ML20092N723
| ML20092N723 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/29/1984 |
| From: | Croneberger D, Lee D, Lee D, Slear D GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20092N717 | List: |
| References | |
| 83-491-04-OLA, 83-491-4-OLA, OLA, NUDOCS 8407030479 | |
| Download: ML20092N723 (14) | |
Text
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CI MWETC3 UNITED STATES OF AMERICA "Anc NUCLEAR REGULATORY COMMISSION
'R ~3 n;;5 Before the Atomic Safety and Licensing _ Board In the Matter of
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)
METROPOLITAN EDISON COMPANY, ET AL.)
Docket No. 50-289-OLA
)
ASLBP 83-491-04-OLA (Throo Mile Island Nuclear
)
(Steam Generator Repair)
Station, Unit No. 1)
)
LICENSEE'S TESTIMONY OF DOUGLAS E.
- LEE, DON K. CRONEBERGER AND DAVID G.
SLEAR ON ISSUE 2 (CONTENTION 1.a)
To Mr. Loor Q1.
Please stato your name and address, and describo your involvement with the TMI-1 steam generator tubo repair.
A1.
My name in Douglas E. Leo.
I am employed by Babcock
& Wilcox, an operating unit of McDormott, Inc.,
P.O. Box 1260, Lynchburg, Virginia 24505.
I managed the Mechanical Enginear-ing Section of the Engincoring Dopartment.
This noction contained the Mechanical Design Unit that was annigned to de-sign, qualify and implomont the kinotic expansion joint in-ntalled ac part of tho,TMI-1 steam generator tubo repair pro-gram.
A statomont of my profoonional qualifications is attached.
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,3 To Mr. Croneberger:
f Q2.,,PleaseEstate'your name and~ address, and' describe your involvement'with the TMI-l steam generator tube repair program.
A2.
My'name is Don K. Croneberger.
I am employed by GPU T'
e.
. Nuclear Corporation, 100 Int 6tpace Parkway, Parsippany, New N
Jersey 07054.
-As~thA Director of Engineering and Design, I s
provided technical--management over'5ight of the failure analysis
.and repair activities with.'special emphasis on evaluation of the steam ~ generator's mechanical design and the impact of any indwelling'deYects on.$he re"sponse of'the components.
More-
-over, : my dypartment provided eriginceEing support in the areas
.of Materials Engineering / Failure Analysis, Chemical Engineer-Ling, Mech'anical EngineeringLand Engineering Mechanics.
.,v.
A. statement of my professional. qualifications is attached.
-To Mr. Sleari Q3 '. -Please state'.your-'name'and address, and describe your
. involvement with the TMI-1 stdam generator tube repair program.
~
A3.
My name is, David G.
Slear.
I a.m employed by GPU Nu-clear _ Corporation,.100'Interpace' Parkway, Parsippany, New
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-Jersey 0705'4.. I.am the Manager of Engineering Projects for c
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-y lTMI-1.
As'suc,h,dI'was the overall: task manager for the TMI s..
- OTSG Tube' Repalr~ ProgFam re,. d,1ng directly to the Vice Presi-
~
%q dentJof'Tec$nical Functions.
'My respensibilitie's included all s
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. activities :. associated with~the evaluation and repair -of the
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steam. generators. m s, -
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-:A statement of-my professional qualifications is attached.
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To !all witnes'ses:
. Q4 - 'What'is the purpose of.your testimony?
A4.
The purpose of this1 testimony is to address Iscue'2 of Contention 1.a as enumerated at page 23 of the Board's Memo-randum-and Orderf(Rulings on Motions for Summary Disposition,
' dated' June 1, 1984), in which the Licensing Board stated:
2.
The effect of inadvertent initiation of emergency feedwater flow at high power or following rapid cooldown
=after a LOCA should be addressed, with attention to calculation of maximum transient stresses in steam generator
. tubes.
QS.
Would inadvertent initiation of emergency'feedwater flow while the plant is_ operating at full power cause rupture of a-steam. generator tube?
AS.
No.
Inadvertent actuation of the emergency feedwater (EFW) system at full power, i.e.,
a failure that results in starting of the EFW pumps while the plant is operating normally at; full-power, will not result in the injection of emergency feedwater into the' steam' generators.
The design of the TMI-1 EFW system is such that'once the EFW pumps are started, the ac-
-tua'l flow to the steam generators is controlled by automatic valves which respond to a flow demand signal generated by-the
~
steam generator level control system.
The water level in the steam generator at' conditions of power operation is higher than the steam generator EFW level setpoint at which the EFW flow
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' control-. valves-are initiated to open.
The EFW pumps are
- started by signals other than and independent of the steam gen-
-erator water' level.
Therefore, inadvertent actuation of the Li !
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9
..EFW pumps will not result in EFW injection into the steam gen-erators and will not result in any change to the steam genera-
-tor tube stresses.
-Nevertheless, for purposes of discussion, even if we were to; assume both inadvertent actuation of the EFW pumps and inad-
'vertent opening of the EFW valves, resulting in' injection of emergency feedwater into the steam generators at full power--a highly-unlikely event--the resulting thermally induced axial t
tube load would not be sufficient to cause rupture of the steam generator tubes.
Emergency feedwater is injected' horizontally into the
. steam' generator tube bundle steam-space via six auxiliary feedwater nozzles located at approximately equal spacing around the. circumference of the steam generator shell.
The nozzles I
have a 2-1/2" diameter throat with a 4" diameter flow expan-
~
sion.
The injection points are-located'near the top of the tube bu,ndle with the nozzle centerlines 2'11" below the bottem surface 6f the upper tube sheet.
As the EFW is injected into
~
~
the steam space in the. tube bundle, upward turbulent steam flow quickly heats and partially vaporizes the water before it Treach'es the top of the steam generator.
At.the top of the steam generator, there is a horizontal steam flow from the cen-ter.to the periphery of the steam generator.
This horizontal steam flow prevents any-residual EFW liquid,'which is now at saturation 1 temperature, from reaching the upper tubesheet and thus itiwould not contact any repair joints of the steam generator tubes, all of which are within the upper tubesheet..-.
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,fThe auxiliary feedwater nozzles penetrate the steam gener-ator shell and pass;through the steam annulus between the steam Jgenerator shell'and the tube. bundle shroud.
As incoming emer-
-_gency feedwater passes through the nozzles and enters the tube bundle steam space, the high heat transfer rate from the steam
.toJthe incoming water.quickly heats the water.
By the time
-that the EFW reaches the tubes, it is approaching the same tem-
.perature as the secondary side steam.
Thus, the affected tubes
- experience only a small temperature change in the small portion of the-tube-being' sprayed, which results in an insignificant
- axial: load change in the tube.
Temperature measurements taken
~
at an~ operating steam generator during EFW injection confirm that t'he temperature change of the affected tubes and thus the
, change in tube axial load is minimal.
=The absence.of'any significant load change can be addressed quantitatively by making'some extremely unrealistic a
--and. con'servative assumptions.
If we were to ignore the turbu-
~ ~
rient and superheated steam' environment and assume that unheated
~
. emergency;feedwater.(40*F minimum) were able to be sprayed di-rectly on the tubes, the' water would impinge directly on only
~
If we were about'eight tubes. opposite each individual nozzle.
~
-further1to assume that water spray from the 4"-diameter nozzles causes impingemention a 12-inch length of each tube, the cool-
"ing effect has been~ conservatively calculated to produce an ap-proximate change in. axial. tube load of only 70 pounds tension.
This tensile load,Lin conjunction with the loads on the
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affected tubes'at full power operation, which are at less than 100(pounds. tension,.is insignificant compared to the joint de-
-signian'd qualification loadiof 3140 pounds tension, or cooldown.
tload -of L1100 pounds tension. - Thus,: EFW injection into the steam generators does notLinduce large changes in tube axial
+1oads'andfdoes.not.cause rupture of,a steam. generator tube..
t Q6.
Has the probabilityLof the-tube. rupture.during the
~'
. rapid cooldown;following a loss of coolant accident (LOCA) been Jincreased by the repair procedure?
-Ai6.
.;No.
The maximum transient loads on the-steam genera-
. torftubes following a LOCA have been conservatively calculated
'.to be 26'41 pounds.
These calculations included the effects of
~
- EFWLinjection into the tube-bundle..This load is considerably
' flesslthanfthe design basis load of 3140 pounds to which the re-,
3
- pair joint'was; designed and qualified.
'The maximum transient Lloadrandithefdesign~ basis load.are'the same for both the re-
- paired tubeslandithe. tub'e~s-in the original design condition.
?Therefore,.the likelihood ofstube rupture during a rapid cool-
- down-lfollowing a LOCA'has not.been increased'by the repair pro-
..n
- cedure.
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PROFESSIONAL QUALIFICATIONS I
f DOUGLAS E. LEE.
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EXPERIENCE i
Babcock & Wilcox Company t
(Current Assignment) Manager, Engineering Department --
Responsible for engineering activities involving system design, performance analysis, component design and structural / stress analysis in' support.of B&W supplied engineering services and engineered service products.
Responsibilities also include engineering efforts to complete nuclear steam supply system backlog contracts in the above areas.
Responsible to define i
and' implement research programs to maintain and advance base technology,-develop new products and services and to automate i
engineering functions.
Work is managed to be in accordance j
with. customer, regulatory and quality assurance requirements.
l Managed the efforts of 250 professionals organized into three l
~
- secti,ons and ten units.
i(1982 - 1983) Manager, Mechanical Engineering Section -
)
Reponsible for reactor component and reactor accessory i
equipment mechanical design, specification, acquisition hardware and related engineering services.
Also responsible
- for component performance'such as steam generator tube l
- integrity _and for reactor plant materials and chemistry.
l Defined and implemented research programs to maintain and strengthen materials and chemistry technology.. Work is managed
[
'to be in accordance with contractural, internal and quality l
assurance requirements.
Managing the-efforts of about 90 t
professionals in four working units.
(1980 - 1982) Manager, Plant Engineering Section - Responsible 6
to provide competitive, quality-engineered nuclear power plant and system level engineering design and analysis including reliability and risk evaluations.
Responsibilities included j
system design' requirements and functional design, performance and safety analyses, preparation of appropriate SAR materials, defining and. implementing computer code' development programs, resolving operational problems and developing operator
(
guidelines to safely manage the plant during anticipated transients.. -Work was managed to be in accordance with contractual and quality assurance rec;uirements.
Managed the efforts of approximately 110 profess.4.onals in six working
-, units.
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~(1980) Manager, Equipment Engineering Section - Responsible to
. develop,.specify, standardize, license and provide competitive, reliable,. quality-engineered equipment and equipment related services for plant protection, control, monitoring and display, for reactor coolant system and auxiliary system operation, and for-fuel storage activities which comply with contractual obligations, satisfy customer needs, meet plant and system performance. requirements and meet applicable quality assurance requirements.- -Managed the efforts of approximately 50 l
professionals in three working technical units.
.(1978 - 1980) Manager, Fluid Systems Unit - Unit responsible l
- for.NSSS auxiliary system design, hardware specification and procurement.
Specific systems are makeup, chemical addition,
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decay heat, emergency safeguard cooling and waste processing.
Hardware responsibilities include valves, heat exchangers, tanks, domineralizers and filters.
Work was managed in i'
accordance with technical,_ contractual and quality assurance requirements.
Directly managed the efforts of 15-20
. professionals.
l (1978) Associate Project Manager - Responsible for portions of t
the NSSS being supplied to the Pcwer Authority of the State of New York for the Greene County Nuclear Power Plant.
Plant
- design and licensing reached the stage of meeting the requirements for a construction permit.
(1977 - 1978) Site Coordinator - Temporarily assigned to TMI-2 oto organize and coordinate site efforts to install
. accelerometers and strain gages in the primary side of a steam j
generator for.the purpose of measuring-tube vibration.
Work j
included supervision of craft personnel, planning and coordination with customer, site personnel and B&W design j
engineering to complete the installation prior to reactor start-up.
(1975 - 1977) Associate Project Manager, NSSS supplied to Power
- Authority of the State of New York.
Responsibilities included i
ensuring that the accessory equipment portion of the B&W scope of-supply is technically acceptable, delivered on time and I
delivered within the contract budget.
Contract in the detailed
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. design. phase requiring frequent, detailed interface with the
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Architect Engineer as well as project direction of engineers in l
' matrix organization assigned to the contract.
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'(1974' - 1975) Generic Project Manager - Responsibilities' included identifying items with-potential risk impact (cost increases) to backlog NSSS contracts and driving these problems to a least impact solution, managing selected programs designed l
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J' to minimiza coat impacts to backlog contracts, and performing r
assigned Project Management Department projects.
Key feature of assignment was to work across NSSS contracts to identify and-minimize contract risk.
(1973 - 1974) Auxiliary Systems Engineer - Responsible for the system design and equipment-procurement for reactor support fluid systems such as makeup and decay heat.
Work included preparing system descriptions, PSAR material, equipment specifications and obtaining quotations for the Toledo Units 2 and 3-(NSS-25 & 26) project as well as providing support for the Toledo Unit 1 (NSS-14) project.
Achieved the functional level of Task Engineer in this assignment.
Division of Naval Reactors, USAEC l
(1968 - 1973) Engineer in the Refueling Branch - Responsible for supervising prime contractor organizations in the refueling and maintenance of U.S. Navy and AEC nuclear reactors.
This wor.k includes technical responsibility for the development of refueling systems, for planning and following refueling work and for design and procurement of specialized refueling equipment.
Work with equipment ranged from approving initial equipment design concepts and specifications through use of the equipment by field organizations such as shipyards.
Have
-extensive experience in planning, design, procurement and use of special purpose weld cutting and welding machines.
EDUCATION University of Virginia, Charlottesville, Virginia B.S. degree in Engineering, graduated with distinction in June, 1968.
Majored in aerospace engineering.
Dean's List, elected to Tau Beta Pi Honorary engineering fraternity.
Naval Reserve Officer's Training Corps scholarship program.
Midshipman Battalion Commander.
Awarded the Commanding Officer's Sword as the outstanding midshipman.
Lynchburg College, Lynchburg, Virginia Master of Business Administration in May, 1980.
Subject area was Management Control.
MILITARY SERVICE Commissioned Ensign, USN in June, 1968 upon graduation from college.
Assigned duty with the Division of Naval Reactors, USAEC, Washington, D.C.
Earned a certificate from the Bettis
-s.
f Reactor Engineering School,.'Pittsburgh, Pennsylvania in June, 1969.
Promoted to grade of Lieutenant in June, 1971.
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A PROFESSIONAL-QUALIFICATIONS
,-Don _K.;Croneberger
.. Director,- Engineering.& Design GPU Nuclear Corporation
- GPU Experience
- :
-Technical responsibility forfthe Mechanical, Electrical, IF Civil / Structural, Chemical, Radwaste:and Materials Engineering
, support'for all nuclear generating stations for the GPU Systems.
1978 to 1980 was Manager
~ Der,ign~ and' later Manager -
Engineering & Design,with'-GPU Service Corporation.
Directed
, design. engineering activities for all nuclear and-fossil power
. generating facilities,andl modifications' assigned to GPUSC.
Other Experience:
)
i Prior work experience' included a number of positions at
._ Gilbert / Commonwealth.during the period 1963 The last'
. position was Manager Structural Engineerinc,'to 1978.
-It included
. technical 1 responsibility for; structural engineering mechanics
^for all nuclear and fossil generating _ facilities.
Some of the
.other positions included Project. Manager for balance of. plant studies for anliquid metal-fast breeder reactor demonstration
- plant.- OtherEpositions as-Project Structural Engineer included 1 responsibility for~ technical supervision of. structural l
. engineering and engineering mechanics for a number of domestic
.j
-nuclear power; plants.
Earlier experience with-the U.S. Navy-included engineering and construction of radio telescope and f
t ancillary experience.
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Industry affiliations.have' included the EPRI Steam
' ; Generator Owners' Group, ASME Section 3 Division 2 (former' Chairman) and other industry nuclear. standards activities
. including Nuclear Structures and Plant Design Against Missiles.
9 Education'and training includes a B.S. degree in Civil-Engineering-from Pennsylvania State University, 1959.
Other technical training includes courses at U.C.L.A., M.I.T. and
'4*'
.the University of Michigan.
[
i I have been involved in the Steam Generator tube failure l
issue from the beginning.
'I provided technical management oversight of failure analysis'and repair activities.
Special
~
emphasis was placed on-understanding the mechanical design of the Steam Generators and applying that understanding to the repair program and the understanding of the impact of the repair on the response of_the components.
My department provided engineering support in the areas of Materials Engineering / Failure Analysis, Chemical Engineering and Chemistry, Mechanical Engineering and Engineering Mechanics.
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PROFESSIONAL QUALIFICATIONS DAVID G. SLEAR WORK'EXPEKDENC2 Company:
GPU Nuclear Corporation i
Title :
TMI-l Manager' Engineering Projects Responsibilities :
Management of TMI-l modification, which f
entails:
Management of the $25 million annual budget allocated for plant modifi-cation; prioritization of'the various phases of plant modification; oversight of the technical adequacy of plant modifi-cation and of the components involved in plant modification;-consultation regarding problem resolution with respect to matters
'I concerning plant modification; and direct supervision of 16 GPU employees.
This position demands constant attention to i
~
long term and daily plant modification concerns and an extremely firm grasp of I
'both the technical aspects of TMI-Unit 1 and of the various modes and components of modification available for implementation at TMI-Unit 1.
Dates:
1983 - Present Company:
GPU Nuclear Corporation j
t t
Title:
OTSG Repair Project Manager Responsibilities :~
Management (in conjunction with individual task managers) of all aspects of the OTSG Recovery program at TMI-l including f ailure analysis, eddy' current testing, corrosion testing, RCS examination, RCS sulfer cleanups, and plant performance analysis.
This position involved direct management of the i
OTSG repair process and personal involvement in. the decision making process with respect to the repair program.
This position also entailed the definition and implementation i
of the overall project, and required a broad overview and analysis of the OTSG Recovery
- program.
In his capacity as OTSG Repair Project Manager, Mr. Slear was also called i
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I David G.-Slear
. Professional Qualifications
' Page Two upon to deliver numerous presentations concerning project details before the NRC, ACRS, TPR, and the GPU Nuclear Corp.
management.
Dates:
~ December.1981 - November 1983 Company:
GPU Service Corporation
Title:
TMI-1 Manager Engineering Projects Responsibilities:
Similar to those listed for Mr. Slear's present position including management of a $20 million budget and of project engineer-ing for modifications.
Dates:
1979 - 1981
- Company:
GPU. Service Corporation
~
Title:
~
Preliminary Engineering Manager 4
Responsibilities:
This~ position entailed: the analysis and.
I preliminary design of 400 Megawatt
{
combustion turbines and of a 600 Megawatt coal fired power plant; extensive analysis l
of the reliability and availability of.the.
components to be installed in the prospec-tive power plant; and the establishment of a-baseline criteria document for the designated plants including the technical documentation and presentation of the plant design for management review.
Dates:
1978 - 1979 i-l Company:
GPU Service Corporation
Title:
. Component Engineer
- Responsibilitie,s:
This position entailed: the review of design specifications and technical details of products going into TMI-2, including the L
L
- steam generators, pressurizer, main l
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' David G. Slear Professional-Qualifications
- Page Three condensors, cooling towers, reactor vessel, and' internals; technical consultation and I
analysis of problems; and review of the contractor's design work on new components going into a plant.
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-UNITED STATES NAVY NUCLEAR SUBMARINE FORCE OFFICER
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l
Title:
Engineer Officer
)
Responsibilities :'
This position entailed: essentially j
primary responsibility and control of : the i
onboard nuclear power plant; control of all l
engineering sections, cormnand of 4 divisions; 1
L and supervision ~of approximately 55 crewmen.
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Dates: ~
1972 - 1974 t
Title:
Machinery Division Officer e
Responsibilities:-
As~ Machinery Division Officer, Mr. Slear was responsible for: all mechanical components of the: primary and secondary systems of the power plant including - the steam generator, L
' reactor, and drive controls; chemistry control
~
of the primary and secondary systems; and
[
the supervision of 15 crewmen.
Mr. Slear
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'also served-as an. Auxiliary Division Officer
'in charge of non-nuclear life rupport systems, and as a Communications Division Officer.
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~
Dates:
1968 - 1972 Mr. Slear also attended the Nuclear Power Submarine School l
g l
from--1966 - 1968, during which time'he obtained one year of nuclear L
power plant training (6 months.-classroom, 6 months actual plant t
xtraining). in addition to the submarine qualification program.
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EDUCATION j
College:
University of' Oklahoma i
Degree:
B.S. Mechanical Engineering l
l --
l Dates:
1961 - 1966 i
College:
Stevens Institute of Technology i
l Degree:
M.S. Mechanical Engineering i
Dates:
1974
.1978
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