ML030870184
| ML030870184 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/10/2002 |
| From: | Leisure M FirstEnergy Corp |
| To: | Anthony Mendiola Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2003-0018 | |
| Download: ML030870184 (5) | |
Text
Steven Long......Sample...Plan..PhaPage 11 From:
<mkleisure@firstenergycorp.com>
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To:
<ajm@nrc.gov>
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Iip-f Date:
9/10102 10:22AM
Subject:
Sample Plan' Phase 3 Tony As you requested this morning, attached is Condition Report (CR) 02-05705 on the clad cracks and related photos. I have also attached a copy of CR 02-05536 regarding a circumferential J-groove weld crack indication that was described in the status update of 9/3 that was transmitted to Jon Hopkins on 9/6.
I discussed the clad crack issue with Hongqing Xu of Framatome. He confirms that there are no indications that the crack is through wall He also confirms that the cracks appear to be at a junction between two weld beads and are running parallel to the direction of the weld beads. All lab activities with this sample are on hold Hongqing is working on updating the Sample Plan to discuss and address the discovery of the clad cracks I will be calling you later today to discuss setting up a conference call for sometime tomorrow morning to further discuss these issues (See attached file. CR02-05705.PDF)(See attached file: piece A2 top view of cavity.jpg)(See attached file: pc A2 crack in clad jpg)(See attached file.
CR02-05536.PDF)
Mike Leisure Davis-Besse Licensing (419)321-7168 CC:
<jbhl@nrc gov>, <drwuokko@firstenergycorp com>,
<mmclaughlin@firstenergycorp com>, <pjmccloskey@firstenergycorp.com>,
<rwschrauder@firstenergycorp com>, <Hongqing Xu@framatome-anp.com>,
<talang@firstenergycorp.com>
[ { teven Long - Sample Plan Phase 3
NOP-LP-2001-01 CONDITION REPORT cR Number TITLE: CLADDING CRACK FOUND IN ORIGINAL RVH CAVITY 02-05705 DISCOVERY DATE TIME EVN AEITIME
!SYSTEM I ASSETS 9/6/2002 NAna
[
NIA NIA N/A EQUIPMENT DESCRIPTION Original Davls-Besse Reactor Head Cavity
-DESECRRI'PT-ION OF CO6NDITION and PROBABLE CAUSE (if known) Summarize any attachments. Identify what, when, where, why, how.
0 The 17" diameter specimen that was removed from the original Davis-Besse Reactor Pressure R
vessel is currently undergoing examination in a laboratory. The laboratory informed Davis-Besse I
today that a crack approximately 3/8" long was found in the center of the exposed cladding area of G
the cavity. This new information will need to be evaluated for possible effects on the safety I
significance analysis.
N The laboratory also performed cladding thickness measurements. The results were as follows:
A T
Average - 0.256" I
Minimum - 0.202" O
Maximum - 0.314" N
These results will also need to be evaluated to determine their effect on the safety significance analysis.
SUPV COMMENTS I IMMEDIATE ACTIONS TAKEN (Discuss CORRECTIVE ACTIONS completed, basis for closure.)
NA QUALITY ORGANIZATION USE ONLY I IDENTIFIED BY (Check one)
AT Self-Revealed ATTACHMENTS Quahty~;,=
Self-Revedaledsi:*
Quality Org. Initiated l, Ye IndividualWork Group
__ Internal Oversight Quality Org Follow-up DI Yes El No EL Supervsion/Management External Oversight
--,Yes E No ORIGINATOR ORGANIZATION1 DATE SUPERVISOR DATE -
PHONE EXT.
MCLAUGHLIN. M CH 919=2002 MCLAUGHLIN, M 9/9/2002 8295 SRO EQUIPMENT EVALUATION IMMEDIATE
'ORGANIZATION MODE CHANGE p
REVIEW OPERABLE REQUIRED INVESTIGATION REQUIRED NOTIFIED RESTRAINT L
RI Noj Yes No NIA [:] Yes & No D Yes &Z No N/A Yes No A
MODE ASSOCIATED TECH SPEC NUMB ER(S)T ASS-0CIATrED LC_ ACTION STATEMENT(S)
N T" ~
/
E T
- 2
- i
- 3 O
DECLARED REPORTABLE?
One Hour N/A APPLICABLE UNIT(S) p NOPERABLE (DatelTime) L.Yes t--No iFourHour NWA1 t,.
E N/A DEval Required Other N/A
- __ U1
_ U2
. Both R
COMMENTS A
NIA T
0 N
Current Mode - Unit Power Level-Unit ICurrent Mode -Unit 2 I Power Level - UnIt 2 S
N/A L
NIA N/A N/A SRO-UNIT 1 SRO-UNIT2 DATE 1 Approved By Supv N/A 9/9/2002 Page I of 2
- 1
- 1
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NOP-LP-2001-01 CONDITION REPORT CR Number TITLE: CRACK INDICATION IN J-GROOVE WELD OF OLD CRDM NOZZLE 3 02-05536 DISCOVERY DATE TIME IEVENT DATE TIME SYSTEM I ASSET#
9/512002 100 915102 NIA 062-01 N/A EQUIPMENT DESCRIPTION Retired Control Rod Drive Nozzle #3 DESCR-Pi'IPN OF CONDITION and PROBABLE CAUSE (if known) Summarize any attachments. Identify what, when, where, why, how.
0 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 I
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.
T 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)
_'J Self-Revealed ATTACHMENTS Quality Org Inibated LI Yes I
Individual/Work Group
-1 Internal Oversight Quality Org Follow-up El Yes D No D Supervision/Management
_71 External Oversight Yes l" No ORIGINATOR ORGANIZATION iDATE jSUPERVISOR DATE
'PHONE EXT.
LANG, T LCM 9/5/2002 LANG, T 9/5/2002 8116 SRO EQUIPMENT EVALUATION IMMEDIATE ORGANIZATION MODE CHANGE p
REVIEW i OPERABLE REQUIRED
- INVESTIGATION REQUIRED NOTIFIED RESTRAINT L
[IYes i:] No I Yes -
No R N/A El Yes W No DI Yes
. No WA Yes V No A
MOOD ASSOCIATED TECH SPEC NUMBER(S)'
ASSOCIATED LCO ACTION STATEMENT(S)
T
- 2 O
DECLARED REPORTABLE?
, One Hour NiA APPLICABLE UNIT(S)
NNOPERABLE (Oate/Time) :)yes
_]No
!Ijr.H-.u-NA.
N/A "Eval Required Other N/A
' U1
" 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.
I N
Current Mode - Unit I Power Level - Unit I Current Mode - Unit 2 i Power Level - Unit 2 S
DEF 0
SRO - UNITI SIRO - UNIT 2 DATE Pierson, J 9/7/2002 Page 1 of 2 I-