*

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0 TENNESSEE VALLEY AUTHORITYCH ATTANOOG A. TENNESSEE 374o1

500C Chestnut Street Tower 11

MR 1J D73

THIS DOCUMENT CONTAINS

Director of Nuclear Reactor RegulationAttention: Mr. S. A. Varga, Chief

Light Water Reactors Branch No. 4Division of Project Management

U.S. Nuclear Regulatory CommissionWashington, DC 20555

Dear Mr. Varga:

In the Matter of the Application of ) Docket Nos. 50-327Tennessee Valley Authority ) 50-328

Enclosed is revision 5 to the "Preservice Baseline Inspection andInservice Inspection Program for Tennessee Valley Authority SequoyahNuclear Plant." The initial draft program was submitted by my letterto you dated August 23, 1977. This revision incorporates changes toclass B preservice inspections to include only those welds and com-ponents which require inservice examination. As additional changesresult from implementation of the preservice program, they will besubmitted.

Revision 5 was intended to be submitted by my letter to you datedOctober 19, 1978; however, revision 4 was inadvertently enclosedin that letter instead of revision 5. We apologize for any incon-venience caused by this oversight.

Very truly yours,N

4 .

'f / c,J. E. Gilleland

#Assistant Manager of Power

Enclosure

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7904240 9 7

gne-o n we n

/',.' ENCLOSURE* * D] T;Tl:Tl:1.'T )' O::.} !,equoyah !!uclear f. j ant g*

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'' ic Pi ro t Ibnter Pile' l. .

3 SuperinLCndenL

' h _ /m i s t an t '' u p e r i n t. c a d e n t. (Ope r . )-,/m i n t an t Superintendent (:'aint . ),.

| Ad uin i s t ra'. i ve fiupe rvi s o r.u

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).C 11ain t en an ce S.upervisor.

.

_IC Ann i s t an t !hintenance SupervisorejIU lhr,ults Supervinori ,

b h.nintant R.uu]tn Supv.IC _ Ope ra t i ca n Supervinor

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I, IU Quali ty h.nurance Su,e rvisor* '| SURVEILI.ANCE INSTRUCTIO:; 1!c a 1 t h P.n,sieist

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-. Pub) i c Saf e '.y Services Supv.

Cnie f Storekeepe r['g 3 3_ g i f,Preop Test Pro;;ran CoordiantoriiOutage Director

,

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Ch e nical En gi nee r .'~ pRESERVICE MASELINE INSPECTIONa AFD INSLRVICl: 1: W :CTION Pl;O._ 1:adiochen ],t.bo rato ry ,

GitA'l iOR TI:NNESSEE VALLEY l n u t r u:cca t Shop

j' AUTil0RITY SEQUOYAll NUCLEAR PLANT Ucactor Engineer3 n n t r u:: en t En g,i nee r

i.licchani cal Eng,incer

Units 1& 2 IU Sta f f Indust ri al Eng,ince t,

~1C Training Cente r CoorGn: cor,I' PSO - Ch i ci n.aup,a En Supv NPliPS ROP,, MS,

6.

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*.. SI-Il4,''6 Page 2 of 23

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tr

| .mA. Ex ac t lecations to he inspec ted by photog raphs , annotated drawi ngs ,

sketches, or' word descriptlon.L

B. Method of examination to be performed on each location and cali-bration standards used for comparison.-a

J C. Method of data collection and reporting." D. A schedule chart including:1

1. Item (s) to be inspected each inspection interval. ',

2. Sizes of inspection areas (linear feet of weld, square inches,,"etc.)

f) 3. Type of examination (Visual, liquid penetrant, ultrasonic, etc.).h*

4. Entimate of inspection area dose rate.!

L 5. Welds known to be inaccessible for inservice inspection.2.0

.INSERVICC II:SPFCTION PROGRA?i,,

The select ion of specific areas for inspection during each 40-nonth cycle wasmade considerin!; and optimizing the various factors affecting performance of'l the program. Of prime consideration in the fulfil haent of the requirennntsjoutlined in Sor t ion 5.2.8 of the Sequoyah FSAR, which ir, attached as Appendix

%./ D of this document, and as closely as possible to Section Xi of the AS:iE Boiler} and Pressure Vessel Code, Rules for Innervice Inspection of !!uclear Plant Plantj Components (through suxier 1975 addenda). Other factors censidered were as

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} A. Areas of t he most nevere service conditions, i.e. rad iation exposure,J ther ,al grad ient , cycling stretses , and high operating st.resses.

I B. In order to limit t he radiation exponure of employeen, thoce areas whereI

the done rate progresses toa higher level each year are to be inspectedearly in t.he inspection period ubere allowable under the program.

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! C. "anpouer econonic< were also considered; i.e., uhen several areas can'h he innpected in the Lan" general location, this uj11 he done to nin-intre scarfolding and expecure to employces.

1

3.0 DAS!:1,I!:C AND I N:W"V I C F. T NSt r.CTION Pn0CCA!! EXA'il !ATION

; TD area to be inspec"cd durlug the first 10- yea r inspect ion interval are,

s,,,,/ taho!ucd i n Ta b l e r A and B in Appendix A. 'Ib e planned innpection areasare eutlined in Table: A and B for each 40--conth innpection period duringthis _i n s tsec t ion i n t.e r v a l .

In nerordance with U:C '' LOO and IWC-2400 of ASME Sect ion XI, only those*Clans U component: chich ':111 he examined ov

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Page 7 of 23

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g %/ 3.2.2 Nozzle-to' Vessel Welds and Nozzle Safe Ends

i" * 'Ibe re a re four 6-inch nozzles, one 4-inch nozzle, one 14-inchnozzle, and one 16-inch I.D. manway pad which will be examined*ultrasonically for the preservice baseline and inservice in-I] *l. * spection interval. The inside radii of each of these will be

W * examined at the time the nozzle-t o-vessel welds are being in-* spected.

r}a

.Nozzle safe ends are welded forgings and will undergo a liquid -penetrant and an ultrasonic examination.

'D * Nozzle and manway f orgings are fabricated of SA-508, class 2,man,",anu se-mol ybder.um stee l . Safe-end connections are SA-182,

[] GR. F-316L forgings.L

3.2.3 Pentrations

There are 78 heater penetrations in tl.e lower head. These areas~

wilI be visua1ly inspected for signs of leakage.

! TVA intends to perform this inspection.

3.2.4 _Pr_e__s s_u_re _n_e_t_a in_i_en._ Bo l t i n_g.

, . .

.J v The ho! Ling on the nanway cover shall be vit.ually examined forsigns, of leakage and/or distress. .f G

u' .i TVA int ends to perform this inspection.,3.2.5 Prcosurizer Support Skirt Weld

'- 'Ihe nupport shirt-to-vessel weld, approximately 23 feet in length,vi11 be untrasonically exauined for the preserv]ce baseline and

,'l inservice inspectien.I .|

'Ihe cupport shirt is fabricated of SA-516, Gr. 70, carbon steel;, plate.

!""

3.2.6 _I_n t_e__r_i__o r C l e d Su.r_f ac e_,

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j A patch (36 square inches) of t he in crior cladding t..'ill be> v:sual!. exanined for the preservice b: uline and inservice

i n c.pec t i on when t he aanway cover is re., aed. This uill be

!] Q * acco plir,hed ett t er cold hydro or af ter ihe hot f unct iona !,; t e s t i v.a is completed.

TVA int endu to per forn thi s innpection..

I Int erior cladding is of austenitic stainleus stcol.

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Rev. 5-,

3.3 Stean Generators (4)'j3.3.1 Primary lle.ad-to-Tobe Sheet Weld,

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The primary head-to-tube sheet weld is approximately 36 feet ina length, totaling 144 feet for the four stean generators. All

these will be exanined ultrasonically for the preservice baselineexamination and during the inservice inspection interval.

g The tube plate is a SA-50S, Class 2, steel forging. The hemi-spherical chamber is a SA-216, Gr. Wec, casting.,

t-

; .3.3.2 Circumferential Welds - Secondary Side

i 'Ihere are 5 circumferential seam welds, totaling 198 feet, or 792

|V** feet for the 4 steam generators. A total of approximately 36 feetof f our velds ull t be ultrasonically examined for t.he preservicehaseline ex wination and during the fenr inservice intervals. A*

* f i f t h ve ld on each generator , SG'.?-DI, D2, D3, and D4 (See drawing No.J Cil-M-2345-B in Appendix A) is partially inaccessible. Approximately*

* 9 feet of one of these welds will be ult rasonically examinated on a* best effort basis for the preservice baseline and during the four in-j

J * service intervals. Approximately 18 feet of two welds will be examined* during the first inservice inspection interval (see Appendix A, Table B).

The vessel shall and head sections are fabricated of SA-533, Gr. A,,

elass 1, steel plate,

l, 3.3.3 St enm Generator Primary 1:ozzles

V The stear generator primary nozzles ans manway pads are an integra.1 part*of the vessel. 'the safe ends of all ciglit prirary nozzles on the four,

! generators shall be liquid penetrant and ultrasonically exanined for the' preservice har.eline inspection at. the same time as the nozzle-to pipe,

velds are being inspected, in addition, the inside radii of all nozzles

) and nantay:. chall be ultrasonically examined for the preservice baseline*I i n s pes'* t. lo u .

AlI safe ends and inside radii shall be exami.ned during the 10-year in-

]' speeLion int erva1.

* The nozzler and nanduay pads are f abricated to SA-216, Gr. Uce. 'lhe- ;nozzler have bettered 30BL safe ends.Jh*.

3.3.4 Steam Generator Secondarv Nozzles, * There is one feelwater nozzle (161nch I.D.), one main steam nozzle

* (32 -inch 1. D. ), and t wo nauway pad s (16-i nch I . D. ) per ct eam gene rator.* Four not :le-(S!anuay)-t o-vessel velds vill be ultrasonically exanined for

]g* the preservice baseline and during the four inspection intervals. A. .J * total of one nozzle vill be inspected durin", the first inservice inspection

* Interval.:

;' Nazzles are f abricated of SA-508, class 2 c.tcel.

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SI-ll4page 9 of 23Rev. 5

3.3.5 pressure. Retaining Bolting

The bolting on the manway covers (2) on the primary side of all'J the generators shall be visually examined during the preservice

baseline and the inservice inspection interval for signs of leakageIl or distress. Each innway has 16 bolts at 1.88 inches.

- * Bol t inp on two nanway covers on the secon. ry side shall be visually* cxamined for the preservice baseline and during each innervice in-

!. * spection interval. A total of four holts shall be ultrasonically' * examined for the preservice baseline and four inservice intervals-,

* (See Appendix A, Table B). pach manway has 20 bolts at 1-1/4 inches.

TVA intends to perform the visual inspections.

'V The bolts are fabricated to SA-183, Gr. B7.

' ~1ti 3.3.6 Int egra 11 y-k'e Ided vesse 1 Support n..]

There are no integra lly-we lded vesse l supports. The four mainsupport pads are secured to the steam generator field support

..). system by high strength bolts..h

3.3.7 Interior Cladding.

After cold hydro or after the hot functiona l testing has beenconp le t ed , the manway covers on each steau generator primary.head shall be renoved and a patch (36 square inches) of cladding

j near each nanway shall be visually excmineci for the preservicej baseline examination.

AlI these wilI he examined again during the inspection interval.

|, TVA intends to perform this inspection.J

3.3.8 St cam renerator Tubing

q Each stean generator consists of a tube bundle of 3,388 Ni-Cr-

j Fe a lloy (luconel SU-163) U-t ubes 01 0.875 0.D. by 0.050 averagewa11 thichness.

During the preoperatinnal haneline and inservice inspection,

3 ntcan generalor tubing sha1I unb rgo eddy current exani'iat f on.Baseline examination of steam generator tubing shall be perf ormedin accor

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| SI-114* *

" Page 11 of 23Rev. 5

D. In the e cnr an excess of 10 percent of the tubes ex-amined exhibito relevant indications in excess of 20,

'

}V percent of t he wall thickness, the next tuo inspectionsj shall be performed at 1- to 2-year intervals. If inthese examinations no more than 10 percent of the tubesexamined exhibits either additional degradation (greaterthan 10 percent of wall thickness) of previously de-graded tubes, tubes with new defects in excess of 20,

V percent wall thic kness , or combination of both, the in-

] spection intervals may continue at 3-1/3 years.Al1 Icaking tubes and tubes exceeding the plugging limit''shall be plugged.

3.4 R!!R Heat Ev.changere (2)y.

3.4.1 Ci rcur ferentia l Seam Ue lds.

There are two circumferential welds on the tube side of each heat] * exchanger, totaling approximately 20 feet for each exchanger. A

* total of nix feet of the two welds will be ultrasonica lly examined3 for the preservice baseline and during the four intervals. Approx-*) imately t wo feet of the welds ulll be innpected for the first in-*

* service inspection interval. 'Ibe uelds include the channel cylinder

j section to channel flange weld and the channel cylinder section to** channel head weld.

3

The channel flange is fabricated from SS, S/.182F304. The channel] cylinder sec tion and channel head are from SS, SA-240, TP-340.

- 3.4.2 No::z le--To-Ve nne l un t as

* The channel cylinder section includes on~e inlet nozzle (14 inch I.D.)| and one outlet nozzle (14 inch I.D.). Two nozzle velds vill be ultra-*3 the preservice baseline and during the four in-sonically c: a m i n ec' ror- a

* tervals. A total of I nozzle will be examined during the first inservice

} * inspettion interval.1 The no:o. le s a re f abrica ted f rom SS , SA-182--F-304.

1 3.4.3 Inter,rc1ly UeIded Supports!i There are tuo int

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SI-Il4Page 12 of 23Rev. 5

'V 3.5 PI p i_ng,_

3.5.1 5'o z z l e-To-Pi pe We l d s

* There are 16 nozzles which have buttered safe end welds. Thesc* are the reactor vessel and stean generator primary nozzles.

U* These nozzle safe end-to pipe welds (steinles, to stainless)will be ult rasonically examined at the same time as the nozzle-*

* to-safe ends welds and are included in the total in section 3.5.2.1.

* Reactor vessel and steam generator nozzle-to-safe end weldsare assigned identical weld numbers as the respective nozzleI

va safe-end to piping welds. ("SE" suffix added to nozzle-to-safee end welds). I'ressurizer saf e-end s are separate forgings.*

3.5.2 Circumferential Pipe .Toint Welds and Branch Pipe Connection Welds _,

All circumferential pressure boundary welds in piping, within thescope of Section XI, shall be ultrasonically exarnined for the*preservice baseline. (See Drawings 30A616-1 and 30A616-4).

Class A branch pipe connection welds exceeding 6 inches in dia-; meter sha ll be alt rasonically examined for the preservice base-

line and innervice inspectien intervals. Class A branch pipeconnect ion velds 6 inches in diameter or mil ler sha l l be liquid

,

pepe r: nit e::amined f or t he lireservice baseline and inservice in-rvspection i nt e rva l . Applicable class B branch pipe connecti.on!we1ds sha11 Le nItranonica11y examined for the preservice base-

' ' 1ine anI inservice inspection intervals.

1

In tha case of longi tudinal-welded pipe , the examination (at thecircenferential joint) will be extended to include at least one,foot e . ie longittulinal weld (s) which intersects the circum-r'

ferentia. joi-'. As information becomes available, a tabulation

of longitudinal pi pe welds sha ll be establi shed and incorpor ated,

into the i nne rv ic e inspection pregram. Any except ions wi ll ba,

noted.i

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d i- 1 l'e* * Pat;e 14 of 23

Rev. 5

3.5.2.4 residual lleat Herova l and Sa f ety In ice tion Pipine,( Rl!R , SI)

s

There are some class A welds which require ultrasonicor liquid penetrant exanination. All of these welds

i will be examined for the preservice baseline and cpprox-', inately 25 percent of these welds will be examined

during, the inservice inspection interval. |W %ds

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SI-ll4Pa ge 15 of 23-

Rev. 5

3. 5.2. 7 Feedwatera

V 'lhere are some class 3 circumferential welds subject toexamination. Approximate 1 of these welds will beexamined during the first inservice inspection interval,and weldo during the four intervals and for the pre-se"vice baseline.

DThe entire system is carbon steel.

In Appendix A, Table B lists the weld size, number ofwelds, sche _duled inspections, and type of examinations.

TVA intends to teruinate feedwater class B on each feed-water loop afLer the outermost containment isolation valve

V (FCV 3-33, 3-47, 3-87, 3-100) for baseline and ISI purposesTh i. s is consistant with Regulatory Guide 1.26.

3.5.3 Pressure R.rtaininn Bolting (Includes valves)

Any clasn A pressure retaining bolting 2 inches in diameter andlarger sha ll be ultrasonically exanined. Class A bolting lessthan 2 inches sha11 he vinua11y examined.Class B pressure retaining bolting larger than 1 inch in d'ametershall he visually exanined in accordance with Ik'C-2400 and tablese

* 1h'C -2520 and n:C-2600 for the preservice baseline and each inserviceA interval. Ten percent of the pressure-retaining bolting (or 2 holtsA or stud. uhichever is greater) in e.ich joint selected for exaninationA i n accor,Luice with ih'C-2100 and lh*C-2411 shall be ultresonically ex-* * amined for t he pres"rvice baseline and four inspection intervalt.

3.5.4 Int er,ra l ly 1:e lded support s and actor Coolant Pumps (4) '

3.6.1.1 presunre "-taining Bol t ing.,

b.dThe main f lan:," on each punp inc lude- 24 holte (4-1/2inchen).

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.SI-Il4Page 16 of 23Rev. 5,

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3.6.1.1 (Cont.)V fach bolt will be ultrasonically examined for the pre-

service baseline and during the ISI intervals.

The main flange bolts are fnbricated from SA-450, Cr.B24. The pump casing is a type 304SST casting.

3.6.1.2 Rapport Components%d

} Each pump has three bolted nupport components. Each| support Lomponent shall be visually examined during the -

preservice. baseline and innervice inspection interval.,

TVA intends to perform this inspection.j

'v 3.6.1.3 Pun t asingsC|

TVA intende to use shop pump casing visua1 inspectionsj in lieu of the on-site preservice baseline visual in-

spoctionc.

During each inspection interval, the internal pressure'

boundary surfaces of one pump shall be visually examined.TVA intends to perform this inspection.

j 3.6.1.4 FlywheelA t. approximately 3-year intervals each pump flywheelshall undergo an in place ult.rasonic examination of

1 arca< of higher

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