ML19276F890

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Forwards Revision 5 to Preservice Baseline Insp & Inservice Insp Program. Incorporates Changes to Class B Preservice Insps to Include Only Welds & Components Which Require Inservice Insp
ML19276F890
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 04/19/1979
From: Gilleland J
TENNESSEE VALLEY AUTHORITY
To: Varga S
Office of Nuclear Reactor Regulation
References
NUDOCS 7904240427
Download: ML19276F890 (16)


Text

0 TENNESSEE VALLEY AUTHORITY CH ATTANOOG A. TENNESSEE 374o1 500C Chestnut Street Tower 11 MR 1J D73 THIS DOCUMENT CONTAINS Director of Nuclear Reactor Regulation Attention: Mr. S. A. Varga, Chief Light Water Reactors Branch No. 4 Division of Project Management U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Varga:

In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 Enclosed is revision 5 to the "Preservice Baseline Inspection and Inservice Inspection Program for Tennessee Valley Authority Sequoyah Nuclear Plant." The initial draft program was submitted by my letter to you dated August 23, 1977. This revision incorporates changes to class B preservice inspections to include only those welds and com-ponents which require inservice examination. As additional changes result from implementation of the preservice program, they will be submitted.

Revision 5 was intended to be submitted by my letter to you dated October 19, 1978; however, revision 4 was inadvertently enclosed in 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 9 ,( !

7904240 9 7 ne-o n we n g

ENCLOSURE

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.. , SI-Il4 6 Page 2 of 23 Rev. 5 tr l

m A. 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-

-a bration standards used for comparison.

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 was made considerin!; and optimizing the various factors affecting performance of

'l the program. Of prime consideration in the fulfil haent of the requirennnts j

%./

outlined 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 Plant j Components (through suxier 1975 addenda). Other factors censidered were as f o i 10.. - :

} 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 where I

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

! 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 areas are eutlined in Table: A and B for each 40--conth innpection period during this _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<r the nervice 1ife of the V* plant will be examined for the preservico baneline.

f 9

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' l

., . SI-114 Page 7 of 23 i? ,

Rev. 5 f

LJ 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-inch

  • nozzle, 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.

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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.

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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 for signs, of leakage and/or distress. .

f G TVA int ends to perform this inspection.

u' .i ,

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 .l

'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 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

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  • 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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. .7-i i

.  :- SI-il4 Page 8 of 23 Rev. 5 j

3.3 Stean Generators (4)

, 3.3.1 Primary lle.ad-to-Tobe Sheet Weld The primary head-to-tube sheet weld is approximately 36 feet in a length, totaling 144 feet for the four stean generators. All these will be exanined ultrasonically for the preservice baseline examination and during the inservice inspection interval.

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

3.3.2 Circumferential Welds - Secondary Side i 'Ihere are 5 circumferential seam welds, totaling 198 feet, or 792 lV*

  • feet for the 4 steam generators. A total of approximately 36 feet of f our velds ull t be ultrasonically examined for t.he preservice haseline 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 j
  • best effort basis for the preservice baseline and during the four in-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.

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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-ll4 page 9 of 23 Rev. 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 leakage Il 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.

' ~1 ti 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 main support pads are secured to the steam generator field support

..)

.h system by high strength bolts.

3.3.7 Interior Cladding After cold hydro or after the hot functiona l testing has been conp 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 preservice j baseline examination.

AlI these wilI he examined again during the inspection interval.

l, 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 average wa11 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 ormed in accor<iance with th" Summer 1976 Addenda of Section XI.

Sg The exaninat ions conduct ed during the firnt inspection interval shall be perf ormed on each nt ei::1 generator. Examinations in i second aed nubsequent inspection intervals vill be from one I

g stean generator.

Examinat iono conducteil during the first inspection i nt:orva l sha l l be perforued on 6 percent of the tube in each steam generator.

V 1:xaminat ions in the second and subseqeent inspection interval, shall be performed on 3 percent of the tubes in one s teem genera tor.

, All tuhm uith *olevant indications great er t han 20 percent of the l neminal ea l l thichnew shall be included in those tubc3 nelected for ree:;a:.:i na t ion .

't b

-) _9_

l SI-114 Page 11 of 23 Rev. 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 inspections j shall be performed at 1- to 2-year intervals. If in these examinations no more than 10 percent of the tubes examined exhibits either additional degradation (greater than 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 examined 3
  • 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.)

l

  • and one outlet nozzle (14 inch I.D.). Two nozzle velds vill be ultra-3

- a sonically c: a m i n ec' ror the preservice baseline and during the four in-

  • 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 <grally welded support attnehmente per vessel. Two

  • nupport pad-te vesseI weIdr vilI he 1iquid penetrant tested during l

w the prenervice baseline and for the four intervals. A total of one jg* support vill be inspected during the first incervice inspection interval.

The nupport pad in fabricated frem RS, SA-240-TP-304.

3.4.4 Presnore 1:et a ining lio l t ina The thannel flan.oe ou each vessel incl" den 36 studs (1-3/8") uith i

  • n o t. t . A tetal of 36 nLuds and 7? nuts - 'll be vinnally examined lV** durinp, the prenervice ba se l i:u- and for em b inspection interval.

A t ot al of 4 ntudn and 8 nuts shall be ultcasonically examined for 3

  • the presa vice baneline and four intervals. A total of I stud and
  • 2 nutt shall be ultrasonically examined for the f i r n t. inspection l

'

  • interval.

The ntedt and nut' are f:tbrica t ed f ro.n SA-193, GR. P.7 and SA-194,

.)Q i GR 2il, respec t Ively.

1 4

SI-Il4 Page 12 of 23 Rev. 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 welds I are assigned identical weld numbers as the respective nozzle va safe-end to piping welds. ("SE" suffix added to nozzle-to-safe e 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 the scope 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 pipe connect ion velds 6 inches in diameter or mil ler sha l l be liquid v peper r: nit e::amined f or t he lireservice baseline and inservice in-

! spection 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 the

, circenferential joint) will be extended to include at least one foot e r . ie longittulinal weld (s) which intersects the circum-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 i noted.

i i '

1 f

9 1

1 1

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 ultrasonic or 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. l

W <

ach system is entirely ctainless steel.

In Appendix.A, Table A lists the pipe size, number of -

! velds, scheduled Junpections, and type of examinations.

v There are sone class B welds subject to examination.

Approximately of there welds will be examined during g

  • the first inservice inspection interval and welds  :
  • during the four intervals and for the preservice baseline.

5 In Appendix A, Table B lints the weld size number of welds, scheduled inspectionn, and type of examinations.

i 3.5.2.5 Upper !!ead In ice tion Pi ping (UllI) 3 There are some class A circumferential welds which re-quire nitrasonic or liquid penetrant examination. All

[

of thene welds will be examined for the prenervice bane-y line, and approximately 23 percent of these we:ds will be examined during each innervice inspection interval.

9

~lhe ent tre system in stain!cs< nte61 except for the lower portion of each Ulli auxiliary head adapter which is Inconel.

k In Appendi> A, Table A lists the pipe nLze, number of ucidn, ncheduled inspections, and type of examinations.

l t 3.5.2.6 11a i n Steam

, 'lhere are some class B c i rc u.,ferent ta l veld s nubject to

  • exam inat ion. /.p p r o x i m t e l y velds will be exauined for

'g* the preservice baseline and during the four int ervals. Ap-w

  • proximtely of thene welds will be examined during the

}

first innervice innpectinn interval.

e 1

The entire system in carbon steel.

.! %,,,,/

in Appendix A, Table n lirts weld size, number of welds, cchedulc d inspectionn, and type of enaninationn.

i 4 TVA intends to terminate nain ctram clans B on eac.h main 3 uteam loop af t er the tS I V (I CV l--4, 1-11, 1-22, 1 -29) for bareline anJ ISL purposes. 'th i s is consintant with Re-1 p,nlatory Guide 1.26.

> %d s

I j

SI-ll4 Pa ge 15 of 23 Rev. 5

3. 5.2. 7 Feedwater a

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

D The entire system is carbon steel.

In Appendix A, Table B lists the weld size, number of welds, 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 purposes Th 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 and larger sha ll be ultrasonically exanined. Class A bolting less than 2 inches sha11 he vinua11y examined.

Class B pressure retaining bolting larger than 1 inch in d'ameter e shall he visually exanined in accordance with Ik'C-2400 and tables

  • 1h'C -2520 and n:C-2600 for the preservice baseline and each inservice A interval. Ten percent of the pressure-retaining bolting (or 2 holts A or stud. uhichever is greater) in e.ich joint selected for exanination A

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 <;upport Components (Includen valves)

Class A intq, rally welded supports shall be ultrasonically examined for the . enervice baseline and during the ISI intervals. Support component: shall be visually exanined for the baseline and during the 131 interval.

Integral'y walded supports of applicable class B piping system co;; pone n t : 1.ba l l be surf ace exar ined for t he preservice baseline A and during the ISI intervals in accordance uit h Ih'C-2100 and Ih'C-

  • 2411. Ion-inter, rally velded support and hanger:. select ed for e: w ination in accordance ei t h 11.'C-2100 and i t'C--24 ] ] will be visually
  • exanined for tbn baseline and each ISI interval.

Support: an 1 hanger:. or applicabib cicus C pipin", syrtem components

  • specifjed in II:n- 2600 sha l I be v i .;na 1 l y exa n i.ned ,

l'n le s - a condition exist.s which hould nerit a detail record or the enud it ion , only a choeholt shs t record vi.ll bu nain-b./

  • tained verifying visual inspection of supports and hangers.

3.6 pem p n 3.6.1 l> actor Coolant Pumps (4) i 3.6.1.1 presunre "-taining . Bol t ing b.d The main f lan:," on each punp inc lude- 24 holte (4-1/2 inchen).

SI-Il4 Page 16 of 23

, Rev. 5 1

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 l 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 tCasings TVA intende to use shop pump casing visua1 inspections l in lieu of the on-site preservice baseline visual in-j 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 Flywheel A t. approximately 3-year intervals each pump flywheel shall undergo an in place ult.rasonic examination of 1

arca< of higher <,t rem c one n n t ra t i on a t the bore and

}

  • ke yua y. A conplote in place ultra.onic examination V nhall be conciucted at approximately 10-year intervals I along uith a nurface ex wination of enpased surfaces.

4 The flywbeci consists of two plat en, appro cimately five inches and eight inches thich, bolted together. Each z

  • plate it fabricated froa vaccum deganned A-533, Gr. E, J

class I steel.

1 3.6.2 ItitR rumpn (2) s 3.6.7.1 Prensure Iterainin:t Bolting

'l he nt uf fing box ext ension to pump casing connee t f on

't includen 24 st uds (1-1/4 inch) w* th can'wrn and nuts.

  • A total of 24 studs and nut;. shall be vinually exanined g,
  • for the preservice baseline and for each inservice inter-i i
  • v,i l . A t o; a l of 3 .Lud> and nut nhall be olt rasonically exrmincd during the four inter vals and for the prest'rvice
  • lonelinc.

r,I s

j y TVA plans to perr,um the vinen1 inspectionn.

1he ;tudo are f abricated to SA--193, GR. B7, and the nuts t o S A- l '3 4 , Cr . 21! .

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