ML20090A819
| ML20090A819 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 10/22/1980 |
| From: | Cooke T CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML17198A223 | List:
|
| References | |
| CON-BOX-12, FOIA-84-96 OL, OM, NUDOCS 8101050512 | |
| Download: ML20090A819 (10) | |
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Education and Training Graduation, LaGrange H.
S., LaGrange, Ohio 1953 1957. - Graduation, Ohio University',' Athens, Ohio, BSCI' '
l Engineer Of fi~cer Basic Course, 7t. Belvoir, VA 1957 Robart Welding Inspection, Course, hoy, Ohio
'1961 CPM Seminar 1963 Fall, cut Shelter Analysis, Grand Rapids,-MI 1966 1968
. Nuclear Steam Supply Design Lecture Series, Windsor, CT public Utilities Report. Home Study 1968 1970's - Various Utility Sponsored Management Courses, MI Experience Upon graduation from Ohio University I served as Second Lieutenant 'and eventually as First Lieutenant in the U.S. Army Corps of Engineers in the cap'acity of Platoon Commander and Assistant Operations Officer in a con-struction battalion. Typical projects included roads, bridges, rifle ranges, cottages, rock crushers, transmission 1.ines, etc.
My career with a major utilrty has provided me with the opportunity to become
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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 porticas 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 in,strumentation for the above and mod-ifications projects. At my last assignment, I was responsible for management 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 fac;ility.
Typicall'y the above assignments have included 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 protection, public relations, labor relations, expediting, scheduling, permits'and i
s':artup. Much of the work has been accomplished utilizing cost plus, unit price,* lump sum and incentive contracts. During the past few years, I have also gained considerable experience in dealing with financial slowdowns, changing govarnment regulations, regulatory enforceme.it, legal proceedings, I
hearings and changes in design.
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f Chronology
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Jun 57 - Aug 57 Graduate Student in Trainihg Program Utility U.S. Army Corps of Engineers Ft. Belvoir,*VA Aug 57 - Aug 59 Ft. Hood, TX i
Graduate Student in Training Frogram Utility Sep'59 - Feb 60 Field Construction Assistant - Cas 24" and 26" Cross Feb 60 - Oct 60 Country Pipeline Field Construction Assistant - 51ectrie 265 W Fossil Oct 60 - Mar 61
. Civil Work F,ield Construction Assistant - Electric 265 W Fossil Mar 61 - Jun 62 Piping Field construction Supervisor - Electric 265 W Fossil
- Jun 62 - Jun 63 Piping & Startup Field Constructiori Supervisor - Electric Gas Compressor Jun 63 - Jun 64 Station Field Construction Supervisor - Electric Steam Heating Jun 64 - Jun 65 Plant
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Field Construction Supervisor - Electric 380 MW Fossil Jun 65 - Oct.65
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UP Boiler General Engineer Instrumentation Oct 65 - Mar 67
& Piping Assistant Field Construction Superintendent
& Startup' Mar 57 - Jul 67 Assistant Field Construction Superintendent 790 MW Nuclear, Jul 67 - Aug 68 General Supervisor 790 MW Nuclear Aug 68 - Mar 71 Startup Project Superintendent 790 MW Nuclear Mar 71 - Dec 72 Modifications Jan 73 - Present - Project Superintendent Twin 800 MW Nuclear Cogeneratio$
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High School Valedictorian College Graduate Cum Laude Organizations:
Phi Eta Sigma Freshman Honorary Tau Beta Pi Engineer Honorary American Nuclear Society Registration:
Michigan Progessional Engineer Ohio Professiona.1 Engineer i
Publications:
Article.for " Military Engineer"
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Mr. J. F. Newgen Bechtel Power Corporation l
P.O. Box 2167 Midland, MI 48640 MIDLAND PROJECT GWO-7020-. ADMINISTRATION BUILDING /CRADE BEAM FAILURE
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File: 0130 1: 253 On August 25 we became aware of the situation regarding settlemen't of the subject beam. Innsmuch as this particular item could fall under the provisions of Articic 9 of the Bechtel Power / Consumers Power Company contract regarding q
repair of defective work at contractor's expense, we are requesting that. you advise us as to the reasons for this failure and set up a separate account for costs incurred for removal and repair of sane (engineering and construction).
I would anticipate that your respcuse to this office would' include some dis
'cussion as to why the incident should or should not come under the provisions of Article 9 of the contract.
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T. C. Cooke Project Superintendent TCc/pp D
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1 Consumers Power Company
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Midland, MI 48640
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Attention:" T. C. Cooke Job'7220 Midland Project Administration Building Gmde Beam Failure BCCC 2794
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Dear Mr. Cooke:
Reference:
T. C. Cooke's latter to J. F. Newgen, Serial No. 2538 dated September 8, 1977 We are in receipt of the' mfemnce correspondence and wish to advise
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that we am still investigating the failure t,o determine the reasco.
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A separate account for the cost of re.5.edial work has been established.
Tnis does not, however, include distributables and design engineering support which would mquire undification to our present costing system.
We will keep you advised of all developments regardihg this matter and provide you with a response to your letter once the investigation is complete and a detemination made.
Very truly yours,
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.,Ne' gen JIN/JIO/af
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- a Midland. MicNgan 4564o t.'.lDLAND Fl. ANT FRONCT r
oilDI.AND. t,ll'CHIGAN Decenter 30, 1977 l
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l Consumers Power Company,
P. O. Box 1963 tiidland, MI 48640 l
Attention: Mr. T. C. Cooke Job 7220 Midland Project Settlement of Administration Building Grade Beam at-0.4 Line BCCC-3010
DearMr.docke:
'. C. Cooke letter to J. F. Newgen - CCSC-1155 - dated T
Reference:
September 8,1977 (Serial 2533)
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 removal of the fill and testing performed on this material indicates
' that the major contributing factor to the failure'was compaction at a value lower than that required by the~ specification. Since United States Testing-(
Company was directly involved'with the testing of the material during installation, we are investigating their liability. We will keep you apprised of subsequent actions in this matter. Per your request, the costs associated with the re-moval and repair of the grade beam have been maintained in 'a separate account.
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' Very truly yours,,
/
Y//~97 J.
sevgen
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A 1.4 PRINCIPAL ARCHITECTURAL AND ENGINEEftING CRITERIA FCR DESIGN
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The p*incipal architectural and engineering criteria for design for the plant are summariied below. (See also Appendix 1C.) The specific architectural and engineering criteria and design features are detailed in later sections.
t 1.4.1 PIANf 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, vindstorms, snov loads, temperature a'nd other deleterious
? natural phenomena which could be expected to occur at the site during the life-f i time of these units. Principal structures and equipment are sized for the msximum expected NSS and turbine generator outputs. Each NSS will be housed in a separate reactor building and viu function independently such that failure of one unit will not result in unsafe condition of the other.
l.h.2 REACTOR The reactors are of the prassurized vater type, fueled with slightly enriched i
uraniu= dioxide. The reactors and associated auxiliary systems are essentially identical.
t Neutron absorption for reactivity control is provided by. ntrol rods and by i
dissolved beric acid in the coolant. The boren chemical shim system is func-tionally independent of the control roi system.
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For all operating conditicas, the control rods are capable of providing an adequate shutdown margin at hot, zero power conditions following a trip, even with the most reactive rod stuck in the fully withdrawn position.
The boron chemical shim system is capable of adding boric acid to the reactor coolant at a rate sufficient to amintain an adequate shutdown margin during reactor system cooldown at the maximum design rate following a reactor trip.
The combined response of the Doppler (fuel temperature coefficient), the mod-erator temperature coefficient,.the moderator void coefficient and the modera-tor pressure coefficient to an increase in reactor thermal 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.
Automatic and redundant reactor trips are provided to prevent anticipated plant transients from producing fuel or clad damage.
'l.k.3 REACTOR COOLANT AND AUXILIARf'SYST54S s
fll/ Heat removal systems are provided which can sai'ely accommodate core put under all credible circumstances. Each of these heat removal systems has sufficient redundancy to provide reliable operation under all credible circum-stances.. -
i.4.4
-REACTOR IUILDING The reactc.,r buildings, including the associated access openings and penetra-tions, are designed to contain the mad== pressures resulting from postulated l
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O loss-of-coolant accidents (LOCA) in which (a) the total energy contained in p
the reactor anolant system vater is assumed to be released into the reactor
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building tnrough a double-ended break of any one of the primary coolant 3
./ pipes, (b) there is a simultaneous loss of external electric power, (c) heat is tran1sferred from the reactor to the reactor building atmosphere by water supplied from the emergency core cooling system (ECCS), (d) either the reactor building air recirculation and cooling units function or the reactorbuildingspraysystemfunctions,and(e)theengineeredsafeguards including safety injection do not operate until 25 to 40 seconds following the accident.
Selected penetrations are provided with either a seal vater injection system or are continuously pressurized with air at a pressure greater than building design pressure.
Means are provided for pressura 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 ecn: pounds.
1.4.5 UGINEERED SAFEGUARDS Engineered safeguards systems with redundant features are incorporated in the plant design which, in conjunction with the reacter building syste=, provide a high degree of assurance that the release of fission products to the envi-ronment following any credible loss-of-coolant accider3. will not exceed the reference doses set forth in 10 CFR, part 100.
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1.k.6 INSTRUME3TAMON AND CONTROL Interlocks and automatic protective systems are provided along with adminis-trative contzcis to insure safe operation of the plant. A reactor protective system is provided to initiate reactor trip if the reactor approaches an operating' limit. An engineered safeguards actuation system is provided to initiate these systems upon detection of ICCA.
Sufficient redundancy is installed to permit periodic testing of the reactor protective systems and so that failure or removal from service of any one protective system component or portion of the system vill not preclude reactor trip or other safety action when required.
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""RTCAL SYSTES Nor=al, standby and e=ergency sources of auxiliary electrical power are pro-i vided to assure safe and orderly shutdown of the plant and the ability to maintain a safe shutdown condition under all credible circumstances.
1.4.8 RADIQACMVE WASTES The radioactive vaste treatment system is designed so that discharge cf radio-activity to the environment is in accordance with the requirements of 10 CFR, part 2o.
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1.4 9 SHIELDING AND ACCESS CONTROL
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The plant is provided with a centralized' control room having adequate shield-ing to pezzit occusancy during all credible accident situations. The 1-16 Amendment No.'2 5/28/69 4
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re.diation shielding in the plant, in combination with plant radiation control procedures, insures that operating personnel do not receive radiation expo-sures in excess of the applicable li=1ts of 10 GR, Part 20, during nomsl operation ahd =aintenance.
1.k.10 WLT., FAI;DLDG AND STORAGE Fuel handling and storage facilities are provided for the safe handling, stor-age, and shipcent of fael, and viu preclude accidental criticality.
1.k.n PROCESS SIIAM Process stea= frc= the plant win =eet regulations as to radicactivity con-tent, within the applicable 1Nts of 10 CFR, Part 20.
15 RESTARCH AND DEVIID?ME'.'T P20UIRDE.TS The research and develo pent progrs=s that have been initiated to establish final design or to de=enstrate the capability of the design for future opera-tion at a higher power level are sn- -d:ed as fonovs:
151 XENON CSCILIATICNS An analysis to evaluate the possibility of xenon oscillations throughout core life is under way.
A odal analysis to deter =ine critical pa:s=eters has been co=pleted, and the detailed spatial ca'.culations are in progress.
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detemined that such oscillations =ay occur, appropriate design changes to If it is
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eli=inate or control the oscillations vill be incorporated.
See also 3 2.2.2 3
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A.5 2 TEIRMAL AND HYDPAULIC FROGRAMS B&W is conducting a continuous research and develo; cent progn= for heat transfer and fluid flov investigations applicable to the design of the Midland units.
Two important aspects cf this progra= are:
Reactor Vessel Flow Distributien and Pressure Drop Tests a.
e 1/6-scale =odel of the vessel ard i=ternals is under test to
=easure the flow distribution t,,he core, fluid =ixing in the vessel and core, and the distribution of pressure drop within the reactor vessel.
b.
Fuel Asse=bly Heat Transfer and Fluid Flev Test Critical teat flux data have been obtained on single-channel tubular and annular test sections with unifom and nonunifom heat fluxec, and on the =ultiple red fuel asse=blies with uni-fom heat fluxes. - T.ese data have been obtained for a range
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of pressure, te=perature, and = ass velocities enco= passing the reactor design conditions. This work is being extended to
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