05000281/LER-1982-075-01, /01T-0:on 821219,while Conducting RCS Integrity Test,Weld Leak on Steam Generator a Channel Head Drain Piping at 2-RC-159 Identified.Probably Caused by Poor Fusion Between Successive Passes in Weld.Defective Weld Repaired

/01T-0:on 821219,while Conducting RCS Integrity Test,Weld Leak on Steam Generator a Channel Head Drain Piping at 2-RC-159 Identified.Probably Caused by Poor Fusion Between Successive Passes in Weld.Defective Weld Repaired

ML20028C276
Person / Time
Site:	Surry
Issue date:	12/30/1982
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20028C269	List: 05000281/LER-1982-075, Forwards LER 82-075/01T-0 05000281/LER-1982-075-01, /01T-0:on 821219,while Conducting RCS Integrity Test,Weld Leak on Steam Generator a Channel Head Drain Piping at 2-RC-159 Identified.Probably Caused by Poor Fusion Between Successive Passes in Weld.Defective Weld Repaired
References
LER-82-075-01T, LER-82-75-1T, NUDOCS 8301070288
Download: ML20028C276 (2)

LER-1982-075, /01T-0:on 821219,while Conducting RCS Integrity Test,Weld Leak on Steam Generator a Channel Head Drain Piping at 2-RC-159 Identified.Probably Caused by Poor Fusion Between Successive Passes in Weld.Defective Weld Repaired

Event date:
Report date:
2811982075R01 - NRC Website

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6 ATIACHMENT 1 SURRY POWER STATIOM, UNIT NO. 2 DOCKET NO:

50-281 REPORT NO:

82-075/01T-0 EVENT DATE:

12-19-82 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 socket weld leak on the ' A' steam generator channel head drain piping at 2-RC-159 was identified. This event is reportable in accordance with Technical Specification 6.6.2.a'.(3).

2.

PROBABLE CONSEQUENCES AND STATUS.0F REDUNDANT EQUIPMENT:

2-RC-159 is connected to the steam generator through a 3/8" pipe approximately 5" long.

A Westinghouse analysis has determined the normal charging system is capable.of maintaining RCS inventory in the event of a 3/8" pipe break.

There-fore the health and safety of the public vere not affected.

3.

CAUSE

The cause of the event is believed to be inadequate fusion between successive weld passes. This may have been due to vater being present at the time the weld was made. Since the defect did not extend to the weld surface it was not detected by the liquid penetrant examination done at the time.

4.

IMMEDIATE CORRECTIVE ACTION

Actions were taken to return the unit to cold shutdown.

5.

SUBSEQUENT CORRECTIVE ACTIO'i:

The weld was ground out in the area of the defect and repaired. A liquid Penetrant Examination of the final weld revealed no defects. Additionally, a hydrostatic test was successfully completed.

l 6.

ACTIONS TAKEN TO PREVENT RECURRENCE:

None.

7.

GENERIC IMPLICATIONS:

i None.