ML19322E852

LER 80-006/01T-0:on 800308,while Performing Reactor Vessel Pressure Test,Several Crack Indications Were Discovered in Pipe to Elbow Welds.Cause Not Determined.Affected Pipe Sections Will Be Replaced W/Carbon Steel Piping

ML19322E852
Person / Time
Site:	Quad Cities
Issue date:	03/22/1980
From:	Dunesia Clark COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19322E848	List: ML19322E847 ML19322E852
References
LER-80-006-01T, LER-80-6-1T, NUDOCS 8004020355
Download: ML19322E852 (7)

Text

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NRC FORM 366 U. S. NUCLE AR REGULATORY COMMISSloN (7 77)

~

• LICENSEE EVENT REPORT

%/

) CONTROL BLOCK: l 1

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo lil8 I9 i l L LICENSEE 7

l Q l CODE A l D l 2 l@l 0 l0 l 0LsCENSE to 15 l- l 0l Ol Ol -l O l 2$0l0l@l4l1l1l1l1l@l NUMSER 26 LICENSE TYPE JG l

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CON'T lOlil 3g y l L l@l 0 l 5 l 0 l 0 lo l 216 l5 l@l 01310 l 8 l 8 l 0 l@l 0 l 3 l 2 l 2 I 81080l@

7 8 60 61 00CKET NUVBER 68 69 EVENT OATE 74 75 REPORT DATE EVENT DESCRIPTION AND PRO 8A8LE CONSEQUENCES h lo l2] i While performing a reactor vessel pressure test as part of the Inservice insnection i 10131 l program (T.S.4.6.F) a visual inspection of the primary coolant system piping revealed I

o ;4; l some water drops on the "A" core spray injection piping, 1ine 2-1403-10"-A. An ultra-l go;3, g sonic inspection of 100 percent of the core spray piping welds in the primary contain-l lO ls i l ment disclosed several crack indications located in the pipe to elbow welds between l lO l 7 l l the reactor vessel and first manual isolation valve in both core spray loops. l 10181l I SYSTEM CAUSE CAUSE COYP. VALVE CODE CODE SU8 CODE COMPONENT CODE SUSCODE SUSCODE 1019l

8 l C l J l@ ]Q l Cl@ l P l1 l P lE lX lX [@ l 0l@ l Z l@

9 to 11 12 13 Id 19 20

, S E QUE NTI A L OCCUR R E NCE REPORT REVISION LER RO EVENT YE AR REPORT NO. CODE TYPE N O.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 11 101 l The cause of the crack indications has not been determined. The cause will be l gl determined following a laboratory failure analysis on the subject pieces of pinino. I

, , l The final results of the laboratory metallurgical analysis will be reported to the l g3g l NRC. The affected sections of pipe on both loops will be replaced with carbon steel l

, , g piping. l 7 J 9 80 STA S  % POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION y l H l@ l0 ' l 0 l0 l@l '

NA l lBl@l* Routine Test l

's2Tlvt TY COkTENT RELEASE LOCATION OP RELEASE riTs 1 l Z l @D OF RELEASE 7 8 9 10 AMOUNT NA l Zl@l OF ACTIVITY 44 l

45

@l NA l tt 80 PERSONNEL EXPOSURES NuveER TYPE DESCRIPTION NA fiTTI I O l o l O l@l z l@l l

' ' PERScNNa',N2u'!,ES "

• NUMBER oESCRiPriON@

m l 8010 7 9 l 0 l@l 11 12 NA 80 l

LOSS OF CR OAMAGE TO FACILtTV TYPE DESCRIPTION g l Z l@l NA l 7 8 9 to 80 ISSUE DESCRIPTION L2_L2]Lgf81 na i i i l l l l i i 11 ! ! l$:

7 8 9 iO "'

D. Clark D O O4()ZO 3 5 5 NAVE OF PREPARER PHON E: 109-M4-2 241 Ex. 170 g

l. LER NUMBER: LER/R0 80-06/0lT-0

11. LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station Ill. FACILITY NAME: Unit Two IV. DOCKET NUMBER: 050-265 V. EVENT DESCRIPTION:

On March 8,1980, during the Unit Two reactor vessel pressure test, a visual inspection of the primary coolant system piping revealed some water drops on the "A" core spray injection piping, line 2-1403-10"-A. The reactor vessel pressure test was performed as part of the inservice inspection proar=~ to meet the surveillance requirements of Technical Specification 4.6.F. A subsequent ul trasonic inspection of 100 percent of the core spray piping welds located in the primary containment was performed under the direct supervision of the Commonwealth Edison Company SNT-TC-1A Level til Examiner. The inspection disclosed several crack indications in the welds in both core spray loops. The Indications were located in the pipe to elbow welds between the reactor vessel and the first manual isolation valve.

VI. PROBABLE CONSEQUENCES OF TPE OCCURRENCE:

The reactor has been in the cold shutdown condition since November 25, 1979 for refueling. The crack indication was first noticed during the vessel pressure test which was required to be performed before the reactor could be returned to operation. No steam or water leakage was detected during the initial drywell entry while the reactor was in the process of being shutdown for the refueling outage. The core spray piping which is included in the primary coolant system boundary is inspected as part of the station inservice inspection program. Several special inspections have also been performed on the core spray piping, These inspections include the inspections required in R.O. Bulletin 75-01; an augmented inspection recommended in General Electric Service Information Letter #117; and a special inspection performed in January, 1978. The results of the inservice inspection and the special inspections have all been satisfactory. A list of welds which have been inspected, and weld maps are attached.

l l

i

l Vll. CAUSE The cause of the crack indications has not been determined.

The cause will be determined following a laboratory failure analysis on the subject pieces of piping. Two of the welds which were found to have crack indications were found satisfactory during the inservice inspection performed during the current outage. We can not specify the reason for missing the indications at that time. We can only speculate that it could have been the failure of the ultrasonic test equipment, f ailure to set-up and calibrate properly, or failure on the part of the testing operator.

The pipe was manufactured by United States Steel Corporation, and is type A-312, grade TP 304, schedule 80 seamless stainless steel pipe, heat number X25210. The elbows were manufactured by Taylor Forge Corporation, type A403 grade L? 304, schedule 80 seamless steel elbows, heat number 251350Cq.

Vill. CORRECTIVE ACTION' Several pieces of the existing core spray line will be cut out as shown in the attached sketches. The removed pieces of piping will be visually inspected by a Commonwealth Edison metallurgist following removal. Commonwealth Edison will send representative samples of the failed pipe to Argonne National Laboratory for failure analysis. Representative samples will also be sent to Brookhaven National Laboratory for the NRC to conduct an analysis parallel to ou r own. The final results of the laboratory metallurgical analysis will be reported to the NRC.

The repair of the core spray piping involves removing the affected sections of pipe on both loops. These sections will be replaced with carbon steel piping and fittings. The existing stainlest , teel isolation valves will be retained in the piping sy r.em. The replaced section will be welded approximately 15 inches from the nozzle safe-end. The heat input created during welding will have no affect on the safe-end.

The replacement carbon steel pipe is type SA-333, grade 6, schedule 80 seamless pipe. The fi ttings are type SA420, grade WPL-6, schedule 80 seamless elbows. The repair work will be performed under the requirements of ASME Boiler and Pressure Vessel Code Section XI. The repair parts have been procured in accordance with ASME Boiler and Pressure Vessel Code Section lit, Class 1.

. _ - - ._ . ~ . _ _ - - .._

1 The carbon steel pipe that will be installed in the core spray lines will be considered as a final fix for that particular section of piping. At this time, Commonwealth Edison does not know if the safe-end and the stainless steel piping between the safe-end and the carbon steel portion is a final fix. The company will address this portion of pipe and evaluate the prospective alternatives to obtain a final fix pending the results of the metallurgical failure analysis.

As requested by the NRC, the safe-end to pipe weld as well as all dissimilar-metal welds made as part of the regair will be inspected for the next two refueling outages. The inspections will be performed using current company approved ultrasonic test procedures. An ultrasonic inspection of the Unit One core spray piping located inside the primary containment will be done during the next refueling outage in the Fall,1980.

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QUAD-C ITIES UtilT TWO CORE SPRAY PIPE flDE HISTORY wint. 78 ISI Weld No Fall 76 ISI Spec, insp. Cracks Found

'A' Loop Type R.O. Bull. 75-01 SIL 117 Jan. 78 Fall 79 ISI tiarch, 1980 14A-Fi N-SE ! X X l X 14A-F2 SE-P X X .' X '

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