Text

Rev 1 to TVA Employee Concerns Special Program,Undersized Socket Welds on Safety Injection Sys
	ML20214V018
Person / Time
Site:	Sequoyah
Issue date:	11/20/1986
From:	Bateman R, Russell J, Stewart D; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20214G966	List: ML20214G963; ML20214G989; ML20214T991; ML20214U124; ML20214U174; ML20214U216; ML20214U247; ML20214U308; ML20214U341; ML20214U367; ML20214U384; ML20214U415; ML20214U473; ML20214U502; ML20214U520; ML20214U550; ML20214U625; ML20214U639; ML20214U689; ML20214U749; ML20214U779; ML20214U814; ML20214U843; ML20214U860; ML20214U882; ML20214U924; ML20214V018; ML20214V037;
References
	WP-20, WP-20-R01, WP-20-R1, NUDOCS 8612090499
	Download: ML20214V018 (62)
	v • d • e

.

TVA EMPLOYEE CONCERNS REPORT NUMBER: WP-20 SPECIAL PROGRAM REPORT TYPE: Welding Project REVISION NUMBER: 1 TITLE: Undersized Socket Welds on the Safety Injection System REASON FOR REVISION: N/A SWEC

SUMMARY

STATEMENT: N/A PREPARATION PREPARED BY:

Original Signed By R. M. Bateman 08-25-86 SIGNATURE DATE i

l REVIEWS PEER:

Original Signed By J. E. Rose 08-25-86 SIGNATURE DATE l

TAS: TECHNI IEW ONLY -

0h h

/

SIGNATURE DATE CONCURRENCES Original Signed By CEG-H:

L. E. Martin 09-12-86 mk Il-20 -8C SRP:

SIGNATURE DATE SIGNATURE

DATE l

APPROVED BY:

"NYh N/A ECSP MANAGBK DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)

SRP Secretary's signature denotes SRP concurrences are in files.

2242T 8612090499 861124 PDR ADOCK 05000327 P

PDR

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WELDING PROJECT

.'A EMPLOYEE CONCERN EVALUATION REPORT REPORT NUMBER: WP-20-SON. R1 DATE 08-26-86

SUBJECT:

UNDERSIZED SOCKET WELDS ON THE SAFETY INJECTION SYSTEM C9NCERN(S) CONSIDERED: SQN-6-008-001

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OC, WP PkEPARED BY N84 OC, WP REVIEWED BY

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9 as[o, 8 f 8S QA, WP REVIEWED BY

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CEG-H, WELDING REVIEWED BY

/ f PROGRAM MANAGE APPROYED BY i

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j-Revision 1 clarified the review of previously conducted reinspections. Par. Senior l

Review Panel cosaments on 8/19/86.

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EMPLOYEE CONCERN

SUMMARY

SHEET.

Report Number: WP-20-SON, R1 Report

Title:

UNDERSIZED SOCKET WELDS ON THE SAFETY INJECTION SYSTEM I.

CONCERN CONSIDERED: SQM-6-008-001 II.

ISSUES INVOLVED 1.

Undersized socket welds on the Safety Injection System in Accumulator Room #5, Reactor II.

III. STATEMENT OF CONCERN / ISSUE VALIDITY Validity: Y X

,N Substantiated: Y X

,N IV.

EFFECT ON HARDWARE AND/OR PROGRAM None (effects of hardware and program were previously evaluated per NCRs 2398 and 2630).

V.

JUSTIFICATION:

m There bas been'reinspections, repairs, and evaluations performed on i

undersized socket welds per NCRs 2398 and 2630 on the identified system.

i l

The locaIion stated in the Employee Concern does not exist.

RECOMMENDTION'AND/ORCORRECTIVEACTIONNEEDED VI.

None l

VII. REINSPECTI.N NEEDED: Y N

X O

VIII.

ISSUE CLOSURE l

l Closed based on this repart.

l IX.

ATTACHMENTS 1

1.

Text of Employee Concern 2.

NCR 2398 3.

NCR 2630 4.

Report Number SQN CEB 8107

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Page 1 of 1 01300 l

4 s'.

EMPLOYEE CONCERN

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Report Number:

WP-20-SON, R1 Report

Title:

UNDERSIZED SOCKET WELDS ON THE SAFETY INJECTION SYSTEM I.

SCOPE OF EVALUATION This engineering analysis covers the following SQN concern:

SQM-6-008-001 II.

ISSUE (S) ADDRESSED BY CONCERN The concern was analyzed to determine the issue voiced by the concerned

~

individual. This issue is as follows:

Socket welds on the Safety Injection System in Accumulator Room #5, 1.

Reactor II are undersized.

III.-. CONCERN VALIDITY OR SUBSTANTIATION Construction NCRs 2398, 2630, and the final 50.55(e) report j

(A17 810406 022) document the identification and resolution of undersized socket welds at SQN unit 2.

Corrective actions te. ken l

included:

' r Development of a sampling plan and performing reinspections.

1.

An al' tie ^rnate weld size criteria was provided by cae Division of 2.

Enginiering Design (EN DES) based on revised criteria for weld size calculations in ANSI B31.1, 1971 Edition, which clarified fillet size. for socket welds to be calculated at 1.25t minimum nominal pipe i

wall,t.hickness.

All accessible fillet welds that were reinspected and did not moot 3.

this alternate criteria were repaired by adding appropriate filler metal and reinspected in accordance with the QA Program after repair.

EN DES evaluated on a case-by-case basis those fillet welds wnich 4.

l were not accessible for, examination using the worst case of 96 l

percent of the fillet welds that were found to be undersized.

l Based on the results of these sample reinspections and evaluations performed on inaccessible walds, the undersized sockat weld conditions were resolved.

O Page 1 of 2 01300

1 WP-20-SQN,'R1 A detailed review of the weld mor.itoring computer program and construction weld maps for the unit 2 Safety Injection System indicate that Accumulator Room #5 for Reactor'II does not exist as stated in the subject Employee Concern. A detailed review of weld maps determined that there are approximately 479 socket welds in the Safety Injection System located in all four Accumulator rooms within Reactor Building unit 2.

(

NCRs 2398 and 2630 document reinspection and repair of schedule l

160 socket welds for numerous unit two piping systems. A review l

of these NCRs as they relate to welds on the Safety Injection System lR1 (SI -system abbreviation) indicates that all accessible socket welds l

were reinspected in the Accumulator Rooms and 15 welds were repaired l

due to undersize conditions. NCR 2398 states an additional sampling of 170 welds in the Safety Injection and Chemical Volume Control System revealed 12 wolds to be undersized by 1/32-inch - 5/32-inch on one leg only (a detail listing of these welds are not available to account for the specific numbers within each system or in the Accumulator rooms).

In summary, this issue has been substantiated and resolved based on the following:

1.

NCRs 2398 and 2630 identified the subject concern and implemented corrective actions to perform sample reinspection for accessible welds and on evaluation of inaccessible welds that were within the identified system and area.

i.

2.

The subject' concern does not sufficiently identify a definite location of undersized socket welds.

~, '

c.

This issue'is closed by this report.

.s l

l Page 2 of 2

u q 3 5 Y D r^h

. s 06/.18/86 (EMPLOYEE CONCERNS)

PAGE:

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, 15:14:47 f *. 'AT ISSU PRIORITY ORG OTC EGG INSP SD RD GD Q -- ----E PLANT 10 ------CONCERN-------

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565

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SOM-6-006-001

!' i-KEYWORDS:

WELDMENT QUALITY SPECIFIC

' PROB: WCMHY b"

WELDS ON PIPING IN ACCUMLATOR ROOM #5. REACTOR ll,sSPECIFICALLY SOCKET WELDS OF THE SAFETY IN.:ECTION SYSTEM, ARE UNDERSIZEO. NUCLEAR POWER DEPARTMENT CONCEAN.

i N3 FURTHER INFORMATION IN FILE.

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STAT:

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TECHNICAL COMMENTARY:

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inspector noticed scane adjacent schedule 160 reactor coolant (RID Hanifold F1 ping).

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Ibnconforunce Descriptions continued l

Subsequent inspection of these velds and others in the same aren

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on one leg only (other leg sizes varied from correct size to 1/8" l

oversize). Dased on these findings, it was decided to reinspect i

all socket velds in the RfD manifold piping. This reinspection revealed approxtrately 109 of 385 velds to be undersized on one 1

I leg only (enzimum of 7/32"--one case only), while IB othere vero l!

l undersized on both legs (vorst case vaa 5/32" x 1/16" undersized).

i An additional sampling of approximately 170 schedule 160 socket I

welds in the Safety Injection and Chemical and Volume Control lf'

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systems revealed 12 velds to be understzed by 1/32"-5/32" (5/32" on one veld only) on one leg only.

i Apparent cause of discrepancies was the ' failure to inspect as ll thoroughly as necessary. Most of these velds have only a portion l

that is uMersized. The inspector apparently failed to measure I'

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G. L. Wade, Construction Un':Incerin; A 50ctsto, Mcchanical and Welding FR031 :

%l li.:poction Unit, Scquayals'l:ucleat float. CC::ST -

DATI: : Septc:nber 3,1981 f

1 1BP 8ttiut;cis SLtVOYAll 1:UCLI: Alt TLAl.T U:llf 2. ECit'S 239S At:0 2630 i

I I

BEFERE!CC: Hemorandum fre.:2 P.11. Csntrcll to C. C. Stack dated liay i

f 22,1901 (SYP i:10526 047)

[ l f

As on alternato to re-prg::Tro testil. rocket-welded pipo joint: which have had wold buildup ci fillet wold: to cerrcet diner.:1onal deficiencies z'

discevered af ter the = fate:a pt::urc to:L, the following were vecified:

r; 1.

There was no evidence of Icsksr,c et: ring the system pressure test.

l 2.

The uciding was perfor:*.cd by qJalif'cd t:clCere u:Inc qualified procedure:. (Docu./.r.ted cn repair check lists, ALL:chment A to L*-7).

3.

'lho curface of the c c;il. ted 1:.:ld ti:!)Jup va: exsul;;cd by the 11guld penetrant method in :ce..rdance with I.'.::I !!31.7. (Cocur.cnted on repair 1

check li ts, Attachr:,a; I. to L' 'i..ad IT-76).

l 4.

B'stiydro wo: perfctr.'t..n all 1: id re;'.stra thst could not be proved

'1 that, fillet si:o wa: 1/U md 1,rcLt.cr.

g q

g 5.

Each.~ropaired t:c1J : et.he ra:1uire.r.::..s en i.:.31-l'-31.1-Is00, i

i Iaracraph 137.6 (IniL101 Scryic3 Les% Te:L) decur..cated on (?crl:

a r}3n s.1823.

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CONST (4) t

0. C. Staalt, Project Nnager, Sequoyah Nuclear Plan,

t mnager.

3. V. Cantrell, Sequoyah and Matts Bar Destan Projec s 204 CS-K IFEB 4 Igel SZQUCT! All INCLEAR F1. ANT 14CR 10. 2398' i,j)7

.. ~

':g l ton dated November 19, N'.

Pleasa refer to my asemorandum to John A. Rau s 1980 ($WP 80112% C14).

recorraended. This

/,

NCR has been Disposition of of the subject NCR shall be as A2 E III. This disposition meets the requirements ofdverse to quality as defined in upgraded to a significant condition aDrawing revision is not required.

' ~ n 2--

Dt IES EF t.26.

Originst Slaned br It.W. C ant r all R. W. cantrell reen,y JAR:DJE:CG h

E. C. Dessley, W12B26 C KR. A. Costner, W11D190 C-K, w/ t p

Attaeninent con A

H. H. Culver, 2ti9A'HDB-K e

HIDS, E4837 C1K. w/.1 H. H. hall, E'[D24 C KJohn A. Rauls}on, W10C126 C K H. N. Sprouf,e W11A9 C-K

')

S.

e E31027 16

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Tro gTAtts covenx> csr SWP '8]. 0 5 2 6 047 fsO.[:W(;. '..'

8 Jemorandum i

rtsnessez vattty Aurnoniry c,m

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k#.lf:.'3'

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' TO 7.'

C. C. Stac'.. Project Manager. Sequoyah Nuclear Plant CO.NST (3) 8

~o.

b T8' i

l-.;[;,.#

1.11. Cantrell. Sequoyah and Watts Bar Design Pro *ects Manager. 204 CB-K-

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I DATr.

Itay 22.1981

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EUBJECTs SEQUOYAll NUC1. EAR Pl. ANT 13 TIT 2 - NCR'S 23')8 AND 2630 l

. g.:.: ?.;

l g : p,. ;;...,.;

.;...,- q i

.,,rt

.4 ;

As,an alternative to re-pressure testing socket-velded pipe joints which

U.M f,'] i lQ 4 4',

l@ '[. jfj $.!>

W4.f, have had weld buildup of fillet velds to correct dimensional deficiencies gt.; * '.. ff.

ig~ *-).

.4. 9.;2.. ' '

discovered af ter the systea pressure test, the following requirements shall be verified:

j 7"(.....'.' {f

\\

3 There was no evidence of 16akage d'uring the system p,ressure test.

i 1.

j

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l i

2.

The velding was perf ormed by qualified welders using qualified

.' '.-('f;..J '

I.

1 p ro c ed ur e s.

...: z. :

.';M:/['

3.

The surf ace of the conpleted weld buildup was exanined by the liquid

.)

penetrant or magnetic particle mathed in accordance with ANSI B31.7.

U.l

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i 6

.ut

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"=

w 7

5 4.

Fasitive controls shall have been provided to ensure that'vald repairs

?

l1 7

are made only on tillec welds 1/8 inch and greater.

,.t,,,,

+

I ur MA"

~

3.

Each repaired veld shall meet the requirements of ANSI B31.1-1930, Faragraph 137.6 't, Initial Service f.eak Test).

M'_

k This position genera'11y conforms to ANSI B31.1-1980 Paragraph 137.1 F M SE N (leak test requir'ements), and a draf t code case entitled " Weld But1 dup l,l Af ter Pressure Telting,Section III. Division 1 Class 1. 2. and 3 I

s Co ns t ruc t ion,"

resently under consideration by the ASME Code Cor.nittee.

p

?.

s n

J.t.,;

m/ cL-co-h

/1 R. W. Cantrell

.h

?

.T RVCtRCPtDB ces R. O. Barnett, W9D224 C-K

[lllHD IROW BESI E. C. Beasley. W12326 C-K A1MLABLE CQPI gN R. A. Costner. W110190 C-K f

J. H. Ballentine. Sequoyah NUC PR

, Af H. H. Hull, E78 24 C-K

h MEDS E4537 C K t

v J. A. Raulseon, W10C126 C-k

/g H. N. Sprouse, W11A9 C-K,

.~

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Parte 12 of 15 fs j

lO' I

A27 8104 0 6.0...e t

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7 400 Chestnut Stroet Touer II I

A c

Aori o, i,ii 6

y y ____

,e f

Iluc 1

L Hr.)a es P. p Pe111y, Cirector f

4 *ang f

ffice of In/pecticas and Enforce nt l

i APR 20193; U.S. Nucle Retulato y Cor. mission Regico Il Sutt7 3100

!!!Eti.*,'$r'sI"huiu f.....ff"FL m

g E BGHEi j

==Dear

. O'Reilly:==

8 I

~5E0VOYAH HUCLEAR PLA!.T tmIt 2 - FAUT.TY FILLET LT1.t3 NCR 2393 AND 2630 -

ylt;1t, bet 0;T The subject deficiency was initially reported to TRC.0IE frSpector h

R. V. VrtrAt on November 7,1980, in accordanes with 10 CFR 50.55(e) as MCR 2393. Interin reports were subsitted on Decenter 3,1930 and Te bruary 11, 1951. Enclosed is our (tr.a1 report.

If you have any questions concerning this astter, please get in touch I

with D. L. Lambert at FTS B57 25S1.

I i,

Yery truly yourr, TEWESSEE VALLEI AtTIH0AITY gituk0 ggni BlSI-aqtt1BLECOPI 1

.rj L. H. H111s Manaser J.

!*uolear Te,tulation and Safety i

s Dti.:DAK Kell

d

f Enclosure

. h'

J,

I ! y, t

N 5

'. i ect Mr. Vio)or Stellp. Director (Enclosure) 71: :-

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Office of Ins eation and Enforce:entJ sv; me G'd U.S. Nuolear egulatory Corsission n'jy,Rh k.

g Vashtr.aton, DC 20555

,b.

cc (Enclosure):

qq 3 'g)

I l

ARMS, 6110 CST 2.C A. V. Crevasse, 401 U33-C i

M H. N. Culver, 249A HBS.X

--. g!,I' q-'LY

'O a.I'

,u E. rord, sequoyan-rinc

~.T' e upC lj ff. J. Creen,1750 CST 2 C

- d*,',*,,8,-. -

~#

/

J. A. Baulaton, W10C126 C.K

'.7.' r * *

T.-

.2 H. 3. Sanger, Jr., E11833 K

l i

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,C. C. St ack _Sequo sh,

0

--7 * *3.*.,;,

j p

f. A. Szczepanski, 417 LDD.

8

.(

C00AD!t'ATIDI

5. Stout /E!! CE5

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DICLfcung

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SEGUOYt.Il IluCLEAn PLAtlT U:11T 2 '

l FAULTY FILLF.T WLD".

F 1

1 CR'S 2T1D IJ:D 2630 1

10CFR50.55(e) l Fit:8L R* font Description or Dericice.cy i

i k

During inspect 10a of reactor coolant piping for arc strikes, the irtspecter nott:ed ser:e adjacent schedule 160 Reacto.- Coolant System socket (fillet) welds that appeared to be analler thsn requ! red.

Furtner Anspection revealed that a significant percentage of 2" schedule 160 tillst welds were undersized. Therefore, in order to determine the total scope of the probles, the following reinspection e

program was implemented.

4l All acce:sible 2" c':hedule 160 sockat welds were reinspected.

h Approximately 25 percent were undersized. A ssrpling plan for the k

reaminder of schedule 160 socket welds was developed as outlined in 5

11tL-STD-414. "Samplir.3 Procedures and Tables for Inspection by

}'

hl 71 Variables for Percent Defective." This is a reference standard in RDT M

Standard F2-TT, " Acceptance Samplir.g Plans." The welds were segregated by pipe size (1/2", 3/4", 1",1.5") into inspection lots of 100 (an 2

S Inspection lot is defined as a specific qaantity of stallar materials or units on which acceptance sampling is to be performed). The welds.

I t-if to be inspected in each lot were identified by using a table of randoa j

N numbers from RDT Standard F2-7T to select a random sample of units 4

E from each lot. A total of 20 wclds per lot, as required by Table 3

(~

(Sample Stre Code Letter F) of the ril standard were randomly selected pq and reinspection of, tpese welds was perforzed. For those welds PDD

'7

' inspected under this sa=pling, a percent deficier.t rate of 4.0 percent g

was established.g According to tho.section entitled " Sampling Risks p_

-T-- *m I.)

and Operating Characteristles (OC) Curves" in EDT Standard F2-7T,

~'

~

" Studies have shown that 100 percent inspection under opti=un NUM P

conditions is only 8(to 95 percent effective in separating bad g

proJuct from geh product (in the absence of co pletely automated L

[

pipe is planned.I{i". Therefore, no further inspection of schedule 160 r

inspection cethods)

P h

A sample of 480'sege'dule 40 and do socket welds, which is N(

)

appronicately 2.5 percent or the total welds in these schedules in "g-

'f unit 2, were selected for reinspection. Seven welds were found to te l%

i deficient. This is a rejection rato of 1.45 percent. Therciore, no 4

further inspection of schedule 40 and 80 welds !s planned.

l A previous sampling of 400 schedule 160 socket welds in unit 1 l

.W revested only ons weld underst:eJ on a portton of ona Icg only.

The re fore, there 13 no indlestion that this a blen exists for unit 1.

7, lh n

rLutoisoid nts i

ATAILABLE COPT l.}

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The apparent cause of this conditicn is a fathJre to thoroughly inspect the complete keld since stany of the deficient welds are undersited only by 1/32" on a portion of one leg. The inspector

{[

spparer.tly failed to measure the smallest portion.

Safety Irplicati g A large number cf schedule 160 socket welds in safety-related systens l

Vere undersized, which might adversely affect the strength of the weld. Thereforo, if this condition had recained uncorrected, nu:sercus leaks or small pipe breaks may have resulted (especially during a seismic event) which ray collectively have affected adversely the I

operation of that safety-related system.

i l

Corrective Action Undersized fillet welds are being evaluated to the alternate weld size f

criterion (included as Attachment A).

Those welds teeting this criterion are accepted without rework.- All accessible fillet welds.

i5 s

which were found to be undersized, and shich did not meet this criterion, will be repaired before fuel load by adding weld metal as

'- afpropriate.

I 1

In addition TVA'c Division of Engineering Design ir evaluating on a case-by-esse basis those fillet welds which are nct accessible for examination. ' The, worst case of 961 of the fillet waads which have been found to be underst:ed is being used to evaluste (i.e., 951 of the welds that were found to be underst:cd, are unders!:ed by less than the l

l amount used for the evaluation) the reserve stress carrying capability 9

of each socket, in order to verify that the welds are adequate to perform the intended' function. If the design calculations do not then show J

adequacy of *these Inucessible welds, the effects of weld failure on I

plant safety will.te ev21usted. All inaccessible undersized fillet l

I f,

welds found tol.h3ve a negative effect on plant safety will be resolved t,efore fuel load.(, Welding inspectors and craf ts personnel have been retrained with emphasis placed on fillet weld sizo requirements. Lead i

I

' welding inspectors have been instructed to increase surveillance of the y

g Work of inspectors assigned to them.

N flLutO FR8W BEst ATALLABLE CDPr lj I

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D r.6,w.iin,- O i, ii.nia, l L I i

4. Tvm O o. a D r.nor.

O o. rat O o x um.ai.u.a eoir-_Undernina Bseket Wele M i ' n e miruoa, sch.aut a..cs.t v u.. 4..c,a.a oo ist. m t.. fl 1j i N 1 810917A0201 y$ Addition.1 sampling of Sch.160 socket velds as referenced in It was decided to 4 H.ac.ntwm.nce oeurioten. 4. reinspect au 2" Sch.140 socket we1ds, and to us, a sampling p1.n for reinspectico or f -l il=8vo.Wa C.ws4 NCR 2396 has been performed as follows: lf. j n.m.pe.u o or.u...... m. 2 e.a. x 0 % t.) p ts. oe... u.. or sos. a o. 14..

~

} k"*===*:"A ":7lt.u 4 I'm. "Ti.. ) "M-M r Detailed as on NCR 2398. .MW i k Acti.a n.gos,.o t. Prw.ni nuverence. ,1 to yhinloppen:1pyg, Mf /E/R9'd M77M'& A 31 9/ 0 9 el J32 l l,- nen,~c.b N tit

J9Am_e.i.

r-2 n [a N Cl*, "*ST,fy'O' %fPi".J@* Of:::Pl."**o'*^'E"'Is. h oes /) f neh%-u.,,e,.,L... 4). TLK 3-2-el o.u go~ io.m% l o,o -o D a ax -~ C h.a $ d.d W(CEBBA%29 LEQ Qln~a-{ g ke 0 h ? 8 M ~ Adh vs.e w o + r..J o, -qa.% n junu m y 7 e//' M/-5A-o.t. ) o- ,-o.,, - n .- ~~..,, soi. av. Om $ dA4A-7h1n l

o..

a'v., Qu CL c.DN6d d. 8g90960 1 1 ,, a n - ,.. c -i., ? v - ~ c.,, ~ u c, -. i mu n..= m u,, t{ _,=== t - u -. -- oc. p w m,oc

=='2 MOM-3.".'s *"'d ,m un ] 1; A'E.iC M U ZI'*~" '8Ea!a,iucm me s v= s een er eaet.s. tse . asme en-6.e 4 A

f. ~ - -. ~.... e .,. 3.... : ;5 - . t, O,., r. f.,.C'i;l it, ' e 3 ** I i I

- - - - helate NONCONFORMING CONDifl0N R1 FORT

.j7 , [.k N. /. Sequoyah Nucleer Plant CONTINUATION PAGE g-t;. ' 7-A WAR K5 h.....,.g 6 welds has been co=pleted, and all of those identified as deficient have M.,2,l[ip f been repaired. Those sites other than 2" were reinspected by a sampling .= s - ...,r. .k;MI: plan as outlined in lHL.SID-414 "Sanpling Procedures and Tablas for p y $i *,;)I..t Inspection by Variables for Percent Defective." This is a reference Q standard in RDT Standard T2-7T, " Acceptance Sam:pling Plans." The welds rs;' ic' :.. T l were segregated by pipe sire (1/2", 3/4",1",11/2") into inspectico

i'/ 7' ['..,, y..'F.

i. lots of 100 (an inspection lot is defined as a specific quantity of

l: : -

sin 11ar r.aterials or units on which acceptance sampling is to be ' Sc j.H Q' l performed). The welds to be inspected in each lot were identified by /.8 % h /*.': >;. t using a table of randas nus.bers &cra RD2 Standard F2-7T to select a %% $ C 1*t^ ' ( rand:ra sample of units from each lot. A total of 20 welds per lot as "1 $'3.'$h required by table 3 (sanple size code letter F) of the mil stasiard were Q,j,.. ". t/. rand:saly selected and reinspection of these welds was performed. For i t. those velds inspected under this sartpling, a percent defective rate of 4.0% was established. According to the sectice titled " Sampling Risks E and Operating Characteristics (CC) Curves" in RDI Standard F2-7T GEQ f " Studies have shown that 100 percent inspection under optimans coniitions gg g 9 is only 85 to 95' percent effective in separating bad product fr:ma good product (in the absence of completely autanated inspection methods)." of all lots sampled, a total of 11 lots were acceptabla, and a total of i 30 were rejected. All welds in the rejected lots were reinspected. I' t A total of 5,405 Sch.160 socket welds have been identified. Of this j total 1,161 have been rejected for insufficient fillet size. Our recactnended disposition to.r these 1,161 welds, other than those [i dispositioned on liCR 2398, is shown on the attach:nents t; this DCE. Three hundred and twenty nine welds out of the total of 5, leos have been i determined to be inaccessible due to insulation, pipe supports, beat ( tra'ce, an,1 pipe sleeves. Our rec:::ssended dispositi: 2 for these ] 'y inaccessible welds is shown on the attachments to this DCR. Welds are g lis}ed by categories of inaccessibility, t i M A' sample of !+00 Sch. 40 and Sch. 80 socket velds, which is approximately q 1p 2,1/2' percent of the total velas in these schedules in Unit 2, were select 6d for reinspection. Deven welds were found to be deficient, sai y repair procedures have been initiated for each of these welds. Because the rejection rate of Sch.1+0 and Sch. 60 welds retnipected la cxil7 r 1.45 percent, no further reinspection of these schedulas is planned. a y g, L 1 ,e I, ( t. i g y.t_y' ( M MW' p w g u s i J Y = y

l yym = _+ mm e meto .;_m,y. y p i m C .y s enrto sum ommatm. - sw '8011.24 014 1 Memora.nd um rtuntsser vAu.tv Attrnonrry l Q 9 \\ 1 l 9 -, 2. A. i.ois. . cue,,osias, ronioser, viocia c-x To R. v. cotreu, s.coya od v.tts zu nesign rroj.ct ne .r, 2cA cs.x I ? ruo= i ) 1 DATE : November 19, 1980 $13 JECT: SIqJOIAS IfCCIZAR Ff.AKT = N3tCCN70PXVICE RIPCRT (NCR) No. 2398 l m.f.rence zx ors-tr 2.26 Attached is the subject N3 for your review and approval. Please prepare = l a memorandum to G. G. Stack for a:y signature indicating the disposition of this NCR vithin $ vorking days. Tbe original NCR is to be attached to = this memorendtna with your initials in section 8 indicating review and 'j I approval; Include in the memorandum a statement cm vbetbar drawings are to be revised as a reruit of the NCR. g a.; w '} I P1 JAR. 17"" pv. i.--- ln n i '=- pi U_ ,gg,. Attacinent i cc: MIIG, IkB37 C-K t, )fU" ll; 17 81020 A0265 /l) e !& Q l E Dg' EfPd10203 290 .~.:.E i w.

n. v. cantre11, se, ora - d u.tts

_............,.., a c3.x x,4 L l:o J h, FRO 4

John AP Raulst,on, Chief Naslaar Iosinoer, W10c126 C-K

? 8 LAI2 : Janary 30; 198L sunJrcri srqJOIAH'IdCLMR FLANT - NGICat730MKCZ RDORT (NCR) P0 23h6 ? ^' .I f ,( s n \\ Attacbed is a memorandum to G. G. Stack for your signature giving the disposition of the subject NCR vith the original NCR attached. l k h{f f yApn 7 v ~.: 1 i g O.lE: & nI{} h Atta4 merA oas Qxp, FA337 c.K I e pv l O 1 y 4 a 7 n n,wu. u A i { a E-j. I L. s E , ';. = i a

l ., n. -,w

9 e, e, a t., o g

f ll. M~ i j 1 A27. 8104 0 6.023 / . I [c'g*~

E]

l f. t00 Chestnut Street Touer II, )] ,:f, M j s { ~~ April 3, 1961 i,j' uk"@M l -%ag h '2 )$ I Hr.Ja se F. e ly, Director 1 ffloe of In peot on and E force nt l Mgg l l, 1931 U.S. Nuolea Segu atory laston 1 Regico II Suit 3100 .bOJOct f,y I 1 ( '* 101 Harle ta St et Atlanta, Georst 303 j, ft.

Dear Hr. O'Reilly:

8 i,'.. SEQUOTUf NUC1. EAR PLA!.T UNIT 2 - FAULT! FIL1.ET vet,D3 NCR 2393 AND 2630 'j i ' \\*

FINAL ptPORT l

the subjoot defloiency vae initially reported to NRC-OIE Inspector R. W. Wright on November 7, 1980, in accordance with to CFR 50 55(e) as-l j j .l HCR 2393. Interio reports were submitted on December 3,1980 ano. m-rin _ _ i February 11, 1931. Enclosed le our final report. L fM_A Q> t 's,. n If you have any questions concernin5 this estter, please get in touch I with D. L. Lambert at FT3 857-25St. t '* 3 Yory truly yours, I I ~$ flLMED FROW 8[$T TENNESSEE VALLET AUTH0'RITY ~ AJAILABLE COPT j- 'i L. H. Hille. Hanager 44 .!!uolear Fe4ulation and Safety-t., LLL DAK:KIl Enclosureg']. 6 I I e

.:e e..

8,. col Mr.* Victor Stello, Director (Enclosure) 'itt..: - .5 + I Office of Inspeetton and Enforcement srvnvi " "'k U.S. Nuolear Regulatcry Commission jgg,"gyg Washinaten;,DC 20555 l 5 *g g. j 1

,1*,

oo (Enclosure): fpR 13 'Q] o.. _ ARH3,' 6110 CST 2.C l - - * ~. / l A. W;' Crevasse, 801 UDB.': '/",g y 1 O p 7* H. N. Culver, 2ti9A HDB.K ". "- Gu e =. - 's

'4

h.',"yC -.

1 E. Ford, Sequoyah.HRC l[ H. J. Creen, 1750 CST 2.C i 7,. r.:,-- iC

,e t

J. A. Bautston, W10C126 C-k I .,1,8';,',"l H. 3. Sanger, Jr., E11833 K t. ,I O. C. Stack, Sequ lo ah 6 ' ' ' * * * ~ T. A. $sotepanaki, 417*UDB 8 U. -- * .L, ---(' ,h

C00ADINATEDI

3. Stout /EN CES i

.m_.- l

- 6*****

. _. =, y . -... n

l ( y -sm m= ~ fksv-y _ - - L"M; mnmi-{ N 7 \\ 2p. wl O t*J 17.:. * ' ENCLOSUllE I i l g.- SEQUOTAll NUCLEAR PLANT UNIT 2 k q (

f, ' '

FAULTY FILLET VELDS P l t 7,, NCR'S 2398 AND 2630 ih i

s.

j 10CFR50.55(e)

,),"

FINAL REPORT . h.d= s _ Description of Defielency 8 f b'. During inspection of reactor coolant piping for arc strikes, the JIA{. inspector noticed sote adjacent schedule 160 Reactor Coolant System l I L d socket (fillet) welds that appeared to be smaller than required. ,ld! Further inspection revealed that a significant percentage of 2" l e 1 ,3 ', schedule 160 tillet welds were undersized. Therefore, in order to determine the total scope of the problem, the following reinspection q ; H g l l h*w,(g. t l program was implemented. i I g j t Y \\ t

Q.

All accessible 2" schedule 160 socket welds were reinspected. l li' .%j Approximately 25 percent were undersized. A sampling plan for the 1 s'

ft-remalnder of schedule 160 socket welds was developed as outlined laa i

l

d.*r HIL-STD-41ti, " Sampling Procedures and Tables for Inspection by o

Variables for Percent Defective." This is a reference standard in RDT 'i / /* 5 **,* Standard F2-77, " Acceptance Sampling Plans." Tho welds were segregated e by pipe size (1/2", 3/4", 1", 1 5") into inspection lots or 100 (an f i

Dj inspection lot is defined as a specific quantity of similar materials

,h cr units on which acceptance sampling is to be performed). The welds s ( ' ' 4 J*d to be inspected in each lot were identified by using a table of randoa ( . *

r. umbers fera RDT Standard F2-7T to select a random sample of units "8 (-.;*

from each lot. A total of 20 welds per let, as required by Table 3 k 3 1 (Sample Site Code Letter F) of the mil standard were randomly selected -[ ] and reinspection of these wclds sas performed. For those welds ppg Inspected under this sszpling, a percent deficient rate of 4.0 percent 'q {,,, was established. According to the,section entitled " Sampling Risks 'p g

and Operating Characteristics (OC) Curves" in RDT Standard F2-7T, W'0

" Studies have shown that 100 percent inspection under optimum i conditions is only 85 to 95 percent effective in separating bad i product 'fr' om good product (in the abschce of completely automated

.f '

t. ...J Inspectioh methods)." Therefore, no further inspection of Jehedule 160 l pipe is planned. q Ld L.s C 4 y l**. A sample of MO schedule 40 and 80 socket welds, which is 1 appresimately 2.5 percent or the total welds in these schedules in t 6lu unit 2,'ere selected for reinspection. Seven welds were found to be w de fici en t.' This is a reject!)n rato of 1.45' percent. Therefore, no y further inspection of schedule 40 and 80 holds is planned. 'a ,J A previous' sampling of 400 schedulo 160 socket welds in unit 1 (d revealed only cie weld unterstred on a portion of one leg only. j i) Therefore, there is no indication that this problem exists for unit 1. ..f l 'h .'fh a5 Illuto %Al Bisp QU8il copy $1 i ( ]i l 8 r s g i 9 i ? 1 .,? d j' I g hm .4. 4 ,o' ' t,M .t \\ i j '.t s g

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'f 0 0.16 6 3//G 'dt. U Z. '. ; '/8 '/L' h. '/1 - ' gh id " 5., b' I h 0170l ,[ bl j O.lil.. r i Bo a.33t .'/4 Vit 1 ' o.314 3l9 "/st ' u O 'tu l,.) ln.1tA rt n & ; '/s *;d.., m".. a N. (1) Thi.. fiht 19 d.Il nof Lc? Im L e 01 ROW gggy N Y... (2). Wild sIall k c. ~ fle i to ; co rtve.x i 1. ;. AI All All t COP T - p. h i 3 :C, 6i (

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tj' j j,1' I: r e g o,tr ed _

g[.h p). Nall,1-idekstess ' i y[., Ju % rod =;0,.'I8$. [N.[ .l.t ' d y.. ).. t i 4a.n.s n omeltel 8 h.* %5 twea su r ect s horlci - I; 4 I d.c k {;b, '.,l' O 'N J 'N q ' N lonyr; lh~ (rausaded ie ; Ile.lnlst/sojice.' *I '( ) : 'f Y = t'c vir'ed l, y = t. 4., m. n. m g s '. b '- h I. /, N h k ..w.. u.. m + j k h h 7h ~ 9 4 l s.< .nvm;: } ;. G?'f 2,3 0lp $..V L&:,A ?: n s ) Y O l, 11M i

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F, b -

,[d<4.WyA1e M i' - W E l r; p; M, i*. MN . ',. P s..gH.Q %W.'$@yMs..; ' i# 4 ~ 9 s e i g, y-., i 'f ' i e. d r,W F i ' w la y _-ym' _@;p4'(_bc.;9y _L7;ms = y .' 9e. p t ~ '- M,. - ' O. y t g,,y o :. 34i ,r- , p.,. M.N ;,,.. yi y, n. q : \\

l wu.se uM43g., 1'agu o uL leu 1Ei 7 , e d. e.. h ,,'D I dl. g {3t'$17to starts covenxutur ,7 g gqh, QLq %j hd ~ ij '. A Pw k..wmm.gh. @ew%j . 3 we w jpdem.orandum TENNESSEE VALLEY AUTIIORITYN d,Y 'p h d ;,73 3; gf.4-MMtEB2'81'0f0.6h020T 4 W l 'EM O T0" G. O. tack, Project Hanager,'_ Sequoyah,Nu'elele'P1E,Cbh3N[(k)Pl\\ [ ; .h.i ' br '- ,id f .p a .n Q& , '(1 4 g Q p ;; %.ag

qq ; or g

y ,i rams I (. R. V. Cantrell, Sequoyah and Watts,B Design,P, j acts Manager.'~. 20ti,GB. Lip,lij l / i ,jf. j i DATC-APR 61981

[ st'sJtcra SEQUO AH NUCLEAR PLANT,#0NCONFORMANCE REPORT (NCR) 630 -

RSIZEDi k MMC ii d{ ' d FILLE VELD 3 ON PIPE QN 810302,608).i Q I 9, @ y p <> V N 2.{ a l ~ 1: , y ('d.' ! Q.' b: The subject NCR is concerned with!the undersizing ofssocket; welds,on - 'd>b, l ? M T 2-inch and less size' schedule.'160 piping With ~ respect to;the code 5 <@' :#.I f (( 8 requirements.

p. ! l

?, L 1 A t i i '.' r From an analysis point of view an undersized weld could result in localized' ' W N {(le overstress. In the analysis stress, an intensification factor'is used for ['Y1 j s f 4 When the weld is undersized, a' larger, stress intensificationi', ' ; jl.i/ I f J the weld. 1 factor is required. .( .4.+ The alternate analysis criteria ~ is a conservative method'or. qualifying y:..,g-li9N+ M. t small pipes. However, it is not possible to provide.less,conservativeJ ' M, ; h s criteria cn a generic basis. ' Relier can,be provided on a system basis or

e r

,' b ' for specific locations in a'systee. Rigorously analyzed lines have. HJ.

MN

,., J . I Q'.hIf approached allowable stress 'at' specific location 6 Ccaputed stresses are f !'M Dj 1 available, and tho' actual weld requirements can be determined if. the QJ %,a ( l undersized weld locations are provided to'the. analyst.ti y%y,t+. y, ;t , ig, f, 7 h 9 .. i. ; ;.. v. 1 r..,

3 y

? Sections D and E of your NCR identify accessible, welds}, and'wa agree with ' jd fc; 2 '( g .j your recocasended disposition.

f. ), g' i

'yy j g Seo)1co G refers to welds that are temporarily inaccessible.'IYouri ii . 4.h i3 + ~ recocnenyd disposition is to reinspect as soon as they become ' accessible

[ 1[ g W

} and repair as required. This task should be completedpbefore fuel, loading. ' 'j ], g y u-j L g Section'.f states that approximately 75 percent of each weld'is ' accessible.

g 7

'l> ,f Later? reports from the field indicate that this is not.the case. This ( M askes'the welds in sections A/B, C,' and F inaccessible, welds.y ..p.. d ' f gy{t ~ (.. :V 'T,;f / % ' . Ct O r N 1-E' ',1,j ) Q[,h' ! ( Sequoyah and Watts Bar Design. Projects will locate each'of these welds on, 'jo i :.g the rigorous piping isometrio or. on the physical for alternately ar.alyzed , l, y, QJ pipe.. The Civil Engineering Branch (CEB) will look at each one on a case- ' ' A.h ) by-case basis and will see if the analysis has enough reserve stress so . 4g Dy I that it would be qualified if.the-stress,es were,1,ncreased,by afa or that pg flLU(D FROM,[sr ! -u u m, ' M ~.Wm r N 1 iS < 7G 00 D3.2Wr !!4 r. h. e L : T V E'3 10 l! ! 3. J< Tn f l. g i,, I l ,,a. ps: 4.: e 4 y o, m u ,. h [w$ [g[1% y;9 [; a 031082.04 Iy s ...; g. g : / .v n. w gy t...._ y

.s 4) mv-f-

i h sy .,ch ' q W Q. XS u g%'. %r. % y,- +; ': w w i by.,. p. v i ~. .te w nM3...Tp QM y.1 e 1 - 't l.;.

13. -

p p p,i Q. Q p g l,,, a y. g $ %. ], f l y @ p [ Q g .g..,v y y.g y. y y( y.7 p. 94gny r

+ w wm aanarr*MM M M19M3M% 1 .Fyi.. s s i 4. <v 4; ,4%@%%g,fi I. M V f,3,e...@ 9 (; (7 % 'f:y.;Q. Ft 'F, y h u s.i. M: tg 1# t "m" p " ~ ;. g, w.,. y > \\ 4 *, a t .' 2 ,Q ,}g

j: g,ggg T-j g f.g,.,,
l "?.T

, C. C. Stack

,$ W ' i ' ; ;. ; p! Q,,,~ s a-a x,, ,, g n l g d, g~g.y.L ,,W, y. 3 q j Q' "{4 : ! O; % ' -. -4 . April 6,1981 ". d V. .T ';*,,. \\. f. q k

sEquCYAH NUCLEAR PLANT - NONCONFORMANCE REPORT (NCR) 2630'($QN 810302 608) s 1

a s - e. -T .C' t,i L Q ' p,f ' '...AN. s, @7,i;'4 4qM. L P . ] .>. 6 < ;. .c g m ; ,', ', h -l,g g, q ;;. y s 1 represents the worst case of 96 percent;of the understred welds (froaW;' j :,; g t .p

3 cm

... v. a.m -o " [ E, .4V" i

section E) that were inspected.. If the point is ' qualified, no inspection [;.

i% -

l

, ;. p,

.,e, is required. , "* veld sites that will be acceptable.If the point will not qualify,'CE8 will provide a, series'of g f p, g y If 'the inspected ' weld does not meet. i b i r, these requirements, it must be repaired. The allestone for inspection andisM a k) p l MM U repair will be determined on a case-by-case basis. ,e the welds that require inspection was informally transmitted to your Ricky.J-]A package identifyin d'% 1 t (#_ g [- 4]

9. Hiles f rom our R. C. Pratt on April 3.1981.' LWe,y 'l disposition this.NCR {..* Q Rb Il%l((f')

wil .4 af ter receipt of your inspection data,fyy y ph ,l. 4.._,,. j',s ,.7q. QA Jpe s{Sy0, g, i

s. g.,

. __c p, h c,. 43, 3 , m 9

c'

,.. ; ' y" . Myy y*!h;p*y,' g t i I, [g ~% ' *f %. ; pl * 'j, n p!. ). Y: Q'o [.* G .t R., W. Cantrell ' ; pp. 5 ..d, h h f.' Qlz,, ~ I '.. ', d *(,,'$'K ? 5) ?I t8- ,g,y, l R08 JEM DCC ,11 'lI',. s . ( ces J. H. Ballantine, Sequoyah NUC FR [c] 'J;6' ,M. -'}. Q.U @ b.h

O t'

R. O. Barnett, W9D224 C-K (2) Q',' 'r "J 4..,, u J-G;I fqg' Nu, d o *.' UU M g I l E. C. Beasley, W12826 C-K lL M FN84 D R. A. Costner, W11D190 C-K , l.t 'e AIdll Aay 80'I ' ".p 'I ' [ d' c$ ? 9p HEDS, E4837 C-K q r e [hh 7,g + Mi b.4 c 2 . q :,..g.,c', H. H. Huli. E7324 C-K q(f ,t ,l ., y. ' h /p,;

e. v y,i ' '

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r 6::...., 3 tv7 ten T^rts C0vcRxHcief SWP '810 5 2 6 047 j Memorandum TElmESSEE VALLEY AUTl!ORITY 1 8 TO C. C. Stack, Project Manager, Sequoyah Nuclear Plant CONST (3) TR011 R. W. Centre 11, Sequoyah and Watts Bar Design Projects Manager, 204 CB-K DATE Hay 22, 1981 j 81MECTs $EQUOYAH NUCl.UR PLANT tlNIT 2 - NCR'S 2398 AND 2630 'a % f ?N if ? As an alternative to re-pressure testing socket-welded pipe joints which tr yd have had weld buildup of fillet velds to correct dimensional deficiencies discovered after the system pressure test, the following requirements shall be verified: g i h 1. There was no evidence of leakage during the system pressure test. 1 ( 4 1 2. The welding was performed by qualified welders using qualified [ procedures. r 3. The surf ace of the completed weld buildup was examined by the liquid penetrant or magnetic particle method in accordance with ANSI B31.7. { ,$,.,( 4 Positive controls shall have been provided to ensure that weld repairs are made only on fillet welds 1/3 inch and greater. } Y d 3 5. Each repaired weld shall meet the requirements of ANSI B31.1-1550 Paragraph 137.6 (Initial Service Leak Test). ,3, 3g l This position ge'gerally conforms to ANSI B31.1-1980, ParaBraph 137.1 JE ~ i [' (leak test ' requirements), and a draf t code case entitled " Weld Buildup I a After Pressure Testing Section !!I. Division 1 Class 1, 2, and 3 j Construction," presently under consideration by the ASME Code Committee. ta a. l t.',. m/ cuew y y )- R. W. Cantrell R L l RWCIRCPID3 i' N cc: R. O. Barnett, W9D224 C-K g ; 'fp,g. E. C. Beasley, W12B26 C-K fllfJfD TD M 8ISI j j R. A. Costner, W11D190 C-K 1,[Jj[gIICOPr kf J. H. Ballentine, Sequoyah NUC PR A. [-3 H. H. Hull, E7824 C-K .J HEDS, E4537 C-K V 't cv v J. A. Rauleton, W10C126 C-K M H. N. Sprouse, W11A9 C-K. 'y k ( *. V Q e i M k t: m r

m., =,.

[ G ,n b m. ~. _ i g g ytTrn, states con:nnKvr , MCMOTand um. r I TENNESSEE VAI. LEY AUTIIORITY. id h tEB '810629 022 M M

c. c. stack, project Hansser, sequoyah nuclose Plant Co:Ist (3) -

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n. v. Cantr*11. Sequoyah and.v.sts nar Deslan Projects Manager.

I l q g i Juli2 91981 2 3 7 p SEQUOT111 ffDC12AR PLANT - It0NCONFORh4ANCE ItEPOST (NCR) 2630 - p 3 - 1TMDCBSIZED FILIIT VII.D CH PIPES ($QN 810302 608) l e i y 1 I Re ference: My memorandum to you dated April 6, 1981 b / l (CI3 810406 020). 1 r ? l We have finished our disposition of the subject NCH. All velds which were determined to be inaccessible were evaluated as r described in the reference. Attachmenta A, B, C, and F of the NCR had a total of 155 welds h tamJred thirty-one fillet Welds were on rigorous analyzed which were evaluated by the Civil Engineering Dranch (CED). m{ riping arw! 24 were on alternatoly analyzed piping. Or these, 19 i .%Qd, of the welds on the rigorously analyzed piping and all 24 on the alternately piping were ruinspected. Acceptable weld s tree were computed for.the welds on the rigorous analyzed piping. If the 1 remeasured weld failed to meet this minimum size it was repaired

1. g to full size. The actual weld sizes of all reinspected welds

f q were then transit,tted to CED so that the rigorous analysis would i

not 7 I be penalized tr the problem is reanalyzed. All welds on alternately analyzed pipes were reinspected and were repatred to a Tull site if necessary, six of these were visually inspected s while the oth,ers were remeasured. j 5 Attachwnts D and k of the llCR identify walds as being EV 9%'h f h accessible, All welds were accessible except one which was (2r2 esesd eva.lunted try Ct5, Land determined to be acceptablo as is. We agree with yoJr.recosce disposition on the other velds. 3 Attachment G re(cra to welds that are temporarily inaccessible. We agree with your recommended disposition to reinspect as soon 4 as they became accessible and repair as required, but this task should be completed before fuel loading. We have received all data relative to reinspection of the F111115 IEW llIU ~ inacces 1ble welds and have concluded our disposition of gg&[L11LL CCPI ] twa 26}s. ~ This baa t>een coerJinaccJ with your Ken Callowey. ~ q l ^ Cristnal 81:ned by b+ YL1LCaALIall 4..j R. W. Cantrell 'f/ 7 U] fJb [ sE10sTC8 c4 8 Ese pJge 2, 0 31 I L*>.2 8 b t i pg; e i .m-- g.

q v k... " WTTED STATES COVERNMENT l 2 Memorandum ? TENNESSEE VALLEY AUTIIORITY sj M 8 Files 1 I89M 8 C. L. Wade, Construction Engineering Associate,'Hechanical,and Welding DATE sep l' EUBJECT: SECD0YAH HUCLEAR PLA(f UNIT 2 - NCR'S 2398 AND 2630 REFEftENCE: Hemorae.dum from R. W. Cantrell to G. G. Stack dated May 22, 1981 (SWP 810526 047) e As on alternate to re-pressure testing socket-welded pipe joints which 3 have had weld buildup of fillet welds to correct dimensions 1 deficiencies i discovered after the systera pressure test, the following were verified: 1. There was no evidence of leakace during the system pressure test. 2. The welding was performed by qualified welders using qualific:1 procedures. (Docuciented ce repair check lists, Attachment A to W-7). [ s 3. The surface of the completed weld buildup was examined by the liquid h. penetrant method in accordance with ANSI 331.7. (Docurnented on repair g i check lists, Attachment A to W-7,and 11-75). / 3 4 Behydro was 'perforced on all weld repairs that could not be p.*oved i that fillet size was 1/8" and greater. ,y 5. Each repaired wild meet the requirements on ANSI-B-31.1-1980, paragrapti 137.6 (Initial Service Leak Testi documented on Work rian 5-1823. t

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i t e.mritq *TATEs covertwar ~ 'M6mOTdM d um f TENNESSEE VALLEY AUTil0RITY 70 s files .g } 5 Y10M C. L. Vade, Construction Engineering Associate. Hechanical and Welding i DATE Lep e b r 9 h" SEQUOYAH NUCLEAR PLANT UNIT 2 - NCR 2630 ATTAC W NT G (WELDS TilAT WERE EUEJECT: TDtPORARILY INACCE.SSIDLE) .1 v All welds listed on NCR 2630 Attach.nent G were reinspected for weld size. N All were found accertable except for the seven welds listed below. All unacceptable welds were repaired by adding additional weld cetal. The welds were then reinspected and all found to be acceptable. t WELD PIPE NOMINAL RE0'D FILLET HEASURED SIZE g . HUMER SIZE THICKNESS SIZE (Before Repair WELD MAP [! h 2CX02715x1 3/4" .218" 1/4" 3/16" x 9/32" 2-CVC-206W 9 2SIO2574 3/4" .218" 1/4" 7/32" x 9/32" 2-SI-094W 2SE16371 1/2" .187" 7/32" 3/16" x 3/16" SEH-433 2UH01448 2" .343" 3/8" 5/16" x 12/32 ' 2-UPI-007V r 1 2U1101415 2" . 3 8. 3" 3/8" 3/8" x 1/4" 2-UPI-007V L 5 20H01441 2" .343" 3/8" 3/8" x 1/4* 2-UPI-007W Tl ICXC3761 1" .250" 9/32" 3/8" x 1/4" cvC-037w i s -r , L. u.ce w g u .?,. t

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ML20214V018

Contents

Text

SUMMARY

SUBJECT:

SUMMARY

Title:

Title:

Dear Hr. O'Reilly:

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Rev 1 to TVA Employee Concerns Special Program,Undersized Socket Welds on Safety Injection Sys
Person / Time
ML20214V018
Site:	Sequoyah
Issue date:	11/20/1986
From:	Bateman R, Russell J, Stewart D TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20214G966	List: ML20214G963 ML20214G989 ML20214T991 ML20214U124 ML20214U174 ML20214U216 ML20214U247 ML20214U308 ML20214U341 ML20214U367 ML20214U384 ML20214U415 ML20214U473 ML20214U502 ML20214U520 ML20214U550 ML20214U625 ML20214U639 ML20214U689 ML20214U749 ML20214U779 ML20214U814 ML20214U843 ML20214U860 ML20214U882 ML20214U924 ML20214V018 ML20214V037
References
WP-20, WP-20-R01, WP-20-R1, NUDOCS 8612090499
Download: ML20214V018 (62)
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ML20214V018

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