ML20090K932

From kanterella
Jump to navigation Jump to search
Exhibits 1-3 from TC Cooke 801022 Deposition
ML20090K932
Person / Time
Site: Midland
Issue date: 10/22/1980
From: Cooke T
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML17198A223 List: ... further results
References
CON-BOX-02, CON-BOX-2, FOIA-84-96 OL, OM, NUDOCS 8405240487
Download: ML20090K932 (10)
v • d • e


Text

4 O

Ex4/4t r fro %

tolzz/'80 DeposUh, of Thm< s C

Gooefe, m,J t<,a b;<d-Sp em te,de ~ r, Coere, ers f%.ser.

Compray Sbtb/s

/

.3 X

i I

)

8405240487 840517 R

EO 96 PDR

__. _=

,( R C,,$g Nls*d,'I

~

=

l Resume Thomas C.'Cooke Education and Training 1953 Graduation, LaGrange H.

S., LaGrange, Ohio 1957. - Graduation, Ohio University Athens, Ohio BSCE

~

,1957 Engineer Offi'cer Easic Course, 7t.,Belvoir, VA Hobart Welding Inspection, Course, Troy, Ohio 1961 CPM Seminar

.1963 1966 Tallout Shelter Analysis, Grand Rapids, MI 1968

. Nuclear Steam Supply Design Lecture Series, Windsor, CT Public Utilities Report, Mcme Study 1968 1970's - Various Utility Sponsored Management Courses, MI Exoerience Upon graduation from Ohio University, I served as Second Lieutenant and eventually a.s First Lieutenant in the U.S. Army Corps of Engineers in the capacity of Platoon Commander and Assistant Operations Officer in a con-struction battalion.

Typical projects included roads, bridges, rifle ranges, enttages, rock cfushers, transmission lines, etc.

My career with a major utility has provided me with the opportunity to become

(

involved in many varied construction projects with progressively more respon-sible assignments.

I have worked as part of the owner's team responsible for significant. portions of several large projects and have often had sole re-sponsibility on smaller projects involving reciprocating and jet compressors, steam heating plants demolition and rebuilding, underground steam mains, associated electrical, mechanical and instrumentation for the abeve and mod-ifications projects.

At my last assignment, I was responsible for nu.nagement of the entire checkout and preoperation test program at a 790 MW nuclear facility to the point of fuel. load.

After fuel load, I was assigned to modifications work at that facility as Project Superintendent.

Presently, I am Project Superintendent responsible for construction of a twin nuclear

/

co generation faqility.

Typicall'y the above assignments have includ'ed working with contractors, subcontra'etors and various archit'ect engineer organizations.

I have been very involved in inspection, testing, coordination, procurement, technical problems, invoice approval, permits, safety, security, fire procaccion, public relacions, labor relations, expediting, scheduling, permits'and startup. Much of the work has been accomplished utilizing cost plus, unit price, lump sua and incentive contracts.

During the past few years, I have also gained considerable experience in dealing with financial slowdowns, changing government regulations, regulatory enforcement, legal proceedings, hearings and* changes in design.

9

i-,

3 6

4

+

- - ~ - - -.,

.,---,,..,.-an 9

-_-,~.,,--.e-

Chronology

(

Jun 57 - Aug 57 Graduate Student in Training Program Utility Aug 57 - Aug 59 U.S. Army Corps of Engineers Ft. Belvoir,*VA Ft. Hood, TX Sep 59 - Feb 60 Craduate Student in Training Program Utility i

Feb 60 - Oct 60 Field Construction Assistant - Gas 24" and 26" Cross Country Pipeline Oct 60 - Mar 61 Field Construction Assistant - Electric 265 MW Fossil Civil Work Mar 61 - Jun 62 Field C:.nstruction Assistant - Electrie 265 MW Fossil Piping Jun 62 - Jun 63 Field Construction Supervisor - Electric 265 MW Fossil Piping & Startup Jun 63 - Jun 64 Field Construction Supervisor - Electric Cas Compressor Station i

Jun 64 - Jun 65 Field Construction Supervisor - Electric Steam Heating Plant Jun 65 - Oct 65 Field Construction Supervisor - Electric 380 MW Fossil UP Boiler 1

4 Oct 65 - Mar 67 General Engineer Instrumentation

& Piping Mar 67 - Jul 67 Assistant Field Construction Superintendent

& Startup a

Jul 67 - Aug 68 Assistant Field Construction Superintendent 790 MW Nuclear Aug 68 - Mar 71 General Supervisor 790 MW Nuclear Startup Mar 71 Dec 72 Project Superintendent 790 MW Nuclear Modifications Jan 73 - Present - Project Superintendent Twin 800 MW Nuclear Cogeneratfor.

e

~

(

-.,. - - - ~ - -.

~.,

r--+

P.iscellaneous l

High School Valedictorian

- ~

College Graduate Cum Laude Organizations:

Phi Eta Sigma Freshisan Honorary Tau Beta Pi Engineer Honorary american Nuclear Society Registration:

Michigan Progessional Engineer Ohio Professiona.1 Engineer Publications:

Article for " Military Engineer" co-authored paper for 1976 ANS convention L

~

.l O

q O

e e

e g

i f)(LC ty # &.4.

~

.,/[0PD'M

.s CSd511m313 10ld " N T

if 1

./

CDMEUIEl uwi er.# a e.e. s.. ins. uws.a.s. m.,

guo 4,

cw. sn sas.oen september 8, 1977

}!r. J. F. Neugen Bechtel Power Corporation P.O. Box 2167 Midland, !!I 48640

}!IDLAND PROJECT GWO-7020-.Ap] MINISTRATION BUILDING /C File: 0130 1 2538 on August 25 we became aware of the situation regarding sectiement of the subject beam.

Inasmuch as this particular item could fall under the provisions of Articia 9 of the Rechtcl Power / Consumers Power Company contract regarding repair of defective work at contractor's expense, we are requesting that you

- q advise us as to the reasons for this failura and set up a separate account for costs incurred for removal and repair of sar.e (engineering and construction).

I would anticipate that your response to this office would' include come dis-cussion as to why the incident should or should not come under the provisions of Articia 9 of the contract.

T. C. Cooks Project Superintendent TCC/pp S

g l

l

(

O 1

fa

~

i-l'~

fil@n@ %.

i

x.

sechter Power corporation 9

,n'6 Post Omce Box 2167 3

'].!

c,6 usciand. uichigan <asso 919 September 23, 1977 l-

'.S m %.c.p.*

g.s -

I Consumers Power Company

[ CIgfy,, URS P. O. Box 1963 i

Midland, lE 48640 h

t Attention:

T. C. Cooke Job'7220 Midland Project Administration Building Grade Beam Failure BCCC 2794

Dear Mr. Cooke:

Reference:

T. C. Cooke's letter to J. F. Newgen, Serial No. 2538 dated September 8, 1977 We are in receipt of the forence correspondence and wish to advise that we are still investigating the failure to determine the reason.

A separate account for the cost of re..edial work has been established.

Tnis does not, however, include distributables and dasign engineering support which would require undification to our present costing system.

We will keep you advised of all developments regarding this matter and provide you with a response to your letter once the investigation is complete and a determination made.

Very truly yours, f

.dg w

.,Ne gen JIN/JD0/af

,a Y

/

.(-

6 N '

'e

-w

U Ib rf ", u. u w

., ;. 3 b,*

pk Pest Office Boa 2187 Midland. Mecn.gan 4as40

'J/

MIDl.AND Ft. ANT PROJECT

>;1DLAND. tMCHIGAN December 30, 1977 3

t e

Consumers Power Company.

l P. O. Box 1963 Midiand, MI 48640 Attention: Mr. T. C. Cooke Job 7220 Midland Project Settlement of Administration Building Grade Beam at-0.4 Line SCCC-3010

Dear Mr. Cooke:

Refemnce:

T. C. Cooke letter to J. F. New September 8,1977 (Serial 2533) gen - CCBC-1155 - dated This letter is written in response to the reference letter and provides an update on our investigation of the subject incident.

Investigation of the area during the mmoval of the fill and testing performed on this material indicates that the major contributing factor to the failure'was compaction at a value (S

Company was directly involved with the testing of the material during installation, lower than that required by the~ specification Since United States Testing -

we are investigating their liability. We will keep you apprised of subsequent actions in this matter.

Per your mquest, the costs associated with the re-c: oval and mpair of the grade, beam have been maintained in 'a _ separate account.

~

Very truly yours.

/

y/G7-

' j a.

6en JFN/AJ8/jae y-S l

I,,

_f...,

.i;II ii 'l i

l lij.

li l

Ig!'

i l I

e i

i' N-I w

7s i lag M01.s51 5,u @ ;li !!!Trr i h j?N i3 j

tra i

.i i::!

i e

.i.

i li, i

o h,k,,

l llt l ! l:

l' I

l i

i!!iii ti ilii l

l ':

O l

i i

I "i

,i a

i f{,.hj*$. l?.'*;YN&.fh'r*h}'f.Q

$ff.,f.,

  • 414 6,6aa.t_;

- - -- 7 g - _ _ ^ ** =*f 3 pg -... _

' i; f

.). i

f h.

I D ikl4 ok f SAlf

[*

4,jgd (&*hN A>

1.4 1

PRINC".'AL ARCHITECIURAL AND ENGINEERING CRITERIA FOR DESIGN The principal architectural and engineering criteria for design for the plant are summarized below.

(See also Appendix 1C.) The specific architectural and engineering criteria and design features are detailed in later sections.

l.4.1 PLArf DESIGN

. ; Principal structures and equipment which may serve either to prevent accidents or to mitigate their consequences are designed, fabricated, and erected in ac-cordance with applicable codes and to withstand the most severe earthquakes, flooding conditions, vindstoms, snow loads, temperature a'nd other deleterious i

? natural phenomena which could be expected to occur at the site during the life-ii time of these units.

Principal structures and equipment are sized for the c:aximum expected NSS and turbine generator outputs.

Each NSS will be housed in a separate reactor building and vill function independently such that failure of one unit will not result in unsafe condition of the other.

l.h.2 REACTOR i

The reactors are of the pressurized water type, fueled with slightly enriched l

uraniu= dioxide.

identical.

The reactors and associated auxiliary systems are essentially Neutron absorption for reactivity control is provided by control rods and by 4

dissolved boric acid in the coolant.

The boren chemical shim system is cane.

tionally independent of the control rod system.

=

For all operating conditions, the control rods are capable of providing an adequate shutdown margin at het, zero power conditions following a trip, even vith the most reactive rod stuck in the fully withdrawn position.

a boron chemical shim system is capable of adding boric acid to the reactor i

coolant at a rate sufficient to maintain an adequate shutdown margin during 1

reactor system cooldown at the marimmn design rate following a reactor trip.

The combined response of the Doppler (fuel temperature coefficient), the =od-4 erator temperature coefficient, the moderator void coefficient and the moders-i tor pressure coefficient to an increase in reactor themal power is a decrease in reactivity. In addition, the reactor power transient remains bounded and damped in response to any finite changes in any operating variable.

i Automatic and redundant reactor trips are provided to prevent anticipated l

Plant transients from producing fuel or clad damage.

'1.k.3 REACf0R COOLANT AND AUXILIARY SYSTDIS s

p ff Heat removal systems are provided which can safely accommodate core heat out-llputunderallcrediblecircumstances.

Each of these heat removal systems has sufficient redundancy to provide reliable operation under all credible circum-l stances.-

s 1.4.4 REACf0R E!ILDING

)

The reactor buildings, including the associated access openings and penetra-tions, are designed to contain the =*wimum pressures resulting from postulated 1-15 E

- ~ - - - ' ~ ~~~~~

~

4 loss-of-coolant accidents (I4X:A) in which (a) the total energy contained in fp the reactor coolant systet water is assumed to be released into the reactor building through a double-ended break of any one of the primary coolant

.! pipes, (b) there is a simultaneous loss of external electric power, (c) heat is tranhferred from the reactor to the reactor building atmosphere i by water supplied from the emergency core cooling system (ECCS), (d) either the reactor building air recirculation and coolin reactor building spray system functions, and (e) g units 1%nction or the the engineered safeguards including safety injection do not operate until 25 to 40 seconds following the accident.

Selected' penetrations are provided with either a seal water injection system or are continuously pressurized with air at a pressure greater than building design pressure.

Means are provided for pressure and leak rate testing of the reactor building system including provisions for leak rate testing of piping and electrical penetrations that rely on gasketed seals or sealing ccapounds.

1.4 5 ENGINEERED SAFE 00ARDS Engineered safeguards systems with redundant features are incorporated in the plant design which, in conjunction with the reactor building system, provide a high degree of assurance that the release of fission products to the env1-ronment following any credible loss-of-coolant accident will not exceed the reference doses set forth in 10 CFR, Part 100.

w

{F 1.4.6 INSTRUMENTATION AND CONTROL Intericeks and automatic protective systems are provided along with adminis-trative controls to insure safe operation of the plant.

A reactor protective system is provided to initiate reactor trip if the reactor approaches an operating limit.

initiate these systems upon detection of LCCA.An engineered safeguards actua Sufficient redundancy is installed to pezuit periodic testing of the reactor protective systems and so that failure or removal faa service of any one I

protective system component or portion of the system will not preclude reactor trip or other safety action when required.

g 1.4 7 EIJ:CTRICAL SYSTME t

vided to assure safe and orderly shutdown of the plant an p

maintain a safe shutdown condition under all credible circumstances.

i 1.4.8 RADICACTIVE WASTES t

The radioactive waste treatment system is designed so that discharge of radio-activity to the environment is in accordance with the requirements of 10 CFR, Pmrt 20.

-l

.}

1.4 9 SEZILDING AND ACCESS CONTROL

.L

(.

The plant is sm vided with a centralised' control roca having adequate shield-ing.to pesuit ocausaney during all eredible accident situattoms.

The 1-16 Amendment No. 2 cW yrn

i radiation shielding in the plant, in combination with plant radiation control Procedures, insures that operating personnel do not receive radiation expo-i sures in excess of the applicable limits of 10 @R, Part 20, during nomal operation and maintenance.

1.4.10 PUEL HANDLING AND STCRAGE Fuel handling and storsge facilities are provided for the safe handling, stor-age, and shi pant of fuel and vill preclude accidental criticality.

1.4.H PROCESS STEAM Process steam from the plant will meet regulations as to radioactivity con-tent, within the applicable limits of 10 T R, Part 20.

15 RESEARCH AND DEVELOPMENT REQUIRDtERJ The research and development programs that have been initiated to establish final design or to demonstrate the capability of the design for future opera-tion at a higher power level are summarized as tonows:

151 XENON OSCILIATIONS An analysis to evaluate the possibility of xenon oscinations throughout core 1

life is under way.

completed, and the detailed spatial calculations are in progress.A mo

g detemined that such escinations may occur, appropriate design changes to If it is eliminate or centrol the oscinations vill be incorporated.

See also 3 2.2.2 3 c

152 i

THERMAL AND HYDRAULIC PRdGRAMS BIM is conducting a continuous research and develo3 ment program for hast I

transfer and fluid flow investigations applicable to the design of the Midland i

units.

Two important aspects of this program are:

3 1:

l Reactor Vessel Flow Distributien and Pressure Drop Tests a.

A 1/6-scale model of the vessel and internals is under test to measure the flow distribution te the core, fluid mixing in the vessel and core, and the distribution of pressure drop within e

the reactor vessel.

b.

Fuel Assembly Heat Transfer and Fluid Flow Test Critical heat flux data have been obtained on single-channel tubular and annular test sections with unifo m and nonunifo n heat fluxes, and on the multiple rod fuel assemblies with uni-fem heat fluxes.

  • These data havt been obtained for a range

' of pressure, temperature, and mass velocities sa :capassing the j}

reactor design conditions. This work is being extended to

(

1-17

_c, m-.__-.,

.-m

-,.., -. _ ~

_r., _.

-,, _

Retrieved from "https://kanterella.com/w/index.php?title=ML20090K932&oldid=4338744"