ML19210D352

LER 79-096/01T-0:on 791110,nonisolable Weld on Pump a Suction Line Test Connection Discovered Leaking.Cause Unknown.Line Cut,Plugged & Capped.Affected Weld Connections Will Be Metallurgically Evaluated

ML19210D352
Person / Time
Site:	Brunswick
Issue date:	11/21/1979
From:	CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19210D351	List: ML19210D350 ML19210D352
References
LER-79-096-01T, LER-79-96-1T, NUDOCS 7911260338
Download: ML19210D352 (1)

Text

-7,77,"'- Y #. ." t.lCENSEE EVENT REPORT CONTROL BLOCK: l llllll(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 GTl I Nl Cl P l El Pl 1[gl50 j 0 ] -l 0 l 0 ] 0 ] 0 l 0 l - l 0 l 0 lgl 4 l 1 l l j 1l l jgl llg 7 8 9 LICENSEE CODE 14 1 LICENSE NUMBER 25 26 LICENSE TYPE JO

$7 CA T 58 CON'T E ERCE IL h l Ol 5l0l-l013l215 @l1lllllOl7l9l@l llllll@" 7 8 60 61 DOCK ET NUMBER 68 69 EVENT CATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o l 2 I lWhile work was progressing on the seal replacement of the"A" reactor recirculation l pump, a mechanic noted that a nonisolable weld on pump"A" suction line test con-lo a o 4 Inection was leaking. The 3/4-inch line is about 2-1/2 feet in length and contains a

, o s 90* elbow, two 3/4-inch valves, and a cap.

The crack was associated with the pipe to l telbow weld away from the recirculation loop.

I o e O 7 i Technical Specifications 6.9.1.8c lI o a i 80 7 8 9 DE CODE SLBC E COMPONENT CODE SU8 CODE S ElClBl@@ l C l@ lP lIl P l E l X l X l@ J@ l Zl @

O 9 7 8 9 10 11 12 IJ 18 19 20 ,_SEOUENTIAL OCCURRENCE REPORT REVISION LE R/RO EVENT YE AR REPORT No.

CODE TYPE N O.OO yUQEl7l9ll-l0l9l6ll/ll0l1ll Tll-ll0 lRE RT 21 22 23 24 26 27 N 3 30 31 32 T KN ACT ON ON PLANT TE hours S8 i O FOR 8.SUPPLIE MANUFACTURER lFl@lXl@Cl@LZ_j@l0l0l7l0ll Y l@lYl@lNl@lBl4l5l0l@

33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h lThe line*was cut upstream of the 90* elbow, plugged, and capped per an approved plant i olTTTl [ modification. A similar modification was performed on the"B" pump during this period.i g JThe Unit No. 2"B" pump was modified in 1977 and the Unit No. 2"A" pump will be modi-l g , l 31 lfied at the next scheduled cold shutdown (presently December 1979). Affected welds on[

L' L4J Iboth Unit No. 1 connections will be metallurgically evaluated to determine the cause

[80 7 8 9 STA S% POWER oTHER STA TUS is O RY DISCOVERY DESCRIPTION W l,_Gj @ l0l 0 l 0l h l N/A ll A l@l Mechanic Surveillance l0 ACTIVITY CO TENT'RETE ASEo CF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

{_gj @ W@l N/A l N/Ali c 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION lO!0l0l@lZl@lN/A l7 PensONNE t iN;u'siES

, h g 9" 3 ,1 g#" 80 'lNOUtt E R DESCitiPT10N l0l0l0lhlN/A

(,Ei (b J-'#i 1 M 9 11 12 go LOSS OF On DAMAGE TO F ACILITY TYPE DE SCniP TION j hlZl@lN/Ali 9 F M'J 10 80 Pt stLL ICl l Y NRC USE ONLY

[1Loj G8f"NE" '

79112603 9/3 iititiiiiiiiil) 68 69 80 5;#M U 10~NAME Of PREPAHEli PHONE:_

-..a..LER CONTINUATION--RO #1-79-96 FACILITY: BSEP Unit No. 1 EVENT DATE:

11-10-79 of failure.

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