ML022620543

Condition Report CR 02-05536 for Davis-Besse, Crack Indication in J-Groove Weld of Old CRDM Nozzle 3

ML022620543
Person / Time
Site:	Davis Besse
Issue date:	09/07/2002
From:	Pierson J FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2003-0018 CR 02-05536
Download: ML022620543 (1)

Text

NOP-LP-2001-01 CONDITION REPORT lCRNumber TITLE: CRACK INDICATION IN J-GROOVE WELD OF OLD CRDM NOZZLE3 l02-05536

- DISCOVERY DATE 7 IE EET DATE lTIME SYSTEM I ASSET#

9/5/2002 130 9112 l NA 062-01 NIA EQUIPMENT DESCRIPTION Retired Control Rod Drive Nozzle #3 DESCRIPTION OF CONDITION and PROBABLE CAUSE (if known) Summarize any attachments. Identify what, when, where, why, how.

A lab report for the old Reactor head nozzle 3 weld sample was received from Framatome with a circumferential J-groove weld crack indication. The indication is located approximately 314" radially R from the penetration bore over approximately a 45 degree span on the cladding side (RCS side),

I slightly offset from the centerline of the nozzle 3 corrosion cavity. It was revealed with fluorescent G penetrant testing. (Many small cracks appear to be linked to comprise the total 45 degree arc.)

I Conversation with Framatome indicated that the indication probably does not extend through the N weld, and thus would NOT have contributed to RCS pressure boundary leakage already reported for A this nozzle under CR 02-00891. This indication is consistent with crack formation due to PWSCC.

I SUPV COMMENTS I IMMEDIATE ACTIONS TAKEN (Discuss CORRECTIVE ACTIONS completed, basis for closure.)

o Although this nozzle is no longer associated with installed plant equipment and therefore has no N operability impact, it has significance for failure statistics, potential use as a qualification sample for NDE, and/or research. It may also be necessary to revise documentation pertaining to the number of crack indications found during 13RFO. It is believed that this weld area was dye penetrant tested under Work Order 02-001917-000, step 13, while on site. This CR should determine whether this test was actually performed and if so, why it did not detect the crack indication.

QUALITY ORGANIZATION USE ONLY IDENTIFIED BY (Check one) Self-Revealed Si ATTACHMENTS Quality Org Initiated n Yes i Individual/Work Group L Internal Oversight Quality Org Follow-up Fl Yes PI No LI Supervision/Management El Extemal Oversight - Yes ,V, No ORIGINATOR ORGANIZATION DATE SUPERVISOR I DATE r PHONE EXT.

LANG, T I LCM 915/2002 LANG, T 1 9/5/2002 , 8116 SRO EQUIPMENT EVALU IMMEDIAT I ORGANIZATION . MODE CHANGE P REVIEW REQUIRED INVESTIGATION REQUIRED NOTIFIED i RESTRAINT L W Yes 3 No Yes l No il N/A D Yes No Yes No N/A _ Yes EV, No A MODE ASSOCIATED TECH SPEC NUMBER(S) ASSOCIATED LCO ACTION STATEMENT(S)

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_ - gF . _ s - _ - . o I t - a  ;- ru O DECLARED REPORTABLE? One Hour N/A APPLICABLE UNIT(S)

NOPERABLE (Date ITime) Dy1Yes iiNo F___

E N/A LCEval Required  ! Other N/A V, U 1 2 []Both R COMMENTS A This is no longer plant equipment. CR erroneously marked as Subsytem 062-01 which automatically T slated it for SRO Review with no Option to change. No SRO Review is required.

I N Current Mode - Unit I Power Level - Unit I Current Mode - Unit 2 PowerLevel-Uni2 S DEF l 0 SRO - UNIT I SRO - UNIT 2 DATE Pierson, J 917/2002

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