ML20040H503
| ML20040H503 | |
| Person / Time | |
|---|---|
| Site: | LaSalle |
| Issue date: | 02/05/1982 |
| From: | TELEDYNE ENGINEERING SERVICES |
| To: | |
| Shared Package | |
| ML20040H502 | List: |
| References | |
| PR-5792, NUDOCS 8202180320 | |
| Download: ML20040H503 (56) | |
Text
{{#Wiki_filter:- =-- =. = -- t I/ [ r i i 1 1 r 9PTELEDYNE ENQiNEEF@!G SERV!CES rcy,,,,p,n -, se, a {yrw,om.,qw.p p g' 1 i
- i
^ :s, ~. 'i' :s cewYu w J '-./ a ' k"as W U d sd d V b u b e.cu w .a PR-5792 TO COl010NWEALTH EDISO'i COMPANY PROGRAM PLAN - INDEPENDENT DESIGN REVIEW LA SALLE COUNTY NUCLEAR STATION i l BOOK 1 0F 2 kgg21so320920211 FEBRUARi 3, 1982 ADOCK 05000373 4 PDR L
t-j,. di C0t#10NWEALTH EDIS0N COMPANY P. O. 80X 767 { CHICAG0, ILLIN0IS 60690 l i ~ TECHNICAL PROPOSAL PR-5792 i l ? I ~ PRCGRAM PLAN - INDEPENDENT DESIGN REVIEW LA SALLE COUNTY NUCLEAR STATION 4 BOOK 1 0F 2 ) i 1 . FEBRUARY 5, 1982 l l I ( SPTELEDYNE ENGINEERING SERVICES P 130 SECOND AVENUE i ' WALTHAM, MASSACHUSETTS 02254 'T i 617-890-3350
RTI:1FVNEE ~ ENGINEERING SERV;CES f NRC Request 1. System Classification 2. Adequacy of Design Bases, Interface, FSAR Compliance 3. Review As-Built Versus Documents 4. Review Nonconformances 5. Review CAR 6. CECO Audit Findings 7. FCR, ECN Control 8. As-Built Comparison 9. . Visual Inspection - Walkdown 10. FCR Versus Records \\ D 4 e i l 1 + + e I =~+-*e,%,, %......_..,.-.y - + -~~**- ~, *___-.--.., Y' ~ ..v.-, m.,,.-._.,-m____
.t-SPTELEDYNE I. ENGGNEERING SERVCES TES Task No. Description NRC Requests 1 Design Process 1, @, 4 2 Review Design Procedures @, 4, 7 3 Review Interface Procedures 1 4 Review Implementation of Design and Interface Procedures 2, @, 5 Determine As-Built Configuration 3, @ ~ G Compare As-Built to Plant Conf.iguration 3,@,9 ~ 7 Design Documents vs FSAR Comitment 1, @ 8 Review CECO Audit Findings 4, 5, @,10 9 Project Review Internal Comittee 10 Reportin*g e 4 t e s
,.7> Data Required Suppler.mtary Ef fort (Secondary) ------. - February March April 8 15 22 1 8 15 22 29 5 12 19 i i e i t i. e i i i TES Task No. Description ! ---------l 1 Design Process 2 Revfew Design Procedures l l
I CECO Data 3 Review Interface Procedures H---
' - - - - -4 4 @ at end of T-6,1/2 way through T-3 4 Review Implementation of Design and Inter" ace Procedures l 5 Detemine As-Built Configuretton Ceco Data ---H }- - - - - - -1 i-6 Compare As-Built to Plant Configuration @ after T-6 7 Design Documents vs FSAR Comitment 8 Review CECO Audit Findings l l - - --i F - - - - - -J ~ 9 Project Review Interrial Comittee b Interim Final y_____e i Report Report 10 Reporting _Open item report of initial findinE(alrmidl _ __ _ y _ _ __ _ _ _ _ _ _ __ _q M
'7 .lj .WTA FT?/NE ENGINEERING SERVICES E Technical Proposal PR-5792 TABLE OF CONTENTS (BOOK 1 0F 2) PAGE 1
1.0 INTRODUCTION
1 2.0 PROGRAM PLAN OUTLINE 1 2.1 General 3 2.2 Plan Outline 4 3.0 PROGRAM PLAN IMPLEMENTATION 4 3.1 General 3.2 Task 1 - Design Process and Control 4 3.3 Task 2 . Review Design Procedures 5 3.4 Task 3 - Review Interface Procedures 6 3.5 Task 4 - Review Irtplementation of Design and 6 Interface Procedures 3.6 Task 5 - Determine As-Built Plant Configuration 7 3.7 Task 6 - Compare As-Built Documentation to 7 Plant Configuration 7 3.8 Task 7 - Des,ign Document Vs. FSAR Comitments 8 3.9 Task 8 - Review CECO Audit Findings 1 3.10 Task 9 - Project Review Internal Comittec 8 [ 9 i 3.11 Task 10 - Reporting 9 3.12 Task Sequence 10 4.0 PROJECT STAFFING 10 4.1 Project Review Team 10 4.2 Project Review Internal Comittee, 12 4.3 TES 10CFR Part 21 Comittee 12 l 4.4 Overall TES Organization 16 5.0 INDEPENDENCE 17 6.0 COMPANY QUALIFICATIONS 18 7.0 RESUMES i i L-
p I I s t I "RTEi r:rf(NE ENGINEERING SERVICES ~ Technical Proposal l PR-5792 \\ i
1.0 INTRODUCTION
Comonwealth Edison (CECO) has been requested by the Nuclear Regula-tory Commission (NRC) to obtain the services of an outside consultant to conduct an independent design review at the LaSalle ;ounty Nuclear Sta-tion, Unit 1. The design review is l'iniited to the Residual Heat Removal system (RHR) in the Low Pressure Coolant Injection mode (LPCI) for Loop C excluding electrical, instrumentation and equipment operational aspects which will be verified during preoperational and start-up testing. The portion of the RHR system subject to the independent design review is shown in Figure 1, which is taken from the P&ID for the RHR system at LaSalle (Sargent & Lundy Drawing Number M-96, Sheet 3. The piping asso-ciated with the RHR Water Leg Pumps is included"in this review as being representative of all small bore piping associated with this system. Two organizations we.re involved in the design of '.he RHR system, Loop C, at LaSalle. These organizations are Sargent & Lundy (S&L) and Quadrex. 2.0 PROGRAM PLAN OUTLINE 2.1 General The final result of this independent review is to determine the adequacy of the design process as it relates to an operating mode of 'a specific system. It is anticipated that this type of review would result in conclusions that are applicable to all work performed by the organiza-tions subject to the review. In general, the reviewer will not perform any detailed analyses to arrive at cc.c usions. Re/iew of existing analyses performed by the organizations involved will be sufficient and further, will provide better insight as to the design of other plant systems for i which they were responsible. This does not preclude th! reviewer from performing any calculations and analyses that are deemed necessary.
b i EXHIBIT 1 4 t l +- l }, ' h i i ' y; e j i k i iv, s C U !. ) n s y 1 . n _w-j - w..., ( j{ -...i r.2 O w d t }, p N:: p ,;, e.;. 1Glj!!,iidd-n o i II ' ",.,, "C, 3 $l ' h 'l <i !, f k h Ii; [ -* I y,,, hY4'.W l% 1 j i !. j g.d ) i'_..
- I i
t,., -,- u ..m p;,/ ' jE (,; 6 rj f.. 3 g f $ I, W}i! 'a p i S ! ':I P; ti f - 1 n w il ), } 'I m pah 6mNg)g
- t
,1 u 2
- r.,
'I N i.!.. : h J.-. 3, .I d -j y'i'T'" A' iG H I ,1 ;; l .a t II t L' y .1 i* d;..e!! L.i u W 3, H.r.: m a,. ] ,,1 y b ..wis. e fr li
- '- 1c
?p: Q or3 l ?,y,yI h,. a g G ;c..-< tede > r-----c Eir erfi 4 3, I tb ".) [ 'I' 4 ,o a T-b a q d5h 4 ~74: 9 I.j I (~a 4 o n ( f1 in pa n e. 5 -Cir-' ') N > [-I@M b} }h e,, m,
- m- > q i p
7 >l
- J ] M r.
Ip ,t 4 g- \\ ( f;h 7., k T hc -h ~~ r, .vt. ma. 4 1-g:. /$ h, (a :$ ' #:j
- h Tg i
s+ n
- p. A
.n I [ a.w e, d!b i f h h...?,. r[t'l s',)k. @m W, i,, '.; h, e y. .P x ( L l N t,4,=== Cs;ri = 1,. 5i i !:'> N p w ; g'.- + ~1.:.f~ b.;I iW .t l W Qt I --+ _;-. m- ,.3
- $ji P[9 9 $
K y o 6@jij);?q ^ !91 ^J [-i'h l {
- 1. h ;
j v.@ j t-y 3 % j,, h{ 4 2,j gg I. l j ,1 { r D51 ~- l ' *r t,b H; ),d y p :r5 3
- 5.
- ,.;, J2 t
.T .I p,. b,, w 'N ~ Y, A .__...3y .N.. \\ ". i f 6. =.c-- w+-aa r i u. D 'r. w-.' e 4 .,..,. x,i a,. Cr &w 2': 5** r j l n. M. ..g, .~ C. .t ! ;.I m, c., ,.,.f.. / ;- Q _.g,',,1, l ,s <.f -m f \\ .. o.,m a .,.. i .t pe 2. ,a .ji-_./[f;I.(y ]V l ['s :{L[ Vp c,[4't;f i ~ 4
- S/
4 3: i..d..t t, d. 2 q, J. -.). %.. 1, u,.,:......l,i.l.. n - vt. 1 hj% y l -gr i } ....s. .a ; u i .l ,.? g% i st.1,. m - . _ '.,., h..m '1':' + - ou w. % i &, d.s.L,, r,.,.. i l i Q b i m -,.c t:t,...sf:.;.~/,f..]1 4,rw ". ,m %,g t f.],,"-, .y q 3, ; ? e. i e
- j
- '
5 L> ,y sN, y p v ',a j, 77i,r,
- y-r(,
7, 5., r __i . : -p._ e y g '+ - g,- l-e D p wA
- :q} g
- M, n*.scy4/.,d.;
'g L.. ' gpL c,y)y ;' m ','*y t i..,, i, -t 3,% y ,Y 4i ., ;g 5 3 M-a
- y l.h.
su -? h S'~~~1, f d j' ..,s, ..a $ h,' i* :j'Sp; 1.p. y ..q 1 li
- +
I' V'C.! !\\, b)97.57M @4 w e tr.W !5 (c$3 3 di 5 / .11 (y. # -+:-,- >s. ; -
- ,.-W_..m '.... d.
-T-j 4 id = A o+ g. > .,_ t ~, r--,v>n ( t.;.E, y :; M er
- w. g.
gn g : r p,'
- ,19 y
t t 4 i .I .: =. A: f; s y A,p y:m k.q4, v' e I y
- y. y gc.
) W' t ~Y- ~ ra g..,L..s!- >?
- \\
W j d Ai.3 I b h M, i r) I, ',. t iy j t L n.
t WTA mYNE Technical Proposal PR-5792 The generation of dynamic spectra and the validation of computer , programs utilized by the organizations involved is specifically excluded !fromreview. The reviewer will accept dynamic spectra for the buildings f nvolved as presented and will only assure that their application to the I i system is appropriate. It is assumed that any computer program used has I already been subjected to procer validation and verification procedures. 2.2 Plan Outline Essentially the reviewer will start with the final design j package which is presented as being representative of the as-built system. { From this point the reviewer will work back through the design process to l the initial design Qsumug that interf ace control (internal and external) {wasapplied. 'Ckupl t e " e, ssu r e'n g gp g The program is separated into 10 tasks as follows: \\ Task 1 - Design Process Task 2 - Review Design Procedures Task 3 - Review Interf ace Procedures i l Task 4 - Review Implementation of Design and Interface Proce- ,I dures Task 5 - Determine As-Built Plant Configuration I l Task 6 - Compare As-Built Documentation to Plant Configuration Task 7 - Design Documents vs. FSAR Comnitments Task 8 - Review CECO Audit Findings Task 9 - Project Review Internal Comnittee I Task 10 - Reporting l e L f
'RTF1 FnYNE ENGINEERING SERVICES l Technical Propcsal ' R-5792 I I PROGRAM PLAN IMPLEMENTATION 3.0 _ 3.1 General The following sections discuss the detailed implementation of each task cutlined in Section 2.0 above. It is anticipated that some tasks will proceed in parallel while implementation of others will be dependent l cn completico of associated tasks. Termino ~ogy is used in the following l task descriptions that may not be particular to S&L and Quadrex. However, ' the intent is to define scope and method and terminology can be revised to suit the particular organizations involved. 3.2 Task 1 - De'sion Process and Control The reviewer will meet with S&L to determine what process is used in taking design requirements and developing construction drawings. Fur-ther, the process of developing revisions to the design will be reviewed. Interfaces between internal organizations will be dAermined in following the proce" of: a) specification of design requirements b) development of preliminary design c) piping analysis d) support location and selection f e) support analysis I f) effect on building structu e g) equipment loading requirem:nts h) development of constructio.1 drawings i) revisions to design Interfaces between external organizations will be determined in following the process of: a) transmitti1 of information to Quadrex ~ b) review of Quadrex procedures I i
WTA mYNE ENGINEERING SERVICES Technical Proposal PR-5792 \\ c) review of Quadrex design d) transmittal of Quadrex developed information to S&L organi-zations (i.e., loads on building structure, etc.) e) dealing with Field Change Requests (FCR) f) dealing with Engineering Change Notices (ECN) g) dealir.g with nonconformance and associated corrective ac-tion. J Based on the re ults of this discussion a design process flow chart indicating interf a..es and required design procedures will be de-veloped. 3.3 Task 2 - Rev(.g Design Procedures Procedures, instructions and methods associated with developing the design of the Rin system, Loop C will be made available to the re-viewer. This will result in a list of procedures with associated descrip-tions which can be utilized with the results of Task 3 to develop a design process. The reviewer must become familiar with these procedures to assure that implementation was adhered to by the design organizations. Since Quadrex was a subcontractor to S&L the compatibility of design procedures of both organizations will be determined. If different procedures, instructions and methods were used by each organization to perform a similar task (i.e., support design) the review must ascertaib that the results are acceptable using either technique. The design procedures will be further reviewed to determine if they are representative of the design criteria established in the FSAR. A detailed review of the Design Specification will be performed to determine its acceptability with respect to the FSAR, the Code and other design requirements. e
I i 'RTF1 prt/NE ENGINEERING SERVICES Technical Proposal pa-5792 3.4 Task 3 - Review Interf ace Procedures Using the design process determined in Task 1 and design proce-dures obtained in Task 2 the required interface procedures or instructiions to implement those procedures will be determined. A review will then be .made to determine if these interface procedures or instructions are avail-able. The reviewer will become familiar with the interf ace or control procedures to assure that implementation was adhered to in the design process. The interf ace procedures in conjunction with the design proce-dures of Task 2 will allow the reviewer to develop a design process for comparison with that obtained in Task 1. 3.5 Task 4 - Review Implementation of Design and Interface Procedures A detail review of the analyses, design and construction draw-ings and reports will be performed to determine' if es,tablished procedures uere adhered to. Information requiring transmittai to others will be .eviewed to determine whether interf ace procedures were followed and whether the information was properly interpreted and applied. This will be particularly important in relation to communication of design requirements and information between Quadrex and S&L. All FCR's and ECN's applicable to Loop C of the RHR system will be reviewed to determine if they were implemented properly in the design process including transmittal of changes in loading to all affected design groups. All nonconformances and resulting corrective actions applicable to Loop C of the RHR system will be reviewed to determine if they impacted design and were implemented properly in the design process. I
m _w W T8 5:rr ME -l ENG! NEE!iiNGSERVICES j Technical Proposal l pg.5792 - 3,6 ~ Task 5 - Determine As-Built Plant Configuration The reviewer will obtain the current data which represents the as-built plant configuration. Using this, a walkdown of the system will be It is not made to develop a general feeling for the accuracy of the data. intended that the reviewer perform a complete dimensional check of the However, dimensional checks of various portions of ti.e system and system. some supports will be performed. Photographs, as deemed necessary, may be taken to provide documentation of significant areas or co7ponents of the system. ~ 3.7 Task 6 - Compare As-Built Documentation to Plant C nfiguration 1 The reviewer will obtain from S&L or CECO the as-built documen-tation which is specified to be representative of the plant coafiguration. Having developed sufficient confidence in the data obtaincd in Task 5, the reviewer will make a compsrison of documentation and plant configuration. Any differences which are in areas of the, system not subjected to dimen-sional check in the field by the reviewer will need to be checked by the reviewer in detail at the site. The as-built documentation obtained in this task is the informa-tion that will be used in the detail review outlined in Task 4. This package should' represent revisions resulting from ECri's, FCR's ind any l applicable corrective action for nonconformances and therefore will allow the reviewer to follow the process of the design back to initiation. i 3.8 Task 7 - Design Documents Vs. FSAR Comitments The as-built documentation established in Task 6 will be used to determine if the FSAR coimiitments have been complied with. It is noted that a detailed review of the design specification will be performed in
p j -] 9PTA PT/NE L .f' ENG:NEERING SERVICES I rechnical Proposal .j pa4792 1 I l Task 2 since that document forms the basis for the design approach. This
- i review will be limited to FSAR requirements associated with the LPCI mode j
]I l of operation which is a Level D,ervice condition. The loads, load combi-nations and criteria will be taken f rom the design specification and the j FSAR. 3i 3.9 Task 8 - Review CECO Aud;t Findings The reviewer will obtain CECO QA and technical audit findings l related to design activities of ML and Qua< trex. The specific activities cited will be reviewed to deternine if corrective action was taken and if CECO audit personnel assured that this happened. 3.10 Task 9 - Project Re.Iw Inter <al Cocmittee The reviewer will form an internal committee whose responsi-bility will be to review all potential findings of the project review team. This review will. include the definition and accuracy of the finding and l assess the impact of the potentie! finding on the overall design adequacy 1 1 of Loop C of the RHR system. i Any potential findingr. determined to have an impact or. <lesign adequacy by the Project Review Internal Committee will be forwarded to the 10CFR Part 21 review conmittee for disposition in accordance with regula-tory and company procedures. Any potential fi nd i n,; s that are not determined to have an j impact on design adequacy will be returned to the project review team with l accompanying discussion related to rejection by the conmittee. Should the f ' individual reviewer or the project review team manager disagree with the review conmittee conclusions the potential finding may be forwarded to the l 10CFR Part 21 review committee for disposition. l c 3, y
VPTA mYNE- ,i ENG!NEERING SERVICES fechnical Proposal PR-5792 - 3.11 Task 10 - Reporting The~ reviewer will provide reports to CECO on the following schedule: Initial Status Report - March-15, 1982 Final Report - April 28, 1932 The initial status report will outline the progress to that date of the independent review and detail any findings which have been through the entire review process at that time. The finil report will contain a!l findings which have been proces' sed in accordance with Task 9. kly T;te%y..itcM+p;c t Migngp-87"; k rgcctr. Observations and suggestions will be available 2/fp/ff,, in the reviewers records and can be f orwarded at -a later date if CECO wishes. \\ The final report will also include details of the review pro-cess and summaries of each task. 3.12 Task Sequence l A number of the above tasks will be carried out simultaneously ( while others are dependent on each other. Further, the numbering of tasks I i does not indicate the order in which they will be performed. Based on current understanding, the following task sequence is established. i Task No. Sequence lio. 1 1 2 2 l 3 3 4 4 1 5 2 I i
"/PTn mYNE ENG!NEERING SERVICES Nchnical Proposal
- R-5792
4 (Cont'd) Task No. Sequence No. 6 3 7 5 8 4 9 N/A 10 6 Tasks 2 and 5, 3 and 6, and 4 and 8 can be carried out simul-taneously but are dependent on completion of previous tasks (i.e., Tasks 2 and 5 cannot comr.ence until Task 1 is completed). 4.0 PROJECT STAFFING 4.1 Project Review Team The work outlined in this plan will be conducted under the general direction of Mr., Donald F. Landers, Senior Vice-President. The Project Manager for TES will be Mr. James A. Flaherty, Manager, Engineer-ing Design and Testing. TES will provide staffing to this project as required to complete the effort outlined. The program as outlined will require the use of a number of senior level staff personnel to make the types of judgements required by this review. Further, the program will also require tt.e use of some personnel familiar with documentation control and record retention as well as personnel with field experient:e to obtain as-built information. Current projections for the Project Review Team Senior Staffing are shown in Figure 4.1. 4.2 Project Review Internal Comnittee This committee approach is currently used by TES for projects that involve state-of-the-art eng'neering. TES forms a committee in such cases composed of senior level personnel who have the necessary expertise to resolve technical issues presented by the particular project under .' l ,m---
= s WTA NIE l EAG!NEERING SERVICES 4 i
- - Technical Proposal-j l
PR-5792,,, i i .,? \\.. - f i i Project Manager J. A'. Flaherty Ai i Tasks 1 thru 4 Task 5 ' Tasks 6 and 7 Task 8 G. A.'Cerpenter R. H. Howard R. M. Pace J. A. Malonson i R. D. Ilockway R. D. Foti i j J. C. Tsacoyeanes i + i \\ - Additional TES staff will be gtilized as required. i l ~ j Project Review Team Senior Staffing i i. I Figure 4.1 l 'i f i l l t 1 I i
~ 9PTF1Fr>/NE l ENG NEERING SERVICES i
- echnical Proposal i
pg.5792 { i review. In this case the comittee will consist of three senior level I engineers who together have a broad backgreund in technical management, I analysis, design, regulatory and Code criteria, and utility experience. .v.r. flicholas S. Celia, Manager, Projects will chair this committee. The organization is shown in Figure 4.2. 4.3 TES 10CFR Part 21 Comittee 4 TES has a standing company policy with respec t to Part 21 issues. This policy is implemented by the use of a Techni:al Engineering I l Procedure (TEP-1-004). Although the find'ngs v.nich appear in the final TES report may not be of 'a Part 21 nature we will use our Part 21 approach in establishing these findings. The two major re. nuns for this are: l (1) The independence of ti e TES Part 21 Coranittee (2) The oppor;tunity for a reviewer to, appeal the Project Manager or the Project Review Intern'al Committee conclu-l sions on his potential findings. l This standing committee is chaired by Mr. Ron Wray, Manager, Engineering Analysis. He has the authority to assemble a comittee of his choosing based on the potential finding presented to him. In the case of this project he will be requasted to reviwi the plan presented here and establish this committee in the near future on:1 to revise the current TEP. with respect to the time allotted therein for his review. This will be done to expedite matters so that the April 28th date can be met. Since the findings being considered may not be Part 21 issues it is felt that this i can be accomplished. ) i I I 4.4 Overall TES Organization j + t i The TES standard organization is shown in Figure 4.3 and the organization for this particular project is shov,n in Figure 4.4. t
g-g-
- i. -
SPTAETVNE 'l: ~ ENGNEERNG SEMCES i .l Technical Proposal j 13-- t PR-5792 I. I f ) H. S. Celia - Chairman ~J. W. Hanson G. May Pro.iect Review Internal Coninittee l l Figure 4.2 r ( l I I \\ i 'I i r + e t Il r ~; 6 e i f
- fo I
i g - 'n s m= w y - -y y tv ewwww v -e n-w er w www-ww.w ev,,-- e-. -ww www -r -,-%v w e-v%=-= ~mmv------
.s " Ug'uQ s. . n o., t er s>vu.., t Fred C. Bailey, President I I I I I A. E. Johnson W. S. Moonan D. F. Landers J. Q. Cragin W. E. Cooper Vice President, Controller Senior Vice President,
- Manager, Consulting Engineer Internal Services Engineering Operations Marketing Services I
I I I N. S. Celia J. A. Flaherty R. Wray C. G. Sprangers
- Manager, Manager,
- Manager, Manager, e
Engineering Projects Engineering Design Engineering Analysis Quality Assurance and Testing I-1 I I Engineering Projects Design Testing Analytical Thermal-Fluids Capabilities Special Projects Engineering Assurotice TES Organization Figure 4.3
1,
- i..
W TELEDYNE EhENEERING SERVICES Technical Proposal PR-5792.- i I t t I F. C. Bailey j President . D. F. Landers Senior Vice President I f l Project Review Project Review 10CFR Part 21 Team Internal Comittee Comittee j J. A. Flaherty N. S. Celi a R. Wray Manager Chairman Cnairman \\ i I l l j LaSalle Project Organization -f Figure 4.4 1 l
/~ "vPTFI m/NE .j ENGJNEERINGSERVCES i 'f ,:nnical Proposal ji.5792 !. i 5,0 INDEPENDENCE TES has not been under contract to CECO to peform any work associated .ith the LaSalle project. With respect to the design agents involved, TES .35 not been under contract to Quadrex in the past Mn years and has had 'j i
- ne contract with S&L in that time frame. The S&L contract was performed j
in 1980 and 1981 and included a management audit of the process used to erform analyses of piping systems. In the process of that audit, techni-1 I
- al issues were discussed related to computer sof tware and hardware used by i
I %L. The inc6:se to Teledyne, Inc. for the S&L contract amounted to 0.000105% of total sales for that year. ( In order to qualify as an independent reviewer for the design verifi-cation program at LaSalle, all personnel assigned to the project will comply with the following: (1) Key project personnel shall have no present or past work ex-perience in design of the LaSalle County Nuclear Station. (2) Project personnel shall not be active on any other CECO, S&L cr Quadrex work. L I (3) No projec t personnel - shall have members of their immediat e f amily (parents, spouse, children and grandchildren) who are ( employed by CECO, S&L or Quadrex. i (4) During the term of the project no project personnel and their immediate family shall have cumulative ownership interest in l l CECO, S&L or Quadrex which exceeds 5% of their gross f amily f annual income. l i i i
1-SPTELEDYNE ENGWEERINGSERVICES gnnical Proposal ii.5792 t The most important factor in completing this design verification pro - ram is competence. This competence must be. based on kncwledge - and ex-perience in the matters under review. The company and individuals involved ,hould also be independent. Independence means that the individuais and c.orpany involved must be able to provide an objective, dispassicnate tech. nical judgement, provided solely on the basis of technical merit. Inde-pendence also means that the verification program mut be condxted by individuals and a company not previously involved with the 3esig.i activi-I ties at the LaSalle County Project. Their integrity must !;e such that they a are regarded as a reputable company or individuals. u 6.0 COMPANY QUALIFICATIONS o TES has been actively engaged in the nucler power irdustry since the early 1960's. Services have been provided to the industry in the areas of mechanical, structural, civil, electrical engineering,' testing and instru-centation. Our engineering activities range from stress analysis to design and material procurement and include fracture mechanics, design I reviews, ASME Code consulting and training activities. In the areas of testing and instrumentation we provide material testing, nondestructive examination, failure analysis and mechanical testing services. TES staff are heavily involved in ASME Code activities, the Pressure Vessel Research Committee, ANSI Standards Committees, ASTM and SESA. I TES has a staff of approximately 220 people of which 195 are involved i in engineering activities. Most of the senior staff are Registered Profes-sional Engineers who have authored numerous papers. l 4 h 6 2 iL'~
W Tri m(NE ENGINEERING SERVICES Technical Proposal -{ A -PR-5792 y l 4 4 'l 7.0 RESUMES f i The following key personnel have been identified to participate in I I one of the major areas of this project: i 1 J. A. Flaherty -j ) N. S. Celia j f R. Wray j G. A. Carpenter j { R. D. Hookway. l R. M. Pace -ls I J. H. Malonson G. Moy 1 1 J. W. Hanson h R. D. Foti i i J. C. 1sacoyeanes i Other personnel whose participation may be required will be drawn from the following individuals: D. F. Landers M. A. Revett J. F. Maher i L. J. Diluna S. D. Wharton R. D. Ciatto D. Messinger R. A. Enos W. J. Carey L. B. Semprucci B. C. Ryder J. P. King J. J. Rivard R. A. Smith M. R. Dellorso D. C. Neal M. F. Moran The resumes of these personnel follow. !g Participation of the above will be subject to their demonstration of { being free of substantive conflict of interest.
r i. "/PTF1 mYNE ENG'.NEERiNG SERVICES Technical Proposal
- R-5792 i
l i l I i I RESU.MES \\ I i I i t 1 1, l e ....... in s. ine mer -w
i j W TELEDYNc ENGINEERING SERVICES r JAMES A. FLAHERTY Manager, Engineering Design and Testing Professional Resume Educatfan Northeastern University, B.S. in Civil Engineering, 1964 Tufts University, M.Sc. in Civil Engineering, 1966 Experiencq Telodyne Enjineering Services and Teledyne Materials Research', since 1962: Er.gmeering manager responsible, for all work performed by Engineering Design and Testing Group. Responsibilities include proj-ect review, technical guidance, manpower assignment, cost and sched-ule review. Diract responsibility for modification program for operating nuclear i power plant ccrponents and their supports including material procure-ment, desigr., fabrication examination and testing requirements. Pr<nide ccnsulting servims in the area of pressure vessels, piping, vahS5 an-J ccmponent supports with the particular emphasis on stress cnalysis ar.d the applicability of the ASME Boiler Code and Pressure Ver.sel Codes. Lecturer at Teledyne Engineering Services sponsored seminars for the nuclear power industry. \\ United States Army, Lexington-Blue Grass Army Depot (Kentucky),1st i Lieutenant, Corps of Engineers, 1966 to 1968: project officer in the Directorate for Data Systems; programmar and system analyst for ac-counting and logistic system support groups. AVC0 Corporation, Missile Systems Division, Associate Engineer, Sum-l rr.er 1966: structural analysis of reentry vehicles and related com-pc. Tents involving static and dynamic 1oadings. Tuf ts University, Graduate Teaching Assistant in Computer' Center, academic years 1964-65, 1965-66: formulating, solving, and grading problems for senior / graduate course in numerical methods and com-puters. Linethal-Becker-Eisenberg, Summer, 1965: analysis and design of structural components. Membership American Society of Civil Engineers Welding Research Council: Pressure Vessel Research Committee Registered Professional Engineer in Massachusetts / (over) ^ w
I ~ 1l -,;, j i a U.. l! i $!p ti ( Authorship I;]. "An Assessment of the Effect of Plate Flexibility on the Design of !.!' !j. Pressure Vessels and Piping Conference,- San Francisco, California, Moment-Resistant Raseplates." with L.J. Diluna, presented at the June, 1979. } [l "The Field Installation of Concrete Anchorage Systems," with L.J. i Diluna, presented at -t.he ASCE Committee on Construction of Nuclear 4 i facilities Conference. Pennsylvania State University, September, 1981.
- i. ;
' j f - "A Method for Digitizing, Preparing and Using Library Tapes of Ship i Stress and Environ. men Data," with Aldie E. Johnson, Jr., and Isaac J. l Walters, Ship Structure Comittee Report SSC-236,1973. { " Computer Programs for the Digitizing and Using of Library Tapes of Ship Stress and Envit enment," with Aldie E. Johnson, Jr., and Isaac J. 'Walters, Ship Structure Comittee Report SSC-237,1973. i L 4 i- \\ l 1 f h o 1 'i l* .i k i i i. -i i i ?
- i t
- I WTF1 FDYNE ENGINEERING SERVICES l
NICHOLAS S. CELIA Manager, "ngine'. ring d Projects 1 Professional Resume i 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 f Experience Engineering manager responsible for Teledyne Engineering Services: Responsibili-all work performed by the Engineering Projects Group. . ties include project review, technical guidance, manpower assignment, I and cost and schedule review. Responsible for analysis and field l survey work for nuclear and LNG projects. Analysis projects include piping, piping supports, and structural analysis. 1974 to 1980: Project Manager in charge of structural analysis, design, and modification projects. Responsibilites include technical performance, cost control, scheduling, and final reporting. Independent Consultant, 1972-1974: analysis of loads and stresses in structures from static, dynamic and acoustic ' environments. Special. problems encountered include pipe rupture and impact analysis, non-8 linear dynamic response analysis, and acoustically-induced pipe Stresses were evalu-i stresses due to sonic flow through large valves. j-ated and reported using criteria of B31.1 and Section III of the ASME Code. ~ l Itek Corporation, 1967-1972: Senior Engineer, responsible for dy-l l ? namic and structural analysis of systems subjected to shock, vibra- } Design and analysis of shock and tion, and acoustic environments. Extensive dynamic and acoustic test vibration isolation ' systems. experience including test specification and fixture design. t I 1960-1967: Dynamic anal-l e Convair, Douglas & North American Aviation, ysis and test, project review and interface, and ground support l, 8 ' l f acilities and equipment design for Apollo, Saturn, MOL, and Atlas } projects. l, Membership 4 l Registered Professional Engineer - State of Massachusetts 4 ! Pi Tau Sigma t Tau Beta Pi j! O l 3/81
a "vPTF1 EDYNE ENG!NEERING SERVICES EONALD WP./d Manager, Engineering Analysis l.'il nl Professional Resume 1 0a Education q ?. Northeastern University, B.S. in Civil Engineering,1955 Rensselaer Polytechnic Institute, M.S. in Enginw.-ina Science. 1962 [ Experience Teledyne Engineering Services, and Teledyne !ktemis hsearcn, since 1971: theoretical stress analysis of pressure '/9ssels, pioing systems and frame structures utilizing computer progrm wNtions and finite element methods; performed and directed static and dyamic analysis W of Nuclear and LNG Piping Systems; conducted design revievs 0f Nuclear l Piping Systems. Instructor at Franklin Institute of Boston, Evening Division. 1962-1971: performed dMai!ed stress and AVC0 Systems Division, buckling analyses of various reentry vehicle shBI uructuces under combined reentry pressure and inertia loads and imating. Ecsigned and analyzed large vacuum and pressurized chamners for a portable sterilization / clean room facility built for flAS?/Lcngley; responsi-ble for the structural design and evaluation of spce power systems and planetary probe systems. T Pratt & Whitney Aircraft, Canal Division, 1958-1962: perfonced 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 inrolving liquid metal coolants under conditions of high temperatur2 operation and ~ severe transients; established design criteria ter compone.nts ex-posed to long-life, high-temperature conditions. U.S. Arnty Corps of Engineers,1st Lieutenant, 1955-1958: served as project officer on military construction sites; field experience in reinforced concrete and steel erection. Membership ASME, Boiler and Pressure Vessel Code, Alternate Menter Task Group on Dynamic Analysis.
i J. IL WTri prWNE ENGINEERiNGSERV!CES GEORGE A. CARPENTER, Jr. Manager, Engineering Professional Resome l E_ducation } Wentworth Institute, Associate in Mechanicc1 Engineering, 1962 Lowell Technological Institute, B.S. in Mechanical En9 neering,1971 i (evenings). Experience I Teledyne Engineering Services, and Teledyne Mccrials Research,1969-Performed and directed ARE Section III flexi-1970; 1971-present: bility and stress analysis of nuclear Class 1. ?, and 3 piping systems in accordance with NC-3600 and NS-3550. Dasign, analyze and review installation of nuclear piping and supports. Directed projects re-lating to modification of existing nuclear end process steam fossil plant piping systems including: Project m nagement, feasibility studies, piping desi.gn/ layout / fabrication dr mings, material pro-curement, pipe support design / selection, wlding and repair pro-cedures, field supervision, all in accordance with Sections III and j XI of the ASME code and ANSI B31.1, 031.3 co u requirements. Directed projects in response to NRC I&E Bulletins 79-02 and 79-14 including: technical procedures, physical testing, stress analysis, and field Sales and client relations develnpment, East and West j engineering. Coast offices. United Shoe Mach'inery, 1967-1969: Design end f atigue stress analysis of plastic molding and shoe machinery; fatigue testing of materials. Foster-Grant ~ Company, 1965-1967: Design and improve methods of production machinery. J. H. Horne Company, 1962-1965; 1970-1971: Design and analysis of paper mill machinery. 3/81 _h
u (' ~j 1PTELEDYNE ENGNEERING SERVICES i ROBERT D.'H00KWAY Principal Engineer i Professional Resume ? Education Lowell Technological Institute, B.S. in Mechanical Engineering, 1963 Northeastern University, M.S. in Mechanical Engineering, 1970 Eggrience Teledyne Engineering Services, and Teledyne Materials Research, since 1967: theoretical and experimental stress analysis of nuclear piping and pressure vessels using thick and thin shell computer programs and finite element tcchniques; temperature distribution computer solu-tiens under transient and steady-state conditions; design of piping j and piping support systems; auditing )of design, and installation of power plant (nuclear and fossil fuel, process plant and Liquefied Natural Gas, piping systems; preparation of design specifications for-piping systems including Class 1 Nuclear. Analysis of piping pover systws incluuing seismic and dynamic analyses using criteria of ANSI B31.1, B31.3, 031.7 and ASME B&PV, Section III Codes. Process plant expo ience includes oil refinery and LNG plants. AVC0 Ccrporation/Spde Systems Division, 1965-1967: theoretical and experimental stress analysis on reentry vehicles (composite mater-ials). Improved Machinery Company, 1964-1965: design of pulp manufacturing i machinery. Dmbershin Registered Professional Engineer in [4assachusetts - No. 28626 e American Society of Mechanical Engineers e Vice Chairman of the Pressure Vessel & Piping Subcommittee of the o ASME Nuclear Engineering Division, 1976-present l Alternate Member of Working Group on Piping Design of Section III e ASME Boiler & Pressure Vessel Code Member Chapter 6 Subcommittee for NFPA-59A e Member ANSI /ASME B31.10 Code Committee " Cryogenic Piping" ee Member ANSI /ASME B31.3 Code Committee, " Chemical Plant and Petrochem Refinery Piping" Authorship " Piping Design Manual," with D. F. Landers, AEC-RDT Standard, June 27, 1969. USNRC Study to Determine " Effects of Postulated Events Devices on ' Normal Operations of Piping Systems in Nuclear Power Plants," i NUREG/CR-2136, 1981. 10/81 t
ll i! 'RT8 EYNE s ENGWEERING SERVICES g RAYM0ND M. PACE Senior Engineer Professional Resume Education t'orthea. tern University, B.S. in Mechanical Engineering,1973 { i Experienco Teledyne Engineering Services, and Teledyne Materials Research,1972 to present: stress analysis of pressure vessel components using / finite element techniques; stress analysis of liquid metal components i at elevated tecmsatures; AS:1E Boiler and Pressure Vessel Code review of design analvns; evaluation of nuclear piping systems under static and dync.nic loLding conditions, including postulated high energy pipe break rnd relief valve blowdown for hanger and support locations a using finite eltat techniques; design, analysis, field engineering and verification associated with plant modification of existing pip-ing systems and related structural components; verification of nuclear piping dasign analyses to ASME Boiler and Pressure Vessel Responsible fo' cryogenic design, analysis and field engineer-Code. r ing including A!!SI B31.3 piping systems and AISC structural modifica-tions associated with LNG facilities and LNG storage tanks. Design revice of cryogenic (LNG) piping systems, components and structural support designs to ANSI B31.3 and The Uniform Building Code. Lead Assisted in Plant Engineer DX:1 Mark 1 Torus requalification program. the davelopment and direction of generic and plant unique analyses for the torus structure and associated components. Responsible for coordinating and scheduling analyses and outage related modifications with the client. Membershin i Registered Professional Engineer - Commonwealth of Massachusetts. l 1 i 3/81 s q
a. l WTELEDYNE-ENCMEERiNG SERVICES JAMES H. MALONSON .{ Project Quality Assurance Specialist i s Professional Resume t ^ Education Wentworth Institute, Mechanical Drawing and Machine Design, 1948-1950 Welding I & II, Shielded metal arc and oxy-acetylene ASQC, Management of Quality Control, 1972 Northeastern University, Work Simplification, Psychology for Industry, 1962-1963 Massachusetts University Extension, AC-DC Theory and Advanced AC Theory, 1961-1962 Ex erience y Teledyne Engineering Services,1979 to present: Quality Assurance Specialist on nuclear projects involving design analysis and modifi-cations. Maroneilan International, Inc., 1977-1979: Quality Assurance Engin-eer in the manufacture of automatic control valves and liquid level ? controllers and transmitters. Responsibility in all phases of pro-duction and quality interface with engineering, purchasing, sales and [ customer representatives. \\ i Megapulse, Inc., 1975-1977: Quality Control Supervisor. Total Q.C. program responsibility on a design and development contract to pro-i duce a LORAN "C" System for the Department of Transportation. i l Bowmar, Inc., 1973-1975: Quality Control Supervisor. Performed l Quality Engineering / Quality Assurance function and supervised inspec-l 'l tion activities: Incoming, machine shop, in process and final in-spection in the production of both commercial and military elec-tronics. I Gaulin Corporation, 1971-1973: As Quality Control Manager, had total l Quality Assurance / Quality Control Program responsibility in the manu- ' f acture of pumps in conformance with the ASME Pump and Valve Draft t Code and for Naval-nuclear contracts for the production of coolant charging pumps for subarines and surf ace ships. Participated in the preparatica of the Quality Assurance Manual and program requirements for N Stanp approval under the ASME Code.. I I RCA Corporation, Aerospace Systems Division, 1959-1975: Technical, j administrative, and supervisory responsibility in Quality Assurance, l l Quality Control Planning and Inspection. .s l l Membership / ? American Welding Society l i 3/81 o
>pcTELFtWNE ENG!NEERiNG SER(/ ICES GEORGE M0Y Principal Engineer ] i Professional Resume j i Education Northeastern University, B.S., 1962, and M.S., 1964, both in o Mechanical Engineering Experience 1 j Teledyne Engineering Services, and Teledyne Materials Research, since 1975: ASME Code Case N-47 (1592) stress analyses of liquid metal fast i breeder reactor components and piping including elastic and inelastic l analyses. This work includes an elastic-plastic-creep analysis, l using state-of-the-art programs, for a full size Liquid Metal Fast Breeder Reactor piping system. Lecturer for Elevated Temperature J Components Seminar, part of the TES Seminar Series. Performance of ASME, Section XI fracture mechanics evaluations of flaws detected during. inservice inspections. Design evaluations and analysis of petrochemical, LNG and nuclear power components and piping systems. 6 i Bechtel Corporation, San Francisco, California, 1971-1975: Lead Stress Engineer on the FFTF project, a liquid metal f ast breeder reactor test facility, responsible for the thermal, stress and seis-i ~ ic analysis of plant piping and related components. Work included } m j clastic and inelastic stress analyses as well as the use of RDT j Standards and ASME Codes. l h The Babcock & Wilcox Co., Boston, MA, 1968-1971: thermal stress and l dynamic analysis of Navy nuclear and liquid metal breeder reactor l pressure vessel components. The analyses were performed in accord- .ance with the Navy Structural Design Code, SDB-63 and Section III of the ASME B&PV Code. Northeastern University, Boston, MA, 1966-1971: part-time Instructor I lt in Mechanical Engineering Technology in the Lincoln College Division. J Dynatech Corporation, Cambridge, MA: 1964-1968: design and stress ,i analysis of nuclear pressure vessels and related components in ac-cordance with ASME and Navy Nuclear Design Codes. l Membership American Society of Mechanical Engineers, Associate Member Pi Tau Sigma
- r. gistered Professional Engineer in California and Massachusetts 4
3/81 i
WTA m(NE I ENGINEERING SERVICES 4 i JOHN W. HANSON Manager, Projects Professional Resume _ Education I University of Houston, B.S. in Mechanical Engineering,1965 i; l Experience i I j Teledyae Engineering Services, since 1979: Field verification of i nuclear plant piping systems. Testing and verification of nuclear piping support baseplates. Client liason. Fossil and nuclear plant i modifications. Project Management activities related to piping sup-ports and Torus modifications. Houston Lighting & Power Company, 1965-1979: Engineering design i. review of 2-1250 MWe PWR's 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 activities of various engineering disciplines related to new fossil plant projects t 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 consistin,g of 1-220 MWe and 1-66 MWe gas-fired units. l Responsible for pre-op testing and various startup activities for new . t fossil units. \\ I Membership l. Registered Professional Engineer - State of Texas American Society of Mechanical Engineers l e 3 1 o 3/81 1
m_ "RTELEDYNE ENGINEERING SERVICES l ROBERT D. F0TI Manager, Projects Professional Resurri Education Tuf ts University, B.S. in Mechanical Engineering,1972 Experience Telodyne Engineering Services, and Teledyne Materials Research, 1972: static and seismic analysis of nuclear power piping Force-time history analysis systems and related components. utilizing finite-element techniques with large-scale structural analysis digital computer programs. Performed audits of analytical procedures used in determining piping support sys-Performed calculations and established procedures for tems. .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 Audited restraint designs and installations power piping systems. Working knowledge of B31.1 ANSI, NB-3652, for nuclear power piping. 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: experimantal stress aralysis of composite materials using moirs techniques. ^ g Membership _ Registered Professional Engineer - Commonwealth of Massachusetts e 3/81
.r r i t "RTm m(NE i ~ ENG' EERINGSERVCES R i: JAMES C. TSAC0YEANES Consulting Engineer Professional Resume Education j l Boston University, B.S. in Aeronautical Engineering, 1959 Northeastern University, Graduate courses in Mechanical i Engineering Experience i Teledyne Engineering Services, Teledyne Materials Research, and l' Lessells and Associates, Inc., since 1960: stress analysis of 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; pre-paration 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 T.emperature Components. Curtiss-Wright Corporation, Propeller Division, Experimental Testing Laboratory, 1959-1960: mechanical and electrical testing of propeller controls. Membership l American Society of Mechanical Engineers, Member ASME Boiler and Pressure Vessel Committee i Working Group on Valves (SG-D SC III) l Safety Code Committee on Nuclear Inspectors and Specialized Professional Engineers Task Group on Qualifications and Duties of Specialized Professional Engineers, Chairman l Registered Professional Engineer in Massachusetts I 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. 3/81 i L
"vPTFiFnyNE l ENGINEERING SERVICES i i i DONALD F. LANDERS { Senior Vice President i Professional Resume I Education Lincoln Technical Institute, A.S. in Mechanical Engineering, 1962 l Northeastern University, B.B.A. in Engineering and Management, 1963 l i Experience 1 1 Teledyne Engineering Services, Teledyne Materials Research, and i I Lessells and Associates, Inc., since 1961: Engineering design, { l analysis and construction management for nuclear power and fossil g , 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 LflG piping systems including installation. Arthur D. Little, 1959-1960: stress analysis and field engineering of fuel loading piping for Atlas and Titan missile bases. Bethlehem Steel Co., Nuclear Power Section, Central Technical Dept., 4 1957-1959, 1960-1961: stress analysis of shipboard piping, pipe hanger design, supervision of nuclear piping installation. Charles T. Main Co., 1955-1957: power plant and textile mill design. U.S. Navy Weather Forecaster, 1951-1955 Membership ASME, Coiler and Pressure Vessel Code, Section III Comittee Member; j Working Group on Piping Design Member; Subgroup on Design Chairma'n. Welding Research Council, Pressure Vessel Research Committee ANSI, B31.7 Code for Nuclear Piping, Member; Chairman, ANSI B31.7 l Task Group on Design. Registered Professional Engineer - Comonwealth of Massachusetts i 4 - (over) t L
t [ l I I i V Authorship \\ o Cooper, AEC Report NY0-3416-1," Specification Guidelines ,j October 1964 II " Nuclear Piping Design Guide," with R.D. Hookway, USAEC Division of -l! Reactor Development and Technology RDT Standard. O4 "Effect of ANSI-B31.7 1969 on the General Piping p il Heating, Piping and Air Conditioning Magazine, June 1970, Industry," Computer Software - Problems and Preferred Resolutions," ASME Booklet on Computer Software. " Problems Occuring in Nuclear Piping System Analysis and Operation," Second International Conference on Structural Mechanics in Technology - Berlin, Germany, 1973. of Mechanical and Electrical Engineers."B31 Piping Desig L " Design Specifications." ASME Philadelphia and Delaware Sections, 1973,1974 and 1975 Nuclear Power Plant Components Course and 1976 j, ASME Annual Meeting Short Course. 8 "Section III ' Nuclear Piping Design," ASME 1975 and 1975 Annual Meeting Short Courses. " Nuclear Piping Design - A Critique ", July 1978. Systems in LWR Power Plants", August 1980 - San Systems in Nuclear Power Plants"- with R.D Hookwa Desai, USNRC - NUREG/CR-2136, May 1981. TES, and K.D. t e t 1/82
j WTEiEYNE ENGWEERINGSERVICES i uj MARK A. REVETT Senior Engineer g Professional Resume 9 4 1 i Educ atic.n h r I!alyoke Coaronity College, Mathematics and Science Courses,1964 t i United Stctes Coast Guard Academy, B.S. in Engineering--Mechanical 1 and Marine, 1969 j Pratt & Whitney FT4A Gas Turbine School, Service and Operation of g Od5 TurdiDe Modified for Marine Propulsion, 1970 Krautkramer-Crenson, Inc., Ultrasonics School, Level I and Level II traininc in nondestructive material examination for subsurface flaws using ultrasonic techniques, 1975 and 1976
- Ntals Ter. ting Co., Inc., Level II training and nondestructive mater-ial ex uination for surface and subsurface flaws using magnetic i
t particle z.nd liquid penetrant techniques, 1975 i riarthestorn University continuing education course, Project Adminis-tration, 1976 and 197P3 j Eas' man Kods, Radiographic Film Interpretation School, 1978 gperiem Ti cdyne Engineering Services, and Teledyne Materials Research, 1974 i to present: stress analysis of piping systems and piping support systems including seismic analysis using criteria of ANSI B31.1 and j A%E B&PV, Section III Codes. Procedures and specifications for t codification of nuclear power plants using criteria of ANSI B31.1; nondestructive examination techniques and procedures. QA Field Engineer for system installation and nondestructive examination. Certified Level III in ultrasonics; Level II magnetic particle, and i liquid penetrant techniques. Engineering Assurance Manager, res~ ons-i ~ p l 151e for Quality Control and related QA/QC activities. ISI Code j consulting, plan review, QC audit of NDE subcontractors for client utilities. United States Coast Guard, 1969-1974: Engineering Officer, qualified in and responsible for operation, maintenance, and repair of diesel, gas turbine, and 600 psi steam turbo-electric marine propulsion sys-l tems. Plan and Specification approval for all new and altered water-borne commercial vessels, cargo and/or passenger, required to meet U.S. Flag Certification Regulations, Title 46 Code of Federal Regula-t tions. Ferro-Cement Project Officer for West Coast. Membership American Society for Nondestructive Testing Member, ASME Section XI, Subgroup on Containments (over) q l L.
L %m. .] q. Authorship 1 ASME Paper 78-ftE-14. "ISI Management and the Role of the Third Party Y Consultant." t 5 t ( 4 i ) i k i 1 5 4 2 F 4 $,it: ^ h'. + j l i
- )
'( i. g 'I If-l e c 7 r 'i T I I f i l 4 .? f 6/81 4 l
~ i, f" ' ENG!NEERNG SEFMCES !i ji i I i LOUIS J. DILUNA a Senior Engineer i Professional Resa Education Cornell University, B.S. Civil and Enviren;rantal Engineering, 1974. Northeastern University, M.S. Civil Engineering, 1979. Experience Teledyne Engineering Services, and T 4 dyne Materials Research, July 1974-present: theoretical stress analysi.s, analy<.is of nuclear power components per,ASME Code _Section Ili, fr: sign and analysis of com-ponent supports and modifications to ihrk. i!WR containment systems. Study of the behavior of pipe sup;wt t; using concrete expansion anchors. Elastic and inelastic analysis, unng state-of-the-art pro-grams and methods, of a full-size elented temperature piping system, as well as smaller verification r.odels, for a LMFBR plant. 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, to be presented at the ASCE Committee on Construction of Nuclear Facilities Conference, September, 1981. i f l ,f 4/81
W TELEDYNE ENGINEERING SERVICES / 1 o k ( i RAYMOND D. CIATTO i Principal Engineer j 7 ! 4 L Professional Rdsumd 1 i ',4 Education i Newark Collep of Engineering, B.S. Civil Engineering,1965 Ncetheastern University, M.S. Civil Engineering, 1967 4 Northeastern University, Boston, Mass., 1971-1972: Lecturer in M?chanical E..gineering Technology for Advanced Stress Analyses Experience Teledyne Engineering Services, and Teledyne Materials Research, since 1971: stress analysis of nuclear components by finite element method; pressure and thermal stress analysis of Naval nuclear components. M 13mic analysis of components for the Liquid Metal Fast Breeder Reactor (U{TBR) program. Nonlinear structural analyses of LMFBR components. Inicstigation of a concrete tunnel subjcted to high pressures caused by a trcTk in a main steaa pipe. Nonlinear impact analysis of swing check vaives. Design and analysis of component supports. Investigations of structural f ailures incl,uding steel roof structures and prestressed con-crete. Conducted column research program using analytical and exper-imental techniques. Project management of design and evaluation proj-2 ects per ASME Boiler and Pressure Vessel Code and AISC Steel Construction Manual. Participation in ASME Code activities, Section III, Subsec-tien NF, Component Supports. The -Babcock & Wilcox Company, Boston, Mass., 1969-1971: thermal and pressure stress ' analysis of a reactor vessel and steam generator; dynamic shock analysis of nuclear power piping; computer program development of piping analysis program; developed an infinite series solution for influence coefficients of rings; thermal analysis of steam generator internals. Dynatech R/D Company, Cambridge, Mass., 1967-1969: stress analysis of nuclear pressure vessels and related components; elasticity analysis of nozzles by finite difference computer method; analyzed piping systeams for earthquakes and other dynamic loads; vibration analysis of jet engine bearing. Membership Registered Professional Engineer in Massachusetts, New York, Texas, and Washington Member, American Society of Civil Engineers Member, American Concrete Institute (Over)
.=
- r;
~ ~. 1 e. r i i i Ii i 4 Authorship 1, " Linear Component Supports in Compression and Bending", presented at the ASCE Convention, Boston, Massachusetts, April 1979. { 4 " Strength of Concrete Expansion Anchors for. Pipe Supports" with R.' R. Boentcen, presented.at ASME Pressure Vessel and Piping Conference, San Francisco, California, August 1980. t, t k. 1 I i i I: x I i ? I I f I 1 I 'Z e t e v 1 g-l l e-L i
~ i WTA mYNE ENG' EERINGSERVICES W j i i a W RICllARD A. ENOS [! Senior Engineer i! 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: ' 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 com-ponents per ASME Code Section III. Application of beam and finite element techniques utilizing STARDYNE, TMRSAP, ANSYS, 8050R-4, and FLUSil computer program solutions. Transient dynamic force-time his-tory analysis using modal analysis techniques. Design and analysis of component supports and modifications to' Mark. I BWR containment systems. Structural analysis task leader responsible for directing the quantity and quality of work performed, as well as interfacing with the client. _ Membership Society for Experiinental Stress Analysis, New England Section Registered Professional Engineer, State of' Massachusetts i'. 6/81 l l t
r-l WTA mYNE ENGINEER'NG SERVICES I LENIN B. SEMPRUCCI Principal Engineer Professional Resume 4 Education Northeastern University, B.S. in Mechanical Engineering,1966 Northeastern University, M.S. in Mechanical Engineering, 1968 Post Graduate Courses " Energy Methods and Variational Techniques in Solid Mechanics," North-l eastern University, 1975 " Gas Dynamics," Northeastern University, 1975/76 " Transients in Pipelines and Hydraulic Machinery," Georgia Tech, 1976 " Unsteady Gas Flow," MIT, 1977 " Advanced Engineering Math," Northeastern University, 1977 " Solar Heating System Design," Northeastern University, 1979 "RELAP 5 International. Workshop," 1981 Idaho National Engineering Laboratory \\ Experience Teledyne Engineering Services, and Teledyne Materials Research, since 1968: Computation of transient temperature distributions in struc-tures using closed form, series, chart solutions and finite differ-Determination of force-time history in piping ence computer codes. systems due to fluid transients caused by relief valve operation, Fluids turbine trip, pump trip, valve stroking and pipe rupture. range from so-called " incompressible fluids" where the fluid velocity l is negligible compared to the fluid acoustic velocity to fully com-l Two-pressible fluids where choking and shock waves are possible. l l phase single component problems such as the rupture of subcooled hot These problems are solved with a l water lines where flashing occurs. variety of techniques from graphical solutions such as the method of l characteristics to computer codes. Computer codes used are: RE LAP, l WHAM, FLASH, PISCES, WAVENET. Solution of steady oscillatory prob-lems such as vortex shedding, turbulent buffeting. Sized components i for steam power plants such as piping, valves, and orifices. l Analysis of plate, shell, and beam structures subject to static, seismic and time varying loads, using classical solutions, finite difference and finite element computer codes. Analysis of structures i to ASME Section III and VIII criteria. i (Over)
m
- m. _
..s A i Experience (Cont'd.) { l Dynatech Corporation, 1966-1968: Co-operative Graduate Work Program: stress analysis of pressure vessels and nuclear reactor components, using Section III of the ASME Boiler and Pressure Vessel Code. j Membership l American Society of Mechanical Engineers Pi Tau Sigma i Registered Professional Engineer ir Massachusetts l Authorship }i I "The Application of RELAP4/REPIPE to Determine Force Time Histories on Relief Valve Discharge Piping," ASME Book, Safety Relief Valves, from 3rd National Congress on Pressure Vessel and Piping Technology, June 1979, co-author. i \\ 8 I l l i l I O 5/81 t
~ '/PTA m/NE ENGWEEENG SERVICES 5 i JAMES P. KING Senior Project Engineer l Professional Resume f Education Lowell Technoicgical Institute, B.S. in Mechanical Engineering Tech-nology (lloncrs), 1972 Loweli Technological Institute, A.E. in Mechanical Engineering Tech-nology (High Honors), 1967 Experience Teledyne Engineering Services, and Telodyne Materials Research, since 1972: flexibility analysis of LNG and SNG piping systems.
- Stress, f atigue and thermal evaluation of nuclear power piping systems and components, including lead project responsibility.
Preparation of design guides, design specifications and stress reports to ASME Code, Section III. Design reviews of piping systems. From 1978 to 1979, an eighteen mont h assignment, in residence, at a utility in Spain. Duties included: introducing a Nuclear Class 1 piping analysis capa-l t bility to staf f engineers, supervising the Class 1 analysis of sys-tems of a three loop PUR and interfacing with the hook-up of applic-able package of computer programs. From 1980 to present, management of nuclear Class 1 piping and component analysis projects. Lowell Technological Institute Research Foundation, 1967-1972: design and packaging instrumented experimental rocket payloads, and j stress analysis of members. i Technical Operations, Inc., 1963-1967: layout and design of experi-l mental and prototype optical hardware systems. C. G. Sargent's Sons Corp., 1957-1963: detailing and layout of tex-tile machinci'y and industrial dryers. Authorship + " Evaluation of Class 1 Nuclear Piping to NB-3600, including NB-3200 for Thermal Stress," ASME Book, Pressure Vessels and Piping Analysis and Computers, from Miami Beach Conf erence, June 1974, co-author. 3/81
n( 4 i "RTF1 FrNNE ENGINEERING SERVICES l } I ROBERT A. SMITH !l l Engineer Professional Resune Education Northeastern University, B.S. in Civil Engineering,1976 Experience Teledyne Engineering Services, 1980 to present: structural design and analysis of nuclear power piping components and compor.cnt supports for static, thermal, and dynamic loading conditions in accordance with ASME Boiler and Pressure Vessel Code, use of structural computer programs, field inspection and design modification of cce.penents and supports. Stone & Webst'er Engineering Corporation, February 1980 to August 1980: pipe support design and analysis for seismic loading, use of structural computer programs, field verification of designs. Bergen-Paterson Pipesupport Corporation, 1977-1980: pipe support design, use of struc,tural computer programs, screduling support design work, ordering and scheduling delivery of nsterials frca manufacturing facility and outside vendors, field verific3*.jon of designs. Titan-Northeast Constructior. 1976-1977: shop drawing submittals, estimating. 4 l f 4 e
r O-YN DIE ENG6NEERiNGSERVICES DAVID C. NEAL Engineer Professional Resume Education University of Lowell, B.S., Civil Engineering, 1978. Experience Teledyne Engineering Services, December 19 I to present : Project Administration for Pipe Support analysis; Pipe Support andy::is util-izing STARDYNE, SC0DE and DC0DE computer programs: deveicpent of Engineering Procedures for Pipe Support analysis; Base Plate and expansion anchor bolt analysis utilizing STRUDL and BOLT 5 cc:aputer programs; site field work for pipe supports and pipe support base plate analysis. Charles T. Main Co.,1978 to 1979: Coal-fired fossil po..er plant design including structural steel, reinforced concrete, and (ivil design. Uhl, Hall and Rich Engs., 1977: Inspection and engineering ccordina-tion of transmission line construction. Membership Engineer-In-Training, Massachusetts Boa,rd of Registration. 3/81 e i
~ WTm m/NE ENGINEERING SERVICES i J J0NATHAN F. MAHER Project Engineer Professional Restne Education Northeastern University, B.S. in Mechanical Engineering, M. 5. in Mechanical Engineering, 1978 Experience Teledyne Engineering Services, April 1980 to present: Deten.inat. ion of support locati.ons and type for nuclear power piping r.ystems, static and seismic criteria. ASME Code Class 1 analysis en nuclear pip.ing components, including temperature distribution deteersination. Use various methods to solve steady and unsteady heat transfer prob-lems. Generated blowdown loads for single and two-phase non in piping systems. Calculated pipe rupture lcads. Calculated n a.a and water hammer loads. General Electric, Aircraf t Engine Group, 6/78 -s 4/80: Design and analysis of cooling configurations for jet engine parts. Radesign and structural analysis of engine parts for both static, dyremic and fatigue criteria. Coordinated test cell operations for J85 engines. ~ Membership Pi Tau Sigma National Mechanical Engineering Honor Society Tau Beta Pi National Engineering Honor Soc'iety Engineer-in-Training, Massachusetts Authorship M r;ter's Thesis: "A Design and Analysis Aid for Piping Subject to Thermal Shock" A 5 4/81 s a l
WTA mYNE ENGNEERING SERVICES DONALD MESSINGER Project Quality Assurance Specialist Professional Resume Education American Society of Nondestructive Testing training courses. Certificates 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 271D, 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 Experience Teledyne Engineering Services,1978 to present; Quality Assurance Specialist, responsible for internal and vendor audits to Code and client requirements. Certified Level III in Magnetic Particle and Liquid Penetrant. Qualified lead auditor per ANSI N45.2.23. Lytron, Inc., 1976-1978: Makers of heat exchangers. Quality Assur-ance 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 Penetrant. The Thompson Lichtner Co., Inc., 1973-1976: Chief Inspector of structural steel, decking and precast. Responsible for inspection of f abrication, erection, welding, bolting and NDE practices in con-struction of schools, hospitals, banks, insurance companies. 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. (over) e
~ _. _ lr. I b d i Experience (Continued) i Bethlehem Steel Corp., Shipbuilding Div,ision, 1955-1963: Radio-grapher 1/C - crew leader responsible for X-ray of pipe, castings and structural steel and MT and PT inspections to meet commercial, mili-tary and nuclear codes. Film interpreter and dark room responsibil-ities. Membership American Society for Nondestructive Testing J ! 4; .I 1 l r 4[ h b g s i \\ 4 I e 3 a e i L 3/81 e a ~O
"/PTELEDYNE ENGINEERING SERVICES t JAMES J. RIVARD Project Engineer Professional Resume Education Lowell Technological Institute, B.S. in Civil Engineering, 1973 University of Lowell, Graduate Courses in Structural Engineering Experience Teledyne Engineering Services, April 1981 to present: design and analysis of nuclear component supports per ASME Code, Section III. Metropolitan District Commission, Engineering Division,1973 to 1981: structural analysis and design of various types of buildings, bridges, hydraulic structures, hard rock tunnels, and supports for mechanical systems. Rehabilitation of existing buildings and Hydraulic design of culverts, pipelines and intake struc-bridges. Responsible for preparation of construction estimates, con-tures. tract plans and specification and review of shop drawings. Membership i .American Society of Civil Engineers Registered Professional Engineer, State of Massachusetts 9/81
t "R TELEET(Ne ENGINEERING SERVICES MICHAEL R. DELLORSO Engineer I Professional Resume Education University of Connecticut, B.S. in Civil Engineering, 1978 Northeastern University, Graduate Level Courses in Civil Engineering Experience l Teledyile Engineering Services, October 1979 to present: structural i analysis and modification of piping restraints and related framed structures utilizing computer program solutions.
- Static, thermal and seismic analysis of nuclear power piping per ASME Code Section I I I'.
Field modification of nuclear systems involving design and analysis of piping supports. Project Lead Engineer responsible for directing and controlling nuclear piping analysis effort. Structural analysis of offshore facilities. Membership American Society of Civil Engineers s Engineer-in-Training, Connecticut i i { I l i l i t' 4/81 o t Q
I 8 I WTF1 FDYNE t ENGINEERING SERVICES ? MICHAEL F. MORAN Project Engineer Professional Resume i i Education Wentworth Institute, Associate, Buildin University of Lowell (Evening Division),g Construction,1971 B.S. in Civil Engineering,1979 Experience Teledyne Engineering Services, since April 1980: stress analysis of piping systems and piping support systems using criteria of ANSI 831.1 s and ASME Boiler and Pressure Vessel Section III Codes. Provided technical leadership on major structural analys is and modification projects. Represented TES at client f acilities controlling interf ace on technical problem areas. Performed field walkdovins of Code class lines and assisted in the resolution of discrepancies at the construction site. Also field routed lines for CR0 system with possible support locations and details. G. F. Moran Construction, 1974-1980: supervised 'and performed work in residential and light commerci al construction. Furnished designs, estimates, bids, and coordinated other subcontractors when necessary. U.S. Army, 1971-1974: Personnel Specialist, E5. Penbership Engineer-in-Training, New Hampshire f 1/82 I I .--}}