Text

Rept to ACRS Re TMI-2
	ML19242A524
Person / Time
Site:	Crane
Issue date:	06/20/1969
From:	; US ATOMIC ENERGY COMMISSION (AEC)
To:	;
References
	NUDOCS 7908030078
	Download: ML19242A524 (91)
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Docke: No. 50-320 June 20, 1969 Recor :o ACRS THRIZ Y.!!.I IS*.AND CTIT :

C.S. A:.::10 Inergy Ccc=issi::-

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2a A3STRACT D.e results of cur saf ety evaluation af :he Three M.ile Island Uni: Nc. 2 are presented in :his report. The nuclear s:eas supply system, engineered safety f eatures,.and reac:or building are similar to Uni: No. 1, Oconee, Cr/stal River, Rancho Seco, and Russellville reac:cr plants. Because of

he similarity of the Uni: No. 2 plant design with these plants, the safety review was primarily directed to those areas which differ from previously approved similar plants. These areas include the applicatien of greuted tendens, the :ype of control red drives, aircraft protection, and areas of continuing ccccern regarding :he pressuriced vatar reac:cr design and ccnstruc:icn. Uni: No. 2 vill have an ul:1:a:e power level of 2772 W: ce= pared with an ultimate power level of 2568 5 : for Uni:

No. 1.

We conclude that these matters have been adequately accc =adated in the design of Uni: No. 2.

The significant safe:y censiderations that will require a con:inued review folleving issuance of :he construction permit are delineated in See ica 19.0.

On the basis of cur review, we have concluded that :he prcpesed facility can be cons:ructed and operated at the proposed site withcut undue risk to the heal:h and saf ety of the public.

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1.0 I:iTRCDUC"'!C::

1 2.0 SITI CHA?aC IRISTICS 3

2.1 Population Distribution 3

2.2

.e'e:eorology 3

2.2 Ceclogy 5

2.4 Seisnology 5

2.5 Hydrology 5

0.6 Inviren= ental Monitori:.;

7 2.7 Airports 3

2.3 Cooling Tcuers 10 3.0 CCMPARISCII CF *MI J1 AliD 12 11 4.0 Ult! ! :;0. 1 A:D 1;0. 2 SHARID SYSTEMS 13 5.0 CC:iTAI';MI;~" A:C 3UII.DI:;G S*RUC"*.*,RAI, DIS!C';

13 5.1 General S :uctural Design 13 5.2 Ceutai.=en: Cescription 14 5.3 A1:::af: Hardening 16 5.4 Ccntain=en: Prestressing Systa=

17 5.5 Su teillance and Testing 22 5.6 Cen:ain=en: Capability 26 5.7 Cenclusion 31 4

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2326 6.0 REACTCR PRIMARY SYSTEM 32 6.1 General 32 6.2 Reacter Internals 32 6.3 Reac:or Vessel Material Su:veillance ? cgras 35 7.0 CVI3ALL PLxiT PROTECT:CN 36 7.1 Tornadic '41nd 36 7.2 Missile ? otec:1:n 36 3.0 INSTRLiI';*ATICN AND CON ROL 40 3.1

?:stecticn Instrumentation Systes 40 3.2 Cent:cl Systes 43 3.3 Inergency ?:ver 46 3.4 Cable Separatica 49 9.0 C;GINEERED SAFE Y FEANES 50 9.1 Isergency Core Cooling Systes (ICCS) 50 9.2

cdine Removal Sys:es 56 10.0 CON 3CL RCD ORI7E MECHANISM 59 3.,.,3 A,,.,W..,-n.,,-..-..

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..w....va 12.0 r.IL $!ORAGE PCCL 65 13. 0 ACCIDC;T ANALYSIS 66 13.1 Less-of-c: clan: Acciden:

67 13.2 Fuel Handling Acciden:

63 13.3 Stea: Oenera::: Tube Failure 69 13. - Radicly:10 Hyd:: gen Generati:n 1

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S Pate l'.0 RESEARCH A'iD DEVELCPME:i!

72 13.0 GEliERAL DESIGi CR:!ERIA 73 16.0 ADDITIC:iAL RE7!E*4 MATTERS 73 16.1 Technical Qualifica:icns 73 16.2 Cenduct of Cperations 76 16.3 Industrial Security 73 17.0 QUALI Y ASEL"uliCE 73 15.0 ".; SERVICE DISPECTIO:i 32 19.0 CC ;CLUSIC:t 34 Appendix A - Chrenslogy of O{I :!2 Review 36 LIST OF TA3LES 2.7 Ol=s: cad State Airport Usage (1969) 10 3.0 Major Design Oif f erences Se:.ieen '.'ni:s 1 5 2 12 3.6 Centain=ent Capability Analysis 30 9.1 Maxinus Fuel Clad Tenperatures Resul:ing from a Loss-of-coolant Acciden:

9.2 Ocse Reduction Iffec:iveness 10.0 Ccmparison of Characteristics of P'4R Cen:rol Red Orive Design 61 13.0 Acciden: Ocses Calculated by S:aff & Applican:

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Be Jersey Central P ver S Ligh: Ccapany (JC?L) sub=1 :ed an appiitati:-

en April 29, 1963, for a c:ns truction per:1: a.d opera:ing license for Uni: No. 2 of :he Oyste: Creek :.uclear ?:ver S:2 tion (OCN?S-2).

he proposed plan: was :o have beea lccated adjacert to the existing Uni: No. 1

n an 300-acre site in Lacey ':vnship, Ocean Caun:y, New Jersey, approxi-mately :wo miles scu:h of the cc : unity of Torked River. Cn " arch 10, 1969, Anendment Sc. 6 was sub=1::ed.icintly b.y the Jersey Cen:rai ? wer a Lis'h: C::aany and the "e:ren. oll.:an Idisen Cc c. anv. as co-cv.ers indica:ing r

a change in f acility sites to the 3:ee Stile Island site abcut 10 miles scucheast of Harrisburg, Pennsylvania.

~he s:a: ion was redesignated as

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he 21! /2 design is the same as the originally preposed Oys:er Creek Uni: ; except for changes incorporated into the E!! :/2 design to acccunt for site-rela:ed catters such as requirements for aircraf pre:ec:1:n and the use of c: cling :: vers as the primary heat sink.

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enera: ing supply systa: eill ':e a :ve-isep 3abecck and.iil:cx Cc= pan r pressuri:ed water reat:or. 2C :!2 will

c. era te at a cere ther a1 cwer level up to 2.'.52 (345 Pae) and will have an 21:1:a:e pcwer level of 1772 tat.

All core physics, thermal and hydraulic characteristics have

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wy:.1 Tae archi:ect/ engineer vill be 3 urns & Roe, Incorporated. Uni:ed ngineers and Construe: ors vill be the cens: rue:icn nanager. MPR Associates will be used as consul:an:s :o assis: in executing and auditing the "!! 1:

quality assurance and quali:7 c:ntrol prograns.

Pickard and Love Assccia:es vill provide design reviev consultant services for Ut! R.

Schupack and Associates v:'l be struc: ural :nsul: ants en the design of the reat:cr centainnent building whi:h will be a crestressed, pos:-tensten reinforced

Oncre:e structure using grouted tendens. Gilb e r: As so cia:es, Incorpora:ed vill provide architect engineer servi:e for design of the ecoling :: vers and censultant service on si:e-related engineering including air: raft protec:1:n'desi n.

..ae nuc. ear s:ean supp.ty systen, engineer 4.ng safety features, anw reactor a

building are sinilar in design :o the Oconee :'uclear Stati n, Crystal River :.uclear Station, Ranche Seco :iucler.: Station, ~aree 'd.ile :sland

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,2:1:n, and :he Russellville.uclear S:a:icn '<hich have already been issued cens:ruction pe mits.

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appr:ved plan:3, cur saf ety evaluation of -he design was principally direc:ed ::vard safety aspec:s for nultiple plants, shared f acility features, and :entinued review of concerns fr:n previously reviewed plants 4.. s s.

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The 'hree Mile Island ';uclear Station Uni: :ic. 2 (~'C 12) vill be '.cca:ed adjacan a Unit '!o. 1 n B ree Mile Island on :he Susquehanna River appror..mately 10 miles scutheast of liarrisburg, Pennsylvania (1960 pcpu-latica 79,697).

Se site is 1 cated in Lcndenderry T:*.'. ship of Dauphin Ccunty, Pennsylvania.

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= unities (22,a50) 21:h their neares: beundary at 3 miles, :he a:pli-cants have pr: posed a law pcpulation :cne radius of 2 miles, :he sa e is approved f or T.C 11.

-ae 1967 popula:1ca within ene pr:pesed 1 v pcpulation : ne was abou: 22CO.

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?O values. For calculating d:ses a: the low population :ene distance of 2 =iles, we have ap lied the same neteorological para =eters used by the applican:3. The para e:ers used are based en Pasquill "?"

condi:icns wi:h absolu:ely inva-iant wind Of 1.0,:eter per secend for the first '2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The sa=e wind dire:-ion was asst =ed for the felicwing 6./2 days bu: with Pasquill "?" and 1.0 me:er/sec:nd 30% of :ha: :L:e and Pasquill "D" wi:5 4.0 me:ers/sec:nd the re=aining 0%.

70: :his sec:nd :ime period the wind direc:ier was averaged over the 22-1/2 degree sect:r.

For the following 24 days :he wind was assumed to blow in the sa:e 22-1/?. degree see:or 30% of thw :1:e wi:h 3; in the Pasquill "C" :a:ege r-r with 2.0 eters/second wind speeds; 33; in the Pasquill "D" ca:egor~ vi:h 4.0 =eters/second wind speed; and 12% in the ?asquill "?"

category wi:h 2.0 ce ers/second wind speeds. '4ind direction was averaged over the sa:e 22-1/2 degree sector. Cur consultants :n =eteorology, ISSA, reviewed the =e*eorol:gy data sub=itted with the IM: Uni: No. 2 application and have :: =en:ed tha: the seteorological docu=en:a:icn and : enc'usions are identical :o :hese whi:h were presented in :he applica:1:n f or 7:C

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dif:usion para:eters used in the dose calculati:ns are reasemabl.7 con-s e rva :1v e.

The ISSA ce=ncnts have been forwarded :o thc Oc==1::ee.

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.a f: :he heat re= oval of other.or al and emergency equipment is su plied

= :he river. ~here is an addi:icnal ecoling ::ver that is used to reduce the servi:e va:e and cooling :: vers b'Ovd:w. vater :e:pera:ure before being returned :: the river. A icv river flow of 17CO :fs, equiva-lent to failure of the downstrea: York Haven Cam, vculd still provide both units of nuclear service pu=ps a supply of a30 :ubi: feet per see:nd.

his =ini=u: ' lev available to the nuclear service purps is five times the flow required f or saf e shu:devn of be:h uni:3 Ouring cur consul:an:s' (USGS) review of the hree !!e Island site hydrology, a check. was made with the Baltimore Ois tri:: :f the U.S. Corps s.

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'4e vill reviev :he design during :he post-constru::1:n review s: age ::

assure tha: prote :1cn is provided agains: the fleed height developed

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2.5 Envir:re. ental Merittorint Metropolitan Edisen C:c:pany t.s

.sen : rdue:ing"a preoperational environ-cantal =cn;:: ring program since January 1968.

'he pr: gram, as described in the 'C 12 appli:ation, has included samples of well and river wate.,

river sedimen:s and fish, an: acil and vegetation fres the site area. A

al of St. sa:ples have been taken in :he program.

he Metz: poli:an Edisen Ccepany has met vi:h the Health 2epartmen: of :he C:c=cnveal:h of Pennsylvania and has sub=1::ed : heir progra: : that agency for 1:3 review and rece==enda' ions.

'4e have received ec ents f r:c the J. 3. Fish and 'iildlif e St ri:e regarding the D.I Uni: No. 2 application. Taese c.0 =ents have been f:rvarded :: :he applicants.

'4e have discussed the :::=ents vich the appli:an:s and -hey indicated :ha: they would :: ply vi:h the re:::=endati:na of the Se 11:e.

We have inf:rred the applican:s : hat additi:nal infor:a:icn is necassary including the type and 1:ca:1:n of sa:ples Of aquatic b10:2 f c= the Sasquehanna liver; the studies : hat ha',e been made :: determine ::1:1:a1 radi:nuclides and criti:al feed chain pa:h.ays :: =an; the use of Susquehanna liver va:er f:r irriga:1:n; and :he possible need f::

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_o-21:h respect to the sa:pling of aquatic bio:2, the applicants have infor ally advised us cha: an ecological survey has been underway for sc e ti=e now to determine wha: aquatic life is presen: in the river and hcw :hese say be involved in the feed chain to man.

hey have also indica:ed tha: the possible incorporation of. radionuclides into foed crops via irrigation water will be investigated. Resui:3 of the eco-logical survey and the study of irrigated food crcps will be used to es:ablish appropriata e:airon=en:a1 enitorinz procedures. Tnese items are discussed in A=end::en: 10 :: the applica ica.

On the basis of cur discussiens with the applicarr.s and nis information, we conclude tha:

the applicants will have an accec. table environ = ental menitorin2

o. r o t. r an.

We will folicw up on this aspec: of the site review to assure that an adequa:e program has been established a: the operating license stage of review.

2.7 Airecr:s

~he Tnr== * 'a Island si:e is loca:ed %*o and ene-ha'.f siles fron the eastarn end of the single 3CCC-fco:-leng runway cf the T.= stead State Airpcrt. Tne 2.arrisburg-?ork Airper: is loca:ed abou: eizh: miles

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is about four ti=es the current aircraf: ::affic at :he Olms:ead S:ste Airport. 3ecause of the proxinity of the si:e :o :he airpcrt, we concluded tha :he effects of aircraft inpac:ing on the f acility nus: be included in the design bases for the Unit 1 facility. The sane conclusion applies to :he design of Uni: 2.

The design aspects are discussed in Sections 3.3 and 11. 0.

Using the May 6,1969 Prorosed Criteria for Siting P0wer Reac cr Facilities

" err Air orts, the TMI site wculd be subjected :: :he requirenents Of sec:ica 100.10 (b) 3 because the c. lant lies w1:hin one nile la:erally alenz_

he fligh: paths.

"cwever, based upon these proposed criteria and an air-

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a t e.U.. c ' *.. ~.' e IMI site would require protecticn aga'ns: an air strike of :he DC-9 (98,000 lbs) aircraf: instead of the 200,CCC-lb aircraf t which is discussed e

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.4 OLMSTEAD STATE AIRPORT USACE (1969)

Average" Tvoe Aircraft

20. (lbs)

Fli2 hts Dailr Frecuenci Seeing (707) 257,000 1/ day 2

3ceing (727) 200,000 2-3/ o.

0.2 Douglas (CC-9) 93,000 3/ day 16 Convair 530 (C-5) 53,000 26/ day 52 Other 50,000 3/ day 16

Landings and Take-off.=

3ased upon cur proposed criteria for aircraf protection requiremen:s

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nus include the ef f ects of aircraf t i= pact.

2.3 Ccolin;: Tcwers he T.!I 'il and :!2 hea: re=cval sys te=s will not discharge facility heat loads into the river except under e=ergency conditions, or during the winter non:hs when the ?.ischarge will be used to pre' rent icing at the river water in:ake structure. Nornal hea: leads of both Uni:s 1 and 2 will be discharged to the at csphere by :vo hyperbolic natural draf:

cooling :cwers per uni:.

S.e blevdevn f rom :he eccling :: vers and all s u> c.-.w'.,.'. ' < =. -

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-s www ww A pr: gram is :urrently in progress to study :he ef f ec:s of large cooling

cuers on the local seteorology. This study is being nade at the Keystone Fossil Plant, located in Chelocca, Pennsylvan:.a.

tne facili:y has four cooling tcwars and a total plant capacity of approxima:ely 13C0 We.

We have discussed this program with the applicants and'they have indicated that the program was initia:ed :o determine the eff ec: of fogging since i:

could affect operations at the Olmstead Airport.

'de shall follev this pregras during the operating license review to assure there are no new significant factors resulting which could affect plant saf ety or public health.

3.3 COMPAR!SCS OF D!I 11 AND d2 The folicwing tab.'e lists the najor differences in system designs for Uf! 11 and 12.

In many instances the differences noted are prinarily the result of design approaches taken by Gilbert Associates and 3 urns and Roe, the archi:ect-engineers for " nits 1 and 2, respectively.

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Oc=e Liner Thickness (inches) 3/3 1/2

'endons Greased 170 wire Creuted Strand Channels over 'iner welds 2naccessible welds All welds Access Cpenings (dia. feet) 22.3 22.0 Cesign Pressure" (psig) 33 60 Separa:e Spen: Fuel Cask ? col No Yes Auxiliary 3cilding A.'

raf:

3elev gr:und ficer Oc=plete Protec:icn

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1 A'!D 50. 2 SH.GID SYSTD!S The applicants have indica:ed tha: the folicving systems will be snared be.aee

e. t.....1

.2 r

3 t.

1.

fire protec: ion systes 2.

=iscellaneous vaste concentrator 3.

fuel handling building crane 4

elec:rical switchyard 5.

auxiliary s:eam genera:Or c.

nev :ue;, s:orage A criterica used in the design of TMI 12 requires that no syste= shall be shared with '"'C 11 unless f ailure of the shared sys tem veuld.c: impair the safety of either unit.

is independe*nce of Unit i fren Uni: : :skes a

it possible :o exclude =ulti-uni: type accidents. The applicants have

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..a er i=:ac: on shared features : hat veuld affect saf e shu:devn cac. abilit.7 T..e applican:s have indicated, and we agree, thc the sharing of :he abcve systers will not cceptcmise :he indepe: dence of ei:her Uni: 1 or Uni-2 e g a,..a t

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n.,

... m and 0.123 (Design 3 asis Earthquake) vi:h sinul:aneous ver:i:a1 accelera-tions of 2/3 of the horizon:a1 accelerations. These 7alues are the sane as are being used for TMI 91.

Tornado leading is based en the nodel as discussed in See:icn 7.1 which we have accepted en previous plants.

C - b

n ed.'.'ad '

o nc'.d - d -"us 4....'. 4.e. b. e s ' -"..'. a. e c u s ' c.-". -. =...c e

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3 fuel handling and centrol buildings, is also hardened agains-i..ect g..-.g.2.

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. d e.

a free volu=e of 2 million cubic feet.

B.e design philosophy under all load cc=binations, except concurrent naxi=u= te=perature and pressure, is tha: :he containment vill be in general me=brane cc=uression and not crack, except at discentinuities.

B.e loading cc:binations have been reviewed by us and fcund to be accact-able.

3.e des'3n of the lar p cptnings (equip =ent hatch and personnel loc'O vill be based on a fini:e ele =ent analv. sis.

D.e tendens vill be draped

a. A,. d

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a 4e openings. The applicants have adequatel'/ described the design parameters by. r...ac h a... e <

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5.3 Aircraf

!!ardeninz-T'e design of IMI 92 against aircraft ispinge=ent is based en the sa:e a

data as were presented in Supple =ent 5 :c :he "ni: 11 PSA2.

Gilber:

Ass o cia:es, Inc., A/I on Uni: 11, is acting as consul: ant for aircraft crash review and design for Uni

12.. Burns 4 Roe is the design A/I for L'ni: 12.

The rodels used in design are all :aken a: 200 knots i= pac:

veloci:7 and are listed as folicvs:

Case Weizh:

Iffective Incac: Area A

6,0004 5' diane:er 3-

',C00#

3' dia:eter L-

.n,J, n C. 0,/

_t a. v d 4 _, _._...

v The reacter building vill be evaluated for Canes A, 3, and C vi:h impinge-ment at the dc=e apex springline, and en :he cylinder valls at or be:veen buttresses. A::ach=ents to the centain=ent structure v'll also be evaluated for these effects of the abcve cases.

The centrcl building vill be checked for impact en the ::cf and side valls.

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tien and perscnnel. The cen:rcl rec: vill also re=ain habita le during a.a a.:.. a e.. a s. a. n <.

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. unO. S will alSo be evalua:ed so as to -r: vide protecti:n belev ele'tatic r

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"ne loading and inpact criteria, as well as omntial secondary eff e::S have been reviewed by us, cur dyna =1c design Sul: ants, and by cur exploSireS and Shock phencnena consultant. This review is a 3011cw ue :1 a Similar one done for "ni: 11.

S.e criteria, as areSen:ed bv. the ac. c. li-e cants, have been accep:ed by us and our consultants.

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4-of systems en the basis of informa:1:n c:ntained in applica:1:ns and obtained inf ernally f rom venders. Our evaluati:n has been Itnized, however, since the inicr:at.'.in in f:::al applications has always been of a preli=i-nary na:ure, and :he vendors indica:ed that needed, details, such as

=penent stress analyses and results of full-scale proof tes ts, ::uld only be supplied af:er a con::act award.

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Previous evaluation work anc ve f eel that sufft:1ent da / ha'te been reviewed

o be able to agree in erinciele to the us2 of anr of the four systems o.- o,csed.

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that post-censtruction per:1 apprcval of :he desi~n prior :o installation 6

will be candatory.

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Large-capacity 33RV :endens have previously 3een reviewed and approved for use en Russellville, with detailed information premised by :he applicants 2f:er vendor selection. Rancho See:

Supplement 11 was si=ilarly reviewed con:ingen: upcn the sa:e da:1 requesta being fulfilled. The use of large si:e tendens on TM 12 is acceptable in principle and subs:antiatin7 infornation vill be included as par: of the detailed material to be submit:ed by the selected vendor.

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Strands have been reviewed en Ran-ho Seco Supple =en: 11 and : heir use in the TMI 12 design 1.', acce;.able to us.

3.

All four anchorage systa=s pr: posed are friction or fri::. n/ bearing anchorages, as opposed to the bearing anchorage installed to date (33RV). Even : hough no final approval has yet been given for their use in nuc' ear con:ai aen:3, they are a'l extensive' y used thr: ugh-Out :he general ::ns:ruction field. The syster propcsed are:

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'J1:iza:e Capacity 194-kies 2021 kips 1280 kips 20C0 kips Desien Capaci:7 1166 kips 121. kio.s 763 cio. s 1 00 kio.s

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Y.a 'd e.mnl sa 'he use of friction anchorages brings up the questien of the relative ductility of bearing er vedge.. gripped tendons. The significance of wedge-grip systens resulting in a due:111:y of less than 3", while s::aight bearing systens generally have greater than 4', elonga:1cn, nust be viewed in relation to.the actual available due:ility in the overall s tru::ure.

Tests ade by Frici: on curved 121 wire tendens wi:h bearing anchcrages showed an elongation of less :ha 3 while for straigh tendens resul:s were grea:er :han a':.

Even l'; elongation of the ~".I #2 137-f cc vertical cylinder walls would resul: in a 1-1/2 f act increase in height an order of nagnitude larger than an:1cio-ted. 3ased on the applicants' appraisal of anticipated deflections unde; 113'! proof test, as s -,rized on page S6-C-3 cf Supple =en: Sc. 6, we believe tha: the relati~.ely Icwer ductility available with wedge anchers should to: preclude the use of vedge ancher In addition, if one accepts the applicants' proposal for grouting systens.

of the tendens, then the conparative inportance of the tenden anchera e systen is reduced s thereby tendin 5-to allay intuitive nisgivings abcu frictica anchorage systens. Ecwever, :he applicants are designing :he anchcrage systens to withstand at leas: :he tendon's guaranteed ul:inate streng:h-and condue:ing full scale proef :ests--thereby ac: :ak.ing any anchcrage :redit for the grouted :enden.

4

he applicants have specified :ha: the na:erial for the tenden wires be e..,e.

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6) %+, <,: Specifica: ions for L*ncea:ed Seven Wire Scress Relieved Strand for Prestressed Concrete, with =inicu: --d-' e strength of 250,000 psi and the seven wire s::and shall also confor: :: A5"'.I-A-16, wi th

=ini=un ul:1:a:e s:reng:h of 270,000 ps'.

A review of Appendix 5K :o the ?SAR, a c.acussion en relaxation Icsses by Schupack 5 Associates, and previous contact and discussion with C7LI on their LOK-Stress (stabili:ed) strand has led us :o :he conclusi:n : hat ei-her stress relieved or stress relieved and stabili:ed strands can be

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used

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losses in the 35'? range are 14 for stress relieved and '.". for stabili:ed.

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s rel.;xa:10n es:i= ate is a: least equivalent :c that f:: stress relieved strand.

It is cur conclusion, therefore, tha: if the same design con-servatism will be used fcr stabil1:ed strand as for stress relieved, tha :

the use of ei:her s trand is acceptable. '!creover, stabili:ed strand is being used a: Ft. St. *lrain and abroad.

n su==a he pres:ressing systems =entioned abcVe share :er ain charac-teristics. Principally, the tenden 1:self is s::anded in each case, and mee:s the sa:e za:erial and strength specifica:i:ns. *hree of the anchcrage asse

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5.5 su:reillance and Tes:in2 Grouting of the stranded tendens with a cement grou has been proposed by the applicants. In the United 5:2:es to da:e, be.nded tendens with ceme :

grcut have been used only once in a cen:ain=en: structure. 3 e con:ain=en:

for the H. 3. Fabinsen f acill:y used grou:ed vertical prestressed steel rods.

The applican:s, raccgni:ing a lack of existing da:s en grouting of large -

capaci:7 (approxirstely 20C0 kips) tend:ts, have conducted a :hree-phase p ro gra:2 of :esting. Phase I investigated whether acr=al grcuting precedures cculd be effec:ive, Phase !! tested the ef f ectiveness of special g cu:ing a

proce.ures :ha: vere deve.3 a.

cpe. vnen :aun.;. :o be necessary, and u..ase...

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checked the repr:ducibill:7 of the results ob: 'ned with the special procedures. Ecri:cntal and draped (arcund a simulated opening) tendens were tes: grauted. Cne of the reasons f or :enducting these :ests was an opinion a cng many s tructural engineers : hat successful grcu:ing of s::anded tendens veuld prove to be cuch =cre dif ficul: :ha: f or indivicual paral' el wire tendens. Se test progra= showed good grouting results, in spite cf sc e dif ficui:ies enccuntered wi:h the greuting sys:en during par: cf :he Phase III program. We have :encluded : hat a :anden sys:e= can be grou:ed in an acceptable anner il properly sualified procedures are empicyec.

.ae ese c: a gr:u:ed :enden syste= has, in i:self, several fesirsbie 4.a3.....s.

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w varia:ica ef fects on the anchorages and assists in the control of a'.ructural c nc e e w-,a,,z.,a..,.

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the c'.'ner thr: ugh the uSe of a less apensive duct fil'er caterial and in not being Suojected to the expenses of future tendon Sur.eillance. We w...S.<A.e, e geg.,a. o.; c o -. Sa.c m. p.,.e..<,n p.,y.i.agA u. n a..a..,.1. g a g g e -

wn A

SySten to be equivalen: to tha: provided by a grou:ed SySte al: hough

he de8ree of inScectacility :o : heck the :endens iS ccvi:uSiv. not equivalen:.

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The applicanti do net consider tha: periedic inserrice surceillance of the conta1.~ ent tenden sys:es is necessary, bu: ha s nevertheless presented the following program. A :est pressure of 69 psig (113*. cf design pressure) will be applied at 2, 10 and 20 years after s:ar: of con =ercial operation of the plant. Visual inspection of cracks and displacement measure =ents with dial guages and :heodolites will be used to evaluate :he pressure effects.

~~ae appli: ants anticipa:e tha: :he :ctal deflections will be s=all, tha: the significance of dif f erences in these s=all deflec'.icns will be difficul: :a evaluate and that caly a gross difference in the struc:ure, such as a large loss cf pres:ress force, would be apparen:

frc the seasure=ents.

In cur opinien the surteillance systes arct.osed bv. :he applicants 'iculd e

show cely whether the strue:ure could f*:nction as designed, or had failed.

There shculd be a capability to detect s true: ural dete.rieration, if such shculd take place, rather than =erely being notified tha: the s:ruc:ure, at scue point in time since :he previcus tes:, had los: the ability ::

withstand the tes: and design leads. We censider that an ac:eptable

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If corrosica pechanisms were present and active, the instru=entation wculd shev decreases in structural capabili:;r before a pein: vculd be reached at which the contaignent could no longer withs:and the design and tes: leads.

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these gauges in da inspec:1ces has de:cnstrated their long life and

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vill be conducted and evalua:ed. The applican:s vill develop specift:

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cen: rete building. All liner seas welds and penetratien we.fs :: :he s: eel liner vill be enclosed in welded channels to provide an addi:icnal leakage

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f an-cooler operatica take suc: ion frc= the river water via the nuclear Services cooling systa= and exhaus directly back to the river.

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Tne isolation valve seal wa:er sys:e= and a con ai=ent c.ene: ration pressuri:ation systes provide a neans to pressuri:e :he contain=en: fluid pene:ra: ions isolation valves and penetrati:ns to a pressure grea:er than the containment design pressure of 60 psig. Tnese two sys:e=s vill inprove the effectiveness of :he contain=en: isolation and reduce leakage fran :he ca..a*..

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of 51.3 psig.

~~he peak pressure in the contain=ent of 52.3 occurs for a 5 f:- break. Since design pressure is 60 psig, :here is abcut 15" cargin available to accc==cdate other ener$y scurces tha: may resui:

fc addi:icnal retal-va:er reac:icn and secondary stea=/condensa:e.

The cargin available in TAI 11 con:ain=ent design was of the order of accu Table 5.6 su=.ari:es sc e of :he results of the 3abecek and 'iilecx cal-cula:icns for the varicus conditions indicated.

Tae applicants have analyzed the contain=ent capabili:y assu=ing a linear re:al-water reaction rate energy inpu: cc the cen:ai=en: concurrent w:.:h an 3. 5 f:,- he t leg rup:ure.

his analysis indica:es the contai=ent can vi:hstand a 100.* metal-va:er reac:ica after 3520 seconds vi h 5 fan ecclers operating or a 100* =etal-vater reac:icn af:er 1170 seconds with 5 f an coolers plus the 2 spray systens operating withcut exceeding the design pressure of 60 psig.

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energy releases of the cc=plete pri=ary cculan:, One 3:e2=

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failure vi:h secondary coolan: release, and retal-va:er reation has been based en the assu ptien that the hydrogen released frca :he metal-va:er

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.- 6.0 REACTOR PRIMARY SYSTEM 6.1 General The reactor primary coolan: sys:em is simila the Unit 1, Rancho Seco and Russellville plant.s.

However.

for TMI 22, the applicants have proposed to design the piping for the primary coolant and emergency core cooling system in accordance with USASI B31.7, Class 1.

Our review of the design of the reactor internals and thE pressure vessel material surveillance program is discussed in the following sections.

6.2 Reactor Int erna ls The reactor internals for TMI =2 will be fabricated f rom SA-240 (Type 304) ma t e ria l.

Radiographic inspection standards for welds and welder qualifications will be in accordance with the ASME Boiler and Pressure Vessel Code Sections III and IX.

For loading due to normal operation and design basia plant transients, comcined witn the operating basis earthquake, the primary and secondary stresses limits for the reactor internals will mee t the requiremen s :# the A3'E 3ciler and Pressur: 'lessel Code Sec:ica !!!.

A find these limits acce :fele.

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.l The reactor internals w':

a ist, be designed to withstand the concurrent blowdown and Design Basis Earthquake (DBE) loa ds The method of combining these loads for analytical purposes w:L1 be to input both seismic and LCCA excitations and then vary the rela tive starting times until maximum structural motions, indicating maximum stresses, are obtained.

Primary stresses under these combined loads will not exceed 2 '3 of '.ne stresses corresponding to the uniform strain value at operating temperature.

This criterion results in allowable strains which are less than 20 percent of uniform strain.

All reactor internal compono :s will be removable ' rom the reactor vessel to allow inspection of the internals and the reactor vessel internal surface.

We' find the general methods of analysis na the design criteria for the reactor internals to be acceptable.

The nuclear steam system supplier for this plant (S&W) is presently conducting research and development programs to more de finitively characterize the blawdown forces on the reactor internals and to demonstrate the adequacy of the internal vent valve design.

I., response to question 11 U-A.

Supplement 3.

tne applicants s ta te tha t information covering the pressure-t;me us trv in

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-w-w the reactor and primary system following an LCCA. and the sultant stresses and deflections in the reactor internals, including those resulting from the combined LOCA and DBE.

will be provided for our review.

This ma t ter is of concern to all the B&W plants.

As stated above, we find the limit-ing design criteria adequate; however, eventual determination of the ad?quacy of the TMI #2 plant for operation will, of course, be predica ted on a realistir appraisal of the actual loadings.

We will pursue this ma t ter with the applicants in the post-construction permit period.

he find several inconsistencies in the sta tements made in the TMI 22 PSAR concerning the test program for the internal vent valves.

Although the response to question ll. 4-Ae s ta tes tha t the program provides for testing unter simula ted reactor opera ting conditions, paragraph 3.3. 4 of the PSAR specifically exempts tests at elevated tempera-tures and tests to show that flow induced vibration, under actual operating conditions, will not allow bypass of significant quantities of coolant nor cause degradation of the valve assemblies or the supporting structure leading to possible systematic f'ailure.

These matters a:e not unique to TMI 2 design. but are of concern to the current generation of the EaN plants.

We have indicated to the applicans that we will require experimental data related to the results af testing a prototype valve at fully simulated conc : Ons to determine long-term effec's In-place functional tests of i

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- a confirmatory nature will be necessary during the cold and hot preoperation testing.

We also find that vibration studies discussed in the PSAR are limited to planned 1/6 scale model flow tests.

While ve concur that such tests are a valua' ale aid in assessing the. vibra tion response characte ristics of the internal components. these tests alone are not a dequa t e, and therefore, we will need to review the results of more detailed tests and their applicability to the T',II =2 design.

The applicantsshculd conduct a confirma tory program rela ting to measurements o: the amplitude and frequency of the reactor internal structure vibrations during the cold and hot pre-opera tional testing of this plant.

These matters have been discussed with the applicants and they indicated that they will develop a program N cover these ma t t e rs.

We plan to follow the progress of :hei ef forts in these areas during our review of other similar plants as well as during the post-construction review stage.

63 Reactor Vessel Material Surveillance Proeram The program as outlined contains four surveillance capsules; the tentative DRL pcsition requires a v.inimum of five.

The applicants hate o ra lly informed us tha: they intend to participate in Eabcock k Wilcox's Integrated Surveillance Program-ELW made an informal presenta an to us or

anuar: 16 1969. and from this we understand t ha -

'.e program

._1.

ase fcur capsules per reac or unit.

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-M-allow E&W to place only four capsules in each reacter in the program we conclude that each applic;nt should re cain sufficient archive ma terial to make uo *w a additional ca p-sule's and to.have space and brackets in the reactor vessel ts allow insertion of a fif tn capsule.

This last provision would protect against an unfavorable conclusion upon evalua-tion of the Integrated Surveillance Program or ;f an appil-cant terminates his intended participation in the program.

We will discuss t his ma t ter with the applican cs prior to the July ACRS meeting.

~.0 OVERALL PLANT PROTECTION 71 Tornadic Wind The applicants have indicated in Amendment N-5 that tae following structures will be designed to withstant the tornadic forces and missiles generated by a 300.pn tangential and 60 mph translational winds includir.g an external pressure drop of 3 psi in 3 seconds We conclude that the design basis in this regard is adequate.

a.

Reactor Building b.

Control Building c.

Auxiliary Building d

Fuel Handling Building e.

Intake Pump House Structure 7.2 Missile Protecti_on 72 1 External 'Jissi~es In Amendment No-5 Table 1 6-1.

I' e a pplican:3 prese n:

a spectrum of missiles yh;ch were considered as to rna do-m~

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-a generated missiles The appl:.can:2 m re reques:ed ::

analyze the effect on Unt: No. 2 of missiles which might be generated from the adjacent Unit No.

1.

Two sources of missiles whl.ch are considered to be generated from Uni:

No. I are the turbine-generator and the 400-foot-high cooling towers.

Aircra f t missile considerations are discussed in Section 11.0.

The analysis by the applicantsindicates. and we agree, t ha t failure of the cooling towers will not affect plant shut-down capability or result in an uncontrolled release of radioactivity from Un.

No.

2.

In the Uni No 1 PSAR, missiles generated by failure of the General Electric designed turbines were analyzed.

The a:plican:s sere requested to analyze the effect of these missiles in the Uni: No. 2 structure.

The Uni: No. I turbine axis of rotation is oriented such that the high speed rotational components. which were considered possible missiles, cannot collide with Uni: No. 2 structures unless deflected off a Unit No. 1 building column. beam or wall.

Analysis of Unit No. 1 turbine missiles presented in Cucple-men: No. 3 o f T'JI el PS.'.R indica t e d a minimum of '. 3 inches of concre:e vas needed to absorb the e ne rgy o f the mos:

cri::. cal missile.

All Un:.: No. 2 s true:ures wn:c:. a re designed to w.:hstand the crna d:.c w.nds anc miss:.ie s e,,

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These wall thickness requirements are established by the aircraf t protection requirement.

722 Internal Missiles The TMI =2 dealgn will include protection of critical components required for safe shutdown, a ga ins t internal missiles genera ted by component failure such as valve bonnets, pump flywheels, or high pressure components.

In Amendment 10 the applicants presented a description, design evalua tion, inspection and testing, and surveillance proposed for the TMI 2 primary coolant pump flywheel.

The control rod drives reactor vessel, core flooding tanks and the reactor building emergency coolers are protected from potential flywheel missiles by shield walls.

Thus, f711ure cf the flywheels is not expec ted to damage these components; however, additional analyses of the possible failure modes including the effects of an earthquake will be necessary.

We intend to discuss this ma tter with the applicants prior to the July ACRS mee ting.

Te have reviewed a pre limina ry design of the flywheel and concluded tha: the proposed inspection during fabrica::cn is no adequate because

only considers surface conditions.

We T121 require tha: the inspection efforts be increased o

incl 0de ra di o g ra p h'? and altrason1C inspeC: 10n Of :ne f l y7 Ce e l

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n.

=

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4 s subassemblies The basis for requiring increased fabri-cation inspection is for assurance that the units are free of gross defects.

Because of limited accessibility of the flywheel for ins e riic e surveillance and inspection, assurance that preservice gross defec ts are not present reduces the likelihood of failure during plant operation-We will review the applicants' program for inser:1:e inspection during our post-construction permit review as part of the overall plant ins e rit:e tnspection program described in Section 18.0.

~.2.3 Conclusiot4 on Missiles We conclude from our review :ha: :he external and in:ernal missile protection provided in the TMI #2 design is adequate.

However, we will require that the inspection p ro posed for the primary pump flywheel during fzbrication be increased to include sufficient volumetric inspection to assure the flywheels are free of gross defects whicn could result in failure during operation.

We also intend to review the results of the applicants' seismic analysis and their plans for inserit:e inspection of the flywheels.

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The Cer. mission's General Oesign Criteria and the ?roposed IIII Criteria

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4;ga:t 25. L, tis, served, vner-a ppli sble, as -he bases 'Or judging tne edequacy Of the Protecticn instr"=ent System and the Centrol System.

A ?cm; arisen has been made with the previously approved ?.ussellville plant f:r the pur;cse o' avoiding repetiticus enslyses. Ae:Ordingly, enly

se design feeturas shien sre nev, or for vni:n addi:1:ns t in'Orma tion has ceer re:eiven, sre addressed herein. We have veri *ied tha-only the rede;igned red :Ontr0L system, including the sersa bus, and a slign:ly

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Cur :si:Jia:1cns cf :ce pctential deses, vittcut any iodine recevsi systen, indieste that iodine reduction fae:crs cf apprcxt:ste'.y c.2 f:

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o

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=. c, o..

a.

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cte ( 30.dar), dcse are required in crder sc ?.eet the guideline val.es

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<n

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a r.

.s Since the research and deve;cpeen for the alkal;ne sedium thicaulfa e spray additive has net been ec=pleted, the applicants previded alternatives vnich vculd be used Oc reduce tne ;odine thyrctd deses telev the 10 ~73 1,0 g;ideline va'.ces using car re ncd cf evaluatien, The applicants have indi:sted that alternate actien cculd be used in tne even: the research sed develepcent for the s'kaline Na 3-0. sdditive

. c

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deses any be reduced, je have used cur standard es;:ula-icr.al etteds a-i e a.,...,.<.e.a.

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a ncncrganic,\\ = 3.lhr-1 370 C

1 Spray enly ',1500 gpe) a.

..s.,.,.

= s e

a prey only (..,, gP /

a.

kra nenergsnic A= 3.lh" '

c.

b.

ergsnic) = 3 3?hr*'

~,

ncnorgsnic 3=3.5 r, ~

290 3"

3 Spray :nly (13C0 gp) s.

b.

crgsnicA = 0 3:hr-'

ncncr ga nic<~t:;.c ar

.. ca se i 1) p.aus a.

u

-en cn

ancho Seco filter b.

crganic)-C.35hr-

3V.Ste3 ncnerganic>=3. ipr ~-

160 200 5

Case (2) and redu:e s.

lesy. rate frem 0.2 c

'o. crgsnic A=0 35hr -

/

3.. WL.e j 4Bj

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9 pplics ".0 3 ' 233u p-ices en Sp"sy effe:tive.ess, chen we een *?Tlire !".e

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ca t, based en the results of en ?.13 program, an icdine removsi sys es

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e a

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u

.4 develo; ental, design, test, and manufacturing experience ob;aine-

"er the years fres the Sb'.pping;cr* ar.d Naval Nucieer Progrs:3.

The centrol red drive systen includes drive cecnanisms vnich a::.. 3

entrol red assemblies (CRA), drive een:rois, power suppliet, ;csi: :n indi:s tors, c;ers ting panels and indi:s ters, sa fety devices, enc.:J;res.

nousings, and =cuntings.

Triteria applicable to :ne drive reenants:

4. e s

3. - - e sv a. - I s ) s 1.-'.a..as *. '." - a. ( ' ') "..... n *.. o 11 4 v i +. ".d..- s vs '., ',.,)

. s.

e re=0vsl (d) pcsition.9diestien, (e) syste: =eni:0 ring, ( f) dri"e speed,

( g) meenani:al stops, ( h) CRA pcsitiening, (1) C?.A trip and ( ') ??A vitndrsval. We have reviewed tne design criteris and :Or. lude ney are essentially ne same cri eris used snd previously revieved for ne rsci-t a nd-pinien driv? rechanis.

In Supplement No. i the s;plicent hem addressed aress in vnt:h w.

na v e a.x

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~. ~... c a.. 0.

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d..- i v a.

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a.s,a "...'.v,

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insertica f:ree of a;;rextra:ely -CC peunds in :te event a cent:01 red sneuld fell to drop to e fully inserted pes;;ict folicving a scre. This

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'I Al'l.l; 10.0 Ctitli' Alii !;nfi tIF Cll AP ACTI It i S I I CS r l' l'UP Ciifl'113it, l'ott Di' I t't. lil.!: I Cils y

~a Cof.u t li.o i n r. i n""' i nn

.N t

II.ilwock & U i t rox Men t inginnine Type ol Drive l'.ir k-4 -l' l u t on 11o l l e r-flu t ti gi_ie t i c. lac k Ro l_l e r - tin t R1ck-A-l'in i. n fly.ne t i. fol y

llo. of Drives / reactor 69 69 52 45 r J.

m e

m a

a flo. of Rols/ilrive 16 16 20 20 1 (Crn"Iform)

'. rr in Con t r o l ik.il Pol non An In Cil Ag i n C<l An in Cil Ag i n 1:.1 gC l'.4C t

fs t

'I o t a l Roil Worth (/ik) 101 10%

7%

91 91 ytv,

b*

Strote I.eng t h ; in.

1 49 1 19 144 I44 1 12 1 12 gy 81$

h lirIve Specil; i n /in i n 25 K

45 15 46 24

[v]

IVl Type Sc r ara Cravity &

Cravity Cravity fio Sctan Cravitv 6 Craviey pj Anto I)r lv e-(Parttal Auto lir Ive-8I e-)

t-t-

Down lengt h roils) Down td g _"]1l'osition Inllration Cear-pot 6 tla y,ne t i c Differential liif f erent ial Gear-pot A Differential 1

, ;,3

- l g_ j In lite t a nce liee.1 Switchen Trannformer Trannformer Plannet le Tr annt or mer e a

{J)

Col 1 flotor pot lice <l Sw i t chen f3 i8 t e -s lYs Trip Time 1.4 sec. for 1.4 nec. for 2.0 sec, full 2.5 9ee. 901

< 2 ne,.

!'8 Ik8

[h 2/3 innertton 2/3 insertton Insertien innertton o

R Ilesign pressiere; pn i r, 2500 2%0 2485 74R5 2500 2500 Design pressure; *F 650 650 650 650 650 Mo RI.D l's og ram Yen Yen fin Yes Yes ve, Approvc<I for (:P Yes (all itM4) tio Yen Yen (all Ven Y e-(fliinc Uentinglionne

( Pa l l n a.len )

Y.inl c.

n PearIorn) of parttal lengtli t' oi. iliiven II II flone Il 4

--~

lienigner It h'l BMI 11en!.

He't t.

Comb. Inri.

C om t,

l'o p,,

it.nnti ;ir i sin e t P hi lih U atol

Went, Uent<

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essenti?;iy :P.e so e es :".e.:E program for the rsek.and.;inien drive

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4. 3 2 p.g 3 w. e..... g A. '.

Ea. cock. & W...x.

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We P. ave reviewed the in'or.ation rega rding -he drive techanis: presented

=,~ 4.,.,.. e.......C.

e4n and sues.4.ns L,.,m o*.

u...,t.....

.~ C.

s r

3esed upen cur review of tr.e a pplican".s' ?C progrsm, we have ressces:le sssursnee tha: the relier.na: Oce:rol red drive seensnism vill "r0V' de v

d e..

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3hift Su;e-visor vill be a licensed senior reseter operster.

"he Shift Fereman and fcur =ntrol operaters vill te licensed reactor cpersters.

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in cur judgment, fer s tve.ur.it station, there shculd be two senics reseter c;ersters en duty at all ti=es.

We have informed the appilcants that this

2tter eculd be resolved at the opersting licensing review stage but that they shculd ca'.e.e previsiens in the precpersticnal training prog s= to ccc cdate such a requirement.

The spplicants plan to use the emergency plan developed for Unit I with 3;ecist provisiens to include possible e:ergencies which eculd cecur while Unit 2 is under ccnstructice and ll nit 1 is opersticnal.

We neve revieved the applicants' sub=ittal for training, sd=inistrstive centrcls, res12v end audit, and their e=ergency plan. All are similar Oc their plans fer ~'CEL whi:h we have previcusly fcund to be satisfactory

. =cre ec prehensive in-depth review of the applicants' final plans in these areas vi'.1 be :ade st tne cperating license stage.

'n the basis Of cur reviev cf the above organi:stions'. sche =e, we have cen-

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We have discussed vitn t".e applicans the proposed industrist security

essures which vill be enployed during construction and operaticn of 2 Cpl.

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bridge er by beat.

'"he appli:en-s..sve indicated tr.e access by. - ncrth and scuth bridges vill have centrol statiens to centrol access to the site du. ring constructica and cperatien of 24Ist end p2.

he applican s also indicated that during constructicn al'. inspecters and supervisory persennei vould be instructed to vatch for any 3 igns cf pctential sabetage.

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the availability of the statien; hcvever, ve censider it highly unlikely fer e large sesie act of industrist sabotage at the station to cccur the:

vculd affect the health and safety of the public. We intend to centi:me cur reviev of the industrial sabotage ;ctential en a gene 1 basis tnrcughcu-the ; cst-censtruction reviev and opersting license review of -he facility.

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.No. 2 faci'ity, ve used tne guidelines based upcn the ;rc;csed acendnen Oc i^ C73 30, A;;endix 3 que'ity Assursnee Criteria fer Nucles: Pcver ?lsnts 'sted

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. e Tecnnical Specifiesticca for the facility.

Inspecti n ;cints selected v4 -... e evs...a eA c n. *.e '.a s '.. c.'

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Tne preps = developed vill be ene vnich assures the centinued integ-ity Of the reacter ecolant syste= censistent vi.h minimum devn::=e and rsdistien ex;csure fer personnel.

On the bar.is of cur review of the a;;'.icants' pregas conca ning inservice inspection. ve cenclude that it represents a reesceable ap;rcach Oc developcent

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.. e ac*ien during the ; cst-censtructten per it phase and therefore intend to require the applicants to sub=it a status re;cr c2 C design previsiens fer inservice

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(2) An inc. esse in airberne activi y la the containment at=cspnere.

(3) An increMse in activ.if in 3*eSO ge-cra ter seccndSry eco'.?**. Cr

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We cen,:1'eae that the abcve methods of detecting primary ecolant leaksge are adequate for the constructica permit review. Ecvever, during the

cst-censtruction permit stage, we intend to review the oversll capability cf the syste: :. c=nsidering ensitivity, respense ti=e and limits for inclusien in the Technica; Specifiestiens.

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Cn the basis of cur review of O C y2 several :stters vere identified that require centinuing reviev after issuance of the ccastruction permit. This ection is acceptable to us becsuse in zany esses the carryever items are of s generic cencern to the 3&W plant design and lign vater reacters vneress in ctr.er instances, the additienal design details that vill be necessary to rescive these :stters vill be rade available prior to construction.

Eased c1 cur review and discussions of these catters with the applicants, we cen;lude tnat they can be resolved adequately within abcut a year felleving issuance of the censtruction per=it.

The ratters of genersi cencern to this class of lign: vater reacter plants that vilirequire a centinuing review effert are:

(1) cc=bined (*CCA/Seis=ic) leading cenditiens en internels, testing aspects en the vent valves, and ccefirmatory vibrstional test pre gs: for cere internals (Section 6.1)

(2) ressure vessel surveillance pregs: (Secticn 6,2)

'2) ICO3 initiatien s.gne; diversity (Section 9.;)

-)

icdine rencvsi effectiveness l3ection C.2) s 53 effects cf rsdiclycia (Sectten i? I LO stes: generster tube fat.are :cin ident vita in 10CA Eee-icn 13 '

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.i v-a ac The netters of particular concer- :o 2Cp2 that will require resciutien as the necessary inf ernation bececes available are:

(7) fleeding protection requirements (Secticn 2 5)

(S) envirennental nenitering progrs: (Sectica 2 6',

(9) tenden anchersge design and surveillance prc6r23 (Secticn 5 5)

(LO) analysis and inspectics of flywheels (Section 7 2.2)

(11) insertice inspection provisions (Secticn 13.0)

(12) leakage detection (Sectica Ic.0)

In viev of the actions proposed to resolve the abcve itees, we cenclude that the pre;csed facility can be constructed and opersted at the proposed site withcut undue risk to the heslth and safey of the public.

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