7 Scale: 5- - 6 ,0 0 &,Icl7/e (AM,)7//,rTC Iszo -620 07 F

SAS alarm limits

Low: A/od/e Reference:

High: /Vo/v e Reference:

EOP (CSF) entry value: Alolve EOP (CSF):

EOP (CSF) control values: rdoste

Input range: 5o-65- 2PeF VS ' Satisfactory: /4 5

I/O range: Fo D0 F

Algorithm:______

Calculation order: S___

Scan intervals: ____s

Safety related Isolation: 5-A

-3ir

Prepared by: 6 61 Reviewed by:

Date: _ _ _ _ _Date:

*

Page 207: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /VL f9 Number

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

I 3.6.1

Display Variable Name:

Input Name: 60// /e 7e1 / A5

: Variable displayed on:

: Top level: KeS

Trend: ______ _7f Scale: o6oo bY2 F ,le e (Ate)7//70 362o-62o De; F

: SAS alarm limits

Low: 520ty /vF ALI/7 Reference: AZ7 i Lo: ,55~/f 7 ,Iv7L

High: 5_S____F___e__1/73 Reference: 197/'7

: EOP (CSF) entry value: 4 oorv-fO,., EOP (CSF): / -- AZ

: EOP (CSF) control values: '27o"F 4_

S3 0 0 oF ______,

* Input range: 5o6b7P F VS Satisfactory:. V

: I/O range: j5o 620 F

Algorithm: t A± .

Calculation order: 5_ _ _5

Scan intervals: IS-11 5

Safety related Isolation:

Prepared by: Reviewed by:

Date: Date:

_, P, , n :Date:Date:

'r

Page 208: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: Al/.-N 3 Number

Display Variable Name:

Input Name: C l/ Aed 7* /a,

Variable displayed on:

Top level: Yes

Trend: Scale: -f' -6,o / ,e F -52-,2o v 7 p

: SAS alarm limits

Low: f 204eD § 71he /7 Reference: 1'747

* High: 55'O(P F/bA A'VI/73 Reference: '97/7 : EOP (CSF) entry value: /EOP (CSF): ______

EOP (CSF) control values: >'.27i'oF

F-oq

Input range: 50-a-o 6ve VS

I/O range: 5o-620 Ve FSatisfactory: - ?e s

Algorithm: 50h 75

Calculation order:

Scan intervals:

Safety related Isolation: -t

Prepared by:

Date:I 5A p gg

Reviewed by: J C. Zi Date: J_ -2PF

~~-r / //~gA~1

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

k,-de FA te 7 3 Andce /?A7 e(1V)7R7p

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

5 75

501 .5

tol(,J ff

Page 209: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: A/V Q 37 Display Variable Name: Number

Input Name: 14 4c4 c-7wv

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 21.3.1

3.3.4

3.2.2

1 3.2.3 3.6.1

Variable displayed on:

Top level: 05 o/ le

Trend: /NO

S a e 7d'v' ,/9 ' evAew de

Scale:

SAS alarm limits

Low: A/ov/e Reference:

High: A/oAle Reference:

EOP (CSF) entry value: Aloi/e EOP (CSF):

EOP (CSF) control values: Deee,4s6,a F-''

Input range: CA__ __ _ /_

IOVSange: _ _ _ _ _ _ Satisfactory:

Algorithm: v 4'

Calculation order: 5

Scan intervals: eP k 5 c j,4

Safety related Isolation: 5 Zcas)

Prepared by: Reviewed by:

Date: Date:

/53 g - 3 -9-- -A

Page 210: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /9AL. 3' Display Variable Name: Number S E

Input Name: S7 c- JA

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

/ 3.6.1

Variable displayed on:

Top level: A0

Trend: 4 RoeA, /V, 5 Scale: /O71/v0 C ,0

SAS alarm limits

Low: IVd^ve Reference:

High: A/o __ Reference:

EOP (CSF) entry value: _Vo___f EOP (CSF):

EOP (CSF) control values: /vo__ _

Input range: A 6 J.A/ VS i Satisfactory: 3

I/O range: /0 14 / C/ ,

Algorithm:

Calculation order: 5

Scan intervals: ____75

Safety related Isolation: Z4 s

Prepared by:

Date:

/ lolyle/ /c//f ~

Reviewed by:

Date: J_ - 3-83'T5< 3, F

Page 211: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS. Point: /_____ Display Variable Name:

Number S /Le/ /eve/

Input Name: ScOaVece

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Aroti. Set b/s Variable displayed on:

Top level: Vf5l Intss/He/

Trend: /V 14e vlel Scale: / 94 /0 6?/'5

SAS alarm limits

Low: A!/Ote Reference:

High: A/oVe- Reference:

EOP (CSF) entry value: A/loaAe EOP (CSF):

EOP (CSF) control values: A/ow_ _

Input range: 5A-54s VS Satisfactory:

I/O range: /0 0k/S

Algorithm: hm:____

Calculation order: _ _75

Scan intervals: _ A __ _

Safety related Isolation:

Prepared by:

Date:

Reviewed by: F ,

Date: 5- -_.3 -<'8

1&nevy / w el/

:

Page 212: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: Display Variable Name: Number

Input Name: Cfetd e/- /&A1 ede 2/e/

Variable displayed on:

Top level: ___ _A/

Trend: C/ Sl415 _,4 Scale: 0-/oo:0;C __

SAS alarm limits

Low: /V^e Reference:

High: N1v_ o_ le-Reference:

EOP (CSF) entry value: /aw EOP (CSF):

EOP (CSF) control values: l/voae-

Input range: 0-10_1o

VS I/O range: /0o0

Algorithm: mA5

Satisfactory: V-s

3.2.2

3.2.3

if 3.6.1

Calculation order; 5_ __s

Scan intervals: _ ____

Safety related Isolation:

Prepared by: 4 ; A L

Date: V2Reviewed by:

Date:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

Page 213: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

dec-7e d

Input Name: d /f /^/01 eAlc 4

Variable displayed on:

Top level: _ /Vo

Trend: /vo7&e-

S c a eA b c _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Scale:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

-7 £Reviewed by:

Date:

SAS alarm limits

Low: A/o1'e Reference:

High: A/oAAF'e Reference:

EOP (CSF) entry value: /Va/v -e EOP (CSF):

EOP (CSF) control values: e-l_

Input range: __/___

VS Satisfactory: _________

I/O range: /Vi /?.fct,(12

Algorithm: Ao/ /Red

Calculation order: ____ e_____

Scan intervals: F,_ -e____2

Safety related Isolation: Mo0 Ft-f Powk

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Verification of SAS Documentation

SAS Point: /______ Display Variable Name:

Number

Page 214: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /V17__

Number

4 aF~J e Po II /vo C aN./ec/? L'

Display Variable Name:

Input Name: ) W.S 7b

Variable displayed on:

Top level: NO

Trend: AhA/ Ze8v (s Scale: 9-/0 %p

SAS alarm limits

Low: A/voe- Reference:

High: A/oCAe Reference:

EOP (CSF) entry value: /Vowe EOP (CSF):_

EOP (CSF) control values: Aowe

Input range: -/ oo , VS

I/O range: 0_-_oo%,

Algorithm: 5$AS

Satisfactory: PC'

Calculation order: 5,1k/s

Scan intervals: SA$IS

Safety related Isolation: 5

Prepared by:

Date:

Reviewed by: ?

Date: ____2 -_ __

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

/ 3.6.1

_

Page 215: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: _________ Display Variable Name:

Number 5k e e A

F* 1a/ e Io Aa0 Input Name: vd 1a/,,74 e 7rd # deve/

Variable displayed on:

Top level: f

Trend: 1 e# Scale: c5-/O

SAS alarm limits

Low: Ac,, e- Reference:

High: / e Reference:

EOP (CSF) entry value: A/e EOP (CSF):

EOP (CSF) control values: /Vov e

Input range: 0-/"o

VS I/O range: o-/,904

Algorithm: SA#7-

Satisfactory: /4-S

Calculation order: ____

Scan intervals: SI/ lee ,,ed/

Safety related Isolation: /_, -,1e7^_ 4,

Prepared by:

Date:

s/2/- g Reviewed by: _ _ _ _ _

Date: _-__ _

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Page 216: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /tAJS9 Display Variable Name:

Number /o

Input Name: 6 /c 6'oo/ yr

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by: 42&Date: _ _13

4 / //'/g/0

Reviewed by: __ __

Date:

Variable displayed on:

Top level: 5

Trend: AIU7 / /d ke &,AScale: 0-5010 GP

SAS alarm limits

Low: //o)- Reference:

.High: Ate - Reference:

EOP (CSF) entry value: /I/o vP EOP (CSP):

EOP (CSF) control values: Ao e

Input range: 7 VS Satisfactory:

I/O range: 6-f0 :'f

Algorithm:

Calculation order: _ _/s

Scan intervals: _A_5

Safety related Isolation:

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

I3.6.1

Page 217: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /Z-&63 Display Variable Name: Number / ,J

Input Name: 8 8 AUX bee(Xe

Variable displayed on:

Top level: e5

Trend: Aix eA' O ( 5 Scale: O-- 5oo 6?-n

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

A34 3q /- q

Reviewed by: -P. £Q Date: __ __ __ _

SAS alarm limits

Low: A_ o e Reference:

High: Ivolve Reference:

EOP (CSF) entry value: /Vo WP EOP (CSF):

EOP (CSF) control values: /Va ve

0 Soof01 Input range: 67

VS Satisfactory: 5 541 I/O range: p-you

Algorithm:

Calculation order:

Scan intervals:

Safety related Isolation:

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

:

:

Page 218: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /cM58 Number

*F F4M ee f por tfLo

Q,,gle l a

Display Variable Name:

Input Name: CA -48 e Aver , , e

: Variable displayed on:

Top level: d/ re /d ae

Trend: Scale:

: SAS alarm limits

: Low:

High:

/de

AlvoI e

EOP (CSF) entry value:

Reference:

Reference:

A1A/le EOP (CSF):

EOP (CSF) control values: Xf2 bo Pa/9ev, F-O*/

Input range: o

VS Satisfactory: I/O range: cI q

Algorithm: 65t?4 s 5

Calculation order:

Scan intervals:

Safety related Isolation: d1A 3- .5 7s

Prepared by: Reviewed by:

Date:/ /

Date: 6 3-S

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

I3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1/

SX /%0e A e'f /,9-,4A6 /C /PVZ / PoW4444L -e7~3 ~ -17 -i~ AV #/IOdRA

'e-13le "?

t0l(plW( j,9

Page 219: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: AAGII5c Display Variable Name: Number. .

Input Name: 2o.- ge A'Se /;xr

No

: Variable displayed on:

Top level: Ye_ _5_4____ __)__e4

: Trend: a//'c-,i, T1v! ' Scale:

tel f SeA y' shlf4'

: SAS alarm limits

: Low: //o_ __ Reference:

: High: /VoAve Reference:

* EOP (CSF) entry value: _ _o _EOP (CSF): *

: EOP (CSF) control values: A/o, e._

* Input range: 0-4207v VS a,

: I/O range: o-720/o

Algorithm: 5fe/5

Satisfactory: Ye- -.

3.2.2

3.2.3

J 3.6.1

: Calculation order: 451 '.5

Scan intervals: 5,f_7 s

Safety related Isolation:

Prepared by:

Date:

Reviewed by:

Date: __ _ -_ _ _

Io//i 9

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

A/, / /0/ ltf f

Page 220: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: AA'LS6& Display Variable Name: Number

Input Name: I5f Aa x (/d 4)

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

I 3.6.1

,vo/el se1 b sb*ac Variable displayed on:

Top level: yeS(Ite551 e We#),vo ef

Trend: ______e_ 2_ _sScale: -O41 /O -145

SAS alarm limits

Low: /VoA__e Reference:

High: A/olve Reference:

EOP (CSF) entry value: A/cl e EOP (CSF):

EOP (CSF) control values: ,ve _e

Input range: 1 5 VS -3 Satisfactory:

I/O range:/O 1j 4,45

Algorithm:

Calculation order: 5 5

Scan intervals:

Safety related Isolation: A'5CfZ!b "'32

Prepared by:

Date:

raz//q'8i

5/3/ 9 I 0/(/" q4_9

Reviewed by:

Date: ~9-3 _-t

Page 221: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: A1-/ / Number

Display Variable Name:

Input Name:

Variable displayed on:

Top level: 6o/SLA I

Trend: 14 a.-JAI

SAS al

Low:

High:

EOP (C

EOP (C

Input VS

Scale: /1vol/ C ,P

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3' 3.5.1

I/O range: /0 -o/

Algorithm: 54$I

Calculation order: 5_____s

Scan intervals: S/l S

Safety related Isolation:

Prepared by:

Date:

Reviewed by:

Date: 5-- 3- r8

arm. limits

/___/e Reference:

Al,/Oe Reference:

SF) entry value: /VOA/e EOP (CSF):

SF) control values: lvow-e_

range: 0Z55 6= C Satisfactory: S__,__s

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

4t 0 G IS-I 01

6av Z ee48l I 6>V- /

:

Page 222: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

.SAS Point: iq/L/ 16, Number

Variable displayed on:

Top level: (o SA aw

Trend: ^/ / o

SAS alarm

Scale: /Ov- /02 Cps

limits

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Calculation order: 5A74 S

Scan intervals: _ _ _ _

Safety related Isolation: /

Prepared by:

Date:

Reviewed by: .r .£ Date: _ -_ _ 3 -__

/eel-/&

5 7, 23

Low: A/Ode Reference:

High: /1v-v e Reference:

EOP (CSF) entry value: Ialv EOP (CSF):_

EOP (CSF) control values: AA)/V ____

Input range: 2"5A45 VS 6 Satisfactory: 5 s

I/ r ianhge:m/ ,_ _

Algorithm: 4

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Display Variable Name:

Input Name: Sk Fo ar IV-32

Page 223: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: Aql,/Z/ 3 Display Variable Name:

Number

Input Name: F_ 1_CFl/ou_ _ _

Variable displayed on:

Top level: 6/ &A

Trend: 16 S4dowA Scale: 0 -'oo0d76}^)

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

/O/40/1 9,C19

Reviewed by: _ _.

Date: 5_- 3 -81r

SAS alarm limits

Low: oAl Reference:

High: Ao_ __e- Reference:

EOP (CSF) entry value: ivoYe EOP (CSF):.

EOP (CSF) control values: A/o-"e_ _

Input range: 10 9 5 Yo Ss , e ,eed

VS Satisfactory: 40t 1o I/O range: _-</oco

Mtse

Algorithm: *sev 9

Calculation order: 541s

Scan intervals: _____

Safety related Isolation: " R

1 3.2.1 3.3.1 3.3.4'

3.2.2

3.2.3

3.6.1

Page 224: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: __/__ Display Variable Name:

Number 9 1,./'eY 7 e s

Input Name:

Variable displayed on:

Top level: __// ____

Trend: 6// S_ scale: :o'5- DEGF

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

A;< /,,~4 o/Ce(( cv

Reviewed by:

Date: 5 _- 2 -Vor*

SAS alarm limits

Low: /VA1e Reference:

High: ANoIJe Reference:

EOP (CSF) entry value: /oale EOP (CSF):

EOP (CSF) control values: lAo-"e

Input range: 6O- "'6O IDE6 F VS Satisfactory: yes

I/O range: 5 - De6 F

Algorithm: SAIs_ _

Calculation order: 5_14_1 __s

Scan intervals: 4A/s

Safety related Isolation: ;e9944+ 's

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Page 225: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: A_______ Number

Display Variable Name:

Hie 1 9 a 1-1eWn/

Input Name: //Y /y ot/ /ac//e 7

Variable displayed on:

Top level: __a___

Trend: //

SAS al

Low:

High:

EOP (C

EOP (C

arm

Scale: 5 A V5o DE'c F

limits

/VCo W Reference:

A/o aReference:

SF) entry value: I/6 41e EOP (CSF):_

SF) control values: A/OAle

Input range: 5o-VroftOEG F VS Satisfactory: __5

I/O range: ,O-VSO/PEC F

Algorithm: S5ft/s

Calculation order: SAs

Scan intervals: SA7/s

Safety related Isolation: S 'v L-9 S

Prepared by:

Date:

Al / 1 ~

Reviewed by:

Date: 5--7 -_r _

/ A J'

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Page 226: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /lil- /7/ Display Variable Name: Number C S /Fess g' l& U

Input Name: -cz 4,4 , 0 ,d r/I4

Variable displayed on:

Top level: Ile //' o

Trend: /V Scale:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Calculation order: 5

Scan intervals: _# _5

Safety related Isolation: At

Prepared by:

Date: ~(-2a -5~'Reviewed by:

Date:

SAS alarm limits

Low: A__ _ _ Reference:

High: C,41 Cu/k ' Reference: P

EOP (CSF) entry value: /VaIfe EOP (CSF):

EOP (CSF) control values: y/o, A,_re_

Input range: 7 ,5O PEc F VS Satisfactory: /4

I/O range:

Algorithm: _____

:

Page 227: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /1l / /7Z Number

Display Variable Name:

,FCs Pess Z.j /

Input Name: feAC/'A e /

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Variable displayed on:

Top level: /o w/

Trend: _ _ _ _ _ _ _ Scale:

: SAS alarm limits

Low: CA CdA eIReference: /_____c

: High: /Vo_ _ e Reference:. ________

EOP (CSF) entry value: A/ EOP. (CSF):

: EOP (CSF) control values: N10

Input range: -50 DEG F : VS Satisfactory: 4

I/O range: A.

Algorithm:_ _ _

Calculation order: _____

Scan intervals: 9_ __75

Safety related Isolation: A

Prepared by:

Date:

- RveReviewed by:

Date: S--2 - tr

AI(X

:

:

:

Page 228: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: #A Display Variable Name:

Number 6I7nNe2 /4tess

Input Name: ,cs es

Variable displayed on:

Top level: #// do/o,

Trend: ANO Scale: A/

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

_yJ L d-Reviewed by:

Z/A2 JDate:

SAS alarm limits

Low: M/o /e Reference: None

High: al//4i L Reference: /___/_'__2

EOP (CSF) entry value: I/oI/e EOP (CSP): .

EOP (CSF) control values: Avow e

Input range: ___oo___

VS Satisfactory: / F I/O range:

Algorithm: _____

Calculation order: _

Scan intervals: $A S

Safety related Isolation: /

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Page 229: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /fA -/741 Display Variable Name: Number o/d Z 4

Input Name: CSp;es

Variable displayed on:

Top level: flo/d

Trend: Al10 Scale: d/0

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Calculation order: ____5

Scan intervals: _ A__'S

Safety related Isolation:

Prepared by:

Date:

Reviewed by:

Date: -___ __

: SAS alarm limits

Low: CA/C / Reference: /________

: High: A/ode Reference: 14/A#'t

: EOP (CSF) entry value: /______ EOP (CSF):

: EOP (CSF) control values: 4 " .

: Input range: 03ovop5 y VS Satisfactory: 4V/

I/O range: . '... 4

Algorithm: __ ____

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

:

:

:

Page 230: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: (O290 Display Variable Name: Number

Input Name: / /Ze wf s,

Variable displayed on:

Top level: Le5 1e 0/ -fOt/0 (,P,1

Trend: AVO Scale:- V/x

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

; V/o //C//ep

Reviewed by: 2- <

Date: f--3-t'

so4 /&(egl

SAS alarm limits

Low: _____v_ e Reference:

High: _ /___e_ Reference:

EOP (CSF) entry value: /A/oie EOP (CSP):

EOP (CSF) control values: A/ov

Input range: VS Satisfactory: Lsc 4 ' '53

I/O range: -- 50 v 7/537,%

Algorithm:m:___

Calculation order: ___s

Scan intervals: _ A_ _5

Safety related Isolation: A(

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Page 231: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: ( Display Variable Name:

Number

Pk'~ ~ a/'/ -c'/ --/nput Name:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Variable displayed on:

Top level: CM

Trend: /V,2 Scale:

SAS alarm limits

Low: _____ _Reference:

High: / _ e Reference:

EOP (CSF) entry value: wDe EOP (CSF):

EOP.(CSF) control values: /1v e_

Input range: NACTM/ C/ . VS

I/O range: _ /_____ _4_ ,/_

Algorithm:

Satisfactory: /

Calculation order: 5#-75

Scan intervals: fr4,1e

Safety related Isolation: 7 /' 77-

Prepared by:

Date: ~/2/~' ~'

Reviewed by:

Date:

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

fe ed lAjle-.e

________

, ,

Page 232: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: .,DT6L VDisplay Variable Name: Number

Input Name: d 7T £'sk. T ,

Variable displayed on:

Top level: GSYAfawwe, t)

Trend: A/O Scale:

SAS alarm limits

Low: /Yo_ ' e Reference:

High: /awwe- Reference:

EOP (CSF) entry value: P EOP (CSF):

EOP (CSF) control values: Al_____e_

Input range: ____0/____

VS I/O range: ___C____rI_

Algorithm:_ ___A__5

Satisfactory: 5

Calculation order: _____

Scan intervals: -P ±b - .s

Safety related Isolation:

Prepared by:

Date:

Reviewed by:

Date:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

I 3.2.3

j 3.6.1

S-3 -8~a~e (6q-9

Page 233: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: TO L93 Display Variable Name: Number e

/oo v Input Name: 6 ~~v,v iec e 7a

Reqmnts : Variable displayed on:

3.1.1 Top level: es(tes/;e Ah A) 3.3.2 3.3.3 : Trend: /VO S 3.1.4

3.3.5 : SAS alarm limits

3.1.3 3.5.1

cale: A

Low: M/on f Reference:

High: AZDIVt_ Reference:

EOP (CSF) entry value: /p-de EOP (CSF):

EOP (CSF) control values: ldAe.

Input range: 1 to/ .&-ls VS

I/O range: -W t/5

Algorithm: +

Satisfactory: 4'F5

Calculation order: / 5

Scan intervals:

Safety related Isolation: /

Prepared by:

Date:

3 / &4t Reviewed by:

Date: _ -_.2 -__

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Page 234: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: b Display Variable Name: Number 4

Input Name: $54/ l-rVec cAov -

Variable displayed on:

Top level: (/efS4v Af/

Trend: /VO Scale:

SAS al

Low:

High:

EOP (C

EOP (C

IV/

arm limits

_ lO_ _ e Reference:

/Un/id Reference:

SF) entry value: Alo ve EOP (CSF):

SF) control values: Alphov e_

Input range: &/0/AT/2A VS

I/O range: __/^_____V _

Algorithm: 51AI5

Satisfactory: L

Calculation order: 5414

Scan intervals:

Safety related Isolation: 7Y/5CfPAA Yf 3

Prepared by:

Date:

/ /o/1,y ,4u

Reviewed by: r L

Date: __ __ __ _

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

(13.2.3 3.6.1

-5Z- $2Z

/ oft, ?CO

Page 235: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: 47D776 /(Q Display Variable Name: Number ;,, k [vep,, L /wee

f a 12eee c/0 . I ,1 Inp ut Name:

Variable displayed on:

Top level: ies Trend: A/0 Scale:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

Reviewed by:

Date: _I-_- -td

SAS alarm limits

Low: /tloe e Reference:

High:/A-"/ /LOPeed Reference:

EOP (CSF) entry value: k'ov_ EOP (CSF):

EOP (CSF) control values: A/Vae e

f,~s6 2CP5 Input range: Lee/ O-fZhe

VS Satisfactory:

I/O range: //

Algorithm: - 5

Calculation order: _ _ _

Scan intervals: 5_ _

Safety related Isolation:

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

Page 236: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

7

Verification of SAS Documentation

SAS Point: .IlT(// Display Variable Name: Number

Input Name: 4if FJT'eAy2 4'vc/ 516

Variable displayed on:

Top level:

Trend: A16) Scale: -V//

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

Prepared by:

Date:

A~V/ //~/~ W

/~ 6 2~~-- 3

Reviewed by:

Date: _ _ _ _ _

SAS alarm limits

Low: A/o /- Reference: AIR1 eJ-ecIOVi Cfi41

High: 2 /ceday 6O00 c,/0 Reference: /''e2

EOP (CSF) entry value: Al'ol e EOP (CSF):

EOP (CSF) control values: /Vale-_

Input range: -r-, VS Satisfactory: //

I/O range: __ _ _

Algorithm: 5

Calculation order: ____

Scan intervals: _ _ _ _

Safety related Isolation:

1/ 3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

I

Page 237: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: rDIG/G5 Display Variable Name: Number ,/ of o/1 -Ole /

4 ,4sdp.4I/- Input Name: KteCfc4eC0IUA0

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

I)

3.2.2

3.2.3

3.6.1

Variable displayed on:

Top level: eId/

Trend: A0 Scale:

SAS alarm limits

Low: _ /VO/e Reference:

High: Alo^xe Reference:

EOP (CSF) entry value: A/6 l/e ' EOP (CSF):

od epamo EOP (CSF) control values: /7 z

Input range: 9i 7r VS Satisfactory: 5

A/o range: "

A lgor ithm: 5,f?7

Calculation order:

Scan intervals: 5_4_/5

Safety related Isolation: _,___s

Prepared by:

Date:

~4 o/~/~ ~

Reviewed by: _4r_ _ ._

Date: 6___3_-&r

Page 238: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: N90Z96 Display Variable Name:

Number

Input Name: SA, k-31Cou&,d

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

32 3.2.2

3.2.3

1/ 3.6.1

Variable displayed on:

Top level: '58 d o4 tpo, 7

Trend: u'1 /</ 0//2 0-oA4cale:

SAS alarm limits

Low: _ _/_ Reference:

High: Reference:

EOP (CSF) entry value: EOP (CSF):

EOP (CSF) control values: _ _

Input range: ' As v s VS _ Satisfactory:

I/O range: /0 Oo /OeCf:s

Algorithm: A*A4

Calculation order: 5_ __s

Scan intervals: _ ____

Safety related Isolation: AFE 6 S

Prepared by:

Date:

Reviewed by:

Date: 5-- 3 -1V-k

~/2-0 / <zuTV-

Page 239: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

Verification of SAS Documentation

SAS Point: /V'!'3&G Display Variable Name: Number

Input Name: A c d

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

13.2.1 13.3.1

3.3.4

3.2.2

3.2.3

/3.6.1

Variable displayed on:

Top level:

Trend: &/4eWl 4 Re01PO"/58cale:

SAS alarm limits

Low: / _ __ Reference:

High: ___ __ Reference:

EOP (CSF) entry value: /VL42 EOP (CSF):

EOP (CSF) control values:

Input range: VS Satisfactory: _4____

I/O range: /0" V /0

Algorithm: 4

Calculation order: _ _ _

Scan intervals: _ _ _ _

Safety related Isolation: e/ -

Prepared by:

Date:

Reviewed by:

Date: 3 -~i'

Page 240: Rev 1 to WPS-1000-88-010, 'Kewaunee Nuclear Power Plant ...IGEN NGINEERING, INC KEWAUNEE NUCLEAR POWER PLANT SPDS DESIGN REVIEW REPORT WPS-1000-88-010, Rev. 1 October 6, 1988 Prepared

SAS Point: 5(_f?_ Number

-j

Verification of SAS Documentation

Display Variable Name: ________

IC20 Woee Z/a 4la41r

Input Name: x7 4 7iits /

lex &v, e

Variable displayed on:

Top level: /_a/_,__ec__

Trend: ,/o^ e

SAS al

Low:

High:

EOP (C

EOP (C

arm

Scale:

limits

/Ale l Reference:

A/to.Ie Reference:

SF) entry value: /of'" EOP (CSF):

SF) control values: Aoai_

Tp/NT~tF

Input range: VS Satisfactory: 5

I/O range -7/0-0

Algorithm: 6A45

Calculation order: ____

Scan intervals: 5/IKS

Safety related Isolation:

Prepared by:

Date:

Reviewed by:

Date:

Reqmnts

3.1.1 3.3.2 3.3.3 3.1.4

3.3.5

3.1.3 3.5.1

3.2.1 3.3.1 3.3.4

3.2.2

3.2.3

3.6.1

f) G