ML19220C763
| ML19220C763 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/28/1977 |
| From: | Mcgurren H NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Linenberger G, Luton E, Salo E Atomic Safety and Licensing Board Panel, WASHINGTON UNIV., ST. LOUIS, MO |
| References | |
| NUDOCS 7905140212 | |
| Download: ML19220C763 (23) | |
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April 28,1977 Edwar 1 Luton, Esq., Chairman Mr. Ernest O. Salo Atomic Safety and Licensing Board Professor, Fisheries Rese.> rch U.S. ?!uelear Rer;ulutory Commission Institute, WH-10 Eshin;; ton, D. C. 2G535 Collece of Fisheries University of Washington Mr. Gustave A. Linenberger Seattle, Wshington 98195 Atomic Safety anti Licensing Board U.S. Nuclear Regulatory Couunission Washington, D. C.
20555 In the Matter of Metropolitan Edison Com-any, et al.
(Three Mile Island Nuclear 5tation, Unit 2)
Docket No. 50-320 Gentlemen:
The purpose of this letter is to inform this Beard, the parties and the Commen-wealth of Pcnnsylvania of certain changcc and additicns regarding presentation of NRC Staff testimony and responses to Board questions at the Three Mile I
Island, Unit 2 hearing scheduled to reconvene May 2, L977. These changes and additions are set forth below:
1.
Dr. Kieth Eckerman and Dr. Frank Congel will address the Board question concerning Regulatcry Guide 1.109 (Professional Qualifications are attached).
2.
Wayne Britz will join Joseph II. Osloond and Phillip Stoddard in presentation of NRC Staff testimony re-garding the environmental monitoring aspects of Contention 6 and join Joceph II. Oulcond in his response to the Board's question concerning Short Time " Samples". (Wayne Brit:'s Professional 106 2/o Qualifications are attached).
3.
Willi.ua Regan will repl.1ce Jan I' n cis for the Etaft's pre-uent tion of testimony on Centennen 3 cir.ce.!an Morris "eill not be avc.ilable. G.illiam Regan's Promsaional om 1 b i atin n a - -,inchadi.
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Wayne Ilouston will 1 eplace C. Richan Van Niel for the Staff's presentation of testimony on Contention 6 (as to radiological monitoring) and Contention 8 cince Mr. Van Niel will not be available. (Wayne Houston's Professional Qualifications are attached).
5.
Anthony H. Fasano will join Lewis Narrow and Alvin B. Davis in the Staff's response to the Board question concerning quality of construction of Three Mile Island, Unit 2.
(Mr. Fasano's Professional Qualifications are attach ed).
Also attached are copies of the NRC Staff responses to the following Board ques-tions (1) concerning the impact of financial considerations on safe operation of Three Mile Island, Unit 2 to be sponsored by Harley Silver and (2) concerning aircraft hazard to be sponsored by Delbert Lunch. (A copy of Delbert Bunch's Professional Qualifications are attached).
Sincerely, f
Hen. y J. McGurren Cour.ael for NRC Staff
Enclosures:
As stated cc w/cnclosures.
Mr. Chancey R. Kcpford Ms. Judith H. Johnsrud Ms. Karin W. Carter Atomic Safety and Licensing George F. Trowbridge, Esq.
Appeal Panel Atomic Safety and Licensing Docketing and Service Section Board Panel DISTRIBUTION:
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i R. Wayne Houston j
Professional Qualifications I am employed as Chief of the Emergency Planning branch in the Office of !!uclear Reactor regulation, U.S. i!uclear Regulatory Ccmmission, Washington, D.C.
My responsibility includes technical directicn, super-vision, and Branch leadership for the develcpment and application of procedures to evaluate technical and adr.:inistrative comaetence of reactor operating organizaticns in the interest of public health and safety.
The scope of this responsibility enccr: asses a comprehensive knowledge of the principles, theory, and practices in the field c' nuclear engineering with specific knculedge of the safety aspects of reactor facilities, adminis-tratica, training, and procedures, particularly as they relate to plans for coping with cmergencies that might arise during the operation of such facilities.
I attended Yale University, majoring in Chemical Engineering, and h?ve both Bachelor's and Dcctoral degrecs.
Between 1949 and 1951, I was employed as a Research Asscciate at the General Electric Company's Kncils Atomic Power Laboratory where I participated in rescarch and develocment activities associated with their 1:ealth Ph sics program.
This included S
particle size analysis of airborne particuiate materials, bicassey orc-cedures, and iodine tonitoring techniques for dissolver off-gas systcm.s.
From 1951 to 1954, I was Assistant Professor of Chemical Engineering at Columbia University and participated in the introduction and teaching of nuclear engintering courses at the graduate level.
During the first two years of this period, I was also a consulttnt to the Columbia Heat Transfer Project Grcun that perforzd burn-cut studies in connection t 'th the Savannah River project that was then underray.
Following one year in a similar pcsition at the University of I;ew Hamoshire, I became an Associate Professor of Cnemical Encineering at tne University of Pennsylvania there I developed severai nuclear engineering courses and a comprehensive i:,b-oratory course in this field.
In 1960, I became Laboratory Director of a five megawatt nuclear research reactor facility in Plainsboro, I!ew Jersey, which was ocerated under con-tract by Columbia University.
Simultaneously, I became Professor of Chemical Engineering at Colunbia and a member of its Division of I:uclear Engineering.
I continued teaching on a part-time basis, particularly in the area of nuclear reactor physics and kinctics, and conducted operating experience laboratory courses at the reactor facility until 1957.
I had total onsite manacenent responsibility for the reactor facility from 1960 through 1971, under successive changes in cupership, becoming Vice President in 1967 of InCustrial I.cactor Laberatories, Inc., and Fresident in 1971.
In additio:1 to serving on IRL's c..n revicw and audit committce 106 250
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throughout this period, I was a member of Columbia's Reactor Safety Ccm-mittee from 1960 to 1967.
During the last three years of this period, I was extensively involved in the development of traini.:g plans for three major utility companies in the New Jersey - Pennsylvania area.
I joined the Regulatory staff of the Atonic Energy Cor. mission in January 1972, as a Lead Reactor Safety Engineer in the Operaticnal Safety Granch, becoming Chief in October 1972.
The Branch was reorganized in April 1974 to place inciee_ed emphasis and attention uppn the areas of physical security and coargency planning and again in !< arch 1977 to consulidate NRC staff efforts in the area of emergency planning cnd preparedness.
I have participated extensively in the preparation of "RC guidance documents Gn emergency planning, supervised the staff reviews and eval-uatiens of the plans for coping with emergencies at the majority of licensed nuclear power reactor sites in the United States, and given lectures and talks on the subject of emargency planning at numerous meetings, symposia, and short courses.
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..m PR0/ESMCnal glAi.IFiCAriO'15 Keith F. Eckerman I am a Radiation Physicist with the RA3 staff of the Nuclear Ragulatory Cc:r issicn. My duties includa the review of Envirnnmental Recorts VS M.i a v;jgart o f ' n: m 3 mp;licati..;. *i
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the pr.:: iration n;:d processing of staff statsents in suppvt cf liccasing furctions.
In additic.* I have the respnnsibility for development of transport models to define the distribution and upta':e of radioactive ma terials in the envircement.
I joined the Ccruissica, then the Atcmic Energy Cc.7 mission, in October of 1974.
Since January'of 1972 I have participated in the evaluation of the radiological inpact of various nucleer facilities.
I am currently a vmaber of Ail 5-18l2 (American Mational St2ndards) subccmmittee !ho is charged wi th development of standards with respect to ccm.outation techniques for inferring environmental doses.
I have a Cachelor of Science Cagree in chemistry and mathema tics frca the University of Uisconsin at Platteville (1952),. a Master of Science Degree in physics frca Marquette Unitersity (1957), and a Doctor of Philosophy Cagre" in Environmental Health Engineering frcm Ucrthwestern University (1972).
Frca 1952-1055, I uas employed by the Harren, Illinois High Sc% col Distri'ct as an instructor of mathematics, chemistry, and physics.
During tr.a su. crees of 1954-1957, I attended an NSF institute at Marquette Universi ty.
Durirr. the acadenic year 1965-1957, I attended :ne Oak Ridre Instituta of Nuclear Studies.
I was involved in several research projacts using accelerators at the University of Georgia and the Oak Ridge.lational Laboratory.
From 1957-1972, I was a graduate student at Northwestern Universi ty.
I was associated with the Argonne National Laboratory in various positions from 1958 to 1974; during the period 1970-1972, as a j
' AUA-A'il Predoc:cral Fellow and from 1972 to 1974 as an Environmental l
Scientist with the Environmental Statement Project.
During these periods,
.research in the general area of dosimetry and measurement of internal l
. deposited low energy emitters was conducted.
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I am a cember of the Health Physics Society.
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7 PROFESSIONAL QUALIFICATI0"5 p_eraldB.Zwetzio OPERATING RE ACTORS BPA"CH NO. 4 DIV)SID" 0F OPERATI"G RETCTORS '
0FFICE OF ':"CElR ~ REACT 0? RE0"L ATIC1 NUClFAR REGULATORY CF'"<!SSIC1, I cm a Project Manacer on the staff of the Division of Onerating Reactors, Office of "uclear Rcactor Regulation, U. S. !!uclear Regulatory Ccomissicn.
My primary respcnsibility is the canagement of licensing actions and the evaluation of cccccmitant safety considerations for operating
. reactors to assure that such actions do not adversely affect the health and safety of the public.
I have primary responsibility for Three Mile Island Unit No. I and have been with the NRC in that s
position since Junc 1976.
I received the degree of Bachelor of Science in "aval Technology fecn the University of "i:,2:0:a in 1926.
I also received the d gree of Master of Biorccicl ;y frca the University of Cclifornia atDrke:ey in 1951.
I have cro!cted studies ir nuclear engincering cnd rel:ted engineering suajects cnd am a registerec professional engineer 1r i
c2chanic;l engiceering in the state of California.
Upon leaving milittry service in 1955, I joined the Atomics International Division of Rcckweil Internaticnal ';here I was engaged ir varicus areas, including he2it: ;nysics, experimental p.hysics, advanced concept evaluation and L"FER safety.
In 1971.1 joined the General Atcmic Company where ny principal duties involved licensing activities related to High Temperature Gas-Cooled Reactors.
I have been a member of the American "uclear Society since 1957.
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I UNITED STATES OF AMERICA NUCLEAR RECULATORY CO..:..IISSION i
l TilREE MILE ISLAND NUCLE /sR STATION, UNIT NO. 2 DOCKET I:0. 50-320 TESTIMONY OF NRC STAFF ON OPERATION OF TliREE MILE ISLAND. UNIT 1 by GERALD B. Z'!ET2IG This testimony responds to the follov/ing Licensing Board question stated at the January 28, 1977 pre-hearing conference (Tr 137-3S) to the e:: tent it relates to the operat.ng experience of Three Mile Island, Unit 1:
Specifically, the Board would like to request both Staff and..pplicar t i: address themselves to the considerrticas of what has been done and is being done to assure that the quality of construction and the reliability of operation, assuming an operating license issues, will not be compromised by the slow 410wn and the construction stretch out of ccustruction schedule.
.In the same context, I think it would be helpful for the Applicant to review just briefly what the opera-ting experience has been with unit (sic], and of course, the Staff would be free to comment on that to any extent they wish.
Metropolitan Edison Company declared TMI-1 to be in commercial operation on September 2,1974. During the first year of operation, svhich did not include a refueling outage, the Unit Availability Factor, which is a measure 106 254
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1 i j of overall plant reliability, was reperted to be 87t. The cumulative Unit f
Availability Factor, from the start of operation through December,1976, I
I (which included one refueling outage) was reported to be 75.8% The 4
cumulative Reactor Availability Factor (which is a measure of the reliability of the reactor portion of the plant) over this same period was reported to be 80.5%
Of these, six During 1975 nineteen reactor shutdowns were reported.
shutdowns required the plant to be at cro power in excess of one day.
The longest reported micrval at zero power was 17 days which was the Three of the other time required to repair a large river water pump.
reported shutdowns, ranging from 4 to 12 days duration, involved repairs to control rod drive units.
During 1976, a total of eight reactor shutdowns were reported. Of these, two were of extended duration. The shutdown for the first refueling of the plant, which was scheduled to take about eight weeks (beginning February 20, 1976) actually extended to about thirteen weeks. Much of the extra time involved in this shutdown resulted from the discovery that the reactor vessel surveillance specimen holders were damaged and the The subsequent need to remove the specimens and damaged holders.
second extended shutdown occurred in November 1976 and lasted about one month. This shutdown was required to repair a valve in the decay heat
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removal system, to perform repairs on the condenser and to repai2 cracks in some of the buried piping adjacent to the river water intake structure.
Based on the experience of other nuclear plants in commercial operation, it is concluded that the plant outages experienced thus far at T.'.!I-l are within the normal range. Based on operating statistics, it can be concluded that the reported cumulative Unit Availability Factor for TMI-l through December 1976 is slightly above the average value for all plants in commercial operation.
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s FRMu' J. C050EL P.... L"a d' 10.',~ :'w' q' U'.'.' ' " v~ 'o' ' 10 ".. a' a.:
I am the Section leader of the Radiological Impact Section in the Offica of Nuclear Reactor Regulation, Nuclear Regulatory Cornission.
My responsibilities include supervision of, as uell as direct participation in the technical review and evaluation of the environmental radiological inpac: associated with reactor and other fuel cycle facility operation.
I was born in Syracuse, New York.
My undergraduata study was done at Le Moyne College, Syracuse, N.
Y., where I received the 3.S. degree in Physica in 1964.
I entered the physics graduate departtent of Clarkson College of Technology, Potsdaa, N29 York, and received the M.S. degree in 1967 and the Ph.D. dagree in 1962 Both degrees include a concentratica in nuclear physics and a cinor 'n catheaatics.
t After cc pleting the Ph.D. degree requirements, I accepted an appointr.ent as a postdoctoral research assistant in the Radiological Physics Divicica
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of the Argonne Na tional Labora tory, Argonne, Illinois.
During cy nine-month stay at the laboratory, I bas engsged in a project 9
to deternine the cnvirenmental neutron flux.
This work included both instrumentacion design and data analysis and interpretation.
I subsequently accepted an academic position in the Physics Department of Malcalester College,
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I contina.-d fundanental ras-: arch at the college and alco-taught physics courses to undergraduates at all levels.
!!y research c:<panded to include reasurenent and interpretation "
of ganna ray spectra in the vicinity of electrical generating stations.
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In February, 1972, I accepted a position with the U.S. Atonic Energy Co=2iccio n, Re3ulatory.
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A ilILLI AM 11. RECA?l, JR.
DIVISICM OF SITE SAFETY A :D E NIRONFUTAL AD.'. LYSIS U. S. f:UCLEAR REGULATOC C0 NI5310'l PROFESSIO:!AL QUAU n CAT 10'IS
!!y name is llillian 11. Regan, Jr.
I am C iicf of Environmental Projects 2 of the Division of Site Safety and Environmental Analysis, Branch I:3.
United States !!uclear Regulatory Corr;nission.
In this capacity, I am respcn-sible for managing and coordina;.ing the review of applicant's erivironmental reports and the preparation of !!RC Enviro m atti Statea.cnts which acet the requirements of the !! EPA and the requirements of 10 CFR part 51, in connection with applications to the Co=iission for construction peraitr. or operating licenses for nuclear power reactors.
I hold a Ecchelor of Chemical Engineering Degree from Villanova University.
I have nad more than twenty-five years of professional experience in the nuclear field / For ten years I was employed as an associate chemical engineer on the scientific staff of the l'uclear Engineering Departmcnt.
Brookhaven t,'ational Labora'ory.
During my e;,ployment at Drookhavcn, I was responsible for the conduct. of original research and develo;aent in the areas of treatment and ultimate siisposa' of high level radioactive vaste, chemical reprocessing of nuclear fueh, and. fluidized bed technslogy as applied to both advanced p'cwcr reactor fuels and nuclear rocket pra-pulsion.
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.mm 2-In 1951, I joined the staff of the Division of Reactor Development, f
s U. S. Atomic Energy Cormission, as a chemical engineer in the Environ-mental and Sanitary Engineering Branch.
During ny employant in this Branch, I was responsible for the Cornission's Civilian Power research and development prcgrams in the areas of high level waste treatment and disposal, as well as certain programs relating to environmental aspects of aerospace safety and nuclear power reacters.
In 1966 I transferred to the Fucl Recycle Branch of Reactor Development and Technology, where I was responsible for direct. ion of research and development programs in the areas of advanc'cd fuel reprocessing, fuel refabrication and recycle, and waste management.
In Mover.6er of 1971 I accepted a positica uith the Regulatory staff of the Atomic Energy Comilission as an environnental Project lianager and was responsible for preparation of environmental s.tatements for Metropolitan Edison's Three Mile Island Station, Units l_ cnd 2., Florida Power and Light's St. Lucie 1 Plant, and Maine Yankee Atcaic Power Company's Maine 4
Yankee Plant.
In October 1972, I assumed ny present position.
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ANTIIONY N. FASANO PROJECT REACTOR INSPECTOR
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REACTOR OPERI.TIONS BRANCH OFFICE OF INSPECTION AND ENFORCE. ENT M
REGION I OFFICE PHILADELPHIA, PA.
PROFESSIONAL QUALIFICATIONS I am a project reactor inspector ' responsible for the inspection of Threc. Mile Island, Units 1 and 2. I have been 'vith the Nuclear Regulatory Co:nmission since February 1971. I received a Bach'elor in Chemical Engineering Degree from Clarkson Colle;;e of Technologf n 1950 and a Masters Degree in Chemical i
Engineering (Nuclear Engineerin;;) mir.or) in 1959 from New York Universitf.
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From 1953 to 1953 I <vas, employed at Brookhaven National Laboratory Graphite 4
Pile Reactor, Up' ton, Ne : York. I worked as a Technical Specialist and as an Engineer in Design and development of ec;uipment and in radiation research.
I From 1958 to 1971 I was employed at 'Sright Patterson Air Force Base.
served as Project Engi.eer, Supervisor, E:.gineer, Branch Chief and finallf as Engineering Division Chief at.the Ylright Patterson Nuclear Reactor.
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I alsc, have taken courses in Nuclear Engineering, Engineering Physics, and Business Adr nistratien at the Air Force Institute of Technolo;;y, the Vlright Patterson Ohio St:.te University Extension and at the Rutgers Universitf -
Morristown, N. J. extension.
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UllITED STATES OF Af' ERICA
!!UCLEAR REGULATORY CCt'i11SS10!1 TifREE ftILE ISLA!!D fUCLEAR STATI0tl, UilIT tj0. 2 DOCKET !!0. 50-320 SUPPLE!:E!!TAL TESTIItCllY OF hRC STAFF Ot1 AIRCRAFT HAZARD This testimony relates to a questicn from the Atomic Safety and Licensing Board on Thursday April 7,1977 with regard to Contention !!o. 5.
The qu'estion frca the Board concerns what actions the staff night take in the event that operations of aircraft larger than 200,000 pounds at Harrisburg International Airport exceeds 2400 per year.
Response
As has been noted during the course of the hearing, the value of 2400 novenents per year was first used in connection with reviews of Three liile Island !!ucicar Station, Unit !!o.1.
In that review, the staff determined ; hat there was then an average of 5-6 novements per -
of large aircraf t exceeding 200,000 pounds at Harrisburg International Airport.
The staff concluded that assuming movements of Targe aircraf t of 6-7 per day, the probability of an aircraf t crashing into the Three flile Island fluclear Station and causing offsite radiological consequences was so small that it did not present an undue risk to the health and safety of the public.
The staff also concluded, considering the conservatisms in the analyses, that reconsideration of this conclusion would Le warranted only if there were a very large increase, more than a factor of ten, in the large aircraf t traffic.
- As has been described in the testimony of Mr. Vallance on behalf of the applicant, the f recuency of large aircraf t is now screwhat lower (currently 1-2 novements per day) than that at the time of the review of Unit flo, l.
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% The Department of Transportation (National Transportation - Trends and Choices, January,1977) projects an increase in operations at Harrisburg Internatiscal Airpor t of fron 50% to 100% in the period of 1975 to 1990, but does not project re-introduction of trunk line connon carrier service.
All available informaticn indicates that this airport will continue to serve predominantly general aviation uses, principally lighter aircraf t.
The conservative f actors used in the estination of aircraf t crash probability at Three Mile Island are consistent with the judgment that a very large increase in large aircraf t tr'f fic at Harrisburg International Airport would be necessary before a re-evaluation would be justified.
The applicant is currently required, via the technical specification for Unit 1, to nonitor the use of the aircort and to inform the MRC periodically of the nunber and sizes of the aircraf t using the field.
The purpose of this monitoring is to ensure that future activities, such as a substantial channe in the frequency of larae aircraf t movenents, do not differ substantially from the estimates used as a basis for our evaluation.
Should large aircraf t movements increase substantially above 2400 per year, the staff may require a reanalysis to determine whether the present esticates of large aircraf t risks should be modified based on the safety record of large commercial aircraf t, or based on a more detailed study of the likelihood of aircraf t crashes damaging safety related systens - both ained at eliminating known and possibly excessive conservatisns in the present estinates.
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, In addition, there are corrective neasures which can be taken to ensure that the risks vf large aircraft impacts at Three Mile Island remain acceptably Icw.
The most direct way to assure that large aircraf t crash risks at Three Mile Island will renain acceptably low would be to cbtain agreement to restrict airspace in the site vicinity. This uculd be the responsibility of the applicant.
The applicant's testimony in the mitter of Three Mile Island Muclear Station, Unit 1, dated October 25, 1973, notes this possibility. The relative positions of the airport traffic pattern and navigational aids in the vicinity are such that there is no apparent reason why such an agreement cannot be obtained.
A second measure would be a possible redesign of exterior plant structures in order to sufficiently harden er protect the facility to withstand the inpacts of these larger aircraf t.
Ultimately, of course, plant shutdown nay be recuired if the risks are determined not to be acceptable.
However, in view of the large margin between current traffic levels and the 2400 novements per year value, and the likely availability of other measures which do not involve an impact on plant operations, the staff is of the opinion that these latter measures are remote contingencies.
In any event, the current level of traffic is sufficiently low that none of these measures is presently warranted and that a choice amonn then is not necessary at this time.
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DELBERT F. BUSCll PROFESSIONAL QUALIFICATICSS ACCIDCST ANALYSIS BRASCll
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DIVISION OF SITE SAFETY ASD ESVIRO:;",ESTAL ASALYSIS I an Chief of the Accident Analysis Branch, Di.ision of Site Saf ety and Envirormental Ar alysis, U.S. ':uclear Regulatory Concission.
My present duties in this position ir.c lud e reviewing calculational models, procedures and acchocs which are developed by members of the Accident Analysis Branch for both conservative and realistic assessments of the consequences of accidents and reviewing analyses of all nuclear power plant sites which are performed by the Accident Analysis Br nch with regard to compliance with the guidelines of 10 CFR Part 10 0.
I graduated f ron Chitnan College in Washington in 1963 with a BA uealth degree in Chemistry.
In 1963 I joined the AEC as a Physics Intern in Idaho Falls, Id ah o'.
Uhile at Idaho I received both formal and field training, the latter of which included review of saf ety analysis reports, environmental nonitoring, energency planning and si:e selection.
Subsequent responsibiliti.-
f included participation in and !ater responsibility for environ-mentally related R & D programs.
In 1966 I j oined Atomics In ter-national Inc. My duties involved development of radiation standards for reutinn operating, hacards analyses and the development of site and facility requirecents for various intilities and systems including a plutonium fuel fabrication facility.
In 1958 I resumed my career with AEC, as a nuclear safety engineer. Assignments included the canagement of R & D programs related to both L'.;Es and advanced nuclear power reactors.
From 1973 to 1974 I was Chief of the Environmental Safety Braach, Division of Reactor Research and Development.
In that capacity I was responsible for the conduct of s iting technology and environmentally-related R & D.
I have authored or c&-authored 15 papers related to the consequences of radioactivity releases to the environment and the estimation of doses to various groups of people from accidental exposures to radioactivity.
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSIOh TilREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 DOCKET NO. 50-320 TESTIMONY OF NRC STAFF ON OPERATION OF THREE MILE ISLAND, UNIT 1 by GERALD B. ZWETZIG This testimony responds to the following Licensing Board question stated at the January 2S,1977 pre-hearing conference (Tr.137-38) to the extent it relatcs to the operating experience of Three Mile Island, Unit 1:
Specifically, the Board would like to request both 1
Staff anci Applicant to address themselves to the considerations of what has been done and is being done to assure that the quality of construcuan and the reliability of operation, assuming an operating license issues, ' vill not be compromised by the slow down and the constru-' ion stretch out of conrtruction schedule.
In the same context, I think it would be helpful for the Applicant to review just briefly what the opera-ting experience has been with unit (sic], and of course, the Staff would be free to comment on that to any extent they wish.
Metropolitan Edison Company declared TMI-1 to be in commercial operation on September 2,1974. During the first year of operation, which did not include a refueling outage, the Unit Availability Facter, which is a n casure 106 267
. _.].
. of overall plant reliability, was reported to be 87%. The cumulative Unit Availability Factor, from the start of operation through December,1976, i
(which included one refueling outage) was reported to be 75.8%. The cumulative Reactor Availability Fr.ctor (which is a measure of the reliability of the reactor portion of the plant) over this same period was reported to be 80.5%.
During 1975 nineteen reactor shutdowns were reported. Of these, six shutdowns *equired the plant to be a, zero power in excess of one day.
The longest reported interval at zero power was 17 days which was the time required to repair a large river water pump. Three of the other reported shutdowns, ranging from 4 to 12 days duration, involved i
repairs to control rod drive units.
During 1976, a total of cight reactor shutdowns were reported. Of these, two were of extended duration. The shutdown for the first refueling of the plant, which was scheduled to take about eight weeks (beginning February 20, 1976) actually extended to about thirteen weeks. Much of the extra time involved in this shutdown resulted from the discovery that the reactor vessel surveillance specimen holders were damaged and the subsequent need to remove the specimens and damaged holders. The second extended shutdown occurred in November 1976 and lasted about one month. This shutdown was required to repair a valve in the decay heat 106 260
..-a 3-removal system, to perform repairs on the condenser and to repair cracks in some of the buried piping adjacent to the river water intake structure.
Based on the experience of other nuclear plants in commercial operation, it is concluded that the plant outages experienced thus fa at TMI-1 are within the normal range. Based on operating statistics, it can be conclucied that the reported cumulative Unit Availability Factor for TMI-l through December 1976 is slightly above the average value for all plants 2n commercial operation.
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PROFESSIONA. QUALIFICATIONS Geral1 B. Zwetzig OPERATING REACTORS CRANCH NO. 4 DIVISION OF OPERATING REACTORS OFFICE OF NUCLEAR REACTOR REGULATIC'l flVCLEAR REGULATORY CCI"4!SSIO:t i
I am a Project Manager on the staff of the Division of Operating Reactors, Office of Nuclear Reactor Reculation, U. S. Nuclear Regulatory Commission.
My primary respcnsibility is the manager.ent of licensing actions and the evaluation of concomitant safety considerations for operating reactors to assure that such actions co not adversely affect the health and safety of the public.
I have prinary responsibility for Three Mile Island Unit No. I and have been with the NRC in that position since June 1976.
I received the decree of Bachelor of Science in Naval Technology frca the University of Minnesota in 1946.
I also received the decree of Master of Bioradiology from the University of California atCerkeley in 1951.
I have completed studies in nuclear engineering and related engineering subjects and am a registered professiorial engineer in ruachanical engineering in the state of California.
Upon leaving military service in 1955, I joined the Atomics International Division of Rockwell International 'ahere I was encaced in varicus areas, including health physics, experimental physics, advanced concept evaluation and LMFBR safety.
In 1971 I joined the General Atomic Company where my principal duties involved licensing activities related to High Temperature Gas-Cooled Reactors.
I have been a member of the Americ=.n Nuclear Society since 1957.
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