RS-12-153, Relief Request Associated with the Third 10-Year Inservice Inspection Program Interval

Relief Request Associated with the Third 10-Year Inservice Inspection Program Interval

ML12283A084
Person / Time
Site:	Braidwood
Issue date:	10/08/2012
From:	Gullott D Exelon Generation Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
RS-12-153
Download: ML12283A084 (29)

Text

RS-12-153 10 CFR 50.55a October 8, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN-50-456 and STN-50-457

Subject:

Relief Request Associated with the Third 1 0-Year Inservice Inspection Program Interval In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(5)(iii), Exelon Generation Company, LLC, (EGC) hereby requests NRC approval of the attached relief request associated with the Third 10-year Inservice Inspection (ISI) Program Interval for Braidwood Station, Units 1 and 2. The third interval of the Braidwood Station ISI program complies with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2001 Edition with 2003 Addenda.

NRC approval of the attached relief is requested on the basis that 100% examination coverage of required surfaces and volumes of Class 1 components has been determined to be impractical.

Due to the original design and/or the base metal materials associated with the specified welds, it is not feasible to effectively perform examinations of 100% of the volume of these welds.

The details of the 10 CFR 50.55a request are enclosed. EGC requests approval of this relief request by October 8, 2013.

There are no regulatory commitments contained within this letter. Should you have any questions concerning this letter, please contact Ms. Dwi Murray at (630) 657-3695.

Respectfully, RS-12-153 October 8,2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN-50-456 and STN-50-457 10 CFR 50.55a

Subject:

Relief Request Associated with the Third 10-Year Inservice Inspection Program Interval In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(5)(iii), Exelon Generation Company, LLC, (EGC) hereby requests NRC approval of the attached relief request associated with the Third 10-year Inservice Inspection (lSI) Program Interval for Braidwood Station, Units 1 and 2. The third interval of the Braidwood Station lSI program complies with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2001 Edition with 2003 Addenda.

NRC approval of the attached relief is requested on the basis that 100% examination coverage of required surfaces and volumes of Class 1 components has been determined to be impractical.

Due to the original design and/or the base metal materials associated with the specified welds, it is not feasible to effectively perform examinations of 100% of the volume of these welds.

The details of the 10 CFR 50.55a request are enclosed. EGC requests approval of this relief request by October 8, 2013.

There are no regulatory commitments contained within this letter. Should you have any questions concerning this letter, please contact Ms. Dwi Murray at (630) 657-3695.

Respectfully, Manager - Licensing Exelon Generation Company, LLC

Attachment:

10 CFR 50.55a Relief Request 13R-10 cc:

NRC Regional Administrator, Region III NRC Senior Resident Inspector, Braidwood Station NRR Project Manager, Braidwood Station Management Nuclear Safety

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 1 of 6 1.0 ASME CODE COMPONENTS AFFECTED:

Code Class:

1

Reference:

IWB-2500, Table IWB-2500-1, Code Case N-460 Examination Category:

B-D Item Number:

B3.110

==

Description:==

Limited Examination Coverage Component Number:

See Tables 1 and 2 Drawing Number:

See Attachments 1-1, 1-2, 2-1, and 2-3 2.0 APPLICABLE CODE EDITION AND ADDENDA:

The Third Interval Inservice Inspection program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 2001 Edition with 2003 Addenda.

3.0 APPLICABLE CODE REQUIREMENT:

ASME Section XI, 2001 Edition with 2003 Addenda requires a volumetric and/or surface examination, which includes essentially 100% of the weld and the applicable base metal, for the affected examination categories of Class 1 components.

Table IWB-2500-1, Examination Category B-D requires volumetric examination of Item B3.1 10 (Pressurizer Nozzle-to-Vessel welds). Figure IWB-2500-7(b) depicts the required examination volume (A-B-C-D-E-F-G-H) which includes the actual circumferential weld and adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the wall from the extremities of the weld crown.

ASME Section XI, Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2 inches thick to be conducted in accordance with ASME Section V, Article

4. ASME Section V, Article 4 requires:

T-472. 1.1 Beam Angle: The search unit and beam angle selected shall be appropriate for the configuration being examined and shall be capable of detecting the calibration reflectors, over the required angle beam path.

ATTACHMENT 10 CFR SO.SSa RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR SO.SSa(g)(S)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 1 of 6 1.0 ASME CODE COMPONENTS AFFECTED:

Code Class:

Reference:

Examination Category:

Item Number:

==

Description:==

Component Number:

Drawing Number:

1 IWB-2500, Table IWB-2500-1, Code Case N-460 B-D B3.110 Limited Examination Coverage See Tables 1 and 2 See Attachments 1-1, 1-2, 2-1, and 2-3 2.0 APPLICABLE CODE EDITION AND ADDENDA:

The Third Interval Inservice Inspection program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 2001 Edition with 2003 Addenda.

3.0 APPLICABLE CODE REQUIREMENT:

ASME Section XI, 2001 Edition with 2003 Addenda requires a volumetric and/or surface examination, which includes essentially 100% of the weld and the applicable base metal, for the affected examination categories of Class 1 components.

Table IWB-2500-1, Examination Category B-D requires volumetric examination of Item B3.110 (Pressurizer Nozzle-to-Vessel welds). Figure IWB-2500-7(b) depicts the required examination volume (A-B-C-D-E-F-G-H) which includes the actual circumferential weld and adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the wall from the extremities of the weld crown.

ASME Section XI, Mandatory Appendix I requires ultrasonic examination of vessel welds greater than 2 inches thick to be conducted in accordance with ASME Section V, Article

4. ASME Section V, Article 4 requires:

T-472.1.1 Beam Angle: The search unit and beam angle selected shall be appropriate for the configuration being examined and shall be capable of detecting the calibration reflectors, over the required angle beam path.

T-472.1.2 Reflectors Parallel to the Weld Seam: The angle beam shall be directed at approximate right angles to the weld axis from both sides of the weld (i.e., from two directions) on the same surface when possible. The search unit shall be manipulated so that the ultrasonic energy passes through the required volume of weld and adjacent base metal material.

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 2 of 6 T-472. 1.3 Reflectors Transverse to the Weld Seam: The angle beam shall be directed essentially parallel to the weld axis. The search unit shall be manipulated so that the ultrasonic energy passes through the required volume of weld and adjacent base material. The search unit shall be rotated 180 deg and the examination repeated.

Braidwood Station has adopted ASME Section XI Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 welds,Section XI Division 1." Code Case N-460 states in part, "...when the entire examination volume or area cannot be examined...a reduction in examination coverage... may be accepted provided the reduction in coverage for that weld is less than 10%."

NRC Information Notice 98-42, "Implementation of 10 CFR 50.55a(g) Inservice Inspection Requirements," termed the reduction in coverage of less than 10% to be "essentially 100 percent." Information Notice 98-42 states in part, "The NRC has adopted and further refined the definition of "essentially 100 percent" to mean "greater than 90 percent"... which has been applied to all examinations of welds or other areas required by ASME Section XI."

4.0 IMPRACTICALITY OF COMPLIANCE:

Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that conformance with the specified Code requirement has been determined to be impractical. Due to the original design and/or the base metal materials associated with these welds, it is not feasible to effectively perform examinations of 100% of the volume of these welds.

Therefore, relief is requested on the basis that the Code requirements to examine essentially 100% of the welds' volume are impractical due to physical obstructions and geometric interference. Attaining the geometry required to achieve the Code required examination coverage would require major modifications to existing components without providing a corresponding increase in the level of quality and safety.

Tables 1 and 2 identify the limitations for examination coverage of the welds encountered at Braidwood Station, Unit 1 and Unit 2, respectively during the first period examinations.

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 2 of 6 T-472.1.3 Reflectors Transverse to the Weld Seam: The angle beam shall be directed essentially parallel to the weld axis. The search unit shall be manipulated so that the ultrasonic energy passes through the required volume of weld and adjacent base material. The search unit shall be rotated 180 deg and the examination repeated.

Braidwood Station has adopted ASME Section XI Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 welds,Section XI Division 1." Code Case N-460 states in part, "... when the entire examination volume or area cannot be examined... a reduction in examination coverage... may be accepted provided the reduction in coverage for that weld is less than 10%."

NRC Information Notice 98-42, "Implementation of 10 CFR 50.55a(g) Inservice Inspection Requirements," termed the reduction in coverage of less than 10% to be "essentially 100 percent." Information Notice 98-42 states in part, "The NRC has adopted and further refined the definition of "essentially 100 percent" to mean "greater than 90 percent"... which has been applied to all examinations of welds or other areas required by ASME Section XI."

4.0 IMPRACTICALITY OF COMPLIANCE:

Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that conformance with the specified Code requirement has been determined to be impractical. Due to the original design and/or the base metal materials associated with these welds, it is not feasible to effectively perform examinations of 100% of the volume of these welds.

Therefore, relief is requested on the basis that the Code requirements to examine essentially 100% of the welds' volume are impractical due to physical obstructions and geometric interference. Attaining the geometry required to achieve the Code required examination coverage would require major modifications to existing components without providing a corresponding increase in the level of quality and safety.

Tables 1 and 2 identify the limitations for examination coverage of the welds encountered at Braidwood Station, Unit 1 and Unit 2, respectively during the first period examinations.

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 3 of 6 Table 1 - Unit I Nozzle -to-Vessel Weld Component ID Outage Cumulative Reference Code Category Examined Examination Sketch/Coverage Remarks Code Item Month/

Coverage Plot Year Achieved 1 PZR-01-N2 Al R15 56.56% -1 Pressurizer Spray Nozzle-to-Shell Category B-D (10/2010) recordable indications noted in any Item 83.110 ultrasonic scans performed.

1PZR-01-N3 A1R15 60.92% -2 Pressurizer Relief Nozzle-to-Shell Category B-D (10/2010) recordable indications noted in any Item B3.110 ultrasonic scans performed.

Table 2 - Unit 2 Nozzle-to-Vessel Weld Component ID Outage Cumulative Reference Code Category Examined Examination Sketch/Coverage Remarks Code Item Month!

Coverage Plot Year Achieved 2PZR-01-N2 A2R15 88.5% -1 Pressurizer Spray Nozzle-to-Shell Category B-D (4/2011) recordable indications noted in an Item B3.110 ultrasonic scans performed.

2PZR-01-N3 A2R15 88.5% -2 Pressurizer Relief Nozzle-to-Shel Category B-D (4/2011) recordable indications noted in an Item B3.1 10 ultrasonic scans performed.

Component 10 Code Category Code Item 1PZR-01-N2 Category B-O Item B3.110 1PZR-01-N3 Category B-O Item B3.110 Component 10 Code Category Code Item 2PZR-01-N2 Category B-O Item B3.110 2PZR-01-N3 Category B-O Item B3.110 ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 30f6 Table 1 - Unit 1 Nozzle-to-Vessel Weld Outage Cumulative Reference Examined Examination Month/

Coverage Sketch/Coverage Remarks Year Achieved Plot A1R15 56.56% -1 Pressurizer Spray Nozzle-to-Shell Weld. No (10/2010) recordable indications noted in any of the ultrasonic scans performed.

A1R15 60.92% -2 Pressurizer Relief Nozzle-to-Shell Weld. No (10/2010) recordable indications noted in any of the ultrasonic scans performed.

Table 2 - Unit 2 Nozzle-to-Vessel Weld Outage Cumulative Reference Examined Examination Month/

Coverage Sketch/Coverage Remarks Year Achieved Plot A2R15 88.5% -1 Pressurizer Spray Nozzle-to-Shell Weld. No (4/2011 )

recordable indications noted in any of the ultrasonic scans performed.

A2R15 88.5% -2 Pressurizer Relief Nozzle-to-Shell Weld. No (4/2011 )

recordable indications noted in any of the ultrasonic scans performed.

I I

ATTACHMENT 1 0 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 4 of 6 5.0 BURDEN CAUSED BY COMPLIANCE:

Compliance with the examination requirements of ASME Section XI would require significant modification of plant components to remove obstructions, redesign of plant systems/components, and/or replacement of components where geometry is inherent to the component design.

The pressurizer vessel spray nozzle-to-vessel weld is approximately 2.7 inches thick.

The pressurizer nozzle and vessel are clad with stainless steel on the inside diameter surface. The geometry of the nozzle along with the presence of the cladding on the inside diameter of the pressurizer resulted in limited access to the entire examination volume. The propagation for the ultrasonic beam was in the shear mode. Normally, this mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-beam axis at right angles to each other, however, the presence of the stainless steel cladding precludes the ultrasound beams from reflecting at the inside diameter from the shell/cladding interface.

The nozzle geometry tapers away from the weld resulted in limited scanning surfaces available for the transducer coupling on the nozzle side of the weld, which resulted in additional examination limitations. These factors resulted in limited examination coverage from the scan directions required by ASME Section V and Section A. These limitations are inherent to the original design of the pressurizer vessel. Conformance with the ASME Section XI requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the pressurizer vessel.

Attachments 1-1, 1-2, 2-1, and 2-2 provide the basis for the limited examination coverage, which include drawings/sketches, as applicable. The differences between the aggregate examination coverage achieved and the coverage previously attained during the Second 10-Year ISI Program Interval examination are due to changes in ASME Section V requirements. While it may be possible to increase the overall coverage using alternative or additional angles, it would not necessarily increase the level of quality and safety in detecting flaws or relevant conditions, and would increase the radiation dose received by the examiners due to additional time spent to scan the welds.

In addition to the completion of required volumetric examination performed to the extent practical, numerous system leakage tests (Section Xl Category B-P and Generic Letter 88-05) at nominal system operating pressure (2235 psig) and temperature (557°F) have been perfor d

ith id f l k

i d

i ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 4 of 6 5.0 BURDEN CAUSED BY COMPLIANCE:

Compliance with the examination requirements of ASME Section XI would require significant modification of plant components to remove obstructions, redesign of plant systems/components, and/or replacement of components where geometry is inherent to the component design.

The pressurizer vessel spray nozzle-to-vessel weld is approximately 2.7 inches thick.

The pressurizer nozzle and vessel are clad with stainless steel on the inside diameter surface. The geometry of the nozzle along with the presence of the cladding on the inside diameter of the pressurizer resulted in limited access to the entire examination volume. The propagation for the ultrasonic beam was in the shear mode. Normally, this mode would allow the ultrasonic beam to reflect off the inside surfaces and create a two-beam axis at right angles to each other, however, the presence of the stainless steel cladding precludes the ultrasound beams from reflecting at the inside diameter from the shell/cladding interface.

The nozzle geometry tapers away from the weld resulted in limited scanning surfaces available for the transducer coupling on the nozzle side of the weld, which resulted in additional examination limitations. These factors resulted in limited examination coverage from the scan directions required by ASME Section V and Section XI. These limitations are inherent to the original design of the pressurizer vessel. Conformance with the ASME Section XI requirements for essentially 100% of the volumetric coverage would require extensive structural modifications to the pressurizer vessel.

Attachments 1-1, 1-2, 2-1, and 2-2 provide the basis for the limited examination coverage, which include drawings/sketches, as applicable. The differences between the aggregate examination coverage achieved and the coverage previously attained during the Second 10-Year lSI Program Interval examination are due to changes in ASME Section V requirements. While it may be possible to increase the overall coverage using alternative or additional angles, it would not necessarily increase the level of quality and safety in detecting flaws or relevant conditions, and would increase the radiation dose received by the examiners due to additional time spent to scan the welds.

In addition to the completion of required volumetric examination performed to the extent practical, numerous system leakage tests (Section XI Category B-P and Generic Letter 88-05) at nominal system operating pressure (2235 psig) and temperature (55rF) have been performed with no evidence of leakage associated with the pressurizer spray nozzle-to-vessel welds. The system leakage tests will continue to be performed throughout the remainder of the interval.

Radiography as an alternative is not feasible because access is not available for film placement. No alternative examinations are planned for the weld during the current inspection interval. No additional ultrasonic examinations will be completed during the inspection interval for these welds since the examination was performed to the extent

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 5 of 6 practical. The results of this examination along with the results of the pressure tests and plant monitoring provide reasonable assurance that pressure boundary integrity has been and will be maintained for the components throughout the interval.

6.0 PROPOSED ALTERNATIVE AND BASIS FOR USE:

Braidwood Station proposes to perform the Code required volumetric examinations to the maximum extent possible. Due to the original design of these welds, there are no alternative examination techniques currently available to increase the examination volume. There were no cases in any of the listed examination components where outside diameter surface features (i.e., weld crowns, weld shrinkage, surface roughness, etc.) could have been conditioned to maximize the coverage attained without major modification to the components.

As a minimum, all components received the required volumetric examination to the extent practical due to limited or lack of access availability. There were no recordable indications requiring further evaluation noted in any of the volumetric examinations performed. The examinations were conducted, and satisfactory results were confirmed, even though essentially 100% coverage was not attained. Additionally, multiple VT-2 examinations were and will continue to be performed on the subject components throughout the interval through the required system pressure tests (examinations required by ASME Section XI and Generic Letter 88-05). No evidence of leakage was observed at these components, providing additional assurance that the structural integrity of the subject components will be maintained throughout the remainder of the interval.

In addition to the periodic visual inspections performed under ASME Section XI and Generic Letter 88-05, reactor coolant pressure boundary leakage is monitored through a number of other activities, which provide a high level of confidence that in the unlikely event that leakage did occur, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications Section 3.4.13, "RCS Operational Leakage," as well as the reactor makeup control system, reactor cavity and containment floor drain sump monitoring, containment radiation monitoring, and containment atmospheric monitoring, provide additional assurance that any leakage would be detected prior to gross failure of these components.

ATTACHMENT 10 CFR SO.SSa RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR SO.SSa(g)(S)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page S of 6 practical. The results of this examination along with the results of the pressure tests and plant monitoring provide reasonable assurance that pressure boundary integrity has been and will be maintained for the components throughout the interval.

6.0 PROPOSED ALTERNATIVE AND BASIS FOR USE:

Braidwood Station proposes to perform the Code required volumetric examinations to the maximum extent possible. Due to the original design of these welds, there are no alternative examination techniques currently available to increase the examination volume. There were no cases in any of the listed examination components where outside diameter surface features (Le., weld crowns, weld shrinkage, surface roughness, etc.) could have been conditioned to maximize the coverage attained without major modification to the components.

As a minimum, all components received the required volumetric examination to the extent practical due to limited or lack of access availability. There were no recordable indications requiring further evaluation noted in any of the volumetric examinations performed. The examinations were conducted, and satisfactory results were confirmed, even though essentially 100% coverage was not attained. Additionally, multiple VT-2 examinations were and will continue to be performed on the subject components throughout the interval through the required system pressure tests (examinations required by ASME Section XI and Generic Letter 88-05). No evidence of leakage was observed at these components, providing additional assurance that the structural integrity of the subject components will be maintained throughout the remainder of the interval.

In addition to the periodic visual inspections performed under ASME Section XI and Generic Letter 88-05, reactor coolant pressure boundary leakage is monitored through a number of other activities, which provide a high level of confidence that in the unlikely event that leakage did occur, it would be detected and proper action taken. Specifically, system leak rate limitations imposed by Technical Specifications Section 3.4.13, "ReS Operational Leakage," as well as the reactor makeup control system, reactor cavity and containment floor drain sump monitoring, containment radiation monitoring, and containment atmospheric monitoring, provide additional assurance that any leakage would be detected prior to gross failure of these components.

7.0 DURATION OF PROPOSED ALTERNATIVE:

Relief is requested for the Third i0-Year Inservice Inspection (lSI) Program Interval for Braidwood Station Units 1 and 2. For the examination categories under this relief, the Third Interval for Braidwood Unit 1 began on July 29,2008 and is currently scheduled to end on July 28, 2018. The Third Interval for Braidwood Unit 2 began on October 17, 2008 and is currently scheduled to end on October 16, 2018.

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R-10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 6 of 6

8.0 PRECEDENTS

A similar relief request was approved for North Anna Power Station, Unit 1 for limited examination coverage for Examination Categories B-A, B-D, B-K, R-A, C-B, C-C, and C-F-1 (NRC Safety Evaluation Report dated January 7, 2011 - ADAMS Accession Number ML110060011).

For Braidwood Station, limited coverage for these components was identified during the previous inspection interval and relief from Code requirements under Relief Request 12R-50 which was approved by NRC Safety Evaluation Report dated March 8, 2010 (ADAMS Accession Number ML100480699).

9.0 ATTACHMENTS

-1: Weld 1PZR-01-N2 (6 pages total) -2: Weld 1PZR-01-N3 (6 pages total) -1: Weld 2PZR-01-N2 (3 pages total) -2: Weld 2PZR-01-N3 (3 pages total)

ATTACHMENT 10 CFR 50.55a RELIEF REQUEST 13R*10 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)

Braidwood Station Third Interval, First Period Limited Examinations Revision 0 Page 6 of 6

8.0 PRECEDENTS

A similar relief request was approved for North Anna Power Station, Unit 1 for limited examination coverage for Examination Categories 8-A, 8-0, 8-K, R-A, C-8, C-C, and C-F-1 (NRC Safety Evaluation Report dated January 7, 2011 - ADAMS Accession Number ML110060011).

For 8raidwood Station, limited coverage for these components was identified during the previous inspection interval and relief from Code requirements under Relief Request 12R-50 which was approved by NRC Safety Evaluation Report dated March 8, 2010 (ADAMS Accession Number ML100480699).

9.0 ATTACHMENTS

-1: Weld 1 PZR-01-N2 (6 pages total) -2: Weld 1 PZR-01-N3 (6 pages total) -1: Weld 2PZR-01-N2 (3 pages total) -2: Weld 2PZR-01-N3 (3 pages total)

ATTACHMENT 1-1 Weld 1 PZR-01-N2 ATTACHMENT 1-1 Weld 1 PZR-01-N2

Calibration Data Sheet search Unit #1 Manufacture:

KBA Serial No.:

No. of Elemen Size:

1.0' Shape:

ound Freq.

l{z Style:

Gamma Exam ri a:

0_

Mode:-Loong Measured Angle:

WA Wedge Style:

Integral Search Unit Cable Type:

RG-174 Length:

12' No-.

0 kisbument Settings Make / Model: Krautkrams / USN 58L SW I RY SI-210

/0 D 071 74'F P 105230

/ 2.0625' T

D Austenltic 0.5" rc. 0 Both Cal. Checks Time Initial Caleb.

08:34 Initial Caleb. Date 10112110 Intermediate 12:21 Intermediate WA Final Caleb.

15:48 Final Calib. Date 10/12/10 M

/ 1 Data Sheet S A1RI5-UT-022 Page 1

of 6

Couplant 803.110 Type:

ULTRAGEL II ch:

Ows em:

aruls)

COMPONENT TEMP:78'F ximately 56.56% Coverage achieved due to ACCESS I1.j W1 +^^lt^ el:f-l NON RELEVANT YEs en RM.)(

NO X

FLAW YES X

EXAM SENS.

(d8) dEl Manufacture Serial No.:

Search Unit 02 No. of Size:

^

Freq.

Style:

Exam MeasuredAngle:

Wedge Style:

Search Unit Cable Type:.

Length:

~ w.~~p'ynii Calibration Data Sheet A'tV.. V'\\ l1J.... (*II.:"... ~

Ii!.

\\

Plant I Unit Braidwood 11 Data Sheet.

A1R1~UT-022 1 4T Is.

Ii' Company Exelon Page 1

of 6

iI2..

~

Comp I System N2/RY til.. l' Procedure No EXE-ISI-210 CaI.Checka Tim.

1\\

Rev I Chng. No.

3/0

\\

Cat Bkx:k No.

BW0071 Initial CUb.

08:34 Cal. Block Temp.

7"-F 1\\

Them10meter SIN:

SAP 105230 Initial caIib. Date 10112110

\\

SiZe 4-Sch.

NJA 12.0625-rr

\\

I Bt!~ I Intennediate 12:21 SAP 105220

[!] Ferritic DAuatenHic SMIdI Unit 11 8Mrch Unit t2 Each Major CRT ON.

• 0.5-Intennec:tiate NJA Manufacture:

KBA Manufacture.

Serial No.:

aumw Serial No.: \\

Cal. Direction:

[!)Axia! 0 Cire. 0 Both Final CUb.

15:46 No. of EJements:

1 No. 01-'

\\

Size: 1.cr

§i8Ipe:

~ound Size:

Shape Scan Area:

I toWetd m Final ea.ib. Date 10112110 Freq.

~.~K gAl Styte:

Gamma Freq.

\\ Styte:

II to Weld Exam Afti,e:

O*

Modi:

Long Exam Angle:

\\

Modi:

CoupIant Measured Ntgte:-

NlA MNaured Angle: \\

Code Category:

8-0 Code Item:

803.110 Type:

UlTRAGElll Wedge Styte:

InteQI*

Wedge Styte:

_\\

Batch:

08225 N

Ieerch Unit CUte 8NrchU Cable lUI \\I~,,.. ",no IXAII ACCESS FLAW NON RELEVANT lENS.

Type:

R(3.174 Type:

Examination Area I Weld YEa NO YEa (>eft IW.) NO (dB)

Length: --1l.... NO. of con.:

0 Length:

. No. T~ : _

1RY01S 11PZR-01-H2 X

X 24 SkMd dB Inatrument 8etIInga lnatrument..

t...

Blffildlal BtaIOO for IIlCOOlRIeto Scao(a\\

COMPONENT TEMP:78*F MIke J Model: Krauduamer I USN 58L SW Make I Model:

No recordable indications. Approximately 56.56% coverage achieved due to nozzle configuration. See attached pages 3 thru 6 for coverage calculations.

Serial No.:

SAP 104391 SeriII No.:

\\

• Cal Check: 1st BW: 2.0 div 0 80% CO dB; 2nd BW: 4.0 div 0 50% CD 0 Probe Delay: ~

Range:

5.cr Probe o.y. _

Range: \\

dB M'U Call Vel: 0.2301 PuMr. Squn M'U cat I Vel:

Puller:

\\

iir Damping:

~ 0%

Damping:

Reject:

\\

PRF:

Auto HIgh Freq:

2.25 MHz PRF:

Freq:

\\

filter:

Fixed Mode: 0U8I Off Filter:

Mode:

\\

ExamineB Paul 8Ied\\a fa.. t~

~ lAM!

Rectify:

Fulwave Voltage:

450 Rectify:

Voltage:

\\

III DaCe 10112110 PuIM Width:

220 OS -

PuIae WidIh:

\\

~A

~ NiA DaCe AlA Display Delay:

0 Display DekAy:

\\

Reference SendMty (dB)

Reference SensitMty (dB)

\\

WeaOyne Re'iIewef I Date: -8..,." &

1 C*

L... m-I~.I" Axial:

10.0 dB Cke:

NlA Aldet:

Cire:

FuI1het Evaludon Reqund1 FSOH SenIitMty:

.MWW/~

LA.

--1"'""'\\

..- \\..

I 1 RY Si-210 0

071 74'F 105230 2-06250 T

D Austen tic 8' t 1.0'

c. 0 Both Data Sheet 0 Al RI 5-UT-022 Page 2

of 6

Calibration Data Sheet Search Unit 01 Manufacture:

KBA Serial No.:

No. of Elements:

Size:

0.5' x 1.00 Shape

-Red Freq. TEW Style:

Gamma Exam di* -"45' ModeShear Measured Angle:

45' Wedge Style:

SWS Search Unit Cable Type:

RG-174 Length:

12 No. of 0

Inatr111116/>t f3etLinge search Unit 02 Manufacture:

KM Serial No.:

OOW$K No. of Elemen.

Size:

0.5' x 1.0' Shape:

Red, Freq.

z Style:

mma Exam Anglia:

60' Mode: -

ar Measured Angie:

60' Wedge Style:

SWS Search Unit Cable Type:

RG-174 Length:

12' No.

0 Inet anent Settfnge Cal. Checks Time initial Caiib.

09:22109:23 Initial Calib. Date 10/12110 intermediate 12:19/12:20 Intermediate 13:57/14:39 Final Cafib.

15:52115:63 Final Calib. Date 10/12/10 pian!

m:

803.110 Type:

ULTRAGEL it ch:

09225 COMPONENT TEMP 78'F ximately, 56.56 % ooverags achlavsd due to ACCESS h-Q-6 Sided TNo7ct3 I.

Mdill FLAW x

NON RELEVANT YES (dolt t;uf.)j x

Make / Model: Krsutkramer I USN 581 SW M

M No Ank

~ W~~p'ynii Calibration Data Sheet A W, ~t,,\\*.. thI4l"'1' '~ * ~UM. C9InpM'l)

Piant I Unit Braidwood 11 Data Sheet,

Company E.xeton Page 2

Comp I System N21 RV Procedure No.

exe-lSI-210 Rev I Chng. No.

3 I a Cal. Checka Cal. Block No.

ewo 071 Cal. Block Temp.

74-F Initial CaIib.

Thermometer ~ :

SAP 105230 Size Sch.

NlA 12.0825" "r Initial Calib. Date I Ref 8todS' I SAP 105220

[!] Ferritic D Au8tenitic Each Major CRT ON. =

a.r, 1.fr Intennediate Intermediate Cal. Direction:

[!)Axial Cl Cire. 0 Both Final CaIib.

Scan Area:

I toW" [!]

II to Weld l!J Final CaIib. Date A1R15-UT-022 of 8

TIm.

09:22/09:23 10112110 I

12:19/12:20 13:57/14:38 15:52115:53 10112110 Couplant Cat89OfY:

8-0 Code Item:

803.110 Type:

UL TRAGEL II Batch:

09225 ElCAII ACCESS FLAW Examination AIea I Weld YU NO (a) 1RY01S 11PZR~1-H2 X

X **

Bematkll BulQO 1m ~

Smnlll Co.FONeHT TEMP:7a-.=

No rec:0fdab6e Indication.. Approximatety 58.56% ~

IICNIYed due to nozzle configuration. See attached pagel 3 thru 6 b' c:ovwage Clllcutdona. Cal Chedt: 1.r:r Radius 0 1.25 diY 0 70% 0 22.5 dB; 2.fT Rlldiua 0 2.5 dN @ 25% CD 22.5 dB

.. 60- Cal Chedc' 1.r:r RadIU' CD 1.0 diY G 80% CD 2e dB; 2.r:r fUdiuI CD 2.0 diY

@50%@26dB.

Exanuneta: Paul 8IectIa fQ..L 0 fi!t..L lewIt NlA L.e¥eI III Date fUADeIe WeaOyne Rewtwer I Dat.e: ~#<..

~,.. ~"IIb I **,$'-/tl Fut1her Evatuatioft RequIred?

10112110 NlA

.l.o..

III.,.

1]11

~~

"l/. T

-E n liT

• Inl Intrt Search Unit 11 Manufacture:

K8A Serial No.:

00B864 No. of EJemenIi:

1 Size: 0.5" x 1,(1' ShiP8: Rect.

Freq. 2:25 URi Styte:

oamma Exam An9Ii:

45-Mode:

SfMNii Meaaured Angta--:-

45-Wedge Style:

SWS 8ean:h Unit cable Type:

R~174 Length:

12' NO. Of con.:

0 Inatrument Setdnge MIke 1 Model: KrautkI8mef I USN 58l SW Serial No.:

SAP 104391 I

Probe Delay. 12.825 Range:

8.0" M'tI Ca 0.1272 Puller: s9U!i!

OampiJag:

500 Re;ed:

0%

PRF:

AutoHigh Freq: 2.25MHz Filler.

Fbced Mode: Dual Off Rectify:

FuIIMM Voltage:

450 Pulse Width:

220 ns -

DiIpIay Delay:

0 Refetence Sen8itMty (dB)

Axial:

37.0 dB Circ:

NlA FSOH SenaNy:

t,,-. I

• l'.n *

.t &

11 !1'"

~4 :t 1'1 UNc ~ *,

i~ ~T Search Unit 12 Manufacture:

K8A SeriIII No.:

008X8K No. of Elemenli:

i Size: 0.5" X 1.rr Sh8P8:

Rect.

Freq. 225 URi Styte:

aamma Exam AIijjIi: eo-Modi:

ShUi Meuured Angae:

so-Wedge Styte:

--:sws~---

Search Unit cable Type:

R~174 length:

12' NO. Of con.: --L lnetnnent Settings Make I Model: Krautkremer I USN 58l SW SenaI No.:

SAP 104381 Probe o.uy. 18.0784 Range:

10.0" M'tI Call Vel: 0.1272 Puller. sQU!i!

DampIng:

500 Rttect 0%

PRF:

Auto High Freq: '"'"2.2S"MHz Filter:

Flx8d Mode: Dual Off Rectify.

FuDwave Voltage:

450 PuIIe W6dth:

220 ns -

Display Oe&ay:

0 Reference SenIiIMty (dB)

Axial:

42.& dB Circ:

NlA FSDH SenaNy:

ON TO EX"' WATION UNIT I

SKETCH PROCEDURE DATE IRL ATED T4.

UT X

PT MT VT (DENT. NO.

IPHOV Dt c04:R L iPtrOr AT+Oi [0 OtSCw&E APPROXIMATE SUE, LOCATION AND TYPE OF L1 A

1 450,600 and 70° Axial Upstream / Downstream Scans otai Exam Volume = Length x W dth x Height Langtn = 40" Width = 4.1" tieoght = 2.52" (40' x 4 1" x 2.52") = 413.28"'

fvt,ssed Volume = Length x Width x Height (in cross hatched a Area1:(40"x1Q" x0.8")/2=16"'

iotai altissea volume (Upstream scan) = Area I + Area 2 1 6"' - 252" = 41.2" oia, rmssej volume (Downstream scan) = Area 1 + Area 3 + Area 4 16`4 1-127"' + 181 44"' z324.44"'

t Ot3i Achieved coverage (per scan) = T.E.V. - T.M.V. I T.E.V.

413 28"' - 41.2`3 1413.28`3 = 901(Upstream Scan) 413 28"' - 32444" 141128"' = 21 (Downstream Scan)

THOLE 70° coverage achieved during Inner Radius Examtior to Nozzle Exam.

4 RMEW I OATS A 1 R15-UT "()22 Page 3 of6 f",.,. It Jir'"

11_.............

LlMITA nON TO EXAMINATION Braidwood RY/N2 RELATED TO:

UT x

PT MT UNIT 1

SKETCH PROCEDURE DATE 1 PZR..() 1 EXE..aSI-210. Rev. 3 1011212010

__ VT __

(DENT. NO.

1PZR"()1-N2 PROVIDE GENERAlINFORMATJOH TO DESCRIBE APPROXIMATE SlZE, LOCATJOH AND TYPE OF UUlTAllON.

45". 60" and 70" Axial Upstream' Downstream Scans Exam Volume:: length x Width x Height length:: 40" Width:: 4.1" Height::: 2.52" (40" x 4.1" x 2.52")::: 413.28'"

Area 1: (40" x 1.0" x 0$') 12:::: 16'"

Area 2: (40" x 1 $' x 0.7") 12 :::: 25.2 '"

Total missed volume (Upstream scan):::: Area 1 + Area 2 16'" + 252'" :::: 41.2'"

Total missed volume (Downstream scan) :::: Area 1 + Area 3 + Area 4 16'" + 127'" + 181.44'" :: 324,44'"

Achieved coverage (per scan) ::: T.E.V. - T.MV 1 T.E.V.

413.28fta - 41.2'" 1413.28'" :::: Ir1l (Upstream Scan) 413.28'" - 324.44'" 1413,28:: ~

(Downstream Scan) 70" coveraae achieved durina Inner Radius Exam Drior to Nozzle Exam,

'~~

~.QJ?nr 10./,,-*'0 ITO f:3 Area 3: (40" x 2.52" x 2.52") 12 :; 127'"

Area 4: (40" x 1.8" x 2.52"):; 181.44"'1 1<eFII'At!'AI¢ 1?Eh,e..,- AIIt15-0T"-O.z.O....

"A44 3 ~" Fo.IIl. rNAle"JII. itAd,(/.s.A..rA.

IO/Z.2./1D l

L..J~

l~ll""tl...l

4

^io INSPECTION SERVICES Page 4 of $

PROFILE OF THE EXAMINATION VOLUME/ DATA UNIT I

SKETCH IPZR-01 PROCEDURE EXE4SI-210, Rev. 3 DATE 10/12/2010 IDENT.

1PZR-01-N2 BraKtwood S, L&VOI III RY / N2

" ~I.I"'~.hIIC *.

"",~

PLANT Braidwood SYST ICOMP.

EXAMINER

&~ D ~1NIr aUt II 45-, 60- & 70-Aletal Scans Tot.. (AD (A.

IN8P£CT1ON SERVICES PROFILE OF THE EXAMINATION VOLUMEI DATA RY IN2 DATE 1:. s" UNIT 1

SKETCH 1011212010 PROCEDURE

IDENT,

>'\\

J: I I

I 1_' '_=-_--=-_

I...

,.. 4ofl lPZR-01 EXE-ISI-210. Rev. 3 1PZR-01-N2 M1.

,~

"'0

/.-/~

... ;.:J ol l-t"""--4. _

l.:;) \\ \\40 \\ \\. ~

A P

Lliv-a1TATIO TO EX4A-iiiiATION UNIT 1

SKETCH 1PZ PROCEDURE EXE-ISI DATE

^rLLATEO TO.

UT X

PT riT IPROV1Ot GENERAL itVrtltt,aA11QN TO i AC40SE APPRO)U RATE 8W% LOCATION AND TYPE OF U TATTON.

45° & 60° CW/CCW Exam & 0° Total Exam Volume = Length x Width x Height length = 40" Adth=41" Height = 2.52" (40"x4 1"x2.52")= 413.28" Nil:,.,-d volume = Le c, J m x Width x Height (in cross hatched area)

Area1 :(4u"x1.0" x0.8")/2=16"'

Area 2: (40" x1.6"x2.52")=161.28"'

A,ea 1 Area 2_ (16 + 161.28") =177.28"'

Total missed volume = 177.28"3 T'otai Achieved overage (per scan) = T.E.V. - T.M.V. / T.E.V.

413.28-177.28"/ 413.28" = 57.1 %

Total Achsevepd coverage _ ^

Deal A: t^Iuva i overage (per exam naLo n) = (Ups m scan + Downstream scan + CW scan + CCW scan + 0° scan) / 5

(;sJ% +21.5%+571%+57.1 %+57.1%)15 tAAMiNER 0dU1 )tea, tevef-I

/COMP.

Braidwood RY / N2 LAN I 10' IDENT. NO.

AfRl5=UT.;Q22 Page 50f6 LIMITAnON TO EXAMINATION Braidwood UNIT..!.

SKETCH 1PZR"()1 SYST/COMP.

PROCEDURE E.XE-ISI-210IR~ :'! ____ _

EXAMINER ~

DATE 1011212010 RELATED TO:

UT x

PT MT __ VT __

IOENT. NO.

1PZR..()1-N2 PROVIDE OENERAlINFORMATIOH TO OESCRtBE APPROXlIlllATE SIZE. LOCATIOH AND TYPE OF LliilTATIOH.

45* & 50* CWICCW Exam & O*

Total Exam Volume =: Length x Width x Height length =: 40" Width =: 4.1" Height =: 2.52" (40" x 4.1" x 2.52");: 413.28"*

Missed Volume;: Length x Width x Height (in cross hatched area)

~

Area 1: (40'" x 1.0" x 0.8") I 2 =: 16"*

Area 2: (40" x 1.6" x 2.52") =: 161.28 "*

Area 1 + Area 2: (16"* + 161.28"*) = 177.28"*

Total missed volume = In.28J!It.l '....

NlA l..eWII III 0eIIt NlA 0.

10112110 NlA I L I I I I li21rut..

tst.. lr.

IMrdl Unit t1 Manuf8dln:

K8A Serial No.:

o,BflYil No. of EJemeri&:

1 Size: 1,(1' Sh8P8: ROUnd Freq. 2:25 fIIti ~: Gimmi EJcam Anji 0-Modi:

LOng Me8Mnd AIge:--

NlA Wedge Style:

Int!pI 8eerch Unit Cable Type:

R~174 Length:

~NO. Ofcon.:

o -

tnetrument 8ettInge MIlke I Model: KnautItrwnef I USN 58L SW SeriIII No.:

SAP 104381 Probe Delay: 0.9468 Renge:

5.fr M'tI Call Vel: 0.2301 PuIMr. s;;e Damping:

500 Rtject:

0%

PRF:

Auto HIgh Fntq: 2.2T'MHz Filter:

Fbced Mode: o..t orr Rectify.

FuMw Voltage: m

".. WidIh:

220 os -

Display Delay:

0 Reference SentiMy (dB)

'RJ,ar cS6' : -- J.#.<< / *. (£-~O Axial:

10.0 dB Cifc:

Fur1her E~

RequIred?~"

__ mHo 1.8W:

WesOyne ~

I o.te:

NJA ClfWl.*M'WIIWJOI\\T(

~ --r-'MTI J

\\. --,..

\\',,,,,,,,,,

\\

~

\\,

8Mrch U~ Cable Type:

---

~~~~---

LengIh:

Make J Model: ------\\0 Serial No.:

Probe Delay:

M'U Cell Vel: --

Oemping:

PRF:

Filler. ___

Rectify:

P&;aeWklh:

~~-.-----------------~

R...... a SenIitMty (dB)

A>>II:

Circ:

FSOH SenIitMty:

\\

Calibration Data Sheet

/ 1 Data Sheet d Page 2

3 Austenitic n / 1.0' RY SI.210 0

071 4'F 105230 2.06W T

c. 0 Both m:

Cal. Checks Time Ini Calib.

09:22 / OW23 Initial Catib. Date 10/12110 Intetnte 12:191112:20 Intermediate 13:57114:39 Final Calib.

16:52/15:53 Final Calib. Cate 10112110 Search UM 01 Manufacb e:

KBA Serial No.:

No. of Elemen.

Size:

0.5' x 1.0' sue: ed.

Freq.

2.

Style:

G arnma Exam rW.

45' Moc e::

Measured Angle:

45' Wedge Style:

SWS Search Unit Cable Search Unit 92 Marwfeckae:

KBA Serial No.:

D K

No. of Elements:

f Sane:

0.5' x 1.0' speed.

Freq.

Style:

GOMM Exam ICNp0' Mo ear Measured Angie:

60' Wedge Style:

SWS Search Unit Cable A1RI5-UT-023 of 6

Coupi-ant 803.110 Type:

ULTRAGEL 11 ch:

09225 l1: i t._ti 1.711 1=3 MON RELEVANT YES >6O% Ret

__.)

No X

S FLAW NO X

so d8 06 d8 Type:

RG-174 Type:

RG-174 Length:

12' No. of 0

Length:

12' No. of 0

Instrument Settings Instrument Settings ants)

COMPONENT TEMP:78'F ximately 60.92% coverage achieved due to Make I Model K tkt

/ US Calibration Data Sheet Plant I Unit BIaidwood I 1 Data Sheet,

A1R15-UT..Q23 of e

Company ElC860n Page 2

Comp I System H31 RV Pro<:edure No.

EXE-tS1-21 0 Rev J Chng. No.

3/0 CeI.CheGka TIme Cat. 8&cJd( No.

BWO 071 Cal. 8&cJd( Temp.

746F Initial CaIib.

09:22/09".23 Thermometer SIN:

SAP 105230 Size 6-Sc::h.

NlA 12.Q825-initial CUb. Date 10112110 i I Rtf BIoq; I SAP',05220

[!J F8fritic DAuatenitic 1ntennediat8 12:19/12:20 e.ch Major CRT ON. =

o.r 11.0" 1ntennediat8 13:57/14:39 Cat. Direction:

[!)Axial 0 eire. 0 BoIh Fin8I c.Jib.

15:52115:53 Sean Area:

I toWetd [!]

II to Weld [!J Final CaIib. Date 10112110 CoupIant Code Categoty:

8-0 Code Item:

803.110 Type:

UL TRAGEL II Batch:

0Q225 11011 'Hr.... IUN~

EXAII ACCESS FLAW NOH Rl!LEVAHT....

examination Area I Wefd VEl NO VII~IW.I NO CdB) 1RY01S 11PZR..Q1-N3 =

X X eo dB

.. dB Ben\\8tt(ll Beaaon fg( IncomDlata Sctn(1l COMPONENT TEMP:78" No recordable indications. Approximately 60.92% coverage achieved due to I

nozzle configuration. See attached pages 3 Ihru 6 for coverage calcu&ations.

• 45" cal Check: 1,(1" Radjus @ 1.25 div @ 70% CD 22.5 dB; 2.0" Radius CD 2.5 I

diY @ 25% @ 22.5 dB

.. 60° Cal Check: 1.0" Radius @ 1.0 div 0 90% (0 26 dB; 2.0" Radius CD 2.0 div

@50%@26dB.

ExamIne,.: Paul 8IItcha &+0 SJll..Level HI"

~

III DatIl

~o.

WeaOyneRewMet/Date: ?j;.,pf"t4,.,' 4.... 11[ /o*/,s:./O Further Evaluation Reqund1 I D -II. -, 0 10112110 N1A I

T.-

JlII.

Ilf II! ~ ] 0 ~

3J~ IT l

ID~ but

~

~

~ c_ ---

8earctI Untt t1 ManufacIure:

KBA Serial No.:

&alA No. of EJamenIi:

1 Size: 0.5" x 1.0" Sh8P8:

ReCt.

Freq. 2:28 MHZ Styte:

oammii Exam AniiI8:

45* Mode:

§i8i; Measured Atge-:--

45*

Wedge Styte:

SWS 8eanIh Unit cable

.1 r!.1

m IJ 'l"

')14 tr I.

1I~'".,.tw I,~ ~T I

~

8eaIch Unit 12 ManufacIure:

KBA Serial No.:

OOIXBK No. of Elemei\\1I:

1 Size: 0.5" x 1.0" Sh8P8: Rect.

Freq. 2.21 fIIIHi Styte:

oamma Exam AniiI8:

eo* Modi:

Sh88i Measured Angle:

eo*

Wedge Style:

SWS Search UnIt CQIe Type:

RG-174 Type:

RG-174

.!!,...NO. Olean.: -L LengIh:

12' NO. or con.: -L Length:

Instrument Sealnge Inatrument Sealnge Make I Model: Ktautkramer I USN 58L SW Make 1 Model: KrautIuamer' USN 58L SW Serial No.:

SAP 104391 Serial No.:

SAP 104391 Probe Delay: 12.1I2aO Range:

8.0" M'II Cal 'Vel: 0.1272 NIet: sguii!

Damping:

500 Retect 0%

PRF:

Auto High Freq: 2:2SMHz Probe Delay: 18.0784 Renge:

10.0" M'II cat 1 Vel: 0.1272 Puller. sguii!

Oamptng; 500 RfIted:

0%

PRF:

Auto High Freq: 2.25'"MHl FIter:

Fbcad Mode: Dual Off FItl8r:

Fbcad Mode: Dual Off Rectify.

Fullwawe Voltage:

450 Pulse WkIh:

220 na -

Rectify.

FuIIwa¥e Voltage:

450 PuIIe WidIh:

220 ns -

0tspIay Delay:

0 Display Delay.

0 Referenee SensItivIty (dB)

Refefaa SenaiIMty (dB)

AxiII; 37.0 dB Circ:

NlA A*I:

42.8 dB Ckc:

NlA FSOH SenINy.

FSOHS.........

1 L

AIR1S-UT-023 Page3of6 LIMITATION TO EXAMINATION UNIT I

SKETCH 1PZR-01 RYI N3 PROCEDURE EXE-ISI-210, Rev 3 DATE 1011212010 MT VT IDENT. NO.

1PZR-01-N3 TO OEUCRIOE APPROXIMATE SUM. LOCATM A11O TYPE OF LWITATION.

45', 60' and 70' Axial Upstream / Downstream Scans Width x Height and 1.2" on each side)

BraKtwood 64 X

PT x Height (in cross hatched area) 0"x0.6')12=14.13"'

.7"x08 )/ 2=32.0"'

can) = Area 1 + Area 2 EJIlI Area 3: (47.10" x2.5"x2.50)12=147.21 H

Area 4: (47 10" x 1.7" x 2.5") = 200.2" A1R1s:uT.m3 Page 3 0'6 UMITATION TO EXAIIINA liON T

Braidwood SYST ICOMP.

RY/N3 EXAMINER (U,.

IS ~..?===

~

Paul B..&itn RELATED TO:

UT x

PT UNIT 1

MT VT SKETCH PROCEDURE DATE 1PZR-01 EXE~St*210. Rev 3 1011212010 IDENT. NO.

1PZR-01-N3 PROVlDE GEJtE.RAL IHFORMATlOH TO 0UCIU8e APPROlUIIATE I&ZE.. LOCATlON AHO nPE 0# LlllllTATlOM.

45-, eo-and 70* Axial UpIbUm 1 00wn1tJUm Scans Total Exam Volume ;: length x Width x Height length;: 47.10*

Width ;: 4.1" (1. r weld crown and 1.2" on each aide)

Height = 2.5-(47.10" x 4.1* x 25*) = 482.8'"

Missed Volume = length x Width x Height (in aosa hatched area)

~

Asea 1: (47 10" x 1.0* x 0.6")' 2.: 14.13'"

~

Area 2: (47.10"x 1.lxO.8")/2=32.0'"

Total missed volume (Upstream scan) = Area 1 + Area 2 14 13'" + 3Z"-;: 46.13'"

Toral missed volume (Downstream scan) = Alea 1 + Area 3 + Area 4 1413** + 147.~

+ 200.2'" = 361.53'"

Total Actlleved coverage (per scan) = T.E.V.

• T.M.V. I T.E V.

482.8" *46.13""482.8"'* ~

(Upstream Scan) 482.8"'*361.53"'482.8"* = B"ll (Downabum Scan)

,e actlleved dunna Inner Radius Exam to NozzJe Elcam.

~

..... ~"

/0- /S-IO

/4-11..1()

[ill

§ Area 3: (47.10" x 2.5* x 2.5") 12 = 147.2'"

Area 4: (47.10- x 1.1 x 2.5") = 200.2*

1l~'Pl6NCe R&ALttr 'litiS -vr- 02',

~/II'S ~"..

?A4-e 3 ell&' ~

~~

.. I..... ~ 10'%..'1-//'

L \\- 't l_\\\\c.. \\'_

!Uf.I^31:S:Iyci^P.

Ft L's I I'lpitl INSPECTION SERVICES PROFILE OF THE EXAMINATION VOLUME! DATA Pape 4 o16 Brudwood RY / N3

,^: 6Ll-,

C112. LOVOI III UNIT 1

SKETCH 1 PZR-01 PROCEDURE EXE-ISI-210, Rev. 3 DATE 10112/2010 IDENT.

IPZR-01-N3 m's INSPECTION SERVICES Paae4of.

PROFILE OF THE EXAMINATION VOLUMEI DATA PLANT Braidwood SYST ICOMP RY I N3 EXAMINER

~. ("i' -

DATE 45-, SO* & 70*

Axial Scans

~I Tot 1"1..Q~

I

't..~

....M-... "..:..

}.".J£-

I~ - ~S - ~d

/1-. ~()f)11r no JL.uJ UNIT 1

1011212010 SKETCH PROCEDURE IOENT.

~

"1-1PZR~1 EXE~SI*210, Rev. 3 1PZR~1-N3 L

\\-'(,,1.

,,~ \\'-\\4..,:)

SYS I iCOMf'.

EXAM NErZ

'i0 stJ r^AIION UNIT 1

SKETCH PROCEDURE PZ EXE-1Si DATE f otai Exam Volume = Lengtn x W^atri x Height L ength = 47 1" Width = 4 1" (11' wt d crown and 1. 2" on each side)

Height = 2 5' (4710"x41"x2. 5")-.482.8"'

M sseo Volume = Length x Width x i-tevjht (in cross hatched area)

Area 1: (4710"x 1.0"x0.6")/2 = 14.13" 2: (47.10" x 1.4" x 2.5") = 164.85 "'

Area 1 t-Area 2 (14 1 7

ita+ misseo volume= C 16485"')= 179"'

j"; o:ai Achieved coverage (per scan) :z T.E.V. - TMV. / T.E.V.

452 8" - 179"' 1482 8 W 63%

Total Achieved coverage =

I ToLai :.cnievec coverage (per examination) = (Upstreeam scan + Downstream scan + CW scan + CCW scan + 00 scan) / 5 1

(904%+252%+ 63%+63% + 63%)/5=

t, hOJ T E 70` coverage acri ;eved duriri Inner Radius Exam rlor to Nox a Exam.

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1PZR-01-N3 PROVIDE GENERAL IHFORMA11OM TO DESCRiBE APPROXIMATE 8Il£, L0CA11OM AND 1YPE Of UIllm'Al1ON.

45° & 80° CWICCW Exam & 0° Total Exam Voiume = length x Width x Height length = 47.1" Width = 4.1" (1.7" weld crown and 1.2" on each side)

Height = 2.5" (47 10" x 4.1" x 2.5") :;: 482.8'*a Missed Volume = length x Width x Height (in cross hatched area)

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Area 1: (47.10" x 1.0" x 0.6") 12 = 14.13'*a

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Area 2: (47.10" x 1.4" x 2.5") = 164.85*

Area 1.. Area 2: (14.13'*' + 164.as'*a) = 17Q"a Total missed voiume = 17IMa Achieved coverage (per scan) = T.E.V. - T.M.V.I T.E.V.

482.8'" - 179*/482.8* = 63%

Achieved coverage = m Achieved coverage (per examination) = (Upstream scan + Downstream scan + CW scan + CCW scan + 0" scan) 15 (904% + 25.2% + 63% + 63% + 63%) 15 = 80.12%

NOTE 70" coveraGe achieved during Inner Radius Exam crior to Nome Exam.

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08:12 / 08:21 Initial Calib. Date 427/2011 Intermediate 09:25110:39 Intermediate N/A Final Calib.

10.45110:60 Final Caiib. Date 4/27/2011 Couplant m:

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09225E Search Unit 81 Manufacture:

KBA Serial No.:

No. of Elemen :

1 Size:

1.0' Shape:

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2.25 MHz Style:

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Integral Search Unit Cable Type:

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instrument Settings Make I Model:

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SWS Search Unit Cable Type:

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12' No. of 0

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71 0'F 108888 2.06250 T

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0.80"

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EXE-tSI-210 Rev I Chng. No.

3/1 IMiaI CaIib.

08:12/08:21 Cal. Bkx:k No.

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