ML042990022
| ML042990022 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/07/2002 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2003-0187, NOP-LP-2001-01 02-05536 | |
| Download: ML042990022 (1) | |
Text
I-NOP-LP-2001 01 CONDITION REPORT CR Number TITLE: CRACK INDICATION IN J-GROOVE WELD OF OLD CRDM NOZZLE 3 02-05536 DISCOVERY DATE I TIME EVENT DATE l TIME I SYSTEM/J ASSET#
9/512002_
13:00 9/5102 l
NIA l02-01 NtA EQUIPMENT DESCRIPTION Retlred 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 R
circumferential J-groove weld crack indication. The indication is located approximately 3/4" radially R
from the penetration bore over approximately a 45 degree span on the cladding side (RCS side),
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.
T 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 ATTACHMENTS Quality Org. Initiated 0 Yes RI Indhidual/Work Group L Internal Oversight Quality Org. Foflow-up [lYes L No I SupervisionrManagement External Oversight i Yes No ORIGINATOR ORGANIZATION DATE SUPERVISOR l DATE PHONE EXT.
LANG, T LCM 9152002 LANG.T i
91512002 i
8116 SRO EQUIPMENT EVALUATION IMMEDIATE ORGANIZATION
'MODE CHANGE P
REVIEW OPERA]LE REQUIRED INVESTIGATION REQUIRED NOTIFIED RESTRAINT L
EŽsYes No E Yes C No E NIA ClYes 2No EI Y
NoA
_- Yes
- NoA, No A
MODE ASSOCIATED TECH SPEC NUMBER(S)
ASSOCIATED LCO ACTION STATEMENT(S)
N jBaiajftesig,,!: }t
![:'>1'it
-Gui
,.>45i T9 T
- 2 O
DECLARED REPORTABLE?
OneHour NWA APPLICABLE UNIT(S)
NOPERABLE (Date ITime)
Yes 2NO.
6rHotirVA=:45 k
y 1
E N/A
[JEval Requred Other lA U2 -
] 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.
N Current Mode-Unit 1l Power Level -Unit i Current Mode -Unit 2 PowerLe S
DEF 0
l SRO - UNIT I SRO - UNIT 2 DATE Pierson, J 9/7/2002 Page 1 of 2