LIC-11-0004, Wesdyne Report No. 1305120-Rpt.1 Fort Calhoun RPV Outlet Nozzle Eddy Current Data Normalization, Dated December 2010

Wesdyne Report No. 1305120-Rpt.1 Fort Calhoun RPV Outlet Nozzle Eddy Current Data Normalization, Dated December 2010

ML110200195
Person / Time
Site:	Fort Calhoun
Issue date:	12/31/2010
From:	Kuljis Z WesDyne International
To:	Office of Nuclear Reactor Regulation
References
LIC-11-0004 1305120-Rpt. 1
Download: ML110200195 (101)

Text

LIC-11-0004 Wesdyne Report No. 1305120-Rpt.1 "Fort Calhoun RPV Outlet Nozzle Eddy Current Data Normalization" Dated December 2010

XWESDyf E Fort Calhoun RPV Outlet Nozzle Eddy Current Data Normalization Report No: 1305120-Rpt.1 OPPD Contract No. 00083453, Release 00097, dated 10/13/2010 Prepared by: Date: December 14, 2010 Zoran Kuljis Principal Engineer, EC LvI. III Reviewed By,: ý - Date: Ek. 16,12o Don Adamonis General Manager Products and Application Engineering Wesdyne International, Inc.

Windsor, CT December 2010 Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 1 of 71

NWESDpynE Table of Contents:

1-Summary 2-Introduction 3- Local Permeability Variation (PV) Measurements 4- Results and Observations 5- References Attachments:

Attachment A: Local Permeability Measurements for Nozzle at 0' Location on RPV Attachment B: Local Permeability Measurements for Nozzle at 1800 Location on RPV Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 2 of 71

JWESDynlE

1) Summary.

Eddy Current Testing (ECT) data collected with a pancake coil probe during the Fall 2009 Fort Calhoun Station refueling outage while inspecting Dissimilar Metal Butt Welds (DMBWs) on two Reactor Pressure Vessel (RPV) outlet nozzles was evaluated to define the level of local permeability changes. In work performed over a decade (from 1999 to 2010) on Control Element Drive Mechanism (CEDM) seal housings at Fort Calhoun Station these local permeability changes were successfully used to monitor material susceptibility conditions that lead to degradation along primary water wetted surfaces and produce stress corrosion cracking (SCC). The work performed on the CEDM seal housings was presented to the 2010 ASME PVP Conference in Seattle (Reference 1).

Measurements taken with a pancake coil probe during the 2009 Fort Calhoun Station refueling outage along two RV outlet nozzles, shop made DMBWs have shown low local permeability variations. These variations are all within ~100% of normalized ECT signal amplitude calculated from normalized average amplitude values. The normalized signal amplitude scale was derived as a response from a 0.030" deep reference Electro-Discharge Machined (EDM) notch, the same methodology used with the CEDM seal housings at Fort Calhoun Station. The actual data collected during the 2009 refueling outage used a 0.040" EDM notch, which was corrected to the standard 0.030" EDM notch, so that direct comparisons of the CEDM seal housing to the RV nozzle outlet DMBWs data could be made.

A low level of local permeability variation in both DMBWs (as evidenced by few color palette changes in the vertical signal amplitude of the three dimensional C-Scans) combined with no detected degradation from extensive Ultrasonic Testing (UT) and ECT define conditions, which are characteristic of isotropic materials with structural stability and continuous homogeneity. No cracking, indications of cracking or repair areas were found in either DMBW. However, it is clear that this combination of examination techniques is capable of finding indications, and even finding areas of repair as evidenced by the permeability changes found in the stainless steel cladding over the nozzle area.

In conclusion, ECT pancake coil data has characterized and compared the material condition of two RV outlet DMBWs at Fort Calhoun Station to the decade of work performed on the CEDM seal housings. Both the CEDM seal housings and the two RPV outlet DMBWs at Fort Calhoun Station show the same stable structure. The lack of any significant, locally high permeability changes (a known precursor to SCC, Reference 1) in the DMBWs of two outlet RPV nozzles at Fort Calhoun Station makes initiation of SCC prior to the 2014 refueling outage a very low probability event.

Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 3 of 71

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2) Introduction In earlier experience with material condition monitoring on CEDM seal housings at OPPD Fort Calhoun Station, we have learned that monitoring local material permeability changes could be used as an indicator to detect susceptible locations where damage mechanism (PWSCC) could be initiated.

Experience with CEDM seal housing has confirmed that local permeability changes measured with normalized amplitude method, using eddy current probe with the pancake type coil, has confirmed stable material structural conditions with local permeability changes deviations measured slightly above 150% of the normalized amplitude (signal amplitude normalized with 0.030" deep calibration notch).

The preferred eddy current probe used for these measurements is one with pancake type coil. Absolute test mode used with this probe and uniform directional detection sensitivity on the inspected surface, combined with relatively large phase angle separation between flaw signals and permeability signals, in the impedance plane at 100 kHz test frequencies, allow us accurate measurements of these permeability changes. This phase angle separation also allows graphic presentation of these changes with plotting vertical signal component in 3-D, C-scan presentation.

To apply this experience on DMBW on RPV outlet nozzles the test data acquired with the pancake coil probe during the 2009 outage was evaluated. This eddy current data acquired with pancake type coil during the 2009 outage at Fort Calhoun was processed with the purpose of assessing local permeability changes along the exposed area of DMBW on two (2) outlet nozzles (nozzles at 00 and 180' orientation on RPV).

To minimize the effects of much higher permeability in the adjacent surfaces with stainless steel cladding we have used the approach to define the average measured value for permeability changes across the fully exposed DMBW surface, and compared this value with local measurements. This approach provided an alternative method to realistically assess the local deviation of these changes along the DMBW surface. Based on earlier experience with CEDM seal housings conclusions were made that the changes, with the value of 150% of the normalized amplitude (normalized with 0.030" deep EDM calibration notch) haven't experienced surface degradation mechanisms.

Local permeability changes were measured with normalized signal amplitude method similar to the process used with CEDM seal housings. The field acquired data evaluated in this report was measured with normalized signal amplitude method where normalized values were defined as a percent value of the signal amplitude from the existing calibration standard notch with nominal depth of 0.040". To compare these values with earlier experience from seal housing data, which were normalized on 0.030" deep EDM notch, we have adjusted these measurements with correction factor defined with specially procured test block containing both 0.040" and 0.030" deep EDM notches. The correction factor is calculated as a ratio between signal responses at 100 KHz test frequency from 0.040" and 0.030" deep EDM notches. Measured values for normalized amplitudes wit 0.040" deep EDM notch were directly proportional corrected for the value of this ratio. These corrected values were used for comparisons with earlier data and observations with CEDM seal housings.

Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 4 of 71

SWESDYnlE In addition to these data acquired with pancake probe the same nozzles were inspected with qualified NDE inspection techniques (UT and ECT) that have confirmed degradation free condition on these surfaces. No detectable degradations were observed.

During the local permeability measurements with pancake type probe we have noticed very low level of eddy current background noise on these surfaces. This phenomenon has produced the best resolution on the higher test frequency of 500 KHz. By observing the test data on this high frequency we were able to confirm earlier conclusions that there are no degradations present on DMBW surfaces.

This conclusion, that no degradations are present on these surfaces, has established a relatively good reference point to monitor and quantify surfaces permeability changes to identify potential locations with relatively large local permeability deviation . The characteristic of such a structurally sound surface, based on experience with CEDM seal housings, expects no major deviations for local permeability changes exceeding 150% of normalized amplitude value.

Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 5 of 71

SWESDynE

3) Local Permeability Variation (PV) Measurement Measurements of these local permeability values on two outlet nozzle were performed along DMBW circumferential direction at intervals of approximately 15 circumferential degrees. The measured values are defined as the maximum predominantly vertical component of the lissajous signal bounded between two neighboring high permeability surfaces established with stainless steel cladding on both side of DMBW-s. The essential details for this measuring process are illustrated on Figure 11.

Normalized signal amplitude from 0.040" deep EDM notch (calibration standard used with field data acquisition in 2009) is shown on Figure 7. All individual local permeability values were measured with this normalized signal amplitude scale. Individual measurements for each of the 25 locations on two outlet nozzle are shown on Figures 1 and 4. Numerical measurement and combined lissajous and 3-D, C-scan presentation are included in Attachments A and B. These measurements were used to calculate the average value of local permeability along full circumferential extent for each DMBW on these two nozzles.

For each nozzle a total of 25 individual measurements were taken along even segments along each weld's full circumference. These absolute measurements are presented in Attachment A, for outlet nozzle at 00 orientation (nozzle A), and in Attachment B, for outlet nozzle at 1800 orientation (nozzle B).

Two graphs with local permeability measurements for two nozzles are shown on Figures 1 and 4.

To calculate the value for correction factor special test block made from inconel alloy 600 was procured containing EDM notches with 0.030" and 0.040" nominal depth. Characteristic signal responses from these two notches are shown on Figures 8 and 9.

Based on measurements of signal amplitude at 100 kHz test frequency the correction factor was calculated to be 1.27.

Individual measurements from field data for each of 25 locations along two outlet nozzles were adjusted with correction factor to normalized measurement signal amplitude scale equivalent to 0.030" deep EDM notch. From corrected measurements we have calculated average value for each nozzle and define local deviation for each of the measuring locations. Calculated average value is defined as an arithmetic average for all measurements along one nozzle. The results of this local deviation from calculated average value for permeability change are shown on Figures 2 and 5. These graphs are produced with corrected values for normalized signal amplitude to reflect the compliance with normalization process using the 0.030" deep EDM notch, the same normalization process used with CEDM seal housings.

Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 6 of 71

4) Results and Observations Results of local permeability variation along two outlet nozzles DMBW on RPV at Fort Calhoun have shown low level of deviation from normalized average value. This low level of permeability variation confirms material isotropic property along the DMBW. In addition to numerical measurements summarized in graphs on Figures 2 and 5, these properties are also visible on 3-D, C-scan presentation with vertical signal amplitude components displayed with color palette image. The presented color palette is associated with the maximum values of detected permeability (dark brown-red colors) along Stainless Steel (S/S) cladding on safe end, and minimum values (blue-green color) along DMBW surface.

Slightly lover than maximum level permeability values are detected on S/S cladding on nozzle side (red-yellow colors). These 3-D, C-scans for both outlet nozzles are shown on Figures 3 and 6. From these 3-D, C-scans we can conclude on repeatable and homogenous material properties along DMBW and adjacent surfaces. Some local repair patches locations were detected along S/S cladding on nozzle sides. Based on manufacturing inspection report it appears that these areas were repaired with local grinding to remove shallow surface indications. These areas have shown lowered level of local permeability changes along S/S cladding surfaces in comparison with the as welded surface on the same material. These patches are visible in individual scan measurements in the enclosed attachments (yellow-green patches on red-orange surfaces and blue-green patches on yellow red surfaces along S/S cladding on nozzle sides).

Local permeability variations from calculated average value along DMBW-s have confirmed low level of deviations, lower than 150% of normalized amplitude with 0.030" deep EDM notch. Based on earlier experience with CEDM seal housings these level of deviations were associated with structure not affected with degradation mechanism. Very low level of permeability variation and consistency of similar properties along adjacent structure confirms that both DMBW-s on two outlet nozzle contain stable and homogenous structure characteristic for isotropic material structure along inspected surfaces.

These results in conjunction with verified structurally sound integrity along DMBW, based on extensive and elaborate combination of NDE performed with qualified UT and similar ECT inspection techniques, provide the basis to characterize these two welds as a structure with minimal property variation and high homogeneity. Such uniform structure with relatively minimal local permeability variations (lower than 150% of normalized amplitudes) were known with earlier experience on CEDM seal housings as a surfaces with minimal susceptibility to the known degradation mechanisms on wetted surfaces.

Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 7 of 71

SWESDynlE

5)

References:

1) "DETERMINING THE ONSET OF STRESS CORROSION CRACKING INAUSTENITIC STAINLESS STEEL WITH PERMEABILITY CHANGE",

Dr. Bob Lisowyj -OPPD, and Zoran Kuljis-Westinghouse Electric LLC Proceedings of the ASME Pressure Vessels and Piping Conference July 18-22, 2010, Bellevue, Washington, USA

2) CEDM Seal Housing Inspection Reports from OPPD Fort Calhoun Station, for refueling outages from 1999 to 2009. Zoran Kuljis-Westinghouse Electric LLC Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 8 of 71

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'WiEsDpfl Fig. 3 - Eddy Current Data with Pancake Coil along DMBW in Outlet Nozzle at 00 Location on Fort Calhoun RPV Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 11 of 71

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dwýEspyfl Fig. 6 - Eddy Current Data with Pancake Coil along DMBW in Outlet Nozzle at 1800 Location on Fort Calhoun RPV Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 14 of 71

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100/78.98= 1.27 Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 16 of 71

~WESpyflE Outlet Nozzle at 1800 Inlet Nozzle at 1200 InetNozzle at24O0 InetNozzle at300O Inlet Nozzle at 600 REACTOR VESSEL SCA-j-.1',,6 Outlet Nozzle at to0 II Fig. 10 - Fort Calhoun RPV Nozzles Configuration Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 17 of 71

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WESyflE Attachment A Local Permeability Measurements with Normalized Signal Amplitude to 0.040" calibration Notch Nominal Depth for Outlet Nozzle at 00 Location on Fort Calhoun RPV Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 19 of 71

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Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 57 of 71

~'WESDyflE IPJ F'VeEck View Test H*l

ILdf'l fi .. IAIO Q9 F WAN Kha-. Pmbe3590 Kb2 0.010O% 0.054%

ft. Le Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 58 of 71

'WiSDlfl

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• 105.26 S5weep 239 Datakt 380 A Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 59 of 71

AW~woýtwf C-mwmv V,_,'riN1 8.0 '0 -PRP -D[I JIN: 1 fdd,ýA:mveid().0.0 File Edit View Tester Help G9ýF bJ0 I.rnA pmba 0.061%

47.14% 306' I

Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 60 of 71

%~W;8sDvnE WN1SI W -PRP DI ION: 1 1ddyC iti rei it 6.0.0 r '1 0751 Fie Ecki View Tester H*k IF 0 ~

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Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 61 of 71

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Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 62 of 71

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lI A ACU~ 9O5-Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 63 of 71

JWEmSDynFl ViN 180 SE -PIT DET ON: I EddvCui ient 0.0.0 "ile Ex View Tester Hel IAieP -0.63 jSwee 154 Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 64 of 71

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'ImEsPvflE Me aCKvoew IM iev Hsw Q; 1FL ' ~ * "i ~ _ _ _ _ _

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Fort Calhoun RPV Outlet Nozzle PV Measurements for 2009 Data Page 71 of 71

LIC-1 1-0004 Map to Westinghouse Rockville, Maryland Nuclear Regulatory Affairs Office

Westinghouse Nuclear Regulatory Affairs Office (Red Line) Station To Frederick,MD

• Legacy Hotel WEC-tro (Red Line) Station Marineelli Road NRC Headquarters Marriott Bethesda North Hotel t 4A East Westinghouse Electric Company Miontrose Road Nuclear Regulatory Affairs 0

12300 Twinbrook Parkway, Suite 150 Rockville, MD 20852 Tel. (301) 881-7040 W E Fax (301) 881-7043 Our office is a five-minute walk from the Twinbrook Metro Station as well as the *Hilton S To Washington, D.C.

Hotel (formerly the Double Tree Hotel) and the

• The Legacy Hotel (formerly the Ramada Inn).

• Revised March 2010

L_,C-1-0004 Enclosure 5 Inspection Data 2009 Weld

WesDyne International React4)r Vessel Nozzle Weld Results Summary Ftort Calhoun Nuclear Power Station WELD NO. DESCRIPTION COVERAGE MRC-2/01 Outlet Nozzle DM Weld @ 1800 100 %

MRC-2/02 Outlet Nozzle SE to Pipe Weld @ 180' 94.24%

• LIMITATIONS NO]1 YES E1i *ID Configuration of Safe End to Pipe Weld.

UT RESULTS NI NO. OF UT INDICATIONS 0 STATUS N/A ET RESULTS X

NI RI NO. OF ET INDICATIONS STATUS N/A 0

EXAM DOCUNIENTATION

-I.

INDICATION DOCUMENTATION FR ANALYSIS LOG (UT/ET) LI ASSESSMENT SHEET F-] ACQUISITION L OG LI PARAGON HARD COPY

-X SCAN PRINTOU r F] OTHER ( specify) 1] COVERAGE BR] ,AKDOWIN WESDYNE ANAtLYST / Level / Date eýfJ 111/ 11 09

/

WesDyne International React( or Vessel Nozzle Weld Results Summary Iort Calhoun Nuclear Power Station WELD NO. DESCRIPTION COVERAGE MRC-1/01 Outlet Nozzle DM Weld @ 00 100%

MRC-1/02 Outlet Nozzle SE to Pipe Weld @ 0' 95.54%

• LIMITATIONS .YESW1X *ID Configuration of Safe NO]1 End to Pipe Weld.

UT RESULTS X

NI NO. OF UT INDICATIONS STATUS N/A 0

ET RESULTS NI NO. OF ET INDICATIONS X STATUS N/A 0

EXAM DOCUIMENTATION INDICATION DOCUMENTATION x ANALYSIS LOG (UT/ET)

D ASSESSMENT SHEET

~ PARAGON HARD COPY FX ACQUISITION 1"G XSCAN PRINTOU T KOTHER ( specify )

• COVERAGE BR 'AKDOWN WESDYNE ANAtLYST / Level / Date *L~e XL4Z-~ III / I IA 3-09

/.

Page 1 of ANALYSIS LOG # DM-SE-0-1 Utility: OMAHA DISTRICTIPUBLIC POWER Plant: FORT CALHOUN Uit: , Otage: R025 Procedure No: I PDI-ISI-254-SE IRD*l* Ll* I A*

• JA* AJAA 4-Procedure Rev. No.: 1 3 I

I ~ I e e..t........ I in

______ Vveld N'o: I MR 1/01,U 1102 J~im j j r xdI. m, uuae -

Applicable Sensitivity Calibration FC-SE-AX-DET Acquisition DM-SE-0-1 PARAGON Anal. Release:

Data Sheet No: FC-SE-CIRC-DET Log No:

UT Examiner Signature: 1 ,4<&.- Lee:I ae 11/13/09 Data File Name UT Beam Angle/ NI RI Indication / Resolution / Examiner ID0 Channel Direction Comments / Limitations Date No. finoow.mCWICv WN0-SE-PRP-DET-ON 1 IN X CSW / 11/13/09 WNO-SE-PRP-DET-ON 2 OUT X CSW 11/13o09 WNO-SE-PAR-DET-ON 1 CCW X CSWI 11/13/09 WNO-SE-PAR-DET-ON 2 CW X CSW /11/13/09 WNO-SE-PAR-DET-ON 3 CCW X Counterbore Geometry - 91.09% CSW 11i1 3/09 WNO-SE-PAR-DET-ON 4 CW X Counterbore Geometry - 91.09% CSW/11/13/09 Form 12.5 PDI-ISI-254-SE, Rev.3

ET Analysis Log: DM-SE-0-1 Utility: OMAHA PUBLIC POWER DISTRICT Plant: FORT CALHOUN Unit: 1 Outage: R026 Procedure No: WDI-STD-146 IProcedure Rev. No.: 9 VVCIWItlg, lYlR*,,- lit/ I* IIU4[ N Weld ype:r

~A eW

.... A~.-

Applicable Sensitivity Calibration Data Sheet No: ET-1I Acquisition Log No: DM-SE-0.1 ET Examiner Signature: Cf,..d' 4Z. Level III Date: 11/13/09 Data ET ET Probe Scan NI RI RI Examiner ID / Date File Name Probe Direction Resolution I Comments I Limitations No. (I aIC .)

I WN0-SE-PRP-DET-ON 1 AXIAL X CSW / 11113109 WN0-SE-PRP-DET-ON 2 AXIAL X CSW/ 11113109 WN0-SE-PAR-DET-ON 2 CIRC X CSW! 11113109 WN0-SE.PAR-OET-ON 2 CIRC X CSW / 11113/09 Form 12-5

Page 1 of 1 DATA ACQUISITION LOG # DM-SE-0-1 Utility: OPPD I Plant: I Fort Calhoun Unit: I Outage: Io02 Procedure No: PDI-ISI-254-SE Procedure Rev. No.: 3 Applicable Sensitivity Calibration Data Sheet No: SE-CIRC-DET & SE-AX-DET M i6 ... 7. Yd I 1,,.I. I II ft-.,' i JI1311YIM I LIT aminarSiemnat~re I ercMreaIVu ev :U

/ I I Data File Name Weld No. Index Scan Total # 'AVE' Gain I Date Time Comments Start Start of Signal Adj. -

Sweeps Amplitude (dB) C c;

a. (mmlddlyy)

(md/y 0-WNO-SE-PRP-DET-ON MRC-1/01 & 0 DEG 100,18" 402 10 0 DM 11/13/09 09:57 1/02 WN0-SE-PRP-DET-ON MRC-1/01 & 0 DEG 100.18" 402 15 0 DM 11/13/09 09:57 1/02 WNO-SE-PAR-DET-ON MRC-1/01 & 105.75" 0 DEG 73 17 0 DM 11/13/09 10:51 1/02 WNO-SE-PAR-DET-ON MRC-1/01 & 105.75" 0 DEG 73 15 +2 DM 11/13/09 10:51 1/02 WNO-SE-PAR-DET-ON MRC-1/01 & 105.75" 0 DEG 73 15 0 DM 11/13/09 10:51 1/02 WNO-SE-PAR-DET-ON MRC-1101 & 105.75" 0 DEG 73 13 0 DM 11/13/09 10:51 1/02 Form 12.4 PDI-ISt-254-SE, Rev. 3

WesDyne International Reactor Vessel Inservice Examination Scan Parameter Execution CUSTOMER .................... OMAHA PUBLIC POWER DISTRICT SITE ........................ FT. CALHOUN UNIT 1 OUTAGE ........................ RF025 VESSEL TYPE .................... CE 2-LOOP WELD IDENTIFICATION - MRC-1-01-02 Weld and Scan Type = NOZZLE SAFE END PERPENDICULAR SCAN Scan Data File Name = WNO-SE-PRP-DET-ONa S:AN AREA PER THE ORIGINAL TECHNIQUES UDRPS SCAN AR3A DEFINITION AZIMUTH DEPTH (DEGREES) (IN)

START CW  : 0.00 100.18 END CCW  : 360.00 100.18 START CW 0.00 117.05 END CCW  : 360.00 117.05 Index Size ( Ln) 0.25 Number of In, lexes Specified 401 Number of In,lexes Completed 401 Time Date Scan Started 08:44:43.008 11/13/09 Scan Complet 09: 56 6.553 11/13/09 Robot Operat )r Signature SDATE______ 7 PARAGON Oper itor Signature 4"#11- DATE //- IT-~ . ,

Comments 4l 0A) 9f - 57f-- Pef- 01 r- 0,L)

I

-*1

WesDyne International Reactor Vessel Inservice Examination Scan Parameter Execution CUSTOMER ..................... OMAHA PUBLIC POWER DISTRICT SITE ......................... FT. CALHOUN UNIT 1 OUTAGE . ...................... RF025 VESSEL TYPE ................. CE 2-LOOP WELD IDENTIFý CATION - MRC-1-01-02 Weld and Scaz Type = NOZZLE SAFE END PARALLEL SCAN Scan Data Fi e Name = WNO-SE-PAR-DET-ON S( .AN AREA PER THE ORIGINAL TECHNIQUES UDRPS SCAN ARI :A DEFINITION DEPTH AZIMUTH

-(IN) (DEGREES)

START CW

• 105.75 0.00 END CCW

• 105.75 360.00 START CW

• 111.47 0.00 END CCW  : 111.47 360.00 Index Size ( [n) 0.08 Number of In ýexes Specified 73 Number of In lexes Completed 73 Time Date Scan Started 10:04:32.962 11/13/09 Scan Complet 10.: 5.361 11/13/09 Robot Operat )r Signature 50,DATE___

PARAGON Oper ator Signature DATE21 Comments -I.

_____i.

Fort Calhoun Nuclear Power Plant DIRECTION / ORIENTATION RPV NOZZLE COVERAGE PARALLEL SCANS CCW/ CW ESTIMATE BREAKDOWNS PERP. SCANS IN/-OUT WELD

• I,..... 5. .J WELD NO. 11,/i111/"* 1 IA1

- ~DESCRiPTION o me il tmuzziJ a to-n y0ý. ---- A BEAM ANGLES BEAM 700 L Dual ET DIRECTION EXAM VOLUME EXAM VOLUME EXAM VOLUME EXAM VOLUME EXAM VOLUME ccw 100 100 cw 100 100 IN 100 100 OUT 100 100 UT COVERAGE =

Combined Coverage (UT & ET) = 100%

See exam volume 100%

EPP sheet 5 of 8 ANALYST 41- -----

Fort Calhoun Nuclear Power Plant DIRECTION / ORIENTATION RPV NOZZLE COVERAGE PARALLEL SCANS CCW / CW ESTIMATE BREAKDOWNS PERP. SCANS IN/ OUT WELD ^ 1 0 WELD NO. &1k 4M a I In,%i DECRWT. t3uII=-C11 r-w LU rV2i I& U V BEAM ANGLES BEAM 700 L Dual ET DIRECTION EXAM VOLUME EXAM VOLUME EXAM VOLUME EXAM VOLUME EXAM VOLUME ccw 91.09 100 cw 91.09 100 IN 100 100 OUT 100 100 UT COVERAGE Combined Coverage (UT & ET) = 100%

See exam volume 95.54%

EPP sheet 5 of 8 ANALYST

Page I of 1 ANALYSIS LOG # DM-SE-180-1 Utility: OMAHA PUBLIC POWERDPlant: FORT CALHOUN Unit: 1 Outage: R025 I DISTRICT Procedure No: PDk-Si-254-SE jProcedure Rev. No.:3 I . r... .. . . . .iI mJJ*BJ ....

r.~.. ~ I in IWeld No: I MRC-d/01, 2/02 1 Weld110 Fvm;= ý rdxam. auuaco I Applicable Sensitivity Calibration FC-SE-AX-DET Acquisition DM-SE-180-1 PARAGON Anal. Release: 6.3.5 Data Sheet No: FC-SE-CIRC-DET Log No:

UT Examiner Signature: LvelIIII Date 11/13/09 Data File Name UT Beam Angle / NI RI Indication / Resolution / Examiner ID /

Channel Direction Comments / Limitations Date No. (i, orot ONor cwj WN180-SE-PRP-DET-ON I IN X CSW / 11/13/09 WN180-SE-PRP-DET-ON 2 OUT X CSW/11/13/09 WN180-SE-PAR-DET-ON 1 CCW X CSw/ 11113/09 WN180-SE-PAR-DET-ON 2 CW X CSW/ 11113/09 WN180-SE.PAR-DET-ON 3 CCW X Counterbore Geometry - 88.48% CSW/11/13/09 WN180-SE-PAR-DET-ON 4 CW X Counterbore Geometry - 88.48%: CSW/11/13/09 Form 12.5 PDI-ISI-254-SE, Rev.3

ETAnalysis Log: DM-SE-180-1 Utility: OMAHA PUBLIC POWER DISTRICT Plant: FORT CALHOUN Unit: 1 Outage: R025 Procedure No: WDI-STD-146 IProcedure Rev. No.: 9 vvcju YV~IU flU. IVIWSU mu. "MV*-"w 0,I, V.UA tnmI fin; ype:* U. ..P Applicable Sensitivity Calibration Data Sheet No: ET-01 Acquisition Log No: DM-SE-180-1 ET Examiner Signature: " Level IlII Date: 11/13109 Data ET ET Probe Scan NI RI RI Examiner ID/ Date File Name Probe Direction Resolution I Comments / Limitations No. [.mO*m.

WN180-SE-PRP-DET-ON 1 AXIAL X CSWI 11113/09 WNI80-SE-PRP-DET-ON 2 AXIAL X CSW/ 11/13/09 WN180-SE-PAR-DET-ON 1 CIRC X CSWI 11113/09 WN180-SE-PAR-DET-ON 2 CIRC X CSWI 11113/09 Form 12-5

Page 1 of 1 DATA ACQUISITION LOG # DM-SE-180-1 Utility: I OPPD Plant: Fort Calhoun Unit: I1 Outage: R025 Procedure No: PDI-ISI-254-SE Procedure Rev. No.: 3 Applicable Sensitivity Calibration Data Sheet No: SE-CIRC-DET & SE-AX-DET

.. m z I I,.~. I m - - I 4414'I rtIIO I

-ITJ ~ i~r~~~uo I c - - -

I I

I I

Data File Name Weld No. Index Scan Total # 'AVE' Gain Date Time Comments Start Start of Signal Adj.

Sweeps Amplitude (dB) 4C. -1= (J m mn/dd iyy) 0-WN180-SE-PAR-DET-ON MRC-2/01 & 105.75" 0 DEG 73 13 0 DM 11/13/09 15:36 2/02/02 WN180-SE-PAR-DET-ON MRC-2101 & 105.75" 0 DEG 73 16 +2 DM 11/13/09 15:38 2/02 WN180-SE-PAR-DET-ON MRC-2101 & 105.75" 0 DEG 73 15 0 DM 11/13/09 15:36 2/02 WN180-SE-PAR-DET-ON MRC-2101 & 105.75" 0 DEG 73 13 0 DM 11/13/09 15:36 2/02 WN180-SE-PRP-DET-ON MRC-2!01 & 0 DEG 100.18" 401 11 0 DM 11/13/09 16:40 2/02 WN180-SE-PRP-DET-ON MRC-2/01 & 0 DEG 100.18" 401 14 0 DM 11/13/09 16:40 2/02 Form 12.4 PDI-ISI-254-SE, Rev. 3

WesDyne International Reactor Vessel Inservice Examination Scan Parameter Execution CUSTOMRR .................... OMAHA PUBLIC POWER DISTRICT SITE ......................... FT. CALHOUN UNIT 1 OUTAGE . .......... ........... RF025 VESSEL TYPE ................. CE 2-LOOP WELD IDENTIF CATION - MRC-2-01-02 Weld and Sca Type = NOZZLE SAFE END PERPENDICULAR SCAN Scan Data File Name = WN180-SE-PRP-DET-ON SCAN AREA PER THE ORIGINAL TECHNIQUES UDRPS SCAN AR-A DEFINITION AZIMUTH DEPTH (DEGREES) (IN)

START CW  : 0.00 100.18 END CCW  : 360.00 100.18 START CW END CCW J  : 0.00 360.00 117.05 117.05 Index Size ( Ln) = 0.25 Number of In, lexes Specified = 401 Number of In, lexes Completed = 401 Time Date Scan Started 15:41:49.208 11/13/09 Scan Complet 1d 16:37:44.775 11/13/09 Robot Operat, )r Signature PARAGON Oper, itor Signature ATEL4~

Comments It

-I.

WesDyne International Reactor Vessel Inservice Examination Scan Parameter Execution i

CUSTOM..R .................... OMAHA PUBLIC POWER DISTRICT SITE ...................... FT. CALHOUN UNIT 1 OUTAGE .......................... RF025 VESSEL TYPE ................. CE 2-LOOP WELD IDENTIFICATION - MRC-2-01-02 Weld and Scai Type = NOZZLE SAFE END PARALLEL SCAN Scan Data Fi e Name = WN180-SE-PAR-DET-ON

ýAN AREA PER THE ORIGINAL TECHNIQUES UDRPS SCAN AR] ,A DEFINITION DEPTH AZIMUTH (IN) (DEGREES)

START CW 105.75 0.00 END CCW 105.75 360.00 START CW 111.47 0.00 END CCW 111.47 360.00 Index Size (. .n) 0.08 Number of In(lexes Specified 73 Number of In(Lexes Completed 73 Time Date Scan Started 14:41:31.656 11/13/09 Scan Complet4 15:35:05.861 11/13/09 Robot OperatIDr Signature DATE__ _

PARAGON Operl itor Signature DAE ý Comments

Fort Calhoun Nuclear Power Plant DIRECTION / ORIENTATION RPV NOZZLE COVERAGE PARALLEL SCANS CCW / CW ESTIMATE BREAKDOWNS PERP. SCANS IN / OUT WELD i~...Ji~ ~bI.1 ~ l~ ~ Aflf0 WELD NO. SMflfl ~

-DESCRPTION- V111jej jv07 o-Sam r-nd Q too - il% lk-, Aful BEAM ANGLES BEAM 700 L Dual ET DIRECTION EXAM VOLUME EXAM VOLUME EXAM VOLUME EXAM VOLUME EXAM VOLUME ccw 100 100 cw 100 100 IN 100 100 OUT 100 100 UT COVERAGE =

Combined Coverage (UT &ET) 100% 100%

See exam volume EPP sheet 5 of 8 ANALYST

Fort Calhoun Nuclear Power Plant DIRECTION / ORIENTATION RPV NOZZLE COVERAGE PARALLEL SCANS CCW/ CW ESTIMATE BREAKDOWNS PERP. SCANS IN / OUT WELD WELD NO.

naflE 0 lOTIf~

1' IJL.~~~.UFaIF ArilDZjfUJ4P4l)A=

DI7Le' ý toJE I MRC-2/02 BEAM ANGLES BEAM 700 L Dual ET DIRECTION EXAM VOLUME EXAM VOLUME EXAM VOLUME EXAM VOLUME EXAM VOLUME ccw 88.48 100 cw 88.48 100 IN 100 100 OUT 100 100 UT COVERAGE =

Combined Coverage (UT & ET) =100%

See exam volume 94.24%

EPP sheet 5 of 8 ANALYST 2x-1z

LIC-1 1-0004 2003 Weld Scanning Information' 1 Proprietary information not pertinent to the request has been redacted.

A FkRAMATOM'E ANP Weld 22 NOZZLE-TO-SAFE END (OUTLET (a 0 DEGREES): Weld No. MRC-1/01 NO RECORDABLE INDICATIONS G22-1 Revision 0

A FRAMATOME ANP Weld 28 NOZZLE-TO-SAFE END (OUTLET A) 180 DEGREES): Weld No. MRC-2/01 NO RECORDABLE INDICATIONS G28-1 Revision 0

1 of 1 Revision 0 FORT CALHOUN EXAMINATION COVERAGE FOR WELD: W22, W28 OUTLET NOZZLE-TO-SAFE END SCAN PLAN DWG NO.: 6025824E-02 AGGREGATE COVERAGE OBTAINED: 100%

FORT CALHOUN WELD NOS:

W22 W28 MRC-1101 MRC-2101 B&I0 B5.10 Zone Coverage Ubtained Weld & Adjacent Base Metal: 100% Near (ID) Surface: 100%

Examination Volume Definition Weld Length: 100.48 in.

Area Measurement Volume Calculation Weld & Adjacent 20.55 sq. in. Weld &Adjacent 2064.864 cu. in.

Base Metal IBase Metal Near Surface 10.14 sq. in. Near Surface 1018.867 cu. In.

I I Examination Coverage Calculations Weld & Adjacent Base Metal, .1-1 Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 r ' 7&8 20.55 100.5 2064.9 2064.9 100%

2 7&8 20.55 100.5 2064.9 2064.9 100%

3 3 20.55 100.5 2064.9 2064.9 100%

4 4 20.55 100.5 2064.9 2064.9 100%

Totals: 8259.5 8259.5 100%

Near Surface (ID)

Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # ,degl Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 axial 10.14 100.5 1018.9 1018.9 100%

2 L circ 10.14 100.5 1018.9 1018.9 2037.7 100%

100%

Totals: 2037.7

A.

FRA.MATOM*E ANP FRAMATOME ANP NONDESTRUCTIVE EXAMINATION PROCEDURE ID Automated Ultrasonic Examination of Austenitic and Dissimilar Metal Piping Welds for Detection and Length Sizing Procedure Number 54-IS 1-821 -00 Issue Date: September 12; 2003 Prepared by:

K. YHacker Level III Apprved by: a M. G. Hacker Level-III THISDOCUMENT ISTHEPROPERTY OF FRAMATOME ANP, INC.,

ANDISLOANED ITNOT BE REPRODUCED OR COPIED, INWHOLE OR INPART; OR USED FOR UPON CONDITION THAT TO OTHERS, OR FOR ANYOTHER PURIPOSE DETRffAL TO THEINTERESTS OF FRAMATOME FURNISHING INFORMATION ANP. INC.,ANDISTO BERETURNED UPON REQUEST.

3 of 28 Revision 0

FRAMATOME-ANP NONDESTRUCTIVE EXAMINATION PROCEDURE ID Automated Ultrasonic Examination of Austenitic and Dissimilar Metal Piping Welds Procedure for Detection and Length Sizing 54-ISI-821 -00

1. Scope 1.1 This procedure shall govern the automated contact ultrasonic examination of full penetration dissimilar metal piping welds and wrought, austenitic piping welds and adjacent base material from the inside surface. Profiling of the surface configuration to aid in determining examination limitations is also addressed in the procedure.

1.2 This procedure has been demonstrated in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Code,Section XI, Appendix VIII, Supplements 2 and 10, 1995 Edition with Editions and Addenda through 2000, as modified the Performance Demonstration Initiative (PDI) program. This demonstration was also conducted in accordance with the requirements of the Federal Register, Part II, Nuclear Regulatory Commission, 10 CFR Part 50, Industry Codes and Standards; Amended Requirements; Final Rule, Dated 26 September, 2002.

1.3 This procedure is applicable to diameter and thickness ranges specified in Table A.

Table A Min. Diameter I Max. Diameter I Min. Thickness I Max. Thickness Supplement 2 - Austenitic Piping Welds 24.0" None 1 2.24" 3.04" Supplement 10 - Dissimilar Metal Piping Welds 24,0" None 1.80' 3.66" 1.4 The objective of the examinations performed in accordance With this procedure is to accurately detect and length size inside surface connected service induced discontinuities within the specified examination area.

1.5 Where accessible, examinations shall be performed from both sides of the weld with the beam directed perpendicular and parallel to the weld.

1.6 This procedure has been demonstrated by scanning the, inside surface of both field and shop weld configurations containing inside surface counterbore, weld root, and smooth surface conditions. Limitations exist for weld configurations for the detection of axial flaws in welds that are not machined or ground smooth. This limitation applies both to field or shop weld configurations.

2. Surface Preparation 2.1 This procedure has been demonstrated using as-welded component configurations.

However, if ultrasonic coverage of the required examination volume is limited due to surface conditions, the conditions shall be documented and reported to the owner for disposition.

THISDOCUMENT ISTHE PROPERTY OF FRAMATOME ANP, INC.,ANDIS LOANED UPON CONDITION THATITNOT BE REPRODUCED OR COPIED, INWHOLEOR INPART, OR USED FOR FURNISHING INFORMATION TO OTHERS, OR FOR ANYOTHERPURPOSE DETRIMENTAL TO THEINTERESTS OF FRAMATOMEANP, INC.ANDISTO BERETURNED UPON REQUEST.

P& 8 Of 26 Revision 0

FRAMATOME-ANP NONDESTRUCTIVE EXAMINATION PROCEDURE IDAutomated Ultrasonic Examination of Austenitic and Dissimilar Metal Piping Welds Procedure for Detection and Lenath Sizing 54-1SI-821 -00 Table E UT System Parameters System Transducer Comments Parameter RF No No This is the minimum amplitude that a peak must have to be Threshold (RG) 5% 5% recorded at RUN gain.

Gain Adjust Dual Dual This value establishes thenhumber of sequential waveforms that Coincidence 1 1 will be compared point by point before feature extraction algorithms are applied.

Rect. Mode FW FW This is'the minimum gain normalized amplitude that a peak must Threshold (CG) 0% 0% have to be to be recorded.

This feature permits the insertion of a delay between subsequent pulses if it is determined that the pulse repetition rate is too high.

D y0 0 The value is measured in ms. Normally; a value of 0 is used Delay 00 unless evidence of wrap~around is noted in the data. If wrap-around is noted, increase the. delay value until the signal disappears.

PR Mode Dual Single Pulse Width 250 100 Pulser Source External Pulser Voltage 300 The pulser voltage for the surface profile scan may beadjusted lower to ensure that the surface response ishnot saturated.

Gain BOost None The systems ability to keep up with recording UT data is a function of several variables and can be controlled by reducing the scan speed. The data analyst can determine during the analysis of the data file if the scan speed was to fast for the Scan Speed Maximum Speed 3" sec. system to record the data of interest that are indicated as intermittent areas of no data along the scan line that is not contributed to coupling effects. If the analyst determines the data is unacceptable due to an excessive scan speeda rescan shall be performed at a slower scan speed.

Index Increment 0.05' axial 050 Along the axis of the pipe.

circ Scan direction Circumferential Axial Index direction Axial Circ This is the interval at Which data is collected along the scan line.

The pulse repetition rate is a function of the speed at which the ACCUSONEXTM data acquisition system can be configured to take multi-channel data during automatic operation. The pulse repetition rate is set by the delay and length of the acquire Sync, Interval 0.05" 0.02" window and the processing'time for each A-scan, The pulse repetition rate is not available to the operator as an adjustable control on the system. For the circumferential directed probes, the sync. Interval shall be converted to degrees based on the largest diameter being scanned.

Active Channel 1, 2, 3, 4, 5, 6 7 Select the channels that are to be active during the scan.

Display Channel 5 7 Activates the channel to be displayed during acquisition.

THIS DOCUMENT IS THEPROPERTY OF FRAMATOME ANP, INC.,ANDIS LOANEDUPON CONDITION THATITNOT BE REPRODUCED OR COPIED, IN WHOLEOR INPART, OR USED FOR FURNISHING INFORMATIONTOOTHERS, OR FOR ANYOTHER PURPOSE DETRIMENTAL TO THE INTERESTS OF FRAmATOME ANP, INC.,ANDIS TOBE RETURNED UPON,REbUEST.

26 Revision 0

FRAMATOME.ANP NONDESTRUCTIVE EXAMINATION PROCEDURE ID Automated UltrasonicExamination of Austenitic and Dissimilar Metal Piping Welds Procedure for Detection and Length Sizing 54-ISI-821-00 ASME Section Xl Examination Volume for Dissimilar Metal Welds A-B-C-D Additional Procedui'e Examination Volume Coverage A-B-E7F ASME Section Xl Examination Volume for Austenitic Piping Welds C-D-E-F Figure 3 - Examination Volume THISDOCUMENT IS THE PROPERTY OF FRAMATOME ANP, INC..ANDIS LOANED UPON CONDITIONTHATIf NOT BE REPRODUCED OR COPIED, IN WHOLEOR INPART. OR USED FOR FURNISHING INFORMATION TO OTHERS, OR FOR ANYOTHER PURPOSE DETRIMENTAL TO THEINTERESTS OF FRAMATOME ANP, INC.,ANDIS*TOBE RETURNED UPON REQUEST.

PO ýf26 Revision 0

FRAMATOME-ANP NONDESTRUCTIVE EXAMINATION PROCEDURE ID Automated Ultrasonic Examination of Austenitic and Dissimilar Metal Piping Welds Procedure for Detection and Length Sizing 54-ISI-821-00 Figure 4 Typical Transducer Head Arrangement THISDOCUMENT IS THEPROPERTY OF FRAMATOME ANP. INC.,ANDIS LOANEDUPON CONDITION THATIT NOT BE REPRODUCED OR COPIED, INWHOLE OR INPART, OR USED FOR FURNISHING INFORMATIONTO OTHERS, OR FOR ANYOTHER PURPOSE DETRIMENTAL TO THE INTERESTS OF FRAMATOMEANP. INC.,ANDIS TO BE RETURNED UPON REOUEST.

PAO-.8f 26 Revision 0

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AXIAL SCANNING) 2:*3 UT HF-E4ONIUATO D

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NOTE:HC-# = HEADCOMPRESSION NOTE- HC-f = HEAD COMPRESSION

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