Text

Summary Description of Application for CP & OL
	ML19206A942
Person / Time
Site:	Crane
Issue date:	09/03/1969
From:	; Metropolitan Edison Co
To:	;
References
	NUDOCS 7904210642
	Download: ML19206A942 (72)
	v • d • e

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4 renar m..:r _ w. m UNITD STA"ES AICMIC ETERGY CCM4ISSICN In the Matter of: 'GTS.CICLITAN DISCU CC:GICFf JERSEY CECFAL FCWER & LIGHT CCIGA Tl THREE MILE ISIXD :TJCLEAR STATIC:1, U: TIT 2 Dcchet No. 50-320 SDtMRY EESCRIPTICN CF AFFLICATICN FCR RFACCR CCUSTFICICH FEEC /dC CFEFATE!G LICEISE IATE: Sep e=ber 3, 1959 Q-1gg 790423y(,9

O u,,m, C: cc..s..a Pa ge 1. Introducticc 1 2. Descrittien of Site and Enviren= ental Characteristics '4hich influence resign 3 2.1 Lccatien 3 2.2 Pcpuhtica 4 23 Airpcrt k 2.4 Metecrology 4 2.5 Rydrology 5 2.6 Grcundwater 6 2.7 ceclogy 6 2.8 Seis= ology 7 29 Aircraet I=pingement Protection 7 2.10 Enviren= ental Menitcring 9 3 Descriptica of Three Mile Island Nuclear Station, Unit 2 10 31 Introduction lo 32 Reacter and Primary Coolant Syste= 11 33 Reactor Building 14 34 Engineered Safety Features 16 35 Instru=entatien and Centrol. 17 36 Electrical Systes 19 37 Auxiliary Systens 20 38 Stea= and Power Conversien Syste=2 21 39 Eadioactivity Centrol Systen 21 3 10 Shared Cc=penents with Unit No.1 22 k. Safety Analysis 22 5 Tests, Inspection, and quality Centrol 2h 6. Research and Develep=ent Progra=3 26 7 Technical Qualifications 31 7.1 Metrcpolitan Edisen Cc=pany 31 7.2 mbcock and *411ccx Cc=tany 32 73 Burns and ace, Inc. 32 7.4 Gilbert Associates, Inc. 33 75 United Engineers and Censtructers, Inc. 34 S. Cc==ents en Ite=s b ACES Letter 35 8.1 Centain=ent Purging to Centrol Hydrogen 35 Ccncentration Folleving LCCA 8.2 Instrt=entatica Can Failure Medes 35 8.3 In-Service Monitcring for Vibratien er Lcese 35 Parts in the Rea.ater Coolant Syste=. 8.k Integrity cf the ? cst-Accident Cccling 37 Syste= 8.5 Reactor Coclant Pu=p Motor Flywheels 37 g, q -q r'n 9 Cennca Defense and Security U t> AdJ 37

6 Page 10. Cenclusien N Appendices Appendix A - List of P.eferences Appendix 3 - Fig 2res Etacaticnal and Professiccal Appendix C qualificatiens of Witnesses 63~160

1 1. I'iTRCIUCTICN 2 This doc =ent is a S-ar/ Description of the Applicaticn, 3 as a= ended by Anend ents 1 thrcugh 10, of Jersey Central Fever & 4 Light Cqany and Metropolitan Edisen Cqany (referred to as "the 5 Applicant") for a Sectica 1Ch(b) construction pe=it and facility 6 license to ecnstract and cperate the Three Mile Ishnd :'uclear 7 Station, Unit 2, to be 2ccated en Three Mile Island in the Susgae-8 banna River in rauphin County, Pennsylvania. This Su==ary Descrip-9 tien includes infor=atien en the Three Mile Island site and enviren-10 cent, a descriptien of the Three Mile Ishnd Nuclear Statien, Unit 2, 11 analyses of the safety aspects of the plant, a su==ar/ cf q;ality 12 centrol procedures, the research and development pre-72=s necessary 13 fcr the final design, the technical Taalificatiens of the Applicant 14 and the principal centracters, and censiderations relating to the 15 e en defense and security of the United States. 16 This Su==ar/ Descriptien also ccustitutes a pcrtion of the 17 prepred testi=cny of the Applicant for the public hearing en the 18 Applicatien for a construction pe=1t, and is spenscred collectively 19 by the fo11cwing witnesses representing Applicant and its centracters: 20 Name Cr anizatien Title 21 John G. Miller Metropolitan Edisen Co. Vice President & Chief Engineer 22 Ronald L. Wilida a Metropolitan Edisen Co. Project Manager-Design 23 George F. 31er=an Metropolitan Ediscu Co. Project Manager-Censt. 24 Richard W. Heward, Jr. General Public Utility Manager, Safety Div. Corp. 25 P. P. DeRience Burns and Roe, Inc. Chief Nuclear and Process Engineer 26 John C. Archer Burns and Roe, Inc. Super. Civil Engineer 27 W. A. Cobb 2abecek & Wilecx Co. Project Engineer 28 W'a~ R. S=1th Eabecek & Wilcox Co. Licensing Sect. Manager 29 W4ir S. Little Esbecek & Wilcox Co. Licensing Supertiser N I61 1 2ree Mile Island, Unit 2, will ecpley a pressurized water 2 nuclear stea= supply system Parnished by the Eabecci & '411ccx Cc=p-3 any (refered to as "E&*4") of the sa=e basic design as the nuclear 4 steam supply system which is being Parnished by E&'d to Metropolitan 5 Idisen Cc=pany fe: its Three Mile Island Unit :To.1 (Decket :Ic. 6 50-289). A constructien pe=it authericing ecastructien of the Three 7 Mile Island Unit 1 facilities was issued in May 1968, pursuant to 3 Secticn 104 (b) of the Atc=ic Energy Act of 1954, as acended. The 9 cuelear stea= sucp2,7 system for Unit 2 vul operate initially at 10 core pcwer levels up to 2452 E4t, which corresponds to a gross elec-11 trical cutput of about 845 T4e. An ulti= ate core cutput of 2772 rit 12 with a correspending gross plant output of 965 E4e is expected. All 13 plant safety systems, including centai==ent and engineered safety 14 features are designed fer operatien at this higher pcwer level. The 15 higher pcwer level is also used in the analyses of postulated acci-16 dents and in the evaluation of all =ajor structures, systems and cc=- 17 penents of the facility which bear significantly en the accep+2bility 18 of the site, thereby establishing the suitability of the site t= der 19 the guidelines set forth in 10 cya 100. 20 The Applicant's constracticn per=it applicaticn, including the 21 amend:ents thereto, has been reviewed by the staff of the Atc=ic 22 Inergy CW ssien, which has prepered and published a safety analysis of 23 the Application. The Advisory C~Httee en Reactor Safeguards (refer-24 red to as " ACE 3") has also reviewed the Applicatien, ss amended threugh 25 A=end=ent :To.10, and reported its findings to the Chai=an of the 26 U. S. Atc=ic Energy Cc==ission in a letter dated July 17,1$69 The 27 ACES cencluded that the preposed reacter can be constracted at the 28 Three Mile Island site "with reasecable assurance that it can be cper-29 ated withcut untae risk to the health and safety of the public." The li3'162 9 1 AIC staff ecceluded sinilarly. Sc h the AEC Ctaff Analysis and the 2 ACES repcrt identify certain aspects of the design with respect to 3 which fu-ther technical info::atien =ust be submitted er with respect 4 te which research and develepnent =ust be conducted prier to issi:ance 5 of an crerating license. These itens are discussed in Sectices 6 and 8 6 herein. 7 The principal design criteria which will govern the plant 8 design are set forth in Section 1.4 of Volt =e 1 cf the Applicant's 9 Pra1 * '~:/ Safety Analysis Repcrt. Applicant vill nec* the intent 10 of the AEC Preposed 70 Criteria. These criteria together with the 11 engineered safety features and cther incorporated sysi.cnc prgvide 12 assurance that the prepcsed Three Mile Island :Tuclear Statien, Unit 2, 13 can and vill be ccustracted and operated at the proposed location lb without undue risk to the health and safety of the public. 15 Metropolitan Edisen Cc=pany is respensible fer enginering, 16 design, ccustraction, cperaticn and naintenance of Three Mile Island 17 Unit 2. Jersey Central Fever & Light Cc=pany and Metrcpolitan Edisen 18 Cc=pany will cwn the facility as tenants in can. 3cth Jersey 19 Central Pcwer & light and Metrepelitan Edisen Cc=pany are wholly 20 cvned subsidiaries of General Public Utilities Corporation, hereinafter 21 called "G?J" 22 2. EESCRIFIICII 0F SITE A:lD EIVIRC:;METIAL CHARACTIRISTICS 23 WHICH ETEGEICE DESIGIT 24 2.1 Locatien 25 The Three Mile Island :Iuclear Statica, Unit 2, vill be cen-26 structed en Three Mile Island in the Susquehanna River, Lcndender:/ 27 Tcwnship, rauphin County, Pennsylvania, just abcve the York Haven 28 ran. The site is located approxinately three niles south of Middle-2c tcwn, Pennsylvania. Its lccation with respect to the over-all General ii3--163 _3_

O 1 Fublic Utilities Corporatica service area is chevn in Figre 1. 2 Appendix 3, and its 1ccaticn with respect to the i=ediate vicinity 3 is chevn 21 Figre 2, Appendix 3. h Metrepc11 tan Edisen Cc=pany evns all of Three Mile Island, 5 and all, except several acres on the scuthern tip, cE shelly Island, 6 which is to the vest cf Three Mile Island. Land evnership in the 7 vicinity cf the site is shcvn in Fi; re 2, Appendix 3. Land within 8 a ten nile radius of the site is used pri=arily for faming.(~) 9 2.2 Populatien 10 The exclusien area, that area which is under the centrol of the 11 Applicant, has a -dad = radius of 2,000 feet. The nearest residence 12 cutside the exclusien area is 2,200 feet east of the centai=ent 13 b..ilding. The 2cv populatien eene has a radius of two -d'es. There 14 are five tevns withdr. a fifty-nile radius of the site with a 1960 15 population of over 25,000. They are: Earristurg, York, In.ncaster, 16 Lebanen, and Reading. 17 23 Ai xrt 18 Olnsted State Airpcrt, located en the north tank of the river, 19 2-1/2 d'es northwest of the site, has enly cne reway (130 /310 ). 20 The noz :a1 landing and take-off patterns do not require the aircraft to pass over the site.(3) 21 22 2.4 Metecrolcgy 23 Metecreicgy in the site regien bas been evaluated to provide 24 a basis for stern protectica criteria and a pra'd-d-ary assesc:ent 25 cf regulated and accidental radicactive gas release at the site. Pre-20 va4'd g vinds are frc= the vest ncrthwest.(4) The probabilities and 27 ra*= intensities of hurricanes, tcreadces, and coastal stc=s were 28 studied in crder to for-"' ate design criteria that would g.:arantee 29 integrity under the nest severe netecrolcgical conditiens.(?') A _g_ G3 fG4

1 study of the site diffusien and dispersica characteristics utiliticing consercative netecrological ccnditicus has been rade.(6) 2 3 2.5 Hydrolecy 4 The najor stream affecting the site is the Susquehanna River, 5 having a drainage area at the site c" a rexi stely 25,CCO square 6 ~dles. A Design Flced of 1,100,000 cfs was chosen, even thcugh the 7 n*= flced of record was enly 750,0cc cfs, and the =ean annual fleed 8 is 300,000 cfs.(7) During the design ficod, the water suritce is cal-9 culated to be at Il 3Ch at the upstres= end of Three Mile Island. 10 At the dcunstreas end of Shelly Island and at the headwater of the 21 York Eaven ran, the water surfacs vill be El 301. The water surface 12 profile elevatien alcng the reach of the plant site vill be between 13 El 3Ch and El 303 No change in any upstrea= f1ced conditica vill be 14 caused by the presence of the generating station.( The Cc:ps of 15 Engineers has recently indicated that the naxi== probable flecd ray b 3 as h1 h as 1.6 cr 1.7 -41' den efs discharge. This analysis 16 6 17 vill be cc=plete in abcut one year. Although we do not necessarily 26 agree with this figure, we vill provide the plant with safe shut-devn 19 capability for a naxinun pretable fleod up to the nagnitude indi-20 cated above. 21 Designs will be prepared for all structures associated with 22 flood protecticn and circulating water facilities at the site includ-23 ing earth dikes, channels, and pressure cenduits. The design cri-24 terb are censervative and based en sound civil engineering practices; 25 the designs will be reviewed and approved by the apprcyriate State 26 and Federal agencies, including the Federal ?cwer Cc 'ssien, the 27 Ccrps of Engineers, and the '4ater and Fever Resources 3 card of the 28 Cc-envealth of Pennsylzania, where applicable.(9} 63 165

1 Applicant will instan tvc naturs1 draft ecoling towers for this 2 nr. clear plant as a result of the=al censidersticns. 3 The present uses of the Susquehanna River and its tributaries 4 in the vicinity of the site are for water supply, both pubHe and 5 industrial, power generatien, teating, sport fishing, and recreatien. 6 Cperatien of the Three Mile Island Unit 2 :Iuclear Statica vill 7 not adversely affect either the scr=al cperatien cf any intastrial 8 or cc=nercial water user er cens= er er public recreaticn; likewise, 9 cernal cperation of these incastrial and ec=ercial facilities vill 10 not adversely affect the opentien of Three Mile Island Unit 2 :Iuclear 11 Station. 12 2.6 Grc=& ant er 13 Grcundvater at the site occurs = der watertable conditiens in 14 the granular alluvial deposits which constitute the island. The 15 static level of groundwater en the island is centrolled by the 16 surrc&d'ac Susq2ehanna River, which nor= ally ficws at Il 277 feet, 17 roughly thirty feet telev the point cf highest elevation en the island. 13 A hydraulic gradient of 0.6 percent sicpes tcward the river frc= points 19 ef =ax1== elevatica near the center of the island. Water discharged 20 at the surfaces vill rapidly infiltrate granular soils and enter the 21 groundwater table, the rate at which it then f1cvs toward the river 22 being dependent upcn river level. Infiltratien of surface water frc= 23 the site to wen supplies en either shcre cf the river is cet expected 2h to cccur. 25 2.7 Geclery 26 Se island en which the site is located is tasically ec=pesed 27 ef flutially deposited sand and gravel of aderste density to suppcrt 28 =cderately hea ry leads. The underlying rock is a sedinentary seq 2ence 29 cf inter %dded sandstene, shaly siltstene, and shaly claystene atich dwI66 1 is capable of bearing leads i pesed by the heaviest structures. Reg-2 icr.al tectonic elenents are inactive and present no threat to the 3 structural integrity of 1ccal geolcgy. The site is geclegically cc=petent to safely support a nuclear statien.() ~ k 5 2.6 Sei=cleg 6 Historically, earthquakes in Fcnnsylvania have been infrequent 7 and of Icv intensity. The highest reccrded intensity within

a. fifty-8

-d'e radius of the site was VI (nedified Mercalli Scale), which was 9 rapidly attenuated with distance frc= the epicenter. The -a v'-un 10 ground acceleratien ecrrespending to an intensity of VI is 0.Chg, 11 and the Three Mile Island Unit :To. 2 :iuclear Statien vill be designed 12 to withstand a nyd u= herirental g cund acceleraticn of 0.C6g and 13 a -nyd= vertical ec=penent of 0.C4c as an added nargin of safety. Ik Further, the c.bility of the plant to be safely shutdevn vill not be 15 d.= paired in the hypothetical event of a naxi = horizental grcund 16 acceleraticn of 0.12g and a nax1== vertical cenpenent of 0.08g.( 3) 17 29 Aircraft Irrinament Protecticn le The probability of aircraft i=pinge:ent to the plant site has 19 been approxinated b/ en d.ning ten years of accident reccrds avail-able h the Bureau cf Safety of the Civil Aerceautics Ecard.(~5) 20 21 It has been censervatively estinated that the chance cf a crash into P2 the plant is ene in a -d

cn per year (larger :jpe aircraft, i.e.,

23

ertified air carrier aircraft).

Ek Although the probability of an aircraft incident at the Three 25 Mile Island site is errenely recte, the vital structures vill be 26 designed to have the capability of withstanding a hypothetical air-27 craft strike. The principal structures analyzed are: the 28 Reacter 2"d ' 44 g, Cc=trel Builfting, yuel :Ja -d'

g Building, A"" ' d e ry 2c Building, the penetratien area, air intake. tunnel and river water W1G7

1 W.cuse. 2 The aircraft strike basically censidered is a 200,000 pc'.:nd 3 aircraft striking the vi:21 structures at the =cs: unfaversble 1cca-k tien and attitude, at a velocity of 2CO kncts, with a centact area 5 nineteen feet in diameter. censideratien is also given in design to 6 = aller objects, representative of separated aircraft engines, 7 i=; acting under tne sa=e cenditiens. Protectica against i=pingenent 8 by larger aircraft, up to 200,000 pcunds, is also afforded under 9 = cat cenceivable icesticn:2 and attitudes. 10 In order that the statien can be naintained in a safe ccndi-11 tien fc11cving a fire which dg11, result frc= a hypothetical aircraft 12 incident, design provisiens will be nade to assure the protectica of 13 persennel and equi nent in vital structures. These provisiens in-i 14 clude the folleving-15 a. An air intake tunnel, vtich brings air into the vi+21 16 structures through a tunnel 'nith a renote intake 17 located appi H"tely 125.*eet frc= the plant. 18 b. Exhaust oper'.ngs fres ventila..: n syste=s, such as 19 the centr:1 tower ce= plex, vill be provided with a 20 protective shicla designed to 11thstand the i= pact 21 of an aircraft strike. 22 In the event that liquid feel and/or vapers are not c. 23 ignited and do enter the intake they will be detected 2k by ec=bustible vapor detectors. 25 d. In the event that burning fuel enters the intake, it 26 vill be detected by any or all of the fc11cv:rg: 27 Ionicatica t',7e detecters, infra-red and ultra-violet 23 fla.se detecters, and rate-of-rise heat detec crs. 29 Acti*.stien of any of these detecters will cause the 63 168 -c-

1 ventilating fan to s:cp, fire dampers to c10se, 2 deluge water spray systes to cperate, and cause the 3 centrol building ventilation systen to operate in the 4 recirculatien =cde. 5 2.20 Invirec= ental Mcai.tc.r..i. ng m 6 Since January of 1968, Metrepelitan Edisen Cc=pany has been 7 conducting a pre-cperational envirc = ental pregrs=.(*M' Meetings 6 were held with the Cr-envealth of Pennsylvnnia Depart =ent of Health, 9 Radiological Health Sectica, and the envircr= ental progrer. was reviewed 10 by the State Health Physicist. These =eetings with the State included 11 a site visit, discussicas of instrrant sensitivity, fish sa=pling 12 and fish sa=pling Iccations. The State als, receives a Susquehanna 13 River sa=ple fL ana17sto es S. ncnthly ba. ss. IL. folleving sa=ples 14 are being taken du irs the pre-operaticcal phase of the preca=: c 15 Well water - Analyzed fer gross alpha and gross beta-ga-a 16 activity at fcur locations within a five ~*1e radius every twelve 17 weeks. le River water - Susqueb--* River water analyzed fer gross alpha 19 and gross beta-gan=a activity collected near the ecoling tcwer dis-20 charge every fcur weeks. 21 River Sedi=ent - Analyzed fer gross alpha and gress beta ; = 22 activity collected near the ecoling tcwer discharge ever/ fcur weeks. 23 Fish - Analyzed for was alpha and gross beta-ga-a activity 24 at Ycra Eaven ever/ twelve weeks. 25 Scil and Vegetatien - analyzed fer gross alphs and gress beta ~ 26 gn.--A activity collected en site and at fcur locaticus surrcunding 27 the site ever/ twelve weeks. bs3 .h

1 The fc11cwing additicnal surveys are planned: 2 1. A biclegical survey based en nacrcinvertebrate crgani =s 3 has been e.<ablished in the Susquehanna River adjacent k to Th', Mile Ishnd. 5 2. A cc=prehensive enviren= ental survey at the site vill 6 be prepared based en the infernatien gathered during 7 the biological study. 6 3 Mili ss=ples will be collected in the 'hree Mile Island 9 area starting ene year prior to reacter s+2rtup. 10 k. It is intended that samples of crops irrigated -#.th 11 Susqua * "" River water be taken in ccnjunction with 12 the ec=prehensive enviren= ental progrs= if studies sc 13 indicate. 14 Applicant vill centinue to cecperate with interested gcVern-15 = ental egencies in :ntters cencerning enviren= ental =cnitoring. 16 3 DESCRIITIC:7 0F TERZI CIT IS~.A'O NUCLEAR STATICII. U' TIT 2 17 31 Introduction 18 A description of the plant features and layout as well as an 19 evaluaticn of the plant safety are set forth in the Application, 20 as amended. Because the final design of t' e station is not yet ec=- 21 plete, the plant descriptien e=ptasizes tue concepts, guidal' es, 22 and criteria which will govern the final design. The s*ation #.21 23 consist of a reacter bud m c, an auxiliary bu m I, a turbine 2k building, a centrol building, a fuel hand 7' g building, a diesel-25 generater b " *g, eccling tcwers, a substatien, and varicus other 26 auxiliary struct: res and equip:ent. A plot plan of the Three Mile 27 Island :iuclear Station, indicating the general station layeuo, is 23 sucwn in Figure 3, Appendix 3. A cutawa', drawing of the reacter, De. 4 m[ L F a

1 centain=ent, and str;cture arrangement is shewn in Figure 4. 2 Appendix 3. Table 1-2 in the Application sets fcrth a tabuhr cc=- 3 parisen of the design parameters of the prcposed Three Mile Ishnd k Nuclear Statica Unit 2 with the Three Mile Ishnd Unit 1, Duke Fever 5 Cc=pany's Ocenee Units 1, 2 and 3, Flcrida ?cwer and Light Cc=pany's 6 Turkey ?cint Units 3 and 4 The following is a st==ary of the principal 7 features cf the punt which are significant te safety censideration:. 8 32 Reacter and Pr4" y cechnt system 9 The reacter fer the Three Mile Island Nuclear Staticn Unit 2 is 10 of the pressurized water type. It has an initial core pcwer level rating --H of 2452 Zit, correspending to a gress electrical cutpus of 845 Mie. ( ~~) ,A The nc=4"' cperating pressure for the reacter is 2185 12 13 psig, with an average tecperature of 579 F. The reacter ecolant is designed fcr 2500 psig pressure and 650 F. te::perature.(^9) 14 syste 15 The reacter core is approxinately 129 inches in dia=eter, with 16 an active height of 144 inches. It is =ade up of 177 fuel asses-17 blies, each censisting of a 15 x 15 array cf Ocel reds enclosed in 16 a square, sta4-7 ess steel, perferated envelope. The array of fuel 19 reds censists of 2c8 zirealey tubes centa4 4 c u.ani= dicxide,16 20 control red guide tubes, and a center tube avaihble fer an in-ccre instr =entatien asse:bly.( There are approxi=stely 201,520 pcunds 21 of urani= dicxide in the core.(~9) 22 23 The the=al and h,-iraulic design limits of the ccre are cen-2k ser rative, and are censistent with these of other pressurined water 25 reacters currently in operaticn er in:1er ecnstraction.(19)(2~0) 26 cere reactivity is centrolled by a ec=binatien of 69 =ciable 27 centrol red assesblies and a neutren absorber dissolved in the eccl-c8 ant. ~he centrol reds are an alley of silver-indi=-cad =i= encap-o9 sulsted in stainless steel.

e di " 1ved neutren abscrber is bcric 63 T71 acid.(23) 2 The centrol reds are used fer shcrt-tem reactivity centrol 3

associated with the changes in power level and also with changes in k fuel bumup between periodic adjustments of dissolved boren cencen-5 tration.(24) The reacter can be shut dcwn by the =ovable centrol reds 6 frc= any powcr level at any ti=e.( 3) Each =ovable control red 7 asse=bly centains 16 centrol pins, and is actuated by a separate 8 centrol rod drive =ecrani= =cunted on the tcp head of the reactor 9 vessel. Upen trip, the 69 centrol red asse=blies fsll into the cere by gravity.(26) 10 11 The centrol red drive =echnM s=s are sealed drives of the 12 roller nut type in which a lend screw coupled to the centrol red 13 assmblies is axially driven by the retary notien of a pair of 14 roller nut seg=ent arms. The segnent a m s which are within the 15 pressure hcusing are part of the drive rotor and are electrically 16 driven by the =cter stater which is extemal to the pressure housing. 17 The segnent a=s are held in engageent with the lead screw when-18 ever the drives are electrically energi::ed. The reacter trip signal 19 or 1 css of power to the drives causes the roller nut ses=ent a=s 20 to disengage frc= the lead screw esusd g the red aseenblica to fall 21 into the core.(27) o 22 Systes are provided so that the concentratien of dissolved 23 neutren absorber in the reacter nay be adjusted to naistain the 24 reactor shutdown at rec = te=persture and to provide a cafe shutdevn 25 nargin duri.g refue'"C.(") The cencentration of dissolved abscrber 26 is reduced to ec=pensate fer icng-ter= reactivity changes, bur: rap 27 of fael and buildup of fissicn products over the cere cycle. 63 172

l The core is centained within a cylindrical reactor vessel having 2 internal dimensicns of 14 feet 3 inches in dianeter and 37 feet 4 3 inches in height. The vessel has a spherically dished bettc= head 4 with a bolted rencvable spherically dished top head.(29) The 5 reacter vessel is constructed of carben steel with all interier sur-6 faces clad with austenitic stainless steel. The reacter vessel is 7 nanufactured under close quality centrol, and several types of non-8 destructive tests are perfer=ed during fabricatien. These tests 9 include radiography cf welds, ultrasenic testing, =agnetic particle 10 e * " tion, and dye penetrant testing.(30) During cperation, speci-11 = ens of reacter vessel naterials vill be placed in the reacter adjacent 12 to the inside surface of the reacter vessel. These speci= ens vill be 13 subject to irradiatica si=11ar to the shell of the reacter vessel. 14 A per:1cn of the specimens can be rencved periedically and tested to 15 ascertain the effects of radiaticn en the reacter vessel naterial.(31) 16 Two ecolant Iceps are cennected to the reacter vessel by nc :les 17 located near the tcp cf the vessel. Each iccp centains ene steam 13 generator, twc notcr-driven ecclant pumps and the inter-cennecting 19 piping. The reacter coc2nnt piping is carben steel chd en the inside 20 surface with austenitic stadnless steel. Reacter coolant is pt= ped El frc= the reacter through each steen generator and back to the reacter 22 inlet by two 88,000 p centrifugal pu=ps located at the cutlet of 23 each steem generater.(50) 24 The steam generater is a vertical, straight-tube-and-shell heat 25 exchanger which produces superheated steam at ccustant pressure over 2*3 the pcwer range. Reactor coolant flevs dcwnward through the tubes 27 and stees is generated en the shell side.(~%) 2S The reacter eco' ant pu=ps are vertical, single-speed, shaft-29 sealed units having bettc= suctica and heri ental discharge. Each 03-173

1 pump has a separate, single-speed, top-=cunted motcr, which is cen-nected to the pu=p by a shaft ceu,'"g.(") 2 3 The pressurizer, a vertical surge tank apprcxi=ately half-fdled 4 with reacter ecchnt and half-filled with steam, is cennected to the 5 reacter ecolant syste= to centrol syste= pressure. The operating 6 pressure of the syste= is naintained by crerating electric is:=ersica 7 heaters to increase pressure er by spraying reactor ecolant water into 8 the steem within this pressurizer tank, to reduce pressure. Self-9 actuated safety relief valves connected to the pressuriser prevent cver-pressurization of the reactor coolant syste=.( 5) 2 10 11 33 Reacter Buildine 22 The reacter building is designed to ec=pletely enclose the M reacter coolant syste= and portions of the auxiliary and engineered 14 safety features syste=s.\\" It is a reinforced cencrete structure in 15 the shape cf a cylin?.er with a shallcw dc=ed roof and a flat founda-16 tien slab. The cylindriesl portien is prestressed by a post-tensicning 17 syste= censisting of hori: ental and vertical tendens. The de=e has a 18 %*ee-way-post-tensiening syste=. The fcuncaticn slab is reinforced 19 with ccnventicnal -4'a steel. The entire structure is lined with 20 welded steel plate,1/4 inch u: thickness, to provide vapor 21 tightness. The foundatica nat will be bearing en scund rock and 22 will be apprcxinately ten feet thick with a two fcot thick concrete 23 slab abcve the bettc= liner plate. The cylinder pertion will tave 24 an inside dismeter of 130 feet, a wall thickness of 4 feet, and a height 25 of 157 feet. The sballcw dame roof vill have a 2nrge radius of 110 26 feet, a transit;.on rsdius of 20 #ect 6 inch u, a thickness cf three 17 feet and 1 hei:Sht frc= sprf g line to ~;ex cf apprcximately 32 feet 28 4 inches.(~~') - lb - 63-174

1 The bndladag is designed to sustain safely all internal and ex-2 ternal leading ccnditiens which nay reasonab].y be e_pected to cecur 3 during the life of the statica er which could result fren the verst 4 postulated accident to the reacter's prinary ecchnt systen. 5 The pre-stressing syste= used in the reactor centai=ent 6 structure censists of strand tendens enciesed within sealed steel 7 ducts. pcrtland cenent greut, which provides a cerresien inhibiting S n m '4 e envire=ent and positive exclusien of ccrresive agents, covers 9 the strands within the duct. The anchcrages at the ends of the strands 10 are also protected by pcrtland cenent gcut within the end caps. 11 The reacter building is se designed that, with the engineered 12 safety features provided, the leakage of radicactive =aterials to 13 the envire=ent win result in doses wen within AEC's lo CFa Tart 1Co 14 guida'daes for any of the postuhted accidents.('9) The integ?.ted 15 leak rate at design pressure (c0 psig) will not exceed cne fia of 15

ne n cent by weight within twenty-four hcurs.

17 Pricr to cperation of the facility, the reacter b"4'ad"g win be 18 s:ubjected to a st=ctural integity prcef test and leak rate test. The 19 structural integity prcef test win be cenducted at H5 percent of 20 design pressure, and the initial leak rate test win be cenducted at 21 design pressure. periedic leak rate tests will be perfc=ed to assure 22 integrity of the reactor b"4'd495 A repetitien of the initial precf 23 test described in Appendix 5F cf the PSAR will be perfcmed periedically 24 and can also be perfc=ed at any other time the reactor is shut devn 25 during the life of the phnt. 304'a4"g deflecticas will be neasured 26 and c g red with the initial proof test deflections. These neasure-27 nents tcgether with an inspecticn for cra*4 g of the ccccrete d' ring 23 each preef test, will provide an indicatica cf centinued structural 29 integity of the centai=ent. cq g ud .s,e

1 3.4 Enrineerad Safety ?=atures 2 Engineered safety features are provided to fulfill the following 3 Pancticcs in the ""'e'y event of an accident: 4 a. Minimize the release of fissica products frc= the fuel 5 to the reacter b"d' Adag; 6 b. Insure reacter building integrity and reduce the driving 7 force for building l e ge; 8 c. Ee=ove fissica prcducts frcs the reacter building 9 at=csphere. 10 The engineered safety features systems can be grcuped into cer-11 gency ccre cooling syste=s, reacter building ecoling syste=s and fissicn 12 product centrol syste=s.(43) 13 The e=ergency cere ecoling syste:s contain both passive ficoding 14 systems and pu= ping systers. The passive flecding systen censists of 15 tvc pressurined core fleeding tanks which autc=atically discharge 16 borsted water into the reacter vessel in the event that the reactor 17 system pressure drcps belcw 600 psi. The pt= ping s'/stec consists of 18 two ec=pletely independent sub-systens. Each sub-systen contains both 19 a high pressure and a 1cw pressure indectica pu=p. Either sub-systen, 20 in conjunction with the core f1 ceding tanks, is capable of protecting 21 the cere for any size leak up to and'. including the dcuble-ended rupture 22 of the hrgest reacter ccchnt pipe. Either sub-syste: can supply 23 cco h nt directly frem the borated water storage tank er by recirculaticn 24 frc= the Reacter M1 ding su=p through heat changers which ecol it 25 before it is returned to ecol the ccre. 26 The reacter budW g ecoling syste= which is nade up of two 27 separate and independent heat rencnal syste:s 1d-4ts the pressure 28 in the reacter bud"g folleving a less-cf-cochnt accident. Cne 29 systen centains five septrate fan and eccler units. The other system 63-176

1 centains redundant spray headers which spray 1cv te=perature bcrated 2 vater into the reacter building to ecc1 it. The cpray water also 3 centains cheical additives as described belev. Each cf these systes L withcut the other has the heat reoval capability to naintain the 5 reacter building pressure belev its design pressure level. 6 The prinary centrol of released fissicn products fc11cvhg a less-cf-7 coolant accident is provided by the reactor building. 3 A secccd means for contrc'14"g released fission products is the 9 iodine renoval spray system which consists of redundant subsystes 10 of the same capacity and which ut4'd ses chenicals =1xed in the reacter 11 building spray water to abscrb the io d" released from the reactor a 12 coolant system and render it unavailable for 1mhge frem the reacter 13 building. The reacter building and either ene of the two redundant 14 reacter building spray systems vill -4t radiation doses at the exclu-15 sica radius and 1cv pcpulation cone boundary to values within the 10 CFR 100 16 guideline values. 17 35 Instrumentation and Centrol 16 A cc=plete and dependable netwerk of instru=entation and cen-19 trols vill be provided to insure the safe cperatien of Three Mile 20 Island Nuclear Statien, Unit 2. The protective syste is designed 21 to meet the ret 2irments of the " Criteria for Nuclear power plant 22 protecticn Syst es", Izzz 279 The reacter protective syste= neni-23 tcrs para eters related to safe operatien and shuts deva the reacter if an operating 1dmit is reached.47) This vill te accc=pl. 2ed by 24 25 interr2pting pcVer to the centrol rod drive mechanis=s and alleving 26 the centrol reds to drop into the reacter core. Alar =s are 27 previded to alert the cperater cf abnc=al cperating conditienc, 28 and inter 1cchs are provided to prevent operations which eculd 29 lead to pctentially bacardcus cenditions. l'<' c' '."3 ' J' "/ s'

1 The nuclear instr.::entatice syste: =cnitcrs reacter pcVer frca 2 startup level through 125 percent cf full pcVer operation. There are 3 sepa:ste overlapping instrumentation channels for the scurce range, 4 the inte=ediate range and the power cperation range. A centrol 5 system autc=atically =eniters reacter syste= conditions and the lead 6 require =ents en the turbine-generatcr unit, and adjusts reactor pcVer, 7 steen generater feedwater flew and the turbine thrcttle for safe. S efficient cperation. 9 The engineered safety features actuation syste= =cniters plant 10 ccnditiens and autc=atically initiates operatien of the engineered 11 safety features syste:s, if required. This system provides that 22 energency core cooling syste=s vil.1 be actuated by high reactor bv* Udng 13 pressure in addition to the redune. ant 1cv pressure sigcals frc= pressure 14 transducers in the tvc pri=ary lecps. 15 Follcwing proven pcVer statica design pbd'nsephy, all centrol 16 stations. switches, centrollers, and indicaters neces.sary to startup, 17 cperate, and shut devn the nuclear unit will be placed in the central'y 16 located centrol recs. The*e vill be sufficient infer.:atien display 19 and alars =enitcring to insure safe and r-1 *able cperatica under acr- ' 20 and accident conditiens. Special emphasis will be given to =aintaining 21 centrol recs integrity during accident ccnditiens.(53) 22 For the "nld'<ely centingency that occupancy of the centrol recs 23 =ay be tecperarily denied, the capability vill be available fer +,'<d c 24 the plant to, and =aintaining the plant in a safe shut-down cenditica 25 frem ether locaticas in the plant. 26 During the detailed design of the instru entatien systems their 27 '"d'.y to ec en failure =cdes vill be evaluated. The possibility d-28 ef syste=atic, ncn-randes, cencurrent failures of redundant devices, 29 net considered in the single failure criterien, vill be taken inte, p.4 m[ V* t A.

1 acccunt in the evaluatien. '"he instr =entation signals sent to cen-2 trol and safety circuits frc c-n tran=itters are nade fully inde-3 pendent by the use cf ischtien a=-14"iers. The effectiveness of these 4 isolatien s=plifiers has been de=cnstrated by analysis and by actual 5 test of prototype equip:ent as described in Sectica 7.1.3.6 of the PSG-6 3.6 Electrical Systets 7 The design of the electrical systees fer Three Mile Island 8 Nuclear Statica, Unit 2, is based en provi15 g the required electrical. 9 equipsent and pcwer scurces to insure safe, reliable cperatica and 10 safe, crderly shutdown of the unit under all nor=al and energency 11 conditions. Three sources of pcwer, each possessing varicus degrees 12 cf redunhncy are available to insure a supply of electrical energy 13 to the staticas' safety syste=s under a accident cenditicas, 14 including the less-of-ccclant accident as cutlined belev: 15 a. Six 230 kv transmissien lines will supply pcwer for 26 the unit aur'7'nry lead thrcugh either cne er both 17 cf the auxiliary transfomers cennected to a 230 kv 18 substatien. Each of the a'+n / transformers will 19 be siced to carry the unit e.:.11 lead an7 aries and d 20 the engineered safety features. A 4160-volt tap cf 21 abcut 4-MVA capacity will be nade frc= the Unit 1 22 a* 14 ~/ transfer =ers to previde ancther source of 23 offsite pcwer en a standby basis to the engineered 24 safety feature busses. 25 b. The nain generater will centinue to supply the statica 26 a'M'dary lead upcn abrupt separation frc= the rest 27 cf the 230 kv systen. 25 c. Upen less of all scurces cf pcwer described in (a) 29 and (b) above, power will be supplied frc= two auto-NO' M g

1 =atic, fast start-up diesel engine generatcrs. These 2 are sized so that either can carry the reqaired engin-3 eered safety features lead. A pra-d"ry esti= ate cf k the rating of each esergency genertter is 3,000 kw. 5 The unit will generate electric pcwer at 22 ' t, which will be r 6 fed threugh an ischted phase bus to the unit ain transfc=er where 7 it will be stepped up to 230 'ct tran=ission voleage and delivered 8 to the substation. The 230 'ct substation will be linked to the 9 Met-Ed tran=issien network by six circuits; three Middletevn Juncticn 10 circuits each capable of carrying the fall output of one unit; cne 11 circuit to Hosensack, capible of carrying the cutput of one unit; and 12 ene line each to Steelten and Jackscn cagble of carrying g eater thu 13 50% cf the cutput of cne unit. 14 37 Aurd Wry Systets 15 Auxiliary systeas are provided to supply reacter ecchst =akeup 16 and pu=p seal water, to ecol the reacter during shutacwn, to coc1 17 cc=penents, to ventilate statica spaces, to bandle fael, and to ecol 13 spent fael. 19 Reacter ecolant =akeup and pu=p seal water is supplied by the 20 =akeup an:1 purification system. This ryste=, which also sertes the 21 engineered safety features fanction of providing high pressure eter-22 gency core ecolant, =aintains the proper coolant inventcry in the pri-23 =ar/ system, maintains the pu=p seal water flew, adjusts the cencentra-24 tien of dissolved neutren abs rber in the reacter ecolant, and maintains 25 yaper water ch mistry. 26 The decay heat reeval system ecols the reacter when the reactcr 27 syste= is depressurized fer maintenance er ref2a g. E s sane syste 26 serves the engineered safety features fanction of providing 1cw 29 pressure energency ccre ecclant and of recirculating berated water to G3 ~190 1 cool the core in the unlikely event of a loss-of-coolant accident.(50) 2 The cooling water systems maintain te=peratures throughcut the 3 equip =ent and structures of tha station.(57) Appropriate nc :a1 4 ventilation systems are provided in the station.(50) 5 A fael ham'4ng syste=(59) provides the =eans for safe, reliable 6 handling of e2el frc= the time it enters the station as new P2el 7 until it is shipped frc= the station as spent fuel. Irradiated fuel 8 is handled under water at all times until after it is placed into 9 a shipping cask. The water provides a radiatien shield as well as 10 a reliable source of cooling for the '.; radiated fuel assemblies. A 11 spent $2el ecolirg syste= :nintains the te=perature of the spent fael 12 storage pcol water within acceptable limits.(60) 13 3.8 stea= and power conversion syste= 14 Se steam and pcver conversicn syste= is designed to re=cve 15 the heat energy generated in the reactor core by producing stes= 16 in the two stes= generaters. This heat energy is converted to 17 electrical energy by the turbine-generater. This cycle, including 13 the necessary equipment to achieve safe cnd reliable operation, is 19 s * -4 ' e in cencept and design to turbine-generator cycles in successful 20 use for my years.(61) 21 39 Radicactivitf centrol syste=s 22 Radicactive gaseous, liquid, and solid war,tes in the statica 23 are bandled by the vaste dispesal syste=s. These syste=s contain 24 the equi; tent necessa.ry to safely collect, process, and prepare for 25 disposal of the radicactive wastes which result frc= reacter cperation. 26 Thest syste=s are designtd to ~4-4-4:e and centrol tne release of radio-27 active s terial frc= the station to the envirec=ent and will naintain 2S releases belcw the 'd-4 ts of 10 CFR 20. (62) Q'j %g 4

1 A process radiation monitcring syste =cnitcrs effit.ent released 2 to the envirc=ent and provides an early nrning of pcssible equirant 3 malfunction er potential radiolcgical ha::ard. "'he radiatica =cnitoring 4 system includes a ec=bination of conti=cus autc=atic =cnitoring and 5 periodic sa=pling.(63) 6 Shielding throughout the station insures that radiation deses 7 to the general public and to cperating personnel during nor=al cpera-3 tion are well within the '4-4 ts cf lo cra 20. (64) 9 3.1o Sbared cc=ronents with Unit :To.1 10 Three Mile Island Unit :!c. 2 vill =ake use of scme facilities en 11 a shared basis with Unit :To. 1. The shared ec=penents include: 12 a. Fire protection system 13 b. Miscellanecus vaste concentratcr lh c. Fuel handling building crane 15 d. Electrical switchyard 16 e. Ainciliary stes= generater 17 f. IIew fuel stcrage 13

icne of the shared cc=penents are required for successful opera-19 tien of safety features er centrol systems of either nuclear steem 20 supply systen.(65) 21 4

SAFE"Y A"ALYSES 22 Potential malfunctions cr equip =ent failures have been analyzed 23 to provide a safety evaluation of the hree Mile Island ::uclear Station. 24 This evaluation de=ctstrates that the public will not be exposed to 25 radiation in excess of the 14-d ts established in the AIC's regulatien 26 for siting requirements, 10 m ICO, even in the very unlikely event 27 that ene of the accidents postulated in the Applicatica should occur.(66) co. 63 182

1 Wo categories of =alfunctions er equip =ent failures have been 2 analyzed; those in which the core and ecolant beundaries are protected 3 and those in which one of these bcundaries is not effective and standby 4 safety features are required. Se core and ecclant betman~/ protection 5 am17 sis shews that, in the event any cf the postulated =alfuncticas 6 were to occur, the no:=al protection syste=s cperate to =aintain the 7 integrity of the core and of the ecolant boi' eda'y. (67) The standby e safety features analysis de=cnstrates the capability of these safety 9 features to assure protection of the public for pcstulated nal^metions 10 in which the nc:=al protactive syste=s =af not =aintain the integrity 11 of the core and ecolant beundary.(50) Sese aMyses shcw tbat for all 12 credible =al^metiens the radiation exposure to the general public is 13 well belcw the 1" ts prescribed in 10 CFR 100. 14 Of the postulated equip.ent fai1= es, a less-cf-ecolant acci-15 dent is the = cst severe. Energency ccre eccling systems are provided 16 to preveat clad and fuel da= age that would interfere with continued 17 core cooling fer reacter coolant system fail = es up to and including 15 the ec=pletc severance of the largest reactor coolant pipe, As prev-19 vicusly discussed in this S u ry Description, the core eccling sys-20 te=s ins r e that the core will ra + n in place and intact.() The ), i. 21 reactor building spraf cr e=ergency cooling units li=it the pressure 22 in the reacter building (k5) and the iodine re=cval che=icals in the 23 reactor building spray solution in conjunction with tre reacter build-2h ing assr e that the public is protected frc= excessive exposure to 25 radiation and radicactive =aterial. E=ergency electrical pcwer is 26 available en-site to insure operation of these s/ stems even if 212 27 external scurces of electric pcwer to the plant are assumed to be un-26 available at the ti=e of the accident.(69) 29 Res"Its of the safety analyser: shcw that, even in the event of 9 4 qq Du ^Lo

l a less-of-coolant accident, no ccre telting will cecur.(70) Ecwever, 2 in order to denenstrate that the cperation of a nuclear pcwer station 3 at the proposed site does not present acy undue hacard to the general 4 public, a hypcthetical accident has been a"alyzed involving a release 5 of 100 percent of the ncble gases, 50 percent of the halogens and one 6 percent of the solids in the fission product inventory. The acalysis 7 evaluated both the direct radiation exposure and the potential total 8 dose to the thyroid frc= the iWmhtien of fission products which leak 9 frc= the reactor building. The lcw leakage rate of the reacter build-10 ing, and iodine re=cval by the spray system reduce the potential radia-11 tien dose to the thyroid to below the 10 CFR 100 guidelines even in the 12 event of such a hypothetical occurrence.(71) This till be even further 13 reduced by the fluid block and penetration pressurization syste=. (72) 14 5. ~~zSTS, I:rSFECTICN. A'D GLUlTI CC?.'"2CL 15 Pressure containing cc=penents of the reactor ecolant syste= 16 will be designed, fabricated, inspected, and tested in accordance with 17 Sect?.cn III, Nuclear Vessesis, of the A=eruan Society of Mechanical 18 Engineers 3 oiler and Pressure vessel Ccde. Piping will be designed, 19 fabricated, inspected, and tested to the applicable previsions of Nuclear 20 Fever Piping USA StnMeds 3 31.7 - 1968.(73) Nondestructive testing, 21 including radiography, ultrasenic, nagnetic particle, er liquid pene-22 trant ey,*ations will be perfor=ed as appropriate during fabrication 23 of the nuclee ec=ponents.(74) 2g AM'4ry sycte=a and eculp=ent will be designed, fab-icated, 25 and tested to the appropriate provisiens of reccgnized codes and 26 standards of organi::aticus such as the A=erican Society of Mechanical 27 Engineers, American Society for Testing Materials, USA Standards 28 Institute, and Institute of Electrical and Electrcnics Engineers. (75) - 2h - Os 4. p 'AL1 <~a

y A cc=prehensive field testing progrs= will be cenducted to insure 2 that egaiment and syste=s are built in accordance with design 3 re @ eee s. ne rea ter builmg v_n be desiped and bum in g acecrdance with applicable pcrtiens of the B'd' Ad g Code Regal e-5 ments for Reinicrced Cencrete, ACI 318-63; Specificatien fer Structural 6 Cencrete for 3'd144 3s, ACI 301-66; AISC Manual of Steel Ccnstracticn; 7 ASME Boiler and Pressure Vessel Code, Secticas III, VIII, and IX. (76) 8 Materials and verk=anship win be inspected to insure ec=pliance with 9 appropriate codes, specifications, and standards. Materials to be 10 inspected and tested include cencrete, liner plate, prestressing n syste= =aterials, batches, penetrations, structural and reinforcing 12 steel. 13 The reacter bed 7 dd I vil.1 be structurally tested at H5 percent 14 of design pressure. bl) In additica, it will be leak tested to insure 15 cc=pliance with a =azi=un alleable gross leak rate of One fifth of 16 ene percent by weight per 24 hours (77) at the design pressure. Pro-17 visiens have been included for in-service pressure testing of batches 18 and other penetratiens.(IO) 19 Censideratien has been given to the inspectability of the reacter 20 coolant syste= in the design and arrange =ent of ec=cenents. Access 21 for inspection of the reacter coolant systes includes access for 22

" 4 m tien by direct er re=ote neans.(N ) (79) 23 Metropolitan Edisen Cc=cany has the respcnsibility to assure 24 that Three Mile Island Unit :To. 2 vill be fabricated and ccustructed 25 in accordance with applicable codes and specificatices. Accer d,:17, e

26 Metropolitan Edisen Cc=pany has established a ec=prehensive qualitf 27 assurance progrm which began with the initial statica desip. This 28 progrs= is censistent with the intent cf the prepcsed AEC Criteria 29 for :Tuclear Power Plants Quality Assurance dated April 17, 1969 G3-tES

1 Metropolitan Edison Cc=pany has established an crganizatien to i=ple-2 cent this quality assurance program. The Metropolitan Edisen Project 3 Directer, respensible for the ccordinatien and duecticn of the pre-4 gram, vin be aasisted by the General Public Utilities Manager of 5 quality Assurance and MFR Associates, Inc., in =enitoring the quality 6 assurance progrs=s of Babecek and Wilecx, Burns and Roe, and United Engineers and Censtructors and their sub-contractors. 50) 7 6 In additien, Babecek and Wilecx, Burns and Roe, and United 9 Engineers and Ccnstructors win perfc= quality assurance su:-te41"ce 10 of the equipnent and cccstruction centracters. n A cc:cprehensive field testing progrs= for the "'hree Mile Island 12 Unit 2 vill be carried out to insure that equi;=ent and systens per-13 form in c.cc reance with design criteria. The testing progrs= will be 14 carried cut according to detailed predeter=ined testing techniques 15 and precedures. The types of testa viH include hydrostatic, functional, 16 electrical, and operatic =al.(81) 6. RESIARCH AND DEVEL0ECIT PROG?AMS A:iD AREAS I:I WHICH FUREZR 17 .S TEC=NICal ritCFyAIIcn IS To EI rEVELoFED 19 ne cuclear steam supply syste for nree Mile Island Unit 2 is 20 of the same basic desiga as Unit 1 and sd d'" in concept to several 21 projects already in operation, under ecnst:ncticn er recently licensed 22 by the Atc=ic Energy Cc=nission. The pra'd-d-nry design is based cn technical data which has been developed in the nuclear indust'y and r 23 24 on data developed by Babcock and Wilecx which is spe.cifically related 2e to the Three Mile Isle.nd Unit 2 nuclear design. Tc cc=plete the final 26 detail design c: sc=e ec=penents additiccal technical infor=atien vill be obtained. 27 2g Most of the verk reported in this section censists of prcef testing of engineered designs, ccnfi:=ater/ tests to confirm e@ftic-29 . 63-186

I ally predicted conditions, or analytical studies to evaluate design 2 or accident ccnditions. 3 The fo11cwing are the areas of the plant design in which 4 additinnal technical data has been or will be developed to finalize 5 design details or cenfi::: the safety analysis. 6 a. Cnce-Throuch Stees Generator 7 The design of the once-thrcugh steem generater is baJed 8 en experinental verk en bom g heat transfer and data 9 obtained by Eabecek and Wilecx in eali length nodel 10 tests of the unit. The testing of a protot jpe unit 11 by Eabecck and Wilecx has been ec=pleted. It included 12 perfor=ance, mechanical, viaratien and blevdevn tests, 13 and cent:~al syste= develep:ent. (82) The results have 14 confiz=ed the analytical predictions of perfc&"ce, and 15 sufficient data en the perfoz=anca and structural design 16 bas been obtained fren cperatic:: of the test nodels to 17 f'm14:e the design of the steen generaters and to 18 confirm the analytical =cdel developed for stees generater 19 depressurization.(33) ne results of the tests will be 20 reported in E&W Tcpical Repo7t EAW-1CCO2 and will be filed 21 with the AZC Staff in the trird quarter of 1969 22 b. Centrol Red Drive Unit 23 The design of the centrol red drive nectanis=s is 24 based en a principle which has been used in operating 25 reacters and which has been extensively tested by 26 Eabcock and Wilecz. Test progrs=s have included fall 27 scale prototype testing under nc-flev cenditiens, 28 fall scale prototfpe testing at operating conditiens, G]-{g7

includi~.g ficw, and cc=penents testing.(84) proof testing 1 2 of a prototype =echanis was carried cut for a fc11-life 3 cycle of strches and trips at cpti=u= and lco percent 4 =isalig=ent conditions, t ' =ajor design parameters 5 were ecnfir ed. Data frc= these test prcgrams confi =ed 6 design require =ents indicating that rod drop time require-7 =ents were =et, that excessive wear cf ec=penents did not 3 occur and that cerrosion was not significant. These test 9 data have been reported in 3&*J Tcpical Report Erd-lCC07 10 and filed with the EC Staff en June 26, 1969 11 c. In-Core :Teutron Detectors 12 The testing to de=enstrate the perfer=ance and 1c=gevity 13 of the self-pcwered detectors in the Babcock and '411ccx 14 Test Reactor and in the Big Rock point :Tuclear power plant 15 has been ec=pleted (86) The tests have de=cnstrated that the 16 detectors perfor= according to specifications and are capahle 17 of =easuring neutron flux locally in a MR envirc=ent over a 18 period of several years with a relative accuracy of 5%. 19 L: the present ti=e, the detecters have ace anted operational 20 experience equivalent to approxirntely four years of fall 21 power operatien in the Three Mile Island Unit 2 reacter. 22 The test results will be reported to the EC Staff in 23 3/14 Tcpical Repcrt Erd-LOC 01 during the fourth quarter of 24 1969 25 d. Core The:nal and Itf raulic Desien d 26 Ccre ther=al perfer=ance was evaluated using the '4-3 27 cor: elation for predicting D G. This correlation is 29 available in the literature aM has been used and found g jgg

1 acceptable in establishing therr.a1 design li=its fer 2 other large prescurized water reacters. With the use 3 of this correlatien, caly the vessel nodel ficw tests k were necessary to substantiate cperation of the plant 5 within acceptable thermal 1<-d ts.(87) These ficw tests 6 have been ec=pleted and have de=cnstrated acceptable ficw 7 distributien fcr the rated pcwer level with internal vent 8 valves in the =cdel. 9 Cther ther=11 and hydraulic verk being dcne by Sabecek 10 and Wilecx is directed tcwards i= prove =ent in Pature 11 core design. The vessel =cdel ficw test results win be 12 reported in 3&W Tcpical Report 3AW-10012 during the fcurth 13 quarter of 1969 14 e. Interrals Vent Valves 15 Tests have been ec=pleted to ccafirm the intermis vent 16 valves design requirements for both ner=al and accident 17 conditions. Prototype valves were tested to ecnfirm that 18 the valve is structurally adequate te withstand bydraulic 19 1 cads a"d to perfc:= its steam venting f nction during a 20 less-of-coclant accident (LCCA), and to insure that the 21 valve will not open when excited by vibrations of the 22 s=plitude and frequency expected during nor=al cperation. (00) 23 Ms work has been reported in a E&W Tcpical Reper 24 3AW-lG005 and filed with the AEC Staff en July 10, 1969 25 f. Riel Clad Failure 26 A Babecck and Wilecx pregrs= is being conducted to inves-27 tigate fuel clad failure =echanis=3 in crder to insure 28 that ncne will interfere with the ability cf the emergency d3~189

1 ccre ecoling syste=s to accc=plish their cb,jectives.(90) 2 The program involves testing and analytical phases. 3 Para =etria asts to investigate the effects of clad 4 te=peraturs N at-up rates, internal pressure, metallur-5 gical and ;bysical clad conditions en clad defemtion 6 are being carried cut. pre'd-dnary results indicate 7 that clad sva'idng is localized and does not bicek ecclant 8 channels. This work will be cc=pleted in late 1969 and 9 repcrted in tcpical report for=at during early 1970. 10 g. Xenen Cscillatiens 11 The possibility of the occurrence of xenon oscillatiens 12 throughout core life is being evaluated analytically by 13 Eabecek and Wilecx.(91) A =cdal analysis has been ec=- 14 pleted and ene, tve, and three dimensional calculations 15 are being carried cut to evaluate axial, aci=cthal, and 16 radial oscillations including =ethods for controlling 17 pcssible esci11ations. Xenen escillatiens are pr m*ily d 18 an cperational proble=, not a critical safety prcble=, 19 because the oscillations would be slev (25-30 hcurs) and 20 can be centrolled by cperator action. The ncdal analysis 21 results bave been repcrted in 3&W Topical Report EAW-lC010 22 and filed with the AEC Staff en August 13, 1969.( W 23 The re=aining analyses will be ec=pleted by late 1969 24 and reported in early 1970. The design of =etheds to 25 el d-dnte er centrol these escillations is being carried 26 cut in parallel with these studies. 27 h. Chemical Spray Additive 23 One of the radiological protecticn sys te=s of the 2:ree ud__4 q L

W 'e Island Unit 2 provides for spraying chemical sclu-2 tiens into the reacter building to ra=cve iodine under 3 accident ecnditiens. Testing to de=enstrate the ability 4 cf the che=ical sprays to re=cve and retain iodine 5 effectively, and te demonstrate solution stabilig and 6 che=ical ec=patibility with plant naterials has been 7 cc=pleted. AEC sponscred prezra=s de=cnstrating the 8 icdine re=cval capabilities cf the spray sclutions have 9 been carried cut and data has been published in the Open 10 literature. Eabecek and Wilecx has cc=pleted a test pre-11 m designed te evaluate the stability, ce=patibility, e 12 and iodine retentien capabilities, cf amline sodium 13 thicsulfate spray sclutions under accident conditiens.(93) Ik The test results indicate that the 9cine sodium thic-15 sulfate spray solution adequately meets the design require-16 =ents for s* ability, cc=patibility, and retention. The 17 test results have been discussed with the AEC Staff.( N 13 7. TECHYICAL QUALIyICATIC:3 19 7.1 Metropolitan Edison Cc=cany 20 Metropolitan Edisen Cc=pany will be responsible for the engineer-22 ing, design, construction, cperatien, and =aintenance of Unit 2, 23 Three Mile Island Ziuclear Station. 24 Met-Ed has 85 years experience in the design, constructica, 25 and Operation of electric generating stations, cperates fcur stea: 26 electric generating plants, arai one hydroelectric staticn with a 27 total net capability of 8h5,300 kv. Met-Ed has a total plant 28 investment of $361,990,0C0 and e=ployes ever 2,300 pecple. 29 Met-Ed is a subsidiary cf C-eneral Public utilities Cerperatica c q -, q Uu A

1 which in 1959 for=ed the Saxton :Melear Experimental Ccrporation 2 to construct and cperate the Sar.cn IMelear Electric Genenting 3 statien for research, cperating, and engineering experience. Met-Ed 4 is the cwner and operator of Three Mile Island Unit 1 which is 5 presently under ecnstruction. :. hey Met-Ed e=picyees who vill be 6 involved in the operation of Three Mile Island Unit 2 will have 7 received training and experience at the Saxten statien and en S Unit 1. 9 The General Public Utilities :Mclear Pcwer Activities Grcup, 10 which has been organi::ed to = cst effectively =cbili::e the capabilities 11 and nuclear experience with the GPU subsidiaries, provides both 12 technical assistance and guidance to the Met-Ed project and cperating 13 stafft en nuclear =atters.(95) Ik 7.2 3abecek and Wilecx Cc=cacy 15 3 G's participatica in the develep=ent cf nuclear power dates 16 frc= the Manhattan Project. 3G's nuclear activities are bread and 17 include applied research to develcp fundam ntal data, desi p, and 16 natufacture of nuclear s/ste=s ce=ponents, and design and nanufacture 19 cf ec=plete nuclear stea: generating syste=s. Through the 3 G 20 Cc=pany's several divisiens a wide range of equip =ent for nuclear 21 application is designed and =anufactured. The 3 R Cc=pany's najor 22 nuclear contracts, in additien to a substantial percentage of ec=- 23 penents for the nuclear Ihvy, have included Indian Point :To.1, 24 ti3 Savannah, Advanced Test Reactor, Ocenee :Mclear Station Units 1, 2, 25 and 3, ~hree Mile Island Unit 1, three units which have received 26 AEC ccustructicn per=its, and three additicnal units for which appil-27 catien for licensing has been nade. (90) 32 - eqq co U0 u.4

1 7.3 Eurns and Ece. Inc. 2 Burns and Roe, Inc., the Architect-Engineer for this project 3 except in the areas of ecoling tcwer design and interfaces with h Unit IIc.1, will asse=ble the necessary infer =aticn for all required 5 site studies and plot plans. In additien, they will furnish an 6 laycuts and syste= ar ange=ents, prepare specifications for najor 7 equip =ent and syste=s, and assist Met-Ed in the evaluation of bids 3 for all purchased equip =ent. 9 Eurns and Roe, Inc., was inecrporated in the State of :Tev 10 Jersey in 1935 and is an independent censulting engineering crgani-11

ation devoted to the practice of engineering, design, construction, 12 and related supporting services. Since 19h9, 3&R has been respctsible 13 for :nny cf the majcr nuclear power and nuclur research facilities, ik radiation laboratories, reacter and pr4-"y heat d ssipation syste=s, 15 reacter fuel processing, reacter test activities, nuclear handling 16 syste=s and uranium cre reductica prccessing.

17 During the past five years, 3&R has e=picyed a staff cf ever 18 800, which includes approxinately 50 specialists in the :luelear Engi-19 neering Di;ision and Quality Assurance perscnnel. The a v capital 20 (constructed) cost of projects verked on by E&R has avaraged over 21 $100,000,000.(97) 22 7.4 Gilbert Assec'ates, Inc. 23 Gilbert Assceiates, Inc., tss been retained by Met-Ed as the 24 Architect-Engineer for design of the ecoling towers and as censul-25 tants en site related engineering. In addition, Gilbert Associates, 26 which is the Architect-Engineer for Unit 1, has responsibility u r 27 interfaces with the Unit 1 plant. 23 Gilbert Asscciates, Inc., engineers and consultants, was ~n.

"Odfm3

1 crganized in 19C6 and has its nain effice at Reading, Pennsylvania. 2 Since 1912 GAI has been responsible for the design cf over 110 ther-3 nal generating units, both fossil and nuclear, represensing =cre k than 16,000,000 kw of capacity. Design experience inclr. des reheat 5 cycles, ence-through boiler units, and supercritical u: tits in rr. tings 6 up to 500,000 kv. At present GAI has over 8,000,c00 les cf generation 7 under design. 8 The Gilbert Asscelates organization incluties nearly cCO 9 e=plcyees with a ec=plete staff of engineers, drafts =en, and nany 10 technical specialists. Included in the total staff are ever 3C0 11 engineers and technical speed ssts ad 180 drafts =en. '"his includes 12 =e=bers cf :nnagement, professional persennel, 2nd individuals in 13 other specialized fields. 14 Since 1750 CAI has played an active and i=portant role in the 15 develepnent of nuclear energy for private utilities, fndustry, and 16 govern = ental agencies. Gilbert projects include ec=plete prep _:s cf 17 nucles" pcVer develep:ent involving analysis cf sites, cc=plete 18 evaluations of proposals, centract and fuel pregrs= assistance, pre-l? paration of license applicaticas, cc=plete plant design and precure-20 =ent.(90) 21 7.5 United Fm ineers and Ccnstructors 22 United Engineers and Constructors, Inc., has been retained 23 as Constractica.vanager to supertise and coordinate the constracticn 24 of both Units 1 and 2. UE&C will work in cocperation with 3&R to 25 establish a schedule for the orderly precurenent and delivery of 26 equipnent snd caterial to the jcb site. 27 United Engineers and Cctstructers, 20. was incorporated in 1928 28 as a censolidation of four successful engineering and ccnstraction - su - g3-194

O 1 crganications. "he present secpe of activities includes the 2 design and/or constraction of fossil and nuclear pcwer plants, 3 research and development facilities, and nary other types of ec=- L tercial and industrial plants. Censulting engineering is also 5 provided for =any facets of this work. c The present United Engineer's Constructicn Department includes 7 =cre than 550 pernanent e=plefees, including construction =anagers, 8 superintendents: resident job engineers, field engineers, craft 9 supervisors, quality centrol engineers, accountancs, and other lo required field service persennel. In addition, United Engineers 11 currently e= ploys =cre than k,8C0 craft labor persennel. A suo-12 stantiG amunt of =cdern constructica equip:ent is naintained and 13 kept in ecnstant use and the latest con. uctica techniques are 14 e=plcyed. 15 United Engineers is current 4 responsible for approxi=ately 16 $1,5C0,C00,000 of ecnstraction work in progress, including =cre 17 than $1,C00,C00,000 in nuclear and fossil pcwered generating plants. le United Engineers & Ccnstructcrs Inc., has participated in 19 either constraction ra mgement, design, or physical ecnstraction 20 of 13 nucitar pcwer facilities. (99) m - q o r-O t> ed

1 8. CC:M i"'S C:7 I""2'S ET ACES LG 2 8.1 centai=ent Purging to centrol Rfdregen concentratien Fenewtg 3 1ccA 4 As stated h the answer to questien 2.2A in Supple =ent 3 cf 5 the PSAR, centro 11ed purging of the centain=ent appears to be at 6 acceptable means of preventing a F.angercus concentratica of h/ regen d 7 within the centai=ent b,

w g.

Further analysis and syste= design 8 are proceeding to establish detailed purging requirenents including 9 alicance for levels of ziree.11u=-water reacticn which eculd occur 10 if the effectiveness of the e=ergency core eccling system is sig=ifi-11 cantly less than expected. S&W will file a topical repcrt en these 12 =atters with the AEC staff prier to the end of 1969 13 If the final evaluation of the proposed purging syste indi-14 cates unexpected problems that i=valif. ate the cenclusiens which havn 15 been drawn to date, alternative =eans for centro 11"g the h-Acgen 16 cencentration will be enitated. 17 8.2 InstNi=entatien Cc=c n Failure Modes 18 The instrt=entatien system will be evaluated for can failure 19 =cdes as described previcurly in Sectic 3.5 of this Sm' y Descrip-20 tien. In addition, studies are being conducted to evaluate the ccuse-21 quences of protective system failure during anticipated transients. 22 8.3 In-Service Lnitcring ter vibratien er Loose Parts 23 in the Reacter coolant System 24 Applicant vill study pcssible =eans for =cnitoring vibraticas er 25 presence of loose parts in the prinary syste=. If a practical and 26 appropriate syste:1 for acec=plishing this is develcped, sericus 27 censiderstics will be given to i=cle=enting the system in the design 28 cf Three Mile Island Unit' 2. un 4 q b-i~a m

a Q 1 3.4 Interit/ of the Post-Accident Ccclin: Syste= 2 The ec=patibility of :sterials in the centainment, reacter 3 syste: and engineered safty features systers, with the che:ical k additives used in the b" 4ing spray syste=, has been studied and 5 tested under eceditiens which s'=ulace the te=perature vs. c1=e 6 ccnditiens expected fc11cwing an accident. "'he tests perferred 7 to date indicate acceptable perfer=ance for the =aterials used in 6 all s'/ste: cenpenents. The Applicant is reviewing the test progrs; 9 to :mke certain that LCCA envirc:=en al effecta en crit' cal car _ pen-10 enta have been evaluated. 11 8.5 Reseter ccchet P.,_ Meter F2cubeels 12 The r meter ccc1&ct p p cotor flywheels vill be s* Meted 13 to the walit7 assurance pregrs=s as cut 11ned in Appendiz 1 E of 14 the ?"AR. The finished flywheels will h volt =etrically inspected 15 by ultrasenic means for scundness using the sa=e acceptance criteria 16 as that used for reactor vessel plate. The flywheels will also be 17 ultrasenically inspected during naintemce cutages that require the 13 =ocer to be din::antled. 19 9 Ccmen DEFETSE A'TD SECURTfY 20 91 There is no ir.dicctica that ccustruction and operation cf the 21 Three Mile Island Nuclear Station Unit 2. rill in any way be inimical 22 to the ec==ca defense and security of the United States. 23 As stated in the Application, Metrepc11 tan Edisen Cc=tany and 24 Jersey Centre.1 ?cwer & Light Cc=ps=y are Pennsylvania and New Jersey 25 corporaticns respectively, and are engaged as public utilities in the 26 production, trans=issien, and sale of electric energy. A1.1 of the 27 directers and principal efficers of the ec=;anies are citizens of 28 the United States, and the ec= anies are not evned, centrc11ed, er 29 "mted by an alie 1, a fere:gn ccrperatien, er a fereign geve.-_.ent. 63 147 _ 37 _

1 '"he Application centains no restricted itta er other defense 2 infcI=ation, and the Applicant has agreed that it vill not pe:=it any 3 indivi aal to have access to restricted data if required =til the Civil !i Service C~--'ssion shall have rade an investigatica and repcrt to the 5 Atc=ic Energy Cc=ission en the claracter, asscciations, and Icyalty 6 cf such indivitaal, and the Atc=ic Derg Cc=ission shall have deter-7 =ined that per=itting :uch persens to have access to restricted data 5 vill not endanger the cc:r.ncn defense and security. 9 As a licensee the Applicant vill be subject to regulatiens of the 10 Atc=ic Energ Cc=issicn relating to the transfer of and accountability 11 for special :raclear =aterial in its possession. A=end=ents to the AEC 12 Eules and ?.egulatiens (10 CFR 50.60) under which the AIC has discontinued 13 allocating q".antities of special nuclear =aterial to reacter licensees 14 evidence that such naterial is nc lenger scarce. Moreover, in the event 15 cf a state of war or national emergency, the AEC =ay crder the recapture 16 cf special nuclear =aterial, as well as the operatica of any licensed 17 facility. (10 CFR 50.103) c ,.0. C -..C L..-,.c.uc ul v.. 19 10.1 Cn the basis of the foregoing and the Application, the Applicart 20 respectfully sub=its that: 21 a. Sis Application, as amended, of Metrepelitan Edisen 22 Cc=pany and Jersey Central pcVer & Light Cc=pany, des-23 eribes the proposed design of the 2ree Mile Island 24

?; clear Station, Unit 2, including the principal archi-25 tectural and engineering criteria for the design, and 26 identifies the =ajor features er cc=ponents'inecrpere.ted 27 in the plant for the protection Of 'the health and 2S safety cf the public;

.2.a - d3 198

1 b. The Applicatien, as anended, identifies the technical 2 cr design infernation necessary to ec=plete the final 3 cafety analysis. Such infernatica can reescrably te k left for later censideratien and will be supplied in 5 the Final Safety Analysis Report. 6 c. Safety features which require P1.rther research and 7 develep:ent, and the research and develepnent pregrs=s 8 to be carried out, are identified in sectica 1.5 of 9 the Applicatien. The research and develep:ent progrs= 10 is reasecably designed to resolve any questicas associ-11 ated with such features at er before the latest date 12 stated in the Applicatien for cc=pletica of constrac-13 tien of the facility; 14 d. Taking into censiderstica the characteristics of the 15 site and envirens and the proposed design of the mee 16 Mile Island Unit 2,such facility can be constructed 17 and operated within the 1 *-itations established by 18 10 CFR 20, withir the site criteria set forth in 19 10 CFR 100, and withcut undue risk to the health 20 and safety of the public; 21 e. The Applicant is technical.17 qualified to design and 22 construct the proposed racility; and 23 f. The issuance of a ecastruction pe: nit fer the Three 24 Mile Island Unit 2 vill not be ininical to the emn 25 defensa and security or to the health and safety of 26 the public. ~ -4 nc Ui u

AHE:0IX A LIST CF RuurTCES 63-200

Append.d.x A Lisc cf =eterences (1) ISAR, Vel =e 1, Sectica 2.2.1 FSAR, Vol=e 1, Seccion 2.2.3 (2) PEAR, Vel =e 1, Section 2.2.2 (3) PSAR, Vol=e 1, Section 2.2.4 (k) PSAR, Vel =e 1, Section 2.3.1 (5) ISAR, volu=c 1, Section 2.3.2 (6) PSAR, vol =e 1, Sectica 2.3.3 FSAR, Vol=e 1, Secticn 2.3.4 (7) PSAR, rol=e 1, Section 2.k.1 (8) PSAR, Volu=e 1, Section 2.k.k (9) PSAR, Volu=e 1, Sectica 2.k.5 (10) PSAR, Vol=e 3, Section 9.3.2.7 (11) PSAR, Vol c e 1, Section 2.k.6 ISAR, Vol=e 1, Appendix 20 (12) SAR, Vel =e 1, Section 2.5 PSAR, Vel =e 1, Appendix 2A PSAR, Volune 1, Apperdix 2D (131 FSAR, Vol=e 1, Section 2.6 PSAR, Vel =e 1, Appe-Ad x 23 FSAR, volu=e 4, Supplement 2 Questien 6.k (ik) PSAR, Vol ce 1, Section 2.7 (15) PSAR, Voice k, Supplement h, Section A (16) PSAR, Voice k, Supple =ent k, Section 3 (17) PSAR, Vol=e k, Supplement 4, Appendix D (16) FSAR, Vol=e 1, Section 1.1 03 201

(19) IT.3, Vol=e 1, 3ble 1-2 (20) PSAR, Vol=e 2, d'cle 3-2 (21) FSAR, Vol=e 2, able 3-1, Section 3.2.4.2 (22) PSAR, Vol=e 2, Section 3.2.3 (23) FSAR, Vel =e 2, Sectica 3.2.2.1.2 PSAR, Vol=e 3, Sectica 7.2.2.1 (24) PSAR, Vol=e 2, Section 3.2.2.1.2 (25) PSAR, Vel =e 2, Sectica 3.2.2.1.3 (26) PSAR, Vol=e 2, Section 3.2.k.3.2 (27) PEAR, Vol=e 2, Section 3.1.2.k.4 (23) PSAR, Vol=e 3, Section 9.2 (29) P512, Vol=e 2, Section 4.2.2.1 PEAR, Vol=e 2, hble k-2 (30) PSAR, Volce 2, Section k.3 PSAR, Volce 2, Appendix 13 (31) PSAR, Vol=e 2, Section L.L.3 (32) PSAR, Vol=e 2, Section L.2.5 (33) PSAR, Vol=e 2, Secticn L.2.2.k (34) PSA2, Voice 2, Section k.2.2.3 (35) PSAR, Vol=e 2, Section k.2.2.2 (36) PSAR, Vol=e 2, Section 5 (37) PSAR, Volt =e 2, Section 5 PSAR, Vol=e 2, Appendix 5H (38) PSAR, Vol=e 2, Section 5.1.3.2 PSAR, Vol=e 2, Appendi:c 5I (39) PEAR, Vol=e 3, Section 14.2.2.3 PSAR, Vol=e 3, Sectica 14.2.2.k -h g L,-,

(LO) PSAR, Vel =e 2, Section 5.5 (41) ISAR, Vol=e 2, Section 5.7 FSAR, Vol=e 2, Appendix 5F (k2) ISAR, Vcl=e L, Supplement 2, Question 5.3 (L3) PSAR, Vol=e 3, Secticn 6 (kh) PSAR, Vol=e 3, Section 6.1 (45) PSAR, Vol=e 2, Section 6.2 (46) PSAR, Vohne 3, Section 14.2.2.k (47) PSAR, Voh=e 3, Section 7.1 (LS) PSAR, Vol=e 3, Section 7.h.3 (49) PSAR, Vol=e 3, Section 7.2.3.2 (50) PEAR, Vol=e 3, Section 7.3.1 (51) ISAR, Vol=e 3, Section 7.2 (52) PSAR, Vol=e 3, Section 7.1 153) PSAR, Vol=e 3, Section 7.1.2.3 9 (54) PSAR, Vol=e 3, Section B (55) PEAR, Vol=e 3, Sectict 9.1 (56) PSAR, Vel =e 3, Secticn 9.5 (57) ISAR, Vol = e 3, Section 9.3 (58) PSAR, Vol=e 3, Sectica 9.7 (59) PSAR, Voice 3, Sectice 9.6 (60) PSAR, Vol=e 3, Section 9.h (61) PSAR, Volume 3, Sectica lo (62) PSAR, Vol=e 3, Seccien 11.1 G3'203

(63) PSAR, Vol=e 3, Section 11.2.2 (64) PSA?, Vol=e 3, Section 11.2 (65) P3AR, Vol=e 1, Secticn 1.2.3 (66) PSAR, Vol=e 3, Section 14 (6"f) PSAR, Vol=e 3, Section 1k.1 (68) PSAR, Vel =e 3, Secticn 1k.2 (69) PSAR, Vol=e 3, Section 6 (70) PSAR, Vol=e 3, Section 14.2.2.3 (71) ?SAR, Vol =e 3, Section 14.2.2.h (72) W.R, Vol=e 2, Section 5.3 (73) PSAh, Vol=e 2, Section h.l.5 PSAR, Vel =e 2, Table 4-9 (74) PSAR, Vol=e 2, Section h.h.1 (75) ?SAR, Vol=e 3, Section 9 (76) PSAR, Vol =e 2, Section 5.1.h (77) PSAR, Vol=e 2, Section 5.7.1.3 (73) PSAR, Vol=e 1, Section 5.5 (79) PSAR, Vol=e h, Supplement 7 (80) PSAR, Vol=e 1, Appe-d4x 13 (31) 3A'J-lC002, "Research and Development Prcgram for the Cnce-Thrcugh Steam Generater" (62) PSAR, Vol=e 3, Sectica 13 (63) PEAR, Volu=e 1, Section 1.2.7, Sectica 1.5.7 (Sk) PSAR, Vol=e 1, Secticn 1.5.6 (35) 3A'4-lccc7, "Centrol Red Drive System Test Progra=" (53 204

(86) FSAR, Volt =e 1, Section 1.5.6 (57) PSAR, Vol=e 1, Secticn 1.5.2 (SS) FSAR, Vol=e 1, Section 1.5.5 (39) RAW-lcc05, "Internan ien: Valve Test Progrs= (90) ISAR, Volu=e 1, Section 1.5.3, Sectica 14.2.2.3 (91) PSAR, Vol =a 1, Section 1.k.1, Secticn 3.2.2.2.3 (92) 2XJ-10010, " Stability trgin for Xenen Cscillatiens-Medal Analysis" (93) ISA2, Vol=e 1, Section 1.5.10 (9h) RAW-10017, "Research and Devele;=ent Repcrt en Stability and Cc=pe.tibility cf Sodit= Thicsulfate Epray Solution" (95) FSA3, Vol =e 1, Appendix 1A, Section 2 (96) ISAP., Vol=e 1, Appe+ x 1A, Section 3 (97) ISAR, Vol = e 1, Appendix 1A Section k 3 (98) PSAR, Vol=e 1, Appendix 1A, Section 5 (99) ISAR, Vcl=e 1, Appendix 1A, Section 6 ~~. ng ;h ~- IL L

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O APF: DIX C EIUCATIC:E A'O ECFrSSICIE QUALIFICATIO::S CF WICESSES li3-?.U.

1 Z::UCAIICNAL A:D FECFESSIC:IAL QUAIIFIGTICUS 2 JCEI G. F R 3 VICE ICISIDETI A:D CHIEF EIGLt:. 4 METROPCLET EDISCN COMPA:T? 5 1. My na e is Jchn G. Miller. My residence is 12C2 East Wyc=issing 6 Soule;ard, Reading, Pennsylvania. I a= e= ployed by Metrcpolitan 7 Cc=may as Vice President and Chief agineer. 8 2. I was graduated frc= Purdue University in 1934 vith a degree 9 of Eachelcr of Science in Mechanical Engineering and received 10 a Master of Science in Engineering degree frem the sa=e Univer-11 site in 1936. 12 3 Frc= 1936 to 1942 I was e=picyed by The Detroit Edisen Cc=pany 13 as a Mechanical hgineer, verking one year in the Research 14 Deprt=ent and five years in the Engineering Divisien. 15 4. Frc= 1942 to 1946 I served in the U. S. Navy, assigned to the 16 Bureau of Ships, Machiner/ and Electrical Secticna, Design 17 3 ranch, returning to inactive status with the rank of Lt. 18 Cc-a "d er. 19 5 Frc= 1946 to 1947 I was e= ployed by Gilbert Associates, Inc. 20 in the Mechanical Engineering ::eprtment. 21 6. In Nove=ber 1947 I was e= ployed by Metropolitan Edisen Cc=mny 22 as Superintendent of ?reductica, and in February 1955 beca=e 23 Assistant Chief Engineer. Since April 1C63 I have been Chief 24 Engineer. In this capeity, I a= directly respcasible for the 25 follcwing dep rt=ents: Syste= Engineering, Producticn, Relay .-Ub, ,9,. 4S

26 and Meter, Sy:: ten Dispatching and Syste= pia-4ng. In March 27 of this year I es appointed ' lice President cf Met-Ed and 28 Project Director, Three Mile Island :iuclear Staticn Unit 2. 29 7 I an a ne:ber of the A=erican Scciety of Mechanical Engineers, 30 The Atemic Industrial Foru:n, and I = Chairnan of the Edisen 31 Electric Institute's Prine Movers Cc-*ttee. 32 8. I as a aegistered Professienal Engineer in the states cf 33 Pennsylvania, Indiana and Michigan. 4 G1we b' d,,.w u

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wv s n..a w... u 2 RC:! AID L. 'JILLIA.v5 3 FRCJECT.VN!AGER-DESIG:l, ~2iEE3 :m IsIx;p :;gcl3Aa 3-'A7Ic:t 4 METRCFOLIT1dl EDISCII CC?GA'Tl 5 1. My rs=e is Ecnald L. '41' " ".

.J residence is 12 dyndwcod 6

acad, Merris Plains, :Tev Jersey. I a= e=plc ed by the f 7 Metrepelitan Edison Cc=pany as Project Manager-Melear and 3 a= assigned to the General Public Utilities Ccrporation's 9 Tuclear Power Activities Group. 10 2. I was graduated frc= the University of Pittsburgh in 1952 11 with a Bachelor of Science Degree in Mechnical Engineering. 12 In 1956 I received a. vaster of Science Degree frc= the sa=e 13 universit7 Ik 3. In 1952 I joined the '4estinghouse Electric Ccrporation as 15 a Graduate Student and after six =cnths was assigned to the 16 3ettis Atc=ic Pcwer Iabcratcry as a Junior Engineer. 17 Until 1958 I was responsible for the design, develep=ent, 18 and procure =ent of =ajor reacter cc=penents for various 19 naval nuclear plants, pri=arily stess generaters, pressuri::ers, 20 and pu=ps. 21 h. In 1958 I ms assigned partial respcnsibility for the develep-22 =ent of an advanced reacter plant design for mani propulsion 23 after which I served in a scaff capacity to coordinate all 24 'aberatery programs associated with reacter plant ec=penents 25 and pcwer plant designs. m _ 91 A 4Ud w.dk

26 5. In 1960 I was given superviscry respcnsibility fer the 27 develop =ent of advanced nuclear cc=penent designs for naval 28 reactor plants and for the cevelopment of structural design 29 criteria for use thrcushcut the naval reseters pregra=. 30 6. Between 1962 and 1966 I was given superviscry responsibility 31 for various technical grcups respcnsible for plant valysis, 32 safety studies, test prcgram, rhid syste=s, egenents, and 33 plant engineering fer the Shippingpert Atc=ic pcwer S+2 tion. 34 7. Between 1966 and 1968 I was given supervisory respgnsibility 35 for the developnent and technical procure =ent of reaeter 36 vessels, centrol red drive =ec + 4 , and replace ent cores 37 for naval reacter plants. 38 8. In 1968 I joined the :Melear pcwer Activities Grcup of G?J 39 with respcnsibility for varicus technical areas including LO accessibility and naintainability, fuel handling equipment, kl control red drive techanis=s, in-service inspecticn pro-h2 gra=s, and overall reacter plant design. h3 9 In 1969 I was appointed Project.vamger for Three Mile Island kh Unit 42 vith responsibility for the cocrdinatien of all h5 =atters pertaining to the design of this unit, h6 10. I am a re=ber of the American Society of Mechanical Engineers k7 and the American :Iuelear Scciety. ,, _9 4 5- ~

48 11. I am a registered &cressional Engineer in the C-onwealth 49 of Pennsylvania, n63'216

1 DCCATIC:IAL A ID LECI"I.SSIC:!AL Q.UA1IICATIC:iS 2 GECEGE F. M 'XI 3 FROJECT >'XiAGER, CC:iSI~EJC*ICII 4 TEREE MI1E ISI/diL IiUCLEAR S"1IIC I 5 MEIECTCLI"A:T CISCN CCMPA'iY 6 1. My name is Gecrge F. 31e:=an. My residence is 1519 Linden 7 Street, Reading, Pennsylvania. I as e= ployed by Metrepelitan 8 Edisen Ccz:pany as Proj ect Manager - Ccnstructien. 9 2. I served in the.tance Le; art =ent, U. S. Ar=y, frcn Cetober 10 19k2 to June 19h6, retiring with the rank of Captain. h 11 3 I was graduated erc= the rennsylvania State University in 19 9 12 with a degree of Bachelcr of Science in Mechanical Engineering. 13 4. Fran February 19k9 thrcugh Febrm:y 1959, while exployed by 14 Gilbert Associates, Inc., I served as Engineering Draft =an, 15 Junicr Engineer, Mechanical Engineer and Project Engineer in 16 the design of varicus central staticn and industrial steen 17 pcwer plants. 18 5 In '.955 I var Guest Engineer at Ereckhaven Natienal Lateratory, 19 as:igned to Reacter Engineering. 20 6. In February 1959 I joined Metrepelitan Edisen Cc=pany as Mechanical 21 Engineer. My initial assig==ent as Project Engineer for the 22 245 MW Unit #2 at ?crtland Statien invclved eccrd"' tion of engin-23 eering, purchasing and censtructica fer the project. Subsequent 24 duties included engineering activities associated with the Produc-25 tien Departnent and staff verk invc1ving generatien studies en 63 217

1 both a syste and intercennectica level. The intercennecticn 2 studies included the pinnning and prald * " ry engineering asscei-3 ated with the Keystene, Cene:nush and H::er Cit 7 Fredects involvins 4 4800 lG of fossil generating esIncity. Syst e investigations 5 involved site evaluations and ecenc=ic studies leading to the 6 decision to proceed with Three Mile Island Nuclear Statien. 7 7. As Predeet Manager, censtructica, for Unit 2, Three Mile Island 8 Nuclear Station, ny duties include the cocrdinatica of all matters 9 pertaining to constructica and functions of the Ccastructica Manager 10 associated with t'. is project.

l I":UCATICIIAL A'iD W.CFESSIC:IAL QUAI.IFICATIC:IS 2 RICRAED W. FZ aE.D, JR. 3 MA"a0ER, :IUCLTAR SAZY O!'CSICN k GEiEFAL IUELIC L""II.I*IES CCEPCFA~!C I 5 1. My name is Richard W. Heward, Jr. My residence is 27 Ferneliff 6 Road, Merris Plains, :Tev Jersey. I a= exployed by the Pennsf - l 7 vania Electric Cc=pany and sssigned to the General Pfalic Utili-6 tier Ccrporaticn, :iuclear TcVer Activities Grcup, as Manager, 9 Nuclear Safety Division. 10 2. I was graduated frc= Swarth =cre College in 1957 with a Bachelcr 11 of Science Degree in Civil Engineering. I cc=pleted a ene yen 12 course at The Cak PJ.dge Schecl of Reacter Techncicgy in 1958. 13 3 In 1957 I joined New Ycrk Shipbuilding Corporatica as Junier 14 Engineer in the Hull Scientific Depart =ent. 15 4. In 1959 I was appointed Assistant Engineer StL*f i= the Reacter 16 Engineering Group of the Naval Nuclear ?cver repart=ent. 17 5 In 1560 I was appointed Nuclear Engineer in charge of the Reacter 18 Ngineering C; cup. 19 6. In 1962 I was appointed Design Superviser in charge of the Reacter 20 Engineering Group and the Radiclegical Centrol Grcup. 21 7 31965 I was appcinted Chief Naval Nuclear Engineer respcnsible 22 for project organi stien of three te+ M cal grcups--Mechanical 23 Frgineering, Reacter Engineering and Radiclogical Centrol--engaged 24 in the ccustructicn and testing of Naval reacter plants fcr nuclear 25 sub:arine and surface vessel centracts. q. 9 4 q (.l u ~a

O 1 8. I an an Associate Member of the Ancrican Societ/ of Civil 2 Sgineers. 3 9 I a: a registered Preressienal agineer in che c anwesith 4 of ?ennsylvania. . a,ayn ~,, 'd * ' AU ,s

O 1 EUCATIC:!Al A'O FECFESSIC:E QI.'ALIFICATIC:;S 2 FAUL P. LE EIEiT.0 3

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, a g m m. -.a n.w ..,c,, 7,.~., a 5 1. .y m es is Paul F. DeRien:c. w .J residence is 210 Eu=sey 6 Ecad, Ycnkers, ?Iew York. I an e=plered by Burns and Ece, 7 Inc. as Chief Engineer cf the :luelear and Prccess 8 Engineering Divisien. 9 2. I was graduated frc= the Polytechnic Institute of 3recklyn 10 in 19h8 with a degree of Bachelcr of Che=ical Engineering. 11 In 1958 I received a degree of yaster of Science in 22 Metallurgical Engineering frc= :Tev York University. 13 3. Frc= 19h6 to 1951 I was engaged in process develep=ent and ik nondestructive testing verk at the Materials Mberatory of 15 the :Tev York :Taval Shipyard. 16 h. Frc= 1951 to 1958 I was e= ployed by the Wright Aerceautical 17 Divisien cf the C atiss-Wright Ccrperation in =etallurgical 13 development progrs=s, cc=ponent failure analysis and ncn-19 destructive testing. At the time I left, I was supervising 20 the development of advanced =anufacturing processes for 21 =issile and jet engine ec=penent fabricatien. 22 5. Frc= 1958 I have been e plcyed by Burns and Ece, Inc. in 23 the nuclear engineering divisien. I lave been actively 2h engaged in the design and construction of nuclear and fossil G3--221

25 fuel power plants, isotcpe prccessing plants, radistica 26 laboratory facilities, test reacters, desalinatica plant;, and 27 water treat =ent facilities. In ic65 I bees =a chief Engineer 28 cf the iuclear and Process Engineering Division in respcnsible 29 charge of technical aspects of c w ny projects in the 30 nuclear and chemical process fields, including studies, 31 evaluations, and design. 32 6. Prc= its inception, I was assigned as Project Engineer of the 33 Three Mile Island, t; nit ::c. 2 project. In that pcsitica, I 3h have been respcnsible for cocrdinating all phases of its 35 design fer Burns and Roe, Inc. 36 7. I a= the Chair an of the Power Piping sectica of the code 37 fer Pressure Piping, USA stahds Institute, 331 and a 38 wnher of its Executive C - 4ttee. I a= also a me=ber of 39 USAS II-11, C 4ttee en Basic Materials and Materials Testing LO for !uclear Ser'. ice as well as nu=ercus technical societies. 41 8. I a= a registered professienal engineer in the States of M Pennsylvania, :Tev York, :Tev Jersey, California, and h3 Washington-en rw UU o$/$

1 EDUCAHC:!AL A:D FECFESSIC:iAL QUALIFICATIC:! 2 JCEI C. AECHER c. -,I'.c...G C....., ~a. 3 o u rse.

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. < Au ..ui. : : n xn..o mD Cs, .7..,.v. n 5 1.

J ex a is Jchn C. Archer. :*J residence is 56 Prcspect 6

Park West, Erecklyn, fiew York. I an e=plcyed by Burn: 7 and Ree, Inc. as Supervising civil Engineer. 3 2. I.us graduated frca Rensselaer Eclytechnic Ins *itute 9 in 19h9 with a degree of sachelcr of Civil Engineering. 1C 3. Frc= 19h9 to 1951 I was empicyed as a str ctural designer 11 cn the design of pcwer plants by Ebasco Sertices Inc., 12

lev York, :Tev York.

13 1+. Frcn 1951 to 1953 I was enlisted in the U. S. A -J Ccrps 1!+ cf Engineers and served as an instructer at the Engineer 15 Schecl, Fort 3elvcir, Va. 16 5. Frcs'1953 to 1955 I ms enployed as a Senier Engineer en 17 the construction of the AEC precus diffusion plant at 13 Porta =cuth, Chic fer the con. .icn centracter, Peter 19 Kievit Sens Co. 20 6. In 1955 I joined Burns and Ree's Construction Departnent. 21 As Ccnstracticn Engineer - Str ctural, fren 1955 to 1959, 22 I supervised constr ction cf vr icus cr- -* cations and 23 power plant stractut es in Virginia, Minnesota, Cregen, and -a evy ) 44

2h

'evada.

In 1959 I transferred to Burns and Ree's Engineering 25 Depart =ent. As Lead structural M neer, frc= 1959 to 1966, 26 I planned structural arrsn pents, supervised deta'. led 27 structural design and prepared specifiestiens fer nuclear 28 facilities including two nuclear research reseter labersteries, 29 a structure to centain an experi= ental reacter and s 30 nuclear pcwer plant. The pcwer plant was Jersey Centrsl 31 Power & I.ight CrAs Cyster Creek Plant. In 1966 I was 32 assigned responsibility, as Supervising Civil Engineer, 33 fer civil engineering policy and design criteria and the 3h naintenance cf design quality thrcugh supervisien and 35 apprevsl of stractural design esiculaticas, drawings, and 36 specifications. ~ 37 7. I a= a =e=ber cf the A=erican Society cf Civil Engineers 38 and its Cennit' ee en Ccnstraction of :helear Facilities. 39 8. I a= a Registered Professional Engineer in the States of LO Pennsylvania, Icwa, New Jersey, and New Yet v,, ~(

9 1 CUCATICNAL AND k?.CFESSICNAL Q.UALIFICATICliS 2 WILLIAM A. CO23 3 IRCJECT EIGETEIR, NUCIZAR m'ER GriEFA*ICN DEFA:CCIT 4 MTR GETEFATICN OI'CSION 5 I:A3cC K & WILCOI Casat 6 1. My na=e is W4713 - A Ccbb. I reside at 1419 Robin Eced ? lace, 7 Lynchburg, Virginia. I as e=plcyed by the Eabecek & Wilecx 8 Cc=pany, ?cver Generation Divisien, Nuclear ?cve r Generaticn 9 De-- ~ent, os a Prcject Engineer. 10 2. I served in the A'./ Air Cerys frc= April 1944 until May 19L6. 11 3 I was graduated frc= virginia ?c17 technic Institute in 1949 with 12 a Escheler of Science Degree in Mechanical Engineering. During 13 1s64-1968, I did gn dnate verk in Nuclear Physics at Lynchburg 14 College. 15 L. I jobed the Babcock & Wilecx Cc=pany in 1951 and held various 16 assig::=ents in the design of large fossil-fueled stea= generators. 17 5 In 1955, I was transferred to the Atecic Energy Divisien of the 23 Eabecek & Wilecx Cc=pany. In this assig::nent, I was initially 19 involved in the design and develep=ent of =adcr cc=cenents fer 20 the caval nuclear sub:ardse pregrs= and for preposal engineering 21 en early ec==ercial nuclear plants. 22 6. In 1956, I became a ? reject Cecrdicater en the 2&W centract for 23 Indian Point Unit No.1 cf Censc11 dated Edisen Cc=pany and verked 2k in 'chis capacity thrcughcut the design period fer this reacter. 25 I subsequently werked en the N.S. Savannah and en other SW 26 centraces and deveLyent progrs=s. va O a.y. 9o g-mZd

9 ~ 1 7 In 1%6, I became a Senicr Systecs Wmeer werking en the E&W 2 centract with Die ?cwer C-/cy fcr the Cconee Statica. 3 8. In 1%7, I became Project Engineer for the I&W centrset with h Jersey C mtral ?cwer & Light Cc=pany; at that ti=e, designated 5 as cyster Creek :7c. 2. 6 9 In 1%8, I was assigned the Project Engineer respensibility 7 fer Ihree Mile Island Unit :To.1 in additica to this respcasi-E bility en the : nit new designated as "'bree.411e Island Unit No. 2. G3 225

= 1 ECUCATICIIAL AliD FECFISSICIIAL QU1LI?!CATICITS 2 W"MM R. SMI"":I 3 SUH/ISCR, LICEISriG GECUP 4

TJCLEAR SAFE"'Y E'IG"A"IG SECTIC:i 5

IUCIIAR PCWIR Griz?ATIC:i III.Grcr!

6 TEE EA3CCCK & WILCOX CCMBCFf 7 1. My csme is Wm '" R. Snith. My residence is 3750 Weedside 8 Arenue, Lynchburg, Virginia, 24503 I as e=1cyed by The 9 3abecch & Wilecx Cc=any, ?cwer Genera *.icn Divisien, in the 10 Nuclear Power Generatien repart=ent. 11 2. I graduated frc= the United States Na'al Acadeny in 1945 with a 12 3achelcr of Science Degree in Marine Engineering and was c d s-13 siened an efficer in the U. S. Navy. I served through 1947 as 14 a junior gunnery officer at sea and as a Radic1cgical Safety 15 Officer at the San Francisec Naval Radic1cgical Defense Ie.bera-16 tory. 17 3 In 1948 I resiped ny e-ission in the U. S. :tavy and joined 18 the Health Fhysics organization b 2g fe::ed at the Gasecus 19 Diffusien Flant in Cak Ridge. In 1950 I vs s nade superviser 20 cf the Health Physics Grcup at that plant. 21 L. In 1951 I was recalled to active duty with the U. S. Naval 22 Reserve and assigned duties of a classified nature in the 23 Specini Weapcas progran. 24 5 In 1955 I joined The sahecch & Wilecx Cc=pany as a nuclear 25 engine e in shielding design. I participated in the shield 26 design work for the Censolidated Edisen Cc= racy's Indian ?cint 27

Ic.1 :Tuclear Plant and was assigned as lead engineer for shield q. rm r, D t.*

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a 1 design for the Nuclear Merchant Ship Heacter for IT.S. Savannah. 2 In 1%0 I was appointed Supertiser of the Shielding Desin Group 3 with respcusibility for basic reacter radiatien analysis and k shield design activities fer plants designed by MW. 5 6. In 1%3 I was assigned to six =enths of specialized tra"": as 6 nuclear adviscr for the anticipated foreign veyages of N.S. 7 Savannah. I subsequently sailed in this capacity en the first 8 tvc foreign voyages of the ship under its general agency charter, 9 and later cc its first foreign voyage in ec==ercial sertice en 10 lease, with respcnsibilities fer advising the = aster with respect 11 to nuclear and regulatcry aspects of reacter plant operatien. 12 7 In 1%5, I was transferred to the Ed Atc=ic hergy Division's 13 Marketing Departnent as cecrdinater fer Marine Markets, with 14 responsibility for coordinating sales and prc=ctional efferts 15 with engineering design in MW's =ariti=e reacter activities. 16 8. In 1%7 I was assigned as Supertiser, Licensing Grcup, Nuclear 17 Safety hgineering Sectien, with direct respensibility fer all 18 licensing activities in reacter plants designed by M*d. 19 9 In 1%5 - 1%7 I serted as a =ceber cf Ihe Eabceck & Wilecx 20 Cc=pany Nuclear Develepnent Center Isetepes Cc==ittee. I have 21 serted as Vice Chair =an of the Ncrth Carolina-Virginia chapter 22 cf the American Nuclear Scciety. I a= a =enber of the A=erican 23 Unclear Scciety, the Society of Na'ral Architects and Marine 24 hgineers, Panel M-13 (Atenic hergy) cf the Ships Macs erv 25 Cc==ittee of S'iA'E, and of the Reacter Safety Cc-ittee of 26 the Atcaic Industrial Fer.:=. g gig

1 EDUCATICNAL A'iD FRCFESSICIIAL GA'AI,IFICA'"IC IS 2 '4ILLIAM S. LITTLE 3 FECJECT E iGI'E, :iUCIZAR FC'4ER GE:EFATIC:I DEFARSE'iT 4 PC'4ER GE EEATIC t DIVISIC:I 5 3ASCCCK & '4ILCCX CC:GAliY 6 1. ?J =a=e is '41111a= S. Little. I reside at 513 Ecrse=an Drive, 7 '.gtnchburg, Virginia. I a= e= ployed by The Babecck & *dilecx 3 Cc=pany, Pcver Generaticn Division, :helear Fever Generation 9 Depart =ent, as a Licensing Superviscr. 10 2. I ns graduated frc= Gecrgia Institute of Technology in 11 1953 with a Bachelor of Che :ical Engineering Degree. Dur-12 ing 1959-1966, I did graduate verh in :melear Engineering 13 at the University of Idahc. 14 3 I jcined the Atc=ic Energy Div:,sion of P4 ' 7 4ps Petrole's 15 Cc=pany in 1956 as a Project Engineer for liquid =etal cceled 16 and fueled experiments in the D and I"2 at the iR'"S. 17 4 In 1959 I beca=e a Plant Engineer with ?dllips verting in 18 the areas of reacter core heat transfer and hydraulics, 19 fuel asse=bly and centrol red develop =ent and testing and 20 reacter safety analysis. 21 5. In ic65 I became Heat Transfer ?J raulics and Radiegraphy d 22 Section Superviser in the Plant Engineering Branch with 23 ? 4 '7 'ps. I was respcnsible for providing engineering 2L support in the general areas of heat transfer and Pt.raulics y 0Scn av~9 9%* N

e i. 25 for the Test Reactors Area at the :as, and providing 26 radiograpby, nagnetic particle and dye penetrant testing 27 services for all :aTS centractors. 28 6. In 1966 I beca:e Superviser of the Energency Core Cec 11ng 29 Test Secticn in the Plant Applicaticns and Engineering Test 30 3 ranch with. 4ps. I was responsible for originating, 31 rece==ending and a*-4nistering experd= ental progrs=s in 32 support of e=ergency core ecoling syste=s for cc==ercial 33 pcwer reactors. 34 7. In May of 1968 I joined The Babecek & Wilecx Cc=pany as a 35 senior engineer in Design Engineering. In Septe=ber of 36 1968 I transferred to the Licensing Section of Centract 37 Engineering where I a= new a Licensing Superviser respensible 3a for licensing activities en the Three Mile Island Unit 2 39 and Toledo Edisen projects. G3 230}}

ML19206A942

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