NG-09-0539, Relief Request for 1st Period Limited Weld Examinations

Relief Request for 1st Period Limited Weld Examinations

ML092230346
Person / Time
Site:	Duane Arnold
Issue date:	07/30/2009
From:	Richard Anderson Nextera Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-09-0539
Download: ML092230346 (20)

Text

NEXTera ENERGY, ARNOLD July 30, 2009 NG-09-0539 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 Relief Request for 1st Period Limited Weld Examinations Pursuant to 10 CFR 50.55a(g)(5)(iii), NextEra M T Energy Duane Arnold, LLC, f/k/a FPL Energy Duane Arnold, LLC (hereafter, NextEra Energy Duane Arnold) hereby requests NRC approval of the enclosed relief request from IWB-2500 to allow performance of limited examinations of various welds. 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. Enclosure 1 of this letter contains the request for relief and Enclosure 2 contains the 1st period non-destructive evaluation reports associated with the components for which relief is sought.

NextEra Energy Duane Arnold requests approval of this request by the end of December 2009.

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

Richard L. Anderson Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC Enclosures cc: Administrator, Region III, USNRC Project Manager, DAEC, USNRC Senior Resident Inspector, DAEC, USNRC .A NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA52324

Enclosure 1 to NG-09-0539 Page 1 of 9 Enclosure 1 10 CFR 50.55a REQUEST IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii)

INSERVICE INSPECTION IMPRACTICALITY

Enclosure 1 to NG-09-0539 Page 2 of 9 10 CFR 50.55a REQUEST IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii)

INSERVICE INSPECTION IMPRACTICALITY Component Identification Code Class: Class 1

References:

ASME Code,Section XI, Subarticle IWB-2500 Table IWB-2500-1 Examination Categories: B-A, R-A Item Numbers: B1.40, and R1.16

==

Description:==

Reactor Vessel Head-to-Flange Weld, and Piping Welds.

Component Numbers: See Table A for Component Identification

Applicable Code Edition and Addenda

ASME Section XI 2001 Edition, 2003 Addenda Code Requirement Section XI (2001 Edition with the 2003 Addenda), Subarticle IWB-2500 states in part "Components shall be examined and tested as specified in Table IWB-2500-1."

Table IWB-2500-1, Category B-A, Item B1.40, requires a volumetric examination of applicable Class 1 pressure retaining welds, which includes essentially 100% of weld length once during the ten year interval.

Relief Request NDE-R005 was approved on January 31, 2007 allowing the use of Risked Informed (RI) Inservice Inspection (ISI) for Class 1 and 2 welds. This relief request states that the original list of intended credited Class 1 welds may have been substituted on specific occasions with similar welds due to accessibility issues that would have resulted in reduced exam volumes. NextEra Energy Duane Arnold chooses welds for examination that are classified within the same risk matrix classification segment, using the same treatment criteria as those originally selected.

Reason for Request

The Duane Arnold Energy Center (DAEC) construction permit was issued in 1970 and the operating license was issued in 1974. The reactor vessel was designed and installed to ASME Section I11,1965 Edition, with the Summer 1967 Addenda. The parameters for accessibility for ISI were not requirements at that time and therefore were not necessarily factored into component and system configurations, thereby creating conditions where ASME Section X1 Code required examination coverage of Class 1 welds cannot be obtained.

Enclosure 1 to NG-09-0539 Page 3 of 9 10 CFR 50.55a recognizes the limitations to in-service inspection of components in accordance with Section XI of the ASME Code that are imposed due to early plants' design and construction, as follows:

10 CFR 50.55a(g)(1): For a boiling or pressurized water-cooled nuclear power facility whose construction permit was issued prior to January 1, 1971, components (including supports) must meet the requirements of paragraphs(g)(4) and (5) of this section to the extent practical.

10 CFR 50.55a(g)(4): Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and pre-service examination requirements, set forth in Section XI of editions of the ASME Boiler and Pressure Vessel Code... to the extent practical within the limitation of design, geometry and materials of construction of the components.

10 CFR 50.55a(g)(5)(iii): If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in § 50.4, information to support the determinations.

Table A - Limited Exam Weld List Exam Item Component Period Code Description Category Number Number Examined Coverage B-A B1.40 HCC-COOI 1 76.05% Reactor Vessel Head-to-Flange Weld Reactor Water Cleanup R-A R1.16 Piping Weld Recirculation Manifold to ARiser Piping Weld Reactor Vessel Head to Flange Weld -

HCC-CO01 This weld is the Head to Flange Weld which can only be examined from the head surface. The examination is limited to approximately 76.05% and is limited due to the configuration of the weld. Note that this weld examination is divided up into thirds, with each third being examined each period. The examination completed was from Stud Holes 60 to 20. There is no feasible option in order to examine the remaining 23.95%.

The Nondestructive Examination (NDE) procedure used for this examination incorporates the examination techniques qualified under Appendix VIII 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.

Enclosure 1 to NG-09-0539 Page 4 of 9 Reactor Water Cleanup Class 1 Weld CUA-J024 This weld is between a containment penetration and a motor operated valve (MO-2701). The valve side of the weld is not accessible for scanning due to geometry.

This weld is the only weld in the risk segment (CU-007) so there is no other weld to select. The consequence evaluation determined this weld to be high because it is the weld between the containment and the isolation valve (MO-2701). The material for the items welded together is Al 82 F316 forging penetration to an A351 CF8M cast valve. Per Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," "Inspection Schedules" position (2), this weld would be considered in the Intergranular Stress Corrosion Cracking (IGSCC) Category A. The A182 F316 is solution heat treated which is an acceptable process for resistance to IGSCC. The staff position states:

"Although castings with higher carbon content than 0. 035% are not considered to be resistant to sensitization, welds joining such castings (in the form of pump and valve bodies) to piping have been relatively free of IGSCC.

This may be attributedto a favorable residualstress distribution,as calculationshave indicated. For this reason, weld joining resistantmaterial to pumps and valves will be consideredto be resistant welds, and included in IGSCC Category A. If extensive weld repairs were performed the residual stress may be unfavorable, in which case such welds should be included in Category D."

Therefore, this weld is considered resistant to IGSCC. The volume examined was from the A182 F316 penetration side of the weld. The weld was not examined from the A351 CF8M cast valve side due to the configuration of the valve (see photo that follows).

Enclosure 1 to NG-09-0539 Page 5 of 9 Since this weld is resistant to the degradation mechanism of IGSCC and there is no other degradation mechanism that has been identified for this weld, the volume examined is acceptable.

Recirculation System Class 1 Weld RMA-J004 This weld is the branch connection of the recirculation manifold to the recirculation riser line. The manifold side is not accessible for scanning due to geometry. There are a total of eight welds with this configuration (8 recirculation risers coming off the two manifolds); see ISI Isometrics 1.2-20 and 1.2-22 that follow.

Enclosure 1 to NG-09-0539 Page 6 of 9 rn RRF-8J-4A C RRFC-EJ4 -

RR-,14 ELD OVECRLAY WELD OVERLAY

'R~ EPROM IN REPAIR IN R 0J A m WELDOVERLAY CINNRHB-REPAIR IN WELD OVERLAY COMMON REPAIR IN 1 A J5 D J3 5 F N2 FPA 4S I" LINE TYP.

DW339 031 j m wW21

-J7 DW2 LUC$ DLS OWt -47

• EICLTO 1NFOO""&RSR I, 4 OM-J

Enclosure 1 to NG-09-0539 Page 7 of 9 The detailed configuration of the branch connection weld provided below is taken from the construction drawing (B31-GO01-RD-N-B3). As the configuration shows it does not allow an examination to be performed from the manifold side.

--.

N VA.

• ' ""* ' * "'"T .

T. ~

• :. . ....: . ... ... . *.. ,.,~ -..

All eight manifold to riser welds were solution annealed which is an acceptable process for resistance to IGSCC. Each weld was identified in its own risk category so there is no other weld that could be selected to obtain a higher examination coverage. These welds were determined to have Thermal Transients as a degradation mechanism under the RI-SI Program. The Degradation Mechanism Evaluation Document (M453-047) states:

For the most part, the RCR System heats up and cools down slowly and uniformly so it is not susceptible to the thermal shocks that result in TT degradation mechanism. However, at the beginning of shutdown cooling, the RCR System does receive a double-shock from the RHR System (cold fluid and then hot fluid into formerly hot lines). The double-shock was analyzed for the RCR main loop discharge, manifold, and riser piping. The results indicate that all of these pipe segments are potentially susceptible to the TT degradation mechanism.

NextEra Energy Duane Arnold proposes to perform the ultrasonic examination on one more of the eight welds (which would only receive 50% coverage) in lieu of performing the examination on just one weld. One weld will be examined from each loop.

Performing two of the eight welds (each receiving 50% coverage) is considered an acceptable alternative.

Enclosure 1 to NG-09-0539 Page 8 of 9 Proposed Alternative and Basis for Use In accordance with 10 CFR 50.55a(g)(5)(iii), relief is requested for the components listed in Table A on the basis that the required examination coverage of "essentially 100 percent" is impractical due to physical obstructions and the limitations imposed by design, geometry and materials of construction. NextEra Energy Duane Arnold performed qualified examinations that achieved the maximum, practical amount of coverage obtainable within the limitations imposed by the design of the components.

Additionally, for the Class 1 examination Category B-P, a VT-2 examination is performed on the subject components of the Reactor Coolant Pressure Boundary during system pressure tests each refueling outage. The examination was completed during the 2009 refueling outage and no evidence of leakage was identified for these components.

Based on the above, with due consideration of the earlier plant design, the underlying objectives of the Code required volumetric examinations have been met.

The examinations were completed to the extent practical and no evidence of unacceptable flaws was detected. VT-2 examinations performed on the subject Class 1 components during system pressure testing each refueling outage (in accordance with examination Category B-P) provide continued assurance that the structural integrity of the subject components is maintained. Additionally, the DAEC Water Chemistry Program and inerted primary containment environment provide added measures of protection for the component materials.

Duration of Proposed Alternative Relief is requested for the Fourth Ten year Interval of the Inservice Inspection Program for the DAEC, which ends on February 21, 2014.

Precedents

1) NRC Letter dated May 1, 2008, "Safety Evaluation for Request for Relief from IWB-2500 and IWC-2500 Requirements to Allow Performance of Limited Examinations of Various Welds for the Third 10-Year Interval of the Inservice Inspection Program (TAC No. MD5669)."

2) NRC Letter dated October 18, 1999, "Safety Evaluation of Third 10-Year Interval Inservice Inspection Program Plan Requests for Relief for Duane Arnold Energy Center (TAC No. MA4151)" specifically for Relief Request NDE-R028.

3) NRC Letter dated March 23, 1998, "Evaluation of Third 10-Year Inservice Inspection Interval Program Plan Requests for Relief for the Duane Arnold

Enclosure 1 to NG-09-0539 Page 9 of 9 Energy Center (TAC No. M95412)" specifically for Relief Requests NDE-R006, NDE-R007, NDE-R008, NDE-R009, and NDE-RO10.

References None

Enclosure 2 to NG-09-0539 Enclosure 2 1st Period Non-Destructive Evaluation Reports 9 Pages Follow

f. UT Vessel Examination FPL Site/Unit: DAEC I I Procedure: ACP1211.27 Outage No.: RFO-20-1 Summary No.: 3300 Procedure Rev.: 1 Report No.: UT-07-100 Workscope: ISI Work Order No.: 1135860 Page: 1 of 3 Code: ASME 2001 Ed thru 2003 Add Cat,/Item: B-A181.40 Location: RB511 Drawing No.: VS-01-06 SHT-01

Description:

REACTOR VESSEL(STUD HOLES 60-20)

System ID: RPV Component ID: HCC-CO0l Size/Length: NWA Thickness/Diameter: 3.93" Limitations: Single sided exam due to configuration Start Time: 1000 Finish Time: 1200 Examination Surface: Inside i Outside [*] Surface Condition: Blended Lo Location: Stud Hole One Wo Location: WCL Couplant: Ultragel II Batch No.: 06225 Temp. Tool Mf9.: PTC Serial No.: 254038 Surface Temp.: 70 'F Cal. Report No.: CAL-07-031 Angle Used 1-I 45 j45Tj 60 - !6 Scanning d8 lndication(s): Yet; No , i Scan Coverage: Upstream ni. Downstream[i) CW

• CCWi Comments:

Scan Sensitivity: Zone 1 / 82.5 Zone 2 1 83.5 Results: Accept 1ýJ Reject i- Info F _-_

Percent Of Coverage Obtained > 90%: 76.05% Reviewed Previous Data: Yes Examiner Level II-PDI *9frature Date Reviewer S)gnature , Date Stevermer, Aaron J. Timm, Jeremy -2/22/2007 .

Examiner Level NIA 2 Signature Date Site Review Sigr(e Date N/A Dohmen, Frank E. 4 Other Level NIA Signature Date ANII Review Signature .' Date NIA Bowers, Jeremy .'3 j .. -__ "____"_

UT Vessel Examination

Supplemental Report PPL Report No.: UT-07-100 Page: 2 of 3 Summary No.: 3300 Examiner-- Stevermer, Aaron J. /:. Level: 11-PDI Reviewer: Timm, Jeremy ., .... 7 Date:

Examiner: NIA Level: N/A Site Review: Dohmen, Frank E. Date: 2:7 r,. ý Other: NIA Level: NIA ANM Review: Bowers, Jeremy Date: 3>)

Comments: Coverage Plots AXIAL PARALLEL Sketch or P~hoto: U:Apps\OAEG D8\ER0CkRF020\REP0RT SOPPLEMENTSWLTXSN_3300 (J:1Apps\0AEC(,DBkEROC\,RFO20\REPC)RTl SUPPLEMrENTS\UT\S N_3a00 CorpIDHOC0_C00l Repo rt UTO 7- GOAxial jpy Cc~rnpIDHCC_ CO0l ReportUT 07_ 100P ara.lel jpg I(.OII Cuwciage dlol- Axial s.waodirciioa 11CCCOO C~we-te p~ Pa ilA~gIca

. ici He-a

-A------

_

• 'r'j Flange Xz / Flange Additional - Supplemental Reports

Supplemental Report F*PI. Energy Report No.: UT-07-.100 Ilinei ArnoldEnerqy Csezi Page: 3 of 3 Summary No.: 3300 Examiner: Stevermer, Aaron J. F Level II-PDI Reviewer: Timm, Jeremy , Date: _____/__

Examiner: N/A Level NIA Site Review: Dohmen, Frank E. 1C Date: 2/Z7Io7 Other: NIA Level NIA ANII Review: Bowers, Jeremy -' Date:

Comments: COVERAGE CALCULATIONS Sketch or Photo: U:AppsOAECDB\EROC\RFO20\REPORT SUPPLEMENTS\UT\SN_3300 ComplDHCCCO01 ReportUTO07_100 CovCalc.jpg RPV Coverage Calculation Sheet Note: calculations performed using 2D plot only Component ID MCC-CO01 Area reuhEd t§eobeexamined Axial scan direction: Height Kwidth 3.93 Inches x 5.3 Inches equals 20.829 square Inches Parallel scan direction: Height x width 3.93 inches X 5.3 Inches equals 20.829 square Inches Total area required to be examined 41,658 square inches required for complete exam Actual area examined 60 degree R.L Axial scan direction: Height x width 3.93 Inches x 5.3 Inches equals 20.829 square inches Triangular area not examined (if applies) 1.53 X .5 X 2.92 height equals 2.,2338 square inches Bass Axial scan direction area examined 18.5952 square Inches 60 degree R.L. Parallel scan direction: Height x width 3.93 Inches x 3.33 Inches equals 13.0869 square inches Additional inner 16% area achieved using 40 & 45 degree shear techniques: Height x width (Nozzle to RPV only) 0 Inches x 0 Inches equals 0 square inches Combining all scan directions: 31.6821 square inches lor total exam Divide area examined by required area: equals coverage achieved 76.05 % coverage for total exam Calculations performed by: Todd Stechinger Level Ill OAEC Review Frank Dohmen Level III ANIP Review J4eremy 5owera Additional - Supplemental Reports

0 FFPL Enerqy. Site/Unit:

DAEC I UT Calibration/Examination RFO-21 O(ane Arnold Energy Ceoe, Procedure: ACP1211.20 Outage No.:

Summary No.: 117900-RI Procedure Rev.: 7 Report No.: UT-09-006 Workscope: is' Work Order No.: 1144503 Page: 1 of 3 Code: ASME 2001 Ed Thru 2003Add Cat./Item: R-A/R1.16-2 Location: DW220 Drawing No.: 1.2-20 SHT-01

Description:

MANIFOLD TO PIPE WELD OFF OF THE RECIRCULATION MAN System ID: RM Component ID: RMA-J004 Size/Length: 1.1" 132" Thickness/Diameter: 0.844" / 12' Limitations: Single side acess due to branch configuration Start Time: 1408 Finish Time: 1506 Instrument Settings Search Unit CaL Time Date Axial Orientated Search Unit Serial No.: 01R6B7 Serial No.: 01RPIH Checks Calibration Signal Sweep Sound Path Manufacturer: Krautkramer Manufacturer: KBA Initial Cal. 1100 2f8209 Refleotor Amplitude % Division Model: USN 6D SW Size: .50" Shape: Round inter. Cal. 1408 218/2009 1.0* Notch 85 5.0 1.413 Delay. 6.8847 Range: 2.828 Freq.: 1.5 MHz Style: Comp G Inter. Cal.

MIT Cal/Vel: 0.1232 Pulser: Square Exam Angle: 452 # of Elements: 1 Inter. Cal. _

Damping: 500 L) Reject 0% Mode: Shear - Final Cal. 1633 218/2009 Rep. Rate: Autohigh Freq.: 2.0 mhz Measured Angle: 452 Couplant _I ......

Filter: NIA Mode: Fullwave Wedge Styte: MSWQC Cal. Batch: 06225 Circumferential Orientated Search Unit Voltage: 450 volts Other: PW 330 nS Type: Ultragel II Calibration Signal Sweep r path Ax. Gain (dB): 11.0 CIrc. Gain (dB): N/A Search Unit Cable Mfg.: Sonotech Reflector Amplitude % Division 1 Screen Div. = .2828 in. of Sound Path Type: RG-174 Exam Batch: 06225 WA Linearity Report No.: L-09-001 Length: 6' No. Corn.: 0 Type: Ultragel II Calibration Block Scan Coverage Mfg.: Sonotech Cal. Block No.: 5539

___________________- Upstream [] Downstream-] Scan dB: 23.0 Reference Block Reference/Simulator Block Thickness: .5"--2.0" Dia.: 0 CW 0 CCW &] Scan dB: 23.0 Serial No.: 08-4349 Gain AmSne % Division Sound Path Cal. 51k. Temp.: 75*2 Temp. Tool: M415 Exam Surface: OD Type: ROMPAS 11.0 FSDH 20 3.8 1.067 Recordable Indication(s): Yes [] No [ (If Yes, Ref. Attached Ultrasonic indication Report.)

Results: Accept [] Reject [J Info [] Comments: See supplemental sheet for thickness and contour and coverage plot, Percent Of Coverage Obtained > 90%: 50%0 Reviewed Previous Data: Yes Examiner Level III-PDf _,Signat Date Reviewer na Dte Davis, Layn R. 020091 Examiner Level II-PDi Signature Date Site Review Sigratur) / Date Totosky, Ryan J. 2//209 f/)Zt*19 Other Level NfA Sidgnature - Date ANII Review Signature Date UT Calibration/Examination

a F4 Energy. Site/Unit: DAEC UT Cal ibration/Examination Duamn Amild Eneigy Coen%*' Procedure: ACP1211.20 Outage No.: RFO-21 Summary No.: ISI 7 Report No.: UT-09-006 I 17900-Ri' Procedure Rev.:

Workscope: 'SI Work Order No.: 1144503 Page: 2 of 3 Code: ASME 2001 Ed Thru 2003Add Cat/Item: R-A/RI.16-2 Location: DW220 Drawing No.: 1.2-20 SHT-O1

Description:

MANIFOLD TO PIPE WELD OFF OF THE RECIRCULATION MAN System ID: RM Component ID: RMA-J004 Size/Length: 1.1" / 3Z' Thickness/Diameter: 0.844" / 12' Limitations: Single side acess due to branch configuration Start Time: 1408 Finish Time: 1506 Instrument Settings Search Unit Cal. Time Date Axial Orfenta-ed Search Unit Serial No.: 01R6B7 Mauacuer rutrme SeriaJ No.: 08-440 Checks .Calibration CS Signal Sweep 1Sound Path Manufacturer: Krautkramer Manufacturer: RTD Initial Cal. 1205 2(8=2009 Reflector Amplitude % Division Model: USN 60 SW Size: 2 (8 x 14) Shape: Rectangle Inter. Cal. 1445 2/8/2009 1.0" Notch so 5.0 2.00 Delay: 8.6128 Range: 4.0 Freq.: 2.0 MHz Style: TRL2-Aust Inter. Cal.

M'tl CarNel: 0.2222 Pulser: Square Exam Angle: 602 # of Elements: 2 Inter. Cal. I Damping: 500 . Reject: 0% Mode: Long - Final Cal. 1637 2/812009 Rep. Rate: Autohigh Freq.: 2.0 mhz Measured Angle: 602 Couplant Filter: N/A Mode: Fullwave Wedge Style: Integral Cal. Batch: 06225 Circumferential Orientated Search Unit Voltage: 450 volts Other: PW 250 ne Type: Ultragel II Calbration Signal Sweep Soud Path N/A Search Unit Cable Mfg.: Sonotech Reflector Amplitude % DMsion Ax. Gain (dB): 51.0 Circ. Gain (dB):

1 Screen Div. = 0.4 in. of Sound Path Type: RG-174 Exam Batch: 06225 N/A Linearity Report No.: L-09-001 Length: 6' No. Conn,: 0 Type: Ultragel II Calibration Block Scan Coverage Mfg.: Sonotech Cal. Block No.: 5539 Upstream [] Downstream-- Scan dr: 67.0 Reference Block Reference/Simulator Block Thickness: .5" - 2.0" Dia.: 0 CW [E CCW E] Scan dB: N/A Gaia Signal Swee Cal, BIk. Temp.: 759_ Temp. Tool: M415 Exam Surface: OD Type: ROMPAS 47.0 FSDH 85 3.5 1D41 Temp. Tool: M415 Surface Condition: Blended Comp. Temp.: 89W Recordable Indication(s): Yes [] No V (If Yes, Ref. Attached Ultrasonic Indication Report.)

Results: Accept [] Reject E] Info [] Comments: See supplemental sheet for thickness and contour and coverage plot.

Percent Of Coverage Obtained > 90%: 50% Reviewed Previous Data: Yes Examiner Level ilI-pot Signature Date Reviewer Signature Date Davis, Layn R. 29W/2009 CC S.(*qj V, Examiner Level iI.pDI Signature Date Site Review S .u Date Tolosky, Ryan J.2/8/2009 Other Level NIA Dale ANII Review Dagnature Signature ' 'Dale UT Calibration/Examinalion

Supplemental Report i::L Report No.: UT-09-006 Page: 3 of 3 Summary No.: 117900-RI Examiner: Davis, Layn R. Level: III-PDI Reviewer: L I S ,, Date:

Examiner: Tolosky, Ryan J. Level: fl-PDI Site Review: ee"', Date: / /<1 Other: N/A Level: N/A ANII Review: -)I (-. Date: -q Comments:

4 t

I I Re Lce r-45 ~

K -

-

eovet~e.

56'Z 6orve,-3 Additional - Supplemental Reports

UT Calibration/Examination F3L Energy Site/Unit:

DAEC I1 Procedure: ACP121i1.20 Outage No.: RFO-20-1 DomneArnold *l*,eOry ICellar Summary No.: 74600-4J Procedure Rev.: 6 Report No.: UT-07-028 Work<scope: Work Order No.: 1135836 Page: 1 of 2 Code: ASME 2001 Ed thru 2003 Add Cat./item: R-A/R1.16-4 Location: RB270 Drawing No.: 1.2-1 IA SHT-01

Description:

PIPE - MOTOR OPERATED GATE System ID: CU Component ID: CUA-J024 Size/Length: .90" 115.75" Thickness/Diameter. .58" /5.0" OD Limitations: Single sided exam due to valve configuration. Start Time: 1400 Finish Time: 1415 Instrument Settings Search Unit Cal. Time Date Axial Orientated Search Unit Serial No.: 01LCBL Serial No.: 01D4NY Checks , Calibration Signal Sweep Sound Path Manufacturer: Krautkramer Manufacturer: KBA Initial Cal. 0735 2/12/2007 Reflector Amplitude % Division Model: USN 60 SW Size: .375" Shape: Round Inter. Cal. 1400 2/1212007 1" Notch 80 8.0 1.43" Delay: 015.30 Range: 1.850" Freq.: 1.50 MHz Style: Comp-G Inter. Cal. 1415 2112/2007 NIA M'tl CalNel: .1223 Pulser: Square Exam Angle: 45° # of Elements: Single Inter. Cal. N/A _

Damping: 5000 Reject: 0% Mode: Shear Final Cal. 1510 2/1212007 Rep. Rate: AutoHigh Freq.: 2.0 MHz Measured Angle: 45* Couplant Filter: Fixed Mode: FullWave Wedge Style: MSWQC Cal. Batch: 06225 Circumferential Orientated Search Unit Voltage: 450 Other. PulseWidth 330 ns Type: Ultragel II Calibration Signal Sweep S P Ax. Gain (dB): 23 Circ. Gain (dB): 23 Search Unit Cable Mfg.: Sonotech Reflector Amplitude % Division SoundPath 10 Screen Div. = 1.850 in. of Sound Path Type: RG-174 Exam Batch: 06225 N/A Linearity Report No.: L-07-ODI Length: 6- No. Conn.: 0 Type: Ultragel 11 Calibration Block Scan Coverage Mfg.: Sonotech Cal. Block No.: 5539 Upstream W Downstream[] Scan dB: 37 Reference Block Reference/Simulator Block Thickness V5"-2.0" Dia.: Flat CWR CCW66 Scan dB: 37 No.a LMT03 Gaia

,oudrit Cal. Bk Temp 78__ Temp Tool: 253987 Exam Surface: OD Sao"d Reflector Amplitude % Division Cal Ek.Tep.78 Tep.Tol:______________________________Type: SS Rompas 23 SDH 18 6.8 1.05",

Comp. Temp.: 78' Temp. Tool: 253987 Surface Condition: Blended N/A __SD Recordable Indication(s): Yes U No [] (If Yes, Ref. Attached Ultrasonic Indication Report)

Results: Accept 6d Reject U Info FU Comments: No downstream scans due to valve configuration.

60° angle reported on UT-07-029 Percent Of Coverage Obtained > 90%: 50% Reviewed Previous Data: Yes Examiner Level III-PDI S' lure Date Reviewer .. .... ignature Date 211212007 Blechinger, ToddP. "..r--/-

Examinear Level ISignature Date Site Review fur / Date Pollock, Norm E. 2112J2007 DheFrank E. 4 U ki,-1"S/.$70" Other Level N/A Signature Date ANII Review Signature Date NIA Bowers, Jeremy .'3 (.... - 7 UT Calibration/Examination

0 FPIL gnargV Supplemental Report Report No.: UT-07-028 auan Arnold Energy Cooler Page: 2 of 2 Summary No.: 74600-RI Examiner: Davis, Layn R 73" 0 .- Level: III-PDI Reviewer: Blechinger, Todd P. Date: 2'ht*7 Examiner Pollock, Norm E, Level: I Site Review: Dohmen, Frank E. Date: 31 )0 Other N/A Level: N/A ANII Review: Bowers, Jeremy )t'* Date:

Comments: Actual configuration penetration fitting to valve.

50 % code coverage due to single sided access.

• Actual diameter 5.0", actual weld length 15.75" Sketch or Photo: U:\Apps\DAECDB\EROC\RFO20\REPORT SUPPLEMENTS\UT\SN_74600-RI CompIDCUA-J024 Report_UT-07-028 Coverage Plot.jpg SYST'MM, RW r C-I COMPONENT ID NO0.,' QA3 5~-

- - - ~CROWN HEIGHT' .

2 .~ - CROWN WIOTH:.9 WELD LENG3TH:..~

6 _ _ _ _ _ _ _ _ _ _ _ _ _ _ F__

C-VePZA&6 tlUe 7V $51I~CLe ,`Z ý 9CC,-k-c 1tO 0i ". -0L I- VALV'E (46 4 0'tL I £ Additional - Supplemental Reports

UT Calibration/Examination Ft E__nergy Site/Unit:

DAEC / Procedure: ACP1211.20 Outage No.: RFO-20-1 Ovane Amnold &, vqy CIlwer Summary No.: 74600-RI Procedure Rev.: 6 Report No.: UT-07-029 Workscope: ISI Work Order No.: 1135836 Page: 1 of 1 Code: ASME 2001 Ed thru 2003 Add Cat/Item: R-AIRI.16-4 Location: RB270 Drawing No.: 1.2-1 1A SHT-01

Description:

PIPE - MOTOR OPERATED GATE System ID: CU Component ID: CUA-J024 Size/Length: .90" 115.75" Thickness/Diameter: 0.580" I5.0" OD Limitations: Single sided due to valve configuration Start Time: 1416 Finish Time: 1422 Instrument Settings Search Unit Cal. Time Date Axial Orientated Search Unit Serial No-: 01LCBL Serial No.: 05-335 Checks _ Calibration Signal Sw S Initiatlo Cal.a S e eP Sound Path Manufacturer: Krautkramer Manufacturer: RTD Initial Cal 0720 21/2/2007 Reflector Amplitude % Division Model: USN 60 SW Size: 2 (7x10 mm) Shape: Rect Inter. Cal. 14116 2112J2007 1" Notch 80 7.0 2.04" Delay: 0/7.050 Range: 3.0" Freq.: 2.0 MHz Style: TRL2 Inter. Cal. 1422 211212007 N/A M'tl CaWel: .2304 Pulser: Square Exam Angle: 60' # of Elements: Dual Inter. Cal. NA Fia1C 15051 2112/200 Damping: 5000 Reject: 0% Mode: Shear Fina Cal.

Rep. Rate: AutoHigh Freq.: 2.00 MHz Measured Angle: 60' Couplant Filter: Fixed Mode: FullWave Wedge Style: NIA Cal. Batch: 06225 Circumferential Orientated Search Unit Voltage: 450 Other: PulseWidth 250 ns Type: Ultragel 11 Calibration Signal Sweep SoundPa.

Ax. Gain (dB): 58 Circ. Gain (dB): 68 Search Unit Cable Mfg.: Sonotech Reflector Amplitude % Division 10 Screen Div. = 3.0 in. of Sound Path Type: RG-174 Exam Batch: 06225NA Linearity Report No.: L-07-001 Length: 6' No. Conn.: 0 Type: Ultragel 11 Calibration Block Scan Coverage Mfg.: Sonotech Cal. Block No-: 5539 Upstream W Downstream[j Scan dB: 64 Reference Block Reference/Simulator Block Thickness .5"-2.0" Die.: Flat CWI- CCW-] Scan dB: N/A SerialNo.: LMT-032 di Signal Sweep SoundPath Cal. Bk. Temp. 78' Temp. Tool: 253987 Exam Surface: OD Type: SS Rompas dB 48 Reflector SDHI Amplitude 60 % Division45 - 1.43" Comp. Temp.: 78. Temp. Tool: 253987 Surface Condition: Blended NIA Recordable Indication(s): Yes No n-/ (IfYes. Ref. Attached Ultrasonic Indication Report.)

Results: Accept [ Reject nJ Info [] Comments: No downstream scans due to valve configuration.

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

Percent Of Coverage Obtained > 90%: 50% Reviewed Previous Data: Yes Examiner Level III-PDI .,, -Sgnature Date Reviewer nature , '.- Date Davis, Layn R , ' 211212007 Blechinger, Todd P....= I ". /* /7 Examiner Level i Signature Date Site Review t e Date Pollock, Norm E. 2/1212007 Dohmen, Frank E. J l C..7 Other Level N/A Signature Date ANII Review Signature Date N/A Bowers, Jeremy '.-- .r3-o 3- 5%0 UT Calibration/Examination

-_-_-_____'__-'_- ............

.__.. __ - ------

. . ..........

......... ----------------

--- '.-__