NG-10-0094, Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations

From kanterella
(Redirected from ML100680431)
Jump to navigation Jump to search

Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations
ML100680431
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 02/25/2010
From: Costanzo C
NextEra Energy Duane Arnold
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-10-0094
Download: ML100680431 (23)
v • d • e


Text

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 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

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

Administrator, Region III, USNRC Project Manager, DAEC, USNRC Senior Resident Inspector, DAEC, USNRC

Enclosure to NG-10-0094 Page 1 of 3 Enclosure Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations

Enclosure to NG-10-0094 Page 2 of 3 Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations NRC Question #1:

Table A from the Enclosure to the licensee's July 30, 2009 submittal lists a Category R-A exam for a R1.16 Item Number, and two welds, RMA-J004 and CUA-J024, with 50% coverage. Please identify clearly on the Isometric Drawings No. 1.2-20 and 1.2-22 which is the RMA-J004 weld that was inspected on Feb. 8, 2009 as well as the 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 as part of the ISI program?

NextEra Energy Duane Arnold Response:

Please refer to Attachment 1 for clarification of the weld identification. None of the eight manifold to riser welds have been previously inspected as part of the ISI program. However, two welds were examined in accordance with Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping." Those two welds are RMA-J002 and RMA-J008; both welds were examined during Refueling Outage 17 in 2001 with no recordable indications.

NRC Question #2:

The staff notes that many of the welds shown in the Isometric Drawings No. 1.2-20 and 1.2-22 have had weld overlays applied to repair cracking and/or leaks. Discuss the 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, Item R1.16 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 EPRI methodology for Risk-Informed Inservice Inspection for the 4 th inspection interval (ML070090357).

The following matrix is from the EPRI Revised Risk-Informed Inservice Inspection Evaluation Procedure TR-1 12657 Rev. B-A. "Risk-Informed Inservice Inspection Evaluation Procedure." The subject welds are Category 2 based on the consequence and degradation mechanisms applied.

Enclosure to NG-10-0094 Page 3 of 3 CONSEQUENCES OF PIPE RUPTURE POTENTIAL FOR IMPACTS ON CONDITIONAL CORE DAMAGE PROBABILITY PIPE RUPTURE AND LARGE EARLY RELEASE PROBAB[LITY PER DEGRADATION MECHANISM SCREENING 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 HIGH OTHER DEGRADATION MECHANISMS Category 7 Category 6 Category 5 Category 2 LOW LOW LOW LOW MEDIUM NO DEGRADATION MECHANISMS Category 7 Category 7 Category 6 Category 4 Figure 3-2 EPRI Matrix for Segment Risk Characterization The EPRI Methodology states that for risk Category 2, 25% of the total number of components shall be inspected (see TR-1 12657 page 3-57). DAEC has a total of 69 Category 2 welds that were previously identified as Cat B-J welds; 18 of those 69 welds are scheduled for examination in the 4th 10 year interval as indicated in the relief request submittal. lists the 18 welds.

The following attachments show the inspection history for other category R-A, Item R1.16 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.

to NG-10-0094 Weld Identification 2 Pages Follow

o 0

,I 4

1 nl 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

U' N

C,)

N N

N U-'

lb NA (LI IU I-

-~ j C ZI O]

C-

-u Ic 0

rn m

ri1 0~

m c-m U-

_u 0-

-U C

m RMB-J12 RECZIRCULRTION MANIFOLD

" B'"

R I SE RS RI11B-Ji A, B, C, ED P&I0 BECH-F1116 APED 831-9 RMB

/

RRR-,

RRB-,

RRC-,

RRD-SS, 16" 10 it ISO.

NO.

1.2-22 2/1212010

-ISSO-1.2-22.dgn to NG-10-0094 Welds Scheduled for Examination 2 Pages Follow

Duane Arnold Nuclear Plant 4th Interval Period I Period 2 Period 3

Category, Item No.,

Class Summary No.

CompiD System Outage I Scope I Method Type I Procedure Dwg/lSO No.

Comp. Desc.

Code Case 0 0 LIL U.

re re O

11.

0L-0 U.

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 s

R1.16-2 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 THE R 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 s

PIPE - 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 s

90 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 RADIUS R1.16-2 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 Plant 4th Interval Period I Period 2 Period 3

Category, Item No.,

Class Summary No.

CompID System Outage I Scope I Method Type I Procedure DwgItSO No.

Comp. Desc.

Code Case NT, 00 U.

U.

n w N

Ili 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 RADIUS R 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 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/

ACP1211.380 RFO-20-1 / ISI / UT I UTI ACP1211.380]

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 RADIUS RI.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 s

PIPE - 90 DEGREE LONG RADIUS R1.16-2 RRG-J005 ELBOW 1

RR 7-~

R-A R1.16-2 1

123900-RI RRG-J007 RR RFO-22 / ISI I / / 01 1.2-20 SHT-01 PIPE ISI S

R-A 4 -)

I N

F i

000UUU-RI RI-U-22 / I1SI / UT

/ AUIP121 1.200 1.2-20 S-HT1-01 PIPE - 90 DEGREE LONG RADIUS ELBOW R1.16-2 I

RRH-.J0o5 RR ISI S

2/12/2010 ScheduleWorks V. 8.1 Page 2 - 2 to NG-10-0094 3rd Interval History for Item Number R1.16 5 Pages Follow

Duane Arnold Nuclear Plant 3rd Interval 6

U-o 6 6 Of of

Category, Item No.,

Class Summary No.

CompID System Outage I Scope / Method Type / Procedure Dwg/iSG No.

Comp. Desc.

Code Case (0

U-0 0 LL 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-A R1.16-2 I1 142700-RI RRA-F002 RR 1.2-22 SHT-01 SAFEEND - NOZZLE ISI AUG OWN PRE c

History:

Outage/Report/Procedure RFO-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 Plant 3rd Interval 66 U_ U_

Ix of t0 6

LL w-700 0

Category, Item No.,

Class Summary No.

CompID System Outage I Scope / Method Type / Procedure Dwg/ISO No.

Comp. Desc.

Code Case Cb LJL w

0 en 0

U..

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 R1.16-2 1

146800-RI RRC-JO04A RR 1.2-22 SHT-01 PIPE ISI AUG OWN PRE c

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

Duane Arnold Nuclear Plant 3rd Interval 6

LL.

V0 (0

6 6 U-L 6

u~-

LL

ý W

-x

Category, Item No.,

Class Summary No.

Comp)D System Outage I Scope I Method Type / Procedure Dwg/ISO No.

Comp. Desc.

Code Case (0

6 70 0 LLO (0

'0 u

Ou-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 I RFO-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-01 ELBOW ISI c

AUG I.

.. I.

iii ii 2/12/2010-ScheduleWorks V.8.1 Page 3 - 5

Duane Arnold Nuclear Plant 3rd Interval 6

LL w* 6 U-LI.

(,

6 LL w*

Category, Item No.,

Class Summary No.

ComplD System Outage / Scope / Method Type I Procedure Dwg/ISO No.

Comp. Desc.

Code Case (0

0L1~

6 U.w, co 0

M~ -

0 C&

C 1O0 7 0U-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-A R1.16-2 1

122600-RI RRG-F002 RR 1.2-20 SHT-01 SAFEEND - NOZZLE ISI AUG OWN PRE E

C C

History:

OutagelReport/Procedure RFO-16/ 199155 / GE-UT-209V7 RFO-16 /199155 1 GE-UT-209V7 RFO-16 /199155 / GE-UT-209V7 RFO-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 Plant 3rd Interval

Category, Item No.,

Class Summary No.

CompID System Outage / Scope I Method Type / Procedure Dwg/ISO No.

Comp. Desc.

Code Case U-U- U-0 U-U-T CT

-0) 0)

rY rw

,-0 L

0 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/INSIG R-A R1.16-2 1

125000-RI RRH-J005 RR 1.2-20 SHT-01 ELBOW ISI AUG OWN PRE C

History:

Outage/Report/Procedure RFO-17 / 10106911211.20 RFO-17 /101069 / 1211.20 Method/Status/Remarks UT45/S/NOREC /

UT70/S/NOREC /

2/12/2010 ScheduleWorks V.8.1 Page 5 - 5 to NG-10-0094 4th Interval History for Item Number R1.16 5 Pages Follow

6Ou-(0 (N10 U-0 U-of

Category, Item No.,

Class Summary No.

ComplD System Outage / Scope / Method Type / 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 c

1 RC OWN PRE History:

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 s

R1.16-2 RMA-JO01 PIPE - PIPE CAP AUG 1

RM OWN PRE R-A 117900-RI RFO-21 / ISI / UT /ACP1211.200 1.2-20 SHT-01 SI c

R1. 16-2 RMA-J004 RECIRCULATION MAN AUG 1

RM OWN PRE History:

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 c

1 RM OWN PRE History:

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 ISI R1.16-2 RRA-FO02A ZetecOmniScanPA_03[1 PIPE - SAFEEND AUG s

1 RR OWN PRE R-A 143600-RI RFO-22 / ISI / UT/

ACP1211.2011 1.2-22 SHT-01 ISI s

R1.16-2 RRA-J005 ELBOW AUG I

RR OWN PRE R-A 144500-RI RFO-21 / AUG / UT / / ACP1211.38D 1.2-22 SHT-01 RFO-21 / AUG / UT/ /

Zetec_OmniScanPA_03L PIPE - SAFEEND ISI AUG c

R1.16-2 RRB-FO02A 2/19/2010 ScheduleWorks V.8.1 Page 1 - 5

Duane Arnold Nuclear Plant 4th Interval 0

QLL o-(0 6

U-tY (NJ 0

LL O-

Category, Item No.,

Class Summary No.

ComplD System Outage / Scope / Method Type / Procedure Dwg/ISO No.

Comp. Desc.

Code Case RFO-21 / PSI/PT/ /ACP1211.30 OWN 1

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 c

R1.16-2 RRB-J005 ACP1211.201 ELBOW AUG c

1 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 ISI R1.16-2 RRC-FO02A ZetecOmniScanPA_03Ei PIPE - SAFEEND AUG s

1 RR OWN PRE R-A 146500-RI RFO-22 / ISI / UT / / ACP1211.200 1.2-22 SHT-01 ISI s

R1.16-2 RRC-J004 PIPE AUG 1

RR OWN PRE R-A 146800-RI RFO-22 / ISI / UT / / ACP1211.20[1 1.2-22 SHT-01 iSI s

R1.16-2 RRC-JO04A PIPE AUG 1

RR OWN PRE K-A 147000-RI-R1.1 6-2 RRC-J005 RFO-22 / ISI / UT / / ACP1 211.20E]

1.2-22 SHT-01 ELBOW ISI AUG s

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

V O-F 0.

" 0 r

L" 04 0UL-o (1) 046 IL x,

Category, Item No.,

Class Summary No.

ComplD System Outage / Scope / Method Type / Procedure Dwg/ISO No.

Comp. Desc.

Code Case 1

RR OWN PRE R-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 - SAFEEND RFO-21 / PSI/PT/ / ACP1211.3 PI OWN 1

RR PRE c

History:

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----------------

s R1.16-2 RRD-J005 ELBOW AUG 1

RR OWN PRE R-A 119800-RI RFO-22 / AUG / UT / /

1.2-20 SHT-01 iSI R1.16-2 RRE-FO02A ZetecOmniScanPA_03[0 PIPE - SAFEEND AUG s

1 RR OWN PRE R-A 120500-RI RFO-22 / ISI / UT/ /ACP1211.200 1.2-20 SHT-01 ISI s

R1.16-2 RRE-J005 ELBOW AUG 1

RR OWN PRE R-A 121300-RI R1.16-2 RRF-FO02A 1

RR RFO-20-1 / ISI / UT / UT /

ACP1211.380 RFO-20-1 / ISI / UT / UT /

ACP1211.380 RFO-20-1 / ISI / UT/UT/

ACP1211.380 RFO-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

Duane Arnold Nuclear Plant 4th Interval 5Cýj0 0

LO Ow o (i-(NJ 0

Ii-6 0:

hL ni"

Category, Item No.,

Class Summary No.

ComplD System Outage / Scope / Method Type / 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 c

R1.16-2 RRF-J003 ACP1211.200 PIPE AUG 1

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 s

R1.16-2 RRF-J005 ELBOW AUG t

1 RR OWN PRE R-A 122800-RI RFO-21 / AUG /UT

/ ACP1211.380 1.2-20 SHT-01 ISI R1.16-2 RRG-FO02A RFO-21 / AUG/UT/ /

PIPE - SAFEEND AUG

-c c

1 RR ZetecOmniScanPA_03[]

OWN RFO-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 R1.16-2 1

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

0 LL Onr 0

LL of (NJ 0

U-w 0

U-Cif

Category, Item No.,

Class Summary No.

ComplD System Outage / Scope / Method Type / Procedure Dwg/ISO No.

Comp. Desc.

Code Case R-A 123500-RI RFO-22 / ISI / UT/ /ACP1211.20E1 1.2-20 SHT-01 ISI s

R1.16-2 RRG-J005 ELBOW AUG t

1 RR OWN PRE R-A 123900-RI RFO-22/ISI/ / /

I 1.2-20 SHT-01 ISI s

R1.16-2 RRG-J007 PIPE AUG t

1 RR OWN PRE R-A 124300-RI RFO-21 / AUG / UT / / ACP1211.380 1.2-20 SHT-01 ISI R1.1 6-2 RRH-FO02A RFO-21 / AUG / UT/ /

PIPE - SAFEEND AUG c

1 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-A R1.16-2 1

125000-RI RRH-J005 RR RFO-22 / ISI / UT / / ACP1211.200 1.2-20 SHT-01 ELBOW ISI AUG OWN PRE 5

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

Retrieved from "https://kanterella.com/w/index.php?title=NG-10-0094,_Response_to_Request_for_Additional_Information_Related_to_Relief_Request_for_1st_Period_Limited_Weld_Examinations&oldid=5302968"