ML20092N721

Testimony of Rf Wilson,Dg Slear & Tg Broughton on Issue 1.c (Contention 1.a) Re Method of Determining Power Ascension Limitations.Prof Qualifications Encl.Related Correspondence

ML20092N721
Person / Time
Site:	Crane
Issue date:	06/29/1984
From:	Broughton T, Slear D, Wilson R GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20092N717	List: ML20092N716 ML20092N719 ML20092N721 ML20092N722 ML20092N723 ML20092N724 ML20092N725 ML20092N726
References
83-491-04-OLA, 83-491-4-OLA, OLA, NUDOCS 8407030477
Download: ML20092N721 (14)

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-Before'th'e Atomic Safety and' Licensing Board V <, '.

f' In the Matter.of;

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METROPOLITAN EDISON COMPANY, E AL.

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Docket No. 50-289-OLA c"

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ASLBP 83-491-04-OLA

' (Three Mile, Island Nuclear-

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(Steam Generator Repair)

. Station,< Unit No.:1)

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LICENSEE'S TESTIMONY'OF. RICHARD F. WILSON,

-DAVID G.

SLEAR AND T. GARY;BROUGHTON ON-ISSUE 1.c (CONTENTION 1.a)-

To Mr. Wilson:

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Please' state your name:and address, and; describe your involvement with the TMI-1 steam generator tube repair program.

.A1.,.My name is Richard'F. Wilson.

I am employed by GPU

' Nuclear Corporation, 100 Interpace Parkway,.Parsippany, New i.

LJersey 07054.

As the Vice President of Technical Functions, I

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was. responsible for the overall' project and technical manage--

q y-ment of the'TMI-1 steam. generator. tube repair. program.

A statement of my professional qualifications is attached.

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'Q2. -Please state your name-and. address,,and describe your involvement with.the 'TMI-1 steam generator tube repair program.

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My name is David G.

Slear.s I am employed by GPU Nu-

' clear-Corporation, 100 Interpace Parkway, parsippany, New s

Jersey.07054.

As -the Manager of Engineeiing Proje' cts for TMI-1,-.I was the'ov'erall task-manager for the TMI-1 Steam gen-

.erator tube. repair program reporting directly to the Vice Pres-

'ident o'f Technical Tbnctions.

My responsibilities included all activities associated with the evaluation and repair of the i

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steam generators.

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A statement.of my p,r fessional qualificat[i,ons is ' attached.

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Broughton:

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Q3..Please - state : your name ' and adcIhess'.,'gand describe your

-involvement with the"TMI-1 steain generator repair program.

m My'name,1sT.(daryfBroughton.

I am employed by GPU A3.

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s Nuclear Corporatioh 100 --1ltiterpac'et Paskwdy,' Parsippany, New n's 9

Jersey lO7054.

As. Director of Syst,e.nt,s Engineering, ~I was re -

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.sponsible for providing suppdrt to the' steam generator tube re-pairprogramprimarilyintheNheaofplaiitperformance.

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A statement of my professional qualifications ~'is attached.

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To all' witnesses:

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"What is the purpose'of yo'Gr testimony?

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The purpose' of this tektd. mony is to address Issue 1.c

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,of Contention a: as enumerated' at-p' age 23 of the Bo rd's Memo-randum"and Order,(Rulings on Motions for Summary Disposition, dated' June 1, 1984),-in which the' Licensing. Board sta6ed:

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.The: rationale underlying certain pro-posed license conditions should be addressed,-with attention to:

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Method of determining power ascen-sion limitations.

~QS.

How were the power ascension limitations determined, and.how-do those: limitations relate to the repair of_the steam generators?

AS.

In addressing the bases for determining those power ascension limitations which relate'to the steam generator re-pair, it:is useful to summarize the power ascension / post-i~

critical' test program, indicate the reason for-including spe-cific. tests 2in the program, and describe the rationale for those' limitations.

The proposed license condition concerning power ascension limitations-is set forth as condition B.3.

in the SER, Supple-iment l',

at 27:

GPU Nuclear' Corporation shall complete the post-critical test program at each power range'(0-5%, 5-50%, 50-100%) in conformance with the program described in Topical Re-

. port 008, Rev. 3, and shall~have available-the results of that test program and a sum-

- mary of its management review prior to as-cension from each power range and prior to normal power operation.

As indicated in the proposed license condition, the post-critical test program (described in TR-008, Rev. 3, Appen-dix'A,Section III) consists of three major phases:

0-5%

power, 5-50% power and 50-100% power.

Testing related to the steam generator repair will be performed during the three stages as follows: L:

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-o Low Power Testing During the-first stage, natural circulation testing will be performed to verify the tuning-of the integrated control system to maintain preset' steam generator levels under loss of main feedwater and natural circulation conditions, and proper response

'of the emergency-feedwater (EEW) system.

t Escalation to 50% Power Testing.at this stage will include loss of

.feedwater tests and a reactor coolant sys-

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' tem (RCS) overcooling control test.

Escalktion=to 100% Power "A variety of testsLwill be performed during this period, including the 100% turbine-generator trip.

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The. initial power ascension program:was. developed, prior

tol knowledge of the damage to the steam generators, by consid-ering-test requirements as a result of' core reload, plant modi-fications'made since the plant was last operated, and operator training requirements.

These considerations resulted in a testing. sequence,-power level plateaus and development of spe-cialitests for-plant modifications and operator training.

Pri-mary; factors in determining.the test sequence and plateaus in-cluded verification that core physics parameters are as

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. predicted and that nuclear instruments, the integrated control system and the turbine protective system are calibrated and functioning properly.

-In: conjunction with the steam generator' tube repair pro-

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gram, special pre-critical. tests were developed to demonstrate steam generator operability, including drip tests, bubble

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tests,;pormal. and accelerated fcooldowns (with their transient-

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iloads) land [long. periods of steady state'1eakage monitoring.

These(tests'have now been performed and. evaluated.

The results

- confirmed-the' adequacy of.the repair process and the op-

erabilitploffthe' steam' generators.

' Additionally; the powercascension/ post-critical testing-fprograml described ab've7was reviewed"for its effect on the

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steam [ generators.

Because the pre-critical' testing verified ithe: adequacy'offthe repair.and the operability of the steam Jgenerators, no additional 1 tests were needed in the post-

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.criticalftestiprogram-because of.the repair.

It was-deter-mined, however,?that two 30-day hold periods should be added to 2

the power ascension program.

This' slow progression from power L

-leven to power level has several purposes:

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To-facilitate monitoring. leak rate changes,

especially after-load-inducing transients, whichtwillLprovide'information on the con-diti'on of the.kinetically expanded-joints.

22 To~' detect ab' normal. trends as early in the Lprogram as possible.

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.To slowly increase plant power-and-op-

erating history to aid?in mitigation of

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cunplanned' events.

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To'gainradditional experience in operating the plant with systems in normal line-ups.

.The.first hold period will-occur at-48% power following

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the'RCS overcooling test.

This point was chosen because it im-mediately:follows tests which load the-steam generator tubes

--(loss of feedwater and.RCS' overcooling)-and because it allows V-

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2 1 operation with-two main feed pumps which is the normal plant

-configuration.

The second hold point follows testing at the

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- 75% power plateau. - Leak rate monitoring, surveillance testing and operator familiarity will occur during this hold period.

-Experience from the steam generator pre-critical tests corrobo-s; rated that 30-day hold periods would provide adequate time for stabilizingLthe plant and collecting statistically valid data.

Management reviews are scheduled prior to power increases

following-the 48% power hold period and the 100% turbine trip test.

The purposeoof these reviews is to assure management that the people, plant, facilities and procedures are in a state of readiness such that the plant can be safely operated

-atJthe next power plateau.

These reviews also provide manage-ment the opportunity to review all open items at that time that may have potential impact on power operations.

'Q6.

Are Licensee's power ascension limitations in accor-dance with the recommendations of the Third Party Review (TPR)

' Group?

A6.

Yes.

In its February 18, 1983 report, the TPR recom-mended that:

GPU. Nuclear should consider substantially extended operation at low' power during a

- slow and deliberate power escalation the first time the plant'goes critical.

Although we do not have an analytical basis for a specific duration, a hold period of perhaps a month or more at 40 percent power should.be considered before the Loss of Feedwater/ Turbine Trip test is performed.

This'might-be:followed by another month or more at 70 percent power before final escalation to 100 percent power..

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.Att.'6~.to}he' Staff'sSER,;TPR. February l1983Reportat11-12, Recommendation'.2.

In aceordance with the TPR's recommendations and its own-evaluation 1ofithe. power. ascension program in light of the-re-

. pair', Licensee' determined-to modify the power. ascension program y

(to;addftwo?30-day'holdJper'iods,1one at 48% power and one at~75%

power.

.In.its.May. 16,11983. report, the TPR stated that "[t]he

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-GPULNuclear response is satisfactory."

Att. 6 to the Staff's

- SER,1TPR:May'1983 Report at 7.

fr EThe TPR also recommended.that Licensee " consider the pos-sibility of deliberately running one steam generator at a.

higher power _'hanDthe'other during the first escalation hold t

<pe'riods." iAtt..6 to-the~ Staff's SER,-TPR February 1983 Report

'at 12, Recommendation 3.

The TPR recognized, however, that-

~thisirecommendation "mayfinvolve.other operating considerations which wouldchave to be weighed before a decision could be imade." ' Ibid.

LLicensee explained to the TPR that significant operating WP considerations rendered this suggested approach infeasible and fimprudent.-

InLparticular,_the mismatch can only be implemented I

1by.Loperation of a single reactor coolaat pump in one loop which would cause mismatched : reactor coolant _ system flow, imbalanced feed? flows'and-different coolant levels in each generator.

.This ;could mask changes in the plant conditions, including any abnormalities in the plant response to transients.

This abnor-

. mal plant configuration would conflict with the intent of

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conducting'the.startup-in a slow, deliberate manner under nor-

-- mal operating conditions.

In-response to Licensee's explanation, the TPR stated that

"[t jhe, GPU Nuclear response is. satisfact.ory. " Att. 6 to the Staff's SER, TPR'May 16, 1983 Report at.7.

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' PROFESSIONAL QUALIFICATIONS Richard lF.: Wilson LVicc '.' resident,. Technical ' Functions

-GPU Huclear Corporation

'GPU;3xperience:

1 Technical responsibility for the Engineering, Design, Licensingrand Technical Support of all nuclear generating stations for the GPU System.-.The position manages the technical resources of GPU Nuclear including day-to-day support for plant operations.

Previously was Acting Director for TMI-2 from September, 1979,.to about March, 1980, and before that was Director of the Engineering and Quality Assurance Departments within the GPU

-Service Corporation.

Between-1975 and-1977, was Manager of

! Quality Assurance for the GPU Service Corporation with responsibilities for-design and construction Quality Assurance.

Other Experience:

Prior work experience included two years (1973-1975) as Manager of. Manufacturing Engineering for Offshore Power Systems,-Jacksonville, Florida.

Responsibilities' included activities associated with manufacturing planning, tooling, industrial engineering, manufacturing engineering, and technical support tx) the planned manufacturing facility.

Prior

'tx> joining Offshore Power Systems, held a number of positions at the Atomic International Division of Rockwell International, 1954 to 1973.

Some of these positions included Engineering Supervisor, Department Manager, Chief Project Engineer, Program i

Manager, and Chief Program Engineer on a wide variety of Atomic

. International. programs. 'The last position was Program Manager for the Atomic International work on the fast breeder program.

Performed and' supervised work in almost every facet of reactor engineering, physics,' facility design, safety, reactor operations, etc.

Committee. affiliations have included the EEI QA Task

-Force, the AIF Committee on Power Plant Design, Construction E

and Operation, B&W Plant Owners and BWR Owners Groups, EPRI Nuclear Divisional Committee, etc.

Outside the utility industry has served on a number of company and company / government advisory groups as related to specific programs.

l Education and training includes a B.S. degree in l.

Mechanical Engineering, University of California at Berkeley, 1951; an M.S. degree in Mechanical Engineering, University of Michigan, 1953; and one year attendance at the former Oak Ridge School of Reactor Technology in 1954.

Has attended a

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large number of, management and other courses, including the University of Michigan Public Utility Executive Program.

2-T PROFESSIONAL QUALIFICATIONS DAVID G. SLEAR WORK EXPERIENCE l

Company:-

GPU Nuclear Corporation

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. Title : -

TMI-l Manager Engineering Projects Responsibilities :

Management of TMI-l' modification, which entails:

Management of the $25 million annual budget allocated for plant modifi-cation; prioritization of the various phases of plant modification; overcight of-the technical adequacy of plant modifi-l 1

cation and of the components involved in plant modification; consultation regarding

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problem resolution with respect to matters concerning plant modification; and direct supervisio.. of 16 GPU employees.

This l

position demands constant attention to

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long term and daily plant modification concerns and an extremely firm grasp of l

-both the technical aspects of TMI-Unit 1 i

and of the various modes and components of i

' modification available for implementation i

at TMI-Unit 1.

Dates:

1983 - Present

~ Company:

GPU Nuclear Corporation

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 failure analysis, eddy. current testing, corrosion l

testing, RCS examination, RCS sulfer cleanups, and plant performance analysis.

This position involved direct management of the OTSG repair process and personal involvement L

in the decision making process with respect to the repair program.

This position also l

entailed the definition and implementation of the overall project, and required a broad

-overview and analysis of the OTSG Recovery n

program.

In his capacity as OTSG Repair Project. Manager, Mr. Slear was also called l

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- Professiont.l l Qualifications

Page~Two upon to deliver numerous presentations

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concerning project details before the NRC,

.ACRS, TPR, and the GPU Nuclear Corp.

management.

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Dates: '

December 1981'- November 1983 l

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. Company:

GPU Service Corporation f

Title:

TMI-l Manager Engineering Projects Responsibilities:

. Similar _ to those listed :for Mr. Slear's l

present position including management of a $20 million budget and of project engineer-ing for-modifications..

t Dates,: ~

1979 - 1981 f

Company:

GPU Service Corporation I

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Title:

Preliminary. Engineering Manager

. Responsibilities:

This position entailed: the analysis and preliminary design of 400 Megawatt combustion turbines and of a 600 Megawatt coal fired power plant; extensive analysis of the reliability and availability of the i

components to be installed in the prospec-i tive power plant; and the establishment of l

a baseline criteria document for the designated j

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plants including the technical documentation and presentation of the plant design for management review.

i Dates:

1978 - 1979 I

Company:

GPU Service ' Corporation

Title:

Component Engineer r

Responsibilitie,s:

'This position entailed: the review of design specifications and technical details of products going into TMI-2, including the

. steam generators, pressurizer, main J

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Dav'id G. Sloar LProfessional Qualifications i

-Page Three condensors, cooling towers, reactor vessel, and internals; technical consultation and i

analysis of problems; and review of the l

contractor's design work on new components

. going-into a plant.

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i UNITED STATES' NAVY NUCLEAR ~ SUBMARINE FORCE OFFICER

Title:

Engineer Officer

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Responsibilities :.

This' position entailed: essentially f

primary responsibility and control of the onboard nuclear power plant; control of all i

engineering sections, command of 4 divisions; and supervision of approximately 55 crewmen.

= Dates:

1972 - 1974 l

-Title:

Machinery-Division Officer i

-Responsibilities:

As Machinery Division Officer, Mr. Slear was j

responsible for: all mechanical components of the pri, mary and secondary systems of the i

power plant including the steam generator, reactor,'and drive controls; chemistry control.

of the primary and secondary systems; and the' supervision of.15 crewmen.

Mr. Slear also. served as an Auxiliary Division Officer il in charge of non-nuclear life support systems, and as a Communications Division Officer.

. Dates :.

1968 - 1972 I

s Mr. Slear also attended the Nuclear Power Submarine School 1968, dur ng which time he obtained one year of nuclear i

from 19661

power plant training ~ (6 months classroom, 6 months actual plant

. training) in addition to the submarine qualification program.

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r EDUCATION

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College:

University of Oklahoma i

Degree:

B.S. Mechanical Engineering i

Dates:

1961 - 1966' l

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College

- Stevens' Institute of Technology

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t Degree :

M.S. Mechanical Engineering

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Dates:

1974

.1978

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_ PROFESSIONAL; QUALIFICATIONS

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T.-GARY-BROUGHTON

. Business Address:!

GPU Service Corporation-

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100 Interpace: Parkway

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Parsippany,iNew Jersey 07054

! Education:(

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B.A.,;.. Mathematics, Dartmouth College, 1966.

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-Exherience:

Corporation, November 1982 to Present.

Director: Systems Engineering, GPU Nuclear

Responsible for Systems Engineering Depart-ment activities. including

operating exper-dx

+-

-ience assessment,. operating plant shift technicalmadvisors, nuclear fuels, integrated M

plant analysis, risk and reliability assess-ment, human engineering and process compu-ters..

Systems Analysis Director, GPU Nuclear Cor-hp, poration,- 1981-1982.

Responsible:for human engineering, control o

b and-safety analysis,' operating experience ireview.and operating plant-shift technical-advisors.

Control and Safety Analysis Manager, GPU

-Service. corporation,11978 to 1981.

(Responsible for nuclear safety analysis and-jy integrated thermal, hydraulic and' control system' analysis of' nuclear and fossil plants.

4'

. Supervised on site--technical support ' groups e

.at Three. Mile Island, Unit 2 during the post-accident period.

Safetygand Licensing Engineer,-Safety and Licensing Manager,"GPU Service Corporation, 1976-1978.

Performed and supervised nuclear licensing, environmental licensing and safety analysis for Oyster Creek,.Three-Mile Island ac '

and Forked River plants.

Served as Technical

. Secretary to Oyster Creek.and Three Mile Island. General Office' Review' Boards.

y Officer,.U.S. Navy, 1966 to 1976.

Trained at Naval Nuclear Power School, Proto-type'and Submarine School.

Positions held include Nuclear Propulsion Plant Watch Super-visor, Instructor at DlG prototype plant and Engineering Officer aboard a fast-attack nuclear' submarine.

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Publica'tions:

EPRI CCM-5, RETRAN - A Program for One-Dimensional Transient Thermal-Hydraulic Analyses of Complex Fluid Flow Systems, Volume.4:

Applications, December 1978, Section 6.1, " Analysis of Rapid Cooldown Transient - Three Mile Island Unit 2",

With N.G. Trikouros and J. F.

Harrison.

"The Use of RETRAN to Evaluate Alternate Accident Scenarios at TMI-2", with N.

G.

Trikouros.

Proceeding of the ANS/ ENS Topical Meeting on Thermal Reactor Safety, April 1980, CONF-800403.

"A Real-Time Method for Analyzing Nuclear Power Plant Transients", with P. S. Walsh.

ANS Transactions, Volume 34 TANSAD 34 1-899 (1980).

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