05000280/LER-1982-024

LER 82-024/01T-0:on 820524,weld Leak on a Steam Generator Channel Head Drain Piping at 2-RC-159 Identified During RCS Integrity Test PT-11.Caused by Random Defect in Root Weld, Possibly Due to Split Pass

ML20054G180
Person / Time
Site:	Surry
Issue date:	06/08/1982
From:	Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20054G165	List: 05000280/LER-1982-024 05000280/LER-1982-027 05000280/LER-1982-057 05000280/LER-1982-058 ML20054G164
References
LER-82-024-01T, LER-82-24-1T, NUDOCS 8206210220
Download: ML20054G180 (2)

LER-2082-024,

Event date:
Report date:
2802082024R00 - NRC Website

text

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? 8 EVENT DATE 74 TS EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h 10121 l Uith unit 2 at HSD, while conducting the RCS Integrity Test (PT-ll), a weld leak on l

[O la l l the 'A' steam generator channel head drain piping at 2-RC-159 was identified. l

[O l4 l l Immediate action was taken to return the unit to CSD. This event is reportable l l0 Isl l pursuant to T.S.6.6.a.(3). The leakage was within the capability of t'he normal l 1016l l make up system, therefore, the health and safety of the public were not affected. l 10l7ll l 10181I l 7 E 9 80 SYSTE M CAUSE CAUSE COMP. VALVE CODE CODE SUSCODE COMPONENT CODE SUSCODE SUBCODE lOl91 7 6 l Cl Blh Wh lC lh l PlIl Pl El Xl Xlh lZ lh lZ lh 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION E VENT YE AR REPORT NO. CODE TYPE NO.

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40 di 42 43 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l1 1OII The cause of this event is believed to be a randoni defect in the Root Weld, possibly l

,, ,, , g caused by a split pass. The unit was returned to CSD. The defective weld was ,

ground out and the valve rewelded in accordance with approved procedures. Liquid Jenetrant Examination revealed no defects.  ;

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Y' ATTACHMENT 1 SURRY POWER STATION, UNIT NO. 2 DOCKET NO: 50-281 REPORT NO: 82-024/0lT-0 EVENT DATE: 05-24-82

. TITLE OF THE EVENT: 2-RC-159 Weld Leak

1. DESCRIPTION OF THE EVENT:

With the unit at hot shutdown, while conducting the Reactor Coolant System (RCS) integrity test (Periodic Test 11) a weld leak on the 'A' steam generator channel head drain piping at 2-RC-159 was identified. Immediate corrective action was taken to return the unit to cold shutdown. The defective weld was ground out, and the valve rewelded. All welds on the 'A' steam generator channel head drain were examined and found acceptable in accordance with NDE-PT-1, Liquid Penetrant Examination. This event is reportable in accordance with Technical Specification 6.6.2.a. (3) .

2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT EQUIPMENT:

2-RC-159 is connected to the steam generator through a 3/8" pipe approximately 5" long. A more conservative case, assuming a 3/8" orifice in the RCS, has been analyzed by Westinghouse and found to be within the capabilities of the normal make up system. The health and safety of the public were not affected.

3. CAUSE:

The cause of this event is believed to be a small defect in the Root Weld, possibly caused by a split pass. During successive passes, such a defect would project into but not through the second pass and therefore would not be detected by the liquid penetrant examination.

4. IMMEDIATE CORRECTIVE ACTION:

Actions were taken to return the unit to cold shutdown.

5. SUBSEQUENT CORRECTIVE ACTION:

The defective weld was completely ground out and the valve rewelded in accordance with approved procedures. Liquid Penetrant Examination revealed no defects. Subsequently the RCS integrity test was performed satisfactorily.

6. ACTIONS TAKEN TO PREVENT RECURRENCE:

All evidence supports the theory that the leak on 2-RC-159 was caused by a random weld defect, therefore no further action is deemed necessary.

7. GENERIC IMPLICATIONS:

None.