NExTera"EN ERGY2MOý
,-ý;ýARNOLD
February 25, 2010 NG-10-009410 CFR 50.55a
U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555-0001
Duane Arnold Energy CenterDocket 50-331License No. DPR-49
Response to Request for Additional Information Related to Relief Request for 1stPeriod Limited Weld Examinations
Reference: 1. Letter, Richard L. Anderson (NextEra Energy Duane Arnold,LLC) to Document Control Desk (USNRC), Relief Request for 1stPeriod Limited Weld Examinations, dated July 30, 2009, NG-09-0539 (ML073320185)
Reference 1 provided a request for relief regarding the 1st period limited weldexaminations. This relief is requested for the Fourth Ten year Interval of theInservice Inspection Program for the Duane Arnold Energy Center (DAEC), whichends on February 21, 2014.
In an email dated January 26, 2010, the Staff issued a request for additionalinformation regarding Reference 1. The response to this email is provided in theenclosure to this letter.
NextEra Energy Duane Arnold, LLC requests approval of the requests ofReference 1 by June 30, 2010.
This letter contains no new commitments nor revises any previous commitments.
If you have any questions, please contact Steve Catron at (319) 851-7234.
s opher R. CostanzoVice President, Duane Arnold Energy CenterNextEra Energy Duane Arnold, LLC Jt -4 I
NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324
NG-10-0094"February 25, 2010Page 2 of 2
Enclosure
cc: Administrator, Region III, USNRCProject Manager, DAEC, USNRCSenior Resident Inspector, DAEC, USNRC
Enclosureto NG-10-0094
Page 1 of 3
Enclosure
Response to Request for Additional Information Related to Relief Request for1st Period Limited Weld Examinations
Enclosureto NG-10-0094
Page 2 of 3
Response to Request for Additional Information Related to Relief Request for1st Period Limited Weld Examinations
NRC Question #1:
Table A from the Enclosure to the licensee's July 30, 2009 submittal lists a CategoryR-A exam for a R1.16 Item Number, and two welds, RMA-J004 and CUA-J024, with50% coverage. Please identify clearly on the Isometric Drawings No. 1.2-20 and1.2-22 which is the RMA-J004 weld that was inspected on Feb. 8, 2009 as well asthe other seven manifold to riser welds that are considered comparable to RMA-J004. Have any of the eight manifold to riser welds been previously inspected aspart of the ISI program?
NextEra Energy Duane Arnold Response:
Please refer to Attachment 1 for clarification of the weld identification. None of theeight manifold to riser welds have been previously inspected as part of the ISIprogram. However, two welds were examined in accordance with Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping." Those twowelds are RMA-J002 and RMA-J008; both welds were examined during RefuelingOutage 17 in 2001 with no recordable indications.
NRC Question #2:
The staff notes that many of the welds shown in the Isometric Drawings No. 1.2-20and 1.2-22 have had weld overlays applied to repair cracking and/or leaks. Discussthe issues that will dictate which welds will be included in the 4th interval Risk-Informed inspection plan. A list of the inspection history for other category R-A, ItemR1.16 welds in the Reactor Coolant Recirculation (RCR) System would be helpful.
NextEra Energy Duane Arnold Response:
NextEra Energy Duane Arnold, LLC has received approval to use the EPRImethodology for Risk-Informed Inservice Inspection for the 4 th inspection interval(ML070090357).
The following matrix is from the EPRI Revised Risk-Informed Inservice InspectionEvaluation Procedure TR-1 12657 Rev. B-A. "Risk-Informed Inservice InspectionEvaluation Procedure." The subject welds are Category 2 based on theconsequence and degradation mechanisms applied.
Enclosureto NG-10-0094
Page 3 of 3
CONSEQUENCES OF PIPE RUPTUREPOTENTIAL FOR IMPACTS ON CONDITIONAL CORE DAMAGE PROBABILITY
PIPE RUPTURE AND LARGE EARLY RELEASE PROBAB[LITY
PER DEGRADATION MECHANISMSCREENING CRITERIA
NONE LOW MEDIUM HIGH
HIGH LOW MEDIUM HIGH :HIGH!FLOW ACCELERATED CORROSION Category 7 Category 5 Category 3 Category 1
MEDIUM LOW LOW MEDIUM HIGHOTHER DEGRADATION MECHANISMS Category 7 Category 6 Category 5 Category 2
LOW LOW LOW LOW MEDIUMNO DEGRADATION MECHANISMS Category 7 Category 7 Category 6 Category 4
Figure 3-2EPRI Matrix for Segment Risk Characterization
The EPRI Methodology states that for risk Category 2, 25% of the total number ofcomponents shall be inspected (see TR-1 12657 page 3-57). DAEC has a total of 69Category 2 welds that were previously identified as Cat B-J welds; 18 of those 69welds are scheduled for examination in the 4th 10 year interval as indicated in therelief request submittal.
Attachment 2 lists the 18 welds.
The following attachments show the inspection history for other category R-A, ItemR1.16 welds in the Reactor Coolant Recirculation (RCR) System as requested.
0 Attachment 3 - 3rd Interval history for Item number R1.16.
0 Attachment 4 -4th Interval history for Item number R1.16.
Attachment 1to NG-10-0094
Attachment 1Weld Identification
2 Pages Follow
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Attachment 2to NG-10-0094
Attachment 2Welds Scheduled for Examination
2 Pages Follow
Duane Arnold Nuclear Plant4th Interval
Period I Period 2 Period 3
Category,Item No.,Class
Summary No.CompiDSystem
Outage I Scope I MethodType I Procedure
Dwg/lSO No.Comp. Desc.Code Case
0 0LIL U.re re
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R-A 109700-RI 1.2-19A SHT-01 ISI----------------- s - - -
R 1 . 1 6 -2 R C A -J 0 4 3 T E E - P I P E C R O S S . . . . . . . . . . . . .
1 RC
R-A 117400-RI RFO-22 / ISI / / 1.2-20 SHT-01 ISI - - - - sR1.16-2 RMA-JO01 PIPE - PIPE CAP - - • - - - -
1 RM
R-A 117900-RI RFO-21 / ISI / UT/ I ACP1211.20D 1.2-20 SHT-01 ISI - c . . . . . . . - -c
MANIFOLD TO PIPE WELD OFF OF THER 1 .1 6 -2 R M A -J 0 0 4 R E C IR C U L A T IO N M A N . . . . . . . . . . . . .
1 RM
R-A 119100-RI RFO-21 /ISI/IUT/ /ACP1211.200 1.2-20SHT-01 ISI - c . . . . . ... . . .
R1.16-2 RMA-J011 PIPE - PIPE CAP . . . . . . . ... . . .
1 RM
R-A 143600-RI RFO-22 / ISI / UT / /ACP1211.200 1.2-22 SHT-01 ISI - - - - sPIPE - 90 DEGREE LONG RADIUS
R1.16-2 RRA-J005 ELBOW
1 RR
R-A 145200-RI RFO-20-1 / ISI /IUT / UT / 1.2-22 SHT-01 ISI c - - . . . . ... . . .ACP1211.200 PIPE - 90 DEGREE LONG RADIUS
R1.16-2 RRB-J005 RFO-20-1 / ISI / UT / UT / ELBOW . . . . . . . ... . . .
1 RR ACP1211.200
R-A 146500-RI RFO-22 / ISI / IT ACP1211.200 1.2-22 SHT-01 ISI - - - - s90 DEGREE LONG RADIUS ELBOW -
R1.16-2 RRC-J004 PIPE
1 RR
R-A 146800-RI RFO-22 / ISI I UT/ I ACP1 211.200 1.2-22 SHT-01 ISI - .. .- - - -
R 1 . 1 6 -2 R R C -J O 0 4 A P I P E . . . . . . . . .- - -
1 RR
R-A 147000-RI RFO-22 ISI UT IACP1211.200 1.2-22 SHT-01 ISI -s .....- - - -
PIPE - 90 DEGREE LONG RADIUSR1.16-2 RRC-JO05 ELBOW . . . . . . . .. . . . .
1 RR
R-A 145500-RI RFO-23/ISI / / /] 1.2-22 SHT-01 ISI S - -
2/12/2010 ScheduleWorks V. 8.1 Page 1 -- 2
Duane Arnold Nuclear Plant4th Interval
Period I Period 2 Period 3
Category,Item No.,Class
Summary No.CompIDSystem
Outage I Scope I MethodType I Procedure
DwgItSO No.Comp. Desc.Code Case
NT,
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PIPE - 90 DEGREE LONG RADIUS
R1.16-2 RRD-JO05 ELBOW . . . ... . . ... . . .
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R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - - --
PIPE - 90 DEGREE LONG RADIUSR 1 .1 6 -2 R R E -J 0 0 5 E L B O W . . . . . - . . . . - - - -
1 RR
R-A 12 1300-R I R FO -20-1 / IS I / IU T / U T I 1.2-20 S H T-01 IS I c . . . . . . . . . . . . .
R 1.16-2 R R F -FO0 2A A C P 12 11.38 0 P IP E - S A F E E N D . . . . . . . . . . . . . .
1 RR RFO-20-1 / ISI / UT / UT/ACP1211.380RFO-20-1 / ISI / UT I UTIACP1211.380]
R-A 121500-RI RFO-20-1 / ISI / UT / UTI 1.2-20 SHT-01 ISI C
R1.16-2 RRF-J003 ACP1211.200 PIPE .. . . ... . . ... . . .
1 RR RFO-20-1 / ISI / UT / UT/ACP1211.200
R-A 122000-RI RFO-22 / ISI / UT / / ACP1211.200 1.2-20 SHT-01 ISI - - - - s
PIPE - 90 DEGREE LONG RADIUSRI .16-2 RRF-J005 ELBOW . . . ... . . ... . . .
1 RR
R-A 123000-RI RFO-23 / ISI/ I// 1.2-20 SHT-01 ISI-- -------- s
R1.16-2 RRG-J003 PIPE . . . ... . . ... . . .1 RR
R-A 123500-RI RFO-22 /ISI/UT/ / ACP1211.201o 1.2-20 SHT-01 ISl - -- - - sPIPE - 90 DEGREE LONG RADIUS
R1.16-2 RRG-J005 ELBOW
1 RR
7-~
R-AR1.16-21
123900-RIRRG-J007RR
RFO-22 / ISI I / / 01 1.2-20 SHT-01PIPE
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000UUU-RI RI-U-22 / I1SI / UT / AUIP121 1.200 1.2-20 S-HT1-01PIPE - 90 DEGREE LONG RADIUSELBOWR1.16-2
IRRH-.J0o5RR
ISI S
2/12/2010 ScheduleWorks V. 8.1 Page 2 - 2
Attachment 3--:to NG-10-0094
Attachment 33rd Interval History for Item Number R1.16
5 Pages Follow
Duane Arnold Nuclear Plant3rd Interval
6U-o 6 6
Of ofCategory,Item No.,Class
Summary No.CompIDSystem
Outage I Scope / MethodType / Procedure
Dwg/iSG No.Comp. Desc.Code Case
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R-A 128300-RI 1.2-21A SHT-01 ISI
R1.16-2 RCB-J009 PIPE AUG - c . ... . . ... . . .
1 RC OWN
PRE
History: Outage/ReportIProcedure Method/Status/Remarks
RFO-15 /198078 / PDI-UT2 UT45/NOREC/R-A 117400-RI 1.2-20 SHT-01 ISI -.......--- c----------
R1.16-2 RMA-JO01 PIPE - PIPE CAP AUG . . . ... . . ... . . .
1 RM OWN . . . .. . . . ... . . .
PRE . . . ... . . ... . . .
History: Outage/Report/Procedure Method/Status/Remarks
RFO-18 /103041 /1211.20 UT/NOREC/R-A 117700-RI 1.2-20 SHT-01 SI . . . .. . . . ... . . . .
R1.16-2 RMA-J002 RECIRCULATION MAN AUG- ------ c----------c
1 RM OWN
PRE . . . ... . . ... . . .
History: Outage/Report/Procedure Method/Status/Remarks
RFO-17 / 101065 / 1211.20 UT45/NOREC /R-A 118700-RI 1.2-20 SHT-01 Is[
R1.116-2 RMA-J008 RECIRCULATION MAN AUG- c------------
1 RM OWN
PRE
History: Outage/Report/Procedure Method/Status/Remarks
RFO-17 / 101066 / 1211.20 UT45/NOREC /R-A 119100-RI 1.2-20 SHT-01 ISI . . . ... . . ... . . .
R1.16-2 RMA-J011 PIPE - PIPE CAP AUG c . . ... . . ... . . .
1 RM OWN - - - - -
PRE . . . ... . . ... . . -
History: Outage/Report/Procedure Method/Status/Remarks
RFO-14 /196075 / PDI-UT2 UT-45/NOREC / . I I . I
R-AR1.16-2I1
142700-RIRRA-F002RR
1.2-22 SHT-01
SAFEEND - NOZZLE
ISI
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OWN
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History: Outage/Report/ProcedureRFO-16 / 199052 / GE-UT-209V7
RFO-16 / 199052 / GE-UT-209V7
RFO-16 /199052 / GE-UT-209V7
R-A 14 3600-RI
Method/Status/Remarks
UT60RL/NOREC /
UT70RLUNOREC /
UT45RL/NOREC /I I
1.2-22 SHT-01 ISI
2/12/2010 ScheduleWorks V.8.1 Page 1 --5
Duane Arnold Nuclear Plant3rd Interval
66U_ U_Ix of
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Outage I Scope / MethodType / Procedure
Dwg/ISO No.Comp. Desc.Code Case
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R1.16-2 RRA-J005 ELBOW AUG- ------ c----------c
1 RR OW N . . . .. . . . .. . . . .
PRE . . . ... . . ... . . .
History: OutagelReport/Procedure Method/StatuslRemarks
RFO-17 / 101076 / 1211.20 UT45/S/NOREC /
RFO-17 /101076 / 1211.20 UT70/S/NOREC /
R-A 144300-RI 1.2-22 SHT-01 ISI
R1.16-2 RRB-F002 SAFEEND - NOZZLE AUG - - c - - - -
1 RR OWN . . . .. . . . .. . . . .
PRE
History: OutagelReportlProcedure Method/Status/Remarks
RFO-16 / 199053 / GE-UT-209V7 UT70RUREC /
RFO-16 / 199053 / GE-UT-209V7 UT45RUJREC /
RFO-16 /199053 / GE-UT-209V7 UT60RUIREC /
R-A 145700-RI 1.2-22 SHT-01 ISI
R1.16-2 RRB-J007 PIPE-PIPE AUG- ------ c----------c
1 RR OWN . . . ... . . ... . . .
PRE
History: Outage/Report/Procedure Method/Status/Remarks
RFO-17 / 101078 / 1211.20 UT45/S/REC /
RFO-17 /101078 /1211.20 UT60/S/REC /
R.A 145900-RI 1.2-22 SHT-01 ISI
R1.16-2 RRC-F002 SAFEEND - NOZZLE AUG - - - - c
1 RR OWN . . . .. . . . .. . . . .PRE . . . . . .. . . . . . . . .
History: Outage/Report/Procedure Method/Status/Remarks
RFO-16-1 / 199116 / GE-UT-209V7 UT60RLUINSIG /
RFO-16-1 /199116 / GE-UT-209V7 UT70RL/INSIG /
RFO-16-1 / 199116 / GE-UT-209V7 UT45RL/INSIG /
R-A 146500-RI 1.2-22 SHT-01 ISI . . . .. . . . .. . . . .
R1.16-2 RRC-J004 PIPE AUG - - - - c
1 RR OWN - - - , - -
- P R E . . . . . . . . . . . . . .
History: Outage/Report/Procedure Method/Status/Remarks
RFO-16-1 /199044 / 1211.20 R.1 UT45/NOREC I I _ II ____
R-A
R1.16-21
146800-RIRRC-JO04A
RR
1.2-22 SHT-01PIPE
ISIAUGOWNPRE
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2/12/2010 ScheduleWorks V.8.1 Page 2 - 5
Duane Arnold Nuclear Plant3rd Interval
6LL.
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Dwg/ISO No.Comp. Desc.Code Case
(06 700 LLO
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History: OutagelReport/Procedure Method/Status/Remarks
RFO-1 8/ 103057 /1211.20 UT/NOREC _
R-A 147000-RI 1.2-22 SHT-01 SI - -.. . ..- "-
R1.16-2 RRC-J005 ELBOW AUG - - - - c- - ------
1 R R O W N . . . . . . . . . . . . . .PRE,
History: Outage/Report/Procedure Method/Status/Remarks
RFO-16-1 /199045 / 1211.20 R.1 UT45/NOREC /
R-A 147600-RI 1.2-22 SHT-01 ISI E E
R1.16-2 RRD-F002 SAFEEND - NOZZLE AUG c -.-------- - -- - ---- -
1 R R O W N . . . . . . . . . . . . .. . .
PRE -------------
History: Outage/Report/Procedure Method/StatuslRemarks,
RFO-14 / 196080 / PDI UT-45/NOREC /
RFO-14 / / UT-225 UT-60//
RFO-16 / 199157 / GE-UT-209V7 UT70RL/REC /RFO-16 / 199157 / GE-UT-209V7 UT45RLJREC /
RFO-16 /199157 / GE-UT-209V7 UT60RLJREC /
R-A 148500-RI 1.2-22 SHT-01 ISI[ .- . .-. .-.-- c -
R1.16-2 RRD-J005 ELBOW AUG .. -.....-.- ---.-. c -
1 RR OW N . . . .. . . . .. . . .PRE . . . . . . . . . . . . . .
History: Outage/Report/Procedure Method/Status/Remarks
RFO-19-1 / 105058 / UT/NOREC /RFO-19-1 / 105058 / UT/NOREC /
RFO-19-1 / 105058 / UT/NOREC /
R-A 119600-RI 1.2-20 SHT-01 ISI - E E . --.. .----.--
R1.16-2 RRE-F002 SAFEEND - NOZZLE AUG c ............
1 RR OW N . . . . . . . . . . . . . .PRE
History: Outage/Report/Procedure Method/StatuslRemarks
RFO-15 / 198071 / UT-209 UT60/NOREC /
RFO-15 / 198071 / UT-209 UTRL/NOREC /
RFO-15 /198071 / UT-209 UT45/NOREC IRFO-16 / 199153 / GE-UT-209V7 UT45RI/NOREC /
RFO-16 /199153 / GE-UT-209V7 UT60RL/NOREC /
RFO-16 /199153 / GE-UT-209V7 UT70RL/NOREC /
R-A 120500-RI
R1.16-2 RRE-JO05
1.2-20 SHT-01ELBOW
ISI cAUG I . . . .. I. iii ii -
2/12/2010- ScheduleWorks V.8.1 Page 3 - 5
Duane Arnold Nuclear Plant3rd Interval
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History: Outage/Report/Procedure Method/Status/Remarks
RFO-18 /103043 / 1211.20 UT/NOREC /
R-A 121100-RI 1.2-20 SHT-01 .. Is[ ........--------- c -
R1.16-2 RRF-F002 SAFEEND- NOZZLE AUG c - B c - - c -
1 RR OWN . . . ... . . ... . . .
PRE . . ..... . . ... . . .
History: Outage/ReportlProcedure Method/StatuslRemarks
RFO-14 /196077 / PDI-UT-225 UT-45/NOREC I
RFO-16 /199154 / GE-UT-209V7 UT70RUJREC /
RFO-16 / 199154 / GE-UT-209V7 UT60RL/REC /
RFO-16 /199154 / GE-UT-231V1 UT45RLJREC /
RFO-16 /199154 1 GE-UT-231V1 UT60RL/REC /
RFO-16 /199154 / GE-UT-231V1 UT70RUREC /
RFO-16 /199154 / GE-UT-209V7 UT45RUREC /
RFO-17 /101068 / 1211.31 UT60/IJREC I
RFO-17 /101068 / 1211.33 UT60/IJREC /
RFO-17 /101068 / 1211.33 UT60/UREC /
RFO-17 /101068 / 1211.31 UT70/LJREC /
RFO-17 /101068 / 1211.33 UT45/UREC /
RFO-17 /101068 / 1211.33 UT45/IJREC /
RFO-19-1 / 105047 / UT-1 03 UT/NOREC /
RFO-19-1 /105047 / UT-1 03 UT/NOREC /
R-A 122000-RI 1.2-20 SHT-01 ISI-- c --- -- -- --
R1.16-2 RRF-J005 ELBOW AUG -. . .. ... . .- ... . . -
1 RR OWN - - .....
PRE - - - -.-.-.-. -. .
History: OutagelReport/Procedure Method/Status/Remarks
RFO-18 / 103059 / 1211.20 UT/NOREC I
R-AR1.16-21
122600-RIRRG-F002RR
1.2-20 SHT-01
SAFEEND - NOZZLE
ISIAUG
OWN
PRE
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History: OutagelReport/ProcedureRFO-16/ 199155 / GE-UT-209V7
RFO-16 /199155 1 GE-UT-209V7
RFO-16 /199155 / GE-UT-209V7RFO-19-1 / 105048 /
MethodlStatuslRemarks
UT70RL/INSIG I
UT60RL/INSIG /UT45RL/INSIG /UT/NOREC /
2/12/2 010 ScheduleWorks V.8.1 Page 4 - 5
Duane Arnold Nuclear Plant3rd Interval
Category,Item No.,Class
Summary No.CompIDSystem
Outage / Scope I MethodType / Procedure
Dwg/ISO No.Comp. Desc.Code Case
U- U- U-0 - U-
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RFO-19-1 /105048/ UT/NOREC /R-A 123000-RI 1.2-20 SHT-01 ISI - - .--- ..-.-.---- c
R1.16-2 RRG-J003 PIPE AUG . . . .. . . . ... . . .
1 RR, OWN
PRE
History: Outage/Report/Procedure Method/Status/Remarks
RFO-19-1 / 105049 / UT/NOREC /
RFO-19-1 / 105049 / UT/NOREC /
R-A 123500-RI 1.2-20 SHT-01 ISI------------ c----------
R1.16-2 RRG-J005 ELBOW AUG c
1 RR OWN
PRE
History: Outage/Report/Procedure Method/Status/Remarks
RFO-14 /196153 / PDI-UT2 UT-45/NOREC /
RFO-18 /103058 / 1211.20 UT/NOREC /
R-A 123900-RI 1.2-20 SHT-01 ISI ------------ c - - - - -
R1.16-2 RRG-J007 PIPE AUG
1 RR OWN
PRE
History: Outage/ReportlProcedure Method/Status/Remarks
RFO-18 /103045 / 1211.20 UT/NOREC /
R-A 124100-RI 1.2-20 SHT-01 ISI - E ... . . ... . . .
R1.16-2 RRH-F002 SAFEEND - NOZZLE AUG c
1 RR OWN
PRE
History: Outage/Report/Procedure Method/Status/Remarks
RFO-1 5/198076 / UT-209 UT60NOREC /
RFO-15 / 198076 / UT-209 UT45/NOREC /
RFO-16 /199156 / GE-UT-209V7 UT70RL/INSIG /
RFO-16 / 199156 / GE-UT-209V7 UT60RL/INSIG /
RFO-16 / 199156 / GE-UT-209V7 .UT45RL/INSIGR-AR1.16-21
125000-RIRRH-J005
RR
1.2-20 SHT-01ELBOW
ISIAUG
OWN
PRE
C
History: Outage/Report/ProcedureRFO-17 / 10106911211.20
RFO-17 /101069 / 1211.20
Method/Status/RemarksUT45/S/NOREC /
UT70/S/NOREC /
2/12/2010 ScheduleWorks V.8.1 Page 5 - 5
Attachment 4to NG-10-0094
Attachment 44th Interval History for Item Number R1.16
5 Pages Follow
6Ou-
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U-ofCategory,Item No.,Class
Summary No.ComplDSystem
Outage / Scope / MethodType / Procedure
Dwg/ISO No.Comp. Desc.Code Case
R-A 109700-RI 1.2-19A SHT-01 ISI------ - - -
R1.16-2 RCA-J043 TEE - PIPE CROSS AUG c1 RC OWN
PREHistory: Outage/Report/Procedure M ethod/StatuslRem arks
6 UT/Accept /
6 UT/Accept /R-A 117400-RI RFO-22 / ISI / /C 1.2-20 SHT-01 ISI - - - - sR1.16-2 RMA-JO01 PIPE - PIPE CAP AUG
1 RM OWN
PRER-A 117900-RI RFO-21 / ISI / UT /ACP1211.200 1.2-20 SHT-01 SI - cR1. 16-2 RMA-J004 RECIRCULATION MAN AUG
1 RM OWN
PREHistory: Outage/Report/Procedure Method/Status/Rem arks
/ Rev. 7 UT/Accept // Rev. 7 UT/Accept /
R-A 119100-RI RFO-21 /ISI/UT! /ACP1211.200 1.2-20 SHT-01 ISI - c
R1.16-2 RMA-J011 PIPE - PIPE CAP AUG - c1 RM OWN
PREHistory: Outage/Report/Procedure Method/Status/Remarks
/ Rev. 7 UT/Accept/
/ Rev. 7 UT/Accept/
R-A 142900-RI RFO-22 / AUG / UT/ / 1.2-22 SHT-01 ISIR1.16-2 RRA-FO02A ZetecOmniScanPA_03[1 PIPE - SAFEEND AUG - - - - s1 RR OWN
PRER-A 143600-RI RFO-22 / ISI / UT/ ACP1211.2011 1.2-22 SHT-01 ISI - - - - sR1.16-2 RRA-J005 ELBOW AUGI RR OWN
PRER-A 144500-RI RFO-21 / AUG / UT / / ACP1211.38D 1.2-22 SHT-01
RFO-21 / AUG / UT/ /Zetec_OmniScanPA_03L PIPE - SAFEEND
ISIAUG c
R1.16-2 RRB-FO02A
2/19/2010 ScheduleWorks V.8.1 Page 1 - 5
Duane Arnold Nuclear Plant4th Interval
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History: OutagelReportlProcedure MethodlStatuslRemarks
RFO-21 / PT-09-005 / ACP1 211.3/ Rev. 11 PT/Sat // Rev. 4 UT/Accept // Rev. 4 UT/Accept // Rev. 4 UT/Accept /ZetecOmniScanPA_03 / Rev. D UT/Accept /
/ Rev. 4 UT/Accept /R-A 145200-RI RFO-20-1 / ISI / UT / UT / 1.2-22 SHT-01 ISI cR1.16-2 RRB-J005 ACP1211.201 ELBOW AUG c1 RR RFO-20-1 / ISI / UT / UT / OWN
ACP1211.201] PRE
History: Outage/Report/Procedure M ethod/Status/Rem arks
6 UT/Accept /6 UT/Accept /6 UT/Accept /6 UT/Accept /
R-A 146100-RI RFO-22 / AUG / UT / UT/ 1.2-22 SHT-01 ISIR1.16-2 RRC-FO02A ZetecOmniScanPA_03Ei PIPE - SAFEEND AUG - - - - s1 RR OWN
PRER-A 146500-RI RFO-22 / ISI / UT / / ACP1211.200 1.2-22 SHT-01 ISI - - - - sR1.16-2 RRC-J004 PIPE AUG . . . ... . . ... . . .1 RR OWN
PRER-A 146800-RI RFO-22 / ISI / UT / / ACP1211.20[1 1.2-22 SHT-01 iSI - - - - sR1.16-2 RRC-JO04A PIPE AUG1 RR OWN
PRE
K-A 147000-RI-R1.1 6-2 RRC-J005
RFO-22 / ISI / UT / / ACP1 211.20E] 1.2-22 SHT-01ELBOW
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2/19/2010 ScheduleWorks V.8.1 Page 2 - 5
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PRER-A 147800-RI RFO-21 / AUG /UT/ /ACP1211.380 1.2-22 SHT-01 ISI
RFO-21 / AUG / UT/ / AUG - c
R1.16-2 RRD-FO02A ZetecOmniScanPA_030 PIPE - SAFEENDRFO-21 / PSI/PT/ / ACP1211.3 PI
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PRE - cHistory: Outage/Report/Procedure Method/Status/Remarks
RFO-21 / PT-09-004 / ACP1 211.3/ Rev. 11 PT/NRI // Rev. 4 UT/Accept // Rev. 4 UT/Accept /
/ Rev. 4 UT/Accept // Rev. 4 UT/Accept /
ZetecOmniScanPA_03 / Rev. D UT/Accept /R-A 148500-RI RFO-23 / ISI/ / /0 1.2-22 SHT-01 ISIl---------------- sR1.16-2 RRD-J005 ELBOW AUG1 RR OWN
PRER-A 119800-RI RFO-22 / AUG / UT / / 1.2-20 SHT-01 iSIR1.16-2 RRE-FO02A ZetecOmniScanPA_03[0 PIPE - SAFEEND AUG - - - - s1 RR OWN
PRER-A 120500-RI RFO-22 / ISI / UT/ /ACP1211.200 1.2-20 SHT-01 ISI - - - - sR1.16-2 RRE-J005 ELBOW AUG1 RR OWN
PRER-A 121300-RI
R1.16-2 RRF-FO02A
1 RR
RFO-20-1 / ISI / UT / UT /ACP1211.380RFO-20-1 / ISI / UT / UT /ACP1211.380RFO-20-1 / ISI / UT/UT/ACP1211.380RFO-20-1 / PSI / PT / PT /ACP1 211.301
1.2-20 SHT-01
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2/19/2 010 ScheduleWorks V.8.1 Page 3 - 5
Duane Arnold Nuclear Plant4th Interval
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9 PT/Accept /3 UT/Accept /3 UT/Accept /3 UT/Accept /
R-A 121500-RI RFO-20-1 / ISI / UT/UT/ 1.2-20 SHT-01 ISI cR1.16-2 RRF-J003 ACP1211.200 PIPE AUG1 RR RFO-20-1 / ISI / UT / UT / OWN
ACP1211.200 PRE
History: Outage/Report/Procedure Method/Status/Rem arks
6 UT/Accept /6 UT/Accept /
R-A 122000-RI RFO-22 / ISI / UT /ACP1211.200 1.2-20 SHT-01 iSI - - - - sR1.16-2 RRF-J005 ELBOW AUG - - - - t1 RR OWN
PRER-A 122800-RI RFO-21 / AUG /UT / ACP1211.380 1.2-20 SHT-01 ISIR1.16-2 RRG-FO02A RFO-21 / AUG/UT/ / PIPE - SAFEEND AUG -c c ..........
1 RR ZetecOmniScanPA_03[] OWNRFO-21 / PSI / PT/ /ACP1211.30 PRE - c
History: Outage/Report/Procedure Method/Status/Rem arks
/ Rev. 4 UT/Accept // Rev. 4 UT/Accept /
/ Rev. 4 UT/Accept // Rev. 4 UT/Accept /
ZetecOmniScanPA_03 / Rev. D UT/Accept /
RFO-21 / PT-09-002 / ACP1211.3/ Rev. 11 PT/Sat /
R-A
R1.16-21
123000-RI
RRG-J003
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RFO-23 / ISI / / / 0 1.2-20 SHT-01
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2/19/2 010 ScheduleWorks V.8.1 Page 4 - 5
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R-A 123500-RI RFO-22 / ISI / UT/ /ACP1211.20E1 1.2-20 SHT-01 ISI - - - - sR1.16-2 RRG-J005 ELBOW AUG - - - - t1 RR OWN
PRER-A 123900-RI RFO-22/ISI/ / / I 1.2-20 SHT-01 ISI - - - - s
R1.16-2 RRG-J007 PIPE AUG - - - - t1 RR OWN
PRER-A 124300-RI RFO-21 / AUG / UT / / ACP1211.380 1.2-20 SHT-01 ISIR1.1 6-2 RRH-FO02A RFO-21 / AUG / UT/ / PIPE - SAFEEND AUG - c1 RR ZetecOmniScanPA_030 OWN
RFO-21 / PSI / PT / / ACP1211.3[ PRE c
History: Outage/Report/Procedure Method/Status/Rem arks
ZetecOmniScanPA_03 / Rev. D UT/Accept /RFO-21 / PT-09-001 / ACP1 211.3 /Rev. 11 PT/Sat /
/ Rev. 4 UT/Accept // Rev. 4 UT/Accept // Rev. 4 UT/Accept // Rev. 4 UT/Accept /
R-AR1.16-21
125000-RIRRH-J005
RR
RFO-22 / ISI / UT / / ACP1211.200 1.2-20 SHT-01
ELBOWISI
AUG
OWN
PRE
5 - - -
t - - -
2/19/2010 ScheduleWorks V.8.1 Page 5 - 5