ML20080S656

Rev 0 to Procedure 2.2.11/090983, Detailed Control Room Design Review Program Plan

ML20080S656
Person / Time
Site:	Pilgrim
Issue date:	10/31/1983
From:	BOSTON EDISON CO.
To:
Shared Package
ML20080S651	List: ML20080S649 ML20080S656
References
RTR-NUREG-0737, RTR-NUREG-737 2.2.11-090983, 2.2.11-90983, GL-82-33, NUDOCS 8310180438
Download: ML20080S656 (100)

Text

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D3 tailed Control Room Design Review Program Plan 1

Pilgrim Station

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REVISION LOG Revision Pages

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1 2.2.I1/090983

,BECO CODE //1000A

DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN TABLE OF CONTENTS Section Title Page

]ABLE OF CONTENTS i LIST OF TABLES iii LIST OF FIGURES IV LIST OF APPENDICES v ACRONYMS AND ABBREVIATIONS vi

1.0 INTRODUCTION

1-1 1.1

GENERAL COMMENT

S 1-1.2 OBJECTIVES 1-3 1.3 PLANT DESCRIPTION 1-4 1.4 DEFINITION OF CONTROL ROOM 1-4 1.5 CONTROL ROOM STATUS AND MILESTONES 1-5 2.0 CONTROL ROOM DESIGN REVIEW PLAN 2-1 2.1

GENERAL COMMENT

S 2-1 2.2 PLANN!NG 2-2 2.3 REVIEW 2-4 2.3.1 METHODOLOGY 2-4 2.3.1.1 CRITERIA 2-4 2.3.1.2 OPERATING EXPERIENCE REVIEW 2-6 2.3.1.3 SYSTEM FUNCTION AND TASK ANALYSIS 2-9 2.3.1.4 CONTROL ROOM INVENTORY 2-10 2.3.1.5 CONTROL ROOM SURVEY 2-11 2.3.1.6 VERIFICATION OF CONTROL ROOM FUNCTION 2-12 2.3.1.7 VALIDATION OF CONTROL ROOM FUNCTION 2-12 2.2.11/090983 BECO CODE #1000A i

Section Title Page 3.0 MANAGEMENT AND STAFFING 3-1 3.1 DETAILED CONTROL ROOM DESIGN REVIEW 3-1 MANAGEMENT PROCEDURE 3.2 INTEGRATION OF DCRDR WITH OTHER HUMAN 3-1 FACTORS PROJECTS 3.3 DCRDR TEAM STRUCTURE AND PERSONNEL 3-1 4.0 DCRDR ASSESSMENT AND IMPLEMENTATION 4-1 5.0 DOCUMENTATION AND DOCUMENT CONTROL 5-1 5.1 DOCUMENTATION USED TO sui 3 PORT THE DCRDR 5-1 5.2 DOCUMENTATION GENERATED BY THE DCRDR 5-1 PROCESS 5.3 DOCUMENTATION SYSTEM AND CONTROL 5-5 6.0

SUMMARY

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LIST OF TABLES Table Title P_ age 2-1 QUESTIONNAIRE AND INTERVIEW SHEET 2-13 REFERENCE TOPICS .

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i LIST OF FIGURES Figures Title Page 1-1 PELATIONSHIP OF NUREG-0660 TASK ACTION ITEMS 1-9 TO BE ADDRESSED 1-2 BOSTON EDISON COMPANY - PILGRIM NUCLEAR POWER l-10 STATION 1-3 LAYOUT OF CENTRAL CONTROL ROOM l-11 2-1 OVERVIEW OF THE DCRDR PROCESS 2-16 2-2 DCRDR REVIEW TEAMS 2-17 2-3 FORMULATION OF THE DCRDR TASK STRUCTURE 2-18 2-4 CONTROL ROOM DESIGN REVIEW SYSTEM BREAKDOWN 2-19 2-5 CONTROL ROOM DESIGN REVIEW EMERGENCY EVENT 2-20 SEQUENCES 2-6 EXAMPLE OF A FUNCTIONAL (DECISION-ACTION) FLOW 2-21 DIAGRAM 2-7 CONTROL ROOM DESIGN REVIEW FUNCTIONAL 2-22 SEQUENCE PER SELECTED OPERATIONAL EVENT 2-8 CONTROL ROOM DESIGN REVIEW FUNCTIONAL SEQUENCE 2-23 PER SELECTED OPERATIONAL EVENT 2-9 CONTROL ROOM DESIGN REVIEW OPERATOR TASK 2-24 IDENTIFICATION AND ANALYSIS 2-10 CONTROL ROOM DESIGN REVIEW INSTRUMENT DETAILS 2-25 2-11 TYPICAL SPATIAL SEQUENCE DIAGRAM 2-26 2-12 EXAMPLE OF A TRAFFIC LINK DIAGRAM 2-27 4-1 ASSESSMENT AND IMPLEMENTATION METHODOLOGY 4-3 4-2 ASSESSMENT FACTOR CRITERIA 4-4 4-3 SELECTION OF DESIGN IMPROVEMENTS [ 4-5 2.2.11/090983 BECO CODE #1000A iv

LIST OF APPENDICES APPENDIX A - QUALIFICATION OF MANAGEMENT REVIEW TEAM AND DESIGN REVIEW TEAM MEMBERS APPENDIX B - TYPICAL REVIEW FORMS

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0 2.2.11/090983 BECO CODE #1000A v

ACRONYMS AND ABBREVIATIONS LISTED ALPHABETICALLY BY ACRONYMS A Area AC Alternating Current ADS Automatic Depressuriza. tion System AO AuxRhry Operator AOG Augmented Off-Gas ANN Annunciator ANALOG Input Cabinet APRM Average Power Range Monitor ASSOC Associated ASST Assistant ATWS Anticipated Transient Without Scram AUX Auxiliary BOP Balance-of-Plant BWROG Boiling Water Reactor Owners Group CAT Category CCI Containment Cooling & Isolation CM Color Monitor COND Condenser, Condensate CONT ,. Control CPC Central Processor Cabinet CR Control Room CRD Control Ecd Drive CRP Control Rod Position CRT Cathode Ray Tube CSCS Core Standby Cooling Systems CSS Core Spray System .

CWS Circulating Water System DC Direct Current DCRDR Detailed Control Room Design Review DI/OC Digital Ir. gut / Output Cabinet 2.2.11/090983 BECO CODE #1000A vi

DRT Design Review Team DWS Drywell Sump ECCS Emergency Core Cooling System ES Electrical System EES Emergency Event Sequences ,

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

EST Estimate (d)

EXPER Experience FSAR Final Safety Analysis Report FW Feedwater FW&R Feedwater and Recirculation HE Human Engineering HEO Human Engineering Observation HED Human Engineering Discrepancy HPCIS High Pressure Coolant Injection System HVACS Heating, Ventilation and Air Conditioning System I&C Instruments and Controls I/O Input / Output INPO Institute of Nuclear Power Operators INSTR Instrument; Instrumentation IRM Intermediate Range Monitor 3P 3et Pump LDR Leader LOCA Loss of Coolant Accident LPCIS Low Pressure Coolant Injection System LPRM Local Power Range Monitor L10GS Low Temperature Off-Gas System MG Motor Generator MCP Main Control Panel M/M Man / Machine MdN Monitor MSIV Mainsteam Isolation Valve i

2.2.I1/090983 BECO CODE #1000A vil

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MT Management Team MW(e) Megawatts (electric)

NMS Neutron Monitoring System NOS Numbers NRC Nuclear Regulatory Commission ,

OC Operator Console i

OER Opersting Experience Review OSC Operational Support Center PCRVICS Primary Containment cnd Reactor Vessel Isolation Control 4

System RM Radiation Monitor i PROC Process PS Power Supply PSAR Preliminary Safety Analysis Report RAS Recirculation Actuation Signal RWCU Reactor Water Clean-Up RBCC'.7 Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCB Reactor Containment Building RCICS Reactor Core Isolatien Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System RECIRC Recirculating RPV Reactor Pressure Vesel REQ'D Required RNMC Reactor Neutron Mapping control RO Reactor Operator RRP Reactor Recirculation Pump RRS Reactor Recirculation System RWST Refueling Water Storage Tank ,

RX Reector '

RWCUS Reactor Water Clean-Up System 2.2.I1/090983 BECO CODE #1000A viii

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SGTS Standby Gas Treatment System SIS Safety Injection System SLCS Standby Liquid Control System SOE Selected Operational Event (s)

SP Suppression Pool SPDS Safety Parameter Display System SRM Stat tup Range Monitor SRO Seelot Reactor Operator SRV Safety / Relief Valve SS. Subsystem ST Steam STAT System Task Analysis Team SUPVR Supervisor SW Switch SYS System TEMP Temperature TBS Tur~u tne Bypass System TG Turbine Generator TMt Three-Mile Island TP Tape Punch TR Tape Reader TS Turbine Supervisory T&M Test and Monitoring TSC Technical Support Center l

l 4-2.2.11/090983 l BECO CODE #1000A ix 1

ACRONYMS AND ABBREVIATIONS LISTED ALPHABETICALLY BY DEFINITION Area A Alternating Current AC Automatic Depressurization System ADS Auxiliary Operator AO Augmented Off-Gas AOG Annunciator ANN Input Cabinet ANALOG Average Power Range Monitor APRM Associated ASSOC Assistant ASST Anticipated Trip without Scram ATWS Auxiliary AUX Balance-of-Plant BOP Category CAT Containment Cooling & Isolation CCI Color Monitor CM Condenser, Condensate COND Control CONT Central Processor Cabinet CPC 1

Centrol Room CR Control Rod Drive CRD Control Rod Position CRP Cathode Ray Tube CRT Core Standby Cooling Systems CSCS Core Spray System CSS Circulating Water System CWS Direct Current DC' Detailed Control Room Design Review DCRDR Digital Input / Output Cabinet DI/OC Drywell Sump DWS Emergency Core Cooling System ECCS 2.2.11/090983 BECO CODE #1000A x

Electrical System ES Emergency Event Sequences EES Emergency Operating Facility EOF Electric Power Research Institute EPRI Engineered Safety Feature (s) .ESF Estimate (d) EST Experience EXPER Final Safety Analysis Report FSAR Feedwater FW Feedwater md Recirculation FW&R Human Engineering HE Human Engineering Observation HEO Human Engineering Discrepancy HED High Pressure Coolant Ir.jection System HPCIS Heating, Ventilation and Air Conditioning System HVACS Instruments and Controls I&C Input / Output I/O Institute of Nuclear Power Operators INPO Instrument; Instrumentation INSTR Intermediate Range Monitor IRM 3et Pump JP Leader, LDR Loss of Coolant Accident LOCA Low Pressure Coolant Injection System LPCIS Local Power Range Monitor LPRM Low Temperature Off Gas System LTOGS Motor Generator MG Main Control Panel . MCP Man / Machine M/M Monitor MON Mainstream Isolation Valve MSIV Maragement Team MT Megawatts (electric) MW(e)

Neutron Monitoring System NMS 2.2.11/090983 BECO CODE #1000A xi

Numbers NOS Nuclear Regulatory Commission NRC Operator Console OC Operating Experience Review OER Operational Support Center .OSC Primary Containment and Reactor Vessel Isolation Control PCRVIC System S Radiation Monitor RM Process . PROC Project Review Team PRT Power Supply PS Preibrinary Safety Analysis Report PSAR Recirculation Actuation Signal RAS Reactor Water Clean-Up RWCU

-Reactor Building Closed Cooling Water System RBCCW Rod Blod Monitor RBM Reactor Containment Building RCB Reactor Core Isolation Cooling System RCICS Residual Heat Removal System RHRS Reactor Protection System RPS Recirculating RECIRC Reactor Pressure Vessel RPV Required REQ'D Reactor Neutron Mapping control RNMC i Reactor Operator RO Reactor Recirculation Pump RRP Reactor Recirculation System RRS Refueling Wate.- Storage Tank RWST Reactor RX Reactor Water Clean-Up System RWQUS

! Standby Gas Treatment System SGTS Safety injection System SIS Standby Liquid Control System SLCS Selected Operational Event (s) SOE 2.2.11/090983 BECO CODE #1000A -

xii

Suppression Pool SP Safety Parameter Display System SPDS 3tartup Range Monitor SRM Senior Reactor Operator SRO Safety / Relief Valve .SRV Subsystem SS Steam ST Systs Task Analysis Team STAT Supervisor SUPVR Switch - SW System SYS Temperature TEMP Turbine Bypass System TBS Turbine Generator TG Three-Mile Island TMI Tape Punch TP Tape Reader TR ,

Turbine Supervisory TS Test and Monitoring T&M Technical Support Center TSC i

2.2.11/090983 BECO CODE #1000A xiii

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1.0 INTRODUCTION

1.1

GENERAL COMMENT

S This report describes the Boston Edison Company plan to perform a detailed c:ntrol room design review (DCRDR) of its Pilgrim Nuclear Power Station Unit No. 1.

The purpose of this DCRUR is to identify and implement control room design improvements that offer high probability for meeting plant safety and availability objectives.

This is part of an integrated plan covering TMI-related actions referenced in the TMI-2 Action Plan, NUREG-0660 and will consider the relationship of the DCRDR with NUREG-0737, Supplement 1: " Requirements for Emergency Response Capability (Generic Letter No. 82-33)" dated 12/17/82 and "NRC staff review of the BWR Owners Group (BWROG) Centrol Room Program,"

(Generic Letter 83-18) dated 4/19/83 including:

o Verification of the SPDS parameter selection, data display and function.

o Design control room modificatioris that correct conditions adverse to safety (reduce significant contributions to risk), and add instrumentation necessary to implement Regulatory Guide 1.97.

o The use of symptom-based emergency operating procedures.

o Training to enhance coping with emergencies. .

o Design considerations for the Technical Support Center, Emergency Operations Facilities and Operations Support Center.

2.2.11/090983 BBCO Code #1000A 1-i

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y Figure 1-1 is a block diagram showing the relationship of the NUREG-0660 Task Action items Boston Edison Company is addressing.

This plan was prepared to be consistent with and responsive to the guidelines provided in NUREG-0700 and NUREG-0801 as directly applicable to the design

. and status of the Pilgrbn Nuclear Power Station Unit No.1. and good human factors principles.

The Pilgrim Station has already received ar. intense review by the BWR Owners Group Control Room Improvewnt Committee with an associate J review by Dr.

T. Sheridan and Dr. D. Lanning, human factors consultants of the MIT Group.

The results of this review will be used in this program.

This report is in compliance with Generic Letter 83-15 which notes:

"Since the BWROG survey program addresses only the planning and review phases of DCRDR, you are expected to complete the following tasks:

"a. Submit an individual program plan to the NRC referencing the BWROG Generic Program Plan. The plant-specific submittal should:

i. Document the qualifications of survey team members, and number and extent of plant personnel participation.

ii. Identify portions of the plant's DCRDR not performed in accordance with the methodology specified in the BWROG Program Plan.

iii. Discuss your program for prioritization of HEDs, reporting of DCRDR results, and implementation of control room enhancements.

"b. Complete the BWROG control room survey Checklist Supplement.

2.2.I1/090983 BECO Code #1000A 1-2

l "c. Prioritize HEDs, determine corrective actions, develop an implementation schedme, and report the results of the DCRDR to the NRC.

"d, Repeat portions of the task analysis using updated plant specific emergency operating procedures to account for differences in the new procedures.

"a. Update operating experience review."

The Boston Edison Company is cournitted to this program for identifying and implementing changes to t!ie plant man / machine interfaces that can reduce the probability of operator error thus resulting in an overall improvement in plant safety and reliability. To this end, Bostca Edison Company has commited the necessary resources, including knowledgeable management, technical personnel, and technical specialists from its human factors consultant, Torrey Pines Technology, to effect the program defined herein.

1.2 OBJECTIVES Boston Edison Company intends to complete this review in a timely and cost-effective manner to:

o Determine whether the control room provides the system status information, control capabilities, feedback, and analytical aids necessary for control room operators to accomplish their fu.etions in an effective, safe and reliable manner.

o Identify characteristics of the existing control room instrumentation, controls, other equipment, and physical arrangements that mr." impact optimum operator performance.

o Analyze and evaluate potential problems that could arise from this review.

, 2.2.11/090983 BECO Code #1000A 1-3

c Define and put into effect a plan of action that applies additioral human factors principles to enhance operator effectiveness. Particular emphasis will be placed on improvements affecting control room design and operator performance under abnormal or emergency conditions.

o Integrate the DCRDR review with other areas of human factors inquiries identified in the NRC Task Action Plan. t 1.3 PLANT DESCRIPTION The Pilgrim Nuclear Power Station is tocated on the western shore of Cape Cod Bay in the Tove of Plyniouth, Plymouth County, Massachusetts. It is 38 miles Southeast of Boston, Massachusetts. Bechtel Corporation was the architect / engineer and constructor of the station. The station consists of one 670 MW(e) (nominal) unit. It is powered by a single cycle, forced circulation General Electric Boiling Water Reactor producing steam for direct use in the General Electric 1,800 RPM tandem compound, four flow, non-reheat turbine gtnerator. Comnercial operation of the unit began in December 1972. A photograph of the plant is shown in Figure 1-2.

1.4 DEFINITION OF CONTROL ROOM i

The control room is defined as the following consoles, bench boards and panels including the SPDS displays which are used by the operators for normal and emergency plant operations:

4 2.2.I1/090983 BECO Code #1000A 1-4

f FRONT PANELS

- 903 Reactor & Containment Cooling & Isolation Bench Tward 904 Reactor Water Clean-up & Recirculation Bench Board

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905 Reactor Control Bench Board C-2 Turbine Bench Board 4

C-1 Feedwater & Condensate Bench Board C-3 345 K.V., Generator A'niliary Power Bench Board C-170 Post Accident Monitoring Panel, Train A C-171 Post Accident Monitoring Panel, Train B CP-600 H2 Recombiner Panel BACK PANELS 902 Area & Process Radiation Recorder Vertical Board 910 Process Radiation Monitoring Vertical Board 911 Area Radiation Monitoring Cabinet C-4 Feedwater Heaters Control Vertical Board C-7 Containment Ventilation, holation & Gas Treatment Vertical Board The DCRDR will extend to other Man / Machine interfaces identified as a result o' the analysis of selected events during the System Function and Task Analysis Activity. Figure 1-3 illustrates the layout in the central control room.

^

1.5 CONTROL ROOM STATUS AND PLANNING The Pilgrim Station control room has been in operation since December 1972 and the obvious human engineering discrepancy have been found and corrected.

However, we are willing to implement this control room design review to assure that Boston Edison Company has provided a control room whose design and environment adeqt.nely supports the operators' abilities to cope with normal operations and degraded conditions.

2.2.I1/090983 BECO Code #1000A 1-5

We have participated actively on the BWROG control room design review committee. A BWROG control room survey has been performed at Pilgrim Station and will serve as the basis of our program. The following improvements are planned for the control room.

o IMPLEMENTATION OF REGULATORY GUIDE 1.97, RP!. 2 In order to provide a comprehensive implementation schedule, Boston Edison Company expects to approach the Pilgrim Nuclear Power Station / Regulatory Guide 1.97 analysis in a two phase manner. The first phase would be to compare the Pilgrim Station design base to Regulatory Guide 1.97 criteria, and if modifications are required, provide an implementation schedule that will be consistent with Boston Edison Comoany proposed Long Term Program.

Boston Edison Con.pany intends to do an item-by-item comparison between all the requirements of Regulatory Guide 1.97, Rev. 2 and the applicable systems and components of Pilgrim Station. Any deviations found will be systematically evaluated and documented ta determine if the deviation is justifiable due to plant-specific design, original design bases, supportive operational requirements, etc. Any deviations not found to be ju:tifiable will be evaluated tc determine what modifications, if any, are needed to conform to Regulatory Guide 1.97, Rev. 2.

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2 2.2.11/090983 BECO Code #1000A

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I o REPLACEMENT OF EXISTING PLANT COMPUTER Boston Edison Company is planning to replace its existing plant 4 l

computer to improve the present acquisition / distribution of information in order to support effectively the operator and enhance the Emergency Response Facilities. We intend to consider the various guidance documents such as NUREG-0696, Regulatory

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Guide 1.97 (Rev. 2), BWROG Graphic. Display system (GDS) evaluation, and the INPO guidelines for an effective SPDS implementation. We believe the best approach to incorporating the suggested guidance is to base the objective for the SPDS on l operator information requirements and augment the Emergency Operating Procedures. This integrated approach is essential to ensure the final product provides reliable, accurate and more importantly useable information for the control room personnel.

j Our plan involves the :nstallation of a SPDS that is convenient to the control room operator. The system will display the information s

from which the plant safety status can be readily and reliably assessed by control room personnel who are responsible for avoiding degraded conditions. The SPDS display will be designed to incorporate acceptea human factors principles.

o UPGRADED EMERGENCY OPERATING PROCEDURES (EOPs)

Our Emergency i monse Capabilities Program is based on the EOPs developed fro... the BWR Owners Group Emergency Procedure Guidelines (EPGs). We are in the process of preparing plant

, specific symptom based EOPs. These EOPs will be available for 4

l- use for the DCRDR. l l

1 1

2.2.11/090983 BECO Code #1000A

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a CONTROL ROOM SIMULATOR We are planning on purchasing a full-scale simulator to aid in training operators. This simulator will be located in the new training facility now under construction in Chiltonville, Massachusetts.

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t r g BWR SYMPTOM-BASF.D OPERATING AND CHANGES IN OWNERS GROUP EMERGENCY PROCED'JRES REQUIREMENTS FOR

+ GENERIC PROCEDURES NUREG 3799 NUREG 0899 NUREG 0660,l.C.1 (3),l.C.8 AND l.C.9) NUREG 0660,l.A.I & l.A.2 I I I PROGRAM PLAN REPORT 1

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INSTRUMENTATION IO EMERGENCY RESPONSE EMERGENCY ASSESS PLANT FACIL!TY PREPAREDNFSS CONDITION (ACClGENTS)

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2.0 CONTROL ROOM DESIGN REVIEW PLAN 2.1

GENERAL COMMENT

S The DCRDR will be conducted principally as recommended by NUREG-0700, NUREG-0801, and Generic Letters 82-33 and 83-18. It will consider the integration of related project requirements that may affect control room human factors discrepancies. The following related activities and documents will be I

coordinated with the DCRDR:

o Development of emergency operating procedures (reference item I.C l(3), I.C.8, and I.C.9 of NUREG-0660).

o Development of a safety parameter display system (SPDS),

(reference Item I.D.2 of NUREG-0660; also N UREG-0696, Functional Criteria for Emergency Response Facilities).

o Upgrading of emergency support facilities (reference Item III.A.I.2 of NUREG-0660 and NUREG-0696, Functional Criteria for Emergency Response Facilities).

o Development of improved control room instrumentation (referenc e Item I.D.5 of NUREG-0660).

o Changes in requirements for training and staffing (reference Items

!.A.1 and I.A.2 of NUREG-0660).

o Implementation of Regulatcry Guide 1.97, Revision 2.

h o Evaluation criteria for DCRDRs (NUREG-0801). '

2.2.11/090983 BECO CODE #1000A 2-1

o Methodology for evaluation of emergency response facilities (NUREG-0814).

o Human factors acceptance criteria for SPDS (NUREG-0835).

The overview of the DCRDR processes is shown in Figure 2-1 which is a copy cf Exhibit 3-1 of (NUREG-0814). This Program Plan describes the following:

o Planning (Section 2.2) i o Review (Section 2.3) o Management and Staffing (Section 3.0) o Assessment and Implementation (Section 4.0) o Documentation and Document Control (Section 5.0) 2.2 PLANNING The planning phase covers relevant actions completed to date or planned as noted here'n.

Boston Edison Company organized an Executive Team to guide, monitor and implement this program. The Executive Team has made provisions for designated alternates to key positions. The functions of this team correspond to those recommended for management in NUREG-0700. They are to:

o Assure proper relationships and awareness between this projar.t and othe- NUREG-0660 efforts.

o Assignment of key Management and Design Review Team personnel (see Figure 2-2).

9 o Approve detail program plan.

2.2.11/090983 BECO CODE #1000A 2-2

o Provide resources required ,to carry out the program plan.

o Identify and assure that plant operational constraints and project re.quirements are properly coordinated.

o Monitor DCRDR progress, o Review and approve control room improvement recommendations.

o Establish and initiate the control room improvement prcgram.

The Management Team has analyzed NUREG-0700 in relation to this plant ftcility and resources and has defined the program described herein. The major activities are shown in Figure 2-3. The planning activity includes, in addition to the above items, the following:

o Definition of all man / machine interfaces and related activities to be reviewed.

o Definition of objectives, o Definition of management team role.

o Formulation of the task structure for the program (see Figure 2-3) and corresponding personnel assignnient.

o Development of administrative procedures to govern this review.

To facilitate this review, project management authorized the construction of a full scale, realistic mock-up for an extensive review by human factors and systems specialists.

Boston Edison Company has assigned engineering anc operations specialists to the Design Review Team that has the responsibility for the technical scope of the DCRDR.

4 2.2.11/090983 BECO CODE #1000A 2-3

2.3 REVIEW -

The review phase is basically the investigative phase. This effort is organized into specialty task group per Figure 2-3. Specialized personnel are selected as required for each task group from Boston Edison Company and Torrey Pines Technology. If necessary, General Electric will be asked to provide system design criteria. Approximately 15 engineers and key operations persor.nel will participate in the detailed reviews and evaluations of the task g'.ups.

The following types of personnel are included:

o Systems designers and analysts o Human factors consultants o Control board designers o Instrumentation and centrol engineers o Computer and data management engineers o Plant operators o Licensing personnel 2.3.1 Methodology 2.3.1.1 Criteria ,

The Design Review Team will prepare control room design and review criteria which will be included in the Criterin Report. This effort will' stress the human factors considerations and requirements for the control room design.

2.2.11/090983 BECO CODE #1000A 24

4 This document will describe the function of the contrra room and plant systems related to external communications. It will also address one of the najor post-TMI-2 concerns, the systems and human factors features for Annunciator / Computer / Safety Equipment interfaces relative to prioritization, csnsistency, and overall integration. .

The following topics will be included in this document.

A. Introduction B. General C. Control Room Layout and Features D. Main Control Panels Layouts and Features E. Human Engineering Guidelines (BWROG specific adaotations of NUREG-0700, Section 6, and other guidelines not covered in other major topics)

F. Special Guidelines Associated with the Application of Human Factors Engineering to Control Room Design G. References Criteria will be developed considering:

o Those human factors engineering practices that have general industry acceptance and have resulted in proven performance.

2.2.I1/090983 BECO CODE #1000A 2-5

o Pertinent NUREG documents, BWROG documents and Regulatory Guides.

o Established criteria from general industry, EPRI, INPO, government sources, Boston Edison Company conventions, - standards and

> practices.

233.1.2 Operating Experience Review 1

The Operating Experience Review Task Team (OERT) will review pertinent operating experience documents and conduct a survey of control room operations personnel. In addition to typical human factors onerator concerns, the OERT will emphasize systems operability. It is anticipated that valuable input will be developed for use by the other task groups, particularly the System Function and Task Analysis Team (STAT). Specific attention will be placed on those normal plant procedures that experienced operators identify as having the greatest potential for human facurs engir.eering enhancements. This information

will be used in the selection process f +c those events to be analyzed by the STAT.

A special meeting will be held to review the methodology used in the preparation of operating procedures. Sample procedures will be reviewed and comments submitted to the operations department. The OERT will perform the following:

A. Meet with key operations and training personnel to determine pertinent information on training, assigned duties, anticipated work

! scheduling, and the availability of the various classes of operations personnel.

4 B. Prepare questionnaires and interview forms. See Table 2'-1.

2.2.11/090983 BECO CODE #1000A 2-6

s C. Review by Management Review Team.

D. Completion of questionnaires by operations personnel.

E. Evaluate the data ob*ained. -

F. . Interview plant personnel.

G. Evaluate and summarize observations, including human engineering observations (HEOs) with recommended corrections.

Interview sheets and questionnElres will be prepared considering a review of I the results of the BWROG control room survey interviews, the special knowledge the control room operations personnel have concerning potential control room problems and positive features as determined by their experience.

A. Interviews will identify those aspects of the control room l

) equipment layout and general design which are considered by the operators to provide opportunities for improvement relative to their decision making processes.  ;

B. Questions will be focused on those details of the control room environment which are projected to indicate notable success, l

failure, and near-miss situations based on past experiences.

f C. Respondents will be advised that the information obtained will not be used for performance evaluation purposes. Project procedures will assure that comments by operations personnel will remain anonimous.

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D. The following NUREG-0700 topics will be included in this operations personnel review:

1. Workspace layout and environment

2. Panel design

3. Annunciator warning system

4. Communications

5. Prosess computers

6. Corrective and preventive maintenance

7. Procedures

8. Staffing and job design

9. Training E. The respondents will be encouraged to speak openly about problems from their past experience or perceived potential problems and suggested solutions.

F. Other kinds of human factors concerns such as those related to employee programs.

G. Other questionnaires developed by industry and research groups in previous projects. l 2.2.11/090983 BECO CODE #1000A 2-8

H. The interviews will be structured to allow for addithns of material developed during the interview.

I. Table 2-1 covers the general topics that will be considered in develcpment of operations personnel questiomaires.

Data evaluation will be done immediately following completion of the interview period to assure maximum benefit from the interview. The data evaluation rcsults will be forwarded to the Management Review Team for review. Th-rcsults of this work will be evaluated and summarized. A re-review of areas of significant changes may be required.

2.3.1.3 System Function and Task Analysis The System Function and Task Analysis Team will perform a functional review and analysis of the control room complex to determine the adequacy of its design, and documentation to facilitate safe plant operations. This work will be done considering the following:

A. Review pertinent piant documents such as configurations, FSAR, systems descriptions, operating procedures Technical Specifications and Licensee Event Reports.

B. Prepare system / subsystem diagrams required for functional evaluation of control board layout.

C. Prepare tabulation of system breakdown, Figure 2-4, and emergency event sequences, Figure 2-5.

D. Review results of operating experience to help identify- events as candidates for review.

2.2.11/090983 BECO CODE #1000A 2-9

E. Prepare selection criteria. Select events to be analyzed in a series of STAT meetings. Such events are defined as selected operational events (SOE).

F. Perform system function and task analysis for each.SOE considering the following:

4

1. Modify BWROG-produced Emergency Procedure Guidelinea functional (decision-action) flow diagrams as necessary, Figure 2-6.

2. Complete functional sequences tabulations, Figures 2 I, 2-8, in STAT n.eetings.

4

3. Continue the heirarchial review process of identifying tasks associated with each function, Figure 2-9, including equipment e

required.

4. Tabulate details about instrumants tasks and task steps, Figure 2-10, such as required range and initial value.

G. Prepare spatial sequence diagrams similar to that shown in Figure 2-11, and traffic link diagrams similar to Figure 2-12.

H. Evaluate data and summarize observations.

2.3.1.4 Control Room Inventory An inventory of controls, instrumentation, displays, and other equipment on the

. . control room man / machine interfaces will be performed. This inventory will establish a reference data base for comparison with the r'equirements 4

2.2.11/090983 BECO CODE #1000A 2-10 4

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established by operator task analysis. The inventory will include component use nd characteristics, and will scve as a support base for assessment of rcview observations. A plant specific computerized format similar to NUREG-0700, Exhibit 3-6 will be used.

2.3.1.5 Control Room Survey A survey of the full scale mock-up and the Pilgrim Station Control Room will be performed to document compliance with the human factors criteria document. The use of a realistic mock-up will permit completion of the bulk of the checklist items developed. Those items that cannot be checked, such as voice-assisting communication devices, control room noise, illumination, use of protective clothing and other environmental considerations, will be completed using the control room in actual service conditions.

The Control Room Survey Task Team will perform the following tasks:

A. Prepare plant specific checklists for the following:

1. Control room workspace

2. Conununications

3. Annunciator warning system

4. Controls

5. Visual displays

6. Labels and location aids

7. Process computers

8. Panel layouts 9 Control-display integration B. Submit checklists for Management Review Team review. .

C. Finalize checklists.

D. Perform control room survey.

2.2.11/090983 BECO CODE #1000A 2-11 l l

E. Evaluate data, summarize observations.

F. Prepare HEOs with recommended corrections.

2.3.1.6 Verification of Control Room Function A velfication will be made of the availability of instruments and equipment needed to implement each task. Thit verification will be made by comparing the requirements identified by the STAT to the Control Room Inventory list.

A determination of operator-equipment interfaces adequacy for task tccomplishment will be made and the observations will be recorded. Formatted information developed during the inventory and system function task analysis activities will be used.

2.3.1.7 Validation of Control Room Function A validation will be performed as part of the SFTA activity to determine whether the control room operating crew can perform allocated functions within defined procedures. The bulk of this effort will be performed on the mock-up using walk-through/ talk-through techniques. In this effort, identification will be made of the time-dependent SOE and plans will be made for their real time rsviews in the control room if it can be made available. Experience to date indicates that validation can be accomplished on a realistic mock-up.

/

2.2.11/090933 13ECO CODE #1000A 2-12 .

TABLE 2-1 QUESTIONNAIRE AND INTERVIEW SHEET REFERENCE TOPICS The following will be covered is: the interview sheets and questionnaires to determine positive and negative features and suggestions for improvements:

o The role of the operations personnel in emergency situations.

o Those normal functions and tasks that the respondents consider should be included in the system function and task analysis.

o Major concerns and strengths of related plant operations.

o Techniques W maintenance of high vigilance. How boredom will be prevented. How proficiency will be maintained.

o Views of engineering and engineered product necessary for plant operation.

o Overall management policies - how perceived by interviewees.

o Views of projected job assignments (work loading - too much, too little?).

o Views of job satisfaction or dissatisfaction (long-range job objectives).

/

2.2.11/090983 BECO CODE #1000A 2-13

TABLE 2-1 (continued) o Views of personal training received to date - adequate?

Suggestions for improvements, o Views of the control center complex - strengths and weaknesses.

o Views of the control room complex in the general areas noted in NUREG-0700 Appendix C and Section 3.3.2.2 for normal and abnormal situations.

o Discussion of emergencies.

o Discussion to determine special techniques useful in plant control.

o Views of the engineering of the products required for plant operations.

o Views of external elements - NRC and press.

o Views of projected shift staffing.

o Relationship with fellow workers 7 maintenance, and other associates.

o Discussion of main concerns, major strengths or weakrasses, and improvements that are most sought for.

o View of projected workload and difficulties in .perfo ming assignments.

2.2.11/090983 BECO CODE #1000A 2-14

TABLE 2-1 (continued) o Views of projected relationship with other groups that effect overall plant operations.

o Views of vaining.

o. Views of administrative procedures.

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3.0 MANAGEMENT AND STAFFING 3d DETAILED CONTROL ROOM DESIGN REVIEW MANAGEMENT PROCEDURE o The management planning activity is described in Section 2.2.

o The basic crganization and functions are shown in Figure 2-2.

o The Management Review Team will meet throughout ti.e program as required to perform its basic functions. Meetings will be called by the Principal Investigator, and directed by Boston Edison Company.

In addition, it may be necessary to hold special meetings to meet scheduled requirements.

o The DCRDR consultant will be available for these meetings as needed to facilitate completion of meeting agenda items.

o Minutes of all meetings will be taken and recorded.

3,2 INTEGRATION OF DCRDR WITH OTHER HUMAN FACTORS PROJECTS The overall relatinaship of NUREC4660 task action items are shown in Figure 1-1. The human factors aspect of the basic activities shown in Figure 1.1 will be reviewed by the Management Review Team working with the Boston Edison Company licensing group.

3.3 DCRDR TEAM STRUCTURE AND PERSONNEL The basic DCRDR team structure and personnel are defined in Figure 2-2 and 2-3. Resumes of assigned personnel are included in Appendix A and are consistent with the review criteria of NUREG-0801.

2.2.11/090983 BECO CODE #1000A -

3-1

4.0 DCRDR ASSESSMENT AND IMPLEMENTATION 4

All observations identified during the review phase will be processed according to the assessment and implementation methodology presented in-Figures 4-1 and 4-3. The Design Review Team will document these observations and recommendations on Human Engineering Observation forms (HEOs) which are then submitted to the Management Review Team for assessment.

The initial st p by the Management Review Team will be to accept or reject the formatted Information where, in the latter case, they return the HEO to the Design Review Team for further evaluation and resubmittal. Accepted HEOs will be categorized according to the Assessment Factor Criteria (Figure 4.2). The criteria chosen provides for a simple, but effective, relationship between assessment factor and imniementation requirements commensurate with the significance of the observation. This approach greatly reduces the need to consider various levels of safety while still accomplishing the assessment objectives of NUREGs 0700 and 0801. To aid the Management Review Team in selecting the appropriate assessment factor for each finding, a set of statements or questions will be developed to the extent that the affected guideline (s) is inadequate in this respect.

All observations assigned Categories A, B or C will be identified as Human Engineering Discrepancies (HEDs) and will be analyzed for correction (Figure 4-3). Correction of Category D results are optional. The first step in this process will be to Identify those HEDs which can be corrected by enhancement. The remaining HEDs will be analyzed to identify design ,

improvement alternatives and to select solutions. In addition, some HEDs may be - corrected th' rough training. An integral part of this step will be a rs-application of the control room review process as appropriate- to ensure that:

i 1

2.2.11/090983 BECO CODE #1000A .

4-1

i o Other guidelines are not violated.

o Other corrections are not invalidated.

o Any resulting increase in significance of other findings la identified and accommodated.

Solutions which do not bring the discrepancies into full compliance with the guidelines will be identified and justified accordingly.

Use will be made of the following activitics in the Assessment Program.

a) Plant computer replacement, including safety parameter display system b) EOP implementation c) Regulatory Guide 1.97 implementation d) Emergency response facility improvements e) Station requested control room improvements 4

4 2.2.11/090983 BECO CODE #1000A ,

DESIGN REVIEW TEAM r-----+

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HE0 - HUMAN ENGINEERING OBSERVATIONS HEr,~- HUMAN ENGINEERING DISCREPANCY

/

Figure 4-1. Assessment and Implementation Methodology 4-3

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REVIEW PROCESS OBSERVATIONS ASSESSMENT FACTOR CRITERIA ASSESSMENT IMPLEMENTATION CATEGORY FACTOR (RATING)

A SAFETY (1) PRIOR TO OR CONSE0"ENCES OURING NEXT REFUELING (MANDATORY)

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ir ANALYSIS FOR CORRECTION BY ENHANCEMENT

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, NO i r ANALYSIS TO 10ENTIFY OESIGN IMPROVEMENT ALTERNATINES AND SELECT RECOMMENDEO SOLUTION DESIGN lMPLE DENT

• FUNCTION ANALYSIS DOCUMENT 4+______________q

• ALLOCATION 1 MAN I MACHINE o VERIFY

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• SELECTPREFERRED DESIGN ALTERNATIVE l

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• VALIDATE DESIGN---------4 FULLY SCHEDULE NOT - CORRECTED IMPLEMENTATION J i'Y ^  : ASS 7SC EXTENT OF CO3RECTION CUMENT 4 PARTIALLY COCUMENT CORRECTED

,r 1 JUSTIFY AND SCHEDULE  % DOCUMENT DOCUMENT IMPLEMENTATION Figure 4-3. Selection of Design Irnprovements 4-5 l

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5.0 DOCUMENTATION AND DOCUMENT CONTROL 5.1 DOCUMENTATION USED TO SUPPORT THE DCRDR o Bostoa Edison Company has established a library to assist the Design Review Team. The documents contained therein are the latest plant construction documents consistent with Section 2.4.1 of NUREG-0700.

o The consultant has also established a reference library of pertinent human factors documerits including many of those listed in NUREG-0700, as well as relevant documents generated in other DCRDRs and relevant EPRI and INPO documents.

5.2 DOCUMENTATION GENERATED BY THE DCRDR PROCESS The following basic documents will be submitted to the NRC for approval in this review:

o Program Plan Report (this document).

o Executive Summary Report, which will address methodology, review findings, and implementation.

The following documents will be generated in support of the review.

o Criteria Report o OER . Report o SFTA Report o CRS Report o Compilation of Observations & HEDs 2.2.I1/090983 BECO CODE #1000A 5-1

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1.2 Program Overview  %

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Section 2.' Methodology , l

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2.2 . Use of Support Materials

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(These sections'wdl reference the ' orig!nail program plan report, anc

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will provide only material which ep,<iates and revises' the original planning material submitted to 'the NRC.)

Section 3. DCRDR Procedures .

This section will surnmarire 'the actual . precedurs used in the review process. Topics shall be as follows. .

3.1 Operating Experience Review o Identify types and time period of records reviewed.

o Review operator survey procedures (e.g., interview) and summa,rize experience levels of surveyed operators.

o Provich samples of the interview questions.

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2.2.11/090983 BECO CODE #1000A ,'

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I 3.2 System Function and Task Analysis Review The following processes will be summarized. Where this material may be covered in other licensee-applicant documents (e.g., Task

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! I. Col emergendy procedure guidelines and reporting analyses),

reference to these documents will be made l

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o Charts or lists of major systems and subsystems and their components.

o Basis for selecting operating events and failure I sequences for analysis.

l o Scenario / assumptions necessary to define the operating events.

o' Functional fhw block diagrams showing systems, subsystems, and major components involved in the selected operating events, coded to identify where control . of

. the function residesd (e.g., manual, l automatic, local).

1 o Hierarchial diagrams developed in the program.

o Functional sequence charts for control room operators

! (for each selected event).

o Task descriptions, organized by functional objective and system.

o Work station instrumentation and control requirements as i drawn from the task analyses.

2.2.11/090983 BECO CODE #1000A t .

5-3

3.3 Control Room Inventory o Summary of the actual control room inventory process.

o Sample inventory forms.

3.4 Control Room Survey o Summary of control room survey process.

o Samples of survey forms (e.g., checklists, HED forms, and measurement forms) ised in the survey process.

3.5 Verification of Task Performance Capabilities o Summary of the verification procedures used.

3.6 Validation of Control Room Functions o Summary of the v-lidation procedures used.

Section 4. DCRDR Findings This section shall review the findings by listing the summaries of discrepancies and highlighting results of the reviews.

Section 5. Implementation This section will summarize (1) recommended design changes, (2) proposed solutions, (3) methodology for implementation, (4) schedule for implementation.

2.2.I1/090983 BECO CODE #1000A 5-4

5.3 DOCUMENTATION SYSTEM AND CONTROL The Design Review Team will develop a data bam which will be reviewed by the Management Review Team. This data base will consist of computerized printouts and hard copy files of cross referenced infonnation includir.;:

o Listings of reference plant documents used.

o Listing of human factors referenced documents used.

o The program plan report (this document).

o Pertinent documents defining requirements for the DCRDR.

o The control room criteria report.

o The outputs of the individual task groups (see Figure 2-3).

o Minutes of meetings.

o All findings, HEDs, and dispositions as processed.

o Executive Summary Report.

o Detailed DCRDR Report.

o Pertinent correspondence.

2.2.11/090983 BECO CODE #1000A 5-5

6.0

SUMMARY

The Boston Edison Company considers that this program plan for the control room review of the Pilgrim Station is extensive, complete and. consistent with the ' pertinent document noted herein.

The program is in progress and it is our intention to comply with the content of this Program Plan. The Boston Edison Company reserves the right to make cha.iges in its best interest and will notify the NRC of all planned or executed de!iations.

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2.2.11/090983 BECO CODE #1000A 6-1

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APPENDIX A Qualification of Management Review Team and

- Design Review Team Members 4

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WILLIAM R. ARNOLD STAFF ENGINEER TORREY PINES TECHNOLOGY MEMBER DESIGN REVIEW TEAM PROFESSIONAL SPECIALTY Reactor protection and instrumente tion systems: design and analysis, operation, startup, trouble shooting, and equipment qualification.

EDUCATION BSEE, University of. Texas,1958.

Graduate Courses, Electrical and Nuclear Engineering.

EXPERIENCE Work on the control room design review Rr the South Texas Project Nuclear Generating Station. Participated in all phases of the review including control room survey, system function and task analysis, and annunciator review. Also, participated in subsequent rc-design of control panel layouts for this project.

Review of qualification data for safety-related equipment for PWR projects.

Responsile for assuring that the data packages met the general requirements of NUREG-0588 and the specific requirements referenced and that the equipment represented is satisfactory for use in a harsh environment.

Review of safety-related plant control and protection system logic and operation to confirm that components important to safety are properly classified for PWR projects at Bechtel.

Field investigation and solution of reactor protection system trips and transients during startup of Fort St. Vrain station. Liaison on operational and licensing aspects with utility operations and with NRC.

Field engineer in successful construction and startup of all internal and adjacent external reactor instruments, pressure test and hot flow test support, and control rod drive checkout for Fort St. Vrain station.

Completed design and documentation for licensing of reactor plant protection svstems. Accomplishments included logic design, cabling,

( customer liaison and review of specifications and layout for compliance with applicable NRC design criteria.

Electrical design of aerospace launch control hardware and systems.

PROFESSIONAL ASSOCIATIONS Registered Control Systems Engineer, California,1975.

3AMES W. ASHKAR NUCLEAR ENGINEERING DEPUTY MANAGER BOSTON EDISON COMPANY MEMBER ADVISORY COMMITTEE EDUCATION Penn State - Master of Engineering, General Engineering EPDA Fellowship for Engineering Education. (9/72 to 9/73)

University of Delaware-MBA Program (27 credits) no degree (9/69 to 12/71)

Penn State - B.S. Mechanical Engineering Honors: Graduated with high distir.ction Harding Loan Fund Award Recipient Tau Beta Pi, member

< Pi Tau Sigma, Chapter President EXPERIENCE ,

Boston Edison Company Assistant to Nuclear Engineering Manager (1/81 to present)

Responsible for planning and implementation of a Risk Management Program based on Probabilistic Risk Assessment, and implementation of a computer-based engineering work management system for all engineering activities.

Group Leader, Systems & Safety Analysis (8/79 to 1/81)

Managed a 10 member staff of engineers and analysts in performing nuclear power plant (BWR & PWR) system deHgn assessment and specification.

Methods included systems engineering, dpamic thermal / hydraulic analysis, reliability, FMEA, and sequence analysis. Administratively responsible for strategy planning, budgeting, staffing,' and training.

Project Manager Fire Protection Modification (4/79 to 8/79)

Responsible for integrated planning (computer-based), budget preparation, licensing coordination, management reporting, licensing coordination, management reporting, and direction of 5-member engineering team.

Implemented major portions of a $5 million capital project.

Senior Systems Analysis Engineet (1/78 to 4/79)

Performed reliability and risk, cost / benefit, and safety evaluations in specification and approval of nuclear pcwer plant systems designs.

Referenced engineering, economic and regulatory standards.

3ames W. Ashkar Page 2 Systems Analysis Engineer (1/77 to 1/78)

Responsible for project engineering coordination, cost control, procedure development for state-of-the-art high density nuclear spent fuel storage racks. Also performed several discrete engineer system design reviews.

University of Nebraska, School of Engineering Tv.hnology, Omaha, NE.

Assistant Professor, Engineering Technology (9/73 to 12/76?

Developed and taught courses in Engineering Technology (mechanical systems, thermodynamics, servomechanisms, dynamics, and industrial engineering). Distinguished by the first annual Outstanding Teacher Award.

Prepared 10-part video taped maintenance training program for Northern Natural Gas Corp.

Gibbs-Hill, Incorporated, Omaha, NE.

Mechanical Engineer, Consultant (6/74 to 9/75)

Prepared systems descriptions .md design cap ulations for coal-fired power plant design. Performed an alternate site evaluation for a nuclear p3wer plant design. Performed an alternate site evaluation for a nuclear power plant project environmental report.

E.I. DuPont, Packaging Films Dept., Wilmington, DE.

Technical Representative Engineer (7/69 to 9/72)

Worked within a specialized marketing division to affect technical coordination between the manufacturing division and major clients.

Union Carbide, Plastics Division, Bound Brook, N.3.

Manufacturing Engineering (6/68 to 9/68, college summer)

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Completed training projects at a manufacturing facility for vinyl resins.

PROFESSIONAL TRAINING / HONORS Registered Professional Engineer, State of Massachusetts / State of Colorado Technical Project Management Seminar, 7/81, AMR Supervision of Engineering Professionals, 8/80, ANA Probabilistic Risk Assessment Seminar, 2/80, JFB Assoc. .

PWR Operator Simulator Training, 6/78, Combustion Engineering -

Kempner Tregoe Decision Analysis Workshop, K-T, t4/78 Nuclear Safety Seminar, 8/78, MIT Member, Boston Edison, Nuclear Safety Review & Audit Committee Member, Atomic Industrial Forum, Probabilistic Risk Assessment

James W. Ashkar Page 3 Committee, 1980-81 Speaker, ASME 3PC, " Utility Decision Analysis Perspective," 1981 ~

Speaker, NRC Advisory Committee on Reator Safeguards Pilgrim-2 PRA/ Design Verification Program,1981 Member, ASME, 1968-81 Panelist, IEEE/ANS PRA Procedure Preparation Program,1981 1

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W. BABCOCK, 3R.

SR. ELECTRONICS ENGINEER i BOSTON EDISON COMPANY PRINCIPAL INVESTIGATOR OF DESIGN REVIEW TEAM l EDUCATION l

Bachelor of Science, Electrical Engineering, Brown University,1968 Graduate Study, Industrial Engineering, Ohio University PROFESSIONAL REGISTRATION Control Systems Engineer, State of California, Certificate No. CS-3575 PROFESSIONAL EXPERIENCE Boston Edison Cornpany (1979 - Present) l Sr. Electronics Engineer, Control Systems Group, Nuclear Engineering -

Department 1 1

Presently working as cognizant engineer for Control Room Design Review Project. Acted as team leader of a BWR Owner's Group control room survey team. Member, BWROG Control Room Improvements Su'o-committee.

Also responsible for design of new control systems and modifications to existing centrol systems at Pilgrim Nuclear Power Station, including oreparation of instructions for installation of new equipment and procedures for check-out and testing of this equipment. Have served as instructor for operator training in electrical / electronic systems operation, Recent Training in Human Factors Engineering: .

Massachusetts Institute of Technology - 1980

" Man-Machine Interfacing" General Electric Nuclear Training Center - 1980 "BWR Owners' Group Human Factors Engineering Workshop" University of Wisconsin - 1981

" Human Performance and Nuclear Safety" ,

W. Babcock, Jr.

Page 2 EXPERIENCE (Continued)

Burns end Roe, Inc. (1977 - 1979) -

Sr. Engineer / Group Supervisor, Instrtsnent and Control Department, Breeder Reactor Division Supervision of I&C engineering group with responsibility for design of balance-of-plant I&C systems for a breeder reactor project. Lead engineer, solid-state logic systems design. Lead engineer, electronic security syttems.

Ebasco Services, Inc.

Sr. , Instrument & Controls Engineer, (1974 - 1977)

Designed I&C systems for application of nuclear and fossil power plants.

Reviewed vendor system design documents for compatibility with clients' specifications. Member of engineering team charged with design and layout responsibilities for control rooms at various powc plants, both fossil and nuclear.

Cryogenic Technology, Inc.

Electrical Engineer, (1974)

Designed control systems and control panels for radkactive liquid and gas process systems. Designed, specified and tested control systems for large cryoger.ic gas liquefication systems.

Stone & Webster Engineering Corporation Control Systems Engineer Designed control panels and control systems for nuclear power applications.

Prepared field test procedures for documentation of installed system performance. Field engineer for checkout and testing of radioactive waste process systems.

Babcock & Wilcox Company Electrial Engineer, Nuclear Power Generation Department Designed and/or specified electronic control systems for nuclear steam supply systems when built in B&W plants. Reviewed vendor specifications and documentation for systems built outside B&W. Instructed customers' engineering personnel on operation and maintenance of B&W's systems.

SIBEN DASGUPTA CONTROL SYSTEMS GROUP LEADER BOSTON EDISON COMPANY MEMBER OF MANAGEMENT REVIEW TEAM EDUCATION Nonheastern University, Massachusetts, USA

" Electrical Engineer" Degree with Power Systems as major - 1979.

Northeastern University, Massachusetts, USA M.S. In Engineering Management with Operations Research as a major -

1973.

Calcutta University, Bengal Engineering College, West Bengal, India Master of Engineering in Electrical Engineering with Power Systems as a major -

1969.

Calcutta University, Bengal Engineering College, West Bengal, India Bachelor of Engineering in Electrical Engineering with Power Systems as a major - 1967.

Registered Professional Engineer (Massachusetts).

TRAINING:

Combustion Engineering Nuclear Power Plant Simulator - Training course in Nuclear Power Plant Operation.

Qual'fication of Safety-Related Equipment for Nuclear Power Generating Stations - Arranged jointly by Drexel University and IEEE.

Kepner-Tregoe Management Training Course.

PROFESSIONAL EXPERIENCE Dec.1981 to Control Systems Group Leader Present Boston Edison Company, Nuclear Engineering Department Oct.1978 to Boston Edison Company, Boston, Massachusetts Nov. 1981 Senior Electrical Engineer, Nucfear Engineering Department Oct. 1975 to Instrumentation and Control Engineer, Boston Edison Sept. 1978 ' Company, Neelear Engineering Department March 1973 Stone and Webster Engineering Corp., Boston, ,

to Sept.1975 Massachusetts Engineer, Control Systems Group, Advisory Operations Group.

Nov. 1970 Bell & Howell Communications Company, Waltham, to Feb.1973 Massachusetts Engineer, Production Engineering Department

Siben Dasgupta Page 2 TEACHING AND RESEARCH EXPERIENCE Sept.1977 Northeastern University, Boston, Massachusetts-to present lecturer, Graduate School of Engineerir.i; Assigned as a part-time lecturer in the Graduate School of Engineering Oct. 1969 Bengal Engineering College, Calcutta University to Sept.1970 Department of Electrical Engineering - West Bengal, India Senior Research Fellow under the Council of Scientific and Industrial Research, Govt. of India. Performed Post Graduate Research work on " Transient Analysis of Three Phase Induction Motors" and was assigned for light teaching load for undergraduate classes in electrical engineering.

PROFESSIONAL ASSOCIATIONS / HONORS Member of Institute of Electrical and Electronics Engineers, USA.

Chairman, IEEE Educational Committee, Boston Chapter.

Member of the Working Group of IEEE Nuclear Power Engineering Committee, Section 4.7, Auxiliary Power Systems.

PUBLICATIONS

" Transient Performance of Three Phase Induction Motors During Sudden Voltage Depressions: Journal of Technology (India) 1969.

" Degraded or Loss of Voltage Protection of Class IE Auxiliary Power Systems in a Nuclear Power Plant"; S. Dasgupta, 3. 3. Murphy; Presented at the IEEE Nuclear Science Symposium, Oct. 1978. Published in the IEEE Nuclear Science Transactions, Feb.,1979.

" Maximum Frequency Decay Rate for Reactor Coolant Pump Motors"; R. S.

Hahn, S. Dasgupta, E. M. Baytch, R. D. Willoughby; Presented at the IEEE Nuclear Science Symposium, Oct., 1978; Published in the IEEE Nuclear Science Transactions, Feb.,1979.

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ERROL P. GAGNON STAFF LICENSING ENGINEER TORREY PINES TECHNOLOGY MMEMBER OF DESIGN REVIEW TEAM PROFE35IONAL IPECIALTY Licensing, safety criteria and technical specification preparation and review.

EDUCATION B.S., Engineering, San Diego State University,1965 PROFESSIONAL EXPERIENCE AT GA TECHNOLOGIES INC. (Since 1969)

Assistant Project Engineer for the control room design review for the South Texas Project under contract to Bechtel Power Corp.

Chairman of the Results Review Committee of the Human Factors Evaluation program for the Palo Verde Nuclear Power Generating Station control room and responsible for coordination of the program tasks.

Developed safGy/ licensing positions and criteria for various applications of nuclear power plants.

Evaluated nuclear power plant systems and components to identify and prioritize technical, safety and licensing issues.

Developed nuclear power plant transient performance specifications.

Senior Technical Representative at Fut St. Vrain responsible for technical coordination and guidance on the conduct and evaluation of the startup test program.

Manager of the French Licensee Program responsible for the administrative and technical-transfer aspects of the nuclear power plant licensing agreements and contracts.

Eerformed simulation studies and evaluations of nuclear power plant transient performance / safety analyses, control systems, control room configurations and plant startup procedures.

OTHER PROFESSIONAL I!XPERIENCE [

General Dynamics Corporation (1965-1969). Performed dynamic analyses of missile control systems.

PROFESSIONAL ASSOCIATIONS / HONORS Member, American Nuclear Society

ROBERT E. GRAZIO GROUP LEADER SYSTEM AND SAFETY ANALYSIS BOSTON EDISON COMPANY MEMBER MANAGEMENT REVIEW TEAM EDUCATION Babson College, Wellesley, MA MBA Program; 45/60 semester hours completed Central New England College of Technology, Worcester, MA BS Mechanical Engineering Technology Graduated Summa Cum Laude PROFESSIONAL EXPERIENCE Boston Edison Corgany, Nuclear Engineering Department (3une 1983 -

Present)

Systems and Safety Analysis Group Leader Responsible for directing the efforts of up to ten senior engineers / engineers in the performance of group functions in support of plant operations, major projects and regulatory activities. Responsible for technical completeness and correctness of all group outputs involving intersystems relationships, compliance with codes and standards and ability to perform intended functions, and impact evaluation of pending and new regulatory activities.

Responsible for group administration such as formulation and adherance to capital and expense budgets and providing recommendations in all areas of personnel administration.

Boston Edison Company, Outage Management Group (Nov.1982 - June 1983)

Senior Project Engineer Responsible for the coordination of all Engineering inputs to the conduct of outages and assisting in the integration of these inputs with those of other departments. This responsiblity was performed in conjunction with the group charter of maintaining overall responsibility and accountability for the conduct of outages. Also responsible for the co-ordination of multiple department inputs to an organizational strategic plan as a supplementary assignment.

Robert E. Grazio Page 2 Boston Edison Conpany, Nuclear Engineering Department (March 1980 -

Nov.1982)

Senior System Analysis Engineer Appointed to functional position of Project Engineer for a $14M multidiscipline project June 1981. Responsibilities included coordination of inputs of various engineering disciplines into an integrated package to meet technical licensing, schedule, and budget requirements.

Responsibilities as Senior Engineer in the Sys+em and Safety Analysis Group as outlined above. Special assignments included feasibility studies, conceptual designs, and operator training. Interfaced with a wide variety of organizations, including regulatory agencies, industry groups, vendors, consultants, and various in-house organizations.

Stone & Webster Engineering Corporation (' July 1977 - March 1980)

Eng'meer Maintained overall responsibility for several engineering retrofit tasks to solve operational problems of an operating power plant. Scope of responsibilities included coordination of the efforts of the required engineering aspects of the tasks and participation in equipment procurement including preparation of specifications, bid cycle activities, and recommendations. Task duration typically from probbm identification and conceptual solutions to completion of system startup. Interfaced with client home office and site engineering, client operations, maintenance and construction, vendors and technical and non-technical support groups.

United States Navy (March 1%9 - June 1977)

Served at various locations including Nuclear Power Training, Fleet Ballistic Missile (Polaris) Submarine, and Submarine Nuclear Repair Facility.

Technical experience included assisting Lockheed shipbuilding engineers in the design of nucicar support facilities for a new class of submarine tender, design of fMid and process system modifications, craft supervision of operating submarine repair and modifications, all phases of power plant operation, shipyard overhaul, and pre-overhaul and post-overhaul testing of primary and secondary systems.

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Robert E. Grazio Page 3 PROFESSIONAL TRAINING / HONORS Engineer-in-Training, Massachusetts (June 1979) -

Member ASME Seminar Training - Battelle Praject Management Seminar W.P.I. Engineering Management Seminar CE PWR Simulator, M.I.T. Reactor Safety Course PUBLICATIONS

" Operational Analysis" presented at Augus; 1982/ANS/ ENS meeting on Reactor Safety

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SAL F. LUNA PROJECT ENGINEER TORREY PINES TECHNOLOGY MEMBER DESIGN REVIEW TEAM PROFESSIONAL SPECIALTY Design and development, instrumentation and control; human factors EDUCATION B.S., Chemistry, Magna Cum Laude, Niagara University,19f47 Specialty courses: Seismic - Wyle Labs, Human Factors - University of Tennessee and Electric Power Research Institute.

EXPERIENCE Project Engineer responsible for NUREG-0700 type design review of the South Texas Project control room.

Project Engineer responsible for Human Factors review of Palo Verde Nuclear Generating Station control rooms. Performed Annunciator Prioritization Study for same.

Directed design of advanced control room control consoles and unitized cabinets including: human factors engineering, full scale mock-ups, modular construction and seismic qualification.

Project Engineer responsible for Prcbabilistic Risk Assessment Study for Fire Protection Program Assessment of Northeast Utilities Nuclear Plants -

Connecticut Yankee, Millstone 1, and Millstone 2.

Cpnsultant, review of PG&E equipment qualification documents for NRC approval. Developed formats and oganized walkdown teams for PP&L equipment qualification program.

Design of a wide variety of systems for advanced HTGR plants. Special studies for application of all technology for modernizing existing nuclear power plants featuring a " Diagnostic Console."

Directed development of in-core and ex-core instrumentation to study Fort St. Vrain core fluctuation phenomena.

Directed site engineering and craft effort to provide fire protection of critical Fort St. Vrain cabling.

Prepared specifications, designed special testing equipment conducted qualification tests, evaluated results and prepared reports for cabling and in~.trumentation for Fort St. Vrain equipment qualification program.

i Sal F. Luna Page 2 Managed a wide variety of instrumentational control and development groups at Westinghouse Electric Corp. for the nuclear navy and commercial nuclear programs. Cognizant engineer for Annunciator Systems for same.

Dirceted the design and development of a wide variety of processing plant instrumentation systems for Catalytic Construction Co.

3 PUBLICATIONS Editor of Cassette Control Valve Training Program.

Author of chapter on Maintenance - ISA Control Valve Handbook.

Author of chapter on Liquid Level Measurement - ISA publication.

Also authored a wide variety of technical f.'.pers including methodology and results of human factors review of Palo Verde, and advanced control raom design.

PROFESSIONAL ASSOCIATIONS Registered Professional Engineer (control) California Fellow Grade Member of ISA Past Vice President Long Range Planning Department of ISA Nuclear Power Plant Standards Committee of ISA Member Human Factors Society

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CHARLES H. MINOTT PROJECT MANAGER BOSTON EDISON COMPANY MEMBER OF DESIGN REVIEW TEAM EDUCATION M. S. Civil Engineering: Project Management Program, M.I.T.,1974 B. S. Civil Engineering, University of Massachusetts, Amherst, MA.,1972.

EXPERIENCE Project Manager, Nuclear Engineering Department, Boston Edison Responsible for managing the following projects in support of Pilgrim Station:

Design / construction of a 130,000 s.f. administration / service building.

Renovation of a 30,000 s f. building for a nuclear training center.

Design / construction of a facility for compaction / shipping of low level radioactive waste Centrol room design review.

Upgrade of emergency responte facilities. -

Replacement of the plant canputer and installation of an SPDS.

Project Engineer, Nuclear Projects Group, Boston Edison Cortpany 9/81-9/82 Responsible for management of the architect / engineer's and turbine supplier's scope of work during close-out of the Pilgrim 2 Project contract protection of assests, and including marketing / sale of assets.Responsible negotiation for

/ settlement, a budget of $4 million.

Responsible for testifying at the Department of Public Utilities regarding Pilgrim 2 cost and contractual issues.

7/80-8/81 Responsible for shipping, receiving, storage and maintenance of all equipment manufactured for Pilgrim Unit #2; this equipment's value exceeded $150 million and was stored in ntrnerous states.

Responsible for developing work plans, assign work to other Boston Edison Departments and principal contractors and monitor progress on this work to assure the storage and maintenance program for the equipment was cost ,

effective, technically correct and adhered to applicable codes. l 1

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CHARLES H. MINOTT Page 2 EXPERIENCE (Continued)

Responsible for developing necessary control systems and insurance and audit programs. Directly responsible for a budget of $1 million per year.

~ Senior Cost Control Engineer, Boston Edison Co.

1/78-6/80 Prepared project procedures for the Pilgrim 2 Project in the following areas: engineering economics, accounting, insurance, tax and cost estimate preparation and reviews.

Cost Control Engineer 9/74-12/77 Developed a management control system for Nuclear Organization purchase orders. Reviewed architect-engineer's project cost estimate for Pilgrim 2; prepared and maintained the owner's scope portion of the cost estimate, prepared periodic cost reports and analyzed cost trends. Reviewed centractor bid analyses and developed recommendations for management approval.

Prepared other project cost estimates, insurance vtluations, cost studies, cash flows, and economic analyses for executive management, other Edison departments, joint owners, and regulatory agencies. Developed and implemented a cost reporting system for a nuclear unit refueling outage.

Coordinated the preparation cf the Nuclear Organization capital and expense budgets.

Responsible for cost / schedule and contract management of two Unit I backfit projects. Represented Edison in the Electric Utility Cost Group.

(1972 - 1974) Manachusetts Institute of Technology Research Assistant; worked under an NSF contract developing a cost estimating method incorporating risk analysis for use in the tunneling industry.

PROFESSIONAL ASSOCIATIONS / HONORS Project Management Institute Chi Epsilon (civil engineering) f Tau Beta Pi (engineering) -

Alpha Phi Gamma (journalism)

Sigma Xi (research)

RICHARD C. POTTER STAFF ENGINEER TORREY PINES TECHNOLOGY MEMBER OF DESIGN REVIEW TEAM PROFESSIONAL SPECIALTY Power plant dynamic and steady-state systems design and analysis including large scale systems simulation.

EDUCATION l B.S., Mechanical Engineering, University of Minnesota l

M.S., Mechanical Engineering, University of Southern California EXPERIENCE Mr. Potter is presently acting as consultant on the control room design review for the Palo Verde Nuclear Generating Station. He recently completed an assignment as Assistant Project Engineer on the control room design review of the South Texas Project Nuclear Generating Station where he performed system functions and task analysis, performed a control room survey, developed program plans and directed other engineers during the review.

Mr. Potter was responsible for a fire vulnerability study of three Northeast Utilities nuclear power plants. Study involved the use of probabilistic risk assessment techniques for predicting the shutdown capability of these plants in the event of a fire.

He also participated in a probabilistic risk assessment of the Fort St. Vrain plant to determine clean up costs versus probability for on-site contamination due to an interruption of cooling event.

On the Fort St. Vrain Nuclear Generating Station project respon:ible for:

modifying and maintaining computer models for the simulation of steady-state and transient plant performance review which included data monitoring and analysis as required to ensure proper plant operation; and performing steady-state and dynamic analysis to support the plant startup testing program.

While assigned to the Gas Cooled Fast Reactor Project he performed a

? conceptual analysis of a natural convection, drum-type and co.ndenser-type shutdown cooling system. ,

On the HTGR nud?ar project he was responsible for the 'ollowing:

modifying and maintaining the steady-state and transient plant performance

! programs, the pipe rupture analysis program and the core afterheat analysis program; predicting power plant nominal, shutdown and refueling performance for use by design and analysis groups within the company and for use by the customers and performing parametric and application stu lies relating to the overall plant design and performance.

Richard C. Potter Page 2 EXPERIF.NCE (Continued)

Prior to joining Torrey Pines Technology, he directed activities involving i-propulsion analyses, application studies and computer simulation work on large liquid rocket engines. He has also worked as a design engineer responsible for design and detailing of ground support equipment for rockets.

PROFESSIONAL ASSOCIATIONS Professional Mechanical Engineer in 5 tate of California Member of the American Society of Mechanical Engineers Member of Pi Tau Sigma i

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JEFFREY L. ROGERS

$YSTEMS ANALYSIS ENGIf1EER BOSTON EDISON COMPANY MEMBER OF DESIGN REVIEW TEAM -

PROFESSIONAL SPECIALTY Opportunity to utilize technical, supervisory and operational experience in the areas of systems analysis and reactor safety.

EDUCATION Clarkson College of Technology, Potsdam, NY; 1975-197.7 B.S. Degree, i 1977; Mechanical Engineering State University of New York at Albany, Albany, NY; 1973-1975 Majored in physics and mathematics Intern Engineer Certificate, State of New York,1977 EXPERIENCE Boston Edison Company, Boston, MA.

Systems Analysis Engineer, (October 1981 to Present)

Accountable for prov* ding nuclear safety evaluations consistent with industry standards and regulatory requirements. Ruponsibilities include the review and approval of safety evaluations / assessments of plant safety system designs, operating practices, system modifications, and Technical Specification changes; establishment, maintenance and approval of the Q-List; review of regulatory guides and information' for PNPS applicability; establish criteria for system design; provide system engineering input to special projects; and perform systematic analysis of special events.

Operations Engineer, (June 1980 to October 1981)

Responsible for the timely and cost effective completion of design modification projects initiated internally by Boston Edison Company and externally by the Nuclear Regulatory Commission (NRC). Ensured on-going progress of corrective action through integration of corporate and plant work activities and monitoring work in accordance with plans, schedules and costs. A;sisted in review of NRC documents to ensure operational compliance. Also responsible for providing operational engineering support to and analysis of the system of Pilgrim Station, Plymouth, MA. ,

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Jeffrey L. Rogers Page 2 EXPERIENCl (ContI.iued)

Niagara Mohawk Power Corporation, Oswego, NY -

Assistant Station shift Supervisor, (June 1978 to June 1980)

, As leader of operations personnel, had responsibility and authority for the implementation, coordination and control of operating policies and practices used in the start-up of a 850 MW power plant. Actively involved in the c.eation of start-up, normal operation and shut-down procedures for plarst equipment and systems; participated in completion of control and mechanical verification system start-up packages; and served as shift supervisor of operating crew during system start-up and full pour operations.

Auxiliary Supervisory Development Course Trainee, (June 1977 to June 1978)

In training for ultimate assignment of a supervisory nature . in. the corporation. Acquired a knowledge of the objectives, functions, organization and key personnel of each department. Emphasis was placed on familiarization with power plant operation and maintenance.

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RAYMOND SABEH HUMAN FACTORS CONSULTANT TORREY PINES TECHNOLOGY MEMBER OF DESIGN REVIEW TEAM PROFESSIONAL SPECIALTY Human Factors Engineering, Operations Research Analysis EDUCATION PH.D., (candidate), Experimental Psychology, Ohio State University M.S., Industrial Psychology, Ohio University B .A., General Psychology, Davis and Elkins College EXPERIENCE Responsible for Human Factors review of Corrective Enhancements, hierarchial labeling, and demarcation for the South Texas Project.

Responsible for special studies and operations personnel validation via operator questionnaire interview evaluations for the Palo Verde Plants. ,

Responsible for preparing and implementing the human factors portion of the NUREG-0700 plan for three NU nuclear operating plants and a fourth NTOL plant. Served as the human factors team member on the NU Safety Parameter Display System (SPDS) program that will be designed, developed, and implemented for as consortium of some 10 separate utility plants.

Prepared Human Facters Engineering Orientation Course material used for instructing nuclear engineers and reactor operators.

Northeast Utilities - served as project leader and carried out nuclear operations analysis assignments concerning nuclear regulatory requirements to conduct human factors study, analysis and review of all activities affecting man-machine power plant design and operation. In this capacity was appointed as subcommittee chairman to technically monitor and direct the Westinghouse Corporation's efforts for developing a generic system function and task cralysis on thei- P%R plants under contract to Westinghouse Owner's Group.

Consultant - responsible for human factors design of a control center for the storage and retrieval of nuclear waste. Currently compiling a handbook of human factors engineering design criteria. ,,

Manager / man-machine analysis branch - performed hurnan engineering analysis of the Automated Record Data System for the Ef4A Aircraft. Also performed a man-machine analysis of the FFGX-CIC space and work place design for SEAMOD, a ship-shore communications effectiveness study.

Designed the operator interface for the Minimum Essential Emergency Communications Network Message Processing Mode including the deve!cpment of computer simulation techniques to assess alternate operator interface designs.

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s R. Sabeh Page 2 EXPERIENCE (Continued)

Engineering Psychologist - initiated and coordinated research in development of methods and techniques used in human factors engineering system design and development. Technical leader of a communications effectiveness study 3 effort and shipboard habitability programs.

Planned and technically directed the National Military Command ~ System and Emergency Action Room study for the Defence Communcations Agency and World-Wide airborne command posts.

PROFESSIONAL ASSOCIATIONS Human Factor Society Operations Research Society of America National Academy of Sciences Armed Forces-NTD Committee on Vision Southeast Regional Director, Society for Information Displays PUBLICATIONS Human Factors Design Considerations for the Monitored Retrievable Storage System. Path Research Technical Document PR81001. June !981.

MMPM Operator Interface Design (OID) Final Report. - SEI Technical Docume.nt. December 1979.

Human Engineering Analysis of the Automated Record Data System for the-E4A Aircraft. SEI Technical Document 0279-1. January 1978.

Human Engineering Analysis and Evaluation of the Integrated Record Data System - for the EC-135 Aircraft. NOSC Technical Document 113. August 1977.

Profile for Open Ocean Crane Ooerators. NELC Technical Note 3209.

August 1976.

Human Factors Analysis of the National Military Command System's Emergency Action Rooms. NELC Technical Note 3109. December 1975.

Preliminary Human Engineering Analysis of the Signal Intelligence Analysis System (SIAS). NELC Technical Note 2252. (U), January 1973. ,

Voice Traffic Analysis of LANTFLEX 66, Racer Run 68, and ROPEVAL 3-71 Exercises. NELC Technical Document 175. May 1972.

USS BLUE RIDGE (LCC 19) Communications Effectiveness Evaluation.

NELC Technical Document 146. (U), October 1971.

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Page 3 PUBLICATIONS (Continued)

Operator Fatigue and Fighter Rance Extension. WADC Technical Report No.53-330. October 1953.

l Comparison of a Single Operator's Performance with Team Performance on a Tracking Task. WADC Technical Note 55-362. July 1955.

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KENNETH NORMAN TAYLOR SENIOR REACTOR OPERATOR BOSTON EDISON COMPANY MEMBER DESIGN REVIEW TEAM EDUCATION Presently attending Northeastern Uaiversity pursuing a degree in engineering.

Nuclear Power Training Unit, West Milton, NY - 1960 U.S. Navy Nuclear Power School, New London, Conn. (1959)

Machinist's Mate "A" School Great Lakes, IL - Cole Trade High School, Southbridge, MA M.A., Nuclear Power Plant Operating Engineer (1978)

NRC Senior Reactor Opreator License S.O.P. 4065 (1977)

NRC Reactor Operator (1975)

M.A., License - 1st Fireman (1975)

EXPERIENCE Boston Edision Company Day Watch Engineer-Pilgrim Nuclear Power Station, (2/81 to present)

Responsible for the safe, efficient operation of Pilgrim Station, under the direction of the Chief Operating Engineer in accordance with the requirements of Station Procedures and Regulatory Agencies. Responsible for rewriting procedures, update of i'&lD's md ensuring a smooth accurate communication with the departments within the station.

Nuclear Watch Engineer-Pilgrim Nuclear Power Station, (11/73 to 2/81)

Responsible for all activities relating to station and safety including, fuel loading, startup and shutdown in accordance with the requirements of the operating license, Technical Specifications, approved operating procedures, regulatory agencies, and the Operations Quality Assurance Program.

Responsible for implementing the station radiation protection program, for the monitoring the performance of station euipment, for assuring that the reactor is shutdown when a condition has been identified such that continued operation would jeopardize station safety and the station security within the confines of the process building.

Nuclear Operating Supervisor-Pilgrim Nuclear Power Station,' (11/75 to 11/78)

Responsible for supervising the Nuclear Plant Operators and implementing operating maneuvers in accordance with approvcu station procedures and for assisting in training the Nuclear Plant Operators in the skill and knowledge required for the safe and efficient operation of a nuclear facility.

Kenneth N. Taylor Page 2 OTHER EXPERIENCES 5/73 to 11/75 -

Served on U.S.S. Skipjack SS(N) 575 as Engineering Watch Supervisor 1 4/72 to 5/73 Served on staff at Engineering Repair Division, New London, Conn.

8/65 to 4/72 Served on U.S.S. Francis Scott Key SSB(N) 657 as Engineering Officer of the Watch 12/62 to 8/45 Served on U.S.S. Stonewall Jackson SSB(N) 634 as Engineering Watch Supervisor 1/61 to 12/62 Served on U.S.S. Ethan Allen SSB(N) 607 as Engine Room Supervisor 1/59 to 1/61 Received U.S. Naval Training at various schools 2/57 to 1/59 Served on U.S.S. Skate SS(N) 578 as Engine Room Operator 12/56 to 2/57 Served on U.S.S. Leyte C.V.S. 32 as Auxilary Operator l '

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l FREDERICK W. TODT STAFF ENGINEER TORREY PINES TECHNOLOGY MEMBER DESIGN REVIEW TEAM PROFESSIONAL SPECIALTY Process computer systems conceptional design, configuration and application

! development.

EDUCATION B.S., Physics, Wayne State University Electronics School, U.S.M.C.

EXPERIENCE -

Performed a control room survey of the plant computer for South Texas Project.

Coordinated proposal efforts to supply computer hardware and softv/are for emergere.y response facilities for nuclear plants.

Implemented computer demonstration of plant disturbance detection concept.

Developed real time application programs to support start-up testing and reactor operation. Monitored system behavior during start-up, located deficienc;es and made modifications as needed. Trained plant personnel to use computer facilities.

Section leader for large plant computer system application software development.

Specification writing for plant computer hardware and software and participation in the vendor evaluation process.

Performed nuclear design and analysis calculations associated with reactor power shaping, fuel cycles, control poison worth, and safety evaluations of HTGR and PWR reactors.

Developed methods and computer programs for nuclear fuel cycle studies, fuel cost analysis, and automation of reactor design parametric studies.

,- Performed nuclear design studies on small power, research,. and space reactor concepts using a variety of fuels, moderators, and coolants.

Evaluated nuclear design calculation programs (computer codes) by comparison with critical experiments.

F. W. Todt Page 2 EXPERIENCE (Continued)

Performed 14boratory work with radioactive isotopes including sample counting, dosage preparation, standardization. Calibrated x-ray machines and radiation measurement equipment. Performed radiation shielding surveys, installed, maintained, and repaired radio receivers, transmitters and telephone carrier equipment.

PROFESSIONAL ASSOCIATION American Nuclear Society l

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WILLIAM J. ARMSTRONG STAFF ASSISTANT-OPERATIONS BOSTON EDISON COMPANY MEMBER MANAGEMENT REVIEW TEAM EDUCAT!ON Dorchester Ilich School - 1448 Wentworth Institute -

1937-1958 l

Peterson School of Steam Engineering - Various time periods in preparation for Mass 1st Class Engineer'a License.

Penn State Trina Facility - Two-week course - Completed lo-week Nuclear Power Preparatory Training Ccus se week BWR.

Technology course. 12-wech BWR Simulator course, and 3-month observation period, including 2 months at Millstone during power test program.

Mass License - 1st Class Fireman -

1957 Mass License - 3rd Class Fireman - 1957 Mass License - 2nd Class Engineer - 1961 Masn License - 1st Class Engineer - 1961 NRC SRO License - 1971-1976 Mass Nuclear Power Plant Senior Supervising Engineer - 1972-Present WORK EXPERIFNCE 6/1/83 - Present Boston Edison Company - Staff Assistant - Operations As Staff Assistant - Operations, responsible for assisting Vice President-Nuclear Operations in developing and le91e-menting policies governing station performance and keeping the Vice President cognizant of the status of plant operations.

Also responsible for ensuring the nucessary support for plant operations through coordinating communications between Nuclear Operations, Nuclear Engineering, and Quality Assurance, other Company organi::ations , contractors and vendors. Advising the Vice President-Nuclear Operations on all significant issues and representine him at mee;ings, conferences, etc., as necessary.

9/82 - 5/83 Boston Edison Company - Special Projects Manager, Pilgrim Nuclear Power Station As Special Projects Manager, responsible fo'r various problems that need to be corrected in order to imorove the overali efficient operation of the plant. These include development and implementation of tasks such as:

(a) Salt Service Water and Condenser Sea Water Mussel Control Program (b) Overall raawaste process refurbishment (c) Removal off site of various amounts of radwaste sludge (d) Development of an on-site Dry Uaste Treatment Facility to reduce volume of low specific activity material s

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i 7/"2 - 5/83 (cor.t'd)

(e) As a member of NEPEX Nuclear Dispatch Task Force have gp the responsibility of resolving ongoing problems that exist between the operating nuclear units and NEPEX present day procedures 6/81 - 9/82 Boston Edison Company - Deputy Manager, Pilgrim Nuclear Power Station As Deputy Manager, responsible for the Tewhnical, Radiological and Radwaste Operations Groups.

Continued involvement with boiling water reactor Owner's Grouc '+

pertaining to Control Room issues. Also was a member of INPO Committaa on control *eom review. These committees are involved with:

- Safety Parameter Display System (SPDS) 4R

- Control Room review _

- Emergency Operating Procedure guidelines

- Implementation of NRC document SECY 82-111B -

9/80 - 6/81 As Deputy Fbnager, responsible for plant operation. =mintenance, security and fire protection.

10/77 - 9/80 Boston Edison Company, Staff Assistant to the Manager of Nuc1 car Operations -

As Staff Assistant, have been responsible for the following:

.xmber of Company Central Safety Committee l Nuclear Operations Departnent representative in the Company j Blackout Study Committee 1 >

l Developed the Planning & Scheduling of Refueling and Maintenance Outage No. 3 s Directly involved in the Group establishing the Company's position regarding " Fire Protection Review A.P.C.S.B.9.5.1.

Member of the Bargaining Committee for the Company involving contract negotiations Involved in all Nuclear Operations Department Union grievances as per Article XXXII 1 (b) of the Contract Work directly with various members of the Nuclear Engineering Group in resolving various plant design and operational problems Directly involved in coordinating efforts to update the plant to the changing requirements of the NRC regarding Fire Protection and Prevention per Branch Position 9.5.'.

Represent the Nuclear Operations Department or the Company's

" Resource Conservation and Recovery" Task Force.

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l 6/76 - 10/77 Boston Edison Company, Special Projects Coordinator Staff Assistant to the Manager of Nuclear Ope;>tions, res-ponsible for the following:

1. Design and implementation of various plant changes such as:

A. Fuel pool ccoling and residual heat removal system piping changes, to allow more flexibility in processing suppres-sion chamber and reactor cavity water volume during refueling.

2. Design and installation of piping changes and the new "Cupco" Instrument Air Compressor.

3. Design of system changes and procedure revision necessary for unit cooldown after complete loss of screenhouse.

( Assigned as an " Employee Discussion Group Leader" to discuss various questions involving the Company which were being voted on during the November elections.

Became involved in re-allocating available space in Unit #1 warehouse, to eliminate the need of establishing off-site storage facilities.

Actively involved in the planning and scheduling of Refueling &

l Maintenance Outage (!3 which began August 3, 1977.

7/68 - 6/76 Boston Edison Company, CSief Operating Engineer, Pilgrim Station The Chief Operating Engineer is responsible for fuel loading, startup and shutdown of the station and its equipment including:

1. System surveillance testing in accordance with requirements outlined in the Station Operations Manual.

2. Informing licensed operators and senior operators of facility design chances, facility license changes and station pro-cedural changes which have an effect on the performance of their duties.

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3. Maintenance of the special order book, for the implementation of special orders, for ensuring that all appropriate per-sonnel are aware of the responsibilities assigned to them by the special orders, and for retiring special orders when they are no longer needed.

4. Maintenance of the control room files, training files for all individuals under his supervision.

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In the event of any absence or unavailabill'y of the Station

! Manager, the Chief Operating Engineer assumes responsibility for overall facility operation.

1/68 - 7/68 Boston Edison Company - Mystic Station - Watch Engineer Responsible for the safe and efficient operation of the station. ,

1/65 - 1/68 Boston Edison Company - New Boston Station - Control Room Supervisor Responsible for the initial startup and operation of two 400 MWe units.

l 7/61 - 12/64 Boston Edison Coupany - Mystic Station - Turbine Operator Responsible under supervision for the operation of turbine generators and associ.,ted equipment.

l 1/61 - 7/61 Boston Ed2 son Company - Various Stations - Fireman 1

( Responsible for the opere. tion, under supervision, of steam generators.

1/59 - 1/61 Boston Edison Coupany - Various stations - Auxiliary render Basically this encompasses operation of auxiliaty equipment in power stations.

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PAUL E. MASTRANGELO CHIEF OPERATIONS ENGINEER BOSTON EDISON COMPANY MEMBER ADVISORY COMMITTEE EDL'CATIO:::

Somerville Trade School Graduated 1956 New England Oil Heat Institute 1960-1961 Peterson School of Steam Engineering 1965 LICENSES:

Nuclear Power Plant Operating Supervisor Engineer (MA) 1982 NRC Senior Reactor Operator S0P 2004-4 1974 Nuclear Power Plant Operating Engineer (MA) 1973 NRC Reactor Operator 1972 2nd Class Fireman 1965 3rd Class Engineer 1969 SPECIAL COURSES: ,

St. cam Eng International Correspondence School 1970 - I.C.S. Certificate NUS Nuclear Prep Course 1971 - Ct.rtificate Penn State Triga Reactor Training 1970 PRESE';T POSITION TITLE: Chit.f Operations Engineer >

EXPERIENCE:

Bosten Edison Comoany:

9/1/82 to Present Chief Operations Encineer - Pilcrim Nuclear Power Station (PNPS)

Responsible for the sate and efficient operation of PSPS in accordance wit.it NRC regulations and Station procedures under ditaction of the Station Manager and other egulatory agencies.

1/27/79 tc ./29/32 Nuclear Watch Engineer - Pilgrim Nuclear Power Station Responsible fcr all activities relating to Station safety and all operations of the Station including fuel loading, startup and shutdown in accordance with the requirements of the Operating License, Technical Specifications, approved f

i operating procedures, regulatory agencies and other governing l ,

bodies.

5/16/78 to 1/20/79 Nuclear Operatine Supervisor - Pil -im Nuclear Power Station l Responsible tor supervising the Nuclear Plant Operators and implementing operating maneuvers in accordance with Station procedures and assist in training the NPos in their akill and knowledge required to safely. operate a nuclear facility.

1970 to May 1978 Nuclear Plant Occrator - Pilcrim Nuclear Power Station Participated in fuel loading, pre-op testing, 20% power testing and operated all station equipment.

Boston Edison Company (cont) 1966 - 1970 Boiler Operator - Mystic Station Operate boilers, including responsibility for the feeduccer driving turbines with a capacity of 150 Fr,G: each.

19c6 - 1968 Fireman - Edgar Station and Kneeland Street Operated boilers, under the direction of the Watch Engineer.

1965 - 1966 Turbine Tender - L Street Station operated turbine and turbine equipment under the direction of the Watch Engineer. '

1964 - 1965 Auxiliary Operator - Mystic Station and Edgar Station Operated boiler and turbine auxiliary equipment under the s direction of tha turbine operator and boiler operator.

1963 - 1964 Auxiliary Tender - L Street Station and Kneeland' Street Station Operated boiler and turbine auxiliary equipment under the direction of the fireman, water tender and turbine tender.

1961 - 1962 Station cleaner General housecleaning duties.

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