ML20079F154
| ML20079F154 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 10/10/1983 |
| From: | TELEDYNE ENGINEERING SERVICES |
| To: | |
| Shared Package | |
| ML20079F130 | List: |
| References | |
| NUDOCS 8401180123 | |
| Download: ML20079F154 (125) | |
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"/PTELEDYNE ENGINEERING SERVICES TECHNICAL PROPOSAL PR-6194 TO CINCINNATI GAS AND ELECTRIC CO.
IN RESPONSE TO RFQ NO. 828 INDEPENDENT DESIGN REVIEW OF THE WILLIAM H. ZIMMER NUCLEAR POWER STATION OCTOBER 10, 1983 hD OC O O 03 8 A PDR
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CGSE-CA- 029 TO: File DATE: January 6 , N1188 BERV, DEPT. FROM: H. Barjian REPLY BY: (M
SUBJECT:
Wm. H. Zimmer Nuclear Power Station Independent Design Review (IDR) Teledyne Engineering Services At the request of P. Hoffmeier, Teledyne was cen-tacted at 12:10PM on 1/6/84, for the purpose of obtaining (1) a project schedule showing the timeframes for each activity and (2) a commitment to issue the Final Report no later than eight (8) months after award. l Mr. D. Landers, Teledyne, provided the following informatien and agreed to confirm by letter:
- 1. Task No. Commence Complete
(@ Start of Month) (@ End of Month) 1 Uoon Award 2 2 2 3 3 2 4 4 2 6 5 3 3 6 4 7 7 4 5 Final Reoort 8 8
- 2. Ficure 4. Procosed Manoower Loadine. of the crocosal will be revised to show "0" manning at the end of the eighth month after contract award.
The foregoing was conveyed to P. Hoffmeier by telephone at 12:45PM on 1/6/84.
/ ..
f' H . mar ~'an Contract Admin'stration HB/ral cc: E. J. Wagner File The Cincinnati Gas & Electric Company AndSubsdam Companes a ses a s
CINCINNATI GAS AND ELECTRIC COMPANY P. O. B0X 960 CINCINNATI, OHIO 45201 i t TECHNICAL PROPOSAL PR-6194 INDEPENDENT DESIGN REVIEW 0F THE WILLIAM H. ZIMMER NUCLEAR POWER STATION OCTOBER 10, 1983 WTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 617-89 4 3360
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4% % NE Technical Proposal ENGNEstNG SERVICES PR-6194 JABLE OF CONTENTS Page
1.0 INTRODUCTION
1 2.0 SCOPE OF THE INDEPENDENT DESIGN REVIEW l 2.1 QA Program for Design 2 2.2 Review of RHR System Design 2 3.0 METHOD OF APPROACH 3 3.1 Task 1 - QA Program for Design 5 3.2 Task 2 - Design Process and Procedures 6 3.3 Task 3 - Review Design Requirements 7 3.4 Task 4 - Review As-Built Design Documents 7 3.5 Task 5 - Determine As-Built Configuration 8 3.6 Task 6 - Compare As-Built Documentation to 8 Plant Configuration 3.7 Task 7 - Preoperational Test Program 8 4.0 EXPERIENCE 9 4.1 Independent Design Review Experience 9 4.2 Design Experience 11 4.3 Code and Licensing Experience 13 5.0 DEFINITIONS 13 5.1 Open Item (TES Internal) 14 5.2 Closed Item 14 5.3 Potential Finding (TES Internal) 14 5.4 Finding 14 5.5 Observation 14 5.6 Request for Information 15 6.0 REPORTING 15 6.1 Independent Design Review Plan 15 6.2 Observations and Findings 16 6.3 Periodic Reports 16 6.4 Final Report 16 6.5 TES Internal Reporting Process 17 6.6 TES External Reporting Process 17 6.7 Follow-Up of Findings 18 I 1 l
W P W NE Technical Proposal ENGNEBilNG SERVICES PR-6194 TABLE OF CONTENTS (Cont'd) Page 7.0 INDEPENDENT AUDIT QUALITY ASSURANCE PROGRAM 19 8.0 PROPOSED ORGANIZATION - INDEPENDENT CESIGN REVIEW TEAM 19 9.0 INDEPENDENCE 21 9.1 Previous Involvement with Zimmer 22 9.2 Similar Audit Work for Major Participating Firms 22 9.3 Previous Employment with Major Participating Firms 22 9.4 Financial and Family Involvement 22 10.0 CONTRACTUAL 24 10.1 Time-and-Material Quotation 24 10.2 Quality Assurance Requirements 26 10.3 Nuclear Incident 26 10.4 Hard Copy 27 10.5 General Contractual Requirements 27 FIGURE 1 - PROJECT ORGANIZATION 30 FIGURE 2 - INTERNAL REPORTING PROCESS 31 FIGURE 3 - EXTERNAL REPORTING PROCESS 32 FIGURE 4 - PROPOSED MANPOWER LOADING 33 FIGURE 5 - COMPLETED INDEPENDENT DESIGN REVIEWS 34 APPENDICES I - TES EXPERIENCE II - MAJOR NUCLEAR POWER ACTIVITIES III - RESUMES IV - PROCEDURES: EP-5-006 AND EP-1-021
l W TF1FD(NE ENGNEERING SERVICES Technical Proposal PR-6194 !
1.0 INTRODUCTION
This proposal is submitted in response to a request for proposal (RFP) from Cincinnati Gas and Electric Co. (CG&E) to perform an Inde-pendent Design Review (IDR) to verify the quality of design of the William H. Zimmer Nuclear Station (Zimmer). This proposal presents Teledyne Engineering Services (TES) program for performing the IDR using the elements identified in Attachment I of the RFP as a basis. 2.0 SCOPE OF THE INDEPENDENT DESIGN REVIEW The scope of the IDR will have two segments; a review of the QA program for design and a review of the overall design process of selected portions of the Residual Heat Removal (RHR) system. The review of both segments will include the development, imple-mentation and audit of: Design Input Documents Design Analysis Control Drawing Control Procurement Control Design QA Design Verification Document Control Design Change Control Corrective Action Audits and Surveillance Test Program Internal / External Interface Control
WM ENGNEERNG SERVICES Technical Proposal PR-6194 2.1 QA Program for Design U:ing the RHR system as a basis, a review to determine the adequacy of the design QA program will be performed. Where it is deter-mined that the RHR system does not include all elements of the design control program, TES will expand our review to assure total coverage. This review will include the design control program utilized by Sargent and Lundy (S&L) on the Zimmer project and the QA program of CG&E ?.s it relates to the S&L design control program. (1) The S&L design control program will be reviewed to determine if acceptable controls and l l procedures exist to provide assurance of design adequacy. (2) S&L QA audits, schedules, implementation and l follow-up on corrective actions will be re-viewed to determine if Quality Assurance l successfully monitored the implementation of the S&L design control program. (3) The CG&E QA audits, schedules, implementation and follow-up on corrective action of the S&L QA program related to design control will be reviewed. 2.2 Review of RHR System Design The scope of the design review will include the eiements delineated in the RFP for all designated plant operating conditions including:
W F W NE ENGNEERING SEFMCES Technical Proposal PR-6194 (1) Review pipe stress analysis for in-containment shutdown cooling system suction piping. (2) Review pipe support design for in-containment RHR cooling system suction piping and the in-reactor building section of the service water piping to the RHR heat exchanger. This review will accept support loads as defined by the S&L design documents for that piping not reviewed in (1) above. (3) Review structural design of the service water structure foundation. (4) Review electrical power supply and control circuit design of the Loop A service water I pumps. i (5) Review seismic equipment qualification for the Class 1 motor operated containment isolation valves and Class 1 service water pumps. (6) Review the adequacy to convey and control details of construction. (7) Perform plant walkdown of those portions of the RHR system subject to review to determine if as-built conditions reflect design assumptions. 3.0 ETHOD OF APPROACH The approach presented by CG&E for performance of the Zimmer IDR is that used by TES on LaSalle 1, Susquehanna 1 and Shoreham. TES strongly
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l WTF1 FrT(NE Technical Proposal ENGNEERNG SERVICES PR-6194 supports the use of a " thin slice" review approach to reaching a conclusion on the adequacy of the design process. Failure of the process has been found to occur in the failure of procedures to properly delineate the process requirements and failure of the users to properly implement acceptable procedures. These occurrences will be found using a " thin slice" review and generic (or plant wide) reviews are therefore limited to areas which have been found to be problematic. This assumes that a breakdown in the design process that has serious implications with respect to the total plant will occur across the board rather than be isolated to a specific design, analysis or qualification test and therefore should be found in a " thin slice" review. Certainly, it is possible for a design error to occur on a single pipe or piece of equip-ment for which failure to function could have serious implications. However, the role of an IDR is not to perform an independent check or verification of each item in the plant but rather to assure that a process is in place and functioning at the design agent to accomplish these tasks. In the performance of independent design reviews, TES does not rely en the use of comparative analysis to determine adequacy of the analysis submitted by the design agent. Rather, we review analyses to determine whether the established design process and implementing procedures (which have already been reviewed and accepted) are used properly. Any analysis performed by TES will only be done to assist the reviewer in making technical judgements on the adequacy of the design process and procedures or in dealing with generic issues resulting from Findings. These analyses would be performed under the requirements of the TES QA Manual. The following task descriptions provide TES approach to performing the IDR of the Zimmer station. The review tasks detailed below are limited to the scope outlined in Section 2.0 of this proposal.
w mVNE ENGINEERING SERVICES Technical Proposal PR-6194 j 3.1 Task 1 - QA Program for Design i TES will review the CG&E and S&L QA programs for design con-trol for the Zimmer project including any procedures referenced by these programs. Of particular concern will be . controls on interfaces between disciplines. TES will then evaluate the implementation and effectiveness of the CG&E and S&L program. This will include the review of CG&E and S&L's audit plans. Audit files will be reviewed to determine: e Conformance with planned schedules e Adequacy of audit questions to the scope of activity audited e Findings, observations or coments identified e Request for corrective action formally documented e Vendor review and acceptance of corrective action and/or follow-up surveillance audits e Conclusions and/or closeouts of corrective action taken The QA audits will also review all records pertaining to implementation of procedures, project instructions and adequate docu-mentation of interfaces. Project organization, personnel and training will be audited to insure adequate implementation. TES mill also audit the procedures and implementation of checking, verification, and/or design review undertaken in the design process. s
l "A V W NE ENGINEERING SERVICES Technical Proposal PR-6194 3.2 Task 2 - Design Process and Procedures The reviewer will meet with S&L to determine the process used in taking design requirements and developing construction drawings, specifications, test procedures and procurement documentation. Further, the process of developing revisions to the design will be reviewed. Interfaceg between internal organizations will be determined in following the process of: a) specification of design requirements b) development of preliminary design c) piping analysis d) support location and selection e) support analysis f) effect on building structure g) equipment loading requirements h) development of construction drawings
- 1) revisions to design Interfaces between external organizatiens, including GE and construction, will be determined in followi g Me process of:
a) transmittal of inform 6. Un . the . external organization b) review of procedures c) review of design d) transmittal of developed information to S&L organizations (i.e., loads on building struc-ture,etc.)
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WTn m(NE ENGINEERING SERVICES Technical Proposal PR-6194 e) dealing with Field Change Requests (FCR) f) dealing with Engineerirg Change Notices (ECN) g) dealing with nonconformance and associated corrective action h) procurement specifications Procedures, instructions and methods associated with develop- t ing the design of the RHR system will be made available to TES. The 1 reviewer must become familiar with these procedures to assure that ! implementation was adhered to by the design organizations. 3.3 Task 3 - Review Deshn Requirements The adequacy of the design requirements as delineated in the l General Electric (GE) and S&L RHR system specifications, standards and procedures will be reviewed for compliance with licensing commitments ( and NRC requirements. This review will include piping, supports, service water structure foundation, Class 1 service water pumps, Class 1 s motor operated contairment isolation valve, electrical power supply and l' control of Loop A service water pumps and containment penetration. 1 l 3.4 Task 4 - Review As-Built Design Documents t The as-built documentation supplied by S&L will be reviewed to determine compliance with Licensing and Design Specification conunit-ments. A detailed review of the Design Specification will be performed in Task 3 since that document forms the basis for the design approach. - The review of as-built design documents will cover the piping, supports, structures and electrical and mechanical equipment defined in the scope of the IDR. Mechanical and electrical components not included in the IDR scope for detailed review will be reviewed for satisfaction of interface requirements only.
W F W NE ENGNEERING SERVICES Technical Proposal PR-6194 ! l 3.5 Task 5 - Determine As-Built Configuration A field walkdown of the system will be performed. This walk-down will develop the geometry of the as-built piping, structure, mechanical and electrical equipment, and supports for all accessible locations. Clearances at any penetrations, pipe whip restraints or l other structures or components will be determined. Nameplate data, details of supports and structures, weld sizes and anchor bolt details are some of the items for which information will be gathered. 3.6 Task 6 - Compare As-Built Documentation to Plant Configuration The reviewer will obtain from CG&E or S&L the as-built documentation which is specified to be representative of the plant configuration. The as-built configuration obtained in Task 5 will be compared with the submitted documentation. The as-built documentation used in this task is the same package that will be used in the detailed review of Task 4. This package should represent revisions resulting from ECN's, FCR's and any applicable corrective action for nonconformance and therefore will allow TES to review the process of the on-going design at S&L in addition to the adequate compliance of the final design. 3.7 Task 7 - Preoperational Test Program A number of elements of design can be, and are, confirmed during preoperational testing. These fall into two categories: (1) specified by the design agent and (2) required by licensing comnitment. 4
W F W NE ENGINEERING SERVICES Technical Proposal PR-6194 Those elements required by licensing commitment will be determined in Task 2. The IDR team will also develop a list of elements that can be confirmed by preoperational testing and compare this with the list ' defined by Items (1) and (2) above. Elements appearing on the IDR list and not included in the Zimmer preoperational test program will be reported to CG&E and S&L using the established reporting process outlined in Section 6.0. The acceptance criteria established for the elements to be confirmed will be reviewed to determine adequacy. This area of criteria is critical to confirmation and requires understanding of the experi-mental results to be obtained as well as a knowledge of the basis for the criteria used in the design process. The IDR work performed in this task will recognize the vintage of the Zimmer licensing comitments. l 4.0 EXPERIENCE The experience of TES is outlined briefly in the general brochure in Appendix I. Our experience in the areas that are applicable to the successful performance of the Independent Design Review are presented l below. 4.1 Independent Design Review Experience TES is an industry leader in the area of independent reviews and audits of nuclear power plant design. The experience of TES in the review and verification of design and construction activities extends from the late 1960's to today. To date, TES has successfully completed the following four Independent Design Review or Verification Programs.
l W F W NE ENGNEERNG SERVCES Technical Proposal PR-6194 Unit Utility Architect Engineer LaSalle 1 Comonwealth Edison Co. Sargent & Lundy Susquehanna 1 Pennsylvania Power & Bechtel Power Corp. Light Co. Shoreham Long Island Lighting Co. Stone & Webster Engineering Co. Diablo Ct# ' Pacific Gas and Electric Utility i l The results of the IDR programs for LaSalle and Susquehanna were accepted by the NRC Staff and the Comission and those units are currently operating. The Final Report on the results of the IDR program for Shoreham and the verification program for Diablo Canyon has recently been issued and is under review by the NRC. l TES experience with LaSalle 1 is very relevant to the per-formance of this independent IDR. Zimmer is essentially a " sister" , plant of LaSalle 1 so our staff is familiar with the plant geometry, ' systems and criteria. Further, the LaSalle review program has provided TES detailed experience with the Sargent and Lundy design process and procedures. It is our intent to include in this IDR the TES individuals who were in lead positions in the LaSalle 1 review. In the early days of commericial nuclear power plant construc-tion TES was under contract to three utilities to perform design and construction audits of piping, mechanical equipment, and supports. The utilities involved wanted a company experienced in nuclear plant requirements to augment their own staff and provide assurance of com-pliance. This involved review of design and analysis to assure com-pliance with licensing and specification commitments as well as a survey of construction. The scope of this review varied from plant to plant but included as a minimum, all systems attached to the Reactor Pressure Vessel. The units and scope of these reviews were as follows:
"RTELEDYNE Technical Proposal PR-6194 Unit Scope Nine Mile Point (1) All safety systems Millstone Point 1 All safety systems plus main steam Vermont Yankee Piping attached to Reactor Pressure Vessel (1) The Nine Mile Point review was not initiated until after commercial operation was begun and a failure occurred in the Core Spray System.
In order to assist CG&E in evaluating this proposal and TES experience, we have included in Figure 5 a comparison of the three IDR's completed to date that best reflect the approach to be used at Zimmer. Significant differences in manhours are reported for each completed IDR. These result for two major reasons: (1) the scope of the initial IDR and (2) the number and extent of generic issues. It is our opinion that the Zimmer IDR scope more closely follows that of Shoreham because of the amount of the RHR system to be reviewed, the inclusion of all operating modes and the extent of the design QA review required. In addition, the " Protocol" reporting and meeting requirements will result in increased manhours and costs. 4.2 Design Experience Prior to the advent of commercial nuclear power, our staff was involved in the U.S. Navy Nuclear Program. This experience was trans-ferred to the commercial nuclear power program in the 1960's. Initially
WTri m(NE ENGINEERING SERVICES Technical Proposal PR-6194 l t our efforts were limited to state of the art design and analysis activi- ' ties associated with reactor vessels, mechanical equipment, containment and complex piping requirements. This was followed by expanding our expertise to design, fabrication and construction activities related to ) plant modification work. ; This expansion of services was a planned approach by TES and resulted in the development of expertise in each service area prior to implementation. The result is a staff that is recognized as leaders in the industry in the service areas we address. These range from support design to inelastic dynamic analysis, from field engineering to non-de(structive examination and from construction supervision to code con-sulting. Since 1975 TES has been involved in construction management activities associated with plant modifications. In these efforts TES has been responsible for design, procurement, fabrication and installa-tion involving structure, piping, equipment and electrical systems. These at tivities have resulted in a staff familiar with the material procurement, fabrication and installation requirements of Codes and applicable standards. For example, TES has developed a team of engineers qualified to perform weld fit-up acceptance inspections; members of our staff are certified Level III ultrasonic, magnetic particle and liquid penetrant examiners; specifications and procedures for construction activities ranging from piping to instrumentation installation have been prepared by the TES staff. Additionally, senior members of our quality assurance staff have a range of 9 to 28 years experience in QA/QC activities. The staff at TES comprises top ranked engineering profes-2 sionals who combine practical knowledge and training with state-of-the-art techniques. Many of our engineers are recognized leaders in
"RTiri m(NE Technical P'raposal
. ENGINEERING SERVICES PR-6194 their fields. Our senior staff of engineers encompass mechanical, structural, civil, electrical, and metallurgical engineering disciplines. Through the completion of hundreds of projects, TES has demonstrated its ability in applying current design and analysis tech- ;
niques, applicable design bases and material technology to nuclear plants under construction and modifications to existing plants. A detailed list of the major nuclear power activities of TES in recent years is given in Appendix II. 4.3 Code and Licensing Experience TES has been a leader since early 1960 in the development of Codes and Standards for use in the construction of nuclear plants and has on its staff personnel who are responsible for the development of major portions of these criteria. This familiarity with Codes and Standards from their inception is important with respect to the Zimer IDR. TES staff is as familiar with Code and licensing criteria of the early 1970's as it is with today's. This has been demanstrated in the successful reviews completed to date, most of which are the same vintage as Zimmer. TES staff members have appeared before the Comissioners, the NRC Staff, Atomic Safety and Licensing Boards, the Advisory Committee on Reactor Safeguards, Public Utility Comissions, and the United States Congress. These appearances were on behalf of individual utilities and the industry in general and involved licensing activities, resolution of generic industry matters and rate setting. 5.0 DEFINITIONS In order to evaluate the impact-of items issued by the IDR it is necessary to understand the details of the terminology used. TES proposes the following definitions for use in this IDR.
'A'TA FTh'NE ENGINEERING SERVICES Technical Proposal PR-6194 5.1 Open Item (TES Internal)
An item requiring further review or more information before a decision can be reached. An Open Item can become a Finding, an Observa- ' tion or a Closed Item but cannot remain an Open Item in the TES Final Report. 5.2 Closed Item An Open Item which after further review is found to be in com-pliance and can be Closed. 5.3 Potential Finding (TES Internal) An item which the Reviewer and Project Manager feel could have an impact on the adequacy of the design or QA process. All Potential Findings will be submitted to the Project Review Internal Committee for disposition. A Potential Finding can become a Finding, an Observation or can be Closed but cannot remain a Potential Finding in the TES Final Report. 5.4 Finding An item which impacts the adequacy of the design or QA process. 5.5 Observation An item that does not impact the adequacy of the design or QA process but has significance relative to conservatism, design practice or ' applicable procedures.
"RTA FfWNE ENGINEERING SERVICES Technical Proposal PR-6194 It should be noted that an Observation does not require corrective action. However, should a number of Observations be issued in a single area, the IDR team will then issue a Finding related to this element of the design or QA Process.
5.6 Request for Information In the process of reviewing a particular item sufficient information may not be currently available to TES. In order to document requests for data, specifications, analyses, etc., TES has used the Request for Information (RFI) form in past IDR's and proposes to use this same approach at Zimmer. 6.0 REPORTING The process used by TES in performing an IDR results in the submittal of scheduled reports as well as the submittal of Observations and Findings as they are developed. In compliance with the requirements of the " Protocol" document all reports identified here will be submitted concurrently to CG&E and the NRC Regional Administrator. In addition, the internal and external reporting process used by TES is defined in this s.ection. 6.1 Independent Design Review Plan An IDR plan will be prepared and submitted thirty days after receipt of a contract from CG&E. This schedule will require submittal of " Licensing Documents and CG&E and S&L Design Control QA Program. During the process of the IDR, and as a result thereof, modifications / revision to the review plan may be submitted. These revisions will be submitted prior to implementation by the IDR team.
W TAPTWNE ENGNEERING SERVICES Technical Proposal PR-6194 , 1 l 6.2 Observations and Findings Observations and Findings will be submitted three working days af ter their classification by TES. This includes both preliminary and final classification of items. 6.3 Periodic Reports TES will submit periodic reports on a monthly basis. These reports will include the following: (1) Status of open items (2) Status of Requests for Information (3) Status of reviews (4) List of any Observations or Findings submitted to date including identification as preliminary or final and status of CG&E response. 6.4 Final Report A Final Report will be submitted at the completion of the IDR. This will consist of an Executive Summary and a Final Report. The Executive Sunnary will provide a sunnary of the review and detail the conclusions of the adequacy of the design process. The Final Report will be submitted thirty days af ter submittal of the Executive Sunnary l and will provide details of the IDR. All items opened by reviewers will be listed and catalogued. Any item which proceeded to the Independent Review Connittee for resolution will be discussed and responses by the CG&E Manager will be included. A list of documents reviewed,. audits and reviews performed will also be reported. All procedures and project quality assurance programs developed and utilized by TES in the per-formance of the review will be included in the Final Report. l l
WTF1 FrWNE Technical Proposal ENGNEERNG SERVICES PR-6194 6.5 TES Internal Reporting Process I The development of items by TES will be controlled and follow an established procedure. Individual reviewers will be responsible for raising issues. These will be documented on a Reviewer Report Form (RRF). The Project Manager will review each RRF with the individual reviewer and a Project Manager Review Form (PMR) will be prepared. At this time an initial classification of the item will be made and agreed upon by the reviewer and the Project Manager. Items classified as Preliminary Observations or Preliminary Findings will be submitted to the Internal Review Comnittee for resolution. The Internal Review Committee will consist of three members of the TES senior staff and their responsibility will be to review all items for-warded by the audit team and to arrive at a final classification. Tieir conclusions will be set forth on an Internal Committee Report Form (ICR) and must include at least two signatures of the committee members and the Project Manager. A flow chart of this TES internal reporting process is shown in Figure 2. 6.6 TES External Reporting Process Items which are classified as Observations or Findings by the Internal Review Committee will be transmitted concurrently to CG&E and the NRC Regional Administrator. These items will be identified as prelininary since this program provides for the opportunity of CG&E and S&L to respond prior to final classification by the IDR team. This is important since it is necessary for S&L to have the opportunity to respond prior to an item becoming an issue which would impact the design adequacy. In most situations an independent reviewer will not have available all of the information, data and background that will allow an initial pronouncement to always be absolute. The issuance of Observations and Findings on a . preliminary basis allows for
"RTF1FnYNE ENGINEERING SERVICES Technical Proposal PR-6194 communication between the parties involved and presentation of information, data and background that may not be readily available or obvious to the auditor.
Responses to preliminary items by S&L will be reviewed by the individual reviewer responsible, the Project Manager and a member of the Internal Review Committee. These three individuals will decide on final classification of the item and a revision to the original ICR will be issued. Items appearing on this revised ICR will be final and can only be classified as Findings, Ot.servations or Closed. Should these three individuals (reviewer, Project Manager and conmittee member) be unable to reach a conclusion on an item the Internal Review Committee will be convened. In such cases the revised ICR must be signed by two members of the committee and the Project Manager. A flow chart of this TES external reporting process is shown in Figure 3. 6.7 Follow-Up of Findings , All Findings of the IDR should result in rework by S&L either on an individual item or on a generic basis. For example, a Finding on the design adequacy of the motor operated valve subject to IDR could result from a mathematical error, failure to follow procedures or inadequate procedures. The mathematical error should not require a gener ic review beyond the work done by the specific individual involved. Failure to follow procedures should fall into the same category. Inadequate procedures should result in a generic review. Depending on the magnitude of the rework resulting from the Finding, TES may perform a statistical review of corrective action or a complete independent review. The decision as to the magnitude of the follow-up work required for generic Findings will be made by the Project Manager. It is anticipated that statistical reviews would be used in all cases prior to implementation of a complete independent review. Should the statistical
1%V I W NE ENGINEERING SERVCES Technical Proposal PR-6194 review provide adequate assurance to the TES review team that appropriate action has been taken by S&L then no further review action would be required. 7.0 INDEPENDENT AUDIT QUALITY ASSURANCE PROGRAM All work performed by TES under this IDR will be in accordance with the TES QA Manual. A specific Project Quality Assurance Program (PQAP) will be prepared and submitted to CG&E and the NRC Regional Administrator. Procedures will be prepared covering the activities to be performed by the TES review team. These procedures will outline the scope of the activity and provide details of implementation and responsibilities. It is anticipated that the procedures TES has used for the four reviews completed will be modified accordingly and in this IDR. Two examples of these appear in Appendix IV. A Project Quality Assurance Engineer (PQAE) will be assigned to perform scheduled audits and to assure that the requirements of the PQAP are complied with. The PQAE will report to the TES Quality Assurance Manager who for this project will report directly to the President of TES. The PQAE assigned to audit the quality activities of TES in per-forming this independent audit will not be the same individual responsi-ble for evaluating the effectiveness and implementation of the design quality assurance program of S&L and CG&E, 8.0 PROPOSED ORGANIZATION - INDEPENDENT DESIGN REVIEW TEAM The work outlined in this proposal will be performed by TES using the organization techniques that have proven effective in the completed reviews outlined in Section 4.0. l l
"WTF1 FrW'NE fechnical Proposal
. ENGINEERING SERVICES PR-6194 TES will utilize as many personnel as possible who were involved in lead positions in the review of LaSalle 1 in order to take advantage of their familiarity with the Zimmer sister plant and the process and procedures used by S&L.
Mr. Donald F. Landers, Senior Vice President of TES, will serve as Project Manager of this IDR. Mr. Landers was Project Manager of both the Susquehanna and Shoreham verification programs. Mr. James A. Flaherty, Manager - Engineering Design and Testing, will serve as Assistant Project Manager. Mr. Flaherty was Project Manager of the LaSalle 1 verification program and was TES representative on the Diablo Canyon 1 construction QA review board. Members of the Internal Review Committee will be Dr. William E. Cooper, Consulting Engineer, Mr. Frank B. Stille, Manager - Projects, Mr. Ronald Wray, Manager - Engineering Analysis, Mr. Nicholas S. Celia, Manager - Engineering Projects (alternate member), and Mr. James J. Balaschak, Senior Engineer (alternate member). Two alternate members are proposed in order to assure that three members are always available to resolve items brought forth by the review team. Alternate members will participate in all activities of the committee but will not be required to formulate an opinion on an item unless they are acting in place of one of the permanent committee members (Messrs. Cooper, Stille and Wray). Dr. Cooper was Project Manager of the IDVP program of Diablo Canyon 1. Mr. John Q. Cragin will serve as Manager - Project Administration for this IDR. In this role he will be responsible for all contractual and administrative activities including the submittal of periodic reports. Mr. Cragin is currently serving in this position on the Diat lo Canyon independent verification program being conducted by TES.
SPTn PTVNE ENGNEERING SERVCES Technical Proposal PR-6194 The transmittal of information between involved parties is important to the review function. Further, TES staff members will be making visits to the S&L offices to perform this review activity. To accommodate the above, TES proposes to locate a member of our staff at the S&L offices until the IDR is completed. The TES representative at S&L will not participate in technical activities of the IDR nor participate in the preparation of review items or reports. It is anticipated that TES personnel will be assigned to the Zicmer site for periods of time in order to fulfill their as-built review activities. However, in order to assure independence of individuals involved and to allow them to participate in the determination of classification of items, their assignment on-site will not be permanent. With respect to total staffing for the IDR TES proposes to provide a peak staff of 20. Based on our past experience in performing IDR's, staffing is anticipated to vary as presented in Figure 4. Resumes of lead personnel are provided in Appendix III, along with sample resumes of TES staff members who could be involved in this IDR. 9.0 INDEPENDENCE The most important attribute of the firm performing .the review is competence which is based on knowledge and experience in the areas under review. However, the independence of the firm and individual performing the review is necessary to assure objective, dispassionate technical judgements based solely on the merits of the case. Undisputed inde-pendence and integrity is essential to the effective completion of .the review function. l With respect to determining financial independence, the RFP lists a number of questions related to company or individual involvement with
' ETA m(NE Technical Proposal PR-6194 ,
Zimmer and the major firms participating in design and construction activities. The following are TES responses to those questions. 9.1 Previous Involvement With Zinsner TES nas reviewed both our financial and QA records back to 1974 and has not had any contracts for work related to Zimmer. 9.2 Similar Audit Work For Major Participating Firms TES has not been previously hired by the Owners, S&L, Kaiser, GE or Bechtel to perform audit work similar to that outlined in the RFP. 9.3 Previous Employment With Major Participating Firms None of the individuals who are listed in the Project Organi-zation Chart (Figure 1) have been previously employed by the Owners, S&L, Kaiser, GE-NED or Bechtel. 9.4 Financial and Family Involvement Neither TES and its parent, Teledyne, Inc., own or control stock of any of the Owners, S&L, Kaiser or Bechtel, nor has TES recently been offered future employment by any of the firms listed. However, the Teledyne Pension Trust has in its portfolio bonds of the Cincinnati Gas and Electric Co. This holding amounts to approximately 0.1% (one-tenth of one percent) of the total assets of the trust. TES has performed work (not related to Zimmer) for American Electric Power (AEP), Bechtel, GE and S&L in the past and will continue to pursue work opportunities with these firms in the future. With respect to individual involvement, all personnel assigned to the audit project by TES will be required to respond to the following questions and these records will be maintained
"RTri PTT(NE ENGINEERING SERVICES Technical Proposal PR-6194 ~
by TES Personnel Department. A positive response by any individual will preclude their involvement in this project. (1) Are you, or have you, engaged in any work or business involved in the design, construction or Quality Assurance of the Zimmer Project? (2) Have your ever been previously employed by any of the Owners, Sargent and Lundy, H. J. Kaiser or Bechtel Power Corporation. (3) Are you or any member of your immediate family (parents, spouse, children and grandchildren) employed by any of the Owners, Sargent and Lundy, H. J. Kaiser or Bechtel Power Corpora-tion? (4) In the past 60 days, have you been offered future employment by any of the Owners, Sargent and Lundy, H. J. Kaiser or Bechtel Power Corporation? (5) Do you or any member of your immediate family have any beneficial interest in common or pre-ferred stock, bonds or other securities of any of the Owners, Sargent and Lundy, H. J. Kaiser or Bechtel Power Corporation? TES has been under contract to AEP, Bechtel, S&L and GE in the past. The contracts for Bechtel and GE were primarily for design and analysis assistance related to new plant construction. TES has had one contract with S&L and that was to perform an organizational review of
'RTF1 m(NE ENGINEERING SERVCES Technical Proposal PR-6194 their analysis process. Work for AEP was related to a response to NRC-I&E Bulletin 79-02 and analysis efforts associated with pressurizer pressure relief operation. This work was performed for the Donald C.
Cook Nuclear Station. In no case has the percent of Teledyne, Inc. income per year from work performed by TES for AEP, Bechtel, S&L and GE exceeded 1 percent. In the independent reviews performed by TES in the past we have reviewed the work performed by all three firms. GE and S&L were reviewed on the LaSalle 1 audit and Bechtel was reviewed on the Susque-hanna 1 audit and was a participant in the Diablo Canyon Project. 10.0 CONTRACTUAL 10.1 Time-and-Materials Quotation The work described in this proposal is quoted on a time-and-materials basis. The TES Project Administration Manager will advise CG&E of work progress and expenditures monthly. Personnel services will be billed at the following rates for work performed at TES offices. Billing Classification Qualified as Rate 8 Engineering Assistant I $ 24.00/ hour 7 Engineering Assistant II 32.00/ hour 6 Engineer 39.00/ hour 5 Project Engineer 48.00/ hour 4 Senior Project Engineer 57.00/ hour 3 Senior Engineer 66.00/ hour l l 2 Principal Engineer 80.00/ hour 1 Senior Principal Engineer 91.00/ hour 0 Consulting Engineer 100.00/ hour
SPTF1 FIWNE ENGNEERNG SERVICES Technical Proposal PR-6194 Personnel services will be billed at the following rates for work performed at the S&L offices or Zimmer site: Billing Classification Qualified as Rate 8 Engineering Assistant I $ 27.50/ hour 7 Engineering Assistant II 35.50/ hour 6 Engineer 42.50/ hour 5 Project Engineer 51.50/ hour 4 Senior Project Engineer 60.50/ hour 3 Senior Engineer 69.50/ hour 2 Principal Engineer 83.50/ hour 1 Senior Principal Engineer 94.50/ hour 0 Consulting Engineer 100.00/ hour All direct charges such as travel, subsistence, direct ma-terials, equipment, and outside computer, outside serv. ices, etc., will be billed at cost plus 15 percent general and administrative expense. Billings will be submitted at the end of each month based on work performed during the month. Terms are net 20 days from date of invoice. Based on the proposed manpower loading presented in Figure 4, and the table of completed IDR's performed by TES (Figure 5), TES estimates that the IDR will cost $876,000.00. Since the results of the-review and therefore the final scope cannot be predicted at this time this estimate should be considered to reflect only our estimated manpower requirements. Contingencies in the order of 10 to 20 percent would be reasonable.
'RTF1 prWNE ENGINEERING SERVICES Technical Proposal PR-6194 10.2 Quality Assurance Requirements The work described in this proposal concerns a comercial nuclear power plant. Should a contract or purchase order result, the work will be controlled, as applicable, by the TES Quality Assurance Program, which meets the requirements of 10CFR50, Appendix B, 10CFR21, ANSI N45.2, and ASME BPVC Section III, NCA-4000. If controlled-release design documents are to be supplied by the client, the TES Quality Assurance Program requires a good quality reproducible or a minimum of two copies. We will require a definition of your QA requirements for this work. Prior to issuance of a purchase order, we suggest a meeting (or telecon) to define, as a minimum, your requirements with regard to design documents, reports, and records and to establish communication cont :t between TES and CG&E by names, positions, and responsibilities.
This information should then be included in the formal procurement docu-ment. Within 30 days of contract award, TES will provide for CG&E approval, a Program QA Plan for the work. 10.3 Nuclear Incident (a) Public Liability: Where the services provided for under this proposal are to be utilized in relation with a i nuclear site, the client represents upon acceptance that the maximum financial protection requirements and in-demnification agreement provided for under the Atomic Energy Act of 1954, or any amendatory law thereto, have been complied with, and include TES as one of the persons l indemnified. l (b) Property Damage Waiver: Neither TES nor its suppliers or l subcontractors shall have any liability to the client, upon acceptance and performance of this proposal, for 1
l "A'Tri m(NE ENGNEERING SERVCES Technical Proposal PR-6194 nuclear damage to any onsite property arising out of a nuclear incident. This waiver includes indemnification to TES for third party recoveries as well as subrogation rights against TES by client insurers. (c) Terminology: The terminology used herein incorporates by reference the definitions and provisions of the Price Anderson Act, and amendments thereto, found in Title 42 of the United States Code. 10.4 Hard Copy To expedite hard copy transmission of data, drawings or other information relative to this proposal, TES has available a Fax machine which can be accessed by calling (617)890-0771. In addition, TWX communication is available through our TWX, call number (710) 324-7508. 10.5 General Contractual Requirements Computer Programl - TES reserves the right to employ, in the conduct of the work, any proprietary computer programs, which may be owned by TES or available to TES on a surcharge basis from others, and to inc.lude a surcharge fee for the use of such computer programs. In all events, TES reserves the right to maintain and protect the proprietary and confidential status of . computer programs in their entirety, and the use of a surcharge by TES shall. not constitute any waiver of such rights. Acceptance - Cost and delivery quoted in this proposal are
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firm for 60 days, af ter which TES reserves the right to revise them. Acceptance is subject to the terms and conditions stated herein and they
'M TF1FrWNE ENGINEERING SERVCES Technical Proposal PR-6194 shall constitute the entire contract between the parties; any terms, conditions or provisions contained in client's purchase orders, corre-spondence or commercial forms which are inconsistent with the provisions of this document are void, unenforceable, and not a part of this con-tract.
The following listed terms and conditions are an integral part of this proposal. (a) Standard of Care: During the performance of the described services, TES shall exercise that degree of diligence, skill and care appropriate to the nature of the project that would ordinarily be possessed by duly qualified engineers performing like or similar services at the same time. All reports, recommendations and guidance by TES personnel shall reflect their best pro-fessional knowledge and judgment to accomplish the pur-pose for which TES services were engaged. (b) Delay: TES shall not be held liable for any delay or failure to perform the described services caused directly or indirectly by fire, flood, explosion, nuclear inci-l dent, or other casualty, strike or other labor distur - bances, existing state of war, insurrection, .nvasion, l l riots, or by any existing or future governmental regula-l tions, restrictions, or appropriations, or any other cause beyond its control and direction. (c) Service Agreement: TES's performance of the work pro-posed shall be conclusively deemed to constitute the rendering of a service and shall not be construed to con-l stitute the sale of goods, materials or products within l
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'RTs i m(NE ENGNEERING SERVCES Technical Proposal PR-6194 the meaning of the Uniform Commercial Code, whether or not the rendering of such service is accompanied by the use or supply by TES of certain goods, etc. Furthermore, there are no warranties, expressed or implied, in connec-tion with the proposed work.
(d) Liability: In the event of a claim regarding performance of the within described services, TES will examine the matter at issue to ascertain what, if any, defects, errors or omissions have occurred. Upon being satisfied, TES shall at its sole option and discretion, either correct or perform again such portion of services as may be necessary, or refund that portion of the original charge attributable te the services in question. Under any and all circumstances TES's total liability for all claims arising out of the services proposed herein shall not exceed an amount equal to the price paid to TES here-under. In applying this limitation, any damages paid or payable, as well as any cost incurred by TES, shall be credited against its total liability. In no event shall TES be liable for special, consequential, or any other kind of damages in excess of its total liability as stated herein. (e) Exclusive ' Remedy: The remedies set forth above are the sole, complete and exclusive remedies available in the event of a breach or repudiation of any provision of an agreement for the work proposed herein. Under no circum-stances shall payments for incidental or consequential damages, exceed the value of assets held and used by TES in rendering its performance under this proposed work.
TE WE ENGNEERNG SERVICES PRESIDENT F.C. BAILEY I PROJECT MANAGER 0^ ASSURANCE D.F. LANDERS C.G. SPRANGERS ASSISTANT PROJECT MANAGER J.A. FLAHERTY I Y QA PROGRAM MECHANICAL INSTRUMENTATION REVIEW EQUIPMENT AND CONTROL SUPPORTS ELECTRICAL PIPING STRUCTURES D. MESSINGER J.C. TSAC0YEANES R.R. 80ENTGEN L.J. DILUNA J.W. WHEATON R.M. PACE R.A. ENOS INTERNAL REVIEW PROJECT C0lHITTEE ADMINISTRATION W.E. COOPER J.Q. CRAGIN R. WRAY F.B. STILLE J.J. BALASCHAK (ALT.) N.S. CELIA (ALT.) FIGURE 1 PROJECT ORGANIZATION
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W F W NE Technical Proposal ENGNEERNG SERVICES PR-6194 FIGURE 5 COMPLETED INDEPENDENT DESIGN REVIEWS Shoreham La Salle Susquehanna Manhours 11,000 3,000 5,000 Costs $560,000 $173,000 $265,000 Elapsed Time (Months) 13 4 7 No. of Documents Reviewed 405 182 240 QC Construction Reviewed Yes No No Preliminary Findings 16 14 10 Prelimin.ry Observations 10 6 17 Generic Items 7 5 5 Final Findings 0 0 1 Documentation Revisions Yes Yes Yes Plant Revisions No No Yes System Reviewed LPCS RHR FWTR (Loop C) (Containment) Operating Mode All(1) LPCI All(1) (1)ExcludesFaulted(i.e.,PipeRupture,LOCA+SSE,etc.) s
WTA RVNE ENGNEERNG SERVICES pjfl[jjalProposal 1 j APPENDIX I TES EXPERIENCE l
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1 TELEDYNE ENGINEERING SERVICES I Efficiently managing a nuclear or fossil electric generating plant today is a formida-ble challenge. Plant owners, and those involved in the manufacture, distribution, and storage of fuels and chemicals, must contend not only with new industry and government regulations; they also face constant deci-sions regarding capacity, efficiency, func-tion, and cost. In this environment, successful manage-ment demands updated information and stateof-the-art skills. Teledyne Engineering Services, an es-tablished consulting firm, provides just such experience. For nearly four decades,TES has proven its capabilities in the following areas: O Engineering Design and Analysis O Plant Modifications and Construction Management O Field Support Services O Quality Assurance and Engineering Assurance O Design Reports and Speciatind Analyses O Fracture Mechanics O Design Reviews O ExperimentalStress Analysis and Field Testing O Material Testing, Metallurgy, and Nondestructive Examination OConsulting on O&s and Standards OSeminars and Training Programs OCasualty loss and Product Uanility Analysis TELEDYNE ENGINEERING SERVICES WHKr WE DO IS IMPORTANT; HOW WE DO IT IS CRITICAL
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CENTRAL FOCUS TES provides expert coverage in a broad i range of analytical and experimental engi-neering disciplines, with primary focus on the following areas: O Electric Power Generation l
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. , Transportation ed O Petrochemical Manufacturing O Process Plants Our exceptional scope of services BACKGROUND includes:
Teledyne Engineering Services originated O Plant Life Extension Programs , in thelate1930 sin theconsultingengineer- 0 Vibration Monitoring ing practice of ProfessorJohn M. lessells of G Ultrasonic Evaluation of Boiler f.11T. The present organization is the result Components of inco.poration in 1949, and of acquisition O StructuralIntegrityTesting byTeledyne, Inc. in 1966. O Elevated Temperature / Creep Analysis During its 35-year history, TES has O Failure Analysis achieved a reputation for providing high- 0 Mxhanical/ Electrical Equipment quality, cost-effective engineering, man- Qualification agement, and technical support services. O Independent Third Party Design Our recent acquisition of Brewer Engi- Reviews neering Laboratories, a highly respected O Modal Analysis of Complex Structures experimental stress analysis firm, inarks
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the latest expansion of our broad DIVERSITY capabilities. Clients, both foreign and domestic, range Company headquarters are located from the individual entrepreneur to the in Waltham, Massachusetts, and offices multi <livision corporate giant, and include in llayward, California and Marion, architect-engineers, manufacturers, utili-Massachusetts ties, government agencies, and insurers. L_ __ _ -
STAFF I i COMPETENT READY PRACTICAL ' The staff at Teledyne Engineering Services TES prides itself on its ability and willing- The high level of competence of our staff comprises top-ranked engineering profes- ness to promptly respond toclients' needs. leads to the use of increasingly sophis- , sionals who combine practical knowledge On short notice, qualified TES engineers ticated techniques for solving engineer-and training with state-of-the-art instru- will address your problem on site. Con- ing problems. However, no matter how
- inentation and analytical techniques. sider our approach in solving past prob- complex the route to the solution, each i
Many of our engineers are recognized lems on site: engineer understands the need for a leaders in their fields. Our senior staff of 0 Visit the plant site to evaluate the hard-headed answer: the result must con-ngistered professional engineers hold ad- problem tribute to a device or a system that can be ,! vanced degrees, and are active in profes- O Discuss systems operations with fabricated and installed economically and i sional and technical societies, and codes plant personnel on schedule, and that will prove service-i and standards development activities. O Perform a walkdown of the system ablein its intended use. Their backgrounds encompass mechan- O Perform NDE to assure integrity ical, civil, electrical, and metallurgical O Suggest an interim fix forcontinued engineering. operation l 0 Perform the minimum required analysis O Issue a report with suggested long-term g preventive measures i
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ENERGY TECHNOLOGY l CAPABILITIES In the critical area of energy technology, Tekx!yne Engineering Services can supply a seasoned team to address your needs for: O Engineering Design and Analysis O Systems Upgrading O Fabrication / Installation Drawings t O Construction Management O Field Site Engineering O Diagnostics and Monitoring l O Life Extension EXPERIENCE Through the completion of hundreds of Work on plants under construction and projects, TES has demonstrated its ability niodifications to existing plants has m applying current analysis techniques, included: materials technology, and applicable O Generic Programs to address design bases to: ndustry needs
.. ,,, O Nuclear and Fossil Generating Stations O Construction and Licensing O LNG Liquefaction and Transfer O System Design and Upgrading Facilities O Design Reviews O I etnx hemical Facilities O On Site Field Audits O Structural Dynamics Analysis O Assistance in responding to NRC Bulletins
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i\//\ l l i UO Utilizing a wide variety of techniques FRACTURE MECHANICS including stateof-the-art computer codes, Fracture mechanics analysis provides an analytical engineering at TES is directed at ncreasingly effective technique for de-a full range of applications, among them: termining the ability of a component or 0 The Analysis of Complex Structural structure to tolerate imperfections without Systems with the Aid of Finite Element suffering disabling or dangerous failures. Methods Recent advances have extended the appli-D The Solution of Static and Dynamic cation of Ihis technique to ductile behavior. Problems, Non-Linear and Creep TES' broad capabilities in this area are its i Fatigue Problems combined analytical, experimental, metal- , O The Preparation of Certified Design largical, and nondestructive examination Reports for Components Ranging from (NDE) staff. Valves and hsel Nozzles to Complete Piping Systems
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Complementing TES' analytical capa-bdities is the full scope of experimental ment can be used to perform a host of engineering services, reinforced recently services: In addition, specialimi portable equip- M.I! by the acquisition of Brewer Engineering 0 VlBRATION ANAL.YSIS for determin-
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laboratories. ing resonant frequencies, operation These calubilities include: spectra, transfer functions, damping O Diagnostics and monitoring to provide ratio, mode shape data, and other verihcation of theoretical analysis and vibration parameters to trouble 3 hoot stru(tural and mechani- 0 Ol'TICAl. TOOLING for precision cal problems alignment of paper, metal, and plastic 11 Rapid response to testing equirements mill roll stands, drive and crankshafts, through the use of specialimi trans- machine tools, and other critical ducers and signal conditioning, data structures acquisition, and pnressing niuipment l'1 MUI.TI-CllANNELSLIP RING AND
! Measurement services on a short-term RADIO TElB1ETRY EQUIPMENT for or long-ter m iusis, either in-house or in signal transfers from rotating machin-the field cry, multi-channel static and dynamic I J Design, fabiication, and installation of signal data acquisition. and on-line permancot measurement systems data processing equipment l
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meets all the rniuirements of 10CFR50 and To provide consistent high-quality per-F ," . IMPVC Section ill NCA-1000. Our lead formance. TES' engineering assurance ! j auditors are qualified to ANSI N15.2.23 program provides explicit guidance to l and have extensive QA/QC experience in engineers engaged in analysis. insjection,
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hs t M iu 2 FIELD StPPORTSERVICES i As part of its overall capabilities,TES pnr 0 Vibration Monitoring IN-SERVICE INSPECTION vides a full range of field support services at 0 Instrumentation l (ISI) SUPPORT the construction site or at the client's office. O Construction Management In-depth experience in the design, analv-Whether to train staff, conduct hsts, or 0 In&rvice inspection sis, modification, and installation of a wide complete a project on-site, we can station a 0 Nondestructive Exam. mat. ion assortment of components, systems, and single engineer or a complete team of pro- structures enables the ISl team at Teledyne fessionals for w hatever time is rnicired. Engineering Services to provide exg5ert Field support services include: -
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management control of field inspections, Cl.lFNI'S OFFICE examinations, and installations. I n Fracture Mechanics - J Active participation on various ASME I 1 hping Analysis *' Section XI Code Committees providesTES t i Training / Seminars staff members with current knowledge and ' U Fluid Dynamics .** interpretation of ISI requirements. ( L ! Finite Element Anahsis . i 0 Cale Interpretation -1. I FIEl.D SITE SUPIN)IU $$.
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I 1 l CODES AXD STANDARDS TES personnel have for years shaped codes and standards development activities, working with groups such as ASME, ANSI, and PVRC. Direct involvement, at both task force and policy-making levels, con-tinues to provide our engineers with a thor-ough understanding of current regulations and impending changes. SEMINARS ANDTRAINDG PROGRAMS For more than two decades, TES has con- these workshops are tailored closely to the SEMINARS ducted seminars and training programs, nents of the client, and held at his home O Design of Nuclear Components to addn ssing the growing nents of the power office, plant site, or the TFS offires. Section ill, Division 1(3 days) industry on a wide variety of topics. Inl by Typical seminars and tra:ning sessions O Power Plant Component Modifications acknowksigal authorities in their fields, include: (3 days) O Nt: clear Class 2 and 3 Piping Systems p- >""
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TRAINING PROGRAMS O In-Service Inspection (one day) O Design of Class 2,3, and B31.1 Piping c-- - (one day) O Design of Section Ill Class 1 Piping , (one day) l 0 Pipe Support Design / Analysis (one day) T' P4 \ ; " .,
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i l MATERIALTESTING, METALLLRGY, AND NONDFSTRLCTIVE EXAMINATION MATERIALTESTING TES regularly performs material properties . Q]~ ~5 l 4 gas . studies using tests such as fatigue, tension, .
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i, or a combination of these can be used in the computerized feedback for test ma-s, ,.I thine control. Rotary bending and high-k g, ;w$ speed cantilever of our fatigue-testing capability.machines are also part CRYOGENIC FACILITIES p Tests can be conducted in a number Typical of the response of TES to the needs s a of different environmental conditions, of industry is our development of a cryo-3 , including: genic test facility, in which materials can s O Elevated or Cryogenic Temperatures be tested at temperatures as low as 4.2 K i 0 Water with Various impurity Irvels (- 452 F) and loads up to 55 Kips. With l 0 liigh Ilumidity the use of computer control, sophisticated 0 Inert Gases tests such as fracture toughness using the single specimen technique for determina-METALLURGY tion of Jlcare routinely performed. To analyze the role of material structure or Our cryogenic facilities have placed pmcessing on failure, basic metallographic Teledyne Engineering Services in the services provided BYTES include: forefront of cryogenic research and [L 1 Optical Metallography applications. O Scanning and Transmission Microscop~y 0 X-Ray Diffraction and Energy Disper. NONDESTRUCTIVE sive X-Ray Analysis EXAMINATION O Chemical Analysis One of many ancillary services provided
,- byTeledyne Engineering Services is a non-destructive examination team comprising engineers certified to ASNT-TC-1 A. The
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REPRFSENTATIVE PROJECT EXPERIENCE NUCLEAR O Engineering design and analysis, mate-rial procurement,and construction management senices to accommcxiate liigh Energy Pipe Rupture Criteria, including Pipe Whip Restraint design, building structures, and piping system l mulifications O Design, analysis, and installation of a radiation leak detection and monitor- l ing system O Design, material procurement, con-struction drawings for modification a l to BWR Mark I containments and associated structures ) O Nondestructive Examination using VT, MT, ITT, l'r to aid in assessment of integrity, and establishment of main-tenance and QA requirements for components O Independent design reviews prior to issuance of plant operating licenses NON-NUCLEAR O Design of vaporization plant O Design of liquefaction plant systems O Instrumentation of Coal Pulverizer Components for Diagnostics and Monitoring O Failure analysis, including field inspx-tion, metallurgical analysis, and repair consultation on main steam line break in fossil plant l l l
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"o=NRESSANALY:Sk Scientific sleuths, who find out where the breaking point is, help make things sofer, lost longer and save us all billions of dollars.
As rigid as concrete, as strong as steel, on solid ground-these are some of the truisms we use in everyday language to describe our world and the structures we build in it. But scientists and engineers who work in the field of materials research and structural engineering know very well that concrete without reinforcement is quite brittle, that steel and other metal alloys are only strong up to a point and under certain conditions, and that the apparently solid ground we build on may only be that way for a little while. Yet we all carry on our everyday lives with great confidence, drive automobiles, cross bridges, work in high rise office buildings, depend on power from generators driven by immense turbines, operate machinery in factories, ride trains, fly in airplanes, take ship cruises and allow our lives to depend in so many ways on machines and other man-made structures. Our confidence is not misplaced, for On the cover: perhaps at no other time in history have the structures and machines we use been as These mesh sa[e as the ones being built today. d'J
,, ,*,5c/,(p*,$70 One of the companies that helps to make things that way is Teledyne Engineering l powerfui computer. Services. It is not an architect / engineering firm, structural contractor or manufac- 1 based stress onolysis turer, but is consulted by these kinds of companies, as well as by users of equipment, t n$Ynheenng machinay and structures, to help make them safe, reliable and cost effective.
Services How it is used Teledyne Engineering Sern,ees is called on to help answer such questions as: Ilow is descnbed of the left. can this structure be best designed; how much load will it withstand; is it safe for its intended use; does it meet all applicable code requirements; ifit fails, how and where will it fail: if it has already failed, why did it; was the design faulty; were improper materials used; was it overloaded by the user: where does the liability lie l CHARTING This work is focused largely on industries where materials are being subjected to high NEW stresses in design configurations that are new.The nuclear power industry is a prime CROUND example. Coal and oil fueled utility power plants, since they have gone to larger sizes and higher power levels, also pose new problems. Larger, longer, faster cargo ships and tankers, taller buildings, huge tanks for storing and transporting liquefied natural gas at a temperature of-258' F, higher efficiency turbines, transcontinental pipelines subjected to seismic forces, dams in unusual geologic regions, the rigors of space exploration-all have presented new and complex problems for mechanical PAGE 1 and structural engineers and materials researchers. c%w su
In its 35 year history in ihis field, Teledyne Engineering Sers ices has developed an expertise in materials science, structural engineering, design analysis and testing that is one of the most respected in this field, both here and abroad. This expertise involves such arcane disciplines as fracture mechanics, finite element analysis, solid and fluid mechanics, thermal mechanics, fractography, modal analysis and nuclear elfects, to name some, employed against a background of mechanical and structural engineering. IN SEARCH Central to the work done at Teledyne Engineering Services is the study of the stresses OF STRE55 that will occur in a structure when certain loads are applied.Those loads can be forces created by pressure inside a tank or pipe, the weight of the structure itself, seismic loads imposed by earth movement, thermal loads imposed by expansion or contrac-tion of the structure due to te nperature changes, or loads created by the violent movement of fluids either within the structure, such as steam and water in a generat-ing plant. or external to it, such as sea waves on the hull of a ship or occan currents on a sea-bottom pipeline. Whenever any load-whatever its nature-is applied to a structure, the forces imposed are distributed throughout that structure in a very complex way that results in some parts of the structure being subjected to very high stresses while others experience much lower stresses or even none. Stress is measured in force units such as pounds per square inch. The points of interest, of course, are where the stresses are concentrated at their highest, for this is where the structure will fail if it is not properly designed, or if an improper material is used. Defining stress distribution in a complex structure is no simple matter. There are two basic approaches. One is analytical, the other is experimental. Teledyne Engineering Services applies both, but in recent years the emphasis has been heavily on the analytical method. Brewer Engineering Laboratories (an operating unit of Teledyne Engineering Services),40-year veterans in the field of experimental stress analysis, has contributed greatly to the company's capabilities in the field of testing and instrumentation. THE The analytical approach is primarily mathematical and computer oriented, THINKING although a great deal of human expertise, experience and judgement are required MAN'S in the process. A computer model is created by supplying the computer with the APPROACH detailed dimensions, configuration and material properties of the structure in ques-tion. The computer also has in its program all the engineering formulas and al-gorithms needed to do the required engmeering calculations.When this information is complete, the computer is instructed to calculate stress distribution and values when various loads are applied to the structure. Because of the incredible speed and capacity of modern digital computers, analyses can be made representing hundreds of different conditions in a matterof minutes or hours.The same analyses would have taken an army of engineers months or years to complete in the days of the slide rule and mechanical calculator,if they could have been done at all. One s ery powerful stress analysis technique, described in detail on the inside front cover of this report,is called finite element analysis.1t permits a complex structure to be broken down into an agglomeration of small, individual finite elements or chunks. The computer then calculates the force experienced by each of these chunks of material, the displacement of the material as a result of the force at the boundaries of each element, the stress, and the strain in each element. A major advantage of finite element analysis is that the analyst can have the computer present a graphic display of the finite element mesh diagram, viewed from any angle or shown in cross section, for use in analyzing the numerical results. In a furt her step, the computer will provide a sort of contour map, called an iso-st ress plot, that connects all points of equal st ress. The plot shows quite dramatically the areas of PAGE 2 highest stress and the stress gradient within the structure.
l I LAsonAfony Experimental stress analysis, on the other hand, involves a great deal of physical woM testing and measurement of actual materials, components, and even total structures. Some of this work is done under laboratory conditions. It involves applying loads to a component or material sample with tensile or compressive load machines and measuring very carefully the amount of strain induced as the load is gradually increased. Some tests are carried to the point of ultimate failure of the material. In others a lower stress is applied repeatedly to determine the fatigue life of the sample. Teledyne Engineering Services has equipment that permits these tests to be done i while maintaining the temperature of the material at any point from near Absolute Zero up to thousands of degrees Fahrenheit. l J m THE Other experimental stress analysis involves making measurements of actual working j RELD structures and machines todetermine their response while in use.Often this testing is necessary not only to determine what the stresses in the structure are, but to deter-mine what actual loads are being applied in service. A good example of this is determining ihe hull stresses in a large seagoing ship, where it is impossible, at least
- at present, to determine all the various combinations ofsea and wave loads that a ship 1
encounters in actual service. Field instru mentation work involves the use of devices such as strain gages that can measure the stretching or other deformation of a material down to a millionth of an , inch, accelerometers which measure changes in the direction and velocity of the
; structure, pressure transducers, torque meters and various other detectors and re-cording devices.
One new experimental technique that the company has used with considerable
, success is called modal analysis. All structures have a series of natural vibration frequencies that are unique to that particular structure.These vibrational modes can contribute to stress effects if they are excited by external forces. New equipment in , use at Teledyne Engineering Services can quickly determine and graphically display j any number of the vibrational modes in a given structure, and greatly speeds the analysis work.
About half the work done at Teledyne Engineering Services involves the creation of new designs for components or systems to meet the specifications of a client. This ' work is necessarily analytical in nature, especially in its initial stages, becausa no testable structure exists.The other half consists of work that is done essentially after the fact.This includes evaluating existing structures in the light of new requirements, operational problems and sometimes complete failure. IIere the work is more often a combination of analytical and experimental approaches. The analytical and experi-mental methods are, in any case, complementary. One points the way to show where experimental measurements need to be made,and those measurements,in turn, are often used to validate and calibrate the mathematical computer models employed in analysis. THE A great deal of this work focuses on the energy industry. An example of the scope of ENEASY some of these projects is a program,just now in its final stages, that was begun almost ' O M TN>NS eight years ago. It inmlves the evaluation of the design of a large torus structure, used in certain nuclear reactors, to account for the effects of recently updated loads after the structures had been put into service.These doughnut shaped structures are about 200 feet in overall diameter with ihe" dough" part of the doughnut about 30 feet in cross sectional diameter. This hollow tank-like structure, mounted beneath the drywell of the reactor, is half filled with water and connected to the drywell by large diameter pipes. When steam is mleased to adjust plant pressure, or in the event of a steam leak into the drywell, it enters the torus below the water surface and is cooled - and condensed by the water, thus mducing the system pressure. Teledyne Engineering Services undertook the evaluation of these structures for five met a utilities. The work involved both analysis and field testing, as well as the design and
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3 6 installation of a number of modifications to the torus at each plant. It was possible to carry out this work without undue interruption of utility operations. ; other nuclear power industry projects have included the recent re-evaluation of hydraulic pressure loadings in the control rod drive systems of certain reactors, and ) independent design verification on reactors that are under construction. l l KEEMNe Much ofIhe company's w ork is also related to coal or oil-fired elect rical power plants. THE F0558t.5 Two basic types of problems exist here: the design and operation of new plants ALIVE intended for much higher power levels than was common just a few years ago; and problems related to plants built thirty or forty years ago that are now approaching the end of their design life. Some of these older plants were designed as base-load plants that were meant to be brought up to full design power and operated at that level for weeks or months on end.The advent of newer, larger plants, either nuclear oi-fossil fueled, has relegated some of these earlier plants to peaking or cyclic load duty. They are started up and shut down to meet demand peaks. Many of these plants were not designed for this type of service and the constant cycling of thermal and pressure stresses is creating operational and maintenance problems. Utilities faced with the high present cost of replacing some of these older plants are understandably con-cerned.Teledyne Engineering Services offers a Life Extension program to help them evaluate the weaknesses in existing plants and to recommend design modifications as well as maintenance and operating procedures that will extend their useful life. THE CASE But even brand new power plants can have problems. One new 400 megawatt OF THE oil. fired plant designed for cycling use that requires frequent daily starts, stops and VISRATING variations in powerlevel, suffered extremely violent vibrations in the two fans used to FANS provide burner draft whenever the power level was changed. Fans may seem a small problem, but each of these was large enough to require its own 4,500 horsepower motor to drive it.The inability to change power levels quickly to meet changing loads severely compromised the efficiency of the plant. Brewer Engineering Laboratories was hired to analyze the problem and find a solution. Using experimental as well as analytical techniques, they found the vibra-tion was caused by transient thermal unbalance of the fan rotors that occurred only when the power level was changed. This vibration was increased to severe levels by coupling with the resonant frequency of the concrete foundation that exactly matched that of the fans. One solution, which would have been very expensive and disruptive due to the physical configuration of the plant and soil conditions, was to pour a much larger concrete foundation to move its resonant frequency out of the critical range. Brewer, however, proposed a much more elegant and less expensive as well as non-disruptive solution. Analysis revealed that a pair of 4,000 pound weights, each mounted on a springy steel support, like an inverted pendulum at each fan bearing, could be tuned to exactly cancel the vibrational frequency of the fans. These vibration absorbers were designed and implemented by Brewer Laboratories and the plant has been operating quite flexibly for six years since without further problems. WNEN THE Much of Teledyne Engineering Services
- cxpertise lies in the area of piping and PRES $URE pressure vessel design. These kinds of systems are found in widely diverse industries, 15 ON including energy production, process machinery, chemical and petroleum manufac-ture, as well as in large ship and submarine propulsion systems and space hardware.
pressure in such str uctures can range from as little as the 20 or 30 pounds per square inch you put in your automobile tires, up to tens of thousands of pounds per square inch in some kinds of process vessels. The concern of t he st ress analyst.ofcourse,is whether or not a certain structure will withstand the pressures expected in the type of service it will experience. In practical situations the stress analyst knows that no large structure can be made absolutely met a perfect. There are bound to be Daws, detectable or not, somewhere in the material.
This does not mean that such a vessel cannot be made safe for some specific set of operating conditions.The materials researcher might try to establish why those flaws are present, or what caused them.The stress analyst is more concerned with what effect those flaws will have on the integrity and life of the vessel. This viewpoint has given rise to a relatively new line of inquiry called fracture mechanics, which goes a step beyond basic stress analysis. It involves both testing and analytical techniques and combines a knowledge of material properties with stress profiles of the structure and the loading environment it will undergo, to predict the probability of and type of fracture that is likely to occur due to a given flaw. PROM NOT pressures are not the only concern in analyzing stresses. Temperatures-particularly TO COLD the extremes of temperature-also hase un important effect on the materials used. t liigher temperatures frequently increase the ductility of metals, leading to creep or permanent stretching of the material. When temperature moves in the opposite direction many materials become more brittie and can fail abruptly. Some common i carbon steels can become unusably brittle at temperatures as mild as 50*E Some years ago, when the production of liquefied natural gas was undertaken on a , large scale, the company became involved in the design and analysis of huge tanks ! and vessels for storing and transporting this ultracold material at a temperature of i
-258*E This involved considerable research into and testing of the effects of extreme l cold on various materials. Today, the emphasis has shifted toward temperatures as low as -452*E, the temperature of liquid helium where research into super-conducting magnets needed for magnetohydrodynamics '
(MHD) and fusion power is being carried out.
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THE Marine struct ures of all sorts also present unique stress analysis problems. Where t he UNPREDICTABLE pressure vessel designer can know exactly what pressure loads he will have to deal l SEA ' wit h, the marine arehitcet usually does not. There is no present way to predict exactly what the sea wave loads will be on the hull of a supertanker, or offshore drilling platform, so a great deal of testing and recording of data in the field ha. been done by the company in these areas, liere, the problem is to define the extent, direction and frequency of these random loads on the structure in question, as well as the stresses they will create. This usually involves considerable instrumentation placed on the structure, such as a ship, to gather data over a period of time while it is actually under typical sea conditions. projects have involved determining the bending and torsional stresses in the new larger cargo and tanker hulls, determining why the huge 47-ton propellers of new high speed container ships were dropping into the sea with embar-rassing regularity, what the stresses were on Coast Guard ice-breaker hulls, the effects of wave motion and sea currents on drill strings during offshore drilling, the ocean i current stresses on underwater pipelines, and the collapse of offshore towers. ! CN Similar work is also done on land with the instrumentation of buses, trains, bridges,- LAN3 AND dams, glass curtain walls on high rise buildings, and large antenna structures. Even INSpACE outer space can be fair game for the stress analyst. One notable project is the instrumentation of the manipulator arm used on the Space Shuttle, done by Brewer Laboratories. Strain gage instrumeritation was designed and installed by the com- - pany on the 50-foot arm that is used to maneuver up to'65,000 pound loads out of or into the cargo bay of the orbiter.These gages measure loads and stresses on the arm , during actual space use.The system has recorded data on three previous missions and was used recently in flight number seven. PORENSICs As may have been surmised in reading the foregoing, some of the work done by the company in the area of failure analysis is related to determining who is legally responsible for those failures. This forensie work is a very small part of the company's activities, but it is an interesting one. Cases have ransed from investigations of the ph4E 7 collapse of a major sports stadium roof and an offshore drilling 1ower to failures of an
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ammonia storage vessel and a sugar silo. Crane failures, breakage of glass in high rise buildings, product liability investigations, vehicular accident reconstruction, causes of fires, and civil engineering problems such as soil movement or foundation failure have all come under the scrutiny of the company's experts. Forensic projects that are accepted by the company usually involve a high technical content, where considera-ble knowledge of fracture mechanics, metallurgy and stress analysis are important. Some work is also done for manufacturers before the fact,in giving an independent analysis of new products to determine their safety and compliance with the large number of codes and regulations that are constantly proliferating. THE Our needs in energy, transportation, structures, defense and space exploration are CONTINUING unlikely to diminish, nor are all the problems in these fields likely to be solved,in the
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NEED foreseeable future. Wherever men are working at the leading edge of various technologies, Teledyne Engineering Services will make valuable contributions. TRANSFER AGENT AND REGISTRAR NOTICE Effective Friday, July 1,1983, the Sole Transfer Agent and Registrar for Teledyne, Inc. Common Stock is: Donk of Americo NTGSA (Delivery Address) Corporate Agency Service Center 55 Hawthorne Street RO. Box 37002 Son Francisco, CA 94105 Son Francisco, CA 94137 New York transfers con be effected through DonkAmerico Trust Company of New York, 65 Broadway, 3rd Floor, New York, New York 10006 PAGE 10 _
l TELEDYNE,INC. AND SUB51 DIANE 5 Consolidated Statements of income (in msthons ency.t ywr sisarc wnousntQ Three Afonths Ended Set Months Ended Jwie 30 Jwre 30 1983 1982 1983 1982 Sales $738.0 $737.3 $1,444.7 $ 1,523.1 Costs and Expenses: Cost of sales 576.1 551.6 1,131.4 1,136.0 Selling and administrative expenses 100.6 102.2 195.5 206.7 Interest expense 7.6 8.0 15.2 14.8 Interest and dividend income (16.9) (16.1) (34.8) (30.2) Provision for income taxes 28.2 37.5 54.3 83.7 695.6 683.2 1,361.6 1.411.0 Income of Consolidated Companies 42.4 54.1 83.1 112.1 Equity in Net income of Unconsolidated Subsidiaries 28.2 23.6 57.2 56.8 Net income - - - -
$ 70.6 $ 77.7 $ 140.3 $ 168.9 Net income Per Share $3.44 $3.76 $6.82 $8.18
= ..u========-_===.-- _
Consolidated Bolonce Sheet (injnulliansd Jwse 30.1983 ASSETS Current Assets: Cash and marketable. securities $ 784.4 Receivables 356.9 inventories 104.2 Prepaid espenses 7.4 Total curreni assets 1,252.9 Investments in Unconsolidated Subsidiaries 1,904.4 Pmperty and Equipment 380.2 Other Assets 33.4
=.. - - - - -
$3,570.9 LIAHil.lTIES AND SIIAREIIOLDERS' EQUITY Curarnt 1. labilities:
Accounts payable $ 127.1 Accrued liabilities 236.0 Current portion oflong-term debt 9.5 Total current liabilities 372.6 long Term Debt 570.2 Other long-Term Liabilities 210.3 Sharvholders' Equity 2,417.8
= =_
$3,570.9
=- -
- ~ _ . -
p ses. The doto ore then fed into o less radiant heat where on open flome ieW forge moinfrome computer for further is undesirable and unsofe. Radiant processing and mon!pulation. heat is directional, like sunshine. ond The new system will be used to de- heots objects and people without velop digital terroin doto for use in heating the surrounding cir. The unit weapons guidance systems. Another uses notural gos or LPG fuel. opplicotion for this equipment is to convert utility mops to digirol doto HIGH PRECISION FORGING MACHINE banks for monogemmt information DEGIN5 OPERATION QUARTER AND FIRST HALF RESULT 5 y ems. Teledyne Allvoc has begun operating ' Net income was $70.6 million or new mtory forging machine. It is the ,
$3 44 per shore for the quarter ended first mochine of its size and copobilities NEW METHOD FOR LEAK DETECTION June 30.1983 compared to net in- in the U.S. devoted ro the processing of Teledyne Geotech has introduced o come of $77.7 million or $3.76 per method for the surveillance and detec- high temperature, corrosion resistont shore for lost year's second quorter. and ritonium olloys.
tion of very small leokoges olong the i Sales were $738.0 million for the sec- The new mochine allows the com-ennre length of pipelines. The system.
; ond quarter of 1983 compared to pony ro supply customers with products j $737.3 million in Ine 1982 period. colled Leokoge Alorm System for Pipelines or LASP will detect and locote hoving superior merollurgical pro-I for the six months ended June 30. perties. Those markers requiring such leokoges os small os 300 cubic cen-1983 ner income was $140.3 million high levels of precision, reliobility and timeras of gas and 5 liters of liquids.
or $6.82 per shore compared to advanced technology include jet The LASP sensor rube is ploced along
$168.9 million or $8.18 per shore for buried pipelines. The tube will collect engines gas turbines, cir frames, di-the some period of 1982. Soles for the esel volves, and o voriety of products in the vopors of ony materials that leak six months were $1.44 billion com- nuclear. biomedicof chemicol and
' out and or regulor intervofs the vapor pared to $1. 52 billion for the first half of concentrations will be pumped to o petrochemical industries. 1982. detector or the end of the line. The The forging mochine, which is mic-The use of equity occounting for cer-microprocessor-controlled detector will toprocessor controlled and weighs two l toin investments of unconsolidored million pounds. simultaneously forges reod concentration profiles of selected subsidiones increosed ner income by l substances and will occurately locore billets of the ro'e of 200 strokes per
$9.1 million or 50.44 per shore for the l le ks. minute while duplicating them with second quarter of 1983 compared to identical dimensional and mechonico!
I $13.3 million or 50.65 per shore for NEW HYDROGEN GENERATOR pmperties. the some period of 1982. For the six Teledyne Energy Systems hos been o in addition to the instollotion of this months ended June 30,1983, equiry major supplier of hydrogen generorors new high copocity precision rotory accounting increased ner income by forging mochine, Teledyne Allvoc's cur-
$16.0 million or 50.78 per shore com- to electric power utillties whose turbine-driven generotors are de. rent expansion program also includes pored to $30.5 million or $1.48 per o new odvonced technology rolling l shore for the some period of 1982. signed to operate in o hydrogen of.
mosphere. mill ond o research and development There were 20.520.464 and laborotory 20.588.998 overage shores outstond- The new Model EC is similor to the
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ing for the three months and six other on-site hydrogen-producing 7y- _. months ended June 30.1983. respec. worer electrolyzers manufactured by v tively compared to 20.657.531 for the company butis more efficient and , the some periods of 1982. During the has nearly four times the hydrogen second quarter Teledyne purchased output copocity of current models. 287.000 shores ofits common stock in Dy introducing the model the com-the open market. At June 30.1983 pony will expond the scope of its mor-the Company had 20,370,531 shores kets to industries thor consume up to 40 of common stock outstonding. million cubic feet of hydrogen per year, such as merol and food process-MAKING SENSE OF COMPLICATED MAPS ing. floot gloss, and chemical indus-Teledyne Geotronics was granted o po. tries. l tent for on automated system de-signed primority to convert line maps FLAMELESS CATALYTIC HEATERS to digirol form. T:odemorked UNETRAC. MADE MORE EFFICENT l It consists of two subsystems. A roster Teledyne Merlo hos introduced o new I sconner quickly scoas mop dato ond line of flameless corolytic heaters for feeds it directly to the UNETRAC digitol the oil Ond gos industry which increoses processor. The processor converts the the level of radiont hear by 250% roster doto to vector format and dis- while reducing emission. plays it on o TV screen for editing pur- The corolytic heoter produces flame-TELEDYNE ALLVAC PRECISION ROTARY FORGING MACHINE
l I ThisM ffW outlines the activities of Teledyne Engineer-ing Sorvices in the field of mechonical and structural engineering design and evoluotion. The goal of this work is to make structures and mochinery sofer. more relioble. longer lived and more cost effective. Stress analysis is or the core of most of this work. whetherit is to determine the sofery and validity of a design for o new structure, to solve operonng problems encountered in existag mochinery or to discover why a failure has occurred. In its 35 year history Teledyne Engineenng Services hos developed on expertise in materials science, structural engineenng. design analysis and resung that is one of the most respected in this field. This expertise involves such disoplines os frocture mechonics. solid. fluid and thermcl mechonics. finite element analysis, fractography, modal onolysis, nuclear effects and others. employed ogoinst o strong background of structural and mechanical engineenng. Much of this work is onolyticol, involving computer-based mothematical models and related techniques to predict stress values in proposed designs. Comptementary to this is experimentol work involving resting, in-strumentonon and measurement of structures in use. Drewer Engineering Laboratories. which is on operating unit of Teledyne Engineering Services. contributes brood expenence in the expenmental areas. Teledyne Report features subjects of porticular interest from Teledyne ocnvities and is issued on o quarterly basis. Previous topics include: Drafring: Screw Threading: The 5eorch for Oll: Designs to build by Machine tools for industry Finding new oil deposits. syst2ms Engineering: Urban %ste: High Speed Steels: Creonng complex systems Recovenng energy and morenols. Premium olloys for mochine tools. Fl:xible Printed Circuits: Aerial Mapping: Energy Crisis in the Computer Room: The space age connecnon. Advanced digirol techniques. Controlling power quolity Mixing: The %ter Pik Story: Roydist: A fine blend of orr and soence. Innovotive consumer product designs. Super-precise rodiolocotion system. Aircraf t Ground Support: Dental Health: Wlding: Soving the oirlines millions: Supplies for the dentist. Advanced olloys forjoining merols. Turbin) Engines: Space Navigotlori: General Aviation Engines: 5moller in size and cost. Computers thor guide spoce launches. Piston power for circroft. Hset!ng Water: Anolytical Instruments: Rubber: for health and home. Cnemical detection for industry Products for outomobiles and industry Rel ys: 1776 1976: Loron: Thnving in on ultrominioture world. Technology then ond now. All-weather navigorion system. Truth in Radiation: Life Insurance: Seismology: A morrer of occurore measurement. F,nonciol security and investment. Instruments for earthquokes. R2m:itely Piloted Vehicles: The Refractory Twins: Casting: Those ingenious flying mochines. Producing tungsten and molybdenum. Precision production of metal ports. Mining Tungsten: The Instrument Mokers: AIDS: From glowing ore to versonle metol. Instruments and optical encoders. Monitoring commercial circraft. Hi Fi: Industrial Engines: Thermoelectrics: Music reproducnon goes hi. tech Small piston engines. Conversion of heot to electricity C lumbium: Job Corps: Thin Metals: Superconductivity to computers. Teoching young people new skills. How they are mode and used. Enirgy: Friendly Explosives: The Reproduction of Music: Fueling spaceship earth Aircrof t emergency escope systems. Speakers for high fidelity sound. R d r: Microelectronic Hybrids: The Crowded Spectrum: Sensing the unseeable. The step beyond integrored circuits. Technology of traveling wave tubes. fluid Power: The Energy Options: Science and Cinematography: Muscle for mochines. Nuclear fuel versus cool. Motion pictures for scientific onolysis. Pipeline Controls: %rkman's Compensation: Superolloys: l Operonng petroleum pipelines. Extending the coveroge. High temperature merols. , The A rospace Metals: Drilling for Offshore Oll: Jets of Water for Dental Health: 1 Superalloys and nronium. Getting the oil out. The Worer Pik oral hygiene oppliance. l 1 iA4% C3 y c g .iftd n[j w
c 1 l
'#PTELEDYNE,lNC.
1901 Avenue of the Stars Los Angeles, Cahf 90067 l l
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'7PTA AWNE Technical Proposal ENGNEERING SERVICES PR-6194 APPENDIX II MAJOR NUCLEAR POWER ACTIVITIES 1
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WTA prWNE ENGNEERNG SERVICES DESIGN REVIEW Acting as an extension of the Utility Engineering Department, TES has participated in Design Review of the following Nuclear plants: Plant System Scope
- 1. Nine Mile Point 1 Critical Systems Review Design, Analysis, and Construction.
Participation in Licensing.
- 2. Millstone Point Entire Plant Review Design, Analysis Unit I and Construction.
Participation in Licensing. Unit 3 Class 1 Piping Review of Analysis Techniques, Operating Condition Specification, and Preliminary Stress Reports.
- 3. Vermont Yankee Critical Systems Review Analysis and Construction.
- 4. Pilgrim 2 Several Review of Design Specifications for Various Components.
- 5. North Anna 1 and 2 All Audit all Field Changes.
- 6. Susquehanna liigh Energy Provide Review of Methods Piping Systems and Procedures for Pipe Rupture Analysis performed by AE.
- 7. Monticello Reactor Review Analysis.
- 8. Prairie Island High Energy Review Design and Pipe Systems -Whip Analysis.
Residual Heat ' Systems Review from Removal and Safety Operational Criteria Injection Systems through Structural Drawings.
- 9. USNRC ---
Provide Engineering Services for USNRC Study "To Determine Effects on Low Probability Events on Nuclear Piping."
W F W NE ENGNEERNG SERVICES DESIGN REVIEW (Continued) Plant System Scope
- 10. LaSalle LPCI Independent Design Review Susquehanna Feedwater prior to issue of OL.
Shoreham LPCS
- 11. Diablo Canyon Utility Supplied Independent Design Review in response to NRC actions.
TF WE ENGNEERNG SERVICES PLANT MODIFICATION AND CONSTRUCTION In addition to structural design and analysis work described herein, TES has perfonned plant modifications services for utilities as follows: Plant Scope of Work
- 1. Millstone Point 1 Various Engineering, Procurement, Construction and Field Services for the following systems: High Energy Pipe Break Criteri a, E0C/PRT Relief Line, Monitoring and Leak Detection Equipment, Core Spray, ECCS, LPCI Supports.
- 2. Millstone Point 2 Engineering, Procurement and Field Services for addition of Scavenger Steam System.
- 3. Connecticut Yankee Engineering, Procurement, and Construction Management Services to accommodate High Energy Pipe Break Criteria, including Pipe Restraint Design, Guilding Structure Modification, and Piping System Modification.
Design and Field Engineering Services for Pressurizer Safety and Relief Valve Piping Modifications.
- 4. Pilgrim 1 Various Engineering, Procurement, and Field Services for the following systems; Reactor Water Clean-up, Core Spray, and Main Steam Relief Line.
- 5. Fitzpatrick Design, Engineering Services for Mark I Containment Vermont Yankee Structures.
- 6. Nine Mile Point 1 Design, Materials Procurement, Fabrication, QA/QC, Field Millstone Point 1 Engineering Services, for Modification to Mark I Pilgrim 1 Containment Structures.
- 7. Brown's Ferry Design and Field Engineering Services for Main Steam Relief Units 1, 2 and 3 Line Modification.
l l 8. Davis-Besse Engineering, Materials Procurement, Construction Drawings associated with responding to NRC NUREG-0737, moving code safety valves closer to the pressurizer. l l l l
i w mme ENGMEERNG SERVICES STRUCTURAL DESIGN AND ANALYSIS TES has performed the following analysis and design of major structures for Nuclear Plants: Plant Structure Loading Client
- 1. Fitzpatrick Entire Reactor Building Seismic Utility
- 2. Nine Mile Main Steam Tunnel Dead Loads Utility Point 1 and Dynamic Pressurization
- 3. Millstone Protective Shields All Utility s Point 1 and Barriers fur Isolation Condenser System Core Spray System Operating / Utility Pipe Supports Seismic Secondary Shield Dead Loads Utility Turbine Building, and Jet Walls, Auxiliary Impingement Walls, and Floor
- 4. Beaver Valley, Pump Foundation All AE North Anna 1,2
- 5. Susquehanna CRD Piping Support Seismic and AE Units 1 and 2- Platfom, including Hydrodynamic Vent Valve Platform (SRV and Chugging
, at High Frequancy)
- 6. Davis-Besse Metal Containment Jet Impingement Equipment Supplier
- 7. South Texas Turbine Generator Design of Utility
, Projects Building Secondary Pipe Units 1 and 2 Whip Restraints i
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1 %' E M ENGNEERNG SERVICES STRUCTURAL DESIGN AND ANALYSIS (Continued) Plant Structure Loading Client
- 8. Millstone Point 1 Torus, Torus Supports, LOCA and Blowdown Utility Pilgrim 1, Nine Torus Piping, Internal Mile Point 1, Structures, Vent System Fitzpatrick, including quenchers Vermont Yankee
- 9. Prairie Island 1,2 I&E Bulletin 79-02 All Utility /
Diablo Canyon 1, 79-14 review and AE Pilgrim 1, analysis of Pipe Donald C. Cooke Supports and 1 and 2 Baseplates Millstone Point 2, Joseph M. Farley Units 1 and 2
- 10. Mark 1 Plants Containment Analysis and NSSS Evaluation of Mark 1 containment columns for axial load, combined with either primary or secondary moment l
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~ TF WE ENGINEERNG SERVCES i
INSTRUMENTATION SERVICES TES is capable of providing instrumentation services to augment analytical services. The following are examples of the type which have been provided to utilities: Plant Data Acquired / Service Pilgrim 1, External strain from torus shell and supports, Millstone Point 1 displacements, deflections, internal and external Nine Mile Point 1 structure strain, pressure and temperature indices. Nine Mile Point 1 On-line valve operation and monitoring, liquid level indicator for SRV system modification. Pilgrim 1 Torus Water Tmperature Millstone Point 1 Transducers and Measurement System Nine Mile Point 1 Millstone Point 1 Design and Installation of Containment Leak Detection Systs. Millstone Point 1 Design and Installation of E0C/PRT System. D.C. Cook Nozzle and Piping Themal Stress Testing Program Kewanee Stress and Motion Studies for Main Feedwater Pumps North Anna Stress and Motion Studies fo Reactor Head and Control Rod Drive Mechanisms 19 Plants Structural Integrity Test Program for Reactor Containment Vessels
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'AT M ENGINEERNG SERVICES PIPING Complete piping analysis, including the preparation of Design Reports, has been performed by TES on the following Nuclear Plants:
System Plant Analyzed Criteria Client
- 1. Nine Mile Point 1 All Class 1,2,3, B31.1 Utility and Radwaste Section III
- 2. Millstone Point Feedwater, Main Steam B31.1 Utility Unit 1 including cross-around relief line Unit 2 All Class 1 Section III Utility Unit 3 All Class 1 Section III AE/ Utility Thermal Analysis
- 3. Connecticut Radwaste, Pressurizer B31.7 Utility Yankee Relief and Safety Valve Piping
- 4. North Anna 1 Chemical - Volume Section III AE Control and Pressurizer Spray
- 5. Edwin I. Hatch All Class 1 plus B31.7 AE Units 1&2 some Class 2 and 3 Section III
- 6. Bellefonte Part of Class 1, 2 Section III Utility
- Units 1&2 and 3 systems
- 7. Susquehanna Control Rod Drive Section III AE Units 1&2 Piping and Support Design
! 8. Virgil C. Summer Class 1, 2, 3 Systems Section III AE
- 9. Watts Bar Main Steam Section III Utility
- 10. Hartsville Main Steam and Main Section III AE/ Utility Phipps Bend Steam Relief Valve Piping
"RTS 1 FnVNE ENGINEERING SERVICES PIPING (Continued) -
System Plant Analyzed Criteria Client
- 11. Browns Ferry Class 1, 2, 3 Systems Section III AE/ Utility Units 1, 2 and 3
- 12. Davis-Besse All Class 1 Section III AE
- 13. Enrico Fermi 2 Control Rod Drive Section III System Class 2 Piping Designer
- 14. Hanford Unit 2 Control Rod Drive Section III System Piping and Support Design Designer
- 15. Doel-Belgium Main Coolant and B31.7 NSS Pressurizer
- 16. Lemoniz 1 Complete Class 1 Section III Utility
- 17. Arkansas 1, 2 Pressurizer Discharge NRC Utilities Davis Besse Valves and Piping NUREG-0737 Rancho Seco ,
Donald C. Cook 1, 2
- 18. Nine Mile Point 1 Control Rod Drive Varied AE/ Utility
, Susquehanna Waterhanner Limerick Hanford Hope Creek Fermi BWROG
- 19. Fitzpatrick Torus Attached Piping Utilities Pilgrim 1 as part of overall Vermont Yankee Mark 1 Program Millstone 1 Nine Mile Point 1 i
WTF1 FTh'NE ENGNEERNG SERVCES SPECIAL DESIGN AND ANALYSIS During the past years, TES has completed many special vessel, valve and piping design and analysis projects. The following sumary describes some of these: System Loading Plant Analyzed Analysis Client
- 1. Nine Mile Point 1 Feedwater and Pipe Break Utility Main Steam and Seismic Austenitic Stainless Study to Determine Inside Drywell Susceptibility for Stress Main Steam Relief Design and Utility Analysis of Relief Valve Enclosure Assemblies Control Rod Drive Varied AE/ Utilities Corrosion Equipment
- 2. Vermont Yankee Off-Gas Cracking Supplier Detonation Recircul ation 3-D Deflection Utility Analysis of Valve for LOCA
- 3. Millstone Point Feedwater Nozzle Fracture and EPRI/
Mechanics Utility Analysis Unit 2 All C1 ass 1 Developed Thermal Utility Response of Fluid in Small Branch Piping Scavenging Steam Design & Analysis Utility System of New Scavenging Steam System
r "RTF1 FnYNE ENGNEERNG SERVICES SPECIAL DESIGN AND ANALYSIS (Continued) System Loading Plant Analyzed Analysis Client
- 3. Millstone Point All Class 1 Detailed Stress AE/ Utility (Continued) Analysis of 10"x450 Unit 3 Lateral to RCS; Finite Element Analysis of Special Nozzles, Thermal Sleeves, Attachments and Flanges
- 4. Pilgrim 1 Main Steam and Evaluate Repair to Utility Feedwater Isolation Valve and As-Welded Lugs on Feedwater Line Main Steam Relief Analyze and Redesign Utility Valve Piping Support System; Prepare Restraint Drawings Reactor Water Complete Analysis Utility Clean-up and Design of RWCU System to Enhance Pump Operability
- 5. Millstone Point 2 All Class 1 Developed Stress Utility Davis-Besse Indices for Class 1 and AE Anchors, Pipe Flanges, Containment Penetrations, ,
and Modified Tees
- 6. Millstone Point 2 Main Steam Dynamic Analysis of Utility and Farley, Davis-Besse Isolation and Valve for Closure Component Swing Check Valves Under Faulted Supplier Conditions
- 7. Virgil C. Sumer RTD Manifold System All operating loads Utility effects of Socket weld fit-up anomali~s e
- 8. Kewaunee Main Steam Pipe Break Utility
- 9. South Texas Project Feedwater and Pipe Rupture Utility Units 1 and 2 Main Steam Outside Analyses, Fluid Containment Load Development, Dynamic Structural
Response
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'R TF1PD(NE ENGINEERING SERVICES SPECIAL DESIGN AND ANALYSIS (Continued) l System Loading Plant Analyzed Analysis Client ;
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- 10. Rancho Seco Thin-wall piping All AE effects of minor welding imperfections
- 11. Millstone Point 1, Torus Fluid Structure Utility Pilgrim 1, Nine Mile Interaction effects Point 1, Fitzpatrick, on water filled tanks Vermont Yankee
- 12. Hatch 1 Reactor Pressure Consideration of Utility Vessel Flaw Indication
- 13. Millstone-1 Feedwater Nozzle Fracture Mechanics Utility Evaluation of Permissible Flaw Size
- 14. Pilgrim-1 Feedwater Nozzle Fracture Mechanics Utility and Recirculation Evaluation of Inlet Nozzle Permissible Flaw Size Recirculation 30 Stress Analysis, Utility Outlet Nozzle Flaw Growth Calculations, Permissible Flaw Size RCS Pressure Appendix G Boundary Evaluation
- 15. Millstone-1/ Feedwater Nozzle Generic Application, EPRI EPRI 3D Stress Analysis; KI by Influence Function Approach
- 16. Point Beach-1,2 Review of Vendor Utility Turkey Point 3 Fracture Mechanics Analysis
- 17. R. E. Ginna RCS Inlet Nozzle Section XI Flaw Utility Evaluation-
- 18. Lemoniz RCS Pressurizer, Fracture Mechanics Utility Outlet Nozzle Evaluation (Spain)
- 19. - RCS Outlet Nozzle Analysis of EDF Underclad Cracks (France)
"MTF1 rrT(NE ENGNEERING SERVICES SPECIAL DESIGN AND ANALYSIS (Continued)
System Loading Plant Analyzed Analysis Client
- 20. CRBRP System 53 Design and Analysis System Storage Vessels Services for 3 Designer Liquid Sodium Dump tanks
- 21. FFTF Primary and Design and Analysis Component Secondary Loop of 10 Liquid Sodium Supplier Vessels Expansion loop and AE Storage Vessels
- 22. FFTF, SPTF Primary, Secondary Complete Analysis of Component (5 projects) and Test Loop Valves Flow Control / Supplier Isolation and Drain Line Valves for Liquid Sodium Service
- 23. LMFBR System Heat Exchanger Complete Seismic Component Analysis Supplier
- 24. BWR Reactor Feedwater Nozzle Detailed Stress System Vessels and Thermal Sleeve Analysis Designer
- 25. 8 Plants Main Steam Turbine Trip Utility /AE 26, 15 Plants Main Steam Relief Valve Utility Prer.sure Relief Blowdown Analysis and AE and Restraint System Redesign
- 27. 5 Plants Pressurizer Detailed Force-Time AE/ Utility Pressure and History Pipe Rupture Safety Relief
- 28. 15 Utilities Baseplate / Concrete Shear-tension Generic Expansion Anchor Interaction and Response to Bolts fatigue cycling NRC I&E Bulletin 79-02
SeTF1 m(NE ENGINEERING SERVCES MECHANICAL AND METALLURGICAL TESTING SERVICES TES har analytical services to provide testing of nuclear components for a variety of clients. Component Service Concrete Expansion Experimental Determination of properties using static / Anchor Bolts cyclic loadings Mechanical / Hydraulic Cperational testing of loadings on prototypes and Shock Arrestors production models, experimentally establish Dynamic Response. Pipe Hangers Load Capacity Data Sheets Reactor Pressure Vessel Failure Analysis followed by Fracture Mechanics Analysis of Vessel Anchor Studs. Main Steam Isolation Failure Analysis of Valve Shaft. Valve Pressure Vessels Nondestructive Examination, using Visual, Liquid and Piping Penetrant, Magnetic Particle, and Ultrasonic Techniques to aid in the assessment of integrity, establishment of maintenance, and Quality Assurance requirements for components. Performance of Quality Control Auditing of NDE Subcon-tractors for utilities during inservice inspection outages. CRD Valves Tested valve actuation time versus flow area / stem position of two major BWR CR0 valves. This work was done for the l BWR Owners Group investigating hydrodynamic loads created i by the f ast actuation of the scram valves. Fossil Plant Analysis of creep rupture failure of main steam line and In-Main Steam Line Plant Inspection of additional suspected creep damage locations using metallurgical techniques. i L
e WTF15TWNE ENGNEERING SERVICES OTHER NUCLEAR-RELATED PROJECTS TES has performed a significant amount of analyses of nuclear plant components in addition to the preceding items which enphasize piping analyses. This tabulation does not permit a complete presentation; however, a brief sumary of the types of components considered follows: Reactor Vessels Valves Containment Storage Vessels Heat Exchangers Pumps Compressors, etc. I e f i i l [ l l
'AP WNE ENGWNEERING SERVCES CODE AND STANDARDS ACTIVITIES The TES staff is continually involved in the codes and standards j groups which formulate the rules for construction and modification in I the energy industry as is evidenced by our membership on the following:
e ASME Council Chairman, Vice President for Codes and Standards e ASME Subcomittee on Design e ASME Subgroup on Shells e ASME Subcomittee III - Nuclear Power Plant Components e Subgroup on Design
- e Working Group on Vessels e Working Group on Valves e Working Group on Piping Design e Working Group on Component Supports e Working Group on Dynamic Analysis
- e Working Group on Faulted Conditions e ASME Subcomittee XI - Rules for Inservice Inspection of Nuclear Power Plant Components e Subgroup on Containments e Working Group on Repair and Replacements e Working Group on Operating Criteria e ANSI Board of Directors e ANSI B31.3 e Joint ACI-ASME Comittee e Working Group on Liners e Pressure Vessel Research Comittee e Subcomittee on Shells e Subcomittee on Piping, Pumps and Valves e Subcomittee on Reinforced Openings e Subcomittee on Elevated Temperature Design e Technical Comittee on Piping Systems
- e Steering Comittee on Piping Systems e Task Group on Laterals
*TES staff members serve as Chairmen.
Other TES staff memberships include: Atomic Industrial Forum American Society Civil Engineers American Nuclear Society American Society Testing Materials American Society Nondestructive Testing Society Automotive Engineers Society Naval Architects and Marine Engineers Society Experimental Stress Analysis
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I SPTA WE Technical Proposal N M M ES PR-6194 APPENDIX III RESUES l l l l l
? WTELED#E ENGNEERNG SERVICES FRED C. BAILE'.' President Professional Resume Education Massachusetts Institute of Technology, S.B. in General Engineering, majoring in Metallurgy and Mechanics, 1948; S.M. in Mechanical Engineering, 1949 Experience Teledyne Engineering Services, Teledyne Materials Research, and Lessells and Associates, Inc., since 1955: primary interests have been theoretical and experimental stress analysis, machine design, materials selection and testing and applied mechanics. National Academy of Sciences-National Research Council, Technical Secretary, Assistant Technical Director, and Acting Technical Director of Committees on Ship Steel and Ship Structural Design, 1952-1955: administration of research on brittle fracture in steel, welded steel structures, ship structural components, and stress analysis of ship structures. Caterpillar Tractor Company, Research Engineer with the Fatigue and Stress Analysis Section, 1949-1952: vibration and stress an: lysis studies of diesel engine and earthmoving equipment components. Membership American Society of Mechanical Engineers, Member Society for Experimental Stress Analysis, Executive Committee, 1960-1961; 1969-71; Treasurer 1961-1965, Vice President, 1965-1967, President, 1967-1969; F.G. Tatnall Award 1974; Fellow 1975 The Society of Naval Architects and Marine Engineers, Member; Linnard Prize 1972 American Welding Society, Member Registered Professional Engineer in Massachusetts (Over)
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l Authorship "An Unmanned System for Recording Stress and Acceleration on Ships at Sea," with D. J. Fritch, Ship Structure Committee Report SSC-150, 1963.
" Preliminary Analysis of Bending-Moment Data from Ships at Sea," with D. J. Fritch and N. S. Wise, Ship Structure Committee Report SSC-153,1963.
" Acquisition and Analysis of Acceleration Data," with D. J. Fritch and N. S. Wise, Ship Structure Consnittee Report SSC-159,1954.
"Results From Full-Scale Measurements of Midship Bending Stresses on Two C4-S-B5 Dry-Cargo Ships Operating in North Atlantic Service," with D. J. Fritch and N. S. Wise, Ship Structure Committee Report SSC-164,1964.
"Results From Full-Scale Measurements of Midship Bending Stresses on Two Dry-Cargo Ships - Report #2," with D. J. Fritch and J. W. Wheaton, Ship Structure Committee Report SSC-181, 1967.
" Slamming of Ships: A Critical Review of the Current State of Knowledge,"
with J. R. Henry, Ship Structure Committee Report SSC-208, 1970.
"Results From Full-Scale Measurement of Midship Bending Stresses on Three Dry-Cargo Ships," with I. J. Walters, Ship Structure Committee Report SSC-209, 1970.
" Analysis of Slamming Data from the SS WOLVERINE STATE," with C. H. Kano, P. T. Diamant, and J. W. Wheaton, Ship Structure Conunittee Report SSC-210, 1970.
" Statistical Study of Wave-Induced Bending Moments on large Ocean-going Tankers and Bulk Carriers," with Robert S. Little and Edward V. Lewis, Transactions SNAME, Vol. 79, 1971.
10/83 1 l l
/ YM ENGMEERNG SERVICES DONALD F. LANDERS Senior Vic'e President Professional Resume Education Lincoln Technical Institute, A.S. in Mechanical Engineering, 1962 Northeastern University, B.B. A. in Engineering and Management,1963 Experience Teledyne Engineering Servias, feledyne Materials Research, and Lessells and Associates, Inc., since 1961: Engineering desi gn, analysis and construction management for nuclear power and fossil power plant modifications; theoretical and experimental stress analysis of piping and pressure vessels; preparation of Design Reports; consulting on design criteria, design specifications, and pressure vessel and piping design and analysis; Design Review of nuclear and LNG piping systems including installation; licensing and regulatory consulting; Project Manager of Susquehanna and Shoreham Independent Verification Programs. Arthur D. Little, 1959-1960: stress analysis and field engineering of fuel loading piping for Atlas and Titan missile bases. Bethlehem Steel Company, Nuclear Power Section, Central Technical Department, 1957-1959, 1960-1961: stress analysis of shipboard piping, pipe hanger design ~, supervision of nuclear piping installation. Charles T. Main Company, 1955-1957: power plant and textile mill design. U.S. Navy Weather Forecaster, 1951-1955. Manbership ASME, Boiler and Pressure Vessel Code, Section III Committee Member; Working Group on Piping Design Member; Subgroup on Design Chainnan. Welding Research Council, Pressure Vessel Research Committee ANSI, B31.7 Code for Nuclear Piping, Member; Chainnan, ANSI B31.7 Task Group on Design. Registered Professional Engineer - Coninonwealth of Massachusetts (over) ! I
h Authorship
" Specification Guidelines for Nuclear Pressure Vessels," with W. E. Cooper, AEC Report NY0-3416-1, October 1964.
" Nuclear Piping Design Guide," with R. D. Hookway, USAEC Division of Reactor Development and Technology RDT Standard.
"Effect of ANSI-B-31.7 - 1969 on the General Piping Industry," Heating, Piping and Air Conditioning Magazine, June 1970.
" Computer Sof tware - Problems and Preferred Resolutions," ASME Booklet on C a puter Software.
" Problems Occuring in Nuclear Piping System Analysis and Operation,"
Second International Conference on Structural Mechanics in Reactor Technology - Berlin, Germany,1973.
"B31 Piping Design Philosophy," 1973 Annual Meeting, Mexican Society of Mechanical and Electrical Engineers. 1
" Design Specifications." ASME Philadelphia and Delaware Sections, >1973, 1974 and 1975 Nuclear Power Plant Components Course and 3976 ASME Annual Meeting Short Course. - -
"Section III - Nuclear Piping Design," ASME 1975 and 1976 Annual Meetir.g Short Courses.
" Nuclear Piping Design - A Critique," July 1978.
" Technical Program to Identify Significant Problems Related ,to Piping Systems in LWR Power Plants," August 1980 - Sandia Laboratories.
" Effects of Postulated Event Devices on Nomal Operation of Piping' Systems in Nuclear Power Plants," with R. D. Hook'way, TES, and K. D. Desai, USNRC
~
- NUREG/CR-2136, May 1981.
" Independent Design Reviews - QA or not' QA,'" ANS 1983 Annual Meeting
- Detroit, Michigan. /
" Progress Report, Technical Committee on Piping Systems PVRC,". Post SMIRT, Seminar - Chicago, Illinois, August 1983.,
" Nuclear Piping Requirements, Background and Implementation,"'1983 French Pressure Vessel and Piping Conference - Paris, October.1983.
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Y g JAMES A. FLAHERTY Manager, Engineering Design and Testing Professional Resume Education Northeastern University, B.S. in Civil Engineering, 1964 Tuf ts University, M.Sc. in Civil Engineering,1966 Experience Teledyne Engineering Services and Teledyne Materials Research, since 1968: Engineering manager responsible for all work performed by Engineering Design and Testing Group. Responsibilities include project review, technical guidance, manpower assignment, cost and schedule review and construction management. Direct responsibility for modification programs for five BWR operating nuclear power plant components and their supports including construction management, material procurement, design, f abrication, examination and testing requirements. Provide consulting services in the area of pressure vessles, piping, valves and component supports.with the particular emphasis on stress analysis and the applicability of the ASME Boiler Code and Pressure Vessel Codes. Lecturer at Teledyne Engineering Services sponsored seminars for the nuclear power industry primarily involving plant / component modifications and construction management. Project Manager of LaSalle 1 Independent Verification Program. Member of Diablo Canyon 1 Construction QA review committee. United States Army, Lexington-Blue Grass Army Depot (Kentucky), 1st Lieutenant, Corps of Engineers, 1966 to 1968: project officer in the Directorate for Data Systems; program er and system analyst for accounting l and logistic system support groups. AVC0 Corporation, Missile Systems Division, Associate Engineer, Sumer 1966: structural analysis of reentry vehicles and related components involving static and dynamic loadings. . l Tufts University, Graduate Teaching Assistant in Computer Center, academic l years 1964-65,1965-66: fomulating, solving, and grading problems for senior / graduate course in numerical methods and computers. ! Linethal-Becker-Eisenberg, Sumer 1965: analysis and design of structural components. , (over) l
~
s Membership American Society of Civil Engir.eers Welding Research Council: Pressure Vessel Research Committee j Registered Professional Engineer in Massachusetts Authorship "An Assessment of the Effect of Plate Flexibility on the Design of Moment-Resistant Baseplates," with L. J. Diluna, presented at the Pressure Vessels and Piping Conference, San Francisco, California, June, 1979.
"The Field Installation of Concrete Anchorage Systems," with L. J. Diluna, presented at the ASCE Committee on Construction of Nuclear Facilities Conference, Pennsylvania State University, September,1981.
"A Method for Digitizing, Preparing and Using Library Tapes of Ship Stress and Environment Data," with Aldie E. Johnson, Jr., and Isaac J. Walters, Ship Structure Committee Report SSC-236, 1973.
" Computer Programs for the Digitizing and Using of Library Tapes of Ship Stress and Environment," with Aldie E. Johnson, Jr., and Isaac J. Walters, Ship Structure Committee Report SSC-237, 1973. s 0
1 ( k -t b
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Y DR. WILLIAM E. COOPER 6 $@{\/ ICES Consulting Engineer Professional Resume Education Oregon State College, B.S. 1947 and M.S. 1948, both in Mechanical Engineering Purdue University, Ph.D. in Engineering Mechanics,1951 Distinguished Engineering Alumnus Award, 1973 Experience Teledyne Engineering Services, Teledyne Materials Research, and lessells and Associates, Inc., since 1963: stress analysis; materials engineering; consulting on design criteria, pressure vessel design and on nuclear power system construction, operation, licensing and regulatory consulting. Formerly Senior Vice President and Technical Director. Project Manager Diablo Canyon 1 Independent Verification Program. General Electric Company, Knolls Atomic Power Laboratory, Engineer-Mechanical Analysis, 1952 to 1954: Consulting Enginecr-Structural Evaluation, SAR Reactor Engineering,1955 to 1959; Manager-S5G Structural Evaluation, 1959 to 1963. Purdue University, Instructor in Engineering Mechanics, 1948 to 1952. Consultant to Advisory Comittee on Reactor Safeguards (1967-1974) and to the Electric Power Research Institute (1974-1978). Membership American Society of Mechanical Engineers: Fellow, 1972; Council Chainnan (1981-1984) and Vice President (1980-1981) for Codes and Standards; Council (1981) or Policy Board
- Codes and Standards (1972-1981); Nuclear Codes and Standards Committee (1974-1980) (Chairman 1975-1977);
Boiler and Pressure Vessel Committee - Honorary Member (1980-); Executive Comittee (1971-1975); Main Committee (1965-1980); SC on Nuclear Certification (1973-1977) (Chaiman 1973-1975); SC on Nuclear Power (1964-1980) (Vice Chairman 1966-1969); SC on Design (1967-1975) (Chainnan 1967-1972); Special Committee to Review Code Stress Basis (1955-1967). American National Standards Institute: Board of Directors -(1981-) Nuclear Standards Management Board (1975-1977) Nuclear Technical Advisory Group for ISO /TC 85 (1974-1979)
.U.S. Representative to TC/85 SC/3 Nuclear Power (1976-1979)
Society for Experimental Stress Analysis (W.M. Murray Lecturer, 1977) Registered Professional Engineer in Indiana, New York and Massachusetts (over) l
s Partial Listing of Publications and Presentations
" Determination of Principal Plastic Strains," Transactions, ASME, July 1952.
"The Significance of the Tensile Test to Pressure Vessel Design," Welding Journal Research Supplement, January 1957.
" Structural Design Basis for Reactor Pressure Vessels and Associated Camponents," U.S. Office of Technical Services PB151987, with B.F. Langer (Westinghouse) and J.L. Mershon (BuShips), December 1958.
" Design Criteria for High-Pressure, High-Temperature Bolting," Nuclear Engineering and Design, 8, with R. Widmer, J. A. Signorelli, R.F. Brodrick, 1968, p.125.
" Interaction of Material and Design Problems in Critical Vessels," Invited Keynote Lecture, First International Conference on Pressure Vessel Technology, Delft, Proceedings, Part III, 1969, p.29.
" Construction, Rating, and Inservice Inspection of Test Tanks,"
Proceedings, 7th U.S. Navy Symposium of Military Oceanography, Vol.1, with B.H. Schofield, 1970, p. 104.
" Codes: Asset or Liability," Fatigue at Elevated Temperature, ASTM STP 520, 1972.
" Development and Operation of the ASME Boiler and Pressure Vessel Code,"
and "An Introduction to the Design Procedures of the ASME Boiler and Pressure Vessel Code," U.S.-Japan Joint Symposium, Pressure Vessel Technology and Pressure Component Codes, Tokyo, 1973.
" Nuclear Vessels are Safe," Mechanical Engineering, with B.F. Langer, April 1975.
" Improving Reactor Pressure Vessel Availability by Design," Nuclear Safety, 17(1), January-February 1976.
" Experimental Mechanics and Nuclear Power", The William R. Murray Lecture, 1977, Experimental Mechanics, 17, 10, October 1977.
" Minimization of Safety and Reliability Concerns by Consideration of Operating Experience," Conference on the Quality of Nuclear Power Stations from American and German Viewpoints, Koln,1978.
" Analysis of Inservice Inspection Flaw Indications," Maintenance Welding in Nuclear Power Plants, American Welding Society,1979.
" Concepts,in the Design and Analysis of Welded Joints," AWS, Indianapolis, 1980.
i "The Development of Codes and Standards for Superconducting Magnet 4 Structures," DOE-NBS Workshop on Materials at Low Temperatures, Vail, 1980. l "0wner Certification," Atomic Industrial Forum Workshop on Reactor Construction and Operation in the New Environment, Atlanta,1980. l
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Y g RONALD WRAY Manager, Engineering Analysis Professional Resume Education Northeastern University, B.S. in Civil Engineering, 1956 Rensselaer Polytechnic Institute, M.S. in Engineering Science,1962 Experience Teledyne Engineering Services, and Teledyne Materials Research, since 1971: theoretical stress analysis of pressure vessels, piping systems and frame structures utilizing computer program solutions and finite element methods; performed and directed static and dynamic analyses of Nuclear and LNG Piping Systems; conducted design reviews of Nuclear Piping Systems. Assistant Project Manager for the Independent Verification Program at Diablo Canyon 1. Instructor at Franklin Institute of Boston, Evening Division. AVC0 Systems Division, 1962 to 1971: performed detailed stress and buckling analysis of various reentry vehicle shell structures under combined reentry pressure and inertia loads and heating. Designed and analyzed large vacuum and pressurized chambers for a portable sterilization / clean room f acility built for NASA / Langley; responsible for the structural design and evaluation of space power systems and planetary probe systems. Pratt and Whitney Aircraft, Canal Division, 1958 to 1962: performed and directed detailed analyses and design evaluation of nuclear reactor core components and pressure vessels; conducted thermo-structural analysis of system piping and heat exchangers involving liquid metal coolants under transients; conditions of high temperature operation and severe established design criteria for components exposed to long-life, high-temperature conditions. U.S. Army Corps of Engineers, 1st Lieutenant, 1956 to 1958: served as project officer on military construction sites; field experience in reinforced concrete and steel erection. Membership American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Chainnan, Special Working Group on Dynamic Analysis. 10/83
( Y MM FRANK B. STILLE Manager, Projects Professional Resume Education Syracuse University, B.S. in Civil Engineering, 1957 Syracuse University, M.S. in Civil Engineering, 1961, College of Engineering, Civil Engineering Department Experience Teledyne Engineering Services and Teledyne Materials Research,1974 to present: Project management of efforts on nuclear power plants including plant modification design. Certified stress reports for Nuclear power plant components and performance of flexibility and seismic response analyses of Nuclear power plant piping systems covered by Section III of the ASME Boiler and Pressure Vessel Code. Perfonnance of elastic non-linear dynamic response analysis of Nuclear power plant piping systems subjected to postulated pipe rupture transient loading. Review of design specifications, design manuals and design analyses for a Heavy Water Nuclear research reactor. Analysis and certification of pressure vessels subjected to Section VIII, Divisions 1 and 2 of the ASME Boiler and Pressure Vessel Code. Member of Internal Review Comittee of Shoreham Independent Verification Program. American Science and Engineering, Senior Mechanical Engineer,1968-1974: static and dynamic analyses, static and dynamic qualification testing of large space X-ray telescopes. AVC0 Missile Systems Division, Lead Engineer, 1962-1968: stress analyses of re-entry vehicles, re-entry vrthicle recovery systems, and re-entry vehicle penetration aids system. Boeing Company, Research Engineer A, 1957-1960: stress analyses of supersonic airframe structures subjected to aerodynamic heating and maneuver loads. Membership Registered Professional Engineer in Massachusetts American Society of Mechanical Engineers AJthorship "A Proposal of the Town of Reading (Mass.) Board of Public Works by the Sturges Road Citizens Committee on the Sturges Tract Storm Sewer System," 1965. The publication consisted of a complete study of the Sturges Tract watershed including a stonn sewer system design and analyses by the author. 10/83
/ TM ENG2EERNG SERVICES JAMES J. BALASCHAK Senior Engineer Professional Resume Education University of Pittsburgh, B.S. in Civil Engineering, 1975 University of. Tulsa, Master of Business Administration,1981 Experience Teledyne Engineering Services,1982 to present: Senior Engineer responsible for design and analysis for the Control Rod Drive Hydraulic System of the Limerick Generating Station, Unit 2. C.E. Natco, Division of Combustion Engineering, 1977-1982: Responsibilities included stress analysis, structural and civil design used in the construction of oil and gas processing plants and equipment. Performed stress analysis and design of pressure vessels according to the ASME Boiler and Pressure Vessel Code, Section VIII; piping to the ANSI B31 code; foundations to the ACI code; and structural design to the AISC and API specifications. Used and developed computer programs to perform design work in FORTRAN and BASIC languages. Lee C. Moore Corporation, 1975-1977: Prepared design drawings, stress analysis and specifications; supervised drafters; and inspected structures during erection. Designs consisted of drilling masts, derricks, and substructures. Membership Registered Professional Engineer, States of California, Pennsylvania and and Oklahoma Associate Member, American Society of Civil Engineers 10/83
/ WTELED(hE NICHOLAS S. CELIA MCES Manager, Engineering Projects Professional Resume Education Northeastern University, B.S. in Mechanical Engineering,1960, Magna Cum Laude University of Southern California, M.S. in Mechanical Engineering,1967, Magna Cum Laude Experience Teledyne Engineering Services, 1974 to Present; Engineering manager responsible for all work performed by the Engineering Projects Group. Responsibilities include project review, technical guidance, manpower assignment, ar.d cost and schedule review. Responsible for design analysis and field survey work for nuclear and LNG projects. Projects include piping, piping supports, and structures. Project Manager for the BWR Mark I Torus Modification Program. Responsible for overall technical direction, costs, schedules, modifications and construction management and manpower requirements for five (5) nuclear pl ants. Member of Internal Review Comittee of Independent Verification Programs. Independent Consultant,1972 to 1974; Conducted analysis of loads and stresses in structures from static, dynamic and acoustic environments. i Special problems encountered include pipe rupture and impact analysis, nonlinear dynamic response and acoustically-induced pipe stesses due to sonic flow through large valves. Stresses were evaluated and reported using criteria of B31.1 and Section III of the ASME Code. Itek Corporation,1967 to 1972; Senior Engineer, responsible for dynamic and structural analysis of systems subjected to shock, vibration and acoustic enviornments. Design and analysis of shock and vibration isolation systems. Extensive experience in seismic and acoustic testing, including specification and fixture design. Convair, Douglas and North American Aviation,1960 to 1967: Dynamic analysis and test, project review and interf ace and ground support facilities and equipment design for Apollo, Saturn, MOL, and Atlas projects. . Membership Registered Professional Engineer - Comonwealth of Massachusetts Phi Tau Sigma Tau Beta Phi 10/83
I 1 Y ENGNEERNG SERVICES DONALD MESSINGER Quality Assurance and Inspection Supervisor Professional Resume Education American Society of Nondestructive Testing training courses: Certif-icates in RT--1957, PT--1958 and MT--1959 Bethlehem Steel Corp., training courses in RT and MT to meet NAVSHIPS 250-1500, 1960 General Dynamics Corp., training courses in MT and PT to meet NAVSHIPS 250-637-1 and MIL STD 2710, 1966 J.J. Devine Company, Ultrasonic School - Level I SNT-TC-1A, 1974 Ultrasonic Test Engineers, MT and PT School - Level II-SNT-TC-1A, 1975 J.G. Sylvester Assoc., Inc., MT and PT School - Level III, SNT-TC-1A, 1978 American Welding Society - Fundamentals of Welding Inspection, 1980 Hartford Steam Boiler I and I, Inc. - Recertification PT Level III,1981 Baker Testing Services, Inc. - RT Interpretation, Level II,1982 Hartford Steam Boiler I and I, Inc. - Radiography Level II, 1982 Tech OPS - Radiation Safety Protection, 1983 Experience Teledyne Engineerinq Services,1978 to present: Quality Assurance Supervisor, responsible fur QA indoctrination and training of all personnel; supervising daily operations with respect to the imple-mentation of TES QA Program on Nuclear projects; participation in, internal, field and vendor audits; certified lead auditor per ANSI N45.2.23; certified Level III in Magnetic Particle and Liquid Penetrant examination; certified Level II in Radiographic Interpretation. Project Quality Assurance Engineer for Susquehanna Independent Verification Program. Lytron, Inc., 1976-1978: Makers of heat exchangers. Quality Assurance Manager - responsible for Q. A. Program to meet 10CFR50 Appendix B, ASME III and VIII, ANSI N45.2 and military requirements. Certified Level III in Liquid Penei. rant. (over)
h Experience (Continued) The Thompson Lichtner Co., Inc., 1973-1976: Chief Inspector of structural steel, decking and precast. Responsible for inspection of fabrication, erection, welding, bolting and NDE practices in con-struction of schools, hospitals, banks, insurance companies, bridges. Ultrasonic Test Engineers, 1973-1977: Consultant-Instructor / Trainer for magnetic particle and liquid penetrant applications. Level II certified in MT and PT. General Dynamics Corporation, Shipbuilding Division, 1964-1973: Quality Control working Leader / Instructor. Inspection of completed subassemblies prior to erection. Instructor for magnetic particle and < liquid penetrant. Bethlehem Steel Corp., Shipbuilding Division, 1955-1963: Radiographer 1/C - crew leader responsible for X-ray of pipe, castings and structural steel and MT and PT inspections to meet commercial, military and nuclear codes. Film interpreter and dark room responsibilities. Membership American Society for Nondestructive Testing i 10/83 l l
/ l TE M EhKMNEERING SEfWICES JAMES C. TSAC0YEANES Consulting Engineer Professional Resume Education Boston University, B.S. in Aeronautical Engineering, 1959 Northeastern University, Graduate courses in Mechanical Engineering Experience Teledyne Engineering Services, Teledyne Materials Research, and Lessells and Associates, Inc., since 1960: design and analysis of mechanical equipment, pressure vessels and piping; application of finite element computer techniques for structural heat transfer and stress analysis; design and evaluation of liquid metal fast breeder reactor components; preparation of ASME Code Design Reports for nuclear reactor system valve and vessel components; fracture mechanics evaluation of flaws to Code non-ductile failure protection criteria; consulting on component design and criteria; lecturer for TES Seminar Series on Class 1 Design of LWR Nuclear Components and Elevated Temperature Components. Responsible for mechanical components on LaSalle 1, Susquehanna 1, Shoreham and Diablo Canyon 1 Independent Verification programs. Curtiss-Wright Corporation, Propeller Division, Experimental Testing Laboratory, 1959-1960: mechanical and electrical testing of propeller controls. Membership American Society of Mechanical Engineers, Member ASME Boiler and Pressure Vessel Committee Working Group on Valves (SG-D SC III) Safety Code Committee on Nuclear Inspectors and Specialized Professional Engineers Task Group on Qualifications and Duties of Specialized Professional Engineers, Chairman Registered Professional Engineer in Massachusetts Authorship ,
" Valve Failures Which Impact the Safety and Operation of Light Water Nuclear Power Plants," with P. P. Raju, ANS Thermal Reactor Safety Meeting, April 7-11, 1980.
10/83
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'MTELEINNE ENGNEERING SERVICES
$ RUDOLF R. B0ENTGEN Manager, Testing Professional Resume
)
Educatio_n_ Polytechnic Institute of Brooklyn, B.S. in Applied Mechanics, 1963 (now Polytechnic Institute of New York)
) Northeastern University, M.S. in Mechanical Engineering,1970 Northeastern University, Master of Business Administration,1974 ,
Experience
> Teledyne Engineering Services, and Teledyne Materials Research, since 1973:
Review and evaluation of mechanical equipment, design and qualification of instrumentation and control systems and components. Experimental analyses of large ship structures and machinery, experimental modal analysis, investigations and testing of aircraft power plants, vibrations, safety and hazard evaluation of machines, structures and mechanisms, product evaluation i of component and machine designs, design of test equipment, instrumentation, and materials properties determinations, Member of review team for Diablo Canyon 1 I&C Systems Independent Verification Program. Avco Corporation, Systems Division, Staff Engineer, Applied Mechanics,1966-1973: design and evaluation of structural, mechanical, fluid and chemical elements of various aerospace vehicles and other mechanisms and structures. , U.S. Amy, Corps of Engineers, Lieutenant, 1964-1966: planning and direction of heavy construction projects, development of passive and active denial systems, management of equipment fleets. Avco Corporation, Research and Advanced Development Division, Associate Engineer, Structures Laboratory, 1963-1964: test planning and design of fixturing and mechanisms for structural testing of composite shell structures. Membership , Society for Experimental Stress Analysis, Past Chairman Society of Automative Engineers, Member Registered Professional Engineer in Massachusetts (over)
( Authorship
" Instrumentation--The Only Way," with John Boylston and James W. Wheaton for the SNAME/SSC Symposium, 1975.
(
" Static Structural Calibration of Ship Response Instrumentation System Aboard the SEA-LAND McLEAN," with J. W. Wheaton, SSC-263 (SL-7-7) for the Ship Structure Committee. . . .
"First Season Results from Ship Response Instrumentation Aboard the SL-7 Class Containership S.S. SEA-LAND McLEAN in North Atlantic Service," with (
R. A. Fain and J.W. Wheaton, SSC-264 (SL-7-8) for the Ship Structure Comittee.
" Strength of Concrete Expansion Anchors for Pipe Supports," with R.D. Ciatto, PVP-40, 1980.
" Developments in Testing and Design of Concrete Expansion Anchor Bolts," (
ASME, 1981.
" Experimental Modal Analysis," for ASCE Specialty Conference, May 1983, with S. Clickner.
t l I 10/83 l l l 1 l l l
"RTF1 FTVNE ENGINEERING SERVICES LOUIS J. DILUNA Manager, Design Professional Resume Education Cornell University, B.S. Civil and Environmental Engineering,1974 Northeastern University, M.S. Civil Engineering,1979 Experience Teledyne Engineering Services, and Teledyne Materials Research, July 1974-present: Design and field verification of steel structures and pressure components. Theoretical stress analysis, analysis of nuclear power components per ASME Code Section III. Design and analysis of component supports and modifications to Mark I BWR containment systems. Study of the behavior of pipe supports using concrete expansion anchors. Elastic and inelastic analysis, using state-of-the-art programs and methods, of a full-size elevated temperature piping system, as well as smaller verification models, for a LMFBR plant. Directed projects in response to NRC I&E Bulletins 79-02 and 79-14 including field walkdowns, analysis l and modifications.
Membership ! American Society of Civil Engineers Registered Professional Engineer, State of Massachusetts Authorship "An Assessment of the Effect of Plate Flexibility on the Design of Moment-Resistant Baseplates," with J. A. Flaherty, presented at the Pressure Vessels and Piping Conference, San Francisco, California, June, 1979.
"The Field Installation of Concrete Anchorage Systems," with J. A. Flaherty, presented at the ASCE Committee on Construction of Nuclear Facilities Conference, Septenber,1981.
" Inelastic Analysis of SNR-300 Piping," with H. Huebel and G. Moy, Pressure Vessel and Piping Conference, Orlando, Florida, June,1982.
10/83 1
TE M ENGNEERING SERVICES JAMES W. WHEATON Consulting Engineer Professional Resume Education Dartmouth College, A.B.1953; Thayer School of Engineering (Dartmouth), M.S. in Electrical Engineering,1957 Registered Professional Engineer Experience 1981 - Consulting engineer in private practice. Teledyne Engineering Services, 1964-1981: Project Engineer, Senior Engineer, Manager--Client Services, Manager--Instrumentation Services; supervised 15 engineers and technicians ~. Team Leader in design review and drawing revisions for modifications to electrical and I&C systems at Nine Mile Point (Niagara Mohawk); Design, installation, and reduction of data from nuclear power and shipboard stress-measurement systems; Physical testing on in-house MTS and Instron machines; Client liaison, project management, preparation of proposals, reports, sales literature. Applied Systems Corporation, Palo Alto, California, 1961-1964: Systems engineering on aerospace projects; marketing, sales of industrial infrared temperature sensors. Anaconda Wire and Cable Company, Hastings-on-Hudson, New York, 1957-1964: Engineering department, consulting to sales department on applications of high voltage power cables in the electric power industry; special studies of high-voltage p'lastic and film-gar experimental cables. A (over)
Authorship (Partial listing)
" Full-Scale and Model Tests of a Great Lakes Icebreaker," with R. Y. Edwards, et al. Transactions of SNAME, Vol. 80, 1972.
" Instrumentation--The Only Way," with R. R. Boentgen and J. W. Boylston.
Presented at the Ship Structure Symposium in Washington, D.C., October 1975.
" Playing Catch-Up with the Computer," The Year 1978-79, Thayer School of ,
Engineering, Hanover, New Hampshire.
" Image Analysis: Applications of New Software for Operator-Dataoase Interaction," American Laboratory, September 1981.
3 10/83
= . TE M ENGNEERING SERVICES RAYMOND M. PACE Manager, Projects Professional Resume Education Northeastern University , B.S. in Mechanical Engineering, 1973 Certified American Red Cross Cardiopulmonary Resuscitation Instructor, 1981 Experience Teledyne Engineering Services, and Teledyne Materials Research,1972 . _ to present: stress analysis of pressure vessel components including - elevated temperature and fracture mechanics analyses using finite - element techniques and requiring knowledge of the ANSYS computer code. ASME Boiler and Pressure Vessel Code verification and review of nuclear cmponent and piping system design analyses. Evaluation and field engineering associated with new and existing 7 nuclear piping systems under static and dynamic loading conditions, - - including postulated high energy pipe break and relief valve blowdown for hanger and support locations using finite element techniques requiring knowledge of the STARDYNE and ADLPIPE computer codes. Responsible for cryogenic design, analysis and field engineering y including ANSI B31.3 piping systems and AISC structural modifications c associated with LNG facilities and LNG storage tanks. Design review M, ,-'~ . of cryogenic (LNG) piping systems, components and structural support designs to ANSI B31.3 and The Uniform Building Code. f).;$C
;j*?
y . *: .y Lead Plant Engineer BWR Mark I Torus requalification program. Assisted g (" in the development and direction of generic and plant unique analyses and evaluation techniques for the torus structure and associated f9 2 .i components. Responsible for coordinating and scheduling analyses and ff;A p .A S.- outage related modifications with the client. .; J ' . i W". , ' ' < Member of the verification team of LaSalle 1 Independent Verification - TM Program. Member of the TES Internal Review Committee of Shoreham Independent Verification Program.
%3l pi.1 ,,
Membership N,F Y h Registered Professional Engineer - Commonwealth of Massachusetts [$ #[
,.t..
.c n .,
f$ lh.: m _ 10/83 S~- _ f] - <. ,
s "RTF1 FTY(NE ENGINEERING SERVICES RICHARD A. ENOS Manager, Projects Professional Resume Education Lowell Technological Institute, B.S. in Civil Engineering, 1974 University of Lowell, M.S. in Civil Engineering,1981 Experience Teledyne Engineering Services and Teledyne Materials Research, June 1974 to present: Concrete structure design and f ailure analysis. Design analysis and modifications to Mark I BWR containment systems. Structural task leader responsible for directing the quantity and quality of work performed, as well as interf acing with the client. Static and seismic analysis of FFTF vessels for storing liquid sodium; theoretical stress analysis of pressure vessel components; flexibility analysis of nuclear piping systems and components per ASME Code Section III. Application of beam and finite element techniques utilizing STARDYNE, TMRSAP, ANSYS, 80RSOR-4, and FLUSH computer program solutions. Transient / dynamic force-time history' analysis using modal analysis techniques. Assistant Project Manager Susquehanna 1 Independent Verification Program. Member of verification team of LaSalle 1 Independent Verification Program. Responsible for structures on Diablo Canyon 1 Verification Program. Membership Society for Experimental Stress Analysis, New England Section Registered Professional Engineer, State of Massachusetts 10/83
Y J0riN Q. CRAGIN 6M Manager, Project Administration Professional Resume Education Northeastern University, M.S. in Engineering Management, 1966 Trinity College, advanced engineering courses,1960 St. Louis University, B.S. in Aeronautical Engineering, 1958 H. H. Ellis Technical School, Connecticut Airframe and Power Plant Mechanics Course, 1955 Experience Teledyne Engineering Services, Teledyne Materials Research, and Lessells and Associates, Inc., since 1962: Review, audit and design of nuclear power plant components and systems. Project administration and management. European sales and project management from London, 1974-1976. Pretrial investigations and expert witness testimony regarding aircraft / helicopter accidents. Manager, Project Administration of Diablo Canyon 1 Independent Verification Program. United Technology Corporation, Research Laboratories, 1958-1962: wind tunnel testing, design and calibration of force transducers, instrumentation systems development. M_embership Experimental Aircraft Association, Member since 1953, Designee Inspector since 1971 American Nuclear Society, Member Instrument Society of America, Senior Member Registered Professional Engineer in Massachusetts Authorship
" Application of Post-Yield Strain Gages to Nylon Tape," Society for Experimental Stress Analysis Paper No. 866, 1963 Annual Meeting.
" Ship Response Instrumentation Aboard the Container Vessel SS BOSTON:
Results from Two Operational Seasons in North Atlantic Service," Ship Structure Committee Report SS-214, 1970.
" Ship Response Instrumentation Aboard the Container Vessel SS BOSTON:
Results from the First Operational Season in North Atlantic Service," with R. A. Fain and B.H. Schofield, Ship Structure Comittee Report SSC-212,1970. 10/83
WM ENGNEERNG SEBCES CORNELIS G. SPRANGERS Manager, Quality Assurance Professional Resume Education The Hague, The Netherlands, A.B., Industrial Relations,1957 Experience Teledyne Engineering Services, and Teledyne Materials Research, since 1972: Quality Assurance Manager: preparation of TES QA Manual, . responsible for all QA/QC activities at TES, designed and implemented TES Document Control procedure, certified as an ANSI N45.2.23 lead auditor; Engineering Computations Supervisor: responsible for Quality Assurance audits on Diablo Canyon Independent Verification Program. Smithsonian Astrophysica10bservatory, Section Manager, Upper Atmospheric Studies, 1962-1971. Mutual Administration Office, The Hague, Group Supervisor, Evaluation of legal cases relative to the Social Laws and its jurisprudence, 1953-1960. l l l l 10/83 ,
'RTF1 FTWNE ENGINEERING SERVICES CYRUS H. KAN0 Principal Engineer Professional Resume Education Massachusetts Institute of Technology, S.B. and S.M. in Mechanical Engineering, 1943 Experience Teledyne Engineering Services, Teledyne Materials Research, and Lessells and Associates, Inc., since 1949: theoretical and experimental stress analysis, internal combustion engine theory, materials engineering, applied electronic instrumentation, vibration analysis, physical testing,' high-energy deformation studies, reconstruction / expert witness.
and accident Massachusetts Institute of Technology, Instructor: Department of Aeronautical Engineering, 1943-1949. Membership Society for Experimental Stress Analysis, Member, Chairman (1981-82) of Local Section Society of Automotive Engineers, Member Registered Professional Engineer in Massachusetts Authorship
" Spring Innovations," Machine Design, May 10, 1962
" Influence of Geometrical Design Factors on the Bending Fatigue Strength of Crankshafts," American Society of Mechanical Engineers, Journal of Engineering for Power, July 1963.
" Analysis of Slanning Data from the SS WOLVERINE STATE," with J.W.
Wheaton, P.T. Diamant, and F.C. Bailey, Ship Structure Committee Report SSC-210, 1970. 4/82
W TA m(NE ENGNEERING SERVICES ROBERT D. F0TI Manager, Projects Professional Resume Education Tufts University, B.S. in Mechanical Engineering, 1972 Experience Teledyne Engineering Services, and Teledyne Materials Research, 1972 to present: static and seismic analysis of nuclear power piping systems and related components. Force-time history analysis utilizing finite-element techniques with large-scale structural analysis digital computer programs. Performed audits of anaiytical procedures used in determining piping support systems. Performed calculations and established procedures for the layout and support placement for small piping to satisfy NB-3652 and NC-3652 of Section III of the ASME-BPVC. Established thermal flexibility modes of operation of various power piping systems. Audited restraint designs and installations for nuclear power piping. Performed independent design reviews on piping analyses for various nuclear utilities. Working knowledge of ANSI B31.1, NB-3652, and NC-3650 Piping Codes of Section III of the ASME-BPVC. Army Materials and Mechanics Research Center, Theoretical and Applied Mechanics Section, Consultant, 1972: experimental stress analysis of composite materials using moire techniques. Membersjhg Registered Professional Engineer - Commonwealth of Massachusetts 11/82
'W TF1 m(NE ENGdNEERING SOMCES ERIC A. SOLLA Project Engineer Professional Resume Education Rensselaer Polytechnic Institute, M.S. in Civil Engineering, 1977 Rensselaer Polytechnic Institute, B.S. in Civil Engineering, 1976 Experience Teledyne Engineering Services, 1979 to present: Project Engineer involved in independent design reviews for nuclear power utilities, responsible for field verification of as-built documentation, and review of structural analysis. Engineering application programming in FORTRAN. Stress analysis !
of piping systems and piping support systems including seismic analysis using criteria of ASME Section III using STARDYNE and TMRSAP. Analysis of restraints for piping in nuclear power plants relating to NRC IE Bulletins 79-02 and 79-14. Field inspection and design of modifications for pipe restraints using latest AISC specifications. Field inspection of electrical equipment for IE Information Notice 80-21. American Electric Power Service Corporation, 1977-1979: Analysis and design of concrete walls and slabs, footings, pile foundations, sheet pile retaining walls and cofferdams. Stability analysis of a hydroelectric plant relative to ACI standards. Membership Registered Professional Engineer in Massachusetts 5/83 e
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'RTELEDYNE ENGINEERING SERVICES LYNWOOD V. PREST Senior Engineer Professional Resume Education Lincoln Institute, Associates in Civil Engineering, 1962 Northeastern University, B.S. in Civil Engineering, 1966 University of California, Berkely, M.S. in Civil Engineering, 1969 Experience Teledyne Engineering Services, June 1982 to present: project management
- verify analyses done on the Mark I Pressure Suppression System.
Sea Plantations Environmental Services, Ltd., 1979 to 1982: Manager of Engineering. Conduct limited marketing, supervise client relationships, conduct feasibility studies, prepare cost estimates, develop and coordinate construction documents, retain consultants, obtain public agency approvals, process bidding and contractor selection and administrate the contract during construction. Projects dealt with various types of industrial, pre-treatment systems and building additions. Frank E. Gallagher Engineering, Inc.,1976 to 1979: Project Manager. Efforts directed to narketing, maintaining client relationships, project super-vision, structural engineering, conducting feasibility studies, estimating costs, developing construction documents (including specifications) and conducting field inspections. Yankee Atomic Electric Company, 1974 to 1976: Review all structural engi-neering by A. & E. consultants and to lead on all in-house structural engineering work on nuclear plants. Various consulting firms as a civil / structural engineer since 1957. Registrations
#4539 - Nat'l Eng. Council Cert. C.E. #3228 - State of Vermont C.E. #18896 - State of California C.E. #3428 - State of Maine C.E. #23133 - Commonwealth of Massachusetts C.E. #57335 - State of New York C.E. #3280 - State of New Hampshire C.E. #E-20398 - State of Wisconsin Memberships American Society of Civil Engineers Boston Society of Civil Engineers 6/82
Y S E gi Professional Resume Education Wayne State University, BSME,1968 Krautkramer-Branson, Inc., Ultrasonics School, Level I and Level II training in nondestructive material examination,1976. Nondestructive Testing Engineering Division, The Hartford Steam Boiler Inspection and Insurance Company School, level I and Level II training in nondestructive material examination using magnetic particle and liquid penetrant techniques, 1977. Experience Teledyne Engineering Services, and Teledyne Materials Research, Waltham, Massachusetts,1974 to present: Experienced in structural analysis, design, modification, field walkdowns and experimental analyses. Project experience includes piping, piping supports and general structural problems for nuclear power plants. Responsible for all aspects of project perfomance including client interf ace, personnel, quality assurance, procurement, cost control, and technical performance. Stress analysis of piping systems and piping support systems using criteria of ANSI B31.1 l and ASME B&PV, Section III, B31.1 and AISC Codes. Certified Level I l ultrasonic inspection of material and welds to Code requirements. Related project experience involving modifications of pipe supports and structures at the following nuclear plants: Diablo Canyon, Prairie Island, Nine Mile Point, Fitzpatrick and Millstone. Kelsey-Hayes Company, S.P.E.C.C. Aerospace Division, Springfield, Ohio, 1968-1974: Project Engineer, 1970-1974, responsible for the proposal, design, manuf acturing, and testing of the flap and slat system for the Rockwell International, Los Angeles, California, B-1 bomber. 1971-1974, responsible for system consulting, proposal, design, manuf acturing, and testing of the conversion system and flap system for the Bell Helicopter Company, Fort Worth, Texas, Model 301 Tilt Rotor Aircraft (NASA XV-15). Design Engineer, 1968-1970, responsible for design of aircraft and industrial mechanical-hydraulic controls systems. Kelsey-Hayes Company, Wheel, Hub and Drum Division, Romulus, Michigan, 1966-1968: Brake and hydraulic skid control research and testing. Membership Registered Professional Engineer in Massachusetts 10/83
f I WTF1 prVNE ENGNEERNG SERVICES MICHAEL F. MORAN Project Engineer Professional Resume Education Wentworth Institute, Associate Building Construction, 1971 University of Lowell (Evening Division), B.S. in Civil Engineering, 1979 Experience Teledyne Engineering Services, 1980 to present: stress analysis of Nuclear Safety Related Piping Systems using TMRPIPE and ASME BPVC Section III Code. Stress analysis of pipe supports and multifunction support structures l including dynamic response using STRUPAK, CENSAP, STAAD-III, and STARDYNE ; computer codes and ASME Subsection NF, AISC and AISI design codes. Also l developed specialty post processors for STARDYNE. Design review and site inspection of a space frame which collapsed. Represented TES at client home office as technical interf ace. Performed field walkdowns of numerous code class piping systems and assisted in the resolution of discrepancies at the construction sites. Lead Field Engineer at Limerick Nuclear Station for CRD systems and supports including Unistrut applications. G. F. Moran Construction, 1974-1980: supervised and performed trork in residential and light commercial construction. Furnished designs, estimates, bids, and coordinated other subcontractors when necessary. U.S. Army, 1971-1974: Personnel Specialist, E5. Membership Engineer-in-Training, New Hampshire 6/83
WTELEDGE ENG3FERNG SERVICES JOHN W. HANSON Senior Engineer Professional Resume Education University of Houston, B.S. in Mechanical Engineering,1965 E_xperience Teledyne Engineering Services, since 1979: Field verification of nuclear plant piping and pipe support systems. Testing and verification of nuclear piping support baseplates. Responsible for evaluating and solving construction related problems on pipe supports at Prairie Island and Donald C. Cook Nuclear Stations. Fossil and nuclear plant modifications. Project Management activities related to BWR MKI torus attached piping and supports analyses and modifications. Houston Lighting and Power Company, 1965-1979: Principal engineer responsible for design and construction activities for the South Texas Project nuclear station. Duties included direct interf acing with the Architect Engineer and subcontractors to meet criteria and schedule. Engineering design review of 2-1250 MWe PWRs and 1-1150 MWe BWR including review / coordination of NSSS vendor and AE design efforts to ensure compliance with ASME Code, NRC Regulations and design criteria. Responsible for coordinating design review and construction activities of various engineering disciplines related to new fossil plant projects including 3-750 MWe and 2-565 MWe supercritical gas-fired units and 1-425 MWe gas / oil fired unit. Assistant Plant Superintendent at a fossil plant consisting of 1-220 MWe and 1-66 MWe gas-fired units. Responsible for pre-op testing and various startup activities for new fossil units. Manbership Registered Professional Engineer - State of Texas American Society of Mechanical Engineers 10/83
f ( TN Technical Proposal ENGNEERtlG SERVICES PR-6194 s i
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4 APPENDIX IV 3 PROCEDURES: EP-5-006 AND EP-1-021 4 d i i s -
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r' l ENGINEERING PROCEDURE EP-5-006 MfTHOD OF DETERMINATION OF AS-BUILT CONFIGURATION OF LOW PRESSURE CORE SPRAY SYSTEM AT NUCLEAR POWER STATION REVISION O PROJECT 5633 JUNE 2, 1982 Prepared by: WA h_ Date d"1dt Approved by: 'A* k Date hi $ 1
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Project Manager
/
Reviewed by: [ /2n 9de Date /f [4 QualitfAssura#nce 8 WTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 617-890-3350 _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . i
l "WTFI mVNE ENGINEERING SERVICES ENGINEERING PROCEDtJRE ITLE: EP 006 [ REV. Q _ REV. METHOD 0F DETERMINATION OF AS-BUILT ORIG.7_ M 1r24LORIG. CONFIGURATION OF LOW PRESSURE CORE SPRAY ENG. AS. /> Jump ENG. AS. SYSTEM AT NUCLEAR POWER STATION Q. A. C65 6AW/z Q.A. PROJ. MGR.WL - PROJ. MGR. L DATE 6/4fft DATE { 'I SECTION DESCRIPTION REV. 1.0 SCOPE This procedure describes the method to' be used in determining the "as-built" configuration of Low Pressure Core Spray System at Nuclear Power, Station. The purpose of this procedure is to obtain dimensional verification of portions of the LPCS system to provide the independent reviewers (TES) sufficient data to verify that, the design was properly implemented. 4 2.0 APPLICATION 2.1 References , a) Project QA Program, Project No. 5633. b) EP-1-017, "TES Project Plan for Independent Design' [ Review of Nuclear Power Station LPCS System. 2.2 Equipment For the equipment to be used in obtaining measurements , required by this procedure, no formal calibration is ' f. required. However, only undamaged measuring tapes, sc'!es, etc.. shall be used. 3.0 METHOD , 3.1 As-Built Data . 3.1.1 The Project Manager shall. obtain from S&W the as-huilt -data , l package, following inteiface definitions described in the, References Section 2.1. 'All documents received shall oe recorded on a document l i st', noting the revision and any applicable Engineering Change Notices (ECN's) or other records of changes in process. 3.1.2 A copy of the as-built isometric .outained from S&W will be i made (preferably traced)' by TES drafting excluding i all dimensions and support locations. Copies of.;the TES-isometric will then be used in the determination of as-built piping configuration. s [ $sunn- ,
"RTFI PTWNE ENGINEERING SERVICES :
ENGINEERING PROCEDURE TITLE: EP 006 2 REV. .O REV. METHOD OF DETERMINATION OF AS-BUILT ORIG. M$. (-1110 RIG. ENG. AS.a M as ENG. AS. CONFIGURATION OF LOW PRESSURE CORE SPRAY SYSTEM AT NUCLEAR POWER STATION Q. A. d Cs %AQ.A. PROJ. MGR.'hlN PROJ. MGR. DATE Lf4 F% DATE SECTION DESCRIPTION REV. 3.1.3 Copies of the support details supplied by S&W will be used to verify support as-built configuration. 3.2 Field "As-Built" System Verification 3.2.1 The Lead Engineer and other engineers performing the verification shall review the documents acquired under Section 3.1. The TES Project Manager shall review and approve the selection of personnel for the field verification. 3.2.2 A general walk-down of the system shall be performed to familiarize TES personnel with the location, general layout, accessibility, and quantity of piping and pipe supports. 3.2.3 The portion of the LPCS System outlined in Figure 1 of EP-1-017 shall be verified. As a minimum, the following shall be verified: a) Piping geometry
- 1) Type of fittings and location
- 2) location of valves and orientation
- 3) Length and orientation of pipe b) Supports
- 1) Location
- 2) Type and direction restrained
- 3) Spring sizes and settings
- 4) Snubber sizes and settings
- 5) Pin-to-pin length for snubbers and struts
- 6) Clearances
- 7) Support hardware - size of primary structural members, component standard part designations (part numbers), overall support configuration
__2181
"#TF1 FOYNE ENGINEERING SERVICES ENGINEERING PROCEDURE PAGE TITLE: EP 006 3 REV. _ . 0 REV.
METHOD OF DETERMINATION OF AS-BUILT ORIG. _QfK. L.2.fl0 RIG. CONFIGURATION OF LOW PRESSURE CORE SPRAY ENG. AS /MM ENG. AS. SYSTEM AT NUCLEAR POWER STATION Q. A. gr M ffgQ.A. PROJ. MlTR. PROJ. MGR. DATE 4(4l t 2. DATE SECTION DESCRIPTION REV. c) Location and nature of pipe attachments, such as lugs, stanchions, etc. d) location and nature of any interferences which may inhibit pipe motion e) Valves
- 1) Record nameplate data on valves and valve operators
- 2) Determine length between the centerline of the valve to the approximate centerline of the valve operator
- 3) Determine the orientation of the valve operator using the horizontal or vertical plane for reference f) Equipment mounting characteristics 3.2.4 Should some locations be inaccessible the Lead Engineer shall document this including reasons why and report this to the Project Manager.
3.2.5 Photographs shall be taken where deemed necessary by TES personnel, to augment the field review, particularly in case of inaccessibility. 3.2.6 A list of all personnel contacted in the field and the reason for the contact will be made. 3.2.7 A written record of all activities accomplished at the site will be made. 1 I 2/81
"RTF1 pnYNE ENGINEERING SERVICES ENGINEERING PROCEDURE TITLE: EP -S-006 N REV. ~ O REV.
METHOD 0F DETERMINATION OF AS-BUILT ORIG. 8 L-1.h 0 RIG. CONFIGURATION OF LOW PRESSURE CORE SPRAY ENG. AS. ////#4- ENG. XS. _ SYSTEM AT NUCLEAR POWER STATION Q A. <::GJ (/w/fg Q.A. PROJ. MGR. 'DFL PROJ. MGR. DATE elH tt DATE SECTION DESCRIPTION REV. 3.3 Documentation 3.3.1 Each dimension and system characteristic checked shcIl be signed by two of the TES personnel present. Upon return to the TES offices the original TES copy of the as-built piping documentation shall be marked up with all information contained on the record copy used in determining as-built configuration. TES personnel initials need not be included but all the members of the field team must sign the TES original isometric indicating that the transfer of information from the record copy to the tracing is correct. 3.3.2 All data sheets shall be initialed and dated by two of the TES personnel present. All data shall be recorded in ink. Any errors / changes shall be lined-out and initialed. 4.0 RECORDS. The originals of all recorded data, photographs and the tracing shall become project QA records. 2/81 ,
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ENGINEERING PROCEDURE EP-1-021 QA REVIEW SAMPLING PROCEDURE NUCLEAR POWER STATION INDEPENDENT DESIGN REVIEW FOR THE LPCS SYSTEM REVISION 1 PROJECT 5633 SEPTEMBER 9, 1982 Prepared by: h h n vid W Date f 9[ ' Approved by: 4 m. ,) Date 9-$1 Project Ma gF - [_ Reviewed by: -hr %> Date N
~,
Quality Assurance WTELEDYNE ENGINEERING SERVICES j 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 617-890-3350
"RTELEDYNE ENGINEERING SERVICES ENGINEERING PROCEDURE PAGE TITLE: EP 021 1 REV. O lREV. .I QA REVIEW SAMPLING PROCEDURE ORIG. JHM NUCLEAR POWER STATION ENG. AS. MAR ORIG.y Jir _ b.
ENG. 4 ...FL INDEPENDENT DESIGN REVIEW FOR THE LPCS SYSTEM Q.A. CGS Q.A. cas PROJ. MGR. JPK PROJ. MG DATE 6/18/82 DATE 8/9 DESCRIPTION REV. SECTION 1.0 SCOPE This procedure describes the sampling plan to be used for the TES QA review of SWEC construction activities for the LPCS ( System at the Nuclear Power Station. This procedure is provided solely to define the lot size and sample size and to assure random selection and review of the sample. The procedure is not intended to provide a statistical inspection sampling plan. 2.0 APPLICATION The sampling plan will be applied to the review of documentation and records for the following: a) training and qualification records of personnel b) identification and control of material, parts and components c) control of special processes d) nonconformance and dispositioning report process e) receiving inspection records f) material certification records g) NDE records
2.1 REFERENCES
)
2.l.1 TES EP-1-017 TES Program Plan For Independent Design Review of NPS LPCS System. i
"RTF1 FtWNE ENGINEERING SERVICES ENGINEERING PROCEDURE PAGE TilLE. EP 021
_2-REV. O REV. I QA RLVILW SAMPLING PROCl htlRL ORIG. JIIM _. NijCLEAR POWER STATION ORIG._I
- ENG. AhT~~PKR ENG. A >
INDEPENDENT DESIGN REVIEW Q.A, ~ ~TCS Q . A . ,_c G 's FOR Tile LPCS SYSTEM PROJ. }MRTJPX PROJ. tGif. T ( 0 ATE 6/T6/E22 DATE.g/'/& SECTION DESCRIPTION REV. 3.0 LOT DEFINITION 3.1 Lot size is established as a nominal count of field pipe walds and support or restraint welds to pipe for the E21 LPCS System as shown darkened in Figure 1 of Enclosure 1 to EP 017 and as clarified by (M. Milligan) letter to TES dated 6/8/82. 3.2 The lot is regarded as homogeneous, including pipe, valve, support and attachment welds. 3.3 for purposes of this review, the lot size will be 83. 4.0 SAMPLE DEf!NITION I 4.1 As a minimum, 35 weld record packages will be the sample size for review. 4.? At the discretion of the reviewer, and to assure a sufficiently represented population and distribution of characteristics (see 2.1), the reviewer may select additional weld record packi2ges for review. 4.3 The sample will not exceed 50% of lot size. 5.0 METIIOD 5.1 The reviewer will prepare a checklist per the form attached. 5.2 Identify the weld location per the As Built isometric drawing. S.3 Apply a random selection of characteristics a thru 9 (sec 2.1). to each of the weld records reviewed. Assure a reasonably equal distribution of characteristics for each record reviewed. g
"RTF1 FDYNE ENGINEERING SERVICES ENGINEERING PROCEDURE PAGE TITLE: EP 021 QA REVIEW SAMPLING PROCEDURE REV. O REV. . _1 NUCLEAR F0WER STATION ORIG. JHM ORIG. 4 /M ,
INDEPENDENT DESIGN REVIEW ENG. AS. MAR ENG. AV,47/ FOR THE LPCS SYSTEM Q.A. CGS Q . A . C 6 5 ,, , PROJ. MGR. JPK PROJ. MGR, JFK DATE 6/18/82 DATE S/9/#s I l 4 SECTION DESCRIPTION REV. 5.4 Enter all reportable conditions in the comuents section of the checklist form. 6.0 REPORTS 6.1 Results of this review will be forwarded to TES QA MGR for reporting in accordance with EP-1-017 Enclosure 1 Section 3.8.2. 7.0 RECORDS Documents produced as a result of this review will become TES project records. I I i
NUCLEAR POWER STATION WM g INDEPENDENT DESIGN REVIEW Attachment EP-1-021 - Checklist Reviewer Date - 10 No. & Rev. , v o Instruction 8 Attach Isometric Drawing - Markei .rcss Sumary
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