Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L]...

23
NExTera" EN ERGY2MOý ,-ý;ýARNOLD February 25, 2010 NG-10-0094 10 CFR 50.55a U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations Reference: 1. Letter, Richard L. Anderson (NextEra Energy Duane Arnold, LLC) to Document Control Desk (USNRC), Relief Request for 1st Period Limited Weld Examinations, dated July 30, 2009, NG-09- 0539 (ML073320185) Reference 1 provided a request for relief regarding the 1st period limited weld examinations. This relief is requested for the Fourth Ten year Interval of the Inservice Inspection Program for the Duane Arnold Energy Center (DAEC), which ends on February 21, 2014. In an email dated January 26, 2010, the Staff issued a request for additional information regarding Reference 1. The response to this email is provided in the enclosure to this letter. NextEra Energy Duane Arnold, LLC requests approval of the requests of Reference 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. Costanzo Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC Jt -4 I NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324

Transcript of Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L]...

Page 1: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

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

Page 2: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

NG-10-0094"February 25, 2010Page 2 of 2

Enclosure

cc: Administrator, Region III, USNRCProject Manager, DAEC, USNRCSenior Resident Inspector, DAEC, USNRC

Page 3: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Enclosureto NG-10-0094

Page 1 of 3

Enclosure

Response to Request for Additional Information Related to Relief Request for1st Period Limited Weld Examinations

Page 4: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

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.

Page 5: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

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.

Page 6: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Attachment 1to NG-10-0094

Attachment 1Weld Identification

2 Pages Follow

Page 7: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

o

0

,I

41nl

1.2-is \i~ 2oe~RMR-Jl I RMP-JJ

RECIRCULATION MANIFOLD "t" // RISERS E, FGH

0N

I&0o

a

'I

RMA- RRE-1 RRF-, RRG-1 RRH-83I 1Sut

I 'ISO. NO. I.2-20

Page 8: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

U'

N

C,)N

N

N

U-'

-;,

lb

NA

(LI

IU

I-

-~ j CZI

O]C-

-u Ic

0

rn

m

ri1

0~m

c-

m

U-

_u0--U

C

m

RMB-J12

RECZIRCULRTION MANIFOLD " B'" R I SE RS

RI11B-Ji

A, B, C, ED

P&I0 BECH-F1116APED 831-9

RMB / RRR-, RRB-, RRC-, RRD-SS, 16" 10 it

ISO. NO. 1.2-22

2/1212010 -ISSO-1.2-22.dgn

Page 9: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Attachment 2to NG-10-0094

Attachment 2Welds Scheduled for Examination

2 Pages Follow

Page 10: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

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

O11.0L-

0U.

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

Page 11: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

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,

00U. U.n w

NIli

0U.

0U.

PIPE - 90 DEGREE LONG RADIUS

R1.16-2 RRD-JO05 ELBOW . . . ... . . ... . . .

1 RR

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

ISI S - - -

R-A 4 -) I N F i

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

Page 12: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Attachment 3--:to NG-10-0094

Attachment 33rd Interval History for Item Number R1.16

5 Pages Follow

Page 13: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

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

(0

U-

0 0LL U.6 6x

. 0 7 0

0 0e'

LL L

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

AUG

OWN

PRE

c

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

Page 14: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Duane Arnold Nuclear Plant3rd Interval

66U_ U_Ix of

t0

6LLw-

700 0Category,Item No.,Class

Summary No.CompIDSystem

Outage I Scope / MethodType / Procedure

Dwg/ISO No.Comp. Desc.Code Case

Cb

LJLw

0en0U..

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

c

2/12/2010 ScheduleWorks V.8.1 Page 2 - 5

Page 15: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Duane Arnold Nuclear Plant3rd Interval

6LL.

V0 (0

6 6U- L

6 u~- LLý W -x

Category,Item No.,Class

Summary No.Comp)DSystem

Outage I Scope I MethodType / Procedure

Dwg/ISO No.Comp. Desc.Code Case

(06 700 LLO

(0'0 uOu-q.L

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

Page 16: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Duane Arnold Nuclear Plant3rd Interval

6LLw•

6U-LI.

(,

6LLw•Category,

Item No.,Class

Summary No.ComplDSystem

Outage / Scope / MethodType I Procedure

Dwg/ISO No.Comp. Desc.Code Case

(0

0L1~

6U.w,

co

0

,- M~ - 0C& , & C

1O0 70U- 0 U

1 RR OWN . . . ... . . ... . . .

PRE . . . ... . . ... . . .

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

E C

C

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

Page 17: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 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-

U-T

CT-0)0)

rYrw

,-0

L0 U

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

Page 18: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Attachment 4to NG-10-0094

Attachment 44th Interval History for Item Number R1.16

5 Pages Follow

Page 19: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

6Ou-

(0(N10U- 0

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

Page 20: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Duane Arnold Nuclear Plant4th Interval

0

QLLo-

(0

6U-tY

(NJ

0LLO-Category,

Item No.,Class

Summary No.ComplDSystem

Outage / Scope / MethodType / Procedure

Dwg/ISO No.Comp. Desc.Code Case

RFO-21 / PSI/PT/ /ACP1211.30 OWN1 RR

PRE - c

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

ISIAUG

st

2/19/2010 ScheduleWorks V.8.1 Page 2 - 5

Page 21: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

V

O- F0." 0

r L"

04

0UL-o

(1)046ILx,Category,

Item No.,Class

Summary No.ComplDSystem

Outage / Scope / MethodType / Procedure

Dwg/ISO No.Comp. Desc.Code Case

1 RR OWN

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

OWN

1 RR

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

PIPE - SAFEEND

ISI

AUG

OWN

c - - -

2/19/2 010 ScheduleWorks V.8.1 Page 3 - 5

Page 22: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

Duane Arnold Nuclear Plant4th Interval

5Cýj00 LOOw o

(i-

(NJ

0Ii-

60:hLni"Category,

Item No.,Class

Summary No.ComplDSystem

Outage / Scope / MethodType / Procedure

Dwg/ISO No.Comp. Desc.Code Case

PRE c

History: Outage/Report/Procedure Method/Status/Remarks

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

RR

RFO-23 / ISI / / / 0 1.2-20 SHT-01

PIPE

ISI

AUG

OWN

PRE

5 s

2/19/2 010 ScheduleWorks V.8.1 Page 4 - 5

Page 23: Duane Arnold - Response to Request for Additional ...R-A 120500-RI RFO-22 / ISI IUT/ ACP1211.20L] 1.2-20 SHT-01 ISI - - - ---PIPE -90 DEGREE LONG RADIUS R 1 .1 6 -2 R R E -J 0 0 5

0

LL

Onr

0LLof

(NJ

0U-w 0

U-

Cif

Category,Item No.,Class

Summary No.ComplDSystem

Outage / Scope / MethodType / Procedure

Dwg/ISO No.Comp. Desc.Code Case

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