05000325/LER-1985-026, :on 850718,92 Indications within Heat Affected Zones & Pinhole Leaks of Welds Revealed During Refuel/Maint Outage.Caused by IGSCC of Class 1,Type 304 Piping Matl. Weld Overlays Acceptable

:on 850718,92 Indications within Heat Affected Zones & Pinhole Leaks of Welds Revealed During Refuel/Maint Outage.Caused by IGSCC of Class 1,Type 304 Piping Matl. Weld Overlays Acceptable

ML20133J012
Person / Time
Site:	Brunswick
Issue date:	07/31/1985
From:	Pastva M CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20133H993	List: 05000325/LER-1985-026, :on 850718,92 Indications within Heat Affected Zones & Pinhole Leaks of Welds Revealed During Refuel/Maint Outage.Caused by IGSCC of Class 1,Type 304 Piping Matl. Weld Overlays Acceptable
References
LER-85-026, LER-85-26, NUDOCS 8508090616
Download: ML20133J012 (7)

LER-1985-026, on 850718,92 Indications within Heat Affected Zones & Pinhole Leaks of Welds Revealed During Refuel/Maint Outage.Caused by IGSCC of Class 1,Type 304 Piping Matl. Weld Overlays Acceptable

Event date:
Report date:
3251985026R00 - NRC Website

text

'

NRC Form 333 U S. NUCLEIJi ELE 1ULATO1V COMMISSION N

LP# ROVED oms NO 3150-0104 LICENSEE EVENT REPORT (LER)

FACILITY NAME (11 DOCKET NUMGER (2)

PAGE G Brunswick Steam Electric Plant Unit 1 0l5l0[0l013 1215 1 lOFl0 l7

"' Pipe Crack Indications Revealed Following Induction Heat Stress Improvement of Unit 1 Reactor Recirculation Piping EVENT DATE 158 LER NUMeER ts:

REPORT DATE 171 OTHER F ACILITIES INVOLVED ISI II MONTM CAv YEAR YEAR n

MONTM DAY YEAR NW WH NU MMU u e 0l5l0l0j0g l [

0l7 0l1 8

5 8l5 0l2l6 0l0 0l7 3l1 8l 5 0 1 5 1 0 tol0 i l l Twis REPORT is sueMiTTEo PuR UANT TO THE REOuiREut=T Or 10 CFR 6 rea==

e, ea een. + nii o,,,,,,,,

5 m *02m 20 0em 30 73i.H2H->

13 rim 20 405:eH1Hil 50.38M118 90.73teH3 Het 73.71m 90WER LEVEL 4101 0 l 0 10 20 ***'*H'it*8 58 38ta"25 e0 73i.H2 Hum O wERyg. A,.7, 20 40SieH1Heill 60.73teH2Hil 90.73ieH2HediHA) 366A)

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20 400isl(1Hivi 50.73(aH2HW OO.73:eH2HveilHS) 20 400(eH1Het 30.73teH21hM to 73(sH2Hal LICENSEE CONTACT FOR TMit LER (123 NAME TELEPMONE NUMBER ARE A CODE M. J. Pastva, Jr., Regulctory Technician 9l i 9 4 1 5 t 71 2[31l5 i

1 1

COMPLETE ONE LINE FOR E ACM COMPONENT F AILURE DESCRIBED IN TMit REPORT (131 "fo ",,'gg O

etE MA A

REPCRTA LE

^O CAU$t Sv8 TEM COMPONENT

CAUSE

Sv 8TE M COMPONENy 7

g yg pq X

Ag D [PgS;X B; 4;5 l 0 Yes X

A,D

, P,S, X B,4,5,0 Yes X

Aj D l P[S ; X B] 4 5;0 Yes X

A;D lP 9 S, X B ; 4; 5,0 Yes

. c 1

$UPPLEMENTAL REPORT EXPECTED 114s MONTM CAV vgAR SUSVi$$104 YES (19 p.e..annetete EXPECTfD SUOMIS$10N OA TE)

NO l

l l

Aem ACT ro,,,,, R, r.co.--.......,,.,,,,,,,,,.. ~,,. ne.,.., n. >

During the Unit 1 1985 refuel / maintenance outage, visual and/or ultrasonic examinations of reactor recirculation piping following induction heat stress improvement revealed the existence of 92 indications within the heat-affected zones of 23 of the 79 welds tested. This includes pinhole leaks at five of the welds.

77 of the 92 indications were axial. Additional inspection of the welds using the General Electric automated SMART ultrasonic testing system yielded a positive correlation between the manual and automated inspections made on circumferential indications. The cause of the indications and pinholes is attributed to intergranular stress corrosion cracking (IGSCC) of the class 1, type 304 stainless steel piping material. Corrective action to the indications and pinholes will consist of acceptable weld overlays and in one case, e'aluation of acceptability as found. A summary description regarding the ide::tified problems is given in Table 1.

8508090616 850731 if PDR ADOCK 05000325 S

PDR

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NRC Form 3088 U S NUCLEAR KEIULAYQQY COMMIS$10N LICENSEE EVENT REPORT (LER) FAILURE CONTINUATION APPROVED OMe NC. 312-cm EXPlRES gr31/g5 FACILITY NAME (14 DOCKET NUMSER (2)

LER NUMSER 18)

PAGE131 "uw mn

, EAR Brunswick Steam Electric Plant Unit I o l5 l 0 l0 j o l3 l 215 8l5 0121 6 Ob 0 12 0F 0 I7 COMPLETE ONE LINE FOR E ACH COMPONENT FAILURE DESCR10ED IN THl3 REPORT (13)

R RTA LE MANhC-RE RfABLE FjC.

M

CAUSE

SYSTEM COMPONENT CA.uSE Sv$7EM COMPONENT pp X

Al D lPlS l X B 14 l 510 Yes X

A lD lP l S1X B l 4 l 5 l0 Yes Y

Al D lPIS l X BI4 15l0 Yes X

A lD lP l SIX B [415[0 Yes X

Al D lPjS l X Bj4 l5l0 Yes X

A ID lP l SlX B l 415 l0 Yes X

Al D l PlS l X B 14 l 5l0 Yes X

A lD lP l SlX B l 4l 5 l0 Yes X

Al D l PlS l X Bl4 l5l0 Yes X

A lD lP l SI X B-l 4l 5 [0 Yes X

Al D l PIS I X Bl4 I5l0 Yes X

AfD lPl SlX B l 415 l0 Yes X

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RC form 3488 U.S. NUCLEAR %EiULAT2SV COMMIS$3ON LICENSEE EVENT REPORT (LER) FAILURE CONTINUATION

^""ov 'D o** *a 3' 52-o*

EXPIRES 8/31/85 FACILITV NAME (1)

DOCKET NUMSER (21 LER NUMSER 161 PAoI III IE YEAR gm I

v e Brunswick Steam Electric Plant Unit 1 0 l S l 0 l0 j o l3 l 215 8l 5 0l2 [ 6 0 l0 0 l3 0F 0 l7 COMPLETE ONE LINE FOR E ACH COMPONENT FAILURE DESCRIBED IN THl3 REPORT (13)

M F AC.

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