ML20084S518
| ML20084S518 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/07/1984 |
| From: | TORREY PINES TECHNOLOGY |
| To: | |
| Shared Package | |
| ML20084S516 | List: |
| References | |
| PROC-840507, NUDOCS 8405250155 | |
| Download: ML20084S518 (64) | |
Text
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PROGRAM PLAN l
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l INDEPENDENT DESIGN REVIEW OF l
LIMERICK GENERATING STATION UNIT NO.1 l CORE SPRAY SYSTEM l
PREPARED FOR i
PHILADELPHIA ELECTRIC COMPANY l
MAY 7,1984 TORREY PINES TECHNOLOGY h
r%- -- -s #2 A Teetanalagiq Ine g P R e OY O $h,1 A PDR
TABLE OF CONTENTS PAGE
- 1.
SUMMARY
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- 2. TASK DESCRIPTIONS ................................... 2-1 i
Task A - Des ign Procedure Review . . . . . . . . . . . . . . . . . . . . 2-1 Task B - Design Procedure Implementation Review ..... 2-4 l Task C - Technical Review . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-6 Task D - Physical Verification Walkdown . . . . . . . . . . . . . 2-10 Task E - Processing of Potential Findings ........... 2-12 s s Task F - Administrative & Reporting .................- 2-16 e
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- 1. SUPMARY This program plan has been developed for an independent design review of l the core spray system for the Limerick Generating Station Unit No. 1. This program will be performed by Torrey Pines Technology, a division of GA Technologies Inc., for Philadelphia Electric Company. The program is divided into six tasks as follows:
Task A Design Procedure Review Task B Design Procedure Implementation Review Task C Technical Review Task D Physical Verification Walkdown Task E Processing of Potential Findings Task F Administrative and Reporting GA Technologies, through its Torrey Pines Technology Division, is eminently qualified to perform this evaluation for Philadelphia Electric Company (PECO). We operate under the first NRC-approved quality assurance program.
We have available the significant expertise in both quality assurance and design required to review in detail the Limerick Unit 1 core spray system, starting with a review of the design procedures and their implementation, through a review of the technical design aspects of this system, and a physical verification.
GA Technologies Inc. has obtained less than 2% of its revenue for the last two years from PEC0 and from its contractors for Limerick Unit 1. The individuals assigned to this program are free from conflict of interest.
Key project personnel cannot have worked on Limerick design or construction currently or within the past three years. Project personnel must not have a family member employed by PEC0, a etnulative ownership and creditor in-terest in PEC0 which exceeds 5% of their gross family annual income or be active on any other current PEC0 plant or PEC0 work.
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The independent review is scheduled to be completed in August 1984, as-suming this program plan is approved by itay 15. The summary schedule for this work is shown in Figure 1.
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The core spray system work performed prior to February 1,1984, is the basis for the review.
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Proposed Schedule for PECO Independent Design Review MAY JUNE JULY AUGUST I. INITIAL EFFORT (Assemble people, clearances, training, z7, program plan, prepare procedures, QA program, acquire data, etc.)
II. CORE SPRAY SYSTEM DESIGN VERIFICATION A. Design Procedure Review B. Design Procedure Implementation Review d, C. Technical Review D. Physical Verification Walkdown III. PFR PROCESSING IV. REPORTS 575 57S srS s7S 57S t7S k7F S = Status Report F = Final Report
- Program Plan Approved Figure I
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- 2. TASK DESCRIPTIONS The purpose of this program is to conduct an independent review of the Limerick Unit 1 core spray system from NRC approved design basis to final .s design documents and system installation. The program will review the design process of the major suppliers, Bechtel and GE.
The program is structured to verify that the design process converted the design basis specified in the FSAR into design documents, and selected .
system components were installed in accordance with these documents. The _
detailed description of the tasks incl uded in this program are in the following subsections.
TASK A - DESIGN PROCEDURE REVIEW Objective To verify compliance of design procedures and controls with the NRC-approved QA section of the PSAR or to 10CFR-Part 50, Appendix B. The procedures and controls used by PEC0, GE, and Bechtel will be reviewed.
Subtasks l Al Prepare a procedure and checklist to accomplish the evaluation described herein. .
A2 Provide a detailed description of the complete structure of the design control procedures applicable to the core spray system j design work performed by PECO, GE and Bechtel. This description will include a comprehensive list of all relevant procedures.
In carrying out this work item, it will be assumed that the major core spray system effort was performed by PECO, GE and Bechtel.
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4 A3 Obtain (or use on-site) copies of PEC0, GE and Bechtel procedures .. Li, identified in A2. I' . k -
.' The initial collection of procedures will include only currently j%
applicable revisions. -'
A4 Determine if Bechtel procedures used for Limerick Unit 1 are r. . ,[.'
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essentially the same as the procedures used for either the San j} '
Onofre or Palo Verde plants. ( ,. s.
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2 p 1. If it is determined that the same procedures were used, then ( ,
no further review of the Bechtel procedures will be per- -[ + t
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- 2. If the titles and revisions of any of the Bechtel procedures .
are different from those used either on San Onofre or Palo . -. ,' > .-
Verde, then the principal aspects, in terms of the "who " ,
J "what," "when," and "how," and the controls described in each '
will be compared to identify differences, if any, in the .4',
approaches taken on the Limerick Unit 1 project versus the '[7 .
i: San Onofre or Palo Verde projects. ['. -
8 a) If the principal aspects of the controls are basically f; the same, then no further review of the Bechtel proce-dures will be performed and the results of the previous
' { (. t TPT reviews will be used as the basis for this review. -
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b) If the principal aspects of the controls described in the ,
2 .s l Bechtel procedures for PECO appear to contain basic dif- j.
, ferences from that described in either the comparable San & ; -l .
Onofre or Palo Verde procedures, then the affected y $
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f Bechtel procedures will be reviewed in detail for compli- [ Ib ance with PSAR commitments and NRC requirements (per A5).
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AS Review all current procedures, as of February 1,1984, affecting the core spray system design work for conformance to the commit-ments in the PSAR (except as modified for Bechtel per A4).
A6 Review selected design control procedure revisions applicable in time periods other than those covered in A5 for compliance to the applicable PSAR, per AS.
A7 Summarize the design procedure review, including any Potential Findings. This information will be included in the reports of Task F.
Milestones Dates Al Procedure and Checklist 5/30/84 A2 Complete Procedure Structure 6/15/84 A3 Access PECO, GE and Bechtel Procedures 6/15/84 A4 Review Bechtel Procedures 7/05/84 AS Review PECO and GE Procedures 7/05/84 A6 Review Selected Procedures from 7/10/84 Previous Time Periods A7 Summarize Results 7/24/84 i
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TASK B - DESIGN PROCEDURE IMPLEE NTATION REVIEW ;
l Objective To evaluate, through a sample of core spray system design documents, com-pliance with the design procedures and controls identified in Task A.
Subtasks B1 Prepare procedure and checklist to accomplish the evaluation described herein.
B2 Select the design documents to be reviewed for compliance with the procedures. The selection of documents for review will be based on the following criteria:
- 1. All documents reviewed in Task C will be included.
- 2. Additional design documents for the core spray system shall be selected for other Quality Class I or II items from the Eqpipment Classification List in the FSAR.
3, The selection shall include work by PEC0, if any, GE and Bechtel.
- 4. The selection shall include design documents such as calcula-tions, drawings, specifications, memos, change nntices, com-puter code verification reports.
- 5. The selection shall include work which spans the calendar l period of the design effort, and which covers all phases of the design process done prior to February 1, 1984.
B3 Locate pertinent design documents.
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l B4 Evaluate implementation of design procedures identified in Task A l by reviewing design documents for compliance with those proce- f dures, i
B5 Sumarize the review work for inclusion in the reports of Task F.
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Milestones l
Dates l
B1 Procedure and Checklist 5/30/84 82 Selection of Design Documents 6/15/84 B3 Location of Design Documents 7/0!/84 l l
B4 Review Design Documents 7/27/84 85 Sumarize Results 8/10/84 2-5
TASK C - TECHNICAL REVIEW The objective of this task is to review the structural, mechanicai and electrical design of a selected portion of the core spray system to assure that the system design is adequate to perform its intended function. This will include review to assure that the design is in compliance with NRC approved design bases and methodologies as given in the FSAR.
Cl Prepare specific procedures and evaluation criteria for the design review using ANSI N.45.2.11, Section 6.3.1 criteria for guidance.
The procedures will selectively address the following as they apply to each subtask:
o Adequacy of design specification o Applied loads o Mathematical model used for analysis o Input to analysis l
o Validation of computer code used o Output of analysis o Calculations showing compliance with approved standards.
l l C2 Prepare a design chain for major structures and components to identify major design organizations and interfaces.
l C3 Select the system features to be reviewed based on the following criteria:
1 o The system features shall include safety-related mechan-ical components, controls, electrical, piping and pro-f cess design.
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o Features which have design interfaces between the var-ious major design organizations shall be included.
o Features selected shall be representative of safety-related portions of the system.
o A range of design methods shall be covered.
C4 Obtain current design documentation from PEC0,-GE and Bechtel and perform review.
The review will be conducted in five major disciplines,
- a. Structural Review The structural review will address the structural adequacy of the piping, pipe supports and pump support. One pump support and one representative pipe hanger will be reviewed in detail to determine their adequacy to properly restrain the equipment for all appropriate FSAR criteria. In addi-
. tion, a sample area of the system piping will be selected and evaluated for adequate damage protection against the i effects of high energy line breaks and/or foreign missiles within the proximity,
- b. Instrumentation and Controls Review Instrumentation and controls, including control logic dia-grams, will be reviewed to confirm that the core spray
- system can be configured to operate properly in both normal and accident modes of operation.
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- c. Mechanical Review The design of the core spray system will be reviewed to con-firm operational capability to function appropriately under both normal and accident conditions. The review will con-sider both the mechanical and hydraulic characteristics /
capabilities to provide assurance of the system adequacy.
- d. Electrical Review The olectrical design of the core spray system will be reviewed to confirm that the supply of electrical power, under both normal and accident conditions, will permit proper operation of the system.
- e. Fluid System Review l
The core spray system review will address the adequacy of the overall system to meet the basic functional requirements t for the system. Capacities, temperatures and pressures will be reviewed.
t C5 Identify need for independent analysis with different analytical models and computer codes than those used by PECO, if any, and by f GE or Bechtel. Independent analysis shall' be done if one of the i following situations arises:
1 o The analytical output cannot be adequately judged based on ANSI N.45.2.11, Section 6.3.1.
o The method of analysis does not appear reasonable.
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o The impact of a Potential Finding cannot be ascertained. !
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C6 Sunnarize the technical review work for inclusion in the reports of Task F.
Milestones Dates C1 Review Procedures and Criteria 5/30/84 C2 Prepare Design Chain 6/08/84 C3 Feature-Selections Ongoing j C4 Design Review 8/10/84 C5 Identify Need for Independent Analysis 7/27/84 C6 Summarize Results 8/17/84 1
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TASK D - PHYSICAL VERIFICATION WALKDOWN Objective To determine that the physical installation of selected portions of the core spray system conform to the requirements of design drawings and specifications.
Subtasks i
D1 Prepare procedures for each unique type of walkdown or inspec-
, tion. Collectively these procedures will address the following as they apply to each feature:
l o Installation of components in accordance with design documents.
o Installation of core spray system in accordance with P&I diagrams.
o Installation of piping in accordance with drawings and isometrics.
o Agreement between component functional rating, as given on nameplates, with design requirements, as given in corresponding specification.
l o Inspection of selected features for compliance with '
design details.
o Equipment part numbers / tag numbers agree with drawings.
l D2 Choose items for physical verification from those features selected for design review under Task C. These will include l l
l m:for components, piping, and pipe supports. Item selection may )
consider design margin as determined from the design review. l l
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i D3 Perform walkdown to verify the adequacy of the installation. The walkdown will visually verify that the selected components, and j piping have been installed in proper relative positions. The
- piping isometric walkdown will dimensionally verify routing and support locations as well as general support arrangement.
Selected components and supports will also be inspected to dimen-I sionally verify such details as material sizes, weld types, fasteners, and attachments to the structure.
04 Sunnarize results of the work in Task D.
Milestones Dates 01 Prepare walkdown procedures 6/15/84 D2 Choose items for physical verification 6/22/84 D3 Complete walkdowns 7/27/84 D4 Summarize results 8/10/84 i
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TASK E - PROCESSING OF POTENTIAL FINDINGS Objective To review and document all Potential cindings identified during the review; to provide for evaluation and classification of the significance of Poten-i tial Findings; and to transmit Findings to PEC0, GE and Bechtel.
Description Tasks A, B, C, or D may identify differences between the core spray system i
design and the design requirements. These differences will be documented in Potential Finding Reports (PFRs). Following the filing of a PFR it is reviewed by the appropriate task leader. The purpose of this review is to determine if the PFR is valid, that is, if it is accurate, well defined and traceable to a specific requirement.
The original der,ign organization constitutes the next level of review. The PFR is sent to the appropriate organization for the same type of accuracy and definition review as was conducted by the task leader. At the same time a copy of the PFR is sent to the PEC0 representative.
When the PFR is returned from the criginal design organization, it is sent back to the initiator and the task leader. Based on the information sup-plied by the design organization, the initiator may modify the PFR or just coment on the organization's response. The task leader can only add his coments. Following this review, the PFR is sent to the Findings Review Comittee.
I An impact assessment for the Potential Finding is prepared to define the potential for impact on the safety of the plant. The impact assessment and 1 the PFR are then submitted to the Findings Review Comittee for evaluation.
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f This committee is comprised of five senior technical people at GA who have extensive experience and broad knowledge of the design and construction of nuclear power plants. It is the purpose of this comittee to evaluate each PFR and classified it according to established criteria.
A Potential Finding is classified as invalid if after the above-described review, the initiator, the task leader, and the original design organiza-tion agree i. hat the Potential Finding is inaccurate. In addition, Poten-1 tial Findings can be classified as invalid if two of the above-identified three reviewers conclude that the Potential Finding is invalid and the Findings Review Comittee also decide it lacks validity.
The review proceaure will contain criteria for classifying a valid Potential Finding as either a Finding or an Observation. Basically, if a Potential Finding is a deviation that could result in a significant safety E hazard, or if there is an indication of a repetitive or generic deviation that could create a significant safety hazard, the Potential Finding is classified as a Finding. Potential Findings that are valid, but that do not satisfy the above criteria for a Finding, are classified as Observa-tions.
The classification of the Potential Finding is reviewed by the Project Manager to determine if the correct procedures have been followed. Subse-quently, the Observations and Findings are sent to the PECO representative A for resolution. In the case' of Findings, a Corrective Action Plan is prepared by PECO and returned for review. This review is to determine if
=) the Corrective Action Plan satisfies the concern expressed in the Finding including identification of the root causes and the extent of the affects of the concern. Each Corrective Action Plan is reviewed by the initiator of the Finding, the task leader, the Findings Review Comittee and the GA project manager.
In each step of this review process the coments and information that are I added become a permanent part of the PFR. All PFRs will be included in the final program report that is transmitted to PECO and to the NRC.
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, Subtasks i
El Establish a Findings Review Comittee. This comittee will be composed of senior technical people with broad experience in engineering management.
E2 The Comittee will identify specific criteria for determining the I degree of impact that Potential Findings have on the design adequacy of the Limerick Unit I core spray system.
9 E3 Establish a detailed procedure to process Potential Findings.
This procedure will assure that PEC0, GE or Bechtel have verified the definition and accuracy of the Potential Finding. The basic process is shown in Figure 2.
E4 Process PFRs.
1 Milestones Dates a .
El Establish Comittee 5/30/84
[ E2 Define Criteria 5/30/84 E3 Establish Specific Procedure 5/30/84 E4 Process PFRs On-going L
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TASK F - ADMINISTRATIVE AND REPORTING i
I Objective F
l Provide administrative and management support for the project. Prepare biweekly status reports, ar.d a final evaluation report on Findings and conclusions with respect to adequacy of the design of the Limerick Unit 1 core spray system. Assure all communication, including reports between TPT, PEC0, BPC, and GE meet the NRC protocol for independent reviews.
Subtasks l
F1 Provide management of the design review program and accumulate a cost and schedule data.
F2 Prepare project procedures to assure that the following protocol is met:
- a. Requests for information may be made directly to the appro-priate organization without documentation other than that required for doctanent control and follow-up.
- b. PFRs, CAPS, and clarification of information may go directly betwween TPT and PECO, BPC and GE. However, all such 4 exchanges shall be docisnented for the permanent record.
- c. Any discussion of tentative conclusions or conclusions between TPT and PEC0, BPC or GE shall only be with an NRC representative present. The biweekly status reports, any.
i interim reports and the final report shall be sent to PECO and the NRC simultaneously, h
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t Milestones l
Dates 1 F1 Management / Cost Continuous F2 Protocol procedures 5/15/84 F3 Complete biweekly status reports Biweekly F4 Complete compliation of information 8/15/84 F5 Complete final report draft 8/24/84 F6 Issue final report 8/31/84 1
The project organization established for this independent design review is j j shown in Figure 3.
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- n INDEPENDENT DESIGN REVIEW LIERICK UNIT 1 CORE SPRAY SYSTEM ORGANIZATION l
i DIRECTOR TORREY PINES TECHNOLOGY G. L. Wessman i PROJECT MANAGER l
F. D. Carpenter TASK F ADMIN. & REPT.
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- 1 ENGINEERING /CONSTR. QUALITY ASSURANCE PFR TASK LEADER TASK LEADER COMMITTEE CHAIRMAN A. Schwartz S. Bresnick +4 MEMBERS TASK C TASK A TECHNICAL REVIEW DESIGN PROCEDURE REVIEW TASK E PFR REVIEW TASK D TASK B PHYSTCAL VERIFI- DESIGN PROCEDURE CATION WALKDOWN IMPLEMENTATION REV.
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TORREY j PINES TECHNOLOGY A ov on of GA Technologies Inc.
PO Box 85608 San Dego, Cahtornia 92138 A
TECHNICAL STAFF RESUMES l
INDEPENDENT DESIGN REVIEW OF l
LIMERICK GENERATING CTATION UNIT NO.1 l
CORE SPRAY SYSTEM PREPARED FOR PHILADELPHI A ELECTRIC COM PANY MAY 7,1984 l
OLOGY A o, vision of GA Technologies Inc. -
PREFACE This document contains resumes of selected primary technical personnel with i possible alternatives who will conduct the independent design review for l Limerick's Core Spray System. The index illustrates the arrangement of the l resumes in relationship to the project organization and established tasks.
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INDEX PAGE TPT Director G. L. Wessman 1 Project Manager F. D. Carpenter 3 Task Leaders Task A & B S. Bresnick 4 Task C & D A. A. Schwartz 6 Task E S. L. Koutz 8 F. O. Hall 10 T. R. Colandrea 12 A. M. Harris 14 R. G. Wunderlich 15 Task A & B J. G. Kelly /R. B. Patten 17/18 W. P. Malay /K. J. Baylor 19/20 Task C & D Structural F. T. Lin/R. T. Sun 22/23 I & C/ Electrical W. R. Arnold /R. G. Benham 24/25 Mechanical K. J. Tong /L. E. Penzes 27/28 ;
Piping P. K. Patel/H. D. Shatoff 29/30 l Fluid Flow J. D. Stanley /E. P. Gagnon 33/34 Walkdown C. F. Dahms/N. Kirkpatrick 35/36 P. C. Rasmussen 28 11
l GEORGE L. WESSMAN Director Torrey Pines Technology PROFESSIONAL SPECIALTY Project, functional, and business management, multi-discipline management e.sd engineering design and development.
EDUCATION B.S., Chemical Engineering, University of Minnesota, 1958 M.S., Chemical Engineering, University of Minnesota, 1964 EXPERIENCE Currently responsible for overall direction and performance of Torrey Pines Technology, the engineering services division of GA Technologies Inc.
Responsible for all phases of organization, marketing, project management and profitability.
Currently active at all levels in the development of codes and standards in the United States. This includes chairmanship of the Nuclear Standards Management Board, American National Standards Institute, Member of the American Nuclear Society's Standard:; Steering Comittee and Member of the American Nuclear Society's Nuclear Power Plant Standards Committee.
Responsible for the integration of all technical effort during the final three years of construction and startup of the Fort St. Vrain Nuclear Power Plant. This included the technical effort in mechanical, electrical, control, systems and fuel engineering and licensing. It included the aspects of analysis, design, field startup, field problem solving and -;
document control. ~
Directed company's Licensing Division during the period of time it was in the commercial nuclear steam supply system business. This included responsibility for all phases of federal and state licensing matters including discernment of trends, reviewing and comenting on draft regulatory documents, establishing licensing strategy, identifying -
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licensing risks and assisting clients to obtain the necessary permits and licenses at both state and federal levels. '
Managed the Plant Engineering Department for GA while the design for the large commercial nuclear steam supply system was developed. This included responsibility for organization, staffing, technical adequacy of the department's work a1d setting departmental policies and procedures for engineering planning, scheduling and budgeting, fluid system design, '
control, electrical and instrumentation design, system performance, safety and analysis. The project engineers for all projects were also included in the department. ..
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l George L. Wessman Page 2 Program manager for the AEC study of the large HTGR design. This program l was directed toward optimizing the design of a large HTGR power plant.
Responsible for various aspects of management of the Peach Bottom project during final construction, startup, and initial operation. This included responsibility as project engineer, site manager and project manager. As project manager responsible for steam generator repair and the design, licensing, production, delivery and installation 'of second core for the Peach Bottom Atomic Power Station Unit #1.
Technical work performed as a shielding design engineer, fluid system design engineer, nuclear engineer responsible for fuel element design and development of chemistry data required for fuel element design.
PROFESSIONAL ASSOCIATIONS Registered Professional Nuclear Engineer, California, 1977 Member, ANS Chairman, ANSI NSMB Member, ANS SSC Member, ANS NUPPSCO Chairman, ANS-40 2
FREDERICK D. CARPENTER Project Manager PROFESSIONAL SPECIALTY Project and Operations Management in nuclear, quality, and metallur-gical engineering, research development, manufacturing and facilities operation.
EDUCATION B.S., (Chemistry), San Diego State University, 1951 Graduate Studies, San Diego State University, Evenings, 1953-1957 Additional Studies, Management, Value Analysis EXPERIENCE - 32 years (26 industrial /6 government)
Professional Experience at GA Technologies Inc. (Since 1957)
Management of a Quality Assurance System Operations responsive to Company, Customer, State and Federal requirements. Functions include Quality Engineering and Quality Operations (procedures, training, audits, records procurement surveillance / inspection, cnd special processes).
Project Manager for independent design verification and quality system evaluation for a major safety system in a nuclear power plant.
Directed separate quality assurance activities for nuclear fuels development and manufacturer. Also directed Company's health physics, nuclear material manajement for special, source, and by-product mater-ials, nuclear waste processing facilities and licensing activities for special nuclear materials handling and reactor operation.
Managed Metallurgical Operations Department, responsible for in pile irradiation testing of materials, ther no-physical properties laboratory, metallographic laboratory, and a 1,000,000 curie hot cell facility for materials post-irradiation examinations.
PROFESSIONAL ASSOCIATIONS Registered Professional Engineer, Metallurgical, California,1956 Registered Professional Enginter, Quality, California, 1975 Registered Professional Engineer, Nuclear, California, 1976 .
Certified Quality Engineer, American Society of Quality Control,1974 Member, ANSI N46.2 Quality Assurance Standard Comittee RSTD Executive Comittee, American Nuclear Society, 3 years Board of Directors, International Metallographic Society, 1968 Member, Energy Element Subcomittee, County of San Diego ADDITIONAL INFORMATION
.nu thor /Co-author - 35 technical papers Holoer of four patents (3 U.S.A., 1 British) 3
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STUART BRESNICK Manager, TPT Projects-QA PROFESSIONAL SPECIALTY QA Program development, implementation and management; materials technology; LWR fuel manufacturing and technology.
EDUCATION B.E., Metallurgical Engineering, Cornell University,1962 M.S., Materials Science, Northwestern University, 1963 M.B.A., Organizational Development, Iona College, 1973 EXPERIENCE Nineteen years of engineering and management experience in nuclear-quality assurance, caterials technology and development, and LWR fuel technology.
Responsible for quality assurance on all projects under Torrey Pines Technology. This responsibility involves defining, implementing and managing QA programs for each of the engineering services projects, as well as providing direct QA support services to outside clients. The latter has included serving as the QA Task Leader for nuclear power plant independent design and construction verification programs.
GA's LWR reload fuel supply obligatioi.s which involved long-term deliveries of fabricated fuel through subcontractors.
Responsibilities included fuel contract negotiations, fuel
- procurement, contract administration, and fuel vendor surveillance.
Also provided LWR fuel consulting services, including technical and financial assessment of TMI-2 fuel damage; QA Auditing Leibstadt initial fuel core manufacturing; evaluation of damage to Surry-1 fuel; preparation and presentation of course on LWR fuel, technology and marketing of LWR fuel services.
QA Manager for Gulf United Nuclear Fuels, responsible for development and management of a QA program responsive to 10CFR50, Appendix B, for the design and manufacture of LWR fuel.
Senior metallurgist responsible for materials development, welding process and weld inspection development, and material failure analysis for LWR fuel core components.
Earlier activities included process engineering for Naval Reactor fuel, and research on the extrusion characteristics of nickel-based alloys.
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l S. Bresnick Page 2 PROFESSIONAL ASSOCIATIONS Registered Professional Quality Engineer, California, 1975 Member ASQC and ASM Chairman ASQC Energy Division Technical Publications Subcomittee Certified Lead Auditor to ANSI N45.2.23 l
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A. A. SCHWARTZ Staff Engineer PROFESSIONAL SPECIALTY Design and analysis of pressure vessels and piping.
EDUCATION Bachelor Degree - Architecture, University of Illinois M.S., Civil Engineering, Massachusetts Institute of Technology M.B.A., Univert,ity of Santa Clara EXPERIENCE Engineering task leader for the independent review and physical verification of the Waterford nuclear plant emergency feedwater l system. Coordinated the overall technical design review of Palo Verde Units 1, 2, and 3; and also served as the lead engineer for the structural review on this project. Identified the equipment to be reviewed for the independent seismic review of San Onofre Units 2 and 3; coordinated processing potential technical findings; and performed seismic review of structures, instrumentation, and mechanical I components on this project.
Prepared conceptual designs of piping systems and their supports.
Performed detailed ASME Code analysis of nuclear piping systems and
, established support loads using the computer program NUPIPE.
Determined pipe rupture locations per NRC criteria and necessity of
! pipe restraints. Evaluated piping system design criteria for adequacy and licensability.
. Responsible engineer for filter related modifications to Rancho Seco
, power plant. This effort was oriented toward reducing radiation exposure to plant personnel in six filter areas of the plant auxiliary building. It included design and analysis of new filter piping, vessel supports, shield structures and filter cartridge handling
- systems.
Responsible engineer for design of liners, penetrations, closures, and cooling water systems in concrete pressure vessels. Supervised a group of 5 engineers and 5 designers who. executed the designs of ASME Class 1, 2, and 3 vessel components. Coordinated i engineering / fabrication /
construction problem solutions, activities, and schedules. Generated safety analysis reports and supported licensing activities. Major vessel component cost reductions were achieved as a result of these efforts.
Developed designs for high temperature pressure vessels hcusing.large
, heat exchangers. Specified the extent of vessel insulation for .the j larger diameter shell sections, and the requirements for application i of the- insulation. Designed the smaller diameter shell sections to l high temperature code case rules.
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A. A. Schwartz Page 2 Lead engineer for development and qualification testing of a l circumferential prestressing system for large concrete pressure vessels. Designed anchor elements and concrete embedments, and coordinated this activity with material suppliers and equipment designers to ensure that prestressing forces could be economically and safety applied, anchored, monitored, and recorded.
' Performed stress and seismic analysis of pressure vessel shells, nozzles, heads, external supports, and internal equipment supports. ,
PROFESSIONAL ASSOCIATIONS i l
Registered Professional Engineer.
American Society of Civil Engineers.
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STANLEY L. KOUTZ Chief Engineer T
PROFESSIONAL SPECIALTY
. Management and direction of engineering organizations. Technical
, expertise in nuclear-thermal systems.
EDUCATION
! B.S., Mechanical Engineering, University of Oklahoma,1948 l
M.S., Aeronautical Engineering, Case Institute of Technology,1952 EXPERIENCE 4
Mr. Koutz is currently Chief Engineer for General Atomic Conpany, i advising the Vice-President of engineering and technology and partic-i ipating in company wide technical matters. He was previously Director of the Plant Engineering Division, responsible for the design and development of the gas cooled fission reactor power plant efforts including the high temperature gas cooled reactor system (HTGR) and i the gas-cooled fast reactor system (GCFR). He has been director of I the New Concepts Division, responsible for work on gas turbine cycle power plants, process-heat systems, heat dissipation systems, fusien power plants, and other advanced equipment related to energy i production. He also spent a year in Japan as Technical Director of the Asia-Pacific Division of General Atomic International.
Mr. Koutz served as Technical Advisor to the President of General i
Atomic from 1969 to 1971. Previously, as General Manager of the gas I
cooled reactor division, his responsibilities included the 300-MW(e) power plant design development, and startup for Public Service of Colorado, Peach Bottom gas cooled reactor activities; the gas cooled j reactor base program for the AEC; and other design and development activities for large power plants.
4 In 1963, Mr. Koutz was Manager of the new high temperature gas-cooled reactor (HTGR) Division, responsible for the design and development of larger HTGR plants, including studies under the ESADA and TARGET .
i programs. In 1962, he was rcsponsible for research and development on l l the ESADA program. He was Associate Project Manager of the HTGR '
, project, a program which led to the Peach Bottom 40-MW(e) power plant. '
In 1959, he was Head of Reactor Design for the HTGR project. In 1956, he spent four months for the company with the Institute for Atomic Energy, Kjeller, Norway, on a study of nuclear propulsion for merchant
- ships. After his return,- he began the preliminary nuclear and.
engineering analysis of the TRIGA~ test reactor series. He was later in charge of design and installation of the first TRIGA test reactors.- !
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Stanley L. Koutz Page 2 Mr. Koutz did research on gas turbines and fluid dynamics for the National Advisory Comittee for Aeronautics before joining Convair Division of General Dynamics Corporation to work on engine analysis in the aircraft nuclear-propulsion program. At Convair he worked on reactor calculations, heat-transfer problems, and power cycle analyses and took part in the critical mockup of Brookhaven National Laboratory's medical reactor.
PROFESSIONAL ASSOCIATIONS Member, American Nuclear Society Registered Professional Engineer - Nuclear - California l
1 9
FREDERICK 0. HALL Manager Mechanical & Electrical Engineering PROFESSIONAL SPECIALTY Engineering management, overall task coordination. Fluid system design, equipment selection, systems testing, troubleshooting.
EDUCATION l
B.S., Chemical Engineering, University of Pittsburgh,1952 EXPERIENCE As Project Manager, directed NSSS Class IE equipment qualification program for PP&L. This project employed 99 people in the initial phases and 33 people at audit time, and was approximately a $6 milion effort. As Project Manager, was responsible for organizational arrangement, staffing, schedule, financial control, meeting QA requirements and all client contacts. The program was completed within a schedule that was compressed 25%, under budget by 20% and resulted in PP&L passing the NRC audit the first time, with no findings.
As Department Manager, responsible for staffing all TPT contracts within the Mechanical and Electrical Engineering Department. This involves an average of six to eignt individual contracts at any one time and includes maintaining budget and schedule as well as monitoring the technical activities of the 45 engineers in the department. Included are responsibilites for technical direction and administrative control of several contracts covering equipment qualification and spare parts classification for LWR and BWR plants.
As Department Manager, responsible for directing activities in control room redesign considering human factors and emergency response facility requirements. Also directed efforts to redesign radwaste systems and handling techniques for LWR.
On special assignment, led an eight-man consulting engineering team advising American Nuclear Insurers on TMI damage claims and represented the insurance adjusters in all technical negotiations concerning the damage payments on TMI.
On special assignment, reviewed systems and accident scenarios to determine system redundancies and operating techniques which justified continued large nuclear plant operation with unqualified equipment.
Presented the results of these engineering studies to the .NRC on behalf of the plant owner.
t As Lead Engineer and later Branch Manager, responsible for design of fourteen fluid systems for a large nuclear plant. Responsible for startup and trouble-shooting of these systems in the pre-operational testing phase.
10 i
Frederick O. Hall Page 2 Responsible for interfaces between various disciplines doing large nuclear plant design.
Responsible for design, vendor follow-up and testing on steam generators, main coolant pumps, heat exchangers and reactor vessels in the Navy nuclear program.
PROFESSIONAL ASSOCIATIONS Registered Professional Chemical Engineer, California, 1973 Local Chapter Vice President, National Management Association
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THOMAS R. COLANDREA Manager Quality Assurance PROFESSIONAL SPECIALTY Analysis / assessment, development / implementation, and management of Quality Assurance Programs. Trouble-shooting of quality and metallurgical problems.
EDUCATION B.S., Metallurgical Engineering, University of Missouri at Rolla, 1959.
M.S., Engineering Science, RPI (Hartford Graduate Center),1965.
M.B.A., Management, Western New England College, 1972.
EXPERIENCE Responsible for administering, coordinating and directing the functions of Quality Assurance within the Company. These functions include the Quality Systems Department, Manufacturing Assurance, Fort St. Vrain QA activities, as well as quality program management on such programs as HTGR Technology and fusion.
Responsible for managing the nuclear quality systems and quality pro-gram management activities. These activities include quality systems development, QA procedures, QA auditing, corrective action, training, qualification and quality program management. Responsible for managing the quality engineering, source surveillance / inspection, and special processes QA (welding, heat treating, nondestructive examina-tion) functions.
Quality Systems Dept. Manager - Combustion Engineering.
Materials Engineering Supervisor - nuclear R&D - Combustion Engi-neering. -
Materials Development Group Supervisor - nuclear submarines - Electric Boat.
Metallurgical Er.gineer - jet engine materials and quality problems -
Pratt & Whitney Aircraft.
PROFESSIONAL ASSOCIATIONS Registered Professional Engineer, Metallurgical Engineering, Conn.,
1967.
Certified Quality Engineer, American Society for Quality Control, 1973.
Qualified Evaluator of Nuclear Suppliers to CASE Procedure, 1974.
Qualified QA Auditor to ANSI N45.2.23, 1974.
Registered Professional Engineer, Quality Engineering, California, 1975.
12
Thomas R. Colandrea Page 2 PROFESSIONAL ASSOCIATIONS (Con't)
Certified Reliability Engineer, Amer. Society for Quality Control, 1976.
Member, ASME Nuclear Quality Assurance Main Comittee.
Member, ASME Sub-Comittee on Personnel Qualification.
Member, ASME/ ANSI N4S.2.23 Work Group on Lead Auditor qualification.
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ARTHtR M. HARRIS Senior Technical Advisor 1
l PROFESSIONAL SPECIALTY Heat transfer analysis, stress analysis, and experimental heat transfer work for the HTGR project.
EDUCATION B.S., Mechanical Engineering, London University,1943 EXPERIENCE Responsible for the design of complete reactors (except fuel elements), including Peach Bottom, Brookwood, and Fort St. Vrain.
Engaged in the initiation, control, and evaluation of R&D work on reactor internals and mechanisms, circulators, steam generators, etc.
Reviewed reactor plant designs and evaluated gas turbine cycles for application to HTGR's. Participated in Dragon /GA HTGR information exchanges as well as ACRS meetings for Peach Bottom and Fort St. Vrain applications,.
Chief Engineer, responsible for all engineering aspects of design and manufacturing methods.
ADDITIONAL INFORMATION Holder of several U.S. patents I4
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l i RICHARD G. WUNDERLICH Manager, Component Engineering PROFESSIONAL SPECIALTY
< Engineering management.
EDUCATION B.S., Mechanical Engineering, Marquette University EXPERIEhCE Managed the management systems review portion of the Zimmer plant Independent Management Review, including comparisons with other nuclear plant management systems. Managed the review of Bechtal data and design calculations for the independent seismic design review of San Onofre Units 2 and 3.
Manager - Mechanical and Electrical Engineering Department, consisting of Mechansisms Design, Rotating Machinery, Control and Electrical Engineering, Auxiliary Process Systems Design and Experimental Engineering.
Manager - Fort St. Vrain Design Engineering Department. Responsible for all plant related engineering involved in supporting the start-up and rise-to-power of the Fort St. Vrain Nuclear Generating Station.
Manager - Systems Engineering Department. Consisted of Auxiliary Process System Design, Control and Electrical Engineering, Plant Computers and Thermal and Fluid mechanics.
Director - Quality Assurance Division during completion of FSV construction and fuel manufacturing.
Site Manager - Quality Assurance, Fort St. Vrain Nuclear Generating Station during major construction and preoperational test period.
Various engineering positions involved in the design and fabrication of concrete reactor vessel liners, penetrations and internal structures.
Various Engineering positions involved with the design, fabrication, field erection, and testing of pressure vessels and heat exchangers for the oil, chemical and nuclear industries.
15
l Wunderlich, R. G.
l Page 2 PROFESSIONAL ASSOCIATIONS Registered Professional Engineer, Wisconsin, California, Mechanical California Nuclear Member: ASME, ANS, NSPE, CSPE, American Management Association I
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JOSEPH G. KELLY PROFESSIONAL SPECIALTY Electrical and Electronic Quality Assurance EDUCATION M.A., Operations Research, Fairleigh Dickinson University, 1962 B.S., Industrial Engineering / Management, Fairlegh Dickinson University, 1959 Graduate, USN Electronic Technician Class A School, 1953 (48 weeks).
EXPERIENCE Responsible for definition and implementation of the GA Quality Program for radiation monitoring and plant protective systems. This program covered QA/QC activities during design verification, procurement, fabrication, qualification, factory testing and field service support for installation, checkout and modification operations.
Quality Project Engineer for Class 1E identification and categorization project for Cleveland Electric Illuminating Company.
Responsible for planning, directing and supervising the Quality Engi-neering Branch which was composed of three technical resource operations.
Provided required quality activities for computer / multiplex systems, instrumentation, and control systems.
Other Professional Experience Program Manager - design and construction of 3200 square feet Class 1000 clean room Director of Quality & Relisbility - relays and switches Ouality Control Manager - nuclear fuel manufacturing Senior Quality Control Engineer - batteries Quality Engineer - ordnance electro-mechanical systems Service Repair Foreman - aircraft navigation systems.
PROFESSIONAL ASSOCIATIONS -
Registered Professional Engineer - Quality, California, 1975 Certified Quality En Senior Member (ASQC)gineer,
, 1972 American Society for Quality Control, 1972 Teacher's Credential (College), California, 1975 Teacher's Credential (College), Florida, 1966 Certified Lead Auditor to ANSI N45.2.23.
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R. B. PATTEN EDUCATION Baccalaureate, Biological Sciences, Eastern Connecticut State College, 1976 Associate of Science, Liberal Arts, Manchester College, 1971 Lead Auditor Training Course - GA Technologies Inc., January 1983 Sperry Univac Computers - 1900 CADE Installation Supervisors Commands NASD License - National Association of Security Eealers - First Investors Corporation,120 Wall St., New York EXPERIENCE Walkdown inspector: Susquehanna Steam Electric Station, Unit 2, Berwick, Pennsylvania. On-site inspection of reactor control room components, data complilation for equipment qualification, and photographed components for inclusion within walkdown.
Quality Assurance - Shoreham Nuclear Power Plant, Unit 1, Shoreham, New York. Review or waldkown packages for accuracy and completeness. Walkdown reverifiction of data collected by walkdown teams, and data analysis for final report.
Initiated and currently manage the mini computer system (Sperry Univac 1900) for the litigation task force in a multi-billion dollar lawsuit.
Responsible for training and supervising 15 data entry personnel, maintenance of general software, assemblage and qualitative analysis of key data for trial preparation, coordination of program changes with computer progra=mer, and upkeep of log ledgers.
Southwest Biological Associates (1978 - 1979) Scientific Literature Research. Compilation and analysis of data for submission to the U.S.
Forest Serv.ce and the Bureau of Land Management for research projects on desert herpetofauna management. Responsibilities included: Museum and library research, writing and editing of reports on over 115 species of amphibians and reptiles, and establishing the parameters for individual species habitat occurrence maps.
Citizens Coordinate for Century 3 (1977-1979) Environmental Analysis-Office Operations. Key projects included reccarch of environmental impact of Balboa Naval Hospital, Sweetwater Reservoir, San Diego waste water manacement, and Mission Valley flood plains.
SOCIETAL AFFILIATIONS Elected Museum Associate-San Diego Natural History Museum, May 1979 American Institute of Biological Sciences, Arlington, VA San Diego Zoological Society, San Diego, CA National Wildlife Federation, Washington, DC San Diego Herpetological Society, San Diego, CA Value Line Investment Survey, New York, NY 18
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a WILLIAM P. MALAY PROFESSIONAL SPECIALTY Auditing and surveillance of quality programs including operating / refueling of commercial nuclear plants. Quality engineering - review of design I documents, quality documentation, preparation of inspection plans.
EDUCATION B.S., Mechanical Engineer, University of Wisconsin, 1949 EXPERIENCE -
Perform internal audits of quality programs of all divisions in a Lead "
Auditor capacity; prepare schedules and audit plan check lists, review and evaluate findings and corrective action, report results in exit meetings
'qd prepare audit reports.
Responsible for establishment cf quality assurance requirements in design .
disclosure documents for HTGR hardware, preparation of inspection plans, making Material Review Board decisions, siupplier evaluations.
Responsible for inspection and surveillance at suppliers plant for hardware and services for a HTGR plant; supplier surveys and audits.
Responsible for performing quality engineering tasks associated with HTGR i hardware, ano for inspections, surveys at suppliers' plants. -
Responsible for performing audits associated with operation, refueling, security, fire protection at San Onofre nuclear plant. Responsible for ]a performing inspections on plant repairs and modifications. 1 Responsible for performing resident engineer tasks at a naval nuclear :
construction shipyard; equipment installation and checkout, plant testing, '
refueling.
PROFESSIONAL ASSOCIATIONS j
Certified Quality Engineer, ASQC, 1975 Professional Engineer, Quality Engineer, California, 1978 "
Member, American Nuclear Society Professional QA lead Auditor, L. Marvin Johnson, 1976 Qualified ,: valuator of Suppliers, CASE,1974 Qualification & Certification, Welding Inspector, AWS,1979
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KATHERINE J. BAYLOR PROFESSIONAL SPECIALTIES Equipment Qualification - Quality Assurance Requirements - Radiation shielding, reactor core / fuel cycle analysis.
EDUCATION B.S., Physics, Pennsylvania State University, 1952 Probabilistic Risk Assessment Seminar, 1980 Quality Assurance Course, 1983 EXPERIENCE Responsible for evaluation of NSSS Class IE equipment for compliance with federal regulatory qualification standards. Analyzed effects of environmental conditions on NSSS Class 1E equipment for Susquehanna Units 1 and2(PP&t.).
Reviewed quality assurance procedures and their implementation in design drawings and documents for compliance with federal regulatory standards in the design and construction of nuclear power plants: San Onofre Units 1 and 2 (SCE); Palo Verde Units 1, 2, and 3 (APSC); Waterford Unit 1 (LP&L);
Ma"bleHillUnits1and2(PSI).
Compiled and maintained data base of effects of nuclear radiation on reactor materials, components, and systems.
Determined sources of radioactivity using piping and instrumentation diagrams and performed analysis of potential radioisotope leakage to environment and equipment.
Calculated radiation absorption rates from PWR components and systems and determined shielding specifications for personnel and equipment in containment, auxiliary, and radwaste buildings.
Participated in thermal stress analysis of reactor fuel block.
Constructed analytical models and calculated reactor performance characteristics including mass flows, recriticality of slumped cores, power distribution in fuel rods, effect of steam entry on recriticality, and sensitivity of performance to reactor variables such as pressure drop, temperature, fuel composition.
Designed electrical coil experiment to measure melting points of metallic materials in electromagnetic fitid.
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Katherine J. Baylor Page 2 EXPERIENCE (Continued)
Analyzed aerodynamic heating of missiles and aircraft at supersonic velocities and calculated resulting fuel heating and losses.
Tested jet engine electronechanical control components for ability to meet pressure, tension, and electrical specifications.
PROFESSIONAL ORGANIZATIONS Member, American Nuclear Society Member, American Society for Quality Control 21
FREDERICK T. LIN PROFESSIONAL SPECIALITY Structural design and analysis, piping analysis,. seismic analysis of nuclear power plaats, structural design.
EDUCATION B.S., Agriculture Engineering, National Taiwan University,1955 B.S., Civil Engineering, University of Missouri,1959 M.S., Structural Engineering, Purdue University,1961 l EXPERIENCE Performed stress analysis of Class 1 piping safety injection lines for San Onofre Nuclear Generating Station and Palo Verde Nuclear Generating Station.
Performed seismic analysis and prepared a Design Report of underground prestressing concrete pipes for nuclear service cooling water system, Korea Nuclear Units 5 & 6.
Author of design reports (equivalent to FDAR & FSAR) on structural design of containment building and fuel building, Korea Nuclear Units 5 and 6.
Performed structural analysis of nuclear core support structures using three dimensional finite element analysis code.
Acted as structural project engineer for Japan EPOC nuclear project study. Designed nuclear power plant structures and facilities.
Designed comnercial and residential buildings.
Directed and supervised the construction of material handling storage rack structures. Designed industrial plant and highway bridges.
PROFESSIONAL ASSOCIATIONS Registered Professional Engineer, Civil, California, 1968 Registered Professional Engineer, Structural, Illinois, 1965 Registered Professional Engineer, Civil, Illinois, 1964 Member, American Society of Civil Engineers ADDITIONAL INFORMATION Speak and write fluent Japanese and Chinese. Understand Spanish for daily conversational use.
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RU-TSUNG SUN PROFESSIONAL SPECIALTY Very familiar with finite element stress analysis on mechanical and thermal loading. Familiar with ASME Boiler and Pressure Vessel Code,Section III. Familiar with piping analysis.
EDUCATION B.S., Civil Engineering, National Cheng Kung University. Taiwan,1963 M.S., Civil Engineering, Wayne State University, 1966 .
M.S., Engineering Mechanics, University of Michigan,1969 Ph.D., Civil Engineering, University of Michigan,1974 EXPERIENCE Five years of experience in design and analyis of prestressed concrete reactor vessels. Work nvolved in the following areas: Design and analysis of PCRV in cong,11ance with ASME Code,Section III, Division 2; performed 2-0 and 3-0 finite element stress analysis under various environmental conditions; performed 2-0 and 3-0 thermal and thermal stress analyses; 2-0 axisymetric crack analysis for PCRV PCRV ultimatc load analysis; correlations between analytical creep r;esults and measured sensor data for Fort St. Vrain PCRV structural response; developed
- new concrete creep model by using Maxwell and Kelvin elaments in series, use non-linear curve fitting to determine the material variables from the test data, computer material subroutine for three dimensional finite t,ement analysis was developed and verified, test data was used again to validate the theoretical development; PCRV model design and analysis.
PROFESSIONAL ASSOCIATIONS / HONORS.
Chi Epsilon, University of Michigan Member of American Concrete Institute Registered Professional Civil Engineer, California 23
WILLIAM R. ARNOLD PROFESSIONAL SPECIALTY Reactor protection and instrumentation systems: design a1d analysis, operation, startup, trouble shooting, and equipment qualification.
EDUCATION BSEE, University of Texas,1958.
Graduate Courses Electrical and Nuclear Engineering.
EXPERIENCE Review of qualification data for safety-related equipment for PWR projects. Responsible 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 systems. Accomplishments included logic design, cabling, custoner liaison and review of specifications and layout for compliance with applicable NRC design criteria.
Electrical design of acrospace launch control hardware and systems.
PROFESSIONAL ASSOCIATIONS Registered Control Systems Engineer, California, 1975.
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ROBERT G. BENHAM PROFESSIONAL SPECIALTY Auxiliary electric power systems for nuclear power plants.
Project engineering for nuclear power plants.
EDUCATION B.S., Electrical Engineering, Washington State University,1950.
EXPERIENCE I
l Currently a senior consultant on nuclear plant electrical systems and equipment. Technical liaison representative to the Westinghouse large rotating apparatus division, developing a 30,000 HP variable speed synchronous motor for the main helium circulators in gas-cooled reactors.
Responsible for design and installation of the Alternate Cooling Method (ACM) system at the Fort St. Vrain nuclear plant. This system consisted of a 2500 KW diesel generator, 4160V switchgcar, 480V switchgear, protective relaying system, underground and in- plant distribution systems and power transfer switches at critical reactor cooldown equipment locations.
Responsible for the engineering content of standard plant proposals and coordinated evaluation of all technical bid specifications.
Coordinated engineering requirements for the Fort St. Vrain project by interfacing with the utility, A/E, and the NRC.
Designed all Nuclear steam supply system electrical systems and coordinated these with A/E balance-of-plant electrical designs.
Managed control and electrical engineering for production reactor operations.
PROFESSIONAL ASSOCIATIONS Senior Member of IEEE, Member, San Diego Section of ANS, Member, IEEE Nuclear Power Engineering Comittee. Member, ANS Nuclear Pcwer Plant Standards Comittee.
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R. G. Benham Page 2 ADDITIONAL INFORMATION His long experience with the IEEE Nuclear Power Generating Comittee provides him with unique expertise in applying IEEE nuclear standards and related NRC regulatory guides to nuclear power plants. As the IEEE representative to the ANS Nuclear Power Plant Standards Comittee l
he understands tha interaction between IEEE and ANS related nuclear standards.
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KAI J. TONG PROFESSIONAL SPECIALTY Design and analysis for creep and fatigue damages and creep instability for pressure vessel and piping at elevated temperatures.
EDUCATION B.S., Civil Engineering, Hon Kong University, 1959 M.s., Engineering Mechanics, Stanford University, 1961 Ph.D., Aeronautic and Astronautic Engineering, Stendard University, 1968 EXPERIENCE Senior Section leader - Responsibilities include the design and analysis of CAHE and steam generator primary pressure boundary, including the feedwate r, hot r% eat, cold reheat and superheat penetrations of the HTGr, as well as tho elastic and inelastic nnalysis of pressure vessels using finite element methods such as MARC, Same-Tepc and SAP-IV. Also involved in ASME Code work on Section III and it's code Cm N-47 which includes design rules on creep / fatigue and strain limits, and Code Case N-253 for Class 2 and 3 vessel and piping at elevated temperature service.
Technical Staff - Design and Levelopment Laboratory: Responsibility involved stress analysis and structural dynamic analysis of rocket engine components and space vehicle, specifically oa L a r itdale Decent Engine of Apollo project, space satellites model 35 and project 777.
Technical Staff - Vulnerability and Hardness Laboratory: Phenomenology studics and development of theoretical and empirical method for ,
prediction on ground shock induced by nuclear weapon detonation establishment of design criteria regarding ground shock nuclear environment; assessment of survivability and hardness of the upgrade Minuteman, and monitoring test projects and research progrars for U.S.
Air Force (SAMS0).
Engineer - Stress analysis of nuclear reactor components such as steam generator and containment vessel for HTGR at Peach Bottom.
PROFESSIONAL ASSOCIATI0:13 Member of Pressure Vessel and Piping Committee of ASME, Nuclear Power Division.
Chairman of Task Force on Component Support at Elevated Temperature Service, ASME Section III, Division I.
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LESLIE E. PENZES PROFESSIONAL SPECIALTY Stress, seismic and flow-induced vibration analysis.
EDUCATION Dip. Eng., Mechanical Engineering, Technical University of Budapest, 1952.
M.S., Applied Mechanics, Rensselaer Polytechnic Institute,1960.
Ph.D., Applied Mechanics, Rensselaer Polytechnic institute,1971.
EXPERIENCE Performed seismic analysis of nuclear reactor components.
Development of seismic model tests.
Performed stress analysis of reactor shield and different components of nuclear steam generators.
Testing life prediction of the high-temperature steam generator tubes.
Testing alternate materials of the nuclear reactor steam generator based on stress allowables.
Performed hydrodynamic and fluid-elastic stability studies, pump-induced vibration, creep buckling.
Development of a shell vibration and buckling computer program (MEVBA).
Pump designs, vibration and stress analysis of pumps.
PROFESSIONAL ASSOCIATIONS Regfstered Professional Mechanical Engineer, California, 1976.
Registered Professional Mechanical Engineer, Connecticut, 1973.
Registered Professional Mechanical Engineer, New York,1975.
Member, AIAA.
Member, Acoustical Society of America.
Member, Sigma X1, Visiting Professor of San Diego State University.
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P. K. PATEL Staff Engineer PROFESSIONAL SPECIALTY Stress analysis, nuclear as well is non-nuclear conponents, stractures, and piping.
EDUCATION B.S., Mechanical Engineering, University of Baroda, India,1962 M.S., Mechanical Engineering, University of California, Berkely, 1964 D. Engineering Science, Applied Mechanics, Columbia University, New York, New York 1970 EXPERIENCE Lead engineer on work related to Class 1, 2, and 3 piping design and stress analysis. Work involved flexibility analyses, heat transfer analyses, dynamic analysis and fatigue damage calculations.
Provided technical support in nuclear plant design and optimization -
studies.
Participated in steam generator tube bundle stress analysis.
Generated response spectra curves for nuclear plant in accordance with NRC Guidelines.
Participated in innovative pressure vessel design concepts. Involved -
in pressure vessel closure design and testing. Actively participated in drafting design rules for Class 1, 2, and 3 components operating in elevated temperature regime. .
Responsible for dump heat exchanger stress analysis report (Class 1).
Performed stress analysis on a cold trap (sodium purification system) to comply with the Class 1 Code requirements.
PROFESSIONAL ASSOCIATIONS Registered Professional Engineer, Mechanical, California,1976.
Member, American Society of Mechanical Engincors.
Member, ASME Working Group on Creep Analysis. ,_
Member ASME Task Force ADDITIONAL INFORMATION Patent on multilayer pressure vessel design.
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HERBERT D. SHAT 0FF PROFESSIONAL SPECIALTY Stress analysis of nuclear pressure vessels, structures, and piping, including thermal and dynamic loading. Linear and nonlinear seismic analysis of nuclear plant components. Development of two- and three-dimensional finite element codes.
EDUCATION B.S. Mechanical Engineerfng, Lehigh University,1960 M.S. Mechanical Engineering University of Colorado, 1963 Ph.D. Solid Mechanics, University of California at San Diego 1972 EXPERIENCE Responsible for core seismic analysis program. This includes planning and directing the program for seismic analysis of the graphite core as well as developing analytical methods, also includes considerations of statistical variations in test results for the core seismic testing program and sensitivity of comptuer corr:lations. Design review of structural design and analysis for concrete and steel vessels, piping systems, seismic qualification testing, etc.
Performed analysis of all types of ASME code nuclear pressure vessels supports and piping systems using criteria of Section !!! and VI!! by hand calculation and finite element methods. Developed techniques to expedite processing of the results of nuclear pressure stress analysis. Developed two-and three-dimensional finite element stress analysis computer codes for mechanical and thermal loading.
Developed seismic qualification testing criteria for components and piping systems.
PROFESSIONAL ASSOCIATIONS Registered Professional Engineer (Mechanical) California.
Member, ASME.
PUBl,! CATIONS
" STRESS 3 - A Computer Program to Combine Stresses for Comparison with ASME Code Nuclear Vessel Stress Limits," Gulf General Atomic GAMD-9644, 20 August 1969.
"The Finite Difference Solution to the Cylinder with a Linear External Taoer." Gulf General AtWr PA9707, 21 MJey 10!?.
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Heroert D. Shotoff b Page 2 '
PUBLICATIONS (Continued)
"A Consistent Numerical Method for the Solution of Nonlinear Elasticity Problems at Finite Strains." with S. Nemat-Nasser, SIAM 20 (1971) pp.
462-481 Tech. Report 2, ORN, Dept. AMES, UCSD, January 1970.
" Numerical Analysis of Pre- and Post-Critical Response of Elastic Continue S at Finite Strains." Presented at the National Symposium on Computerized Structural Analysis and Design at George Washington University, Washington, D.C., March 1972. Pubitshed in Comouters and Structures Pergamon Press.
"$AFE PACE - A Computer Program for the Structural Analysis of Two- -
Dimensional Plant Configurations with In Plano Loading," Part ! Basic =
Development, Part !! User's Manual, Gulf General Atomic GA-10246, 5 October .
1970.
"!NFMAT - A Computer Program for the Direct Cholesky Solution of Sets of Symmetric Linear Algebraic Equations with large Bandwidths," Gulf General Atomic 3AMD-10496, 27 October 1970.
" Preliminary Investigations for the ' Mixed' 3-Dimensional Higher Order -
Finite Element Program," Gulf General Atomic GAMD 10566,1 April 1971.
"AXIPACE A Computer Program for the Structural Analysis of Two-Dimensional Axisymetric and Plano Configurations with Axisym, metric and f
Plane Loading," a User's Manual, Gulf General Atomic GA-10603,16 March 1971.
" SAFE-SOLIDS - A Computer Program for the Structural Analysis of Three-Dimensional Configurations - Version I," A User's Manual Gulf General Atomic GA-A12060, 3 November 1972.
" Stress Analysis for PSC Helium Circulator, Tort St. Vrain Nuclear Generating Station," Gulf General Atomic GADR-13, 1 February 1971, contributor and compiler.
"On Numerical Solutions of Nonlinear Elasticity Problems," Ph.D. i dissertation, University of California at San Diego 1972.
"SHELL PACE - A Subsructured Computer Program for the Structural Analysis of Two Dimensionc1 Plane and Axisymetric Shells and Solids," a User's Manual, Gulf General Atomic.
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i "Three Dimensional Elastic Finite Element Analysis Using Gradient Degrees '
of Freedom with Node Order Mixture." Presented at the 2nd International 2 Conference on Structural Mechanics in Reactor Technology, Berlin, September 1973.
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l Herbert D. Shatoff Page 3 l
PUBLICATIONS (CONTINUED)
SAC Manual - A User's Guide to the SAC program (for the stress analysis of axisymmetric pressure vessels with axisymmetric leads), Gulf General Atomic GAMD-9710, 4 August 1969.
" Core Seismic Verification Plant," General Atomic Co., GA-A13934 April 1976.
" Approximation of Corner and Edge Lands from HTGR Core Seismic Analysis Code." General Atomic Company, GA-A14247 April,1977.
"Use of the MARC CoJo for Thermal Barrier Cover Plate Creep Analysis,"
General Atomic Company Report, June,1977.
" Nonlinear Dynamic Analysis of Prismatic Elements for High Temocrature Gas-Cooled Reactor Coros," for the 5th International Conference on Structural Mechanics.
" Core Seismic Verification Status Report," General Atomic Co., GA-A14012, June 1979.
- $"FR Seismic Development Plan Scope," General Atomic Co., GA 014096, March 1979.
1 32
JAMES D. STANLEY PROFESSIONAL SPECIALTY Systems engineering, balance of plant design. A-E liaison, pipirg, and mechanical equipw nt.
EDUCATION 0.S., Mechanical Engineering, Wayne State University,1949 EXPERIENCE Responsible for reactor process steam / cogeneration and process heat plants penitininary design and economics.
Responsible for gas turbino project balance of plant design and plant a.ost ostimates.
Performed systems engineering, A-E liaison and piping design for nuclear reactor 90 wor plant projects.
Sito construction, pro. core testing, and plant startup engincor for Peach Bottom I nuclear power station.
Rosponsible for Peach Gottom I nuclear power station steam generators, hollum circula tor s, primary coolant piping and reactor auxiliary systems.
Responsible for synthetic rubbar plant and missile test fact 11tles piping and mechanical design.
Missile test factl-ty
- construction sito engineer. .
Perfcrmed piping and mechanical design, refinery and potrochemical plants.
Performed process piping and rmchanical design, urantum enrichnont plants.
PR0fES$10flAL ASSOCIAT!0riS/tt0t10RS Registered Professional Mochanical Engincor, California, 1969 Member, ASME 33
ERROL P. GAGNON PROFESSIONAL SPECIALTY Licensing, safety criteria and technical specification preparation and review.
EDUCATION B.S., Engineering, San Diego State University, 1965 PROFESSIONAL EXPERIENCE AT GENERAL ATOMIC COMPANY (Since 1969)
Chairman of the Results Review Committee of the Human Factors Evaluation program for the Palo Verdo Nuclear Power Generating Station control room and responsible for coordination of the program tasks.
Developed safety / licensing positions and critoria for various applications of nuclear power plants.
Evaluated nuclear power plant systems and components to identify and prioritizo technical, safoty and licensing issues.
Developed nuclear power plant transient performance specifications.
Senior Technical Representativo at Fort St. Vrain rcsponsible for technical coordination and guidance on the conduct and evaluation of the startup test program.
Manager of the French Licensoo Program responsible for the administrative and technical-transfer aspects of the nuclear power plant Itcensing agreements and contracts.
Performed simulation studios and evaluations of nuclear power plant transient serformance/ safety analyset, control systems, control room configurations and plant startup procedures.
OTHER PROFES$10NAL EXPERIENCE General Dynamics Corporation (19651969). Performed dynamic analyson of missilo control systems.
PR0fES$10NAL ASSOCIATIONS / HONORS Mombor, American Nuclear Society 34 ..
CHARLES F. DAHMS PROFESSIONAL SPECIALTY Stress Analysis Relating to the Design and Failure of Structures at Elevated Temperatures EDUCATION AND PROFESSIONAL ASSOCIATIONS B.S., Engineering, University of California at Los Angeles, June 1981 Registered Engineer-in-Training, California, 1981 EXPERIENCE Inspected boilers located at fossil fuel power plants in order to perform a system stress analysis on the superheater and reheater piping. Conducted computer analysis of the piping layouts and support systems which assisted in a failure analysis program which studied the problems of dissimilar metal weldments and their uses in steam generator tubing.
Performed inelastic stress analysis which studied the effects that varying the ratio of axial to hoop stress had on the relaxation of 2-1/4Cr-1Mo ferritic steel at elevated temperature.
Assisted in sensitivity study of heat exchanger tube life considering the effect of material recrystallization on creep and stress-rupture properties. This included the modification of programs to incorporate the effects of recrystallization.
Assisted in stress analysis performed on core support structures for an HTGR and GCFR. Assisted in the documentation of stress analysis programs.
Performed plant walkdown at a PWR power plant in order to verify construction tolerances. This was a detailed inspection which compared various piping systems, valves, and equipment to the latest as-built drawings.
Performed seismic design technical reviews on various structures and components of a PWR power plant. Prepared procedures and assisted in coordinating documents for the review.
Performed plant walkdown at a BWR power plant in order to verify Class 1E electrical equipment for a qualification program. Assisted in preparation of program procedures and instructions and clarified information given to the engineers.
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NORBERT KIRKPATRICK PROFESSIONAL SPECIALTY Quality Field Representative.
EXPERIENCE s .
Twenty years in industry, including thirteen years in the field of Nuclear Power and Quality Assurance.
Professional Excerience at General Atomic Company (Since 1963)
Quality Assurance Analyst - HER Programs and Fort St. Vrain Support - perform review of procedures, drawings, records, and source inspection planning. This responsibility also includes , .
quality source surveillance, review and verification of the supplier's manufacturing and quality compliance of documents and records; also assist or reconsnend to the supplier, ways and means to meet the quality requirements of General Atomies Quality Assurance Manual.
Cognizant QA Inspector - Surveillance and Inspection of Rotating Machinery: Performed supplier survaillance and witnessed test operations for pumps manufactured for the Fort St. Vrain Plant.
Inspected steam turbine and compressor blades for the Fort St.
Vrain helium circulators. Performed surveillance and witnessed rotational testing of prototype helium circulator for Fort St.
Vrain plant. Directed the tear down and refurbishment of the Fort St. Vrain helium circulator.
Was responsible for Field Inspectors and all field inspection activities such as piping, piping restraints, equipment installation, electrical components and cable installation, receiving inspection, and .0E examination; also Cognizant Inspector on the removal and installation of nuclear components.
This required the coordination of quality documents and requirements between craft personnel and the GAC engineering and construction branch, the review and acceptance of craft action operations within the work authorization and field change notice.
Mechanical Inspector - This position required the dimensional inspection of complex machining operations and set-ups which required the use of sine plates, height gauges, rotabs, etc.
During the six and one-half years on the shop floor, was Welding Inspector for three years in the areas of ASME Code fabrication, welding fit-up, and welder qualification and testing.
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4 Norbert Kirkpatrick page 2 EDUCATION San Diego City College, San Diego, California,1962 to 1967 Degree: Associates of Arts (Social Sciences).
Additional classes: Blueprint reading, tool design, slide rule, math (three semesters; one review and two of shop math), quality control concepts and engineering, and introduction of nondestructive testing (24 units).
PROFESSIONAL ASSOCIATION Member, American Society for Quality Control (ASQC).
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PETER C. RASMUSSEN 1
1 PROFESSIONAL SPECIALTY Design and analysis of reinforced concrete and steel structures.
EDUCATION B.S., Civil Engineering, Iowa State University 1981 EXPERIENCE Technical Graduate Program - Responsibilities included analysis of piping supports, floor slabs and secondary shield walls in the seismic review of the San Onofre Nucleatr Generating Station. Other responsibilities included finite element stress analysis of fuel blocks for the HTGR.
PROFESSIONAL ASSOCIATIONS Member of the San Diego Chapter of ASCE.
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TORREY J PINES TECHNOLOGY 4 A r>wwn of GA Technologies Inc.
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PO Box 85608 San Dego Ca4fcenia 92138