ML20100D718
| ML20100D718 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/22/1985 |
| From: | SARGENT & LUNDY, INC. |
| To: | |
| Shared Package | |
| ML20100D707 | List: |
| References | |
| PROC-850322, NUDOCS 8504030116 | |
| Download: ML20100D718 (173) | |
Text
SARGENTS LUNDY O
PROGRAM PLAN FOR HOPE CREEK INDEPENDENT DESIGN VERIFICATION PROGRAM i
PUBLIC SERVICE ELECTRIC AND GAS COMPANY l
l l
l 8504030116 850329 PDR ADOCK 0500 4
Controlled Copy No. 26 A
SABOENTS LUNDY Program Plan for Hope Creek i
Independent Design Verification Program REVISION 0 3/22/85 TABLE OF CONTENTS Page I.
Introduction I-l II.
Compliance with Program Requirements II-l A. Objective 11-1 B. Independence II-1 C. Design Review Experience 11-1 D. Review Team 11 - 1 E. Interfacing II-2 F. Use of Data 11-3 G. Work Output II-3 III.
Scope and Approar.n to Work III-l A. Tasks 111 - 1 1.
Finalize Program Plan and O
Report Outline III-l t
l 2.
Prepare Project Manual 111 - 1 3.
IDVP Kickoff Meeting 111-1 4.
Assemble Design Requirements, Design Control and Interface Documents, and i
Design Documents III-2 5.
System Walkdown III-2 6.
Electrical Design Review III-3 7.
Instrumentation and Controls Design Review III-3 8.
Mechanical / Structural Design Review III-3 9.
Environmental Qualification and Pipe Break Analysis Review III-3 l
- 10. Design Control Process Review III-3
- 11. Review of Observations III-9
- 12. Prepare Interim Report III-9
- 13. Prepare and Issue Final Report III-9
- 14. Project Administration III-10 I
IV.
Project Schedule and Controls IV-1 A. Project Schedule IV-1 B. Project Controls and Reporting IV-1 V.
Organization V-1 A. Project Team V-1 B. Internal Review Committee V-3 g
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SARGENTE LUNDY 11 REVISION O 3/22/85 Page VI.
Qualifications and Experience VI-l A. Direct and Related VI-l B. Nuclear Design Experience VI-1 VII.
Protocol VII-l VIII.
Resumes VIII-1 A. Project Team VIII-1 B. Internal Review Committee VIII-2 C. Senior Review Committee VIII-3 APPENDIX A. Quality Assurance Program Plan B. Forms and Sample Checklists C. Glossary D. System Selection Criteria
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SARGENT& LUNDY Exhibits
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EVISION O 3/22/85 III-l Precedence Diagram III-2 Sequence of Design Review Activities III-3 Processing of Observations III-4 Prepared Project Documents III-5 Project Design Requirements III-6 Documents Required for Design Control and Interface Adequacy Review III-7 Required Design Documents III-5 Preliminary Final Report Outline V-1 Sargent & Lundy Hope Creek IDVP Organization V-2 Hope Creek Team Personnel VI-l Operating BWRs Sargent & Lundy is Currently Servicing VI-2 Experience Complying with Audits and Design n
Reviews
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VI-3 Nuclear Units Authorized for Design by Sargent & Lundy O
s SARGENTS LUNDY I. Introduction 1-1
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REVISION 0 3/22/85 This program plan for the Hope Creek Generating Station (Hope Creek) Independent Design Verification Program (IDVP) describes the scope and approach to work; the schedule for carrying out the work and the project controls Sargent & Lundy (S&L) will employ to manage the project; the project team, Internal Review Committee and Senior Review Committee, and S&L's qualifications and experience.
The Program Plan is described in Chapters !! through VIII.
Chapter II, Compliance with Program Requirements, discusses how S&L will meet the requirements outlined in section II of the Hope Creek Generating Station Independent Design Review Work Scope Document (Work Scope Document) transmitted by Mr. J. P. Boyle's (PSE&G) letter of November 14,1984, to Mr. L. E. Ackmann of S&L, l
O subsequent meetings with PSE&G on February 11 and I C February 12,1985, and agreements between PSE&G and the Public Advocate of New Jersey.
Chapter 111, Scope and Approach to Work, discusses how S&L will carry out the design review. It also includes a precedence diagram of the key events leading to issuance of the final report.
Chapter IV, Project Schedule and Controls, includes a discussion of the project schedule, the precedence network diagram, and S&L's approach to monitoring progress on this project.
Chapter V, Organization, contains a description of S&L's company organization, project team approach, identi-fication of key personnel, and the strengths the project team will bring to this review.
In Chapter VI, Qualifications and Experience, S&L presents our experience on similar recent projects.
Chapter VII, Protocol and Forms, includes the communication protocol to be used on the project.
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SARGENTS LUNDY I-2 REVISION 0 O
3/22/85 Chapter VIII, Resumes, includes the resumes of the key project team members and the Senior Review Committee members.
O O
SARGENT& LUNDY II. Compliance with Program Requirements 11-1 O
REVISION 0 C
3/22/85 A. Objective The Independent Design Verification Program (IDVP) is a design review to provide additional assurance that the design of the Hope Creek Power Station meets licensing requirements, through a review of the technical adequacy of selected systems and the design process, including both vertical and horizontal-type reviews.
B. Independence Prior to this IDVP assignment, Sargent & Lundy has never had any contractual relationship with PSE&G, Bechtel, or GE relative to Hope Creek. Furthermore, the key team members (see Exhibit V-2) have not had any direct engineering involvement with the Hope Creek engineering and design activities in the last five years. To support this statement each member of the IDVP team will sign an IDVP agreement and questionnaire (see Appendix B). In addition, the Sargent & Lundy partnership does not jointly hold PSE&G, Bechtel, or GE stock or ownership. Therefore, S&L is independent from previous Hope Creek engineering and design activities.
C. Design Review Experience Sargent & Lundy is one of the largest multi-disciplined, full-service architect-engineering firms in the country. We have been a leader in the design of electric generating plants since 1891.
Sargent & Lundy's participation in the nuclear industry began in 1955. Sargent & Lundy has been involved with the complete integrated design of 24 nuclear power plants. A listing of the nuclear units we have designed is included in Chapter VI(see Exhibit VI-3). Sargent & Lundy has been involved with eleven independent design verification or design review programs involving ten nuclear units during the past 5 years (see Exhibit VI-2).
D. Review Team Sargent & Lundy brings to this project a team that is experienced in the design and the design review of BWRs.
The Project Manager will be S&L's primary technical and commercial interface with PSE&G and its other contractors. A detail discussion of S&L's organization for this project can be found in Chapter V.
Sargent & Lundy will establish an Internal Review Committee and a Senior Review Committee which will be responsible for reviewing and making recommendations regarding the disposition of observations and potential A)
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findings identified by the project team. The Internal Review Committee will consist of Departmental Design Directors for the major engineering disciplines and the head l
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11-2
(] SARGENTSLONDY REVISION O V
3/22/85 of our Quality Assurance Division as chairman. The Senior Review Committee will consist of Department Managers for the major engineering disciplines, their assistants as alternates and the Director of Engineering as chairman.
E. Interfacing All interf acing with personnel from PSE&G, Bechtel, GE, other contractors, and the NRC will be in accordance with the communication protocol. (See Chapter VII.)
The S&L program plan precedence diagram (Exhibit III-1) graphically shows the flow of work activities. This diagram is supplemented by Exhibit III-2, Sequence of Design Review Activities, and Exhibit III-3, Processing of Observations. A discussion of each task in the plan is found in Chapter III, Scope and Approach to Work.
Following the initial preparation tasks a meeting will be held in Bechtel's San Francisco office to review the objective, intent, scope, and administration of the IDVP.
Information will be supplied to S&L during Task 4.
Telephone and written requests may be made during that period. The engineering and design review and analysis will be performed in S&L's Chicago offices. However, meetings involving key S&L team members are anticipated to take place in San Francisco and San Jose as necessary to clarify, l
with personal interviews, the design documents supplied in Task 4. Additionally, a meeting is anticipated at the Hope Creek site for reviews, clarifications, and interviews.
I Other meetings and telecons will be held as needed.
The Hope Creek plant familiarization tours and systems' walkdowns (Task 5) will be held during the review phase. During the review phase, reporting of observations
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and potential findings will occur. Exhibit III-3 shows the procedures for processing these items.
For the purposes of this Independent Design i
Verification Program, S&L will be reviewing design l
interfaces at General Electric, Bechtel Power Corporation, PSE&G and other subcontractors as appropriate. This process will involve meetings, telecons, and correspondence as appropriate to accomplish the design verification.
A l U Sargent & Lundy will prepare and distribute required communication and record keeping documents per the protocol.
SANSENT& LUNDY ll-3 7
REVISION 0 (V
3/22/85 l
F. Use of Data Sargent & Lundy will hold all proprietary design codes, information, and methods received from Bechtel, GE, and any other engineering or equipment firm in the strictest confidence. Sargent & Lundy will not make use of this information other than in performing the IDVP work and will release it only to S&L employees requiring such information. Sargent & Lundy will return or destroy all material received at PSE&G's direction.
G. Work Output During the course of this work, S&L will provide the following documents to PSE&G and others as provided in the protocol.
o Bi-weekly status reports o A work schedule o Notes of meetings, telecons, and correspondence 3
o Written documentation of observations and
,/
potential findings o An interim report (by approximately May 24, 1985)
A final report (by Aug. 2,1985) o OV
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SARGENTS LUNDY IIL Scope and Approach to Work 111-1
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REVISION 0 V
3/22/85 Our approach to work is shown on the precedence diagram (Exhibit III-1).
The sequence of activities on Tasks 6,7,8,9, and 10 is shown in Exhibit III-2. We will process observations as shown in Exhibit III-3.
A. Tasks Task 1. Finalize Program Plan and Report Outline The submittal of this program plan including the report outline (see Exhibit III-8) completes S&L's action for Task 1.
Task 2. Prepare Project Manual In order to properly control engineering assignments, S&L will provide PSE&G with a project manual. The project manual includes the following:
o Program plan Organization chart Schedule i
o Man-hour estimate d
o Project administrative instructions o Project instructions Project administrative instructions are prepared to cover interfaces between S&L and PSE&G, its contractors and NRC that are not quality assurance related. Project instructions are project-specific quality assurance procedures. The remaining sections of the project manual include the Program Plan including organization chart and schedule, and a man-hour estimate. The planned project documents are identified in Exhibit III-4.
The project manual will be issued to PSE&G for comments and will be revised to incorporate these comments. Additional sections are added to the project manual as work is assigned. This manual ensures that all quality-related work meets the requirements of S&L's Quality Assurance Program as outlined in Appendix A.
The S&L Project Manager is responsible for setting up l
the project manual and ensuring that all project personnel are properly instructed in its use.
Task 3. IDVP Kickoff Meeting S&L attended the IDVP kickoff meeting held in Bechtei's offices on Jan. 30, and 31,1985.
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SARGENTS LUNDY 111-2 p
REVISION O U
3/22/85 Task 4. Assemble Design Requirements, Design Control and Interface Documents, and Design Documents The timely completion of this project requires that S&L obtain all relevant design requirement documents design control and interfacing documents, and design documents on the designated systems and structures from PSE&G and BPC within 4 weeks af ter identification of those systems. These documents will include, but not be limited to, those listed on Exhibits !!!-5,111-6, and III-7.
Following the receipt of the design requirements, design control and interface information, and design documents, the detailed design review of elements of the selected systems will begin. These reviews will follow the sequence shown in Exhibit III-2.
Task 5. System Walkdown Sargent & Lundy's Project Manager and key personnel (d
N will perform systems walkdowns to familiarize themselves with the plant. They will use the procedures and checklists prepared as identified in Exhibit III-4 to confirm:
o That the designated systems are configured in the manner for which they were designed.
o That the characteristics used in the design have been properly established and utilized and that the criteria has been applied to the configuration as intended.
The walkdown will visually verify that the selected components, piping and supports have been installed in proper relative positions. Selected components and supports will also be examined to verify such details as relative sizes, weld types, and attachments to the structure.
There is no intention for these walkdowns to include material selection, application, fabrication, examination or inspection, or the pre-service inspection requirements that may be applicable, or the'taking of detailed measurements.
PSE&G and BPC will provide working facilities at the site, the necessary personnel to escort the team within the plant, access in the form of ladders or scaffolding and any required training in plant safety and security.
SARGENTS LUNDY 111-3 REVISION 0 p).
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3/22/85 Task 6. Electrical Design Review Task 7. Instrumentation and Controls Design Review Task 8. Mechanical / Structural Design Review Task 9. Environmental Qualification and Pipe Break Analysis Review Task 10. Design Control Process Review The activities for Tasks 6 through 10 described here have been organized to allow a thorough review of the specified systems and design process. Upon completion of the review, conclusions will be drawn appropriate to the objectives and commensurate with the review work performed.
The designated systems to be reviewed are:
(TO BE IDENTIFIED)
U The criteria used to select these systems is shown in Appendix D.
System boundaries will be as generally described in the FSAR. The review will cover mechanical, structural, electrical, environmental, instrumentation and control, plant arrangements, and fluid system aspects of the design l
of each system.
The design process will be evaluated by assessing the Hope Creek-specific work, as well as reports of similar reviews of other relevant designs by BPC (i.e., IDRs on Susquehanna and Limerick and the IDI on Callaway). This will be accomplished through the techniques of both l
horizontal and vertical reviews.
The extent to which reports of these other reviews will be used will be determined by their relevance to Hope Creek and overall value to assessing effectiveness of the design process on Hope Creek.
The extent of the review in any given technical area will be determined by the review team, on the basis of the f
safety significance of the area and what is found during the review. If the review detects deficiencies, then the area l
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SARGENTE LUNDY III-4 A
REVISION O 3/22/85 will be reviewed more intensively. Special effort will be directed to determining the underlying cause for significant or recurring deficiencies.
The review of each system has been divided into four activities: design requirements, design process, design adequacy and general assessment. In practice these activities will be integrated and performed as a relatively continuous activity for each area of the design. That is, each design area being reviewed will(1) have its requirements established, (2) have the design process assessed, (3) be reviewed for technical adequacy, and (4) be incorporated into the evaluation of broader implications.
o Activity 1, Design Requirements Activity I will be to determine the extent to which design criteria or other design objectives meet
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licensing commitments. These will be used to
'd implement Activities 2, Design Process and 3, Design Adequacy and to assess how design inputs are specified.
The sources of the commitments will be the FSAR, including responses to NRC questions on the FSAR, the SER and supplements thereto, as well as other documents S&L determines to be relevant.
o Activity 2, Design Process Activity 2 will be to provide an assessment of the effectiveness of the design process based upon review of the specified systems and of other technical areas as necessary (ie. high and moderate energy line break i
analysis - HELBA/ MELBA). In performing this task, reviews will be made to evaluate the extent to which the design process is sufficiently controlled so that safety-related design requirements are met, and that relevant commitments in the FSAR are complied with. This includes both establishment of suitable controls and proper and consistent implementation of them.
In making this assessment, due consideration will be O
given to the extent to which engineering judgment is C/
appropriate, in lieu of written procedures. Recognition i
SARGENT& LUNDY III-5 A
REVISION O
(,)
3/22/85 will be made of the complexity of the work, how unique it is, qualifications of personnel performing it, and other relevant factors.
Selected documents in the specified systems will be reviewed for adequacy of procedural requirements, and for general ef fectiveness in controlling the design process. Where procedural requirements are not applicable, the actual process will be evaluated to determine the extent to which the design is adequately controlled.
Documents reviewed will include those related to design criteria, calculations (both by hand and computer), drawings, specifications, and design change authorizations.
The documents will be reviewed for elements which n
(v) include the following:
- 1. Adequacy of documentation of the design calculations.
- 2. Interface design control between BPC and General Electric, and other important design contractors.
- 3. Design change and configuration control.
- 4. Design reviews performed by BPC, covering the specified systems, for technical adequacy.
- 5. As-built drawing reviews to determine degree of compliance with procedures, timeliness of release, and accuracy of information. These reviews will be performed in conjunction with the system walkdown activity.
- 6. Such other elements related to design control which bre embodied in the FSAR and its referenced documents.
Activity 3, Design Adequacy (Q>
Activity 3 will be to review each of the selected systems for adequacy in meeting the licensing
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SARSENTS LONDY III-6
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I-REVISION O 3/22/85 commitments and safety-related design requirements.
These commitments and requirements will be those determined from Activity 1. This will include a review of the installed (as-built) condition as compared to the actual configuration used in the final design.
To assess design adequacy, primary reliance will be placed on the results as described in output documents. It will be recognized there are many ways to arrive at an adequate design which meets require-ments. No attempt will be made to re-verify each step in designing the specified systems. Instead, the designs will be reviewed for accurate inputs and reasonableness of outputs, and adequacy of the design techniques based on a review and sampling of the work. Independent calculations will be performed to the extent appropriate to provide alternate means of verification, q
but not as a general rule.
In judging accuracy and completeness of design documents, due recognition will be given to established professional engineering practices and other precedents established in the nuclear industry. This judgment will consider the level of detail needed to link design requirements with the output documents, and the process employed. it will also consider needs to justify design decisions and assumptions.
Selected design documents will be reviewed for the following:
- 1. Safety classifications, to determine if the structures, systems, and components have been properly classified as to safety significance as defined in 10 CFR 50.
- 2. Accuracy and completeness of the design criteria and other inputs, including assumptions and codes or standards.
- 3. Applicability of standard design methods.
- 4. Method of analysis, to determine if an appropriate h
method was used, including mathematical models, d
and use of standards.
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SARGENTS LUNDY III-7 p
REVISION O V
3/22/85
- 5. Engineering judgments and assumptions and the basis en which they were exercised and utilized.
- 6. Accuracy of implementing the analysis, including use of properly validated computer codes.
- 7. Adequacy of means by which designs were verified.
- 8. Translation of design into output documents, for completeness, clarity, and proper control.
- 9. Reasonableness of the output, in relation to similar designs.
In performing the above reviews, each system will be reviewed frorn the standpoint of an integrated gi design, properly coordinated between disciplines. It will include mechanical, electrical, nuclear, id instrumentation and. control, and civil / structural aspects of the design.
A cut-off date will be established to ensure the integrity of the IDVP. The design revision applicable at the IDVP cut-off date will be censidered as the basis of the review in-process work will be included, where appropriate.
o Activity 4, General Assessment In Activity 4, the results of Activities 2 and 3 will be assembled and analyzed to determine what conclusions can be drawn regarding systems, structures and components which were not reviewed.
A summary list of observations will be prepared and analyzed for trends and underlying causes, and possible generic implications. Public Service Electric and Gas Company will investigate possible deficiencies in systems or areas outside the scope of that review.
The summary list will be prepared near the end of the review, using all available information, recognizing
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that conclusions must be commensurate with the nature of what was reviewed.
e III-8 Q] SARGENTSLUNDY
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REVISION O 3/22/85 The objective will be a balanced assessment, and one which emphasizes the likely impact c4n safety from observations made. As such, both positive and negative results will be considered, and the significance of all of them will be weighed.
Examples of what is anticipated to be included in the review are the following:
Mechanical Systems include process design, environ-mental and separation requirements, and system descriptions Mechanical Components include stress analysis, piping design, pipe supports, environmental qualification, seismic qualification, and design specifications
/O Civil-Structural includes load determination, load U
combination, analytical techniques, and design procedures Instrumentation and Control include control system design, separation, protection system, and annunciation Electrical Systems include system desi ;n, cable t
separation and system descriptions Electrical and Instrumentation and Control Components include environmental qualification, seismic qualification, design specifications, and cable installations Design Systems include procedures and other controls, design tools, and quality program Design Standards include standard drawings and requirements, interpretations of codes and standards and standard specifications Common Requirements include design requirements for HELB/MELB, fire protection, and Class II-over-I design.
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SANSENTS LUNDY III-9 REVISION O p) 3/22/85 (m/
Task 11. Review of Observations In the event that the review of the specified systems reveals certain design activities which are not accepted by the reviewer, they will be termed potential observations and processed in accordance with an established procedure.
The program will ensure that the potential observations made are fully understood, validated, evaluated as to safety-significance, and closed-out through appropriate corrective action. To this end, two internal review steps will be established within S&L's procedure. The first step of internal review will be carried out by the Internal Review Committee comprised of the current Head, Quality Assurance Division and the Mechanical, Structural and Electrical Design Directors. In addition, a Senior Review Committee will be formed comprised of the Director of Engineering and the Mechanical, Structural and Electrical Department Managers (with their assistants as alternates).
O' This Senior Review Committee will review all potential V
safety-significant observations and will determine the disposition of them as valid or invalid on an individual basis. All valid and invalid observations and corresponding PSE&G, Bechtel and GE responses, where applicable, shall be incorporated into the final report.
Key steps in processing potential observations are shown in Exhibit III-3 including steps by the reviewer and other parties. At any point the processing may be closed out if the reviewer determines no further action is appropriate.
Task 12. Prepare Interim Report Sargent & Lundy will prepare an interim report providing a " snapshot" of progress at that point. Individual reports on observations or potential findings will be issued as they are determined by the internal or senior review committees.
i Task 13. Prepare and Issue Final Report A final report will be prepared and issued. A preliminary outline of the final report is included in Exhibit III-8.
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SARGENT & LUNDY 111-1 0 REVISION O 3/22/85 Task 14. Project Administration The Project Manager will be responsible for the daily administration of this project and will be the major contact at S&L for PSE&G and its contractors. The Project Manager will be responsible for issuing all correspondence, meeting minutes, telecons, and bi-weekly status reports.
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Sequence of Design Review Activities Exhibit lll-2 Requirements Checklists identify Design Process Project instructions Checklists Flowcharts Design Adequacy Project instructions Review against requirements General Assessments Observations Trends Processing observations I
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SARSENTS LUNDY Prepared Project Documents Exhibit 111-4 REVISION O
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3/22/85 i
i Independent Design Review Quality Assurance Project Plan
-(Part of Program Plan)
Project Administrative Instructions SPAl-HC-01 Correspondence with Client SPAI-HC-02 Travel to Client Engineering Of fices or Station SPAI-HC-03 Format for Progress Reporting to Client SPAI-HC-04 Procedure for Processing Changes in Scope SPAI-HC-05 Implementation of Small Projects Monitoring System Project Instructions P!-HC-O L Evaluation of Design Process and Design Adequacy PI-HC-02 Processing of Observations PI-HC-03 System Walkdown O
f.)
SARSENTS LUNDY Project Design Requirements Exhibit 111-5 REVISION 0
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3/22/85 Licensing commitments contained in the Hope Creek Docket:
o Final Safety Analysis Report o Hope Creek SER o ACRS commitments o Code of Federal Regulations o industry codes and standards as committed to in FSAR o Applicable IE bulletins, notices, and circulars Design and licensing commitments made to NRC-o NRR and I&E Branches o Fire protection report Heavy loads report (response to NUREG 0612) o O
SARSENTE LUNDY Documents Required for Design Exhibit III-6
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Control and Interface Adequacy REVISION O Review 3/22/85 o PSE&G, GE, and Bechtel Quality Assurance Manuals o PSE&G - Hope Creek Generating Station Project Manual o PSE&G - Hope Creek Site Engineering Division Instructions Manual o PSE&G - E&C Department Discipline Procedures o Bechtel - Hope Creek Project Engineering Procedures Manual o PSE&G, GE and Bechtel current organization charts that represent design flow o PSE&G and its contractors' appropriate engineering p
standards gi Interface design specifications (CE, Bechtel) o
SARGENTS LUNDY Required Design Documents Exhibit III-7 A
1 of 3 C
REVISION O 3/22/85 i
Design documents or information anticipated to be pertinent to the systems, structures or components being reviewed include:
o System piping and instrumentation diagrams o General arrangement drawings o Applicable engineering standards o System and component design criteria o Technical specifications o Design installation and test specifications o Design drawing hierarachy Logic diagrams (with legend sheets) o o Loop diagrams o Instrument index o Instrument data sheets o Instrument location drawings Computer I/O list o
o Annunciator drawings 3(v) o Instrument procurement specifications o Control board arrangement drawings o Control board physical drawings o Control board wiring drawings o Intermediate instrumentation cabinet physical drawings o Intermediate instrumentation cabinet wiring drawings o Instrument impulse line routing drawings o Electrical single-line drawings o Electrical schematic diagrams o Electrical raceway and routing drawings o Cable tabs o Termination cards o Master control diagrams or equivalent Design basis criteria calculations and/or analysis o
for:
d-c on-site power systems d-c power systems a-c instrumentation power systems power cable ampacity and derating power and control circuit voltage drop o Cable routing block diagrams o Cable type code listing Equipment specifications and equipment data o
Q packages V
o Equipment list o Valve list o Specification index
Exhibit III-7
(_) SABOENT&LUNDY 2 of 3
'V REVISION 0 3/22/85 o ASME design specifications o System piping drawings o Piping isometric drawings o Seismic 11 over I assessment report o Flooding report o Pipe whip restraint drawings o GE system design specifications and data sheets o GE instrument data sheets o Environmental data o Environmental qualification reports o Approved design change documents o Hanger sketches o Hanger installation drawings o The following design basis documentation:
Pipe support and restraint calculations Pipe support auxiliary steel calculations Data prepared for input to the pipe program used in analysis p
Special calculations used for flange (j
qualification Stress indices calculations used for non-standard fitting including integral attachments Structural anchor calculations, if any Calculations for fluid transient loads, if any Pipe sizing for pressure and flow including corrosion allowances used in calculating pipe wail thickness o Stress reports including the following aspects:
Functional capability assurance Pipe break location identifications, based on stress criteria or lack thereof Any ISI requirements Thermal transient stress evaluation Fatigue evaluation of gamma plugs Class I fitting details and contours from field measurements Stress indices for small taps o Existing input data including:
Site seismic g-level and related geological data prepared by Dames and Moore Building seismic response spectra prepared by
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EDS/Impell
SARSENTS LUNDY Exhibit III-7 3 of 3 REVISION 0 3/22/85 Instrumentation and Controls standard specifications provided by Bailey Controls, Inc.
Standard equipment product literature and test reports supplied by vendors to PSE&G or Bechtel Generic engineering or test data supplied by General Electric Company Drywell environmental responses supplied by Bechtel O
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SARSENTE LUNDY Preliminary Exhibit 111-8
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Final Report Outline REVISION O b]
3/22/85 1.
Executive Summary A.
Purpose B.
Scope C.
Project Organization D.
Methodology E.
Results F.
Overall Conclusions Program Detail A.
Objectives and Scope B.
Systems and Components Reviewed C.
Method Utilization D.
Description of Expertise involvement E.
Delineation of Aspects 1.
Licensing 2.
Design Adequacy 3.
Design Procedures 4.
Design Interface 5.
Control of Design Changes 6.
Design Reviews 7.
As-Built Verification III.
Results A.
Observations B.
Potential Safety-Significant Observations C.
Disposition of Potential Safety-Significant Observations IV.
Conclusions and Recommendations A.
Findings B.
Recommendations C.
Conclusions l
V.
Appendices A.
Project Team B.
Senior Review Committee C.
Management Methodology D.
Definitions E.
List of Documents Reviewed F.
Review Criteria
- p G.
Review Records H.
Observation Reports I.
Dispositions J.
Independence Statement K.
IDVP Project Manual U
SANSENTS LUNDY IV. Project Schedule and Controls IV-1 q
REVISION O Q
3/22/85 A. Project Schedule S&L has divided the scope of work on the project into the fourteen tasks presented on the precedence network (Exhibit III-1) described in detail in chapter III.
The precedence diagram illustrates the inter-relationship of each task to its predecessors and successors, and indicates whether tasks are to be performed by S&L or PSE&G.
The precedence diagram will be revised af ter project commencement to show the following additional information as appropriate:
o Assigned character code for each task o Estimated duration of each task in work days o Schedules start and finish dates for each task o Designation of specific lags between tasks The project schedule milestones are targeted as:
OO o May 24,1985, Issue Interim Report o August 2,1985, Issue Final Report B. Project Controls and The revised precedence diagram will be used by Reporting Project Manager to monitor and report on project progress. Revised start and finish dates for a rescheduled task will be shown on the precedence diagram. Also, actual start and finish dates will be added to the diagram as tasks are completed. Graphical notations will be used to show tasks which have started and those which have finished.
The bi-weekly engineering progress report is a cost / schedule report. The format of this report will be tailored to PSE&G's needs.
SANSENTS LUNDY V.
organization V-t REVISION 0 O'a 3/22/85 The review organization team chosen for this project is shown in Exhibit V-1. Resumes for these individuals are included in Chapter VIII.
The project team is supported by engineers, designers, and other specialized personnel as required to perform the work associated with this project. A listing of anticipated team personnel is shown in Exhibit V-2. Additional personnel will be added as necessary.
A review of the project team's results will be provided by the Internal Review Committee. The Committee will be headed by Mr. H. S. Taylor, currently the Head, Quality Assurance Division, and will include representatives from the mechanical, structural, and electrical engineering disciplines. The representatives from the mechanical, structural and electrical engineering disciplines will be the Design Directors from each of these departments.
p An executive-level review of the results will be
(")
provided by the Senior Review Committee. The Committee will be headed by Sargent & Lundy's Director of Engineering, Mr. W. G. Hegener, and will include the Department Managers of the mechanical, structural and electrical departments with the Assistant Department Managers acting as alternates. The Senior Review Committee will perform Task 11 with the primary function of assuring the validity of potential safety-significant observations.
l The strengths that S&L's project team and Internal Review Committee will bring to the project are described l
below.
l A. Project Team o Project Director - P. L. Wattelet Mr. Wattelet, a partner of S&L, is the designated Project Director. He has over 17 years experience in the design and engineering of major nuclear-fueled electric generating stations. He has been the Project Director for numerous backfit and betterment projects at several nuclear units. He served as Mechanical Project Engineer, Project Manager, and Project Director for a two-unit 2250 MW PWR project. He has been supervisor of l
Safeguards Systems Analysis in our Nuclear Safe-h guards and Licensing Division, responsible for u
l l
SARSENTS LUNDY V-2 r3 REVISION 0 ty 3/22/85 methods development and analysis of nuclear safe-guards systems. He is a registered professional engineer in Illinois, Indiana, Kansas, Michigan, and New York.
o Consultant - R. J. Pruski Mr. Pruski has been associated with the nuclear industry for over 16 years. He was most recently the Project Manager for an 839 MW nuclear unit project. His responsibilities included planning, coordination, and performance monitoring for S&L's work on the design, construction, testing, and licensing phases of the project. As a Project Manager and as a Mechanical Project Engineer, he has been responsible for various assignments on numerous projects in our Project Management Division. He served as a member on a task force addressing the S&L Quality Assurance Program.
(V)
Mr. Pruski also serves as Task Force Chairman of S&L's Emergency Planning Program. As a Project Manager in our Nuclear Services Section, he is active in a variety of backfit, betterment, and evaluation projects. Mr. Pruski is a registered professional engineer in New Jersey, Illinois, and Ohio.
o Project Manager - W. A. Bloss Mr. Bloss has been associated with the nuclear industry for over 15 years. He was most recently the Chief Support Design Engineer in charge cf all pipe support design personnel in S&L's Mechanical Design and Drafting Division. He has been a project manager on the Commonwealth Edison Company's Carroll County Station. Mr. Bloss is a registered professional engineer in Illinois.
o Mechanical Project Engineer - D. P. White Mr. White, the designated Mechanical Project Engineer, has 18 years of experience in the design, engineering, and analysis of nuclear power plants, including betterment work. He has provided input for PSAR, FSAR, and modification requirement responses for two major nuclear projects. His p
experience includes serving as a project engineer
(
for S&L on the Commonwealth Edison Company's
5ABSENTE LUNDY V-3 REVISION 0 LJ 3/22/85 Zion Nuclear Station. Mr. White also has 15 years experience with another large A-E. This included working as a Project Engineer on a number of nuclear projects, as a Supervisor of the Mechanical Engineering Department, and most recently, as Manager of the Nuclear Section of the Mechanical Engineer Department. Mr. White is a registered professional engineer in Illinois, Oregon, Pennsylvania, and Washington.
o Structural Project Engineer - O. Zaben Mr. Zaben has 15 years experience in the structural and architectural engineering and design of nuclear power plant structures. He has been involved, at various levels of responsibility, in the planning, design, licensing, and modification work associated with twelve nuclear plants. His responsi-bilities include reviewing and approving plant design
,(v; criteria and authorizing construction drawings. He is a registered professional engineer in Illinois, Indiana, Kansas, New York, and Wisconsin.
Mr. Zaben is a member of the S&L Structural Standards Review Committee.
o Electrical Project Engineer - R. M. Schiavoni Mr. Schiavoni has 13 years experience in the engineering and design of two BWR nuclear I
generating stations. At increasing levels of responsibility, he has been involved in all phases of the project including conceptual design and layout, equipment procurement and installation, and licensing. In his current position as Senior l
Electrical Project Engineer, he has principal responsibility for all electrical aspects of the l
project, as well as the coordination of project I
efforts within the Electrical Department and its interfacing disciplines. Mr. Schiavoni is a registered professional engineer in Illinois.
B. Internal Review Committee o Quality Assurance Division Head - H. S. Taylor As the Quality Assurance Division Head, Mr. Taylor has developed and maintained QA procedures that are necessary for the implementa-(q tion of S&L's QA program and has coordinated the j
preparation of detailed procedures by other
SARSENTS LUNDY V-4 (O
REVISION O V
3/22/85 engineering disciplines. He has been responsible for ensuring that an entire project team adheres to S&L's QA standards and procedures that have been established to meet U.S. government and industry requirements for nuclear power plants. He has been responsible for conducting training sessions in the use and implementation of S&L's QA program and procedures for all personnel involved in safety-related activities and has been responsible for internal and external audits of consulting organi-zations retained by S&L. He has established and maintained controls for identification, storage, and retrieval of safety-related documents. Prior to assuming these responsibilities, Mr. Taylor was the lead Electrical Engineer responsible for the design and engineering of electrical systems for fossil and nuclear power plants, including specifying equip-p ment, reviewing specifications, and vendor design i
f documents. He assisted in the preparation of the V
electrical portion of the PSAR for a 1000 MW nuclear generating station.
o Mechanical Design Director - E. B. Branch Mr. Branch has over 15 years of experience in the stress analysis of piping systems and mechanical equipment for power plants. He has extensive experience not only in the design process, but also with the design philosophy changes that have l
occurred in the nuclear industry through participa-l tion in ASME, PVRC, and NRC licensing activities.
Mr. Branch has been active in the ASME Working Group on Piping Design, the Subgroup on Design, and the Section 111 Committee. He is also an active l
contributor in the PVRC Technical Committee on l
l Piping Systems and is chairman of the Task Group on Industry Practices. He is currently involved in i
studies leading to more realistic design practices and methodologies. Mr. Branch is a registered I
professional engineer in the State of Illinois.
o Structural Design Director - B. A. Erler Mr. Erler has more than 14 years experience in the design of nuclear power plants, involving work
[]
on eight nuclear stations. He has been responsible V
for the design and analysis of all the containment
SARSENT5 LUNDY V-5 A
REVISION O V
3/22/85 vessels in S&L's power plants since he assumed his current position. He has supervised the design of prestressed and reinforced concrete containments for many plants and has been responsible for seismic analysis of these structures. He has helped develop several national standards for the structural design of nuclear power plants. Through his work with professional committees, he has been involved in the development of criteria for nuclear containment design and design for extreme loads on nuclear plant structures. Mr. Erler is a registered professional engineer in the State of Illinois.
o Electrical Design Director - L. R. Stensland Mr. Stensland has 30 years experience in electrical engineering of steam-electric generating stations. He has worked on numerous station design projects, as well as various backfit projects at both
- O fossil-and nuclear-fueled plants. Before assuming V
his current position, he was the Senior Electrical Project Engineer for the Illinois Power Company's Clinton Station. His current job responsibilities include monitoring the flow of design information and the effectiveness of the Electrical Drafting Standards and the Draf ting and Field Standards. He currently heads up S&L's task force program for conduit. When required, he reviews and comments on independent design review reports. He is S&L's I
specialist on transformers and a member of the I.E.E.E. Committee on Transformers. Mr. Stensland is a registered professional engineer in Arkansas, l
Illinois, Indiana, Kentucky, Louisiana, Michigan, New York, Ohio, Texas, and Wisconsin.
r i
I
}
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d' EXHIRIT V-1
)
.J SARGENT & LUNDY HOPE CREEK IDR ORGANIZATION PROJECT DIRECTOR P. L. WATTELET CONSULTANT R. J. PRUSK!
PROJECT TEAM INTERNAL REVIEW COMMITTEE CHAIRMAN PROJECT MANAGER TECHNICAL DIRECTION AND OVERSIGHT W.
A. BLOSS H.
S. TAYLOR
[^N STRUCTURAL S&L STRUCTURAL l
-'f PROJECT ENGINEER DESIGN DIRECTOR
- 0. ZABEN B. A.
ERLER MECHANICAL S&L MECHAhlCAL PROJECT ENGINEER DESIGN DIRECTOR D. WHITE E. B. BRANCH ELECTRICAL S&L ELECTRICAL PROJECT ENGINEER DESIGN DIRECTOR
- 4. M.
SCHIAVONI L. R. STENSLAND SENIOR REVIEW C0ftt1TTEE CHAIRMAN W.
G. HEGENER DIRECTOR OF I 4GINEERING l
l MANAGER MANAGER MAN A E R STRUCTURAL DEPT.
MECHANICAL DEPT.
ELECTRICAL DEPT.
J. M. MC LAUGHLIN E. V. ABRAHAM R.
- x. FRENCH
[N )
i e
ASST. MANAGER ASST. MANAGER ASST. MANAGER g
STRUCTURAL DEPT.
MECHANICAL DEPT.
ELECTRICAL DEPT.
ALTERNATES K. T. KOSTAL H.
M.
CHIAPPETTA
SARGENTS LUNDY Hope Creek Team Personnel Exhibit V-2 REVISION O (m) 3/22/85 Project Management P. L. Wattelet Project Director R.3. Pruski Consultant W. A. Bloss Project Manager Mechanical Engineering D. P. White Mechanical Project Engineer R. M. Tjernlund Component Qualification Engineer P. R. Olson Engineering Mechanics Specialist W. D. Crumpacker Control and Instrumentation Engineer R. L. Givan Control and Instrumentation Supervisor J. Fortunski Senior Project Planning Engineer H. G. L. McCullough Quality Assurance Coordinator Structural Engineering O. Zaben Structural Project Engineer T. J. Duffy Structural Project Engineer R. 3. Small Head, Structural Project Engineering Division v'
A. K. Singh Assistant Head, Structural Analytical Division Electrical Engineering R. M. Schiavoni Senior Electrical Project Engineer W. G. Berger, Jr.
Electrical Project Engineer Internal Review Committee H. S. Taylor Head, Quality Assurance Division B. A. Erler Structural Design Director E. B. Branch Mechanical Design Director L. R. Stensland Electrical Design Director Senior Review Committee W. G. Hegener Director of Engineering
- 3. M. McLaughlin Manager, Structural Department K. T. Kostal Assistant Manager, Structural Department (Alt.)
E. V. Abraham Manager, Mechanical Department H. M. Sroka Assistant Manager, Mechanical Department (Alt.)
R. X. French Manager, Electrical Department C. M. Chiappetta Assistant Manager, Electrical Department (Alt.)
O
SARSENTE LUNBY VI. Qualifications and Experience VI-l o
REVISION 0 l]
3/22/85 A. Direct and Related Sargent & Lundy has been providing nuclear services for new and operating BWRs and PWRs for over 30 years.
Our nuclear services assignments cover a full range of TMI-related backfits, other NRC requirements, NRC bulletin-designated modifications, and plant betterment modifications. Exhibit VI-l shows the operating BWRs we are currently servicing.
Exhibit VI-2 shows our experience with audits and design reviews similar to the proposed work. We have been involved in eleven such programs on ten nuclear units.
Included among these is a self-initiated evaluation of the design control, construction control, scheduling, planning, quality assurance, and administrative procedures used in design and construction of the Texas Utilities Generating Company's Comanche Peak Station which S&L conducted.
Sargent & Lundy also has provided personnel to the Institute of Nuclear Power Operations to assist in the f) development of procedures and practices used for the V
Construction Evaluation Project (CEP) in the mechanical and instrumentation and controls areas. In addition, an S&L mechanical engineer was a member of the CEP review team for one year.
B. Nuclear Design Experience Sargent & Lundy provides comprehensive engineering, design, and construction management services for electric power generating and transmission facilities. Founded in 1891, we are today one of the nation's leading engineering partnerships. Over the years our clients have authorized us to design more than 700 units representing 90,000 MW of generating capacity. Since 19M, we have provided a wide range of these services to clients on more than !!0 projects, including 17 large nuclear units.
Sargent & Lundy's overall nuclear design experience is summarized in Exhibit VI-3.
(D
()
SARGENT& LONDY Operating BWRs Sargent & Lundy Exhibit VI-1 n
is Currently Servicing REVISION O Q) 3/22/85 MWT CP Commercial Unit Model Containment Licensed Date Operating Date La Crosse Unique Unique 165 1963 1969 Dresden 2 BWR-2 Mark i 2527 1966 1971 Dresden 3 BWR-2 Mark I 2527 1966 1971 La Salle 1 BWR-5 Mark 11 3323 1973 1982 La Salle 2 BWR-5 Mark 11 3323 1973 1984 Quad Cities 1 BW R-3 Mark 1 2311 1967 1972 Quad Cities 2 BWR-3 Mark i 2511 1967 1972 Brunswick i BWR-4 Mark i 2436 1970 1977 Brunswick 2 BWR-4 Mark i 2436 1970 1975 Susquehana 1 BWR-4 Mark 11 3439 1973 1983 Susquehana 2 BWR-4 Mark II 3439 1973 1985 O
227,204EX
SARSENT SI.5NBY Experience Complying with Exhibit VI-2 Audits and Design Reviews 1 of 3 (p)
REVISION 0 3/22/85 Client Station / Unit Description of Audit or Design Review The Cincinnati Gas &
Zimmer 1 Bechtel Power Corporation, as the Electric Company construction manager and constructor, performed a detailed review of our design and the status of engineering.
Commonwealth Edison Braidwood 1,2 The Institute of Nuclear Power Company Operations conducted an evaluation of our control of the design, including examinations of our organization and administration, design control, project support, training, quality control, and test control. The evaluation involved a detailed vertical path examination through the design combined with a O
horizontal examination at several points.
O Byron 1,2 Bechtel Power Corporation reviewed our design of the essential service water system, component cooling water system, and 125 volt de distribution system for adherence to design requirements, technical adequacy, and adequacy of the design process.
A Nuclear Regulatory Commission inte-grated design inspection team performed a detailed review of our design of the auxiliary feedwater and containment spray systems. The team evaluated the project organization, the technical aspects of mechanical, electrical, instrumentation, and structural design, and the adequacy of compliance with design requirements. The design process, including the adequacy of our design interface with the NSSS vendor, was also reviewed in detail.
The Institute of Nuclear Power O
Operations conducted an evaluation of C
our control of the design, including examinations of our organization and administration, design control, project
SARSENT S LUNDY Exhibit VI-2 (V,,)
20f3 REVISION O 3/22/85 Client Station / Unit Description of Audit or Design Review support, training, quality control, and test control. The evaluation involved a detailed vertical path examination through the design combined with a horizontal examination at several points.
Teledyne Engineering Services con-ducted an independent design review of our design for the residual heat removal system in the low pressure coolant injection mode for loop C.
The Detroit Edison Company Enrico Fermi 2 Cygna performed an Independent Design Verification Program of Sargent &
Lundy's design. Included a horizontal review to confirm that an adequate (3
design control process was established
\\
l and implemented; and an in-depth, v
multi-disciplined technical review to confirm that the as-built configuration agreed with c esign specifications, criteria, and licensing commitments.
This vertical review confirmed the accuracy and completeness of the design process including interf aces and design changes. Systems investigated included the RHR primary shutdown path compo-nents, RHR5W fluid path components, and the RHR cooling tower.
!!!inois Power Company Clinton 1 Bechtel Power Corporation reviewed our design of the high pressure core spray system and the Class IE ac distribution system for adherence to design require-ments, technical adequacy, and adequacy of the design process.
The Institute of Nuclear Power Operations reviewed our control of design and construction processes associated with the residual heat removal system, the shutdown service water system, and the auxiliary power v
and dc systems.
l l
t
SARGENT E LONDY Exhibit VI-2 O
3 of 3
,V REVISION 0 3/22/85 Client Station / Unit Description of Audit or Design Review Public Service Indiana Marble Hill 1 Nova, an outside engineering consulting firm, performed an engineering review to examine the engineering techniques Sargent & Lundy used in developing the Marble Hill design. The scope of Nova's 1
review was directed to the instrumenta-tion and controls area, it included documentation reviews, field examina-tion and interviews with Sargent &
Lundy engineering personnel.
Texas Utilities Generating Comanche Peak Sargent & Lundy conducted an INPO-5 Cornpany 1, 2 type, self-initiated evaluation of the construction project including an evalua-tion of the design control, construction control, scheduling, planning, quality 3
assurance, and administration. The Q
evaluation included examination of Texas Utilities Generating Company organization and administration, the design process, training, quality control, quality assurance, testing, planning, and scheduling and involved a detailed vertical path examination through the organization's design and construction functions, as well as horizontal examination at several points of the design process.
v
SARGENTE LUNDY Nuclear Units Authorized for Design Exhibit VI-3 (3
by Sargent & Lundy REVISION 0 CJ 3/22/85 Rated Type of Gross Year of Client Station-Unit Reactor
- MW Operation Commonwealth Edison Dresden 2 BWR 850 1971 Company Dresden 3 BWR 850 1971 Quad-Cities 1 BWR 850 1972 Quad-Cities 2 BWR 850 1972 Zion 1 PWR 1085 1973 Zion 2 PWR 1085 1974 La Salle 1 BWR I122 1982 La Salle 2 BWR 1122 1984 Byron 1 PWR 1175 1985 Byron 2 PWR 1175 1986 Braidwood 1 PWR 1175 1986 Braidwood 2 PWR 1175 1987 Carroll County 1 PWR 1175 2000 Carroll County 2 PWR 1175 2001 s
)
The Cincinnati Gas and Zimmer BWR 839 Converted *
- Electric Company Dairyland Power Cooperative La Crosse BWR 48 1969 Illinois Power Company Clinton i BWR 985 1986 Public Service Company of Fort St. Vrain i HTGR 330 1979 Colorado Public Service Indiar.a Marble Hill 1 PWR ll75 Cancelled *
- Marble Hill 2 PWR 1175 Cancelled *
- Southwest Atomic Energy SEFOR LUMBER 7
1967 Associates United Power Association Elk River BWR 20 1961 U.S. Atomic Energy Borax 111 BWR 3
1955 Commission EBWR BWR 5
1956 l
l
- BWR - boiling water reactor l
HTGP. - high temperature gas reactor I p LUMBER - liquid metal fast breeder reactor d
PWR - pressurized water reactor l
l
- *The designs were completed at the time the projects were coverted or cancelled.
l 210,010EX
SANSENTSI. UNDY VII. Protocol VII-1 e
REVISION 0
(
3/22/85 In the conduct of the IDVP by Sargent & Lundy (S&L),
the following protocol shall be adhered to:
1.
Recommendations, findings, evaluations and all exchange of correspondence, including draf ts between S&L and Public Service Electric & Gas Company (PSE&G)(including its contractors and subcontractors) will be submitted to the NRC at the same time as they are submitted to PSE&G.
2.
S&L may request documentation material, meet with and interview individuals, conduct telephone conver-sations, or visit the site to obtain information without prior notification to the NRC. All communications and transmittals of information shall, however, be docu-mented and such documentation shall ha maintained in a location accessible for NRC examination.
Communications between S&L and PSE&G solely with respect to the financial and administrative aspects of the IDVP contract are outside the scope of this g
(v) protocol.
3.
If S&L wishes to meet with PSE&G to discuss substantive matters related to information obtained, to provide an interim report to PSE&G, or to discuss its findings or conclusions with PSE&G in advance of completing its final report, or if PSE&G desires such a meeting, PSE&G shall provide a minimum of two days advance notice to the NRC of any such meeting.
4.
When S&L or PSE&G have telephone conversations to discuss substantive matters or S&L's conclusions, S&L shall provide a written summary of each conversation and provide such summary to the NRC in a timely manner. The summary will include the substance of the discussion, problems identified by either party, any potential resolutions to those problems and action required.
After written responses to Potentially Safety -
Significant Observation Reports have been transmitted to S&L and S&L and PSE&G desire to have telephone conversations to discuss these written responses, then the NRC will be notified 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in advance of such telephone conversations to enable NRC participation.
O v
i SARSSNTS LUNDY VIII.
Resumes VIII_I O
REVISION 0 3/22/85 A.
Project Team O
l o
SARGENT& LUNDY Resume 1 of 4 william A.Bloss O
Title Associate and Chief Support Design Engineer Mechanical Design and Drafting Division Education Loyola University - M.B.A. - 1977 University of Wisconsin - B.S.M.E. - 1969 Registration Professional Engineer - lilinois Appointed Associate - 1981 Responsibilities As chief support design engineer, Mr. Bloss is responsible for providing administration and direction to the Support Design Section/ Mechanical Design and Drafting Division. He is responsible for coordinating the section's activities to sufficiently satisfy production and technical requirements.
Through the section supervisors, he ensures the preparation of man-hour estimates and the proper distribution of manpower to efficiently meet project schedules. Mr. Bloss coordinates the section's activities with the work of the various interfacing project teams. By virtue of his position, he has the authority to call upon the resources of the firm to meet the demands of the project.
Experience Mr. Bloss has extensive experience in the design and engineering of major steam-electric generating stations. He has worked as a mechanical engineer, mechanical project engineer, or project manager on six nuclear units and four fossil units with a capacity in excess of 7500 MW. He has also participated in studies, analyses, and reports encompassing preliminary engineering evaluations, system designs, piping analyses, pressure and temperature effects on structures, environmental problems, and radioactive waste removal.
Mr. Bloss joined Sargent & Lundy in 1969.
l l
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p t
LJ 970,054 101084
hN[(ence Record 2d4 SARGENT 8 LUNDY O
Power Plant Desian Projects Rated Gross Operating Assignment Station - Unit Fue_1 MW Date(s)
Client Assianment Date(s)
All projects Coordinates and super-1981 to present vises the Support l
Design Section of MDDD 1
La Salle i Nuclear
!!22 1982 Commonwealth Coordinated the "For 1983 to 1981 i
Edison Company Record" release of piping system and l
support designs; re-sponsible for work of j
MDDD component support personnelin the office i
I and in the field Fairview 1,2 550 Illinois Power Directed preparation of 1979 to 1980
[
(each)
Company Environmental Report, I
developed scope of work and project schedule with the client Collins 4,5 Oil / Coal 504 1978/1979 Commonwealth Directed the design of (each)
Edison Company mechanical systems for coal conversion; coordi-nated structural and electrical design with work being done by the Mechanical Department; de-l veloped scope of work I
and project schedule with the client 1
Carroll Nuclear 1175 2003/2001 Commonwealth Directed the design 1977 to 1979 County 1,2 (each)
Edison Company of mechanical systems for nuclear plants, including preparation of design criteria, piping and instrumenta-l tion diagrams, and speci-fications; coordinated the Structural and Electrical Departments with the work being done in the Mechanical Department; coordinated the work of Mechanical Davisions to l
support the project I
schedule; developed the scope of work with the client; developed the project schedule with the client; and developed the internal project schedule with all departments O
970,054 101084 l
1
Selected Experience Record 3 of 4 SARGENT5 LUNDY villiam A.Bloss m
)
J Powee Plant Design Projects, Continued Rated Gross Operating Assignment Station - Unit Fuel MW Date(s)
Client Asananment Date(s)
Kaiseraugst Nuclear 932 Deferred Swiss Coordinated the design 1976 to 1977 Consortium effort of all disci-plines for the design of GEX containment and internal systems, in-ciuding structural design, piping design and analysis for seismic / transients and accident desiEn such as LOCA and pipe rupture Miscellaneous During the Bailly N1 1975 to 1976 shutdown, participated in the following a.
Cardinal - minor bid evaluations b.
La Salle - nitrogen piping and instru-fg mentation diagram j
c.
Byron /Braidwood -
valve specification bid evaluation Bailly NI Nuclear 684 Cancelled Northern Indiana Assumed the position 1973 to 1975 Public Service of Mechanical Project Company Engineer responsible for the coordination of the Nuclear Steam Supply System contract; the Engineering Mechanics Division (EMD); the l
Heating, Ventilating, and Air Conditioning r
Division (HVAC); the Electrical, Mechanical and Structural work in in the reactor building areas; piping design and analysis development; and pipe rupture Fort St. Vrtin 1 Nuclear 330 1979 Public Service During the Bailly NI 1972 to 1973 Colorado shutdown, worked on the system piping and instrumentation diagram updates to as-built con-ditions; coordinated EMD work in seismic system transients and analysis of as-built piping systems; and coordinated pipe rupture Ob 970,054 101084 t
l l
I l
Selected Experience Record
% of 4 SARGENT & LUNDY William A. Bloss O
Power Plant Desaan Projects, Continued Rated Gross Operating Assignment Station - Unit Fuel MW Datds)
Client Asslanment Date(s)
Bailly NI Nuclear 684 Cancelled Northern Indiana Responsible for the 1971 to 1972 Public Service beginning design stages Company of equipment drains, floor drains, fire protection, and rad-waste systems Quad Nuclear 850 1972 Commonwealth Responsible for the 1969 to 1971 Cities 1,2 (each)
(each)
Edison Company design and specifica-tion of several systems and equipment which came late in the project; i.e., nitrogen inerting system; supervised the piping analysis for seismic and pipe rupture; and liaison with the field and the General Electric field personnel on miscellaneous items required to complete construction and pre-op testing O
970,054 101084
SARGENTa LUNDY Resu 1 of 3 g
ger,3r.
O Title Electrical Project Engineer Education lilinois Institute of Technology - M.S.E.E. - 1976 Purdue University - B.S.E.E. - 1972 l
Registration Professional Engineer - Illinois Responsibilities Mr. Berger directs electrical analysts and draftsmen in development of the conceptual design, design of individual system components, and preparation of bid procurement specifications. In consultation with the senior electrical project engineer, Mr. Berger evaluates the proposals of manufacturers, makes purchase recommendations, and monitors the activities of manufacturers to ensure that manufacturers' drawings and finished components are received on schedule. He works with the client and with manufacturer and contractor representatives to ensure that the electrical design, engineering, and construction of the power plant incorporate the latest techniques. He coordinates the electrical engineering work with that of other Sargent & Lundy departments. Mr. Berger reviews specifications and drawings to see that all electrical work is correctly done. After plant construction begins, he rnay make occasional visits to the site to check on progress of the electrical work and to ensure that it is done properly.
Experience Mr. Berger has experience in the electrical design, engineering, and analysis of major stesm-electric generating stations, both fossil-and nuclear-fueled. His scope of work has involved the design of plant electrical auxiliary systems, including determination of the size and rating of major electrical equipment. Mr. Berger has sized and routed cable and designed control systems. He has also prepared and reviewed specifications, reviewed vendor proposals, and issued letters of recommendation for motors, transformers, switchgear, and motor control centers.
Mr. Berger has extensive experience in coordinating the electrical interface on nuclear regulatory licensing matters for a pressurized water reactor (PWR) project. This work includes responding to Nuclear Regulatory Commission (NRC) questions regarding plant design, regulatory guides, and other NRC documents. He has developed and implemented the environmental qualification program for electrical equipment. He is also currently involved in developing nuclear industry standard criteria for analyzing the reliability of offsite and onsite power systems for nuclear plants.
970,042 051684
i SARGENT S LUNDY Resume 2 of 3 William E. Berger, Jr.
O Experience, Continued Before assuming his current responsibilities, Mr. Berger was
)
an electrical analyst investigating protective relay schemes, calculating breaker settings, and performing short circuit calculations. He also examined specific motor applications for their voltage profile.
Mr. Berger joined Sargent & Lundy in 1972, left in 1975, and rejoined the company in 1976. For the 14-month period he was absent from Sargent & Lundy, he worked for another archi-tect-engineer in the systems planning department. He did generation and system studies involving stability and load flow analysis. This work involved extensive computer studies and modeling. Mr. Berger also reviewed and developed programs used to design the auxiliary power system and to evaluate cable tray loading.
Membership Institute of Electrical and Electronics Engineers (IEEE)
- Vice Chairman of Nuclear Power Engineering Committee, Subcommittee 4, Working Group 4.3, Loss of All AC Power"
- IEEE Liaison Member on the Atomic Industrial Forum Steering Committee on Station Blackout t
i i
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O 970,042 051684
SARGENT E LUNDY Selected Experience Record 3 of 3 William E. Berger, Jr.
s Power Plant Newn Proiects Rated Gross Operating Asagnment Station - Unit
_Pur!
MW Date(s)
Client Asanarwnent Date(s)
Marble Hill 1,2 Nuclear i175 Suspended Public Service Electrical Project 1977 to 1984 (each)
Indiana Engineer Cardinal 3 Coal 615 1977 American Electric Electrical Engineer 1975 Power Service Corporation / Buckeye Power, Inc.
LACBWR Nuclear 48 1969 Dairyland Power Electrical Engineer 1975 Cooperative Fort St. Vrain Nuclear 330 1979 Public Service Electrical Engineer 1974 Company of Colorado Bailly N-1 Nuclear 684 Cancelled Northern Indiana Electrical Engineer 1972 to 1974 Public Service Company
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970,042 051684
Resume 1 of 2 SARGENT E LUNDY william o. Crumpacker O
Title Control & Instrumentation Project Engineer Control & Instrumentation Division Education Purdue University - B.S.E.E.T. - 1975 Purdue University - Associate in Industrial Supervision - 1975 Responsibilities As a control and instrumentation project engineer, Mr. Crumpacker has primary responsibility for the development of control and instrumentation systems for nuclear generating stations. He must perform or delegate all tasks required to be performed on his project. These include preparation of design criteria and Safety Analysis Reports; general arrangements of control rooms, computer rooms, and other C&I areas; control and instrumentation diagrams; instrument portions of Piping and Instrumentation Diagrams; preparation of instrument indexes, data sheets, logic diagrams, master diagrams, loop schematics, instrument location drawings, and installation details; control board layouts and arrangements; preparation of C&l specifications, evaluation of proposals, and purchase recommendations; monitoring of vendor's engineering and manufacturing schedules, and review N
of vendor's drawings. He also trains C&l engineers in the s
performance of these tasks.
Experience Mr. Crumpacker has experience in the design and engineering of control and instrumentation systems for nuclear power plants and for modifications to nuclear power plants.
He is currently responsible for the engineering design of TMI-related modifications to the Clinton Power Station. He previously served as the C&I engineer for the initial design, i
I system instrumentation, procurement, control room panel design and specifications of control room instrumentation for the Radwaste Control and Operation Center. This design included engineering of the liquid, gaseous, and solid radioactive waste processing and disposal systems.
During a 3-month absence from the firm, before rejoining in January 1982, Mr. Crumpacker worked for another major consulting engineer and was assigned to projects involving TMI modifications.
Prior to joining Sargent & Lundy in 1976, he was employed by Inland Steel Company as an instrument technician responsible for field maintenance and instrument repairs.
Membership Instrument Society of America l
O 970,120 121084
SARGENT S LUNDY SelcCted Experience Record 2 of 2 William D. Crumpedcer Power Plant neelen Projects Rated Cross Operating Assigrunent Station - Unit Fuel MT Dete(s)
CEent Assignment Deuds)
Clinton 1 Nuclear 985 1986 tilinois Poe'er Cal Engineer (initial 9-78 to 10-81 Company design, system instru-mentation and procure-ment for the Radwaste Operatica Center)
C&! Engineer (control 5-77 to 9-78 room panel design and specifications of control room instru-mentation)
Design Engineer 5-76 to 5-77 (wiring design)
Power Plant Betterment Projects Rated Gross Assignment Station - Unit Fuel MW Client Assignment Date(s)
Clinton 1 Nuclev 935 tilinois Power C&l Engineer 6-82 to present Company (TMI modifications)
Zimmer i Nuclear 839 tilinois Power Cal Engineer 1-82 to 6-82 Company (TMI modifications)
O 970,120
!?!OP J
SARGENTE LUNDY Resume 1 of 4 Thomas 3. Duffy Title Structural Project Engineer Education University of Illinois - M.S.C.E. - 1971 University of Illinois - B.S.C.E. - 1969 Loras College - B.A. Pre-Engineering - 1969 Registrations Professional Engineer:
Arizona New York Structural Engineer - Illinois Responsibilities Mr. Duffy is responsible for and directs the work of his department's engineers engaged in the architectural, civil, and structural design of systems and components for major steam-electric generating stations. He disseminates applicable project-related information to the structural design team for each individual project and reviews project work with them to ensure its conformance with client requirements, applicable standards, codes, and regulations, and Sargent & Lundy design standards. He also interacts with the client to ensure that their requirements are properly integrated into the final design.
Experience Mr. Duffy has been engaged in the design and supervision of the design of the civil / structural systems and components of more than 13 nuclear-and fossil-fueled power plants. He is currently working on one fossil-fueled power plant in the initial stages of design and on a nuclear-fueled power plant in the final stages of construction. He has been engaged in the development of structural design standards dealing with the design of air and gas ducts, cable tray design, boiler suspension steel, and precipitator support steel, as well as coordinating all structural design on these items. He has coordinated the work on civil / structural design criteria, PSARs, and FSARs for several nuclear power plants. For the past several years, he has been a mtcher of Sar, gent & Lundy's Reference Design for a Coal-Fired Unit Committee. He joined Sargent & Lundy in 1971.
Memberships American Society of Civil Engineers American Concrete Institute, Committee ACI 349, Nuclear Safety Related Concrete Structures O
970,156 120784
SARGENT & LUNDy Selected Experience Record 2 of 4 Thomas 3. Duffy 9
Power Plant Desian Projects Rated Gross Operating Assagnment Station - Unit Fuel MW Date(s)
Client Annaanment, Date(s)
Enrico Fermi 2 Nuclear
!!23 1983 The Detroit Edison Structural Project 2-83 to present Company Engineer MTA Fossil Plant Coal, Oil, 697 1996 New York Power Structural Project 2-83 to present
& Refuse (held)
Authority Engineer Schahfer 17,18 Coal &
393 1983/1986 Northern Indiana Assistant Division Head 1-80 to 2-83 Oil (each)
Pubhc Service Company East Bend 2 Coal 648 1981 The Cincinnati Assistant Division Head 9-78 to 2-83 Gas & Electric Company Coleto Creek Coal 1277' 1980/1992 Central Power and Assistant Division Head 9-78 to 2-83 1,2 (total)
Light Company /
Central and South West Services, Inc.
Weston 3 Coal 321 1981 Wisconsin Public Assistar t Division Head 9-78 to 2-83 Service Corporation Clinton 1 Nuclear 985 1986 Illinois Power Assistant Chief Struc-9-78 to 9-79 Company tural Design Engineer Marble Hill 1,2 Nuclear 1175 Suspended Public Seevice Assistant Chief Struc-9-75 to 9-78 (each)
Indtana tural Engiswer Byron 1,2 Nuclear
!!75 1985/1986 Commonwealth Assistant Chief Struc-9-75 to 9-78 Lach)
Edison Company tural Design Engineer Braidwood 1,2 Nuclear
!!75 1986/1987 Commonwealth Assistant Chief Struc-9-75 to 9-78 (each)
Edison Company tural Des.gn Engineer La Salle 1,2 Nuclear 1122 1982/1984 Commonwealth Assistant Chief Struc-3-74 to 9-75 (each)
Edison Company tural Des'gn Engineer Zimmer i Nuclear 839 1986 The Cincinnati Gas & Senior Structural 7-73 to 8-73 (suspended)
Electric Company Engiswer Structural Engineer 6-71 to 7-73 Zion i,2 Nuclear 1085 1973/1974 Commonwealth Edison Structural Engineer 6-71 to 7-73 (each)
Company O
970,156 120784
l SARGENT & LUE4 7 Selected Experience Record 3 of 4 Thomas 3. Duffy O
Nurinar Power Plant Betterment Proincts Rated Gross Assignment Station - Unit MW Cuent Assignment Date(s)
Surry 1,2 773 Virginia Electric and Structural Project Engineer 2-83 to 10-83 (each)
Power Company Assistant Division Head 9-78 to 2-83 North Anna 1,2 865/890 Virginia Electric and Structural Project Engineer 2-83 to 10-83 Power Company Assistant Division Head 9-78 to 2-83 Dresden 2,3 850 Commonwealth Edison Assistant Division Head 9-78 to 2-83 (each)
Company Quad Cities 1,2 850 Commonwealth Edison Assistant Division Head 9-78 to 2-83 (each)
Company Donald C. Cook 1,2 2126 Indiana and Assistant Division Head 9-78 to 2-83 (total)
Michigan Electric Company Fossil Power Plant Betterment Projects Rated Groes
" '. -,t Station - Unit Fuel MW Client Assispment Date(s)
E. W. Brown 2,3 Coal 156/445 Kentucky Utilities Structural 54ervising 8-73 to 3-74 Company Design Engineer (precipitator backfit)
Green River 4 Coal 125 Kentucicy Utilities Structural Supervising 8-73 to 3-74 Company Design Engineer (precipitator backfit)
Pineville 3 Coal 30 Kentucky Utilities Structural Supervising 8-73 to 3-74 Company Design Engineer (precipitator backfit)
Beckjord 4,5 Coal 172/240 The Circinnati Cas &
Structural Supervising 8-73 to 3-74 Electric Company Design Engineer (precipitator backfit)
M.ami Fort 5,6 Coal 80/172 The Cincinnti Gas &
Structural Swervising 8-73 to 3-74 Electri: Company Design Engineer (precipitator backfit)
Lansmg 13 Coal 38 Interstate Power Structural SwervMrq 8 73 to 3-74 (total)
Company Design Engineer (precipitator backfit) 970,156 120784
SARGENT & LUNDY Selected Experience Record 4 of 4 Thomas 3. Duffy O
Fossli Power Plant Betterment Projects, Continued Rated Gross Assignment
. '_ _- c.t Date(s) 5tation - tJnit Fuel MT Cuent Dubuque 5,6 Coal N.A.
Interstate Power Structural Supervising 8-73 to 3-74 Company Design Engineer (precipitator backfit)
M.L. Kapp 1 Coal 15 Interstate Power Structural Supervising 8-73 to 3-74 Company Design Engineer (precipitator backfit)
Watkegan 7 Coal & Gas 325 Commonwea'.th Edison Structural Servising 8-73 to 3-74 Company Design Engineer (precipitator backfit) 9 l
l O
970,156 120784
SARGENT& LUNDY Resume 1 of 2 John Fortunski O
Title Senior Project Planning Engineer Education Illinois Institute of Technology - B.S.C.E.
(Management Option)- 1966 Registration S;ructural Engineer - Illinois Responsibilities As a senior project planning engineer, Mr. Fortunski works with the project team to implement the Engineering Project Monitoring System (EPMS) and any other schedule, progress, and man-hour monitoring systems that may be required to rneet the needs of the client, Sargent & Lundy's management, and the project team. From the project scope of work, he develops the project scope of work breakdown structure and assists the project team in developing precedence networks with task durations and imposed milestone and significant event dates. He inputs man-hour, schedule, and progress data to produce the project progress report for distribution to the project team, Sargent & Lundy management, and the client.
He analyzes schedule and man-hour performance and prepares O
variance analysis reports for project team resolution. He also sees that the engineering schedule and progress interface with the requirements of the construction schedule.
Experience Mr. Fortunski has considerable experience in the civil and structural design and engineering of nuclear and fossil power plants, including project planning and scheduling functions. He was lead planning and scheduling engineer on a two-unit nuclear power plant functioning as a primary interface be-tween Sargent & Lundy and client engineering and construction staff. He has been associated with fossil-fueled and nuclear-powered design projects at increasing levels of responsibility.
Before assuming his current responsibilities, he was a struc-tural project engineer. In this position, Mr. Fortunski directed the work of structural engineers and draftsmen who were engaged in the design and engineering of the structural and civil portion of a central power plant, including the complete coal handling facilities.
Prior to joining Sargent & Lundy in 1965, Mr. Fortunski worked for a number of firms as a senior structural engineer responsible for the design of a major portion of a paper mill plant; as a structural designer for steel mills and industrial process plants; and as a design engineer and vice-president for a firm that designed specialized materials handling equipment.
I Membership American Society of Civil Engineers 970,184 i
122784
SARGENT & LUNDY Selected Experience Record 2 of 2 John Fortunski Power Plant Design Projects Rated Gross Operating Assignment Station - Unit Fuel MW Date(s)
Client Assignment Date(s)
Marble Hill 1,2 Nuclear
!!75 Cancelled Public Service Senior Project 1982 to 1984 (each)
Indiana Planning Engineer Pleasant Prairie Coal 370 1980/1985 Wisconsin Electric Structural Project 1975 to 1981 1,2 (each)
Power Company Engineer Newton I Coal 367 1977 Central Illinois Supervising Structural 1973 to 1975 Public Service Design Engineer Company Baldwin 3 Coal 585 1973 tilinois Power Supervising 5tructural 1971 to 1973 Company Design Engineer 9
O 970,184 122784
SARGENTa LUNDY Resume 1 of 2 Richard L, Givan O
Title Assistant Division Head Control and Instrumentation Division Education Colorado College - B.S. Mathematics - 1961 Responsibilities Mr. Givan is the Assistant Head of a group of engineers and designers who develop control and instrumentation systems for major nuclear steam-electric generating stations. He assists in the overall management of the division and ensures that the engineering and design on nuclear projects is in accordance with the client's requirements, company standards, industry standards, government regulations, and Quality Assurance requirements and includes the best technology available. He estimates manpower requirements and provides infor..Ttion for the preparation of schedules. He recommends personnel assignments, assists in interviewing applicants and doing performance evaluations, and consults in salary adminis-tration. He makes recommendations regarding the technical training of division personnel and in the development and maintenance of division standards, practices, and procedures.
Experience Mr. Givan has been involved with many projects as Assistant Division Head and supervisor of project engineering. Prior to joining Sargent & Lundy in 1975, he was an instrumentation engineer involved in installation and checkout of instru-mentation systems in a BWR plant, a project engineer with operational control and responsibility for checkout and launch operations of Saturn V booster and ground support systems, a systems engineer engaged in electrical and mechanical systems analysis and development of checkout requirements and operations for spacecraft, and a missile systems engineer involved in electrical and mechanical missile systems operational evaluation and technical assistance to Department of Navy Operational Forces.
Membership Instrument Society of America
~
Publication
" Controls Miniaturization - How and Why" (coauthor J.P. Faber), General Engineering Conference, March 20 21, 1980
/~
k 970,208 022784
Selected Experience Record 2 of 2 SARGENT & LUNDY Richard L. Givan O
Power Plant Design Projects Rated Gross Operating Assignment Station - Unit Fuel MW Date(s)_
Client Assianment Date(s)
Enrico Fermi 2 Nuclear 1123 1983 The Detroit Controls and Instrumenta-3 77 to present Edison Company tion Supervisor (mis-cellaneous engineering and design work)
Clinton 1 Nuclear 985 1986 Illinois Power Controls and Instrumenta-176 to present Company tion Supervisor Zimmer 1 Nuclear 839 Cancelled The Cincinnati Controls and Instrumenta-3 77 to 1-84 Gas & Electric tion Supervisor Company Marble Hill 3,4 Nuclear 1175 Cancelled Public Service Controls and Instrumenta-5 79 to 1-80 (each)
Indiana tion Supervisor Bailly NI Nuclear 684 Cancelled Northern Indiana Controls and Instrumenta-3 77 to 5.78 Public Service tion Supervisor Company GEX-Kaiseraugst Nuclear 932 Deferred General Electric Controls and Instrumenta-3 77 to 5 78 Company tion Supervisor (pre-liminary review of pri-mary containment and BOP equipment within contain-ment)
La Salle 1,2 Nuclear 1122 1982/1984 Commonwealth Edison Controls and Instrumenta-1 75 to 1-76 (each)
Company tion Engineer Studies Assignment Type of Study Client Assianment Date(s)
Computer System Carolina Power &
Controls and Instrumentation 3 83 to 4 83 Implementation Light Company Supervisor O
970,208 022784
SARGENT E LUNDY Resume 1 of 6 Henry G. L. McCullough mU Title Project Quality Assurance Coordinator Quality Assurance Division Education U.S. Air Force Officer's Training - Graduate - 1962 University of Arizona, Tucson, Arizona - M.S. Program Nuclear Science and Engineering - 1962 Grinnell College, Grinnell, Iowa - B.S. Physics-Mathematics -
1961 Registrations Professional Engineer - Illinois ASQC - Certified Quality Engineer (test taken)
Responsabilities As a Project Quality Assurance Coordinator, Mr. McCullough is responsible for assisting the nuclear or project team with the effective implementation of the quality assurance pro-gram. Mr. McCullough participates in all audits of Sargent &
Lundy for the assigned nuclear projects. He consults with the project personnel to resolve possible nonconformances, h Experience Mr. McCullough has extensive experience in the design, N
engineering, and related disciplines of nuclear steam-electric generating stations. Mr. McCullough is currently assigned as the Project Quality Assurance Coordinator on four nuclear units being designed and under construction. He monitors effective project implementation of Sargent & Lundy's Quality Assurance program and performs periodic reviews (overview) of design control documents, such as design criteria, change j
documents, calculations, and drawings. He performs investigations throughout the project when potential generic concerns are identified on other nuclear projects. These reviews and investigations may cover any engineering discipline, structural, mechanical, electrical, or nuclear.
Mr. McCullough interfaces with nuclear project personnel on matters relating to quality assurance of safety-related items in accordance with the requirements of ANSI-N45.2.ll and the Nuclear Regulatory Commission's 1.E.
Bulletins and I.E. Notices. As the Project Quality Assurance Coordinator, he provides Quality Assurance requirements to technical consultant specifications and i
work procedures. His attendance at project l
interdepartmental meetings, as needed or requested, allows i
Mr. McCullough to identify potential Quality Assurance concerns or problems for evaluation and resolution.
Mr. McCullough participates in all Nuclear Regulatory Commission (NRC), Institute of Nuclear Power Operations 972,863 120584
SARGENT E LUNDY Resume 2 of 6 Henry G. L. McCullough 9
Experience, Continued (INPO), independent, and client audits of Sargent & Lundy on the assigned nuclear projects.
Previously, as a Safeguards Project Engineer, Mr.
McCullough's experience and expertise had been utilized in the design of many nuclear power generating stations, six of which are in operation today. He had performed advanced analytical, evaluative, and support analyses for both boiling water reactor (BWR) and pressurized water reactor (PWR) nuclear plant designs. He helped develop and complete a fully automated nuclear fuel cycle and management computer program and the successful benchmarking against plant operational data. He prepared required calculations for safety analysis reports on design basis accidents and postulated high-energy line ruptures in either the primary or secondary containment. The computerized mathematical simulation models he utilized met the Nuclear Regulatory Commission acceptance criteria and had been satisfactorily benchmarked against other industry-wide calculational approaches. He completed the development efforts to improve the mathematical models for two-phase and two-component air, steam, water, and thermal-hydraulic calculations.
Prior to joining Sargent & Lundy in 1974, Mr. McCullough was a Senior Nuclear Specialist and a Senior Engineer for a specialized nuclear and development consulting firm.
Having detailed nuclear system design experience, Mr.
McCullough was responsible for the verification, expansion, and maintenance of the complete nuclear computer code library of over fif ty programs. He helped develop new marketing avenues and advertising ideas for the nuclear programs. Customer service as a technical consultant, was also provided to individual users in the actual design and/or theoretical evaluation of reactor systems. He also provided consulting assistance to electric utilities and engineering firms who were having difficulties in performing their calculations. Mr. McCullough also worked with new reactor -
physics analytical and computer techniques for large and small reactors. A preliminary nuclear analysis was performed by Mr. McCullough for a multipurpose prototype plant. He was preparing a determination of conditions for a specific fuel lifetime estimate, using different codes for cross-section generation, transport, diffusion, and depletion calculations, when the project was cancelled.
Before this, Mr. McCullough was an engineering analyst for a major reactor vendor. He helped pregare the determination of the azimuthal xenon osci ations on the 972,863 120584
SARGENT S LUNDY Resume 3 of 6 Henry G. L. Mc -%h o
O IV
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Experience, Continued stability of large reactor cores. This analysis required detailed two-dimensional physics calculations of beginning and different times during core life. The results of this analysis were essential for final core designs and final safety analysis reports for several nuclear plants now in operation. Before this, Mr. McCullough helped develop a 1
digital simulation of an analog model to perform a thermal transient analysis of the core following a loss-of-coolant accident. Output from this program was used to calculate a pressure-temperature time history in the containment building. Results of these programs were used for various safety analysis reports, as well as final nuclear steam supply system (NSSS) design considerations.
Previous to this, Mr. McCullough was commissioned and served in the U.S. Air Force as a research engineering physicist. He performed and directed research in nuclear radiation effects, gas dynamics, and equation of state determinations. He also served as a project officer where he directed a theoretical program based on detailed experiments to predict radiation effect in solids. This work h) was essential for further system development. He also used U
large digital computer programs to aid in the solution of typical energy transport equations.
Memberships American Society of Quality Control American Nuclear Society (ANS), Chicago Section
- ANS-9, National Standards Subcommittee
- Chairman - ANS-9.7, Standards Working Group Publications
" Glossary of Terms in Nuclear Science and Technology,"
i ANS Publication (in printing), ANS-9 Subcommittee Member
" LWR In-Core Fuel Management Analysis"(coauthor) 4 "PWR Benchmark of Computer Code Power /s"(coauthor),
SL-3743,1979 i
"BIMSA - BWR Image Method Suppression Pool Analysis,"
Computer Code (09.5.142-1.0)(coauthor), May 1976, Proprietary
" Mark II Containment Dynamic Forcing Functions Information Report"(coauthor), jointly issued by General Electric Company and Sargent & Lundy, NEDO-21061, September 1975
,O 972,863 120584
SARGENT & LUNDY Resume 4 of 6 Henry G. L. McCullough O
Publications, Continued
" Computer Methods for Utility Reactor Physics Analysis,"
Reactor and Fuel Processing Technology (coauthor), Vol.12, No. 2, Spring 1969 1
i O
972,863 120584
SARGENT E LUNDY Selected Experience Record 5 of 6 Henry G. L. McCullough DC Nuclear Power Plant Deelen Projects i
Rated Cross Operating
. i - _..t Station - Unit MW Date(s)
Client Assignment Dese(s)
Byron 1,2
!!73 1985/1986 Commonwealth Project Quality 184 to present Braidwood 1,2 (each) 1986/1987 Edison Company Assurance Coordinator Project Management 3-81 to 1-84 Mechanical Engineer Safeguards Project 8-76 tc 3-81 Engineer Nuclear Analyst Engineering Analyst 2-74 to 8-76 Dresden 2,3 850 1971 Commonwealth Project Quality 1-84 to present (each)
Edison Company Assurance Coordir.ator Nuclear Analyst 8-76 to 1179 Engineering Analyst 2-74 to 8-76 p La Salle County 1,2 1122 1982/1984 Commonwealth Project Quality 1-84 to present (each)
Edison Company Assurance Coordinator Nuclear Analyst 8-76 to 11-79 Engineering Analyst 2-74 to 8-76 Quad Cities 1,2 850 1972 Commonwealth Project Quality 1-84 to present (each)
Edison Company Assurance Coordinator Clinton i 985 1986 tilinois Power Project Quality 8-84 to present Company Assurance Coordinator Nuclear Analyst 8-76 to 11-79 Engireering Analyst 2-74 to 8-76 Zimmer !
839 Suspended The Cincinnati Project Quality 1-84 to 2-84 Cas at Electric Assurance Coordinator Company Nuclear Analyst 8-76 to 11-79 Engineering Ana:yst 2-74 ts 8-76 Bailly N-1 684 Cawlled Northern trdana Safeguards Project 8-76 to 3-81 Public Service Engbeer Nuclear Company Analyst Zion 1.2 1085 1973/1974 Commonwealth Nuclear Analyst 8-76 to 11-79 (each)
Edison Company Kaiseraugst 932 Deferntd General Electric Nuclear Analyst 8-76 to 11-79 Company /$wiss Consortium a
972,863 120584
SARGENT & LUNDY Selected Experience Record 6 of 6 Henry G. L. MCCullough Nuclear Power Plant Dessen Proiscts. Contanued Rated Gross Operaths Assagnment Station - Unit MT bate (s)
Client A '_..a.t Date(s)
I l
Enrico Fermi 2
!!23
!)SS The Detroit Nuclear Analyst 8-76 to 11-79
)
Edison Company l
Dresden 1 200 1960 Commonwealth Engineering Analyst 2-74 to 8-76 Edison Company 1
Power Plant Betterment Project Rated Gross
?*.. _.t Station - Unit Fuel MW Client
? - '_.s.t Date(s) i Byron 1.2 Nuclear
!!75 Commonwealth Project Management 1-83 to 1-84 Braidwood 1,2 (each)
Edison Company Mechanical Engineer (new etfort pipe vibration testing)
Study I
Assignment Type of Study / Station - Unit (s)
Client Aasianment Date(s)
Nuclear Fuel Evacuation for Public Service Nuclear Analyst 7-78 to 8-78 Marble Hill Generating Station -
Indiana Units 3 and 4 l
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l O
972,863 120584 l
I cf 1 SARGENTS LUNDY Paul R. Olson O
Title Supervisor Engineering Mechanics Division Education University of lilinois - B.S.M.E. - 1973 Responsibilities Mr. Olson is responsible for the coordination of project and design work pertaining to the analysis of power plant piping systems. Working with engineering project teams, he supervises design efforts related to all aspects of piping analysis in accordance with ASME and ANSI codes.
Experience Mr. Olson's assignments over the last eleven years have included all phases of fossil and nuclear plant piping layout, design, and analysis. He has been actively involved in analysis work for three major nuclear facilities and has supervised various aspects of engineering work on ten major projects, including PWR and BWR plant designs. Other areas of experience include preparation of design specifications, review of component support designs, preparation of licensing documents, pipe rupture studies, and all interdivisional and
(
client / vendor communications to resolve design problems, identify interfacing procedures, and set project schedules.
Memberships ASME Special Working Group on Faulted Conditions Past Member - Mark 111 Containment Owners SRSS Subgroup O
970,462 061384
"%.a I ?f 3 Rided J. Pruski SARGENT & LUNDY Title Associate and Project Manager FAration University of Illinois - M.S. Nuclear Engineering - 1969 University of Illinois - B.S. Mechanical Engineering - 1968 Registrations Professional Engineer:
Illinois New Jersey Ohio Appointed Associate - 1978 Responsibilities As project manager, Mr. Pruski is responsible for the planning, coordination, and performance monitoring of Sargent & Lundy's work on the project. He leads the project engineering staff in the preparation of schedules, the project cost estimate, and the project scope of work. Mr. Pruski con-trols Sargent & Lundy's project engineering man-hour expendi-tures by regularly monitoring expended man-hours versus pro-jected man-hour estimates. He advises the client regarding the project's status in the monthly reports during review meetings and in his day-to-day communications with the client. He coordinates the development of documents such as p
design criteria, specifications, licensing documents, schematic V
and working drawings, bid evaluations, and design instruc-tions. On major purchases, Mr. Pruski works with the client and vendors to select equipment best suited for specialized plant operating duty. By virtue of his position, he has the authority to call upon the resources of the firm to meet the demands of the project.
Experience Mr. Pruski has extensive experience in the design and engi-neering of nuclear-fueled steam-electric generating stations.
He had served for 9 years in his present capacity as project manager on an 839-MW nuclear-fueled unit. Prior to his ap-pointment to project manager, Mr. Pruski served for 5 years as mechanical project engineer, responsible for the coordination of all the efforts between the engineering and other support specialists within the mechanical disciplines. He directed and,
supervised the work of mechanical engineers assigned to the project. Mr. Pruski was also responsible for ensuring conformance of mechanical project work to applicable Sargent & Lundy standards and procedures. This included preliminary design studies to determine general plant layout and sizing, specifying equipment, analysis of economic factors, preparation of flow diagrams, and sizing of piping including analysis of flexibility and support systems. He maintained client contact and incorporated operating philosophies into 970,507 101784
SARGENT & LUNDY Resume 2 of 3 Richard 3. Pruski O
Experience, Continued design parameters. He also interfaced with suppliers in selecting equipment, materials, and labor packages, evaluated proposals, and recommended parchases.
l Prior to this, Mr. Pruski served as an engineering analyst in the Mechanical Analytical Div.ision where he prepared numerous studies in the area of thermal-hydraulic analysis.
l Additionally, he performed engineering studies for power plant cooling systems.
In addition to his responsibilities on project werk, Mr. Pruski has also served as a member on a task force addressing the Sargent & Lundy Quality Assurance Program. The task force reports directly to the Director of Engineering recommending changes to the Quality Assurance Program and suggesting improvements in engineering irnplementation. Additionally, Mr. Pruski serves as Task Force Chairman of Sargent &
l Lundy's Emergency Planning Program. The task force is responsible for developing company programs for emergency planning to support client requ;rements for actual emergencies and emergency drills. Mr. Pruski joined Sargent & Lundy in 1968.
Memberships American Society of Mechanical Engineers (ASME)
AIF Cost Impact Subcommittee O
970,507 101784
SANGENT S LUNDY
- l**d Experience Record 3 of 3 Richard. Pruskt
[
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Power Plant Desian Proiects Rated Gross Operating A2 _ _.t Sution - Unit Fuel MW Date(s)
Client Assianment Da'te(s)
Zimmer 1 Nuclear 839 Suspended The Cincinnati Project Manager 10-74 to 4-84 Gas & Electric Company Mechanical Project 949 to 10-74 Engineer Dresden 2,3 Nuclear 850 1971 Commonwealth Engineering Analyst 648 to 949 (each)
Edison Company s
4 970,507 101784
SARGENT & LUNDY Resume 1 of 3 Roger M. Schiavons.
mU
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Title Senior Electrical Project Engineer Education University of Illinois - B.S.E.E. - 1971 a
Registration Professional Engineer - Illinois Responsibilities Mr. Schiavoni directs electrical engineers, analysts, and draftsmen in the development of the conceptual design, the design of individual system components, and the preparation of bid procurement specifications. Mr. Schiavoni supervises the project electrical engineering team that evaluates the proposals of manufacturers, makes purchase recommendations, and monitors the activities of manuf acturers to ensure that manufacturers' drawings and finished components are received on schedule. He works with the client and with manuf acturer and contractor representatives to ensure that the electrical design, engineering, and construction of the power plant incorporate the latest techniques. He coordinates the electrical engineering work with that of other Sargent & Lundy departments. Mr. Schiavoni reviews specifications and
/]
drawings to ensure that all electrical work is correctly done.
(/
Af ter plant construction begins, he may make occasional visits to the site to check on progress of the electrical work and to ensure that it is done properly.
Experience Mr. Schiavoni has been involved with the electrical engineering and design of two nuclear powered g;enerating stations. His assignments have included electrical design work related to turbine-generator and main cycle systems as well as the main and auxiliary power systems. He has participated in specif ying, evaluating, and integrating such items as the main and auxiliary power transformers, isolated and nonsegregated phase buses, medium and low voltage switchgear, large motors, and main control boards into the overall station design. Other responsibilities have included administration anc coordination of the electrical installation contract with the client and contractor, and coordination of electrical portiols of the safety analysis report. He currently has the priricipal responsibility for the engineering and design of all electrical aspects of a two-unit nuclear powered generating station.
G(G i
970,554 080784
SARGENT & LUNDY Resume 2 of 3 Roger M. Schiavoni O
Experience, Continued From 1978 through 1982, Mr. Schiavoni served on the Sargent & Lundy Quality Assurance Coordinating Committee.
This committee is responsible for reviewing, resolving, and coordinating departmental comments on the firm's quality assurance program and procedures. Committee members also serve as liaison between their respective engineering l
departments and the Quality Assurance Division.
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Mr. Schiavoni joined Sargent & Lundy in 1971.
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SARGENT & LUNDY Selected Experience Record 3 of 3 Roger M. Schiavoni Nuclear Power Plant Denisp Projects Rated Gross Operating Assignment Station - Unit MW Date(s)
Client Assignment Date(s)
La Salle 1,2 1122 1982/1984 Commonwealth senior Electrical 10-81 to present (each)
Edison Company Project Engineer Electrical Project 1-77 to 9-81 Engineer Electrical Engineer 6-71 to 12-76 Enrico Fermi 2 1123 1984 The Detroit Edison Electrical Engineer 6-71 to 6-72 Company l
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970,554 i
080784
Resume 1 of 8 SARGENTa LUNDY Anand K. Singh
/
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V Title Associate and Assistant Head Structural Analytical Division Education University of Illinois - Ph.D. Structural Engineering - 1972 University of Illinois - M.S. Structural Engineering - 1970 Indian Institute of Technology - B.S.C.E. - 1965 Registrations Professional Engineer - Illinois Structural Engineer - Illinois Appointed Associate - 1980 Responsibilities Dr. Singh supervises and coordinates the work of the Structural Analysis Sections in the preparation of analytical studies, special problem analyses, and computer program development.
Experience Dr. Singh has been engaged in static and dynamic analyses of power plant structures and in the development of general purpose computer programs for static, dynamic, and code
(
stress analyses of structures and piping. He has been involved
(.
in seismic response analysis of structures and piping, soil structure interaction; boiling water reactor (BWR) pool dynamics due to safety / relief valve (SRV) and loss-of-coolant accident (LOCA); design and analysis of cable trays and heating, ventilating, and air conditioning (HVAC) ducts; design of buried pipelines; design of pipe whip restraints; nonlinear response analysis; and American Iron & SteelInstitute (AISI),
American Institute of Steel Construction (AISC), and American Society of Mechanical Engineers (ASME) code stress analysis of structures and piping systems. In addition, he has worked to apply new concepts in earthquake engineering and vibrations to power plant structures.
Prior to joining Sargent & Lundy in 1972, Dr. Singh worked as a research assistant in the areas of earthquake engineering and computer program development, and as a design engineer.
of buildings and foundations.
Membership American Society of Civil Engineers (ASCE)
- Committee on Nuclear Standards - Seismic Analysis of Safety Class Structures Committee
- Task Committee on Turbine Foundations
- Nuclear Structures and Materials - Dynamic Analysis Committee 970,587 101584
SARGENT & LUNDY Resume 2 of 8 Anand K. Singh O
Publications "A Stochastic Model for Predicting Seismic Response of Light Secondary Systems" (coauthor A. H. S. Ang), Proceedings of the Fif th World Conference on Earthquake Engineering, Rome, 1973
" Influence of Closely Spaced Modes in Response Spectrum Method of Analysis" (coauthors S. L. Chu and S. Singh),
Proceedings, ASCE Specialty Conference on Structural Design of "uclear Plant Facilities, Chicago, Illinois, December 1973
'Qochastic Prediction of Maximum Seismic Response of Light Secondary Systems"(coauthor A. H. S. Ang), Nuclear Engineering and Design 29, pp. 218-230,1974
" Reliability Assessment of ASME Code Equations for Nuclear Components" (coauthor M. K. Ravindra), Reliability Engineering in Pressure Vessels and Piping, American Society of Mechanical Engineers (ASME), June 1975
" Seismic Response of Pipelines on Friction Supports"(coauthor
- 3. C. Anderson), Journal of the Engineering Mechanics Division, ASCE, EM2, pp. 275-291, April 1976
' inelastic Response of Nuclear Piping Subjected to Rupture Forces"(coauthor 3. C. Anderson), Journal of Pressure Vessel Technology, ASME, pp.98-104, May 1976 l
"A Probabilistic Model for Seismic Analysis of Nuclear Plant Structures" (coauthor S. Singh), Paper K3/3,4th International Conference on Structural Mechanics in Reactor Technology, l
San Francisco, California, August 15-19, 1977
" Dynamic Analysis of Piping Systems Using Substructures" (coauthor V. Kumar), presented at the ASME Design Engineering Technical Conference, Chicago, Illinois, Preprint,
No. 77-DET-144, September 26-30, 1977
" Technical Bases for the Use of the Square Root of the Sum of Squares (SRSS) Method for Combining Dynamic Loads for Mark 11 Plants" (coauthors S. W. Tagart and C. V. Subramanian),
General Electric Company Report NEDE 24010, July 1977
" Dynamic Analysis Using Modal Synthesis," Journal of the Power Division, ASCE, P02, pp.131-140, April 1978 0
970,587 101584
SARGENTS LUNDY Resume 3 of 8 Anand K. Singh V
Publications, Continued
" Response Analysis Using Dynamic Influence Coefficients" (coauthors T. P. Khatua, N. A. Holmes and S. L. Chu),
Proceedings of the 7th Conference on Electronic Computation, American Society of Civil Engineers, St. Louis, Missouri, August 1979
" Structural Building Response Review" (coauthors T. I. Hsu and T. P. Khatua), NUREG/CR 1423, Vol. II, U.S. Nuclear Regulatory Comraission, Washington, D.C., May 1980
" Prevention and Control of Vibrations"(coauthor D. E. Olson),
presented at the General Engineering Conference, Chicago, Illinois, March 1980
" Vibration in Power Plant Structures and Piping"(coauthor D. E. Olson), Proceedings of the American Power Conf erence, Chicago, Illinois, April 1980
" Soil Structure Interaction Using Substructures" (coauthors
/3 T. I. Hsu and N. A. Holmes), Proceedings of the ASCE
()
Specialty Conference, Civil Engineering and Nuclear Power, Knoxville, Tennessee, September 1980
" Evaluation of Soil Structure Interaction Methods"(coauthors T. I. Hsu, T. P. Khatua and S. L. Chu), presented at the second ASCE Engineering Mechanics Division Specialty Conference on Dynamic Response of Structures, Atlanta, Georgia, January 1981
" Seismic Analysis - Changing Considerations," Proceedings of the American Power Conference, Chicago, Illinois, April 1981 "An Integratec and Interactive Piping Analysis and Design Information System"(coauthor C. A. Podczerwinski),
Proceedings of the General Engineering Conference, Chicago,,
l Illinois, March 1982 "Modeling Considerations for Pool Dynamic Analysis" (coauthor D. C. Gupta), presented at the International Workshop on Soil Structure Interaction: Practical Solutions for Static and Dynamic Loading, Rurkee, India, October 10-14, 1983 f
\\
I V
970,587 101584
SARGENT S LUNDY Resume 4 of g Oj Anand K. Singh Publications, Continued "Use of Sampling in Nuclear Power Plant Applications" (coauthors M. Amin and P. Y. Wang), presented at the ASCE Speciality Conference on Probabilistic Mechanics and Structural Reliability, Berkeley, California, January 11-13, 1984
" Factors Controlling Strength of Structures, and Anticipated Overstrength for Seismic Load Conditions," presented at the EPRI/NRC Workshop on Nuclear Power Plant Reevaluation for Earthquakes Larger than SSE, San Francisco, California, October 14-17, 1984 l
l I
i l
O 970,587 101584
SARGENT5 LUNDY Selmed Experience Record 5 of 8 Anand K. Suigh O
V Power Plant Design Prow Rated Gross Operating
.^ ^
- a..t Station - Unit Fuel MW Date(s)
Client Asasanment Dese(s)
Clinton 1 Nuclear 983 1986 Illinois Power Seismic analysis; 1975 to present Company piping analysis; SRV-LOCA load analysis; seismic rask analysis; cable tray supports design; seismic reevaluation Byron 1,2/
Nuclear
!!73 1983/1986/
Commonwealth Seismic analysis; 1974 to present Braidwood 1,2 (each) 1986/1987 Edison Company turbine missile risk; piping analysis shear and block wall design; HVAC duct qualifica-tion; cable support design; seismic re-evaluation; pipe whip analysis i
w South 1,2 Coal 300 1986/1987 The Israel Electric Fan foundation design 1984 (each)
Corporation, Ltd.
s Seismic design criteria 1982 Marble Hill 1,2 Nuclear
!!73 Suspended Public Service Seismic analysis; cable 1979 to 1983 (each)
Indiana tray supports; HVAC duct qualification; reactor shield design; expansion anchor criteria Zimmer i Nuclear 839 Suspended The Cincinnati Seismic analysis; 1973 to 1983 Gas & Electric piping analysis; Company SRV-LOCA load analysis; HVAC cuct qualification; cable support design; SR55 load combination study; seismic re-evaluation La Salle 1,2 Nuclear 1122 1982/1984 Commonwealth Seismic analysis; SRV/
1972 to 1982 (each)
Edison Company LOCA analysts; piping analysis; shear and block walls; cable support design; SR$5 load combination; seismic reevaluation; pipe whip analysis Dolet Hills !
Lignite 107 1986 Southwestern Fan foundation design 1982 Electric Power Company / Central Louisiana Electric Company N.
970,587 101534
Selected Experience Record 6 of 8 SARGENT& LUNDY Anand K. Singh O
Power Plant Design Projects, Continued Rated Gross Operating Assignment Station - Unit Fuel MW Date(s)
Client Assignment Date(s)
B-2 Coal 750 1997 Middle South Seismic design criteria; 1980,1982 (held)
Services, Inc.
fan foundation design Enrico Fermi 2 Nuclear
!!23 1983 The Detroit Edison Seismic reevaluation 1981 Company H. W. Parkey 1 Lignite 707 1985 Southwestern Fan foundation design 1980 Electric Power Company Weston 3 Coal 321 1981 Wis:onsin Public Fan foundation design 1978 Service Corporation Lawton Tire Coal &
N.A.
1979 The Goodyear Tire & Fan foundation design 1978 Oil Rubber Company Pleasant Coal 570 1980 Wisconsin Electric Fan foundation design 1978 Prairie 1 Power Company GEX-Kaisera Jgst Nuclear 932 Deferred General Electric Seismic analysis; SRV/
1976, 1977 Company LOCA analysis MD l-4 Coal &
394 1981 1984 The Israel Electric Fan foundation design 1976 Oil (each)
Corporation, Ltd.
Power Plant Betterment Projects Rated Gross Assignment Station - Unit Fuel MW Client Assignment Date(s)
Dresden 2,3 Nuclear 850 Commonwealth Seismic SEP review; 1975 to 1982 (each)
Edison Company compressor vibration; tornado missile risk; Mark I torus modifi-cations; piping analysis Collins 4,5 Oil &
504 Commonwealth Fan vibrations; 1981,1982 Coal (each)
Edson Company tu-bine vibrations l
Coleto Creek 1 Coal /Ligr'ite 570 Central Power and Fan vibrations 1981 i
Light Company Colbert 3 Coal 350 Tennessee Valley Fan foundation design 1951 Authority Zion 1,2 Nuclear 1085 Commonwealth Seismic ultimate capa-1980,1981 (each)
Edison Comaany city; turbine missile risk Quad Cities 1.2 Nuclear 850 Commonwealth Seismic review; Mark i 1975,1979 (each)
Edison Company torus modification 970,587 101584 1
L
SARGENT E LUNDY Selected Experience Record 7of8 Anand K. Singh b
%J Power Plant Betterment Projects, Continued Rated Gross A, - - r.t Station - Unit Fuel MW Client A-2_
aat Date(s)
Dresden i Nuclear 200 Commonw ealth Seismic reevaluation; 1977 Edison Company tornado missile analysis Ghent 2 Coa!
311 Kentucky Utilities Fan duct vibration 1977 Blend Company Michigan City Coal N.A.
Northern Indiana Fan vibration 1976 Public Service Company Newton 1 Coal 56 7 Central I linois Fan foundation design 1975 Public Service Company Computer Protram Development Experierce A ', _.c.^
Prosram Program Description Assignment Date(s)
/
SMLBOR Small bore piping and Development of an interactive program 1983 to present support design and system to automate all aspects of draf ting system small bore piping and support design and draf ting activities SE15 HANG Analysis, design and Development of interactive program to 1976 to present draf ting of cable tray design and draf t supports for cable and HVAC duct supports trays and HVAC ducts PIPSYS Integrated piping Development of the analysis system; 1972 to present analysis system upgrading analysis capabilities to meet changing requirements; addition of interactive front and back end pro-cessors to increase productivity HANCAD 1.arge bore piping sup-Development of an interactive program 1984 port design and draf t-system to automate all aspects of large ing system bore piping s@ port design and draf ting activities PIPOPT Pipe support optimiza-Derelopment of an optimization pregram 1984 tion program system to minimize the number of snubbers anel spring hangers required to support a piping system DYNA 5 Dynamic analysis of Development of frequency domain analysis 1980 structures for soil structure interaction analysis us.ng soil impedance f unctions DINFU Dynamic soilimpec'ance Scil impedance f unctions f or layered 1980 functions soil media using integral equatio.
fctmulation v
970,587 101584
SARGENT& LUNDY Selected Experience Record 8 of 8 Anand K. Singh O
Computer Program Development Eurwience, Continued Assignment Program Program Description Assignment Date(s)
FLUSH Finite element soil Incorporate 3D structural modelin SSI 1979 structure interaction model using substructure formulation analysis FAST Frequency domain Development of program capabilities for 1976 to 1979 analysis of axisymmetric efficient analysis of containment structures structures for SRV/LOCA pool dynamic loads using the dynamic influence coefficient approach NONLIN2 Nonlinear analysis of Development of curved pipe element, gap 197te 2D piping and structures element, and program vahdation 9
l O
970,587 101384
SARGENTQ LUNDY Resume 1 of 3 Robert 3. Small 1
U(h Title Associate and Head Structural Project Engineering Division Education Purdue University - M.S.C.E. - 1964 Purdue University - B.S.C.E. - 1963 Registrations Professional Engineer:
Indiana Israel Louisiana Ohio Oklahoma Wisconsin Structural Engineer - Illinois Appointed Associate - 1973 Responsibilities Mr. Small directs the work of the senior structural project engineers and structural project engineers. His group is responsible for assuring that structural design conforms to applicable client, industry, and Sargent & Lundy standards and procedures. His group participates in major decisions concerning the plant design and construction in consultation with the client and other project-related disciplines. The major areas of development, abroect involvement include siting, sitecivil and structu
>b' treatment.
Experience Mr. Small has 20 years of experience in structural engineering and design of nuclear and fossil power plants. At increasing levels of responsibility, he has supervised the preparation of project design criteria, specifications, project criteria, and drawings. He also has analyzed and designed the sub-and superstructures and auxiliary components of major generating plants. Mr. Small joined Sargent & Lundy in 1964.
A4emberships American Society of Civil Engineers Chairman - Task Committee on Turbine Foundations - Energy Division American Concrete Institute Publications
" Low-Tuned Turbine Generatr Foundations"
" Post-Tensioned Concrete Nuclear Structures"(Coauthor)
"Effect of Earthquake Criteria on Nuclear Plant Design" (Coauthor) 970,596 101184
SARGENT S LUNDY
((*3,3,,13 2 of 3 9
Publications, Continued
" Seismic Analysis of Nuclear Power Plant Structures" (Coauthor)
" Current Considerations in the Seismic Design of Nuclear Power Station Equipment" (Coauthor) 9 l
O 970,596 101184
Se Expxh Rewd 3 gg 3 SARGENTS LUNDY Robert 3.Sm:dl t'C Power Plant Desian Projects Rated Grass Operating Assignment Station - tJnit M
MW onte(s)
Clien t Assianment Date(s)
Schahfer 17,18 Coal &
393 1983/1986 Northern Indiana Senior Structural 1977 to 1981 Oil (each)
Public Service Project Engineer Compwy Edgewater 3 Coal 180 1985 Wisco isin Power and Senior Structural 1977 to 1981 Light Company Project Engineer Bailly NI Nuclear 684 Cance!!ed Northetn Indiana Senior Structural 1977 to 1981 Public Service Project Engineer Comp!.ny Weston 3 Coal 321 1981 Wisco1 sin Public Senior Structural 1974 to 1978 Servicia Company Project Engineer NP.I Nuclear 900 Cance!!ed The Is ael Electric Senior Structural 1975 to 1977 Corpo ation, Ltd.
Project Engineer Pleasant Coal 570 1980/1985 Wisconsin Electric Senior Structursi 1974 to 1977 Prairie 1,2 (each)
Comptny Project Engineer
(
970,596 101184
SARSENTa LUNDY Resume I of 2 Robert M. Wd OJ Title Project Engineer Component Qualification Division Education University of Illinois (Urbana)- B.S. Engineering Mechanics -
1975 Registration Professional Engineer - Illinois Responsibilities Mr. Tjernlund is responsible for demonstrating the adequacy of all of the safety-related equipment used in nuclear power generating stations to perform their safety-related functions in the event of a seismic occurrence or accident. He supervises a project team staff in the Component Qualification Division in the preparation and review of equipment and design procurement specifications, performance of bid evaluations, calculation of loads required for design of equipment foundations and building floor slabs, preparation and review of equipment dynamic qualification reports, preparation and review of ASME certified design reports, preparation and review of NRC licensing documents, and in the design and analysis of mechanical piping penetration assemblies.
Experience Mr. Tjernlund has nine years of nuclear experience in the design and analysis of mechanical piping penetration assemblies and seven years of nuclear experience in qualifying equipment for postulated seismic and accident events. He has experience in Fortran IV programming, including program development and maintenance, component stress analysis, finite element modal analysis, dynamic testing techniques used l
for seismic qualification of equipment, impedance testing techniques used for determining the dynamic characteristics of equipment, and fatigue analysis. In addition, he is familiar with several codes and standards, including ASME B&PV Code Sections 111 and XI; AISC Steel Construction Manual; AWS standards; IEEE-323,344; and NRC regulatory guides. Mr.
Tjernlund joined Sargent & Lundy in 1975.
1 Membership American Society of Mechanical Engineers i
O I
970,638 031934
SARGENT & LUNDY Selected Experience Record 2 of 2 Robert M. Tjernlund O
Nuclear Power Plant Projects Rated Gross Operating Assignment Station - Unit MW Date(s)
Client Assignment Date(s)
Clinton !
983 1986 Illinois Power Project Engineer 1984 to present Company (equipment qualification)
Zimmer 1 839 Cancelled The Cincinnati Gas &
Project Engineer 1979 to 1984 Electric Company (equipment quali-fication)
Carroll County
!!75 2000/2001 Commonwealth Edison Project Engineer 1977 to 1979 1,2 (each)
Company (equipment quali-fication)
Clinton !
983 1986 Illinois Power Engineering Analyst 1976 to 1979 Company (penetration design and analysis)
La Salle 1,2 1822 1982/198'*
Commonwealth Edison Engineering Analyst 1975 to 1976 (each)
Company (penetration design and analysis)
O 970,638 031984
Resu...
I vi 3 Paul I. Wateld SARGENT & LUNDY O
Title Partner and Project Director Education Purdue University - Ph.D. Nuclear Engineering - 1966 Illinois Institute of Technology - B.S. Physics - 1962 Registrations Professional Engineer:
Illinois Indiana Kansas Michigan New York Admitted to Partnership - 1982 Appointed Associate - 1981 Responsibilities As a project director, Dr. Wattelet is responsible for the implementation of the work and the technicalintegrity of the project during its execution. In the course of discharging these responsibilities, Dr. Wattelet directs project teams staffed by project managers, project engineers, and other technical personnel. Dr. Wattelet consults with the clients and project teams in planning and scheduling the project, and developing the appropriate cost control systems. He leads the development of and monitors project management documents O
such as engineering and construction schedules, man-hour U
estimates, project cost estimates, and scope of work.
Dr. Wattelet regularly reports to the client regarding performance on the project and the status of engineering and construction. He works jointly with the client and project team on setting design parameters and operating philosophies which have significant engineering and economic implici.tions. Dr. Wattelet directs the appropriate application of the Sargent & Lundy engineering policies and philosophies and maintains surveillance of the design to ensure their implementation throughout the project.
i Experience Dr. Wattelet has over 17 years of experience in the engineering and design of major nuclear steam-electric l
generating stations, including the design of nuclear steam l
supply systems. At Sargent & Lundy he has been involved with, balance-of-plant designs for large central generating station projects and also with backfit and betterment engineering services for several nuclear units.
Dr. Wattelet was a mechanical project engineer, project manager, and project director for a two-unit 2250-MW pressurized water reactor project. In these positions, he controlled Sargent & Lundy's project engineering man-Four expenditures by regularly monitoring expended man-hours versus projected man-hour estimates. He coordinated the V
970,679 102484
SARGENT E LUNDY Resume 2 of 3 Paul L. Wattelet 9
Experience, Continued development of engineering documents such as design ~ criteria, specifications, licensing documents, schematic and working drawings, bid evaluations, and design instructions. On major purchases, he worked with the client and vendors to select equipment best suited for specialized plant operating duty.
Dr. Wattelet was also responsible for conformance of mechanical project work to applicable Sargent & Lundy standards and procedures. These included preliminary design studies to determine general plant layout, sizing, specification of equipment, analysis of economic factors, preparation of flow diagrams, and sizing and flexibility analysis of piping and support systems.
He has also been supervisor of Safeguards Systems Analysis in Sargent & Lundy's Nuclear Safeguards and Licensing Division responsible for methods development and analysis of nuclear safeguards systems.
Prior to joining Sargent & Lundy in 1972, Dr. Wattelet was a Senior Engmeer for plant safety analysis in the Advanced Reactor Division of Westinghouse Electric Corporation. He developed methods for analyzing accidents in Liquid Metal Fast Breeder Reactors (LMFBR) and performed safety analyses on the Fast Flux Test Facility (FFTF). He organized and participated in regulatory proceedings for FFTF and interfaced with the AEC/RDT, who provided the funding for the LMFBR projects he worked on. Before this, Dr. Wattelet was an engineer at NASA where he participated in core design of the tungsten-water moderated rocket reactor.
Memberships American Nuclear Society Society of Sigma Xi Western Society of Engineers Publications "Two Years After TMl"(coauthored), Midwest Engineer, publication of Western Society of Engineers, September 1981 "TM1-2 Plus Two"(coauthored), Sargent & Lundy General Engineering Conference, Chicago, Illinois, March 1981
" Multi-Cell Analysis of High-Energy Fluid Line Breaks,"
American Nuclear Society Winter Meeting, San Francisco, California,1973 "FFTF Barriers to Fuel Failure Propagation," American Nuclear Society Summer Meeting, Boston, Massachusetts,1971 O
970,679 102484
SARGENT S LUNDY Selected Experience Record 3 cf 3 Paul L. Wattelet s
Power Plant Design Projects Rated Grose Operating Assagnment Statnon - Unit Fuel MW Date(s)
Client Assignment Dete(s)
Marble Hill 1,2 Nuclear 1175 Suspended Public Service Project Director 1982 to present (each)
Indiana Project Manager 1978 to 1982 Mechanical Project 1973 to 1978 Engineer 1
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- - _ _ _- _ _ - _. ~ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _.. _ _ _. _ _ _ _ - - _ _, _
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1 SARGENT E LUNDY Resume 1 of 3 Donald P. White
,O i V
)
Title Project Manager Education University of Illinois - B.S.C.E. - 1958 lowa State University - M.S./ Nuclear Engineering - 1961 Registrations Professional Engineer:
Illinois Oregon Pennsylvania Washington Responsibilities As project manager, Mr. White is responsible for the plan-ning, coordination, and performance monitoring of Sargent &
Lundy's work on the project. He leads the project engineering staff in the preparation of schedules, the project cost estimate, and the project scope of work. Mr. White controls Sargent & Lundy's project engineering man-hour expenditures by regularly monitoring expended man-hours versus projected man-hour estimates. He advises the client regarding the project's status in the monthly reports during review meetings and in his day-to-day communications with the client. He coordinates the development of documents such as design criteria, specifications, licensing documents. schematic and working drawings, bid esaluations, and design instructions. On d
major purchases, Mr. White works with the client and vendors to select equipment best suited for specialized plant operating duty. By virtue of his position, he has the authority to call upon the resources of the firm to meet the demands of the project.
Experience Mr. White has a long and distinguished career record in the engineering and design of nuclear power stations. Before rejoining Sargent & Lundy this year, he served for 15 years as a nuclear engineer, at increasing levels of responsibility, for another large AE serving the power industry. His most recent position there was as Manager of Engineering, directing the technical performance of all engineering and drafting personnel assigned to the firm's West Coast office (approximately 100 engineers). Prior to this position, he was Manager of the Nuclear Section of the Mechanical Engineering Department. He was responsible for the administration of a large group of mechanical engineers and development and maintenance of design guides, guide specifications, and department procedures. He also provided liaison with clients, prepared estimates and proposais, and consulted and advised the Advanced Engineering Group on all aspects of mechanical design. His project engineering experience with that firm O
972,850 121084
SARGENT & LUNDY
@P. White O
Experience, Continued included work on three nuclear station design projects. One of these projects included HTGR and LWR reactor technologies.
Another of these stations was a two 1200-MW unit BWR de-sign. His prior project engineering experience with Sargent &
Lundy included work for two nuclear station design projects; a two 1100-MW unit PWR station and a 330-MW HTGR unit.
Mr. White also directed S&L's efforts on feasibility studies for liquid metal fast breeder reactor power plants.
O O
972,850 121084
SANGENT5 LUNDY Selected Experience Record 3 of 3 Donald P. White
[
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Power Plant Desian Projects Rated Gross Operating Assignment Station - Unit Fuel MW Date(s)
Client Aasianment Date(s)
Perry 1,2*
Nuclear 1200 1985/1988 The Cleveland Senior Project 1972 to 1973 (each)
Electric Engineer Illuminat ng Company i
Takahamn 1*
Nuclear 826 1973 Kansal Electric Project Engineer 1969 to 1972 Power Company, Japan Fort St. Vrain Nuclear 330 1979 Public Service Nuclear Project 1966 Colorado Engineer Commonwealth Nuclear Project 1967 to 1969 Zion 1,2 Nuclear 1100 (each)
Edison Company Engineer
- Projects performed with Gilbert / Commonwealth, i
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972,850 121084
SARGENT & LUNDY Resume 1 of 3 Osama Zaben O
Title Associate and Senior Structural Project Engineer Faration Illinois Institute of Technology - M.S.C.E. - 1972 University of Illinois - B.S.C.E. - 1968 Registrations Professional Engineer:
Illinois Indiana Kansas New York Wisconsin Structural Engineer - Illinois Appointed Associate - 1982 Responsibilities As a senior structural project engineer, Mr. Zaben supervises the structural project engineers. Mr. Zaben is responsible for seeing that structural design conforms to applicable client, industry, and Sargent & Lundy standards and procedures. He participates in major decisions concerning the plant design and construction in concert with the client and other project-related disciplines. The major areas of his project involvement include siting, site development, all civil and structural work, and architectural treatment. He reviews and approves the basic plant desig,n criteria and any unique structural engineering design concepts. He authorizes Sargent & Lundy drawings for construction by his sigaa ure and seal. Mr. Zaben reviews structural engineering and construction schedules and the project scope of work. Mr. Zaben coordinates the structural activities in the preparation of monthly project engineering and construction reports. Mr. Zaben coordinates preparation of specifications for equipment, materials, and labor packages. He evaluates proposals and makes purchase recon.mendations.
Experience Mr. Zaben has extensive experience in the civil, structural, and architectural engineering and desiga cf fossil and nuclear power plants. As a structural project engineer, he has been in, i
charge of six power plant projects and seven power plant modifications, studies, and sitework. Prior to that, he worked on seven coal, one coal and oil, and three nuclear stations at increasing levels of responsibility. He in a member of Sargent & Lundy's Reference Design Plant Committee and Structural Standards Review Committee.
j Throughout his 15-year power plant career, Mr. Zaben has designed or supervised the design of power plant structures; l
site selection and site layout, including road and railroad I
layout; water intake and discharge structures; coal unloading l
facilities; disposal dike facilities for fly ash, bottom ash, and 970,717 l
101184 l
SARGENT & LUNDY Resume 2 of 5 Osama Zaben Experience, Continued flue gas desulfurization byproducts; and design of chimneys and chimney liners, coal silos, coal bunkers, and wastewater treatment structures.
As an assistant chief structural design engineer, he was involved in one nuclear unit and five fossil units. He reviewed project work with the supervisors for conformance with codes and criteria, and he assisted them in solving special problems.
He monitored project progress and manpower requirements, developed design standards, and gave lectures on the structural design of power plants to new engineers.
As a supervising design engineer, Mr. Zaben coordinated the structural work on a nuclear project. He collected, reviewed, and disseminated information to his assigned engineers. He developed project design criteria and procedures and guided engineers in their design work. As a structural engineer, he was involved in the design of fossil and nuclear power plant structures.
Prior to joining Sargent & Lundy in 1970, Mr. Zaben worked as a designer of highway bridges and as a designer of power plants and precipitator support structures.
Membership American Society of Civil Engineers O
970,717 101184
Selected Experience Record 3 of 5 SARGENTS LUNDY Osama Zaben f%b Power Plant Desean Protects Rated Gross Operating Assignment Station -lJnit Fuel MT Date(s)
Client Asenanment Date(s)
Pleasant Coal 570 1985 Wisconsin Electric Senior Structural 1982 to present Prairie 2 Power Company Project Engineer Reference Plant Coal 600-700 Sargent & Lundy Senior Structural 1979 to present Project Engineer Marble Hill 1,2 Nuclear 1175 Suspended Public Service Senior Structural 1979 to 1983 (each)
Indiana Project Engineer MTA Fossil Plant
- Coal, 697 1996 New York Power Senior Structural 1982 to 1983 Oil, &
(held)
Authority Project Engineer Reluse Gibson 3 Coal 618 1982 Public Service Senior Structural 1982 Indiana Project Engineer (includes coal unloading)
Weston 3 Coal 321 1981 Wisconsin Public Structural Project 1977 to 1982 p
Service Corporation Engineer k,/ Braidwood 1,2 Nuclear 1175 1986/1987 Commonwealth Senior Structural 1979 to 1981 (each)
Edison Company Project Engineer Byron 1,2 Nuclear 1173 1985/1986 Commonwealth Senior Structural 1979 to 1981 (each)
Edison Company I'roject Engineer Lawton Tire 1,2 Coal &
NA 1979 The Goodyear Structural Project 1977 to 1979 Oil Tire & Rubber Engineer (process Company steam)
Havana 6 Coal 439 1978 Illinois Power Assistant Chief 1975 to 1977 Company 5tructur11 Engineer East Bend 2 Coal 648 1981 The Cincinnati Assistant Chief 1975 to 1977 Gas & Electric Structural Engineer Company Coleto Creek i Coal 570 1980 Central Power and Assistant Chief 1974 to 1977 Light Company Structural Engineer
~
Zimmer 1 Nuclear 839 Suspended The Cincinnati Assistant Chief 1974 to 1977 Gas & Electric Structural Engineer Company Lansing 4 Coal 252 1977 Interstate Power As,sistant Chief 1974 to 1976 Company Structural Engineer Miami Fort 8 Coal 312 1978 The Chcinnati Assistant Chief 1975 Gas & l'lectric Structural Engineer Companf Clinton i Nuclear 985 1966 Illinois Power Supervising Structural 1973 to 1974 (q)
Company Engineer v
970,717 l
101184 l
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IM Experience Record 4 OI 5 SARGENT& LUNDY Osama Zaben O
Power Plant Desian Proiects, Continued Rated Gross Operating Assignment Station - Unit Fuel MW Date(s)
Client Asmanment Date(s)
Ghent!
Coal 511 1974 Kentucky Utilities Structural Engineer 1970 to 1973 Company Bailly NI Nuclear 684 Cancelled Northern Indiana Structural Engineer 1972 Public Service Company Power Plant Betterment Projects Rated Gross Assignment Station - Unit Fuel MT
_Clienj Assignment Dete(s)
Cayuga1,2 Coal 531 Public Service Senior Structural 1982 to present (each)
Indiana Project Engineer (chimney steel liner examinations)
Fort St. Vrain 1 Nuclear 330 Public Service Senior Structural 1979 to present Company of Colorado Project Engineer (miscellaneous modifications)
Grand Tower 3,4 Coal 60/100 Central lilinois Senior Structural 1984 Public Service Project Engineer Company (modifications to levee and to crib house) l Surry 1,2 Nuclear 775 Virginia Electric Senior Structural 1983 (each) and Power Company Project Engineer (miscellaneous modifications) l North Anna 1,2 Nuclear 1755 Virginia Electric Senior Structural 1983 (total) and Power Company Project Engineer (miscellaneous modifications)
Newton 1,2 Coal 567 Centrallilinois Senior Structural 1983 (each)
Public Service Project Engineer Company (chimney, liners, and coatings examination)
Coffeen 1,2 Coal 938 Central Illinois Senior Structural 1983 (total)
Public Service Project Engineer Company (examination of repair of silos) 9 970,717 101184
SARGENT & LUNDY Selected Experience Record 5 of 5 osama Zaben C'
Power Plant Betterment Pro' wets, Continued Rated Gross Assignment Station - Unit Fuel MW Client Assisnment Date(s)
Virginia Electric Senice Structural 1983 Various Fossil &
Nuclear and Power Company Prcjeet Engineer (conc eptual studies for fossi and nuclear plants)
Wabash River 1-6 Coal 886 Public Service Senice Structural 1982 to 1983 (total)
Indiana Project Engineer (ash pond extension)
Senice Structural 1982 to 1983 Project Engineer (ductwork and chimney)
Muskogee Coal 572 Oklahoma Gas and Senice Structural 1982 to 1983 Electric Company Project Engineer (evaluation of pre-cipitator support steel) x Sooner Coal N.A.
Oklahoma Gas and Senice Structural 1982 to 1983 f"d)
Electric Company Project Engineer N
(evaluation of pre-cipitator support steel)
{
Wolf Creek i Nuclear 1100 Kansas Gas and Senice Structural 1982 Electric Company Project Engineer (site work)
R. A. Gallagher Coal 150 Public Service Senice Structural 1982 1-4 (each)
Indiana Project Engineer (chimney repairs)
Sequoyah1,2 Nuclear 1128 Tennessee Valley Senice Structural 1980 (each)
Authority Project Engineer (containment venting cerceptual design)
Zion 1,2 Nuclear 1085 Commonwealth Edison Senice Structural 1979 to 1980 (each)
Company Project Engineer (misc ellaneous
~
modifications)
CN I
)
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970,717 101184
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SARGENT5 LONDY VIII-2 REVISION O i
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Internal Review Committee O
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Resume 1 of 3 SARGENTS LUNDY Ernest B. Branch O
Title Associate and Mechanical Design Director Education Virginia Polytechnic Institute - B.S. Engineering Mechanics -
1964 Registration Professional Engineer - Illinois Appointed Associate - 1973 Responsibilities Mr. Branch is the mechanical design director with responsibility for the Engineering Mechanics Division and the Mechanical Design and Draf ting Division. He is responsible for the integration and coordination of the divisions' output with that of other divisions and departments. He assigns areas of responsibility to each division and ensures that the divisions perform all assigned work within budget, within schedule, and with an acceptable level of quality. He performs other functions and tasks as required by the assistant department manager or the department manager, p
Experience Mr. Branch has extensive experience in the stress analysis of Q
piping systems and mechanical equipment for power plants.
Before assuming his position as mechanical design director, he was the head of Sargent & Lundy's Engineering Mechanics Division. In this capacity, Mr. Branch directed a group of systems analysts, component analysts, and computer specialists. The division's scope of work involved stress analysis of the pip equipment for maj,ing systems and associated mechanical or steam-electric generating stations, both nuclear-and fossil-fueled. The division has been responsible for evaluating the seismic qualifications of the safety-related mechanical and electrical equipment used in nuclear plants and provided the piping and equipment criteria used in Safety Analysis Reports. The division also has done design and analysis for penetration assemblies and performed hydraulic and thermal transient analyses for piping and mechanical equipment.
Before joining Sargent & Lundy in 1969, Mr. Branch did stress analysis of piping systems for naval nuclear power plants. He determined the specification requirements for the purchase of piping, fittings, and valves, and qualified certain pieces of equipment for shock analysis and testing.
O 970,059 101584
Resume 2 of 3 SARGENT& LUNDY Ernest B. Branch O
Memberships American Society of Mechanica1 Engineers
- Boiler and Pressure Vessel Code
- Section III Committee
- Section III Subgroup on Design
- Section III Working Group on Piping
- PVRC Technical Committee on Piping Systems Publications
" Stress Limits for Class 2 and Class 3 Components Under Upset, Emergency, and Faulted Conditions" (coauthor
- 3. Gascoyne), ASME Paper No. 76-PVP-61 "The Impact of ASME Section Ill," Power Magazine, October 1975
'"cconomic Impact of Seismic Requirements in Nuclear Power Stations," (coauthor R. Small), Sargent & Lundy General Engineering Conference,1971 1
" Transient Thermal Gradient Stress," Heating / Piping / Air Conditioning, January 1971 i
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970,059 101534 1
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SARGENT & LUNDY Selected Experience Record
.3of3 Ernest B. Branch O
jdgjear Power Plant Desian Proisets Rated Gross Operating
? ';-
t Station - Unit MW Date(s)
Client Asetsunent Date(s)
Zion 1,2 1085 1973/1974 Commonwealth Edison Division Head 1974 to 1981 (each)
Company Quad Cities 1,2 850 1972 Commonwealth Edison Division Head 1973 to 198!
(each)
Company Marble Hill 1,2 1175 Suspended Public Service Indiana Division Head 1973 to 1981 (each)
Clanton 1,2 985 1986/ Cancelled lilinois Power Company Division Head 1972 to 1981 (each)
Braidwood 1,2
!!75 1986/1987 Commonwealth Edison Division Head 1972 to 1981 (eacn)
Company Byron 1,2 1175 1985/1986 Commonwealth Edison Division Head 1971 to 1981 (each)
Company Dresden 2,3 850 1971 Commonwealth Edison Division Head 1970 to 1981 (each)
Company
\\
La Salle 1,2
!!22 1982/1984 Commonwealth Edison Division Head 1970 to 1981 (each)
Company Zimmer 1 839 Suspended The Cincinnati Gas &
Division Head 1970 to 1981 Electric Company Bailly N-1 684 Cance!!ed Northern Indiana Division Head 1970 to 1981 Public Service Company Enrico Fermi 2
!!23 1984 The Detroit Edison Division Head 1970 to 1981 Company Carroll County
!!75 2000/2001 Commonwealth Edison Division Head 1978 to 1979 1,2 (each)
Company Fort St. Vrain 1 330 1979 Public Service Company Division Head 1970 to 1979 of Colorado
[
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970,059 101584 l
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SARGENT & LUNDY Resume 1 of 3 Bryan A. Erler Title Associate and Structural Design Director Education Purdue University - M.S.C.E. - 1970 Purdue University - B.S.C.E. - 1969 Registration Structural Engineer - Illinois Appointed Associate - 1979 Responsibilities Mr. Erler directs the following four Structural Design Divisions, the Structural Engineering Division, the Structural Draf ting Division, the Architectural Design Division, and the Structural Engineering Specialist Division. The principal responsibilities for the four divisions include preparation review, and approval of all Structural Engineering cciculations for reinforced concrete and steel structures; and preparation, and review of Structural, Civil, and Architectural drawings for all power plant structures. This would include all structural aspects of Sargent & Lundy projects, including foundations, structural steel, reinforced concrete, air and gas duct work, g) prestressed concrete, siding, roofing, windows, and laterior
(
architectural work. In order to perform the above primary v
responsibilities, personnel from these four Divisions participate in many support activities, such as developing General Arrangements, performing design studies, reviewing procurement specifications, and reviewing vendor drawings.
Experience Mr. Erler has been responsible for the design and analysis of all containment vessels in Sargent & Lundy nuclear power plants. He has supervised the design of prestressed and reinforced concrete containments for many plants and has been responsible for seismic analysis of these stations as well. Mr. Erler has also been active in the development of several national standards for the structural design of nuclear power plants. Through his work with professional committees he has been involved in the development of criteria for nuclear, containment design and design for other extreme loads on nuclear plant structures, such as high energy line break effects and seismic excitation. Mr. Erler joined Sargent & Lundy in 1970.
Memberships American Concrete Institute American Society of Civil Engineers Post-Tensioning Institute l
970,166 101284
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SARGENT S LUNDY Resume 2 of 3 I
Bryan A. Erler O
Committees ASME/ACI Joint Technical Committee on Concrete Pressure Vessels for Nuclear Application ACI-348 Structural Safety t
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SARGENT4 LUNDY Selected Experience Record 3 cf 3 aryan A.Erler O
Power Plant Deslan Proiects Rated Gross Operating Assignment Station - tJnit Fuel MT Date(s)
CEent Anianment Date(s)
Marble Hill 1,2 Nuclear 1175 Suspended Public Service Containment Design 1973 to 1975 (each)
Indiana and Seismic Analysis Clinton 1 Nuclear 985 1986 tilinois Power Containment Design 1972 to 1973 Company and Seismic Analysis Braidwood 1,2 Nuclear 1175 1986/1987 Commonwealth Containment Design 1972 to 1975 (each)
Edison Company and Seismic Analysis Byron 1,2 Nuclear 1175 1985/1986 Commonwealth Containment Design 1971 to 1975 (each)
Edison Company and Seismic Analysis La Salle 1,2 Nuclear 1122 1982/1984 Commonwealth Containment Design 1971 to 1975 (each)
Edison Company and Seismic Analysis Zimmer 1 Nuclear 839 Suspended The Cincinnati Gas & Containment Design 1971 to 1975 Electric Company Zi Nuclear 1085 1973/1974 Commonwealth Containment Design 1971 to 1973 O
on 1,2 (each)
Edison Company D.C. Cook 1,2 Nuclear
!!26 1975/1978 Indiana & Michigan Auxiliary Building 1970 to 1971 (total)
Electric Company Design Reinforced on Concrete O
970,166 101284
SARGENT & LUNDY Resume 1 of 3 Leonard R. Stenslanc O
Title Associate and Electrical Design Director Electrical Design & Drafting Division Fahr ation Illinois Institute of Technology - M.S.E.E. -1956 lilinois Institute of Technology - B.S.E.E. - 1952 Registrations Professional Engineer:
Arkansas Illinois Indiana Kentucky Louisiana Michigan New York Ohio Texas Wisconsin Appointed Associate - 1969 Responsibilities Mr. Stensland develops and monitors the effectiveness of procedures for the efficient flow of design information from the Electrical Project Engineering Division and other departments to the Electrical Design and Draf ting Division in order to enhance the quality of the work and minimize she man-hours needed to perform it. He also develops and' monitors the effectiveness of the Electrical Drafting l
Standards and the Drafting and Field Standards. Mr. Stensland is responsible for establishing and monitoring Electrical Design and Drafting offices at power plant sites; recommending hirings, promotions, transfers, terminations, and salary adjustments for the individuals at those offices; and approving expense accounts. He is responsible for negotiating, preparing, and maintaining contracts for contract personnel for Electrical Design and Draf ting. for both main office assignments and power plant site assignments. In addition, he supervises the work of the Electrical Department Computer Applications l
Coordinator, including investigation of methods of utilizing new technology to reduce the man-hours for Electrical Department work (computers, computer-aided draf ting, microfiche, aperture cards, etc.).
Experience Mr. Stensland has 30 years of experience in the electrical engineering and design of major steam-electric generating stations, both nuclear-and fossil-fueled, and associated substations. He has held numerous responsible positions at Sargent & Lundy, including head of the Electrical Project Engineering Division and head of the Electrical Design and Drafting Division, since he joined the firm in 1952. He is currently Sargent & Lundy's specialist in transformers.
OV 970,615 100884
Resume 2 of 3 SARGENT & LUNDY Lecnard R. Stensland 9
Memberships Illinois Society of Professional Engineers National Society of Professional Engineers Institute of Electrical and Electronics Engineers
- Transformer Committee Publication "A Study of Twin Conductor Arrangement"(coauthor Dr.
E.T.B. Gross), AIEE Transactions, Vol. 72, Pt. 3 (1958) 1
(
100884
Selected Experience Record 3 cf 3 SARGENT & LUNDY Leonard R. Stensland I
Power Plant Desian Projects Rated Gross Operating Assignment Station - Unit Fuel MW Date(s)
Client Assisnment nite (s)
Havana 6 Coal 439 1978 tilinois Power Senior Electrical 1974 to 1976 Company Project Engineer Newton I Coal 567 1977 Central Illinois Senior Electrical 1973 to 1976 Public Service Project Engineer Company Meredosia 4 Oil 194 1975 Central Illinois Senior Electrical 1973 to 1975 Public Service Project Engineer Company Ghent1,2 Coal 511 1974/1977 Kentucky Utilities Senior Electrical 1972 to 1975 (each)
Company Project Engineer Baldwin 1-3 Coal 1655 1970/1973/
Illinois Power Senior Electrical 1968 to 1974 (total) 1975 Company Project Engineer Coffeen 2 Coal 612 1972 Central Illinois Senior Electrical 1970 to 1973 Public Service Project Engineer Company
\\/
Kincaid 1,2 Coal 580 1967/1968 Commonwealth Electrical Project 1964 to 1968 j
(each)
Edison Company Engineer j
Wood River 3 Coal 356 1964 Illinois Power Electrical Engineer 1961 to 1964 Company State Line 4 Coal &
325 1962 Commonwealth Electrical Engineer 1955 to 1961 Gas Edison Company Hennepin 2 Coal &
200 1959 Illinois Power Electrical Engineer 1956 to 1959 Gas Company 970,615 100884
5 ARGENT 8:LUNDY Resume 1 of 3 Homer S. Taylor Title Associate and Head Quality Assurance Division Education Ohio State University - B.E.E. - 1972 Appointed Associate - 1983 Responsibilities Mr. Taylor is responsible to the Director of Services for formulating and administering the Quality Assurance Programs for both nuclear-and fossil-fired power plants. He develops the general Quality Assurance procedures necessary for implementation of the programs and coordinates the preparation of detailed procedures prepared by other departments and divisions. He is responsible for interfacing with the client's Quality Assurance organizations and the Nuclear Regulatory Commission (NRC). He also takes responsibility for training sessions in the use and implementation of the Quality Assurance program and procedures for all personnel involved in safety-related activities. He directs internal and external audits of pQ consulting organizations retained by Sargent & Lundy. He is also responsible for establishing and maintaining controls for identification, storage, and retrieval of quality assurance records.
l Experience Mr. Taylor has served in his present capacity since May of 1982 and has extensive experience in Quality Assurance administration. Since January of 1974, when Mr. Taylor was appointed senior Quality Assurance instructor, he has developed and maintained Quality Assurance procedures that l
meet established government and industry requirements for nuclear power plant quality assurance. In 1979 he developed the Sargent & Lundy Quality Assurance Program for fossil-fueled power plants.
Before assuming the position of head of the Quality Assurance Division, Mr. Taylor served as assistant head for 6 years. He was responsible for assisting the head of the l
Division in the operation, planning, and supervision of the Quality Assurance Division.
l Previous to this, Mr. Taylor served as senior Quality Assurance administrator for nearly 2 years. During this time, he was responsible for the preparation and maintenance of the Sargent & Lundy Quality Assurance Manual and ensuring its continued conformance to applicable codes, standards, and regulatory requireme:nts.
U 970,631 102684
SARGENT & LUNDY Resume 2 of 3 Homer S. Taylor O
Experience, Continued Prior to moving to the Quality Assurance Division in January of 1974, Mr. Taylor served as an electrical engineer for 1-1/2 years on a 985-MW nuclear-fueled generating station.
His responsibilities included design engineering on various electrical plant systems. Mr. Taylor joined Sargent & Lundy in 1972.
Membership American Society of Mechanical Engineers (ASME) Committee on Nuclear Quality Assurance - Main Ccmmittee
- Design and Procurement Subcommittee
- Procurement Control Work Group 9
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O 970,631 102684 1
Selected Experienca Record 3 cf 3 SARGENT & LUNDY Homer S. Taylor OG Power Plant Desian Project Rated Gross Operating A - ; _.c.t Station - Unit Fuel MW Date(s)
Client Assignment Date(s)
Clinton i Nuclear 985 1986 Illinois Power Electrical Engineer 6-72 to 1-74 Company
)
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102684
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1 SARGENT E LUNDY VIII-3 REVISION O 3/22/85 j
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Senior Review Committee t
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Resume 1 of 3 SARGENTS LUNDY Eugene V. Abraham GV Title Pa-tner and Manager Mechanical Department Education Uriversity of Illinois - B.S.M.E. - 1960 Registrati< ns Professional Engineer:
Arizona Illinois Indiana Kansas Kentucky Michigan Nevada New York Oklahoma Wisconsin Admitted to Partnership - 1976 Aapointed Associate - 1971 Responsibilities Mr. Abraham directs all mechanical engineering and design at Sargent & Lundy. He reviews and participates in major rratters of engineering and design of projects. He ensures the coordination of mechanical engineering activities with those of other departments. He authorizes department standards for eagineering, design, and administration. Mr. Abraham also has responsibility for all project directors and all Mechanical Department division heads.
AU Experience:
Mr. Abraham has 24 years of experience in mechanical engineering. lie has had extensive experience in all phases of tne mechanical engineering design of major power plants encompassing over 20 units with more than 12,000 MW of renerating capacity. Prior to becoming manager of the Mechanical Department, Mr. Abraham was assistant manager. Previous to that, he was a Partner and project director who was responsible to the Sargent & Lundy Partnership for the execution of power plant projects including two ll75-MW ruclear units. He has directed numerous special studies including site evaluation, gas turbine, and coal
- onversions.
Prior to his admission to the Partnership, he was the project manager for four 618-MW fossil-fired generating units for an indiana utility, three 511-MW coal-fired stations for a Xentucky client, and a 697-MW fossil unit for a utility in New York. Before this, he was the project engineer on a number of large power plant installations. Mr. Abraham joined Sargent &
Lundy in 1960.
Membershirs American Power Conference American Society of Mechanical Engineers National Society of Professional Engineers O
970,001 101084
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Resume 2 of 3 SARGENT& LUNDY Eugene V. Abraham O
Publications Mr. Abraham has also directed the preparations and prepared a number of reports, studies, and technical papers.
i 970,001 101084
)
Mected Experience Record 3 og 3 SARGENT & LUNDY Eugene V. Abraham Power Plant Deseen Projects Rated Gross Operating Station - Unit Fuel MW Date(s)
Client Aamesnment Marble Hill 1,2 Nuclear 1175 Suspended Public Service Indiana Project Director (each)
Hancock 1,2 Coal 650 1993/1999 Kentucky Utilities Project Director (each)
(held)
Company Gibson 3 Coal 618 1982 Public Service Indiau Project Director Edgewater 3 Coal 380 1985 Wisconsin Power and Project Director Light Company MTA Fossi1 Plant
- Gas, 697 1996 New York Power Project Marager Oil & Refuse (held)
Authority Gibson 1-4 Coal 618 1975-1979 Public Service Indiana Project Marager (each)
Ghent 2-4 Coal 511 1977/1981/198ts Kentucky Utilities Project Manager (each)
Company Teche 3 Gas & Oil 361 1971 Central Louisiana Project Manager Electric Company Wilkes 2,3 Gas 352 1970/1972 Southwestern Electric Mechanical Project Engineer (each)
Power Company Coughlin 7 Gas & Oil 230 1966 Central Louisiana Elec-Mechanical Project Engineer tric Company Colleen 1 Coal 358 1965 CentralIllinois Public Mechanical Project Engineer Service Company O
970,001 101084
SARGENT E LUNDY Resume 1 of 4 Carmen M. Chiappetta O
Title Partner and Assistant Manager Electrical Department Education Illinois Institute of Technology - B.S.E.E. - 1960 Registrations Professional Engineer:
Illinois In & na Michigan Ohio South Carolina Wisconsin Admitted to Partnership - 1982 Appointed Associate - 1974 Responsibilities As assistant manager of the Electrical Department, Mr.
Chiappetta assists in the direction of the work of electrical engineers engaged in the design and engineering of the electrical systems for fossil and nuclear power plants, in engineering substations and transmission lines and in making power system engineering studies.
Experience In his previous assignment as senior electrical project engineer, Mr. Chiappetta has been en a electrical phases of large nuclear-fuefefed in the desig,n of the k
steam-electric generating stations. His work included the basic station layout, the engineering and design of the various plant electrical systems, the development of control schemes and schematic diagrams, the overall responsibility for development of the single-line diagram, guiding the preparation of the specifications for the equipment, reviewing proposals, making recommendations to the client for purchases, and the preparation of the electrical portions of Nuclear Regulatory Commission (NRC) licensing safety analysis reports. He worked with the client and with suppliers' representatives to resolve design problems, and coordinated the electrical design with the work of other Sargent & Lundy departments.
Mr. Chiappetta's assignments have included the Southeast Fast Oxide Reactor Test Facility (SEFOR) and six ll30-MW units of three major nuclear generating stations in the Midwest. He has also made special studies in nuclear areas, such as reactor containment electrical penetration assemblies, cable system nuclear applications, plant security systems, l
environmental qualification of electrical equipment, and quality assurance requirements related to the design of nuclear plants. Mr. Chiappetta joined Sargent & Lundy in 1964.
970,092 101184
Resume 2 of 4 SARGENT& LUNDY Carmen M. Chiappetta O
Memberships Institute of Electrical and Electronics Engineers (IEEE)
- Power Engineering Society Nuclear Power Engineering Committee (1969 to present)
- Secretary and Chairman of the General Plant Criteria Subcommittee Publications
" Nuclear Power Generating Stations: An Overview of ElectricalInsulation Applications," presented at the Advanced Materials Symposium of the American Ceramic Society, May 10,1974
" Nuclear Power Standards - A Status Report of Work in Progress within Subcommittee 1 (General Plant Design Criteria) of the IEEE Nuclear Power Engineering Committee,"
presented at the Institute of Electrical and Electronics Engineers (IEEE) Nuclear Power Systems Symposiums, November 1973,1974,1975, and 1976
" Power Supplies"(coauthor D. C. McClintock), a guide to choosing power source systems published as a chapter in the Atomic Energy Commission's Nuclear Power Reactor Instrumentation Systems Handbooks TD-25932-P1,1973
" Nuclear Plant Security: Plant Physical Design Features" (coauthor C. B. Brown, Jr.), a technical paper presented at the 128th meeting of the Edison Electric Institute in Los Angeles, California, February 1976, published in the IEEE Transactions on Power Apparatus and Systems, January / February 1977 "Two Years Af ter TMI," a summary of a technical panel presentation on Post-Three Mile Island Events, given at the Sargent & Lundy General Engineering Conference, March 1981, published in the September 1981 issue of the Midwest Engineer, Directory Issue
" Qualifying Safety-Related Nuclear Power Plant Electric Equipment: A Dilemma," a technical paper presented at the 1978 Annual Meeting of the American Nuclear Society, published in the Transactions of the meeting
" Nuclear Plants Require Tight Security"(coauthor C. B. Brown, Jr.), a technical paper published in Electrical World, August 1975 0
970,092 101184 t
SARGENTS LUNDY Resume 3 of 4 Carmen M. Chiappetta m
Publications, Continued
" Electrical Design Considerations at the SEFOR Project" (coauthor D. C. McClintock), a technical paper presented at the Atomic Power Engineering Group Conference in Fayetteville, Arkansas, October 1967 "Special Electrical Design Features" (coauthor B. G. Treece), a technical paper presented at the Atomic Power Engineering Group Conference at the Zion Nuclear Power Plant, October 1971
" Nuclear Power Generation: An Overview of the Electrical Engineered Safety Features," a technical paper summarizing application of the current regulatory requirements to the design of electrical systems and features, presented at the Chicago Chapter of the IEEE, March 1971 O
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970,092 101184
SANGENT& LUNDY Selected Experience Record 4 of 4 Carmen M. Chiappetta Power Plant Damian Projects Rated Gross Operating Assignment Station - Unit Fuel MtT_
Date(s)
Client Assisnment Date(s)
Marble Hill 1,2 Nuclear 1175 Suspended Public Service Senior Electrical 1974 to 1982 (each)
Indiana Project Engineer Byron 1,2 Nuclear 1175 1985/1986 Commonwealth Electrical 1972 to 1974 Braidwood 1,2 (each) 1986/1987 Edison Company Project Engineer Zion 1,2 Nuclear 1085 1973/1974 Commonwealth Electrical 1968 to 1972 (each)
Edison Company Project Engineer SEFOR Nuclear 7
1967 Southwest Atomic Electrical 1964 to 196&
Energy Associates Engineer 9
O 970,092 101184
Resume SARGENT& LUNDY 1 of 2 Richard X. French
[O Title Partner and Manager Electrical Department Education Illinois Institute of Technology - Graduate Courses in Electrical and Nuclear Engineering Illinois Institute of Technclogy - B.S.E.E. - 1948 Registrations Professional Engineer:
Alabama Arizona Florida Illinois Indiana Kansas Kentucky Louisiana Michigan Minnesota Mississippi Nebraska Nevada New York Ohio Oklahoma Wisconsin Illinois Teaching Certificate as Instructor - Industrial Electronics Admitted to Partnership - 1977 Appointed Associate-1970 Responsibilities As manager of the Electrical Department, Mr. French directs the work of electrical engineers who are engaged in d
designing and engineering electrical systems for fossil and nuclear power plants, substations, and transmission lines and in making power system engineering studies.
Experience Mr. French has extensive experience in electrical engineer-ing, at increasing levels of responsibility. Before his appointment as manager of the Electrical Department, he was the assistant manager of the Electrical Department. Previous to that, as head of the Electrical Analytical Division, Mr.
French was responsible for planning studies for power system capacity additions and interconnections, and for planning and design studies involving transmission substations and lines, distribution systems, and other special power system problems. This work included economic analyses, load flows, short circuits, stability, insulation coordination, grounding,.
load control, relay applications and settings, metering, and communications. He also supervised the design of cathodic protection systems and noise abatement systems for power stations, and the development of company-wide computer applications related to the design of the electric facilities for power stations. In addition, he has served as a consultant on power system studies for projects outside the United States, including a transmission interconnection project in the Dominican Republic.
O 970,188 101084
SARGENT & LUNDY Resume 2 of 2 Richard X. French Experience, Continued He has extensive experience in the basic design and engineering of the electrical systems for power plants and substations. This work involved developing the basic electrical diagrams, determining requirements for specifications, analyzing proposals, and making recommendations for purchase and liaison with the client and suppliers. Projects on which he has worked include major power stations; large inter-connections, substations, and transmission lines up to 345 kV; and an 1100-kV ac test substation. Mr. French joined Sargent & Lundy in 1948.
Memberships Senior Member of Institute of Electrical and Electronics Engineers (IEEE)
- Power Engineering Society
- Past-Chairman, Power Systems Engineering Committee
- Working Group 84 - Rotating Equipment Noise
- Industry and Applications Society
- Computer Society
- Engineering Management Society Publications Mr. French has written numerous papers and is the author of the Bulk Power Supply Economics section of the McGraw-Hill 8
Standard Handbook for Electrical Engineers.
O 970,188 101084
SARGENT & LUNDY Resume 1 of 4 Wilbert G. Hegener Title Partner and Director of Engineering Education Northwestern University - Graduate Courses in Business Administration Northwestern University - M.S.M.E. - 1948 University of Detroit - B.S.M.E. - 1947 Registrations Professional Engineer:
Arkansas lilinois Kansas Kentucky Louisiana Michigan New York Ohio Texas Wisconsin Appointed Director of Engineering - 1984 Admitted to Partnership - 1974 Appointed Associate - 1970 Responsibilities As Director of Engineering, Mr. Hegener is responsible for ensuring the application of competent power plant design engineering. He supervises the managers of Sargent & Lundy's Structural, Mechanical, and Electrical Departments. He n
reviews and participates in major matters of engineering and Q
design. Mr. Hegener assists the Senior Partner in formation of company policies.
Experience Mr. Hegener has extensive experience in the mechanical engineering and design of major steam-electric generating stations. Prior to his appointment as Director of Engineerinh, Mr. Hegener was Assistant Director of Engineering. He assisted the Director of Engineering to ensure the application l
of competent power plant engineering. Before becoming l
Assistant Director of Engineermg, Mr. Hegener was manager of the Mechanical Department. Previous to that, he was assistant manager. He also was a Partner a.nd project director who was responsible to the Sargent & Lundy Partnership for l
the execution of power plant design projects f or several client i
firms. These projects included a variety of fossil fuel and nuclear plant designs for utilities in the U.S.A. and overseas.
~
The projects involved 16 g,enerating units in various stages of completion and other project consulting services.
I Prior to his admission to the Partnership, Mr. Hegener was a project manager with responsibility for manag;ement of design of fossil-fueled and nuclear generating statior s. His design l
experience involved a wide variety of design conditions, site conditions, and operating conditions. His responsibility included the preparation of preliminary design studies, the l
selection of the basic plant parameters, the development of the station general arrangements, the coordination of 970,246 100984
SARGENT 8 LUNDY Resume 2 of 4 Wilbert G. Hegener O
Experience, Continued engineering schedules, construction schedules, and station cost estimates. He coordinated the project design activities of the Mechanical, Electrical, and Structural Engineering disciplines as well as the related staff activities in the support of a project design.
Mr. Hegener joined Sargent & Lundy in 1948. Between 1957 and 1965, he was engaged in high-pressure valve manufacturing as a research coordinator and chief engineer. He rejoined Sargent & Lundy in 1966. He was appointed assistant manager of the Mechanical Department in 1977, manager of the Mechanical Department in 1978, and Assistant Director of Engineering in 1982.
Memberships American Society of Mechanical Engineers
- ASME Sec.111 Pump and Valve Code (1965-1968)
Western Society of Engineers American Nuclear Society
- ANSI B31.1 Power Piping Code (1960-1974)
- ANSI B16 Subcommittee 4 Steel Flanges and Flanged Fittings (1960-1974)
- ANSI B16 Subcommittee 3 Details and Stresses (1960-1974)
Manufacturers Standardization Society of Valve & Fitting Industry (1958-1965) l l
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SARGENT& LUNDY Selected Experience Record 3 of 4 Wilbert G. Hegener m
Fossil Power Plant Deslan Projects Rated Gross Operating
. ' - _xc.t Station - Unit Fuel MW Date(s)
Client Assunment Date(s)
Six Standard Coal /
750 1993-1999 Middle South Project Director 1977 to 1978 Units Lignite (each)
(held)
Services, Inc.
Pleasant Prairie Coal 570 1980/1985 Wisconsin Electric Project Director 1974 to 1978 1,2 (each)
Power Company Edgewater 5 Coal 380 1985 Wisconsin Power and Project Director 1974 to 1978 Light Company Flint Creek 1 Coal 512 1978 Southwestern Elec-Project Director 1974 to 1978 tric Power Company Welsh 2,3 Coal 512 1980/1982 Southwestern Elec-Project Director 1974 to 1978 (each) tric Power Company Columbia 1,2 Coal 512 1975/1978 Wisconsin Power and Project Director 1974 to 1978 (each)
Light Company East Bend 2 Coal 648 1981 The Cincinnati Gas & Project Director 1974 to 1978 p)
Electric Company (V
Miami Fort 8 Coal 512 1978 The Cincinnati Gas & Project Director 1974 to 1978 Electric Company MD l-4 Coal &
394 1982-1984 The Israel Electric Project Director 1974 to 1978 Oil (each)
Corporation, Ltd.
Welsh I Coal 512 1977 Southwestern Elec-Project Director 1974 to 1977 tric Power Company Miami Fort 7 Coal 512 1975 The Cincinnati Gas & Project Director 1974 to 1975 Electric Company Battle Creek Gas & 200,000 lb/hr 1942 Kellogg Company Project Manager 1%8 to 1970 Oil Edgewater 4 Coal 339 1969 Wisconsin Power and Mechanical Project 1965 to 1966 Light Company Engineer Beckjord 2-4 Coal 397 1953/1954/
The Cincinnati Gas & Mechanical Project 1948 to 1957
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(total) 1958 Electric Company Engineer Beckjord 1 Coal 100 1952 The Cincinnati Gas & Mechanical Engineer 1948 to 1957 Electric Company bV 970,246 100984 1
SARGENT & LUNDY Selected Experience Record 4 of 4 Wilbert G. Hegener
@ lear Power Plant Dew!r* P.oiects Rated Gross Operating Assapment Station - Unit Fuel MT bate (s)
Client Assignment Date(s) l Golf Creek 1 Nuclear 1100 1985 Kansas Gas and Project Director 1974 to 1978 Electric Company t
Zimmer i Nuclear 839 Suspended The Cincinnati Gas & Project Director 1974 to 1978 Electric Company Project Manager 1970 to 1974 NP.1 Nuclear 900 Cancelled The Israel Electric Project Director 1976 to 1977 Corporation,1.td.
Fort St. Vrain 1 Nuclear 333 1979 Public Service Project Manager 1966 to 1972 Colorado Donald C. Cook Nuclear 2126 1975/1978 Indiana-Michigan Project Manager 1967 to 1970 1,2 (intake (total)
Electric Company structure)
Point Beach 1,2 Nuclear 495 1970/1972 Wisconsin Electric Project Manager 1966 to 19/0 I
(intake (each)
Power Company structure)
Experimental Nuclear 5
1956 U.S. Atomic Energy Mechanical Project 1955 to 1957 Bothng Water Commission Engineer i
Reactor 1 l
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SARGENTS LUNDY Resume 1 of 3 Kenneth T. Kostal
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Title Partner and Assistant Manager Structural Departm en':
Education University of Illinois - M.S. Architectural Engineering - 1967 University of 111acis - B.S. Architecture - 1965 Registrations Professional Engineer Arizona Arkansas California Canaca (Alberta)
Colorado Florida Indiana lowa Kansas Ker.tucky Louisiana Michi.3an Minnesota Mississippi Nebraska New York North Carolina Ohio Oklahoma Pennsylvania Tennessee Texas Utah Virginia Washington West Virginia Wisconsin Structural Engineer - Illinais Admitted to Partnership - 1979 Appointed Associate - 1978 O
Responsibilities Mr. Kostal assists the manager of the Structural Department V
in coordinating all architectural, structural, and civil engineering and design for Sar. gent & Lundy. He as.sists the Department Manager in matters of supervision, administ ation, personnel, and technical policies. He provides direct administrative supervision of the Specification, Geotechaical, and Water Resources Site Development Divisions.
Experience Mr. Kostal has been involved in the structural, architectural, and civil engineering aspects of numerous power plants. He began his Sargent & l. undy career as a designer on a high-temperature gas-cooled reactor (HTGR) nuclear plant specifically involved in concrete foundation and steel superstructure design. He has progressed through a serles of supervisory positions on various nucles.r and fossil power plants coordinating structural, architectural, civil engineering, and draf ting activities.
In the area of nuclear power plants he has been respansible in the role of senior structural project engineer for the design of both pressurized water reactor (PWR) and boiling water reactor (BWR) plants. This responsibility included the supervision of the design of the containment structures and associated other safety-related structures. While assigned to these projects he was intimately involved in the licensing activities associated with these projects and on numerous occasions presented technical discussions with the Nuclear 970,329 101084
SARGENT E LUNDY Resume 2 of 3 Kenneth T. Kostal O
Experience, Continued Regulatory Commission (NRC) relating to all structural aspects. He has also presented expert testimony to the Atomic Safety and License Board (ASLB) on various occasions.
Prior to joining Sargent & Lundy in 1967, Mr. Kostal was a university instructor in structural design and an engineer responsible for the structural design and construction drawings for light office buildings.
Memberships American Concrete Institute American Nuclear Society American Society of Civil Engineers Structural Engineers Association of Illinois Western Engineering Society
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970,329 101084
SARGENT& LUNDY Selected Experience Record 3 of 3 Kenneth T. Kostal OL)
Power Pht Dessan Proiects Rated Gross Operating A 'yz.t Station - Unit Fuel MW Date(s)
Client A - _..,t Date(s)
Braidwood 1,2 Nuclear
!!73 1986/1987 Commonwealth Preject Director 1984 to present (each)
Edison Company MTA Fossil Plant
- Coal, 697 1996 New York Power Senior Structural Project 1977 to 1979 Oil &
(held)
Authority Engineer Refuse Marble Hill 1,2 Nuclear 1173 Suspended Public Service Senior Structural Project 1977 to 1979 (each)
Indiana Engineer Byron 1,2 Nuclear 1173 1983/1986 Commonwealth Senior Structural Project 1973 to 1979 Braidwood 1,2 (each) 1986/1987 Edison Company Engineer / Structural Project Engineer Fort St. Vrain 1 Nuclear 330 1979 Public Service Senior Structural Project 1967 to 1978 Colorado Engineer / Structural Project Engineer / Structural Engineer p)
Gibson 1 Coal 618 1976 Public Service Assistant Chief Structural 1971 to 1973 g
Indiana Design Engineer l
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Powerton 3,6 Coal 828 1972/1973 Commonwealth Assistant Chief Structural 1971 to 1973 l
(each)
Edison Company Design Engineer Knox Lee 3 Gas &
324 1974 Southwestern Elec-Assistant Chief Structural 1971 to 1973 Oil tric Power Company Design Engineer La Salle 1,2 Nuclear 1122 1982/1984 Commonwealth Assistant Chief Structural 1970 to 1973 (each)
Edison Company Design Engineer / Supervising Design Engineer Donald C. Cook Nuclear 2126 1973/1978 Indiana-Michigan Assistant Chief Structura!
1970 to 1973 1,2 (total)
Electric Company Design Engineer / Supervising Design Engineer i
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SARGENT& LUNDY Resume 1 of 3 John M. McLaughlin
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Title Partner and Manager Structural Department Education Illinois Institute of Technology - M.S.C.E. - 1970 Illinois Institute of Technology - B.S.C.E. - 1958 Registrations Professional Engineer:
Alabama Alberta Arizona Arkansas California Colorado Florida Illinois Indiana Iowa Kansas Kentucky Louisiana Maryland Michigan Minnesota Mississippi Nebraska New York North Carolina North Dakota Ohio Oklahoma Pennsylvania South Carolina Tennessee Texas Virginia Washington West Virginia Wisconsin Civil Engineer - Israel Structural Engineer - Illinois Admitted to Partnership - 1977 Q
Appointed Associate - 1973 G'
Responsibilities As manager of the Structural Department, Mr. McLaughlin is responsible for and coordinates all the architectural, structural and civil engineering and design for Sargent &
Lundy. Mr. McLaughlin initiates, reviews, and authorizes all Structural Depat tment standards, procedures, and reports, including those pertaining to technical administration and quality assurance.
Experience Mr. McLaughlin has 22 years of experience in the field of civil engineering, which includes civil-structural-architectural engineering and design work for fossil and nuclear power i
plants. His assignments have included 16 units with total capacity in excess of 10,000 MW. He has also been involved with numerous studies.
Prior to joining Sargent & Lundy in 1964, he practiced civil engineering for a private firm and with the U.S. Air Force.
Mernberships American Concrete Institute American Institute of Steel Construction American Society of Civil Engineers Building Officials & Code Administrators International, Inc.
Earthquake Engineering Research Institute Post-Tensioning Institute n
Seismological Society of America U
970,397 101984
SARGENT & LUNDY Resume 2 of 3 John M. McLaughlin 9
Memberships, Continued Structural Engineers Association of Illinois Structural Stability Research Council Publications
" Foundation Design"(coauthored), Sargent & Lundy General Engineering Conference, Chicago, Illinois, March 1976
" Tornado-Generated Missiles"(coauthor W. Huang), American Society of Civil Engineers Specialty Conference on Structural Design of Nuclear Plant Facilities, New Orleans, Louisiana, December 1975
" Comparison of Steel Trusses and Girders for Long Span Roof Framing," American Society of Civil Engineers Annual Structural Conference, Cincinnati, Ohio, April 1974 "Unusuai Loadings for Nuclear Power Plants," General Engineering Conference, Chicago, Illinois, March 1973
" Design of Nuclear Power Plant for Tornados," Tornado Phenomenology and Related Protective Design Measures Conference, University of Wisconsin, April 1970 "The First Prestressed Concrete Reactor Vesselin the U.S.,"
Atomic Power Engineering Group, Denver, Colorado, October 1969 "Effect of Earthquake Criteria upon Nuclear Plant Design" (coauthored), American Power Conference, Chicago, Illinois, April 1969 O
970,397 101984
SARGENTE LUNDY Selected Experience Record 3 of 3 John M. MCLaughlin n
Power Plint Desian Projects Rated Gross Operating Assignment Station - Unit Fuel MW Date(s)
Client F _...t Dase(s)
Coleto Creek 1 Coal 570 1980 Central Power and Senior Structural 9-74 to 1977 Light Company Project Engineer B.M. Davis 2 Gas &
324 1976 Central Power and Senior Structural 3-73 to 1977 Oil Light Company Project Engineer Ghent 2 Coal 511 1977 Kentucky Utilities Senior Structural 1-73 to 1977 Blend Company Project Engineer Byron 1,2 Nuclear
!!75 1985/1986 Commonwealth Edison Senior Structural 9-71 to 1977 Braidwood 1,2 (each) 1986/1987 Company Project Engineer Fort St. Vrain 1 Nuclear 330 1979 Public Service Structural Project 447 to 1977 Colorado Engineer Chenti Coal 511 1974 Kentucky Utilities Structural Project 6-69 to 1-75 Company Engineer A
Indiana Harbor
- Coal, 720,000 1967 Youngstown Sheet &
Structural Supervising 1-66 to 6-67 I
J Works Oilat
- /hr Boiler Tube Company Design Engineer V
Gas 680,000 CFM Turbo Blower Riverside 5 Coal 125 1961 lowa-lilinois Gas and Structural Supervising 9-66 to 5-67 Electric Company Design Engineer Beckjord 6 Coal 434 1969 The Cincinnati Gas &
Structural Engineer 545 to 1245 Electric Company Kincaid 1,2 Coal 580 1967/1968 Commonwealth Edison Structural Engineer 8-64 to 5-65 (each)
Company Warren HPB 1,2 Coal 300,000 1965/1972 Republic Steel Structural Engineer 144 to 8-64 l
- /hr Corporation l
Boiler l
i l
L 970,397 101984 i
i
Resume I of 3 SARGENT & LUNDY Henry M. Sroka O
Title Partner, Project Director and Assistant Mechanical Department Manager Faration University of Illinois - B.S.M.E. - 1957 Registrations Professional Engineer:
Arkansas Florida Illinois Kansas Louisiana Mississippi Wisconsin Admitted to Partnership - 1977 Appointed Associate - 1971 Responsibilities As a project director, Mr. Sroka is responsible for the implementation of the work and the technical integrity of the project during its execution, He directs a project team staffed by a project manager, project engineers, and other technical personnel. Mr. Sroka consults with the client and the project team in planning and scheduling the project, and developing the appropriate cost control systems. He leads and monitors the development of project management documents such as engineering and construction schedules, man-hour estimates, D
project cost estimates, and the scope of work. Mr. Sroka V
regularly reports to the client regarding performance on the project and the status of engineering and construction, directs the appropriate application of the Sargent & Lundy engineering policies and philosophies, and maintains surveillance of the design to ensure their implementation throughout the project.
Experience Mr. Sroka has experience in all phases of the mechanical engineering design of major steam-electric generating stations. At present he is responsible for development of six 750-MW standard coal / lignite-fired units and a 380-MW coal-fired unit. He is also responsible for the design of a 985-MW nuclear powered unit. Previously, he directed work on three coal-fired 585-MW units, and one 439-MW unit in the Midwest. He also led the design and construction management of the Southwest Experimental Fast Oxide Reactor Facility (SEFOR) in Fayetteville, Arkansas, and a 356-MW coal facility in Illinois.
Mr. Sroka has experience with preliminary engineering necessary to support environmental studies and licensing. He has directed projects of this kind in four states. Mr. Sroka joined Sargent & Lundy in 1957.
1O 970,607 102484 i
i
SARGENT& LUNDY Resume 2 of 3 Henry M. Sroka O
Memberships American Society of Mechanical Engineers
~
Former member of Executive Committee, Code for Pressure Piping ANSI B31 and ASME National Nominating Committee 1st Alternate Panelist " Standard Fossil Plants - What are They?" 1979 Joint Power Generation Conference, Charlotte, North Carolina, October 1979 Publications
" Reference Design for a Coal-Fired Unit," Paper No. GEC-P187, General Engineering Conference, Chicago, Illinois, March 1980
" Standard Plants - What Are They?" Southeastern Electric Exchange, Washington D.C., April 1978
" Equipment and Material Lead Times and Plant Schedules,"
Paper No. GEC-P136, General Engineering Conference, Chicago, Illinois, March 1975 "Look Before You Peak," Paper No. GEC-P65, General Engineering Conference, Chicago, Illinois, March 1969 "Baldwin Power Station Takes Advantage of Mine Mouth Coal" (coauthors T. W. Schroeder and E.E. Connon), Proceedings of the American Power Conference, pp. 377-391, 1969 "AEC Information Meeting on the High Temperature Gas-Cooled Reactor," Paper No. APEG-P105, Atomic Power Engineering Group Meeting, Chicago, Illinois, February 1961 "AEC Information Meeting on Advanced Materials for Gas-Cooled Reactors," Paper No. APEG-P82, Atomic Power Engineering Group Meeting, Chicago, Illinois, February 1960 O
970,607 102484
SARGENT& LUNDY Selected Experience Record 3 of 3 Henry M. Sroka Power Plant Deman Proiects Rated Gross Operating
? ' (s)^
Station - Unit Fuel MW Date(s)
Client Assisprwit Date Edgewater 5 Coal 380 1985 Wisconsin Power and Project Director 1981 to present Light Company Six Standard Coal /
750 1993-1999 Middle South Project Director 1977 to present Units Lignite (each)
(held)
Services, Inc.
Clinton 1 Nuclear 985 1986 111inois Power Project Director 1977 to present Company Project Manager 1972 to 1977 Havana 6 Coal 439 1973 Illinois Power Project Director 1973 Company Project Manager 1973 to 1977 Budwin 3 Coal 585 1975 1111nois Power Mechanical Project 1973 to 1975 Company Engineer Baldwin 2 Coal 585 1973 1111nois Power Mechanical Project 1971 to 1973 n
Company Engineer
(
V) Baldwin !
Coal 585 1970 Illinois Power Mechanical Project 1966 to 1970 Company Engineer SEFOR Nuclear 20 1967 General Electric Mecharucal Project 1964 to 1%6 Company Engineer Wood River 5 Coal 356 1964 Illinois Power Mechanical Project 1961 to 1964 Company Engineer Elk River Nuclear 58 1961 United Power Assistar.t Nuclear 1961 Association Project Engineer Preliminary Ergineerita Projects to Support Erivironmental Studies and Licensing 3
Assignment 5
Proiect Client Asalanment Date(s)
Uilton Site Geotechnical site Louisiana Power &
Project Director 1981 evaluation Light Company New Orleans Area Geotechnical site New Orleans Public Project Director 1981 evaluation Service Inc.
Fairview Site Preliminary engi.
Illinois Power Project Director 1979 neering for EIS Company j
DeSoto Site BACT, PSD hput for Mississippi Power &
Project Director 1979 site Light Company Wilton Site Preliminary engineering Louisiana Power &
Project Director 1978 ior EIS Light Company 970,607 102484
SANSENTN LUNDY A mendix A REVISION 0 O
3/22/85 l
APPENDIX A QUALITY ASSURANCE PROGRAM O
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SARSENTS LUNDY A >pendix A R EVISION 0 3/22/85 SARGENT & LUNDY QUALITY ASSURANCE PROGRAM FOR INDEPENDENT DESIGN VERIFICATION PROGRAM OF HC'PE CREEK GENERATING STATION O
Approved By P. L. Wattelet Project Director H. S. Taylor Head, Quality Assurance Division Revision Date i
SANSENTS LUNBY A gndix A s
R :.YlSION O 3/22/85 QUALITY ASSURANCE PROGRAM FOR INDEPENDENT DESIGN VERIFICATION PROGRAM OF HOPE CREEK GENERATING STATION O
TABLE OF CONTENTS t
Section TITLE l
1.0 Introduction 2.0 Organization and Responsibilities 3.0 Design Review Contro!
4.0 Document Control and Records 5.0 Quality Monitoring I
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SARSENTS LUNDY QUALITY ASSURANCE PROGRAM A >pendix A
,m R EVISION O
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3/22/85
1.0 INTRODUCTION
This program establishes the quality assurance requirements for work performed by Sargent & Lundy (S&L) on the independent de: sign review of the Hope Creek Generating Station. This program provides controls for the design review activities specified in the work scope document.
This quality assurance program complies with the requirements of 10 CFR Part 50, Appendix B, as described in the NRC approved S&L Quality Assurance Program Topical Report, SL-TR-1 A, Revision 6, to the extent applicable to a design review process and as described herein. Criteria addressed by this program are organization, design control, document control, and QA monitoring. Compliance with the requirements of this quality assurance program and the implementing project program plan and instructions is mandatory for personnel performing the design review.
Personnel participating in the design review are provided with indoctrination and training covering the quality assurance program and specific project instructions applicable to their work.
/7
] 2.0 ORGANIZATION AND RESPONSIBILITIES 2.1 Organization Chart The organization chart for the review team is shown in the review program plan. The organization chart indicates lines of authority and lines of communication for the project team.
2.2 Responsibilities 2.2.1 Project Director The Project Director is a Partner of the firm and represents S&L Management on the review team. He is responsible to the Client for the overall conduct and results of the design review. The Project Director shall be responsible for approval of this quality assurance program.
2.2.2 The Head, Quality Assurance Division l
The Head, Quality Assurance Division is responsible for preparation, approval t
and control of this project quality assurance program.
He is also responsible for reviewing and concurring with the project review plan.
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SARSENTS LONBY A wndix A R iVISION O (q
g 3/22/85 2.2.3 Project Manager The Project Manager reports to the Project Director. He shall be responsible for:
- The execution of the review activities in accordance with this quality assurance program.
- The preparation, approval, and control of a project review plan and instructions.
- Acting as the main contact at S&L for PSE&G and its contractors.
- Coordinating all meetings and controlling and distributing correspon-dence, meeting notes, telecopies and bi-weekly status reports.
- Ensuring that the project personnel are properly trained in the use of the project review plan and instructions.
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2.2.4 Quality Assurance Coordinator (PQAC)
The Quality Assurance Coordinator repcrts to the Senior Quality Assurance Coordinator. He shall be responsible for:
- Review and approval of the project review instructions.
- Monitoring of the review work to determine conformance to this quality assurance program.
- Participation in the review of the design process.
- Issuance of corrective action requests on the deficiencies identified during the monitoring process.
- Maintaining a QA activity log.
2.2.5 Project Review Team The responsibilities of the members of the Project Review Team are addressed in the review program plan and instructions.
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SARGENTS LUNDY A mendix A A
R EVISION O Q
3/22/85 3.0 DESIGN REVIEW CONTROL 3.1 General The design review shall comply with the requirements of this quality assurance program. The necessary controls to be used by the design review team are governed by the project review program plan and instructions, which shall be included in the Project Manual. The project review program plan and instructions shall clearly state the requirements and practices for the project team. Preparation and issuance of the Project Manual shall precede initiation of the actual design review work.
3.2 Project Review Plan The project review plan shall describe the review scope, the overall approach to the design review and the responsibilities for the review team. The plan shall define the project instructions required for the review.
C) 3.3 Review Project Instructions
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The project instructions shall address the following reviews, as applicable:
- Systems design compliance with the FSAR and licensing commitments.
- Technical adequacy of system design.
- Proper control of design process and interfaces.
- Adequacy of design change document control.
- Adequacy of the documentation of design (calculations, analyses, drawings, specifications).
- Potential safety concerns in the system design.
- Adequacy of conveyance of design information to the constructors.
4.0 DOCUMENT CONTROL AND RECORDS 4.1 General The quality assurance program is prepared under the direction of the Head, Quality Assurance Division and approved by the Project Director and Head, A
Quality Assurance Division.
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SARGENTliLONIlY A pndix A R :. VISION O (J
3/22/85 A Project Maqual shall be established by the Project Manager. It shall contain the project re vie v program plan and project instructions.
The project review plan is prepared and approved by the Project Manager, and concurred wi:h by the Head, Quality Assurance Division.
Projict instructions are prepared by the Project Manager or a designated Projtct Engineer, reviewed by the PQAC, and approved by the Project Mant ger.
4.2 Doctment Contr al The project review program plan u?.ed to implement the quality assurance program shall pr.avide for the preparation, apprcval, issuance, distribution and revision of the project review plan and instructi.ans.
The ?roject Mariager shall establish a plan for the turnover of program documents. The turnover plan shall be concurred with by PSE&G and may be completed progressively upon issuance of the document or at the termination of g/
the design review effort.
Sargent & Landy retention of these documents shall be determined by the Proyect Man ager and addressed in the project review plan.
Figure I lists tt e review program documents which control the design review activities, and identifies the personnel responsible for their preparation, review and approval, i
5.0 QUALITY MONITOIM]
The PQAC shall perform both scheduled and unscheduled monitoring and/or inv 2stigaticus for assessing the effective implementation of the quality assurance prcgram by the project. The PQAC has access to appropriate levels of management, anc is independent from the direct review activities.
The PQAC shall issue corrective action requests on deficiencies and/or questions identified during this manitoring process. These requests shall be responded to by the Project Team. Both requests and their responses shall bir filed by the PQAC.
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a umi A
"m er
SARSENTS LONDY A mendix A R EVISION 0 h
3/22/85 Figure 1 DESIGN REVIEW DOCUMENTS REVIEW FOR QA PROGRAM DOCUMENT PREPARER COMPLIANCE APPROVAL Quality Assurance Head, QA Division Head, QA Division Project Director Program and Head, QA Division Project Review Plan Project Manager Head, QA Division Project Manager Project instructions Project Manager Quality Assurance Project Manager Coordinator Oo
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SARSENTS LUNDY AGREEMENT CONCERNING Appendix B INDEPENDENT DESIGN VERIFICATION PROGRAM REVISION O
/]
OF HOPE CREEK POWER STATION 3/22/85
'o I
(print or type name) hereby agree that:
1)
I will notify the Project Manager if during the term of this project I, or any member of my immediate f amily (parents, spouse and children) acquire any financial interest in Public Service Electric & Gas (PSE&G), Bechtel Power Corporation or any other PSE&G contractor working on Hope Creek.
2)
If I identify what I believe to be a potential discrepancy having the potential for a significant safety impact, I will immediately notify the Project Manager for further evaluation.
3)
I will treat information revealed to me in the course of my work on this project as confidential and will not disclose it to others outside the S&L project team except as directed by the Project Manager.
O-(Signature)
(Date) i O
SARSENTS LUNDY HOPE CREEK IDVP Appendix B O
PERSONNEL QUESTIONNAIRE REVISION O V
3/22/85 After first being duly sworn breby deposes and says:
1.
I have no previous involvement with the Hope Creek Project, except as noted on the reverse side.
2.
I have not previously been hired by Public Service Electric & Gas (PSE&G), Bechtel Power Corporation (BPC), or any other PSE&G contractor working on Hope Creek to perform similar design review, except as noted on the reverse side.
3.
I have not been previously employed by PSE&G, BPC or any other PSE&G contractor working on Hope Creek except as noted on the reverse side.
4.
I do not own or control stock of PSE&G, BPC, or any other PSE&G contractor working on Hope Creek, except as noted on the reverse side.
5.
No member of my immediate family (parents, spouse and children) is employed by PSE&G, BPC, or any other PSE&G contractor working on Hope Creek, except as noted on the reverse side.
6.
I have not been offered future employment by PSE&G, BPC, or any other PSE&G contractor working on Hope Creek, except as noted on the reverse side.
I hereby affirm that the above is true and correct to the best of my knowledge.
(Signature)
(Date)
Subscribed and sworn to me before me on this day of
,1985 My commission expires:
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Notary Public OO
HOPE CREEK GENERATING STATION Appendix B - SAMPLE
/] SARGENT& LUNDY INDEPENDENT DESIGN VERIFICATION PROGRAM REVISION 0 V
ELECTRICAL CHECKLIST 2 3/22/85
Subject:
Redundancy and Class IE Channel Separation Between Circuits for Isolation Valves A.
Description of redundancy requirements for subject valves.
B.
Source documents identifying redundancy requirements for subject valves.
C.
Description of Class IE channel separation requirements for subject valves.
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D.
Source documents identifying Class IE channel separation requirements for subject valves.
l E.
Discussion of the general Class IE channel separation requirements for the station relative to whether meeting the general requirements will satisfy the specific redundancy and separation requirements for the subject valves. If meeting the general requirements is not suf ficient, indicate the additional requirements that must be imposed for the case of the subject valves.
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SARSENTS LUNDY HOPE CREEK GENERATING STATION Appendix B - SAMPLE (D
INDEPENDENT DESIGN VERIFICATION REVISION 0
\\b PROGRAM ELECTRICAL CHECKLIST 2 3/22/85 (Cont'd)
F.
Sourca documents identifying the general Class IE channel separation requirements for the station.
G.
Design documents reviewed which implement the electrical (circuit) redundancy and Class IE channel separation requirements for power circuits from subject valves to the source 480V Unit Substations.
O V
H.
Design documents reviewed which implement the electrical (circuit) redundancy and Class IE channel separation requirements for control circuits from subject valves to the source 480V MCC's, control power cabinets and first level interlock / sensors.
I.
Design documents reviewed which implement the physical Class IE channel separation requirements for power circuits from subject valves to the source 480V Unit Substations.
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SARSENTS LUNDY HOPE CREEK GENERATING STATION Appendix B - SAMPLE
/7 INDEPENDENT DESIGN VERIFICATION REVISION O V
PROGRAM ELECTRICAL CHECKLIST 2 3/22/85 (Cont'd) 3.
Design documents reviewed which implement the physical Class IE channel separation requirements for control circuits from subject valves to the source 480V MCC's, contro!
power cabinets and first level interlocks / sensors.
K.
Equipment and cables verified by field walkdown to meet design document redundancy and Class IE channel separation requirements.
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Comments:
M.
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Conclusions:==
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Apoenclx B SA*1pLE I
File No.: COD-Project Name:
Project No.:
Revision:
l Reviewed By:
Date:
I*'8"*'"I Specification Review
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Number:
Approved By:
Date l
(signature)
Quellfication Report No.,
Title, Rev. and Date:
j A. REFERENCES In addition to References D1 and D2 in Form MAS-COD-2.3, the following documents were used as a basi,s for developing this qualification checklist:
A1.
IEEE Standard 382-1980,"lEEE Standard fo: Qualification of Safety-Related Valve Actuators" A2. Otner specify:
B EQUIPMENT IDENTIFICATION B1. Does the qualification report identify the samples and the bases on which samples were selected to represent a generic actuator group?
O Yes O No O Not Applicable Comments B2. Is the equipment listed in the report identical to that is being supplied under the specification?
O Yes C No -justify if acceptable B3. Does the report include the document requirements specified in Ref. A1, Sec. 7.2 and 7.37 O Yes O No O Not Applicable i
l Comments l
l l
l C. QUALIFICATION SY ANALYSIS Does the analysis include the following details?
i C1. Identification of Valve Actuators' performance requirements.
O Yes O No O Not Applicable Comments THIS FORM MAY BE USED ONLY AS A CHECKLIST FOR ENVIRONMENTAL SUPPLEMENT TO FORM MAS-COD 2.3 OUALIFICATION OF CLASS 1E VALVE ACTUATORS COD 213 SARGHT&LUNDY Page 1 of 4 i
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a7nanM v n e n.."' E
- No.:
File No.: COD.
Revision C2. A listing of qualified service conditions.
O Yes O No O Not Applicable Comments C3. Do the service conditions erivelop the plant operating conditions?
O Yes O No O Not Applicable Comments C4. Do the mounting method and external connections of the Valve Actuator in the report sirquiate plant conditions?
O Yis O No O Not Applicable Comments CS. Mathematical Model.
CS.1 Description of mathematical model (A regression analysis is considered a mathematical model).
O Yes O No O Not Applicable Comments l
I C5.2 Pr'inciples by which model was developed (e g., standards, test data, operating expenence).
O Yes O No O Not Applicable Comments CS.3 A listing of the environmental variables monitored which affect equipment performance.
O Yes O No O Not Applicable Comments
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C5.4 Justification for any environmental variable not listed in C5.3.
O Yes O No O Not Applicable Comments
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CS.S Modelidentified such that equipment performance is a function of time and vanables as listed in CS 3.
O Yes O No O Not Applicable Comments l
COD 2.13 SARGENTELUNDY i
= eneewes ene Page 2 of 4 1
Angnai v n.
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p Proket No.:
, File No.: COD-
-e.ision-1V C6. Extrapolation of the Model.
C6.1 Identification of postulated equipment failure modes.
O Yes O No O Not Applicable Comments C6.2 The postulated failure modes for the equipment should be shown to be the : ame as those produced by the model.
O Yes C No O Not Applicable C6.3 The extrapolason of the model to the desired life must be justified by using
' a. Confidence bounds.
O Yes O No O Not Applicable
- b. Thermal testing of 5 component based on the aging rate of the regression line and to same failure criteria.
O Yes O No O Not Applicable
- c. Through surveillance requirements.
O Yes O No O Not Applicable
- d. Other:
O Comments:
C6.4 Description of Analytical Methods. A written explanation of how the riodel was selected to represent a generic actuator group and the parameters on which the ' select:on was based.
O Yes O No O Not Applicable Comments C7. A companson of the Valve Actuator to be qualified to the qualified generic Valve Actuator:
Operating principle:
Materials manufacturing processes, finishes and tolerances:
Size and weight:
Operating characteristics, including time and load:
i Auxiliary components:
Structuralintegrity:
Qualification parameters:
Design margins:
COD-213 SARGENTELUNDY
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Page 3 of 4
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e-. y.
Project No.:
File No.: CCD-Revision:
I Mounting requirements:
Power supply-Other:
C8. Determination of quellfled life. The model must demonstrate that the equipment performance exceeds requirements for an environment a: severe as that anticipated in service.
O Yes O No O Not Applicable Comments C9. Maintenance. A description of periodic maintenance and replacement requirements O Yes O No O Not Applicable Comments I
D. COMMENTS l
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i E. TYPE TESTING AND OPERATING EXPERIENCE If the method of qualification (Section B, Form MAS COD-2.3) involves type testing or operating expenence complete sections F, G and I of Form MAS-COD 2.3.
CO D-213 SAUENTLLUNDY i
Page 4 of 4
SAE8ENT SI. UNDY GLOSSARY
_A_ppendix C REVISION O 3/22/85 w
Observation - A condition wherein the IDVP Internal Review Committee believes there may be a failure to meet licensing commitments or other safety-related design requirements.
Potential Observation Report (POR)- A preliminary internal report for the documentation of an Observation.
Observation Report (OR) - Internal Review Committee documentation of its evaluation of an Observation.
Resolution Report - Documentation of the resolution of an Observation.
Completion Report - Documentation of action taken (disposition) to complete the review ef fort associated with an Observation.
Safety-Significant Condition - A condition confirmed to exist which results in a loss of safety function to the extent that there is a malor reduction in the degree of protection provided to public health and safety.
Og internal Review Committee - A committee made up of the Engineering Design Directors and key IDVP team members.
Senior Review Committee - A committee made up of senior members of Sargent & Lundy who are not part of the IDVP team.
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SARGENTS LUNDY HOPE CREEK GENERATING STATION Appendix D p
INDEPENDENT DESIGN VERIFICATION PROGRAM REVISION O y
CRITERIA FOR SYSTEM SELECTION 3/22/85 The Systems selected to be reviewed in the Hope Creek Independent Design Verification Program were chosen considering the following criteria:
l.
The system must be safety-related.
2.
The system should involve a cross-section of engineering and design disciplines within the Bechtei Power Corporation.
3.
The concept and implementation of the system design should be by Bechtel Power Corporation.
4.
The system should be reasonably complex, requiring several modes of operation involving redundancy and single failure considerations.
5.
The system should involve interfaces with General Electric and/or others.
6.
The system should have required design changes over the plant design period.
(d 7.
The system should include new or unique design fe.atures.
It is recognized that each of the systems selected may not encompass all of the above criteria. However, by choosing a number of different systems for review, it is intended that the above criteria be covered.
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ATTACHMENT II Summary of the liope Creek Engineering and Design Prcgram
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SUMMARY
OF THE HOPE CREEK ENGINEERING AND DESIGN PROGRAM Public Service Electric and Gas Company has been an active participant in the review, approval, and implementation of design control and surveillance programs since the inception of the Hope Creek project.
PSE&G is known throughout the industry for their experience in the design and construction of nuclear projects and has made numerous contributions to the industry through active technical participation in IERE, ASME, EPRI, BWROG and other industry sponsor societies and programs.
It is this experience and these resources that have been assembled and utilized on the Hope Creek project to insure and confirm that the design is consistent with the requirements and details as set forth in the Final Safety Analysis Report (FSAR), the Safety Evaluation Report (SER),
and supporting documents.
Presently, PSE&G maintains 245 managers, engineers, and support people on the Hope Creek Project working closely with Bechtel Power Corporation.
The responsibility for the overall Engineering and design of Hope Creek rests with the PSE&G Engineering Department.
Within the Engineering Department exists separate engineer-ing groups in the functional divisions.
These groups receive technical and administrative direction from their Chief Engineers.
The activities of the Engineering Depart-ment on Hope Creek consist of, but are not limited to, the review and approval of:
o All equipment suppliers o
Equipment specifications o
Systems descriptions o
P& ids o
All engineering information submitted to regulatory agencies o
Major piping diagrams, one-lines, general arrangements, and control and instrumentation schematics o
Engineering procedures and policies l
I 1
MP 85 46/09 1-az
An early decision was made by PSE&G management to assume total responsibility of the startup and operational pro-grams, including the confirmatory preoperational testing and surveillance testing.
PSE&G's management and control of these activities will provide additional confidence in the HCGS design and the engineering and quality review progams.
GENERAL ELECTRIC AND BECHTEL The utilization of experienced Bechtel/GE teams on the Hope Creek Project has resulted in unique and beneficial design enhancements to the project.
A. GENERAL ELECTRIC The General Electric BWR 4/5 nuclear steam supply system is a proven design.
The Mark I ccatainment design incorporates the latest regulatory design and safety requirements for this containment.
PSE&G has maintained overall administrative control of the General Electric Contract.
Technical direction and communication between General Electric and Bechtel requires the concurrence of PSE&G.
In addition to its membership in the BWR Owners Group, PSE&G maintains full active technical participation in all working level BWROG subcommittee activities.
PSE&G's technical involvement includes, but is not limited to the following areas:
(1) Control Room Improvements Committee (2) CRD Water Hammer (3) ATWS (4) IGSCC (5) PASS (6) Set-Point Methodology (7) SRV Testing (8) SPDS/ Procedures Integration Committee (9) IDCOR (10) Suppression Pool Temperature Limit Committee (11) Decay Heat Removal (12) ICC/ Water Level Subcommittee MP 85 46/09 2-az i
For example, PSE&G has actively participated in the BWR IGSCC Owners Group in permanently resolving the concern of IGSCC in BWRs.
The outgrowth of this ef fort has been the development of remedies which remove the necessary conditions for IGSCC.
PSE&G, GE, and Bechtel have completed a program of implementing these remedial actions to all safety related welds and materials in the HCGS nuclear piping systems that may be susceptible to IGSCC.
Based on the construction stage of HCGS at that time, the optional mitigation techniques were chosen.
These actions will effectively eliminate the concern for IGSCC over the life of the plant.
We will continue to participate and monitor BWR IGSCC Owners Group activities for possible application to HCGS.
B.
BECHTEL Bechtel's engineering organization and experience is well established in the industry.
BWR design and construction of the Peach Bottom, Susquehanna, and Limerick Generating stations provides assurance that design evolution and modifications / enhancements which have been utilized within these plants have been incor-porated in the Hope Creek design.
In addition, as a result of the above projects having being designed by the SPHO Engineering Group, the experience and knowledge obtained from the other projects were utilized in the design evolution of Hope Creek.
OA PROGRAMS PSE&G OA involvement in the design, procurement, construc-tion, and startup activities has always been a key element in the identification and confirmation of design processes.
As early as 1974, independent audits have been performed by PSE&G of the SFHO design responsibilities.
To date, twenty-seven (27) Bechtel Home Office audits have been performed by PSE&G OAD.
These audits verified that the design processes conform to Reg. Guide 1.28, the Project Manual, and the OA program.
For example, audit H-84-1 conducted in 1984 evaluated the following issues:
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1.
Procedures for:
Engineering, QA, M&QS, Con'cract Admin., Administrative Service Department and Procurement Supplier Quality Department.
2.
As-built program 3.
Design Change Control 4.
Environmental Qualification Program 5.
Service Info Letters (SILs) 6.
Fuse Sizing Methods 7.
Procurement Document Control 8.
Consultant Services
- 9. Control of SDDRs
- 10. Problem Info Reports In the initial development of the Projects Engineering Procedures, both the Bechtel Engineering Department Procedures (EDP) and Engineering Department Project Instructions (EDPI) required both Engineering and QA approvals by PSE&G.
During the initial development of these procedures an independent consultant (Southwest Research Institute) was contracted by PSE&G for con-firmatory review and analysis of these procedures.
f Concurrently, a '" Key Document" designation was estab-lished requiring PSE&G Engineering identification and approval of key specifications and engineering and design documents prior to their use.
In addition, any significant revisions to the " Key Documents" require prior approval by PSE&G.
Elements of the PSE&G QA involvement include but are not limited to:
1.
An in-place QA program updated to current additions of ANSI 45.2.12, ANSI 45.2.23, and Reg. Guide 1.144.
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2.
A continuing. review of the Bechtel two-tier Internal Audit Program consisting of:
a.
Project QA Group Audit - lim.ted scope audit of design process, b.
Management Group Audit - a full scope audit that assures adherence and compliance to the Project Engineering Procedures Manual (PEPM).
The involvement of the PSE&G QA organization is not limited to reviewing the design process for conformance to applicable procedures, but includes the review and approval of all SFHO suppliers of nuclear safety related material.
The Hope Creek Project OA program has gone beyond the requirements of Reg. Guide 1.28 by imposing PSE&G unique requirements on the Bechtel QA programs.
These areas include not only the Key Document Program, supplier review, and independent audits of SFHO, but are expanded to include Fire Protection and selected BOP systems.
ENGINEERING DESIGN REVIEWS AND SURVEILLANCE In addition to developing and auditing the engineering and design control processes to insure that the Hope Creek Generating Station is consistent with the design description of the Final Safety Analysis Report (FSAR),
engineering / design reviews and surveillance reviews have been performed since project inception.
PSE&G has always maintained an in-house engineering staff capable of doing the engineering and design of all facilities, including nuclear power plants.
Because of certain manpower limitations, it was decided to contract with Bechtel to provide those services for Hope Creek.
However, PSE&G management dedicated experienced, quali-fied, technical staff to the Hope Creek project to over-see Bechtel and GE engineering and design actvities.
Since 1974, PSE&G's emphasis has always been to insure reviews and confirmatory analysis were performed by experienced and qualified technical personnel.
The utilization of an experienced engineering cadre with MP 85 46/09 5-az
both engineering and construction experience in the nuclear industry was the cornerstone of PSE&G's control program.
In addition, after the demise of the Atlantic Project, two key, experienced, PSE&G engineers were transferred to Bechtel offices in San Francisco on a permanent basis.
This provided PSE&G direct and contin-technical liaison with Bechtel engineering.
This uous San Francisco staff was complimented by additional PSE&G engineers on a temporary basis, as required.
This in conjunction with detailed operability and maintain ability reviews by experienced PSE&G Operations Depart-ment personnel were essential to insure that the com-pleted plant would indeed be safe, operable, and maintainable.
Some of the notable programs and processes incorporated throughout the project's design and implementation period are highlighted below.
1.
EQUIPMENT QUALIFICATION The Hope Creek Environmental Qualification Program is based on the requirements set forth in 10CPR50.49, NUREG 0588, Category I and IEEE 323-74.
The intent of the program is to comply fully with these requirements.
Although requirements appli-cable to HCGS are those set forth under Category II of NUREG 0588, it is PSE&G's objective to meet Category I requirements whenever possible.
Unlike many of the tasks required for completion of the Hope Creek Project, the Environment Qualifica-tion Program is the direct responsiblility of the PSE&G Engineering and Construction Department.
PSE&G assumed this responsibility from Bechtel in October 1982.
PSE&G chose to take advantage of in-house available personnel who were experienced in Nuclear EQ programs.
A The responsibility for the development and ongoing technical review of the HCGS EQ program, including the creation and updating of the EQ central file, has been undertaken by the Controls and Electrical Division of the PSE&G Engineering and Construction Department.
As such, it is responsible for the MP 85 46/09 6-az
coordination and monitoring of the efforts of the various participants involved in the EO progam including the A/E (Bechtel), NSSS supplier (GE), and other PSE&G division personnel as well as associated independent consultants, component suppliers, and testing labs.
2.
CONTROL ROOM The design of the Hope Creek control room was initiated by Public Service Engineering and Construction Department, with Bechtel, in 1975.
Public Service dictated the overall philosophy while Bechtel implemented that philosophy in the specific design.
That design was then verified by Public Service in the form of a review of loop and logic drawings and equipment purchase specifications.
The Public Service philosophy is one of an advanced but proved design.
That design has evolved over a twenty year period through the design and construction of Public Service's four most recent generating units which used low voltage plug-in control modules.
A full size control room mock-up was built in order to evaluate the design and arrangement of the Hope Creek control room.
An Operability Analysis was performed on the mock-up in 1977.
The analysis team was made up of Public Service Engineering and Nuclear Operations, Philadelphia Electric Opera-tions, General Electric, Bechtel and the equipment supplier, Bailey Controls Company.
Peach Bottom operating procedures were walked through and veri-fied in order to finalize the design and assure it supports effective operations.
Ths analysis also consisted of a Human Factors Engineering Review.
An additional confirmation of the control room design was accomplished through Public Service's start-up program.
The control room complex was completed and turned over to Public Service's start-up group early in the construction of the plant.
The start-up group then conducted an integrated test of the complex itself to verify MP 85 46/09 7-az
system interfaces functioned properly.
The standard systems start-up provides a final validation of design correctness.
Another human f actors engineering review of the control room is currently underway.
The review team consists of PSE&G engineering and operations personnel, Bechtel, and outside experienced consultants.
3.
COM PLETE PLANT MODEL To facilitate the design (and subsequent construc-tion) effort, an extensive use of a " Design Model" was employed.
Beyond utilizing the model for con-structability, spacial / interference reviews, or training, the Hope Creek model was unique in that the model was the "first-line" confirmatory process in system / equipment location design.
From its inception, a multi-disciplined PSE&G design review team was assigned to insure, via monthly audits, the design adequacy and conformance of the model to design drawings.
4.
CIE From the developed drawings evolving out of the model use, a computerized three dimensional model was developed by Computerized Interference Elimination, Inc.
This computerized model selected the three most congested areas of the plant ( Drywe ll, Torus area, and Turbine Generator area and independently veri-fied physical interferences for improved construc-tibility and maintainability.
It was a valuable tool for plant separation and ALARA reviews.
Through this independent review, confirmatory eval-uation of the plant design was accomplished prior to construction mobilization.
As findings were identified through the CIE program, the issues were corrected and the Bechtel procedures were amended to insure that the design process methodology was corrected for subsequent issues.
PSEGG Engineering and Design personnel were involved in all aspects of this progam.
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i 5.
ALARA AND PIPING REVIEWS Additionally, PSE&G analysis and independent reviews of the Bechtel design processes include:
Direct involvement of PSE&G technical engineering and operations personnel in the design review and implementation of the Alara program.
Analysis of shielding design and extensive technical reviews of drawings and the " Plant Model" provided invaluable confirmation for shielding requirements, insert /
withdrawal space allocation, attenuation calcula-tions, etc.
Piping stress and design work performed by Bechtel has been independently verified by PSE&G in selected areas (RHR and Main Steam Systems).
In addition, selected piping and hanger supports were reviewed by PSE&G and the NRC.
PROGRAMATIC DESIGN VERIFICATION PROCESSES Concurrent with the design review and audit processes described earlier, PSE&G has conducted and incorporated additional programs and processes to insure a smooth and orderly transition of engineering and design documenta-tion between Bechtel, vendors and PSE&G.
In the course of these transitional reviews, technical reviews and process surveillances are accomplished.
Following are summaries of these programs
- 1.
VENDOR DOCUMENTATION PROGRAM In 1983, PSE&G inititated an extensive pilot program on "O" and "non-Q" plant equipment.
This program consisted of actual hardware walkdowns and software document verification by a team of PSE&G and Bechtel technical engineers.
The preliminary findings of this program confirmed a high level of confidence in the as-built consistency of "O" and "non-Q" vendor documentation.
The program was expanded in early 1984 to all vendor supplied "non-Q" panel and skid mounted equipment.
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Although a very high level of confidence existed for all "O" vendor equipment, PSE&G expanded the program to the Diesel Generator equipment.
The results of any open issues identified through this program which concluded in late 1984 are tracked to closure through established project procedures and programs.
2.
COMPOSITE DRAWING EFFORT The Hope Creek Control Room Complex is a unique combination and interfacing of General Electric, Bechtel and Bailey Control equipment and logic.
The Control Room Complex represents both the state of the art in solid state design and the interfacing of various logic networks.
In early 1983, PSE&G embarked on an independent composite drawing program that provided:
A.
Translation from Bechtel " bulk" logic information into an PSE&G integrated system document.
B.
Drawing volume reduction to support logic in integration and verification.
C.
An independent review by PSE&G personnel of all Bechtel, GE and Bailey interface documentation.
This effort by PSE&G supported the advanced turnover of the control room complex and subsequent early completion of Control Room Complex checkout and functional testing.
3.
MEL (Master Equipment List)
Prior to issuance of Generic Letter 83.28, PSE&G initiated a Master Equipment List development program to confirm and upgrade existing data and information on all plant components and devices.
By using existing Quantity Tracking Systems (OTS) and Material Labor Control Systems (MLCS) a team of MP 85 46/09 10-az
PSE&G and Bechtel discipline engineers performed engineering verficiation in accordance with the requirements of ANSI N45.2.ll.
This effort confirmed a high level of confidence of the safety classification of O, P, and R equipment (as well as select BOP equipment).
Through Generic Letter 83.28, formal identification and implementation of PSE&G's initial program - MEL, was established.
In addition, an aggressive vendor manual documentation control program above and beyond INPO Good Practice MA-304 was implemented which is now supported through the Hope Creek Response Coordination Team output.
4.
RES PONSE COORDINATION TEAM ( RCT)
In order to evaluate and verify the applicability and impact of nuclear industry lessons learned on Hope Creek, PSE&G established a Response Coordina-tion Team (RCT) consisting of representatives from Nuclear Assurance and Regulation, Engineering, OA-E&C, and Hope Creek Operations.
As appropriate, Bechtel utilizes the project and staff engineering groups to review all NRC Bulle-tins, Information Notices, Circulars and Generic Letters and GE Service Information Letters (SILs) after 1983, and provides their Hope Creek specific evaluations, including GE inputs where necessary, to PSE&G Engineering.
The evaluations are reviewed for PSE&G concurrence and required commitments are incorporated into the Hope Creek design, construc-tion, licensing, and operating activities.
In addition, further confirmation is obtained by PSE&G by requiring RCT review of all GE Technical Information Letters (TILs), Service Advice Letters (SALs), and Application Information Documents (AIDS) and INPO Significant Operating Experience Reports (SOERs), Significant Event Reports (SERs), and Operating and Maintenance Reports (O&MRs).
A computerized tracking system maintains current status on all issues.
Commitments are tracked by MP 85 46/09 Il-az w
-r
the RCT until verified and confirmed complete by PSE&G.
QA-E&C monitors, by means of surveillance and audit programs individual organizations responsible for verifying completed actions.
5.
CONFIGURATION CONTROL Configuration Control at Hope Creek Generating Station (HCGS) is maintained by integration of Bechtel, GE, supplier / vendor, and PSE&G design control processes.
PSELG personnel have been actively involved in the design change process of HCGS from its incaption.
The configuration control process basically consists of design criteria / basis (PSAR, FSAR, design cri-teria, etc.)., design documents, implementing docu-ments, data bases, change authorizing documents, and verification walkdowns.
[t is the responsibility of PSE&G, Bechtel and GE QA/QC organizations to assure that all of these systems are being implemented properly.
At any given time, Hope Creek documents reflect the as - constructed condition when the base document is coupled with the various change authorizing docu-ments which describe the particular change.
Conformance to design document restraints for "O" components is verified through the various OA/QC organizations of both PSE&G and Becthel.
To supple-ment this verification process, both PSE&G and Bech-tel jointly perform various engineering / design related walkdowns as follows:
WALKDOWN TYPE WALKDOWN SCOPE ALARA
- verify implementation of AAI's
- field check of potential ALARA violations DRAIN LINES
- evaluate drain line leaks on safety-related equipment MP 85 46/09 12-az
WALKDOWN TYPE WALKDOWN SCOPE HAZARDS REVIEW
- evaluate consequences of PBOC and missiles outside containment PENETRATION SEALING
- radiation sealing for pipe HVAC, gaps and electrical /
instrumentation penetrations SEISMIC II/I
- evaluation of f' eld installed equipment, i.e. conduit, instrument lines and equipment not on model EOUIPMENT BOP SEISMIC
- verify installation per equipment documents PROXIMITY
- Verify proximity clearance for Class IE Electrical cabinets STRUCTURAL
- verify that loads do not exceed design allowables for ficor beams, and floor dead load STRESS
- Verify type and location of support
- perform functionality review of snubbers, springs, rigids, etc.
- verify cold clearances THERMAL DEFLECTION
- Verify clearances per antici-pated pipe movements MISSILES
- pressurized components inside the primary containment FIRE PROTECTION
- identification of hidden smoke detectors requiring remote indicating lights on wall MP 85 46/09 13-az
1 WALKDOWN TYPE WALKDOWN SCOPE
- inadvertent actuation of fire protection system on safety related equipment.
ELECTRIC RACEWAY
- verify electrical separation of electric raceway VENDOR /
- verify equipment configuration DOCUMENTATION is reflected in vendor documentation.
HVAC INSTRUMENTS
- verify installation of HVAC instruments and controls These walkdowns are conducted to accomplish the following:
identify design estimates made previously regarding design provisions.
provide verification that the installation was accomplished as intended.
provide verification that vendor supplied equipment reflects an as-constructed condition.
For "Q" components design compliance is verified by the OC inspection function.
The transition from Bechtel construction to PSE&G startup/
operations methodology is embodied by a dif ferent set of change authorizing documents (CAD).
These documents are in place during the startup phase and are incorporated into design and implementing documents.
As PSE&G assumes design / configuration control responsibilities from Bechtel, PSE&G will implement the Design Change Request (DCR) program.
This design change process also requires that design changes are reflected to the design documents and implementing documents.
The Interim Design Change Notice (IDCN) when coupled with the documents will provide, at any given time, the as-construc-ted configuration of the plant.
This DCR process will remain in place throughout the life of the plant.
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i Inheront in the process described above are the ongoing training programs for engineering, construction, and QA/QC personnel to assure famillarity and cognizance of the processes.
As Hope Creek approaches the operating phase, this training is expanded to include operating personnel and operating procedures which reflect the design documonta.
Therefore, the PSE&G DCR process requires that design changes also be reflected to operating procedures, which are an additional category of implementing documents.
AUDITS In addition 1:o extensive audits of Hope Creek by outside agencies and organizations as well as imposed audits b PSE&G management, specific evaluations have been per y
formed relative to the engineering design processes and their results as follows:
1.
INPO - PILOT /SELP EVALUATION A Pilot Program was initiated by INPO in July 1982 through an audit of three nuclear power plants, Hope Creek being one of them.
Fif teen members represent-ing INPO, utility industry, AE's and consultants, conducted a two week audit in San Francisco, Newark, and at tha site for the purpose of developing cri-teria for future evaluations.
The results were several minor findings recommended by the audit team for implementation by mid-1983.
Since this was a pilot program, no final report was issued.
As a resu:.t of the Pilot Program, INPO issued criteria for self-evaluation by the utility for construction of nuclear stations.
An audit team of approximately twenty engineers were assembled to perform a two week audit of San Francisco, Newark and Hope Creek in October 1982.
Areas of design that were investigated were as follows:
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design input documents specifications and procedures PSAR commitments calculation development, control and verification performance criteria design change control program A clear consistent orderly approach to the develop-ment of design documents and calculations were found to be noteworthy.
2.
NRC - HOME OFFICE - UNANNOUNCED The NRC sent a two man evaluation team from Region IV to Bechtel's San Francisco Home Office for an unannounced four day audit (March 14-18, 1983).
A problem was identified at the Midland Project where Bechtel was the Architect Engineer.
The NRC audited Bechtel to evaluate if a similar generic issue existed on the Hope Creek Project.
The result of the audit was positive with no open items and no findings.
Bechtel was aware of the Midland problem and had taken corrective action on the Hope Creek Project via existing programs.
Areas investigated were:
design interfaces and verification adherence to 10 CFR Part 21 design procedures and manuals design drawings and DITS 3.
INPO - HOME OFFICE A three week intense evaluation of design took place by INPO representatives in San Francisco in June 1984.
Areas investigated were:
definition and control of design process achievement of a high quality of design design interfaces and incorporation of all requirements design verification process design change process verification of design adherence to FSAR and Regulatory commitments MP 85 46/09 16-az
k Pour good practices were identified exemplifying practices extraordinary to the industry.
Specifi-cally noteworthy was the ef fective program utilized for load verification structural beams.
4.
NRC - HOME OFFICE The NRC conducted an audit of Bechtel Home Office engineering operations in the area of pipe break and structural analysis on August 27-30, 1984, for the Hope Creek, Limerick and Susquehanna plants.
Areas investigated were as follows:
high energy pipe break analysis computer usage on analysis on H PCI turbine valve operability related to acceleration resulting from pipe breaks FSAR requirements and adherence No findings or comments established.
SUMMARY
The engineering and design surveillance program, as high-lighted by examples above, represents a cross-section of the review and verification activities that have been and con-tinue to remain key to PSE&G's personal involvement with the Hope Creek Project.
Innovative inspection and evaluation programs, an excellent enforcement history, independent verifications, and the establishment of an engineering division with experienced, technical personnel on site directly involved with engineering, design, and verification activities provides further confidence that the -design of Hope Creek is consistent with the FSAR, SER, and their supplements.
PSE&G's commitment of experienced personnel and resources in engineering, construction, startup, and operations during the transition period between construction and operation insures that the design parameters / procedures in place have been and will remain active throughout the life of the project.
MP 85.o/09 17-az E
e As further verification and confirmation of the engineering and design of Hope Creek Generating Station, we propose that an Independent Design Review (IDR) be conducted by Sargent and Lundy (S&L).
This review would censist of vertical and horizontal reviews of representative systems selected by S&L, and addressing all engineering disciplines.
It would also include plant walkdowns and review of the as-built program and preopera-tional test procedures.
In addition, several environmental qualification packages will be reviewed to assure the adequacy of that program.
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