ML15202A034

Relief Request Serial 15-ON-002: Limited Volume Examinations Per 10 CFR 50.55a(g)(5)(iii) for Unit 1 and 2, Fourth Inservice Inspection Interval. Part 1 of 3

ML15202A034
Person / Time
Site:	Oconee
Issue date:	07/15/2015
From:	Duke Energy Carolinas
To:	Office of Nuclear Reactor Regulation
Shared Package
ML15202A032	List: ML15202A033 ML15202A034 ML15202A035 ONS-2015-086, Relief Request Serial 15-ON-002: Limited Volume Examinations Per 10 CFR 50.55a(g)(5)(iii) for Unit 1 and 2, Fourth Inservice Inspection Interval. Part 3 of 3
References
ONS-2015-086
Download: ML15202A034 (77)

Text

Enclosure to ONS-2015-086 Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1 and 2 Relief Request Serial #15-0N-002:

Limited volume examinations per 10 CFR 50.55a(g)(5)(iii) for Unit 1 and 2, Fourth lnservice Inspection Interval

Oconee Relief Request 15-0N-002 1.0 Scope of Relief Request Relief is requested pursuant to 10 CFR 50.55a(g)(5)(iii) for welds listed in Table 1.

These welds were required to be examined in accordance with lnservice Inspection Plans for the following Units.

Oconee Nuclear Station - Unit 1 Fourth 10-Year lnservice Inspection Interval Interval Start Date: January 1, 2004 Interval End Date: July 15, 2014 Table 1 Relief Oconee Examination Weld ID Number ltem/Summarv Examination Request Unit Performed Number Data Section Number (Refueling Number Outage}

2.0 1

1EOC27 1-RPV-WR34 01.81.11.0005 See Attachment A Pages 1-2 3.0 1

1EOC27 1-RPV-WR35 01.81.21.0001 See Attachment A Pages 3-8 4.0 1

1EOC27 1 LDC8-INLET 01.82.51.0003 See Attachment A Pages 9-21 5.0 1

1EOC27 1 LDCB-OUTLET 01.82.51.0004 See Attachment A Pages 22-34 6.0 1

1EOC27 1-PDA1-1 01.89.11.0059 See Attachment A Pages 35-44 Note:

1. Duke Energy procedures require ASME Code,Section XI examinations that do not meet the requirements of Code Case N-460 to be marked "reject" for tracking purposes, regardless of whether indications were noted. Therefore, the limited exams in 15-0N-002 without indications were marked "reject" on data sheets.

2. Duke Energy has invoked Code Case N-663 which allows elimination of Code required surface exams for welds listed in Section 6.0 of this Relief Request.

Page 1 of31

Oconee Relief Request 15-0N-002 2.0 Weld # 1-RPV-WR34 2.1.

ASME Code Component(s) Affected Unit 1 Reactor Vessel Lower Shell Course to Lower Ring Section Weld, Reactor Coolant System, Weld # 1-RPV-WR34, Summary Number 01.81.11.0005, and ASME Code Class 1.

2.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

2.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number 81.11 Fig. IWB-2500-1, 100% Volume Coverage of Examination Volume A-B-C-D.

2.4.

Impracticality of Compliance Component configuration:

Surface 1 : Lower Shell Course - Carbon steel Surface 2: Lower Ring Section - Carbon steel Diameter: 170.000 in.

Thickness: 5.500 in.

This component was scanned with automated methods from the Reactor Vessel interior. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Inner 15% thickness (T) coverage using 45°& 70° longitudinal waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained 36.00% coverage.

Outer 85% thickness (T) coverage using 45° longitudinal waves and 45° shear waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained 44.00% coverage.

The aggregate coverage was calculated to be (15%)(36%) + (85%)(44%) = 43.00%.

The impracticality was caused by the Reactor Vessel Interior configuration (Core Guide Lugs and Flow stabilizers) that does not allow meaningful interrogation.

The current configuration does not allow scanning of all of the required volume for this weld. The weld configuration would have to be redesigned and replaced, which is impractical.

Page 2 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

Indications were recorded and found to be acceptable during this examination.

2.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

2.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

2.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 01.B1.11.0005 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), 'Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

2.8.

References Duke Energy Relief Request 02-0N-005 was approved by the NRC during the last inspection interval. The previous approved SE is documented in Accession Number ML032721404, TAC No.MB5830 dated September 29, 2003.

Page 3 of31

Oconee Relief Request 15-0N-002 3.0 Weld # 1-RPV-WR35 3.1.

ASME Code Component(s) Affected Unit 1 Reactor Vessel Lower Head Cap Section to Lower Head Ring Section Weld, Reactor Coolant System, Weld# 1-RPV-WR35, Summary Number 01.81.21.0001, and ASME Code Class 1.

3.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

3.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number 81.21 Fig. IWB-2500-3, 100% Volume Coverage of Examination Volume A-B-C-D.

3.4.

Impracticality of Compliance Component configuration:

Surface 1: Lower Head Cap Section - Carbon steel Surface 2: Lower Head Ring Section - Carbon steel Diameter: 143.00 in.

Thickness: 5.375 in.

This component was scanned with automated methods from the Reactor Vessel interior. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Inner 15% thickness (T) coverage using 45°& 70° longitudinal waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained 33.00% coverage.

Outer 85% thickness (T) coverage using 45° longitudinal waves and 45° shear waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained 37.00% coverage.

The aggregate coverage was calculated to be (15%)(33%) + (85%)(37%) = 36.00%.

The impracticality was caused by the Reactor Vessel interior configuration (lncore Nozzles and Flow Stabilizers) that does not allow meaningful interrogation. The current configuration does not allow scanning of all of the required volume for this weld. The weld configuration would have to be redesigned and replaced, which is impractical.

Page 4 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

Indications were recorded and found to be acceptable during this examination.

3.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

3.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

3.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 01.B1.21.0001 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

3.8.

References Duke Energy Relief Request 02-0N-005 was approved by the NRC during the last inspection interval. The previous approved SE is documented in Accession Number ML032721404, TAC No.MB5830 dated September 29, 2003.

Page 5 of31

Oconee Relief Request 15-0N-002 4.0 Weld # 1 LDCB-INLET 4.1.

ASME Code Component(s) Affected Unit 1 Letdown Cooler, Head to Head, Reactor Coolant System, Weld # 1 LDCB-INLET (same as weld ID: WJ-32), Summary Number 01.B2.51.0003, and ASME Code Class 1.

4.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

4.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-B, Item Number B2.51, Fig. IWB-2500-3, 100% Volume Coverage of Examination Volume A-B-C-D.

4.4.

Impracticality of Compliance Component configuration:

Surface 1: Chemical Connector - Stainless steel Surface 2: Channel Body - Stainless steel Diameter: 8. 75 in.

Thickness: 0.875 in.

This component was scanned manually with conventional methods. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5, and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Axial scan coverage (S1,S2) using 4.5° Shear and Longitudinal and 60° &

70° Longitudinal waves obtained 97.2% coverage.

Circumferential scan coverage (CW, CCW) using a 45° shear wave obtained 78.1 % coverage.

The aggregate coverage was calculated to be (97.2% + 78:1%)/2 = 87.7%.

The impracticality was caused by the taper configuration and nozzle on the chemical connector that does not allow meaningful interrogation. In order to scan all of the required volume for this weld. The shell to sampling nozzle weld would have to be redesigned and replaced, which is impractical.

Page 6 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

No relevant indications were recorded during this examination. The reject box on data sheet is marked for internal tracking purposes of the coverage limitation only.

4.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

4.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

4.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 01.B2.51.0003 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

4.8.

References Duke Energy Relief Request 12-0N-001 was approved by the NRC during the last inspection interval. The previous approved SE is documented in Accession Number ML13365A023, TAC No.MF0648 and MF0649 dated January 17, 2014.

Page 7 of31

Oconee Relief Request 15-0N-002 5.0 Weld # 1 LDCB-OUTLET 5.1.

ASME Code Component(s) Affected Unit 1 Letdown Cooler, Head to Head, Reactor Coolant System, Weld# 1 LDCB-OUTLET(same as weld ID: WJ-35), Summary Number 01.82.51.0004, and ASME Code Class 1.

5.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

5.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-B, Item Number 82.51 Figure IWB-2500-3, 100% Volume Coverage of Examination Volume A-B-C-D.

5.4.

Impracticality of Compliance Component configuration:

Surface 1: Chemical Connector --Stainless Steel Surface 2: Channel Body - Stainless Steel Diameter: 8. 75 in.

Thickness: 0.875 in.

This component was scanned manually with conventional methods. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Axial scan coverage (S1,S2) using 45° Shear and Longitudinal and 60° &

70° Longitudinal waves obtained 97.2% coverage.

Circumferential scan coverage (CW, CCW) using a 45° shear wave obtained 78.1 % coverage.

The aggregate coverage was calculated to be (97.2% + 78.1%)/2 = 87.7%.

The impracticality was caused by the taper configuration and nozzle on the chemical connector that does not allow meaningful interrogation. In order to scan all of the required volume for this weld. The shell to sampling nozzle weld would have to be redesigned and replaced, which is impractical.

The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. Therefore, the available coverage will not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

Page 8 of31

Oconee Relief Request 15-0N-002 No relevant indications were recorded during this examination. The reject box on data sheet is marked for internal tracking purposes of the coverage limitation only.

5.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography {RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other technique available would incur the same physical scanning limitations.

5.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

5.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 01.B2.51.0004 was

• conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

5.8.

References Duke Energy Relief Request 12-0N-001 was approved by the NRC during the last inspection interval. The previous approved SE is documented in Accession Number ML13365A023, TAC No.MF0648 and MF0649 dated January 17, 2014.

Page 9 of31

Oconee Relief Request 15-0N-002 6.0 Weld# 1-PDA1-1 6.1.

ASME Code Component(s) Affected Unit 1 Reactor Coolant Pump 1A1, RCP-1A1 to Safe-End, Reactor Coolant System, Weld# 1-PDA1-1, Summary Number 01.89.11.0059, and ASME Code Class 1.

6.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

6.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-J, Item Number 89.11, Figure IWB-2500-8 (c), 100% Volume Coverage of Examination Volume C-D-E-F.

6.4.

Impracticality of Compliance Component configuration:

Surface 1: Safe-end - Stainless Steel Surface 2: RCP-1A1 - Stainless Steel Diameter: 33.50 in.

Thickness: 2.330 in.

This component was scanned manually with conventional methods. Scanning requirements are described in 1 OCFR.50.55a (b )(2)(xv)(A)( 1 ). These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Examination coverage using a 45° shear wave and a 60° longitudinal wave for axial scans (S1) and 60° & 70° longitudinal waves for axial scans (S2).

Examination coverage using 45° shear waves for circumfere'ntial (CW, CCW) scans (S1) and 60° & 70° longitudinal waves for circumferential (CW, CCW) scans (S2).

Surface (S2) was scanned 100% but, no credit for Surface 2 volume is being taken since this side is fabricated from cast stainless material.

The aggregate coverage was calculated to be (100.0% + 0% + 50.0%+ 50.0%)/4 = 50%.

The impracticality was caused by the cast stainless material that does not allow meaningful interrogation from the Surface 2 RCP-1A1side. The current configuration allows 100% scanning of all of the required volume for this weld, but credit for the surface 2 cast stainless side which is considered "best effort" is not being claimed. The weld configuration would have to be redesigned and replaced, which is impractical.

Page 10 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. Therefore, the available coverage will not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

No indications were recorded during this examination. The reject box on data sheet is marked for internal tracking purposes of the coverage limitation only.

6.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component cast stainless material. The use of any other technique available would incur the same physical scanning limitations.

6.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

6.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 01.B9.11.0059 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

6. 8.

References None.

Page 11 of31

Oconee Relief Request 15-0N-002 7.0 Scope of Relief Request Relief Relief is requested pursuant to 10 CFR 50.55a(g)(5)(iii) for welds listed in Table 2.

These welds were required to be examined in accordance with lnservice Inspection Plans for the following Units.

Oconee Nuclear Station - Unit 2 Fourth 10-Year lnservice Inspection Interval Interval Start Date: September 9, 2004 Interval End Date: July 15, 2014 Table 2 Oconee Examination Weld ID ltem/Summarv Examination Reguest Unit Performed Number Number Data Section Number (Refueling Number Outage) 8.0 2

2EOC26 2-RPV-WR18 02.81.11.0003 See Attachment 8 Pages 1-4 9.0 2

2EOC26 2-RPV-WR34 02.81.11.0004 See Attachment 8 Pages 5-11 10.0 2

2EOC26 2-RPV-WR35 02.81.21.0001 See Attachment 8 Pages 12-15 11.0 2

2EOC26 2-PZR-WP26-1 02.83.110.0009 See Attachment 8 Pages 16-28 12.0 2

2EOC26 2-PZR-WP26-2 02.83.110.0010 See Attachment B Pages 29-40 13.0 2

2EOC26 2-PZR-WP26-3 02.83.110.0011 See Attachment 8 Pages 41-48 14.0 2

2EOC26 2-LDC8-IN-

02. 83.150.0003 See Attachment WJ33V 8 Pages 49-58 15.0 2

2EOC26 2-LDC8-0UT-02.83.150.0004 See Attachment WJ36V 8 Pages 59-68 16.0 2

2EOC26 2-SG8-W69 02.C1.30.0001 See Attachment 8 PaQes 69-80 Page 12 of31

Oconee Relief Request 15-0N-002 8.0 Weld# 2-RPV-WR18 8.1.

ASME Code Component(s) Affected Unit 2 Reactor Vessel Upper Nozzle Belt to Upper Shell Weld, Reactor Coolant System, Weld# 2-RPV-WR18, Summary Number 02.B1.11.0003, and ASME Code Class 1.

8.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

8.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500.-1, Examination Category B-A, Item Number B1.11 Fig. IWB-2500-1, 100% Volume Coverage of Examination Volume A-B-C-D.

8.4.

Impracticality of Compliance Component configuration:

Surface 1: Upper Nozzle Belt - Carbon steel Surface 2: Upper Shell Weld - Carbon steel Diameter: 167.63 in.

Thickness: 12.00 in.

This component was scanned with automated methods from the Reactor Vessel interior. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Inner 15% Thickness coverage using 45° & 70° longitudinal waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained 83.2% coverage.

Outer 85% Thickness coverage using 45° longitudinal waves and 45° shear waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained 77.8% coverage.

The aggregate coverage was calculated to be 78.60%. See attached

.examination coverage sheet for calculations.

The impracticality was caused by the Reactor Vessel Outlet Nozzle Boss configuration that does not allow meaningful interrogation. The current configuration does not allow scanning of all of the required volume for this weld.

The weld configuration would have to be redesigned and replaced, which is impractical.

Page 13 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

Two indications were recorded during this examination and determined to be acceptable per IWB-3510-1.

8.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT} is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

8.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

8.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 02.B1.11.0003 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

8.8.

References None.

Page 14 of31

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Oconee Relief Request 15-0N-002 9.0 Weld # 2-RPV-WR34 9.1.

ASME Code Component(s) Affected Unit 2 Reactor Vessel Lower Shell to Transition Piece Weld, Reactor Coolant System, Weld# 2-RPV-WR34, Summary Number 02.81.11.0004, and ASME Code Class 1.

9.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

9.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number 81.11 Fig. IWB-2500-1, 100% Volume Coverage of Examination Volume A-B-C-D.

9.4.

Impracticality of Compliance Component configuration:

Surface 1: Lower Shell - Carbon steel Surface 2: Transition Piece - Carbon steel Diameter: 170.25 in.

Thickness: 5.5 in.

This component was scanned with automated methods from the Reactor Vessel interior. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Inner 15% Thickness coverage using 45° & 70° longitudinal waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained 35% coverage.

Outer 85% Thickness coverage using 45° longitudinal waves and 45° shear waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained 44% coverage.

The aggregate coverage was calculated to be 42.7%. See attached examination coverage sheet for calculations.

The impracticality was caused by the Reactor Vessel interior configuration (Guide Lugs and Flow Stabilizers) that does not allow meaningful interrogation.

The current configuration does not allow scanning of all of the required volume for this weld. The weld configuration would have to be redesigned and replaced, which is impractical.

Page 15 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

Fourteen indications were recorded during this examination and determined to be acceptable per IWB-3510-1.

9.5.

Proposed Alternative and Basis for Use.

No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

9.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

9.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 02.81.11.0004 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

Page 16 of31

Oconee Relief Request 15-0N-002 9.8.

References Duke Energy Relief Request 04-0N-003 was approved by the NRC during the last inspection interval. The previous approved SE is documented in Accession Number ML051640307, TAC No. MC2704 dated July 22, 2005.

Page 17 of31

Oconee Relief Request 15-0N-002 10.0 Weld # 2-RPV-WR35 10.1.

ASME Code Component(s)Affected Unit 2 Reactor Vessel Transition Piece to Lower Head Weld, Reactor Coolant System, Weld# 2-RPV-WR35 Summary Number 02.81.21.0001, and ASME Code Class 1.

10.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

10.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-A, Item Number 81.21 Fig. IWB-2500-3, 100% Volume Coverage of Examination Volume A-B-C-D.

10.4.

Impracticality of Compliance Component configuration:

Surface 1: Transition Piece - Carbon steel Surface 2: Lower Head - Carbon steel Diameter: 143.00 in.

Thickness: 5.375 in.

This component was scanned with automated methods from the Reactor Vessel interior. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Inner 15% Thickness coverage using 45° & 70° longitudinal waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained

32. 7% coverage.

Outer 85% Thickness coverage using 45° longitudinal waves and 45° shear waves for axial scans (S1, S2), and circumferential scans (CW, CCW) obtained 37.1 % coverage.

The aggregate coverage was calculated to be 36.4%. See attached examination coverage sheet for calculations.

The impracticality was caused by the Reactor Vessel interior configuration (lncore Nozzles and Flow Stabilizers) that does not allow meaningful interrogation. The current configuration does not allow scanning of all of the required volume for this weld. The weld configuration would have to be redesigned and replaced, which is impractical.

Page 18 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

No indications were recorded during this examination.

10.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

10.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

10. 7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 02.B1.21.0001 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

10.8.

References Duke Energy Relief Request 04-0N-003 was approved by the NRG during the last inspection interval. The previous approved SE is documented in Accession Number ML051640307, TAC No. MC2704 dated July 22, 2005.

Page 19 of31

Oconee Relief Request 15-0N-002 11.0 Weld # 2-PZR-WP26-1 11.1.

ASME Code Component(s) Affected Unit 2 Pressurizer Shell to Sampling Nozzle Weld, Reactor Coolant System, Weld# 2-PZR-WP26-1, Summary Number 02.B3.110.0009, and ASME Code Class 1.

11.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

11.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-D, Item Number B3.110 Fig. IWB-2500-7 (a), 100% Volume Coverage of Examination Volume A-B-C-D-E-F-G-H-1.

11.4.

Impracticality of Compliance Component configuration:

Surface 1: Shell - Carbon steel Surface 2: Sampling Nozzles - Carbon steel Diameter: 1.00 in.

Thickness: 6.187 in.

This component was scanned manually with conventional methods. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Weld coverage using 45°, 60° & 70° shear waves for axial scans (S1, S2),

and 45° & 60° shear waves for circ. scans (CW, CCW) obtained 12.3%

coverage.

Base material coverage using 45°, 60° & 70° shear wave for axial scans (S1) and 45° & 60° shear waves for circ. scans (CW, CCW) obtained 49.3% coverage.

0° scan coverage obtained 29.1 % coverage.

The aggregate coverage was calculated to be (12.3% + 49.3% + 29.1 % )/3 = 30.2%.

The impracticality was caused by the weld taper configuration of the sampling nozzle to the shell that does not allow meaningful interrogation from Surface 2 nozzle side. In order to scan all of the required volume for this weld. The shell to sampling nozzle weld would have to be redesigned and replaced, which is impractical.

Page 20 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

No indications were recorded during this examination.

11.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

11.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

11.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 02.B3.110.0009 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

11.8.

References Duke Energy Relief Request 01-0N-001 was approved by the NRC during the last inspection interval. The previous approved SE is documented in Accession Number ML020840711, TAC No. MB1706 through MB1708 dated April 2, 2002.

Page 21 of31

Oconee Relief Request 15-0N-002 12.0 Weld# 2-PZR-WP26-2 12.1.

ASME Code Component(s) Affected Unit 2 Pressurizer Shell to Sampling Nozzle Weld, Reactor Coolant System, Weld # 2-PZR-WP26-2, Summary Number 02.B3.110.0010, and ASME Code Class 1.

12.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

12.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category 8-D, Item Number B3.110 Fig. IWB-2500-7 (a), 100% Volume Coverage of Examination Volume A-B-C-D-E-F-G-H-1.

12.4.

Impracticality of Compliance Component configuration:

Surface 1: Shell - Carbon steel Surface 2: Sampling Nozzles - Carbon steel Diameter: 1.00 in.

Thickness: 6.187 in.

This component was scanned manually with conventional methods. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Weld coverage using 45°, 60° & 70° shear waves for axial scans (S1, S2),

and 45° & 60° shear waves for circ. scans (CW, CCW) obtained 12.3%

coverage.

Base material coverage using 45°, 60° & 70° shear wave for axial scans (S1) and 45° & 60° shear waves for circ. scans (CW, CCW) obtained 49.3% coverage.

0° scan coverage obtained 29.1 % coverage.

The aggregate coverage was calculated to be (12.3% + 49.3% + 29.1%)/3 = 30.2%.

The impracticality was caused by the weld taper configuration of the sampling nozzle to the shell that does not allow meaningful interrogation from Surface 2 nozzle side. In order to scan all of the required volume for this weld. The shell to sampling nozzle weld would have to be redesigned and replaced, which is impractical.

Page 22 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

No indications were recorded during this examination.

12.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

12.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

12. 7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 02.B3.110.0010 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

12.8.

References Duke Energy Relief Request 01-0N-001 was approved by the NRC during the last inspection interval. The previous approved SE is documented in Accession Number ML020840711, TAC No. MB 1706 through MB 1708 dated April 2, 2002.

Page 23 of31

Oconee Relief Request 15-0N-002 13.0 Weld # 2-PZR-WP26-3 13.1.

ASME Code Component(s) Affected Unit 2 Pressurizer Shell to Sampling Nozzle Weld, Reactor Coolant System, Weld# 2-PZR-WP26-3, Summary Number 02.B3.110.0011, and ASME Code Class 1.

13.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

13.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-D, Item Number B3.110 Fig. IWB-2500-7 (a), 100% Volume Coverage of Examination Volume A-B-C-D-E-F-G-H-1.

13.4.

Impracticality of Compliance Component configuration:

Surface 1 : Shell - Carbon steel Surface 2: Sampling Nozzles - Carbon steel Diameter: 1.00 in.

Thickness: 6.187 in.

This component was scanned manually with conventional methods. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Weld coverage using 45° & 60° shear waves for axial scans (S1, S2),

and 45° & 60° shear waves for circ. scans (CW, CCW) obtained 15.4%

coverage..

Base material coverage using 45°, 60° & 70° shear wave for axial scans (S1) and 45° & 60° shear waves for circ. scans (CW, CCW) obtained 54.8% coverage.

0° scan coverage obtained 33.8% coverage.

The aggregate coverage was calculated to be (12.3% + 49.3% + 29.1%)/3 = 34.7%.

The impracticality was caused by the weld taper configuration of the sampling nozzle to the shell that does not allow meaningful interrogation from Surface 2 nozzle side. In order to scan all of the required volume for this weld. The shell to sampling nozzle weld would have to be redesigned and replaced, which is impractical.

Page 24 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

No indications were recorded during this examination.

13.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

13.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

13. 7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 02.B3.110.0011 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

13.8.

References Duke Energy Relief Request 01-0N-001 was approved by the NRC during the last inspection interval. The previous approved SE is documented in Accession Number ML020840711, TAC No. MB 1706 through MB 1708 dated April 2, 2002.

Page 25 of31

Oconee Relief Request 15-0N-002 14.0 Weld# 2-LDCB-IN-WJ33V 14.1.

ASME Code Component(s) Affected Unit 2 Letdown Cooler 2B, Nozzle to Channel Body Weld, Reactor Coolant System, Weld# 2-LDCB-IN-WJ33V, Summary Number 02.B3.150.0003, and ASME Code Class 1.

14.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

14.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-D, Item Number B3.150, Fig. IWB-2500-7(a),100% Volume Coverage of Examination Volume A-B-C-D-E-F-G-H-1.

14.4.

Impracticality of Compliance Component configuration:

Surface 1: Channel Body - Stainless steel Surface 2: Inlet Nozzle - Stainless steel Diameter: 6.00 in.

Thickness: 0.875 in.

This component was scanned manually with conventional methods. Scanning requirements are described in ASME Section XI, Appendix Ill, 111-4420 and 111-4430. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Axial scan coverage: 45° shear waves and 60° and 70° longitudinal waves in the S1 and S2 direction obtained an aggregate coverage of 41.0%.

Circumferential scan coverage: 45° shear waves obtained an aggregate coverage of 68.6%.

The total aggregate coverage was calculated to be

( 41.0% + 68.6% )/2 = 54.8%.

The impracticality was caused by the weld taper configuration of the inlet nozzle to the channel body that does not allow interrogation from Surface 2 the nozzle side. In order to scan all of the required volume for this weld. The channel body to inlet nozzle weld would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical.

The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

Page 26 of31

Oconee Relief Request 15-0N-002 No indications were recorded during this examination.

14.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

14.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

14.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 02.B3.150.0003 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

14.8.

References Duke Energy Relief Request 12-0N-002 was approved by the NRG on the PSI examination during the last inspection interval. The previous approved SE is documented in Accession Number ML13365A023, TAC No. MF0649 dated January 17, 2014.

Page 27 of31

Oconee Relief Request 15-0N-002 15.0 Weld# 2-LDCB-OUT-WJ36V 15.1.

ASME Code Component(s) Affected Unit 2 Letdown Cooler 2B, Nozzle to Channel Body Weld, Reactor Coolant System, Weld# 2-LDCB-OUT-WJ36V, Summary Number 02.B3.150.0004, and ASME Code Class 1.

15.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

15.3.

Applicable Code Requirement

IWB-2500, Table IWB-2500-1, Examination Category B-D, Item Number B3.150, Fig. IWB-2500-7 (a), 100% Volume Coverage of Examination Volume A-B-C-D-E-F-G-H-1.

15.4.

Impracticality of Compliance Component configuration:

Surface 1: Channel Body - Stainless steel Surface 2: Outlet Nozzle - Stainless steel Diameter: 6.00 in.

Thickness: 0.875 in.

This component was scanned manually with conventional methods. Scanning requirements are described in ASME Section XI, Appendix Ill, 111-4420 and 111-4430. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Axial scan coverage: 45° shear waves and 60° and 70° longitudinal waves in the S1 and S2 direction obtained an aggregate coverage of 41.0%.

Circumferential scan coverage: 45° shear waves obtained an aggregate coverage of 68.6%.

The total aggregate coverage was calculated to be (41.0% + 68.6%)/2 = 54.8%.

The impracticality was caused by the weld taper configuration of the inlet nozzle to the channel body that does not allow interrogation from Surface 2 the nozzle side. In order to scan all of the required volume for this weld. The channel body to inlet nozzle weld would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical.

Page 28 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. The achieved coverage did not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

No indications were recorded during this examination.

15.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated UT techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component configuration. The use of any other UT technique available would incur the same physical scanning limitations.

15.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

15.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 02.B3.150.0004 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each refueling outage in accordance with Table IWB-2500-1, Examination Category B-P requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring and Reactor Building process radiation monitoring contribute to ensuring pressure boundary integrity by providing means to detect reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

15.8.

References Duke Energy Relief Request 12-0N-002 was approved by the NRC on the PSI examination during the last inspection interval. The previous approved SE is documented in Accession Number ML13365A023, TAC No. MF0649 dated January 17, 2014.

Page 29 of31

Oconee Relief Request 15-0N-002 16.0 Weld # 2-SGB-W69 16.1.

ASME Code Component(s) Affected Unit 2 Steam Generator 2B, Upper Tube Sheet to Shell Can Weld, Feedwater System, Weld # 2-SGB-W69, Summary Number 02.C1.30.0001, and ASME Code Class 2.

16.2.

Applicable Code Edition and Addenda

ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.

16.3.

Applicable Code Requirement

IWC-2500, Table IWC-2500-1, Examination Category C-A, Item Number C1.30, Figure IWC-2500-2, 100% Volume Coverage of Examination Volume E-F-G-H.

16.4.

Impracticality of Compliance Component configuration:

Surface 1: Tube Sheet - Carbons Steel Surface 2: Shell - Carbon Steel Diameter: 148 in.

Thickness: 5.125 in.

This component was scanned manually with conventional methods. Scanning requirements are described in ASME Section V, Article 4, T-441.1.2(a), T-441.1.3, T-441.1.4, T-441.1.5 and T-441.1.6. These requirements describe and are specific to scanning components in two axial and two circumferential directions. This component was scanned to the extent possible to meet these requirements. The aggregate coverage that was obtained is described and calculated from the following:

Weld coverage using 35°, 45° & 60° shear waves for axial scans (S1, S2),

and 45° & 60° shear waves for circ. scans (CW, CCW) obtained 73.8%

coverage.

Base material coverage using 35°, 45° & 60° shear wave for axial scans (S1) and 45° & 60° shear waves for circ. scans (CW, CCW) obtained 78.4% coverage.

0° scan coverage obtained 73.1 % coverage.

The aggregate coverage was calculated to be (73.1 % + 73.8% + 78.4% )/3 = 75.1 %.

The impracticality was caused by four lateral restraints that did not allow scanning from the Surface 1, CW and CCW direction, and only partial scanning from the Surface 2 direction, as well as the location of two lifting trunnions and a manway which allowed only partial scanning from Surface 1. In order to scan all of the required volume for this weld, the lateral supports, lifting trunnions, and manway would have to be redesigned and replaced, which is impractical.

Page 30 of31

Oconee Relief Request 15-0N-002 The Oconee lnservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage. Therefore, the available coverage will not meet the acceptance criteria of this Code Case.

This relief request is specific to examination volume coverage limitations only. All other Code requirements were satisfied.

No indications were recorded during this examination.

16.5.

Proposed Alternative and Basis for Use No substitution alternative for this weld is available which would provide better coverage. Radiography (RT) is not a desired option because RT is limited in the ability to detect service induced flaws. Use of other manual or automated techniques, whether conventional or phased array, were considered, but would not increase coverage due to the limitation created by the component cast stainless material. The use of any other technique available would incur the same physical scanning limitations.

16.6.

Duration of Proposed Alternative This request is for the fourth inservice inspection interval. The interval ended on July 15, 2014.

16.7.

Justification for Granting Relief Ultrasonic examination of the weld for the item number 02.C1.30.0001was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition with the 2000 Addenda.

The system leakage test performed each period in accordance with Table IWC-2500-1, Examination Category C-H requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.

In addition to the above Code required examinations (volumetric and pressure test), Reactor Building Normal Sump monitoring contribute to ensuring pressure boundary integrity by providing means to detect feed water, steam or reactor coolant leakage and take prompt corrective actions.

Duke Energy has examined the weld to the maximum extent possible utilizing approved examination techniques and equipment. Based on the acceptable results for the coverage completed by the volumetric examination, the pressure testing (VT-2) examinations required by Section XI, and the leakage monitoring, it is Duke's position that the combination of examinations provides a reasonable assurance of quality and safety.

16. 8.

References None Page 31 of31

._~*

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to Relief ~equest 15.-0N-002 UT Detail Data sheets from

• lEOC-27 Limited Exam. Coverage

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AREVA Document No.: 51-9193316-000 Duke Energy I Oconee Unit 1 EOC27 RPV 10 Year ISi Final Report lnnu1ll1't:

OCONEE'.* UNIT<1 EXAMINATION COVERAGE FOR WELD: WU&

LOWER SHELL TO LOWER HEAD WELD S11mmuy Hwmber: 01.s1.11.aoo1 Compon.ntlD: 1*RPV.WR34

• sou Pl111Drawing1t11111b1ar:. 10&!8640. 81\\!1*, '2 & n WELD VOLUME COVERAGE OBTAINED: *43%

Zofie Coverage O~lned

• . lmert5'!1.T Outer85'!1.T 5674.8 cu. ill.

Llmltallons INNER15%T Aallll 8""m Dlnlcllon Co1lllnlga9

&1!111.

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f.

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Up/On a.OIL Tolll All.tat c-ra11*.

Clrr:umfllnlnllill Baent Dll9Cflon Co~*.

Exw:

• . AANI A¥ Be11111 Examined Entry I (f/flg.J Olm:l/on (sq. in.)

7 451.

I

.~

S 70l.J45l.. CWK:.CW

US. 72 OUTER 85% T Alllel Seim Citvl:tlon COWtllQllll E.am.

Anr;.

Enl!yl (Clag.)

2 3

45U45S UplDn 4Sl/4SS.

~

Total Allllll Co~twll*

Cimiml!ml11tial 8*aal Ol-"on Covengu Exem.

Aree Ang.

Exllnlined

)

(sq. Irr.

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Ex*milled Examined ;

(%)

(%)

.C5'1' 57%

T4*t Clrc. Btam Oltftlion Coverage; 1!1G.4 280.7..

aa.***

31%

~.4 0.0 8328.t 70%

6~

SS98.ll 124Ml.2 23937.1 Total Ciro. 811111 Dl~don C-111911; Yes Yes es Yes Nan*

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ATTACH

'I I

A OocumentNo.: 51-919331&,000 AREVA Ouke*Energy} Oconee Unit 1 EOC2l.RPV 10 YeatlSt Final Report Figure 1-2 TWS Weld W06: LOWER SHELL TO LOWER HEAD WElD View of TWS robOt in vessel lower head region showing scan limllations caused by the COfe Guide Lugs and FloW Stabilizers. Tile weld Is partially covered by the core Gulde Lugs. Flow Stabilizers welded to the head belOW the weld and the core Gulde Lugs restrid the u* head from scanning the entire weld. *tiese !imitations occur between each tug set. Single sided scan param-s are used near ob$1rudlons to improve examination coverage. Coverage obtained on this weld is 43%.

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AREVA Document No.: 51-9193316-000

• • r.***

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Duka Et,lergy /.Oconee Unit 1 f§OC27 ~PV 10 Year ISi Final Report OCONEE

• UNIT 1 EXAMINATION COVERAGE FOR WELD: W07 LOWER1HEAD'*TO LOWER HEAD DOME WELD

&11111mary Numb.,.: 01.S1.2Ullill1 *

• Compon*nl!O: 1-RPV.WIU.5 llos11 Plan Oniwlng Nllmbltr:.* BOSUMD ShHt 14 WELD VOLUME COVERAGE OBTAINED:' 36%

lone.Covorago Obtidnod IMor. 16'1.T:

o.itar MT:

37%

AQare111io:

• 36%

"'* aawnr111*nt1ul11! piano Inner 15,,.T S.77 sq. in, Outer 85'M>T 33.04 IQ; In.

Umlta OllS UlCDt1> 1nstrumentellan Nm:

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EJ<alll. *.,..

Ama

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Vfllllme *.. Vlllume Anpio e.xtJ11!1Md E.smlned Ewnlned Requimd

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(sq. in.J (m. *'

(cu.In.)

(t:U. in.J Pcn:ent fEx4mlned.

Um/led

• .~... *.~.

Comment*,....

. 7 100.11 S21l.

1 Co.anige -

llOZZle'*

S!llblfttetll..

3.28 1.07 4

UpiOn 0.00 To\\al 4Jllal co.. ra;e cthMf!f!mmlcl Bum lJlnrotliln Covmon Ei4Jn,;

A11tt1 Entry II s

6 CWICCW 20.16

• . 7 CWICCW

• 10.08 OUTERB5%T ArW Dnm.OlrNt/011 Co~

E*am.

Atoe Angle Beam Eromlned EnlryO

. )

CYIVClion fS

• ln.J 451.14 On 33.04 45U4SS Up/On 26.96 3

4SLJ4SS Up/On 17.01 4

45U4SS 4Jl0n 0.00 Toi.I Alllal Connio*

Circurnflln>ll!ial Bnm Olroodon ColllH'QflM Exam.

Ams.

Angis E1'tlllfin1Jd

('20'].

(:iq, /n.J 4

~ s 6

6 45U4SS OIVICCW

!41.84 7

4SLJ~SS CWICCW 70.92 34.)

1 S'llo smi.

l%

4Z%

Total Cite. l!IHm Olr*~Uon Covons1e:

/nMr 7~ O'OW f.Bnglb Volumv ExlJllWned EX1Jl'll/ned 1138.0

m.t IJIJ27.7 14843.1 Cite Extent Eumlned I

1 6%

81'16 3%

39%

Total Cira. seem Olt'llcttGil CoY<tnigo:

OutwllSKo 51%

tll'!I..*

O'lf.'/.

41'\\I; Potr:enl E.amlned 4'16 1%

26%

PelCl!Jlt EtlllnJnoct tWi' 68%

54'11.

O'!!.

44" Pere<rnl E*BJFrirrot:t 2

4%

11' 3Q'lr, 37%

Yes Yes Yes umttfKI es Vas Yes Umifo<I..

No' Ya Yes Yes Umitlld Yes Yes ColGllllO ahaw mUI~ 45 t1l1d 52 c.,...,,....obc>'.enoule46 OIJslruChld comment Gowtall(l noutes e.nd stalillzoni

~

Elbow nou!Os 45 Md 5Z

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sbo<a noule '1CI*

Common!

~

betWaen noule& B!ldal -

c:wnoe allole noum 46 and 52 CoUll'al)Q tlboll) noul9 "8 Obsfluded Contt*ll*nt ae berv.een nozztss and stlllli!lim Cowmge aboie llOZZ!ml.45 Sid 52 Ca>etuga abolo nazzle 46 UUCUUlt 1au3 ut

A AREVA Document No.: 51-9193316--000 Duke Energy I Ooonee Unit 1 EOC27 RPV 10 Year ISi Final Report Figure 1-3 TWS Weld W07: LOWER SHEU TO LOWER HEAD WELD View of TWS robot in vessel lower head region showing scan limitations caused by the lncore Nozzles and Flow Stabilizers. The weld is partially covered by the Flow Stabilizers. Flow Stabilizers welded to the head above the weld and the lncore Nozzles restrict the UT head from scanning the entire weld. The Core Guide Lugs also provide some interference with robot movement. These limitations occur between each Flow Stabilizer/Core Guide Lug set.

Single-sided scan parameters are used near obstructions to improve examination coverage.

Coverage obtained on this weld is 36%.

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Oconee 1

'*'> Procedure:

'-NDE-3830 Outag& No.:

OM!7

~-~---------~

Summary No.:

01.B2.51.0003 Procedure Rev.:

2 Repost No.:

UT-12*1059.*

Workscope:

181 Work Order No.:

1992022 Pago:

1 of 13 Code:

1998/2000A

• • CaUl.tem:

• Leceilon:

-.:¥:

Drawing No.:

0-1$1N4o101A*1.1

==

Description:==

Head to Head System ID:

S1A

~---~--------------------,----~-----------~---------------

Com pone nt 10: 1 LDCS.INLET SiZell..ength:

• • . NIA Thlckness/OlamGter:

SS I.875 f NA

~~--*-

Yes - See ettached sheets Start Time:

0821 Flnlsh Tline:

0835 Umllatlons:

lnslrurnent Settings Sean:h Unit Cal.

• / **';

• Altlal Orientated So11rch Unit*

Time Dllte Serial No.:

0265P4 Serial No.:

01F3J5 Checks Callbrallon Signal Sweep Manufac:turar:

GE Manufacturer.

KBA lnlllal Cal 0807 1117/2012 Refteetor Amplitude%

OMslon SoundPalh M~el:

USN80SW Size:

.25 Shape:

Round Inter. Cal.

~-.*

NIA Delay:

4.1050 Range:

2.s*

Freq.:

2.25MHz Style:

comp*G lntur. Cal.

0820 11n12012 M'U CallVel:

.1280 Pulser:

Square exam Anglo:

45

1. of Elements: Slngl.t lnter>Cal.

C*

Damping:

soo Reject:

fl%

Mode:

Shear Final Cal 1000 11m2012 Rep. Rate:

Autohlgh Freq.;

2.25MHz C~uplant Measured Angle:

45 Filler.

FIIad Mode:

PE Wed911 Style:

MSWQC Cal. Balch:

12125

• Clrcumterentlol Otlontated Sear? Unit

• Vollage:

'50 Other.

Full_..,.

Type:

ULTRAGELll Calibration Slgnst Sweep Ax. Gain (dB):

NIA Clrc. Gain (dB):

38.0 Search Unit Cable Mfg.:

MAGNAFLUX

. Reftedior Amplitude '14 Division SO\\J!ld Path 1

SaeenOIY.::

.25 In.of Sound Path Type:

RG.114 Exolm Batch *..

12125 ID Natch 80 5.3 1.35" Length:

6' No.Conn.:

0 Unearlty Report No.:

L-12*225 Type:

ULTRAGELll fi'.

,.*Y/

Callbn.rtlon Block Scan Covenee..

Mfg.:

MAGNAFLUX Cal. Block No.

40411 Upstream O Downstream O Sean dB:~

Referttnce Block Ret.reneelSlmulator Diode Thickness 0.875 Ola.:

8.75 cwi;a CCW i;a $c:an dB: 52.0 Gain Slgilal

• Sweap Sound Path

-:-- Serial No.:

117-5590 dB Refl~r Am11lltude%

Division Cal. 811<. Temp.

84 Temp. Tool:

MCNDE40129 Exam Surface:

O.D.

Type:

ROM PAS 2'9Radlus 8.0 29.0 80 2.00" Comp. Temp.

60 remp. Tool:

MCNDE40129 Surface Condition:

As Ground Recordable lndlcatlon(e):

YHO No~

(If Yes. Raf. Attached Ultrasonic Indication Report.)

/,.*;

Results:

Accept 0 Reject !i!J Info Q Comments: FC 11.16 Reviewed Previous Dsta:

Y1111

UT Calibrationi~minatlon SitelUnit:

Oconee 1

Procedure:

NOE-3630 Outage No.:

01.27

• Summary No.:

01.B2.S1.0003 Procedwe Rev.:

2 Report No.:

UT-12*1059

---

~

Wortuu:ope:

ISi Work prder No.:

1992022 Page:

2 o(

13 Code:

1998/2000A CatJltem:

. ** B*B JB2.S1.

Loc811oii:

Orawlng No.:

0.fSIN4-101A-1.1 OescripUon: Hud to Heed System 10:

51A

---

~--------------------------------------------------------------~----~------------------~---

Compo nan t ID: 1LDCB.,NLET Size/Length:

NIA Thlc:kness/Dfamster:

SS f.875 /NA

---

~---------------~~~------------------~---------

S~rt Time:

• *0 9~1

• Fl~lsh Time:

• 0850 *x um ltallons:

Yes* Sea attached sheets Instrument Settings Serial No.:

0285P4 Manufacturer:

GE Model:

USN SO SW Delay:

4.1050 Range:

4.s*

M'UCaWel:

.1280 Pulser:

Squaro Camping:

SOD Reject:

0%

Rep. Rate:

Autohlgh Freq.:

2.25MHz Filter:

Fil:ed Mode:

PE Voltage:

~o Olher:

Fullwave Ax. Gain {dB):

26.7 Circ. Gain (dB):

NIA 1

Screen Div.=

.45 In. of Sound Peth Linearity Report No.:

L*12-225 Calibration Blin:k Cal. Block No.

40411 Thickness 0.875 Ola.:

8.75 C&l. Blk. Temp.

84 Temp. Tool:

MCHDE40129 Camp. Temp......!!.. Temp. Tool:

MCNOE40129 Recordable lndlc:atlon(o):

Yesb!j NoO Acc:ept 0 Examiner Level Griebel, David M.

Examiner Level Bull, W. Keith Other NIA Level Search Unit Cal.

Time Date Serial No.:

01F3J5 Checks Manufacturer:

KBA lnitlalCal 0800 111712012 Slze:

.25 Shape:*.*.

Round Inter. CSI.

Freq.:

2.2SMHZ

• .Style:

comp*G lnter:ca1.

0836 11n12012 Exam Angla:

45

1. of Elements: Slngle Inter. ca1.

Mode:

Shear F!na1ca1 1005 1117/%012 Measured Angle:

45 Covplant Wedge Styte:

MSWQC' Cal. Balch:

12125 Type:

. Ut TRAGEL II Sean:h Unit Cable Mfg.:

MAGNAFLUX Type:

RO *174 Exam eatdt 12125 Length:

8' No. Conn.:

0 Type:

ULTRAGELll

• Scan Caverage.,

M~::

MAGNAl'LUX Upslleam li2iJ Oownslr88m QI SC81'1 dB: ~

Raf9nlnc:t1 Block

• cwo CCW0 Scan dB: NIA S l1 IN..

ea o..

97-4590 E>Cllm Surface:

O.D.

Type:

ROMPAS Surface CandlUon:

A*Gtound

{Ir Vos, Ref. Attached Ultrasonic indication Report.)

Into 0 Yes Data Revlewer-111712012 ~~e:~ a: fl~'blc Ill

• Date Site Review 11m2012

• Axial Orlontated Search Unit Callbrallon Signal Sweep Sound Path Reftector.

Amplitude%

Division IDNotc:ll eo*.*

. 2.7 1.18" OD Notch 40

.*, f'i. s.*

'ur IOHotch 20 8.2 3.Gr Clr!lumfe,.ntlal Orlen~ Search Unit..

• Calibration*

Signal.

• Sweep/~; Sound'~ai?i Reflector Amplibide%

Division.'* "\\:::-,

NIA

~

~

~., :-

-~>

• • 1<.

Referonce/Slmulator Block Gain Signal

'Swe111>

Sound Patti dB Reflector Am11lltude% Division 21.7 Z-Radlua 80 4.S 2.00*

..:rf.b<._

UT Calibrationilamination Site/Unit:

0(:Qneo 1

Pn:>CGdUf'll:

NDE-3830

~utege No.:

01*27 Summary No.:

01.82.51~0003 Procedure Rev.:

2

• • -=:--,..,.

Re po it No.;

UT-12*1059

~-----------~

Wolliscope:

ISJ Wo111 Oilier No.:

1992022.

Page:.;:;. :f of 13.

Code:

189812000A 8-6 /BU1 Drawing No.:

0-ISIN4-101A-1.1

==

Description:==

Head to Head System ID:

51A

---

~-----------~--~

Component 10: 11.DCIMNLET Size/Length:

NIA ThicknesSJolameter:.. SS I.875 fNA LlmltaUons:

Yu

• See attac:hed ah11t11ta Start Tlme:

0852 AnlshTlme:

osos

• **sean:tl Unit '

$$rial No.:

03-794 1na'1\\llnant Settings Serial No.:

0285P4

• *** Cel.

Time Date CheciluJ Manufacturer.

GE Ma nufa cbJ ra r..

RTO Initial Cal 0810 11ii12G12 S lze:

2(71110)

Model:

USN 60 SW Inter. Cat.

Shape:

Rec:L Delay:

8.9147 Fn1q.:

2.0 MHZ Style:

TRL2 Inter. Cal.

0851 111712012 M'U CaWel:

.2293

--......:-..-..;...-- Exam Angle:

45

1. of Elamen1$: Dual Long.

Inter. Cal.

Fina1Ca1 1007 11m2012 Damping:

500 Mode:

Rep. Rate:

Autohlgh

---

Messurad Angle: ____ 45 Couplant cat. Boteh:

12125 Type:

ULTRAGELll FIA*d

---

Wedge Style: ____

1n_t....

eg0:-,ra_1 ___ _

451)

Other:

FullweYD Filter:

Voltage:

MAGNAFl..UX f'dfg.:

s1...;..o __ Clrc. Gain (~8):

NIA AJt.. Gain (dB):

Soerch Unit Cable 1

Saven Div.=

.25 In. of Sound Path Type:

RG

• 174 Exam Batch 12125 Linearity Report No.:

l*12-225 Length:

r No.Corin::~ __ o __ Type:

ULTRAGELll CallbraUon Block Scan CC>¥DflllJ9

r.ffg.:

MAGNAFLUX Cal. Block No. ______

4_D4_1_1 ______ Upstream 6!j Downstream 0 Scan dB: 53.0 Rorontnco Block Thlcknsas __ o_.a_1_s__

Dia.: ___ e_.1_s___

cw D ccw 0 Scan dB:~* Serlat No.:

97"5~

Cal. Bill. Temp.

84 Temp. Tool: __

M_C_N_D_E_40_129 __ Eiram SUl'face:

O.D.

Type:

ROMPAS Comp. Temp.

60 Temp. Toal:

MCNDE40129 Rocordable lndlcatlon{s):

Yes fi!l No O SUl'face Condilian:

As Ground (If Yes, Raf. Attached UltraSonlc lndlcallon Report.)

Axial Orientated Search Unit

• .* CaDbratlon

• '. Signal S~

• • Refleclor Amplitude %

Division Sound Paltl ID Notch 80 4.9 Clrcumferentlal Orientated Search Unit Cellbrallon Reflector

'i;.

NIA'...

Signal Amplitude %

Sweep Division Reference/Sltnutator Bloc:ll Sound Patti Gain *

..

• 8 ; Slgnal

• Sweep Sol.ind.Path dB Reflector AinoDlilde 'JI. OMillon 22.8 2" Radius 80 8.0 2.00*

Results:

Accept O Raj&ct ~

Info Q Comment&: FC 11*16 Scanning d8 lowared to maintain a 2:1 elgnal to nolae rstJo

• ~

Percent Of Coverage Obtained > 90%:

Dara:

Vee Examiner Level 11-H Date Reviewer Dale Grlsbal, David M.

111112012 i]N1E'.. J. /1 '-A£li LE' /II

//-/()-/L-Examiner Leval Date Site Rellfew

~oate

UT Calibratf on mi nation Site/Unit:

Oconee 1

Procedure:**..

• . '(

NDE-3630

---

~

Oumga No.:,.

01*27 Summary No.:

01.82.51.0003 P roced U 19 Rev.:

2 Report No.:

UT-12-1059

---

~

Workscope:

ISi

. Work Ol'dar No.:

• 1"2022 *>

' r~~e: ~

of

.13 Code:

199B/2000A Cat/Item:

B-8 /.2.51 Location:

Drawing No.:

~SIN4-101A-1.1

==

Description:==

Head,;Hiiad

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

System ID:

51A Com pone n I 10: 1LDCB*INLET

---

~----------~

.*SlmfLenutt::

NIA Thlcknesa/Olameter.

SS I \\&TS., NA

• "\\.

0920

• ~*,

Limitations:

Yea

• See attached sheets Instrument Setting*

Serial No.:

0285P4 Manufactunir:

GE Model:

USN80SW Coley:

8.0128 Range:

4.oo*

M'UCal/Vol:

.2196 PUl68r:

Square Damping:

500 Reject:

0%

Rep.Rate:

Autohlgh Fniq.:

2M~

Fiiter.

Fbied Mode:

Duaf Voltage; 450 Other:

Fullwave AM.. Gain (dS):

45.3 Cite. Gain (dS):

NIA 1

Seteen Div. = *"

In. of Sound Path Unaanty Report No.:

L*12*2215 Callbratlon Block Cal. Block No.

40411 Thickness 0.875 Ola.:

8.75 Cal. Blk. Tomp.

84 Temp. Tool:

MCNDE.40129 Comp. Temp.

80 Temp. Tool:

MCNDE40129 Recordable lndlcatlon(a):

Yes O No li2I ResullS:

Accept Q Reject 6!JI Percent Of Coverage Obtained > 90%:

Examiner Level 11-N Griebel, David M.

Examiner Level 11-N Bull,W.Kolth Other NIA Level NIA Ho Start Time:

0907 Finish Time:

' $ean;h Unit

.~"::

Cal.

Time

'Data

. ~lal Orientated SHtch Un!t

• • ~

Cheella Serielj'lfo.:

Ol-788 Calibration Slgrwl

• SWeep :*

Initial Cal 0813 11"12012 Sound Path Manufacturer.

RTDx Rellaccor Amplitude 'If.

Division

• "'p:

Size:

Inter. Cal.

'--'iv, 2(7a10)

Shape:

Rect.

IDNotcli

80.

5.0 u2*

Freq.:

2.0MHZ Style:

TRL2 Inter. Cal.

0908 11m2012 Exam Anglo:

1. ot Elements: Dual Inter. Cal. '

• ">t 60

~;t-,

Final Cal 1012 111712012

• \\

Mode:

Long.

Meaaured Angle:

60 gouplent..,,.

c1rcumf9rent1111 Ortentat\\!d Sean:~ Unit Wedge Style:

Integral Cal. Saleh:

12125 Type:

ULTRAGELll Callbratlon Signal "Sweep Sound Path

.: MAGNAFi..UX

~elleetor ;*

Amplltu~'I!.

Dlvlslqn Sean;h Unit Cable Mfg.:

Y<NIA

""Y

• -,h***'

Type:

RG

• 17<4 Elcsm Batch 12125 Length:

e-No.Conn.:*

0 l~:

ULTRAGl!L 11 **

.. \\t, Scan Coverage Mfg.;

.MAGNAFLUX Upstream ~

Downstream fa Scan dB: ~

Refannoe Block 1::-;_;:._

Reforence/SlmuiStor Block cwo CCW 0 Seen dB: ~

Serial No.:

Gain Signal Sweep

, --~.;~.

97*SS90 cfB Rellector AmpllliJde% Division Sound Path Exam Surface; O.D.

Type:

ROMPAS 26;6 2*Rad1ua 80 s.o 2.00*

Surface Condition:

As Ground

., ;: *"" ~:

(If Yea, Rel. Attadled Ull.r8&onlc Indication Report.)

Info O Comments: FC 11-16

~'

Reviewed Pravious Data:

'~.

Yell Date

• Re...WWW 1117'2012 ::1i, l'fE~J". t1 c.A-te>ls /I(

Date Site Review 1117/2012

• • Oatii Scanning dB 1-en1d to maintain a 2:1 algnal to noise ratio

UT Calibratio mi nation Sits/Unit:

Oconee

• Procedure:

HDE-3630

.;\\

Outsge No.:

01*2T Summary No.:

01.82.51.0003 ProoedUl8 Rev.:

2 Report No.:

UT*12*1059

~~~~~~~~~~~~~

Woril.scope:

ISi Worll Order No.:

1992022 Paga:

5 ot 13 Code:

199812000A CalJltem:

a.a 182.51 Location:

Drawing No.:

O-ISIN4-101A-1.1 Desetlptlon: Heed to Head System ID:

51A

---~~---------------~------~-----------------~-------~-----------~~--------~----------------------------~~~------~---

Compo n en l 10: 1LDCB-INLET Slza/Lenglh:

' N/A ThleknessJDlemeter.

SS I.8751 NA

~~~~---------~~~~---------~~------~------~---~~~-------------

~--~~~---

li ml tall ona:

Yee

• See attached eheeta Start Time:

0922 Finish Time:

0937 Instrument S.ttinga Serial No.:

02S5P4 Manufacturer:

GE Model:

USN80SW Delay; 7.3091 Range:

s.oo*

M't!Cal/Val:

.~66 Pulser:

Square Dampl119:

500 Re Jed:

0%

Rep. Rate:

Autohlgh Freq.:

2MH1:

Filter:

Fixed Mode:

Dual Voltage:

450 Olher:

Fullwaw Ar.. Gain {dB):

42.3 Ctrc. Gain (dB):

NIA 1

SauenOlv. =

.5 in.of Sound Path Unaarity Report No.:

L*12*225 CallbratiOll Block cat. Bloc:k No.

411411 Thickness 0.875 Dia.:

8.75 Cal. Bile. Temp.

84 Temp. Tool:

MCNDE40129 Comp. Temp.

60 Temp. Tool:

MCNDE40121 Recordable lndlcatlon(a):

Yes~

NoO Resulls:

Accept O Rejed 0 Perc:ent Of Coverage Obtained > 90%:

No Examiner l.aval II.ff Grte!Mll, David M.

Examiner Level If.ti Bull, W. Keith Olher Level NIA NIA Search Unit

• .='*L Cal.*,

Time Data

..... AxlSI Orientated Sean:h Unit

• Serial No.:

03-TT1 Checks CaBbrntion S!gnal Sweep Manufacturer:

RTD Initial Cal 0815 11"12012 Refledor Ampllrude'l!i Division Sound Path Size:

Z(7x10)

Shape:*.

Rect.

Inter. Cal.

ID Notch 80 5.0 2.SO"

11"12012 F111q.:

2.0MHZ Style:

TRL2 Inter. Cal. 0921 Exam Angle:

70

1. of EIBmenta: Dual Inter. Cal.

Final Cal 1015 11"12012 Mode:

Long.

Couplant:*

~*

Measured Angle:

70 Clrcwnfarentlal Ortontiited Se11rch Uqlt Wedge Style:

lntegnil Cal. fletch:

12125 Type:

ULTRAGEL.11 Callbnltlon Signal s-p Sound Path Searc:h Unit Ca!)le Mfg.:

MAGNAFLUX Raflec:lcr

~mplltude%

Division Type:

RO *174 Exam Batc:h

12125

.. NIA Length:

e*

No.Conn.:

0 Type:

ULTRAGELll Sc:en Coverage Mfg.:

MAGNAFLUX Upstream ~ Oownstniarn fiZJ Sc:an dB: ~

Reference Block R11fllronce.ISlmu1otor Bloc:k cwo CCW O Scan dB: NIA Serial No.:

87-590 Gain Signal Sweep SoundPalh dB Refledor Amplllud8% OIYlalon ElC&m Surface:

O.D.

Type:

ROM PAS 30.6 2*Radlua 80 4.0 z.oo*

Surface Condition:

Ail Ground (II Yes. Ref. Attached Ultrasonic lndlcaUon Report.)

Info 0 Reviewed Prevl.ous Data:

Yes Date 11n12012 Date Sita RaYlew 11"12012 oate Comments: FC 11*18 Scanning dB lowered to maintain a 2:1 elgnal to noise ratio Date 103.v.-l--.*

DUKE POWER COMPANY ISi LIMITATION REPORT ComponentJWeld ID: WJ-32

~ NOSCAN 0 LIMITED SCAN FROM L 0+3" to L 0-3" ANGLE:

0 0 12$3 45

~ 60 D NOSCAN r8I LIMITED SCAN FROM l N/A to L NIA ANGLE:

0 O 181 4!)

~ 60 0 NOSCAN 0 LIMITED SCAN FROM L to L Item No:

01.82.51.0003 SURFACE BEAM DIRECTION r81 1 D 2 181 1 rE1 2 r81 C\\Y ~ ccw INCHES FROM WO CL +1.1 to Beyond

~.,

other 70'*,

FROM 0 DEG to 360' *DEG

)

SURFACE BEAM DIRECTION 0 1

~ 2 1:81 1 r8I 2 ~cw r8I ccw INCHES FROM-WO

+0.6 to +1.5 other 70 FROM 0 DEG to 360

• DEG BEAM DIRECTION SURFACE D 1 D 2 0 1 D 2 D cw D.;CCW INCHES FROM WO to ANGLE:

0 0 0 45 0 60 other FROM 0 E Gt o DEG 0

NOSCAN BEAM DIRECTION remarks:

• . No scan due to nozzle & taper "h*

on chemical connector/..

0 LIMITED SCAN SURFACE D 1 D 2 0 1 D 2 D cw o, ccw UT-12-1059 FROM L INCHES FROM WO to Sketch(s) attached ANGLE:

0 O 0 FROM DEG to DEG l8I yes 0

No

Summary No.: 01.82.51.0003 Examiner: Griebel, David M.

Examiner: Bull W. Keith Other:..;N,;,;;/A;.;_ _____

Comments: Weld WJ-32 0-

.. Suppleme'l~I Report Level:

11-N Level:

11-N "i Level:~

Ind. # 1, 2 & 4 are root geometry. Ind. 0 3 Is a geometric reflector from offset on the I. D. aurface.

Sketch or Photo:

52..

~H'.£,?J.1-eAL.

~,t;,,V.Ne-tt:. ?'Z:>A:?'

51 Report No.:

UT*12*1059 Page:

7 of 13

, : ;*.:. ~...

Let Down Cooler.. Chemical Connector to Channel Body 0k coverilge Calculations Weld No. :

WJ-32*

0 =

8.625" 11f' =

0.875 11 Weld Length =

27.1" Total Inspection Area= < 2.28 sq. in.

% Length Limited due toriozzfe = s* 121.1~ x 100 = 22.1%

Aggregate Coverage Calculation > <

Axial Scans*

22~ 1 % of length x 96.5% of the volume of length / 1 OD = 21.3%

77.9% of length x 97.4%*of the volume of length 1100 = 75.9%

Aggregate coverage Axial scans= 21.1 + 75.9 = 97:2".4 Circ. Scans.

100% of length x 78.1 % of the volume of length / 100 = 78.1%

Total= (97.2 + 78.1) / 2 = 87.7% Aggregate Coverage Page if of JJ

tdown Cooler Chemi~

• co,J.~ ector to Channel l3ody Total EXamArea Weld No. :

WJ-32 Item No. :

NIA Tube Sheet-S2 Channel~ - Sl Scale: I" = 1.,

}~...

Weld No. :

WJ-32 Item No. :

NIA

=Area ~ot Examined= 0.05 + 0.01 = 0.06 sq. in.

~.:

=Area Examined= 2.2a. - 0.0612.28 ?C JOO= 97.~%

. : <*;*\\.* _":.

Tube Sheet - 82

. t_."'.

~~1}1oor-s1 70° Scale: l" = 1" l~

'. /"

"-t":':

• ~

~down Cooler Chemicaj Co1'"'_,ect9f to (hannel Body Area Examined.@Nozzle -Axial Scans Weld No. :

WJ-32

. item N~. :., NIA*..:z.

=~

~ *..

=Area Not Examined= 0.05 + 0.01 + 0.02 = 0.08 sq. in.

Noz:zle

=Area Examined= 2.28 - 0.08 / 2.28 x 100 = 96.5%

.:;_{:

=:._.-j 70° 45° 45~ µ 700 Tube Sheet - 82

.. j*

Channel Body - Sl Scale: 1" = 1"

• .. */*..

~ ':*

• ~tdown Cooler Chemiqal Cp1_:;.ector.tg Ch~el ~~Y Area Examined - Circ. SCan -

Item No. : _-.::.N..:;.::./A-=---

Weld No. :

WJ-32

=Area Not Examined= 0.5 sq. in.

• I J =AreaExamined= 228-0.S/2.28x 100=7~.1%

Channel Body-St Tube Sheet~ S2 45° 45° Scale: 1" = 1"

~

~

ti:~:.

~

SlteJUnit:

Oconee 1

Ultrase>11ic lndic~tion Report

• .(

Procedure:

NDE-3630 Outage No.:

01*27

~--------------~

Summary No.:

01.82.51.0003 Workscope:

Search Unit Angle:

45 & 70 o

Wo Location:

Weld Centerllno Lo Localion:

9.1.1.1 MP Metal Path RBR Remaining Back Reflection l

Distance From Datum Comments:

Weld WJ

• 32 lndi~tton

'Ma w

Angle No.

Of Max OAC w

MP S1 1-45" 90 1.5 2.14 S2 2-45° 85 0.9 1.20 S3 3-70° 55 0.9 NIA S4 4-45\\.

80 0.9 1.20 Examiner Level Griebel, David M.

ISi Wmax W1 W2 Forward Of Mall'.

W1 MP NIA NIA NIA NIA NIA NIA NIA NIA Procedure Rev.:

2 Wo~ Order No.:

1912022..,

Q Piping We!ds 0 Ferrltic yessels ? 2"T

@ Other Vessels < 2"T Distance From Wo To S.\\J. At Maximu!Tl Response pislance From Wo At Of Max {Fotward}

Distance From Wo At Of Max (Forward)

Backward L1 L

L2 RSR Of Max Of Max Of Amp.

W2 MP Max

Max NIA NIA 380° 0-1*

.INT N/A.

NIA NJA 38°'7 0+1*

INT NIA NIA

'NJA 380" o+e*

INT NIA NIA NIA 3eo*

0+1*

INT NIA Examiner Level ll*N ~

~

Sinn"'",...

Bull, W. Keith

- c __. l

-~ ~

Other Level NIA

/

Signature N/A Re po rt No.: __

u_T-_1_2-_1_o_s9 __

P15ge:

13

• or + 13

-~

Wo' Wma:

CL I.

WI W2

• .. !'*~/

Remarks Root geometry Root 88°'1'."Btry Root geometry Date

/(-/Z--/?_ *

.. Date Date

/ / /f 3/1.;L-

~ ;->-.

UT CalibratiorJ~mination Site/Unit:

Oconee 1

Procedure:

NDE*3830 Outage No.:

01-27

~-------------------

Summary No.:

01.B2.51.000-4 Procedure Rev.:

2 Report No.:

UT~12.1oeo

~-------------------~

Workacope:

ISi Work Order No.:

Page:

1

• .of 13 Code:

199812000A Catlltem:

B-B 182.51

• Location:

Drawing No.:

O~SIN4-101A*1.1 Oesctlptlon: Hoed to Hoed System ID:

51A --------------------------------------------------------------------------

Component ID: 1LDCB-OUT1.ET Limitations:

Yes

• soo 11tteched aheete lnetnnnent Settings Serlal No.:

0265P4 Manufacturer.

GE Modet USN GOSW Delay.

4.1050 Range:

2,5*

M'tlCaVVel:

.1280 Pulser.

Square Damping:

500 Rllfect:

0%

Rep. Rate:

Autohlgh Freq.:

2.2SM.U Fiiler.

Fixed Mode:

PE Voltage:

450 Other:

Fullweve Ax. Gain (dB):

NIA Clrc. Gain (dB):

38.0 1

Screen Div.=

.25 In. of Sound Path Uneartty Report No.:

L-12-225 Calibration Block Cal. Block No.

40411 Thickness 0.875 Dia.:

8.75 Cal. Blk. Temp.

64 Temp. Tool:

MCNOE40129 Comp. Temp.

60 Temp. Tool:

MCNOE40129 Recordable lndlcatlon(<<I):

Yes O No li2J Results:

Accept O Reject~

Pen:ent Of Coverage Obtained "'90%:

No Examiner Level ll*N Griebel, David M.

Examiner Level ll*N

.Bull, W. Keith Level NIA Size/Length:

NIA Thlckness/Olam.eter.

SS I.8151 NA Start Time:

0821 Finish Time:

0835 S.an:h Unit Cal.

~la! Orientated Search Unit

~' :**;v Tlmo Dm Serial No.:

01F3J5 Cheeks Calibration Signal Sweep Manufacturer:

KBA lnltlal Car 0807 111712012 ROllactor Amplitude%

Division Scund Path Size:

.25 Shape:

Round lntar. Cat.

NIA Fraq.:

2.25MHz Style:

Comp*O Inter. Cal.

0820 11nl2012 E118m Angle:

45

1. of Elements: Single Inter. Cel.

<. :s, ::.

~.. :

Mode:

Shear

/,:"

Final Cal 1000 1117/2012 Musured Angle:

45 Couplant Wedge Style:

MSWQc**

cat. Batch:

12125 Clrcumferontlal Orientated Search Unit Type:

ULTRAGELll Callbrallon Signal Sweep

Search Unit Cable Mfg.:

MAGNAFLUX

• • Reflector Amplitude 'Mt Division Sound Path T)'P&:

RG -174 Exam Batch 12125 ID Notch 80 5.3 us*

Length:

6' No.Conn.:

0 Type:

ULTRAGELll Scan Coverage Mfg.:

MAGNAFLUX Upstream O Oownslnlam O Scan dB: ~

Reference Block RllferencelSlmulator Blodc cw li2I CCW ~ Scan dB: 52.0 Serial No.:

97-5590 Galn Slgnal Sweep Sound Patti dB Reflactor Am11litude% Division Exam Surface:

O.D.

Type:

ROMPAS 80 2.00*

29.0 2" Radius 8.0 Surface Condltlcn:

AaGround (If Yes* Ref. Attached Ultrasonic lndltalion Report.)

=~

Info O Comments: FC 11*16 RG\\'iewed Previous Data:

Yes Date Re~ewer 11m2012 3ftMe$.J.

Data Site Review 111712012 Date

UT Calibratlo mi nation Site/Unit:

Oconee 1

Ptocedure:

NDE-3830 Outage No.:

• 01-27 '.;

Summary No.:

01.82.51.0004 Procedum Rev,:

2 Report No.:

UT*12*1080 W o ita c:.o pe:

ISi Worll Order No.:

1992022 Page:

2 of 13 Coda:

199812000A CatJltem:

a-a 1e2.s1 Location:

Drawing No.:

O-'SIN4-101A-1.1 Descdplion: Head to Head System ID:

51A

---

~-------------~---~----~-~-----------

CO m pone n t 10: 1 LDCB..OUTLET Size/Length:

NIA Thlckneas/Dlametef:

SS I.876 i NA Umllalions:

Yes

• See attached sheets Start Tima:

0837 Finish Time:

0850 Instrument SsttJnge Sean:h Unit *.

Cal.

• Date "Axlal Orlontatad Sean:h Unit T

Time Serial No.;

0265P4 Serial No.:

01f3J5 Checks CaUbraUon Signal Sweep Manufacturer.

GE Manufacturer:

KBA Initial Cal 0800 111712012 Reflector Amplitude%

Dl'll$1on Sound Peth Model:

USN80SW Intel'. Cat.

80 2~7 Size:

.25 Shape:

Round.

ID Notch 1.1e-Delay:

4.1050 Range:

4.5" Freq.:

2.25MHz Style:

Comp-*G Inter. c81.

0838 11m2012 OD Not<:h 40 SA 2.43*

M'tlCalNel:

.1280 Pulser:

Square Exam Angle:

45

1. of Elements: Single Inter. Cal.

tDNotc:h 20 8.2 3.69" Damping{

500 Reject:

0%

Mode:

shear FlnaJCal 100I 11"12012 Freq.:

2.25MH:i:

Measured Angle:

~-

Couplant>,

• Rep. Ra~e:

Auto high 45

. -~~

Filter:

Fixed Mode:

PE Wedge Style:

MSW QC Cal. Balch:

12125 Clrcumfentntlaf Orhlntated Sean:h Unit*,,

Voltago:

450 Other:

Futlwave Type:

ULTRAGEL II Calibration

$1gne1 heep

!Sound Path Ax. Gain (dB):

28.7 Cin:. G~ln (dB):

NIA Search Unit Cable Mfg.:

MAGHAFLUX

< :-~

Refleclor, AmpUIUde %

Dlvlslan 1

.45 Sound Path RG

• 174

,. NIA

..w*

Sc:teen Div. =

In. of Type:

EK.am 6alCl1

• . '"12125

._....,,:z'.**

Unear1ty Report No.:

L*12*225 Length:

6' No.Conn.:

0 Type:

ULTRAGEl.U Scan Coverage Mfg.:

MAGNAFLUX Caflbratlon Block

• • t=>-".*.,.

Cal. Block No.

40411 Upsti'eum li2) Downstream li!J Sc:en dB: ~ 'ReferetJCe Bi~ct

~

ReferenoefSlmullltor Bloc:tt Thickness Q.876 Ola.:

8.75 cwo CCW D Scan dB: ~

SellalNo.:

97-5590 Gain Signal Sweep Sound Path dB Refledor Amplitude '!lo Division Cal Blk. Temp.

64 Temp. Tool:

MCNDE40129 Exam Surfaoa:

O.D.

Type:

ROM PAS 21.7 rRedlue 80 4.5 2.00" Comp. Temp.

80 Temp. Tool:

MCNDl!40129 Surface Condition:

AaGfound Recordable lndlcallon(a):

Ves b!I NoO (If Yu, Ref. Attached Utlrasonlc lndlcallon Report.)

Results:

Ac:cept D Re}ect 6'JI Info D Comments: FC 11-18 Pnwious Data:

Yes

UT Cafibration.mination

. *.*-?

Sita/Unit:

Oconoe 1

Procedure:

NDE-3630 Outage No.:*

01-27 Sum ma ry No.:

01.82.51.0004 Procedure Rev.:

,2 Report No,:.

UT*12*1080 Worll Order No.:

Page:

3

. of 13' Workacope:

ISi 1992022

Code:

199812000A Cat.ntem:

8-B 182~1 Drawing No.:

O-'SIN4-101A-1.1 Dell(;liptlon: Head lo HHd System ID:

51A

---

,...,...------,-----------~--~--------------

Compo n ant ID: 1LDCS.OUTLET SiZeJLength:

NIA Thlckn8Ssiolameter:

Um1tat1011s:

Yes

• See attached 11he1lts lnatniment Settings Serial No.:

0285P4 Manufacturer:

GE Model:

USN80SW Oela:i:

8.9147 Range:

2.5" M11CaWel:

.2293 Pulser:

Squaro Oampin1r 500 Reject:

O'Jli Rep. Rate:

Autohl9h Freq.:

2MHz Fill.Br.

Fiiied Mode:

Dual Voltaga:

450 Other:

Fullwave Ax. Gain (dB):

51.0 Clrc. Gain (dB):

NIA 1

Screen Div. =.25 In. of Sound Path uneartty Report No.:

L*12*225 Calibration Block Cal. Block No.

40411 Thlc:knets 0.875 Dia.:

8.75 Cal. Blk. Temp.

64 Temp. Tool:

MCNOE40129 Comp. Temp.

80 Temp. Tool:

MCNOE40129 Recordable Indication(&):

Ye50 NoQ Results:

Ac:cepl 0 No Eliamlner Level' 11-N Griebel, David M.

Examiner Level Bull, W. l<ellh Other Level

.NIA Seiirch Unit Serial No.:

03-164 Manufacturer:

RTD Size:

2(71110)

Shape:

Reel Freq.:

2.0 MHZ Sl}18:

TRL2 Exam Angle:

45

1. of Elements: Dual Mode:

Long.

Measured Angle:

45 Wedge Style:

Integral Search Unit Cable Type:

RG* 174 Length:

No.Conn~:

-~..'

0 Scan Coverage Upstream O Oownsttaam ~ Scan dB:.!!:!_

cwo CCW O Scan dB: NIA Exam Surface:

0.0.

Surface Condition:

AJs Ground Start Time:

0852 Finish Time:

SS 1.875/NA 0905 Cal.

Axial Orlent.atDd Semh Unit..

llme Date CheckS Calibration Signal Sweep lnltlalCal 11'712012 Sound Path 0810 Renaclof AmpUIUde%

• Division Inter. Cal ID Notch 80 4.9 1.22" Inter. Cal.

0851 11'7/2012 Inter. Cal.

Final Cat 1007 111712012

. Couplant Cal. Batc:h:

12125 Cln:umferenUal Orientated Search Unit Type:

ULTRAGELll CeUbratlon Signal

• sweep Mfg.:

MAONAFLUX Rellector

'Amplitude %

Division Sound Path Exam Batch 12125 NIA Type:

ULTRAGEl.11 Mfg.:

MAGNAFl.UX

• .. h **

Refarence/Slmukrtor Sloclc Reference Bloctl Serial No.:

97-5590 Gain Slgnal Sweep Sound Palh dB Reflector Amnlitude % Division Type:

ROM PAS 22.8 2" Radius 80 8.0 2.00" (tr Yes, Ref. Attached Ultrasonic Indication Report.)

Info O Comments: FC 11*18 Seannlng dB lowe~d to maintain a 2:1 algnal to nolut:i Reviewed Previous Data:

ril!lo

• Date 1/-/o-lz..,

Cate

r.Ly.

'..';J

~

~

-.s:::.-

UT Calibration

.rnination Site/Unit:

Oconee Procedura:

NDE-3630 Outage No.:

01*27

~-~---------~

Summary No.:

01.82.51.0004 Procedure Rev.:

2 Report No.:

UT*12*1080

~-~---------~

Workscope:

ISi Work Ordef No.:

• .*.. *Page:

4 of 13 i 1992022 Code:

1998f2000A Call!tem:

a.a 1s2.s1 location:**

---

~------~----

Drawing No.:

0-ISIN4-101A-1.1 08$Cripllon: Head to Head System ID:

51A

---

~-----------~--~----------------

Component ID: 1LDCB.OUT1.ET Umitallons:

Ye**Seeattachedshoets Instrument Settings Serial No.:

0285P4 Manufacturer; GE Model:

USN60SW Delay:

6.0128 Range:

4.oo*

M'tlCalNsl:

.21&8 Pulser:

Square Damping:

500 Reject:

0%

Rep. Rate:

Autohlgh Freq.:

2MHz Fiiier:

Fbted Mode:

Dual Voltage:

• so Other:

Fullw&Ye Ax. Galn (dB):

45.3 Clrc. Gain (dB): '>

NIA 1

Screen Olv. =

.4 in. of Sound Path Uneartty Report No.:

L-12*225 Calibration Block Cal. Block No.

40411 Thickness 0.875 Dia.:

8.75 Cel. Blk. Temp. "

Temp. Tool:

MCNDE40129 Comp. Temp.

80 Temp. Tool:

MCNDE'°129 Recordable lndlc:atfon(a):

YesQ No~

Results:

Accept O Reject~

Percent Of Coverage Obtained > 90%:

No

• Examiner Level Griebel, David M.

Examiner Level Bull, W. l<elth Other level NIA Sl2ellength:

NIA

• Thlckness/C!lameter.

SS I.8151 NA Start Time:,'

• 0907 Flnlilh Time:

0920

'. ~..

Search Unit Cal.

**** v i

• . ~

Aalal Orlanillted Search Unit'?+..

Time*

• Data Serial No.:

03-786 '*

Checka Callbratlon Signal Sweep Manufac:turer:

RTD lnlUalCal 0813 11n12012 Ren actor Amplitude%

OMslon Solltld Path Size:

2(7x10)

Shape:

Rect.

Inter. Cel.

ID Notch BO s.o 2.02'"

Frt1q.:

2.0 MHZ Sly!~:

TRL2 '.

Inter. Cal. 0908 11m2012 Exam Angle:

80

1. of Elements: oua1"' l!IWr.Cal.

!;~;-

':""."~

Final Cal 1012 11f7/2012

.V<

Mode:

ton1;:

Measured Angle:

80 Couplant Wedge Style:

lnt.gral

'eat. Batch:

12125 Cln:\\lm~rentlal Orientated Search Unit Type; ULTRAGELll Calibration Signal Sweep Sound* P~lt\\

Search Un~,t Cablo Mfg;:

MAGNAfl.Ux Rallactor Amplitude%

Div la Ion Hf A'

~..,.

~

Type:

RG-174 Exam Batch 12125

.;>.~.

/.*-

~."!?.....

Length:

6' No.Conn.:

0 Type:

ULTRAGELU Scan Coverage Mfg.;

MAGNAFLUX Upstteam !;a Downstream 2J Scan dB: ~

Reference Bloc:lc Refenmce/Slmulator Bloctc cwo CCW 0 Scan dB: ~

Serial No.:

97,a90 Gain';.*.

Signal Sweep *s01.111dPath dB ReftaCIDr Amplllude% Division Eaam Surface:

O.D.

Type:

ROM PAS 28.8 rRadlua 80 5.0 2.00*

Surface Condition:

As Ground (If Yes, Ref. Attached Ultrasonic lndlcallon Report.)

Info 0 Commenta: FC 1'"1&

RevleW$'d Previous Delli:

.Yea Date Revltlw&r 11m2012 iL Date 111712012 Date Scanning d9 lowered to malnlaln a 2:1 signal to noise ratio

UT Calibration mination Sita/Unit:

Oconee 1

Procedure:

NDE-3830 Oulage No.:

01-27 Summary No.:

01.82.51.0004 Procedure R~v.:

2 Report No.:

UT-12*1060.

Wortcscope:

Worll Order No.:

~------

Pegs: *i 5 ISi 1992022 of 13 Coda:

199812000A CatJltem:

B-8 IBUl1 Drawing No.:

0-tSIN4-101A-1.1 Oesalption: Head to Head System ID:

51A

---

~~--------------~-------~------------------------~-----------------------

Component ID: 1LOCB-OUTLET SIZelt.ength:

NIA Thlckness/Dlameter:.*

SS I.815 I NA Umitatlons:

Yes

• See attached sheets Start Time:

0922 Finish Time:

0937 lnatrument Settings Search Unit Cal.

Axial gr!entattd Sean:h Unit Time

. Dato Serial No.:

0285P4 Serial No.:

v 03-n1'

• Checks

-~,. ~-< *.

~-.

lnltia1 Cat Callbrallon Signal sweep Sound Path Manufacturer.

OE Manufllcturer:

RTD 0815 111712012 Reflector AmpllWde%

Division Model:

USN SO SW Size:

2(7x10)

Shape:

Rect.

Inter. Cal.

ID Notc:h 80 5.0 2.so*

Delay:

7.3091 Range:

s.oo*

Freq.:

2.0MHZ Style:

TRL2 Inter. Cal.

0921 1117/2012 M'UCalNel:

.2266 Pulll&r:

Square Exam Angle:

70

1. of Elemeots: Duaf Inter. Cal.

FlnilCal 1015 111712012 Damping:

500 ReJect:

O'tf.

Mode:

Long.

Rep. Rate:

Autohlgh Fraq.:

2MHz MealllPIJd Angle; 70 Couplant Filter:

Fixed Mode:

Dual Wedge Style:

lntogral Cal. Batch:

12125 Circumferential Orientated Search Unit Voltage:

450 Other:

Full-ve Type:

ULTRAGELll Calibration Signal Sweep Ax. Gain (dB):

41.3 Clrc. Gain (dB):

NIA Search Unit Cable..

Mfg.:

MAGNAFLUX Ref!eetcir Amplitude%

Division Sound Path 1

Screen Div. "

.5 in. of Sound Path Type:

RG-174'

• Exam Batch 12125 NIA Llneartty Report No.:

l-12*225 Length:

No.Conn.:

0 Type:

ULTRAGELll Calibration Block Sean Coverage Mfg.:

MAGNAFLUX Cal Block No.

40411 Upstream Ii?} l)ownstmam b2J Scan dB: 42.3 Reference Block Raference/Slmulator Block Thickness 0.875 Dia.:

8.7!5 cwo CCWO Scan~B: NIA Senal No.:

97-5!190 Gain

' Signal Sweep Sound Path dB Reflector AmDUlude % Division Cal. Slk. Tamp.

84 Temp. Tool:

MCNDE40129 Exam Swface:

O.D.

Type:

ROM PAS 30.6 2* Radius 80 4.0 2.oo*

Comp. Temp.

60 Temp. Tool:

MCNDE4'0129 Surface CondlUon:

AaGround Recordable lndlcatlon{a):

YesO No E2ll (If Yes, Ref. Attached Ultrasonlc lncllcatlon Report.)

Results:

Accept 0 Reject li2J Info 0 comments: FC 11-18 Scanning dB lowered to maintain a 2:1 signal to noise Percent Of Coverage Obtained > 90%:

No Reviewed Pnivious Data:

Yea ratio Examiner level ll*N

\\\\

~

• ~\\"

~ ~=

~~

rfl~

"W DUKE POWER* COMPANY ISi LIMITATION REPORT Component/Weld ID: WJ-35 Item No:

01.B2.Sl.0004 121 NO SCAN 0 LIMITED SCAN FROM L 0+3" to L 0-3" SURFACE 1:211 D 2 BEAM DIRECTION 1:21 1 1:21 2 r.81 cw 181 ccw INCHES FROM WO CL +1.1 to Beyond remarks:

No scan due to nozzle & taper

• '*c.**..

on chemical connector. *.

ANGLE:

oo~ 45 l8J 60 other 70 FROM 0 DEG to 360 DEG I-------==--==----=-----_;_;:_==-~_;.*:.;;;*,,_.

.;_*....:::::::::::=:._.....:.....:.::.:_*_::::::::::::::=....:**:.J*,:;:::_. -+------..;_;:__..:..____,_~--

D NO SCAN 121 LIMITED SCAN FROM L N/A to L ANGLE:

DO l8J 45 D NO SCAN 0

LIMITED SCAN FROM L to L NIA jg! 60 SURFACE BEAM DIRECTION D 1 t?:?J 2 181 1 t?:?J 2 l8J cw 181 ccw INCHES FROM WO

+o.6 to

+1.5 other 70 SURfACE 0 1 0 2 FROM 0 DEG to 360 DEG BEAM DIRECTION-0 1 D "£*.'f] f?f.. D c~

INCHES FROM WO ---- to __

• • , (**

~

ANGLE: ooo 45 0 60 other

• FROM DEG to DEG

~.:.==--=:_:_...::::._.:.:.___.:::::...:::..:__-=.::..:..:..-====:___:...::..::.::_:.:.:..::==-=-~_::_:_-==:...:::.;.:::--=-i1--:.;;;_ ______

_.;.___J '

,,.. *. ~..

D NO SCAN.

D LIMITED SCAN FROM L ANGLE: ooo Reviewed By:

J"'ftttE:~ J, BEAM DIRECTION SURFACE D 1 D 2 D 1 0 2 0 cw D ccw UT-12-1060 INCHES FROM WO to*:-

FROM DEG to II Date:

11/07/12

• • ~

- '()-/1-DEG

• .* *Sketch{s} attac~ed 181 yes

,_: ~, *:

. *... *~~-~.

D No l~'S

-~ -

~

Summary No.: 01.82.51.0004 Examiner: Griebel, David M.

Examiner. Bull W. Keith O~er._N_IA.___~~~~--~~~~~~-

Comments: Weld WJ-35 Ind. ti 1, 2 & 3 are root geometry.

Sketch or Photo:

51-

• r..-:-

Supplemental Report J-evel:

11-N Level: _!!::r!_

Level:~

Report No.:

UT-12*1060 Page:

7 of 13

• -*~..

-~

.=

~~§

~~

~------~----------------------------------------------~-------------------------------------------

_j">

~,-

.-s;::._ -

~

/;

'*;-.*t..;-... :

Let Down,Cooler.. Chemical Conne.ctor to Channel Body

%. Coverage Calculations.

Weld No.:

"WJ-35; 0 =

8.625" Weld Length=

27.1" Total Inspection Area =

2.28 sq. in *. *.* ***

% Length Limited due to nozzle= 6" / 27.1" x 100 = 22.1%

Agareqate Coverage Calculation t'Xial Scans 22.1 % of length x 96.5% of the volume of length/ 100 = 21.3°4 77.9% of length x 97:4% of the volume of length / 100 = 75.9%

Aggregate coverage Axial scans= 21.1 + 75.9 =

97.2%

Circ. Scans.

100% of length x 78.1% of the volume of length / 100 = 78.1%'

Total= (97.2 + 78.1) / 2 = 87.7% Aggregate Coverage Page_:[_ of.Jl_

ATTACHMENT A 7-'l 4 t/ ~ - -~*

tdo'W!l Cooler Chemical Cq1 *~". * *.ort9~el ~qpy Total

.. **Area Weld No. :

WJ-35

\\N >

~ c:

':Po-

~;

-.t:.. ~

. --t:: ::

Exam.. +

~

Item No. :

NIA Tube Sheet-S2 aiann,el Body-Sl Scale: l 11 = 1"

Weld No.:

WJ-35

=Area Not Examined= 0.05 + 0.01 = 0.06 sq. in.

.____l =Area Examined= 228 - 0.061228 x 100 = 97.4%

• • .*s Tube Sheet* S2 ChannelBocfy-Sl f'.

700 Scale: 1" = 1" j._.

~-:

~tdown Cooler Chemical Co~ ector to Omnnel Body Area Examined@Nozzle -*Axial Scans Item No. : -"'"'"""Nl

...... A Weld No.:

WJ-35

=Area Not Examined= 0.05 + 0.01 + 0.02 = 0.08 sq. in.

No:zzle

=Area Examined= 2.28 - 0.08 I 2.28 x 100 = 96.S'Yt>

• .**** 0 700 45 Tube Sheet - S2 Channel Body-S 1 Scale: 1" = l"

,down Cooler Cheini~eq~.,.~est9f ~ ~r~ *

• Area~aminoo~ Cifc: 1r~Qmi*~' *,,

<;/';; '*/"

Weld No. : __

WJ~-3;.::;..5 __

=Area Not Exan;Uned = 0.5 sq. in.

r

=Area~ed= 2.28-0.5/2.28x 1()9=78.J%

Tube Sheet* S2 45° 45° Scale: l " = I "

~

~

Ultrasonic Indication Report SiteiUnit:

Oconee I

1 Summary No.:

01.82.51.0004 Woi1<scope:

Search Unit Angle:

45 WoLocation:

Lo Location:

Weld Centertlne 9.1.1.1 MP M

IP t eta ah RBR Remaining Back Reflection L

Distance From Datum Comments:

WeldWJ-35 Indication w

An91e No.

Of Max DAC w

MP S1 1-45 90 1.5 2.20 S2 2.-45 100 0.9 1.2.5 S3 3-45L 85 0.9 1.25 ISi w max W1 W2 Forward Of Max W1 MP NIA N/A NIA N/A NIA NIA Examiner Level l~NA0/~~-/

Griebel, David M.

Examiner Level 11-N~~

I

.~

Bull, W. Keith

./" _'Sle'(. r

]

. Other Level NIA

)

Signature NIA Procedure:

NDE-3630 Outage No.:

01-27

~----~--~

Procedure Rev.:

2

• Report No.:

UT-12*1080 Work Order No.:

1992022 Page:

13 of 13 Wo w-*

O Piping Welds O Ferritic Vessels ?. 2*r CLj I

Wl W2 C~

1 l

@ Other ifessels < 2" T F

WTSUAtMxl R

a* t is ance rom 0

0 a mum esponse I

--, T *~

--l>AnJM Distance From We At Of Max (Forward)

Lo

=-~

1l I

Distance From Wo Al Of Max (Forward) l..amc

-r~ 6 0 il.2 j. 'L J

• • wt~Wi I

Backward L1 L

L2 RBR Remarts OIM.ax Of Max Of Amp.

W2 "MP Max Max NIA NIA seo*

0-3""

INT NIA Root geometry

_:,J.:

KIA NIA SllO*

0+3" INT NIA Root 9eomat1y NIA NIA 3so*

0.. 3..

INT.

NIA Root geometry

. *.*~. *~

'**>)*>

~<.

Date Reviewer*-

)~~Q.k/r 5

l°JJ1i.--m 0a1e 11'7/2012 Jfiri5.r.fl1tA-R~Ln.

l/-/D-/?

Date Site Review

.. v

-- *v Signature Dale

)

111712012

~1~

.Date

~*At.. ~.~ **

Stbriature

~ Date

,'../ -AJ1-: :. L.. U/1 L 1 J

• ~A~

///1 r/.).-*

&.I"

~

1tr.**-

• v

• • h.

• ~.*.

UT Calibration

<~ =.

Site/Unit:

Oconee 1

Proeedura:

NDE-830 Outage No.:

01-27

--~------------------------

Summary No.:

01.89.11.0059 Procedure Rev.:

1 Report No.:

UT *12*1078 Workscope:

ISi Work Order No.:

1981596 Page:

1 of 3

Code:

199812000A Cat.lllBin:.

B..J 189.11 LocaUon:+ ---------------------------------------

Drawing No.:

O.tSIN'-100A-1.1

==

Description:==

RC Pump 11\\1 to Safe end System ID:

50

--~-------------------------------------------------------------------------_;;;""-------~------....... ----------------~~

Component ID: 1*PDA1*1 Size/length:

NIA Thlckn&sa/Dlameter: SS I 2.330 I 33.5

---

~

Llmllallons:

Yes

• Sae att&chad sheets Start Time:

1315 Finish Time:

1355 lnllttvment Settings Search Unit

" Cal.

Tlme Date

. Axtal Orientated Search Unit Serial No.:

01*738 Serial No.:

OJ.789 ctieck1 Calibration Signal Sweep Manufacturer:

KRAUTKRAMER Manufacturer:

RTD lnl1la1Cal 1110 1111112012 Reflector Amplitude%

OM a Ion Sound Path Model:

USN-60SW Size:

2{20J:34)

Shape:

Roel.

Inter. Cal.

3/4TSDH 80 4.8 3.15.

Delay:

15.1378 Rango:

1.0*

Freq.:

1.0 MHz

,,Style; TRL1 lnler. Cal.

1315 1111112012 fy**

• • t;..

lnler. Cal M'UCeWel:

.2478 Pulser:

Square Exam Angle:

eo II of Elements: Dual --

Final Cal 1540 1111112012 Damping:

500 Reject 0%

Mode:

Long.

Rep.Rate:

Autohlgh Freq.:

1 MHz Mea~Angte:

60 Couplant

!j Alter:

Fblad Mild&:

Dual Wedge Style:

Integral Cal. Batch:

12125 Circumferential OrlentetVd search Unit * '

Voltage:

450 Other:

Fullwaw Type:

UlTRAOEL!I Callbrallon Signal Sitteep Ax. Gain (dB):

61.8 Clrc.. Gain (dB):

70.0 Search Unit Cable Mrg.:

MAGNAFLUX RfJflector Amplltude%

Division Sound Palh 1

Screen Olv. "

.7 In.of Sound Patti Type:

R0*174 Exam Batch

. 12125 3J4T SDH 80 5.2 3.8o*

Linearity Report No.:

l*1Z*228 Length:

6' No.Conn.:

D Type:

Ul.TRAGEL!I Cellbratlon Block Scan Coverage Mfg.:

MAGNAfLUX Cal. Block No.

50214 Upstream J;!j Dov.nstream O Scan dB:..!!:!_

Reference Block

~>Y Referonee/Slmulator Bloc;k Thickness

'U84 Dia.:

Flat cw~

CCWJ;!} Scan dB:~

Gain Signal Sweep Sound Pait!

Sel1al No.:

• • .. °'"8740 dB Reflector Amo61ude 'lit Division Cal. Blk. Temp.

70 Temp. Tool:

MCNDE40130 Exam Surface:

0.0.

Type:

ROM PAS 46.0 2* Rad!Q 80 2.8 2.00*

Comp. Temp.

73 Temp. Tool:

MCNDE<&0130 Surface COndl lion:

As Ground Recordable lndlcatlon(a}:

Yes O No Ii!)

{IC Yes. Ref. Attached Ultrasonic Indication Report.)

Reject 0 Info 0 Comments: Initial Section XI Eum FC 11-08 See Report UT*12*1073forT & C; also coverage plot Results:

Accept 0 Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

No Examiner

• Level

• • n-N

• Date Relliewet Osle Griebel, Davld M.

1111112012 ::!Mc-s 3'. /1c/ftt.'Al.~ 111

//-/3-/z_

Date

SiteJUnll:

Ocvnee 1

Procedure:

NDE*830

. Outage No.:

01*27 Summary No.:

01.88.11.0058

~

Procedure Rev.;

Report No.:

UM2-101a Wortcscope:

ISi Work Order No.:

19111188

\\

Page:

2

• of 3

a.J /89.11 Code:

CatJJtem:

199812000A location:.*

____________________ _..;... **~...

Drawing No.:

O*ISIN4-100A*1.1 Oescrip!lon: RC Piimp 1A1 to Simi end System 10:

&a ------------------------------------------------------------------------------------

Com pone n t ID: 1*PDA1*1 Sl.telLength:

NIA Thlckn~aa/Dlameter: SS 12.330 / 33.S UmllaUona:

Yee

• See attached aheeta Start Time:

1315 Finish Time:

lnatrumorrt Settings t>Gan:ll Unit c81.>/

~:::-:::~

< *.Axial Orlontabid Search Unit"' <

Time Date' SoltalNo.:

014738 Serial No.:

90*371 CltecklJ Calibretlon Signal Sweep Manufac:turer:

KRAUTKRAMER Manufacturer:

RTD lnltlalCal 1122 ttl11l2012 Refleetor Ampll\\ude %

OIYialon Sound Path Model:

USN-GO SW Sb:e:

2(10x18)

Shape:

Re cit.

Inter. Cal.

1/4TSDH 80 3.4 us*

Delay:

9.9722 Range:

15.00" Freq.:

2.0MHz Style:

TRl-2..

Inter. Ce!.

1333 1111112012

1. of Eluinen\\S:

Inter. Cal.

M'tlCulNel:

.2302 Pulser.

Squ&l'9 Exam Angle:

TOL Dual

.....___ Final Cal 1545 11/1112012 Oampln9:

500 Reject:

0%

Mode:

Long.

Rap. Rate:

Autol'llgh Freq.:

ZMHz Measured Angla:

TO Covplant Fnter:

Fixed Mode:

Dual Cel.Batch:

1212$

Wedge Styta; Integral Cln:umfvruntlal ()flentated Sea~ Unit Voltage:

450 Ottier:

Fullwave '

Type:

ULTRAGELll

'Calihratlon Slgn8'.

Sweep.*.. iSoWld Path Ax. Gain (dB):

53.2 Clrc. Gain (dB):

158.0 Search Unit Cable Mfg.:

MAGNAFLUX Reflector Amplitude'*'

Division 1

Screen Div. =

.5 In. of Sound Path Type:

RG-174 Exam Batch 1/4TSOH 80 3.8 1.12" 12125 Linearity Report No.:

L*12*Z28 Length:..

No. Conn.:

0 Type:

ULTRAOELll

~-*.. :

Callbndlon Block Scan Coverage Mfg.:

MAGNAFLUX Cal. Bicek No.

50214 Upstream~ Downslnlam O Scan dB: ~

Reference Block '.

Reference/Simulator Plock Thickness 2.464 Dia.:

Flat cw~

CCW [;a Scan dB: ~

Serial No.:

04-8740 '

Gain Signal s-ep Sound Palh dB Retluctar Amolilude % Olvialon Exam Surface:

o.o.

Cal. Blk. Temp.

70 Temp. Tool:

MCNDE40130 Type:

ROM PAS 44.0 2* Radlua 80 2.8>.

2.00*

Comp. Temp.

73 Temp. Tool:

MCNDE40130 Recordable lndlcatlon(e):

Yea O No (i!1 Resulta:

Accept 0 Rejeet ~

Emrn\\Mt Levo\\

ll*N Griebel, David M.

Examiner Level 11-N

l,

Deen, Steven Surface Condition:

Al Ground (II Yes. Ref. Altached Ultrasonic Indication Repat1.)

lnfu O Pmvious Oa\\a:

No 1111112012 Date 11/1112012 Site ROYllJW tJ'

.. A

./* ':V.

Comments: Initial Section XI Eum FC 11..08 See Report o UT*12*1073 Date Li:11*

'/-/J-/?....

Date

\\/\\)

Oll'ler Level NIA Dato ANll Review Signature

~~~---Nl_A __________________________ ~------.--~-------------......._~N.......,.~~* -----------~~-----------------------------'

~~

~:~

~=

Oate

DUKE POWER COMP ANY ISi LIMITATION REPORT Component/Weld ID: 1-PDA1-1 Item No:

01.89.11.0059

• ; f!marks:

~ NO SCAN SURFACE BEAM DIRECTION Procedure allows scanning from 0 LIMITED SCAN l8J 1 02 D 1 l8J 2 181 cw 1:81 ccw cast side only.

FROM L NIA to l NIA INCHES FROMWO Cl to Be:tond ANGLE: ooo 45 t8I 60 other 70 FROM 0 DEG to 360 DEG D NO SCAN SURFACE BEAM DIRECTION 0

LIMITED SCAN D 1 02 0 1 0 2 D cw 0 ccw FROM L to L INCHES FROM WO to ANGLE:

oo 0 45 D so other FROM DEG to DEG D NO SCA~

SURFACE BEAM DIRECTION 0

LIMITEDSCAN 01 02 D 1 02 0 cw 0 ccw*

~~ :.*'

FROM L to L INCHES FROM WO to ANGLE: oo D 45 0 60 other FROM DEG to DEG D NO SCAN SURFACE BEAM DIRECTION 0

LIMITED SCAN 0 1 02 0 1 020 cw 0 ccw UT-12-1078 FROM L to L INCHES FROM WO to Sketch( s) attached 4

D yes f8I No ANGLE: ooo 5 Dao

/other FROM DEG to DEG Prepared By:

David Griebel L_

1 )~_/

_t/Level:

II Date:

11/11/12 I Sheet 3 of 3 Reviewed By:

\\

~l'AJ~CJ.. Jllc' a11e~~:

I Authorized Inspector:

~/A Date:

JJ!Jtf:s 1. /'1c&.}i/.r ***

J/-13-;z_

~

v l

UT Calibration@amination

, /

~,.;.,~

Sile/Unit:

Oconee 1

Procedure:

PDl*UT*2 Outa90 No.:

01*27

~~~~~~~~~~~~~~

Summary No.:

01.89.11,0059 Procedure Rev.:

Report No.:

.. ~= UT-~2~1073 Workscope:

ISi Work Order No.:

1981596 Page:

, 1 of 7

Code:

1998/2000A.

CatJltein:

B..J /BB.11

• * ", Location:

Drawing No.:

0°1SIN4-100A*1.1

==

Description:==

RC Pump 1A1 to Safa end System ID:

50

~~~~~~~~~~~~~~~~~~~~~~~~~~~----~~~~----~--~~~~~~~--~--~~~

Component ID: 1-?DA1*1 Size/Length:

NIA Thicl<nes.s/Dlameler: SS/2.330133.50

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-

limitations:

Yes - See attached sheets Instrument Settings Serial No.:

014738 Manufacturer.

KRAUTKRAMER Model:

USN-60SW Delay:

8.8388 Range:

8" M'UCaWel:

.1238 Pulser.

Square Damping:

5(10 Reject:

0%

Rep. Rate:

Autohlgh Freq.:

2.25 Fiiler:

Fixed Mode:

PE Voltage:

450 Other:

Fullwave Ax. Gain (dB):

31.0 Circ. Gain (dB):

31.0 1

Screen Div. "'

.8 in. of Sound Path Linearity Report No.:

L-12*228 CallbraUon Block Cal. Block No.

40397 Thickness J.000 Dia.:

Flat Cal. Blk. Temp.

70 Temp. Tool:

MCNDE40130

• Comp. Temp.

73 --

Temp. Tool:

MCNOE40130 Recordable lndlcatlon(s):

Yes O No li!J Results:

Accept 0 Reject Ii!]

Percent Of Covera90 Obtained > 90%:

No Examiner Level 11-N Dean, Steven Examiner Leval ll*N Griebel, David M.

Other Level NIA NIA

. Start Time; 1405 Finish Time:.

1503.*

Search Unit Cal.

Axlal Orientated Sillln:h Unit Time Data Serial~o.:

SE0355 Checks Calfbrauori Swbep Slgnal Sound Path, Manuracturar:

GE lnlllalCal 1220 1111112012 Reflector Amplllude%

OMslon Size:

.5 Shapo:

Round Inter. Cal.

ID Notch 80 5.5 4.45".

Freq.:

2.25MHz Style: ' *comp*G Inter. ea1.

1405 1111212012 Exam Angle:

45

1. of Elements: Single Inter. Cal.

Mode:

Shear.i Final Cal 1515 11/11120.12

~:.

MeasUl'!ld Angla:

45 Couplant

.r Wedge Style:

MSW QC Cal. 6atctt:

12125 Clr~umferontlal Orlonlatod Search Unit Type; ULTRAGEL 11 Calibration Signal Sweep

~ound Path Search Unit Csble Mfg.:

MAGNAFLUX Re Rector Amplitude%

Division Type:

RG-174 Exam Belch

,SeeAidal 12125 Length:

6' No. Conn.:

0 Type:

ULTRAGEl.11 Scan Coverage Mfg.;

MAGNAFLUX Upstream O Downstream 0 Scan dB: ~

Reference Block Referonce/Slmulator Block CWfi21 CCW Ii!] Scan dB: 50.0 Gain Signal,, *.*sweep

-- SerlalNo.:

04-8740 dB Refloc!or Amplllude % Division Sound Pat11 Exam Surface:

o.o.

Type:

ROM PAS 16.0 1"Radlus 80 1.25 1.0" Surrace Condi~on:

As Ground

,* **. *:.~ f

0.

(If Yes, Ref. Attached Ultrasonic Indication Report.)

lrofo O Comments:, Purse Width: 220ns Initial Section XI Exem **

Reviewed Previous D11ta:

No Date Reviewer Data*

11/11/2012 Dale 11/1112012 Date

'/-13-1 Ca~

Date

{'lsJ/~.

Site/Unit Oconee

~/

Procedure:

PDl*UT*2

/,

001*27 Outage NC?.:

Summary No.:

01.B9.11.0059 Procedure Rev.:

E Report No.:

UT-12*1073

~------------------------

Works cope:

ISi Work Order No.:

198159~

P~ge:

2.-;.

Of 7

Code:

1998/2000A CetJltem:

B..J /B9.11 Location:

Drawing No.:

O-ISIN4-100A-1.1

==

Description:==

RC Pump 1A1 to Safe end

. =~..

System ID:

50 Component ID: 1*PDA1-1 limitations:

Yes* Sea attached sheets Jnslrument Settings Serial No.:

014738 Manuracturar:

KRAUTKRAMER Model:

USN.SO SW Delay:

8.8319 Range:

10.00" M'UCaWel:

• 2010 Pulser.

Square Damping:

500 Reject:

.. 0%

Rep. Rate:

Autohlgh Freq.:

2MHz Filler:

Fll<ed Mode:

Dual Voltage:

450 Olher:

Fullwavo Ax. Gain (dB):

47.6 Clrc. Gain (dB):

NIA 1

Screen Div.=

1.0 in. of Sound Path Linearity Report No.~

L-12-228 Calibration Block Cal. Block No.

40397 Thickness 3.000 Ola.:

Flat C81. Blk. Temp.

70 Temp. Toot:

MCNDE.(Q130 Comp. Temp.

73 Temp. Tool:

MCNDE40130 Recordable lndlcalion(s):

Yes O No li'.J Results:

Accept O Reject!!!]

Percent Of Coverage Obtained > 90%:

No Examiner l.evel ll*N Dean, Steven Examiner l.evel 11-N Griebel, David M.

Olher l,evel NIA NIA Size/Length:.

NIA

• 1tc*.. **

Start Time:

Thickness/Diameter: SS/2.330/33.50 Finish Time:

1503..

1405 S&Bf'Ch Unit Cal.

Time Date

.* Axial ()rlentated Search Unit

'.);

Serial No.:

03-795 Checks v~'.

Initial Cal 1225 11/11/2012 CalibraUon Signal Swoop* Sound Path Manufacturer:

RTD Re Hector Ampfiludo %

Division Size:

2(20x34)

~pe:

Rect.

Inter.Cal.

314 TSDH

<ao 4.2.

4.222

• Inter.Cal.

1435 11111/2012 Freq.:

2.0MHZ Style:*.

TRL2 Exam Angle:

60

1. of Elements: Dual Inter. Cal

• Mooe:

Final Cal 1520 11111i2o12

'.+.:..,

Long.

0.

.-(:"

. ~= *.~:

Measured Angle:

Couplant

j"

• .~

60 Wedge Style:

Integral Cal. Batch:

12125 Cln;umferontlal Orientated Search Unit

~>*

Type:

ULTRAGELll CaflbraUon*

'.'Signal

'+

>Sweep Sound Path Search Unit Cable Mfg.:

MAGNAFLUX Rel!ector AmpUtude %

Division Type:

RG-174 Exam Batch 12125 NIA

~

~*.

/..,;:_..

Length:

6' No.Conn.:

0 Type:

ULTRAGELfl.

Scan Coverage Mfg.:

MAGNAFLUX Upstream O Downstream !!!] Scaii dB: 65.0

.. /::

~>.

ReferellcelShnulator Bloc!i'!\\ *

• Reference Block cwo CCW O Scan dB: NIA Sertal No.:

04-8740 Gain Signal Sweep Sound Path dB Renector Amplllude% Division Exam Surface:

0.0.

Type:

ROMP AS 36.6 2." Radius,/\\*BO 2.0 2.00" Surface Conclltlon:

As Ground (If Yes, Ref. Attached Ultrasonlc Indication Report.)

Info O Comments: Pulse Width: 250ns lnltlal Section XI Exam

-~..

• Reviewed Previous Data:

No Date Reviewer 11/1112012 ih.~$ :r;

_pate Sile Review 11111/2012

~f RITCHIE-SLAUGHTE

.=:-:*.*,;

Data Date

-/3-/Z.

D11ta

~~~-::t /t:

'.t~:w.*.

.. \\*.

.= **~-

'1'.J J Si!e/Unlf; Oconee 1

Procedure:

NDE-640 Outage No.:

01-27 Summary No.:

01.89.11.0059 Procedure Rev.:

5

~eportNo::

UT-12-1073 Worf<scope:

ISi Work Order No.:

1981596 Page:

3 of 7

Code:

1998/2000A Cat.Jltem:

B.J 189.11 LocaUon:

Drawing No.:

O-ISIN4-100A*1.1 DescripUon: RC Pump 1A1 to Safe end System ID:

SO

---

~------~--""---------------------"-*.*~':....;.~---------~

Component ID: 1*PDA1-1

.* Size/L:engtll:

• NfA

.Thlckness/Olanieter: SS/2.330133.50

>~~ >.".-7,,.:-

Umltatfons:

None Start Time:<

1348

., : Finish Time:

1402 Search Unit Cal.

Time D8te Instrument Settings Serial No.:

014738 Axial or18Ti1at~d seal'l:h unit Serial No.: ____

c_1_2_004 S_P ____ 1--C_h_ec_k'-s-1---1------1

.;..;;.~~;;.;;..;.;..;..;;;.;..;_ ____ Manufacturer: _______ K..;.B_A______ Initial Cal 1348 11111/2012

~1..;.n..;.w'-~'-c'-a..;.l *.i.---i------1~:-om_,_p_on_e_n_t_s_w+-__ so ____ -+-_

.. _,_s._s __ _2._70_o_n_

Manufacturer:

KRAUTKRAMER Calibration Slgnal Sweep/ S d p Reffector Amplitude o/o Division,

oun ath Model:

USN-SO SW Delay:

0.5487 Range:

5.0M M'UCalNel:

.2250 Pulser:

Squani Damping:

500 Rejed:

0%

Rep. Rate:

Auto high Freq.:

2.25MHz Filter:

Fixed Mode:

PE Voltage; 450 Other:

Fullwave A:.:. Galn (dB):

24.5 Circ. Gain (dB):

NIA Size:

1.0 Shape

Round Freq.:

2.25 MHz Style:

Gemma Exam Angla:

0

1. of elements: Slngle Mode:

Long.

Measured Angle:

0 Wedge Style:

Integral Search Unit Cable Inter. Cal.

lnier. Cal.

Final Cal 1402 1111112012 Couplant Cal. Batch: __

..;..12.c.1;...25~-- f------C-lr_cu_rm--.o_re_n_u_a_r O_rf_e_nt_a,_te_d_sa_11_rc_h-,-U_n1_t ___ _

Type: __ ___;U;;.;L;;.;T..;..RA;;.;.;cG_E;.,;L...;.11.__

Galibrallon Signal Sweep Reflector Amplilud.. e. %

Division Sound Palh Mfg.: _.....;.;M.;..;AG.;.,N;..;;A.;.,F...;;L.;.,UX~-

~Screen Div.= _.s_ In. of __

s_ou_n_d_P_a_th __ Type:

RG

• 174 exam Batch 12125 NIA Linearity Report No.:

L-12-228 Callbretlon Block Cal. Block No.

Component Thickness 2.330 Ola.:

33,500" Cal. Blk. Temp.

73 Temp. Tool:

MCNOE40130 Comp. Temp.

73 Temp. Tool:

MCNDE40130 Recordable lndlcatlon(s):

Yes O No ~

ResU!ts:

Accept fiZI Reject O Percent Of Coverage Obtained > 90%:

Yes Examiner Level ll*N Oaan, Steven Examiner Level Griebel, David M.

Other Level NIA Length:

6' No. Conn.: __ o __ Type:

Ul.TRAGEL 11 Scan Coverage

. Mfg:: ___

M_A_G...;.N_A_F_LU_x __

Upstrvam i;zi Downstream li?J Seen dB: 28.0 Reference Block CW 62j CCW 621 Seen dB: 28.0.;..S

• rl I N

• 04* a 735 ea o..

Exam Surface:

o.o.

\\ Ty~;

ROMPAS Surface COnd!tlon:

As Ground Gefn dB 2.2 Reference/Simulator Block Signer*'* <~y.;eep Sound'Palh Reftactor Amplitude % Dlvfsliln (If Yes, Ref. Attached Ultrasonic lndlcaUon Report.)

Info O Comments: lnlllel Section XI Exam Reviewed Previous Data:

No Date 11/1112012 Date 1111112012 Data RevieweG.E. HOUSER Date Site Review m~af RITCHIE-SLAUGH

• I.. *

• • • ~. "

c.;7*:\\

~*

Component/Weld ID:

l8l NO SCAN D LIMITED SCAN DUKE POWER COMPANY ISi LIMITA'l'ION REPORT 1-PDA1-1 Item No:.. 01.89.11.0059 SURFACE BEAM DIRECTION 01 IZJ 2 l8l 1 D 2 D cw remarks:

Due to 1A1 RCP nozzle 0 ccw configuration.

.x~..

FROM L N/A to L NIA INCHES FROM WO CL to Beyond ANGLE:

0 0 [gJ 45 0 60 other FROM 0 DEG to 360 DEG 0

NO SCAN SURFACE

'*.*BEAM DIRECTION D LIMITED SCAN D 1 02 D 1 D 2 D cw D ccw FROM L to L INCHES FROM WO to ANGLE: oo 0 45 0 60 other FROM DEG to DEG 0 NO SCAN SURFACE

.. BEAM, f?IRECTION D LIMITED SCAN 01 02 0 1 02 0 cw D CCW FROM L to L INCHES FROM WO to ANGLE: ooo 45 0 60 other FROM DEG to DEG D NO SCAN SURFACE BEAM DIRECTION D LIMITED SCAN D 1 02 0 1 02 D CW*, CJ ccw ;*

UT-1271073 FROM L to L INCHES FROM WO to Sketch(s) attached 4

~ yes ANGLE: ooo 5 0 60 other FROM DEG to DEG v

Prepared By:

Steve Dean -:::;U 7~

_Level:

II Date:

11/11/12 I Sheet 4 of 7

)

D No

• ";_i/

Reviewed By:

Jfl~s.J, Mc.lfr1)./ e-111

... I 1 );;; llf

e.,,_

1/-1~ -1z.._I ~est l!itfeJ!ffE-sLAUGHTE~~ ~

~

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cv

/0"J'

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I I I i

Summary No.: 01.89.11.0059 Examiner: Dean, Steven Examiner: Grlebel David M.

Other:...;N..;.;.:/A'-'-------------

Comments: Coverage plot of weld: 1*PDA1-1 Sketcll or Photo:

Supplemental Report Level:

ll*N Reviewer:

I l

1' I

I I.,

/.

I I

• • ~

.=

Report No.:.**

UT-12*1073 Page:

5 of 7

../.. *

"SAi:E* 6..,D

'SJ.

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'i Summary No.; 01.89.11.0059 Examiner: Dean, Steven Examiner:.=..:..::=::.:.i....::;.=..;;.:.;;..;;:,;;_.....c;;="'---"----..'---

Other:...;,N.;..;./A;...;_ _____________ _

Comments: Profile of weld: 1-PDA1*1 Sketch or Photo; Sate. f.-..t

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'9 M

rl\\

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f"' *

...0...,

'\\"'"

-.SI I'.*,...,....,.

Supplemental Repo,rt Level:

ll*N Level:

R*N Level:~

~

~ rr' °"

N y

~,....

0.

'QO.

~

~ N t-1 N

N

~ N NN

~ N

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Report No::

UT-12*1073 Page:

6 of 7

.:;..:..;..=...;.,;_:,_~~:.;;;,,,,:;""4=~;....4:~=;ra.~~Dale: //-;-:,'-/ 2....

~

~

Dale: --,-.--,.-

Dale: / 0r//...:l-

Determination of~ercent Cd~erage f~~:.

UT Examinations - Pipe Site/Unit Oconee /

1 5 um ma ry No.:

01.89.11.0059

~ ;

Procedure:t' PDl-UT-2

---

~-

Procedure Rev:::.

E Outage No.:

01 *27

{ '.;~

Report No.; __

u_r._1_2._10_1_3_ \\~

Page:

7 of 7

~

Works cope:

ISi Work Order No.:

1981596 45deg.

"f:

~/:'

!:/*

-.A,.*:,.

% totat'for Upstream Upstream 100.000

% Le,l'l_gthX 100.000>

% volume of iength / 100 =

100;000

..... p Downstream.

100.000

% LengthX 0.000

% volume of length I 100 =

0.000

% total for Downstream cw 100.000

% Length X 50.000

, -*~

% volume of length/ 100"'

50.000

% total for CW

% tot~!" for CCW c,cw 100~000 0Jl. LengthX 50.000

% vollime of length 1100 =

50.000 Add totals and divide by # scans =

50.000

% total for 45 deg Otherdea -

(to be used for suppfemental scans)

The data to be listed below is for coverage that was not obtained with the 45 deg scans.

Upstream

% Length X

% volume of length I 100 =

% total for Upstream Downstream * *

% Length X

% volume of length 1100 "'*

% total for Downstream CW

% Length X

% volume of length I 100 =

% total for CW CCW

% Length X

% volume of length/ 100 =

% total ror CCW

~---------

Percent complete coverage Add totals for each scan required and divide by# of scans to determine:

50.000

% Total for complete exam Site Field Supervisor:

Date: zlz/is I

I