NG-10-0328, Response to Supplemental Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations

Response to Supplemental Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations

ML101660124
Person / Time
Site:	Duane Arnold
Issue date:	06/15/2010
From:	Costanzo C NextEra Energy Duane Arnold
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-10-0328
Download: ML101660124 (17)

Text

June 15,2010

. ----~-

~~----

NEXTera" ENERGY~

DUANE ARNOLD NG-10-0328 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 Supplemental Request for Additional Information Related to Relief Request for 1 st Period Limited Weld Examinations

Reference:

1.

2.

Letter, Richard L. Anderson (NextEra Energy Duane Arnold, LLC) to Document Control Desk (USNRC), Relief Request for 1 st Period Limited Weld Examinations, dated July 30, 2009, NG 0539 (ML092230346)

Letter, Christopher R. Costanzo (NextEra Energy Duane Arnold, LLC) to Document Control Desk (USNRC), Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations, dated February 25, 2010, NG-10-0094 (ML100680431)

Reference 1 provided a request for relief regarding the 1 st 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.

Reference 2 provided additional information regarding the request for relief regarding the 1 st period limited weld examinations of Reference 1.

In an email dated May 24,2010, the Staff issued another 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 July 30, 2010.

NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324

NG-10-0328 June 15, 2010 Page 2 of 2 This letter contains no new commitments nor revises any previous commitments.

If you have any questions, please contact Steve Catron at (319) 851-7234.

Christopher R. Costanzo Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC Enclosure

Enclosure to NG-10-0328 Page 1 of 4 Enclosure Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations

Enclosure to NG-10-0328 Page 2 of 4 Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations NRC Question #1:

For CUA-J024 weld in the Reactor Water Cleanup System, this is a weld between a forged penetration and a cast valve, 50% coverage was probably the best coverage to be expected by the inspection. You have said in the July 30, 2009 submittal that 50% coverage is OK because the weld is not susceptible to IGSCC. But the only reason that weld is in RI Category 2 is because it is susceptible to IGSCC, otherwise, it is Category 4. Please clarify this apparent discrepancy.

NextEra Energy Duane Arnold Response:

The CUA-J024 weld in the Reactor Water Cleanup System is a Category 4 weld.

Please refer to Attachment 1 for 4th interval inspection information for Category 4 welds from the Duane Arnold Energy Center (DAEC).

NRC Question #2:

There is an inconsistency in the documentation provided. Page 1 of 1 on report no.

UT-07-029 UT Calibration/Examination shows the exam angle of the Search Unit as 60o, and the mode is listed as shear. But Page 2 of 2 on UT-07-028 Supplemental Report shows a sketch of the inspection configuration and it includes a notation that the transducer was at 60o RL, not 60o, shear mode. Please clarify.

NextEra Energy Duane Arnold Response:

On UT-07-029, the mode should have been listed as Longitudinal. This is a typographical error; the datasheet has been corrected and an image of the corrected datasheet is provided as Attachment 2.

NRC Question #3:

Please clearly identify the wave modality, insonification angles, and scan directions used for all ultrasonic examinations.

Enclosure to NG-10-0328 Page 3 of 4 NextEra Energy Duane Arnold Response:

The following table is provided with information from the examination datasheets:

Weld Wave Mode Insonification Angles Scan Direction HCC-C001 Refracted Longitudinal 60° Upstream (Axial), CW &

CCW (Parallel)

RMA-J004 Shear Longitudinal 45° 60° Downstream, CW & CCW Downstream CUA-J024 Shear Longitudinal 45° 60° Upstream, CW & CCW Upstream NRC Question #4:

Did the inspection exam category R-A meet ASME Code,Section XI, App VIII qualification requirements?

NextEra Energy Duane Arnold Response:

Yes, ASME Section XI Code Case N-578 paragraph -2500 (c) states Examination qualification and methods and personnel qualifications shall be in accordance with the Edition and Addenda of Section XI specified in the Owners Inservice Inspection Program.

NRC Question #5:

Supply a description of the materials of construction for the B1.40 RV head to flange weld and the R1.16 RMA-J004 weld.

NextEra Energy Duane Arnold Response:

Please refer to the following table for materials of construction:

Weld Materials HCC-C001 A508 Class 2 - head flange SA533 Class 1 GR. B - side plate RMA-J004 A182 304SS - sock-o-let A240 304SS - pipe

Enclosure to NG-10-0328 Page 4 of 4 NRC Question #6:

Provide a better copy of the photo in submittal for CUA-J024 weld.

NextEra Energy Duane Arnold Response:

Please refer to Attachment 3 for photos.

NRC Question #7:

The original July 30, 2009 submittal includes the following statement:

The Nondestructive Examination (NDE) procedure used for this examination incorporates the examination techniques qualified under Appendix Vlll of the ASME Section XI Code by the Performance Demonstration Initiative (PDI).

That procedure was approved under Relief Request NDE-R008 on January 31, 2007.

The January 31, 2007 document provides authorization to use an alternative to Code requirements, not NRC approval of a procedure. Reword this paragraph to reflect the fact that the NRC authorized the use of the alternative for the remainder of the 4th ISI interval at DAEC.

NextEra Energy Duane Arnold Response:

NextEra Energy Duane Arnold hereby rewords the statement in Reference 1 as follows (change in italics):

The Nondestructive Examination (NDE) procedure used for this examination incorporates the examination techniques qualified under Appendix Vlll of the ASME Section XI Code by the Performance Demonstration Initiative (PDI).

That alternative was approved under Relief Request NDE-R008 on January 31, 2007.

References:

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 (ML092230346)

2.

Letter, Christopher R. Costanzo (NextEra Energy Duane Arnold, LLC) to Document Control Desk (USNRC), Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations, dated February 25, 2010, NG-10-0094 (ML100680431) to NG-10-0328 5 Pages Follow 4th Interval History for Category 4 Welds

Period 1 Period 2 Period 3

Category, Item No.,

Class Summary No.

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

Comp. Desc.

Code Case RFO-20-1 RFO-21 RFO-22 RFO-23 R-A 61200-RI 1.2-07 SHT-01 ISI c

R1.16-4 CSA-F002A SE EXT - SAFEEND AUG c

1 CS R-A 61400-RI 1.2-07 SHT-01 ISI c

R1.16-4 CSA-F004 PIPE - PIPE AUG c

1 CS R-A 61600-RI 1.2-07 SHT-01 ISI s

R1.16-4 CSA-J003 PIPE - PIPE AUG c

1 CS R-A 64500-RI 1.2-08 SHT-01 ISI c

R1.16-4 CSB-F002A SAFEEND - S/E Extension AUG c

b 1

CS R-A 64700-RI 1.2-08 SHT-01 ISI s

R1.16-4 CSB-F004 PIPE - PIPE AUG c

b 1

CS R-A 64900-RI 1.2-08 SHT-01 ISI c

R1.16-4 CSB-J003 PIPE AUG c

b 1

CS R-A 74600-RI 1.2-11A SHT-01 ISI c

R1.16-4 CUA-J024 PIPE - MOTOR OPERATED GATE AUG c

b 1

CU R-A 103000-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-F002 NOZZLE - SAFEEND AUG c

b 1

RC R-A 103200-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J003 SAFEEND - PIPE AUG 1

RC Duane Arnold Nuclear Plant 4th Interval RFO-21 / ISI / UT / / ACP1211.38

RFO-21 / ISI / UT / / ACP1211.38

Category 4 RFO-21 / AUG / UT / /

ACP1211.20

RFO-22 / ISI / UT / / ACP1211.20

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

ACP1211.38

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

ACP1211.38

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

ACP1211.38

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

ACP1211.38

RFO-22 / ISI / UT / / ACP1211.38

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

ACP1211.20

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

ACP1211.20

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

ACP1211.20

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

ACP1211.20

RFO-22 / AUG / UT / /

Zetec_OmniScanPA_03

6/7/2010 ScheduleWorks V. 8.1 Page 1 - 5

Period 1 Period 2 Period 3

Category, Item No.,

Class Summary No.

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

Comp. Desc.

Code Case RFO-20-1 RFO-21 RFO-22 RFO-23 Duane Arnold Nuclear Plant 4th Interval Category 4 R-A 103500-RI 1.2-19A SHT-01 ISI s

R1.16-4 RCA-J004 PIPE - 90 DEGREE LONG RADIUS ELBOW AUG 1

RC R-A 103900-RI 1.2-19A SHT-01 ISI s

R1.16-4 RCA-J005 90 DEGREE LONG RADIUS ELBOW -

PIPE AUG 1

RC R-A 104500-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J006 PIPE AUG 1

RC R-A 104800-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J008 PIPE AUG 1

RC R-A 105100-RI 1.2-19A SHT-01 ISI s

R1.16-4 RCA-J012 PIPE - 90 DEGREE LONG RADIUS ELBOW AUG 1

RC R-A 105500-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J013 90 DEGREE LONG RADIUS ELBOW -

MOTOR OPERATED GATE AUG 1

RC R-A 105700-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J015 MOTOR OPERATED GATE - PIPE AUG 1

RC R-A 106400-RI 1.2-19A SHT-01 ISI s

R1.16-4 RCA-J021 PIPE - 90 DEGREE SHORT RADIUS ELBOW AUG 1

RC R-A 106800-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J022 90 DEGREE SHORT RADIUS ELBOW -

UNKNOWN PUMP TYPE -

AUG 1

RC RFO-22 / ISI / UT / / ACP1211.20

RFO-22 / ISI / UT / / ACP1211.20

RFO-23 / ISI / / / 

RFO-22 / ISI / UT / / ACP1211.20

6/7/2010 ScheduleWorks V. 8.1 Page 2 - 5

Period 1 Period 2 Period 3

Category, Item No.,

Class Summary No.

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

Comp. Desc.

Code Case RFO-20-1 RFO-21 RFO-22 RFO-23 Duane Arnold Nuclear Plant 4th Interval Category 4 R-A 107000-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J024 UNKNOWN PUMP TYPE - PIPE AUG 1

RC R-A 107500-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J028 PIPE - MOTOR OPERATED GATE AUG 1

RC R-A 107700-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J030 MOTOR OPERATED GATE - 90 DEGREE LONG RADIUS ELBOW AUG 1

RC R-A 108100-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J032 90 DEGREE LONG RADIUS ELBOW -

PIPE AUG 1

RC R-A 108800-RI 1.2-19A SHT-01 ISI R1.16-4 RCA-J038 PIPE AUG 1

RC R-A 109300-RI 1.2-19A SHT-01 ISI c

R1.16-4 RCA-J041 PIPE - TEE AUG 1

RC R-A 126100-RI 1.2-21A SHT-01 ISI c

R1.16-4 RCB-F002 NOZZLE - SAFEEND AUG c

B 1

RC R-A 126300-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J003 SAFEEND - PIPE AUG 1

RC R-A 126700-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J004 PIPE - 90 DEGREE LONG RADIUS ELBOW AUG 1

RC RFO-20-1 / ISI / UT / UT /

ACP1211.20

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

ACP1211.20

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

ACP1211.20

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

ACP1211.20

RFO-21 / ISI / UT / / ACP1211.38

RFO-21 / ISI / UT / /

Zetec_OmniScanPA_03

6/7/2010 ScheduleWorks V. 8.1 Page 3 - 5

Period 1 Period 2 Period 3

Category, Item No.,

Class Summary No.

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

Comp. Desc.

Code Case RFO-20-1 RFO-21 RFO-22 RFO-23 Duane Arnold Nuclear Plant 4th Interval Category 4 R-A 127300-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J005 90 DEGREE LONG RADIUS ELBOW -

PIPE AUG 1

RC R-A 127600-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J006 PIPE - TEE AUG 1

RC R-A 128000-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J007 TEE - PIPE AUG 1

RC R-A 128800-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J015 PIPE - 90 DEGREE LONG RADIUS ELBOW AUG 1

RC R-A 129200-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J016 90 DEGREE LONG RADIUS ELBOW -

MOTOR OPERATED GATE AUG 1

RC R-A 129400-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J018 MOTOR OPERATED GATE - PIPE AUG 1

RC R-A 130100-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J024 PIPE - 90 DEGREE SHORT RADIUS ELBOW AUG 1

RC R-A 130500-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J025 90 DEGREE SHORT RADIUS ELBOW -

UNKNOWN PUMP TYPE -

AUG 1

RC R-A 130700-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J027 UNKNOWN PUMP TYPE - PIPE AUG 1

RC 6/7/2010 ScheduleWorks V. 8.1 Page 4 - 5

Period 1 Period 2 Period 3

Category, Item No.,

Class Summary No.

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

Comp. Desc.

Code Case RFO-20-1 RFO-21 RFO-22 RFO-23 Duane Arnold Nuclear Plant 4th Interval Category 4 R-A 131200-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J031 PIPE - MOTOR OPERATED GATE AUG 1

RC R-A 131400-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J033 MOTOR OPERATED GATE - 90 DEGREE LONG RADIUS ELBOW AUG 1

RC R-A 131800-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J035 90 DEGREE LONG RADIUS ELBOW -

PIPE AUG 1

RC R-A 132500-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J041 PIPE AUG 1

RC R-A 133000-RI 1.2-21A SHT-01 ISI R1.16-4 RCB-J044 PIPE - TEE AUG 1

RC R-A 89700-RI 1.2-14 SHT-01 ISI s

R1.16-4 RHB-F003 PIPE - PIPE AUG 1

RH RFO-22 / ISI / UT / / ACP1211.38

6/7/2010 ScheduleWorks V. 8.1 Page 5 - 5 to NG-10-0328 1 Page Follows Revised UT-07-029 UT Calibration/Examination

R Energy Ocane Arnold Ezi-rav C;>nler UT Cali bration1Examination Sitelunit:

DAEC I

1 Procedure:

ACP1211.20 Summary No.:

74600-Rl Procedure Rev.:

6 Workscope:

IS1 Work Order No.:

1135836 Outaae No.:

RFO-20-1 Report No.:

UT-07-029 Page:

1 of 1

Code:

ASME 2001 Ed thru 2003 Add Cat.1ltem:

R-AIR1.I 6-4 Location:

RB270 Drawing No.:

1.2-11A SHT-01

==

Description:==

PIPE - MOTOR OPERATED GATE System ID:

CU Component ID: CUAJ024 SizeILength:

.90" 1 15.75" ThicknesslDiameter: 0.580" 1 5.0" OD Limitations:

Sinale sided due to valve confiauration Start Time:

1416 Finish Time:

1422 Percent Of Coverage Obtained > 90%:

50%

Reviewed Previous Data:

Yes

?

/,

Examiner Level 111-PDI ignature Date Davis, Lay n R 2/12/2007 Examiner Level I Signature Date Pollock, Norm E.

211 a2007 Other Level NIA Signature Date NIA Instrument Settings Search Unit Serial No.:

01 LCBL Serial No.:

05-335 Manufacturer:

Krautkramer Manufacturer:

Model:

USN 60 SW Size:

2 (7x10 mm)

Shape:

Rect Delay:

0R.050 Range:

3.0" M'tl CalNel:

.2304 Pulser:

Square Damping:

5008 Reject:

0%

Rep. Rate:

AutoHigh Freq.:

2.00 MHz Filter:

Fixed Mode:

FullWave Wedge Style:

NIA Cal. Batch:

06225 P

Reviewer Date Blechinger, Todd P.

3k (9 7 Site Review Dohmen, Frank E.

AN1 I Review Signature '

Bowers, Jeremy fiL 3-y-0 7 Axial Orientated Search Unit Voltage:

450 Other: Pulsewidth 250 ns Type:

Ultragel I1 Ax. Gain (dB):

58 Circ. Gain (dB):

58 Search Unit Cable Mfg.:

Sonotech P

10 Screen Div. = 30 in. of Sound Path Type:

RG-174 Exam Batch:

06225 P

Linearity Report No.:

L-07-001 O

Type:

Ultragel II Length:

6' No. Conn.:

P Calibration Block Scan Coverage Mfg.:

Sonotech Calibration Reflector 1" Notch NIA Circumferential Orientated Search Unit Division Sweep 7.0 Signal Amplitude %

80 Cal. Block No.:

5539 Upstream Downstream0 Scan dB: -

64 Reference Block ReferencelSimulator Block Thickness

.5"-2.0" Dia.:

Flat cw

• C C W U Scan dB: NIA Gain Serial No.:

LMT-032 Sound path Cal. Blk. Temp. 78" Temp. Tool:

253987 Exam Surface:

OD Type:

SS Rompas 1.43" Comp. Temp.:

78" Temp. Tool:

253987 Surface Condition:

Blended NIA Recordable Indication(s):

Yes No (If Yes, Ref. Attached Ultrasonic Indication Report.)

Results:

Accept Reject Info Comments: No downstream scans due to valve configuration.

Reference Coverage plot on 45" angle report# UT-07-028.

Calibration Reflector NIA Sound Path 2.04" Signal Amplitude %

Sweep Division Sound path to NG-10-0328 2 Pages Follow CUA-J024 Weld Photos