ML13015A007

Response to Request for Additional Information -Relief Request RR-ISI-04-07A, Dissimilar Metal Butt Welds Baseline Examinations

ML13015A007
Person / Time
Site:	Calvert Cliffs
Issue date:	01/10/2013
From:	John Stanley Calvert Cliffs, EDF Group, Constellation Energy Nuclear Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13015A007 (52)

Text

- f Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 CENG.

a joint venture of constellation -

OEnergy ~ eDF CALVERT CLIFFS NUCLEAR POWER PLANT January 10, 2013 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Response to Request for Additional Information -Relief Request RR-ISI-04-07A, Dissimilar Metal Butt Welds Baseline Examinations

REFERENCES:

(a) Letter from Mr. J. J. Stanley (CCNPP) to Document Control Desk (NRC) dated June 7, 2012, Relief Request for Unit 2 Dissimilar Metal Butt Welds Baseline Examinations (RR-ISI-04-07A)

(b) Letter from Ms. N. S. Morgan (NRC) to Mr. G. H. Gellrich (CCNPP),

dated November 7, 2012, Calvert Cliffs Nuclear Power Plant, Unit No. 2 -

Request for Additional Information Regarding Relief Request RR-ISI-04-07A, "Dissimilar Metal Butt Welds Baseline Examinations" (TAC No. ME8871)

In Reference (a), Calvert Cliffs Nuclear Power Plant, LLC (Calvert Cliffs) submitted relief request RR-ISI-04-07A, for Calvert Cliffs Unit 2, for authorization of proposed alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-770-1. In Reference (b), the Nuclear Regulatory Commission requested additional information be submitted to support their review of Reference (a). The responses to Reference (b) are attached.

The response to Reference (b) includes some proprietary information from Structural Integrity Associates, Inc.*. The response containing proprietary information is contained in Attachment (1). Attachment (2) is an affidavit signed by Structural Integrity Associates, Inc. requesting withholding of the proprietary information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission, and addresses, with specificity, the considerations listed in 10 CFR 2.390(b)(4). Accordingly, it is requested that the information that is proprietary to Structural Integrity Associates, Inc. be withheld from public disclosure. A non proprietary version of our response to

. I Document Control Desk January 10, 2013 Page 2 Reference (b) is included in Attachment (3). Enclosures 1 through 4 are applicable to both the proprietary and non proprietary versions.

Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.

Very truly yours, James J. Stanley Manager-Engineering Services JJS/KLG/bjd Attachments: (1) Response to Request for Additional Information - Relief Request for Calvert Cliffs Unit 2 RR-ISI-04-07A Proprietary Version (2) Affidavit for Withholding Proprietary Information (3) Response to Request for Additional Information - Relief Request for Calvert Cliffs Unit 2 RR-ISI-04-07A Non Proprietary Version

Enclosures:

I Procedure SI-UT-130 Qualification Summary 2 30-RC-2 1B-10 Examination Coverage 3 30-RC-22A-10 Examination Coverage 4 300 Beam Width/Sound Field Energy Angle Simulation cc: N. S. Morgan, NRC Resident Inspector, NRC W. M. Dean, NRC S. Gray, DNR

ATTACHMENT (2)

AFFIDAVIT FOR WITHHOLDING PROPRIETARY INFORMATION Calvert Cliffs Nuclear Power Plant, LLC January 10, 2013

CStructuralIntegrity Associates, Inc!

5215 Myer Ave.

Sufs 210 San Jose, CA 95136-1025 Phone: 406-978-8200 Fax: 406-97849M4 wwwcw.com December 17, 2012 AFFIDAVIT I, Marcos Legaspi Herrera, state as follows:

(1) I am Vice President of Structural Integrity Associates, Inc. (SI) Nuclear Plant Services and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in SI "Manual RL38 Wedge Assembly" Design Drawing 100100 Rev. 0, and "Manual R555 Wedge Assembly" Design Drawing 100101 Rev. 0. Information from these design drawings is to be treated as SI proprietary information, because it contains significant information that is deemed proprietary and confidential to Structural Integrity Associates. The design of Structural Integrity Phased Array wedges, if used by a competitor, would reduce the competitor's expenditure of resources and improve its competitive position in the design and manufacture of similar products for their use during qualification and application of Phased Array Ultrasonic Examinations.

Paragraph 3 of this Affidavit provides the basis for the proprietary determination.

(3) SI is making this application for withholding of proprietary information on the basis that such information constitutes Trade Secrets, which if used by a competitor, would reduce the competitor's expenditure of resources and improve its competitive position in the design and manufacture of similar products for their use during qualification and application of Phased Array Ultrasonic Examinations. This application for withholding of proprietary information complies with the exemption of disclosure set forth in 10CFR2.390(a)(4) pertaining to "Trade secrets and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4). Information for which exemption from disclosure is herein sought is considered proprietary for the following reasons:

a) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.

SI Affidavit for Phased Array Wedge Design Information December 17, 2012 Page 2 of 4 I declare under penalty of perjury that the above information and request are true, correct, and complete to the best of my knowledge, information, and belief.

Executed in San Jose, California on this 17"' day of December, 2012.

Matros Legaspi Herrera, P.E.

Vice President Nuclear Plant Services State of California Subscribed and sworn to (or affirmed) before me County of " . r-0a""- on this H4 day of C_,, "- ,20 2M, Date Month Year by U Na&, of Signer proved to me on the basis of satisfactory evidence a - - - -

to be the person who appeared before me (.) (*

SOVM C R (a9d Convnisalon

• I SM27 Notary Pulft - California (2)

Clara County SUNExpires Name of Signer Mir Comm. S" 27.2013 t r0rW-AM proved to me on the basis of satisfactory evidence to be the persornwho appeared before me.)

Place Notary Seal and/or Stamp Above CStructuralIntegrity Associates, Inc

SI Affidavit for Phased Array Wedge Design Information December 17, 2012 "Pages 3 & 4 intentionally omitted as they contain proprietary information."

CStructuralIntegrity Associates, Inc2e

ATTACHMENT (3)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -

RELIEF REQUEST FOR CALVERT CLIFFS UNIT 2 RR-ISI-04-07A NON PROPRIETARY VERSION Calvert Cliffs Nuclear Power Plant, LLC January 10, 2013

ATTACHMENT (3)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -

RELIEF REQUEST FOR CALVERT CLIFFS UNIT 2 RR-ISI-04-07A NON PROPRIETARY VERSION By letter dated June 7, 2012 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML12164A372), Calvert Cliffs Nuclear Power Plant, LLC, the licensee, submitted Relief Request RR-ISI-04-07A for authorization of proposed alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Case N-770-1 for Calvert Cliffs Nuclear Power Plant, Unit No. 2. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and requests the following additional information:

1. Describe the hardship associated with obtaining 100 percent axial scan coverage of the susceptible mnaterialfor welds 30-RC-21A-JO and 30-RC-21B-JO.

The physical restriction limiting the axial scanning coverage for welds 30-RC-21A-10 and 30-RC-21B-10 are the nozzles to the Reactor Coolant System (RCS) piping which connect to the pressurizer spray system. Each nozzle is a three inch branch connection off the 30 inch cold leg loop piping and is located on the downstream side of each of the subject welds. The nozzle bosses extend for a 10 inch arc length along the circumference of the RCS piping. The necessary pull back distance of the inspection probe is limited along this 10 inch arc length resulting in reduced coverage of the examination volume in this area only. The limitation was conservatively determined assuming the most limiting exam restriction (i.e., top dead center) for the full 10 inch arc length. In order to improve axial scanning coverage in this area a significant amount of base metal would have to be removed from the nozzle bosses. For weld 30-RC-21B-10 there is also a structural steel support that is directly upstream and in line with the base of the nozzle boss. This obstruction only extends for 4 inch arc length and is bounded by the 10 inch arc length of the nozzle boss. Therefore, removal of the support steel will not significantly improve coverage.

2. State whether any indications were found in the five subject welds of this proposedalternative during the 2011 refueling outage examinations, and how these indicationshave been dispositioned.

The ultrasonic examination (UT) volumetric examinations conducted on the five subject welds reported no recordable indications.

a. If reportable indications were found that were identified as embedded flaiws due to lack of apparent connection to the weld root, provide information on the depth of the indications.

Not Applicable. There were no recordable indications reported for the subject welds.

3. Provide a copy of the performance demonstration qualification summary and identifv any specific limitations associatedwith the scope of the SI- UT-130 R3 ultrasonicexamination (UT) procedure.

The Performance Demonstration Qualification Summary (PDQS) for procedure SI-UT-130 R3 is attached in Enclosure 1.

According to the procedure's PDQS (PDQS No. 632, Revision 1) issued on August 26, 2009 by the Electric Power Research Institute Performance Demonstration Initiative Program, the following limitations are specified:

• This procedure is not qualified for examinations from the cast stainless steel side of a component.

• This procedure is only qualified to depth size flaws in accessible regions of the examination volume.

• This procedure is only qualified to length size circumferentially oriented flaws.

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• This procedure is not qualified for examinations where the ultrasound is required to propagate through an adjacent austenitic weld prior to impinging on the dissimilar metal weld.

" This procedure is qualified for examinations from both single and dual sided access as applicable.

• This procedure is only qualified for examinations on demonstrated configurations.

• This procedure is not qualified to detect axial flaws on the far side of a single-sided access component containing a tapered weld configuration.

a. Did the UT procedurepass the ASME Code.Section XI. Appendix VIII requirements with the 10 degree mcrinmuni skew angle?

Yes, procedure SI-UT-130 R3 was qualified with a +10° electronic skew angle in accordance with the Performance Demonstration Initiative implementation of ASME Code Section XI, Appendix VIII.

4. For welds 30-RC-21B-IO and 30-RC-22A-lO, provide an estimate of the time requiredfor the largest potential undetected root-connectedflaw in the susceptible materialto grow by pritnaly water stress corrosion cracking (PWSCC) in response to operationaland weld residualstresses to exceed ASME Code,Section XI, IWB-3600 allowable size.

WCAP-17128-NP, Revision I (Reference 1) and Electric Power Research Institute MRP-349 (Reference 2), provides circumferential and axial flaw evaluations in accordance with ASME Code Section XI, that bound this Request for Additional Information Questions 4 and 5.d.i. Input to the flaw evaluations use the highest stresses and bending moments for all Combustion Engineering, Inc.-

designed plants participating in the evaluation which includes Calvert Cliffs. Operating pressure is 2,250 psi, and the temperature ranges between 543°F and 553°F for the associated plants. Calvert Cliffs Cold Leg operating temperature is 548°F. The design pressure of 2,500 psi and temperature of 553°F were used in these flaw evaluations. Higher pressure results in higher stress, and higher temperature results in higher crack growth rates. Therefore the flaw evaluations are conservative for Calvert Cliffs.

Results of the flaw evaluation for circumferential flaws are presented in Figures 6-17 through 6-20 of WCAP-17 128-NP, Revision I and Figures 5-2 and 5-3 of MRP-349. These flaw evaluations provide the maximum acceptable initial flaws accounting for PWSCC and fatigue crack growth. For weld 30-RC-2113-10 the maximum undetected circumferential crack depth (a), length (1), and thickness (t) are 1.2 inch, 10 inches, and 3.15 inches, respectively such that a/l = 0.12 and a/t = 0.381. In the residual stress cases, the time to reach the ASME allowable crack size, for an initial undetected flaw of this size, is more than 120 months.

Results of the flaw evaluation for axial flaws are presented Figures 6-13 through 6-16 of WCAP-17128-NP, Revision 1. These flaw evaluations provide the maximum acceptable initial flaws accounting for PWSCC and fatigue crack growth. For weld 30-RC-22A-10 the maximum undetected axial crack depth (a), length (I), and thickness (t) are 0.2 inch, 0.4 inches, and 3.1 inches, respectively such that a/I = 0.5 and a/t = 0.065. In the residual stress cases, the time to reach the ASME allowable crack size, for initial undetected flaws as describe above, is much more than 48 months. Another conservatism of this result is that the maximum undetected flaw is bounded on two sides by base metal such that PWSCC will not extend in these directions. Furthermore the examination limitation for the 3C-RC-22A-10 is only in the extension of the butter weld that serves as cladding to the carbon steel pipe which would arrest further PWSCC growth.

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5. In order to permit the Nuclear Regulatory Commission staff to verify the flav analyses:

a. Providedatafor:

i. Pipe diameter.

Approximately 36 inches OD (outer diameter) and 30 inches ID (inner diameter).

ii. Wall thickness.

Approximately 3.1 inches.

iii. Safe end length.

Approximately 2.1 inches at the OD, not including the weld.

iv. Weld operatingtemperature.

5480 F

v. Internalpressure.

Operating pressure is 2,250 psi.

vi. Axial stress due to internalpressure.

Hoop stress is equal to 13,725 psi at operating pressure using minimum design wall thickness of 2.50 inches.

vii, Global bending stress.

Design membrane stress equals 16,500 psi at minimum design thickness of 2.50 inches.

b. Provide drawings of the circumferential cross sectional arc of weld 30-RC-21B-IO and caxial cross section of weld 30-RC-22A-lO showing the scale of the drawing and:

Enclosures 2 and 3 contain the details discussed below in 5.b. (i. - iii.) for welds 30-RC-2IB-10 and 30-RC-22A- 10.

i. Coverage maps showing the uninspected region of the susceptible material.

The green area shown on the coverage maps for welds 30-RC-2 1B- 10 (Enclosure 2) and 30-RC-22A-10 (Enclosure 3) illustrate the area of the weld joint that ultrasonic coverage was achieved.

ii. Dimensions of the largestpotential undetected P WSCC flaw.

See Enclosures 2 and 3.

iii. Position of theflaw when it can first be detected using the UT procedure employed See Enclosures 2 and 3.

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1. What criterion is used for determining how far the hypothetical flaw must extend into the inspected region before it is detected?

The hypothetical flaw for weld 30-RC-2 11B- 10 would be detected at recordable levels as soon as it breaks into the inspected region shown in Enclosure 2. The basis for this is the conservatisms set in place with the graphical depiction of the ultrasonic coverage plot shown in Enclosure 2. The lowest qualified angle used for claiming ultrasonic coverage is 300. The beam width/sound field energy for the 300 angle is shown in Enclosure 4. The beam modeling image shows that the sound field energy/width extends both below and above the generated 300 angle. Furthermore, the technique used in the SI-UT-130 R3 procedure generates a range of angles from 00 to 85' in 1' increments. Therefore, the weld is also being interrogated using angles less than 300. The sound field energy at the area of interest is more than adequate to produce an ultrasonic response when the theoretical flaw would cross into the insonified area (depicted on Enclosure 4). Combining the 30' qualified angles with the lower unqualified angles that are interrogating the inspection area, it is plausible to say that a flaw initiating from the obstructed area would be detected by the techniques and technology employed at Calvert Cliffs. The procedure also calls for manual skewing to be used to the maximum extent that the scanning surface will allow.

Scanning these large diameter welds using a flat wedge allowed manual skewing of approximately 20' to be achieved during the examinations.

For weld 30-RC-22A-10, the hypothetical flaw shown in Enclosure 3 will arrest in PWSCC growth in the through-wall direction once it reaches the carbon steel base material. Any further PWSCC crack growth would occur in the axial direction. This flaw would be detected by using the electronically generated 100 skew for circumferential scans coupled with the procedurally required manual skewing before growing beyond the cladding level.

c. Provide a description of the weld process, including am' post-weld machining (including back chipping and rewelding on the inside diameter).

The typical fabrication practice for these welds were to back-chip the root of the weld to sound metal from the inside surface and re-weld flush with the ID. This fabrication practice is equivalent to performing an ID repair to a depth of approximately ten percent of the wall thickness for the full 3600 around the pipe.

d Provide the acial weld residual stress (WRS) profile used for weld 30-RC-21B-IO and hoop WRS profilefor weld 30-RC-22A-10.

Guidelines found in Electric Power Research Institute MRP-287, Section 3.6. suggest using a weld repair depth of 50 percent for calculation of the WRS profile. If a weld repair depth of less than 50 percent is usedfor the present WRS determination, provide justification for the weld repair depth assumed. This justification could include documentation of the number and depth of weld repairsfor the subject welds.

Several weld repair depths were used to determine various WRS profiles in WCAP-17 128-NP, Revision 1.

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1. A 10% MD weld repair with heat treatment after the loop piping butter, but with no heat treatment after the weld repair. Note that this condition is similar to the actual fabrication condition of this region with no repair, as the weld is back chipped from the inner diameter.

2. A 10% ID weld repair with heat treatment after the loop piping butter and with heat treatment after the weld repair.

3. A 25% ID weld repair with heat treatment after the loop piping butter and with heat treatment after the weld repair.

4. A 50% ID weld repair with heat treatment after the loop piping butter and with heat treatment after the weld repair.

All crack growth rates and flaw tolerance evaluations were determined using all these cases which include a 50% ID weld repair.

ii. If post-repair heat treatment is used in the WRS calculation, provide documentation that the heat treatment was perfornmed.

Fabrication records indicate there were no repairs of the butter or the dissimilar metal weld for weld 30-RC-21A-10 and 30-RC-22A-10.

There was one repair of the butter weld associated with 30-RC-21B-10 and no repair of the dissimilar metal weld joining the safe end. Since the repair was in the butter it was post weld heat treated before the dissimilar weld joining the safe end was made.

There was no post-repair heat treatment since there were no repairs of the dissimilar welds joining the safe end. Therefore, WRS case I above applies to these welds.

iii. Is the effect of the safe end stainless steel weld used in determining the stress profiles?

The safe end stainless steel weld was not used in determining the weld residual stress profiles.

6. As a defense in depth measurefor indications which may exist in the areas that cannot be examined and may grow through-wall, leakage monitoring is useful in the early detection of through wall cracks. Describe the leakage monitoring usedfor the reactor coolant pressure boundari. including leak rates or trends that would cause actions to be taken to determine the location of leaks.

The primary method for characterizing RCS identified and unidentified leakage is by means of a reactor coolant inventory analysis (commonly called a water balance inventory) performed under surveillance test procedures every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Leak detection at Calvert Cliffs Nuclear Power Plant is also provided by three systems: 1) containment sump level alarm system; 2) containment atmosphere particulate monitoring system; and 3) containment atmosphere gaseous radioactivity monitoring system.

The leak rate calculated using water balance inventory method is the most sensitive of the methods available with the leak rate calculated to the nearest 0.01 gallons-per-minute (gpm). The sensitivity 5

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RELIEF REQUEST FOR CALVERT CLIFFS UNIT 2 RR-ISI-04-07A NON PROPRIETARY VERSION of the containment radioactivity monitors varies depending on the amount of radioactivity in the primary coolant, which depends on the percentage of failed fuel. The time to detect a 0.1 gpm leak with the containment atmosphere radioactivity monitors varies from 61 minutes for 1% failed fuel to 1743 minutes (29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />) for 0.001% failed fuel. The containment sump alarm response is also highly variable dependent on the location of the leak, how much vapor condenses and where it condenses. A total amount of leakage of approximately 49 gallons will cause a sump level alarm.

Calvert Cliffs Nuclear Power Plant Technical Specification 3.4.14, "RCS Leakage Detection Instrumentation," also requires that the containment atmospheric radiation monitor and containment sump alarm be operable or other compensatory actions be taken, such as performing the water balance leak rate calculation more frequently (at a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> rather than 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> interval).

Action Levels on the absolute value of Unidentified RCS Inventory Balance (from surveillance data):

• Level 1 - One Seven day rolling average of Unidentified RCS Inventory Balance (from surveillance data) greater than 0.1 gpm.

" Level 2 - Two consecutive Unidentified RCS Inventory Balance Values > 0.15 gpm.

• Level 3 - One Unidentified RCS Inventory Balance value > 0.3 gpm.

Action Levels on Deviation from the Baseline Mean:

• Level 1 - Nine consecutive Unidentified RCS Inventory Balance values > baseline mean [lt]

value.

" Level 2 - Two of three consecutive Unidentified RCS Inventory Balance values > ((t + 27],

where a is the baseline standard deviation.

• Level 3 - One Unidentified RCS Inventory Balance value > [gt + 3y].

7. In order to assess when the UT examinations would be expected to detect PWSCC flaws, examinations of welds 30-RC-21B-10 and 30-RC-22A-10 need to be modeled In order to make these models accurate, information is needed concerning the as-built geometries of the subject welds and variablesassociatedwith the phased array method Provide the following information."

a. As-built weld geometry:

i. Scaled drawings are needed to create accurate CAD models of the weld and surrounding geometry. Provide dimensioned drawings of the subject welds including the immediate region around the weld location.

See Enclosures 2 and 3 for scaled drawings of welds 30-RC-21B-10 and 30-RC-22A-10.

ii. Estimate and provide depth of geometrical anomalies (e.g., concavity or waviness) on the outside diameter surface of the welds that impact volumnetric inspection. Also, provide distancesfr-om weld to any obstructions that limit the inspection of the weld region.

The scaled drawings provided in Enclosures 2 and 3 include the outside diameter surface profiles for 30-RC-21B-10 and 30-RC-22A-10 and include dimension to any associated obstructions.

b. Phased arrayprobe:

i. Centerfrequency, bandwidth, pulse excitation type and duration.

See Table 1.

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RELIEF REQUEST FOR CALVERT CLIFFS UNIT 2 RR-ISI-04-07A NON PROPRIETARY VERSION ii. Operatingmode.

1. Transmit-receive (TR), pulse / echo, etc.

Transmit / Receive

2. Longitudinal(L) and/or shear (S) wave.

In accordance with examination procedure SI-UT-130 R3, longitudinal and shear waves are used for the detection and sizing of circumferential flaws. Only longitudinal waves are used for the detection and sizing of axial flaws.

iii. Array configuration (natrix)):

1. Whether identical or different transmit-receivearrays were used (if applicable).

Identical transmit-receive arrays were used.

2. Physical separation between arrays (if TRL/TRS configuration). Identifv distance between first element of one array and first element of second array (array separation-seeFigure 1.).

3.

[If TRL or TRS mode is used, identify transmit and receive arrays (relative to weld

]

geometry).

Dual side by side arrays are used. When a -10' electronic skew is used the transmitter is closest to the weld and when a +10' electronic skew is used the receiver is closest to the weld.

iv. Total number of elements per array:

1. Number of elements along the primaty caxis.

16

2. Number of elements along the secondary cLviS.

Two transmit and two receive

v. Element dimensions along primary and secondary axes, spacing between elements, and center-to-centerdistance (pitch- see Figure 2):

See Table 1.

1. Element shape if not rectangular.

Not applicable. Element shape was rectangular.

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RELIEF REQUEST FOR CALVERT CLIFFS UNIT 2 RR-ISI-04-07A NON PROPRIETARY VERSION vi. Element wiring configuration and element firing/receiving ordering sequence ]br each array.

See Table I for wiring configuration. The element firing/receiving ordering sequence for each array are found in the focal laws which are unavailable, however the focal laws were developed using the Zetec Advanced Focal Law Calculator software Revision 1.0R5.

vii. Probe manufacturerand/orpart number.

See Table 1.

c. Wedge (see Figure 3):

i. Materialtype-Rexolite, other, etc.

Wedge material is Rexolite.

1. Longitudinaland shear wave velocity.

The probe generates longitudinal waves only. Wedge velocity for longitudinal waves:

2330 m/s.

2. Attenuation.

Unknown

3. Density.

1.05 g/cm 3 per typical Rexolite material specifications ii. Geometry:

1. Wedge angle.

2.

[Roof angle (if used).

]

3.

[ ]

All physical dimensions necessary to create 3-D solid model, such as height at fiont of wedge, height at back of wedge, width ofwedge, and length of wedge

+

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4. Placement of each probe on each wedge, i.e., what is the height of the middle of the

[first element?

]

5. Is wedge contact geometry contoured to the specimen? If not, what contour does it have, any?

The wedges used for scanning the subject welds were flat.

d Beam focusing:

The type offocusing technique is needed as well as the specific parametersassociatedwith each type. The four types offocusing techniques are listed below and shown graphically in Figure 4. State the type of focusing used and include associated details, as listed below:

1. Projection-focusing in a specific verticalplane.

a. Parameters: distance from probe reference point, sweep angles (start, stop, interval), skew angle(s).

Not applicable, the half-path focusing method was used.

2. True depth-focusing at specific constant depth with all anglesfocused at this depth.

a. Parameters:focusing depth, sweep angles (start,stop, interval), skew angle(s).

Not applicable, the half-path focusing method was used.

3. Half-path-soundpath held constant as beam is swept.

The examination procedure utilizes the half-path focusing method.

a. Parameters: sound path length, sweep angles (start, stop, interval), skew angle(s).

See Table 2.

4. Focalplane - arbitraryuser-definedplane offocus.

a. Low angle path length, high angle path length, sweep angles (start, stop, interval), skew angle(s).

Not applicable, the half-path focusing method was used.

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RELIEF REQUEST FOR CALVERT CLIFFS UNIT 2 RR-ISI-04-07A NON PROPRIETARY VERSION ii. Number and configuration of elements used in data acquisition (active aperture), if different than total number of elements within each probe (e.g., if a linear arrayprobe physically contains 64 elements but only the first 32 were active - this needs to be defined).

Not applicable. All elements within the probe were used and there were no inactive elements.

iii. If possible, please provide a set of transmit and receive delay law values for each element at a particularangle andfocus to validate model.

Focal laws were developed using Zetec Advanced PA Calculator Software, Revision 1.0R5.

Table 1 - Probe Specifications GEITPhased Array Probe Specifications Part Number 115-000-566 Number of Elements Dual 32 Center Frequency (MHz) 1.53 Bandwidth 88% @ -6dB Pulse Excitation Type Negative Square Wave Pulse Duration 2.69ps @ -20dB 3.54ps @ -40dB Connector I-Pex Cable Type 111-160-085, 34 Conductor Coaxial 500 Cable Length 8 ft.

Total Crystal Size 1.246" x 0.274" Nominal Ceramic Volume % 30%

KT Min (efficiency) 0.6 Nominal Ceramic Thickness 0.373" Element Dimensions Inch mm Primary Axis Pitch (16el) 0.078 2.0 Spacing (Kerf) 0.002 0.05 Element Size (16el axis) 0.076 1.95 Secondary Axis Pitch (2el) 0.138 3.5 Spacing (Kerf) 0.002 0.05 Element Size (2el axis) 0.136 3.45 10

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RELIEF REQUEST FOR CALVERT CLIFFS UNIT 2 RR-ISI-04-07A NON PROPRIETARY VERSION Table 2 - Half-Path Sound Parameter Axial Circumferential Examinations Examinations Long. Wave Shear Wave Long. Wave Exams Exams Exams Beam Range 00 - 850 250 - 750 00 - 850 Resolution (Interval) 1.00 1.00 1.00 Sound Path 113 mm 113 mm 111.7 mm Skew Angle N/A N/A +/-100 Electronic w I I -

m U Axi- of -ff a

i

' i.

I ------------

I I Lo l *o 1 Figure 1 - Top View of 2D Matrix Array Depicting Separation Dimension I1

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RELIEF REQUEST FOR CALVERT CLIFFS UNIT 2 RR-ISI-04-07A NON PROPRIETARY VERSION SeconOY aS Es Rb 81 R E11 30 3* aR

mo q iao aa E4 at %

-0 - -4 s k.

swn ary is pkch 3

spitch Figure 2 - Top View of 2D Matrix Array Depicting Primary and Secondary Axis Pitch Dimensions Figure 3 - Definition of Wedge Angle 12

ATTACHMENT (3)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -

RELIEF REQUEST FOR CALVERT CLIFFS UNIT 2 RR-ISI-04-07A NON PROPRIETARY VERSION Projection. (z) True depth (x) Half path Focal plane z = ax + b 1i Figure 4 - Beam Focusing Options for Phased Array Probes

REFERENCES:

1. WCAP-17128-NP, Revision 1, Flaw Evaluation of CE Design RCP Suction and Discharge Nozzle Dissimilar Metal Welds, Phase III Study, May 2010

2. Electric Power Research Institute, MRP-349, PWR Reactor Coolant System Cold-Loop Dissimilar Metal Butt Weld Re-Examination Interval Extension, August 2012 13

ENCLOSURE1 Procedure SI-UT-130 Qualification Summary Calvert Cliffs Nuclear Power Plant, LLC January 10, 2013

Performance Demonstration Initiative Program Pited:

PDQS No:

26-Aug-09 632 In Acconmace with the PD! Implementation of Section XI, Appendix VM 04061103 Specific Detail of Qualifications Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS FDQ Rev: I -bvSWTyP.RS MA DidethoJam 26-Aug-09 Ope~rsW Ty"I"BM~ MA BenApleades-mammac R-nga D ntng Raneyes Demonstrated:

Dabs 011-M4l9 11001111400 2.00 MInThick 0.280, MazDbm 50-0 NEMa cicbn 5200 Mearihb DisfnlrMOWl Zznamll J26ACdh Ancon SingleSided Wedi Coindesm GUusd Flush bZAeidM* L400 izif Asuan Single Sided WWd C~alidev Gound Flush Exaoludes: TflEugh Wfil Sizing AGO= Singe Sided Weddeaideu: aroun Flush Page 1 of 21

Printed: 26-Ang-09 Performance Demonstration Initiative Program PDQS No: 632 In Accordance with the PDI Implementation of Section XI, Appendix VII 04061103 Specific Detail of Qualifications Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: I Anmaysis SW Typa(Rev: N/A Date of Isaae 26-Aug-09 Operator SW Type/Rev: N/A Hardware: N/A Scan Applicatioa: Manual Category: Piping ExamiSurfaes: Outside Whb "Lmgth Sig* inindicated, the 0.750 RMS acceptnce criteria per the PD! Program Description has bee achieved.

When Trluog Wan Sizi* is indicated, the 0. 125 RMS acceptace aitia per the PDI Program Description has bew achieved.

Tarnesen fr add appdiceams -S alows:

Dio . Lower.. 500"am be sukacted from to h inuandiasmue denunstrted.

Uppiar. DWia ers grater daem 24" need not be auutrafe Thicnams: Low 0.100" co be subtracted fom the mwn* umthi, mesa democsrated bfor boath msitic and feritic 2*% of the niminim thickness destmitraed ft dissimilar metal welds Upp. 1.000" ca be added to the m inmum thicitme demonstrated for feniuic material.

0."00" be added to the nuxinan thickmess damonaated for autenitic material.

25% of the mnximnun thicness demonstrated fir dissimilar metal welds ConamnamtL I See procedure and attached Table I for qualified search unit/instrument combinations.

2 The PDl Dissirnlar Metal Weld Mock-up Criteria document may be used in conjunction with this procedure to address configurations which am not represented in the PDI sample inventory.

3 Weld joint designs of demonstrated component configurations are included in the subsequent pages of this PDQS docurnt.

4 Reftated longitudinal wave examination angles of 30" to 709 or shear wave exanination angles of 45" to 70" may be used to calculate and document coverage of the ASME Code required examination volume with this procedure.

5 Personnel qualified to Rev. 0, 1and 2 are also qualified to Rev. 3 of this procedure.

Limitations: I This procedure/candidate is not qualified for oxainations performed from the cast stainless steel side of a component.

2 This procedure/candidate is only qualified to depth size flaws in accessible regions of the examination volume.

3 This procedure/candidate is only qualified to length size circuniferentially oriented flaws.

4 This procedure/candidate is not qualified for examinations where the ultrasound is required to propagate through an adjacent Austenilic weld prior to inpinging on the dissinilar metal weld.

5 This procedure/candidate is qualified for examination from both single and dual sided access as applicable.

6 This procedure/candidate is only qualified for examinations performed on demonstrated configurations. Additional lirnrtations for a specific configuraiton may be listed on the corrponent drawing included in subsequent pages of this PDQS document.

Page 2 of 21

Printed: 26-Aug-09 Performance Demonstration Initiative Program PDQS No: 632 In Accordance with the PDI Implementation of Section XI, Appendix VIII 04061103 Specific Detail of Qualifications Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: 1 Analysis SW Type/Rey: N/A Date of issue: 26-Aug-09 Operator SW Týpe/Rev: N/A Hardware: N/A Scan Application: Manual Category: Piping ExamSurface: Outside The above procedure has met the requirements of The Performance Demonstration Initiative's I lementation of The American Society of Mechanical Engineers Boiler and Pru5 e elffode,Section XI, Appendix VIII, as stated in this document.

j~jflJ/V~j~~ A JULI lsA~q~J Date: 7i~ M (Jiohh Langevin V/

Performance Demonstration Initiative Piping and Bolting Supervisor/Level 1II

~1~1fJ

/Ro~iad V.Swain" Date. ftcw2 et Performance Demoofshtion Initiative Piping Project Manager This doeunnent is not authentic without a raised seal.

Page 3 of 21

Performance Demonstration Initiative Program Printed: *26-Aug49 632 In Accordance with the PDI Implementation of Section XI, Appendix VIII PDQS No:

04,1103 Specific Detail of Qualifications Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: 1 Analysis SW Type/Rev: N/A Date of Isue: 26-Aug-09 Operator SW Type/Rev: N/A Hardware: N/A Stan Application: Manual Category: Piping kaim Surface: Outside INCONEL 82 FLOW I-UP STREAM 30488 N -_

ALLOY 600 DOWN STREAM 02.W 0.38 3.94 3.94 01.44" 701/X - PDI Generic Standby Liquid Control Line Design Page 4 of 21

Performance Demonstration Initiative Program Printed. 26-Au409 of Section A Apopnd amplementation VI PDQS No: 632 In Accordance with the PDI 04061103 Specifle Detail of Qualiflations Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS

• PDQS Rev: I Ana1yesa SW TypMw. NIA Dole .flaue. 26-Aug-09 OperatorSWTypw. N/A Hardwa9. N/A Sean Appfleation: Manual Catelry Piping Exam Surfike Ouluide 0.666 - 0.859 FLOW DOWN STREAM

-- -------- ______ 5.93 UP STREAM Inc.182 ~ AOCNu 0.585 316 SS Safe End 0.637 u.te0.81 04.23 03.79 02.62 02.63 0 3.07 PDI GENERIC 702/X SAMPLE 702/X - PDI Generic Westinghouse Spray. Nozzle Page 5 of 21

Performance Demonstration Initiative Program Printed: 26-Aug-09 In Accordance with the PDI Implementation of Section X1, Appendix VIII PDQS No: 632 04061103 Specific Detail of Qualiflcatlons Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: I Analysis SW Type(Rev: N/A Date of b*oe: 26-Au#-09 Operator SW TypeJRev: N/A Hardware: N/A Scan Application: Manual Category: Piping Exam Surface: Outside FLOW 15.M 4.93 SA 508 NOZZLE 1.05 0.45 316 Safe End DOWN STREAM USTE 0.60 05.90 04.60 UP STREAM Inc 182 Weld and Butter 04.90 03.69 03.85 7031X - PDI Generic CRD & Jet Pump Return Nozzle Design Page 6 of 21

Performance Demonstration Initiative Program Printed: 26-Aug-09 PDQS No: 632 In Acoedance with the PDT Impleme-ta.on of Secion X14 Appendix VIII 04061103 Specific Detail of Qual=Nfition, Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: I Analysis SW Type/Rev: N/A Date of Imse: 26-Aug-09 Operator SW Type/Rev: N/A Hardware. N/A Scan Application: Manual Catqeory: Piping Exam Surface: Outside FLOW 6.00 .. . ... . ........ 5.99 "

• -0.68!

- - - -- 0 _ --.

1~_____ 314~ .00Inc18" T 182 8udMICIAd DOW N SýTREAM UPSTREAM Inc 182 Wld 05.35 0*4.98 03.37 2.72 704/X - P01 Generic Westinghouse Pressurizer SafetylRellef Paeg 7 of 21

Performance Demonstration Initiative Program rined 26-Aug409 In Accordance with the PDI Implementation of Section XI, Appendix VII PDQS No: 632 04061103 Specific Detail of Qualificationi Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Revs I Analysis SW Type/Rev: N/A Dateofinue: 26-Aug-09 Operator SW Type(Rev: N/A EllwHara. N/A Scan Application: Manual Catqiary: Piping Exam Surface: Outside FLOW

- 1.077

/1t 2/V1f VESSEL -.-- 1 318 S.S, SAoW CS N=z DOWN STREAM UP REAM -f 1S2 NozCa 5.930 .- --- 4.940 12.0 DWA.

14.2500 705/X - PD1 Generic BWR N2 Replacement Nozzle Design Page 8 of 21

Performance Demonstration Initiative Program Puinted: 26-Aug4 632 In Azcerdance with the PD1 Implementation of Seedon XI, Appdi VIII PDQS Ne-of QualfleaolUs 04061103 Specific Det Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PRASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS v. 1 Aualyis SW TypaRev: WA Date of hae.: 26-Aug-09 Operwtor SW Typify: NIA Hardwarm NIA Sen Appliena: Manuel Catagory. Piping Eum Surfsa OuW&ide ORIGINAL INC 182 WELD INC 182 BUTTER FLOW _

/ -- INC 182 BUTTER SA 508 Carbon Steel Nozzle 1.310 316 Stainless Steel Safe End 012.36" L UP STREAM ... ....

Tnlar, Secftn Smulatng The Ori'al rco~1d 88-16 Bate-end Remnant/rAt Repair.

• - -* 0.508 0.190 CLAD - 09.99" 6.000 6.000 706/X - PDI Generic BWR N2 Replacement Nozzle Design Pog 9 of 21

Performance Demonstration Initiative Program I.ditem ,6-Aus-In Accordance with the PDI Impilentation of Section X, A dx V PDQS N: 632 04061103 Specific Ntall of Qualifations Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF A DISSIMILAR METAL WELDS PU*QS Ray I Aunly*s SW TypRmv: WA Date of Ime 26-Aug-09 Opantor SW Typ&eRw: N/A

,udwqw N/A Sum Appflafto: Mmual Category: Piping Exam Surfaw Outaide

.1 4 Well APT 5L REV APT 5

• REV 95 Nozzle FLOW 012.7,3" UP STREAM ....... ..... _.+2_3utt+ DOWN STREAM::

010.47' 5.96 .

5.98 7071X - PDI Generic N4, N5, & N6 Core Spray/Feedwater Nozzle Design Page 10 of 21

Performance Demonstration Initiative Program print 26a,-0

,DQS No: 632 In Accorduce with the PDI Implementation of Secon XI, Appendix VIII Specific Detal of Qualinfalions 04061103 Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: I Analysis SW TypedRev: N/A Date of.Isue: 26-Aug-09 Operator SW Type/Rev: N/A Hardware. N/A Scan Application: Manual Category: Piping Exam Surface: Outside FLOW -- 1.356 H i---1.673 - H,

-T - -r. . . . . . . SA 508 CS Nozzle SA 182 VESSEL .- -.

2.016 2.393 GR 316L SAFE-END DOWN STREAM UP STREAM 1.000 .. -

5.0( DO0 308/30 STAINLESS STEEL CLAD 708/X - PDI Generic Pressurizer Surge Nozzle Design Page 11 of 21

__ _= .- .*=** **M **..****' - .. 4*..*% *'1* * "-* _ 1,:* "****Q** , **,0. k**p ;Lp~ ~i***,4* 1 -4 *

• Performance Demonstration Initiative Program Imed.

In Atowdamc with tie PDIImpqmntafUou of Setion XI, Appendx VM PDQS N.: 632 Speuf Detail of Qualificatom 040661103 Owner: Structural Integrity Procedur SI-UT-130;-Revislon: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULIRASONIC EXAMINATION OF DISIMLA METAL WETDS PDQ aw. 1 Anur SWTypemr: . N/A Dateef Js. 26-4Aa--9 Opmt 8W Typ~w NWA Narw N/A SonAppltatm MURW catp p SPrkA*g outW

..1.566 INC 182 BUTTER INC 182 BUTTER ASTIVA182F30- SA 508 CS NIOZZLE 023.07N U~P SWTMA M INC 182 WELD & INC 82 ROOT ___ _0 ..... DOWNSTRAM 4.D 7.8 019.94*

7.91 Z 7.I SS 308 NOZZLE CLAD 7091X - PDI Generic BWR N1 Recirculation Outlet Nozzle Design Page 12 of 21

Performance Demonstration Initiative Program Pdae4*' 26-Aug49 In Ateordace with the PDI Implementation of Sction Xtl Appmdk VIII PDQS No: 632 04061103 Speeffie Detail of Qualficatlo.

Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS wRv: Analysis SW TypedRev: N/A Date oflmue: 26-Aug-09 Operstor SW Type~v: N/A HBardware: N/A Scan Application: Manual Cate7 Piping Exam Surface. Outside INC 82/182 WELD 0.46 1 FLOW --

2.13 ASTM A 182 F304 SA 508 DOWN STREAM 0.19 i

LP STREAM WI-IA- 4 I.I,, ,308 SS CLAD 1I14%,.I.0Z DU I I cEl 7.97 3.97 -

7101X - PDI Generic BWR N1 recirculation Outlet Nozzle Design Page 13 of 21

Performance Demonstration Initiative Program m"t': 26-Aug-09 In Aceordance with the PDI Implementation of Section XI, Appendix VII PDQS No: 632 04061103 Specific Detail of Qualifications Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WVELDS PDQS Rev: I Analysis SW Type/Rev: WA Date of

• bue: 26-Aug-09 Operator SW Type  : N/A Hardware: N/A Sean Application: Manual Category: Piping Exam Surface: Outside 6.13-1 0.6:

FLOW INCONEL 82 ROOTS. 182 WELD ALLOY 600 SA 508650 5.16 3W8 SS Cad 0 .6 5 - . "

O*J6s'1tu UP S¶fmA 0.; - ---0.28

-" ~~7.22 ........... ~8 5.93 712/X - PDI Generic Steam Generator Nozzle Design (Flat)

Page 14 of 21

Performance Demonstration Initiative Program Printed: 26-Aug-09 In Accordance with the PDI Implementation of Section XI, Appendix VIII PDQS No: 632 Specific Detail of Qualifications 04061103 Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: I Analysis SW Type/Rev: N/A Date of Issue: 26-Aug-09 Operator SW Type/Rev: N/A Hardware: N/A Scan Application: Manual Category: Piping Cateory PiingExam Surface: Outside sfguration Specific Techniques:

" Examination must be BLTTEKNGf 6 C.LADDI[NG performed from both sides of l.r QIE 12NI

- /

the weld from all available surfaces including the taper ITEL 14M2R /

and nozzle boss.

" The 1.5 MHz array must be used for both axial and -,2o6 circumferential scans 3 rANE A detailed scan plan must be STA:NLESS *rEEL 31h "-.mnv developed prior to the 1,694 examination

• Contours must be taken at the 14,930 location of each flaw detected t2.800 and beam plotting must be 1Q74f 10.488 performed in order to measure the depth of the flaw accurately

• Wedges used for circumferential scanning must e,0a 3.

be contoured .... .. .. .... ...

71 51X - Iaul Generic B&w Decay Heat Nozzle Design Page 15 of 21

Performance Demonstration Initiative Program Mated: 26-Ag4r9 PDQS No: 632 In Accordance with the PDT Implementation of Section XI, Appendix VIII 04061103 Specifit Detail of Qualifations Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDs Rzv. I AnlySW SW Type' N/A Date of Iue.: 26-Aug-09 Operator SW Typeftm NA Hardwam IVA Sean Appilatloo: Manl Category: Piping EYam Surface Outaide FL ]W VESSEL

'ELO MAIE!AL B'¶LBI[Nr L LA DOI C~

INCOIC, le?

SISILE 300 VEL D CA8BfY'. STE NW."~

-V 4 DCVN $ QLA' 04 503 0 C1 C)ý-

06 0 0 0 3 4r9 04 250 03 3530 4 310

. . ;D0.3 702-1-X - Pressurizer Spray Nozzle Design (Westinghouse)

Page 16 of21

Performance Demonstration Initiative Program f m-Au OwI Imp wih the entatlos of SeatIon X1 A VI F"(s No: 632 In Aoamn 04061103 specifi D"of o Quetuam Owner; Structural Integrity Procedurem SI-UT-130; Reviuion: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WEL-S FQ Uhv Aualyu sW Typ~' N/A Daisef 1an 26-Ang- Opettr8SW TypWRer NIA Habrwam N/A Scas Apposlem. Manual CAUqna Pips ExAM Surfza= 00 r.XAMPLr- Ot 702-2-X SAMFPLC I Al"b B MakU

• *1"*)

B ll

~. l r

• v S r.-V 0 a.Sia 0-4$7 0.410 amac I Ss weld Inco 182 ID 03.587 ID 03.277 Page 17 of 21

Performance Demonstration Initiative Program PAVted 26-Aug-*9 PLQS NG: 632 In Accordance with the PDI Imaplementatio of Section XI, Appemdk VIII

@4061103 Specific D o" f Qualifleatlon Owner: Structural Integrity Procedure. SI-UT-130; Revilson: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: I Analysis SW Type/Rev: N/A Date of Issue: 26-Aug-09 Operator SW Type/Rev: N/A Hardware: N/A Scas Application: Manual Category: Piping Exam Surface: Outside

-- 6.942 WELD MATERIAL BUTTERING & CLADDING INCONEL 162 INCONEL 182 SISTEEL 309 WELD S/STEEL 3)16 PIPE 23 / I0.,140 SISTEEL 316 SAFE ENO

--i U"

06.515 2 030

• 5.500 go .001 5 ISO E 5.160 1 584 2.20 0 3,156 7041X - PRESSURIZER SAFETYIRELIEF NOZZLE DESIG N (WESTINGHOUSE)

Page 15 of 21

M11, 1rQ;F;z -- am ý -v--T, 'tý 1A -- -, ýý F ý - ý-, i 7T= 77C:1--1-x; -11

Performance Demonstration Initiative Program Printed: 26-Aut0" In Accordance wtth the PDI Implementation of Section XI, Appendix Vi PDS No: 632 04061103 Specfic Detail of Qualifications Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev- I Analyvis SW Type/Rev: NIA Date of Issue: 26-Aug-09 Operator SW TypelRev: N/A Hardware: N/A Scan Application: Manual Category: Piping Exam Surface: Outside FXAAAF'I F OF 70lf-4P-X 99AAAI' F (cc-) Pr4CGU.-ZCR SUF70 NOZZL\"

sasa - - 0a PC&s Pam S 1,1 H 00~M AM h WI#c io 0"o0-12Z Page 19 of 21

Performance Demonstration Initiative Program Printed: 26-Aug-09 PDQS No: 632 In Accordance with the PDI Implementation of Section XI, Appendix VIII 04061103 Specific Detail of Qualifications Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: I Analysis SW TypewRev: N/A Date oflnue: 26-Aug-09 Operator SW Typd/Rev: N/A Hardware: N/A Scan Application: Manual Category: Piping Exam Surface: Outside Configuration Specific Techniques:

" Examination must be performed from both sides of the weld from all available surfaces.

" A detailed scan plan must be 0.063 developed prior to the examination

" Both mechanical and electronic skewing must be used, per Para. 7.375 2.750 6.6, for this configuration 1.689

" Length and depth sizing techniques for tapered surfaces in appendices must be used on this configuration.

I PWR (Combustion Engineering Design) - Charging Inlet Nozzle Mockup (719/X)

Page 20 of 21

Performance Demonstration Initiative Program Printed: 26-Aug-09 PDQS No: 632 In Accordance with the PDI Implementation of Section XI, Appendix VIII 04061103 Specific Detail of Qualifications Owner: Structural Integrity Procedure: SI-UT-130; Revision: 3; Addenda: 0 PROCEDURE FOR THE PHASED ARRAY ULTRASONIC EXAMINATION OF DISSIMILAR METAL WELDS PDQS Rev: 1 Analysis SW Type/Rev: N/A Date of Issue: 26-Aug-09 Operator SW Type/Rev: N/A ConfigurationSpcific Techniques: Hardware: N/A Scan Application: Manual A detailedan plain ust be Category: Piping Exam Surface: Outside

'devope pror to the examination.

• Both mechanical and electronic skewing must be used, per Para. 0.M ,37 6.6, for this configuration.

• Procedural length and depth sizing techniques for tapered surfaces must be used for this configuration.

• For depth sizing axial flaws in the weld, the transducer must 037.475 be located on the carbon steel base material and skewed in ---

toward the weld flaw.

Specific Limitation for Tapered Welds:

• This procedure is not qualified fO&M7 to detect axial flaws on the far 6.= ra side of a single-side access component containing a tapered weld configuration PWR (Combustion Engineering Design) - Reactor Coolant Pump Safe-end to Elbow Weld (717/X)

Page 21 of 21

ENCLOSURE2 30-RC-21B-10 Examination Coverage Calvert Cliffs Nuclear Power Plant, LLC January 10, 2013

ENCLOSURE 2 30-RC-21B-10 Examination Coverage CCNPP U2 LTP # 110310 / 30-RC-21B-10 Examination Coverage for Circumferential Flaws Uninspected Region of Largest Potential Susceptble Material Undetected PWsCC Flaw I

ENCLOSURE 2 30-RC-21B-10 Examination Coverage CCNPP U2 LTP # 110310 / 30-RC-21B-10 Examination Coverage for Circumferential Flaws F10L I i i 2

ENCLOSURE 2 30-RC-21B-10 Examination Coverage CCNPP U2 LTP # 110310 / 30-RC-21B-10 Examination Coverage for Circumferential Flaws 4" Wide Insulation Support I1Scl V I

l l Note: As-built surface profile and dimensions taken from component walkdown are shown.

-111.2.W

-2.10r 416 1.55" ,019" 0/

CARBON 2.990 STEEL PIPE mitmI...'

3.3V' 3

ENCLOSURE 3 30-RC-22A-10 Examination Coverage I

Calvert Cliffs Nuclear Power Plant, LLC January 10, 2013

ENCLOSURE 3 30-RC-22A-10 Examination Coverage CCNPP U2 LTP # 111310 / 30-RC-22A-10 Examination Coverage for Axial Flaws Largest undetected PWSCC flaw contained within the weld buttering I

ENCLOSURE 3 30-RC-22A-10 Examination Coverage CCNPP U2 LTP # 111310 / 30-RC-22A-10 Examination Coverage for Axial Flaws Scale: 1 1" Note: As-built surface profile and dimensions taken from component walkdown are shown.

2.30" 1 1.45" <-0.~125" 2

ENCLOSURE 4 300 Beam Width/Sound Field Energy Angle Simulation Calvert Cliffs Nuclear Power Plant, LLC January 10, 2013

ENCLOSURE 4 300 Beam Width/Sound Field Energy Angle Simulation FLAW DECTION USING 30 DEGREE ANGLE OD Surface ID Surface Figure 4-1: Sound Field Energy Simulation for 30' Angle, Scan from on top of DMW I

ENCLOSURE 4 30° Beam Width/Sound Field Energy Angle Simulation FLAW DETECTION USING 30 DEGREE ANGLE OD Scanning Umliation as Surface shown In Endoure 2 3*Agewith -6dB

-'I 3"

ID 1.2" Flaw Height Surface m*O Figure 4-2: Sound Field Energy Simulation for 30' Angle, Scan from the Pipe Side 2