ML073180447

Request for Relief Number 07-CN-004 Limited Weld Examinations During the End-of-Cycle 16 Refueling Outage

ML073180447
Person / Time
Site:	Catawba
Issue date:	08/27/2007
From:	Morris J Duke Energy Carolinas, Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
07-CN-004
Download: ML073180447 (84)

Text

JAMES R MORRIS Duke Vice President Energy Catawba Nuclear Station 4800 Concord Road / CN0J VP York, SC 29745-9635 803 831 4251 803 831 3221 fax August 27, 2007 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)

Catawba Nuclear Station, Unit 1 Docket Number 50-413 Request for Relief Number 07-CN-004.

Limited Weld Examinations During the End-of-Cycle 16 Refueling Outage Pursuant to 10 CFR 50.55a(g) (5) (iii), please find attached Request for Relief 07-CN-004. This request for relief is associated with limited weld examinations during inservice inspection activities for the subject refueling outage.

The attachment to this letter contains'all technical information necessary in support of this request for relief Duke is requesting NRC review and approval of this request at your earliest convenience.

There are no regulatory commitments contained in this letter or its attachment.

If you have any questions concerning this material, please call L.J. Rudy at (803) 831-3084.

Very truly y urs, James R. Morris LJ/Rs Attachment

ý0(47 www. duke-energy. com

Document Control Desk Page 2 August 27, 2007 xc (with attachment):

W.D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 A.T. Sabisch, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.F. Stang, Jr., Senior Project Manager (addressee only)

U.S. Nuclear Regulatory Commission Mail Stop 8-H4A Washington, D.C. 20555-0001

Document Control Desk Page 3 August 27, 2007 bxc (with attachment):

R.D. Hart L.J. Rudy K.E. Nicholson M.A. PynEe A.J. Hog ge, Jr.

R.N. McG ill RGC File Document Control File 801.01 ELL-EC050 NCMPA-1 NCEMC PMPA SREC

Attachment Request for Relief 07-CN-004

Relief Request 07-CN-004 Page 1 of 36 Relief Request 07-CN-004 Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii)

Inservice Inspection Impracticality Duke Energy Corporation Catawba Nuclear Station - Unit I (EOC-16)

Third 10-Year Interval - Inservice Inspection Plan Interval Start Date = 6-29-2005 Interval End Date = 6-29-2015 This Relief Request has ten (10) welds. for which relief is being sought.

The ID's and Item / Summary Numbers for the ten (10) welds are as follows:

List Number Weld ID Item / Summary Numbers

1. I NC28-1 1 B09.011.020

2. 1NC31-1 B09.011.030

3. IN118-2 B09.011.155 4, 1NI148-10 B09.011.163

5. 1N1148-11 B09.011.164

6. ISWRF- 1-OUTLET C02.011.003

7. IND3-1 C05.011.065

8. INII-12 C05.011.105

9. 1NV-309-INLET C05.021.146

10. 1NV-309-OUTLET C05.02 1. 147 Attachment A contains the inspection data for Weld ID 1NC28-11.

Attachment B contains the inspection data for Weld ID INC3 I-1.

Attachment C contains the inspection data for Weld ID IN118-2.

Attachment D contains the inspection data for Weld ID 1NI148-10.

Attachment E contains the inspection data for Weld ID IN1148-1 1.

Attachment F contains the inspection data for Weld 1ID 1SWRF-I-OUTLET Attachment G contains the inspection data for Weld ID 1ND3-1.

Attachment H contains the inspection data for Weld ID 1NII-12.

Attachment I contains the inspection data for Weld ID 1NV-309-INLET.

Attachment J contains the inspection data for Weld ID INV-309-OUTLET.

Relief Request 07-CN-004 Page 2 of 36 Items in this relief request were examined during August, November, and December, 2006.

I. ASME Code Component Affected Weld ID = INC28-11 Item / Summary Number = B09.01 1.020 Reactor Coolant System (NC)

NC System Elbow to Valve IN1134 Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III. Applicable Code Requirement Table IWB-2500- 1, Examination Category B-J Item / Summary Number B9.11 Figure IWB-2500-8 (c), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance Weld joint geometry and material selection caused limitations resulting in the inability to achieve the required coverage. The valve and elbow material is stainless steel. This weld has a diameter of 6.625 inches and a wall thickness of 0.714 inch. During the ultrasonic examination of this weld, 35. 10% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 50% of the weld and base material; 600 shear wave scan from the elbow side perpendicular to the weld covered 40.50% of the weld and base material. In accordance with Duke Energy Procedure NDE-9 1, scan areas S1 and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit covered 22.20% of the examination volume on the valve side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of IOCFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the taper on the valve side of the weld which prevented scanning from that side. In order to scan all of the required volume for this weld, the valve would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld. I (Examination Data is shown in Attachment A)

Relief Request 07-CN-004 Page 3 of 36 VI. Alternate Examinations or Testing Use of radiography (RT) to achieve more coverage has been evaluated. RT is less sensitive to service induced cracking and has not been subjected to the performance demonstration requirements in a manner similar to the ultrasonic method. Therefore, while RT could in most cases provide more coverage, the reduction in sensitivity and lack of performance demonstration mitigates its use.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item / Summary Number B09.011.020 was conducted using personnel qualified in accordance with ASME Section XI, Appendix VII.

The ultrasonic procedures, personnel and equipment used complied with the requirements of ASME Section XI, Appendix VIII, 1998 Edition through the 2000 Addenda as administered by the Performance Demonstration Initiative (PDI). In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found.

The piping containing weld 1NC28-11 is an ASME III, Class 1 line with a design temperature of 650'F and a design lpressure of 2500 psia. This weld is located inside the Unit I containment. The piping line containing this weld connects the safety injection (NI) pump IA discharge to the reactor coolant system hot leg lB. As such, the primary function of this piping is to serve as 1) the reactor coolant system pressure boundary during normal operation and 2) part of the flow path that provides ECCS injection from the NI system to the reactor coolant loop during accident conditions.

Weld INC28-1 1 is a circumferential butt weld on a 6" schedule 160 line just downstream of check valve 1NI134. The weld is between the 6" valve and a 450 (cut at 220) seamless, butt welded elbow. The elbow material is SA403 WP304 and the valve body is SA182 F316.

These materials are austenitic (18Cr-8Ni for SA403 WP304, 16Cr-12Ni-2Mo for SA182 F316) base materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due tochloride contamination and cracking in stagnant borated

Relief Request 07-CN-004 Page 4 of 36 systems. Chemistry limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for Stress Corrosion Cracking (SCC) are precluded. Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.

This piping is normally covered by metal reflective insulation. During each refueling outage, multiple walkdowns of containment are performed to determine the presence of external leakage. These walkdowns include a boric acid walkdown (PT/l/A/4150/001H) while the primary system remains at temperature and pressure (Mode 3). Other walkdowns performed during the outage are system engineer walkdowns (PEP 3.09),

operation walkdowns at 350 psi, 1000 psi and normal operation pressure (OP/1/A/6100/001) and the ASME XI, IWB 5220, Class A System Leakage Test Procedure MP/0/A/7650/088A. During these various walkdowns, any leakage from this weld would be recognized by active leakage or boron deposit buildups around the valve and mirror insulation.

In addition, leakage during operation at this weld location would be detected by various other leakage detection systemý available to the operator. These systems identified with plant technical specifications include:

a) Containment Atmosphere Particulate Radioactivity Monitor which would detect airborne radiological activity; b) Containment Ventilation Unit Condensate Drain Tank Level Monitor which collects and measures as unidentified leakage the moisture removed from the containment atmosphere; c) Containment Floor and Equipment Sump Level Monitors where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes.

d) A reactor coolant system water inventory balance is performed on a regular basis (i.e.

at least once every three days). The normal operating practice is toperform this computer based program on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems. A Plant Technical Specification requires system leakage from "unidentified" sources be maintained below I gpm; however, plant operation procedure (PT/I/A/4150/OOD, NC System Leakage Calculation) establishes an administrative limit of 0.15 gpm above which the source of leakage will be investigated.

Leakage as a result of a failed weld discussed in this section would show.up as unidentified leakage and subject to the 0.15 gpm administrative limit.

Other leakage detection parameters available to the operator include 1) Volume Control Tank (VCT) level changes, 2) VCT make-up frequencies, 3) Cold Leg Accumulator level

Relief Request 07-CN-004 Page 5 of 36 changes, 4) Containment Humidity indication and 5) Containment Air Temperature and Pressure variations.

These walkdowns and leakage detection systems provide a high level of confidence that any leakage would be promptly identified at this welded joint inside containment. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity of the piping.

References:

1) Weld Isometric CN"1NC-0028

2) Piping Isometric CN-1491-NCO58

3) Flow Diagram CN-1562-1.2

4) Flow Diagram CN-1553-1.0

5) Valve Drawing for INI134, CNM-1205.00-0063

6) Technical Specification 3.4.13, RCS Operational Leakage

7) Technical Specification 3.4.15, RCS Leakage Detection Instrumentation r

Relief Request 07-CN-004 Page 6 of 36 ASME Code Com ponent Affected Weld ID = INC31-1 Item / Summary Number = B09.011.030 Reactor Coolant System (NC)

NC System Valve IN1160 to Elbow Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable II. Applicable Code Requirement Table IWB-2500- 1, Examination Category B-J Item / Summary Number B9. 11 Figure JWB-2500-8 (c), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance Weld joint geometry and material selection caused limitations resulting in the inability to achieve the required coverage. The valve and elbow materials are stainless steel. This elbow has a diameter of 6.375 inches and a wall thickness of 0.719 inch. During the ultrasonic examination of this weld, 37.50% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 50% of the weld and base material on the elbow side; 60' shear wave scan from the elbow side perpendicular to the weld covered 50% of the weld and base material. In accordance with Duke Energy Procedure NDE-9 1, scan areas S i and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit covered 20% of the examination volume on the valve side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of 10CFR50.55 a (b)(2)(xv)(A)(l) which mandates scanning from four directions. The limitation was caused by the slope on the valve side of the weld which prevented scanning from that side. In order to scan all of the required volume for this weld, the valve would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld.

(Examination Data is shown in Attachment B)

Relief Request 07-CN-004 Page 7 of 36 VI. Alternate Examinations or Testing Use of radiography (RT) to achieve more coverage has been evaluated and discarded because RT is less sensitive to service induced cracking and has not been subjected to the performance demonstration requirements in a manner similar to the ultrasonic method.

While RT could in most cases provide more coverage the loss of sensitivity and lack of performance demonstration mitigates against its use.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item Summary Number B09.011.030 was conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII.

The ultrasonic procedures, personnel and equipment used complied with the requirements of ASME Section XI, Appendix VEII, 1998 Edition through the 2000 Addenda as administered by the Performance Demonstration Initiative (PDI),. In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found.

The piping containing weld 1NC31-1 is an ASME III, Class 1 line with a design temperature of 650'F and a design pressure of 2500 psia. This weld is located inside the Unit I containment. The piping line containing this weld connects the safety injection (NI) pump IB discharge to the reactor coolant system hot leg ID. As such, the primary function of this piping is to serve as 1) the reactor coolant system pressure boundary during normal operation and 2) part of the flow path that provides ECCS injection from the NI system to the reactor coolant loop during accident conditions.

Weld INC3 1-1 is a circumferential butt weld on a 6" schedule 160 line just downstream of check valve INIO 160. The weld is between the 6" valve and a 450 (cut at 220) seamless, butt welded elbow. The elbow material is SA403 WP304 and the valve body is SA182 F316.

These materials are austenitic (18Cr-8Ni for SA403 WP304, 16Cr-12Ni-2Mo for SA182 F316) base materials and a) have a high corrosion resistance with low'contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. However chemistry limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative

Relief Request.07-CN-004 Page 8 of 36 procedures at Catawba to ensure that any favorable conditions for Stress Corrosion Cracking (SCC) are precluded. Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.

'This piping is normally covered by metal reflective insulation. During each refueling outage, multiple walkdowns of containment are performed to determine the presence of external leakage. These walkdowns include a boric acid walkdown (PT/1/A/4150/001H) while the primary system remains at temperature and pressure (Mode 3). Other walkdowns performed during the outage are system engineer walkdowns (PEP 3.09),

operation walkdowns at 350 psi, 1000 psi and normal operation pressure (OP/l/A/6100/001) and the ASME XI, IWB 5220, Class A System Leakage Test Procedure MP/0/A/7650/088A. During these various walkdowns, any leakage from this weld would be recognized by active leakage or boron deposit buildups around the valve and mirror insulation.

In addition, leakage during operation at this weld location would be detected by various other leakage detection systems available to the operator. These systems identified with plant technical specifications include:

a) Containment Atmosphere Particulate Radioactivity Monitor which would detect airborne radiological activity' b) Containment Ventilation Unit .Condensate Drain Tank Level Monitor which collects and measures as unidentified leakage the moisture removed from the containment atmosphere; c) Containment Floor and Equipment Sump Level Monitors where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes.

d) A reactor coolant system water inventory balance is performed on a regular basis (i.e.

at least once every three days). The normal operating practice is to perform this computer based program on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems. A Plant Technical Specification requires system leakage from "unidentified" sources be maintained below 1 gpm; however, plant operation procedure (PT/1/A/4150/OO1D, NC System Leakage Calculation) establishes an administrative limit of 0.15 gpm above which the source of leakage will be investigated. Leakage as a result of a failed weld discussed in this section would show up as unidentified leakage and subject to the 0.15 gpm administrative limit.

Other leakage detection parameters available to the operator include 1) Volume Control Tank (VCT) level changes, 2) VCT make-up frequencies, 3) Cold Leg Accumulator level changes, 4) Containment Humidity indication and 5) Containment Air Temperature and Pressure variations.

Relief Request 07-CN-004 Page 9 of 36 These walkdowns and leakage detection systems provide a high level of confidence that any leakage would be promptly identified at this welded joint inside containment. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity of the piping.

References:

1) Weld Isometric CN-INC-0031

2) Piping Isometric CN-1491-NCO60

3) Flow Diagram CN-1562-1.2

4) Flow Diagram CN-1553-1.0

5) Valve Drawing for 1NI160, CNM-1205.00-0063

6) Technical Specification 3.4.13, RCS Operational Leakage

7) Technical Specification 3.4.15, RCS Leakage Detection Instrumentation

Relief Request 07-CN-004 Page 10 of 36 I. ASME Code Component Affected Weld ID = 1NI18-2 Item / Summary Number = B09.01 1.155 Safety Injection System (NI)

NI System Valve IN176A to Pipe Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III. Applicable Code Requirement Table IWB-2500-1, Examination Category B-J Item / Summary Number B9.11 Figure IWB-2500-8 (c), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance Weld joint geometry and material selection caused limitations resulting in the inability to achieve the required coverage. The valve and pipe materials are stainless steel. This weld has a diameter of 10.75 inches and a wall thickness of 1.0 inch. During the ultrasonic examination of this weld, 62.50% coverage of the required examination volume was obtained. Coverage was limited to the pipe side for 100% of weld length. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 100% of the weld and base material; 600 shear wave scan from the pipe side perpendicular to the weld covered 50% of the weld and base material in one direction perpendicular to the weld. In accordance with Duke Energy Procedure NDE-9 1, scan areas S I and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit covered 50% of the examination volume on the valve side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of 10CFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the slope on the valve side of the weld which prevented scanning from that side. In order to scan all of the required volume for this weld, the valve would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld.

(Examination Data is shown in Attachment C)

Relief Request 07-CN-004 Page 11 of 36 VI. Proposed Alternate Examinations or Testing Use of radiography (RT) to achieve more coverage has been evaluated and discarded because RT is less sensitive to service induced cracking and has not been subjected to the performance demonstration requirements in a manner similar to the ultrasonic method.

While RT could in most cases provide more coverage the loss of sensitivity and lack of performance demonstration mitigates against its use.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Ultrasonic examination of themweld for Item / Summary Number B09.011.155 was conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII.

The ultrasonic procedures, personnel and equipment used complied with the requirements of ASME Section XI, Appendix VIII, 1998 Edition through the 2000 Addenda as administered by the Performance Demonstration Initiative (PDI). In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found.

The piping containing weld IN118-2 is an ASME III, Class I line with a design temperature of 650'F and a design pressure of 2500 psia. This weld is located inside the Unit I containment. The associated piping line connects the cold leg accumulator 1C to the reactor coolant system cold leg IC. As such, the primary function of this piping is to serve as part of the flow path that provides ECCS injection from the NI system to the reactor coolant loop during accident conditions. The piping containing this weld is exposed to cold leg accumulator pressure of 650 psig and ambient containment temperature (approximately 100lF) during normal operating conditions.

Weld INI18-2 is a circumferential butt weld on a 10" line immediately downstream of motor operated gate valve 1NI076A. The weld is between the 10" valve and the 10 schedule 140 piping. The pipe material is SA376 TP316 and the valve body is SA182 F316.

These materials are austenitic (16Cr-12Ni-2Mo) base materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with.stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. However chemistry

Relief Request 07-CN-004 Page 12 of 36 limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for Stress Corrosion Cracking (SCC) are precluded.

Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.

This piping is not insulated. During each refueling outage, multiple walkdowns of containment are performed to determine the presence of external leakage. These walkdowns include a boric acid walkdown (PT/1/A/4150/001H) while the primary system remains at temperature and pressure (Mode 3). Other walkdowns performed during the outage are system engineer walkdowns (PEP 3.09), operation walkdowns at 350 psi, 1000 psi and normal operation pressure (OP/1/A/6100/001) and the ASME XI, IWB 5220, Class A System Leakage Test Procedure MP/O/A/7650/088A. During these various walkdowns, any leakage from this weld would be recognized by active leakage or boron deposit buildups around the valve and piping.

In addition, leakage during operation at this weld location would be detected primarily by a decrease in the cold leg accumulator level. The Containment Floor and Equipment Sump Level Monitors would also provide indication of leakage at this location. However, without primary valve leakage, reactor coolant inventory would not be affected by a through wall leak here. Thus leakage detection by the Containment Atmosphere Particulate Radioactivity Monitor, the Containment Ventilation Unit Condensate Drain Tank Level Monitor or reactor coolant system water inventory balance would not be as effective in leakage detection.

These walkdowns and leakage detection systems provide a high level of confidence that any leakage would be promptly identified at this welded joint inside containment. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity of the piping.

References:

1) Weld Isometric CN-INI-0018

2) Piping Isometric CN- 1491-NI046

3) Flow Diagram CN-1562-1.1

4) Valve Drawing for 1N1076A, CNM-1205.00-0071

6) Technical Specification 3.4.13, RCS Operational Leakage

7) Technical Specification 3.4.15, RCS Leakage Detection Instrumentation

Relief Request 07-CN-004 Page 13 of 36 I. ASME Code Component Affected Weld ID = lN1148-10 Item / Summary Number = B09.011.163 Safety Injection System (NI)

NI System Tee to Valve 1N181 Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III. Applicable Code Requirement Table TWB-2500-1, Examination Category B-J Item / Summary Number B9.11 Figure IWB-2500-8 (c), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance Weld joint geometry and material selection caused limitations resulting in the inability to achieve the required coverage. The valve and tee material is stainless steel. This weld has a diameter of 10.75 inches and a wall thickness of 1.0 inch. During the ultrasonic examination of this weld, 37.50% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 50% of the weld and base material; 60' shear wave scan from the pipe side perpendicularto the weld covered 50% of the weld and base material. In accordance with Duke Energy Procedure NDE-9 1, scan areas S I and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit covered 41.50% of the examination volume on the valve'side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of IOCFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the taper on the valve side of the weld which prevented scanning from that side. In order to scan all of the required volume for this weld, the valve would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld.

(Examination Data is shown in Attachment D)

Relief Request 07-CN-004 Page 14 of 36 VI. Alternate Examinations or Testing Use of radiography (RT) to achieve more.coverage has been evaluated and discarded because RT is less sensitive to service induced cracking and has not been subjected to the performance demonstration requirements in a manner similar to the ultrasonic method.

While RT could in most cases provide more coverage the loss of sensitivity and lack of performance demonstration mitigates against its use.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item / Summary Number B09.011.163 was conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII.

The ultrasonic procedures, personnel and equipment used complied with the requirements of ASME Section XI, Appendix VII, 1998 Edition through the 2000 Addenda as administered by the Performance Demonstration Initiative (PDI). In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found.

The piping containing weld IN1148-10 is an ASME II1, Class I line with a design temperature of 650'F and a design pressure of 2500 psia. This weld is located inside the Unit I containment. This piping line containing this weld connects the cold leg accumulator IC to the reactor coolant system and also ties the RHR pump discharge header to the RCL cold leg IC. As such, the primary function of this piping is to serve as part of the flow path that a) supplies ECCS injection from the NI and RHR systems to the reactor coolant loop during accident conditions and b) provides core decay heat removal during shutdown / startup operations. This line is stagnant during normal plant operation.

Weld 1N1148-10 is a circumferential butt-weld on a 10" schedule 140 line just downstream of check valve 1N10081. The weld is between the 10" valve and the run side of a 10" x 10" x 6" electronic fusion welded, reducing tee. The tee material is SA403 WP316 and the valve body is SA182 F316.

These materials are austenitic (16Cr-12Ni-2Mo) base materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. However chemistry limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure

Relief Request 07-CN-004 Page 15 of 36 that any favorable conditions for Stress Corrosion Cracking (SCC) are precluded.

Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this.material at this particular location within the system.

This piping is not insulated. During each refueling outage, multiple walkdowns of containment are performed to determine the presence of external leakage. These' walkdowns include a boric acid walkdown (PT/l/A/4150/001H) while the primary system remains at temperature and pressure (Mode 3). Other walkdowns performed during the outage are system engineer walkdowns (PEP 3.09), operation walkdowns at 350 psi, 1000 psi and normal operation pressure (OP/l/A/6100/001) and the ASME XI, IWB 5220, Class A System Leakage Test Procedure MP/O/A/7650/088A. During these various walkdowns, any leakage from this weld would be recognized by active leakage or boron deposit buildups around the valve and piping.

In addition, leakage during operation (assuming leakby of the primary isolation valve, IN10082) at this weld location would be detected by various other leakage detection systems available to the operator. (Note: without leakby of the primary isolation valve, leakage would be promptly identified through a continuous decline in the Cold Leg Accumulator level.) These systems identified with plant technical specifications include:

a) Containment Atmosphere Particulate Radioactivity Monitor which would detect airborne radiological activity; b) Containment Ventilation Unit Condensate Drain Tank Level Monitor which collects and measures as unidentified leakage the moisture removed from the containment atmosphere; c) Containment Floor and Equipment Sump Level Monitors where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes.

d) A reactor coolant system water inventory balance is performed on a regular basis (i.e. at least once every three days). The normal operating practice is to perform this computer based program on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems. A Plant Technical Specification requires system leakage from "unidentified" sources be maintained below 1 gpm; however, plant operation procedure (PT/l/A/4150/OOID, NC System Leakage Calculation) establishes an administrative limit of 0.15 gpm above which the source of leakage will be investigated. Leakage as a result of a failed weld discussed in this section would show up as unidentified leakage and subject to the 0.15 gpm administrative limit.

Other leakage detection parameters available to the operator include 1) Volume Control Tank (VCT) level changes, 2) VCT make-up frequencies, 3) Cold Leg Accumulator level changes, 4) Containment Humidity indication and 5) Containment Air Temperature and Pressure variations.

Relief Request 07-CN-004 Page 16 of 36 These walkdowns and leakage detection systems provide a high level of confidence that any leakage would be promptly identified at this welded joint inside containment. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity of the piping.

References:

1) Weld Isometric CN- INI-0 148

2) Piping Isometric CN- 1491-NI015

3) Flow Diagram CN-1562-1.1

4) Valve Drawing for IN1081, CNM-1205.00-0062

6) Technical Specification 3.4.13, RCS Operational Leakage

7) Technical Specification 3.4.15, RCS Leakage Detection Instrumentation

Relief Request 07-CN-004 Page 17 of 36 ASME Code Component Affected Weld ID = 1NI148-11 Item / Summary Number = B09.011.164 Safety Injection System (NI)

NI System Tee to Valve 1N182 Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III. Applicable Code Requirement Table IWB-2500-1, Examination Category B-J Item / Summary Number B9.11 Figure IWB-2500-8 (c), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance Weld joint geometry and material selection caused limitations resulting in the inability to achieve the required coverage. The valve and tee material is stainless steel. This weld has a diameter of 10.75 inches and a wall thickness of 1.0 inch. During the ultrasonic examination of this weld, 37.50% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 100% of the weld and base material; 60' shear wave scan from the tee side perpendicular to the weld covered 50% of the weld and base material. In accordance with Duke Energy Procedure NDE-9 1, scan areas S I and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 60' refracted longitudinal wave search unit covered 39.70% of the examination volume on the valve side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of IOCFR50.55 a (b)(2)(xv)(A)(l) which mandates scanning from four directions. The limitation was caused by the taper on the valve side of the weld which prevented scanning from that side. In order to scan all of the required volume for this weld, the valve would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld.

(Examination Data is shown in Attachment E)

Relief Request 07-CN-004 Page 18 of 36 VI. Alternate Examinations or Testing Use of radiography (RT) to achieve more coverage has been evaluated and discarded because RT is less sensitive to service induced cracking and has not been subjected to the performance demonstration requirements in a manner similar to the ultrasonic method.

While RT could in most cases provide more coverage the loss of sensitivity and lack of performance demonstration mitigates against its use.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item / Summary Number B09.011.164 was conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII.

The ultrasonic procedures, personnel and equipment used complied with the requirements of ASME Section XI, Appendix VIII, 1998 Edition through the 2000 Addenda as administered by the Performance Demonstration Initiative (PDI). In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found.

The piping containing weld 1N1148-11 is an ASME I, Class 1 line with a design temperature of 650'F and a design pressure of 2500 psia. This weld is located inside the Unit 1 containment. This piping line containing this weld connects the cold leg accumulator IC to the reactor coolant system and also ties the RHR pump discharge header to the RCL cold leg IC. As such, the primary function of this piping is to serve as part of the flow path that a) supplies ECCS injection from the NI and RHR systems to the reactor coolant loop during accident conditions and b) provides core decay heat removal during shutdown / startup operations. This line is normally stagnant during normal plant operation.

Weld IN1148-11 is a circumferential butt weld on a 10" schedule 140 line just upstream of check valve IN10082. The weld is between the 10" valve and the run side of a 10" x 10" x 6" electronic fusion welded, reducing tee. The tee material is SA403 WP316 and the valve body is SA182 F316.

These materials are austenitic (16Cr-12Ni-2Mo) base materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. However chemistry

Relief Request 07-CN-004 Page 19 of 36 limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for Stress Corrosion Cracking (SCC) are precluded.

Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.

This weld is at a mirror insulation boundary. During each refueling outage, multiple walkdowns of containment are performed to determine the presence of external leakage.

These walkdowns include a boric acid walkdown (PT/l/A/4150/001H) while the primary system remains at temperature and pressure (Mode 3). Other walkdowns performed during the outage are system engineer walkdowns (PEP 3.09), operation walkdowns at 350 psi, 1000 psi and normal operation pressure (OP/l/A/6100/001) and the ASME XI, IWB 5220, Class A System Leakage Test Procedure MP/0/A/7650/088A. During these various walkdowns, any leakage from this weld would be recognized by active leakage or boron deposit buildups around the valve, piping or mirror insulation.

In addition, leakage during operation (assuming leakby of the primary isolation valve, 1N10082,) at this weld location would be detected by various other leakage detection systems available to the operator. (Note: without leakby of the primary isolation valve, leakage would be promptly identified through a continuous decline in the Cold Leg Accumulator level.) These systems identified with plant technical specifications include:

a) Containment Atmosphere Particulate Radioactivity Monitor which would detect airborne radiological activity; b) Containment Ventilation Unit Condensate Drain Tank Level Monitor which collects and measures as unidentified leakage the moisture removed from the containment atmosphere; c) Containment Floor and Equipment Sump Level Monitors where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes.

d) A reactor coolant system water inventory balance is performed on a regular basis (i.e. at least once every three days). The normal operating practice is to perform this computer based program on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems. A Plant Technical Specification requires system leakage from "unidentified" sources be maintained below 1 gpm; however, plant operation procedure (PT/l/A/4150/OOD, NC System Leakage Calculation) establishes an administrative limit of 0.15 gpm above which the source.of leakage will be investigated. Leakage as a result of a failed weld discussed in this section would show up as unidentified leakage and subject to the 0.15 gpm administrative limit.

Relief Request 07-CN-004 Page 20 of 36 Other leakage detection parameters available to the operator include 1) Volume Control Tank (VCT) level changes, 2) VCT make-up frequencies, 3) Cold Leg Accumulator level changes, 4) Containment Humidity indication and 5) Containment Air Temperature and Pressure variations.

These walkdowns and leakage detection systems provide a high level of confidence that any leakage would be promptly identified at this welded joint inside containment. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity of the piping.

References:

1) Weld Isometric CN-INI-0 148 2). Piping Isometric CN- 1491-NI015

3) Flow Diagram CN-1562-l.1

4) Valve Drawing for 1N1082, CNM-1205.00-0062

6) Technical Specification 3.4.13, RCS Operational Leakage

7) Technical Specification 3.4.15, RCS Leakage Detection Instrumentation

Relief Request 07-CN-004 Page 21 of 36

1. ASME Code Component Affected Weld ID = 1SWRF- 1-OUTLET Item / Summary Number = C02.011.003 Chemical and Volume Control System (NV)

NV System Nozzle to Shell Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III. Applicable Code Requirement Table IWC-2500-1, Examination Category C-B Item / Summary Number C2.11 Figure IWC-2500-3 (a), 100% Volume Coverage of Examination Volume A-B Code Case N-460, Greater than 90% Volume Coverage of Examination Volume A-B IV. & V. Impracticality/Burden Caused by Code Compliance The vessel, nozzle and weld materials are stainless steel. The nozzle side of the weld has a diameter of 2.875". During the Liquid Penetrant examination of this weld, 74.60%

coverage of the required surface examination area was obtained. The areas that were not examined were inaccessible due to the proximity of the Seal Water Filter Housing Legs to the Nozzle to Shell Weld. Two of the four Housing Legs are welded to the vessel in a manner that covers a portion of the required base metal on the vessel side of the weld at both 90 °and 270' as shown on the surface exam data in Attachment F. The' Liquid Penetrant exam performed covered 100% of the weld and the required base metal on the nozzle side of the weld. The required area of base metal on the vessel side of the weld was examined from 350' to 100 and 170' to 1900; however the base metal from 10' to 1700 and 190' to 3500 was inaccessible due to the legs. In order to perform a Liquid Penetrant exam on all of the required surfaces, the welds attaching the legs to the shell would have to be cut out and the legs removed, which is impractical. There were no recordable indications found during the inspection of this weld.

(Examination Data is shown in Attachment F)

VI. Alternate Examinations or Testing Use of the ultrasonic inspection method was evaluated for inspecting the limited area.

Due to the stainless steel material and configuration, of the component and the close proximity of the legs to the weld, the area was not accessible for ultrasonic examination.

Relief Request 07-CN-004 Page 22 of 36 A Pressure Test and Visual Examination VT-2 were completed on this component with no observed leakage.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Liquid Penetrant examination of the weld for Item / Summary Number C02.011.003 was conducted using personnel qualified in accordance with ASME Section XI, 1998 Edition through 2000 Addenda. The Liquid Penetrant examination was performed on the weld using exam procedures that are in accordance with ASME Section XI. No recordable or rejectable indications were found.

Weld lSWRF-I-OUTLET is located on the outlet side of the Unit I Seal Water Return Filter. This filter is an ASME III, Class 2 component with a design temperature of 250°F and a design pressure of 315 psia. The filter is part of the letdown flowpath of the NV (Chemical and Volume Control) System and is located in room 451 on Elevation 560 of the auxiliary building.

Weld I SWRF- 1-OUTLET is a circumferential nozzle weld connecting the shell of the filter housing to the 2" outlet nozzle. The shell material is SA312 TP304 fabricated from a 6" schedule 10S pipe. The nozzle material is SA479 TP304. These materials are austenitic (18Cr-8Ni) base materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking Stress Corrosion Cracking (SCC) due to chloride contamination and cracking in stagnant borated systems. Chemistry limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for SCC are precluded. Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.

During normal operation, the pressure at the filter is approximately 40 psi. This 1w pressure and the related low operating stresses minimize the susceptibility to pressure boundary leakage. If a failure were to occur at this location, it would be identified through the periodic reactor coolant system water inventory balance or through changes in volume control tank levels. Any failure resulting in leakage or evidence of leakage would also be detected during periodic filter cartridge changeouts.

Relief Request 07-CN-004 Page 23 of 36 The combination of low operating stresses and the small margin between the required and achieved surface examination coverage indicate that the likelihood of pressure boundary failure at this location is small. Furthermore, should a failure occur, the leak would be promptly identified. As a result, the limited surface examination coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity of the filter.

References:

1) Seal Water Return Filter Drawing CNM- 1201.04-0078

2) Flow Diagram CN-1554-1.6

3) Auxiliary Building Drawing CN-1200-8.2

4) Auxiliary Building Drawing CN-1220-27

5) Technical Specification 3.4.13, RCS Operational Leakage

Relief Request 07-CN-004 Page 24 of 36

1. ASME Code Component Affected Weld ID = 1ND3-1 Item / Summary Number = C05.011.065 Residual Heat Removal System (ND)

ND System Valve IN1185A to Pipe Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III. Applicable Code Requirement Table IWC-2500- 1, Examination Category C-F-I Item / Summary Number C5.1 1 Figure IWC-2500-7 (a), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance Weld joint geometry and material selection caused limitations resulting in the inability to achieve the required coverage. The valve and pipe materials are stainless steel. This weld has a diameter of 18 inches and a wall thickness of 0.562 inch. During the ultrasonic examination of this weld, 37.50% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave Circumferential scans, both clockwise and counter-clockwise covered 100% of the weld and base material; 600 shear wave scan from the pipe side perpendicular to the weld covered 50% of the weld and base material. In accordance with Duke Energy Procedure NDE-9 1, scan areas S1 and 52 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit and a 700 shear wave covered 3.50% of the examination volume on the valve side and from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of IOCFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the taper on the valve side of the weld which prevented scanning from that side. In order to scan all of the required volume for this weld, the valve would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld.

(Examination Data is shown in Attachment G)

Relief Request 07-CN-004 Page 25 of 36 VI. Alternate Examinations or Testing

.Use of radiography (RT) to achieve more coverage has been evaluated and discarded because RT is less sensitive to service induced cracking and has not been subjected to the performance demonstration requirements in a manner similar to the ultrasonic method.

While RT could in most cases provide more coverage the loss of sensitivity and lack of performance demonstration mitigates against its use.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item / Summary Number C05.011.065 was conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII.

The ultrasonic procedures, personnel and equipment used complied with the requirements of ASME Section XI, Appendix VIII, 1998 Edition through the 2000 Addenda as administered by the Performance Demonstration Initiative (PDI),. In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section Xl: No recordable or reportable indications were found.

Weld 1ND3-1 is between 18" schedule 40 Electronic Fusion Welded piping and valve 1NIl 85A. The associated piping is ASME Class 2 piping with a design temperature of 400°F and design pressure of 540 psia. The weld is in the flowpath from the Train 1A, ECCS sump to the suction of the ND Pump IA. At this location, this weld acts to maintain the pressure boundary 1) as part of ECCS flow path under accident conditions and 2) as part of the core heat removal flow path during startup / shutdown operations. The pipe containing this weld is located in the auxiliary building and is at ambient temperature conditions and statically pressurized during normal operation.

The subject weld is between the valve body of 1N1I 85A (SAl 82 F316 body) and 18" SA358, Class 1, TP304, EFW schedule 40 piping. These materials are austenitic (18Cr-8Ni for SA358 TP304, 16Cr-12Ni-2Mo for SA182 F316) base materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. However chemistry limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure

Relief Request 07-CN-004 Page 26 of 36 that any favorable conditions for Stress Corrosion Cracking (SCC) are precluded.

Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.

This piping is not insulated and is located in Room 217 (Unit 1 Mechanical Penetration Room) on the 543 ft elevation of the auxiliary building. Leakage during normal operation would be seen as active leakage due to low fluid temperature conditions and readily identified on the floor below. The room is accessible during normal operation and is within the scope of daily operation walkdowns. Periodic system engineer walkdowns are also performed that include leakage identification on the ND system.

In addition to walkdowns, an operational leak rate determination test (PT/1/A/4203/003) for the ND system is performed with the system pressurized on an eighteen month frequency. An ASME XI, IWC-5220 system leakage test (Procedure MP/O/A/7650/088A) is also performed every ISI period. Either of these tests would identify leakage at this particular weld.

These walkdowns and leakage tests provide a high level of confidence that any leakage would be promptly identified at this welded joint in the Unit I Mechanical Penetration Room of the Auxiliary Building. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity for the ND piping.

References:

1) Weld Isometric CN-IND-0003

2) Piping Isometric CN-1492-NDOOI

3) Piping Isometric CN-1492-ND002

4) Flow Diagram CN-1561-1.0

5) Flow Diagram CN-1562-1.3

6) Valve Drawing for 1N1185A, CNM-1205.00-0073

Relief Request 07-CN-004 Page 27 of 36

1. ASME Code Component Affected Weld ID = 1NI1-12 Item / Summary Number = C05.011.105 Safety Injection System (NI)

NI System Pipe to Valve 1N1180 Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III. Applicable Code Requirement Table IWC-2500-1, Examination Category C-F- I Item / Summary Number C5.11 Figure TWC-2500-7 (a), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance Weld joint geometry and material selection caused limitations resulting in the inability to achieve the required coverage. The valve and pipe material is stainless steel. This weld has a diameter of 6.625 inches and a wall thickness of .719 inch. During the ultrasonic examination of this weld, 37.50% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 50% of the weld and base material; 600 shear wave scan from the pipe side perpendicular to the weld covered 50% of the weld and base material. In accordance with Duke Energy Procedure NDE-9 1, scan areas S I and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit covered 18.90% of the examination volume on the valve side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of IOCFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the taper on the valve side of the weld which prevented scanning from that side. In order to scan all of the required volume for this weld, the valve would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical.

(Examination Data is shown in Attachment H)

Relief Request 07-CN-004 Page 28 of 36 VI. Alternate Examinations or Testing Use of radiography (RT) to achieve more coverage has been evaluated and discarded because RT is less sensitive to service induced cracking and has not been subjected to the performance demonstration requirements in a manner similar to the ultrasonic method.

While RT could in most cases provide more coverage the loss of sensitivity and lack of performance demonstration mitigates against its use.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item / Summary Number C05.011.105 was conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII.

The ultrasonic procedures, personnel and equipment used complied with the requirements of ASME Section XI, Appendix VIII as administered by the Performance Demonstration Initiative (PDI), 1998 Edition through the 2000 Addenda. In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found.

The piping containing weld INII-12 is an ASME III, Class 2 line with a design temperature of 650'F and a design pressure of 2500 psia. This weld is located inside the Unit I containment. This piping line containing this weld connects the discharge of the safety injection pumps IA and IB to the reactor coolant system cold leg lB. As such, the primary function of this piping is to serve as part of the flow path that supplies ECCS cold leg injection from the NI pumps to the reactor coolant loop lB during accident conditions.

The pressure inthis line is typically limited to the static head from the Refueling Water Storage Tank.

Weld INII-12 is a circumferential butt weld on a 6" schedule 160 line just upstream of check valve 1NI180. The weld is between the 6" valve and the seamless piping. The piping material is SA376 TP304 and the valve body is SA182 F316.

These materials are austenitic (18Cr-8Ni for SA376 TP304, 16Cr-12Ni-2Mo for SA182 F316) base materials and a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. However chemistry limits on chlorides, fluorides and sulfides and dissolved

Relief Request 07-CN-004 Page 29 of 36 oxygen are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for Stress Corrosion Cracking (SCC) are precluded. Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.

This piping is not insulated. During each refueling outage, multiple walkdowns of containment are performed to determine the presence of external leakage. These walkdowns include a boric acid walkdown (PT/l/A/4150/001H) while the primary system remains at temperature and pressure (Mode 3). Other walkdowns performed during the outage are system engineer walkdowns (PEP 3.09), operation walkdowns at 350 psi, 1000 psi and normal operation pressure (OP/1/A/6100/001). An ASME XI, IWC-5220 Class B leakage test Procedure (MP/0/A/7650/088A) is performed once per period. This weld would be recognized by active leakage or boron deposit buildups around the valve and piping.

In addition, leakage during operation at this weld location would be detected by various other leakage detection systems available to'the operator. The primary detection method at this location is the Containment Floor and Equipment Sump Level Monitors where unidentified accumulated water on the containment floor would be monitored and evaluated as sump level changes.

These walkdowns and the leakage detection system provide a high level of confidence that any leakage would be promptly identified at this welded joint inside containment. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity of the piping.

References:

1) Weld Isometric CN- INI-0001

2) Piping Isometric CN- 149 1-NIO 11

3) Flow Diagram CN-1562-l.1

4) Flow Diagram CN-1562-1.3

5) Valve Drawing for 1NI180, CNM-1205.00-0063

6) Technical Specification 3.4.13, RCS Operational Leakage

7) Technical Specification 3.4.15, RCS Leakage Detection Instrumentation

Relief Request 07-CN-004 Page 30 of 36 ASME Code Component Affected Weld ID = INV-309-INLET Item / Summary Number = C05.021.146 Chemical and Volume Control System (NV)

NV System Valve Body to Concentric Reducer Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable III. Applicable Code Requirement Table 1WC-2500-1, Examination Category C-F-I Item / Summary Number C5.21 Figure IWC-2500-7 (a), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance Weld joint geometry and material selection caused limitations resulting in the inability to achieve the required coverage. The valve and reducer material is stainless steel. This weld has a diameter of 2.375 inches and a wall thickness of .344 inches. During the ultrasonic examination of this weld, 37.50% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 50% of the weld and base material; 70' shear wave scan from the pipe side perpendicular to the weld covered 50% of the weld and base material. In accordance with Duke Energy Procedure NDE-91, scan areas S I' and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 600 refracted longitudinal wave search unit covered 50% of the examination volume on the valve side from one direction .

perpendicular to the weld but is not included in the coverage calculations because of the requirements of 10CFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the taper on the valve side of the weld which prevented scanning from that side. In order to scan all of the required volume for this weld, the valve would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld.

(Examination Data is shown in Attachment I)

Relief Request 07-CN-004 Page 31 of 36 VI. Alternate Examinations or Testing Use of radiography (RT) to achieve more coverage has been evaluated and discarded because RT is less sensitive to service induced cracking and has not been subjected to the performance demonstration requirements in a manner similar to the ultrasonic method.

While RT could in most cases provide more coverage the loss of sensitivity and lack of performance demonstration mitigates against its use.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item / Summary Number C05.021.146 was conducted using personnel, qualified in accordance with ASME Section XI, Appendix VII.

The ultrasonic procedures, personnel and equipment used complied with the requirements of ASME Section XI, Appendix VIII as administered by the Performance Demonstration Initiative (PDI), 1998 Edition through the 2000 Addenda. In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found.

Weld INV-309-INLET is between a 2" diaphragm actuated control valve (INV309) and a 3" x 2" concentric reducer. The weld is downstream of the Centrifugal Charging.(NV)

Pumps on ASME Class.2 piping with a design temperature of 2500 F and design pressure of 2750 psia. The pipe containing this weld is located in the auxiliary building and is pressurized during normal operation. This weld maintains the pressure boundary 1) as part of normal charging flowpath and 2) as part of the ECCS flow path boundary under accident conditions.

The subject weld is between a seamless pipe fitting component made from SA403 WP316 material and a valve body (SA351-CF8M). These materials (16Cr-12Ni-2Mo) are austenitic base materials that a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. However chemistry limits on chlorides, fluorides and sulfides are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for Stress Corrosion Cracking (SCC) are precluded.

Additionally, controls on welding filler'material consistent with Regulatory Guide 1.31

Relief Request 07-CN-004 Page 32 of 36 J

also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.

This piping is not insulated and is located in Room 233 (Reciprocal Charging Pump Room) on the 543 ft elevation of the auxiliary building. Leakage during normal operation would be seen as active leakage due to low fluid temperature conditions and readily identified on the floor below. The room is accessible during normal operation and is within the scope of daily operation walkdowns. Furthermore, this weld is part of the NC system mass balance performed daily. Periodic system engineer walkdowns are also performed that include leakage identification on the NV system.

In addition to walkdowns, an operational leak rate test (PT/1/A/4206/006) for the NV system is performed with the system pressurized on an eighteenth month frequency. An ASME XI, IWC-5220 Class B leakage test Procedure (MP/O/A/7650/088A) is performed once per period. Either of these tests would identify leakage at this particular weld.

These walkdowns and leakage tests provide a high level of confidence that any leakage would be promptly identified at this welded joint in the Reciprocal Charging Pump Room of the Auxiliary Building. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity for the NV piping.

References:

1) Flow Diagram CN-1554-1.2

2) Valve Drawing for INV309, CNM-1205.06-0048

Relief Request 07-CN-004 Page 33 of 36

1. ASME Code Component Affected Weld ID = INV-309-OUTLET Item / Summary Number = C05.021.147 Chemical and Volume Control System (NV)

NV System Valve Body to Concentric Reducer Circumferential Weld II. Applicable Code Edition and Addenda ASME Section XI Code - 1998 Edition thru the 2000 Addenda Code Case N-460 is applicable -

III. Applicable Code Requirement Table IWC-2500- 1, Examination Category C-F-I Item / Summary Number C5.21 Figure IWC-2500-7 (a), 100% Volume Coverage of Examination Volume C-D-E-F Code Case N-460, Greater than 90% Volume Coverage of Examination Volume C-D-E-F IV. & V. Impracticality/Burden Caused by Code Compliance Weld joint geometry and material selection caused limitations resulting in the inability to achieve the required coverage. The valve and reducer material is stainless steel. This weld has a diameter of 2.375 inches and a wall thickness of .344 inches. During the ultrasonic examination of this weld, 37.50% coverage of the required examination volume was obtained. The percentage of coverage represents the aggregate coverage from all scans performed on the weld and adjacent base material. The coverage from each scan was as follows: 450 shear wave circumferential scans, both clockwise and counter-clockwise covered 50% of the weld and base material; 600 shear wave scan from the pipe side perpendicular to the weld covered 50% of the weld and base material. In accordance with Duke Energy Procedure NDE-9 1, scan areas S1 and S2 are defined as scans perpendicular to the weld and scan areas S3 and S4 are the clockwise and counter-clockwise scans parallel to the weld. A supplemental scan using a 700 refracted longitudinal wave search unit covered 50% of the examination volume on the valve side from one direction perpendicular to the weld but is not included in the coverage calculations because of the requirements of IOCFR50.55 a (b)(2)(xv)(A)(1) which mandates scanning from four directions. The limitation was caused by the taper on the valve side of the weld which prevented scanning from that side. In order to scan all of the required volume for this weld, the valve would have to be redesigned and replaced to allow scanning from both sides of the weld, which is impractical. There were no recordable indications found during the inspection of this weld.

(Examination Data is shown in Attachment J)

Relief Request 07-CN-004 Page 34 of 36 VI. Alternate Examinations or Testing Use of radiography (RT) to achieve more coverage has been evaluated and discarded because RT is less sensitive to service induced cracking and has not been subjected to the performance demonstration requirements in a manner similar to the ultrasonic method.

While RT could in most cases provide more coverage the loss of sensitivity and lack of performance demonstration mitigates against its use.

VII. Implementation Schedule and Duration No alternative examinations are planned for the weld during the current inspection interval.

VIII. Justification for Granting Relief Ultrasonic examination of the weld for Item / Summary Number C05.021.147 was conducted using personnel, qualified in accordance with ASME Section XI, Appendix VH.

The ultrasonic procedures, personnel and equipment used complied with the requirements of ASME Section XI, Appendix VIII as administered by the Performance Demonstration Initiative (PDI), 1998 Edition through the 2000 Addenda. In addition, a dye penetrant examination was performed on the weld in accordance with the ASME Section XI. No recordable or reportable indications were found.

Weld 1NV-309-OUTLET is between a 2" diaphragm actuated control valve (INV309) and a 3" x 2" concentric reducer. The weld is downstream of the Centrifugal Charging (NV)

Pumps on ASME Class 2 piping with a design temperature of 250'F and design pressure of 2750 psia. The pipe containing this weld is located in the auxiliary building and is pressurized during normal operation. This weld maintains the pressure boundary 1) as part of normal charging flowpath and 2) as part of the ECCS flow path boundary under accident conditions.

The subject weld is between a seamless pipe fitting component made from SA403 WP316 material and a valve body (SA351-CF8M). These materials (16Cr-12Ni-2Mo) are austenitic base materials that a) have a high corrosion resistance with low contribution of corrosion products to the coolant, b) have good mechanical properties and c) are highly weldable. Very few service induced problems with stainless steel in PWR primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking due to chloride contamination and cracking in stagnant borated systems. However chemistry limits on chlorides, fluorides and sulfides are controlled by Selected Licensee Commitment (SLC) and other administrative procedures at Catawba to ensure that any favorable conditions for Stress Corrosion Cracking (SCC) are precluded.

Additionally, controls on welding filler material consistent with Regulatory Guide 1.31 also have served to limit the susceptibility of these welds to SCC. No other known

Relief Request 07-CN-004 Page 35 of 36 degradation mechanisms are applicable to this material at this particular location within the system.

This piping is not insulated and is located in Room 233 (Reciprocal Charging Pump Room) on the 543 ft elevation of the auxiliary building. Leakage during normal operation would be seen as active leakage due to low fluid temperature conditions and readily identified on the floor below. The room is accessible during normal operation and is within the scope of daily operation walkdowns. Periodic system engineer walkdowns are also performed that include leakage identification on the NV. system.

In addition to walkdowns, an operational leak rate test (PT/l/A/4206/006) for the NV system is performed with the system pressurized on an eighteenth month frequency. An ASME XI, IWC-5220 Class B leakage test Procedure (MP/O/A/7650/088A) is performed once per period. Either of these tests would identify leakage at this particular weld.

These walkdowns and leakage tests provide a high level of confidence that any leakage would be promptly identified at this welded joint in the Reciprocal Charging Pump Room of the Auxiliary Building. As a result, the limited volumetric coverage associated with this particular weld has no significant impact on the continued assurance of structural integrity for the NV piping.

References:

1) Flow Diagram CN-1554-1.2

2) Valve Drawing for 1NV309, CNM-1205.06-0048

Relief Request 07-CN-004 Page 36 of 36 IX. Other Information The following individuals contributed to the development of this relief request:

James J. McArdle (Principal UT NDE Level TIf Examiner), T. L. Tucker (NDE Level III PT) provided Sections mI, IV, V, VI, VII and part of Section VIII.

W.O. Callaway (Catawba Engineering) provided part of Section VIII.

Andy Hogge (Catawba ISI Plan Manager) compiled the remaining sections.

Request for Relief 07-CN-004 Attachment A Weld 1NC28-11 Number of Pages = 4

UT Pipe Weld Examination Site/Unit: Catawba / 1 Procedure: PDI-UT-2 Outage No.: CNS1-16 Summary No.: B09.011.020 Procedure Rev.: IC Report No.: UT-06-662 Workscope: ISl Work Order No.: 01121681 Page: 1 of 4 Code: 1998 thru 2000 Addenda Cat./Item: B-J- /B9.111.20 Location:

Drawing No.: CN-1NC-28

Description:

Elbow to Valve 1NI134 System ID: NC Component ID: B09.011.020/1 NC28-11 Size/Length: N/A Thickness/Diameter: .719/6.0 Limitations: Yes-See Attached Limitation Report Start Time: 1228 Finish Time: 1320 Examination Surface: Inside rD Outside F] Surface Condition: GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGELII Batch No.: 06125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32808 Surface Terr P.: 64 °F Cal. Report No.: CAL-06-646, CAL-06-647, CAL-06-648 Angle Used 0 45 45T 60 60L Scanning dB 41.5 41.5 58.3 60.0 Indication(s): Yes [ No W Scan Coverage: Upstream Downstrearr R[ CW~ WCC WI Comments:

Results: Accept W Reject IInfo D Initial Section XI Exam Percent Of Coverage Obtained > 90%: No 35.1% Reviewed Previous Data: No 62~- 6V-e9 ~

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: B09.011.020 Component ID 1NC28-11 remarks:

Z NO SCAN SURFACE BEAM DIRECTION Valve Configuration F-- LIMITED SCAN El1 [2 [1 -2 cw ccw FROM L N/A to L N/A INCHES FROM WO C/L-,5 to BEYOND ANGLE: El 0 Z 45 Z 60 other FROM 0 DEG to 36o DEG El NO SCAN SURFACE - BEAM DIRECTION Adjacent Weld Z LIMITED SCAN Z 1 -- 2 7l 1 Z2 E] cw D ccw FROM L 13.75 to L 17.75 INCHES FROM WO CfL+1.4 to BEYOND ANGLE: El 0 [] 45 Z 60 other 60L FROM N/A DEG to N/A DEG El NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN El1 El2 El 1 E2 -cw E- ccw FROM L to L INCHES FROM WO to ANGLE: E] 0 El 45 El 60 other FROM

• DEG to DEG E-l NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN l1 -- 2 l1 -- 2 E] cw l ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: EJ 0 Ij 45 [] 60 other FROM DEG to DEG Z yes El No Prepared By: Jay Eaton Level: 11, Date: 12/10/06 Sheet Z- of I Reviewed By: "i.1.A-f/Y!_ Date: aAuthorized

[/"**Ispc !i2" **\ Date: x . ,4/%

Item No: B09.011.020 Weld No: 1NC28-11 Weld Length = 21"

%weld length examined from SI side = (21"- 4") / 21" x 100= 81%

% of weld length limited due to adjacent weld = 100 - 81 = 19%

SI = Elbow = 40.5% (81% of the length x 50% of required volume)

- 0.0% (19% of the length x 0% of required volume)

- 40.5%

S2 Valve = 0% (0% of the length x 0% of required volume)

S3 CW = 50% (100% of the length x 50% of required volume)

S4 = CCW 50% (100% of the length x 50% of required volume)

Total = 140.5 I 4 = 35.1 % Aggregate Coverage Inspector / Date: ,' z - *'-d6 Page -3 of f'

Item No. B09.011.020 Weld No. 1NC28-11 600 RLWave 600 Shear Scale: I"= Ii, Pipe Valve S1 S2 No Coverage Claimed Coverage Claimed = 50%

Supplemental coverage with 600 RL Wave Only See Note:

Note: 600 RL scan not included in percentage coverage due to requirements of 10CFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 60' RL obtained 22.2% coverage in one axial direction.

Weld 1NC28-11 2"

Surf. 2- Valve Plan View - Not to Scale Limited scan from Surface 1 - 2" on each side of the intrados of the elbow for a total of 4".

Inspector /Date: *

.It

- Page 'y of ___i

Request for Relief 07-CN-004 Attachment B Weld 1NC31-1 Number of Pages = 3

Duke UT Pipe Weld Examination Site/Unit: Catawba / 1 Procedure: NDE-600 Outage No.: CNS1-16 Summary No.: B109.011.030 Procedure Rev.: - 17 Report No.: UT-06-667 Workscope: ISI Work Order No.: 01121680 Page: 1 of 3 Code: 1998 thru 2000 Addenda Cat./Item: B-J-/B9.11.30 Location:

Drawing No.: CN-1NC-31

Description:

Valve (1NI160)to Elbow System ID: NC Component ID: B09.011.030/1NC31-1 Size/Length: N/A Thickness/Diameter: .719 / 6.0 Limitations: Yes - See Attached Limitation Report Start Time: 1345 Finish Time: 1406 Examination Surface: Inside D] Outside n] Surface Condition: AS GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 06125 Temp. Tool Mfg.: FISHER Serial No.: MCNDE 27220 Surface Temp.: 75 OF Cal. Report No.: CAL-06-652, CAL-06-653, CAL-06-654 Angle Used 0 45 45T 60 60L Scanning dB 46 42.9 62.2 Indication(s): Yes [ No nv Scan Coverage: Upstream [] Downstream [ CW [] CCW [

Comments:

Results: Accept k Reject n Info n Percent Of Coverage Obtained > 90%: No - 37.5 % Reviewed Previous Data: Yes Examiner Level ii.N .Signature -- , Date Reviewer 12/12/2006/_ Signature,* Date Mauldin, Larry E.

Examiner Level II-N j i nre Date Site Review Signature Date Day, John, C. i/ L 12/12/2006 N/A Other Level N/A / Signatu&'e Date ANII Review .. ignature Date N/A __ __ _ __ _ __ _ __ __ _ __ _ __ _

ee ,,/7-

ý1701ý e

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: B09.011.030 Component ID 1NC31-1 remarks:

[ NO SCAN SURFACE BEAM DIRECTION Due to Valve Configuration DLIMITED SCAN ] 1 Z 112 2Zcw Z ccw FROM L N/A to L N/A INCHES FROM WO CL-.6. to Beyond ANGLE: II 0 Z 45 Z 60 other FROM o DEC to 360 DEC I-I NO SCAN SURFACE BEAM DIRECTION

-]LIMITED SCAN -1 [-]2 ii- 1 E 2 E cw ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 II 45 El 60 other FROM DEC to DEC r- NO SCAN SURFACE BEAM DIRECTION

-LIMITED SCAN [-i 1 [1 2 0 1 - 2 ] cw r] ccw FROM L to L INCHES FROM WO to ANGLE: lj 0 El 45 El 60 other FROM DEG to DEG E-l NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN [-7 1 - 2 El 1 E- 2 cw Elccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: El 0 El 45 7fiO other FROM_ DEG to DEG El yes Z No Prepared By: Larry MaLudir . ' _7 . evel: Date: 12-12-2006 Sheet .2 of 3 Reviewed By: Date: Authorized Inspector: Z*_ Date:

Item No. B09.011.030 Weld No. INC31-1 600 RLWave 600 SI Scale: 1" = 1" Valve S2 Coverage Claimed = 50% No Coverage Claimed Supplemental coverage with 600 RL Wave Only See Note:

Note: 60' RL scan not included in percentage coverage due to requirements of 10CFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 600 RL obtained 20% coverage in one axial direction.

% Coverage Calculations

/"1 S 1.= Elbow = 50% (100% of the length x 50% of the volume)

$2, = Valve = 0% (0% of the length x 0% of the volume)

S3 = CW = 50% (100% of the length x 50% of the volume)

S4 = CCW = 150% (100% of the length x 50% of the volume)

Total =150/4 = 37.5 % Aggregate Coverage Inspector / Date : At /g De j7tt Page 5 of

Request for Relief 07-CN-004 Attachment C Weld 1NI18-2 Number of Pages = 3

UT Pipe Weid -Examcini0a ion Site/Unit: Catawba / 1 -.... Pr.cedu re...

... -PDIU.T-2 Outage No.: CNS1-16 Summary No.: BO9.011.155 ...Procedure; Rev,: ..,-. - - . C Report No.: UT-06-625 Workscope: Is' Work Order No.: 01121677 Page: 1 of 3 Code: 1998 thru 2000 Addenda Cat./Item: .B.. /B9.11.155 .. Location:

Drawing No.: CN-1NI-18

Description:

__Valve.(1N.7dA) t -Pipe System ID: NI Component ID: B09.011.155/1N118-2 Size/Length: N/A Thickness/Diameter: 1.0 / 10.0 Limitations: Yes - See Attached Limitation Report

• Start Time: 1350 Finish Time: 1420 Examination Surface: Inside D Outside [] Surface Condition: GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 06125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32808- . Surface Temp.: 77 'F Cal. Report No.: CAL-06-607, CAL-06-608, CAL-0-6-:609 Angle Used 0 45 45T 60 60L Scanning dB 31.0 31.0 40.0 66.3 Indication(s): Yes D] No F] Scan Coverage: Upst ream .. Downstream [ CW R] CCW R Comments:

Previously recorded indications were verified @ below recordable amplitude ..... .

Results: Accept fv Reject F Info E]

Percent Of Coverage Obtained > 90%: No - 62.5% Reviewed Previous Data: .... ... Yes ....

Examiner Tucker, David Level Il-N ,jSig* /Dae ie Signature K. 'J /**____ 1*-/

12/11/200,61 *:.*,: LAN.... t*'3-71 0Dater

_ZA 0)

Examiner Level II-N- Signa*,ture Dat te.Rjeeview .... " Signature Date Ransom, Greg -..1.2/1-12*. f.*6-0A_=.

Other Level N/A Signature - Date, ANKITIjevw. Signature Date rN/A.

/ý &z.4E7_ ~6-6/ 6 7- ew-ee '246  ;ý?-

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: B09.011.155 Component ID 1N118-2 remarks:

N NO SCAN SURFACE BEAM DIRECTION Valve Configuration I- LIMITED SCAN r0 1 2 l 1 [] 2 El cw -- ccw FROM L N/A to L N/A INCHES FROM WO C/L-.55 to BEYOND ANGLE: Ej 0 [] 45 Z 60 other 60L FROM 0 DEG to 360 DEG

-- NO SCAN SURFACE BEAM DIRECTION F-] LIMITED SCAN i [2 1 2 [] cw --1 ccw FROM L to L INCHES FROM WO to ANGLE: E:1 0 [] 45 F- 60 other FROM DEG to DEG F1- NO SCAN SURFACE BEAM DIRECTION F-1 LIMITED SCAN L--- 1'2 i-1 -2 ] cw i ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 F-1 45 Li 60 other FROM DEG to DEG Fii NO SCAN SURFACE BEAM DIRECTION F-1 LIMITED SCAN L-71 -2 i"i1 2t -- cw -Iccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: E 0 E] 45 1j60/. her FROM / DEGto DEG Z yes -- No Prepared By: Jay Eaton Level: III: Date: 123/06 Sheet - of D3 Reviewed By: Date: Authorized Inspector:.,._,...2.7 Date: , ,

J

Item No. B09.011.155 Weld No. 1N118-2 600 RLWave 600 Shear Valve Pipe S2I Si No Coverage Claimed Coverage Claimed = 50% Supplemental coverage with 600 RL Wave Only Scale: V"= 1" See Note:

Note: 600 RL scan not included in percentage coverage due to requirements of 10CFR50.55a(b)(2)(xv)(A)(-1). Best effort scan with 600 RL obtained 39.7% coverage in one axial direction.

Pipe Dia. = 10" SI Pipee = 50% (100% of the length x 50% of the volume)

S2 - Valve - 0% (0% of the length x 0% of the volume)

S3 CW -100% (100% of the length x 100% of the volume)

S4 =CCW = 100%- (100% of the length x 100% of the volume)

Total = 250 / 4 = 62.5 % Aggregate Coverage Inspector / Date: 6ýýL Tcc IZj1156, Page S of "3 IpV I

Request for Relief 07-CN-004 Attachment D Weld 1NI148-10 Number of Pages = 3

UT Pipe Weld Examination Site/Unit: Catawba / 1 Procedure: NDE-600 Outage No.: CNS1 -16 1

Summary No.: BO 9.011.163 Procedure Rev.: 17 Report No.: UT-06-536 Workscope: IS' Work Order No.: 01121676 Page: 1 of 3 Code: 1998 thru 2000 Addenda Cat./Item: B-J- /B9.11.163 Location:

Drawing No.: CN-1 NI-1 48

Description:

Tee to Valve ((1N181)

System ID: NI Component ID: B09.011.163 /1NI148-10 Size/Length: N/A Thickness/Diameter: 1.0/10.0 Limitations: Yes - See Attached Limitation Report Start Time: 1050 Finish Time: 1117 Examination Surface: Inside D Outside 7v Surface Condition: AS GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 06125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32823 Surface Temp.: 64 -F Cal. Report No.: CAL-06-557, CAL-06-558, CAL-06-559 Angle Used 0 45 45T 60 60L Scanning dB 53.8 51 52 Indication(s): Yes D] No [] Scan Coverage: Upstream E] Downstream WJ CW R] CCW W Comments:

Results: Accept v] Reject FD Info FD Percent Of Coverage Obtained > 90%: No - 37.5 Reviewed Previous Data: Yes-100%

Examiner Level Il-N IS a re Date Reviewer Signature Date Mauldin, Larry E. 11/22/2006 i731 1 0o ,

Examiner Level II-N nature Date Site Review Signature Date Stauffer, Lester, E. Z* * -------- 11/22/2006 N/A Other Level N/A Signature Date ANII Review Signature Date N/A ~*

7 Aý776,6),e/ e4&J zý ff,ýý,o

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: B09.011.163 Component ID 1NI148-10 remarks:

[ NO SCAN SURFACE BEAM DIRECTION Weld Taper D'* LIMITED SCAN 2 Z 1 2 -cw ccw FROM L N/A to L N/A INCHES FROM WO c/L to 0.7 ANGLE: [] 0 F 45 Z 60 other FROM 0 DEG to 360 DEG Z NO SCAN -SURFACE BEAM DIRECTION Valve Configuration 0 LIMITED SCAN ii 1 Z 2 Z 1 [1 2 Z cw Z ccw FROM L N/A to L N/A INCHES FROM WO ciL to Beyond ANGLE: E] 0 Z 45 2 60 other FROM 0 DEG to 360 DEG 0" NO SCAN SURFACE - BEAM DIRECTION D- LIMITED.SCAN r-1 L-l2 - 1 il2 -icw iccw FROM L toLL INCHES FROM WO to ANGLE: L] 0 Li 45 Li 60 other FROM DEG to DEG Li NO SCAN SURFACE BEAM DIRECTION L-i LIMITED SCAN 1 1i- i2 -1 -7 2 El cw Ei ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: E] 0 L] 45 DA/90 other FROM DEG to DEG Z yes EL No Prepared By: Larry Mauldi/ Level: Date: 11/22/2006 Sheet 2 of 3 Reviewed By: Date: Authorized Inspect o Date:

A %j_1tcos( -

Item No. B09.011.063 Weld No. IN1148-10 600 Shear Valve Tee S2 S1 I

Coverage Claimed 50%

Scale: 1"= I" No Coverage Claimed Supplemental coverage with 600 RL Wave Only See Note:

Note: 60' RL scan not included in percentage coverage due to requirements of 10CFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 60' RL obtained 41.5% coverage in one axial direction.

Pipe Dia. = 10" S1 =Tee 50% (100% of the length x 50% of the volume)

S2 = Valve 0% (0% of the length x .0% of the volume)

S3 = CW 50% (100% of the length x 50% of the volume)

S4 = CCW 50% (100% of the length x 50% of the volume)

Total = 150/4 = 37.5 % Aggregate Coverage Inspector / I'lL Awa,4ý Page 3 of 3 23:U VIL (,10(

Request for Relief 07-CN-004 Attachment E Weld 1NI148-11 Number of Pages = 3

UT Pipe Weld Examination Site/Unit: Catawba / 1 Procedure: NDE-600 Outage No.: CNS1-16 Summary No.: BO!9.011.164 Procedure Rev.: 17 Report No.: UT-06-537 Workscope: ISl Work Order No.: 01121676 Page: 1 of 3 Code: 1998 thru 2000 Addenda Cat./Item: B-J- /B9.111.164 Location:

DrawingNo.: CN-1 NI-1 48

Description:

Tee to Valve (1NI82)

System ID: NI Component ID: B09.011.164 /1 NIl 48-11 Size/Length: N/A Thickness/Diameter: 1.0/1 0.0 Limitations: Yes - See Attached Limitation Report Start Time: 1056 Finish Time: 1113 Examination Surface: Inside D] Outside [] Surface Condition: AS GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 06125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32823 Surface Temp.: 64 OF Cal. Report No.: CAL-06-557, CAL-06-558, CAL-06-559 Angle Used 0 45 45T 60 60L Scanning dB 53.8 51 52 Indication(s): Yes D] No W Scan Coverage: Upstream R] Downstream [] CW S] CCW R1 Comments:

Results: Accept [] Reject D -] Info W]

Percent Of Coverage Obtained > 90%: No - 37.5 Reviewed Previous Data: Yes Examiner Level II-N _"//*,, tu e Date Reviewer / .* Signature* Date Mauldin, Larry E. Z)1,ý11/22/2006 (A /1iý lku-,)ý,

i-"r Examiner Level III-N" t-3. .- Signature. Date Site Review.I Signature I Date Stauffer, Lester, E. 11/22/2006 N/A Other Level N/A Signature Date ANII Review .- ,_ Signature Date N/A 6/7~ &A/- 6~6 4

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: B09.011.164 Component ID 1N1148-11 remarks:

[ NO SCAN SURFACE BEAM DIRECTION Weld Taper

-- LIMITED SCAN [ 1 1 [. 2 [i cw Iccw FROM L N/A to L N/A INCHES FROM WO c/L to 0.7" ANGLE: l- 0 LI 45 N 60 other FROM 0 DEG to 360 DEG Z NO SCAN SURFACE BEAM DIRECTION Valve Configuration r-- LIMITED SCAN [1 0i 2 r-] 1 N 2 cw Z ccw FROM L N/A to L N/A -INCHES FROM WO C/L to Beyond ANGLE: LI 0 [ 45 N 60 other FROM 0 DEG to 360 DEG

-- NO SCAN SURFACE BEAM DIRECTIONý rILIMITED SCAN - 1 L 2 1 -2 I cw I ccw FROM L to L INCHES FROM WO to ANGLE: L] 0 L 45 LI 60 other FROM DEG to DEG LI NO SCAN SURFACE BEAM DIRECTION F-I LIMITED SCAN I- 1 EL 2 - 1i 2 Icw E] ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: L] 0 LI 45 [:] ,0 other FROM DEG to DEG Z. yes I No PLarry Maul Level: Dt 11/22/2006 Sheet 2 of 3 Reviewed By: Date: Authorized Inspecto : - Date:

Uý-

I &

/0(1ý o(

I

Item No. B09.011.164 Weld No. IN1148-11 60 R60°Wave[

Shear Valve Tee S1 S2 Coverage Claimed = 50% Nco.

Coverage Claimed WU pplemental coverage th 600 RL Wave Only Scale 1"= 1" See Note:

Note: 60' RL scan not included in percentage coverage due to requirements of IOCFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 600 RL obtained 39.7% coverage in one axial direction.

Pipe Dia. = 10" S I =Valve = 0% (0% of the length x 0% of the volume)

S2 = Tee = 50% (100% of the 'length x 50% of the volume)

S3 = CW - 50% (100% of the length x 50% of the volume)

S4 = CCW = 50% (100% of the length x 50% of the volume)

Total =150/4 = 37.5 % Aggregate Coverage Inspector / Date: /4 ____________ ._____ Page of 3 E[W- ý Zjo(0ý

Request for Relief 07-CN-004 Attachment F Weld 1SWRF-1-OUTLET Number of Pages = 4

MIL AWN" Liquid Penetrant Examination iý,11 ive-i Site/Unit: Catawba / 1 Procedure: NDE-35 Outage No.: CNS1 -16 Summary No.: C02.011.003 Procedure Rev.: 21 Report No.: PT-06-375 Workscope: ISI Work Order No.: 01121673 Page: 1 of 4 Code: 1998 thru 2000 Addenda Cat./item: C-B- /C2.11.3 Location:

Drawing No.: CN-ISIN3-1554-1.6

Description:

Nozzle to Shell System ID: NV Component ID: C02.011.003 /1SWRF-1-OUTLET Size/Length: .154/2.0 Limitations: Yes - See Calculation Report Light Meter Mfg.: Lutron ' Serial No.: MCNDE32804 Illumination: >1200 LX Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32823 Surface Temp.: 73 °F Comparator Block Temp.: Side A: N/A 'F Side B: N/A 'F Resolution: Not Used Lo/Wo Location: N/A Surface Condition: AS WELDED Cleaner Penetrant Remover Developer Brand MAGNAFLUX MAGNAFLUX MAGNAFLUX MAGNAFLUX Type SKC-S SKL-SP SKC-S SKD-S2 Batch No. 05BO1K 97A10K 0513B6K 04C10K Time Evap. 5 Min. Dwell 10 Min. Evap. 5 Min. Develop 10 Min.

Time Exam Started: N/A Time Exam Completed: N/A Indication Loc Loc Diameter Length Type Remarks No. L W R/L NRI Comments:

Penetrant Category A - Acceptance Standard "L" Results: Accept

• Reject F-1 Info F_-

Percent Of Coverage Obtained > 90%: No - 74.7 Reviewed Previous Data: Yes Examiner Level I Signatur- Date Revi tJver / Signature Date Resor, James H. 11/29/20066 O/iZ K---0*7 Examiner Level N/A ( Signee/ Date Site Review Y Signature Date N/A N/A/,

Other Level N/A Signature Date AN ,R)ie Signature Date N/A ,2O' N

/zV~7

no-1111 Determination of Percent Coverage for Surface Examinations Site/Unit: Catawba / 1 Procedure: NDE-35 Outage No.: CNS1-16 Summary No.: C02.01 1.003 Procedure Rev.: 21 Report No.: PT-06-375 Workscope: ISI Work Order No.: 01121673 Page: 2 of 4 Area Required (as shown in applicable code reference drawing)

Length 9.032

• Width 1.750

= Total Area required 15.806 square inches Coverage Achieved Area examined 11.806 sq. in. / Total area required (100%) 15.806 sq. in.

= Percent coverage 74.693  % (area required - area of limitations = area examined)

To determine length of a circumferential weld Note Diameter refers to actual external diameter not pipe size (see table below)

Diameter 2.875 * (Pi) 3.1416

=.Length 9.032 inches Pipe Actual (Length) Pipe Actual (Length)

Size Diameter Circumference Size Diameter Circumference 2 2.375 7.46 12 12.75 40.06 2.5 2.875 9.03 14 14.0 43.98 3 3.5 1.1.0 16 16.0 50.27 3.5 4.0 12.57 18 18.0 56.55 4 4.5 14.14 20 20.0 62.83 5 5.563 17.48 22 22.0 69.12 6 6.625 20.81 24 24.0 75.40 8 8.625 27.10 30 30.0 94.25 110 L_:J .75 .33.771 Site Field suDeate Z- /& Date: 2 12,1, 0?7

/--7

Page 3 of 4 Revised Summary No.: C02.011.003 W/O#: 01121673 Vessel C02.011.003 Seal Water Return Outlet Nozzle (no scale)

Exam Area Width = 1.750" Exam Area Length = 9.032" (2.875" x 'T")

Total Required Exam Area = 15.8062 (9.032" x 1.75")

Area of No Exam Coverage = 42"1 (0.50" x 8.00")

Area of No Exam Coverage = 25.30% (4 - 15.806)

Total Exam Coverage = 74.7% (100- 25.30)

Examiner: -~

Page 4 of 4 Revised Seal Water Filter PT Exam 11-29-2006 W/O #01121673 Summary No. 002.011.003 Limited 0.50" x 4.00" on two sides due to Vessel legs as shown on drawing below (drawing not to scale) qagr 4naV~ Pr F-4Co*Z Owe-fl Examiner:

Request for Relief 07-CN-004 Attachment G Weld 1ND3-1 Number of Pages = 3

UT Pipe Weta Examination Site/Unit: Catawba / 1 Procedure: PDI-UT-2 Outage No.: CNS1 -16 Summary No.: Co 5.011.065 Procedure Rev.: C Report No.: UT-06-272 Workscope: ISI Work Order No.: 01132910 Page: 1 of 3 Code: 1998 thru 2000 Addenda Cat./Item: C-F-1/C5.11.65 Location:

Drawing No.: CN-1ND-3

Description:

Valve (1NIl85A) to Pipe System ID: ND Component ID: C05.011.065/1ND3-1 Size/Length: N/A Thickness/Diameter: .562/18.0 Limitations: Yes - See Attached Limitation Report Start Time: 1142 Finish Time: 1220 Examination Surface: Inside E] Outside V Surface Condition: AS GROUND Lo Location: 9.1.1.3 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 05125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32819 Surface Temp.: 104 OF Cal. Report No.: CAL-06-322, CAL-06-323, CAL-06-324 Angle Used 0 45 45T 60 70 Scanning dB 36.0 68.0 64.0 Indication(s): Yes Li No W Scan Coverage: Upstream E] Downstream E] CW 9] CCW ov Comments:

No scan on upstream side due to valve to pipe configuration.

Results: Accept [] Reject F] Info L_

Percent Of Coverage Obtained > 90%: No .e; 3-. 0 Reviewed Previous Data: Yes Examiner Level II-N *_ _Signatu Date Reviewer Signature Date Tucker, David K. 8/22/2006 - Z -2" O4, Examiner Level II-N Signature Date Site Review Signature Date Brown, Thomq ,. 8/22/2006 N/A Other Level N/A Signature Date ANII Review Signature Date N/A R4

&.1 I/

/~ ~~Z*/lX47 7

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: C05.011.065 Component ID 1ND3-1 remarks:

[* NO SCAN SURFACE BEAM DIRECTION Valve Configuration I- LIMITED SCAN [i1 1 [Z 2 Z i 2Zcw ccw FROM L N/A to L N/A INCHES FROM WO- CL-.45" to Beyond ANGLE: 0 0l -45 [ 60 other 70 FROM o DEG to 360 DEG

• NO SCAN SURFACE BEAM DIRECTION

[- LIMITED SCAN -- 1 l2 Ei1 L-]l2 i-cw Lijccw FROM L to L INCHES FROM WO to ANGLE: ElI 0 El 45 El 60 other FROM DEG to DEG E NO SCAN SURFACE BEAM DIRECTION E-LIMITED SCAN i 1 ]2 0i 1 2 - cw i ccw FROM L to L INCHES FROM WO to ANGLE: D] 0 El 45 El 60 other FROM DEG to DEG D-- NO SCAN SURFACE BEAM DIRECTION D LIMITED SCAN i]1 - 22 Ei E]27 cw ccw FROM L to L INCHES FROM WO to ___1__0 Sketch(s) attached ANGLE: D] 0 D 45 El 6p,, 14her FROM DEG to D DEG Z yes El No Prepared By: Jay Eaton Level: 111, Date: 11-16-2006 Sheet 2 of 3 Reviewed By: Date: Authorized lnspectorK-,,,-*,ý Date: /

Item No. C05.011.065 Weld No. IND3-1 60, RLWave 70' Shear Valve 1NI185A S2 70 Shear No Coverage Claimed Supplemental coverage with 609 RL Wave Only Scale: 1" 1" See Note:

Note: 60' RL scan not included in percentage coverage due to requirements of 10CFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 60' RL obtained 3.5% coverage in one axial direction.

Pipe Dia. = 18" t = 0.562" 1/3 t = 0.19" Weld Length = 56.6" Weld + 11/4" ea. Side = 1.5" S1I Pipe z 50% (100% of the length x 50% of the volume)

S2 =Valve 0% (0% of the length x 0% of the volume)

S3 CW 50% (100% of the length x 50% of the volume)

S4=CCW 50% (100% of the length x 50% of the volume)

Total = 150 / 4 -37.5  % Aggregate Coverage Inspector / Date: Page 3_of 3

Request for Relief 07-CN-004 Attachment H Weld 1NI1-12 Number of Pages = 5

UT Pipe Weld Examination Site/Unit: Catawba I 1 Procedure: PDI-UT-2 Outage No.: CNS1-16 Summary No.: CO5.011.105 Procedure Rev.: C Report No.: UT-06-568 Workscope: IS1 Work Order No.: 01121663 Page: 1 o1 5 Code: 1998 thru 2000 Addenda Cat./Item: C-F-1/C5.11.105 Location:

Drawing No.: CN-1 NI-1

Description:

Pipe to Valve (1NI180)

System ID: NI Component ID: C05.011.105/1 NI1-12 Size/Length: - N/A Thickness/Diameter: .719 / 6.0 Limitations: Yes - See Attached Limitation Report Start Time: 1145 Finish Time: 1200 Examination Surface: Inside FD Outside [] Surface Condition: AS GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 06125 Temp. Tooi Mfg.: D.A.S Serial No.: MCNDE32823 Surface Temp.: 72 OF Cal. Report No.: CAL-06-591, CAL-06-592, CAL-06-593 Angle Used 0 45 45T 60 60L Scanning dB 38 40 71 Indication(s): Yes F] No FD Scan Coverage: Upstream 9] Downstream 0 CW [] CCW W Comments:

Results: Accept [] Reject D Info D_

Percent Of Coverage Obtained > 90%: No- 37.5% Reviewed Previous Data: Yes Examiner Level Il-N , Signature Date Reviewer Signature Date Brown, ThoM2=____/ý-- . 11/27/2006- 02 -6 (,

Examiner Level I-N Signature Date Site Review Signature Date Waddel, Joey, 11/27/2006 N/A Other Level N/A Signature Date ANII Review Signature / Date N/A A. I-/ / i 7 6A-41t <74/6

/7'x

Ultrasonic Indication Report Site/Unit: Catawba 1 Procedure: PDI-UT-2 Outage No.: CNS1-16 Summary No.: C05 .011.105 Procedure Rev.: C Report No.: UT-06-568 Workscope: ISI Work Order No.: 01121663 Page: 2 of 5 Wo Wmax Search Unit Angle: 60 () Piping Welds WL 11W2 Wo Location: CL of Weld o Ferritic Vessels > 2T Lo Location: 9.1.1.1 o Other MP Metal Path Wmax Distance From Wo To S.U. At Maximum Response

-) --- .. 0I*

. .... .... DATUTA

....*-

---

RBR Remaining Back Reflection Wl Distance From Wo At Of Max (Forward) T Tu----

L Distance From Datum W2 Distance From Wo At - Of Max (Forward)

Lnvm L2 L Comments: Also seen with 60°RL. This indication has been previously recorded. No change.

I Lý::

Scan Indication  % W Forward Backward Li L L2 RBR Remarks

1. No. Of Max Of Max Of Max Of Max Of Amp.

DAC W MP Wl MP W2 MP Max Max 2 1 75% 1.2 1.48 N/A N/A N/A N/A N/A 2.25 N/A N/A Root Geometry Examiner Level Il-N Signature Date Reviewer Signature Date Brown, Tho m, 11/27/2006, /,-' (..

Examiner Level Il-N / Signature Date Site Review Signature Date Waddel, Joey c, . 11/27/2006 N/A Other Level N/All Signature Date ANII Review

• Signature Date N/A V----- .- )-.- ./7 /94 _a

Supplemental Report Report No.: UT-06-568 AS COW! r19 Y Page: 3 of 5 Summary No.: C05.011.105 Examiner: Brown, Tqnw ý -.- , Level: Il-N Reviewer: Date:/l.(.. o4 Examiner: Waddel, Joey , ,,,.' Level: Il-N Site Review: N/A Date:

Other: N/A Level: N/A ANII Review: _ . Date:

Comments: Indication #1 - 600 was determined to be root geometry. Indication was also seen with 60'L. Previously recorded. No change.

Sketch or Photo: Z:\UT\1 IDDEAL\Prof ilel-ine2.jpg

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: C05.011.105 Component ID 1NII-12 remarks:

[ NO SCAN SURFACE BEAM DIRECTION Valve Congifuration 0I LIMITED SCAN 1 N 2 i1 2 N cw ccw FROM L N/A to L N/A INCHES FROM WO CL -.4 to Beyond ANGLE: EJ 0 E 45 N 60 other FROM o DEG to 360 DEG

--1 NO SCAN SURFACE BEAM DIRECTION E-I LIMITEDSCAN []1 -] 2 El[ 1 2 El cw El ccw FROM L to L INCHES FROM WO to ANGLE: El 0 El 45 0l 60 other FROM DEG to DEG El NO SCAN SURFACE BEAM DIRECTION L-- LIMITED SCAN El1 -- 2 Lii1 -- 2 L cw [ccw FROM L to L INCHES FROM WO to ANGLE: [] 0 El 45 El 60 other FROM DEG to DEG E-l NO SCAN SURFACE BEAM DIRECTION D-1 LIMITED SCAN E-1 L-]2 El 1-2 -- cw -ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: 0l 0 Fl 45 El 60 other FROM DEG to DEG [ yes -- No Prepared By: Thomas Bro~wr) - -.- 7 ., vLevel: iI Date: 11/27/2006 Sheet 4 of 5

• -.. * ~~~~D at e:\-- ' / .

Reviewed By: Date: Authorized Dnspectorate,

Item No. C05.011.105 Weld No. 1MI-12 Coverage Claimed = 50% No Coverage Claimed Supplemental coverage Scale: 1"= 1" with 600 RL Wave Only See Note:

Note: 600 RL scan not included in percentage coverage due to requirements of I0CFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 600 RL obtained 18.9% coverage in one axial direction.

Pipe Dia. = 6" Sl=Pipe = 50% (100% of the length x 50% of the volume)

S2 =Valve = 0% (0% of the length x 0% of the volume)

S3 = CW = 50% (100% of the length x 50% of the volume)

S4=CCW. = 50% (100% of the length x 50% of the volume)

Total =150 /4 = 37.5 % Aggregate Coverage hispector / Date: Inpetr Dt: t Page_:ý_of Pge01o 6

Request for Relief 07-CN-004 Attachment I Weld 1NV-309-INLET Number of Pages = 3

UT Pipe Weld Examination Site/Unit: Catawba / 1 Procedure: NDE-600 Outage No.: CNSI-16 SummaryNo.: Co 5.021.146 Procedure Rev.: 17 Report No.: UT-06-553 Workscope: ISI Work Order No.: 01121907 Page: 1 of 3 Code: 1998 thru 2000 Addenda Cat./Item: C-F-1/C5.21.146 Location:

Drawing No.: CN-1NV-36

Description:

Valve Body to Concentric Reducer System ID: NV Component ID: C05.021.146/1 NV-309-INLET Size/Length: N/A Thickness/Diameter: .344/2.0 Limitations: Yes - See Attached Limitation Report Start Time: 1342 Finish Time: 1402 Examination Surface: Inside [] Outside [] Surface Condition: AS GROUND Lo Location: 9.1.1.1 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 06125 0

Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32796 Surface Temp.: 75 F Cal. Report No.: CAL-06-579, CAL-06-580, CAL-06-581 Angle Used 0 45 45T 60 38 70 Scanning dB 44 34.7 46 Indication(s): Yes [ No F] Scan Coverage: Upstream [ Downstream [ CW [ CCW R]

Comments:

Results: Accept [] Reject E] Info D .-- v'.

Percent Of Cove-rage Obtained > 90%: No-37.5% Reviewed Previous Data: Yes [

Examiner Level II.N ,igna preS*

• Date Reviewer .*,* 1 Signature [Date Mauldin, Larry E. " 11 /26/2006.., *, 7 , l Examiner Level IL / ) igaue.,Date, , iee, eview Signature. Date Ross, Jake E. .1126/2006..N/A ..-......

Other Level N/A Signature Date- ANII Review Signature Date FN/At1A-A'--... 7'c  !

&I eý g7- 6/-a 64 z/7 4A4/&~~f7 2: Ify/07

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: C05.021.146 Component ID 1NV-309-INLET remarks:

[ NO SCAN SURFACE BEAM DIRECTION Due to Valve Configuration

-[- LIMITED SCAN Z 1 E] 2 l1 Z Z cw Z ccw FROM L N/A to L N/A INCHES FROM WO .3T' to Beyond ANGLE: - 0 [Z A Z 60 other 70 FROM 0. DEG to 36o DEG

--I NO SCAN " SURFACE BEAM DIRECTION D LIMITED SCAN [-] 1 i]2 E 1 [-2. E cw t] ccw FROM L to L INCHES FROM WO to ANGLE: 0I 0 [] 45 [] 60 other FROM DEG to DEG F-1 NO SCAN SURFACE BEAM DIRECTION

[7i LIMITED SCAN -1 EL 2 1-] 1, E- 2 il--cw -- ccw FROM L to L INCHES FROM WO to ANGLE: E] 0 Ij 45 [] 60 other FROM.__ DEG to DEG

-- NO SCAN SURFACE BEAM DIRECTION DLIMITED SCAN F-1 1 2 1 L 2 cw ]ccw FROM L to L_ INCHES FROM WO to Sketch(s) attached ANGLE: - E] 0 E] 45 0 other FROM DEG to DEG Z yes El No Prepared By: Larry Maul, Level: ii Date:, *1 '26=2006; Sheet 2 of 3 Reviewed By: Date: Authorized lnspectQ-* Date:

Item No: C05.021.146 Weld No. 1NV-309-UNLET Valve-Body - S1 Reducer - S2 700 Shear Coverage Claimed 50% 600 Shear No Coverage Claimed Supplemental coverage with 700 Shear Wave Only Scale: 1"= 1" See Note:

Note: 70' shear scan not included in percentage coverage due to requirements of IOCFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 70 shear obtained 50% coverage in one axial direction.

Pipe Dia. = 2" SI = Valve = 0% (0% of the length x 0% of the volume)

S2 = Reducer = 50% (100% of the length x 50% of the volume)

S3 = CW = 50% (100% of the length x 50% of the volume)

S4 = CCW = 50% (100% of the length x 50% of the volume)

Total = 150/4 = 37.5 % Aggregate Coverage Inspector/ Date: -e Page 3 off -3

-IE I-I 3[9

Request for Relief 07-CN-004 Attachment J Weld 1NV-309-OUTLET Number of Pages = 3

UT Pipe Weld Examination Site/Unit: Catawba / 1 Procedure: NDE-600 Outage No.: CNS1 -16 5.021.147 Summary No.: CO Procedure Rev.: 17 Report No.: UT-06-554 Workscope: ISI Work Order No.: 01121907 Page: 1 of 3 Code: 1998 thru 2000 Addenda Cat./Item: C-F-1/C5.21.147' Location:

Drawing No.: CN-1NV-36

Description:

Valve Body to Concentric Reducer System ID: NV Component ID: C05.021.147/1 NV-309-OUTLET Size/Length: N/A Thickness/Diameter: .344/2.0 Limitations: Yes - See Attached Limitation Report Start Time: 1347 Finish Time: 1404 Examination Surface: Inside D] Outside j[] Surface Condition: AS GROUND Lo Location: 9.1.1.A Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 06125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32796 Surface Temp.: 75 OF Cal. Report No.: CAL-06-579, CAL-06-580, CAL-06-581 Angle Used 0 45 45T 60 38 70 Scanning dB 44 34.7 46 Indication(s): Yes F-ý No [] Scan Coverage: Upstream D Downstream W] CW W CCW 66 Comments:

Results: Accept f] Reject D] Info D-_

Percent Of Coverage Obtained > 90%: Yes-37.5 % Reviewed Previous Data: Yes Examiner Level Il-N Si/gnre Date Reviewer Signature Date Mauldin, Larry E. C 11/26/2006  :-. /*I -T5. .

Examiner LeveL lIE Signature .,Date Site Review Signature Date Ross, Jake E. . 11/26/2006 N!/A .

OtherN Level N/A Signture Date ANII Review Signature Date rN/At /

/P,Y, U

A~A~ ýZ4101

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: C05.021.147 Component ID 1NV-309-OULET remarks:

[ NO SCAN SURFACE BEAM DIRECTION Due to Valve Configuration I'- LIMITED SCAN L1 Zi 2 Z 1 r 2 Z*cw Zccw FROM L N/A to L N/A INCHES FROM WO .3" to Beyond 3e*

ANGLE: [i 0 Z 45 Z 60 other 70 FROM o DEG to 360 DEG IZ NO SCAN SURFACE BEAM DIRECTION D LIMITED SCAN 0 1 - 2 i]1 -]2 Lcw Dccw FROM L to L INCHES FROM WO to ANGLE: Li 0 0i 45 Li 60 other FROM DEG to DEG F-1 NO SCAN SURFACE BEAM DIRECTION 1- LIMITED SCAN 1 -2 E] 1 E] 2 L- cw D ccw FROM L to L INCHES FROM WO to ANGLE: Li 0 Li 45 Li 60 other FROM DEG to DEG

-- NO SCAN SURFACE BEAM DIRECTION 1- LIMITED SCAN 01 11 2 E] iF D2 0cw 0ccw FROM L to L INCHES FROM WO to Sketch(s) attached ANGLE: [L 0 El 45 I,6P0 0 ther FROM DEG to DEG E yes Dj No Prepared By: Larry Date: 11-26-2006 1 Sheet 2 of 3 Date:

Reviewed By: ,rized Insi rized Insi Date:

'k, Item No: C05.021.147 Weld No. 1NV-309-OUTLET Valve Body - S2 Reducer - S1 700 Shear Coverage Claimed = 50% - 600 Shear No Coverage Claimed Supplemental coverage with 700 Shear Wave Only Scale: 1'= I" See Note:

Note: 70' shear scan not included in percentage coverage due to requirements of 10CFR50.55a(b)(2)(xv)(A)(1). Best effort scan with 70 shear obtained 50% coverage in one axial direction.

Pipe Dia. 2" SI = Reducer:= 50% (100% of the length x 50% of the volume)

S2 = Valve = 0% (0% of the length x 0% of the volume)

S3 = CW = 50% (100% of the length x 50% of the volume)

S4=CCW = 50% (100% of the length x 50% of the volume)

Total = 150 /4 = 37.5 % Aggregate Coverage Inspector / Date:, .-06 Page 3 of 3 Mý,- jV[3 JOý'