ML20083M528

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Rev 0 to Control Room Design Review;Sys Function & Task Analysis Validation Rept
ML20083M528
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 03/19/1984
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20083M504 List:
References
NUDOCS 8404180184
Download: ML20083M528 (267)


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S ECTIO N TITLE PAGE TABLE OF CONTENTS i LIST OF TABLES lii LIST OF FIGURES iv APPEN DICES -

v ACRONYMS AND ABBREVIATIONS vi PREFACE ix

SUMMARY

xiii 1.0 INTRO DUCTIO N '

I 1.1 OBJECTIVE l-1 l-1 1.2 TASK DESCRIPTION 1-1 2.0 M ETHODOLOGY 2-1 2.1 OPERATOR TASK IDENTIFICATION AND AN ALYSIS (FORM E) 2-1 2.2 OPERATIONAL SEQUENCE DIAGRAM 2-2 I 2. 3 2.4 TRAFFIC LINK DIAGhAM W ALK-THROUGil/ TALK-THROOGH METHODOLOGY 2-2 2-2 3.0 SELECTED OPERATION AL EVENTS 3-1 4.0 AN ALYSE OF SOES 4-1 4.1 SM ALL BREAK LOCA -

4-5 4.2 STEAM LINE BREAK 4-19 4.3 STEAM GENERATOR TUBE RUPTURE ,

4-30 4.4 LOSS OF OFFSITE POW ER 4-44 4.5 TURBINE LO AD REJECTION 4-59 4.6 PLANT STARTUP 4-68 l

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SECTION TITLE PAGE 5.0 OVERALL SFTA RESULTS AND OBSERVATIONS b-1 5.1 PANEL 001 5-1 5.2 PANEL 002 5-3 5.3 PANEL 003 5-5 5.4 PANEL 004 5-5 5.5 PANEL 005 5-6 5.6 PANEL 006 5-8 5.7 PANEL 007 5-10 5.8 PANELS 008 and 009 5-10 5.9 PANEL 010 5-11 6.0 RESULTS AND OBSERVATIONS OF W ALK-THROUGH/ 6-1 TALK-1 HROUGH I ,

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SUMMARY

xiii 1.0 INTRO DUCTIO N 1-1 8 1.1 OBJECTIVE 1-1 1.2 TASK DESCRIPTION 1-1 2.0 METHODOLOGY 2-1 2.1 OPERATOR TASK IDENTIFICATION AND AN ALYSIS (FORM E) 2-1 2.2 OPERATION AL SEQUENCE DIAGRAM 2-2

2. 3 TRAFFIC LINK DIAGRAM 2-2 2.4 W ALK-THROUGH/ TALK-THROUGH METI ODOLOGY 2-2 3.0 SELECTED OPERATION AL EVENTS 3-1 4.0 AN ALYSE OF SOES 4-1 4.1 SM ALL BREAK LOCA 4-5 4.2 STEAM LINE BREAK 4-19 4.3 STEAM GENERATOR TUBE RUPTURE 4-30 4.4 LOSS OF OFFSITE POWER 4-44 I 4.5 TURBINE LO AD REJECTION 4-59 4.6 PLANT STARTUP, 4-68 l

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xiii 1.0 INTRO DUCTIO N 1-1 1.1 OBJECTIVE l-1 1.2 TASK DESCRIPTION 1-1 2.0 METHO DO LOG Y 2-1 2.1 OPERATOR TASK IDENTIFICATION AND AN ALYSE (FORM E) 2-1 2.2 OPERATIONAL SEQUENCE DIAGRAM 2-2

2. 3 TRAFFIC LINK DIAGRAM 2-2 2.4 W ALK-THROUGH/ TALK-THROUGH METhO DO LOG Y 2-2 3.0 SELECTED OPERATION AL EVENTS 3-1 4.0 AN ALYSE OF SOES 4-1 4.1 SM ALL BREAK LOCA 4-5 4.2 STEAM LINE BREAK 4-19
4. 3 STEAM GENERATOR TUBE RUPTURE 4-30 4.4 LOSS OF OFFSITE POW ER 4-44 4.5 TURBINE LOAD REJECTION 4-59 4.6 PLANT STARTUP 4-68 i

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SECTION TITLE PAGE 5.0 OVERALL SFTA RESULTS AND OBSERVATIONS 5-1 5.1 PANEL 001 5-1 5.2 PANEL 002 5-3 5.3 PANEL 003 5-5 5.4 PANEL 004 5-5 5.5 PANEL 005 5-6 5.6 PANEL 006 5-8 5.7 PANEL 007 5-10 5.8 PANELS 008 and 009 5-10 5.9 PANEL 010 5-11 6.0 RESULTS AND OBSERVATIONS OF W ALK-THROUGH/ 6-1 TALK-THROUGH I

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I SECTIO N TITLE PAGE 8 TABLE OF CONTENTS i LET OF TABLES iii E LIST OF FIGURES iv APPEN DICES y ACRONYMS AND ABBREVIATIONS vi PREFACE ix

SUMMARY

xiii 1.0 INTRO DUCTION

' 1-1 l.1 OBJECTIVE l-1 1.2 TASK DESCRIPTION 1-1 2.0 METHODO LOGY 2-1 2.1 OPERATOlt TASK IDENTIFICATION AND ANALYSIS (FORM E) 2-1 2.2 OPERATIONAL SEQUENCE DIAGRAM 2-2

2. 3 TRAFFIC LINK DIAGRAM 2-2 2.4 W ALK-THROUGH/ TALK-THROUGH METh0DOLOGY 2-2 I 3.0 SELECTED OPERATION AL EVENTS 3-1 4.0 AN ALYSIS OF SOES 4-1 4.1 SM ALL BREAK LOCA 4-5 4.2 STEAM LINE BREAK 4-19
4. 3 STEAM GENERATOR TUBE RUPTURE 4-30 4.4 LOSS OF OFFSITE POW ER 4-44 4.5 TURBINE LOAD REJECTION 4-59 )
4. 6 PLANT STARTU P 4-68 I

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TABLE TITLE PAGE I 4.1-1 TASK GROUPING REVIEW-SMALL BREAK LOCA 4-18 4.2-1 TASK GROUPING REVIEW-STEAM LINE BREAK 4-29 4.3-1 TASK GROUPING REVIEW-STEAM GENERATOR TUBE RUPTURE 4-43 4.4-1 TASK GROUPING REVIEW-LOSS OF OFFSITE POWER 4-58 4.5-1 TASK GROUPING REVIEW-TURBINE LOAD REJECTION 4-67 4.6-1 TASK GROUPING REVIEW-PLANT STARTUP 4-99 5.1-1 PANEL 001-PANEL TRAFFIC PATHS 5-2 5.2-1 PANEL 002-PANEL TRAFFIC PATHS 5-4 I 5.5-1 PANEL 005-PANEL TRAFFIC PATHS 5-7 5.6-1 PANEL 006-PANEL TRAFFIC PATHS 5-9 I

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FIGURE TITLE PAGE E

P-1 STP CRDR MAJOR REPORTS xil 2.1-1 CONTROL ROOM LAYOUT 2-4 2.4-1 STP CONTROL ROOM MOCK-UP 2-5 m

! 2.4-2 PORTION OF TYPICAL OPERATING PROCEDURE 2-6 4.1-1 TRAFFIC LINK DIAGRAM -SMALL BREAK LOCA 4-9 4.1-2 OPERATIONAL SEQUENCE DIAGRAMS -SMALL BREAK

. LOCA 4-10 4.2-1 TRAFFIC LINK DIAGRAM -STEAM LINE BREAK 4-22 4.2-2 OPERATIONAL SEQUENCE DIAGRAMS -STEAM LINE BREAK 4-23 l

$ 4.3-1 TRAFFIC LINK DIAGRAM -STEAM GENERATOR TUBE RUPTURE 4-34 y 4.3-2 OPERATIONAL SEQUENCE DIAGRAMS - STEAM $

GENERATOR TUBE RUPTURE 4-35 y 4.4-1 TRAFFIC LINK DIAGRAM - LOSS OF OFFSITE POWER 4-47 4.4-2 OPERATIONAL SEQUENCE DIAGRAMS - LOSS OF g OFFSITE POWER 4-48 j 4.5-1 TRAFFIC LINK DIAGRAM -TURBINE LOAD REJECTION 4-61 g 4.5-2 OPERATIONAL SEQUENCE DIAGRAMS -TURBINE LOAD

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OPERATIONAL SEQUENCE DIAGR AMS - PLANT STARTUP 4-75 d 6.0-1 RCS HEATUP RATE 6-4

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APPENDICES A PPENDIX TITLE A. OPERATOR TASK IDENTIFICATION AND ANALYSE FORMS t

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E ACRONYMS AND ABBREVIATIONS

  • E ARO Auxiliary Reactor Operator "

ASSOC Associated ASST Assistant h

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AUX Auxiliary CAT Category CLO Checklist Observation CONT Control CR Control Room -

CRDR Control Room Design Review _

CVCS Chemical Volume Control System _

EES Emergency Event Sequences ,

EOF Emergency Operating Facility EPRI Electric Power Research Institute ESF Engineered Safety Feature (s)

EST Estimate (d)

ERG Emergency Response Guidelines EXPER Experience _

FW Feedwater _

IIE Iluman Engineering _

fiED liuman Engineering Discrepancy _

fillSI liigh IIead Safety Injection llL&P Ilouston Lighting and Power Company IIPSI fligh Pressure Safety Injection E I&C Instruments and Controls E INPO Institute of Nuclear Power Operators -

INSTR Instrument _

LDR Leader _

LiiSI Low IIcad Safety Injection _

LOCA Loss of Coolant Accident _

LOSP Loss of Offsite (AC) Power y LPSI Low Pressure Safety Injection LROI Licensed Reactor Operator # 1 vi -

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ACRONYMS AND ABBREVIATIONS (Cont.)

l LRO2 Licensed Reactor Operator #2 l M/M Man / Machine MCP Main Control Panel MON Monitor MSR Moisture Separator Reheater e MT Management Team MW(e) Megawatts (electric)

NOS Numbers NRC Nuclear Regulatory Commission OERT Operating Experience Review Task Group OSC Operational Support Center PORV Power Operated Relief Valve PRT Project Review Team PSAR Preliminary Safety Analysis Report I RAS Recirculation Actuation Signal PZR Pressurizer RCB Reactor Containment Building RCP Reactor Coolant Pump RCS Reactor Coolant System RECIRC Recirculating REQ'D Required RG Regulatory Guide RHR Residual Heat Removal I RO Reactor Operator RwST Refueling Water Storage Tank RX Reactor SBCS Standby Cooling System SFTA System Function and Task Analysis SG Steam Generator SIS Safety Injection System SOE Selected Operational Event (s)

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E ACRONYMS AND ABBREVIATIONS (Cont.)

SPDS Safety Parameter Display System SRO Senior Reactor Operator SS Subsystem STAT Systems Task Analysis Team SUPVR Supervisor SW Switch System S YS g

TMI Three-Mile Island E TSC Technical Support Center  !

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I PREFACE E

The control room design review (CRDR) of the South Texas Project (STP)

Nuclear Generation Station was started in September 1982. This review is being I

performed by Torrey Pines Technology for Houston Lighting & Power Company (HL&P) with Bechtel Energy Corporation (Bechtel) acting as agent.

Prior to completion of the CRDR, a decision was made by HL&P to redesign six of the ten main control panels. This redesign effort is required to accommodate design changes resulting from plant design evolution and Reg. Guide 1.97 requirements. Human engineering discrepancies determined in the CR DR for the six panels will be corrected in the redesign effort.

The CRDR is described in the Program Plan document. It contains a detailed description of the tasks to be performed and the reports documenting the overall results.

Due to the control room redesign effort, a modified approach is required to complete and document the CRDR program. The following changes have been made in the CRDR:

I A.

The documentation program described in the Program Plan was changed to allow reporting of results on the individual CR DR tasks.

B.

An Implementation Plan Report was written to describe the background and reasons for the redesign effort. It outlines the approach to be used for implementing panel layout changes.

C.

The tasks described in the Program Plan will be completed for the original design. The SFTA and the control room survey have been updated to validate any design revisions.

This report is one of several documents (see Figure P-1) that describe the CRDR and the associated redesign effort on the STP control panels. 'the following is a description of these documents:

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A. Program Plan - Defines the plan for performing the CR DR.

t B. Criteria Report - Provides the detailed guidelines and basis for the CRDR and describes the interface between the control room and plant systems.

C. Operating Experience Review Report (DER) - Describes the review process results, conclusions and recommendations of the operating experience review (OER) task defined in the Program Plan.

D. system Function and Task Analysis (SFTA) Report - Describes the methodology, results, conclusions and recommendations for the SFTA effort defined in the Program Plan.

E. Control Room Survey (CRS) Report - Describes the review process, results, conclusions and recommendations of the control room survey task defined in the Program Plan. This report also includes the final results and dispositions for the human factor observations obtained from the OER and the SFTA.

F. Annunciator Report - Describes the review process, results, conclusions and recommendations of the annunciator review task defined in the Program Plan.

G. Special Studies Report - Describes details of any miscellaneous studies performed as part of the CRDR. This includes the anthropometric study, the hierarchiallabeling study and the demarcation study.

H. Implementation Plan Report - Summarizes the CRDR, the control room design changes, and the proposed methods of implementing the design changes.

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L. Executive Summary - Summarizes the CRDR, results, conclusions and recommendations. Technical details are in the Operating Experience Review Report, the System Function and Task Analysis Report, the Control Room Survey Report, and the Annunciator Report.

L SFTA Validation Report - Summarizes the secont SFTA review based on relayed out panels and walk-through/ talk-through validation.

J. OER Validation Report - Summarizes the review made by operators to determine if the redesigned panels corrected concerns reported in the OER Report and if any new problems were created.

K. CBS Validation Report -Summarizes the review made to determine if the category A and representative samples of the Category B HEDS are satisfactorily corrected and if any new problems were created.

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SUMMARY

This document describes the details of the SFTA validation er:! the walk-through/ talk-through validation that was performed as part of the control room design review of the South Texas Project Nuclear Generating Station. An original SFTA was performed on the previous control room design as recommended in the Program Plan. This work was documented in the SFTA Report. The SFTA validation was performed on the revised control room design. This report supplements the original I SFTA Report.

The analysis performed for this supplementary SFTA included a traffic flow analysis and a control panel operational seguence analysis of the ten control panels in the control room. These activities were performed for the six operational events (SOEs) selected in the original SFTA.

1 A. Small break loss of coolant accident B. Steam line break I C.

D.

Steam generator tube rupture Loss of offsite power E. Turbine load rejection F. Plant Startup The selection of these events was based on criteria that provided a good cross section of operator actions for the expected normal and emergency plant operating events.

I The identification of potential human engineering discrepancies (HEDS) was based on I human engineering recommendations of NUREG-0700. These potential HEDs are initially considered to be observations that are subject to review by the Project Review Team (PRT). They will be submitted for review to the PRT on checklist observation forms.

The PRT will evaluate the observatioris, identify HEDs, and recommend resolutions.

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The traffic flow analysis was performed for the six SOEs using link diagrams.

The traffic paths between control panels were identified and the frequency of travel (number of trips) by the operator along these paths was determined. Tables summarizing the paths and number of trips are presented in Section 5 for the panels and events showing significant travel. None of the traffic paths were considered to have excessive operator a travel for any of the SOEs.

The operational sequence analysis was performed using operational sequence diagrams and operator task identification and analysis forms (Form E). Major factors considered in identifying potential HEDs from this analysis were the functional and task related arrangement of control panel devices and an orderly grouping of task related devices. To evaluate the functional and task panel arrangement a task grouping review was performed. In this review, tables were developed (from data on Form E) showing all E

tasks which are performed on more than a single panel. These tables which are presented E in Section 4 represent potential cases of violation of task grouping criteria. These cases were then reviewed individually to obtain final observations of potential HEDs. In nearly E all the cases the device arrangements were found to satisfy the functional and task grouping criteria for one of the following reasons.

A. Although on seperate panels the devices were grouped together near the boundary line between the panels (grouped within a workspace).

B. Steps occurring on two different panels were handled by two different operators.

C. Alternate methods were identified for performing all the steps in the task I

on a single panel.

l D. The event was a non-emergency, non-time dependent event (plant startup) and the task occurred only once or twice during the ever.t.

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E. When two panels were involved in the task, one of the panels was small (either panel 007 or 009).

As a result of the review one case was found which did not satisfy the task grouping criteria. This involved task 9.10 of the LOCA event where the RCS is

- depressurized using SI pump controls on panel 001 and pressurizer spray controls on panel 004. The devices for this task are not grouped to minimize operator movement. It should be noted that this occurred only once for all the six SOEs and the layout of these systems g with regard to all the events must be considered before identifying this observation as an m HED.

With regard to the orderly grouping of step sequences, the review of the operational sequence diagrams showed no significant incidents of violation of the orderly grouping criteria.

I The walk-through/ talk-through validation effort showed that the control room crew could accomplish the allocated control room functions as defined in the normal and I emergency operating procedures. No additional observations of potential HEDs were identified during the walk-through/ talk-through.

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1.0 INTRO DUCTION l Due to the redesign effort on the STP control panels, significant changes occurred involving relocation of the panel devices. As a result, the original System Function and Task Analysis (SFTA) was validated for the redesigned control panels. This document supplements the original SFTA report and presents the results, conclusions and recommendations of the SFTA validation effort.

In addition to the SFTA validation a walk-through/ talk-through validation was

. performed for two of the events analyzed in the SFTA. The results, conclusions and recommendations from this effort are also presented.

1.1 OBJECTIVE The objective of the initial SFTA phase of the Control Room Design Review (CRDR) was to perform a functional review and task analysis of the control room complex. This is required to determine design and documentation adequacy for safe plant operation. The objective of the SFTA validation was to review the initial SFTA work described in the SFTA Report and revise any portions of the review and analysis that have changed as a result of the control panel redesign.

I The objective of the walk-through/ talk-through validation was to assure that the redesigned panels would allow the operators to perform the vital control room functions effectively.

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1.2 TASK DESCRIPTION Many of the activities which were performed ducing the initial SFTA were not affected by the control panel redesign. These include the document review, system familiarization, review of plant events, selection of operational events, etc. As described l in the SFTA Report, the following activities are required as a result of the relocation of I many of the panel devices.

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A. Performance of the SFTA for each SOE.

1. Revise the panel and the panel face locations as required for the task steps on the Operator Task Identification and Analysis forms (Form E).
2. Revise the designated operator performing or monitoring the task steps on Form E.

B. Revise the traffic flow analysis to correspond to the latest panel layouts including revised operational sequence diagrams..

C. Revise the operational sequence analysis to correspond to the latest panel layouts including revised operational sequence diagrams.

D. Evaluate the analyses and summarize observations and recommendations.

E. Perform a walk-through/ talk-through validation of two of the SOE studied in the SFTA.

F. Summarize and document the results and observations obtained from the SFTA validation.

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2.0 METHODOLOGY The procedures used to perform the overall SFTA are described in the SFTA Report. Most of this initial analysis is still valid for the redesigned control panels. The initial work involving document review, system seminars and the development of system background information remains as documented in the SFTA report. Also, the functional review which included the identification of the system functions and the development of functional flow diagrams remains the same as before. Changes are, however, required in the task analysis part of the SFTA. The following sections discuss the required revisions to the task analysis and the SFTA forms and the methods used to perform the I walk-through/ talk-through validation.

2.1 OPERATOR TASK IDENTIFICATION AND ANALYSIS (FORM E)

As described in the SFTA report, this form was used to tabulate the task and task steps for each SOE. Additional task information included on this form was sequential functions, task, and step number; identification of the operator that performs the step; I equipment number of the display or control device used in the steps and the panel and panel face location of the display or control device.

The panel design changes involved the relocation of many of the devices within panels and in many cases from one panel to another. As a result, the information on the Operator Task identification and Analysis Form required revision to reflect the new panel l and panel face locations of the devices. For some of the steps, the device was moved to an area across the control room, thereby requiring a revision of the designated operator on Form E.

l" The panel and panel face designations followed the convention shown in the control room layout, Figure 2.1-1. This figure also shows the areas of responsibi!!ty for each operator.

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2.2 OPERATIONAL SEQUENCE DIAGRAM This diagram shows the operator actions or steps for an individual control E

panel. For each SOE, operational sequence diagrams were drawn for every control panel that had significant sequential operator activity. The purpose of these diagrams.was to show the sequence of operator actions for evaluation of the device layout on the panels.

Operational sequence diagrams were developed to evaluate the revised layout of the panel devices with respect to the six SOEs using the revised data presented on Form E.

2. 3 TRAFFIC LINK DIAGRAM This diagram is a plan view of the overall control room layout showing the relationship of the ten control panels. Also shown is operator travel on traffic paths between panels for the selected event. The panel number and step sequence number from Form E is used to develop the sequence of operator motion shown on this diagram.

The traffic link diagram is used to evaluate traffic flow patterns in the control room. Long trips by the operator such as travel between non-adjacent panels and multiple trips between panels are illustrated on this diagram.

2.4 W ALK-TilROUGil/ TALK-TilROUGli METilODOLOGY This effort consisted of a walk-through/ talk-through of the simulated control room operation during two operating events. This exercise was performed on the STp control room mock-up, Figure 2.4-1. plant specific procedures were used by two plant crews and the exercises were video taped.

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PORTION OF TYPICAL. OPE!!ATING PROCEDURE Fitne 2.4 2 l

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I The liL&P technique also emphasizes good communications among all the plant personnel involved in monitoring and controlling a plant operation. The procedures include these communications as specific steps. Further, the procedure lists both the primary and secondary operators steps side by side in a coordinated sequence. Thus each operator is aware of what his associate is doing. See Figure 2.4-2 for a typical portion of an operating procedure.

l The operating procedures used in these exercises are in the later formative stages but lacking simulator trial uscage. The procedures were prepared using the Westinghouse generic emergency response guidelines.

The following equipment was used in video taping the two exercises:

o Panasonic Model PK 800 video camera mounted on a wheeled tripod.

o Panasonic Model NV-1300 cassette recorder o Panasonic Model CT-1910M video TV monitor o 1/2 inch VSli tapes I The acting operations manager assigned roles to the operators for each I procedure. lie assigned the role of unit supervisor to the operator who wrote the procedure. The primary operator and secondary operator roles were filled at random.

A panel layout familiarization period of about one hour was taken by each crew. This is significant since it represents working with a crew that is not thoroughly versed in the location of all system components, thus the effectiveness of the hierarchial labeling could be observed.

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3.0 SELECTED OPERATIONAL EVENTS The following six events were selected in the initial SFTA work.

A. Small break loss of coolant accident (LOCA).

B. Steam line break (loss of secondary coolant).

C. Steam generator tube rupture.

D. Loss of offsite power (LOSP).

I E.

F.

Turbine load rejection.

Plant startup.

These events were selected on the basis of criteria which required a broad range of control room functions with emphasis on abnormal and emergency conditions.

The tesk analysis relating primarily to the task descriptions, the traffic flow (link diagram) analysis, and the operational sequence analysis was reviewed and revised for each of the six SOEs.

For the walk-through/ talk-through validation two of the above six events were selected; the steam generator tube rupture and the plant startt;p.

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4.O ANALEIS OF SOEs in the initial study of the six SOEs, the following review and analysis phases were performed.

A. Systen functional review.

B. Traffic flow analysis.

C. Operational sequence analysis.

The functional review phase involved the identification of the functions for g each event including the functional flow diagrams. This task did not require B

any change as a result of the control panel design changes since the systan functions were not changed. The basic elanents diagram (Figure 5.1-1 of SFTA Report) and the functional flow diagrams (Appendix of the SFTA Report ) were not affected by the panel design changes.

I The second phase of the study of the SOEs was the traffic flow analysis. This phase involves the developnent of a traffic link diagrams that show the operator traffic flow fran panel to panel for each event. These I diagrams where drawn fran the detailed task and task-step information listed on Form E (operator task identification and analysis) which is described in Section 2.1. Sequence ntnbers fran Fonn E were listed on each panel and lines connected operator paths between panels. The ntnber of trips on each path are shown next to the path. The traffic link diagrams were reviewed to determine where excessive operator travel would occur between panels. In general, the ntnber of trips was used to determine high traffic patterns.

In the traffic link analysis it should be noted that a trip is g defined as operator travel fran one panel to another. For a step such as 3

checking the availability of offsite power, where the operator goes to panel 010 and returns the link diagram would show two trips.

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For three events, small break IJOCA, steam line break, and steam generator tube rupture, an initial series of control roan operations is required prior to the diagnosis of the event. 'lhi s sequence of operator actions is the diagnostic procedures referred to as the E-0 sequence of operations f rom the Westinghouse ERG. In the initial SFTA, the traffic paths for the E-0 sequences were only shown for the ILCA event. Since all three of g

these events will be preceded by the diagnostic E-0 operations, the link a diagrams for all three cases were developed including the E-0 traffic paths.

Sane changes were assuned in the area of responsibility for the I

operators. In general the anergency events followed the breakdown of responsibility shown in Figure 2.1-1. However, for the turbine load rejection event the nonnal condition breakdown was assuned, to equalize the distribution of tasks for the operators.

For the plant startup in the original SFTA, the emergency condition breakdown was assuned. In this analysis, the redesigned panels showed that the nonnal condition breakdown would provide a better distribution of operation tasks as discussed in Section 4.6.2.

Overall, the traffic diagrans provided a cowrehensive and visual review of the panel device layout (and to sane extent the operating procedures) with regard to efficiency of movanent for the operators. Once the high traf fic paths are identified, the detailed step listing on Fonn E was g

reviewed to detennine the functions and tasks that require excessive operator 3 movanent . 'Ihe devices were then identified that violated the hunan factors criteria requiring grouping by task sequence or by syston function (Section 6.8.1.1 of l @ BG 0700).

'Ihe sequence of operations shown for the tasks and task steps on Fonn i E were assuned to be significant in the evaluation of traf fic paths. 'lhe actions (task / steps) were assuned to be perfonned by the operators sequentially and in the order shown on Fonn E for each event. In the listed sequence many times the steps shift fran one operator to L 4-2 j 2.5.8/10193 4 3424N/ 010SV

E HOUSTON CONTROL ROOM E LIGHTING DESIGN REVIEW

. N OWER CO.

the other. When this shift to a second operator occurs, the first operator is asstmed to have sane time for travel between panels. In the analysis, operations involving consecutive steps are asstmed to have less time available for travel than those involving non-consecutive (broken up by a shift to another operator) steps. As a result, in the review of the traf fic paths, travel between non-adjacent panels was considered more acceptable if it involved the performance of non-consecu t ive steps. And conversely, consecutive operations between non-adjacent panels were considered less acceptable.

The final phase of the SOE analysis was the operational sequence analysis. For this review the panel devices accessed in each step were f identified fran the labels on the control panel mockup. This information was used to draw the operational sequence diagrams for each SOE. 'Ihese diagrams show the operator movenents for individual tasks on each panel.

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On the diagrams square syiTbols were used for status (e.g, "ON" or "OFF") verification activities, round synbols were used for reading / monitoring activities and diamond symbols were used for control / adjustment activities. '

Numbers shown in the syntols represent the step sequence nunbers fran Fonn E.

Lines are drawn connecting consecutive steps wi th arrows showing direction of operator action.

l In cases where multiple actions are required at a single panel device, the sequence ntubers are listed beside the syrrbol .

l I The operational sequence diagrams were used to evaluate the layout of devices on the panels with regard to the htman engineering criteria. The major criteria considered in this analysis were as follows: (fran Section I 6.8.2.1 of NLRED 0700)

A. Controls and displays grouped by task sequence the minimize operator movanent.

I B. Controls and displays grouped according to systen functions.

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C. Controls and displays grouped according to their sequence arranged in an orderly pattern.

By reviewing the operational sequence diagrams with regard to the above eriterla specific reemmendations were made for relocating panel devices.

In performing the review of the results from the operational sequence diagrams, the following guidelines and asstnptions were used:

A. The steps for the individual tasks should generally all be performed on a single control panel. In cases where all the steps in a task did not occur on a single panel, sane consideration was given if two adjacent panels were involved and one of the panels was a short panel (panel 007 or 009). I Also '8 allowance was made for steps which occur near the boundary lines between panels, for non-frequently occurring tasks and for g non-t ime dependent tasks.

B. The diagrams were drawn using the sequences shown on Form E, I

however, in sane cases this sequence was considered to be arbitrary. In general, for systen monitoring tasks, such as a s ta'.as check on a series of valves, the sequence shown was considered arbitrary. In perfonning monitoring tasks it was asstmed that the operator would adopt a sequence that would minimize movenent. 3 C. For systen monitoring tasks, many times several different systens are involved with the displays for these systems located on several different control panels. For these type tasks, it was considered acceptable for the steps to be performed on more than one panel.

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D. He convention asstrned for the review of the arrangement of controls and displays according to their sequence was in general B a left-to-right or top-to-bottom pattern. %is was not strictly I E.

followed in cases where the devices were grouped close together.

In sane sequences, the arrangenent of controls may not be strictly sequential, but the frequency of occurrence of this particular sequence had to be evaluated against other events where the arrangenent was optinun.

F. He plant startup event is a non-energency situation in which the operators are not constrained by time or stress as is the case for the five energency events. Derefore, for this event sane allowance was made with regard to the grouping of devices by task on a single panel. Tasks performed on two adjacent panels were considered acceptable for the startup.

I 4.1 SMAll BREAK IJOCA 4.1.1 Revised Task Analysis

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De operator task identification and analysis forms presentea in the SFTA Report were revised to reflect the changes in panel and panel face L locations for each operator step. Also, for some of the steps the operator responsibility designation was changed. Rese revised forms for the small IDCA event are presented in appendix A.

j Using the information fran the operator task identification and analysis forms, the new traffic link diagram shown in Figure 4.1-1 was developed. Also, the operational sequence diagrams presented in Figures 4.1-2a through 4.1-2h were drawn for the IOCA.

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4.1.2 Results Figure 4.1-1 shows the operator travel paths between the panels during plant operation after a I.OCA event. The sequence nmbers of the steps which occur at each panel are shown and also the nmber of times (frequency) the operator traverses each path are shown.

The longest traf fic path was the single trip fran panel 010 to panel 005 by IR02. 'Ih i s , however, only occurs once during the event and is therefore not considered significant. Also the trip to panel 010 is to check for offiste power availability (step sequence 117) and the operator could check for offsite power by looking at the bus voltage reading on panel 007 and eliminate the trip out to panel 010.

Other long trips (trips between non-adjacent panels) occur between panels 005 and 007, one trip by IR02; between panels 007 and 010, one trip by IR02; between panels 002 and 004, four trips by IR01; and between panel 006 and the supervisory panel, two trips by IR02. These are all infrequently occurring trips and are, therefore, not considered excessive.

The most frequently occurring trips are the paths between panels 001 and 004 (15 trips) and between panels 001 and 002 (nine trips). Since these are trips between adjacent panels, this travel is not considered excessive. i It should, however, be noted that several of the trips to panel 004 fran  :

panels 002 and 001 (see step sequences 51, 59, 84, 134 and 138) will be eliminated by monitoring a duplicate reading of RCS pressure on the QDPS located on panel 001.

l As shown in Figures 4.1-2a through 4.1-2h, most of the devices on the individual panels are grouped according to order of use use during the event.

In general, the devices are grouped in a left-to-right and top-to-oottan convention for the IOCA tasks. In the few instances when the devices were not grouped according to this convention, the order of the step sequence was ~

coasidered to be arbitrary (Figure 4,1-2d, step sequences 28 through 32). e 4-6 2.5.8/10193 3424N/ 010Si

E HOUSTON E UGHitNG CONTROL ROOM o,, ,- & DESIGN REVIEW ff!9!KI POWEfl CO.

On panel 004 step sequences 10 through 12 are not performed in an orderly manner. Since this panel has the devices functionally grouped with mimic lines, the sequence of operations is not necessarily a lef t-to-right or top-to-botton pattern. This sequence of operation was considered acceptable.

I Thble 4.1-1 shows a list of the tasks which are perfonned on more than a single panel. These tasks are potential situations where controls and displays are not grouped by task sequence to minimize operator nuvement.

Task 2.5 involves a veri fica tion of valve al igrrnent for several I

sys ters. This is an overall system status monitoring task which could have been defined as several smaller tasks for each of the systens. The layout for l this task was, therefore, considered to be acceptable.

B l Tasks 3.8 and 3.9 involve status verification for the three OQV and EOV loops, respectively. For both cases the indicator lights for two of the l l loops are on panel 002 and the indicator lights for the third loop are on l panel 001. Since the displays for the three loops are adjacent to each other near the boundary line between panels 001 and 002 the layout is acceptable for l these tasks. I I

For task 7.7 the RG pressure (panel 004) and the HIBI flow (panel 001) are monitored to determine if charging ptmps should be started. This l multi-systen task could have been defined as two separate tasks. Also the operator could monitor the RG pressure using the plasma display on panel 1 001. The layout for this task was considered to be acceptable.

l Thsk 7.9 entails the caTparison of the RG and SG pressures on panels

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004 and 006 and the setting of steam dunp controller on panel 007. IROI would monitor RG pressure on panel 004 while IR02 would monitor SG pressures on '

panel 006 and control the steam dtnp on panel 007. Since the steam dunp controls are adjacent to panel 006 (also, panel 007 is a small panel) this arrangenent is considered acceptable.

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Task 9.2 involves checking offsite power availability and starting one charging pmp. Although this was defined as a single task, IR02 would verify power availability on panel 010 and IR01 would start the charging pmp fran panel 004. This arrangement is considered acceptable.

hsk 9.5 involves initiation of RG cooldown by adjusting pressurizer spray on panel 004, rate of steam dmp on panel 007 and AFW flow on panel 006. IR01 performs the operation on panel 004 and IR02 performs the other operations. Since the steam dmp controller on panel 007 is a near the boundary line between panels 006 and 007, the device layout for this task was assessed as acceptable.

Ask 9.10 involves depressurizing RG by adjusting SI valves and monitoring SI pmp discharge pressure on panel 001 and adjusting pressurizer spray valves on panel 004. The device layout is not grouped to accmplish this task with mininun operator movenent. It should be noted that task 9.10 is a multi-systen task involved the control of pressure using devices fran two nujor sys tans . The feasability of grouping these systens together is questionable since only a single task out of the six SOE's showed a violation of the task grouping criteria.

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TABLE 4.1-1 TASK GOUPING REVIBV - SWALL BREAK IDCA Function /A sk Panel No No Step Secuence. 2 .

2.5 002 9A-9H, 12G-12L I

004 10A-12F 3.8 002 22, 23 001 24 3.9 002 25, 26 001 27 7.7 004 77 001 78-80 7.9 004 84 006 85 007 86-88 9.2 010 117 004 118 9.5 004 122 007 123 006 124, 124A 9.10 001 135-137, 139 004 138, 140 I

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6 4-18 2.5.8/10193 3424W/0105W

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4.2 S E 1 LINE BRFE 4.2.1 Revised Task Analysis As outlined in 4.1.1, the operator task identification and analysis fomis were revised to reflect the changes in panel and panel face locations for each operator step. Since sane of the changes involved the transferring

[ of certain devices across the roan, the responsibilities for sane steps were shifted fran one operator to another. The revised forms for the steam line break event are presented in Appendix A.

u Figure 4.2.-l presents the revised traffic link diagram. The paths shown include the operator actions that occur during the diagnostic phase, prior to the identification of the event, and the operator actions that occur

) after the steam line break is identified. The operational sequence diagrams l

developed for this event are presented on Figures 4.2-2a through 4.2-2f. I 4.2.2 Results

)

i Figure 4.2-1 shows the traffic link diagran for the steam line break event.

This figure includes the sequence nunter of the steps in the operator task sequence (both ERG E-0 and ERG E-2), and the total nmter of occurrences for each path.

I The largest traffic path occurs fran panel 005 to panel 010 by IR02.

Although '.his is considered a long trip (between non-adjacent panels), it {

occurs only twice during the event. In addition, this path is only traveled l during non-consecutive steps, and therefore it is not considered significant.

" {

The only instance in which IR02 performs a long trip during consecutive steps, is between panels 007 and 010. However, this observation can also be , {

l neglected because of its low nmter of occurrences.

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IR01, on the other hand, is faced with 12 trips between panels 002 and 004 with six trips occurring during consecutive steps. Frequently, these long trips are required in order to perform one or two steps at a time, therefore decreasing the time spent on each panel. Although these trips appear to be excessive, the individual steps do not interrupt the tasks being pe r formed. In other words, the steps are grouped by task, therefore diminishing their inpact on the operator perfomunce.

Other frequently occurring trips take place between panels 001 to 004 and 001 to 002, 13 times each. Since these are trips between adjacent panels, these paths are not considered excessive.

As shown on Figures 4.2-2a through 4.2-2f, it was observed that the sequence of steps is arranged in a lef t-to-right, top-to-bottom fashion for operations occurring on each panel. There are a few instances in which this may not be the case (see Figure 4.2-2c steps 71 through 76). In this case, the CVCS controls and displays are functionally grouped (mimiced) and as a result sane of the devices are not grouped by task sequence.

'Ihble 4.2-1 presents a list of the tasks which have controls and displays which are not grouped on a single panel. This list provides an indication of the devices that are not grouped by task sequence for mininun operator movenent.

'lbsk 7.3 and 7.4 are perfonned primarily on panel 001 but require checking the RCS pressure on panel 004. A plasma display device is available I on panel 001 which will provide an alternate method of checking the pressure.

1

'lhsk 8.13 involves nonitoring several systen parameters on panels 004, 005, and 006 before tenninating SI. For an overall systen monitoring task of this type it was not considered necessary for the devices to be grouped by task sequence.

4-20 2.5.8/10193 3424W/0105W

fp HOUSTON CONTROL ROOM I LIGHTING

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I "Ihsk 9.6 is similar to task 8.13 above. Also, the devices for steps I 66 and 67 are grouped close together near the boundary between panels 004 and 005.

Task 9.14 involves establishing OGV flow the seal water heat exchanger on panel 002 followed by the opening of the RCP seal return isolation valves on panel 004. This task should be per formed entirely on l l panel 004, which would require nnving the OOV flow valves to panel 004.

I For task 9.18 the pressurizer heaters are energized using controls on the right side of panel 004 and the RCS subcooling margin is verified using the tmperature displays on the lef t side of panel 005. Although on different panels these devices are grouped close together.

l Task 9.21 was defined as the maintaining of stable plant conditions.

This is similar to an overall systen nonitoring task where it was not necessary for the devices to be grouped by task sequence. Also, the operator has two plasma displays on panel 006 where all the major systen parameters can I be monitored.

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TABLE 4. 2- 1 I TASK GUJPING REVIBV - STEA\1 LINE BREAK Function / Task Panel No No Step Sequence. ?b.

7.3 B 004 001 4

5-10 7.4 001 11-13 004 14 8.13 004 51, 52 005 53 006 54-58 I 9.6 005 004 66 C

I 9.11 002 001 004 77, 78 79 80-84 I I 9.18 004 005 107, 108 109 I 9.21 004 006 005 114, 115 116-119 116-119 I

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4-29 2.5.8/10193 3424W/0105tV

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4. 3 STEATI GENERA'IDit 'IU3E IUFIULE 4.3.1 Revised 'Ihsk Analysis The operator task identification and analysis fomis were revised to reflect the changes nude on the panels and panel face location for each operator. Some of the changes involved the transferring of certain devices across the roan, causing a shif t of responsibilities between operators. The revised fonns, for the steam generator tube rupture event are presented in Appendix A.

Figure 4. 3-1 presents the revised traffic link diagram. The paths shown include those that occur after the event is identified and the diagnostic phase of the operator actions prior to the identification of the event. The updated operational sequence diagrams developed for this event are presented on Figures 4.3-2a through 4.3-2h.

4.3.2 Results Figure 4.3.-l shows the traffic link diagram for the steam generator tube rupture event. As in the steam line break event, this diagram includes both the operator actions that occur after the event, as well as the diagnostic phase of the operator actions. Also, the sequence numbers of the steps at each panel are included.

There are nine long trips (between non-adjacent panels) performed by I

l U10 2. Five of these are between 005 and 010, one between 006 and 010, and three between 005 and 007. The first path above appears to be excessive.

However, this trip never takes place between consecutive steps. The operator has anple time to make changes between panels, therefore, the significance of this path is diminished. The other two paths are also considered insignificant because of their low ntnber of occurrence.

l 4-30 2.5.8/10193 3424W/0105W

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1101 has five long trips, one between 003 and 004, four between 002 I and 004. The later ones occur during the diagnostic phase of the procedure and are considered of low enough frequency to be insignificant. 'lhe trip l

between 003 and 004 occurs only once, and at non-consecutive steps. '

'Ihe renaining high frequency paths occur between adjacent panels: 16 t imes between 001 and 004, 8 times between 005 and 006, 5 times between 006 l and 007, and 7 times between 001 and 002. 'lhese trips are not considered significant because of the proximity of the panels. It is irrportant to point out that a ntsrber of these occurrences are carried out during the diagnostic procedure. To irrprove the diagnostic phase of these events, thus irrproving the perfomunce of the operator when the energency is confronted, the operator can monitor the QDPS. A ntriber of trips will be eliminated, decreasing even further their occurrence. Another advantage of this duplication is to avoid

) the breakup of task 4 between panels 004 and 001.

I Most of the devices in the operational sequences are arranged according to the convention left-to-right and top-to-bottan. 'lhe few l

instances in which this is not the case involve tasks that require a large ntsrber of steps (see Figure 4.3-2d). In this procedure, the operator enters 1

f ran the lef t of panel 004 on step sequence 108. 'Ihe procedure continues on 1 004 up to step 124. 'Ihe arrangenent of the devices does not follow the convention desired, however, because of the large ntsrber of steps perfomed in j consecutive order. A rearrangerent cannot be made without affecting other procedures that are perfomed on the same panel. In addition, panel 004 has devices laid out in a functional fonnat including mimic lines. In this case it is considered acceptable not to follow the conventional left-to-right,

top-to-bottan fonnat.

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In the analysis of the panel content according to the guideline of grouping devices by tasks, it was found that during the steam generator tube rupture event, 14 tasks were broken up between several panels. hble 4.3-1 list these tasks, illustrating the panels on which the tasks take place, and the step ntmbers that correspond to each panel.

Task 4 is divided between panels 001,004 and 005. The steps on panel 001 and 004 are performed by IR01 and the steps on panel 005 are performed by IRO2. Step 30 on panel 004 could be included on 001 by duplicating RC-PI-457, and RC-PI-458 as previously mentioned. The operator also has the option of monitoring pressures on the panel 001 plasma display. Voice conmunication between the operators may be required when IR02 trips the four RCPs (steps 31 through 34), but the split of the steps for this task between two operators is considered acceptable.

Task 7 is broken up between panels 010 and 003. 'lko operators are used on this task. Alternate methods of verifying of fsite power from 003 are available, however, with appropriate ccumunication between operators this task is acceptable.

Task 8 reads RG hot leg tmperature on panel 005 (s teps 44-47) and the steam generator pressures on panel 006 (steps 56-59). This is considered to be a system monitoring task and was therefore acceptable.

Ask 9 involves monitoring RG teTperatures on panel 005, monitoring SG pressures on panel 006 and opening dtnp valves on panel 007. The basic controls and displays for this task are not located together for minimtm operator movement, but the operator has the option of monitoring the RCS tmperatures and SG pressures using the plasma displays located on panel 006.

Since a plasma display is on the right side of panel 006 and the dinp controls are on the left side of panel 007 the layout is considered acceptable for this task.

I 4-32 2.5.8/10193 3424W/0105W

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I On Task 11, once more the instrtments liC-PI-457 and 458 on panel 004 are involved. 'Ihe duplication of these devices on panel 001 or the use of the plasma displays would prevent the breakup of this task, u

Task 13 is performed on panels 010 and 004, involving the two L operators. Voict comunication may be an alternative, unless a method of verifying offsite vwer is available at 004. Consideration should be give to the distance between the operators and noise levels in the control roan.

p Tasks 19, 23, 36, 42, 51 and 58 involve steps in which devices are L located between panels 004 and 005. Table 4.3-1 indicates the step ntnber and the panels for each task. In this instance, the two operators have to work simultaneously on each panel, so minimun operator movanent will be required.

Because of the proximity of the two panels voice comunicat ion should be

[ adequate.

l Task 46 is broken up with cooldown monitoring perfonneo on panel 005 1 and steam dtnp performed with devices PK-556 and 01-555 on panel 007. 'Ihi s

, requires a trip between non-adjacent panels during the task. These devices are not located to minimize operator movanent. However, the operator has the alternative method of checking the cooldown rate using the plasma display I located on the right side of panel 006. As a result, the device layout was considered to be acceptable for the task.

Task 49 requires the verification of RG pressure on IC-PI-457, 458 on 004. As mentioned previously, the duplication of these ins t rtnents on panel 001 or the use of plasma displays will avoid this movanent.

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l Panel Task No. No Sten Sequence. No.

4 001 24-29 004 30 005 31-34 7 010 42 003 43 I 8 005 44-47 006 56-57 9 007 60-62, 64 006 63 005 GS 11 004 75 001 76-78 13 010 83 004 84, 85 19 004 95, 96 005 97, 98 I 23 005 004 105, 106 107 36, 42 004 132A 5 005 132B l 46 I 005 007 144 145 49 004 150 001 151-153 51 005 155 004 156 58 004 164, 164A 005 164B 4-43 2.5.8/10193 B 3424W/0105lV

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4. 4 11]SS OF OFFSITE IUVH1 4.4.1 Revised 'Ihsk Analysis The operator task identification and analysis fonns presented in the SFTA report were updated to reflect changes made in device locations. Since g

sane changes involved the transferring of certain devices across the roan, a sane responsibilities were shif ted between the operators. The updated forms for the IJOSP event are presented in Appendix A.

Using the updated information f ran the operator task identification and analysis fonns , the new traffic link diagram was developed (Figure 4.4-1). In addition, the operational sequence diagrams (Figures 4.4-2a through 4.4-2j) were drawn for this event, based on the information available fran the above forms.

4.4.2 Results I

During the perfonnance of this event, IRO2 has to perform four long I

trips between non-adjacent panels (see Figure 4. 4. -1 ) . The low number of occurrences of these paths, plus the fact that they do not occur on consecutive steps, implies that they will not pose any significant problans for the operation.

The same observation is made on the long trips . required of UOI:

between panels 003 and 004 (4 times), and panels 002 and 004 (1 t inn ) . This time, however, DOI has a long trip (003 to 004) on consecutive steps 8 to 10 (9 was deleted). Step 8 is on panel 003 and step 10 is on 004. This occurrence only happens once and it is, therefore, not considered significant.

The canaining paths involve trips between adjacent panels: once between 003 and 002, four between 002 and 001, and seven times between 001 and 004. Because of the proximity of the panels, and the low ntmber of 1 occurrences, these are also considered inconsequential.

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There is a good concurrence between the arrangenent of devices in a panel and the lef t-to-right and top-t o-bot tan convention adopted l

l for consecutive steps in a panel (see Figures 4.4-2a through 4. 4-2j ) . On the occasions in which this is not the case, the steps nny be arranged arbitrarily by the operator since they involve steps that require verifications and checks which do not necessarily have to follow the sequence shown on the diagram.

I Based on the panel content guideline, devices should be grouped by I tasks on single panels.

follow this guideline.

Table 4.4-1 lists a nunber of tasks that do not Function, task, and the corresponding step sequence I ntubers are indicated for the tasks associateo with the IDSP event.

'Ihsk 3 is perfonned on four different panels: 004, 001, 002 and 006. The task to be accaTplished is to pull-to-lock the ptrrps listed on the operator task identification and analysis forms (Appendix A) (steps 3 to 16).

This task was judged as similar to a systen monitoring task and therefore considered acceptable to involve several panels.

I On task 23 panels 001 and 002 are used to verify EOV operation. The devices are grouped together for the three loops of the EGV systen, therefore, this arrangenent is acceptable.

Task 30 involves the IICP thermal barrier cooling. Steps 111-112 are perfonned on panel 002, while 113 and 114 are perfonned on panel 001. This is

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I Steps 96 and 97 of task 27 are perfonrad on panel 001 while steps 98 and 99 take place on panel 002. This task involves the activation of several ptnps which could have been defined as two different tasks. The layout for this task is within a fairly small area covering the two panels. 1 I

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Tasks 15 and 20 involve steps which require panels 005 and 004, however, only monitoring tasks are involved and the proximity of the two adjacent panels is considered adequate.

Task 16 involves panels 005 and 001. Verification that Si has actuated can be done on panel 001, also, and this arrangenent is considered adequate.

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'It'RBINE IIMD REJECI' ION 4.5.1 Revised Task Analysis The traffic link diagran of Figure 4.5-1 was developed based on the revised infonmtion available frcm the operator task identification and analysis forms. These revisions reflect device relocations among the panels, the elimination of certain steps due to design changes and the shif ting of responsibilities between the operators due to across-roon relocations. These forms are presented in Appendix A. New operational sequence diagrams were

- {

drawn to reflect rearrangments made on the panel faces, and the grouping of

~ devices by tasks. These diagrams are presented on Figures 4.5-2a through L 4.5-2e.

l 4

4.5.2 Results I In Figure 4.5-1 it can be seen that LRO2 has to perfotTn two long trips fran panel 007 to 010. Step 4 on panel 010 specifies that 1102 check the offsite power availability. These trips can be eliminated by reading bus voltage on panel 007.

I 1102 has two other long trips, between panels 007 and 009. This occurs on consecutive steps: steps 5 and 6 are performed on panel 007; step 7 l is on panel 009 and finally steps 8 to 10 are on panel 007. It was observed that the change breaks up task 1.2 between the two panels. The small length of both panels, however, makes the distance between then about the same as the distance between two adjacent panels of average length. The remining trip between panels 009 and 007 is performed for non-consecutive steps,. and therefore it is not considered significant.

The traffic link diagran shows a ntmber of trips made between adjacent panels; eight trips involve the area covered by panels 006, 007, 003

{ and 009. Since panels 007 and 009 are small, the total distance covered by the operator is inconsequential.

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The operational sequence diagrams of Figures 4.5-2a through 4.5-2e show groups of three or more consecutive steps performed on a single panel.

Although in sane instances the arrangment of devices being useo does not agrec with the lef t-to-right, top-to-bottan convention, the performance of the operator will not be af fected markedly because of the small nurrber of steps involved in each group of sequences. This case is observed on Figure 4.5-2b on the operations involving steps 11 through 15. This is primarily a E

5 monitoring operation where the operator can arbitrarily rearrange the sequence and the overall task will be perforned satisfactorily.

Table 4.5-1 was developed to list the tasks whose devices were not grouped in a single panel as outlined on the panel contents guidelines.

Task 1.1 consists of checking the main generator status. To accaTplish this, IR02 performs steps I through 3 on panel 007 and then checks for offsite power availability on panel 010. As discussed earlier, this step can be performed on panel 007, thus eliminating the task break-up.

Task 1.2 was discussed above. Task 14. 2 involves the monitoring of I

secondary parameters on panels 006 and 007. For an overall system monitoring task of this type, it was not considered necessary for the devices to be grouped by task sequence.

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4.6 PLANT STAKlUP l 4.6.1 Revised Task Analysis I

'lko traffic link diagrams shown in figure 4.6-la and 4.6-lb were developed based on the revised information on the operator task identification g and analysis forms. He revisions reflect device relocations among the M panels, the elimination of certain steps due to design changes, and the shif ting of responsibilities between the operators due to a':ross-rocm device relocations. These forms are presentea in Appendix A, and reflect the original responsibility split between operators (see figure 4.6-la). Figure 4.6-lb shows how changing to a ntmal split affects the tasks division.

New operational sequence diagrams were drawn to reflect rearrangenents made on the panel faces, and the grouping of devices by tasks.

%ese diagrams are shown on Figures 4.6-2a through 4.6-2x.

4.6.2 Results As can be seen on the traf fic link diagram for the startup event (Figure 4.6-la), 1102 makes a ntmber of long trips (between non-adjacent panels). %e most frequent one is between panels 005 and 007 which is performed five times. All of these trips occur during consecutive steps, thus time sensitive tasks could be affected. Five trips were however, not considered excessive for a non-ane rgency event. Procedures are now being prepared, and will divide responsibilities at the panel 005 and 006 break.

I he of these trips occur on task 15.2. Steps 371 through 383 are done on panel 007, then the operator moves to panel 005 to increase reactor power to approximately 6 percent (step 384) and returns to panel 007 to check for DCS tmperature increase on step 385.

It is also observed that task 17.1 is broken up between three panels: 005, 007, and 008. On this task, the operator is to increase the 4-68 2.5.8/10193 3424N/ 010SV

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t 4rbine load to 20 percent by using the " REFERENCE" and "CD" buttons on panel 007. When the reactor power has increased above 10 percent, it is necessary B to travel to 005 to perform steps 431 through 433. On steps 434 and 435, the operator goes to 008 and terminates the task on panel 007 by activating "IMI'UISE IN" button as described in step 436.

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All the other trips between non-adjacent panels were considered

{ nonsignificant for this type event due to low frequency.

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It should be noted that the same operator area of responsibility was asstaned for the startup validation as was used in the SFI'A Report , with IR01 ,

responsible for panels 001 through 004 and IBD2 responsible for panels 005 through 010. As shown in Figure 2.1-1, this was a change from the recannended operator responsibilities for normal events such as the startup. This change h was made in the initial SFTA to equalize the distribution of operations between the operators.

f hith the panel redesign the distribution of actions between the I operators has shif ted so that now 1RO2 is responsible for 291 steps and 1101 is responsible for 115 steps (see f igure 4.6-la) . To equalize the operator responsibility with the new design, it is recaTmended that panel 005 be operated by IBOl (nomal conditions in Figure 2.1-1). 'Ihis will redistribute the steps with IBO2 responsible for 240 steps and IROI responsible for 169 l steps, still unequal but a significant inprovanent . The traf fic link diagram for this revised arrangenent is shown in Figure 4.6-lb.

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'Ihe revised traf fic link diagram shows that the five traverses between 005 and 007 are eliminated and the long path between 005 and 008 will also disappear.

f In addition, the four trips by 1102 between 005 and 006 will be replaced by 12 trips between panels 004 and 005 by IROI.

Also with the revised traf fic link diagram, IBOl will have to make l one long traverse fran panel 005 to panel 001 at consecutive steps. Step 135 I

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is on the central desk, step 136 is on 005 and 137 is on panel 001. If step 136 can be performed on 001, IK>l will have eliminated this long trip. 'Ih i s trip, however, should not be considered significant because of its single occurrence, although consideration should be given to the tine factor involved in making a long trip at consecutive steps.

Other long paths of travel on Figure 4.6-lb are observed. %ree timas between 006 and 008 which do not involve a transfer at consecutive steps, therefore, no significance is given to this path; also a path between 008 and 010, 006 and 009, 010 and 007 are shown, each happening only once, thus they are considered inconsequential.

hith the revised link diagran, IROI has to nake 4 changes of panel at 004 and 005, involving the perfomance of one or two steps. It is observed that task 9.1 would require this operator to made 2 round trips between 004 and 005: steps97-100 on 004; steps 101-102 on 005; 103-104 on 004; and 105-107 on 005. 'lhe next three tasks (9.2, 9.3, and 9.4) involve the repetition of steps 103 and 104 to verify themm1 barrier flow and pressure, hhile it is desirable to include all these steps in a single panel to carply with the guideline of grouping devices in a panel by tasks, the arrangenent was considered acceptable for the startup event since this is a non-anergency event.

Table 4.6-1 lists the tasks with devices not grouped in a single panel. %ey are listed in two groups; one is the steam bubble startup phase of the startup procedure, followed by the reactor coolant heatup phase.

Task 3.1 is to establish ICS letdown flow path. This task is I

performed primarily on 004 by starting on step 36 which verifies the pressure spray valves and then activating valves fran 1016 to CVCS on panel 001. "Ihe task ends on panel 004 f ran steps 41 through 45. 'Ihe devices are not located for minimun operator movanent during this task, but since these panels are adjacent this was considered acceptable for the startup event as discussed in Section 4.0.

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Task 3.2 also requires the nanipulation of valves fran RBRS to CRS on 001 af ter monitoring the pressurizer level on 004. In addition, the task 4.1 requires the break-up of steps between 001 and 004. Again the IGiR to CVCS valves are involved in this procedure and monitoring on the @PS on panel 001 will avoid these task breakups.

Task 5.1 requires the operator to verify the status of condensate l punp discharge valve on panel 008 (step 186) and then move to 006 to verify the steam generator feedpmp discharge valve and the steam generator feeopunp recirculation valve. It is observed that to emply with this task, the I operator goes fran the extrane right of panel 008 to the left of panel 006.

'Ihe devices are not arranged for mininun operator movement for this task.

However, since this task occurs only once during the event and since the I startup is a non-time dependent event, this task was considered acceptable. l l

Task 6.1 involves verifying SGFPT and nmin steam crain valve status and is perfonned on panels 006 and 007. Although different panels a; e involved, the panels being adjacent and the snell size of 007 reduces the significance of this occurrence.

I Task 15.2 involves rolling the main turbine which is performea primarily on panel 007. Ilowever, one step is performed on panel 008, one step on panel 005 and one step on panel 006, out of a total of 24 steps. Since this task occurs only once during the startup, and since panel 007 is a small panel with the device on panel 008 located adjacent to panel 007 this task was judged to be acceptable. Also for the Figure 4.6-Ib link diagram the step on panel 005 would be perfonned by UCI with the other 22 steps perfonnea by UD2.

I Tasks 17.1 and 17.10 involve increasing the main turbine load which requires turbine adjustments on panel 007 and power adjustments on panel 005.

Task 17.1 also involves using NSR devices on panel 008 and task 17.10 involves 4-71 2.5.8/10193 342M/0105W -

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monitoring the FW system on panel 006. 'lhe layout for these tasks was judged acceptable due to the low frequency of the task, the non-time dependent nature of the event, the small size of panel 007, and the proximity of the devices on panel 008 to panel 007 and the split in operator responsibilities being used g

in the procedure. W Fran the operational sequence diagrams (Figures 4.6-2a through 4.6-2x) the operator's moveTents within a panel were analyzed with respect to the lef t-to-right, top-to-bottan convention adopted. Because of grouping the devices by tasks, some panels involve several tasks and as many as 20 or more steps perfomed sequentially within one panel.

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B TA13LE 4.6-1 TASK GROUPING REVIEW - PLANT STARTUP l

I Function / Task Panel No. No. Step Seq. No.

I 3.1 004 001 36,41-45 37,38 Steam 3.2 004 46 Bubble 001 47 Startup 4.1 004 51-55 I 001 004 56 57-68, 70-71 I 5.1 008 006 186 188-189 6.1 007 198,200,202,204 006 205-208 15.2 008 370 I Reactor Coolant Ileatup 007 005 371-383,385,387 389-393 384 1

006 386 17.1 007 430,436 005 431-433 008 434,435 17.10 007 491 I 005 006 492 493 l I

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5.0 OVERALL SFTA RESULTS AND OBSERVATIONS The major results of the SFTA were obtained from the traffic link diagrams and the operational sequence diagrams. Discussion of these results for each SOE is presented I

in Section 4. Additional results are discussed in this section based on the consideration of all the diagrams as they pertain to a given panel.

5.1 PANEL 001 l

This panel is primarily an SI control panel containing the control devices and displays for the fillSI, the LHSI, and the RHR systems. The devices for each of the I

systems are grouped together and those for each of the three trains of these systems are grouped together. The link diagrams and the operational sequence diagrams for all six l SOE's were reviewed to obtain an overall evaluation of panel 001.

)

} The link diagrams were reviewed with regard to operator travel between panel 001 and the other panels. Table 5.1-1 summarizes the results. As shown all the travel for panel 001 is to or from the two adjacent panels 004 and 002 with most of the trips between panels 001 and 004. None of these traffic paths were considered to have excessive frequency for travel to adjacent panels. But, as discussed in Section 4 a significant number of these trips to panel 004 could be eliminated by adding a duplicate display of RCS pressure on panel 001 or by using the plasma display to read RCS pressure

{ on panel 001.

I l The operational sequence diagrams were reviewed for panel 001 with regard to the human engineering criteria that requires task grouping of devices (See Section 4). A single observation was made regarding task 9.10 of the LOCA event. For this task the RC3 is cepressurized by adjusting SI pump flow on panel 001 and pressurizer spray flow on panel 004. The devices are therefore not grouped to minimize operator movement for this task. All the other events showed that the layout on panel 001 was acceptable with regard to task grouping criteria. Also, no cases were found of operational sequences on this panel that were not grouped in an orderly manner.

2.5.8/10193 3435W/0105W

HOUSTON CONTROL ROOM UGHTlNG DESIGN REVIEW

.._1s POWER CO.

TABLE 5.1-1 PANEL 001 - PANEL "lRAFFIC PA'116 To/Fran No. of Event Panel bo. 't r i ps IDCA 004 15 002 9 Sterin Line Break 004 13 002 13 SG hbe Itupture 004 16 002 7 IDSP 004 7 002 4 hrbine load Rejection -

0 Plant Startup 004 9 I

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5.2 PANEL 002 l

Panel 002 contains the equipment for controlling and monitoring the containment spray system, the CCW system,the ECW system, the RCFC devices, the containment isolation devices, and the primary system sampling devices. All the I multi-train systems on this panel have the controls and displays grouped by train. All the SOEs except the turbine load rejection and the plant startup involve operations on this panel.

Table 5.2-1 summarizes the results of the traffic link review for panel 002.

Most of the paths occur between adjacents panels 001 cr 003 and occur infrequently.

I The most significant cperator travel occurs during the steam line break event with 13 trips to/from adjacent panel 001 and 12 trips to non-adjacent panel 004. These were not considered excessive because half of the 12 trips to the non-adjacent panel were non-consecutive steps.

With regard to the task grouning, the operational sequence diagrams and the corresponding task / step data on form E showed no cases of unacceptable grouping of equipment for panel 002. Also, no cases were found of operational sequences occurring on this panel that were not grouped in an orderly manner.

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TAB 11 5.2-1 PANEL 002 - PANEL 'IltAFFIC PA'IIS To/Fran No. of Event Panel bo. "Irips IOCA 001 9 004 5 Stetm Line lircak 001 13 I

004 12 SG 'Ibbe Itupture 001 7 003 1 IDSP 004 4 001 4 003 1 004 1 I

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l 5.3 PANEL 003 l

I Panel 003 contains the diesel generator and the DC power supply control devices and displays. Of the six SOEs only the SG tube rupture event and the LOSP event include operations on panel 003.

For the SG tube rupture the traffic link analysis showed one operator trip from panel 002 to 003 and one trip from panel 003 to panel 004. For the LOSP the analysis indicated one trip from panel 003 to panel 002 and four trips between panels 003 ano 004. The low frequency of occurrence for these operations shows that the traffic flow to and from panel 003 is relatively insignificant.

In the operational sequence analysis only one operator step occurs on panel 003 during the SG tube rupture event and ten steps occur during the LOSP. The layout of the equipment was determined to be acceptable with regard to task grouping and orderly grouping according to sequence.

I 5.4 PANEL 004 I This panel contains the equipment for controlling and monitoring the CVCS I system and associated subsystems, and the pressurizer. The devices for the CVCS are functionally arranged and mimiced to represent the flow related layout of this system.

Significant operator activity is required on panel 004 for all six of the SOEs.

Since the assumed area of responsibility for the LRO 1 in this analysis is generally panels 001 through 004 the traffic paths to and from panel 004 were discussed in I the results for panel 001 through 003 (Sections 5.1 through 5.3). Tables 5.1-1 and 5.2-1 include the traffic flow path for panel 004. The only significant traffic path was the 12 trips between non-adjacent panels 002 and 004. This path is discussed in Section 5.2.

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The operational sequence analysis on panel 004 showed that the panel layout was acceptable with regard to task grouping criteria.

Of all the panels, panel 004 showed the least orderly grouping of devices with respect to sequence of use in individual tasks. However, since this panel has the CVCS layed out on a functional basis, the left-to-right or top-to-bottom convention was not adhered to closely for tasks involving this system.

5.5 PANEL 005 This panel holds the devices and displays for the reactor control system, the I

reactor coolant pumps, the safety actuation systems, and other miscellaneous systems relating to reactor vessel isolation, pressurizer conditions, and boron concentration. All six SOEs have operator activities that are performed on panel 005.

A review of the link diagrams with regard to traffic paths to and from panel 005 was performed. Table 5.5-1 summarizes the traffic paths for this panel. The maximum number of trips to an adjacent panel (006) was eight and the maximum number to a non-adjacent panel was five. These were not considered excessive.

The operational sequence diagrams for the six SOEs were reviewed with regard to task and orderly grouping criteria. The layout of the devices on panel 006 was judged to be acceptable.

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'IABLE 5.5-1 PANEL 005 - PAbEL 'lIMFFIC PNI16 I Event To/Fran Panel No.

No. of

'Irips lira 006 2 007 1 010 1 Stemi Line Break 006 6 007 2 I 010 Console 2

1 I SG 'Ibbe Itupture 006 007 010 8

3 5

Console 2 IDSP 006 1 010 3

'Ibrbine load llejection 004 4 Plant Startup I 006 007 008 4

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5.6 PANEL 006 Panel 006 contains the control equipment for controlling and monitoring the operation of the auxiliary feedwater systems, steam generators and the boiler feedpumps. The devices are grouped together for each of the four loops. All of the SOEs have operator actions that are performed on this panel.

The traffic link analysis is summarized in Table 5.6-1. The maximum number of operator trips is 12 trips to/from adjacent panel 007 during the plant startup. The maximum number of trips to a non-adjacent panel was three to panel 008, also during the plant startup. None of the trips shown for panel 005 are considered excessive.

All of the operations on panel 006 for the six SOEs showed satisfactory and orderly grouping by sequence for all tasks. In general all tasks follow the left-to-right convention in order of use.

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TAB 12 5.6-1 PANEL 006 - PANEL 11tAFFIC PA116 E To/Fran No. of Event Panel No. Trips 10 0\ 005 2 007 2 Console 2 Stean Line Break 005 6 007 1 I 010 Console 1

3 SG lbbe Rupture I 005 007 010 8

5 1

Onsole 2 IDSP 005 1 010 1 Onsole 2 Turbine lead Rejection 007 4 ,

Plant Startup 005 4 007 12  ;

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I S .7 PANEL 007 Panel 007 contains the control devices and displays for turbine-generator control (the EllC panel and monitoring), the turbine generator sychronization system, and the steam generator dump system. All the SOEs except the LOSP have operator actions occurring on this panel.

The link diagram analysis showed that the maximum number of trips to/from other panels was 12 between panels 006 and 007 during the plant startup. This was not considered excessive because the panels are adjacent and panel 007 is a small panel. A maximum of five trips occurs between panel 007 and a non-adjacent panel (005).

The operational sequence analysis showed that most of the operations on panel 007 occur during the plant startup. Many of these did not follow a strict left-to-right or top-to-bottom sequence due in part to the many operations required on the EHC panel.

This was, however, considered acceptable because of the small size of this panel.

E No observations were found on panel 007 regarding the grouping of devices by task.

5.8 PANELS 008 AND 009 {

These panels contain the controls and displays for the MSR system, the g feedwater heaters and the condensate system. The SOEs that involve these panels are the R turbine load rejection and the plant startup. These two panels were treated as a single panel in this SFTA due to the small size of panel 000 and the related nature of the equipment on these panels.

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HOUSTUta l CONTROL ROOM l MMG DESIGN REVIEW

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The link diagram analysis fcc panets 008 and 009 r,howed that a maximurn of five trips occurred between panel 008 and adjacent panel 007 during the plant startup. A maximum of three trips occurred between panel 008 and non-adjacent panel 006 during i the plant startup. Also three trips occurred bety.cen panel 009 and non-adjacent panel 007 during the turbine load rejection event. None of the traffic paths for panels 008 or 000 were considered unacceptable.

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, The operationel sequence analysis showed very little sequential activity on panels 098 and 009. The turbine bld rejection had eight ateps and the plant startup had 12 steps occurring on these panels. The layout of the devices for these operations was considered sotisfactory.

5.9 PAN EL 010 s

i This panel is the electrical distribution panel *vhich contains the electrical power distribution controls and displays le addition the panel has displays for monitoring the bus sychronization. All the SOEs have some operator actions that occur on panel 010 but only the startup event shows any significant activity (19 s eps).

I The link diagram analysis shoveed a maximum of five trips occurrad between I panels 010 and 005 during the SG tube ruphre event. This is a long trip for three steps involving the verification cf off-site power a>ailability. This was considered acceptable because of the low frequency and also because. the operator has the option of performing this step on panel 007.

A single operational sequence diagram was developed for panel 010 or. the startup event steps. For these steps the LRO2 performs a series of four sychronization operations (See Fig. 4.6-2x) involving auxiliary buses.

)

The location of the devices wabjudged to be satisfactory for this sequence of 8 operations.

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.,. . . & DESIGN REVIEW I . _. W POWER CU.

I 6.0 RESULTS AND OBSERVATIONS OF W ALK-TIIROUGil/ TALK-THROUGH In general the exercise shows that most of the activity takes place on the front panels i.e., panels 001, 004, 005, 006 and 007. Dere were several cifferences noted between the nomenclature used on the panel labeling and that referred to in the procedures. These were noted by the operators for correction. De exercises helped to l Identify a few missing functional activities and procedural steps. These were noted for procedure modification.

The hierarchial labeling was obviously helpful in locating equipment to be operated. It was also obvious by observing the eye-hand motions of the operators that the demarcation patches will reduce the search time for panel devices.

T' I

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The following specific observations were maoe for the steam tube rupture event:

Condsideration should be given to providing graphics on the plasma wplay that are tailored for specific operating evolutions or emergency situations. During the walk l

through for Steam Generator Tube Rupture and Plant Start Up it was noted that displays, such as those listed below would be useful:

l o

Steam Generators; a graphic display of steam generator level and 5

I pressure and auxiliary feedwater flow. Two steam generators should be I

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on each of the plasma displays on CP-006.

o Reactor Coolant System lleatup Rate; a graphic display for heatups that will be similar to figure 6.0-2 and show:

1

- Minimum pressurization temperatures

, - Coolant temperature I - Heatup rate

- Minimum pressure to run reactor coolant pumps I

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o Ileactor Coolant Systems Cooldown Itate; a graphic display for cooldown rate that will be s'milar to figure 6.0-1 and show:

- Coolant temperature

- Cooldown rate

- Coolant pressure

- Minimum pressurization temperatures This graphic should be available on the plasma diQiay on CP-004.

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o Subcooled Margins; a graphic display of parameters that need to be I

checked to assure adequate subcoolings Pressurizer pressure

- Pressurizer level

- Core exit thermocouples, average

- Subcooling, calculated value

- Subcooled margins I

o Containment; a graphic display of parameters used to determine the status of the containment.

- Containment pressure E

- Containment moisture 5

- Containment temperature

- Containment emergency sump levels

- Containment hydrogen i

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o Reactor Power; a graphic display of the nuclear instrumentation.

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- Source range level

- Source range start up rate

- Intermediate range level

- Intermediate range start up rate

- Power range level i o Generator Capability; a graphic display to show the allowable I turbine-generator loading similar to figure 6.0-3. .

Observations of the operators motion during the walk throughs demonstated that it could be beneficial to revise the procedures to have the operators perform operating / checking / verifying equipment on a system or sub-system basis. Checking by system or subsystem is made easy because of the demarcation color patches. 'Ihis would significantly reduce operator motion and the time to perform the evolution. The sequence should start at the right side of the Engineered Safety Feature panels, (because of its orientation with regards to the CVCS and Reactor Control Panels) and proceed to

, the left.

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I HOUSTON CONTROL ROOM LIGHTING DESIGN REVIEW

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l APPENDIX A l

OPERATOR TASK INDENTIFICATION AND AN ALYSIS

1. SMALL BREAK LOCA
2. STEAM LINE BREAK
3. STEAM GENERATOR TUBE RUPTURE
4. LOSS OF OFFSITS POWER
5. TURBINE LOAD REJECTION
6. PLANT STARTUP Steam Bubble Startup I Reactor Cociant Heatup I i l

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APPENDIX A.1 OPERATOR TASK IDENTIFICATION AND AN ALYSIS SMALL BREAK LOCA q

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M M W W.W W W W W W W W~M' CONTROL ROOM DESIGN REVIEW EVALUATOR G. J. Malek

. HOUSTON LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE

- m. & DATE NE POWER CO. PAGE 1 0F m SMALL BREAK LOCA W ERG E-O Julv 82 LIST OF TASKS FOR EVENT: REF l

TASK / STEP TASK SSJECTIVE DESCRIPTION PERFORIAED IAONITORED PANEL LIST EQUIPteENT REQUIRED TO REFEREllCE aY aY 110 8. CotePLETE TASK IlliteSEA (LIST IN SEQUENCE) liRG SEQ LRO

  • STEP N O. N O.

1.1 All rod bottom lights-LIT E0-1 1 2 SRO 5B 1.2 All rod position indic ators - 2 2 SRO SD ZERO 1.3 Neutron flux - DECREASING 3 2 SRO 5B/C 1.4 All turbine stop valves - E0-2 4 2 SRO 7D CLOSED 1.5 AC Emerg bus voltage - NORM AL E0-3 5 1 SRO 1 A-1 1.6 Annunciation "SI Actuation" E0-4 6 2 SRO SA-2 LIT {

2.1 FW Flow Control: FK E0-5 Valves - Closed: FK-551 7A 2 SRO 6D Panel IM 28 FK-552 B GB Status Lights FK-553 C 6B Status Lights FK-554 D 6B Status Lights 3089W/0091W Revised 7/12/83 R. C. Pottek

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  • POWER CO. SM ALL BREAK LOCA PAGE g "'Y LIST OF TASKS FOR EVENT: REF TASK 88JECTIVE DESCRIPTION PERFORABED RIONITORED PANEL LIST EOUIPetENT REGUIRED TO TASM/5TEP REFERENCE NUARSER (LIST IN SEGUENCE) sy By N0L CORAPLETE TASK ERG SEQ LRO -

STEP N O. N O. -

2.5.1 Verify following isol. EO-6 9 1 SRO Valves - CLOSED RIllt sample: FV-4458 9A 2D FV-4459 B FV-4460 C FV-4461 D St Accum Sample: FV-4463 E FV-4464 F FV-4465 G FV-4466 11 RMWS to PRT: FV-3651 10A 1 SRO 4C CVCS Letdown Line:XCV-023 B XCV-024 C RCP Seal 112 0 Return Line: XCV-077 IIA XCV-079 B CYCS Charging Line:

. XCV-025 12A 1 4D 11CP Seal 112 0 Injection: XCV-033A B 1 4C XCV-0338 C 1 4C i XCV-033C . D 1 4C XCV-033D E 1 4C '

avoan, uu:n n Revised 7/12/83 R. C. Potter

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CONTROL ROOM DESIGN REVIEW EVALUATOR G. J. Mnf ek HOUSTON LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSl5 SIGNATURE g

- mm & DATE N'E PCWER CO. ^ U SM ALL BREAK LOCA D' ER G E-O .My A9 LCT OF TASKS FOR EVENT: REF TASK / STEP TASK 88JECTIVE DESCRIPTION PERFOR40E0 800NITORED PANEL LIST EOUIPteENT REQUIRED TO REFERENCE ay By NOS. C004PLETE TASK NutetER (LIST IN SEQUEllCE)

ERG SEQ LRO STEP N O. N O.

3.5 Charging Pump Breaker Indicator Lights - LIT Note: For STP, this step is uncertain.

3.6 IlliSI Pumps Breaker E0-8 Indicator Lights - LIT 16 1 1B Trains A, B, C 17 1 IB Panel 2M24 18 1 IB Panel 3MI1 3.7 LHSI Pumps Breaker Indicator Lights - LIT 19 1 IB Trains A, B, C 20 1 IB Panel 2M24 21 1 IB Panel 3Mll 3.8.1 Verify CCW Pumps Running E0-9 22 1 SRO CCW Pump Breaker Bypass /Inop Panels:

2B A = 1M23 Indicator Lights - LIT 2B B = 2M22 3.8.?, Repeat for Trains A, B, C 23 1 2B 3.8.3 C = 3M10 24 1 IB le 3.9.1 Verify ECW Pumps Running E0-10 25 1 ECW Pump breaker Bypass /Inop Panels:

2B A = IM23 Indicator Lights - LIT 2B B = 2M22 E

3089W/0091W Revised 7/12/83 R. C. Potter

. . Ja h CONTROL ROOM DESIGN REVIE!) EVALUATOR NOUSTON LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSl5 SIGNATURE

-.- & DATE

" "I 6 21 POWER CO. SM ALL BilEAK LOCA PAGE REF E July 82 LIST OF TASKS FOR EVENT:

I PERFORttED tt0NITORED PANEL LtET EQUlretENT REGUIRED TO TASK /5TEP TASK OBJECTIVE DESCRIFTION REFERENCE BY BY NOL C0terLETE TASK butBSER ILIST IN SEQUENCE)

EllG SEQ LRO .

STEP N O. N O.

3.9.2 llepeat for Trains A, B, C 26 1 2B C = 3M10 3.9.3 27 1 IB 3.10.1 Verify Containment Fan E0-11 28 Bypass /Inop Panels:

Coolers llunning 29 2B A = 1 M21 Fan Cooler Indicator 30 2B B = 2M20 lights - LIT 2B C = 3M08 l 3.10.2 Repeat for Trains A, B, C 3.10.3 3.11 Containment Purge Valves E0-12 31 1 Silo 2B Bypass /Inop Panels llA-008 - CLOSED 32 2B A = 1M20 II A-010 - CLOSED B = 2M19 II A-009 - CLOSED l II A-007 - CLOSED .

l l II A-002 - CLOSED l II A-003 - C LOSED II A-001 - CLOSED II A-004 - CLOSED l II A-005 - CLOSED ll A-006 - CLOSED 3.12 Check if Main Steamline E0-13 33 2 6B Isolation is Actuated Method Uncertain l

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aucun/tuulW llevised 7/12/83 R. C. Potter

- -___. . M_ M M M M

CONTROL ROOM DESIGN REVIE'*) EVALUATOR G. J. Melek NOUSTON LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE g== ., & DATE EM- POWER CO* PAGE 7 0F  ?!

SM ALL BitEAK LOCA W ERG E-O Julv 82 LIST OF TASKS FOR EVENT: REF TASK /5TEP TASK S8JECTIVE SEscairrieu PfarenalEs seemlTeafa PANEL LIST EOUlre8ENT REGUIRES TO REFERENCE 3Y SY IBGE, CORAPLETE TASK Nute8ER ILIST lel SESUENCEI ERG SEQ LRO '

STEP N O. NO.

4.1 Check Containment Pressure E0-14 1 SRO Available Instrume.its:

34 2B PI - 934 PI - 935 35 2B PI - 93G PI - 937 4.2 Compare to Ili-2 and fli-3 For the small break LOCA, assuroe the pressure is 1 :ss than 111-2 alid 111-3.

4.3 Verify SI Flow. E0-15 1 SRO Read HCS.

Available Instruments: 4B 36 PI - 455 PI - 456 PI - 457 PI - 458 4.4 Compare to:

(a) 1600 psig = lillSI Pump shut off head (b) 288 psig = LilSI Note: For this event, assume pre ,sure is less than I iOO psig.

Revised 7/12/83 R. C. Potter E 3089W/0091W

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-, & DATE 8 21

"" POW 4R CO. SM ALL BREAK LOCA PAGE gF LIST OF TASKS FOR EVENT: REF TASK /5TEP TASK SSJECTIVE DESCRIPTION PERFORRIED IGONITORED PANEL LIST EQUIPteENT REQUIRED TO NEFERENCE SY aY NOS. CDeePLETE TASK Bue0SER (LIST lE SESUENCE)

ERG SEQ LRO -

, STEP N O. NO.

4.8 Cheek RC Pump Seal E0-18 44 1 SRO 4A Cooling Anunneistor for CCW flow to RCP thermal barriers

-Normal 5.1 AFW Valve Alignment: E0-19 45A 2 SRO 6D FV-7525 Open 45B FV-7524 Open 45C FV-7522 Open 45D FV-7526 Open 46A FV-7518 Closed 46B FV-7517 Closed 46C FV-7516 Closed 46D FV-7515 Closed 5.2 Verify SI Valve E0-20 SRO Alignment Si Valve Lineup, 48 IB Train A

. RWST Isol Valve XSI-001 A, B, C, Open E

3089W/0091 W Revised 7/12/83 R. C. Potter

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= =, & DATE ER CO.

SM ALL BitEAK LOCA PAGE -; ;;;&f;g 3; 32

. LET OF TASKS FOR EVENT: REF TASM/5TEP TASK 88JECTIVE DESCRIPTION PERFORGIES 300NITORES PANEL LIST EBUIPt0ENT REQUIRED TO NutBSER (LIST IN SEGUENCEI REFEMNCE ay sy NOL C0eAPLETE TASK ERG SEQ LRO .

STEP N O. N O.

6.2 Compare to 1600 psig.

Note: For this event, pressure it assumed to less ti an 1600 psig.

6.3 Check if RCS Depressurization EO-30 can be stopped.

Close pressurizer spray 52 1 SRO 4B PCV-6558 valve PCV-655B Close pressurizer i SRO 4B PCV-655A PORV PCV-655A

' 6.4 Check if RC Pumps EO-31 should be stopped 53 1 SRO ID IlliSI Pumps Running: 54 ID 55 ID

1. Check breaker indicator light.  ;
2. Check SI Flow 56 1 SRO IC FI-901, 902, 903 57 1 IC 58 IC Assume result is yes 6.5 Check RCS Pressure, 59 1 SRO 4B PI-455 Compare to NPSil( 400 psi) PI-456 i Assume result is not to stop PI-457 l the ItC pumps.  ;

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3089W/0091 W Revised 7/12/83 R. C. Potter L_ _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ .

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SMALL BitEAK LOCA W ERG E-O July 82

! LIST OF TASKS FOR EVENT: REF TASM/STEF TASK SSJECTIVE DESCRIFileN PERFOA8AES RIONITSAES FANEL LIST ERulPMENT REGulAEO TO REHRENCE EV 3Y NOS. CDAAPLETE TASK NutteEA ILIST le SESUENCE)

ERG SEQ LRO -

STEP NO. N O.

7.1 Check if RC Pumps should be El-1 This step is omitted. '

stopped. (Same as Step 6.4).

l 7.2 Check RWST Level El-2 64 SitO 1 ID LI-931 Head 65 I ID Assume slowly decreasing, which is OK.

7.3 Check Containment Sump Level El-3 66 1 4C LI-7812 Assume slowly increasing, OK.

7.4 Steam Generator Levels, Narrow Hange: El-4 69 2 SRO SG 1 A: LI-518 6B LI-517 NR 28 A SG IB: L!-527 SG IC: LI-538 LI-529 Nlt 2B B SG ID: Ll-547 LI-537 NR 2B C LI-549 Nlt 2B D LI-502 WR 2B B LI-504 Wil 2B D

. LI-519 WR 2B A LI-539 Wit 2B C 7.5 Throttle AFW Flow to Maintain SG Level at (?)

70 2 SitO GD FV-7525 71 6D FV-7524 72 2 GD FV-7522 73 6D FV-7526

(?) Many setpoints are not availat le.

E 3089W/0091W llevised 7/12/8311. C. Potter

G. J. Melek CONTROL ROOM DESIGN REVIE3 EVALUATOR NOU$TCJ LIGHTING OPERATOR TASK 10ENTIFICAT10] ATO ANALYSl3 SIGNATURE

..& DATE

~

  • PAGE I4 0F 2f SM ALL BREAK LOCA jf ERG E-O July 82 REF LCT CF TASKS FOR EVENT:

PERf0RetED ttomlTORED PANEL LIST EOUIPteENT REGulRED TO TAsu/5TEP TASK S5JECTIVE DESCRIPTION REFERENCE SY SY NOS. CotIPLETE TASK NueBSEA (LIST IN SEGUENCEI ERG SEQ LRO

  • STEP N O. N O.

7.6 Pressurizer POltV & Block El-5 Valves: (Is there 1 Silo 4B

1. Power Available to block a way 74 Valves - Yes to check) i
2. PORV I 75 1 4B PCV-655A Closed PCV-655B Closed .
3. Block Valves l 76 1 4C XitC-001 A Open l XitC-001B Open  !

7.7 Check if charging Pumps should El-6 SRO l l be started  !

l 1. Read RCS Pressure '77 1 4B PI-455, 456, 457, 4 58 l

2. Read lillSI Flow 78 I IC FI-901, 902, 903 l 79 1 1 IC 80 1 IC
3. Assuming the event is pro-gressing normally, Si is not terminated, and Charging Pum >s are not started. (i.e Go to E-1, Step 16).

Note: For STP, the charging pump controls are not final. They may or may not >e started at this point.

E 3089W/0091 W Revised 7/12/83 R. C. Potter

_ __ _ sm t a ms e m . u!= sus _ sam __ims

G. J. Malek HOUSTON CONTR2L ROOM DESIGN REVIEC EVALUATOR OPERATOR TASK IDENTIFICATION AND ANALYS15 SIGNATURE g

LIGHTING OATE 0.

SMALL BitEAK LOCA PAGE 15 0F 21 REF E E4 July 82 LIST OF TASKS FOR EVENT:

TASK / STEP TASK S8JECTIVE DESCRIFTION PERF0RetED RIONITORED PANEL LIST EQUIPheENT REQUIRED TO REFERENCE BY SY NOL COAAPLETE TASK Nut 0SER (LIST IN SEQUENCE)

ERG SEQ LRO '

STEP N O. N_O.

7.8 Check if LIISI Pumps El-16 1 SRO should be stopped

1. Let RCS pressure stabilize at about 1000 psig. Shutoff head for LilSI pump is 288 psig; therefore 81 ID PI-861,862,863
2. Reset SI 82 ID
3. Stop LII Pumps and place in 83 ID standby.

7.9 Compare RCS and SG pressure. El-17 If RCS SG, reduce SG pres- Assume result i syes RX=I'l-455, 56, 57, 58 sure to 1285 - 200 = 1085 psig 84,85 1.2 48,6B

1. Place Steam dump control 86 2 SRO 7C SG = PI-514,15,16 in manual SG = PI-524, 25, 26
2. Set PI Controller 87 SG = PI-534, 35, 36 to 1085 psig SG = PI-544, 4 5, 4 6
3. Observe Steam lleader 88 PK-557 Pressure to verify action PI-557 Implement ES-12 Post LOCA El-19 Cooldown 8 Check for switchover to Cold El-20 Leg Recirculation.
1. Check RWST Level 89 ID 90 1 SRO ID LI-931, 932, 933 91 1D Assume level is approximate (?;, and transfer to ri circulation is r ecessary.

Plant Status Check i

3089W/0091 W

' Revised 7/12/83 R. C. Potter l

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EVALUATOR G. J. Malek HOUSTON CONTROL ROOM DESIGN REVIEW LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE m & DATE SMALL BREAK LOCA PAGE 17 0F 98 IV ERG E-O July 82 LIST OF TASKS FOR EVENT: REF TASK /5TEP TASK OBJECTIVE DESCRIFileu PERFORGIED 400NITORED PANEL LIST EQU1PetENT REQUIRED TO REFERENCE BY SY NOS. COttPLETE TASK NuteSER (LIST IN SEGUENCE)

ERG SEQ LRO '

STEP N O. N O.

8 Enter ES-1.3 Transfer to Cold lxg Recirculation.

Reset SI Already accomplished l

Note: STP incorporates a feature involving automa .ie line-up of valves for transfe to recirculation from the containment sump. The fc!!owing ste as are required for verification only.

8.2 Verify CCW Flow to 104 1 2D RilR lleat Exchangers 105 1 2D FI-4530, 4547, 4564 106 1 ID 8.3 Determine if charging Omit-Step 31 resulted in Charging Pumps not running, pumps should be stopped 8.4 Open Containment Sump 107 1 ID l Recire. Valve to Full Open 108 ID Valves SI-016A, B, C i

109 ID 8.5 Close valve from RWST I10 1 ID to SI Pumps 111 1D Valves SI-001 A, B, C 112 ID 8.6 Check illlSi Pump 113 I ID Mini-flow valves are 114 1 ID Valvees SI-0011 A, B, C closed 115 1 ID I

i Note: ES-1.3 is complete Reset S1 Omit. These St 3ps are already done. l Reset Phase A isolation

)

E 3089W/0091 W Revised 7/12/83 R. C. Potter

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KM M W W M M W W W M M G. J. Malek CONTROL ROOM DESIGN REVIEW EVALUATOR HOUSTON LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE w.. & DATE ER CO.

SMALL BREAK LOCA PAGE 19 0F 21

}{ ERG E-O July 82 REF LIST OF TASKS FOR EVENT:

PERFORRIE0 800NITORED PANEL LIST EOUIPRSENT REQUIRED TO TASK / STEP TASK OBJECTIVE DESCRIPTION REFERENCE BY SY NOL C0terLETETASK NtiteSER (LIST IN SEGUENCE)

ERG SEQ LRO '

STEP NO. NO.

9.5 Initiate RCS Cooldown ES I .2-8

1. Slowly open pressurizer spray valve 122 1 SRO 4B PK0655B Caution: The maximum allowable cooldown rate is l00*F/hr.

Note: Assume that loop 4 is the Llowing loop (Ref s ep 9.3.2) j

2. Increase rate of steam 123 2 SRO 7C dumping by reducing the Controller PK-557 Valves:

PV-7488 thru PV-7496 pressure setpoint on (12 valves) steam dump valves.

3. Maintain SG level NR at 124 2 SRO GB Instrument. LevelIndicators:

approx 50% by adjusting LI-517, 527, 537, 54 7, 571, 519 AFW flow control valves.

572,529,573,539,574,549, 518,528,538,548. I IIC 7522,7524,7525,7526.

9.6 Try to restore pressurizer ES I .2-9 124A GD level above 20%.

1. Maintain RCS subcooling 125 1 4B TI0607,0608 greater than 20*F.
2. Reduce pressurizer pressure 126 1 4B PK-655B,C with normal spray.

Assume the above steps lead to pr2ssurizer level rea thing greater than 20%.

Notes:

1. An increase in steam dump rate will increase RCL subcooling.
2. An increase in pressurizer spra r flow will decrease RCS subcooli g.

ausun/ JUUI W E Revised 7/12/83 R. C. Potter

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G. J. Malek NOUSTom CONTROL ROOM DESIGN REVIEW EVALUATOR l OPERATOR TASK IDENTIFICATION AND ANALYS13 SIGNATURE LIGHTING

- -s & DATE

" '" POWER CO. SM ALL BitEAK LOCA PAGE ---[gg r.-v auty uz LIST OF TASKS FOR EVENT: REF TASK SSJECTIVE DESCRIPil0E PERFORetED bt0NITORED PANEL LIST EOUlretENT REQUIRED TO TASK / STEP REFERENCE BY SY NOL C00sPLETE TASK BUISSER (LIST IN SEGUEt!CE)

ERG SEC LRO -

STEP N O. NO.

4. Check S1 Pump discharge 139 1 IB PI-904, 861 pressure.

If greater th

( 1600 psig)g Shutoff pump (Train A).

Note (1) 1600 psig should the shutoff head at n ini-flow.

5. Check RCS Pressure 140 1 4D PI-455 If 400 psig, continue 456 steps in this sequence, I thro 4 45 7 until RCS pressure drops belo w 45 3 400 psig. If Train A SI becornes fully isolated, then begin throttling in Train D.

10.0 When RCS is depressurized to ES t.2-15 400 psig and 350*F, initiate transfer to RIIR

10. De-isolate RilR, Example for Train A:
1. Open Valves: 141 ID

. 142 ID XRil-060 143 ID XRil-061

2. Open Valve: 144 ID XRil-066 IICV-864 END The plant is now in a long term cold shutdown mod 3.

ausun/uust w Revised 7/12/83 R. C. Pottef a

HOUSTON CONTROL ROOM LIGHTING a DESIGN REVIEW

- - - POWER CO.

APPENDIX A.2 j OPERATOR TASK IDENTIFICATION AND ANALYSIS l STEANI LINE BREAK l

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G. J. Malek CONTROL ROOM DESIGN REVIEW EVALUATOR HOUSTON LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSl5 SIGNATURE m_& DATE E'E POWER CO*

STEAMLIN E BREAK -INSIDE CONTAINMENT

'^ 2 E-2 July 1982 REF

-W El LIST OF TASKS FOR EVENT:

PERFORIBED is0NITORED PANEL LIST EQUlft4ENT REQUIRED TO TASK / STEP TASK SSJECTIVE DESCRIFT10N REFERENCE C0tePLETE TASK BY BY NOS.

MuteSER (LIST IN SEQUENCE)

ERG SEQ REF. NO.

7.3.1 Check RCS Pressure 4 1 SRO 4B PI-455, 6, 7, & 8 Compare to Shutoff IIead, 288 psig.

For this event, the expected P. ant response is a decrease in RCS pressure due t ) over co > ling, followed by a recovery of RCS pressure via autoo .atic pressure control.

7.3.2 Reset SI E-2 3 5 1 SRO 19 6 ID 7 19 7.3.3 Stop LilSI Pump and place 8 1 SRO ID in standby 9 ID

- 10 g9 7.4 Check if RC Pumps E-2 should be stopped 4 7.4.1 Check lillSI Pumps 11 1 SRO ID running - Pump Breaker 12 ID Lights - LIT 13 ID 7.4.2 Check RCS Pressure 14 1 SRO 4B PI-455, 6, 7, & 8-If greater ( ) RC Pump should be kept running. Assumt result is that RC aumps continuc to run.

7.5 Identify faultec SG E-2 5

E 2984W/0086W Revised 7/12/83 R. C. Potter W W mW W .. . -

  • * #I*

HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR

~ LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSIS SIGNATURE

-n.... & DATE

    • " 3 14

-- E POWER CO. PAGE STEAMLINE BitEAK -INSIDE CONTAINMENT -W EFG e-2 auiy 1982 LIST OF TASKS FOR EVENT: REF TASK / STEP TASK OBJECTIVE DESCRIFil0N PERFCF1VEC 000NITORED PANEL LIST ENIPMENT REGUIRED TO REFERENCE sy my NGL COMPLETE TASK MUMSER ILIST IN SEQUENCE) l ERG SEO e l It E F. NO 7.5.1 Read SG Pressures -

The faulted SG should 15 2 6B PI-514, 24, 34, & 44 indicate a pressure significantly lower 7.6 Isolate faulted SG E-2 6

7.6.1 Main steam is already isolated 7.6.2 Isolate AFW to faulted SG 16 2 6D Example: SG A M OV-0048 Note: After the faulted SG hos dried out, RCS rressure would i egin to recove .

8.0 llecovery of RCS to stable conditions 8.1 Check Non-Faulted SG E-2 Levels 7 8.1.1 Head Level Indicator 17 2 6B SG A LI-519 SG B LI-529 SG C LI-539 SG D LI-549 8.1.2 Adjust Throttle valves to j maintain SG level at 18 2 6D Valves SG A FV-7525 '

approx. 50% NR 19 2 6D SG B FV-7524 20 2 GD SG C FV-7522 SG D FV-7526 E

2934W/0086W Hevised 7/12/83 11. C. Potter

G. J. Malek CONTROL ROOM DESIGN REVIE") EVALUATOR HOUST0J OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE LIGHTING h.,.

- & DATE ER CO. STEAMLIN E BitEAK - INSIDE CONTAINMENT PAGE fg gggFg _; ,;,;y ;,!,i j REF LIST OF TASKS FOR EVENT:

PERFOR40E0 is0NITOREO PANEL LIST EOulPetENT REOUIRED TO TASK /5TEP TASK OBJECTIVE DESCAril0N REFERENCE NOL C0tsPLETE TASK SY SY NutesER (LIST IN SEQUENCEI EltG SEQ .  ;

it E F. N O.

8.2 Check Condensate Storage Tani: E-2 }

Level 8 {

! 8.2.1 Read LevelIndicator 21 1 See Computer Should be greater than ( ) % 22 -

See Computer 8.3 Check Containment E-2 ,

l Spray 9 i

8.3.1 Verify Pumps Running 23 1 2D 24 2D 25 2D 8.3.2 Check Containment Pressure 26 1 2B PI-934, 35, 36, 37 Maintain Containment Spray 27 2B until containment pressure is reduced to normal (specific value?)

Note: Assuming the faulted SG is successfully isolated, containm 2nt pressure would soon eturn to normal, i.e. O pisg.

8.3.3 lleset Containment Spray E-2

- 9 28 1 2D 29 1 2D 30 1 2D E

2984W/0086W Revised 7/12/83 11. C. Potter

. N_- M M M N MNA

G. J. falek HOUSTON CONTROL ROOM DESIGN REVIEC EVALUATOR LIGitTING OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE

. .. & DATE

?_#049 POWER C0~

LIST OF TASKS FOR EVENT:

STEAhlLINE IIREAK -INSIDE CONTAINMENT PAGE REF

-5g Y I4 l

TASM/ STEP TASK OSJECTIVE DESCRIFil0N PERF0RetED tt0NITORED PANEL LIST EQUIPMENT REQUIRED TO NutesER R FERENCE SY SY NOS. COMPLETE TASK (LIST IN SEQUENCE)

ERG SEQ '

It E F. N O.

8.3.4 Stop CS Pumps and place 31 1 27 in standby 32 27 33 27 8.4.1 Check 11WST Level E-2 10 34 I ID LI-931 if less than ( )%, Traasfer 35 ID to fleeirculation.

Assume no action required at 36 ID this time. No Instrurnent Hequired 8.5.1 Check itCS Cold Leg E-2 Temperature 1I 37 2 SB TI-451 A, B, etc.

If less than 350*F, ti.en skip to step ( ).

Assume temp is 350aF.

8.6.1 Check RCS Pressure greater E-2 than shutoff head for lillSI 12 38 1 4tl pumps (1600 psig) PI-4 55, 56, 57, 58 For expected plant response, r asult is true.

8.7.1 lteset SI E-2 13 39 I ID 40 ID 41 ID 8.8.1 Ileset Containment isolation E-2 Phase A 14 42 1 2C 43 2C 44 2C

' E 2084W/0086W Hevised 7/12/83 It C. Potter

G. J. Alalek CONTROL ROOM DESIGN REVIEW EVALUATOR H:UST0J LIGHTING OPERATORTASKIOEETIFICATION ATD ANALYSIS SIGNATURE ,

I

    • ~$ & DATE l

?.*.0J'.i! POWER CO* ^

STEAMLINE BILEAK -INSIDE CONTAINMENT -V EHG E-2 July 1982 REF LIST OF TASKS FOR EVENT:

PERFORMED

' HONITORED PANEL List EQUIPMENT REGulRED TO J

TAsutsTEP TASK 05MCTIVE DESCRrileu REFERENCE COMPLETE TASK BY BY NOS.

NUMSER tLIST IN SEQUE NCE) f I

EltG SEQ IL E F. N O.

f 8.9 ltestablish Instrument Air E-2

! to Containment 45 1 2C

! Open Valve FV-8565 8.10 Check Power available to E-2 Charging Pumps 16 j 8.10.1 Offsite Power -Available 46 2 10B 8.11 Start one Charging Pump E-2 (To establish seal 17,18 47 1 4D injection flow) 10 8.11.1 Start additional charging pump if necessary to meet 48 1 4D i

Si termination criteria i 8.12 Check Containment E-2 l Conditions 20 8.12.1 Containment Pressure 49 1 2B l PI-934, 35, 36, 37 Containment Temperature 50 1 2 11 TI-9681 l

l Check if Si can be 8.13 E-2 terminated: 21 8.13.1 Check itCS Pressure 51 1 411 PI-4 55, 56, 57, 58 Greater than (?) psig, Stable or increasing E

2084W/0086W llevised 7/12/83 11. C. Potter O M _ _ M__ M __

M M U

- G. J. Malek HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYS15 SIGNATURE

-.& DATE I4

~

STEAMLINE BitEAK -lNSIDE CONTAINMENT PAGE -[ J g,7 ,gg LIST OF TASKS FOR EVENT: REF TASM/5TEP TASK 68JECTIVE DESCRAFT10W PERFORMED MONITORED PANEL LIST EQUIPMENT REQUIRED TO MUMsEn REFERENCE BY sy NOS. COMPLETE TASK lil5T IN SEQUENCE)

ERG SEQ .

It E F. NO.

8.13.2 Check Pressurizer Level 52 1 4B L1-465, 66, 67 Greater than 20%

8.13.3 Check RCS Subcooling 53 2 SB No instrument available Greater than (?) *F 8.13.4 Check AFW Flow to 54 2 6D Non-faulted SG. 55 2 6D F1-7525, 24, 23, 2 6 Greater than 500 gpm 56 2 GD 8.13.5 Check SG level in 57 2 6D LI-518, 27, 38, 4 7 Non-faulted SG. 58 2 GD FV-7519, 20, 21, 22 Nominal control point = 50%

I E

2984W/0086W llevised 7/12/33 It. C. Potter l

  • 8' CONTROL ROOM DESIGN REVIE") EVALUATOR f HOUSTON '

LIGHTING OPERATORTASKIDENTIFICATIO^J AND ANALYSIS SIGNATURE

~$ & DATE 8 4 ERCO. STEAMLINE BitEAK -INSIDE CONTAINMENT PAGE REF dE-2 % 1982 LIST OF TASKS FOR EVENT:

PERFORABED RBONITORED FANEL LIST EQUIPteE4T REQUIRED TO TASu/5TEP TASK SEJECTIVE DESCRIFil0N REFERENCE BY BY N05. CotePLETE TASK ButISER (LIST IN SEQUENCE)

ERG SEQ -

1 REF. N O. l 9.0 Si Termination following less of Secondary Coolant L

9.1 lleset SI ES-2.1 Omit. Already accomplished in Step 8.7.

i 9.2 Stop Safety Injection ES-2.1 2

9.2.1 Stop all lillSI Pumps. 59 1 1D LIISI Pumps were previously 60 1 ID l stopped in Step 7.3. Verify 61 1 ID 9.3 Reset Containment ES-2.1 62 1 2C isolation Phase A 3 63 1 2C Already accomplished in 64 1 2C Step 8.8. Verify 9.4 lleestablish Instrument ES-2.1 Air to Containment 4 65 1 2D Valve FV-8565

. This step was completed at step 8.9. Verification only.

9.5 Align IIIISI Pump Suction from B AT to itWST Note: For STP, t.ie normal aligament is to the R0 ST, therefore, this step is om tied.

E 2984W/0086W Revised 7/12/83 R. C. Potter M ___ M _ M ______ M _ ___ M M M

~WW W W W WM WW W~M M W W mW W W W CONTROL ROOM DESIGN REVIEW EVALUATOR G. J. Klatek HOUST03 LIGHTING OPERATOR TASKIDENTIFICATION AND ANALYSIS SIGNATURE

    • * & DATE

. ?_*.9!"'.EPOWER C0' STEAhlLIN E BitEAK - INSIDE CONTAINhlENT IV EltG E-2 July 1982 LIST OF TASKS FOR EVENT: REF TASK /5TEP TASK SSMCTIVE DESCRIFT805 PEAFORAIED 400NITDAED PANEL LIST EQUIP 41ENT AEQUIRED TO REFERENCE sy IeutesER ILIST IN SEGUENCE) av N05. CaterLETE TA5K l

EHG SEQ , '

HEF. N O.

9.6 Verify SI Heinitiation ES-2.1 not required 6 9.6.1 Check HCS Subcooling: 66 2 .

Greater than (?) *F 5 11 No instrument available U.6.2 Check Pressurizer Level: 67 2 4B Greater than 20% LI-465, 66, 67 The expected plant response is hat both of the co iditions will be true.

9.7 Control HCS Ileat Hemoval ES-2,1 7

9.7.1 Place steam dump control 68 2 7D in Pressure Klode OS-0555Z Dump 9.7.2 Heduce steam dump pressure 69 2 setpoint to increase rate 7C PK-557 of heat removal from HCS 9.7.3 Observe steam header to verify action 70 2 7C PI-557  :

9.8 Verify Offsite Power ES-2.1 available 8 71 2 l

1011 E

/ 2084W/0086w Hevised 7/12/83 H. C. Potter

. . Malek CONTROL ROOM DESIGN REVIEW EVALUATOR H0usTON LIG TING OPERATOR TASK C'ECTIFICATION A D ANALY$l$ SIGNATURE g

-.m. & DATE T'E POWER CO. '^0 10 l4 STEAMLINE 131 TEAK -INSIDE CONTAINMENT -W El E-2 July I982 REF LE2T OF TASKS FOR EVENT:

TASK esJECTIVE DESCAlriles PERFORMED 800NITORES PANEL LIST EQUIPMENT AEGutRFD TO TASK /5TEP REFERENCE BY SY N05. C04ePLETE TASK NutesEA ILIST IN SEGUENCEI EltG SEQ .

It E F. N O.

9.9 Check Charging Pump Status: ES-2.1 9

j 1

9.9.1 Verify at least one 72 1 4D  !

Charging Pump-flunning  !

l 9.9.2 Verify valve FCV-205 73 1 4D F K-205 l OPEN 1 9.10 Check VCT Makeup Control ES-2.1 j

System II I i 9.10.1 Check VCT Level-NOltMAL 74 1 4D LI-l 12 9.10.2 Set makeup for Automatic 75 1 4D F K-l l i

, Control 1

9.10.3 Set Makeup for proper 76 1 4D FCV-110 Boron concentration FK-110 9.11 Establish Letdown ES-2.1 12 9.11.1 Verify CCW flow to Letdown 77 1 2 11 Panel IM23 or TK-130 lleat Exchanger 78 1 2Il or 41 ) Panel 2M22 (Verify CCW l' umps running) 79 1 t il Panel 3M 10 9.11.2 Open Letdown line Containmen . 80 1 4C CV-0240C isolation Valve 81 1 4C CV-0231C E

  • / 2984W/0086W Hevised 7/12/83 It. C. Potter E_E. M E E M M W

N M M M M M M W W W M M W'W W W W W W HOUSTON CONTROL ROOM DESIGN REVIEC EVALUATOR LIGHTING OPERATOR TASKIDENTIFICATION AND ANALYSIS SIGNATURE

... & DATE

0. PAGE II I4 LG]T OF TASKS FOR EVENT:

STEAMLIN E BitEAK -INSIDE CONTAINhlENT REF

-- JF TASK /5TEP TASK SSJECTivE DESCR4PTieu PERFORMED 800NITORED PANEL L88T EQUIPMENT REGUIRED TO REFERENCE N05.

NUMSER lil5T im SEGUENCEI SY BY COMPLETE TASK EllG SFQ -

it E F. NO.

9.11.3 Open Letdown line 82 1 4C LCV-465 isolation valves 83 1 4C LCV-468 9.11.4 Open Letdown orifice 84 1 4C isolation valves as Probably one of the following appropriate valves:

CV-12,13, or 14 9.12 Verify Charging Pump ES-2.1 alignment to VCT: 13 9.12.1 Open valves 85 1 4D XCV-112B, i 13A 86 1 4D 9.13 Cheek itC Pump Cooling ES-2.1 14 9.13.1 Verify CCW flow to 87 1 4C thermal barrier; i.e. CC-339

  • 88 1 4C isolation valves - OPEN CC-374 89 1 4C CC-356 90 1 4C CC-390 9.13.2 Verify itC Pump Seal 91

. Injection flow - NOllM AL 1 4 11 Fit 0156,7,8,9 9.14 Establish itC Pumps Seal ES-2.1 Iteturn Flow 15 l

\

E 2984W/0086W llevised 7/12/83 It. C. Potter

CONTROL ROOM DESIGN REVIEW EVALUATOR HOUSTON OPERATORTASKIDENTIFICATION AND ANALYSl5 SIGNATURE LIGHTING

-. ... & DATE

- O. STEAMLINE BitEAK -INSIDE CONTAINMENT PAGE -ff K,pb E-2 July 1982 REF LIST OF TASKS FOR EVENT:

PfRFORMED MONITORED PANEL LIST EQUIPMENT REQUIRED TO TASN/5TEF - ASK DSJECTIVE DESCRIFil0N REFERENCE COMPLETE TASK SY SY N05.

NUMSER (LIST IN SEQUENCEI ERG SEQ It E F. N O.

9.14.1

  • Verify CCW flow to seal 92 1 2D Train A - Valve CC-316 water heat exchanger; i.e. 93 1 2D Train B - Valve CC-314 Open valve CC-236 l

9.14.2 Open RC Pump seal 94 1 4C CV-077 return isolation valves 95 1 4C CV-079 l 1 4 9.15 Check non-faulted SG ES-2.1 Levels 16 9.15.1 Check SG Level Nlt 97 2 6B, D SG A L1-519 FV-7525 98 SG B LI-529 FV-7524 i

9.15.2 Adjust AFW throttle valve 99 SG C L1-539 FV-7522 to maintain level at 50% 100 SG D LI-548 FV-7526 9.15.3 Repeat for each SG 9.16* Check CST levci, ES-2.1 Greater than % 17 101 1 -

Check Computer 102 1 -

Check Computer 9.17 Establish Pressurizer ES-2.1 Level in Normal Operating 18 Range 9.17.1 Adjust Letdown flow 103 1 4D PI-135 PK-134 1

E 2984W/0086W Revised 7/12/83 R. C. Potter mMM M M M

'M M W W M M W W W W W W W EVALUATOR G. J. Altelek HOUSTON CONTROL ROOM DESIGN REVIE']

LIGHTING OPERATORTASKIDENTIFICATION ANO ANALYSl3 SIGNATURE

-, & DATE


POWER CO. PAGE 13 0F 14 REF W ERG E-2 July 1982 LIST OF TASKS FOR EVENT:

TASK /5TEP TASK BBJECTIVE OESCRIFil0E PERFORt0E0 t00NITOREO PANEL LIST EQUIPedENT REQUIRED TO REFERENCE BY SY NOL C0ldPLETE TASK NueseER (Liff lef SEQUENCEI ERG SEQ '

REF. NO.

9.17.2 Adjust Charging flow 104 4D 1 F1-205 FK-205 9.17.3 When pressurizer level is ' 105 4D 1 Same as above normal, place controls in 106 1 4D AUTO 9.18 Control Pressurizer Pressure ES-2.1 19 9.18.1 Energize pressurizer heaters, 107 1 4D and/or; 9.18.2 Adjust pressurizer spray 108 4B 1

PK-655A, B, C valve Manipulate above controls to maintain pressure at ( ) and RCS sub- 109 2 SB cooling at Greater than 50*F 9.19 Check RC Pump Status ES-2.1 At least one RC Pump 21 110 2 SC RUNNING 9.20 Check Intermediate Range ES-2.1 22 9.20.1 Flux: Should be below ( ) 1II SD 2 NI-35, 36 E

2984W/0086W Revised 7/12/83 R. C. Potter

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HOUSTON CONTROL ROOM UGHTING DESIGN REVIEW

. _ _ ' . . 0WER

. CO.

l APPENDIX A.3 I OPERATOR TASK IDENTIFICATION AND ANALYSIS STEAM GENERATOR TUBE RUPTURE l

1 1

1 1

1 1

1 1

1 I

I I

I I

I i

1 l auswloiosw

C E E E E E E E E" -' E M K'W HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR W.11. Arnold LIGHTING OPERATOR TASK IDENTIFICATION ANO ANALYSIS SIGNATURE m, & lief: E-3, Hnergency Instructions, LP-Ilasic, July 5,1982 DATE

  • POWER CO. t i*

'^0 0' S'ITAI GENIR"s'IQt 'IUIE IIUI'IUtE LIST OF TASKS FOR EVENT: REF TASM/8TEP TASK SSJECTIVE BE5CAIFTieu PERFOA48E8 RIONITSAES FANEL LIST EQUIPteENT REGulRED TO REFERE ME SY SY NOS. C04tPLETE TASK ButASEA ILIST IN SE8UENCE) 1.1 Oneck Aux. Feedwater Flow is 1,2,3,4 '

6D AC-F1-7525 liccaced or Stopped AF-FI-7524 AF-F1-7523 UD 2 AF-F1-7526 1.2 Oieck Stm. Gen. 14vels in Narrow Range 5,6,7,8 6B HV-LI-519 UD 2 6B HV-LI-529 68 HV-LI-539 UD 2 6 11 HV-LI-549 1.3 Oneck Iligh Rr.diation on 9 B1 omjown Cmnunicato with ch anistry, plus open blowdown 1i aes.

a) b)

c) d)

1.4 Oieck liigh Itadiation on 10 Stm. Gen. Sesiples Comunicate with ch fili s t ry a) b)

c) d)

1.5 Dieck liigh Itadiation on hhin Steum Comunicate with choni s t ry a) I b)

! c)

I d) l l 3127W/0091W E llevised 7/13/83 It. C. Pot ter

W.11. Arnold CONTROL ROOM DESIGN REVIEW EVALUATOR HOUSTON OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE LIGHTING m,,,,, &

lie f: E-3, lhergency Instructions, LP-Hasic, July 5,1982 DATE 2 0F 14

"~ PAGE STEMI GIMRYlGI 'lVBE IlUI'IUIE REF LIST OF TASKS FOR EVENT:

RIONITORED PAIIEL LIST EQUIPteENT REQUIRED TO TASK SSMCTIVE DESCRFtl0E PERFORIAES TAS40 STEP REFERENCE BY NOS. C04sPLETE TASK SY IIUGASER (LIST 181 SEOUENCEI Ibsitively identify the s faulted Stetun Generator

( Asstane SG201A Faulted) 2.1 Stop all Feedwater Flow to 11 UO 2 GC Stm. Gen. 201A. Close Valve FW-FV-7141 2.2 Isolate Stm. Gen. 201A by IIO 2 closing the KEIV & Bypass Valves 12 GC MS-FSV-7414 13 6C hE-FV-7412 2.3 Adjust IOllV Gontroller 14 UO 2 6C hE-lK-7411 on Stm. Gen. 201A 2.4 01eck that IOllVs are closed 15 UO 2 6C hE-PV-7411 or closed after press deer.

2.5 NA to STP 2.6 Oteck that'Stm. Gen. 201A 17 UO 2 GD SB-FV-4153 Blowdown is isolated 3.1 Verify Power available to UO 1 Indicator Lights on Pressurizer Block Valves:

a) NIC-001A 18 4C NtC-001A b) M C-001B 19 4C N C-00lft E

3127W/0091W llevised 7/13/83 II. C. Potter m m m W M E

IV.11. .Arn Id NOUSTON CONTROL ROOM DESIGN REVIEC EVALUATOR LIGHT 3Ng OPERATOR TASK IDENTIFICATION AND ANALYSi$ SIGNATURE Ref: E-3, Bnergency Instructions, LP-Basic, July 5,1982 0 ATE R CO. PAGE 3 0F I4 SM1 GmDIA'IUt 'IUBE ItUFIUIE LIST OF TASKS FOR EVENT:

TASK /5TEP TASK SSMCTIVE BESCRIPflG5 PERF0Aa4ED SIONITORED PANEL LIET EGuiresENT REGulRED TO REFERENCE SY sy NOS. C04APLETE TASK NNAISER (LIST IN SEGUENCE) 3.2 Geek Pressurizer IOtYs 20 CIOSID UO I -

21 4C IC-ICV-655A 4C IO-ICV-656A 3.3 Geck Pressurizer Block 110 1 i Va 1ves-OPEN 22 ICP Trip Criteria 4C NO-001A 23 4C N C-001B 4.1 Head liigh Ilead SI Flow or 24,26,28 UO 1 IC SI-FI-917, 918, 919 4.2 Ptsm running 25,27,29 UO 1 ID Punp Running Li tes-LIT 4.3 Read 30 UO 1 IKS Pressure less Than 1300 4B llc-PI-457, 458 If 4.1, 4.2, and 4.3 are met, then 4.4 Trip IC Ptsm lA 31 UO 2 SC 4.5 Trip 10 Ptsm IB 32 UO 2 SC 4.6 Trip IC lism IC 33 UO 2 SC 4.7 Trip 10 Ptsm ID 34 UO 2 SC 5.1 Reset SI 35,36,37 UO 1 ID Train A, B, C 6.1 Reset Contairment Isolation 38,39,40 UtO 1 2C Phase A Train A, B, C

{

l 3i 2 Lu uuom Revised 7/13/83 R. C. Potter

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\v' It* ^'" Id CONTROL ROOM DESIGN REVIE1 EVALUATOR HOUSTON SIGNATURE LIGHTING ite f: ,pFERATOR TASK IDENTIFICATION AND ANALYSl3 3 Energency Instructions, LP-11asie, July 5,1982 DATE

_ g 6 0F 34

'NU POWER CO. FilW1 GEN 13tNIOt 'lu1E ItUlrlutE PAGE REF LIST OF TASKS FOR EVENT:

PEAf0AttED tt0NITDAES PANEL LIST EQUlftBENT REQUIRED TO TASK 15TEP TASK SSMCTIVE SEstairfl0g C0tePLETE TASK REFERENCE BY SY 505.

NutetER (LIST 15 SESUENCEI 13.2 Establish Mux. Giarging Flow 84,85 IJO I 41) -FK-205, F1-20SA f 14.1 Oieck IKE Pressure-200 PSI 86 110 1 48 IC-PI-457 Greater tiian ruptured IC-PI-458 Stm. Gen.

15.1 N/A to STP 87 thru 89 not used 15.2 N/A To STP IC-IK-6558 & C 15.3 Gieck IKE Pressure Ibereasing 90 IJO 1 4B IC-PI-457, 458 l 16.1 Oicek IKE Pressure Equal to 90 IJ O 1 4B l'7-PI-457, 458 l Faulted Stm. Gen. Pressure or l

16.2 Ilead Pressurizer level Greater 91 110 1 4B IC-LI-675, 46ti than .

16.3 Stop lbpressurization by 92,93 IJO 1 4 11 IC-IK-6550 & C Closing Spray Valves 16.4 leek Pressurizer level 94 IJO I 4H 10-1,1-675, 466 Ircater 'lhan 16.5 6'eri fy IRS Pressure Increasing 95 IJO'l 4H IC-PI-457, 458 l Tasks 17 & 18 lbleted) 19.1 ,erify is3 Pressure Incr. by 95 110 1 4H IC-PI-457, 458

!00 PSI E

L12%V/0091W Itevised 7/13/83 R. C. Ibt ter i l. I l_ _

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W. R. Arnold CONTROL ROOM DESIGN REVIE*7 EVALUATOR NOUSTON RATORTASKIDENTIFICATION AND ANALYSl3 SIGNATURE LIGHTING Ref: f-3, Bnergency Instructions, LP-Basic, July 5,1982

_g DATE I4

- -- MER CO. S1EMI GENERYI0ft 'llEE ItUI'IUIE PAGE OF REF LIST OF TASKS FOR EVENT:

PERFORetED bt0NITORED TANEL LIST EQUIPetEllT REQUIRED TO TASIU5TEP TASK SSJECTIVE DESCRIFHON REFERENCE C0tAPLETE TASK SY SY NOL BeteBER (LIST le SESUENCE) 27.2 h keup Controller Set to 114 110 1 4D FK-Oll! -

Autonatic 27.3 2keup Set for " Greater than 114 110 1 4D FK-0110 l 10 Boron Gone" - 01eck Oionistry for Amount.

28.1 Veri fy Oxrponent Cooling Water 115 IRO 1 4D OC 'lK-130 for Flow to letdown lleat Exch. TV-4494 28.2 Open letdown Line Contain- 116,117 110 1 4C CV-0240C, CV-0231C ment Isolation Valves 28.3 Open letdown Line Isolation 118,119 IJ O 1 4C ICV-465, ILV-468 Valves l 28.4 Open Letdown Orifice Isolation 120 IJO 1 4C CV-012 Valve as Appropriate 29.1 Verify Qiarging Punp Suction Aligned to Volune Control Tank a) Open Valves 121,122 110 1 4D MN-l l28, l l 3A I 30.1 Dieck ICP Onponent Cooling 123 IJO 1 4C OC-356 Water Syston F1ow-M)l5%L 30.2 Oieck ICP Seal Inj. Flow 124 110 1 4B F11-156, 157, 158, 159 Do not continue until 30.1 or 30.2 are met.

31.1 Check (DV Flow to Seal Water AO local O'-F1-4614 Local lleat Exch.

E

, 312'M/ 0091W llevised 7/13/83 R. C. Potter R .1 L ___

E E E . U_

T"M M M M M M M E E E E E E E E~E E E CONTROL ROOM DESIGN REVIEW EVALUATOR

  1. ' II* ^#" Id l NOUSTON LIGHTigg SPERATORTASKIDENTIFICATiON AND ANALYSIS SIGNATURE

,,,. A f: E-3, Ihergency instructions, LP-Ilasic, July 5, 1982 DATE

" POWERCO. bWI GINIRYlGR 'lulE ItUl'IutE PAGE 9 0F Id LIST OF TASKS FOR EVENT: REF Tass /sTEF TASIC SSJECTIVE DESCAriles PERF8AatES 4008ITSAES FABEL LIST EQUIPteENT AEGUIRED TO REFEAEBCE ay ay meL C0tAPLETE TASat IHiteBER ILIET LEI SESUENCEI 31.2 Open ICP Seal iteturn Line 125, 126 IJO I IC OC-403, 404

  • lsolation Valves I

l 32.1 Mjust Garging & Seal Inject- 127,128 IJO I 4D T-FK-205, l

lon Faual to letdown & Seal IK-135 Leakoff F1ows 33.1 See Plant Specific List to Recheck AEl V lllowdown & \S IV lly[ ass.

hiinimize Secondary Syst.

Con tanina t ion 3 4. !

  • Itead GT Imvel 129,130 11 0 2 -

See caiputer 35.1 Ihergize Pressurizer lleaters 131 IJ O I 4D 5 lleaters 36.1 Read Pressurizer Water Taip. 132 A 110 1 4 11 IC-TI-608, TI-411 hhi t ti1 Taip. 36.1 & Taip. I33 11 110 2 Sil of Faulted Stm. Gen. are Faual.

37.1 Itcad Pressurizer Level 133 IJO I 411 10-L1-675, 466 37.2 If greater than 90%, draw 11 0 1 a bubble

$instrun nt deleted due to design change 3127W/0091W Itevised 7/13/83 11. C. Ibt ter E

EVALUATOR W. 112 Arnold NOUSTON CONTROL COOM DESIGN REVIEJ OPERATORTASKIDENTIFICATION ANO ANALYSl5 SIGNATURE LIGHTING m,, & Ref: E-3, ilnergency Instructions, LP-Basic, July 5, 1982 0 ATE

" POWER CO' ^

  • STFAI GWERNIOt 'IUBE RUPIUtE REF LIST OFTASKS FOR EVENT:

PERFORGAED 000NITORED PANEL LIST E8UlretENT REQUIRED TO TASK / STEP TASK SEXCTIVE DESCRIFtleu REFERENCE N0L C0esPLETE TASK SY SY BuessER (LIST BE SEGutsCE) 37.3 If less than 30%; increase 134 110 1 4D GC-IE-205 charging-flow & spray j pressurizer to maintain j R G pressure constant j 38.1 Dieck at least one ICP 135 IJO 2 SC running - Start one if none running 38.2 Stop all but one TCP 110 2 39.1 Read Flux below 136 IJO 2 SC,D 39.2 Verify source range detectors 137 110 2 SC,D re-energized -

39.3 Transfer nuclear racorders 138 IJO 2 SD Plasim display to source range scale 40.1 Shutdown unnecessary plant 110 1, 2 j equignent 41.1 Go to ES-3. l A, SGHL al ternate Staff cooldowns by backfil1ing IOS or 41.2 Go to ES-3.lu SUnt alternate If do not I ave stean dm ps.

cooldown using Stm. Gen.

B1owdown or E

3121W/0091W Revised 7/13/83 11. C. Potter e _f l_ _m e M M.. h . 6 WM

CONTROL ROOM DESIGN REVIE~7 EVALUATOR W. R. -Arnold NOUSTON LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYS15 SIGNATURE

-, & Ile f: E-3, Huergency Instructions, LP-Basic, July 5, 1982 0 ATE U POWER CO. ,,

'^

STFlat GINHIATQt 'IUBE ItUI'lulE LIST OF TASKS FOR EVENT: REF TASIVETEF TASK SSJECTIVE BESCAril0E FEAFenaeEs ABONITORED PANEL LIST EOUIPteENT REQUIRES TO REFEREME SY sy NOS. C00sPLETE TASK MURASER ILIST BN SEGUENCE) 41.3 Go to 5-3.lC SGut alternate ' '

cooldown by steamir.g ruptured ' ~

Stm. Gen (s).

42.1 Repeat 36.1 139A DO1 4B ~ Tasks 42 Repeat tasks 139B UO 2 SD f-' perfomed at end of E-3

,/

43.1 Hepeat 37.1 140 UO I UO I 4B 44.1 Adjust 'Ibtal charging & seal 141 \ . DO 1 4D T-lE-20 5 injection flows to equal to - < '

l-CC-lK-135 letdown & seal. leakoff flows , , -

45.1 Sanple ruptured stm. gen. -

UO 2 Ocumunicate with Chanistry ,

45.2 SaTple HG -

UO 2

  • Cmmunicate wi th Oranistry 45.3 Horate as r.ecessary - check .- UO 2 wi th chanistry .

~'

'h , d f a jf r

4 G.1 Maintain coolda@ rate-less 144 UO 2 Sl1 'IU ,

than 50*F/lii ,

y 46.2 Durip steam fran non-ruptured 145 UO 2 IK-557, UI-555 7C steam generators to condenser

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  • E 312'M/ 0091W Hevised 7/13/83 H. C. Potttr

h' H. Arnold CONTROL ROOM DESIGN REVIE-^) EVALUATOR NOUSTON OPERATORTASKIDENTIFICATION AND ANALYS15 SIGNATURE LIGHTING

,,,, a itef: E-3, Ene gency Instructions, LP-Basic, July 5,1982 DATE 12 0F 14 R CO. 3,IEMI GINHINIQt TulE ItUI'IUIE PAGE REF i LIST OF TASKS FOR EVENT:

1 B00NITORED PANEL LIST EQUIPteENT RECUIRED TO l TASK SSJECTIVE DESCRWTION PERFORGAEB l TASIU5TEP REFERENCE SY NO S. CotePLETE TASK BY l useseER (LesT su SEGUENCE) 47.1 Start pressurizer spray 146 lj o I 4B H{ 0655C, Hi 06538 47.2 Control Pressurizer lleaters 147 11 0 1 4D as necessary to naintain sub-cooling 47.3 Check pressi:rizer level- 148 1110 1 4B IO-LI-675, 466 l greater than 25% and less than 70%

48.1 Verify stm. gen. level- 149 110 2 6B LI-571, 572, 573, 574 grreater than 25%

49.1 Verify llG pressure less than 150 11 0 1 4B llc-PI-457, 458 or equal to about 700 psig.

49.2 Close al1 SI acetnulator 151, 152, 153 11 0 1 IC SI-039A, -039B, -039C isolation valves .

50.1 Adjust charging & Seal Inject- 154 110 1 4D CC-R{-205 ion equal to letdown & seal leakage flows 51.1 Head IES Tenp. 350*F 155 IJ O 2 SB 'IC 51.2 Ilead H G press 400 psig 156 110 1 4B ItC-PI-457 52.I N/A to STP 3127W/0091W llevised 7/13/83 11. C. Potter R f I f } R f~ l l I __ E . E E E

M WhNW E H M' W W M M M m.

CONTROL ROOM DESIGN REVIE"J EVALUATOR W. R. Arnold HOUSTom LIGHTlifG OPERATORTASKIDENTIFICATION AND AN41Y515 SIGNATURE l

,& Hef: E-3, Energency instructions, LP-Basic, July 5, 1982 0 ATE E "* PAGE M 0F '3 SM1 GENHlA~IOil 'lulE RUI' lute LIST OF TASKS FOR EVENT: REF TASK /8TEP TASK SSJECTIVE DESCRIPTIOu PEAFORGIES SIONITORES PANEL LIST EQUIPteENT REGulAEB TO REFERENCE sy SY NOL COGAPLETE TASK l 5000SER ILIST 15 SEQUENCE) 53.1 Sample ruptured stm. gen. -

UtQ l

  • 53.2 Sarrpie HES -

UO 1 53.3 Borate as necessary -

IRO 1 f

54.1 Ahintain cooldown rate at 157 UO 2 58 'IR-612 less than 50'F/hr 54.2 Verify at least one ICP 158 IRO 2 SC running 55.1 Repeat 47.1 159 UO 1 411 55.2 Hepeat 47.2 160 UO 1 4D 55.3 Itepeat 47.3 161 UO 1 4B 56.1 Hepeat 48.1 162 UU 2 GB 57.1 Adjust charging & Seal inject- 163 UO 1 411,D ion equal to letdown & seal leakage flows 58.1 Head if No. I seal diff. 164 UtO 1 4C PI-152, 153, 154, 155 press less than psig or 58.2 No. I seal leakage flow less 164A DO 1 4 11 than _

gpn aum/ 0091W E Revised 7/13/83 R. C. Potter

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HOUSTON CONTROL ROOM LIGHTING gggggy ggyjgy

. _ _ _ . . POWER CO.

APPENDIX A.4 ,

l OPERATOR TASK IDENTIFICATION AND ANALYSIS E

l LOSS OF OFFSITE POWER I

l 1

I I

l 1

5 E

Il l

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W. R. Amold l CONTROL ROOA4 DESIGN C:EVIE~3 EVALUATOR NOUSTSH OPERATOR TASK BOENTIFICATION AND ANALYSl3 SIGNATURE LIGHTING

& DATE

~n A MER CO. PAGE 3

0F LOSS OF OFFSITE POWER RG ECA-2 dtd 5 July 1982 REF LIST OFTASKS FOR EVENT:

PERFemalEs RISSATSAES PANEL LIST E8Dlrestaf AEtelAES TS

~TAsafsTEP TASK SsJECTlWE BE8CRIPTieu REFERENCE NOL C0taPLETE TASK SY 8Y InutesEA tLIST IN SESUEI6CEl l

1 Verify ReactorTrip(See LOCA) 1 2 Verify Turbine Trip (SEE LOCA) 2 3.1 Start Diesel & Load 3,4,5,6,7 LRO I 3C,D Trip reset, control, ready light (Choose DG 13 as available) syncroscope, output breaker

3. 2 Verify Automatic loading 8 (Plant Specific) If not loaded, load to any power supply 3B Check 3 D/O MW, amps, volts 3.3 If power is restored, go to 19. .If not, then:

(Assume no_t restored) 3.4 Before restoring AC power -

Pull-to-lock the following:

A. Charging Pumps I A, IB 10 LRO 1 4D B. IIllSI Pumps l A, IB, IC 11 LRO1 IC C. LIISI Pumps I A, IB, IC 12 LRO 1 IC D. Containment Spray 2D Pumps I A,18, IC 13 LRO I E. CCW Pumps I A, IB, IC 14 LRO 1 2D F. AFW Pumps 12,11,13 16 LRO 2 GD G. Containment Fan Coolers 15 LRO 1 2D 11 A,3,C, and 12 A,B,C Revised 7/13/83 R. C. Potter 3135W/0091W

  1. R ^*""Id EVALUATOR CONTROL ROOM DESIGN REVIEW HOUSTON SIGNATURE Ll4NTigg OPERATORTASK CENTIFICATION AND ANALYSIS DATE

..& PAGE 2 0F -- A

-- ERCO. LOSS OF OFFSITE POWER ERG ECA-2 dtd 5 July _1982 I REF l

LIST OF TASKS FOR EVENT: FANEL LIST ESUdPRIENT REeulAES T8 i PERFeassEs lessTSRES C04APLETE TASK TASKJ5TEF TASK 86JECTivt SEscatFress DEFERENCE SY BV NOL

    1. teSER (LIST 101 SESUEleCEI 4.1 Verify pressurizer PORVs- 17 LRO 1 4C PCV-655A, 656 A closed l

4.2 Verify Letdown isolation Valves-closed 18,19 LRO 1 4C XCV-023, 024 4.3 Verify Excess Letdown Iso. i Valves 20,21 LRO 1 4D CV-082, 083 l 5.1 Close RCP Seal Return OC iso. Valve 22 AO Local ,

5.2 Close RCP SealInjection 23 LRO 2 or Local l OC Iso. Valve AO I 5.3 Close RCP Thermal llarrier 24 LRO 2 or Local l CCW Return OC Iso. Valve AO 6.1 Check for AFW Flow LRO2 6B F1-7526, 7525, 7524, 7523 25 7.1 N/A to STP 7.2 N/A to STP 8.1 Check MSIV's Closed 26,28,30,32 LRO 2 6C FSV-7414, 7424, 7434, 7444 8.2 Check MSIV Bypass Closed 27,29,31,33 LRO 2 6C FV-7412, 7422, 7432, 7442 8.3 Check Blowdown Iso. Valves Closed 34,35,36,37 LRO 2 6D F V-4123, 4152, 4151, 4150 E

Revised 7/13/83 R. C. Potter 3135W/0091W M M M M M M MRM

W W W W W W W W W W W M W W W W M~ W W

  • * ^*" Id CONTROL ROOM DESIGN REVIED EVALUATOR N00STON OPERATORTASK10EllTIFICATl0N AND ANALYS45 SIGNATURE LIGHTING

& DATE a= = 3 6

--- POWER CO. LOSS OF OFFSITE POWER PAGE REF

{ uly 1982 LIST OF TASKS FOR EVENT:

ble8ITSAES PANEL LIST EeutPtsENT RE4WIAES TS PERFORGAES TAsutsTEp Tass eaJECTIVE BESCAFileu REFERENCE sy NOS. C0taPLETE TASK SY EURASER ILIST 15 SEGUEIICEl u.1 Head all stm. gen. Pres-sures equal 38,39,40,41 LRO 2 Sil PI-516, 526, 536, 546 10.1 Verify condenser air ejector 42 ,

Desk Communicate with chemistry radiatiorr-Normal 10.2 Verify stm. gen. blowdown radiation-Normal 43 Desk Communicate with chemistry.

I1.1 Read stm gen narrow range 44,45,46,47 LRO 2 6 13 L1-519, 529, 539, 549 Less than 11.2 Manually Control AFW Flow to 48,49,50,51 LRO I SD IIC-7525, 7524, 7522, 7526 control level at 6B LI-519, 529, 539, 549 212.1 Read CST Level greater than 52, 53, 54 Not Us ed LRO 2 13.1 Shed large non-vital DC Local Loads 55 AO 13.2 Monitor DC Power Supplies 56 LRO 1 3C 14.1 Manually open and throttle 57 LRO2 6C PV7411, 7421, 7431, 7441 Stm. Gen. POltVs; reduce RCS Pressure to 14.2 Manually control AFW flow 58 LRO 2 6D IIC-7525, 7524, 7522, 7526 Maintain sim. gen, level 58,59,60,61 6B Ll-519, 529, 539, 549 at 62 Not Used Revised 7/13/83 R. C. Potter E 3135W/0091W

    • " * ^
  • Id .

CVALUATOR NOUSTON CONTROL ROOM DESIGN REVIE'J OPERAT02 TASK CENTIFICATION AND ANALYSIS SIGNATURE LIGHTING OATE

~= ,... & 4 8 f PAGE 0F

-~~ POWER CO. LOSS OF OFFSITE POWER A- dtd 5 July 1982 REF

- LIST OF TASKS FOR EVENT: LIST ESUIPteENT REGulAtt TS PERF8AAAES SIONITSAES PAllEL ITASKf5TEP TASK SSJECTlWE SE5CRFTISE SEFERENCE N05. C00APLETE TASK 3Y BY ButesER (LIST IN SEGUENCE) 15.1 ;tead RCS Pressure 63 LRO 1 4B PI-457, 458 l 15.2 Read Core Exit TCs greater 64 LRO 2 5B than 16.1 Verify Si actuated 65 LRO 2 SD 16.2 Reset SI 66,67,68 LRO 1 ID Reset SI A, P, C 17.1 Verify Isolation Phase A valves Closed 69 LRO 1 l 18.1 Verify power restored to i one AC emergency bus 70 LRO 2 10B If not, return to Step 14 19.1 Maintain Stable RCS temp & 71,72 L RO 1 4R Pressure during Step 20 20.1 Check RCS subcooling greater than _ or go 73,74 LRO 1 4B PI457, 458 to ECA-2.2, Step 1 20.2 Check Pressurizer Level l greater than 10 % or go 75 LRO 1 4R LI-675, 468 to ECA-2.2, Step 1 20.3 Verify Si not automa-tically actuated on power 76 LRO 2 SD to ECA-2.2, Step 1 restoration. If so, go E

Revised 7/13/83 R. C. Potter 3135W/0391W H __ M M h M M M_ O ..

^#

CONTROL ROOM DESIGN REVIEC EVALUATOR NOUSTON OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE LIGHTING DATE

. ... & 5 6

-- ERCO. PAGE uly 1982 LOSS OF OFFSITE POWER A-REF LIST OF TASKS FOR EVENT:

PERFORette meglTORES PANEL LIST EtutretENT RESU4AEB TS TAsutsTEP YAss asJEctivt sESCRAFiles #EEEEEECE sy sy not coasPLETE TASK mutesEn (Last se sfeuf acel

'20.4 If 20.1, 20.2, & 20.3 are met, go to ECA-2.1, Step 1 Choose to go to ECA-2.2 21.1 Read AC Emergency Bus 77,78 LRO 2 10B VI-21.2 Voltage Normal LRO 2 FI-21.3 Frequency Normal LRO 2 22.1 Verify Emerg. Bus to 79,80,81 A. 480 V Buses LRO 1 3D B. Battery Chargers 3C C. Instrumentation

& Control (DC Buses)

LRO 1 LRO 1 23.1 ECW Operation A. Valve Positions 82,84,86 LRO1 2D,l D 23.2 Verify ECW Pump Running 83,85,87 LRO 1 2 D,l D 24.1 Verify RCP Scalinjection 88,89,90,91 LRO 1 4C CV-033 A, B, C, D Iso. Valves Closed 24.2 Verify RCP Thermal Barrier 92 LRO 1 4C CC-0339 CCW Return Iso. Valve CC-0374 Closed CC-0390 CC-035G 25.1 Check RWST Level greater 93,94 LRO I ID L1-931, 933 than E )

3135W/0091W Revised 7/13/83 R. C. Potter

  • " * ^ #""I#

EVALUATOR NOUSTON CONTROL ROOM DESIGN REVIEU OPERATORTASKCERTIFICATION Allo ANALYSIS SIGNATURE LCHTING DATE

== => & 6 s PAGE A- uly 1982 NU POWER CO. LOSS OF OFFSITE POWER REF LIST OFTASKS FOR EVENT:

8005178AE3 PANEL LIST EtulPt4ENT RESUIRES TO PERFOAAAES CotePLETE TASK J TA$d";TEP TASK SSJECilVE DESCRIFilSE REF1RENCE SY SY NOS.

NuesSEA (LIST IN SEGUENCE) 26.1 Check BAT Temp greater 95 LRO 1 4D TI-104/7 than 27.1 Manually restart the following:

I l A. tillSI Pump 96 LRO 1 1D l B. LiiSI Pump (If Press 97 LRO 1 1D

! less than )

C. CCW Pump 98 LRO 1 2D D. RCFC 99 LROI 2D 28.1 Non-faulted Stm. Gen. Level 100,101,102,103 LRO 2 6B LI-519, 529, 539, 549 28.2 AFW Pump Switches in 104,105,106 LRO2 6D Pump 11,12,13 Pull-to-Lock i

20.1 Containment Pressure has 107 stayed below LRO 1 2B PR-934 29.2 Containment Spray Pump- 108,109,110 LRO 1 2D CS-00 IC,015C, Pump IC Standby 30.1 RCP Thermal Barrier Cooling 111,112,113,114 LRO 1 IC,2C CC-404, 318, 291, FV-4493 31.1 Go to E-0, Step 5 E

Revised 7/13/83 R. C. Potter 3135W/0091W hW W..M M M Mh

I Houston CONTROL ROOM IGHMG g gggg y gg ygg y I _ _ __ ,om co.

^"""""^'

I OPERATOR TASK IDENTIFICATION AND AN ALYSIS B

l TURBINE LOAD REJECTION l

l L

E l

l l

I l

B i ,

I I l

l W

I 3435W/0105W

^*

HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSIS SIGNATURE

-.& DATE EE POWER CO. PAGE I 0F 7 LIST OF TASKS FOR EVENT: REF TASM/ STEP TASK OBJtCTIVE DESCRIPTION PERFORMED IAONITORED PANEL LIST EQUIPtBENT REQUIRED TO REFERENCE BY sy NO S. CORIPLETE TASK FUGASER ILIST IN SEQUENCE)

Check main generator status 1.1 l.1.! Megawatt output - 1 UO 2 SiO 7B Nomal Ibuse lead 1.1.2 VAllS output - 2 UO 2 SiO 78 Nonml Ibuse load 1.1. 3 AdlE output - 3 UO 2 SiO 73 Nomal Ibuse load 1.1.4 Offsite power _vailable- 4 UO 2 SiO 108 Nonml Bkr Align.

1.2 Gleck main turbine status

1. 2.1 Turbine oil pressure - 5 UO 2 SiO 7A Annunciator lights Unlit
1. 2. 2 Turbine bearings - G UO 2 SiO 7A Annunciator lights Unlit 1.2.3 Q)nd vacuan 7 UO 2 SiO UA Annunciator lights Unlit
1. 3 Oneck stean duip operation 1.3.1 Valve status lights - 8 UO 2 SiO 7C PV-7485 thru PV-7496 Open 1.3.2 Oieck interlock and node 9 UU 2 Sto 70 selector switches JJ4mi/uiusi lleva sed 7/13/d3 11. C. IN> t t e r E

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W W W W W W W W W W W W W W W W W W ~

C. A. Bolig HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSIS SIGNATURE

- ,.m & DATE

'EE POWER CO. PAGE 5 0F 7 STP 401, Nov.1982 LIST OF TASKS FOR EVENT: REF TASK /5TEP TASK OBJECTIVE DESCRIFTION PERFORIGED RIONITO RED PANEL LIST EQUIPRIENT REGUIRED TO REFERENCE BY BY N05. CORAPLETE TASK cut 0BER ILIST IN SEQUENCE) 7.2.2 Use steun duip pressure controller 36 UO 2 slo 7C IK-0557 7.2.3 Place niode selector in Tavg mode 37 DO 2 S10 70 US-0555Z 8.1 Monitor przr. pressure 38 UO 1 slo 4B PI-0457, 458

8. 2 Use przr. spray to control pressure 8.2.1 Oncek pzr press. 39 UO 1 SiO 4B PI-0457 8.2.2 Oontrol pressure with przr.

pressure manual control 40 UU 1 SiO 4C IK-0655A 9.1 Cheek RO) seal water flow 41 UO 1 slo 4B Fit-0156, 7, 8, 9 9.2 Adjust itCP seal water flow ,

wi th IKN-218 42 11 0 1 SiO 4C IKN-0218 10.1 Check stean generator levels 43 UU 2 SiO 6B LI-519, 529, 539, 549 10.2 Adjust feed flow as necessary 44 UO 2 SiO GD FK-0551, 2, 3, 4 11.1 Check turbine for vibration or bearing problons 45 UO 2 SiO 7A Annunciator lights 1

I 3345V/0103V itevised 7/13/83 11. C. Pot t e r E

C. A. Bolig CONTROL ROOM DESIGN REVIEC EVALUATOR l HOUSTON LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSl3 SIGNATURE

& OATE

'E3 POWER CO.

'IUtBINE 100 ilEJIX! PION PAGE REF 6

p ' g* 7 LIST 0F TASKS FOR EVENT:

PERFORMED MONITORED PANEL LIST EQUIPMENT REGUIRED TD TASK / STEP TASK OBJECTIVE DESCRIPTION REFERENCE SY SY NO S. COMPLETE TASK NU100ER illST IN SEGUENCE) 11.2 01cck generator f req. 46 UO 2 SiO 78 Panel 7\104 12.1 Check FW leater status 47 UU 2 SiO 8A Annunciator lights 12.2 Oteck drip pmp status 48 UO 2 SIO 88/A Meter indication annunciator status 13.1 Tave decreasirg until steun durps close j 13.1.1 0)eck Tave -Decreasing , 49 UO 1 SiO SB l 13.1.2 lleduce reactor power as ,

necessary - llods Inserting 50 UO 1 SiO 50 j l

13.2 Cicek That stean duips are l closed l

13.2.1 Oteck steau duip donatxi -

Zero 51 UO 2 SiO 7C UI-0555 13.2.2 Stean durp valve position indication - Closed .52 UO 2 SiO -

7C 14.1 . ilonitor prinnry paraicters 14.1.1 Oieck Tave 53 UO 1 S10 5B 14.1.2 Cicek przr. pressure 54 UO 1 Stu 48 14.1.3 \1onitor itx power 55 UO 1 slo SC/D 22 :1?/2PJ21 ite vi seo 4 /14/ 64 n. U. Potter E M_M_M M M M M W.M M

M ' M M ~' M M W W'M M M M M M M M'M M M HOUST0J CONTROL ROOM DESIGN REVIEW EVALUATOR LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSl3 SIGNATURE

" POWER CO.

DATE 7 7 PAGE 0F LIST OF TASKS FOR EVENT: lul81NE IGW ltEJECTION STP MI, Nov.1982 REF TASK / STEP TASK OBJECTIVE DESCRIPTION PERFORGAED REFERENCE 800NITORED PANEL LIST EQUlratENT REQUIRED TO NUGASER ILitiIN SEQUENCE) BY SY N05. C04APLETE TASK 14.2 enitor secondary paraneters '

14.2.1 Dieck stm. dmp status 56 UO 2 SIO 7C 14.2.2 Ocek gen. f requency 57 UO 2 slo 78 Panel 7.5104 l

! 14.2.3 Week AW output 58 UO 2 SiO 713 14.2.4 Ocek Stm. gen levels 59 UO 2 SiO 68 15.1 tteset stm. duip interlock -

lteset 60 UO 2 SIO 7C 15.2 Cicek prinnry (ItG) inter-locks cleared 15.2.1 Oieck OP T - Cleared 61 UO 1 SiO SA Annunciator lights 15.2.2 Cleek Of I' - Cleared 62 UO I SiO SA Annunciator lights 16.1 Gieck I tine violation N/A N/A SiO N/A Nuclear Inst. Panel 16.2 Detennine power level N/A UU 1 S10 N/A Plant 201

17. Iteturn to J005 or restricted See plant, power leve1 S/U SOE 334M/0102W ttevised 7/13/83 11. C. lb t t e r E

~~

B B "*U' " CONTROL ROOM lGHTING DESIGN REVIEW i . - - . .

,_ s POWER CD.

APPENDIX A.6 OPER ATOR TASK IDENTIFICATION AND ANALYSIS 1

PLANT STARTUP 1 Steam Bubble Startup Reactor Coolant Heatup r

B l

I 1

l

] -

\

l 1 s

J435W/0105W

- --- - _ _ __-- - - - - . - - - _ _ _ _ _ _ - - - l

~

~M M M M M M M M M M M M M M M M M l HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR LIGHTING OPERATOR TA5K !OENTIFICATION AND ANALYSIS SIGNATURE

.. & 1 5-82 DATE

'*"U -

POWER CO. I 13 Startup From Cold Stutdown(Preliminary) AGE Pg PJ,7g,l LIST OF TASKS FOR EVENT: REF TASK / STEP TASK OBJECTIVE DESCR4 Filets PERFORetED Is0NITORES PANEL REFERENCE LitT EQUIPtaENT REL'891 RED TS Mue86ER (LIST IN SEGUENCE) BY BY NOL CatePLETE TASK 1.1 Startup preparation

  • 1.1.1 Obtain approval froin inaint.

l Gen. Supervisor for startup 1 SitO -

i

1. 2.1 Verify primary & secondary systems maint. completed 2 SitO -

l

1. 3. ! Verify itCS lus been filled and vented 3 SitO -

1.4.1 Plant controls & instrumen-tation elecklist coinplete 4 SitO -

1.5.1 Plant electrical distribution -

system efecklist coinplete 5 Silo -

i l

I. 6. I iteactor coolaat armi assoc.

systems efecklist complete 6 SitO -

1.7.1 Secosulary, secondarf assoc.

anxi plant common elecklist 1 complete 7 SitO -

l

1. 8 -

Plant safety systems Operability elecklist complete

1. 8.1 Slutdown maagin OK 8 Sito -

i.8. 2 Lloron concentration OK 9 Sito -

3347W/0102W llevise 7/13/83 II.C. Potter

CONTROL ROOM DESIGN REVIEW EVALUATOR .

HOUSTON LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSl3 SIGNATURE ,

10-5-82

~~~ A DATE 2 13

'E9 POWER CO. ^

Startup F.um Cold Slutdown(Prelimirury) PO P3- -l r LCT OF TASKS FOR EVENT: REF TASK BBMCTIVE DESCR8Fil0E PERFORetEB is0NITOREB PANEL LIST Eeuere8ENT REGUIRED TO l TLSK/5TEP REFERENCE BY av NOS. CaesPLETE TASK suessEA (LIET IN SEQUESCEl l

1. 9.1 1%m ilVAC checidist complete 10 SitO -

!.10.1 itCS chemistry within spec.

for startup 11 SitO - .

1.11 Put main turtx lobe system in service 1.11.1 SG feedpump i1 AC lube oil pump munirg 12 Alto SitO Local 1.11.2 Turnity gear in operation 13 Att0 SitO Local 1.11.3 SG feedpump 12 AClube oil pump mnning 14 Allo SitO Local 1.11.4 Turnity gear in operation 15 AntO S 11 0 Local 11.11.5 SG feedpump 13 AC lube oil pump mnnirg 16 AttO SitO Local l

1.11.6 Turnity gear in operation 17 Alto SitO Local 1.12 Condensate & feedwater

- systems on recirculation 1.12.1 Verify pump disert valve closed 18 LitO 2 SitO 8D CD-107, CD-097, CD-088 1.12.2 Verify pump recite. valve Ago ,

in auto control 19 latO 2 ' SitO Local FV-7022 E

3347W/0102W llevise 7/13/83 It.C. Potter M M M M M M M_ H. M ,

^

w

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EVALUATOR y NOUST0m CONTROL ROOM DESIGN REVIEW OPERATOR TASK 10E81TIFICAT10N AND ANALYSIS SIGNATURE LIGHTING 1 5-82

.& DATE M 'S POWER CO. 4 I3 l

PAGE Startup Froin Cold Shutdown (Steain Bubble Startup) POP.s kb-1 LIST OF TASKS FOR EVENT: REF

' TABE OBJECTIVE DESCAIFileg PERFORIAES 30051TGRES FANEL LIST EeulPRIENT REGulAES TO TASK /5TEP REFERENCE BY BY N05. C04tPLETE TASE muassER ILIST IN SEeufmCE) 2.2.4 Adjust drain valve as reg'd to control PitT press, close valve wten desired PatT level is reacted 30 LitO I SitO 4D LV-3655, L1-0670 2.2.5 Stop itC drain tank pump 31 LitO 1 Sild 40 CP-004

2. 3 Open power operated relief -

valves arut block valves l

2. 3.1 Power operated relief valve l O PEN 32 LitO I SitO 4C PCV-656A I

( 2.3.2 Block valve-OPEN 33 L1101 SitO 4C itC-0010 2.3.3 Power operated relief valve 34 LitO I SitO 40 PCV-655A l

2.3.4 Block valve-OPEN 35 LitO ! SitO 4C itC-001 A 3.1 Estatiish itCS letdown flow l path 3.1.1 verify pre =surizer spray valves-CLOSED 36 LitO 1 SitO 4 11 PCV-655B, PCV-655C 3.1. 2 If only "C% loop of itilat runnity, place "A" or "B" in service 37 LitO I SitO ID 3.1. 3 Open valve from,,ltilits to CVCS 38 LitO I Sito 10 Itll-066A or 1111-06G11 3347W/0102W llevise 7/13/83 It.C. Potter EE E E E E E_ h

11. C. Potter y NOUST0m CONTROL ROOM DESIGN REVIEW OPERATOR TASK IDENTIFICATION AND ANALYSl3 EVALUATOR LIGHTING SIGNATURE

& DATE Io-5-82 T'E POWER CO.

pAgg 5 0F 13

" "" ""*"" " "P l'O P3-ZG-1 LET OF TASKS FOR EVENT: REF TASK / STEP TASK 891ECTIVE BESCAaril0N PERF0AteEB RIONITORES PANEL LIST ESUIPetENT REtulAEa Te REFERENCE sy 508. CoasPLETE TASK muteSEN (LIST la SE EUENCE) BY -

3.1. 4 Set 112 gas regulator to VCT at 15 psig 39 Alto SitO Local PC-3110 3.1. 5 11 2 leader isolation valve-OPEN 40 Allo SitO Local llY-019 3,1.6 Letdown isolation valves-OPEN 41 LitO 1 SitO 4C CV-231C, CV-0240C 3.1.7 Letdown pressure control valve-O PEN 42 LitO 1 SitO 4D PCV-135 3.1. 8 Position letdown divert to recycle toldup tank valve 43 LitO I SitO 4D LCV-I! 2A 3.1. 9 Monitor PatT pressure, maintain min. of 0.5 psig N2 press. 44 LitO I SitO 4D PI-669 3,1.10 Tlirottle letdown press, co.: trol valve, as regiired 45 LitO I SitO 4D PCV-135

3. 2 At per level of 25%, stop drainity 3.2.1 - Monitor pressurizer le vel, '

wien 25% 1evel, 46 LitO 1 SitO 4B LI-675 3.2.2 Close valve from IllittS to 47 LitO 1 SitO 10 Itll-066A or Illi-066B CVCS 3.3.1 Low-press. regulated N2 valves-CLOSED 48 AttO SitO Local NI-040, NI-041 E

3347W/0102W llevise 7/13/83 It.C. Potter

CONTROL ROOM DESIGN REVIEW EVALUATOR HOUSTON LIGHTING OPERATOR TASK IDENTiflCATION AND ANALYSIS SIGNATURE 10-5-82

.& DATE 6 13

"" POWER CO. ,,_g_,

PAGE Startup From Cold Shutdown (Steaan Bubble Startup)

REF .

LIST OF TASKS FOR EVENT:

PERFORIGED 100NITSRES PANEL LIST E0uiretENT AFGUIRES TS TASK /5TEF TASK 08MCTIVE BESCR8Fil0E REFERENCE By gy BOL CoedPLETE TASK muteSER ILIST III SESUENCEI 3.4.1 PitT vent valve-OPEN 49 Allo SitO Local ItC-031 3.5.1 Energize all pressurizer heaters 50 LitO 1 Silo 4D 4.1 Establish norinal letdown

& seal injection flow 4.1.1 Place letdown divert to recycle lioldup tants valve ,

in auto 51 LitO I Silo 4D LCV-112A l 4.1.2 ItC pump seal water injection isolation valves-O PEN 52 LilO 1 SitO 4C CV-033A, CV-0338,

! CV-033C, CV-033D 4.1. 3 itC pump seal waterinjection flow control calve-O PEN 50% 53 LilO 1 SitO 4C llCV-218 4.1. 4 VCT outlet isolation valves-O PEN 54 LitO I SitO 4D C V-l l 211, CV-I l 3 A 4.1. 5 Letdown press. contiul valve in auto., adjust controller

. for o psig 55 LitO 1 SitO 4D PCV-135, PK-135 4.1. 6 Itllit to CVCS valve-OPEN 56 LitO I SitO 10 itil-066A or 1t11-06611 4.1.7 Verify centrifugal clurgirg inini-flow valve-O PEN 57 LitO 1 SitO 4D FCV-201 or FCV-202 3347W/0102W llevise 7/13/83 It.C. Potter I 1O M M M M_.M

M M M M M M M M M M M M M M M MR U NOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR II. C. Potter LIGHTINs l#ERATOR TASKIDENTIFICATION AND ANALYSIS SIGNATURE

<& DATE 10-5-82


POWER CO. 7 13 PAGE 0F Startup From Cold Shutdown (Steam Bubble Startup) PO P3-ZG-1 LIST OF TASKS FOR EVENT: REF TASEATEP TASK 88JECTivE BEscaar:ses PEarsaasES seestTenEs PANEL LIET EautresENT AESWIRES TS messein REfERESCE (List SH SEGUENCE) BY aV Net. CetaPLETE TASK l 4.1.8 Verify pump cubicle cooler

  • starts 58 LRO I SRO 4D l 4.1.9 Start one centrifugal I

charging pump 59 LROI SRO 4D 4.1.10 Monitor pressurizer level 60 LilO I SHO 4fl LI-675

, LI-466A 4.1.11 Throttle seal injection flow valve as required 61 LRO I SRO 4C llCV-218 .

l 4.1.12 Normal charging flow valve-OPEN 62 LRO I SitO 4D CV-003B 4.1.13 Charging flow isolation valve-OPEN 63 LRO I Silo 4D CV-025 4.1.14 letdown stop valves-OPEN 64 LROI SRO 4C LCV-465, LCV-468 4.1.15 Letdown orifice valves-OPEN 65 LRO I SHO 4C CV-012, CV-013, CV-014 4.1.16 Pressurizer level control valve-OPEN SLOWLY 66 LRO I SitO 4C LK-0665 4.1.17 Throttle seal injection flow 1 1

control control valve 67 LRO 1 SitO 4C If CV-218 4.1.18 Monitor seal injection flow

( 8 gpm) 68 LRO I SitO 4 11 Fit-156,157,158,159 f

3347W/0102W Revise 7/13/83 R.C. Potter

P 'I N" ' ' I NI

11. C. Potter EVALUATOR CONTROL ROOM DESIGN REVIEW NOUSTON SIGNATURE OPERATORTASKIDENTIFICATION AND ANALYS48 l LIGHTING DATE 1 &s-82

.n.. & g n .

" POWER C4.

^

Startup From Cold Shutdown (Steam Bubble Startup) POP 3' -1 REF LIST OF TASKS FOR EVENT: LIST EtuarteENT REeulAES TS FEnfenests asestTSAES FANEL TASE SSJECTIVE BEstarties 585. C04APLETE TASK TASE/5TEF REFERENCE BV SV mueesta ILeSTla stautscEl 4.1.19 Adjust pump throttle valves as required to balance - -

pump seal injection flows 69 ARO SRO local CV032A, CV03211, CV032C, CV032 4.1.20 Place pressurizer level control valve in auto 70 LROI SRO 4C LK-0665 4.1.21 Monitor pressurizer relief temp. 71 LRO 1 SRO 4 11 TI-676 .

5.1 increase PRT level to 80%

5.1.1 Start one reactor make-up water pump 72 LRO 1 SHO 4D 5.1.2 Reactor make-up water to PRT valve-OPEN 73 LRO I SRO 4C F V-3650 ..

5.1.3 Monitor PRT level, when level .

reaches 80% 74 LRO I SitO 4D LI-670 5.1.4 Close make-up water valve 75 LRO I SRO 4C FV-3650 5.1.5 Stop reactor make-up water

- pump 76 LRO I SitO 4D =-

6.1 PRT on recirculation Stop both itC drain tank pumps 77 LitO 1 SitO 4D I;.

6.l.1 i

2 E ~

as47 W/t 102W Revise 7/13/83 R.C. Potter

- e. .

- . . ._ . I. .

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W W W W W W W W W W W W W W W W W W W

. . ter.

CONTROL ROOM DESIGN REVIEW EVALUATOR NOUSTON OPERATORTASKIDENTIFICATION AND ANALYSi$ SIGNATURE t

LIGHTING 10-5-82 l ., & DATE I3 .:

MER CO. Startup From Cold Shutdown (Steam Bubble Startup) PAGE _ QF REF LIST OFTASKS FOR EVENT:

FERFORieED Is0NITORES FANEL LIST ERulresENT REQUIRES TO TAsm/ STEP Tass esJECTivt sESCRIFileu REFERENCE sy NOL C0eePLETE TASK (LIET is SEGUENCE) SY ruessEA 6.1.2 Close RC drain tank level -

3ontrol valve 78 LROI SRO 4D LV-4911 6.1.3 31ose RC drain tank reeire. .

ine isolation valve 79 LRO I SRO 4D FV-4910 6.1.4 lose RC drain tank isolation -

talve 80 LRO I SRO 4D FV-4903 /

6.1.5 i

) pen pressurizer relief tank

< ! rain valve 81 LROI SRO 4D LV-3655 6.1.6 Open return to PRT isolation

'alve 82 LROI SRO 4D FV-4907 ,

6.1.7 Start one RC drain tank pump 83 LROI SRO 4D

~

7.1 Form steam bubble -

.q 7.1.1 (  : lose one pressurizer power o perated relief valve 84 LROI SRO 4C PCV-655A or PCV-656A 7.1.2 Uhen PRT press. starts i aereasing, close the open

-ower operated relief valve 85 LRO I Silo 4C PCV-655A or PCV-65GA

~~

j3 laintain 50 psig pressurizer l 7.1.3 P -

1 ress by eyeling the power d

rperated relief valve and 4C PCV-655A or PCV-656A  :)

pressurizer heaters 86 LRO I SRO 4D PI-457, PI-455, PI-456 ,j 1B ]

)

, ., A u n m Revise 7/13/83 R.C. Potter

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EVALUATOR CONYROL ROOM DESIGN REVIEW HOUSTON SIGNATURE OPERATORTASKIDENTIFICATION ANO ANALYSIS 1 5-82 LIGHTING OATE m, & 10 13 N H POWERCo. Startup From Cold Shutdown (Steam Bubble Startup)

PAGE- tuta-z.bi REF LIST OF TASKS FOR EVENT: FAMEL LIST ESUIPteENT RESUSAES TO MRFSAa0ES IIGNITORES Tf.1K S4JECTIVE BESCRIFTISE NOL C0tePLETE TASK TAsuJ5TEF REFERENCE EV BY ruessEn (Lisiim EfestacEl 7.1.4 Monitar PitT press., when press.

stops increasing as the power operated relief valve is open 4D PI-669

=

87 LROI Silo N2 venting is complete 7.1.5 Open one pressurizer power operated relief valve for SRO 4C PCV-655A or PCV-656A 15 see. 88 LRO I 8.1 Increase letdown press. to 400-450 psig 8.1.1 When 11CS press. increases above 100 psig, open RC pump 1 A seal leakoff isolation SRO 4f3, C FV-3154 89 LRO1 valve 8.1.2 Open 11C pump IB seal leakof f SRO 4C FV-3155 isolation valve 90 LRO I 8.1.3 Open RC pump IC sealleakoff SRO 4C FV-3156 91 LRO I isolation valve 8.1.4 Open 11C pump ID seal leakof f SitO 4C FV-5157 92 LRO I isolation valve 8.1.5 Open seal water return SRO 4D CV-077, CV-079 isolation valves 93 LRO I 8.2 Stabilize pressure 94 LRO I SitO 4 13 PI-455, 56, 57, & 58 8.2.1 hlonitor RCS pressure, E

llevise 7/13/83 II.C. Potter aag4 N u u'm

R. C. Potter CONTROL ROOM DESIGN REVIED EVALUATOR NOUSTON OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE

LIGHTING 10-5-82

& DATE m .. 1I i3

--- PMNER CO. Startup From Cold Shutdown (Steam Bubble Startup)

PAGE POP 3-Z -1 REF LIST OF TASKS FOR EVENT:

RISBITORES PANEL LIST ESulPteENT REGUIRES Te TAsa seJECTIVE BESCRIPHSN PERFSRIAEB TAsutsTo REFERENCE SV 3Y NOL C0tePLETE TASK mutesER (LIST IN SEGUENCEI 8.2.2 Cycle pressurizer heaters -

as required or adjust e pressurizer 95 LRO 1 SRO 4D 8.2.3 Adjust pressurizer auxiliary spray as required 96 LRO 1 SRO 4B PK-0655C 9.1 Start RC pumps 9.1.1 Verify component cooling water to RC pump thermal barriers, RC pump 1 A thermal barrier isolation valve-OPEN 97 LRO I SRO 4C CC-339 9.1.2 RC pump IB thermal barrier isolation valve-OPEN 98 LRO I SRO 4C CC-374 9.1.3 RC pump IC thermal barrier isolation valve-OPEN 99 LROI SRO 4C CC-390 9.1.4 RC pump ID thermal barrier isolation valve-OPEN 100 LRO I SRO 4C CC-356 Note: Preferred starting sequence 1or RC pumps is IIJ,1 A, & IC.

> 9,l.5 Start ID RC pump oillift

. pump 101 LRO 2 SRO SC 9.1.6 After pump has run for 2 min. verify the white start l l .> ermissive light is lit 102 LRO 2 SRO SC l

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HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR lt. C. Potte'r g

. m.

LIGHTING OPERATOR TASK IDENTIFICATION AND ANALY315 SIGNATURE DATE 10-5-82

    • POWER CO. 2 PAGE 0F 37 LIST OF TASKS FOR EVENT: St rtup From k.d Shutdown (Reactor Coolant lleatup) PO P3-ZG-1 REF TASKisTEP TASK OBJECTIVE DESCAril0E PERfGRIGES NuteSER REFERENCE IsotiTORES PANEL LIST EOUIPtBENT REcutRES TB ILIST IN SEGUE NCE) BV BV N05. C0tePLETE TASK 2.1.8 Close IlllR pump suction valve
  • Train C 143 LiiO I SitO Perforrn steps 2.1.9 thru 2.1.20 ID Ril-06tc for those HilR trains that were in service 2.1.9 Open Hillt pump mini-flow valve 144 LROI SRO ID Ril-067A, B, or C 2.1.10 Open Rlill Seat exch. outlet valve to 50% 145 LRO I SRO ID FCV-851,852, or 853 2.1.11 Open Rillt bypass valve to 50% 146 LRO 1 SHO ID llCV-864,865, or 866 2.1.12 Verify open Hillt to CVCS valve 147 LRO I SRO ID llll-066A 2.1.13 Start itillt pump 14 8 LRO I SRO 2.1.14 Monitor 111111 loop temp 149 LRO I SRO IB TI-874 2.1.15 When temp 120*F stop llillt pump 150 LitO I SRO ID 2.1.16 Close illlR pump mini-flow valvo LRO I 151 SitO ID ltll-067 A, B, or C 2.1.17

. Close the Itlllt to CVCS letdown isolation valve 152 LRO I SRO l ID it ti-066 A 2.1.18 Close heat exch, bypass valve 153 LRO I SitO ID FCV-851,852, or 853 3279W/0098W E um,s.,,. n e u ro , o c- n-...

M M M M Q Q '

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7 F1 f 1 I 1_ l l J l 1 m M M 1.__] .

~M M M M M-MOUSTON CONTROL ROOM DESIGN REVIE'3 EVALUATOR R. C. Potter LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSl3 SIGNATURE

,, & 1 & S-82 DATE

-M#* POWER CO. 3 37 PAGE 0F LIST OF TASKS FOR EVENT:

Startup From Cold Shutdown (Reactor Coolant Ileatup) PO P3-ZG-1 REF TASK /5TEP - TASK FAJECTIVE DESCRiFil0E ' PERFORetEB RIONITORER PANEL REFERENCE LIST ESUlretENT REGUIRES TO l NuetSER (LIST III SEBuENCEI BY BY N05. C00erLETE TASK 2.1.19 Close comp. cooling water from

  • IlllR heat exch. 154 LRO I SRO ID FV-4531,4548, or 4565 2.1.20 Open IlllR heat exch. outlet .

valve 155 LRO 1 SRO ID IICV-864,865 or 866 3.1 Increase itCS press. & temp.

and plot results 3.1.1 Monitor pressure 156 LRO 1 SRO 4B TI-0608, PI-0457 Monitor temp. ISGA 3.1.2 Plot heatup rate 157 LRO 1 SRO 3.1.3 Monitor seal injection flow 158 LRO I SHO 4B F R-156,157,158,150 3.1.4 Monitor seal press.

differential 159 LRO 1 SRO 4B PI-152 Caution: Do not exceed 1600 psig see, press. differential 3.2 Open steam generator main steam line drain valves 3.2.1 Open drain valve 160 LRO 2 SRO 6C FV-7900 3.2.'2 Open drain valve 161 LRO 2 SRO 6C FV-7901 3.2.3 Open drain valve 162 LRO 2 SRO GC F V-7902 3.2.4 Open drain valve 163 LRO 2 SRO 6C FV-7903 1

3279W/0098W Revised 7/14/83 R. C. Potter

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-q HOUSTON CONTROL ROOM DESIGN REVIED EVALUATOR i LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSIS SIGNATURE

.. & 0-5-82 ]

DATE ,

"" *T 6 37 POWER CO.

PAGE pg p3_gg_qF Startup From Cold Shutdown (Reactor Coolant lleatup)

LIST OF TASKS FOR EVENT: REF t- TASM/5TEP TASK SSJECTIVE DESCROFTION PERFORIGED RIONITORED PANEL LIST EQUIPteENT REQUIRED TO NuestER REFERENCE l (LIET IN SESUENCE) BY BY NOS. CORAPLETE TASK 4.2.1 Steam generator feedpump . -

t No.11 AC lube oil pump 183 ARO SRO Local l unning, turning gear in l speration 183A ARO SRO Local 4.2.2 Steam generator feedpump No.12 AC lube oil pump 184 ARO SRO Local running, turning gear in operation 184A ARO SRO Local 4.2.3 Steam generator feedpump ,

No.13 AC lube oil pump 185 ARO SRO Local l l running, turning gear in operation 185A ARO SRO Local 5.1 Main condensate system on recire ,

l 5,1.1 Verify condensate pump l disch. valve-CLOSED 186 LRO 2 SRO 80 CD-107, CD-097, CD-088 l l

5,1.2 Verify pump recirculation l valve in auto control 187 ARO SRO Local FV-7022 l 5,1.3 Steam generator feedpump disch. valve-CLOSED 188 LRO 2 SRO GD FW-061, FW-072, FW-Il9 5.1.4 ' Steam generator feedpump recirculation valve-CLOSEli, 189 LRO 2 SRO GD FV-7114, FV-7109, FV-7104 3279W/0098W Revised 7/14/83 R. C. Potter E

- L' ]__ _ E __ _ E . .. M M M

M M W W W M M M M W W W W W W W"M W ~

HOUSTON CONTROL ROOM DESIGN REVIEW EVALUAT0 h *

) LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE

- ..., & 10+82 DATE N49 POWER CO. 3 Startup From Cold Shutdown (Reactor Coolant lleatup) PAGE OF ru t'a-z.u- a LIST OF TASKS FOR EVENT: REF TASEATEP TASE SSJECTIVE DESCRIFTION PERFORME0 ISONITOREO NEFERENCE PANEL LIST EQUIPteENT REOUIRED TO NUI8SER ILIST IN SESWENCE) By ay NO S. CetIPLETE YASK 5.1.5 or feedpump lube oil systems .

must be operating 190 ARO SRO Local 5.2 Start other condensate systems '

5.2.1 Start main circulating water system 191 LRO 2 SRO 9D 5.2.2 Verify main turbine and feed-pump turbine gland seal system in operation using aux steam 192 ARO SRO Local 5.2.3 Start main condenser vacuum pumps 193 ARO SRO Local 5.2.4 Close main condenser vacuum breakers 194 LRO 2 SRO 9C 5.2.5 Verify condensate deacrator in operation using aux. steam 195 ARO SRO Local 5,2. 6 Verify main generator pressurized with 112 196 LRO 2 SRO 78 PI-6059 5.2.7 Verify seal oil system in operation 197 ARO SRO Local 6.1 Verify MS, main turbine &

feedpump drains oper/ auto l 6.1.1 Verify main steam drain valve LV-7919 open or auto 198 LRO 2 SRO 7C LV-7919 3279W/0098W llevised 7/14/83 R. C. Potter E

HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR it . C. Potter i LIGHTING OPERATOR TASK IDENTIFICATION AND ANALY$l$ SIGNATURE 'j p%fdi OATE 1n-s-99 PAGE R OF 37 LIST OF TASKS FOR EVENT: Startun Penm Cold Shutdown (Reactor Coolant lleatup) REF PO P3-ZG-1 TASE/ STEP TASE SSJECTIVE DESCRWileN PERFORMES MONITORED PANEL gg,ERENCE LIST ESUIPMENT REeulAED TO NuessER (LIST IN SEGUENCE) SY SY NOS. COMPLETE TASK l

l 6.1.2 Verify SGP PT low point drain valve FV-7975 open or auto 199 ARO SRO Local FV-7975 l 6.1.3 Verify main steam drain valve ,

LV-7918 open or auto 200 LRO 2 SRO 7C LV-7918 6.1.4 Verify SGFFT low point drain  !

valve PV-7974 open or auto 201 ARO SRO Imal FV-7974 l

- 6.1.5 Verify main steam drain valve LV-7916 open or auto 202 LRO 2 SRO 7C LV-7916 6.1.6 Verify SGPPT low point drain valve PV-7973 open or auto 203 ARO SRO Local FV-7973 6.1.7 Verify main steam drain valve LV-7917 open or auto 204 LRO 2 SRO 7C 1,V-7917 6.1. 8 Verify main steam drain valve FV-7900 open or auto 205 LRO 2 SitO 6C F V-7900 6.1.9 Verify main steam drain valve PV-7901 open or auto 20G LRO 2 SitO 6C FV-7901 6.1.10 Verify main steam drain valve PV-7'"'" pen or auto 207 LitO 2 SRO 6C F V-7902 6.1.11 Verify main steam draia valve PV-7903 open or auto 208 LitO 2 SRO 6C FV-7903 3279W/0098W Revised 7/14/83 11. C. Potter i I M M_W M M M. O

W W W ~~ M M M M M M W W'M M M'W W W W '

NOUST0] CONTROt. ROOM DESIGN REVIEW EVALUATOR LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE DATE 10-5-82

" POWER CO. 8 37 PAGE pF LIST OF TASKS FOR EVENT: *# "P # * " *" ** # "" ""* "E REF TASE/5TEP TASK SSJECTIVE DESCRIPTION PE RFORI8E D ISONITORED NuestEN EFERENCE l PANEL LIST EeveralENT REGUIRED TO (LtST IN SEGUENCE) BY BY NOL C00sPLETE TdSE 6.1.12 Verify drain valve FV-7950 .

open or auto 209 ARO SRO Local PV-7950 6.1.13 Verify drain valve FV-7951 open or auto 210 ARO SRO Local FV-7951

6.2.1 Open main steam isolation valve bypass valve FV-7412 214 LRO 2 SRO 6C FV-7412 6.2.2 Open main steam isolation valve bypass valve FV-7422 215 LRO 2 SRO GC FV-7422 6.2.3 Open main steam isolation valve bypass valve FV-7432 216 LRO 2 SRO GC FV-7432 6.2.4 Open main steam isolation valve bypass valve FV-7442 217 LRO 2 SRO 6C FV-7442 i

3279W/0098W Ilevised 7/14/83 R. C. Fotter E

MOUSTON CONTROL ROOM DESIGN REVIED EVALUATOR LIGHTING OPERATORTASKIDENTIFICATION AND ANALYSIS SIGNATURE

-.& DATE 10-5-82

" POWER CO.

Startup From Cold Shutdown (Reactor Coolant lleatup)

'^ 10 PO P3-ZG-37 LIST OF TASKS FOR EVENT: REF TAsutsTEP TAsa ssJECTIVE DESCAlm05 PERFORGIES RIONITORES PANEL LIST EOUIPt0ENT REQUIRED TS REFERENCE BY BY Net. CatePLETE TA$st muassEn itest au SEeUENCE) 6.3 Monitor llCS conoitions ,

6.3.1 Monitor RCS temp. 510*F 218 LROI SRO 4B TI-0608 6.3.2 Monitor SG pressures 735 psig 219 LRO 2 SRO GB PI-0516, 26, 36, 4 6 .

6.3.3 Monitor RCS press 2000 psig 220 LROI SRO 4B PI-4 57, PI-4 58 7.1.1 When llCS press. 2000 psig verify pressurizer permissive P-11 clears 221 LRO 2 SRO SB 7.2 When RCS press = 2235 psig transfer press. control to auto 7.2.1 Monitor IICS press., when press. = 2235 psig 222 LRO I SitO 4B PI-457, PI-458 7.2.2 Place pressurizer spray valve controller in auto 223 LRO 1 Silo 4B PCV-655B 7.2.3 Place pressurizer spray valve i

controller in auto 224 LRO I Silo 4B PCV-655C 7.2.4 Place pressurizer pressure controller in auto 225 LRO I SitO 4C PK-0655A I

3279W/0098W llevised 7/14/83 11. C. Potter 1 ) M M ____ h _ E E . E E .. E - -

=

R. C. Potter NOUSTON CONTROL ROOM DESIGN REVIEC EVALUATOR LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSIS

-.& SIGNATURij DATE

.E!E POWER CO. II 37 Startup From Cold Shutdown (Reactor Coolant IIcatup) PAGE ru r ez.u-9E l LIST OF TASK 0 FOR EVENT: REF TAsumTar TASK SSMCTIVE Bf 5CRIPTISE PERFORGAEB Is0NITORED PANEL LIST EGuiretENT REGutRES TG 2000sER (LIST IN SESUENCEI REFERENCE BY sY NOL CotAPLETE TASK 7.2.5 Place pressurizer backup -

heater groups in auto except for one group 226 LRO I SRO 4D 3 switches 7.3.1 Request Chem. Group to '

sample RC for boron 227 SRO SRO -

7.4.1 Close the reactor trip switch 228 LRO 2 SRO SC 7.5.1 Push " Full-Length Rod Control Startup" and " Rod Control Alarm iteset Buttons" 229 LRO 2 SRO SC 7.6 Monitor / withdraw control rods 7.6.1 Withdraw shutdown banks of control rods 230 LRO 2 SRO SD 7.6.2 Monitor rod position indi-cations for misaligned or inoperable rods 231 LRO 2 SHO 5 13 8.1.1 Perform surveillance test PS P3-R X-01 232 LRO I SRO -

8.2.? Verify itCS and FW system chemistry 233 LRO 1 SRO -

i 1

8.3.1 Complete POP 3-ZG-7

" Estimated Critical Position" 234 LRO SitO -

l 3279W/0098W E Revised 7/14/83 R. C. Potter

CONTROL ROOM DESIGN REVIEC EVALUATOR

11. C. Potter NOUSTON

$ LIGHTING OPERATORTASKIDENTIFICATION AND ANALYS15 SIGNATURE m i.. & OATE 10-5-82 "R"' POWER CO.

PAGE 12 0F 37 Startup From Cold Shutdown (Reactor Coolant Ileatup) PO P3-ZG-1 LIST OF TASKS FOR EVENT: REF TASIUSTEF TASK SSJECTIVE DESCAlrfl85 PERFORe6ED RIONITORER PANEL LIST ESUIPtIEET RE004AEB TO N4iteSER (LIST III SE00ElsCE)

REFER N E BY SY NOS. C0taPLETE TASK 8.4 Boron dilution

8.4.3 When dilution is complete request boron sample 237 SRO 9.1 Commence reactor startup -

9.1.1 Announce commencement of startup 238 SRO -

9.1.2 Select highest reading source and intermediate range NI channel for recording on N-45 239 LRO 2 SRO SB plasma display 9.1.3 Defeat the " Source Range Ili-flux at Shutdown" alarm with manual block switches at N-31 & N-32 drawer assys 240 SHO 9.1.4 Verify at least 2 CPS count rate on Source Range Instru-ment selected 241 LRO 2 SRO SD 9.1.5 Verify the RC system avg.

temp. 5400F on all loops within 15 min. of withdrawing rods 242 LRL 2 SRO SB l

3279W/0098W Revised 7/14/83 R. C. Potter

[ } M M M M M

R. C. Potter NSUSTON CONTROL ROOM DESIGN REVIE"] EVALUATOR LIGHTING OPERATOR TASKIDENTIFICATION AND ANALYSIS

-& SIGNATURg DATE -

--- -- POWER CO. I3 37 Startup From Cold Shutdown (Reactor Coolant IIeatup) PAGE poppggJ)F LIST OF TASKS FOR EVENT: REF TASK /5TEP TASK SSJECTIVE DESCAIFt195 PERFemaIED as051 TORES PANEL meassEn REFERENCE LIST EGuire8ENT REQUIAEB Te (Lisila SEeUENCEI BY sy NOS. C00dPLETE TASK 9.1.6 Bring recctor critical 243 SRO SD .

9.1.7 Monitor count rate, criticality must occur at 500 CPM 244 SRO SD 9.1.8 Withdraw rods to criticality 245 LRO 2 SRO SD 9.1.9 Monitor count rate

( lDPM) 246 LRO 2 SRO SD 9.1.10 hlonitor control rod bank overlap 247 LRO 2 SRO SD 9.2.1 Announce criticality 248 LRO 2 SRO -

9.3 Increase powe-/ stabilize 9.3.1 Verify source range-intermediate range overlap 249 LRO 2 Silo SD 9.3.2 Verify P-6 permissive when intermediate ranges are 1 x 10-10 amp 250 LRO 2 SRO SB 9.3.3 Block the " Source Range liigh Voltage" on N-31 and N-32 with pushbutton 251 LRO 2 SRO SD l

89.3.4 Select a power range channel for N-45 252 LRO 2 SRO SB

  • deleted 3279W/0098W Revised 7/14/83 R. C. Potter E

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HOUST0ft CONTROL ROOM DESIGN REVIEW EVALUATOR R . C. Potter i . LIGHTING OPERATOR TASK IDENTIFICATION AND ANALY$l$

,& SIGNATURE DATE 80-s-82 N"*E POWER CO.

PAGE I5 0F 37 LIST OF TASK 3 FOR EVENT: Startua From Cold Shutdown (Reactor Coolant lleatup) REF PO P3-ZG-1 TASE/5TEP TASE SSJECTIVE DESCRIPTION PERF OR ABE 0 000NITORES PANEL NutesER ILIET le SEBUENCE) REFERENCE By LIST EQUIPRIENT RE0VIAES TS sy NO S. CotePLETE TASK 11.1 Open MSIV valves

  • 11.1.1 Monitor main steam press when P_ 50 psig, 262 LRO 2 SRO 6 13 PI-514,15,16, P -524, 25, 26 PI-534, 5, 6, PI-5(44, 5, 6 11.1.2 Open the MSIV, loop A 263 LRO 2 SRO 6C FSV-7414 11.1.3 Test / record closure time 264 LRO 2 SRO GC FSV-7414 11.1.4 R,sopen Loop A MSIV 265 LRO 2 SitO 6C FSV-7414 11.1.5 Opea the MSIV Loop B 266 LRO 2 SRO GC FSV-7424 11.1.6 Test /recoro closure time on Loop B 267 LRO 2 SRO GC FSV-7424 11.1.7 lleopen Loop 11 MSIV 268 LRO 2 SILO GC FSV-7424 11.1.8 Open the MSIV, Loop C 269 LRO 2 SRO 6C FSV-7434 l

11.1.9 Test / record closure time on Loop C 270 LilO 2 SRO GC FSV-7434 11.l*.10 iteopen Loop C MSly 271 LitO 2 Sito UC FSV-7434 l 11.1.11 Open the MSIV, Loop D 272 LRO 2 SRO GC FSV-7444 1 1.1. I 's Test / record closure time on Loop D 273 LRO 2 SRO GC FSV-7444

.I1.1.1; lleopea Loop D MSIV 274 LRO 2 SitO 6C FSV-7444 3279W/0098W llevised 7/14/83 11. C. Potter

R HOUSTON CON 1 ROL ROOM DESIGN FIEVIE"J EVALUATOR it . C. Potter LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSf3 SIGNATURE

~~. & 10-5-82

  1. " DATE f 39 POWER CO. 16 37 PAGE 0F LIST OF TASKS FOR EVENT: Startuo From Cold Shutdown (lleactor Coolant lleatup) REF PO P3-ZG-1 TAsa/ step TAsat SSJECTlWE DESCarilem PE RFORI8ES SIONITORES PANEL REFERENCE List ESUIPG4ENT REGUIRES TS muassEn ILIsT se steUEhCEI SY SY N0s. C048FLETE Tesa 11.2 Close MSIV bypass valves 11.2.1 Close MSIV bypass valve Loop A 275 LRO 2 SRO 6C FV-7412 ,

l 11.2.2 Close MSIV bypass valve LRO 2 SRO 6C FV-7422 14op B 276 11.2.3 Close MSIV bypass valve Loop C 277 LRO 2 SRO GC FV-7432 11.2.4 Close MSIV bypass valve Loop D 278 LRO 2 SRO 6C FV-7442 11.3.1 Open main steam supply to gland seal GS-007 PI-0050 279 ARO SRO Local GS-007 11.4.1 Close aux. steam supply to PI-0010

( turb. gland system AS-008 PI-0050 280 ARO SRO Local AS-008 11.5 Shift turb. aux steam loads 11.5.1 Open main steam to aux, steam PI-0010 281 ARO SitO Local MS-186, MS-304 l l.fi.2 Close aux. boiler supply to turb. loads 282 ARO SRO Local AS-128 12.1.1 Start one cond. pump (Sec Task No. 5.1) and condenser (See Task No. 5.2) 283 l

l l

l 3279W/0098W Revised 7/14/83 11. C. Potter Q O h h M M M W-. .

NOUSTON CONTROL ROOM DESIGN REVIEW EVALUAT0ly. C. Potter LIGHTING OPERATOR TASKIDENTIFICATION AND ANALYSl3

& SIGNATURE

--i 2 00. 0 ATE I0-5-82 PAGE 17 0F 37 LIST OF TASKS FOR EVENT: Startua From Cold Shutdown (lleactor Coolant lleatup) REF PO P3-ZG-1 TASE/ STEP TASE SSJECTIVE SESCAr! ION f

PEAfSAISED RIONITORED FANEL mUsseER IL88T IN SEGUENCE) EFERENCE LIST EOUIP90ENT REGUIRED TS BY av NOS. ConsPLETE TdSK 13.1.1 Verify steam dump control is in

  • in steam press. mode con-trolling header press at 1183 psig 284 LRO 2 SRO 7D ,

13.2 Start one steam generator feedpump 13.2.1 Verify feedpump sealwater established 285 ARO SRO Local 13.2.2 Verify the selected feedpump disch. valve-Closed PI-0061 286 LRO 2 SRO 6D FW-061, FW-072, or FW-II9 13.2.3 Open the Selected feedpump PI-0061 recire, valve PI-0022 287 LRO '. SRO GD FV-7114, FV-7109, or FV-7104

. 13.2.4 Depress " Latch" button for selected feedpump 288 LRO 2 SRO 6D 13.2.5 Verify turbine in

" Latched" mode 289 LRO 2 SRO GD 13.2.6 Trip the turbine (depress

" Trip" button) 290 LRO 2 SitO GD 13.2.7 After verifyisy trip operation l relatch feedpump turbine 291 LilO 2 SRO GD l 13.2.8 Open low press. stop valve PI-0050 292 L110 2 SitO 6D 13.2.9 Open high press. stop valve PI-0050 293 LRO 2 SRO GD 3279W/0098W llevised 7/14/83 11. C. Potter

MOUSTON CONTROL ROOM DESIGN CEVIEW EVALUATOR 11. C. Potter LIGHTING OPERATOR TASKIDENTIFICATION AND ANALYSi$ SIGNATURE I DATE 10-5-82 p% jib ER CO. N 37 PAGE OF LIST OF TASKS FOR EVENT: Startun From Cold Shutdown (Reactor Coolant lleatup) REF PO P3-7.G-1 TASE/ STEP TASK SSJECTivE DESCRIFT195 PERFenesED ge0NITSRED PANEL LIST EeutralENT REeulAES Te REFERENCE muensEn Ittsila stauf mCO SY aT N05. CetePLETE TASE 13.2.111 Verify turning gear has stopped 294 ARO SRO Local Cautlor: Move thru 2500 llPM critical speed rapidly ,

l 13.2.11 Depress "lacrease Speed" button 295 LRO 2 SRO 6D 1 1

I 13.2.12 Monitor turbine IIPM for slow speed increase 296 LitO 2 SRO GD 13.2.12 Monitor for vibration or eccentricity, trip if req'd 297 ARO SRO Local 13.2.14 At 3300 ftPM speed control shifts from " Speed setter control" to " Steam Generator Control", push " Increase Speed" button until button is lit 298 LRO 2 SitO GD 13.2.1 f Monitor feedpump lube oil temps (140-160*F) 299 ARO SRO Local l 13, *. l t Verify master speed controller in manual 300 LRO 2 SRO GD SK-05590 l

l 13.2.11 Place feedpump speed controller in auto 301 LitO 2 SitO GD SK-0559 A 13.2.11 Place feedpump recire. valve in auto 302 LitO 2 SitO GD FV-7104 l

l 3279W/0098W Revised 7/14/83 11. C. Potter f l_ E Um m m M _h

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mW W W W W W W \ Wl F HOUSTON CONTROL COOM DESIGN REVIEW EVALUATOR R. . Potter.

LIGHTING OPERATOR TASK IDENTIFICATION AND ANALY$l$ SIGNATURE

- ,., & 10-5-82 DATE ME POWER CO. 23 Startup From Cold Shutdown (Reactor Coolant lleatup)

PAGE 0F 37 PO P3-ZG-1 TASK /5TEP TASK SSJECTIVE DESCRIPTION PERFORetED 800NITORED PANEL LIST EQUIPtsENT REGutRED TO muassEn tuST BN SEGUENCEI REFERENCE BY BY 180 5. COAAPLETE TA5K 14.1.40 Close aux. feedwater header *

. cross conn. valve 343 LRO 2 3RO GD A F-258 (F'v-7517) 14.1.41 Close aux. feedwater header ,

cross conn. valve 344 LRO 2 SRO GD AF-259 (FV-7516) 14.1.42 Close aux, feedwater header valve 345 LRO 2 SRO tid A F-260 (FV-7515) 13.1.43 Close aux. feedwater header valve 346 LRO 2 3RO GD AF-261 (FV-7518) 814.1.44 Open feedwater bypass valve, Loop A 347 LRO 2 SRO 3D FV-7129A j *14.1.45 Flace valve in auto 348 LRO 2 3RO BD FV-7129A

) loop D 353 LRO 2 iRO 3D FV-7126A

  • 14.1.51 Place valve in auto 354 LRO 2 3RO iD FV-7126A
  • step deleted due to design change I

3279W/0098W Revised 7/14/83 R. C. Potter E

HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR 11. C. Potter LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSIS SIGNATURE

~ ~., & OATE in_%n9 PAGE 98 0F '17 LIST OF TASKS FOR EVENT: Startun From Cold Shutdown (Reactor Coolant lleatup) REF PO P3-ZG-1 TAllt/5TEP TASK SaJECTIVE DESCRIFilem PE RFORGAE B 800NITORED PANEL LIST EQUIPteENT REQUIRED Te hueseER l LIST le SEGUENCEI RHERENCE BY sY NO S. CotePLETE TASK

  • 14.1.5 ! Place feedwater bypass valve in auto, Loop A 355 LRO 2 SitO 6D FV-7129 1

in auto, Loop B 356 LRO 2 SRO 6D F V-7128

  • l4.1.5 i Place feedwater bypass valve in auto, Loop D 358 LRO 2 SRO 6D. FV-7126 15.1 Prepare to roll turbine 15.1.1 Verify main generator 112 press. in normal range 359 LRO 2 SRO 7B PI-6059

. 15.1.2 Start stator water cooling systen 360 Allo SitO Local 15.1.3 Request permission from System Load Dispatcher to open main generator breakers 361 LRO 2 SRO -

15.1.4 Open main generator breaker Y510 362 LRO 2 SRO 7C 15.1.5 Open main generator breaker YS20 363 LRO 2 SitO 7C 15.1.6 Close main generator disconnects 364 ARO SRO Local

  • step deleted due to design chant e E

3279W/0098W Ilevised 7/14/83 11. C. Potter R C M M E M E . M_E

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f HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR l g..&

LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSIS SIGNATURE DATE 10-5-82

'" " POWER CO. 26 37 PAGE 0F LIST OF TASKS FOR EVENT: Startup From Cold Shutdown (Reactor Coolant lleatup) PO P3-ZG-1 REF TASM/ STEP TASE OSMCTIVE DESCRlrileN PERFORaK D RIONITOREO PANEL LIST EGulpteENT REQUIRE 0 TO muassER ILIST IN SEGUENCE) REFERENCE i BY SY NO S. ConerLETE TASE l l

15.2.5 Verify " Reheat Stop" and

" Intercept" valves open 374 LRO 2 SRO 7D 15.2.6 Verify the turbine throttle and governor valves closed 375 LRO 2 SRO 7D 15.2.7 Push " valve Position Limit" button until 100% reached 376 LRO 2 SRO 7D 15.2.8 Push "l'urbine Trip" button 377 LRO 2 SitO 7D 15.2.9 Verify all turbine valves close 378 LRO 2 SRO 7D 15.2.10 lleduce " Valve Position Limit" to 0% 379 LRO 2 SRO 7D 15.2.11 llelatch/ verify turbine valve position 380 LRO 2 SitO 70 l

15.2.12 Raise " Valve Position Limit" to 100% 381 LRO 2 SRO 7D 15.2.[3 Set acceleration thumb-wheel to 100 RPM / min 382 LRO 2 SRO 7D 15.2.14 Push " Increase lieference" button until 520 RPM 383 LRO 2 SRO 7D 15.2.15 increase reactor power

, to 6% (withdraw rods) 384 LRO 2 Silo SD E

3279W/0098W _

llevised 7/14/83 R. C. Potter O R E M E E E h_

HOUSTON CONTROL ROOM DESIGN REVIEW EVALUATOR R. C. Potter LIGHTING OPERATOR TASK IDENTIFICATION AND ANALYSIS '

SIGNATURE p%j7c"} & OATE

- --- POWER CO. in_5 99 PAGE 27 0F  ??

LIST OF TASKS FOR EVENT: startup Frem ceM heanwn inaerne enniant staatuni PO P3-ZG-1 HEF

, TA5st/5TEP TASK OBJECTIVE DESCRIPTION

' PERFORetE0 IAONITOREO PANEL Nut 08ER ILIST IN SEQUENCE) REFERENCE LIST EQUIPteENT REQUIRE 0 TO SY BY NOS. C0AerLETE TASK 15.2.16 AS RCS temp. increases or j steam dumps open, push 385 LitO 2 SitO 7C l "Go" button LRO 2 SitO 70 l

15.2.17 Monitor steam generator water level 38S LRO 2 SRO Gil l

l 15.2.18 At speed =520 rpm verify supervisory instruments are 387 LRO 2 SRO 7tl within limits

15.2.19 Verify cooling water is cut-in to generator 112 and turoine tube coolers 388 ARO SRO Local 15.2.20 Increase reference setpoint to 1700 rpm by pushing "lacrease Reference" button 389 LRO 2 SRO 7D 15.2.21 Push "Go" button 390 LRO 2 SitO 7D 15.2.22 Verify turb. vibration begins recording above 600 rpm 391 LRO 2 SRO 70 15.2.23 At 1700 rpm transfer control by pushing "TV-GV Transfer" button 392 LRO 2 SRO 70 l

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. Itevised 7/14/83 R. C. Potter

. C. Potter. j N00STON CONTRHL ROOM DESIGN REVIEW EVALUATOR LIGHTING OPERATORTASK10ENTIFICAT10] AND ANALYSi$ SIGNATURE 10-5-82 g&


POWER CO.

DATE 28 37 tartup From Cold Shutdown (Reactor Coolant Ileatup) PO P3-ZG-1 LIST OF TASKS FOR EVENT: RE TASK /5TEP TASE SSJECTIVE DEscherfl0E PERFORetED bt0NITORES PANEL LIST EQUIPteENT REGulRED TO REFERENCE NOS. COAAPLETE TASK asutASER (LIST 95 SEQUENCE) BY SY 15.2.24 Monitor transfer complete, *

" Governor Valve Control" is lit 393 LRO 2 3RO 7 11 Caution: After opening FW .

isolation bypass valve, if steam gen. press. decreases by 50 psig, close bypass valve 15.3 Open feedwater isolation bypass valves 15.3.1 Maintain steady steam flow for 5 min. then 394 LRO 2 iRO iD FI-7104, 9,14 15.3.2 Open FW isolation bypass valve 395 LRO 2 3RO iC FV-7148 15.3.3 Place valve control switch in auto 396 LRO 2 iRO iC 15.3.4 Open FW isolation bypass valve 397 LRO 2 sRO iC FV-7147 15.3.5 Place valve control switch in auto 398 LRO 2 sRO iC 15.3.d Open FW isolation bypass valve 399 LRO 2 iRO iC FV-7146 15.3.7 Place valve control switch in auto 400 LRO 2 sRO iC 15.3.8 Open FW isolation bypass valve 401 LRO 2 sRO iC FV-7145 3279W/0098W Revised 7/14/83 R. C. Potter R R_ m a e a m W M