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| number = ML072470492
| number = ML072470492
| issue date = 08/28/2007
| issue date = 08/28/2007
| title = Oconee Nuclear Station, Unit 2, Inservice Inspection Report Fourth Ten-Year Inservice Inspection Interval
| title = Inservice Inspection Report Fourth Ten-Year Inservice Inspection Interval
| author name = Hamilton B H
| author name = Hamilton B H
| author affiliation = Duke Energy Carolinas, LLC, Duke Power Co
| author affiliation = Duke Energy Carolinas, LLC, Duke Power Co

Revision as of 09:02, 10 February 2019

Inservice Inspection Report Fourth Ten-Year Inservice Inspection Interval
ML072470492
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 08/28/2007
From: Hamilton B H
Duke Energy Carolinas, Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML072470492 (242)


Text

SDuke BRUCE H HAMILTON Vice President S Energys Oconee Nuclear Station Duke Energy Corporation ONO1 VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax bhhamilton@duke-energy.

corn August 28, 2007 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)Oconee Nuclear Station, Unit 2 Docket No. 50-270 Unit 2 EOC 22 Refueling Outage Inservice Inspection Report Fourth Ten-Year Inservice Inspection Interval Please find attached a copy of the Inservice Inspection Report for Oconee Unit 2 End of Cycle 22 Refueling Outage. This report is submitted pursuant to Section XI of the ASME Boiler and Pressure Vessel Code, 1998 Edition, with 2000 addenda, Article IWA 6230.If there are any questions you may contact R. P. Todd at (864) 885-3418.B. H. Hamilton, Site Vice-President Oconee Nuclear Station Attachment A oL4 q www. duAP-eneygv.

corn INSERVICE INSPECTION REPORT DUKE ENERGY CAROLINAS OCONEE NUCLEAR STATION UNIT 2 TWENTY-SECOND REFUELING OUTAGE P Duke oEnergy Owner's Report For INSERVICE INSPECTIONS OCONEE UNIT 2 2007 REFUELING OUTAGE EOC22 (OUTAGE 2)Plant Location:

7800 Rochester Highway, Seneca, South Carolina 29672 NRC Docket No. 50-270 Commercial Service Date: September 9, 1974 Document Completion Date 3"/,.-4 -9 Owner: Duke Energy Carolinas 526 South Church St.Charlotte, N. C. 28201-1006 Revision 0 Prepared By: Reviewed By: Approved By: AMA~ C Date 7-1 ?- a Date 7- 1 c Date _ _ _ _

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 1. Owner: Duke Energy Carolinas, 526 S. Church St.. Charlotte, NC 28201-1006 (Name and Address of Owner)2. Plant: Oconee Nuclear Station, 7800 Rochester Highway, Seneca, SC 29672 (Name and Address of Plant)3. Plant Unit: 2 4. Owner Certificate of Authorization (if required)

N/A 5. Commercial Service Date: September 9, 1974 6. National Board Number for Unit N/A 7. Components Inspected:

Component or Appurtenance Manufacturer Installer Manufacturer Installer Serial No.State or Province No.National Board No.See Section 1.1 in the Attached Report Note: Supplemental sheets in the form of lists, sketches, or drawings may be used provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.Total number of pages contained in this report 240 FORM NIS-1 (Back)b 8. Examination Dates November 30, 2005 to May 30, 2007 9. Inspection Period Identification:

10. Inspection Interval Identification:
11. Applicable Edition of Section XI 12. Date/Revision of Inspection Plan: First Period Fourth Interval 1998 Addenda 2000 June 23, 2004 / Revision 0 13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. See Sections 2.0, 3.0 and 6.0 14. Abstract of Results of Examination and Tests.15. Abstract of Corrective Measures.See Sections 4.0 and 6.0 See Subsection 4.3 We certify that a) the statements made in this report are correct b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the rules of the ASME Code,Section XI.Certificate of Authorization No. (if applicable)

NA Expiration Date NA D ate ",j -[ f o '7 Signed Duke Energy Carolinas.

Owner By IA U'CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of A4l*,,A-,

employed by Hartford Steam Boiler of Connecticut (HSBCT) have inspected the components described in this Owner's Report during the period //".fo -Co -to -- go -,o 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in the Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, test, and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection

_____________________Commissions

/VtL/ /'4'C.Inspector's Signature National Board, State, Province, and Endorsements Date .9 -/3- o 7.0 HSBCT 200 Ashford Center North Suite 205 Atlanta, GA. 30338-4860 (800) 417-3721 www.hsbct.com DISTRIBUTION LIST 1. Duke Energy Carolinas Nuclear Technical Services Division Section XI Inspection Program Section 2. NRC Document Control Desk 3. HSBCT (AIA)c/o ANII at Oconee Note: The following personnel are to be notified via e-mail after the Inservice Inspection Report has been stored in the Nuclear Electronic Document Library: GO Nuclear Assurance c/o Bruce Nardoci Inspection and Welding Services (ISI Coordinator) 0 TABLE OF CONTENTS Section Title Revision 1.0 General Information 0 2.0 Fourth Ten Year Inspection Status 0 3.0 Final Inservice Inspection Plan 0 4.0 Results of Inspections Performed 0 5.0 Owners Report for Repair/Replacement Activities 0 6.0 Pressure Testing 0

1.0 General

Information This report describes the Inservice Inspection of Duke's Oconee Nuclear Station, Unit 2, during Outage 2/EOC 22. This is the last outage in the first inspection period of the Fourth Ten-Year Interval.

ASME Section XI, 1998 Edition with the 2000 Addenda, was the governing Code for selection and performing of the ISI examinations.

Included in this report are: the inspection status for each examination category, the final inservice inspection plan, the inspection results for each item examined, and corrective actions taken when reportable conditions were found. In addition, there is an Owner's Report for Repair/Replacement Section included for completed NIS-2 documentation of repairs and replacements.

1.1 Identification

Numbers Manufacturer Item Manufacturer or Installer State or National or Installer Serial No. Province No. Board No.Reactor Vessel Babcock & Wilcox 620-0004-51-52 N/A N-105 Reactor Vessel Babcock & Wilcox 068S-02 N/A 209 Head (replaced head)Steam Generator A Babcock & Wilcox 006K03 N/A 207 Steam Generator B Babcock & Wilcox 006K04 N/A 208 Pressurizer Babcock & Wilcox 620-0004-59 N/A N-106 Main Steam Duke Power NA NA NA System Auxiliary Steam Duke Power NA NA NA System Feedwater System Duke Power NA NA NA Emergency Duke Power NA NA NA Feedwater System Steam Generator Duke Power NA NA NA Flush System Condensate Duke Power NA NA NA System EOC 22 Refueling Outage Report Oconee Unit 2 Section 1 Page 1 of 4 Revision 0 July 18, 2007 Manufacturer Item Manufacturer or Installer State or National or Installer Serial No. Province No. Board No.Vents and Exhaust Duke Power NA NA NA System Condenser Duke Power NA NA NA Circulating Water High Pressure Duke Power NA NA NA Service Water System Low Pressure Duke Power NA NA NA Service Water System Reactor Coolant Duke Power NA NA NA System High Pressure Duke Power NA NA NA Injection System Low Pressure Duke Power NA NA NA Injection System Reactor Building Duke Power NA NA NA Spray System Component Duke Power NA NA NA Cooling System Spent Fuel Cooling Duke Power NA NA NA System Vents -Reactor Duke Power NA NA NA Building Components Drains -Reactor Duke Power NA NA NA Building Components EOC 22 Refueling Outage Report Oconee Unit 2 Section 1 Page 2 of 4 Revision 0 July 18, 2007 1.2 Personnel, Equipment and Material Certifications All personnel who performed or evaluated the results of inservice inspections during the time frame bracketed by the examination dates shown on the NIS-1 Form were certified in accordance with the requirements of 1998 Edition of ASME Section XI with the 2000 addenda including Appendix VII for ultrasonic inspections.

In addition, ultrasonic examiners were qualified in accordance with ASME Section XI, Appendix VIII, and 1998 Edition with the 2000 Addenda through the Performance Demonstration Initiative (PDI) for Supplements 2, 3, 4, 6, 8 and 10. Preservice examinations of weld overlays were conducted in accordance with Code Case N-504-2 including non-mandatory Appendix Q.The appropriate certification records for each inspector, calibration records for inspection equipment, and records of materials used (i.e., NDE consumables) are on file at Oconee Nuclear Station or copies can be obtained by contacting Duke's Corporate Office in Charlotte, North Carolina.The copies of the certification records for Washington Group International inspectors and Atlantic Group inspectors can be obtained by contacting Duke's Corporate Office in Charlotte, North Carolina.1.3 Reference Documents The following reference documents apply to the inservice inspections performed during this report period. A copy may be obtained by contacting the ISI Plan Manager at Duke's Corporate Office in Charlotte, North Carolina.Code Case N-460 (Applicable to items in this report where less than 100%coverage of the required weld examination volume was achieved.)

These items are identified on the Run D that is located in Section 4 of this report.Code Case N-695 (Qualification Requirements for dissimilar metal piping welds)Items are identified by the use of UT procedure PDI-UT-10 and are listed in the Plan Report in section 3.0 of this report as dissimilar metal welds.Code Case N-504-2 (Applicable to items that weld overlay was performed on.During 2EOC-22 outage there were welds that had weld overlay performed on them and the PSI exams were performed per Code Case N-504-2.)Duke Power Company Problem Investigation Process Report 0-07-0870, 0-07-0890, 0-07-0895, 0-07-01151, 0-07-02700, 0-07-02836, 0-07-02917, 0-07-03154, and 0-07-03172.

Each PIP was written to track the Relief Request process for limited coverage on UT examinations of welds that were inspected during EOC-22 for Unit 2. The welds with limited coverage are listed in Section 4.4 of this report.EOC 22 Refueling Outage Report Page 3 of 4 Oconee Unit 2 Revision 0 Section 1 July 18, 2007 Duke Power Company Problem Investigation Process Report 0-07-02608 was written to document weld problems identified during an ISI examination on the Letdown Storage Tank support.Request for Relief 07-ON-001 (Allows Duke an alternative to perform examinations of weld overlays per Code Case N-504-2.)Request for Relief 03-006 (Allows Duke an Alternative for the Snubber Examinations required in IWF-5000 for the 4 th interval.)

1.4 Augmented

and Elective Examinations Augmented and elective examination information found within this Inservice Inspection Report is not required by the ASME Section XI Code; therefore, it is exempt from ANII review, verification, and/or record certification.

1.5 Responsible

Inspection Agency Hartford Steam Boiler of Connecticut (HSBCT) is responsible for the third party inspections required by ASME Section Xl.Authorized Nuclear Inservice Inspector(s)

Name: Employer: Business Address: Gary Brouette and Nancy Slaughter HSBCT 200 Ashford Center North Suite 205 Atlanta, GA 30338-4860 (800) 417-3721 www.hsbct.com EOC 22 Refueling Outage Report Oconee Unit 2 Section 1 Page 4 of 4 Revision 0 July 18, 2007

2.0 Fourth

Ten Year Interval Inspection Status The completion status of inspections required by the 1998 ASME Code Section Xl, with the 2000 Addenda, is summarized in this section. The requirements are listed by the ASME Section Xl Examination Category as defined in Table IWB-2500-1 for Class 1 Inspections, Table IWC-2500-1 for Class 2 Inspections, and IWF-2500-1 for Class 1 and 2 Component Supports.

Augmented inspections are also included.Class 1 Inspections Examination Inspections Inspections Percentage

  • Deferral Category Description Required Completed Completed Allowed B-A Pressure Retaining Welds 6 Welds .5 Weld 8% Yes in Reactor Vessel B-B Pressure Retaining Welds 10 Welds 2 Welds 20% No in Vessels Other than Reactor Vessel B-D Full Penetration Welds of 54 12 22% Partial Nozzles in Vessels Inspections Inspections Inspection Program B B-F Pressure Retaining 2 Welds 0 Welds 0% Yes Dissimilar Metal Welds B-G-1 Pressure Retaining Bolting 128 Items 41.33 Items 32% Yes Greater than 2 Inches in Diameter B-G-2 Pressure Retaining Bolting 20 Items 9 Items 45% No 2 Inches and Less in Diameter B-J Pressure Retaining Welds 165 Welds 37 Welds 22% No I in Piping III_ I B-K Welded Attachments for 18 3 17% No Vessels, Piping, Pumps and Valves*Deferral of inspection to the end of the interval as allowed by ASME Section XI Tables IWB and IWC 2500-1.EOC 22 Refueling Outage Report Oconee Unit 2 Section 2 Page 1 of 4 Revision 0 July 18, 2007 Class 1 Inspections (Continued)

Examination Inspections Inspections Percentage

  • Deferral Category Description Required Completed Completed Allowed B-L-1 Pressure Retaining Welds 1 Weld 1 Weld 100% Yes in Pump Casings B-L-2 Pump Casings 1 Casing 0 Casing 0% Yes B-M-1 Pressure Retaining 1 Valve Body 0 Valve Body 0% Yes Welds in Valve Bodies Weld Weld B-M-2 Valve Bodies 3 Valves 0 Valves 0% Yes B-N-1 Interior of Reactor Vessel 3 Inspections 1 Inspection 33% No B-N-2 Welded Core Support 1 Inspection 0 Inspections 0% Yes Structures, and Interior Attachments to Reactor Vessels B-N-3 Removable Core Support 1 Inspection 0 Inspections 0% Yes Structures B-0 Pressure Retaining Welds 12 Housing 4 Housing 33% Yes in Control Rod Housings Welds Welds B-P All Pressure Retaining Components REFERENCE SECTION 6.0 OF THIS REPORT B-Q Steam Generator Tubing N/A N/A N/A N/A F-A Class 1 Component 37 Supports 13 Supports 35% No F1.10 & F1.040 Supports (Except items. Snubbers)F-A Class 1 Component
    • F1.050 items Supports, Snubbers Deferral of inspection to the end of the interval as allowed by ASME Section Xl Tables IWB and IWC 2500-1.Inspected under Selected License Commitment 16.9.18 per Relief Request 03-006 EOC 22 Refueling Outage Report Oconee Unit 2 Section 2 Page 2 of 4 Revision 0 July 18, 2007 Class 2 Inspections Examination Inspections Inspections Percentage
  • Deferral Category Description Required Completed Completed Allowed C-A Pressure Retaining Welds 11 Welds 5 Welds 45% No in Pressure Vessels C-B Pressure Retaining Nozzle 4 Welds 2 Welds 50% No Welds in Vessels C-C Integral Attachments for 38 14 37% No Vessels, Piping, Pumps Attachments Attachments and Valves C-D Pressure Retaining Bolting 2 Items 0 Items 0% No Greater Than 2 Inches in Diameter C-F-1 Pressure Retaining Welds 164 Welds 42.5 Welds 26% No in Austenitic Stainless Steel or High Alloy Piping C-F-2 Pressure Retaining Welds 66 Welds 16 Welds 24% No in Carbon or Low Alloy Steel Piping C-G Pressure Retaining Welds N/A N/A N/A N/A in Pumps and Valves C-H All Pressure Retaining Components REFERENCE SECTION 6.0 OF THIS REPORT F-A Class 2 Component 137 Supports 47 Supports 34% No F1.020 & F1.040 Supports (Except items. Snubbers)F-A Class 2 Component
    • F1.050 items Supports, Snubbers I Deferral of inspection to the end of the interval as allowed by ASME Section XI Tables IWB and IWC 2500-1.Inspected under Selected License Commitment 16.9.18 per Relief Request 03-006 0 EOC 22 Refueling Outage Report Oconee Unit 2 Section 2 Page 3 of 4 Revision 0 July 18, 2007 Augmented/Elective Inspections Augmented and elective examination information found within this Inservice Inspection Report is not required by the ASME Section XI Code; therefore, it is exempt from ANII review, verification, and/or record certification.

Summary Number Description Percentage Complete 02.G1.1. Reactor Coolant Pump Flywheel 100% of EOC 22 Requirements 02.G2.1. HPI Nozzle Safe End Examinations 100% of EOC 22 Requirements 02.G3.1. Pressurizer Surge Line Examinations None scheduled for EOC 22 02.G4.1. Thermal Stress Piping (NRC Bulletin 88-08) 100% of EOC 22 Requirements 02.G11.1.0001 Reactor Pressure Vessel Head Penetration Nozzle by None scheduled for EOC 22 UT Examination per NRC Order EA-03-009.

02.G1 1.1.0002 Bare Metal Visual Examination of the Reactor Pressure None scheduled for EOC 22 Vessel Head Surface per NRC Order EA-03-009.

02.G12.1.

UT Examination per MRP-139 100% of EOC 22 Requirements 02.G12.2.

UT Examination per MRP-139 None scheduled for EOC 22 02.G12.3.

UT Examination per MRP-139 None scheduled for EOC 22 02.G13.1.

VT-2 Examination per MRP-1 39 100% of EOC 22 Requirements 02.G13.2.

VT-2 Examination per MRP-139 100% of EOC 22 Requirements 02.G14.1.

VT-2 Examination per Oconee Response to BL-2004-01 100% of EOC 22 Requirements 02.H1.1. Pressurizer Sensing/ Sampling Nozzle Safe Ends None scheduled for EOC 22 02.H2.1. Class 1 RTE Mounting Bosses 100% of EOC 22 Requirements 02.H3.1. Main Feedwater Piping in the East and West None scheduled for EOC 22 Penetration Rooms per QA-513J (ER-ONS-04-03) 02.H4.1. Main Feedwater and Main Steam Piping Supports and 100% of EOC 22 Requirements Attachment Welds per OA-513J (ER-ONS-04-05)

EOC 22 Refueling Outage Report Oconee Unit 2 Section 2 Page 4 of 4 Revision 0 July 18, 2007

3.0 Final

Inservice Inspection Plan The final Inservice Inspection Plan shown in this section lists all ASME Section Xl Class 1, Class 2, Class 3, and Augmented examinations credited for this report period.The information shown below is a field description for the reporting format included in this section of the report: Summary/Item Number ID Number Sys Iso / Dwg. Numbers= ASME Section Xl Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2), IWF-2500-1 (Class 1 and Class 2 ), Augmented Requirements

= Unique Identification Number= Component System Identification

= Location and/or Detail Drawings Proc= Examination Procedures Insp Req.Mat / Sch.Diam. / Thick Cal Blocks Comments-Examination Technique

-Magnetic Particle, Dye Penetrant, etc.= General Description of Material= Diameter/Thickness

-Calibration Block Number= General and/or Detail Description EOC 22 Refueling Outage Report Oconee Unit 2 Section 3 Page 1 of 1 Revision 0 July 18, 2007 DUKE bfRGY QUALITY ASSURANCE.ECHNICAL SERVICES Inservice Inspection Database Management System Plan Report Oconee 2, 4th Interval, Outage 2 (EOC-22)This report includes all changes through addendum ONS2-057 The user is responsible for verifying this report against the issued plan.Summary Num Component ID / Type Cate pan'AUG Insp Procedure Req System ISO/DWG Numbers Mat Sched ThickWDia Cal Blocks Comments / Historical Data 02.G1 .1.0001 2-RCP-2A1 50 OM-201D-038 Class 1 O-ISIN4-100A-2.1 54-11-117 UT CS 9.500 / 72.000 GO1.001.001, G01.001.001 A RCP 2A1 Flywheel.

Reference Section 7 of the ISI Plan, General Requirements.

--(GO1.001.001A)Whenever maintenance or repair activities necessitate flywheel removal, a surface examination of exposed surfaces and a complete volumetric examination shall be performed if the interval measured from the previous such inspection is greater than 6 2/3 years.G01.001.001, GO1.001.001A RCP 2A1 Flywheel.

Reference Section 7 of the ISI Plan, General Requirements.

--(GO1.001.001A)Whenever maintenance or repair activities necessitate flywheel removal, a surface examination of exposed surfaces and a complete volumetric examination shall be performed if the interval measured from the previous such inspection is greater than 6 2/3 years.02.G1.1.0001 2-RCP-2A1 50 OM-201 D-038 Class 1 O-ISIN4-100A-2.1 54-1SI-271 MT CS 9.500 / 72.000 02.G1.1.0005 GO1.001.002, G01.001.002A 2-RCP-2A2 50 OM-201 D-038 NDE-900 UT CS 9.500 / 72.000 Component RCP 2A2 Flywheel.

Reference Section 7 of the ISI Class 1 O-ISIN4-100A-2.1 Plan, General Requirements.

-- (GO1.001.002A)

Whenever maintenance or repair activities necessitate flywheel removal, a surface examination of exposed surfaces and a complete volumetric examination shall be performed if the interval measured from the previous such inspection is greater than 6 2/3 years.02.G1.1.0006 GO1.001.003, GO1.001.003A 2-RCP-2B1 50 OM-201D-038 NDE-900 UT CS 9.500 / 72.000 Component RCP 2B1 Flywheel.

Reference Section 7 of the ISI Class 1 O-ISIN4-100A-2.1 Plan, General Requirements.

-- (GO1.001.003A)

Whenever maintenance or repair activities necessitate flywheel removal, a surface examination of exposed surfaces and a complete volumetric examination shall be performed if the interval measured from the previous such inspection is greater than 6 2/3 years.Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 1 of 70 This report includes all changes through addendum ONS2-057 Th Ter is responsible for verifying this report against the issued plan. , 0 Oconee 2, 4th Intersp; utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched ThickWDia Cal Blocks Comments / Historical Data Catego' AUG 02.G1.1.0007 GO1.001.004, GO1.001.004A 2-RCP-2B2 50 OM-201 D-038 NDE-900 UT CS 9.500 / 72.000 Component RCP 2B2 Flywheel.

Reference Section 7 of the ISI Class 1 O-ISIN4-100A-2.1 Plan, General Requirements.

-- (GO1.001.004A)

Whenever maintenance or repair activities necessitate flywheel removal, a surface examination of exposed surfaces and a complete volumetric examination shall be performed if the interval measured from the previous such inspection is greater than 6 2/3 years.02.G12.1.0005 G 12.001.005 2-PDB2-11 50 ISI-OCN2-014 PDI-UT-10 UT SS-CS 0.750 /3.500 40416 2B2 HPI Nozzle Pc.46 to Safe End Pc.47. Augmented B&W146629E Component Inspection Per MRP-139. Contact Jody Shuping for Circumferential Class 1 additional information on this examination.

Examination O-ISIN4-100A-2.1 schedule cannot exceed 5 years between examinations.

Dissimilar Nozzle to Safe End 02.G13.1.0001 G13.001.001 2-PZR-WP45 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 0.750 / 4.000 Pressurizer Spray Nozzle Pc. 9 to Spray Nozzle Safe Circumferential Class 1 B&W149679E End Pc. 45.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.002.

Dissimilar Terminal End Nozzle to Safe End 02.G13.1.0002 G 13.001.002 2-PSP-1 50 ISI-OCN2-016 NDE-68 VT-2 SS-Inconel 0.531 / 4.000 Pressurizer Spray Piping. Nozzle Pc. 45 to Pipe Pc. 90.Circumferential Class 1 OFD 100A-2.2 Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Pipe Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 2 of 70 This report includes all changes through addendum ONS2-057 Th ler is responsible for verifying this report against the issued plan.0 Oconee 2, 4th Interfutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor AUG 02.G13.1.0003 2-PZR-WP23 Circumferential 50 ISI-OCN2-002 Class 1 B&W149768E NDE-68 VT-2 SS-CS 1.063 / 11.375 G13.001.003 Pressurizer Surge Nozzle Pc. 8 to Surge Nozzle Safe End Pc. 37. Material thickness ranges from 1.250 to 1.063.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Safe End 02.G13.1.0004 G13.001.004 2-PZR-WP91-1 50 ISI-OCN2-002 NDE-68 VT-2 SS-CS 0.375 / 2.500 Pressurizer Relief Nozzle Pc. 31 to Relief Nozzle Safe Circumferential Class 1 OM-1201-1526 End Pc. 32. W-X Quadrant.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Safe End 02.G13.1.0005 G 13.001.005 2-PZR-WP91-2 50 ISI-OCN2-002 NDE-68 VT-2 SS-CS 0.375 / 2.500 Pressurizer Relief Nozzle Pc. 31 to Relief Nozzle Safe Circumferential Class 1 OM-1201-1526 End Pc. 32. X-Y Quadrant.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Safe End Printed 7/18/2007 1 :08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 3 of 70 This report includes all changes through addendum ONS2-057 Th mer is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter. outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor AUG 02.G13.1.0006 G 13.001.006 2-PZR-WP91-3 50 ISI-OCN2-002 NDE-68 VT-2 SS-CS 0.375 /2.500 Pressurizer Relief Nozzle Pc. 31 to Relief Nozzle Safe Circumferential Class 1 OM-1201-1526 End Pc. 32. Z-W Quadrant.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Safe End 02.G13.1.0007 G 13.001.007 2-PHA-17 50 ISI-OCN2-005 NDE-68 VT-2 CS-Inconel 1.125 /12.750 Steam Generator 2A Hot Leg to Reactor Vessel.Circumferential Class 1 B&W146630E Decay Heat Nozzle Pc. 34 to Inconel Buttering Pc. 17.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.008.

Dissimilar Stress Weld Nozzle to Buttering 02.G 13.1.0008 G 13.001.008 2-53A-10-10A Circumferential 53A 2-53A-10 Class 1 B&W146630E O-ISIN4-1 OOA-2.1 NDE-68 VT-2 SS-Inconel 1.125 / 12.000 Low Pressure Injection System. Decay Heat Nozzle Inconel Buttering Pc. 34 to Pipe (12" NPS).Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Nozzle Inconel Buttering to Pipe Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 4 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. A Oconee 2, 4th Inter .. utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor AUG 02.G13.1.0009 2-PHB-17 Circumferential 50 ISI-OCN2-006 Class 1 B&W146622E NDE-68 VT-2 CS-Inconel 1.000 / 10.750 G13.001.009 Steam Generator 2B Hot Leg to Reactor Vessel. Surge Nozzle Pc. 25 to Inconel Buttering Pc. 17.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.010.

Dissimilar Stress Weld 02.G13.1.0010 2-PSL-10 Circumferential Nozzle to Buttering 50 ISI-OCN2-015 Class 1 B&W146622E NDE-68 VT-2 SS-CS 1.000 / 10.750 G13.001.010 Pressurizer Surge Piping. Nozzle Pc. 25 to Pipe Pc. 85.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld 02.G13.1.0011 2-PZR-WP63-1 Circumferential Nozzle to Pipe 50 ISI-OCN2-002 Class 1 B&W149771E NDE-68 VT-2 CS-Inconel 1.185 / 1.000 G13.001.011 The surface of the Pressurizer Sensing and Sampling Nozzle-to-Safe End Welds shall be examined (W-X Quadrant).

Augmented Inspection Per MRP-139.Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.012.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 Printed 7/18/2007 1:08:45 PM 1ck8302 v.07/02/07 SDQA Cat 'C" Oconee 2 7/18/2007 1:07:38 PM Page 5 of 70 Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 5 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. A Oconee 2, 4th Interoutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched ThickWDia Cal Blocks Comments / Historical Data Cateaor AUG 02.G13.1.0012 G13.001.012 2RC-240-6B 50 2RC-240 NDE-68 VT-2 CS-Inconel 1.185 /1.000 Augmented Inspection Per MRP-139. Contact Jody Circumferential Class 1 Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0013 G 13.001.013 2-PZR-WP63-2 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 The surface of the Pressurizer Sensing and Sampling Circumferential Class 1 B&W149771E Nozzle-to-Safe End Welds shall be examined (Y-Z Quadrant).

Augmented Inspection Per MRP-139.Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.014.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 02.G13.1.0014 G 13.001.014 2RC-240-9A 50 2RC-240 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 Augmented Inspection Per MRP-139. Contact Jody Circumferential Class 1 Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0015 2-PZR-WP63-3 Circumferential 50 ISI-OCN2-002 Class 1 B&W149771E NDE-68 VT-2 CS-Inconel 1.185 / 1.000 G13.001.015 The surface of the Pressurizer Sensing and Sampling Nozzle-to-Safe End Welds shall be examined (Z-W Quadrant).

Augmented Inspection Per MRP-139.Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.016.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 6 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor AUG 02.G13.1.0016 2RC-240-4A Circumferential 50 2RC-240 Class 1 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 G13.001.016 Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0017 G13.001.017 2-PZR-WP63-4 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 The surface of the Pressurizer Sensing and Sampling Circumferential Class 1 B&W149771E Nozzle-to-Safe End Welds shall be examined (W-X Quadrant).

Augmented Inspection Per MRP-139.Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.018.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 02.G13.1.0018 G 13.001.018 2RC-240-25V Circumferential 50 2RC-240 Class 1 NDE-68 VT-2 CS-Inconel 1.185/1.000 Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0019 2-PZR-WP63-5 Circumferential 50 ISI-OCN2-002 Class 1 B&W149771E NDE-68 VT-2 CS-Inconel 1.185 / 1.000 G13.001.019 The surface of the Pressurizer Sensing and Sampling Nozzle-to-Safe End Welds shall be examined (Y-Z Quadrant).

Augmented Inspection Per MRP-139.Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.020.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 Printed 7/18/2007 1 iO8:45 PM Ick83O2 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 7 of 70 This report includes all changes through addendum ONS2-057 T _ er is responsible for verifying this report against the issued plan. *Oconee 2, 4th nte , outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catego, AUG 02.G13.1.0020 G13.001.020 2RC-240-1A 50 2RC-240 NDE-68 VT-2 CS-Inconel 1.185 /1.000 Augmented Inspection Per MRP-139. Contact Jody Circumferential Class 1 Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0021 G 13.001.021 2-PZR-WP63-6 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 The surface of the Pressurizer Sensing and Sampling Circumferential Class 1 B&W149771E Nozzle-to-Safe End Welds shall be examined (Z-W Quadrant).

Augmented Inspection Per MRP-139.Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.022.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 02.G13.1.0022 G 13.001.022 2RC-240-21V 50 2RC-240 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 Augmented Inspection Per MRP-139. Contact Jody Circumferential Class 1 Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0023 G 13.001.023 2-PZR-WP63-7 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 The surface of the Pressurizer Sensing and Sampling Circumferential Class 1 B&W149771E Nozzle-to-Safe End Welds shall be examined (Z-W Quadrant).

Augmented Inspection Per MRP-139.Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G13.001.024.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 8 of 70 This report includes all changes through addendum ONS2-057 Th -er is responsible for verifying this report against the issued plan. 0 Oconee 2 4th Inte outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catepor AUG 02.G13.1.0024 2RC-206-6 Circumferential 50 2RC-206 Class 1 NDE-68 VT-2 SS-Inconel 1.250 / 1.000 G13.001.024 Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0025 2-50-16-8A Circumferential 50 2-50-16 Class 1 NDE-68 VT-2 SS-Inconel 0.250 / 1.000 G13.001.025 1 inch PZR vent nozzle SB-166 Nozzle to SS pipe weld. (Examine the PZR surface where the PZR Vent Nozzle and the PZR Head/Shell interface and also examine the Nozzle to SS Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0026 2RC-278-66 Circumferential 50 2RC-278 Class 1 NDE-68 VT-2 CS-Inconel 0.250 / 1.000 G13.001.026 1 inch HL SB-166 Pressure Tap SE to CS Nozzle weld and SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage.'Dissimilar Pipe to Safe End Printed 7/18/2007 1 :08:45 PM 1ck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 9 of 70 Printed 7/18/2007 1 ý08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 9 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th InterWrutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catego, AUG 02.G13.1.0027 2RC-278-70V Circumferential 50 2RC-278 Class 1 NDE-68 VT-2 CS-Inconel 0.250 / 1.000 G13.001.027 1 inch HL SB-166 Pressure Tap SE to CS Nozzle weld and SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0028 2RC-277-50 Circumferential 50 2RC-277 Class 1 NDE-68 VT-2 CS-Inconel 0.250 / 1.000 G13.001.028 1 inch HL SB-166 Pressure Tap SE to CS Nozzle weld and SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0029 2RC-277-71V Circumferential 50 2RC-277 Class 1 NDE-68 VT-2 CS-Inconel 0.250 / 1.000 G13.001.029 1 inch HL SB-166 Pressure Tap SE to CS Nozzle weld and SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End Printed 7/18/2007 1:08:45 PM 1ck8302 v.07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 10 of 70 Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 10 of 70 This report includes all changes through addendum ONS2-057 Th eer is responsible for verifying this report against the issued plan. T Oconee 2, 4th lntell"utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor AUG 02.G13.1.0030 2RC-278-23 Circumferential 50 2RC-278 Class 1 NDE-68 VT-2 CS-Inconel 0.250 / 1.000 G13.001.030

.75 inch ID HL SB-167 Flowmeter Nozzle SE to CS Nozzle weld and SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0031 2RC-278-69 Circumferential 50 2RC-278 Class 1 NDE-68 VT-2 CS-Inconel 0.250 / 1.000 G13.001.031

.75 inch ID HL SB-167 Flowmeter Nozzle SE to CS Nozzle weld and SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.1.0032 2RC-277-24 Circumferential 50 2RC-277 Class 1 NDE-68 VT-2 CS-Inconel 0.250 / 1.000 G13.001.032

.75 inch ID HL SB-167 Flowmeter Nozzle SE to CS Nozzle weld and SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End Printed 7/18/2007 1:08:45 PM 1ck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 11 of 70 Printed 7/18/2007 1 ý08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 11 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. A Oconee 2, 4th Inter u utage 2 (EOC-22)Summary Num Component ID / Type Cateqor AUG System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 02.G13.1.0033 2RC-277-70 Circumferential 50 2RC-277 Class 1 NDE-68 VT-2 CS-Inconel 0.250 / 1.000 G13.001.033

.75 inch ID HL SB-167 Flowmeter Nozzle SE to CS Nozzle weld and SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G13.2.0001 2-RPV-WR53 Circumferential 50 ISI-OCN2-001 Class 1 OM-1201-1528 NDE-68 VT-2 SS-CS 1.688 / 15.625 G13.002.001 RV A-Side Core Flood Nozzle Pc. 17 to Safe End Pc.89. W-Axis.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End 02.G13.2.0002 2-RPV-WR53A Circumferential Nozzle to Safe End 50 ISI-OCN2-001 Class 1 OM-1201-1528 NDE-68 VT-2 SS-CS 1.688 / 15.625 G 13.002.002 RV B-Side Core Flood Nozzle Pc. 17 to Safe End Pc.89. Y-Axis.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Safe End Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 12 of 70 haddendum ONS2-057 Thier is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Cate o' AUG 02.Gt3.2.0003 G 13.002.003 2-PIB1-11 50 ISI-OCN2-009 NDE-68 VT-2 CS-Inconel 0.672 /3.500 Reactor Coolant Pump 2B1 Suction Piping. Nozzle Circumferential Class 1 B&W146635E Pc. 87 to Safe End Pc. 88.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Examine with item G13.002.004.

Dissimilar Stress Weld Nozzle to Safe End 02.G13.2.0004 G 13.002.004 2-51A-35-15A 51A 2-51A-35 (1) NDE-68 VT-2 SS-Inconel 0.375 /2.500 Augmented Inspection Per MRP-139. Contact Jody Circumferential Class 1 O-ISIN4-101A-2.1 Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Elbow to Pipe 02.G13.2.0005 G 13.002.005 2-PIAl -7 50 ISI-OCN2-007 NDE-68 VT-2 SS-CS 3.000 / 33.500 Reactor Coolant Pump 2A1 Suction Piping. Pipe Pc.Circumferential Class 1 OM-1201-966 56 to Safe End Pc. 55.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Pipe to Safe End Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 13 of 70

'This report includes all changes through addendum ONS2-057 Th ,er is responsible for verifying this report against the issued plan. .i Oconee 2, 4th Inter utage 2 (EOC-22)Summary Num Component ID / Type Cate AUG Insp Procedure Req System ISO/DWG Numbers Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 02.G13.2.0006 2-PIA2-7 Circumferential 50 ISI-OCN2-008 Class 1 OM-1201-966 NDE-68 VT-2 SS-CS 2.330 / 33.500 G13.002.006 Reactor Coolant Pump 2A2 Suction Piping. Pipe Pc.56 to Safe End Pc. 55.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Pipe to Safe End 02.G1 3.2.0007 2-PIB1-7 Circumferential 50 ISI-OCN2-009 Class 1 OM-1201-966 NDE-68 VT-2 SS-CS 2.330 / 33.500 G13.002.007 Reactor Coolant Pump 2B1 Suction Piping. Pipe Pc. 56 to Safe End Pc. 55.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Pipe to Safe End 02.G13.2.0008 2-PIIB2-7 Circumferential 50 ISI-OCN2-010 Class 1 OM-1201-966 NDE-68 VT-2 SS-CS 2.330 / 33.500 G13.002.008 Reactor Coolant Pump 2B2 Suction Piping. Pipe Pc.56 to Safe End Pc. 55.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Pipe to Safe End Printed 7/18/2007 1:08:45 PM 1ck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 14 of 70 Printed 7/18/2007 1:08:45 PIM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 14 of 70 This report includes all changes through addendum ONS2-057 Thmer is responsible for verifying this report against the issued plan.0 Oconee 2, 4th Intero utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched ThickWDia Cal Blocks Comments / Historical Data Catego, AUG 02.G1 3.2.0009 G 13.002.009 2-PDA1-2 50 ISI-OCN2-011 NDE-68 VT-2 SS-CS 2.330 / 33.500 Reactor Coolant Pump 2A1 Discharge Piping. Safe End Circumferential Class 1 OM-1201-966 Pc. 49 to Elbow Pc. 53.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Safe End to Elbow 02.G13.2.0010 G 13.002.010 2-PDA2-2 50 ISI-OCN2-012 NDE-68 VT-2 SS-CS 2.330 / 33.500 Reactor Coolant Pump 2A2 Discharge Piping. Safe End Circumferential Class 1 OM-1201-966 Pc. 49 to Elbow Pc. 53.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Safe End to Elbow 02.G13.2.0011 G13.002.011 2-PDB1-2 50 ISI-OCN2-013 NDE-68 VT-2 SS-CS 2.330 /33.500 Reactor Coolant Pump 281 Discharge Piping. Safe End Circumferential Class 1 OM-1201-966 Pc. 49 to Elbow Pc. 53.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Safe End to Elbow Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 15 of 70 This report includes all changes through addendum ONS2-057 Th iner is responsible for verifying this report against the issued plan. A Oconee 2, 4th Inter!utage 2 (EOC-22) , Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categori AUG 02.G13.2.0012 2-PDB2-2 Circumferential 50 Class 1 ISI-OCN2-014 OM-1201-966 NDE-68 VT-2 SS-CS 2.330 / 33.500 G 13.002.012 Reactor Coolant Pump 282 Discharge Piping. Safe End Pc. 49 to Elbow Pc. 53.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Safe End to Elbow 02.G13.2.0014 G13.002.014 2RC-279-19AA 50 2RC-279 NDE-68 VT-2 SS-Inconel 0.250 / 1.000 1 inch LCL-SB-166 Pressure Tap SE to CS nozzle weld Circumferential Class 1 O-ISIN4-10OA-2.1

& SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Nozzle to Elbow 02.G13.2.0015 G13.002.015 2RC-279-20 50 2RC-279 NDE-68 VT-2 SS-Inconel 0.250/ 1.000 1 inch LCL-SB-166 Pressure Tap SE to CS nozzle weld Circumferential Class 1 O-ISIN4-10OA-2.1

& SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Nozzle to Elbow Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDOA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 16 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. A Oconee 2, 4th Intero utage 2 (EOC-22) 0 Summary Num Component ID / Type Insp Procedure Req System ISOIDWG Numbers Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catepor AUG 02.G13.2.0016 G13.002.016 2-PIAl-11 Circumferential 50 ISI-OCN2-007 Class 1 B&W146823E NDE-68 VT-2 SS-Inconel 0.816 / 3.500 Reactor Coolant Pump 2A1 Suction Piping. Nozzle Pc. 64 to Safe End Pc. 65.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Examine with item G13.002.017.

Dissimilar Stress Weld 02.G13.2.0017 2-50-7-29 Circumferential Nozzle to Safe End 50 2-50-7 (1)Class 1 0-ISIN4-100A-2.1 NDE-68 VT-2 SS-Inconel 0.281 / 1.500 G13.002.017 Reactor Coolant Pump 2A1 Suction Drain Piping.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Nozzle to Elbow 02.G13.2.0018 2-PIA2-11 Circumferential 50 ISI-OCN2-008 Class 1 B&W146823E NDE-68 VT-2 SS-Inconel 0.816 / 3.500 G13.002.018 Reactor Coolant Pump 2A2 Suction Piping. Nozzle Pc. 64 to Safe End Pc. 65.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Examine with item G13.002.019.

Dissimilar Stress Weld Nozzle to Safe End Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" PvOconee 2 7/18/2007 1:07:38 PM Page 17 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee Z 4th Inter outage 2 (EOC-22)Summary Num Component ID / Type Insp Procedure Req System ISO/DWG Numbers Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catego, AUG 02.G1 3.2.0019 G1 3.002.019 2-50-7-14 Circumferential 50 Class 1 2-50-7 (1)0-ISIN4-100A-2.1 NDE-68 VT-2 SS-Inconel 0.281 / 1.500 Reactor Coolant Pump 2A2 Suction Drain Piping.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Nozzle to Elbow 02.G13.2.0020 2-PIB2-11 Circumferential 50 ISI-OCN2-010 Class 1 B&W146823E NDE-68 VT-2 CS-Inconel 0.816 / 3.500 G13.002.020 Reactor Coolant Pump 2B2 Suction Piping. Nozzle Pc. 64 to Safe End Pc. 65.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Examine with item G13.002.021.

Dissimilar Stress Weld Nozzle to Safe End 02.G13.2.0021 2-50-7-8 Circumferential 50 2-50-7 (2)Class 1 0-ISIN4-100A-2.1 NDE-68 VT-2 SS-Inconel 0.281 / 1.500 G13.002.021 Reactor Coolant Pump 2B2 Suction Drain Piping.Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Elbow to Nozzle Printed 7/18/2007 1:08:45 PM Ick83O2 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 18 of 70 This report includes all changes through addendum ONS2-057 Th 'ier is responsible for verifying this report against the issued plan. A Oconee 2, 4th Inter outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Cateoor AUG 02.G13.2.0022 G 13.002.022 2RC-279-21 50 2RC-279 NDE-68 VT-2 SS-Inconel 0.250 /1.000 1 inch UCL-SB-166 Pressure Tap SE to CS nozzle weld Circumferential Class 1 O-ISIN4-10OA-2.1

& SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Nozzle to Elbow 02.G13.2.0023 G 13.002.023 2RC-279-22A 50 2RC-279 NDE-68 VT-2 SS-Inconel 0.250 / 1.000 1 inch UCL-SB-166 Pressure Tap SE to CS nozzle weld Circumferential Class 1 O-ISIN4-100A-2.1

& SS pipe weld. (Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Augmented Inspection Per MRP-139. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed once every third refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Stress Weld Nozzle to Elbow 02.G14.1.0001 G14.001.001 2-PZR-THERM 50 NDE-68 VT-2 CS-Inconel 0.250 / 1.000 1.5 inch Thermowell located on the Pressurizer.

Circumferential Class 1 OM 1201-1135 Augmented Inspection Per Oconee Response to BL-OM 100-1189 2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Nozzle to Elbow Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 19 of 70 This report includes all changes through addendum ONS2-057 Thmer is responsible for verifying this report against the issued plan.Oconee 2, 4th Interoutage 2 (EOC-22)Summary Num Component ID / Type Catepor AUG 02.G14.1.0002 2-PZR-WP45 Circumferential System ISO/DWG Numbers Pnsp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 50 ISI-OCN2-002 Class 1 B&W149679E NDE-68 VT-2 CS-Inconel 0.750 / 4.000 Gi14.001.002 Pressurizer Spray Nozzle Pc. 9 to Spray Nozzle Safe End Pc. 45.Augmented Inspection Per Oconee response to BL-2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G14.001.003.

Dissimilar Terminal End Nozzle to Safe End 02.G14.1.0003 2-PSP-1 Circumferential 50 ISI-OCN2-016 Class 1 OFD 100A-2.2 NDE-68 VT-2 SS-Inconel 0.531 / 4.000 G14.001.003 Pressurizer Spray Piping. Nozzle Pc. 45 to Pipe Pc. 90.Augmented Inspection Per Oconee response to BL-2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Pipe 02.G14.1.0004 2-PZR-WP23 Circumferential 50 ISI-OCN2-002 Class 1 B&W149768E NDE-68 VT-2 SS-CS 1.063 / 11.375 G14.001.004 Pressurizer Surge Nozzle Pc. 8 to Surge Nozzle Safe End Pc. 37. Material thickness ranges from 1.250 to 1.063.Augmented Inspection Per Oconee response to BL-2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Safe End Printed 7/18/2007 1:08:45 PM 1ck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 20 of 70 Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 20 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.0Oconee 2, 4th Intero utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched ThickWDia Cal Blocks Comments / Historical Data Categor AUG 02.G14.1.0005 2-PZR-WP91-1 Circumferential 50 ISI-OCN2-002 Class 1 OM-1201-1526 NDE-68 VT-2 SS-CS 0.375 / 2.500 G14.001.005 Pressurizer Relief Nozzle Pc. 31 to Relief Nozzle Safe End Pc. 32. W-X Quadrant.Augmented Inspection Per Oconee response to BL-2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Safe End 02.G14.1.0006 2-PZR-WP91-2 Circumferential 50 ISI-OCN2-002 Class 1 OM-1201-1526 NDE-68 VT-2 SS-CS 0.375 / 2.500 G14.001.006 Pressurizer Relief Nozzle Pc. 31 to Relief Nozzle Safe End Pc. 32. X-Y Quadrant.Augmented Inspection Per Oconee response to BL-2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Safe End 02.Gl4.1.0007 2-PZR-WP91-3 Circumferential 50 ISI-OCN2-002 Class 1 OM-1201-1526 NDE-68 VT-2 SS-CS 0.375 / 2.500 G14.001.007 Pressurizer Relief Nozzle Pc. 31 to Relief Nozzle Safe End Pc. 32. Z-W Quadrant.Augmented Inspection Per Oconee response to BL-2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Terminal End Nozzle to Safe End Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 21 of 70 This report includes all changes through addendum ONS2-057 Th ier is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter utage 2 (EOC-22)Summary Num Component ID / Type Categorv AUG 02.G14.1.0008 2-PZR-WP63-1 Circumferential System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 50 ISI-OCN2-002 Class 1 B&W149771E NDE-68 VT-2 CS-Inconel 1.185 /1.000 G14.001.008 The surface of the Pressurizer Sensing and Sampling Nozzle-to-Safe End Welds shall be examined (W-X Quadrant).

Augmented Inspection Per Oconee response to BL-2004-01.

Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G14.001.009.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 02.G 14.1.0009 G 14.001.009 2RC-240-6B 50 2RC-240 NDE-68 VT-2 CS-Inconel 1.185 /1.000 Augmented Inspection Per Oconee response to BL-Circumferential Class 1 2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G14.1.0010 G 14.001.010 2-PZR-WP63-2 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 The surface of the Pressurizer Sensing and Sampling Circumferential Class 1 B&W149771E Nozzle-to-Safe End Weldsshall be examined (Y-Z Quadrant).

Augmented Inspection Per Oconee response to BL-2004-01.

Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G14.001.011.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 22 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Interoutage 2 (EOC-22)Summary Num Component ID / Type Categor AUG Insp Procedure Req System ISOIDWG Numbers Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 02.G14.1.0011 2RC-240-9A Circumferential 50 2RC-240 Class 1 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 G14.001.011 Augmented Inspection Per Oconee response to BL-2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G14.1.0012 2-PZR-WP63-3 Circumferential 50 ISI-OCN2-002 Class 1 B&W149771E NDE-68 VT-2 CS-Inconel 1.185 / 1.000 G14.001.012 The surface of the Pressurizer Sensing and Sampling Nozzle-to-Safe End Welds shall be examined (Z-W Quadrant).

Augmented Inspection Per Oconee response to BL-2004-01.

Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G14.001.013.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 02.G14.1.0013 2RC-240-4A Circumferential 50 2RC-240 Class 1 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 G14.001.013 Augmented Inspection Per Oconee response to BL-2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End Printed 7/18/2007 1:08:45 PM 1ck8302 V. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 23 oF 70 Printed 7/18/2007 1 i08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 23 of 70 This report includes all changes through addendum ONS2-057 Thmer is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter outage 2 (EOC-22)Summary Num Component ID / Type System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor AUG 02.G14.1.0014 G 14.001.014 2-PZR-WP63-4 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 The surface of the Pressurizer Sensing and Sampling Circumferential Class 1 B&W149771E Nozzle-to-Safe End Welds shall be examined (W-X Quadrant).

Augmented Inspection Per Oconee response to BL-2004-01.

Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number Gi14.001.015.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 02.G14.1.0015 G 14.001.015 2RC-240-25V 50 2RC-240 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 Augmented Inspection Per Oconee response to BL-Circumferential Class 1 2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G14.1.0016 G14.001.016 2-PZR-WP63-5 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 1.185 /1.000 The surface of the Pressurizer Sensing and Sampling Circumferential Class 1 B&W149771E Nozzle-to-Safe End Welds shall be examined (Y-Z Quadrant).

Augmented Inspection Per Oconee response to BL-2004-01.

Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G14.001.017.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 24 of 70 This report includes all changes through addendum ONS2-057 Thier is responsible for verifying this report against the issued plan. 1 Oconee 2, 4th Intermutage 2 (EOC-22) W Summary Num Component ID / Type System ISO/DWG Numbers Insp Procedure Req Mat Sched ThickWDia Cal Blocks Comments / Historical Data Categor AUG 02.G14.1.0017 G14.001.017 2RC-240-1A 50 2RC-240 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 Augmented Inspection Per Oconee response to BL-Circumferential Class 1 2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G14.1.0018 G14.001.018 2-PZR-WP63-6 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 1.185 / 1.000 The surface of the Pressurizer Sensing and Sampling Circumferential Class 1 B&W149771E Nozzle-to-Safe End Welds shall be examined (Z-W Quadrant).

Augmented Inspection Per Oconee response to BL-2004-01.

Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G14.001.019.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 02.G14.1.0019 G14.001.019 2RC-240-21V 50 2RC-240 NDE-68 VT-2 CS-Inconel 1.185 /1.000 Augmented Inspection Per Oconee response to BL-Circumferential Class 1 2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 25 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor AUG 02.G14.1.0020 G 14.001.020 2-PZR-WP63-7 50 ISI-OCN2-002 NDE-68 VT-2 CS-Inconel 1.185 /1.000 The surface of the Pressurizer Sensing and Sampling Circumferential Class 1 B&W149771E Nozzle-to-Safe End Welds shall be examined (Z-W Quadrant).

Augmented Inspection Per Oconee response to BL-2004-01.

Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Inspect with item number G14.001.021.

Dissimilar Nozzle Pc.30 to Safe End Pc.42 02.G14.1.0021 G 14.001.021 2RC-206-6 50 2RC-206 NDE-68 VT-2 SS-Inconel 1.250 / 1.000 Augmented Inspection Per Oconee response to BL-Circumferential Class 1 2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02.G14.1.0022 G 14.001.022 2-50-16-8A 50 2-50-16 NDE-68 VT-2 SS-Inconel 0.250 / 1.000 1 inch PZR vent nozzle SB-166 Nozzle to SS pipe Circumferential Class 1 weld. (Examine the PZR surface where the PZR Vent Nozzle and the PZR Head/Shell interface and also examine the Nozzle to SS Pipe weld.)Augmented Inspection Per Oconee response to BL-2004-01. Contact Jody Shuping for additional information on this examination.

Bare Metal Visual Examinations are to be performed each refueling outage by a VT-2 qualified inspector.

Acceptance criteria is "no evidence of borated water leakage." Dissimilar Pipe to Safe End 02 G2 1 0nn1 G02.001.005C 2-PDB1-46 50 ISI-OCN2-013 B&W146629E Class 1 O-ISIN4-100A-2.1 NDE-690 UT CS 2.500 / 3.500 40410 2B1 HPI Nozzle Pc.46. Perform UT on the nozzle inside 40350 radius (knuckle area). Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 Printed 7/18/2007 1:08:45 PM 1ck8302 v. 07/02/07 SOQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 26 of 70 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 26 of 70 This report includes all changes through addendum ONS2-057 Thmer is responsible for verifying this report against the issued plan.Oconee 2, 4th Intero, outage 2 (EOC-22)Summary Num Component ID / Type Insp Procedure Req System ISO/DWG Numbers Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor AUG 02.G2.1.0002

'G02.001.005B 2-PDA2-46 50 ISI-OCN2-012 NDE-690 UT CS 2.500 / 3.500 40410 2A2 Make-Up Nozzle Pc.46. Perform UT on the nozzle B&W 146629E 40350 inside radius (knuckle area). Reference Section 7 of the Class 1 ISI Plan, General Requirments.

This schedule cannot O-ISIN4-100A-2.1 be changed without Engineering approval.02.G2.1.0003 G02.001.005A 2-PDA1-46 50 ISI-OCN2-011 NDE-690 UT CS 2.500./ 3.500 40410 2A1 Make-Up Nozzle Pc.46. Perform UT on the nozzle B&W 146629E 40350 inside radius (knuckle area). Reference Section 7 of the Class 1 ISI Plan, General Requirements.

This schedule cannot O-ISIN4-100A-2.1 be changed without Engineering approval.02.G2.1.0004 G02.001.005D 2-PDB2-46 50 ISI-OCN2-014 NDE-690 UT CS 2.500 / 3.500 40410 2B2 HPI Nozzle Pc.46. Perform UT on the nozzle B&W146629E 40350 inside radius (knuckle area). Reference Section 7 of Class 1 the ISI Plan, General Requirements.

This schedule O-ISlN4-1 OOA-2.1 cannot be changed without Engineering approval.02.G2.1.0005 G02.001.006A 2-PDA1-11 50 ISI-OCN2-011 PDI-UT-10 UT SS-CS 0.750 /3.500 40416 2A1 Make-Up Nozzle Pc.46 to Safe End Pc.47.Circumferential Class 1 B&Wt46629E Perform UT on the nozzle to safe end weld. Reference O-ISIN4-100A-2.1 Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.This weld was cut out and welded back in EOC-20. The new weld is also listed as weld 29 on rev .11 of iso 2RC-204.Dissimilar Nozzle to Safe End 02.G2.1.0006 G02.001.006B 2-PDA2-11 50 ISI-OCN2-012 PDI-UT-10 UT SS-CS 0.750 / 3.500 40416 2A2 Make-Up Nozzle Pc.46 to Safe End Pc.47.Circumferential Class 1 B&W146629E Perform UT on the nozzle to safe end weld. Reference O-ISlN4-100A-2.1 Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.This weld was cut out and welded back in EOC-20. The new weld is also listed as weld 22 on rev. 10 of iso 2RC-203.Dissimilar Nozzle to Safe End Printed 7/18/2007 1:08:45 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 27 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Interolutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor AUG 02.G2.1.0007 2-PDB2-11 Circumferential 50 ISI-OCN2-014 Class 1 B&W146629E 0-ISIN4-100A-2.1 PDI-UT-10 UT SS-CS 0.750 / 3.500 G02.001.006D 40416 2B2 HPI Nozzle Pc.46 to Safe End Pc.47. Perform UT on the nozzle to safe end weld. Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.Dissimilar Nozzle to Safe End 02.G2.1.0008 G02.001.006C 2-PDB1-11 50 ISI-OCN2-013 PDI-UT-10 UT SS-CS 0.750 /3.500 40416 2B1 HPI Nozzle Pc.46 to Safe End Pc.47. Perform UT Circumferential Class 1 B&W146629E on the nozzle to safe end weld.0-ISIN4-100A-2.1 This weld was cut out and welded back in EOC-20. The new weld is also listed as weld 16 on rev .8 of iso 2RC-202.Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.Dissimilar Nozzle to Safe End 02.G2.1.0009 G02.001.007C 2-PDB1-47 50 ISI-OCN2-013 PDI-UT-10 UT SS 0.750 /3.500 40416 Safe End Pc.47 adjoining HPI Nozzle 2B1. Perform UT Class 1 B&W146629E on the Safe End base metal (between the nozzle to 0-ISIN4-100A-2.1 safe end weld and the safe end to pipe weld).Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.02.G2.1.0010 G02.001.007D 2-PDB2-47 50 ISI-OCN2-014 PDI-UT-10 UT SS 0.750 / 3.500 40416 Safe End Pc.47 adjoining HPI Nozzle 2B2. Perform UT Class 1 B&W146629E on the Safe End base metal (between the nozzle to 0-ISIN4-10OA-2.1 safe end weld and the safe end to pipe weld).Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.02.G2.1.0011 G02.001.007A 2-PDAl-47 50 ISI-OCN2-011 PDI-UT-10 UT SS 0.750 / 3.500 40416 Safe End Pc.47 adjoining Make-Up Nozzle 2A1.Class 1 B&W146629E Perform UT on the Safe End base metal (between the 0-ISIN4-100A-2.1 nozzle to safe end weld and the safe end to pipe weld).Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 28 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.T Oconee 2, 4th Inter outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched ThickWDia Cal Blocks Comments / Historical Data Categor AUG 02 G2 1 0012 G02.001.007B 2-PDA2-47 50 ISI-OCN2-012 Class 1 B&W146629E 0-ISIN4-100A-2.1 PDI-UT-10 UT SS 0.750 / 3.500 40416 Safe End Pc.47 adjoining Make-Up Nozzle 2A2.Perform UT on the Safe End base metal (between the nozzle to safe end weld and the safe end to pipe weld).Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.02.G2.1.0013 2RC-204-28 Circumferential 50 2RC-204 Class 1 B&W146629E 0-ISIN4-100A-2.1 NDE-995 UT SS 02.G2.1.0014 2RC-202-17 Circumferential 50 2RC-202 Class 1 B&W146629E 0-ISIN4-100A-2.1 NDE-995 UT SS G02.001.008A 0.375 / 2.500 Component Make-Up Nozzle 2A1. Perform UT on weld 2RC-204-28 and adjoining base metal out to weld 2RC-204-20 (at valve 2HP-127).Weld 2RC-204-18 was cut out and replaced with weld 2RC-204-28 during EOC-20.Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.

Note: The inspection performed for this G02 item number will satisfy the requirements for G04.001.029.

Safe End to Pipe G02.001.008C 0.375 / 2.500 Component HPI Nozzle 2B1. Perform UT on weld 2RC-202-17 and adjoining base metal out to weld 2RC-202-19 (at valve 2HP-153).

Reference Section 7 of the ISI Plan, General Requirements.

Weld 2RC-202-1 was cut out and replaced with weld 2RC-202-17 during EOC-20.This schedule cannot be changed without Engineering approval.Note: The inspection performed for this G02 item number will satisfy the requirements for G04.001.001.

Safe End to Pipe G02.001.008B 0.375 / 2.500 Component Make-Up Nozzle 2A2. Perform UT on weld 2RC-203-21 and adjoining base metal out to weld 2RC-203-3 (at valve 2HP-126).

Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.Weld 2RC-203-2 was cut out and replaced with weld 2RC-203-21 during EOC-20.Note: The inspection performed for this G02 item number will satisfy the requirements for G04.001.027.

02.G2.1.0015 2RC-203-21 Circumferential 50 2RC-203 Class 1 B&W146629E 0-ISIN4-100A-2.1 NDE-995 UT SS Safe End to Pipe Printed 7/18/2007 1:08:46 PM 1ck8302 v.07/02/07 SDQA Cat "C" Oconee2 7/18/2007 1:07:38 PM Page 29 of 70 Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 29 of 70 This report includes all changes through addendum ONS2-057 Thier is responsible for verifying this report against the issued plan. , Oconee 2, 4th Interoutage 2 (EOC-22) W Summary Num Component ID / Type System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categorv AUG 02.G2.1.0016 G02.001.008D 2RC-205-1 50 2RC-205 NDE-995 UT SS 0.375 / 2.500 Component HPI Nozzle 2B2. Perform UT on weld 2RC-205-1 and Circumferential Class 1 B&W146629E adjoining base metal out to weld 2RC-205-3 (at valve 0-ISIN4-100A-2.1 2HP-152).

Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.Note: The inspection performed for this G02 item number will satisfy the requirements for G04.001.004.

Safe End to Pipe 02.G2.1.0017 G02.001.010B 2RC-203-3 Circumferential 50 2RC-203 Class 1 B&W146629E 0-ISIN4-100A-2.1 NDE-995 UT SS 0.375 / 2.500 Component Make-Up Nozzle 2A2. Perform UT on weld 2RC-203-3 at valve 2HP-126. Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.Note: The inspection performed for this G02 item number will satisfy the requirements for G04.001.028.

02.G2.1.0018 2RC-202-19 Circumferential 02.G2.1.0019 2RC-204-20 Circumferential 02.G2.1.0020 2RC-205-3 Circumferential Pipe to Valve G02.001.010C 50 2RC-202 NDE-995 UT SS 0.375 / 2.500 Component HPI Nozzle 2B1. Perform UT on weld 2RC-202-19 at Class 1 B&W146629E valve 2HP-153. Reference Section 7 of the ISI Plan, 0-ISIN4-100A-2.1 General Requirements.

This schedule cannot be changed without Engineering approval.Weld 2RC-202-3 was cut out and replaced with weld 2RC-202-19 during EOC-20.Note: The inspection performed for this G02 item number will satisfy the requirements for G04.001.003.

Pipe to Valve G02.001.01OA 50 2RC-204 NDE-995 UT SS 0.375 / 2.500 Component Make-Up Nozzle 2A1. Perform UT on weld 2RC-204-Class 1 B&W146629E 20 at valve 2HP-127. Reference Section 7 of the ISI 0-ISIN4-10OA-2.1 Plan, General Requirements.

This schedule cannot be changed without Engineering approval.Note: The inspection performed for this G02 item number will satisfy the requirements for G04.001.030.

Pipe to Valve G02.001.010D 50 2RC-205 Class 1 B&W146629E 0-ISIN4-100A-2.1 NDE-995 UT SS 0.375 / 2.500 Component HPI Nozzle 2B2. Perform UT on weld 2RC-205-3 at valve 2HP-152. Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.Note: The inspection performed for this G02 item number will satisfy the requirements for G04.001.006.

Pipe to Valve Printed 7/18/2007 1:08:46 PM 1ck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 30 of 70 Printed 7/18/2007 1:08:46 PM lck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 30 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.0 Oconee 2, 4th Interib.utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Category AUG 02.G2.1.0021 G02.001.011 B 2A2 THERM-SLEEVE 50 ISI OCN2-012 NDE-105 RT SS 0.750 / 3.500 Make-Up Nozzle 2A2. Perform RT between the nozzle Circumferential Class 1 B&W146629E to safe end and safe end to pipe weld in the thermal O-ISIN4-100A-2.1 sleeve expansion area as described in Procedure NDE-105. Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.02.G2.1.0022 G02.001.011 C 2B1 THERM-SLEEVE 50 ISI OCN2-013 NDE-105 RT SS 0.750 /3.500 HPI Nozzle 2B1. Perform RT between the nozzle to Circumferential Class 1 B&W146629E safe end and safe end to pipe weld in the thermal O-ISIN4-10OA-2.1 sleeve expansion area as described in Procedure NDE-105. Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.02.G2.1.0023 G02.001.01 1A 2A1 THERM-SLEEVE 50 ISI OCN2-011 NDE-105 RT SS 0.750 / 3.500 Make-Up Nozzle 2A1. Perform RT between the nozzle Circumferential Class 1 B&W146629E to safe end and safe end to pipe weld in the thermal O-ISIN4-100A-2.1 sleeve expansion area as described in Procedure NDE-105. Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.02.G2.1.0024 G02.001.011 D 2B2 THERM-SLEEVE 50 ISI OCN2-014 NDE-105 RT SS 0.750 / 3.500 HPI Nozzle 2B2. Perform RT between the nozzle to Circumferential Class 1 B&W146629E safe end and safe end to pipe weld in the thermal O-ISIN4-100A-2.1 sleeve expansion area as described in Procedure NDE-105. Reference Section 7 of the ISI Plan, General Requirements.

This schedule cannot be changed without Engineering approval.02.G4.1.0001 G04.001.001 2RC-202-17 51A 2RC-202 NDE-995 UT SS 0.375 / 2.500 Inspect 100% of weld &V" of base material (axial &Circumferential Class 1 0-ISIN4-10OA-2.1 circumferential).

This weld was listed previously as 2-51A-39-90C until iso 2-51A-39 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Weld 2RC-202-1 was cut out and replaced with weld 2RC-202-17 during EOC-20.Note: The inspection performed for G02.001.008C will satisfy the requirements for this G04 inspection.

Pipe to Safe End Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 31 of 70 This report includes all changes through addendum ONS2-057 Th ier is responsible for verifying this report against the issued plan.0 Oconee 2, 4th Intero'Dutage 2 (EOC-22)Summary Num Component ID / Type Categor AUG System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 02.G4.1.0002 2RC-202-19 Circumferential 51A 2RC-202 Class 1 O-ISIN4-101A-2.4 NDE-995 UT SS 0.375 / 2.500 Pipe to Valve 2HP-153 02.G4.1.0003 2RC-205-1 Circumferential 51A 2RC-205 Class 1 0-ISIN4-100A-2.1 NDE-995 UT SS 0.375 / 2.500 G04.001.003 Inspect 100% of weld &1" of base material (axial &circumferential).

This weld was listed previously as 2-51A-39-91 until iso 2-51A-39 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Weld 2RC-202-3 was cut out and replaced with weld 2RC-202-19 during EOC-20.Note: The inspection performed for G02.001.01OC will satisfy the requirements for this G04 inspection.

G04.001.004 Inspect 100% of weld &M" of base material (axial &circumferential).

This weld was listed previously as 2-51A-39-92A until iso 2-51A-39 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Note: The inspection performed for G02.001.008D will satisfy the requirements for this G04 inspection.

G04.001.006 Inspect 100% of weld &1" of base material (axial &circumferential).

This weld was listed previously as 2-51A-39-93 until iso 2-51A-39 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Note: The inspection performed for G02.001.010D will satisfy the requirements for this G04 inspection.

G04.001.007 Inspect 100% of weld &l" of base material (axial &circumferential).

This weld was listed previously as 2-51 A-27-73 until iso 2-51A-27 (2) was redrawn.Reference Section 7 of the ISI Plan, General Requirements.

Pipe to Safe-End 02.G4.1.0004 2RC-205-3 Circumferential 51A 2RC-205 Class 1 0-ISIN4-101A-2.4 NDE-995 UT SS 0.375 / 2.500 Pipe to Valve 2HP-152 02.G4.1.0005 2HP-218-18 Circumferential 51A 2HP-218 Class 1 0-ISIN4-101A-2.4 NDE-995 UT SS 0.375 / 2.500 Elbow to Pipe 02.G4.1.0006 G04.001.010 2HP-214-13 51A 2HP-214 NDE-995 UT SS 0.375 / 2.500 Inspect 100% of weld &M" of base material (axial &Circumferential Class 1 0-ISIN4-101A-2.4 circumferential).

This weld was listed previously as 2-51A-27-108 until iso 2-51A-27 (3) was redrawn.Reference Section 7 of the ISI Plan, General Requirements.

Pipe to Elbow Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2. 7/18/2007 1:07:38 PM Page 32 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter Dutage 2 (EOC-22) is Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catepor AUG 02.G4.1.0007 2HP-214-15 Circumferential 51A 2HP-214 Class 1 0-ISIN4-101A-2.4 NDE-995 UT SS 0.375 / 2.500 Pipe to Valve 2HP-488 02.G4.1.0008 2RC-202-4 Circumferential G04.001.011 Inspect 100% of weld & 1" of base material (axial &circumferential).

This weld was originally 2-51 A-27-1 10.It was cut out during outage 15 and replaced as 2HP-214-15. Reference Section 7 of the ISI Plan, General Requirements.

G04.001.013 Use Procedure NDE-995 to perform a circumferential scan of the weld and half of an inch of base metal on each side of the weld as access permits.Use procedure NDE-12 to perform RT on 100% of the weld and a quarter of an inch of base metal on each side of the weld.See PIP # 0-99-02157 and PIP # 0-01-04673 for examination methods and area of coverage for this item number.51A 2RC-202 Class 1 0-ISIN4-101A-2.4 NDE-12 RT SS 0.375/2.500 Valve 2HP-488 to Valve 2HP-153 02.G4.1.0008 G04.001.013 2RC-202-4 51A 2RC-202 NDE-995 UT SS 0.375 /2.500 Use Procedure NDE-995 to perform a circumferential Circumferential Class 1 0-ISIN4-101A-2.4 scan of the weld and half of an inch of base metal on each side of the weld as access permits.Use procedure NDE-12 to perform RT on 100% of the weld and a quarter of an inch of base metal on each side of the weld.See PIP # 0-99-02157 and PIP # 0-01-04673 for examination methods and area of coverage for this item number.Valve 2HP-488 to Valve 2HP-153 02.G4.1.0009 G04.001.014 2RC-203-4 51A 2RC-203 NDE-12 RT SS 0.375 / 2.500 Use Procedure NDE-995 to perform a circumferential Circumferential Class 1 O-ISIN4-1 01 A-2.4 scan of the weld and half of an inch of base metal on each side of the weld as access permits.Use procedure NDE-12 to perform RT on 100% of the weld and a quarter of an inch of base metal on each side of the weld.See PIP # 0-99-02157 and PIP # 0-01-04673 for examination methods and area of coverage for this item number.Valve 2HP-486 to Valve 2HP-126 Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 33 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. , S Oconee 2, 4th Intermutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catecor AUG 02.G4.1.0009 2RC-203-4 Circumferential 51A 2RC-203 Class 1 0-ISIN4-101A-2.4 NDE-995 UT SS 0.375 / 2.500 G04.001.014 Use Procedure NDE-995 to perform a circumferential scan of the weld and half of an inch of base metal on each side of the weld as access permits.Use procedure NDE-12 to perform RT on 100% of the weld and a quarter of an inch of base metal on each side of the weld.See PIP # 0-99-02157 and PIP # 0-01-04673 for examination methods and area of coverage for this item number.Valve 2HP-486 to Valve 2HP-126 02.G4.1.0010 G04.001.015 2RC-204-4 51A 2RC-204 NDE-12 RT SS 0.375 /2.500 Use Procedure NDE-995 to perform a circumferential Circumferential Class 1 0-ISIN4-101A-2.4 scan of the weld and half of an inch of base metal on each side of the weld as access permits.Use procedure NDE-12 to perform RT on 100% of the weld and a quarter of an inch of base metal on each side of the weld.See PIP # 0-99-02157 and PIP # 0-01-04673 for examination methods and area of coverage for this item number.Valve 2HP-487 to Valve 2HP-127 02.G4.1.0010 G04.001.015 2RC-204-4 51A 2RC-204 NDE-995 UT SS 0.375 / 2.500 Use Procedure NDE-995 to perform a circumferential Circumferential Class 1 0-ISIN4-101A-2.4 scan of the weld and half of an inch of base metal on each side of the weld as access permits.Use procedure NDE-12 to perform RT on 100% of the weld and a quarter of an inch of base metal on each side of the weld.See PIP # 0-99-02157 and PIP # 0-01-04673 for examination methods and area of coverage for this item number.Valve 2HP-487 to Valve 2HP-127 02.G4.1.0011 G04.001.016 2RC-205-4 51A 2RC-205 NDE-12 RT SS 0.375 /2.500 Use Procedure NDE-995 to perform a circumferential Circumferential Class 1 0-ISIN4-101A-2.4 scan of the weld and half of an inch of base metal on each side of the weld as access permits.Use procedure NDE-12 to perform RT on 100% of the weld and a quarter of an inch of base metal on each side of the weld.See PIP # 0-99-02157 and PIP # 0-01-04673 for examination methods and area of coverage for this item number.Valve 2HP-489 to Valve 2HP-152 Printed 7/18/2007 1-08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 34 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. ** Oconee 2, 4th Inter outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catepor AUG 02.G4.1.0011 2RC-205-4 Circumferential G04.001 .016 51A 2RC-205 Class 1 0-ISIN4-101A-2.4 NDE-995 UT SS 0.375 / 2.500 Use Procedure NDE-995 to perform a circumferential scan of the weld and half of an inch of base metal on each side of the weld as access permits.Use procedure NDE-12 to perform RT on 100% of the weld and a quarter of an inch of base metal on each side of the weld.See PIP # 0-99-02157 and PIP # 0-01-04673 for examination methods and area of coverage for this item number.Valve 2HP-489 to Valve 2HP-152 02.G4.1.0012 2HP-214-14 Circumferential 51A 2HP-214 Class 1 0-ISIN4-101A-2.4 NDE-995 UT SS 0.375 / 2.500 G04.001.017 Inspect 100% of weld & 1" of base material (axial &circumferential).

This weld was listed previously as 2-51A-27-109 until iso 2-51A-27 (3) was redrawn.Reference Section 7 of the ISI Plan, General Requirements.

Elbow to Pipe G04. 00 1.0 18 02.G4.1.0013 2HP-216-7 Circumferential 51A 2HP-216 Class 1 0-ISIN4-101A-2.4 NDE-995 UT SS 0.375 / 2.500 Inspect 100% of weld & 1" of base material (axial &circumferential).

This weld was listed previously as 2-51A-30-51 until iso 2-51A-30 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Pipe to Elbow 02.G4.1.0014 G04.001.019 2HP-216-8 51A 2HP-216 NDE-995 UT SS 0.375 /2.500 Inspect 100% of weld & 1" of base material (axial &Circumferential Class 1 0-ISIN4-101A-2.4 circumferential).

This weld was listed previously as 2-51 A-30-52 until iso 2-51A-30 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Elbow to Pipe 02.G4.1.0015 G04.001.020 2HP-216-9 51A 2HP-216 NDE-995 UT SS 0.375 / 2.500 Inspect 100% of weld & 1" of base material (axial &Circumferential Class 1 0-ISIN4-101A-2.4 circumferential).

This weld was listed previously as 2-51A-30-54 until iso 2-51A-30 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Pipe to Valve 2HP-486 02.G4.1.0016 G04.001.021 2HP-217-10 51A 2HP-217 NDE-995 UT SS 0.375 / 2.500 Inspect 100% of weld & 1'" of base material (axial &Circumferential Class 1 0-ISIN4-101A-2.4 circumferential).

This weld was listed previously as 2-51 A-30-28 until iso 2-51A-30 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Pipe to Elbow Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 35 of 70 SThis report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.* Oconee 2, 4th Intero utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categorv AUG 02.G4.1.0017 G04.001.022 2HP-217-11 51A 2HP-217 NDE-995 UT SS 0.375/ 2.500 Inspect 100% of weld & 1" of base material (axial &Circumferential Class 1 O-ISIN4-101A-2.4 circumferential).

This weld was listed previously as 2-51A-30-29 until iso 2-51A-30 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Elbow to Pipe 02.G4.1.0018 G04.001.023 2HP-217-12 51A 2HP-217 NDE-995 UT SS 0.375 /2.500 Inspect 100% of weld & 1" of base material (axial &Circumferential Class 1 O-ISIN4-101A-2.4 circumferential).

This weld was listed previously as 2-51A-30-31 until iso 2-51A-30 was redrawn. Reference Section 7 of the ISI Plan, General Requirements.

Pipe to Valve 2HP-487 02.G4.1.0019 G04.001.024 2HP-218-20 51A 2HP-218 NDE-995 UT SS 0.375 / 2.500 Inspect 100% of weld & 1," of base material (axial &Circumferential Class 1 O-ISIN4-101A-2.4 circumferential).

This weld was listed previously as 2-51A-27-79 until iso 2-51A-27 (2) was redrawn.Reference Section 7 of the ISI Plan, General Requirements.

Pipe to Elbow 02.G4.1.0020 G04.001.025 2HP-218-21 51A 2HP-218 NDE-995 UT SS 0.375 /2.500 Inspect 100% of weld & 1" of base material (axial &Circumferential Class 1 O-ISIN4-101A-2.4 circumferential).

This weld was listed previously as 2-51A-27-80 until iso 2-51A-27 (2) was redrawn.Reference Section 7 of the ISI Plan, General Requirements.

Elbow to Pipe 02.G4.1.0021 G04.001.026 2HP-218-22 51A 2HP-218 NDE-995 UT SS 0.375 / 2.500 Inspect 100% of weld & 1," of base material (axial &Circumferential Class 1 O-ISIN4-101A-2.4 circumferential).

Reference Section 7 of the ISI Plan, General Requirements.

Pipe to Valve 2HP-489 02.G4.1.0022 G04.001.027 2RC-203-21 50 2RC-203 NDE-995 UT SS 0.375 / 2.500 Component Inspect 100% of weld & 1" of base material (axial &Circumferential Class 1 B&W146629E circumferential).

Reference Section 7 of the ISI Plan, O-ISlN4-100A-2.1 General Requirements.

Weld 2RC-203-2 was cut out and replaced with weld 2RC-203-21 during EOC-20.Note: The inspection performed for G02.001.0083 will satisfy the requirements for this G04 inspection.

Safe End to Pipe Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 36 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. d Oconee 2, 4th InterM utage 2 (EOC-22) 1 Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catecor AUG 02.G4.1.0023 G04.001.028 2RC-203-3 Circumferential 50 2RC-203 Class 1 B&W146629E 0-ISIN4-1 OOA-2.1 NDE-995 UT SS 02.G4.1.0024 2RC-204-28 Circumferential 50 2RC-204 Class 1 B&W146629E 0-ISIN4-10OA-2.1 NDE-995 UT SS 0.375 / 2.500 Component Inspect 100% of weld & 1" of base material (axial &circumferential).

Reference Section 7 of the ISI Plan, General Requirements.

Note: The inspection performed for G02.001.010B will satisfy the requirements for this G04 inspection.

Pipe to Valve 2HP-126 G04.001.029 0.375 / 2.500 Component Inspect 100% of weld & 1" of base material (axial &circumferential).

Reference Section 7 of the ISI Plan, General Requirements.

Weld 2RC-204-18 was cut out and replaced with weld 2RC-204-28 during EOC-20.Note: The inspection performed for G02.001.008A will satisfy the requirements for this G04 inspection.

Safe End to Pipe G04.001.030 0.375 / 2.500 Component Inspect 100% of weld & 1" of base material (axial &circumferential).

Reference Section 7 of the ISI Plan, General Requirements.

Inspect this weld at the same time item number G02.001.010A is inspected.

Note: The inspection performed for the G02 item number will be sufficient to meet the requirements for the G04 inspection.

02.G4.1.0025 2RC-204-20 Circumferential 50 2RC-204 Class 1 B&W146629E 0-ISlN4-100A-2.1 NDE-995 UT SS Pipe to Valve 2HP-127 Categor B-A 02.B13.30.0001 2-RPV-WR19 Circumferential 50 ISI-OCN2-001 OM-1201-454 Class 1 NDE-650 UT CS 12.000 / 167.630 B01.030.001, B01.030.001A Reactor Vessel Upper Shell Forging Pc. 86 to Flange CB-08-99 Pc. 7. (B101.030.001)

Inspect from Vessel ID.(automated scan) -- (B01.030.001A)

Inspect from Flange Surface. (manual scan)Shell to Flange Cateaor, B-D 02.B3.110.0001 2-PZR-WP15 Circumferential B03.1 10.001 40394 Pressurizer Surge Nozzle Pc. 8 to Lower Head Pc. 6.50 ISI-OCN2-002 Class 1 OM-1201-456 B&W149768E NDE-820 UT CS 4.750/15.250 Nozzle to Head Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 37 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. *Oconee Z 4th Inter utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor B-D 02.B3.110.0001 2-PZR-WP15 Circumferential B03.110.001 40394 Pressurizer Surge Nozzle Pc. 8 to Lower Head Pc. 6.50 ISI-OCN2-002 Class 1 OM-1201-456 B&W149768E NDE-640 UT CS 4.750 / 15.250 Nozzle to Head 02.B3.110.0006 B03.110.006 2-PZR-WP26-4 50 ISI-OCN2-002 PDI-UT-7 UT CS 6.187 / 5.750 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell OM-1201-456 50470 Course Pc. 1. W-X Quadrant.Circumferential Class 1 B&W149771 E Nozzle to Shell 02.B3.110.0006 B03.110.006 2-PZR-WP26-4 50 ISI-OCN2-002 NDE-820 UT CS 6.187 / 5.750 40338 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell Circumferential Class 1 OM-1201-456 Course Pc. 1. W-X Quadrant.B&W149771E Nozzle to Shell 02.B3.110.0006 B03.110.006 2-PZR-WP26-4 50 ISI-OCN2-002 NDE-640 UT CS 6.187 / 5.750 40338 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell Circumferential Class 1 OM-1201-456 Course Pc. 1. W-X Quadrant.B&W149771E Nozzle to Shell 02.B3.110.0007 B03.110.007 2-PZR-WP26-5 50 ISI-OCN2-002 NDE-820 UT CS 6.187 / 5.750 40338 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell Circumferential Class 1 OM-1201-456 Course Pc. 1. Y-Z Quadrant.B&W149771 E Nozzle to Shell 02.B3.110.0007 B03.110.007 2-PZR-WP26-5 50 ISI-OCN2-002 NDE-640 UT CS 6.187 / 5.750 40338 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell Circumferential Class 1 OM-1201-456 Course Pc. 1. Y-Z Quadrant.B&W149771 E Nozzle to Shell 02.B3.110.0008 B03.110.008 2-PZR-WP26-6 50 ISI-OCN2-002 NDE-640 UT CS 6.187 / 5.750 40338 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell Circumferential Class 1 OM-1201-456 Course Pc. 1. Z-W Quadrant.B&W149771E Nozzle to Shell Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 38 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan..Oconee 2, 4th Inter utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched ThickWDia Cal Blocks Comments / Historical Data Categor B-D 02.B3.110.0008 B03.110.008 2-PZR-WP26-6 50 ISI-OCN2-002 NDE-820 UT CS 6.187 / 5.750 40338 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell Circumferential Class 1 OM-1201-456 Course Pc. 1. Z-W Quadrant.B&W149771 E Nozzle to Shell 02.B3.120.0001 B03.120.001 2-PZR-WP15 50 ISI-OCN2-002 NDE-3620 UT CS 4.750 13.250 40394 Pressurizer Surge Nozzle Pc. 8 to Lower Head Pc. 6.Class 1 B&W149768E (Inside Radius Section)Nozzle to Head 02.B3.120.0006 B03.120.006 2-PZR-WP26-4 50 ISI-OCN2-002 NDE-680 UT CS 2.531 5.750 40338 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell B&W149771 E 50237E Course Pc. 1. W-X Quadrant. (Inside Radius Section)Class 1 Nozzle to Shell 02.B3.120.0007 B03.120.007 2-PZR-WP26-5 50 ISI-OCN2-002 NDE-680 UT CS 2.531 5.750 40338 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell B&W149771 E 50237E Course Pc. 1. Y-Z Quadrant. (Inside Radius Section)Class 1 Nozzle to Shell 02.B3.120.0008 B03.120.008 2-PZR-WP26-6 50 ISI-OCN2-002 NDE-680 UT CS 2.531 5.750 40338 Pressurizer Sampling Nozzle Pc. 30 to Upper Shell B&W149771 E 50237E Course Pc. 1. Z-W Quadrant. (Inside Radius Section)Class 1 Nozzle to Shell Categor B-G-1 02.B6.40.0001 B06.040.001 2-RPV-LIGAMENTS 50 B&W151997E NDE-640 UT CS 12.500 / 200.000 40387 Reactor Vessel Flange Threads. Stud Holes 1 Thru 60.Class 1 Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 39 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. ,0.Oconee 2, 4th Intero utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catecor B-G-2 02.B7.50.0005 2HP-217-2A1-FLG 51A Class 1 2HP-217 0-ISIN4-101A-2.4 NDE-62 VT-1 CS 0.000 / 1.000 Flange Bolting on 2.5 inch piping flange located on the 2A1 HPI line. Flange is located on weld iso 2HP-217.Class 1 Bolting (B-G-2)02.B7.50.0006 2HP-216-2A2-FLG 51A Class 1 2HP-216 0-ISIN4-101A-2.4 NDE-62 VT-1 CS 0.000 / 1.000 Flange Bolting on 2.5 inch piping flange located on the 2A2 HPI line. Flange is located on weld iso 2HP-216.Class 1 Bolting (B-G-2)02.B7.50.0007 2HP-214-2B1-FLG 51A Class 1 2HP-214 0-ISIN4-101A-2.4 NDE-62 VT-1 CS 0.000 / 1.000 Flange Bolting on 2.5 inch piping flange located on the 2B1 HPI line. Flange is located on weld iso 2HP-214.Class 1 Bolting (B-G-2)02.B7.50.0008 2HP-218-2B2-FLG 51A 2HP-218 Class 1 0-ISIN4-101A-2.4 NDE-62 VT-1 CS 0.000 / 1.000 Flange Bolting on 2.5 inch piping flange located on the 2B2 HPI line. Flange is located on weld iso 2HP-218.Class 1 Bolting (B-G-2)Printed 7/18/2007 1 ý08:46 PM lck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 40 of 70 This report includes all changes through addendum ONS2-057 Th r is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter'N utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched ThickWDia Cal Blocks Comments / Historical Data Catepor B-J 02.19.11.0002 B09.011.002, B09.011.002A 2-PSL-9 50 ISI-OCN2-015 NDE-35 PT SS 1.000 /10.000 Pressurizer Surge Piping. Elbow Pc. 80 to Pipe Pc. 85.Circumferential Class 1 O-ISIN4-1 OOA-2.2 Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Weld 2-PSL-9 was examined during 2EOC-22(outage

2) and was limited due to weld overlay performed on an adjoining weld. The examinations on weld 2-PSL-9 during 2EOC-23 will be performed in order to achieve the required coverage (> than 90%). Phased Array UT or RT may be options or a UT examination using PDI-UT-2 or NDE-660 may be performed if some of the Weld Overlay is removed from the examination area for weld 2-PSL-9. We don't know until summer of 2008 whether we can UT using Phased Array; therefore we are scheduling both RT and UT exams for 2EOC-23. It is our intent not to perform RT if we can perform phased array UT. For Code percentage purposes, in outage 2EOC-22, Partial credit (/2 credit) was taken for weld 2-PSL-9 and in outage 2EOC-23, 1/2 credit will be taken for which ever exam (UT or RT) is performed on this weld.Stress Weld Elbow to Pipe Printed 7/18/2007 1:08:46 PM 1ck8302 v.07/02/07 SOQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 41 of 70 Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 41 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. A Oconee 2, 4th Interou; utage 2 (EOC-22)Summary Num Insp Component ID / Type System lSO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor B-J 02.B9.11.0002 2-PSL-9 Circumferential 50 ISI-OCN2-015 O-ISIN4-10OA-2.2 Class 1 PDI-UT-2 UT SS 1.000 / 10.000 B09.011.002, B109.011.002A Component Pressurizer Surge Piping. Elbow Pc. 80 to Pipe Pc. 85.PDI-UT-2-O Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Weld 2-PSL-9 was examined during 2EOC-22(outage

2) and was limited due to weld overlay performed on an adjoining weld. The examinations on weld 2-PSL-9 during 2EOC-23 will be performed in order to achieve the required coverage (> than 90%). Phased Array UT or RT may be options or a UT examination using PDI-UT-2 or NDE-660 may be performed if some of the Weld Overlay is removed from the examination area for weld 2-PSL-9. We don't know until summer of 2008 whether we can UT using Phased Array; therefore we are scheduling both RT and UT exams for 2EOC-23. It is our intent not to perform RT if we can perform phased array UT. For Code percentage purposes, in outage 2EOC-22, Partial credit (V2 credit) was taken for weld 2-PSL-9 and in outage 2EOC-23, Y2 credit will be taken for which ever exam (UT or RT) is performed on this weld.Stress Weld Elbow to Pipe 02.B9.111.0022 2RC-279-92V Circumferential Terminal End 50 ISl-OCN2-006 Class 1 2RC-279 0-ISIN4-100A-2.1 NDE-25 MT CS 3.500 / 36.000 B09.011.022, B09.011.022A Steam Generator 2B Inlet Nozzle to Hot Leg. Weld 92V is listed on weld iso 2RC-279 but drawing ISI-OCN2-006 is listed as the iso to show where the weld is located on the 2B Hot Leg Piping Loop.B09.011.022, B09.011.022A Steam Generator 2B Inlet Nozzle to Hot Leg. Weld 92V is listed on weld iso 2RC-279 but drawing ISI-OCN2-006 is listed as the iso to show where the weld is located on the 28 Hot Leg Piping Loop.Nozzle to Pipe 02.B9.11.0022 2RC-279-92V Circumferential Terminal End 50 lSI-OCN2-006 Class 1 2RC-279 0-ISlN4-100A-2.1 NDE-600 UT CS 3.500 / 36.000 Component Nozzle to Pipe Printed 7/18/2007 1:08:46 PM 1ck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 42 of 70 Printed 7/18/2007 1 ý08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 42 of 70 This report includes all changes through addendum ONS2-057 Th mer is responsible for verifying this report against the issued plan.0Oconee 2, 4th Interoutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor B-J 02.B9.11.0029 B09.011.029, B09.011.029A 2SGB-W2 50 ISI-OCN2-010 NDE-25 MT CS 3.500 / 33.500 Steam Generator 2B Outlet Nozzle to Pump 2B2 Circumferential Class 1 OM 201.S--0033.001 Suction Piping.O-ISIN4-100A-2.1 Weld 2SGB-W2 is listed on drawing OM 201 .S--0033.001 but drawing ISI-OCN2-010 is listed as the iso to show where the weld is located on the 2B2 Suction Piping Loop.Terminal End Nozzle to Pipe 02.B9.11.0029 109.011.029, 809.011.029A 2SGB-W2 50 ISI-OCN2-010 NDE-600 UT CS 3.500 / 33.500 Component Steam Generator 28 Outlet Nozzle to Pump 282 Circumferential Class 1 OM 201.S--0033.001 Suction Piping.O-ISIN4-100A-2.1 Weld 2SGB-W2 is listed on drawing OM 201.S--0033.001 but drawing ISI-OCN2-010 is listed as the iso to show-where the weld is located on the 2B2 Suction Piping Loop.Terminal End Nozzle to Pipe 02.B9.11.0036 B09.011.036, B09.011.036A 2-PSL-1 50 ISI-OCN2-015 NDE-35 PT SS 1.000 /10.000 Pressurizer Surge Piping.Circumferential Class 1 O-ISIN4-10OA-2.2 Surge Nozzle Safe End Pc. 37 to Elbow Pc. 80. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Stress Weld Terminal End Safe End to Elbow 02.B9.11.0036 809.011.036, B09.011.036A 2-PSL-1 50 ISI-OCN2-015 PDI-UT-2 UT SS 1.000 / 10.000 Component Pressurizer Surge Piping.O-ISIN4-10OA-2.2 PDI-UT-2-O Surge Nozzle Safe End Circumferential Class 1 Pc. 37 to Elbow Pc. 80. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Stress Weld Terminal End Safe End to Elbow Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 43 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter, outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor B-J 02.B9.11.0059 2-PDB1-1 Circumferential 50 ISI-OCN2-013 Class 1 OM-1201-966 NDE-35 PT SS 2.330 / 33.500 B09.011.059, 909.011.059A Reactor Coolant Pump 2B1 Discharge Piping. RCP 2B1 Casing to Safe End Pc. 49. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Procedure NDE-830 and either Cal Block 50386 or Cal Block 50214 are to be used only for a supplemental UT performed from the pump side. The supplemental exam is being performed as requested by Jim McArdle which will be used to justify limited coverage from the code exam (performed using NDE-600 or PDI-UT-2).

Stress Weld Terminal End Casing to Safe End 02.89.11.0059 2-PDB1-1 Circumferential 50 ISI-OCN2-013 OM-1201-966 NDE-600 UT SS 2.330 / 33.500 Component 40397 50386 Class 1 B09.011.059, B09.011.059A Reactor Coolant Pump 2B1 Discharge Piping. RCP 281 Casing to Safe End Pc. 49. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Procedure NDE-830 and either Cal Block 50386 or Cal Block 50214 are to be used only for a supplemental UT performed from the pump side. The supplemental exam is being performed as requested by Jim McArdle which will be used to justify limited coverage from the code exam (performed using NDE-600 or PDI-UT-2).

Stress Weld Terminal End 02.B9.11.0059 2-PDB1-1 Circumferential Casing to Safe End 50 ISI-OCN2-013 OM-1 201-966 NDE-830 UT SS 2.330 / 33.500 Component 40397 50214 Class 1 B09.011.059, B09.011.059A Reactor Coolant Pump 281 Discharge Piping. RCP 2B1 Casing to Safe End Pc. 49. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Procedure NDE-830 and either Cal Block 50386 or Cal Block 50214 are to be used only for a supplemental UT performed from the pump side. The supplemental exam is being performed as requested by Jim McArdle which will be used to justify limited coverage from the code exam (performed using NDE-600 or PDI-UT-2).

Stress Weld Terminal End Casing to Safe End Printed 7/18/2007 1 ý08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 44 of 70 This report includes all changes through addendum ONS2-057 Th rer is responsible for verifying this report against the issued plan.Oconee 2, 4th Intervlutage 2 (EOC-22)Summary Num Component ID / Type Categor B-J 02.B9.11.0060 2-PDB1-3 Circumferential System ISO/DWG Numbers lnsp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 50 ISI-OCN2-013 Class 1 OM-1201-966 NDE-25 MT CS 2.330 / 33.500 Stress Weld B09.011.060, B09.011.060A Reactor Coolant Pump 281 Discharge Piping. Elbow Pc. 53 to Pipe Pc. 44. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.B09.011.060, B09.011.060A Component Reactor Coolant Pump 281 Discharge Piping. Elbow 40350 Pc. 53 to Pipe Pc. 44. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Elbow to Pipe 02.89.11.0060 2-PDBl-3 Circumferential 50 ISI-OCN2-013 OM-1201-966 Class 1 NDE-600 UT CS 2.330 / 33.500 Stress Weld Elbow to Pipe 02.B9.11.0061 B09.011.061, B09.011.061 A 2RC-279-94V 50 ISI-OCN2-010 NDE-25 MT CS 3.500 / 33.500 Reactor Coolant Pump 2B2 Circumferential Class 1 2RC-279 Suction Piping. Pipe to Elbow Pc. 45.O-ISIN4-100A-2.1 Weld 94V is listed on weld iso 2RC-279 but drawing ISI-OCN2-010 is listed as the iso to show where the weld is located on the 282 Suction Piping Loop.Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Stress Weld Pipe to Elbow 02.89.11.0061 B09.011.061, B09.011.061A 2RC-279-94V 50 ISI-OCN2-010 NDE-600 UT CS 3.500 /33.500 Component Reactor Coolant Pump 282 Circumferential Class 1 2RC-279 Suction Piping. Pipe to Elbow Pc. 45.0-ISIN4-100A-2.1 Weld 94V is listed on weld iso 2RC-279 but drawing ISI-OCN2-010 is listed as the iso to show where the weld is located on the 2B2 Suction Piping Loop.Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Stress Weld Pipe to Elbow Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 45 of 70 This report includes all changes through addendum ONS2-057 Th r is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Cateaorl B-J 02.89.11.0066 B09.011.102, B09.011.102A 2-51A-30-1 51A 2-51A-30 NDE-35 PT SS 0.531 / 4.000 Procedure NDE-600 uses the component for Circumferential Class 1 0-ISIN4-101A-2.4 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Valve 2HP-194 to Pipe 02.B9.11.0066 B09.011.102, B09.011.102A 2-51A-30-1 51A 2-51A-30 NDE-600 UT SS 0.531 / 4.000 Component Procedure NDE-600 uses the component for 0-ISIN4-1 01A-2.4 PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of Circumferential Class 1 procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Valve 2HP-194 to Pipe 02.B9.21.0001 B09.021.001 2-50-7-8 50 2-50-7 (2) NDE-35 PT SS-Inconel 0.281 / 1.500 Reactor Coolant Pump 2B2 Suction Drain Piping.Circumferential Class 1 0-ISIN4-100A-2.1 Code Case N-624 Dissimilar Elbow to Nozzle 02.1B9.21.0002 B09.021.002 2-50-7-14 50 2-50-7 (1) NDE-35 PT SS-Inconel 0.281 /1.500 Reactor Coolant Pump 2A2 Suction Drain Piping.Circumferential Class 1 O-ISIN4-100A-2.1 Code Case N-624 Dissimilar Stress Weld Nozzle to Elbow 02.B9.21.0003 B09.021.003 2-50-7-29 50 2-50-7 (1) NDE-35 PT SS-Inconel 0.281 / 1.500 Reactor Coolant Pump 2A1 Suction Drain Piping.Circumferential Class 1 O-ISIN4-100A-2.1 Code Case N-624 Dissimilar Stress Weld Nozzle to Elbow 02.B9.21.0006 B09.021.006 2-PDBl-11 50 ISI-OCN2-013 NDE-35 PT SS-CS 0.750 /3.500 Reactor Coolant Pump 281 Discharge Piping. Nozzle Circumferential Class 1 B&W146829E Pc. 46 to Safe End Pc. 47. This weld was cut out and welded back in EOC-20. The new weld is also listed as weld 16 on rev .8 of iso 2RC-202.Dissimilar Stress Weld Nozzle to Safe End Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 46 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter* utage 2 (EOC-22) 1 Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor B-J 02.39.21.0012 B09.021.012 2-PSP-1 1 50 ISI-OCN2-016 NDE-35 PT SS 0.375/ 2.500 Pressurizer Spray Piping. Tee Pc. 106 to Valve Circumferential Class 1 O-ISIN4-100A-2.2 Pc. 111.Stress Weld Tee to Valve 2RC-001 02.B9.21.0013 B09.021.013 2-PSP-13 50 ISI-OCN2-016 NDE-35 PT SS 0.375 / 2.500 Pressurizer Spray Piping. Pipe Pc. 92 to Elbow Circumferential Class 1 O-ISIN4-10OA-2.2 Pc. 98.Stress Weld Pipe to Elbow 02.B9.21.0023 B09.021.023 2-PSP-22 50 ISI-OCN2-016 NDE-35 PT SS 0.375 /2.500 Pressurizer Spray Piping.Circumferential Class 1 O-ISIN4-100A-2.2 Pipe Pc. 93 to Pressurizer Spray Nozzle Pc. 51.Stress Weld Pipe to Nozzle 02.B9.21.0024 B09.021.101 2-51A-144-24 51A 2-51A-144 NDE-35 PT SS 0.438 / 3.000 Letdown Cooler 2B.Circumferential Class 1 0-ISIN4-101A-2.1 Inlet Nozzle to Elbow Weld.Terminal End Elbow to Nozzle 02.39.21.0025 B09.021.102 2-51A-145-1 51A 2-51A-145 NDE-35 PT SS 0.438 / 3.000 Letdown Cooler 2B.Circumferential Class 1 O-ISIN4-101A-2.1 Outlet Nozzle to Elbow Weld.Terminal End Nozzle to Elbow 02.1B9.21.0040 B09.021.117 2RC-204-20 51A 2RC-204 NDE-35 PT SS 0.375 / 2.500 This weld was listed previously as 2-51A-39-46 until iso Circumferential Class 1 O-ISIN4-101A-2.4 2-51A-39 was redrawn as 2RC-204 and was given weld number 2RC-204-3.

Revision 4 to this iso. deleted weld 3 and reassigned weld number 20 for this weld.Inspect with Item Number G02.001.01 OA.Stress Weld Pipe to Valve 2HP-127 Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 47 of 70 This report includes all changes through addendum ONS2-057 Thmer is responsible for verifying this report against the issued plan. 1 Oconee 2, 4th Inter outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched ThicklDia Cal Blocks Comments / Historical Data Categor B-J 02.B9.21.0050 2-51 A-30-32 Circumferential B09.021.127 51A 2-51A-30 Class 1 O-ISIN4-101A-2.4 NDE-35 PT SS 0.375 / 2.500 Reducer to Pipe 02.B9.21.0053 B09.021.130 2-51A-35-24 51A 2-51A-35 (1) NDE-35 PT SS 0.375 / 2.500 Circumferential Class 1 0-ISIN4-101A-2.1 Elbow to Pipe 02.B9.31:0001 B09.031.001, B09.031.001 A 2-PHB-16 50 ISI-OCN2-006 NDE-25 MT CS 2.875/ 23.000 Steam Generator 2B Hot Leg to Reactor Vessel.Branch Class 1 B&W149768E Pressurizer Surge Nozzle Pc. 25 to Pipe Pc. 32. NPS of Branch Piping is 10 inches. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Stress Weld Nozzle to Pipe 02.B9.31.0001 B09.031.001, B09.031.001A 2-PHB-16 50 ISI-OCN2-006 PDI-UT-1 UT CS 2.875 / 23.000 Component Steam Generator 2B Hot Leg to Reactor Vessel.B&W149768E 40350 Pressurizer Surge Nozzle Pc. 25 to Pipe Pc. 32. NPS Branch Class 1 of Branch Piping is 10 inches. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Stress Weld Nozzle to Pipe 02.19.31.0002 B09.031.002, B09.031.002A 2-PHA-16 50 ISI-OCN2-005 NDE-600 UT CS 2.875 / 25.000 Component Steam Generator 2A Hot Leg to Reactor Vessel.B&W146330E 40350 Decay Heat Nozzle Pc. 34 to Pipe Pc. 32. NPS of Branch Class 1 Branch Piping is 12 inches. Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used. MT or PT or a combination of the two methods together are exceptable to meet the surface examination requirements.

Stress Weld Nozzle to Pipe Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 48 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan. *0Oconee 2, 4th Intero utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor B-K 02.B130.10.0013 2-LDCB-SUPPORT B10.010.013 OM-201-3107 Class 1 O-ISIN4-101A-2.1 1-34097-2 NDE-25 MT CS 0.000 / 0.000 Letdown Cooler 2B Support.Pc.12 to Casing Shell Pc.8 Categor B-L-1 02.B12.10.0001 2RCP-2A1 Circumferential Categor C-A 02.C1.10.0003 2-LDFTRA-SH-FL Circumferential O2.C1.20.0003 2-LDFTRA-HD-SH-1 Circumferential 02.C1.20.0004 2-LDFTRA-HD-SH-2 Circumferential B12.010.001 50 ISI-OCN2-007 Class 1 OM-1201D-0005 OM-1 201 -0001 NDE-65 VT-1 SS 0.000 / 68.000 Reactor Coolant Pump 2A1 Casing Weld.Casing to Casing C01.010.003 51B OM-201-0128 Class2 G-ISIN4-101A-2.2 OM 201-129 NDE-35 PT SS 0.109 / 0.000 Letdown Filter 2A.Shell to Flange C01.020.001 51B OM-201-0128 Class 2 O-ISIN4-101A-2.2 OM 201.129 NDE-35 PT SS 0.187 / 0.000 Letdown Filter 2A.Upper Head to Shell C01.020.002 51B OM-201-0128 Class2 O-ISIN4-101A-2.2 OM 201-129 NDE-35 PT SS 0.187 / 0.000 Letdown Filter 2A.Lower Head to Shell 02.C1.20.0005 2-LST-HD-SH-1 Circumferential G2.C1.20.0006 2-LST-HD-SH-2 Circumferential C01.020.003 50469 Letdown Storage Tank Upper Head to Shell.51A OM 201-63 Class 2 O-ISIN4-101A-2.2 OM 201-64 NDE-3630 UT SS 0.375 / 96.000 Head to Shell C01.020.004 50469 Letdown Storage Tank Lower Head to Shell.51A OM 201-63 Class2 G-ISIN4-101A-2.2 OM 201-64 NDE-3630 UT SS 0.375/ 96.000 Head to Shell Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 49 of 70 This report includes all changes through addendum ONS2-057 Thmer is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter , outage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor C-C 02.C3.10.0003 C03.010.001 2-LDFTR-A 51A OM-201-0128 NDE-35 PT NA 0.250 / 0.000 Letdown Filter 2A Support Leg Attachments (3 legs).Class 2 O-ISIN4-101A-2.1 Only required to inspect one of the attachments, inspector shall identify which attachment was examined for successive interval exams.02.C3.10.0005 C03.010.002 2-LS-TANK 51B OM 201-63 Class 2 O-ISIN4-101A-2.2 NDE-35 PT SS 0.500 / 0.000 Letdown Storage Tank (4 Support Legs)Plate to Shell 02.C3.20.0008 2-03-0-1479A-H1 B Rigid Support 02.C3.20.0010 2-14B-0-1479A-H1 Rigid Restraint 03 0-1490B-2(S)

Class2 O-ISIN4-121B-2.3 2-03-06/sht.3 NDE-25 MT NA 0.280 / 14.000 C03.020.014 Calculation No. OSC-1316-06(Vol.

A). Inspect with F01.020.011.

C03.020.022 14B 2-14-14/sht.1 Class 2 0-ISIN4-124B-2.2 NDE-25 MT NA 0.216 / 6.000 Calculation No. OSC-1325-06.

Inspect with F01.021.026.

02.C3.20.0012 2-14B-0-1479A-H2 Rigid Restraint 02.C3.20.0030 2-54A-3-0-1439B-H1-3 Rigid Restraint 02.C3.20.0033 2-54A-3-0-1439B-H1-5 Rigid Support 14B 2-14-13/sht.1 Class 2 0-ISIN4-124B-2.2 54A 2-54-03/sht.

1 Class 2 0-ISIN4-103A-2.1 NDE-25 MT NA NDE-35 PT NA 0.216 /8.000 0.125 /8.000 C03.020.024 Calculation No. OSC-1325-06.

Inspect with F01.021.025.

C03.020.052 Calculation No. OSC-496. Inspect with F01.021.071.

C03.020.055 Calculation No. OSC-496. Inspect with F01.020.094.

54A 2-54-03/sht.1 Class 2 0-ISIN4-103A-2.1 NDE-35 PT NA 0.125 / 8.000 Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 50 of 70 This report includes all changes through addendum ONS2-057 Th mer is responsible for verifying this report against the issued plan.0 Oconee 2, 4th Inters utage 2 (EOC-22) i Summary Num Component ID / Type Categor C-F-1 02.C5.11.0004 2LP-148-90 Circumferential Insp Procedure Req System ISO/DWG Numbers Mat Sched ThickWDia Cal Blocks Comments / Historical Data 53A 2LP-148 Class 2 O-ISIN4-102A-2.2 NDE-35 PT SS 160 0.000 / 12.000 Reducer to Valve 2LP-18 (forged)C05.011.004, C05.011.004A Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was previously listed as 2-53A-8-19 until iso 2-53A-8(1) was redrawn. This weld was previously listed as 2LP-148-19 before it was deleted and remade as 2LP-148-90.(CO5.011.004A)

Note that the ID of the 12" end of the 12"x10" reducer is machined to 10.413" plus/minus

.010". (Ref. isometric 2LP-148).C05.011.004, C05.011.004A Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was previously listed as 2-53A-8-19 until iso 2-53A-8(1) was redrawn. This weld was previously listed as 2LP-148-19 before it was deleted and remade as 2LP-148-90.(C05.011.004A)

Note that the ID of the 12" end of the 12"x10" reducer is machined to 10.413" plus/minus

.010". (Ref. isometric 2LP-148).02.C5.11.0004 2LP-148-90 Circumferential 53A 2LP-148 O-ISIN4-102A-2.2 Class 2 NDE-600 UT SS 160 0.000 / 12.000 Component PDI-UT-2-O Reducer to Valve 2LP-1 8 (forged)02.C5.11.0006 C05.011.006, C05.011.006A 2LP-150-36 53A 2LP-150 NDE-35 PT SS 1.125 / 10.000 Procedure NDE-600 uses the component for Circumferential Class 2 O-ISIN4-102A-2.3 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-9-36 until iso 2-53A-9 was redrawn.Pipe to Elbow 02.C5.11.0006 C05.011.006, C05.011.006A 2LP-150-36 Circumferential 53A 2LP-150 O-ISIN4-102A-2.3 Class 2 NDE-600 UT SS 1.125 / 10.000 Component Procedure NDE-600 uses the component for PDI-UT-2-O calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-9-36 until iso 2-53A-9 was redrawn.Pipe to Elbow Printed 7/18/2007 1:08:46 PM 1ck8302 v.07/02/07 SOQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 51 of 70 Printed 7/18/2007 1 ý08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 51 of 70 This report includes all changes through addendum ONS2-057 Th e r is responsible for verifying this report against the issued plan.T Oconee 2, 4th Intervo utage 2 (EOC-22) W Summary Num Component IDI/ Type Insp Procedure Req System ISO/DWG Numbers Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Category C-F-i 02.C5.11.0007 2LP-150-37 Circumferential 53A 2LP-150 Class 2 0-ISIN4-102A-2.3 NDE-35 PT SS 1.125 / 10.000 C05.011.007, C05.011.007A Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-9-37 until iso 2-53A-9 was redrawn.Pipe to Elbow 02.C5.11.0007 2LP-150-37 Circumferential 53A 2LP-150 0-ISIN4-102A-2.3 Class 2 NDE-600 UT SS C05.011.007, C05.011.007A 1.125 / 10.000 Component Procedure NDE-600 uses the component for PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-9-37 until iso 2-53A-9 was redrawn.Pipe to Elbow 02.C5. 11.0008 2LP-150-38 Circumferential 53A 2LP-150 Class 2 0-ISIN4-102A-2.3 NDE-35 PT SS 1.125 / 10.000 C05.011.008, C05.011.008A Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-9-38 until iso 2-53A-9 was redrawn.Pipe to Elbow 02.C5.11.0008 C05.011.008, C05.011.008A 2LP-150-38 53A 2LP-150 NDE-600 UT SS 1.125 / 10.000 Component Procedure NDE-600 uses the component for 0-ISIN4-102A-2.3 PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-9-38 until iso 2-53A-9 was redrawn.Pipe to Elbow 02.C5.11.0017 C05.011.017, C05.011.017A 2LP-189-12 53A 2LP-189 NDE-35 PT SS 1.000 / 10.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-102A-2.2 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-8-12 on iso 2-53A-8(1) until it was transferred to iso 2LP-189.Pipe to Elbow Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 52 of 70 his report includes all changes through addendum ONS2-057 Th. r is responsible for verifying this report against the issued plan.Oconee 2, 4th 2 (EOC-22) w Summary Num Component ID / Type Categor C-F-1 02.C5.11.0017 2LP-189-12 Circumferential System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 53A 2LP-189 0-ISIN4-102A-2.2 Class 2 NDE-600 UT SS C05.011.017, C05.011.017A 1.000 / 10.000 Component Procedure NDE-600 uses the component for PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-8-12 on iso 2-53A-8(1) until it was transferred to iso 2LP-189.Pipe to Elbow 02.C5.11.0029 C05.011.029, C05.011.029A 2-53A-9-7 53A 2-53A-9 NDE-35 PT SS 1.000 / 10.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-102A-2.2 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Pipe to Elbow 02.C5.11.0029 C05.011.029, C05.011.029A 2-53A-9-7 53A 2-53A-9 NDE-600 UT SS 1.000 /10.000 Component Procedure NDE-600 uses the component for 0-ISIN4-102A-2.2 PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Pipe to Elbow 02.C5.11.0030 C05.011.030, C05.011.030A 2-53A-9-8 53A 2-53A-9 NDE-35 PT SS 1.000 / 10.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-102A-2.2 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Pipe to Elbow 02.C5.11.0030 C05.011.030, C05.011.030A 2-53A-9-8 53A 2-53A-9 NDE-600 UT SS 1.000 / 10.000 Component Procedure NDE-600 uses the component for 0-ISIN4-102A-2.2 PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Pipe to Elbow 02.C5.11.0031 C05.011.031, C05.011.031 A 2-53A-9-9 53A 2-53A-9 NDE-35 PT SS 1.000 /10.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-102A-2.2 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Pipe to Elbow Printed 7/18/2007 1:08:46 PM 1ck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 53 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Interj~utage 2 (EOC-22) 0 Summary Num Component ID / Type Categor C-F-1 02.C5.11.0031 2-53A-9-9 Circumferential 02.C5. 11.0032 2LP-1 89-11 Circumferential 02.C5.11.0032 2LP-189-11 Circumferential System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 53A 2-53A-9 0-ISIN4-102A-2.2 Class 2 PDI-UT-2 UT SS 005.011.031, C05.011.031A 1.000 / 10.000 Component Procedure NDE-600 uses the component for PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Pipe to Elbow C05.011.032, C05.011.032A 53A 2LP-189 NDE-35 PT SS 1.000 / 10.000 Procedure NDE-600 uses the component for Class 2 0-ISIN4-102A-2.2 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-8-1 1 on iso 2-53A-8(1) until it was transferred to iso 2LP-189.Pipe to Elbow C05.011.032, C05.011.032A 53A 2LP-189 0-ISIN4-102A-2.2 Class 2 NDE-600 UT SS 1.000 / 10.000 Component Procedure NDE-600 uses the component for PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-53A-8-1 1 on iso 2-53A-8(1) until it was transferred to iso 2LP-1 89.Pipe to Elbow 02.05.11.0072 C05.011.072, C05.011.072A 2LPS-724-14 14B 2LPS-724 NDE-35 PT SS 0.432 / 6.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-124B-2.2 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Pipe to Elbow 02.05.11.0072 C05.011.072, C05.011.072A 2LPS-724-14 14B 2LPS-724 NDE-600 UT SS 0.432 / 6.000 Component Procedure NDE-600 uses the component for 0-ISIN4-124B-2.2 PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Pipe to Elbow 02.05.11.0073 C05.011.073, C05.011.073A 2LPS-724-15 14B 2LPS-724 NDE-35 PT SS 0.432 /6.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-124B-2.2 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Elbow to Pipe Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 54 of 70 This report includes all changes through addendum ONS2-057 Th Pr is responsible for verifying this report against the issued plan.* Oconee 2, 4th Inter utage 2 (EOC-22) W Summary Num Component ID / Type Categor C-F-1 02.C5.11.0073 2LPS-724-15 Circumferential 02.C5.21.0003 2-RCP-FTR2B-SH-1 Circumferential System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 14B 2LPS-724 0-ISIN4-124B-2.2 Class 2 NDE-600 UT SS C05.011.073, C05.011.073A 0.432 / 6.000 Component Procedure NDE-600 uses the component for PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Elbow to Pipe 51A 2-51A-28(1)

Class 2 OM-201-0473 O-ISIN4-1 01 A-2.4 NDE-12 RT SS 0.531 / 4.000 C05.021.003, C05.021.003A Reactor Coolant Pump Seal Supply Filter 2B. Pc. 10 to Pc. 1. -- (C05.021.003)

Remove filter from housing to insure the system is drained prior to performing RT.Terminal End Filter Hub to Filter Housing 02.C5.21.0003 2-RCP-FTR2B-SH-1 Circumferential 51A 2-51A-28(1)

Class 2 OM-201-0473 O-ISIN4-1 01A-2.4 NDE-35 PT SS 0.531 / 4.000 C05.021.003, C05.021.003A Reactor Coolant Pump Seal Supply Filter 2B. Pc. 10 to Pc. 1. -- (C05.021.003)

Remove filter from housing to insure the system is drained prior to performing FIT.Terminal End Filter Hub to Filter Housing 02.C5.21.0004 2-RCP-FTR2B-SH-2 Circumferential 51A 2-51A-28(1)

Class 2 OM-201-0473 0-ISIN4-101A-2.4 NDE-35 PT SS 0.531 / 4.000 C05.021.004, C05.021.004A Reactor Coolant Pump Seal Supply Filter 2B. Pc. 10 to Pc. 1. -- (C05.021.004)

Remove filter from housing to insure the system is drained prior to performing RT.Terminal End Filter Hub to Filter Housing 02.C5.21.0021 2-51A-17-147 Circumferential 51A 2-51A-17 (7)Class 2 0-ISlN4-101A-2.3 NDE-35 PT SS 0.531 / 4.000 C05.021.029, C05.021.029A Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Valve 2HP-148 to Elbow 02.C5.21.0021 2-51A-17-147 Circumferential 51A 2-51A-17(7) 0-ISIN4-101A-2.3 Class 2 NDE-600 UT SS C05.021.029, C05.021.029A 0.531 / 4.000 Component Procedure NDE-600 uses the component for PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Valve 2HP-148 to Elbow Printed 7/18/2007 1:08:46 PM Ick83O2 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 55 of 70 This report includes all changes through addendum ONS2-057 The er is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter gutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor C-F-1 02.C5.21.0022 C05.021.030, C05.021.030A 2-51A-17-158 51A 2-51A-17 (7) NDE-35 PT SS 0.531 / 4.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-101A-2.3 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Elbow to Elbow 02.C5.21.0022 C05.021.030, C05.021.030A 2-51A-17-158 51A 2-51A-17 (7) NDE-600 UT SS 0.531 / 4.000 Component Procedure NDE-600 uses the component for 0-ISIN4-101A-2.3 PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Elbow to Elbow 02.C5.21.0023 C05.021.031, C05.021.031 A 2-51A-27-25 51A 2-51A-27 (1) NDE-35 PT SS 0.531 /4.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-101A-2.4 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Elbow to Pipe 02.C5.21.0023 C05.021.031, C05.021.031 A 2-51A-27-25 51A 2-51A-27 (1) NDE-600 UT SS 0.531 /4.000 Component Procedure NDE-600 uses the component for 0-ISIN4-101A-2.4 PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used.Elbow to Pipe 02.C5.21.0024 C05.021.032, C05.021.032A 2HP-220-9 51A 2HP-220 NDE-35 PT SS 0.674 / 4.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-101A-2.4 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-51A-27-41AA until iso 2-51A-27(1) was redrawn.Valve 2HP-27 to Pipe 02.C5.21.0024 C05.021.032, C05.021.032A 2HP-220-9 51A 2HP-220 NDE-600 UT SS 0.674 / 4.000 Component Procedure NDE-600 uses the component for 0-ISIN4-101A-2.4 PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-51A-27-41AA until iso 2-51A-27(1) was redrawn.Valve 2HP-27 to Pipe Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 56 of 70 This report includes all changes through addendum ONS2-057 Th e er is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter Dutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Cateaor C-F-1 02.C5,21.0025 C05.021.033, C05.021.033A 2HP-220-14 Circumferential 51A 2HP-220 Class 2 O-ISIN4-101A-2.4 NDE-35 PT SS 0.674 / 4.000 Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-51 A-27-41C until iso 2-51 A-27(1)was redrawn.Tee to Pipe C05.021-.033, C05.021 .033A 02.C5.21.0025 2HP-220-14 Circumferential 51A 2HP-220 0-ISIN4-101A-2.4 Class 2 NDE-600 UT SS 0.674 / 4.000. Component Procedure NDE-600 uses the component for PDI-UT-2-0 calibration.

Procedure PDI-UT-2 may be used in lieu of procedure NDE-600. If PDI-UT-2 is used, then the calibration block listed shall be used. This weld was listed previously as 2-51 A-27-41C until iso 2-51 A-27(1)was redrawn.Tee to Pipe 02.C5.30.0002 2-51 B-23-64 51B 2-51B-23 NDE-35 PT SS 0.154 / 2.000 Socket Class 2 0-ISIN4-101A-2.2 Pipe to Valve 2HP136 Catepor' C-F-2 C05.030.002 C05.051.001, C05.051.001 A Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used. This weld was listed previously as 2-01A-4-17 on iso 2-01A-4(1) until it was transferred to iso 2MS-133.02.C5.51 .0001 2MS-133-17 Circumferential 01A 2MS-133 Class 2 0-ISIN4-122A-2.1 NDE-25 MT CS 1.164 / 36.000 Reducing Y Fitting to Elbow 02.C5.51.0001 C05.051.001, C05.051.001 A 2MS-133-17 01A 2MS-133 PDI-UT-1 UT CS 1.164 / 36.000 Component Procedure NDE-600 uses the component for O-ISIN4-122A-2.1 PDI-UT-1-O calibration.

Procedure PDI-UT-1 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used. This weld was listed previously as 2-01A-4-17 on iso 2-01A-4(1) until it was transferred to iso 2MS-133.Reducing Y Fitting to Elbow Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 57 of 70 This report includes all changes through addendum ONS2-057 Th tr is responsible for verifying this report against the issued plan. 0 Oconee 2, 4th Interoutage 2 (EOC-22)Summary Num Component ID / Type System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catecor C-F-2 02.C5.51.0009 2MS-123-70V Circumferential 01A 2MS-123 Class 2 0-ISIN4-122A-2.1 NDE-25 MT CS 0.969 / 24.000 C05.051.009, C05.051.009A S/G 2B Main Steam Nozzle to Reducer weld.Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Terminal End 02.C5.51.0009 2MS-123-70V Circumferential Terminal End 02.C5.51.0010 2MS-123-71V Circumferential Terminal End 02.C5.51.0010 2MS-123-71V Circumferential Terminal End 02.C5.51.0015 2-03A-10-61 Circumferential Nozzle S/G 2B to Reducer 01A 2MS-123 0-ISIN4-122A-2.1 Class 2 NDE-600 UT CS 0.969 / 24.000 Nozzle S/G 2B to Reducer 01A 2MS-123 Class 2 0-ISIN4-122A-2.1 NDE-25 MT CS 0.969 / 24.000 C05.051.009, C05.051.009A Component S/G 2B Main Steam Nozzle to Reducer weld.PDI-UT-1-0 Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.C05.051.010, C05.051.010A S/G 2B Main Steam Nozzle to Reducer weld.Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used..C05.051.010, C05.051.010A Component S/G 2B Main Steam Nozzle to Reducer weld.PDI-UT-1-0 Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Nozzle S/G 2B to Reducer 01A 2MS-123 0-ISIN4-122A-2.1 Class 2 NDE-600 UT CS 0.969 / 24.000 Nozzle S/G 2B to Reducer 03A 2-03A-10 Class 2 0-ISIN4-121D-2.1 NDE-25' MT CS 0.562 / 6.000 C05.051.015, C05.051.015A Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Tee to Pipe Printed 7/18/2007 1:08:46 PM 1ck8302 v.07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 58 of 70 Printed 7/18/2007 1 ý08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 58 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th InterMutage 2 (EOC-22)Summary Num Component ID / Type Insp Procedure Req System ISO/DWG Numbers Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor C-F-2 02.C5.51.0015 2-03A- 10-61 Circumferential 005.051.015, C05.051.015A 03A 2-03A-10 0-ISIN4-121D-2.1 Class 2 NDE-600 UT CS 0.562 / 6.000 Component Procedure NDE-600 uses the component for PDI-UT-1-0 calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Tee to Pipe 02.C5.51.0016 2SGA-W277 Circumferential 03A OM 201.S--0155.001 Class2 0-ISIN4-121B-2.3 NDE-25 MT CS 0.432 / 6.000 C05.051.016, C05.051.016A Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Pipe Cap to Pipe 02.C5.51.0016 2SGA-W277 03A OM 201.S--0155.001 NDE-600 UT CS 0.432 / 6.000 0-lSIN4-121 B-2.3 Circumferential Class 2 Pipe Cap to Pipe C05.051.016, C05.051.016A Component Procedure NDE-600 uses the component for PDI-UT-1-0

  • calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.C05.051.020, C05.051.020A Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used. Subassembly Weld. This weld was listed previously AS 2-03-18-3 on iso 2-03-18 (1) until it was transferred to iso 2FDW-253.02.C5.51.0020 2FDW-253-3 Circumferential 03 2FDW-253 Class2 0-ISIN4-121B-2.3 NDE-25 MT CS 0.750 / 14.000 Elbow to Reducer 02.C5.51.0020 C05.051.020, C05.051.020A 2FDW-253-3 03 2FDW-253 NDE-600 UT CS 0.750 / 14.000 Component Procedure NDE-600 uses the component for O-ISIN4-121 B-2.3 PDI-UT-1-0 calibration.

Procedure PDI-UT-1 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used. Subassembly Weld. This weld was listed previously AS 2-03-18-3 on iso 2-03-18 (1) until it was transferred to iso 2FDW-253.Elbow to Reducer 02.C5.51.0021 C05.051.021, C05.051.021 A 2FDW-226-101V Circumferential 03 2FDW-226 Class 2 0-ISIN4-121B-2.3 NDE-25 MT CS 0.750 / 14.000 Procedure NDE-600 uses the component for calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Pipe to Elbow Printed 7/18/2007 1 ý08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 59 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Intero utage 2 (EOC-22)Summary Num Component ID / Type Categor C-F-2 System ISO/DWG Numbers Insp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments /Historical Data 02.C5.51.0021 C05.051.021, C05.051.021 A 2FDW-226-101V 03 2FDW-226 NDE-600 UT CS 0.750 /14.000 Component Procedure NDE-600 uses the component for 0-ISIN4-121B-2.3 PDI-UT-1-0 calibration.

Procedure PDI-UT-1 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Pipe to Elbow 02.C5.51.0023 C05.051.023, C05.051.023A 2SGA-W242 03 OM 201.S--0155.001 NDE-25 MT CS 0.750 /14.000 Procedure NDE-600 uses the component for Circumferential Class 2 0-ISIN4-121B-2.3 calibration.

Procedure PDI-UT-1 may be used in lieu of procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Pipe to Pipe Cap 02.C5.51.0023 C05.051.023, C05.051.023A 2SGA-W242 03 OM 201.S--0155.001 PDI-UT-1 UT CS 0.750 / 14.000 Component Procedure NDE-600 uses the component for O-ISIN4-121 B-2.3 PDI-UT-1-0 calibration.

Procedure PDI-UT-1 may be used in lieu of Circumferential Class 2 procedure NDE-600. If PDI-UT-1 is used, then the calibration block listed shall be used.Pipe to Pipe Cap 02.C5.81.0002 C05.081.002 2-MS20A-B 01A 2MS-134 NDE-25 MT CS 0.562 /12.000 Subassembly 2MS-20A.Branch Class 2 0-ISIN4-122A-2.1 This weld was listed previously on iso 2-01A-4(1) until 2MS-20A it was transferred to iso 2MS-134.Main Steam Header to Pipe Categor D-A 02.D1.10.0002 D01.010.002 2-DHRC-A 53B OM 201-0286 NDE-65 VT-1 NA 0.500 / 0.000 Decay Heat Removal Cooler 2A. Welded attachment at Class 3 0-ISIN4-102A-2.2 the two support cradles to cooler.OM 2201-277 02.D1.10.0003 D01.010.003 2-SSF-SWST 13 OM 240.-0031 NDE-65 VT-1 NA 0.500 / 0.000 Auxiliary Service Water Strainer.Class 3 0-ISIN4-133A-2.5 02.D1.10.0004 D01.010.004 2-MCD-C 07 OM-202-5 Class3 0-ISIN4-121A-2.3 OM-202-25 NDE-65 VT-1 NA 0.000 / 0.000 Main Condenser 2C. Welded Attachment at 4 Support Legs.Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 Printed 7/18/2007 1:08:46 PM 1ck8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/i 8/2007 1:07:38 PM Page 60 of 70 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 60 of 70 This report includes all changes through addendum ONS2-057 Th eIr is responsible for verifying this report against the issued plan.Oconee 2, 4th Interfutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched ThicWlDia Cal Blocks Comments / Historical Data CateDior 0-A 02.D1.10.0005 2-UST-A 14B OM 1149-0001 Class 3 0-ISIN4-121A-2.7 0-1348-B NDE-65 VT-1 NA 0.000 / 0.000 D01.010.005 Upper Surge Tank 2A. (2 Support Cradles) See Dwg 0-1348-B-001 for BasePlate details.Plate to Shell 02.D1.10.0006 2-UST-DOME D01.010.006 Upper Surge Tank Dome. (4 Support Legs)14B 0-348 Class 3 0-ISIN4-121A-2.7 0-348.A-02 NDE-65 VT-1 NA 0.000 / 0.000 Plate to Shell 02.D1.20.0006 2-03A-1-0-1439B-H1 1 Rigid Support D01.020.012 Calculation No. OSC-459. Inspect with F01.030.028.

03A 2-03A-06/sht.3 Class3 0-ISIN4-121D-2.1 NDE-65 VT-1 NA 0.375 / 6.000 02.D1.20.0021 2-14B-0-1439B-RJP-3104 Rigid Support 02.D1.20.0022 2-144B-1-0-1439B-H1-2 Rigid Restraint D01.020.064 14B 4-14-04/sht.3 NDE-65 VT-1 NA 0.237 / 8.000 Calculation No. OSC-474. Inspect with F01.030.078.

Class 3 0-ISIN4-124B-2.2 D01.020.065 14B 4-14-04/sht.2 Class 3 0-ISIN4-124B-2.2 NDE-65 VT-1 NA 2.000 / 14.000 Calculation No. OSC-474. Inspect with F01.031.064.

02.D1.20.0025 D01.020.068 2-14B-1439B-DE154 14B 2-14-06/sht.2 NDE-65 .VT-1 NA 0.187/8.000 Calculation No. OSC-475. Inspect with F01.030.075.

Rigid Support Class 3 0-ISIN4-124B-2.2 02.D1.20.0175 D01.020.052 2-13-0-345A-PS1 -A Rigid Support 13 0-345A Class 3 0-ISIN4-133A-2.1 NDE-65 VT-1 NA 0.375 / 96.000 Calculation No. OSC-681 or OSC-605. Welded attachment associated with support located on discharge piping at the Condenser Circulating Water Intake Pump 2A.02.D1.30.0001 2-CCWP-A D01.030.01 0 13 OM 202.-0003 Class 3 0-ISIN4-133A-2.1 0-345 NDE-65 VT-1 NA 2.000 / 0.000 Condenser Circulating Water Intake Pump 2A. Welded attachment to Pump Casing.Attachment to Casing Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 61 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Interv utage 2 (EOC-22)Summary Num Component ID / Type Categor ELC 02.H2.1.0004 2-PHB-13 Circumferential System ISO/DWG Numbers lnsp Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data 50 Class 1 ISI-OCN2-006 OM-1201-1521 NDE-35 PT CS-Inconel 2.875 / 9.000 H02.001.004 RTE Mounting Boss Pc.12 to Pipe Pc.7. This weld covers the X-Axis. The diameter of hole that penetrates the nozzle into the Hot Leg = .613. Reference Section 7 of the ISI Plan, General Requirements.

Dissimilar Pipe to Pipe 02.H2.1.0005 H02.001.005 2-PHB-14 50 ISI-OCN2-006 NDE-35 PT CS-Inconel 2.875 9.000 RTE Mounting Boss Pc.12 to Pipe Pc.7. This weld Circumferential Class 1 OM-1201-1521 covers the Y-Z Axis. The diameter of hole that penetrates the nozzle into the Hot Leg = .613.Reference Section 7 of the ISI Plan, General Requirements.

Dissimilar Pipe to Pipe 02.H2.1.0006 H02.001.006 2-PHB-15 50 ISI-OCN2-006 NDE-35 PT CS-Inconel 2.875 9.000 RTE Mounting Boss Pc.12 to Pipe Pc.7. This weld Circumferential Class 1 OM-1201-1521 covers the Z-W Axis. The diameter of hole that penetrates the nozzle into the Hot Leg = .613.Reference Section 7 of the ISI Plan, General Requirements.

Dissimilar Pipe to Pipe 02.H4.1.0004 H04.001.004 2-03-0-1439B-H52 03 2-03-01/sht.1 NDE-66 VT-3 NA 0.000 / 24.000 Calculation No. OSC-454.Rigid Support Class 3 O-ISIN4-121B-2.3 Inspect with item number F01 030.022.02.H4.1.0023 H04.001.023 2-01A-0-1441-H3 01A 2-01-01/sht.1 NDE-66 VT-3 NA 0.000 / 36.000 Calculation No. OSC-440.Rigid Support Class 2 O-ISIN4-122A-2.1 02.H4.1.0024 H04.001.024, H04.001.024A 2-01A-0-1441-R2-2 01A 2-01-01/sht.1 NDE-25 MT NA 0.688 / 36.000 Calculation No. OSC-440.Hyd Snubber Class 2 O-ISIN4-122A-2.1

-- (H04.001.024A)

Perform a Surface exam on the attachment welds.Note: Magnetic Particle examinations (with the use of procedure NDE-25) may be performed on carbon steel material in lieu of or in conjunction with liquid penetrant examinations.

Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 62 of 70 This report includes all changes through addendum ONS2-057 Th r is responsible for verifying this report against the issued plan.Oconee 2, 4th Intervfbutage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catecor ELC 02.H4.1.0024 2-01A-0-1441-R2-2 Hyd Snubber 01A 2-01-01/sht.1 Class 2 O-ISIN4-122A-2.1 NDE-66 VT-3 NA 0.688 / 36.000 H04.001.024, H04.001.024A Calculation No. OSC-440.-- (H04.001.024A)

Perform a Surface exam on the attachment welds.Note: Magnetic Particle examinations (with the use of procedure NDE-25) may be performed on carbon steel material in lieu of or in conjunction with liquid penetrant examinations.

02.H4.1.0025 2-01A-0-1441-H4 Rigid Support 02.H4.1.0026 2-01A-0-1401 B-H5 Spring Hgr H04.001.025 01A 2-01-01/sht.1 Class 2 0-ISIN4-122A-2.1 NDE-66 VT-3 NA 0.000 / 36.000 Calculation No. OSC-440.H04.001.026 Calculation No. OSC-440.01A 2-01-01/sht.1 Class 2 O-ISIN4-122A-2.1 NDE-66 VT-3 NA 0.000 / 36.000 02.H4.1.0027 H04.001.027 2-01A-0-1401B-R3 01A 2-01-01/sht.1 NDE-66 VT-3 NA 0.000 / 36.000 Calculation No. OSC-440.Rigid Support Class 2 O-ISIN4-122A-2.1 02.H4.1.0028 H04.001.028 2-01A-0-1401 B-H6 Spring Hgr 01A 2-01-01/sht.2 Class 2 O-ISIN4-122A-2.1 NDE-66 VT-3 NA 0.000 / 36.000 Calculation No. OSC-440.02.H4.1.0030 2-01A-0-1401 B-H8 Rigid Support 02.H4.1.0031 2-01A-0-1401B-H9 Rigid Support 02.H4.1.0047 2-01A-0-1401 B-H23 Rigid Support H04.001.030 01A 2-01-01/sht.2 NDE-66 VT-3 NA 0.000 / 36.000 Calculation No. OSC-440.Class 2 0-ISIN4-122A-2.1 H04.001.031 01A 2-01-01/sht.2 NDE-66 VT-3 NA 0.000 / 36.000 Calculation No. OSC-440.Class 2 0-ISIN4-122A-2.1 H04.001.047 01A 2-01-01/sht.2 Class 2 O-ISIN4-122A-2.1 NDE-66 VT-3 NA 0.000 / 12.000 Calculation No. OSC-440.Inspect with item number F01.020.004.

Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 63 of 70 This report includes all changes through addendum ONS2-057 Th .r is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter, "utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor ELC 02.H4.1.0049 2-01 A-0-1 401 B-H24 Spring Hgr H-04.001 .049 01A 2-01-01/sht.2 Class 2 O-ISIN4-122A-2.1 NDE-66 VT-3 NA 0.000 / 36.000 Calculation No. OSC-440.Inspect with item number F01.022.003.

Categor F-A 02.F1.10.0001 F01.010.011 2-51A-0-1479A-H12B 51A 2-51-24 NDE-66 VT-3 NA 0.500 / 2.500 Calculation No. OSC-1323.

HPI West Coolant Loop.Rigid Support Class 1 O-ISIN4-101A-2.4 02.F1.11.0006 F01.011.031 2-53A-0-1479A-H24C 53A 0-2RB-25314-02 NDE-66 VT-3 NA 0.000 / 1.500 Calculation No. OSC-1324-06.

Rigid Restraint Class 1 O-ISIN4-100A-2.2 02.F1.12.0004 F01.012.004 2-50-1479A-H3A 50 0-2491B-2A NDE-66 VT-3 NA 0.000 /10.000 PZR Surge Line.LJ Hyd Snubber Class 1 O-ISIN4-100A-2.1 02.F1.12.0005 F01.012.011 2-51A-0-1479A-H1A 51A 0-2RB-25315-04 NDE-66 VT-3 NA 0.000 / 2.500 Calculation No. OSC-1324-06.

Spring Hgr Class 1 O-ISIN4-101A-2.4 02.F1.20.0004 F01.020.004 2-01A-0-1401B-H23 01A 2-01-01/sht.2 NDE-66 VT-3 NA 0.000 / 12.000 Calculation No. OSC-440.Rigid Support Class 2 O-ISIN4-122A-2.1 Inspect with item number H04.001.047.

02.F1.20.0005 F01.020.011 2-03-0-1479A-H1B 03 0-1490B-2(S)

NDE-66 VT-3 NA 0.280 / 14.000 Calculation No. OSC-1316-06(Vol.

A). Inspect with Rigid Support Class 2 O-ISIN4-121B-2.3 C03.020.014.

2-03-06/sht.3 02.F1.20.0009 F01.020.021 2-14B-0-1479A-H18 14B 2-14-13/sht.1 NDE-66 VT-3 NA 0.000 / 8.000 Calculation No. OSC-132506.

Rigid Support Class 2 O-IS1N4-124B-2.2 Printed 7/18/2007 1:08:46 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 64 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Intertautage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor F-A 02.F1.20.0013 2-51-0-436J-H1-42 Rigid Support F01.020.041 51 0-2AB-25102-01 Class 2 O-ISIN4-101A-2.2 NDE-66 VT-3 NA 0.000 / 6.000 Calculation No. OSC-481.02.F1.20.0018 F01.020.046 2-51A-6-0-435B-SR58 51A 0-2AB-25102-02 NDE-66 VT-3 NA 0.000 /6.000 Calculation No. OSC-481.Rigid Support Class 2 O-ISIN4-101A-2.3 02.F17.20.0022 F01.020.050 2-51A-0-1444-H187 51A 0-2AB-25118-02 NDE-66 VT-3 NA 0.000/4.000 Calculation No. OSC-1023.Rigid Support Class 2 O-ISIN4-101A-2.4 HPI Crossover Line.02.F1.20.0039 F01.020.077 2-53B-0-435B-DE019 53B 0-2AB-25301-03 NDE-66 VT-3 NA 0.000 /10.000 Calculation No. OSC-487.Rigid Support Class 2 O-ISIN4-102A-2.2 02.F1.20.0041 F01.020.079 2-53B-0-439A-H60 53B 0-2AB-25302-01 NDE-66 VT-3 NA 0.000 / 10.000 Calculation No. OSC-493.Rigid Support Class 2 O-ISIN4-102A-2.2 02.F1.20.0048 F01.020.086 2-53B-2-0-436E-H5 53B 0-2AB-25102-03 NDE-66 VT-3 NA 1.000 / 8.000 Calculation No. OSC-481.Rigid Support Class 2 O-ISIN4-101A-2.3 02.F17.20.0052 F01.020.094 2-54A-3-0-1439B-H15 54A 2-54-03/sht.1 NDE-66 VT-3 NA 0.125 / 8.000 Calculation No. OSC-496. Inspect with C03.020.055.

Rigid Support Class 2 O-ISIN4-103A-2.1 02.F 1.20.0059 F01.020.103 2-56-2-0-437B-H30 56 4-56-02/sht.4 NDE-66 VT-3 NA 0.00/8.000 Calculation No. OS-421.Rigid Support Class 2 O-ISIN4-104A-1.1 Saddle is not welded.Printed 7/18/2007 1:08:47 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 65 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter, utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catecor F-A 02.Fl.21.0003 2-14B-0-1479A-H19A Rigid Restraint F01 .021.021 14B 0-1492A-2(S)

Class 2 O-ISIN4-124B-2.2 2-14-15/sht.1 NDE-66 VT-3 NA 1.625 / 8.000 Calculation No. OSC-1325-06.

02.F1.21.0007 F01.021.025 2-14B-0-1479A-H2 14B 2-14-13/sht.1 NDE-66 VT-3 NA 0.216 / 8.000 Calculation No. OSC-1325-06.

Inspect with Rigid Restraint Class 2 O-ISIN4-124B-2.2 C03.020.024.

02.F17.21.0008 F01.021.026 2-14B-0-1479A-H1 14B 2-14-14/sht.1 NDE-66 VT-3 NA 0.216/6.000 Calculation No. OSC-1325-06.

Inspect with Rigid Restraint Class 2 O-ISIN4-124B-2.2 C03.020.022.

02.F17.21.0014 F01.021.042 2-51A-436J-DE001 51A 0-2AB-25101-01 NDE-66 VT-3 NA 0.000 / 2.500 Calculation No. OSC-479.Rigid Restraint Class 2 O-ISIN4-101A-2.3 02.F1.21.0017 F01.021.045 2-51A-0-1479A-H19C 51A 2-51-12/sht.5 NDE-66 VT-3 NA 0.000 / 2.500 Calculation No. OSC-1660-06.

Rigid Restraint Class 2 O-ISIN4-101A-2.1 HPI System.02.F17.21.0020 F01.021.048 2-51A-2-0-1439C-H12 51A 2-51-18/sht.5 NDE-66 VT-3 NA 0.000 / 4.000 Calculation No. OSC-1023.Rigid Restraint Class 2 O-ISIN4-101A-2.4 HPI System.02.F1.21.0022 F01.021.050 2-51B-436J-DE009 51B 0-2AB-25101-04 NDE-66 VT-3 NA 0.000 / 4.000 Calculation No. OSC-Rigid Restraint Class 2 O-ISIN4-101A-2.1 479.02.F1.21.0034 F01.021.071 2-54A-3-0-1439B-H13 54A 2-54-03/sht.1 NDE-66 VT-3 NA 0.125 / 8.000 Calculation No. OSC-496. Inspect with C03.020.052.

Rigid Restraint Class 2 O-ISIN4-103A-2.1 Printed 7/18/2007 1:08:47 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 66 of 70 This report includes all changes through addendum ONS2-057 Th ler is responsible for verifying this report against the issued plan.Oconee 2, 4th Interfautage 2 (EOC-22)Summary Num Insp Component ID / Type System lSO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catecor F-A 02.F1.21.0037 2-56-1439E-DE001 Rigid Restraint F01.021.081 56 4-56-02/sht.5 Class 2 O-ISIN4-104A-1.1 NDE-66 VT-3 NA 0.000 / 8.000 Calculation No. OS-421.02.F71.22.0003 2-01A-0-1401B-H24 Spring Hgr 02.F17.22.0021 2-53B-5-0-435B-H71 Spring Hgr 02.F1.22.0022 2-53B-1439C-H5394 Hyd Snubber 02.F1.22.0024 2-53A-4-0-435B-H1-9 Spring Hgr 02.F1.30.0007 2-03A-1-0-1439A-H23 Rigid Support 02.F1.30.0012 2-03A-1401A-JG-1 101 Rigid Support 02.F1.30.0015 2-03-0-1439B-H52 Rigid Support F01.022.003 01A 2-01-01/sht.2 Class 2 O-ISIN4-122A-2.1 53B 0-2AB-25301-03 Class 2 O-ISIN4-102A-2.2 NDE-66 VT-3 NDE-66 VT-3 NA 0.000 /36.000 Calculation No. OSC-440.Inspect with item number H04.001.049.

Calculation No. OSC-487.F01.022.055 NA 0.000 / 10.000 F01.022.056 53B 0-2AB-25302-01 Class 2 O-ISiN4-102A-2.2 53A 0-2AB-25301-01 Class 2 0-ISIN4-102A-2.2 NDE-66 VT-3 NDE-66 VT-3 NA 0.000/10.000 Calculation No. OSC-493.Calculation No. OSC-487.F01.022.058 NA 0.000 / 12.000 F01.030.014 03A 2-03A-05/sht.

1 Class 3 0-ISIN4-121D-2.1 03A 2-03A-06/sht.1 Class3 0-SIN4-121D-2.1 NDE-66 VT-3 NDE-66 VT-3 NA 0.000 / 6.000 Calculation No. OSC-447.Calculation No. OSC-1213.F01.030.019 NA 0.000 / 6.000 F01.030.022 03 2-03-01/sht.1 Class 3 O-ISIN4-121B-2.3 NDE-66 VT-3 NA 0.000 / 24.000 Calculation No. OSC-454.Inspect with item number H04.001.004.

Printed 7/18/2007 1:08:47 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 67 of 70 This report includes all changes through addendum ONS2-057 Th ar is responsible for verifying this report against the issued plan.Oconee 2 4th Inter ,utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Catecor F-A 02.F1.30.0019 F01.030.026 2-03A-1401A-GC-0804 03A 2-03A-06/sht.1 NDE-66 VT-3 NA 0.000 / 6.000 Calculation No. OSC-459.Rigid Support Class 3 O-ISIN4-121D-2.1 02.F1.30.0021 F01.030.028 2-03A-1-0-1439B-H11 03A 2-03A-06/sht.3 NDE-66 VT-3 NA 0.375 / 6.000 Calculation No. OSC-459. Inspect with D01.020.012.

Rigid Support Class 3 O-ISIN4-121D-2.1 02.F1.30.0030 F01.030.047 2-07A-1400A-H4090 07A 0-2TB-20701-06 NDE-66 VT-3 NA 0.000 / 10.000 Calculation No. OSC-467.Rigid Support Class 3 O-ISIN4-121A-2.8 02.F1.30.0032 F01.030.061 0-13-447A-H7024 13 4-13-01/sht.1 NDE-66 VT-3 NA 0.000 / 12.000 Calculation No. OSC-1224-25.

Rigid Support Class 3 O-ISIN4-133A-2.5 02.F1.30.0038 F01.030.075 2-14B-1439B-DE154 14B 2-14-06/sht.2 NDE-66 VT-3 NA 0.187 / 8.000 Calculation No. OSC-475. Inspect with D01.020.068.

Rigid Support Class 3 O-ISIN4-124B-2.2 02.F 1.30.0041 F01.030.078 2-14B-0-1439B-RJP-3104 14B 4-14-04/sht.3 NDE-66 VT-3 NA 0.237 / 8.000 Calculation No. OSC-474. Inspect with D01.020.064.

Rigid Support Class 3 O-ISIN4-124B-2.2 02.F1.30.0044 F01.030.082 2-57-1480A-NWIX 57 0-2RB-25701-01 NDE-66 VT-3 NA 0.000 / 12.000 Calculation No. OSC-1332-06.

Rigid Support Class 3 O-ISIN4-107A-2.1 02.F1.30.0359 F01.030.063 2-13-0-345A-PS1-A 13 O-345A NDE-66 VT-3 NA 0.375 / 96.000 Calculation No. OSC-681 or OSC-605. Support located Rigid Support Class 3 O-ISIN4-133A-2.1 on discharge piping at the Condenser Circulating Water Intake Pump 2A.02.F1.31.0009 F01.031.018 2-03A-1-0-1401A-SR2 03A 2-03A-05/sht.5 NDE-66 VT-3 NA 0.000 / 6.000 Calculation No. OSC-447.Rigid Restraint Class 3 O-ISlN4-121D-2.1 Printed 7/18/2007 1:08:47 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 68 of 70 This report includes all changes through addendum ONS2-057 Th er is responsible for verifying this report against the issued plan.Oconee 2, 4th Inter utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISO/DWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Category F-A 02.F1.31.0021 2-14B-438C-DE107 Rigid Restraint 02.F1.31.0022 2-14B-1-0-1439B-H12 Rigid Restraint 02.F1.32.0006 2-03A-1-0-1401 B-H45 Spring Hgr 02.F1.40.0004 2-LDCB-SUPPORT F01.031.063 14B 0-2AB-203A14-02 Class3 O-ISIN4-121D-1.2 NDE-66 VT-3 NA 0.000 / 6.000 Calculation No. OSC-466.F01.031.064 Calculation No. OSC-474. Inspect with D01.020.065.

14B 4-14-04/sht.2 Class 3 O-ISIN4-124B-2.2 NDE-66 VT-3 NA 2.000 / 14.000 F01.032.014 03A 2-03A-08/sht.4 Class 3 O-ISIN4-121D-2.1 OM-201-3107 Class 1 O-ISIN4-101A-2.1 1-34097-2 OM-1 149-0001 Class 3 O-ISIN4-121A-2.7 0-1348-B OM-200.B-0006 Class 3 O-ISIN4-122A-2.4 NDE-66 VT-3 NDE-66 VT-3 NA 0.000 / 6.000 Calculation No. OSC-449.Letdown Cooler 2B Support.F01.040.004 CS 0.000 / 0.000 02.F1.40.0008 2-UST-A 02.F1.40.0010 2-EFDW-PU-T 02.F1.40.0013 2-MCD-C NDE-66 VT-3 NA 0.000 / 0.000 F01.040.008 Upper Surge Tank 2A Support Legs.See Dwg 0-1348-B-001 for BasePlate details.F01.040.010 Emergency Feedwater Pump Turbine. Reference Figure.1 in Manual OM-200.B-0006, Items 12 & 18.NDE-66 VT-3 NA 0.000 / 0.000 F01.040.013 OM-202-5 Class 3 0-ISIN4-121A-2.3 OM-202-25 NDE-66 VT-3 NA 0.000 /0.000 Main Condenser 2C Support Legs.02.F1.40.0020 2-LS-TANK OM-201-63 Class 2 0-ISIN4-101A-2.2 NDE-66 VT-3 NA 0.000 / 0.000 F01.040.020 Letdown Storage Tank Support. Rescheduled as a result of PIP 0-06-4249.

Printed 7/18/2007 1 ý08:47 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 69 of 70 This report includes all changes through addendum ONS2-057 Th ir is responsible for verifying this report against the issued plan. b 0 Oconee 2, 4th InterO utage 2 (EOC-22)Summary Num Insp Component ID / Type System ISOIDWG Numbers Procedure Req Mat Sched Thick/Dia Cal Blocks Comments / Historical Data Categor F-A 02.F1.40.0024 2-LDFTR-A 51B OM-201-0128 Class2 O-ISIN4-101A-2.1 NDE-66 VT-3 NA 0.250 / 0.000 F01.040.024 Letdown Filter 2A Support.The examination in outage 1 does not count in the percentages.

Work Order 98674855 was written to perform this exam in outage 1.The exam scheduled for outage 5 will count in percentages to meet Section Xl requirements.

Rescheduled to outage 2 as a result of PIP 0-06-4249.

02.F1.40.0025 2-50-RCPM-2A2-SS1 Hyd Snubber 02.F1.40.0031 2-UST-DOME 02.F1.40.0061 2-SSF-SWST F01.040.025 0-1066A NDE-66 VT-3 NA 0.000 / 6.000 Calculation No. OSC-0991-01-0001.

Reactor Coolant Class 1 O-ISIN4-100A-2.1 Pump 2A2 Motor Snubbers.

Reference PIP 0-096-O-ISIN4-10OA-2.3 1575.F01.040.031 14B O-348A-02 NDE-66 VT-3 NA 0.000 / 0.000 Upper Surge Tank Dome Support Legs. Rescheduled Class 3 O-ISIN4-121A-2.7 as a result of PIP 0-06-4249.

13 OM 240.-0031 Class 3 O-ISIN4-133A-2.5 NDE-66 VT-3 NA 0.500 / 0.000 Auxiliary Service Water Strainer.02.F1.40.0062 F01.040.032 2-CCWP-A 13 OM 202-0003 NDE-66 VT-3 NA 2.000 0.000 Condenser Circulating Water Intake Pump 2A. Examine Class 3 0-ISlN4-133A-2.1 the Pump Thrust Support shown in the "Plan View" of 0-345 drawing 0-345 and also examine the Pump Floor Plate and associated bolting shown in "View A-A" on drawing OM 202-0003.02.F1.40.0067 2-SGB-LATERAL 50 0-1065Y NDE-66 VT-3 Unit 2 Steam Generator B Lateral Support. Drawings 0-Class 2 0-1065-D 1065X, O-106Y, O-1065-D, and 0-65G should be used 0-ISIN4-100A-2.1 for inspection of the lateral support.Steam Generator.B Lateral Support Printed 7/18/2007 1:08:47 PM Ick8302 v. 07/02/07 SDQA Cat "C" Oconee 2 7/18/2007 1:07:38 PM Page 70 of 70

4.0 Results

Of Inspections Performed The results of each examination shown in the final Inservice Inspection Plan (Section 3 of this report) are included in this section. The completion date and status for each examination are shown. All examinations revealing reportable indications and any corrective action required as a result are described in further detail in Subsections 4.1 and 4.2. Corrective measures performed and limited examinations are described in further detail in Subsections 4.3 and 4.4.The information shown below is a field included in this section of the report: Summary/Item Number ID Number Sys Insp Date description for the reporting format ASME Section Xl Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2), IWF-2500-1 (Class 1 and Class 2), Augmented Requirements Unique Identification Number Component System Identification Date of Examination Insp Status Insp Limited Geo. Ref.(Geometric Reflector applies only to UT)RFR (Relief Request)Comments= CLR Clear REC Recordable REP Reportable Indicates inspection was limited.Coverage obtained is listed Y Yes N No Y Yes N No= General and/or Detail Description EOC 22 Refueling Outage Report Oconee Unit 2 Section 4 Page 1 of 3 Revision 0 July 18, 2007

4.1 Reportable

Indications EOC 22 (Outage 2) did not have any reportable indications during this report period.4.2 Corrective Action Corrective action is action taken to resolve flaws and relevant conditions, including supplemental examinations, analytical evaluations, repair / replacement activities, and corrective measures.

There were no problems that required corrective action during this report period.4.3 Corrective Measures Corrective measures are actions (such as maintenance) taken to resolve relevant conditions, but not including supplemental examinations, analytical evaluations, and repair / replacement activities.

Any corrective measures performed for examinations associated with this report period will be shown on the examination data sheets which are on file at the Duke's Corporate Office in Charlotte, North Carolina.PIP 0-07-02608 was written to document problems found with welds on the Letdown Storage Tank Support. The support was evaluated by civil engineering at Oconee and was found to be acceptable for service. Work Order 924525 was written to correct the problems.4.4 Limited Examinations Limited examinations (i.e., less than or equal to 90% of the required examination coverage obtained) identified during EOC 22 (Outage 2) are shown in the table below.A Request for Relief will be submitted to seek NRC acceptance of the limited coverage for the items listed in the table below.Summary/Item Description of Limitation Number 02.B3. 110.0001 Coverage limitation (41.70%)02.B3.110.0006 Coverage limitation (36.70%)02.B3.110.0007 Coverage limitation (36.70%)02.B3.110.0008 Coverage limitation (36.70%)EOC 22 Refueling Outage Report Oconee Unit 2 Section 4 Page 2 of 3 Revision 0 July 18, 2007 Summary/Item Description of Limitation Number 02.B9.11.0059 Coverage limitation (37.50%)02.C1.20.0006 Coverage limitation (80.26%)02.C5.1 1.0004 Coverage limitation (37.50%)02.C5.21.0021 Coverage limitation (75.00%)02.C5.21.0024 Coverage limitation (37.50%)02.C5.21.0025 Coverage limitation (78.70%)Note: 02.B9.11.0002 was examined during 2EOC-22 and had limited coverage.

This item is rescheduled to be examined again in 2EOC-23 in order to achieve the required coverage (> 90%). Relief Request will be filed after the examination is performed during 2EOC-23 if the required coverage cannot be achieved.EOC 22 Refueling Outage Report Oconee Unit 2 Section 4 Page 3 of 3 Revision 0 July 18, 2007 0 DUKE ENERG YfORPORA TION QUALITY CHNICAL SERVICES Inservice Inspection Database Management System Inspection Results Oconee 2, 4th Interval, Outage 2(EOC-22)Insp Insp Insp Geo Summary No Component ID System Date Status Limited Ref RFR Comment 02.B13.30.0001 2-RPV-WR19 50 05/03/07 CLR N N N UT-07-032 02.B10.10.0013 2-LDCB-SUPPORT 05/20/07 CLR N N N MT-07-017 02.B12.10.0001 2RCP-2A1 50 05/03/07 CLR N N N VT-07-130 02.B3.110.0001 2-PZR-WP15 50 05/15/07 CLR N N N UT-07-089 50 05/15/07 CLR 41.70% N Y UT-07-090 Relief Request will be filed for the limitation.

02.B33.110.0006 2-PZR-WP26-4 50 05/09/07 REC 36.70% Y Y UT-07-048 Indications

  1. 1-45' & 2-35' were determined to be geometric reflectors.

Indication

  1. 3-351 was acceptable per Section XI IWB-3512.Relief Request will be filed for the limitation.

50 05/09/07 CLR 36.70% N Y UT-07-051 Relief Request will be filed for the limitation 50 05/09/07 REC 36.70% N Y UT-07-067 Indication

  1. 1-450 was acceptable per Section XI IWB-3512.Relief Request will be filed for the limitation.

Printed 7/18/2007 1:38:19 PM 1ck8302 SDOA Cat "C' v.07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 1 of 29 Printed 7/18/2007 1:38:19 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 1of29 6 Summary No Component ID 02.B3.110.0007 2-PZR-WP26-5 Insp Insp Insp Geo 0 System Date 50 05/09/07 50 05/09/07 02.B3.110.0008 2-PZR-WP26-6 50 05/09/07 50 05/09/07 Status Limited Ref RFR Comment CLR 36.70% V Y UT-07-049 Indication

  1. 1-451 & 2-35° were determined to be geometric reflectors.

Relief Request will be filed for the limitation.

CLR 36.70% N Y UT-07-052 Relief Request will be filed for the limitation.

CLR 36.70% Y Y UT-07-050 Indication

  1. 1-45' & 2-35* were determined to be geometric reflectors.

Relief Request will be filed for the limitation.

CLR 36.70% N Y UT-07-053 Relief Request will be filed for the limitation.

CLR N N N UT-07-097 CLR N N N UT-07-054 CLR N N N UT-07-055 CLR N N N UT-07-056 CLR N N N UT-07-033 CLR N N N VT-07-135 CLR N N N VT-07-136 02.13.120.0001 02.B3.120.0006 02.B3.120.0007 02.B3.120.0008 02.B6.40.0001 02.17.50.0005 02.B7.50.0006 2-PZR-WP15 2-PZR-WP26-4 2-PZR-WP26-5 2-PZR-WP26-6 2-RPV-LIGAMENTS 2HP-217-2A1-FLG 2HP-216-2A2-FLG 50 50 50 50 50 51A 51A 05/15/07 05/09/07.05/09/07 05/09/07 05/03/07 05/07/07 05/07/07 Printed 7/1812007 1:38:20 PM 1ck8302 SDOA Cat "C" v. 07/02107 Oconee 2 7/18/2007 1:37:36 PM Page 2 of 29 Printed 7/1 BJ2007 1:38:20 PIM Ick83O2 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 2 of 29 0 Summary No Geo Ref RFR 0 Insp System Date Insp Insp Status Limited Component ID Comment 02.B7.50.0007 2HP-214-281-FLG 51A 05/07/07 CLR N N N VT-07-137 Rust exist on flange bolting inside flange but does not reduce thickness more than 5%. There is minor thread deformation due to corrision between the flange. The thread deformation is not in the zone of thread engagement.

02.87.50.0008 2HP-218-2B2-FLG 51A 05/07/07 CLR N N N VT-07-138 There is some rust inside the flanges but does not reduce the section thickness more than 5%.02.B9.11.0002 2-PSL-9 50 05/15/07 CLR N N N PT-07-042 50 05/16/07 CLR 84.80% N Y UT-07-095 This weld was scheduled to be examined again during the 2EOC-23 outage to try and achieve the required coverage (>90%). Relief Request will be filed for the limitation after the examination is performed in 2EOC-23 if the required coverage cannot be achieved..

02.B9.11.0022 2RC-279-92V 50 05/18/07 CLR N N N MT-07-013 50 05/18/07 CLR N N N UT-07-099 02.89.11.0029 2SGB-W2 50 05/11/07 CLR N N N MT-07-005 50 05/12/07 CLR N N N UT-07-074 02.B9.11.0036 2-PSL-1 50 05/15/07 CLR N N N PT-07-043 50 05/16/07 CLR 93.90% N N UT-07-096 02.89.11.0059 2-PDBl-1 50 05/06/07 CLR N N N PT-07-013 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 3 of 29 lnsp Ge Insp Insp Summary No Component ID 02.B9.11.0059 2-PDBl-1 s)02.B9.11.0060 2-PDB1 -3 02.B9.11.0061 2RC-279-94V 02.B9.11.0066 2-51A-30-1

'stem Date Status Limited Ref RFR Comment 50 05/08/07 CLR 37.50% N Y UT-07-046 Relief Request will be filed for the limitation.

50 05/08/07 CLR 37.50% N Y UT-07-047 Relief Request will be filed for the limitation.

50 05/06/07 CLR N N N MT-07-002 50 05/08/07 CLR N N N UT-07-045 50 05/11/07 CLR N N N MT-07-006 50 05/12/07 CLR N N N UT-07-075 51A 05/11/07 CLR N N N PT-07-030 51A 05/13/07 CLR N N N UT-07-077 50 05/12/07 CLR N N N PT-07-034 50 05/12/07 CLR N N N PT-07-035 50 05/12/07 CLR N N N PT-07-036 50 05/06/07 CLR N N N PT-07-014 50 05/08/07 CLR N N N PT-07-026 02.B9.21.0001 02.B9.21.0002 02.B9.21.0003 02.B9.21.0006 02.B9.21.0012 2-50-7-8 2-50-7-14 2-50-7-29 2-PDBl-11 2-PSP-1 1 Printed 7/18/2007 1:38:20 PM 1ck8302 SDQA Cat 'C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 4 of 29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 4 of 29

,Insp System Date Insp Insp Status Limited Summary No 02.B9.21.0013 02.B9.21.0023 02.B9.21.0024 02.19.21.0025 02.B9.21.0040 02.B9.21.0050 02.B9.21.0053 02.B9.31.0001 Component ID 2-PSP-13 2-PSP-22 2-51A-144-24 2-51A-145-1 2RC-204-20 2-51 A-30-32 2-51 A-35-24 2-PHB-16 50 50 51A 51A 51A 51A 51A 50 05/08/07 05/06/07 05/21/07 05/21/07 05/02/07 05/11/07 05/12/07 05/15/07 CLR CLR CLR CLR CLR CLR CLR CLR N N N N 0 Ref N N N N RFR N N N N N Comment PT-07-025 PT-07-015 PT-07-045 PT-07-046 PT-07-012 N N N N N N N N PT-07-031 PT-07-037 MT-07-008 N N N 02.B9.31.0002 02.C1.10.0003 02.Cl.20.0003 02.C1.20.0004 2-PHA-16 2-LDFTRA-SH-FL 2-LDFTRA-HD-SH-1 2-LDFTRA-HD-SH-2 50 50 51B 51B 51B 05/16/07 05/18/07 05/07/07 05/07/07 05/07/07 CLR CLR CLR CLR CLR N N N N N N N N N N N N N N N UT-07-098 UT-07-1 00 PT-07-021 PT-07-022 PT-07-023 Printed 7/18/2007 1:38:20 PM 1ck8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 5 of 29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 5 of 29 S Summary No 02.Cl.20.0005 Component ID 2-LST-HD-SH-1 Insp System Date 51A 05/10/07 Insp Status CLR Insp Limited N 0 Geo Ref N RFR Comment N UT-07-068 02.Cl .20.0006 2-LST-HD-SH-2 51A 05/10/07 CLR 80.26% N Y 02.C3.10.0003 2-LDFTR-A 51A 05/07/07 CLR N N N 02.C3.10.0005 2-LS-TANK 51B 05/10/07 REC N N N 02.C3.20.0008 02.C3.20.0010 02.C3.20.0012 02.C3.20.0030 02.C3.20.0033 02.C5.11.0004 2-03-0-1479A-H 1 B 2-14B-0-1479A-H1 2-14B-0-1479A-H2 2-54A-3-0-1439B-H 13 2-54A-3-0-1439B-H15 2LP-148-90 03 14B 14B 54A 54A 53A 53A 05/18/07 05/13/07 05/13/07 02/15/07 02/15/07 02/12/07 02/12/07 CLR CLR CLR CLR CLR CLR CLR N N N N N N 37.50%N N N N N N Y UT-07-069 Relief Request will be filed for the limitation.

PT-07-024 PT-07-029 Five rounded indications were recorded during the PT examination.

These indications were determined to be acceptable per NDE 35 Acceptance Standards H & L.MT-07-014 MT-07-009 MT-07-01 0 PT-07-001 PT-07-002 PT-07-003 UT-07-005 Relief Request will be filed for the limitation.

Printed 7/18/2007 1:38:20 PM 1ck8302 SDOA Cat "C" v.07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 6 of 29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 6 of 29 Summary No Component ID System Insp Insp Insp Geo Date Status Limited Ref 2/14/07 CLR N N 2/14/07 CLR N N 02.C5.11.0006 2LP-150-36 53A 53A 0: 0: RFR N N Comment PT-07-004 UT-07-001 02.C5.11.0007 2LP-150-37 53A 02/14/07 CLR N N N PT-07-005 53A 02/14/07 CLR N N N UT-07-002 02.C5.11.0008 2LP-150-38 53A 02/14/07 CLR N N N PT-07-006 53A 02/14/07 CLR N N N UT-07-003 02.C5.11.0017 2LP-189-12 53A 05/10/07 CLR N N N PT-07-027 53A 05/10/07 CLR N N N UT-07-057 02.C5.11.0029 2-53A-9-7 53A 05/15/07 CLR N N N PT-07-038 53A 05/15/07 CLR N N N UT-07-087 02.C5.11.0030 2-53A-9-8 53A 05/15/07 CLR N N N PT-07-039 53A 05/15/07 CLR N N N UT-07-088 02.C5.11.0031 2-53A-9-9 53A 05/12/07 CLR N N N PT-07-033 53A 05/12/07 CLR N N N UT-07-076 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 7 of 29 Insp Insp Insp System Date Status Limited Summary No Component ID 0 Geo Ref N N 0 02.C5.11.0032 2LP-189-11 53A 53A 05/10/07 05/10/07 CLR CLR N N RFR N N Comment PT-07-028 UT-07-058 02.C5.11.0072 2LPS-724-14 14B 05/15/07 CLR N N N PT-07-040 14B 05/15/07 CLR N N N UT-07-091 02.C5.11.0073 2LPS-724-15 14B 05/15/07 CLR N N N PT-07-041 14B 05/15/07 CLR N N N UT-07-092 02.C5.21.0003 2-RCP-FTR2B-SH-1 51A 05/07/07 CLR N N N PT-07-019 51A 05/12/07 CLR N N N RT-N/A 02.C5.21.0004 2-RCP-FTR2B-SH-2 51A 05/07/07 CLR N N N PT-07-020 02.C5.21.0021 2-51A-17-147 51A 02/21/07 CLR N N N PT-07-010 51A 02/21/07 CLR 75.00% N Y UT-07-010 Relief Request will be filed for the limitation.

02.C5.21.0022 2-51A-17-158 51A 02/21/07 CLR N N N PT-07-011 51A 02/21/07 CLR N N N UT-07-009 02.C5.21.0023 2-51A-27-25 51A 02/20/07 CLR N N N PT-07-009 Printed 7/18/2007 1:38:20 PM Ick8302 SDOA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 8 of 29 0 Summary No Component ID 02.C5.21.0023 2-51A-27-25 02.C5.21.0024 2HP-220-9 Insp System Date 51A 02/20/07 51A 02/13/07 51A 02/13/07 Insp Status CLR Insp Limited N N 37.50%0 G eo Ref N RFR Comment N UT-07-008 CLR CLR N N N Y PT-07-007 UT-07-006 Relief Request will be filed for the limitation.

02.C5.21.0025 2HP-220-14 51A 02/13/07 51A 02/13/07 CLR CLR N 78.70%N N N Y PT-07-008 UT-07-007 Relief Request will be filed for the limitation.

02.C5.30.0002 2-5113-23-64 51B 05/17/07 CLR N N N PT-07-044 02.C5.51.0001 2MS-133-17 01A 05/21/07 CLR N N N MT-07-018 01A 05/21/07 CLR N N N UT-07-103 02.C5.51.0009 2MS-123-70V 01A 05/09/07 CLR N N N MT-07-003 01A 05/12/07 CLR N N N UT-07-071 02.C5.51.0010 2MS-123-71V 01A 05/11/07 CLR N N N MT-07-007 01A 05/12/07 CLR N N N UT-07-072 02.C5.51.0015 2-03A-10-61 03A 02/12/07 CLR N N N MT-07-001 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 9 of 29 0 Summary No Component ID 02.C5.51.0015 2-03A-10-61 02.C5.51.0016 2SGA-W277 Insp Insp Insp System Date Status Limited 02.C5.51.0020 2FDW-253-3 02.C5.51.0021 2FDW-226-101V 03A 03A 03A 03 03 03 03 03 03 01A 53B 13 07 02/12/06 05/16/07 05/16/07 05/09/07 05/12/07 05/16/07 05/16/07 05/18/07 05/18/07 05/21/07 01/29/07 01/23/07 04/05/07 CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR REC Geo Ref N N N N N N N N N N N N N RFR N N N N N N N N N N N N N Comment UT-07-004 MT-07-011 UT-07-093 MT-07-004 UT-07-073 MT-07-012 UT-07-094 MT-07-015 UT-07-102 MT-07-019 VT-07-002 VT-07-001 VT-07-1 10 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.C5.51.0023 2SGA-W242 02.C5.81.0002 2-MS20A-B 02.D1.10.0002 2-DHRC-A 02.D1.10.0003 2-SSF-SWST 02.D1.10.0004 2-MCD-C Printed 7/18/2007 1:38:20 PM 1ck8302 SDOA Cat "C" v.07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 10 of 29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 10 of 29 0 Summary No Insp Insp Insp G9-o System Date Status Limited Ref Component ID RFR Comment 02.D1.10.0005 2-UST-A 14B 01/09/07 CLR N N N VT-07-009 02.D1.10.0006 2-UST-DOME 14B 01/25/07 REC N N N VT-07-099 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.D1.20.0006 2-03A-1-0-1439B-H11 03A 02/15/07 REC N N N VT-07-111 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.D1.20.0021 2-14B-0-1439B-RJP-3104 14B 02/07/06 CLR N N N VT-07-024 02.D1.20.0022 2-14B-1-0-1439B-H12 14B 03/21/07 REC N N N VT-07-112 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.D1.20.0025 2-14B-1439B-DE154 14B 03/22/07 CLR N N N VT-07-010 02.D1.20.0175 2-13-0-345A-PS1-A 13 11/07/06 REC N N N VT-07-100 The discrepancies found were reviewed by civil engineering and the support was found to be acceptable for service. Work Order 00910733 was written to correct problems.02.D1.30.0001 2-CCWP-A 13 11/07/06 REC N N N VT-07-101 The discrepancies found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.10.0001 2-51A-0-1479A-H12B 51A 05/02/07 REC N N N VT-07-113 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 11 of 29 0 Summary No Component ID 02.F1.11.0006 2-53A-0-1479A-H24C GV Insp Insp/nsp 02.F1.12.0004 02.F1.12.0005 2-50-1479A-H3A 2-51A-0-1479A-H1A 02.F1.20.0004 2-01A-0-1401B-H23 02.F1.20.0005 2-03-0-1479A-H1B System Date Status Limited Ref RFR Comment 53A 05/02/07 REC N N N VT-07-114 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service. Work Order 00924660 was written to correct problems.50 05/07/07 CLR N N N VT-07-139 51A 05/07/07 REC N N N VT-07-145 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.01A 01/09/07 REC N N N VT-07-102 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.03 05/07/07 REC N N N VT-07-147 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service. Work order 00924642 was written to correct problems.14B 05/06/07 CLR N N N VT-07-142 51 05/10/07 CLR N N N VT-07-149 51A 03/15/07 CLR N N N VT-07-011 51A 03/12/07 CLR N N N VT-07-012 53B 03/15/07 -CLR N N N VT-07-013 02.F1.20.0009 02.F1.20.0013 02.F1.20.0018 02.F1.20.0022 02.F1.20.0039 2-144B-0-1479A-H118 2-51-0-436J-H1-42 2-51A-6-0-435B-SR58 2-51A-0-1444-H1187 2-53B-0-435B-DE019 Printed 7/18/2007 1:38:20 PM 1ck8302 SDOA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 12 of 29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 12 of 29 0 Summary No 02.Fl.20.0041 O2.F1.20.0048 O2.F1.20.0052 O2.F1.20.0059 Component ID 2-53B-0-439A-H60 2-53B-2-0-436E-H5 2-54A-3-0-1439B-H15 2-56-2-0-437B-H30 System 53B 53B 54A 56 Insp Date 03/22/07 03/15/07 02/15/07 02/19/07 Insp Status CLR CLR CLR REC Insp Limited N N N N Geo Ref N N N N RFR N N N N Comment VT-07-0 14 VT-07-0 15 VT-07-020 VT-07-115 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.VT-07-143 VT-07-153 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service. Work Order 00926389 was written to correct problems.O2.F1.21.0003 02.F1.21.0007 2-1 4B-0-1479A-H1 9A 2-14B-0-1479A-H2 14B 05/07/07 14B 05/13/07 CLR REC N N N N N N O2.F1.21.0008 2-14B-0-1479A-H1 14B 05/13/07 REC N N N VT-07-154 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service. Work Order 00926385 was written to correct problems.O2.F1.21.0014 2-51A-436J-DE001 51A 05/10/07 CLR N N N VT-07-150 O2.F1.21.0017 2-51A-0-1479A-H19C 51A 05/02/07 REC N N N VT-07-116 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service. Work Order 00924605 was written to correct problems.Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 13 of 29 0 Summary No Component ID 02.F1.21.0020 2-51A-2-0-1439C-H12 Insp Insp Insp System Date Status Limited 51A 02/07/06 REC N Ge Ref RFR N N Comment VT-07-103 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.VT-07-151 02.F1.21.0022 02.F1.21.0034 02.F1.21.0037 2-54A-3-0-14391B-H 13 2-56-1439E-DE001 51B 05/10/07 54A 02/15/07 56 03/21/07 CLR CLR REC N N N N N N N N N-VT-07-021 VT-07-117 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.22.0003 2-01A-0-14011B-H24 01A 05/04/07 REC N N N VT-07-131 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.22.0021 2-53B-5-0-435B-H71 53B 03/15/07 CLR N N N VT-07-016 02.F1.22.0022 2-53B-1439C-H5394 53B 03/22/07 REC N N N VT-07-118 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.22.0024 2-53A-4-0-435B-H119 53A 03/15/07 CLR N N N VT-07-017 02.F1.30.0007 2-03A-1-0-1439A-H23 03A 03/22/07 REC N N N VT-07-119 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.30.0012 2-03A-1401A-JG-1101 03A 01/09/07 CLR N N N VT-07-008 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 14 of 29 0 Summary No Component ID 02.F1.30.0015 2-03-0-14391-H52 Insp Insp System Date Status 03 04/28/07 REC Insp Limited N 9 Ref RFR N N Comment VT-07-120 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.30.0019 2-03A-1401A-GC-0804 03A 01/09/07 REC N N N VT-07-104 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.30.0021 2-03A-1-0-1439B-H11 03A 02/15/07 CLR N N N VT-07-022 02.F1.30.0030 2-07A-1400A-H4090 07A 01/18/07 CLR N N N VT-07-007 02.F1.30.0032 0-13-447A-H7024 13 01/11/07 REC N N N VT-07-105 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.30.0038 02.F1.30.0041 02.F1.30.0044 02.F1.30.0359 2-14B-1439B-DE154 2-14B-0-1439B-RJP-3104 2-57-1480A-NWIX 2-13-0-345A-PS1-A 14B 14B 57 13 03/22/07 02/07/06 05/07/07 11/07/06 CLR CLR CLR REC N N N N N N N N N N N N VT-07-018 VT-07-025 VT-07-144 VT-07-106 The discrepancies found were reviewed by civil engineering and the support was found to be acceptable for service. Work Order 00910733 was written to correct problems.Printed 7/18/2007 1:38:20 PM 1ck8302 SDQA Cat "C" v.07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 15 of 29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 15 of 29 0 Summary No 02.F1.31.0009 Insp Insp Insp Geo System Date Status Limited Ref Component ID 2-03A-1-0-1401A-SR2 RFR Comment 03A 03/12/07 REC N N N VT-07-121 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.31.0021 2-14B-438C-DE107 14B 01/18/07 CLR N N N VT-07-006 02.F1.31.0022 2-14B-1-0-1439B-H12 14B 03/21/07 CLR N N N VT-07-019 02.F1.32.0006 2-03A-1-0-1401B-H45 03A 03/15/07 REC N N N VT-07-122 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.40.0004 2-LDCB-SUPPORT 05/21/07 REC N N N VT-07-155 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.40.0008 2-UST-A 01/09/07 CLR N N N VT-07-005 02.F1.40.0010 2-EFDW-PU-T 01/24/07 CLR N N N VT-07-004 02.F1.40.0013 2-MCD-C 04/05/07 REC N N N VT-07-123 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.40.0020 2-LS-TANK 05/10/07 REC N N N VT-07-152 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service. Work Order 924525 was written to correct problem. PIP 0-07-02608 was written to document the weld problems with this support.Printed 7/18/2007 1:38:20 PM lck8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 16 of 29 0 Summary No Insp Insp Insp 9-o System Date Status Limited Ref Component ID RFR Comment 02.F1.40.0024 2-LDFTR-A 51B 05/08/07 CLR N N N VT-07-140 02.F1.40.0025 2-50-RCPM-2A2-SS1 05/09/07 CLR N N N VT-07-141 02.F1.40.0031 2-UST-DOME 14B 01/25/07 REC N N N VT-07-107 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.40.0061 2-SSF-SWST 13 01/23/07 CLR N N N VT-07-003 02.F1.40.0062 2-CCWP-A 13 11/07/06 REC N N N VT-07-108 The discrepancies found were reviewed by civil engineering and the support was found to be acceptable for service.02.F1.40.0067 2-SGB-LATERAL 50 05/21/07 REC N N N VT-07-156 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service. Work order 00926701 was written to obtain measurements that will be used to update Calculation OSC-7723.02.G1.1.0001 2-RCP-2A1 50 12/11/06 CLR N N N MT-NA 50 12/11/06 CLR N N N UT-N/A 02.G1.1.0005 2-RCP-2A2 50 05/05/07 CLR N N N UT-07-044 02.G1.1.0006 2-RCP-2B1 50 05/05/07 CLR N N N UT-07-042 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 17 of 29 0 Summary No Insp System Date Insp Insp t Status Limited Ref Component ID RFR Comment 02.G1.1.0007 2-RCP-2B2 02.G12.1.0005 2-PDB2-11 02.G13.1.0001 2-PZR-WP45 02.G13.1.0002 2-PSP-1 02.G13.1.0003 2-PZR-WP23 02.G13.1.0004 2-PZR-WP91-1 02.G13.1.0005 2-PZR-WP91-2 02.G13.1.0006 2-PZR-WP91-3 02.G13.1.0007 2-PHA-17 02.G13.1.0008 2-53A-10-10A 02.G13.1.0009 2-PHB-17 02.G13.1.0010 2-PSL-10 02.G13.1.0011 2-PZR-WP63-1 50 05/05/07 50 05/05/07 50 05/01/07 50 05/01/07 50 05/01/07 50 05/01/07 50 05/01/07 50 05/01/07 50 05/02/07 53A 05/02/07 50 04/30/07 50 04/30/07 50 05/01/07 CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR N UT-07-043 N UT-07-070 N VT-07-032 N VT-07-033 N VT-07-034 N VT-07-035 N VT-07-036 N VT-07-037 N VT-07-128 N VT-07-129 N VT-07-038 N VT-07-039 N VT-07-040 Printed 7/18/2007 1:38:20 PM 1ck8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 18 ot29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQ Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 18 of 29 Insp System Date Insp Insp Status Limited Summary No 02.G13.1.0012 02.G13.1.0013 02.G13.1.0014 02.G13.1.0015 02.G13.1.0016 02.G13.1.0017 02.G13.1.0018 02.G13.1.0019 02.G13.1.0020 02.G13.1.0021 02.G13.1.0022 02.G 13.1.0023 02.G13.1.0024 Component ID 2RC-240-6B 2-PZR-WP63-2 2RC-240-9A 2-PZR-WP63-3 2RC-240-4A 2-PZR-WP63-4 2RC-240-25V 2-PZR-WP63-5 2RC-240-1 A 2-PZR-WP63-6 2RC-240-21V 2-PZR-WP63-7 2RC-206-6 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR GOc Ref N N N N N N N N N N N N N RFR N N N N N N N N N N N N N Comment VT-07-041 VT-07-042 VT-07-043 VT-07-044 VT-07-045 VT-07-046 VT-07-047 VT-07-048 VT-07-049 VT-07-050 VT-07-051 VT-07-052 VT-07-053 N N N Printed 7/18/2007 1:38:20 PM 1ck8302 SDOA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 19 of 29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 19 of 29 O Insp Insp Insp v Summary No Component ID System Date Status Limited Ref RFR Comment 02.G13.1.0025 2-50-16-8A 50 05/01/07 CLR N N N VT-07-054 02.G13.1.0026 2RC-278-66 50 04/30/07 CLR N N N VT-07-055 02.G13.1.0027 2RC-278-70V 50 04/30/07 CLR N N N VT-07-056 02.G13.1.0028 2RC-277-50 50 05/01/07 CLR N N N VT-07-057 02.G13.1.0029 2RC-277-71V 50 05/01/07 CLR N N N VT-07-058 02.G13.1.0030 2RC-278-23 50 04/30/07 CLR N N N VT-07-059 02.G13.1.0031 2RC-278-69 50 04/30/07 CLR N N N VT-07-060 02.G13.1.0032 2RC-277-24 50 05/01/07 CLR N N N VT-07-061 02.G13.1.0033 2RC-277-70 50 05/01/07 CLR N N N VT-07-062 02.G13.2.0001 2-RPV-WR53 50 05/20/07 CLR N N N VT-07-157 02.G13.2.0002 2-RPV-WR53A 50 05/20/07 CLR N N N VT-07-158 02.G13.2.0003 2-PIB1-11 50 05/01/07 CLR N N N VT-07-063 02.G13.2.0004 2-51A-35-15A 51A 05/01/07 CLR N N N VT-07-064 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM .Page 20 of 29 nsp lnsp Insp Summary No Component ID System Date Status Limited Ref RFR Comment 02.G13.2.0005 2-PIA1-7 50 04/30/07 CLR N N N VT-07-065 02.G13.2.0006 2-PIA2-7 50 04/30/07 CLR N N N VT-07-066 02.G13.2.0007 2-PIB1-7 50 05/01/07 CLR N N N VT-07-067 02.G13.2.0008 2-PIB2-7 50 04/30/07 CLR N N N VT-07-068 02.G13.2.0009 2-PDA1-2 50 04/30/07 CLR N N N VT-07-069 02.G13.2.0010 2-PDA2-2 50 04/30/07 CLR N N N VT-07-070 02.G13.2.0011 2-PDB1-2 50 04/30/07 CLR N N N VT-07-071 02.G13.2.0012 2-PDB2-2 50 04/30/07 CLR N N N VT-07-072 02.G13.2.0014 2RC-279-19AA 50 05/01/07 CLR N N N VT-07-073 02.G13.2.0015 2RC-279-20 50 04/30/07 CLR N N N VT-07-074 02.G13.2.0016 2-PIAl-11 50 04/30/07 CLR N N N VT-07-026 02.G13.2.0017 2-50-7-29 50 04/29/07 CLR N N N VT-07-027 02.G13.2.0018 2-PIA2-11 50 04/29/07 CLR N N N VT-07-028 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 21 of 29 0 Summary No 02.G13.2.0019 02.G13.2.0020 02.G13.2.0021 02.G13.2.0022 02.G13.2.0023 02.G14.1.0001 02.G14.1.0002 02.G14.1.0003 02.G14.1.0004 02.G14.1.0005 02.G14.1.0006 02.G14.1.0007 02.G14.1.0008 GIP 0 Insp System Date Insp Insp Status Limited Component ID 2-50-7-14 2-PIB2-11 2-50-7-8 2RC-279-21 2RC-279-22A 2-PZR-THERM 2-PZR-WP45 2-PSP-1 2-PZR-WP23 2-PZR-WP91

-1 2-PZR-WP91-2 2-PZR-WP91-3 2-PZR-WP63-1 04/29/07 04/30/07 04/29/07 04/30/07 04/30/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR Ref N N N N N N N N N N N N N RFR N N N N N N N N N N N N N Comment VT-07-029 VT-07-030 VT-07-031 VT-07-075 VT-07-076 VT-07-077 VT-07-078 VT-07-079 VT-07-080 VT-07-081 VT-07-082 VT-07-083 VT-07-084 Printed 7/18/2007 1:38:20 PM 1ck8302 SDOA Cat 'C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 22 of 29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 22 of 29 0 Insp System Date Insp Insp Status Limited Summary No 02.G14.1.0009 02.G14.1.0010 02.G14.1.0011 02.G14.1.0012 02.G14.1.0013 02.G14.1.0014 02.G14.1.0015 02.G14.1.0016 02.G14.1.0017 02.G14.1.0018 02.G14.1.0019 02.G14.1.0020 02.G14.1.0021 Component ID 2RC-240-6B 2-PZR-WP63-2 2RC-240-9A 2-PZR-WP63-3 2RC-240-4A 2-PZR-WP63-4 2RC-240-25V 2-PZR-WP63-5 2RC-240-1A 2-PZR-WP63-6 2RC-240-21V 2-PZR-WP63-7 2RC-206-6 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 05/01/07 CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR Geo Ref N N N N N N N N N N N N N RFR N N N N N N N N N N N N N Comment VT-07-085 VT-07-086 VT-07-087 VT-07-088 VT-07-089 VT-07-090 VT-07-091 VT-07-092 VT-07-093 VT-07-094 VT-07-095 VT-07-096 VT-07-097 Printed 7/18/2007 1:38:20 PM 1ck8302 SDOA Cat "C' v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 23 of 29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 23 of 29 Summary No Component ID Insp Insp Status Limited Ref Insp System Date RFR Comment 02.G14.1.0022 2-50-16-8A 02.G2.1.0001 2-PDB1-46 02.G2.1.0002 2-PDA2-46 02.G2.1.0003 2-PDA1-46 02.G2.1.0004 2-PDB2-46 02.G2.1.0005 2-PDAl-11 02.G2.1.0006 2-PDA2-11 02.G2.1.0007 2-PDB2-11 02.G2.1.0008 2-PDBl-11 02.G2.1.0009 2-PDB1-47 02.G2.1.0010 2-PDB2-47 02.G2.1.0011 2-PDA1 -47 02.G2.1.0012 2-PDA2-47 50 05/01/07 50 05/06/07 50 05/02/07 50 05/02/07 50 05/06/07 50 05/05/07 50 05/02/07 50 05/05/07 50 05/05/07 50 05/05/07 50 05/05/07 50 05/05/07 50 05/02/07 CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR N N N VT-07-098 UT-07-040 UT-07-012 UT-07-013 UT-07-041 UT-07-026 UT-07-024 UT-07-027 UT-07-028 UT-07-029 UT-07-030 UT-07-031 UT-07-025 Printed 7/18/2007 1:38:20 PM 1ck8302 SOQA Cat "C" v.07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 24 ot29 Printed 7/18/2007 1:38:20 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 24 of 29 0 Summary No Component ID Insp Insp Insp Status Limited 02.G2.1.0013 02.G2.1.0014 02.G2.1.0015 02.G2.1.0016 02.G2.1.0017 02.G2.1.0018 02.G2.1.0019 02.G2.1.0020 02.G2.1.0021 02.G2.1.0022 02.G2.1.0023 02.G2.1.0024 02.G4.1.0001 2RC-204-28 2RC-202-17 2RC-203-21 2RC-205-1 2RC-203-3 2RC-202-19 2RC-204-20 2RC-205-3 2A2 THERM-SLEEVE 2B1 THERM-SLEEVE 2A1 THERM-SLEEVE 2B2 THERM-SLEEVE 2RC-202-17 System Date 50 05/02/07 50 05/10/07 50 05/02/07 50 05/11/07 50 05/02/07 50 05/10/07 50 05/02/07 50 05/11/07 50 05/04/07 50 05/09/07 50 05/04/07 50 05/09/07 51A 05/10/07 CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR v Ref N N N N N N N N N N N N N RFR N N N N N N N N N N N N N 0 Comment UT-07-016 UT-07-062 UT-07-017 UT-07-078 UT-07-018 UT-07-061 UT-07-019 UT-07-079 RT-n/a RT-N/A RT-n/a RT-N/A UT-07-063 Printed 7/18/2007 1:38:20 PM 1ck8302 SDOA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 25 of 29 Printed 7/18/2007 1:38:20 PM Ick83O2 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 25 of 29 0 Summary No Component ID 02.G4.1.0002 2RC-202-19 02.G4.1.0003 2RC-205-1 02.G4.1.0004 2RC-205-3 02.G4.1.0005 2HP-218-18 02.G4.1.0006 2HP-214-13 02.G4.1.0007 2HP-214-15 02.G4.1.0008 2RC-202-4 Insp System Date 51A 05/10/07 51A 05/11/07 51A 05/11/07 51A 05/11/07 51A 05/10/07 51A 05/10/07 51A 05/10/07 51A 05/10/07 51A 05/06/07 51A 05/02/07 51A 05/06/07 51A 05/02/07 51A 05/09/07 51A 05/11/07 CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR Insp Insp Status Limited N N N N N N 97.00%N 99.80%N N N N N Geo Ref N N N N N N N N N N N N N N RFR Comment N UT-07-060 N UT-07-080 N UT-07-081 N UT-07-082 N UT-07-065 N UT-07-064 N RT-N/A N UT-07-059 N RT-N/A N UT-07-014 N RT-N/A N UT-07-015 N RT-N/A N UT-07-085 02.G4.1.0009 2RC-203-4 02.G4.1.0010 2RC-204-4 02.G4.1.0011 2RC-205-4 Printed 7/18/2007 1:38:20 PM 1ck8302 SDOA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 26 of 29 Printed 7/18/2007 1:38:20 PM Ick83O2 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 26 of 29 Summary No Component ID 02.G4.1.0012 2HP-214-14 Insp Insp Insp GO System Date Status Limited Ref RFR 51A 05/10/07 CLR N Comment UT-07-066 Indication

  1. 1 was determined to be a geometric reflector due to ID weld root geometry.02.G4.1.0013 2HP-216-7 51A 05/04/07 CLR N N N UT-07-034 02.G4.1.0014 02.G4.1.0015 02.G4.1.0016 02.G4.1.0017 02.G4.1.0018 02.G4.1.0019 02.G4.1.0020 02.G4.1.0021 02.G4.1.0022 02.G4.1.0023 2HP-216-8 2HP-216-9 2HP-217-10 2HP-217-11 2HP-217-12 2HP-218-20 2HP-218-21 2HP-218-22 2RC-203-21 2RC-203-3 51 A 05/04/07 51 A 05/04/07 51A 05/05/07 51A 05/05/07 51A 05/05/07 51A 05/11/07 51A 05/11/07 51A 05/11/07 50 05/02/07 50 05/02/07 CLR CLR CLR CLR CLR CLR CLR CLR CLR CLR UT-07-035 UT-07-036 UT-07-037 UT-07-038 UT-07-039 UT-07-083 N N N N N N N N N N N N UT-07-084 UT-07-086 UT-07-020 UT-07-021 Printed 7/18/2007 1:38:21 PM 1ck8302 SDQA Cat "C" v.07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 27 of 29 Printed 7/18/2007 1:38:21 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 27 of 29 0 Summary No Component ID 02.G4.1.0024 2RC-204-28 02.G4.1.0025 2RC-204-20 02.H2.1.0004 2-PHB-13 02.H2.1.0005 2-PHB-14 02.H2.1.0006 2-PHB-15 02.H4.1.0004 2-03-0-1439B-H52 Insp System Date 50 05/02/07 50 05/02/07 50 05/07/07 50 05/07/07 50 05/07/07 03 04/28/07 lnsp Status CLR CLR CLR CLR CLR REC Insp Limited N N N N N N G9 Ref N N N N N N 0 RFR Comment N UT-07-022 N UT-07-023 N PT-07-016 N PT-07-017 N PT-07-018 N VT-07-124 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.H4.1.0023 2-01A-0-1441-H3 01A 05/01/07 REC N N N VT-07-125 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.H4.1.0024 2-01A-0-1441-R2-2 01A 05/19/07 CLR N N N MT-07-016 01A 05/04/07 REC N N N VT-07-146 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service. Work Order 00926712 was written to correct problems.02.H4.1.0025 2-01A-0-1441-H4 01A 05/06/07 REC N N N VT-07-148 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.Printed 7/18/2007 1:38:21 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 28 of 29 0 Summary No Insp Insp G9 Status Limited Ref Component ID Insp System Date 01A 05/04/07 RFR Comment 02.H4.1.0026 2-01A-0-1401B-H5 REC N N N VT-07-132 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.H4.1.0027 2-01A-0-1401B-R3 01A 05/04/07 REC N N N VT-07-133 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.H4.1.0028 2-01A-0-1401B-H6 01A 05/01/07 REC N N N VT-07-126 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.H4.1.0030 2-O1A-0-1401B-H8 O0A 04/28/07 CLR N N N VT-07-023 02.H4.1.0031 2-01A-0-1401B-H9 01A 04/28/07 REC N N N VT-07-127 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.H4.1.0047 2-O1A-0-1401B-H23 01A 01/09/07 REC N N N VT-07-109 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.02.H4.1.0049 2-01A-0-1401B-H24 01A 05/04/07 REC N N N VT-07-134 The discrepancies that were found were reviewed by civil engineering and the support was found to be acceptable for service.Printed 7/18/2007 1:38:21 PM Ick8302 SDQA Cat "C" v. 07/02/07 Oconee 2 7/18/2007 1:37:36 PM Page 29 of 29

5.0 Owner's

Report for Repair and Replacement Activities As required by the applicable code, records of Class 1 and Class 2 Repair and Replacement work is included on NIS-2 forms in this section.Due to station processing and approval time frames, three categories of repair and replacement documentation exist for: 1) work performed during a prior refueling cycle; 2) work performed during the current refueling cycle; and 3) work completed but documentation not yet reviewed and approved.There were 9 work orders for category 1 repair and replacement documentation for this reporting period. Work Orders 98742091, 98555377, 98626098, 98669959-01, 98701069, 98701070, 98704023, 98727683-10, and 98536821 had work completed prior to 11-15-2005 and copies of the NIS-2 forms are included in this report. The NIS-2 forms associated with the nine work orders are the first 36 pages that immediately follow this page. PIP 0-06-01571, PIP 0-06-0476 and PIP 0-06-01083 were written at the end of the Unit 2 EOC-21 refueling outage to document the late submittal for the NIS-2 forms associated with the 9 work orders listed previously in this paragraph.

Category 2 had 36 NIS-2 forms for work orders completed during this reporting period. Copies of the NIS-2 forms are included in this section of the report.* There were no items for Category 3 during this reporting period.The individual work request documents and manufacturers' data reports are on file at Oconee Nuclear Station.5.1 Class 1 and 2 Preservice Examinations As required by the applicable code, Preservice Inspection (PSI) Examinations were performed on ISI Class 1 items during this report period. PSI Examination data for items listed below is on file in the Oconee Nuclear Station QA Vault.Work Orders Weld ISI Type of Comments Numbers Class Inspection 1723280 2-PZR-WP91-1-WOL A UT Weld Overlay PZR Relief Nozzle 1723280 2-PZR-WP91-2-WOL A UT Weld Overlay PZR Relief Nozzle 1723280 2-PZR-WP91-3-WOL A UT Weld Overlay PZR Relief Nozzle 1723281 2-RC-0266-23V A UT Weld Overlay PZR Spray Nozzle 1723282 2-RC-0326-21 V A UT Weld Overlay Hotleg Surge Nozzle 1723282 2-RC-0326-22V A UT Weld Overlay PZR Surge Nozzle EOC 22 Refueling Outage Report Oconee Unit 2 Section 5 Page 1 of 1 Revision 0 July 18, 2007

-eFiti NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI-I --Work Order Number 98742091 Sheet 1 of 2 Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 2/8/2006 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date-Not Applicable

4. Identification of System, ASME Class Steam Generator, ASME Class 1 5.(a) Applicable Construction Code: ASME Section III 19 9,7 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)Inspection Port over @ Port #9 B & W Canada 006K-03 207 PN# 5206081 2003 Removed YES Inspection Port cov Port B & W Canada 006K-03 207 PN# 5206081 2003 Removed YES Inspection Port Cvr@Pr#1I B & W Canada 006K-03 207 PN# 5206081I 2003 Removed YES Cover @ Port # I I Inspection Port B & W Canada 006K-03 207 PN# 5206081 2003 Removed YES Cover @ Port #14 Inspection Port Test Cover B & W Canada 160K-01 214 PN# 5231484 2005 Installed YES Assembly #I Inspection Port Test Cover B & W Canada 160K-02 215 PN# 5231483 2005 Installed YES Assembly #2 Inspection Port Test Cover B & W Canada 160K-03 216 PN# 5231760 2005 Installed YES Assembly #3 Inspection Port Test Cover Assembly B & W Canada 160K-03 216 PN# 5231854 2005 Installed YES Assembly #3 Flange Inspection Port Test Cover B & W Canada 160K-04 217 PN# 5231790 2005 Installed YES Assembly #4 _ 1 1 -7. Description of Work On Unit 2 "A" Steam Generator one inspection port cover was removed at each support location at #9, #10, #11 and #14 and a instrumented cover was installed.
8. Test Conducted E-- Hydrostatic E] Pneumatic Z Nominal Operating Pressure El Exempt El Other Pressure PSI Test Temperature OF

.. Foym NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI rCERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed / Engineer Date 2/9/2006 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of -, and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 3- 2g6- ,. to -3 e_ 6> , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions

/SIs ector's Signature National Board, State, Province, and Endorsements Date .3 -2&oC' Problem Investigation Process Oconee Nuclear Station PIP SerialN: gin~f .NNo Other 'Re rtv 0-06-01571I 4 Corrective Actions CA Seq. No: 1.Status:., -Orig

-'p CAC ,-: Ch ii1% de , IWS Closed IWS 02a E R Proposed Corrective Action: To enter applicable work.packages that are received for QA final review that contain ASME Section XI components that require NIS-2 reports ne-d to be submitted to the General Office for NRC with in the 45 day window after start up of the applicable units RFO.Originated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 03/22/2006 Signaie Tin<'~ div: a~K Q ru. ae Approval Assigned To: WTM5506 WTM5506 IWS 03/22/2006 Assigned To: TRB6214 WTM5506 IWS 03/29/2006 Ready For Approval:

TRB6214 WTM5506 IWS 03/29/2006 Approved By: WTM5506 WTM5506 IWS 03/29/2006 General:Outage:

N/A Mode: N/A Other Tracking Processes T Number Text Actual Corrective Action: Priority:

13b Actual CAC: J Status: Open Due Date: 04/12/2006 The following work order package was received past the 45 day window after start up of unit 2 RFO and for submitting required NIS-2 report to General Office.***** Work Order package-S74-209:-INIS-2 form was initiated by Accountable Engineer on 2/09/2006-24 days past deadline and actual work was completed at the end of November 2005 for MOD package #OD200349.

Originated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 03/29/2006 SignathreTyp.. , !ndi,,-' ate'. --.. Teain ;i G ..::: 1 ..::v Dat Assigned To: TRB6214 WTM5506 IWS 03/22/2006 Due Date: 04/12/2006 Accepted By: WTM5506 WTM5506 IWS 03/29/2006 End of the Document for PIP No: The status of this PIP is:& e duration of this PIP was: 0-6-1571 Screened 2 days 0312912006 11:16 Page I PIP No:-0z067-0157Z1-Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI U Work Order Number 98555377 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 2/2/2006 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable CharlQtte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Reactor Coolant, ASME Class 1 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)Hanger 2-64-I 479D DPC None None None 1974 Corrected NO 1479D-H6451
7. Description of Work Loose bolts to allow replacement of operator on valve 2RC-6.Test Conducted[] Hydrostatic

[] Pneumatic

[-- Nominal Operating Pressure Exempt []Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 98555377 Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o 1/2 by 2 inch A 325 Type I bolts in hanger, UTC # 1063576.0 o 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed , / Senior Engineer Date 2/2/2006 Owner or Owner s Desiee, f.le CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period -to z -,/4 -a e- , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this,, certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

I Commissions , -/'-i" --'f -ector s Signature National Board, State, Province, and Endorsements Date l(

Problem Investigation Process Oconee Nuclear Station PIPSerial ,No: ::.. ActionhCat6 : o .LER.. No ..." ...... ...r Re 0-06-00476 3 Problem Identification Discovered Time/Date:

10:42 01/27/2006 Occurred Time/Date:

Unit(s) Affected: Unit Mode %Power Unit Status Remarks N/A N/A 100 N/A System(s)

Affected: N/A Not Related to a Unit"s System.Affected Equipment (No Equipment Affected)Location of Problem: Bldg: Column Line: Elev: Location Remarks: Method Used to Discover Problem: Brief Problem

Description:

Work Packages not processed by Mechanical Services teams in a timely manner.Stail Problem

Description:

98656697-01 998536821-010 98586396-01 98657709-01 98671891-01 Last Updated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 02/02/2006 This work orders 98674209-01, 98674628-01, 98641556-02, 98634132-01, 98656284-01 should be included in this PIP.Last Updated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 01/30/2006 It was recently discovered that a population of old work orders and their associated packages had not been turned in to QC for final review. As a result, some upgraded Section X I components had not had their NIS-2 documentation completed as required.

In many cases, packages are held when the technical work is completed so that support tasks for scaffold removal, coating, grouting, or similar tasks can complete.

When that occurs and the work order in WMS is completed, the paper packages are sometimes delayed in getting back to QC/Engineering for final evaluation.

In the case of this population of work orders, these packages have been significantly delayed, leading to a failure in the timely completion of NIS-2 paperwork and violation of Maintenance Directive MD 7.5.10. The work orders affected are 98536821-01, 98625986-09, 985553771l0,98624861-

22. 98671891-01, 98656697-01, 98657709-01, 98586399-01, 98586396-01, and 98656689-01.

The supervisor who had possession of these packages has now processed all of them and turned them in. He has been counseled on the timely completion and submission of paperwork following the completion of the work. A process will be put in place this week to ensure that all work packages are monitored on a weekly basis to ensure that none are retained after field work completes.

  • ign this PIP to ONS Maintenance Mechanical Services for documentation of further corrective actions.0412.512006 05:18 Page I PIP No: 0-06-00476 Q Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 98626098 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 7/20/2005 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable
4. Identification of System, ASME Class Low Pressure Injection, ASME Class 1 5.(a) Applicable Construction Code: ASME Section I1 19 ?J3 Edition, Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)Valve 2LP-0048 Crane Nuclear C7871 UNK Item #9 1998 Installed NO 7. Description of Work Replace Retaining ring 8. Test Conducted L] Hydrostatic LI Pneumatic Pressure Nominal Operating Pressure []1 Exempt PSI Test Temperature

_Other OF Visual inspection Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI IWork Order Number Sheet 98626098 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o Replaced internal retaining Item #9 on drawing OM 245 0001 001 o 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authp atio Number NtA lcbeExpiration Date NtApial Signed Dat re_ _ __ _ _ _CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 4~.~ ~c~~and employed by HSB CT of Hartford, Connecticut have inspected the components described in thiis Owner's Report during the period _______________

to -- -Z" 0.- , and state that to the best of my knowledge and belief, the Owner has performed examinations and 'taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.By signing thts certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

______________________Commissions

~//</44~M~ecors Signature National Board, State, Province, and Endorsements Date (:, 42'.

Problem Investigation Process Oconee Nuclear Station[0 -1 -LER-4Not 0-06-01571 4 a Problem Identification Discovered Time/Date:

14:29 03/20/2006 Occurred Time/Date:

Unit(s) Affected: Unit M 2 N.System(s)

Affected: FDW RC --ode %Power Unit Status Remarks/A 100 operating cf-i-,eedwater Reactor Coolant Affected Equipment (No Equipment Affected)Location of Problem: Bldg: Column Line: Elev: Location Remarks: Method Used to Discover Problem: Final Q. A. review of work order packages.&ief Problem

Description:

0 ASME Section X1 repair/replacement NIS-2 forms and report completions for work orders mentioned in detailed problem discription.

Detail Problem

Description:

The pip is also to capture other work orders that maintenance has held pending engineering information or needed documentation required to satisfy QA or ANII requirements for final review. These work orders will be captured in actual CA I of this pip.Last Updated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS -Date: 04/10/2006 Please consider this as a category 4 pip, for tracking and trending only!This pip is being generated to identify NIS-2 report not being filed for ASME Section Xi component within 45 day time frame after start-up of refueling outage. The work was not sent to QA for final review until the mid February.Work Order 98727683 for components associated with the 2B2 RC Pump Motor. The work order has the ISI class listed as class "C" but Engineering has listed the components that were noted as corrected, as IS] Class "B".Please reference pips 06-00750 & 01083 as similar examples of this pip.Also please include work order package 98669959-01 for hanger number 2-03-0-1480A-H7A component class "B" material replacement.

Please reference pip 06-00476 written by Maintenance which was closed before this work order package could be added.Please keep pip open if possible to make other entries of work orders numbers for same discrepancy as mentioned above: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 03/20/2006 Other Units/Components/Systems/Areas Affected(YN,U):

U Oustru Plants Affected(YNU):

U 04/25t2006 13:49 Page 1 PIP No: 0-06-01571 0412512006 13:49 Page I PIP No: 0-06-01571 Problem Investigation Process Oconee Nuclear Station Immediate Corrective Actions: 0 Immnediate Corrective Action Documents

/ Work Orders: Problem Identified By: Problem Entered By: Indiv Team TRB6214WTM5506 TRB6214WTM5506 Group IWS IWS Date 03/20/2006 03/20/2006 Corrective Actions CA Seq. No: 1 IWS Closed [WS 02a E R Proposed Corrective Action: To enter applicable work packages that are received for QA final review that contain ASME Section XI components that require NIS-2 reports need to be submitted to the General Office for NRC with in the 45 day window after start up of the applicable units RFO.Originated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 03/22/2006 Approval Assigned To: WTM5506 WTM5506 IWS 03/22/2006 Assigned To: TRB6214 WTM5506 IVS 03/29/2006 Ready For Approval:

TRB6214 WTM5506 ]WS 03/29/2006 Approved By: WTM5506 WTM5506 IWS 03/29/2006 General:Outage:

N/A Mode: N/A Other Tracking Processes Type Number Text Actual Corrective Action: Priority:

13b Actual CAC: J Status: Open Due Date: 05/04/2006 Work order 98624863-10 should be added to this pip to identify another work order that was held by Mnt. and was not captured in pip 06-00476.Last Updated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 04125/2006 Work Order 98657709-Olshould be included in this pip for ASME Section Xl QA review 2 years after installation.

Last Updated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 04/1712006 Work Ordq 8f ý as statfised to Maintenance 04/13/05 and received back in QA and ANII 02/16/06.Last Updated By: TRB6214: BOWEN. THOMAS R Team: WTM5506 Group: IWS Date: 04/10/2006 The following work order package was received past the 45 day window after start up of unit 2 RFO and for submitting required NIS-2 report to*eral Office.04/2512006 13:49 Page 2 PIP No.?0-06-01571=.

Problem Investigation Process Oconee Nuclear Station I***** Work Order package 98742091 NIS-2 form was initiated by Accountable Engineer on 2/09/2006-24 days past deadline and actual work was completed at the end of November 2005 for MOD package #0D200349.

e ginated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 03/29/2006 Assigned To: TRB6214 WTM5506 Accepted By: WTM5506 WTM5506 Due Date: 05/04/2006 IWS 03/22/2006 IWS 03/29/2006 a End of the Document for PIP No: The status of this PIP is: The duration of this PIP was: 0-6-1571 Screened 2 days 04/2512006 13:49 Page 3 PIP No: 0-06-0)571 0412.512006 13:49 Page 3 PIP No: 0-06-01571

1. kD u Power Company 528 S. Church Stree Charlotte, NO 28M1.1006 2. Plant Ocone Nuclear Stafon Address 7800 Rochester HEwy. 8necaj S.C. 29672 2a. Unht 0i 0 3 0 Sbaod (Spclf S Ia. Date 9VýSheet.LQQ lUnfts-3. Work Performed By Duke Power Compy Address 52S S. CfturcbStreet, Chadotht NO 2820-1008 Type Code Symbol Stamp WA Authoftation No. WA Expration Date WA ft Work Order#3b. NSM or MM #Repair Organizaton Job #4. Identification of sni ,, -'.-,, ',, 'Crm 1:'5. (a) Appkiabl:

Constamon 1ode2?3/,7R z Adeda W. Code Cases (le M +/-of eco 3 M zfor Rep IorRep e 1989, NoAd9end2 tb192 1992 Addewda fo Claus MC and CC and their: supp;ort~se)

6. Identfilcation of Components Repaired or Replace and Replicement Components COW= I CiUu03 i iW0m4 Columns COL6 Winn7 OW=l Manfacure NMOI1camhe Yea Rep~d ASME Code Hame of Component Name of Manufacturer Board ReIoron Bi .R Stamped_ _ _ _ Number Rumba__ _ _______ _ pan t (ye" or no)A O ', e]iacndR e' .u3' []Replac~edt Yes A Repehed -No 3 ORepafod LtaRebwmen~t 0 Yes olh rl t Yes 0 Repalro No 0 [:] =nt 0 Y83 D 0 Replaced Reptacement 0 Yes Page 1 of 2 Form NIS-2 (Back)NOTE: Supp:. -iental sheets in form of lists, sketches, or drawings may be used, provided (1) sizv 8 1/2 in. x 11 .(2) information in items 1 through 6 on this report is included on each sheet, and each sheet is !mbered and the number of sheets is recorded at the top of this form.7. Descriptior.

of Mv'N d/d"4/..4>~

~,/ 4~ ~8. Test Conducted:

Hirostatic C3 Pneumatic 3 Nominal Operating Pressure [3 Other 1 Exempt 0 Pressure Pressure Pressure~psg pslg Test Temp.Test Temp.Test Temp.*F OF"F 9. Remarks (Appicable Manuta~irerz Ona Records to be aUaChed)CERTIFICATE OF COMPUANCE We certify #tat the statements made in the regort are correct and this rmair or rem-. nt conforms to the rues of the ASME Code, Secti on Xl.Type Code Symbol Stamp WA Certificate of Authorization No. NA Expiration Date WA Signed~ <_4j-zg~a.9ar't Date Owner or Owners Designee.

mTle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board. of Boiler ard Pressure Vessel Inspectors and theStataor Providence of .4I,,e7w and, employed by HsaI nd I Comnany Of Hanford Connec-flett have kSpet~d the components desered in this Ownert Rot during the penod J -40 no to -zo .' ar0d state that to tMh best of my knowledge and bWif, the Owner has performed examintions ad taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificat neither the Inspector nor his employer makes any warranty, expressed or implied;concerning te examinations and corrective measures described in this Owners Repot Furthermore, neither the Inspector nor his employer shall be labe in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection O.'e Slgn-wre -/./o Coails.ions Ndfional Board, State, Provtoomm.

amo Erzoorsememns I-Page 2 of 2 Revson 4 Problem Investigation Process Oconee Nuclear Station PI P Seriil.No:', -.. :MCtion1:,Categ;o : :LERNo Other. Re r:.0-06-01571 Problem Identification Discovered Time/Date:

14:29 03/20/2006 Unit(s) Affected: Unit Mode %Power Unit Statt 2 N/A 100 operating System(s)

Affected: FDW Feedwater RC .7 Reactor Coolant Affected Equipment (No Equipment Affected)Location of Problem: Bldg: Colunui Line: Location Remarks: Occurred Time/Date:

us Remarks Elev: Method Used to Discover Problem: Final Q. A. review of work order packages...-..Brief Problem

Description:

V he ASME Section Xl repair/replacement NIS-2 forms and report completions for work orders mentioned in detailed problem discription.

Detail Problem

Description:

'Please consider this as a category 4 pip, for tracking and trending only!This pip is being generated to identify NIS-2 report not being tiled for ASME Section XI component within 45 day time frame after start-up of refueling outage. The work was not sent to QA for final review until the mid February.Work Order 98727683 for components associated with the 2B2 RC Pump Motor. The work order has the ISI class listed as class "C" but Engineering has listed the components that were noted as corrected, as IS! Class "B".Please reference pips 06-00750 & 01083 as similar examples of this pip.Also please include work order package 98669959-01 for hanger number 2-03-0-1480A-H7A component class "B" material replacement.

Please reference pip 06-00476 written by Maintenance which was closed before this work order package could be added.Please keep pip open if possible to make other entries of work orders numbers for same discrepancy as mentioned above: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 03/20/2006 Other Units/Components/Systems/Areas Affected(YNU):

U Industry Plants Affected(YNU):

U Inmiediate Corrective Actions: Immediate Corrective Action Documents

/ Work Orders: W Indiv Team Group Date 0312012006 14:50 Page I PIP No: 0-06-01571 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI-V --Work Order Number 98701069 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date'ee Sheet 2 of2 Charlotte, NC 28201-1006 Seneca, SC 29672 2/27/06 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class 2A Reactor Building Cooling Unit (RBCU) Coils, ASME Class 2 *See Sheet 2 of 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped.(Yes I No)2A RBCU Coils Aerofin See Item (I) in Not available Not available None 1994 Corrected YES Remarks Section Corporation
7. Description of Work PM o01 the 2A RBCU Coils (tube cleaning and eddy current testing) required disassembly/reassembly of the cooler channel head. This involved disassembling the Low Pressure Service (LPSW) piping from the coils. The 5/8-inch diameter LPSW piping bolting material for the piping-to-coil flanges required replacement due to surface degradation.

Additionally, due to coil tube inlet erosion, protective stiffener sleeves were installed in the ends of selected tubes.-F 8. Test Conducted D Hydrostatic D Pneumatic D Nominal Operating Pressure E] Exempt Other pressure test Pressure PSI Test Temperature

_F Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number Sheet 98701069 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 Replaced one hundred twenty-eight (128) 5/8-inch diameter nuts and sixty-four (64) 5/8-inch diameter studs on the 2A RBCU Coil flanges (UTC # 0001074343, Stock Code 293556, and UTC # 0001074195, Stock Code # 297412)Installed stiffener sleeves in selected tube ends of the 2A coils (approximately 50 sleeves in each of the 4 coils). Framatorne part number 5055094-002, Stock Code # 576062, UTC # 0001083956.

0 O *The original NIS-2, completed on 11/16/05, incorrectly identified the ASME class of the system as Class 3, O instead of Class 2. This NIS-2 has been corrected to reflect the Class 2 (IS! Class B) designation of the LPSW§ System. (Reference PIP 0-06-01083.) -Z27/O(, CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Sign e __ _ Date 2_ _7_0 __, I Owner or (Owner's Designee, 4 ji 1 lenree21 7/(CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , and employed by HSB CT of. Hartford, Connecticut have inspected the components described in this Owner's Report during the period z -, to -- o <9 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

___________________________

Commissions

,-,-Inspector's Signature National Board, State, Province, and Endorsements Date " -'-o -

Problem Investigation Process Oconee Nuclear Station No:.::,;'i

...tiri Catei LEER No: ,'. Other Rert:.0-06-01083 3 Problem Identification Discovered Time/Date:

12:14 02/27/2006 Occurred Time/Date:

Unit(s) Affected: Unit Mode %Power Unit Status Remarks 2 N/A 100 System(s)

Affected: LPS Low Pressure Service Water RBC Reactor Building Cooling Affected Equipment Affected Equipment.'WMS',' quippdnt~ode.

ON2RBCHX000B ON2RBCHXOOOC ON2RBCHXOOOA.Uiii..Code.i>.:

.S~temCd T ode Si.. iSffi i , .2 RBC HX 000B 2 RBC HX 000C 2 RBC HX OOOA.ECo:Ede..;'

181543 181544 181542 Manufactuiei':

Location of Problem: Bldg: Column Line: Elev: Location Remarks:* ethod Used to Discover Problem: QA Review of ONS-2 EOC-21 related NIS-2's in WO packages.Brief Problem

Description:

The ASME Section XI repair/replacement NIS-2 forms completed for the 2A. 2B and 2C RBCU coil repairs incorrected identified the ISI class as C rather than B.Detail Problem

Description:

The ASME Section X! repair/replacement activity NIS-2 forms completed for the 2A, 2B and 2C RBCU repairs during Unit 2 EOC-21 outage incorrectly identified the In-service Inspection (ISI) class for the cooler as "C", whereas it should have been designated as ISI Class "B". The Reactor Building Cooling Unit Coils. as components, are constructed to ASME Section III Class 3 (Class C). However, they are contained within the Low Pressure Service Water (LPSW) piping system which is designated as Duke Class F, ISI Class B.From an ISI standpoint, the LPSW piping bolt material replacement performed under the referenced Work Orders below should have been treated as ISI Class B. since the flanged bolted connections are part of the system. The cooling coil tube plugging and sleeving repairs performed under the same Work Orders could have been treated as ISI Class C. since they are repairs to the coils themselves and not the system. Conservatively no distinction is being made and the entire repair scope is being treated as ISI Class B.

References:

OFD- 124B-2.2 OM 235-0513 -RBCU Cooling Coil outline drawing Work-Ord-r-#-9870T69Tf5f-W0 7 U--Work Order # 98704023 task 01 -2B RBCU Work Order 4 98701070 task 01 -2C RBCU The ASME Section XI report submitted to the NRC after a refueling outage is only required to include repair/replacement documentation (NIS-2's)associated with class A and B repair/replacements.

Since the Section XI documentation for the 2A, 2B and 2C RBCU Cooling Coil repairs was incorrectly designated as Class C. it was not included in the last NRC report.*e Section XI documentation (NIS-2 forms) needs to be corrected and submitted to the NRC with the next Section XI report.This is a documentation only issue.04/04/2006 15:17 Page I PIP No: 0-06-01083 Problem Investigation Process Oconee Nuclear Station his is similar to the incorrect designation of ISI Class that occurred for the 2A Letdown Cooler replacement, documented in PIP 0-06-00750.)

Originated By: JHB7315: BATI'ON, JAMES H Team: PMS7313 Group: MCE Date: 02/27/2006 Other Units/Components/Systems/Areas Affected(YNU):

U Industry Plants Affected(YNU):

U Immediate Corrective Actions: Immediate Corrective Action Documents

/ Work Orders: lndiv Team Group Date Problem Identified-By:

JHB7315 PMS7313 MCE 02/27/2006 Problem Entered By: JHB7315 PMS7313 MCE 02/27/2006 Problem EvaluationCause .uaeiscptln

' aUsingG 'Code. .7,mix 02a F3e Self-checking not applied to ensure intended Yes MCE actio Problem Evaluation From: Resp. Group: MCE Status: Closed OEDB Checked: Yes* ovided additional information in Problem Evaluation below.Last Updated By: JHB7315: BATTON, JAMES H Team: PMS7313 Group: MCE Date: 03/09/2006 PROBLEM DESCRIPTION:

The ASME Section XI repair/replacement activity NIS-2 forms completed for the 2A, 2B and 2C RBCU repairs during Unit 2 EOC-21 I outage incorrectly identified the In-service Inspection (ISI) class for the coolers as "C". whereas it should have been designated as ISI Class "B". The Reactor Building Cooling Unit Coils, as components, were constructed to ASME Section III Class 3 (Class C). However, they are contained within the Low Pressure Service Water (LPSW) piping system which is designated as Duke Class F, ISI Class B (Class 2).INAPPROPRIATE ACTION: This was a human error that occurred in completing Line 4 of the NIS-2 form. The ASME Class for the RBCU Coil repairs (bolting replacement and tube plugging/sleeving) should have been designated to be "Class 2" instead of "Class 3" to be consistent with the class designation for the LPSW System.SYSTEM EQUIPMENT PROBLEM: N/A -No system or equipment problem associated with this incident.APPARENT CAUSE: The Apparent Cause is umsufficient understanding of the Section XI program and lack of questioning attitude by the MCE VHE engineer in completing the NIS-2 form -a relatively new. infrequently performed activity for the engineer.The MCE VHE Engineer completing the NIS-2 should have had more of a questioning attitude in completing the form and should have reviewed D. 2.1.9, ASME Section XI Repair/Replacement.

On the NIS-2 form, Line 4, Identification of System, ASME Class, clearly requests the class signation for the "system", which would be Class 2 for the LPSW system in the case of the RBCU Coil flange bolting replacement and tube plugging/sleeving activities.

04/04/2006 15:17 Page 2 PIP No: 0-06.01083 Problem Investigation Process Oconee Nuclear Station discussing this further with the MCE Repair/Replacement Program engineer, in Line 4 of the NIS-2 the "ASME Class" has basically two eanings: I ) when working on a system or replacing a component in the system the ASME class is the system construction code class or ISI class.2) when repairing a component such as welding plugs in a heat exchanger tube or replacing the disc in a valve, the ASME class is determined from the construction code of the component (or if that is unknown it is the construction code for the system).Thus, there could be times in component repair in which Line 4 of the NIS-2 would NOT be the ASME Class of the system, but rather the Class to which the component was constructed. (For example, just plugging tubes in a RBCU Coil could be classified as a ASME Class 3, the construction code for the coils, whereas replacing the bolting that connects the RBCU Coil flanges to the LPSW piping flanges would need to be Class 2.consistent with the LPSW piping classification.)

For the RBCU Coil NIS-2's in question, the Line 4 "ASME Class" was unfortunately identified incorrectly by the MCE VHE engineer and needed to be corrected.

SUPPORTING INFORMATION:

Side note: This event is nearly identical to the incorrect NIS-2 form completion documented in PIP 0-06-0750 on the Unit 2A Letdown Cooler replacement.

The NIS-2 forms for the Letdown Cooler and for the RBCU coils addressed in this PIP were completed at about the same time, fall 2005. by the same MCE VHE engineer.CORRECTIVE ACTIONS: The NIS-2 forms for the 2A, 2B and 2C RBCU Coil maintenance were rewritten with the proper ISI Class identified.

The NIS-2's were re-routed to the ASME Section X! Reviewer, the ANII and QA. The rewritten NIS-2 included a footnote with a brief description of the changes made and a-. reference to this PIP for historical purposes.e.MCE VHE engineer has reviewed S.D. 2.1.9 and become more familiar with the requirements and intent of the NIS-2 form.10"o additional corrective actions are required for this PIP.OEDB Comments: OEDB search performed using Description keywords:

NIS-2.Section XI. ASME Class 2.3.No pertinent operating experience items were found.Originated By: JHB7315: BATTON, JAMES H Team: PMS7313 Group: MCE Date: 03/08/2006 Remarks Conmments:

'7]36". Indiv<Q'......Ta

.Due Date: 03/29/2006 Accepted By: PMS7313 PMS7313 MCE 03/02/2006 Assigned To: JHB7315 PMS7313 MCE 03/02/2006 Approval Assigned To:- PMS7313 PMS7313 MCE 03/09/2006 Ready For Approval:

JHB7315 PMS7313 MCE 03/09/2006 Approved By: PMS7313 PMS7313 MCE 03/13/2006 O nd of the Document for PIP No: 0-6-1083 The status of this PIP is: Closed 04/04/2006 15:17 Page 3 PIP No: 0-06-01083

-' t Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 98701070 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Datexee Sheet 2 of 2 Charlotte, NC 28201-1006 Seneca, SC 29672 2/27/2006 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Qjurch Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class 2C Reactor Building Cooling Unit (RBCU) Coils, ASME Class 2 )See Sheet 2 of 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section X1 Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)2C RBCU Coils Aerofin See Iteme(o)ii Seemark Sectin Corporation Not available Not available None 1994 Corrected YES Remarks Section Coprtn 4
  • t I I 4 4
  • I I +4 4 4 4 4 +___ ___ ___I ___ _ __ I __7. Description of Work PM on the 2C RBCU Coils (tube cleaning and eddy current testing) required disassembly/reassembly of the cooler channel head. This involved disassembling the Low Pressure Service (LPSW) piping from the coils. The 5/8-inch diameter LPSW piping bolting material for the piping-to-coil flanges required replacement due to surface degradation.

Additionally, due to coil tube inlet erosion, protective stiffener sleeves were installed in the ends of selected tubes.8. Test Conducted D Hydrostatic E Pneumatic D Nominal Operating Pressure D Exempt E Other pressure test Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 98701070 I Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o Replaced one hundred twenty-eight (128) 5/8-inch diameter nuts and sixty-four (64) 5/8-inch diameter studs on the 2C RBCU Coil flanges (UTC # 0001074343, Stock Code 293556, and UTC # 0001074195, Stock Code # 297412)Installed stiffener sleeves in selected tube ends of the 2C coils (approximately 50 sleeves in each of the 4 coils). Framatome part number 5055094-002, Stock Code # 576062, UTC # 0001083956.

O .The original NIS-2, completed on 11/16/05, incorrectly identified the ASME class of the system as Class 3, o instead of Class 2. This NIS-2 has been corrected to reflect the Class 2 (ISI Class B) designation of the LPSW 0 System. (Reference PIP 0-06-01083.)

=A6&UM- ZI Z77O(-0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed ___ __ __ __/__ _ nee__ Date .2127106t/,' Owvner or O~~ner~s Designee.

Title .J F CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the" State or Province of .0,,e' and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period /- 5-o to c/-&//- ,, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions o.A Inspector's Signature National Board, State, Province, and Endorsements Date __ _ _ _ _ _

Problem Investigation Process Oconee Nuclear Station 0-06-01083 Action Category:<,:" 'LEP,.No .-i '. *therReport:

0 3 Problem Identification Discovered Time/Date:

12:14 02/27/2006 Occurred Time/Date:

Unit(s) Affected: Unit Mode %Power Unit Status Remarks 2 N/A 100 System(s)

Affected: LPS -Low Pressure Service Water RBC -Reactor Building Cooling Affected Eniuipment

.:WMS<Eiiilnient S'Uit tCode'".:-

,..syemCode., u:.T d.od suffix".ON2RBCHXOOOB 2 RBC HX 000B ON2RBCHXOOOC 2 RBC HX O00C ON2RBCHXOOOA 2 RBC HX OOOA 181543 2 181544 181542 Location of Problem: Bldg: Column Line: Elev: Location Remarks: Olethod Used to Discover Problem: QA Review of ONS-2 EOC-21 related NIS-2's in WO packages.Brief Problem

Description:

The ASME Section Xl repair/replacement NIS-2 forms completed for the 2A. 2B and 2C RBCU coil repairs incorrected identified the ISI class as C rather than B.Detail Problem

Description:

The ASME Section XI repair/replacement activity NIS-2 forms completed for the 2A, 2B and 2C RBCU repairs during Unit 2 EOC-21 outage incorrectly identified the In-service Inspection (ISI) class for the cooler as "C", whereas it should have been designated as ISI Class "B". The Reactor Building Cooling Unit Coils, as components, are constructed to ASME Section III Class 3 (Class C). However, they are contained within the Low Pressure Service Water (LPSW) piping system which is designated as Duke Class F. ISI Class B.From an ISI standpoint, the LPSW piping bolt material replacement performed under the referenced Work Orders below should have been treated as ISI Class B, since the flanged bolted connections are part of the system. The cooling coil tube plugging and sleeving repairs performed under the same Work Orders could have been treated as ISI Class C, since they are repairs to the coils themselves and not the system. Conservatively no distinction is being made and the entire repair scope is being treated as ISI Class B.

References:

OFD- 124B-2.2 OM 235-0513 -RBCU Cooling Coil outline drawing Work Order # 98701069 task 01 -2A RBCU Work Order # 98704023 task 01 -2B RBCU The ASME Section Xl report submitted to the NRC after a refueling outage is only required to include repair/replacement documentation (NIS-2's)associated with class A and B repair/replacements.

Since the Section XI documentation for the 2A, 2B and 2C RBCU Cooling Coil repairs was incorrectly designated as Class C, it was not included in the last NRC report.Whe Section XI documentation (NIS-2 forms) needs to be corrected and submitted to the NRC with the next Section XI report.This is a documentation only issue.04/04/2006 15:17 Page I PIP No: 0-61iýý01083_

Problem Investigation Process Oconee Nuclear Station his is similar to the incorrect designation of ISI Class that occurred for the 2A Letdown Cooler replacement, documented in PIP 0-06-00750.)

Originated By: JHB7315: BATTON, JAMES H Team: PMS7313 Group: MCE Date: 02/27/2006 Other Units/Components/Systems/Areas Affected(YNU):

U Industry Plants Affected(Y,NU):

U Immediate Corrective Actions: Immediate Corrective Action Documents

/ Work Orders: Problem IdentifiedBy:

Problem Entered By:-Indiv Team JHB7315 PMS7313 JHB7315 PMS7313 Group MCE MCE Date 02/27/2006 02/27/2006 Problem Evaluation.vent., CauseDescinption 2 C-ausingGroups v " ' Code ". 1.. ." 'O2a F3e Self-checking not applied to ensure intended Yes MCE actio Problem Evaluation From: Resp. Group: MCE Status: Closed OEDB Checked: Yes.rovided additional information in Problem Evaluation below.Last Updated By: JHB7315: BATTON, JAMES H Team: PMS7313 Group: MCE Date: 03/09/2006 PROBLEM DESCRIPTION:

The ASME Section XI repair/replacement activity NIS-2 forms completed for the 2A, 2B and 2C RBCU repairs during Unit 2 EOC-2 I outage incorrectly identified the In-service Inspection (ISI) class for the coolers as "C", whereas it should have been designated as ISI Class "B". The Reactor Building Cooling Unit Coils, as components, were constructed to ASME Section III Class 3 (Class C). However, they are contained within the Low Pressure Service Water (LPSW) piping system which is designated as Duke Class F. ISI Class B (Class 2).INAPPROPRIATE ACTION: This was a human error that occurred in completing Line 4 of the NIS-2 form. The ASME Class for the RBCU Coil repairs (bolting replacement and tube plugging/sleeving) should have been designated to be "Class 2" instead of "Class 3" to be consistent with the class designation for the LPSW System.SYSTEM EQUIPMENT PROBLEM: N/A -No system or equipment problem associated with this incident.APPARENT CAUSE: The Apparent Cause is unsufficient understanding of the Section XI program and lack of questioning attitude by the MCE VHE engineer in completing the NIS-2 form -a relatively new, infrequently performed activity for the engineer.The MCE VHE Engineer completing the NIS-2 should have had more of a questioning attitude in completing the form and should have reviewed jj D. 2.1.9, ASME Section XI Repair/Replacement.

On the NIS-2 form, Line 4, Identification of System, ASME Class, clearly requests the class signation for the "system", which would be Class 2 for the LPSW system in the case of the RBCU Coil flange bolting replacement and tube plugging/sleeving activities.

04/04/2006 15:17 Page 2 PIP No: 0-06-01083 0410412006 15:17 Page 2 PIP No: 0-06-01083 Problem Investigation Process Oconee Nuclear Station discussing this further with the MCE Repair/Replacement Program engineer, in Line 4 of the NIS-2 the "ASME Class" has basically two Wean ings: I) when working on a system or replacing a component in the system the ASME class is the system construction code class or ISI class.2) when repairing a component such as welding plugs in a heat exchanger tube or replacing the disc in a valve, the ASME class is determined from the construction code of the component (or if that is unknown it is the construction code for the system).Thus. there could be times in component repair in which Line 4 of the NIS-2 would NOT be the ASME Class of the system, but rather the Class to which the component was constructed. (For example, just plugging tubes in a RBCU Coil could be classified as a ASME Class 3, the construction code for the coils, whereas replacing the bolting that connects the RBCU Coil flanges to the LPSW piping flanges would need to be Class 2.consistent with the LPSW piping classification.)

For the RBCU Coil NIS-2's in question, the Line 4 "ASME Class" was unfortunately identified incorrectly by the MCE VHE engineer and needed to be corrected.

-SUPPORTING INFORMATION:

Side note: This event is nearly identical to the incorrect NIS-2 form completion documented in PIP 0-06-0750 on the Unit 2A Letdown Cooler replacement.

The NIS-2 forms for the Letdown Cooler and for the RBCU coils addressed in this PIP were completed at about the same time, fall 2005, by the same MCE VHE engineer.CORRECTIVE ACTIONS: The NIS-2 forms for the 2A, 2B and 2C RBCU Coil maintenance were rewritten with the proper IS Class identified.

The NIS-2's were re-routed to the ASME Section XI Reviewer, the ANII and QA. The rewritten NIS-2 included a footnote with a brief description of the changes made and a reference to this PIP for historical purposes.O he MCE VHE engineer has reviewed S.D. 2. 1.9 and become more familiar with the requirements and intent of the NIS-2 form.additional corrective actions are required for this PIP.OEDB Conmments:

OEDB search performed using Description keywords:

NIS-2,Section XI. ASME Class 2, 3.No pertinent operating experience items were found.Originated By: JHB7315: BATTON, JAMES H Team: PMS7313 Group: MCE Date: 03/08/2006 Remarks Comments: Signature Type JjdvTeahl".Groulp

'~ D Due Date: 03/29/2006 Accepted By: PMS7313 PMS7313 MCE 03/02/2006 Assigned To: JHB7315 PMS7313 MCE 03/02/2006 Assigned To:- PMS7313 PMS7313 MCE 03/09/2006 Ready For Approval:

JHB7315 PMS7313 MCE 03/09/2006 Approved By: PMS7313 PMS7313 MCE 03/13/2006

  • nd of the Document for PIP No: 0-6-1083 The status of this PIP is: Closed 0410412006 15:17 Page 3 PIP No: 0-06-01083 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 98704023 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy DateSee Sheet 2 of 2 Charlotte, NC 28201-1006 Seneca, SC 29672 2/27/2006 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 2820 1-1006 Expiration Date Not Applicable
4. Identification of System, ASME Class 2B Reactor Building Cooling Unit (RBCU) Coils, ASME Class 2 kSee Sheet 2 of 2 5.(a) Applicable Construction Code: USAS B331.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Component Name of Manufacturer Manufacturer Serial Number National Board No.Other Identification Year Built Corrected, Removed, or Installed ASME Code Stamped (Yes / No)2B RBCU Coils See Item (I) in Remarks Section Aerofin Corporation Not available Not available None 1994 Corrected YES 1- 1 1 1 1- t 4- I 1- I 1- *_ *1 ____________

____________

I ___________

I _____________

__________

_____7. Description of Work PM onl the 2B RBCU Coils (tube cleaning and eddy current testing) required disassembly/reassembly of the cooler channel head. This involved disassembling the Low Pressure Service (LPSW) piping from the coils. The 5/8-inch diameter LPSW piping bolting material for the piping-to-coil flanges required replacement due to surface degradation.

Additionally, due to coil tube inlet erosion, protective stiffener sleeves were installed in the ends of selected tubes.8. Test Conducted Hydrostatic E Pneumatic EI Nominal Operating Pressure Eli Exempt Z Other pressure test Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASMIE Code Section XI Work Order Number 1 98704023 I Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o Replaced one hundred twenty-eight (128) 5/8-inch diameter nuts and sixty-four (64) 5/8-inch diameter studs on the 2B RBCU Coil flanges (UTC # 0001074343, Stock Code 293556, and UTC # 0001078280, Stock Code # 297412)Installed stiffener sleeves in selected tube ends of the 2B coils (approximately 50 sleeves in each of the 4 coils). Framatome part number 5055094-002, Stock Code # 576062, UTC # 0001083956.

O )(The original NIS-2, completed on 11/16/05, incorrectly identified the ASME class of the system as Class 3, O instead of Class 2. This NIS-2 has been corrected to reflect the Class 2 (ISI Class B) designation of the LPSW O System. (Reference PIP 0-06-01083.)

t,_/( 7jt Z/Z7/c(,, CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date *Not Applicable Signed Desgne er q ,i e-ew Date /_/27/04 Owneor 0(kner's DsgeTitle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period /-,Y_- -o6- to 15'-/,/-o. , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

-

Signature Date -'-'--c-6 Commissions ,u(L Jl'-! / Az -National Board, State, Province, and Endorsements 6 Problem Investigation Process Oconee Nuclear Station Pieial .. yAction Category:

'ERN: , Otser~R~t'~

10-06-01083 3 Problem Identiflcation Discovered Time/Date:

Unit(s) Affected: Unit Mode 2 N/A System(s)

Affected: LPS RBC 12:14 02/27/2006 Occurred TimelDate:

%Power Unit Status Remarks 100 Low Pressure Service Water Reactor Building Cooling Affected Equipmentuipment Code :. :jit Code? .,S eiiode -'o .T T Co : Suffi` "'ECde -Manufactiirei,:, ON2RBCHXOOOB 2 RBC HX 0OOB 181543 ON2RBCHXOOOC 2 RBC HX 000C 181544 ON2RBCHXOOOA 2 RBC HX OOOA 181542 Location of Problem: Bldg: Column Line: Elev: Location Remarks:*ethod Used to Discover Problem: QA Review of ONS-2 EOC-21 related NIS-2's in WO packages.Brief Problem

Description:

The ASME Section XI repair/replacement NIS-2 forms completed for the 2A, 2B and 2C RBCU coil repairs incorrected identified the ISI class as C rather than B.Detail Problem

Description:

The ASME Section XI repair/replacement activity NIS-2 forms completed for the 2A, 2B and 2C RBCU repairs during Unit 2 EOC-21 outage incorrectly identified the In-service Inspection (ISI) class for the cooler as "C", whereas it should have been designated as ISI Class "B". The Reactor Building Cooling Unit Coils, as components, are constructed to ASME Section III Class 3 (Class C). However, they are contained within the Low Pressure Service Water (LPSW) piping system which is designated as Duke Class F, ISI Class B.From an ISI standpoint, the LPSW piping bolt material replacement performed under the referenced Work Orders below should have been treated as ISI Class B, since the flanged bolted connections are part of the system. The cooling coil tube plugging and sleeving repairs performed under the same Work Orders could have been treated as ISI Class C. since they are repairs to the coils themselves and not the system. Conservatively no distinction is being made and the entire repair scope is being treated as ISI Class B.

References:

OFD- 124B-2.2 OM 235-0513 -RBCU Cooling Coil outline drawing Work Order # 98701069 task 01 -2A RBCU'o k-Orde r-#-98 70023--task-._._-2B-R-B CEO=Work Order # 98701070 Lask 01 -2C RBCU The ASME Section XI report submitted to the NRC after a refueling outage is only required to include repair/replacement documentation (NIS-2's)associated with class A and B repair/replacements.

Since the Section Xl documentation for the 2A, 2B and 2C RBCU Cooling Coil repairs was incorrectly designated as Class C, it was not included in the last NRC report.e Section XI documentation (NIS-2 forms) needs to be corrected and submitted to the NRC with the next Section XI report.10his is a documentation only issue.0410412006 15:16 Page I PIP No: 0-06-01083 Lliý Problem Investigation Process Oconee Nuclear Station* his is similar to the incorrect designation of IS! Class that occurred for the 2A Letdown Cooler replacement, documented in PIP 0-06-00750.)

Originated By: JHB7315: BATI'ON, JAMES H Team: PMS7313 Group: MCE Date: 02/27/2006 Other Units/Components/Systems/Areas Affected(YNU):

U Industry Plants Affected(Y.N,U):

U Immediate Corrective Actions: Immediate Corrective Action Documents

/ Work Orders: Problem Identified-By:

Problem Entered By:-lndiv Team JHB7315 PMS7313 JHB7315 PMS7313 Group MCE MCE Date 02/27/2006 02/27/2006 Problem Evaluation Event .Cause

.:. ,' " .Primary Causing Groups 02a F3e Self-checking not applied to ensure intended Yes MCE actio Problem Evaluation From: Resp. Group: MCE Sta erovided additional information in Problem Evaluation below.tus: Closed OEDB Checked: Yes Last Updated By: JHB7315: BATTON, JAMES H Team: PMS7313 Group: MCE Date: 03/09/2006 PROBLEM DESCRIPTION:

The ASME Section XI repair/replacement activity NIS-2 forms completed for the 2A, 2B and 2C RBCU repairs during Unit 2 EOC-21 outage incorrectly identified the In-service Inspection (ISI) class for the coolers as "C". whereas it should have been designated as ISI Class "B". The Reactor Building Cooling Unit Coils. as components, were constructed to ASME Section III Class 3 (Class C). However, they are contained within the Low Pressure Service Water (LPSW) piping system which is designated as Duke Class F. ISI Class B (Class 2).INAPPROPRIATE ACTION: This was a human error that occurred in completing Line 4 of the NIS-2 form. The ASME Class for the RBCU Coil repairs (bolting replacement and tube plugging/sleeving) should have been designated to be "Class 2" instead of "Class 3" to be consistent with the class designation for the LPSW System.SYSTEM EQUIPMENT PROBLEM: N/A -No system or equipment problem associated with this incident.APPARENT CAUSE: The Apparent Cause is unsufficient understanding of the Section XI program and lack of questioning attitude by the MCE VHE engineer in completing the NIS-2 form -a relatively new, infrequently performed activity for the engineer.The MCE VHE Engineer completing the NIS-2 should have had more of a questioning attitude in completing the form and should have reviewed2.1.9, ASME Section XI Repair/Replacement.

On the NIS-2 form, Line 4, Identification of System, ASME Class, clearly requests the class si gnation for the "system", which would be Class 2 for the LPSW system in the case of the RBCU Coil flange bolting replacement and tube plugging/sleeving activities.

04/04/2006 15:16 Page 2 PIP No: 0-06-01083 PIP No: 0-06-01083 0410412006 15:16 Page 2 Problem Investigation Process Oconee Nuclear Station~ discussing this further with the MCE Repair/Replacement Program engineer, in Line 4 o1 the NIS-2 the "ASME Class" has basically two Weanings: 1) when working on a system or replacing a component in the system the ASME class is the system construction code class or ISI class.2) when repairing a component such as welding plugs in a heat exchanger tube or replacing the disc in a valve, the ASME class is determined from the construction code of the component (or if that is unknown it is the construction code for the system).Thus, there could be times in component repair in which Line 4 of the NIS-2 would NOT be the ASME Class of the system, but rather the Class to which the component was constructed. (For example, just plugging tubes in a RBCU Coil could be classified as a ASME Class 3, the construction code for the coils, whereas replacing the bolting that connects the RBCU Coil flanges to the LPSW piping flanges would need to be Class 2, consistent with the LPSW piping classification.)

For the RBCU Coil NIS-2's in question, the Line 4 "ASME Class" was unfortunately identified incorrectly by the MCE VHE engineer and needed to be corrected.

SUPPORTING INFORMATION:

Side note: This event is nearly identical to the incorrect NIS-2 form completion documented in PIP 0-06-0750 on the Unit 2A Letdown Cooler replacement.

The NIS-2 forms for the Letdown Cooler and for the RBCU coils addressed in this PIP were completed at about the same time, fall 2005, by the same MCE VHE engineer.CORRECTIVE ACTIONS: The NIS-2 forms for the 2A, 2B and 2C RBCU Coil maintenance were rewritten with the proper ISI Class identified.

The NIS-2's were re-routed to the ASME Section XI Reviewer, the ANII and QA. The rewritten NIS-2 included a footnote with a brief description of the changes made and a reference to this PIP for historical purposes.The MCE VHE engineer has reviewed S.D. 2.1.9 and become more familiar with the requirements and intent of the NIS-2 form.So additional corrective actions are required for this PIP.OEDB Comments: OEDB search performed using Description keywords:

NIS-2,Section XI. ASME Class 2, 3.No pertinent operating experience items were found.Originated By: JHB7315: BATTON, JAMES H Team: PMS7313 Group: MCE Date: 03/08/2006 Remarks Conmments:

Tyjpi6 div .','-. Te, Grup '.DatDe Due Date: 03/29/2006 Accepted By: PMS7313 PMS7313 MCE 03/02/2006 Assigned To: JHB7315 PMS7313 MCE 03/02/2006 Approval Assigned To:- PMS7313 PMS7313 MCE 03/09/2006 Ready For Approval:

JHB7315 PMS7313 MCE 03/09/2006 Approved By: PMS7313 PMS7313 MCE 03/13/2006 O nd of the Document for PIP No: 0-6-1083 The status of this PIP is: Closed 04/04/2006 15:16 Pave 3 PIP No: 0ll-f0l6008

---0--

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI U Work Order Number 98727683-10 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -Z 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 11/9/2005 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class LPSW, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)2RC MR 0004PUM Westinghouse 2S-76P 1 na na 1970 Corrected NO 7. Description of Work.Test Conducted FI Hydrostatic L Pneumatic L Nominal Operating Pressure LI Exempt [EOther-, , ', Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 98727683-10 Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)I o Install new threaded rod/bolts on the LPSW flanges as follows:"'

Threaded Rod, SC# 297412, 5/8-11, SA193 B7, UTC# 1083362..Hex Nut, SC# 131549, 5/8-11, UNC-2B, SA563 Gr A, UTC# 1074008\Threaded Rod, SC# 297413, 3/4-10, UNC-2A, SA 193 GR B7, UTC# 1077723 ,Hex Nut, SC# 131729, 3/4-10, UNC-2B, SA 194 GR 7\Threaded Rod, SC#29741 1, 1/2-13 UNC-2A, SA 193 Gr B7, UTC# 1079049'Hex Nut, SC# 131512, 1/2-13 UNC-2B, SA563 GrC, UTC# 989650 0 C A.0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authoriztion Number Not Applicable Expiration Date Not Applicable Signed Alar or&A' Date I1 /1 7/o owner or Owner's Designee, Title If CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ,,zT"X4'zC,,2,sz and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period f- 2_-, to Z-ZL-,'6 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, Concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the nspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Inspector's Signature Commissions

/ WA6L National Board, State, Province, and Endorsements Problem Investigation Process Oconee Nuclear Station PIP Serial No: ActionCat egoi: LER No;..0-06-01571 4OteRpo: Problem Identification Discovered Time/Date:

14:29 03/20/2006 Occurred T"ime/Date:

Unit(s) Affected: Unit Mode %Power Unit Status Remarks 2 N/A 100 operating System(s)

Affected: FDW Feedwater RC Reactor Coolant Affected Equipment (No Equipment Affected)Location of Problem: Bldg: Colunm Line: Elev: Location Remarks: Method Used to Discover Problem: Final Q. A. review of work order packages Brief Problem

Description:

Whe ASM E Section XI repair/replacement NIS-2 forms and report completions for work orders mentioned in detailed problem discription.

Detail Problem

Description:

The pip is also to capture other work orders that maintenance has held pending engineering information or needed documentation required to satisfy QA or ANII requirements for final review. These work orders will be captured in actual CA I of this pip.Last Updated By: TRB62 14: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 04/10/2006 Please consider this as a category 4 pip, for tracking and trending only!This pip is being generated to identify NIS-2 report not being filed for ASME Section XI component within 45 day time frame after start-Lip of refueling outage. The work was not sent to QA for final review until the mid February.WjkrOrder_98727683-ffr components associated with the 2B2 RC Pump Motor. The work order has the ISI class listed as class "C" but Engineering has listed the components that were noted as corrected, as ISI Class "B".Please reference pips 06-00750 & 01083 as similar examples of this pip.Also please include work order package 98669959-01 for hanger number 2-03-0-14SOA-H7A component class "B" material replacement.

Please reference pip 06-00476 written by Maintenance which was closed before this work order package could be added.Please keep pip open if possible to make other entries of work orders numbers for same discrepancy as mentioned above: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 03/20/2006 Other Units/Components/Systems/Areas Affected(YN,U):

U*ndustrv Plants Affected(Y,N,U):

U 0411012006 10:40 Page I PIP No: 0-06-01571 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 98536821 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 3/1/2006 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charl.-tte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Emergency Feedwater, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)Hanger 2-03A DPC None None None 1974 Corrected NO O-1439A-R61 (1)7. Description of Work Repair weld quality. During an inspection the quality of one of the welds was determined not to be up to current standards.

Ak 8. Test Conducted D Hydrostatic 1 Pneumatic 1 Nominal Operating Pressure [ Exempt D Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASMNE Code Section X1.Remarks (Applicable Manufacturer's Data Reports to be attached)o No material installed except weld metal Filler Material ER705-2. UTC # 1052667 Filler Material ER7018, UTC # 1059149 0 C 0§0 S CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Autho Zization Number Not Applicable Expiration Date Not Applicable Signed Senior Engineer Date 31112006 Owner or s Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of j/ ,: ,o and employed by HSB CT of Hartford, Connecticut have inspected the components describe(d in this Owner's Report during the period 1',- to V-,o .-oG, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions

--,/6,<19Y Date'---Inspector's Signature National Board, State, Province, and Endorsements Z-d 2I,0t1-999-t;192 8t~t~99-t99SNO-OO/NO dgi,:C0 LO LI, Inr Problem Investigation Process Oconee Nuclear Station.......,,.,.A. ction C3ate or ..... LER .No, : .OtherRel rt'. ". ,:....!QO0600476 3 _Problem Identification Discovered Time/Date:

10:42 01/27/2006 Occurred Time/Date:

Unit(s) Affected: Unit Mode %Power Unit Status Remarks N/A N/A 100 N/A System(s)

Affected: N/A -Not Related to a Unit"s System.Affected Equipmeit (No Equipment Affected)Location of Problem: Bldg: Column Line: Elev: Location Remarks: Method Used to Discover Problem: Brief Problem

Description:

Work Packages not processed by Mechanical Services teams in a timely manner.*ail Problem

Description:

98656697-0.1

.98536821:01 98586396-01 98657709-01 98671891-01 Last Updated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 02/02/2006 This work orders 98674209-01, 98674628-01, 98641556-02.

98634132-01, 98656284-01 should be included in this PIP.Last Updated By: TRB6214: BOWEN, THOMAS R Team: WTM5506 Group: IWS Date: 01/30/2006 It was recently discovered that a population of old work orders and their associated packages had not been turned in to QC for final review. As a result, some upgraded Section XI components had not had their NIS-2 documentation completed as required.

In many cases, packages are held when the technical work is completed so that support tasks for scaffold removal, coating, grouting, or similar tasks can complete.

When that occurs and the work order in WMS is completed, the paper packages are sometimes delayed in getting back to QC/Engineering for final evaluation.

In the case of this population of work orders, these packages have been significantly delayed, leading to a failure in the timely completion of NIS-2 paperwork and violation of Maintenance Directive MD 7.5.10. The work orders affected are ,9.85368-2*01:?98625986-09.

98555377-10, 98624861-22, 98671891-01, 9865669'7-01, 98657709-01, 98586399-01, 98586396-01, and 98656689-01.

The supervisor who had possession of these packages has now processed all of them and turned them in. He has been counseled on the timely completion and submission of paperwork following the completion of the work. A process will be put in place this week to ensure that all work packages are monitored on a weekly basis to ensure that none are retained after field work completes.

Ogn this PIP to ONS Maintenance Mechanical Services for documentation of further corrective actions.0412.512006 05:18 Page I PIP No: 0-0&00476ý:ý

" Problem Investigation Process Oconee Nuclear Station riginated By: PJC6846: CULBERTSON, PHILIP J Team: CEC0320 Group: MNT Date: 01/27/2006 Other Units/Components/Systems1Areas Affected(Y,NU):

U Industry Plants Affected(Y,N.U):

U Immediate Corrective Actions: Immediate Corrective Action Documents

/ Work Orders: lndiv Team Problem Identified By: "PJC6846 CEC0320 MNT Problem Entered By: PJC6846 CEC0320 MNT Group Date 01/27/2006 01/27/2006 End of the Document for PIP No: The status of this PIP is: The duration of this PIP was: 0 04/25/2006 05:18 0-6-476 Closed 39 days Page 2 PIP No: O-O6~00476~

Page 2 PIP No: 0-06-00476ý=

Form NIS-2 Owner's Report for Repair/Replacement Activities Z-SV 1066A As required by the provisions of the ASME Code Section Xl Work Order Numbe Sheet I s'0 1 01621909-17 Pagel of, , 1. Owner Duke Power Company 2. Plant Oconee Nuclear Station unit 526 South Church Street 7800 Rochestor Hwy I Date Charlotte, NC 28201-1006 Seneca, SC 28672 5/21/2007 3. Work Performed By Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of Systems, ASME Class Reactor Coolant , ASME Class 1 5-(a) Applicable Construction Cod USAS B31.7 1967: Edition, No Addenda No Code Case (b) Applicable Edition Section XI Utilized For RJR Activity 1998: Edition, 2000 Addenda (c) Applicable Section Xi Codes Cases(s) None 6. Identification of Coimponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)(1) Size 5 rear bracket assembly w/ Grinnell N/A UNK N/A UNK , Removed No ears removed.2) 3" x 3" x 1-0" plate. N/A N/A UNK N/A UNK Removed No (3) 1 1/2" x 11" x 11" plate. N/A N/A. UNK N/A UNK Removed No (4) 3" x 7 1/2" x 1-2 5/8" plate. N/A N/A UNK N/A UNK Removed No (5) Size 5 rear braclket assembly.

Grinnell N/A UNK N/A UNK Removed No (6) Glastic isolation plate. N/A N/A UNK N/A UNK Removed No (7) Size 5, Fig. 201 ext. piece Anvil n UNK UTC UNK Installed No 1845586 1 1/2" x 11" x 11" plate (item #20) N/A N/A UNK UTC UNK Installed No 1823969 3" x 3" x 1-0" plate (item #11) N/A N/A UNK UTC UNK Installed No 1067870'x 7 1/2" x 1-2 5/8" plate (item # 1) N/A N/A UNK UTC UNK Installed No 1846011 y'r Form NIS-2 Owner's Report for Repair/Replacement Activities

' required by the provisions of the ASME Code Section Xl Work Order Numbe 01621909 -17 Sheet 3 Page 2 of/1. Owner Duke Power Company 2. Plant Oconee Nuclear Station unit I 2 526 South Church Street 7800 Rochestor Hwy Date Charlotte, NC 28201-1006 Seneca, SC 28672 5/21/2007 3. Work Performed By Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of Systems, ASME Class Reactor Coolant , ASME Class 1 5.(a) Applicable Construction Cod USAS B31.7 1967: Edition, No Addenda No Coda Case (b) Applicable Edition Section XI Utilized For RIR Activity 1998: Edition, 2000 Addenda (c) Applicable Section Xl Codes Cases(s) None 6. Identification of Coimponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)Glastic isolation plate (item #18) N/A N/A UNK UTC LUNK Installed No 1090272 ize 5 rear bracket assembly Anvil N/A UNK UTC UNK Installed No 1833955 Size 5 rear bracket assembly Anvil N/A UNK UTC UNK Installed No 1824112 7 Description of Work S/R was redesigned per OE200140.8. Test Conducted F] Hydrostatic P] Pnuematic L] Nominal Operating Pressure El Excempt [ Other Visual Pressure PSI Test Temperature Deg. F Form NIS-2 Owner's Report for Repair/Replacement Activities required by the provisions of the ASME Code Section Xl Work OrderN01621909-17 Sheet Page/of/ 7. Remarks (Applicable Manufactuenrs Data Reports to be attached)(1) New item installed in lieu of existing.(2) New item installed in lieu of existing.(3) New item installed in lieu of existing.(4) New item installed in lieu of existing.

A single 6" bar piece instead of 2- 3" pieces was installed.

(5) New item installed in lieu of existing.(6) New item installed in lieu of existing.(7) Installed new extension piece CERTIFICATION OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl Type Code Symbol Stamp Not Applicable Certificate of Authrization Number Not Applicable

.. Expiration Date Not Applicable Signed ________________

D Date __ 11 ____7 Owner or Owner's Designee, Title CERTIFICATION OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and State or province of .r,, 6,,e ,,,,',,p and employed by HSB CT of Hartford, Connecticut have inspected the components described in the Owner's Report during the period ? to 7-.I'- o p , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the inspector nor his employer make any warrenty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind rising from or connected with this inspection.

Inspector's Signature National Board, State, Province, and Endorsements Date 7 Form NIS-2 Owner's Report for Repair/Replacement Activities 51r 7,4 -D-0O- o, V As required by the provisions of the ASME Code Section XI Work Order Numbe Sheeto 17 1 01621909 -18 Page 1 of/, 1. Owner Duke Power Company 2. Plant Oconee Nuclear Station unit I I 2 526 South Church Street 7800 Rochestor Hwy Date Charlotte, NC 28201-1006 Seneca, SC 28672 1 5/21/2007 3. Work Performed By Type Code Symbol Stamp I Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of Systems, ASME Class Reactor Coolant , ASME Class 1 6.(a) Applicable Construction Cod USAS B31.7 1967: Edition, No Addenda No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 1998: Edition, 200Q Addenda (c) Applicable Section X1 Codes Cases(s) None 6. Identification of Coimponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)(1) Insulating tube for 1" Dia. Bolt N/A N/A UNK N/A UNK Removed No (2) 1" Dia. Bolts N/A N/A UNK N/A UNK Removed No (3) 1" Dia. Nuts N/A N/A UNK N/A UNK Removed No (4) 6" Dia. Sch 160 pipe N/A N/A UNK N/A UNK Removed No (5) 1 1/2" plate Grinnell N/A UNK N/A UNK Removed No (6) Size 5 rear bracket assemblies N/A N/A UNK N/A UNK Removed No (2)(7) Glastic isolation plate N/A N/A UNK N/A UNK Removed No 1 1/2" plate N/A N/A UNK UTC UNK Installed No 1823969-1" Dia. Nuts N/A N/A UNK UTC UNK Installed No S1079050 Dia. threaded rod N/A N/A UNK UTC UNK Installed No 1846535 I ~

Form NIS-2 Owner's Report for Repair/Replacement Activities required by the provisions of the ASME Code Section Xl Work Order Numbs 01621909 -18 Sheet Page 2 of/1. Owner Duke Power Company 2. Plant Oconee Nuclear Station Unit 2 526 South Church Street 7800 Rochestor Hwy Date Charlotte, NC 28201-1006 Seneca, SC 28672 5/21/2007 3. Work Performed By Type Code Symbol Stamp I Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of Systems, ASME Class Reactor Coolant , ASME Class 1 5.(a) Applicable Construction Cod USAS B31.7 1967: Edition, No Addenda No Code Case (b) Applicable Edition Section Xi Utilized For R/R Activity 1998: Edition, 2000 Addenda (c) Applicable Section Xl Codes Cases(s) None 6. Identification of Coimponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)3/4" plate N/A N/A UNK UTC UNK Installed No 1091175'Dia. Sch 160 pipe N/A N/A UNK UTC UNK Installed No 0877294 ,'Glastic isolation plate N/A N/A UNK UTC UNK Installed No 1090272 Size 5 rear bracket assembly Anvil N/A UNK UTC UNK Installed No 1824112 Size 5 rear bracket assembly Anvil N/A UNK UTC UNK Installed No 1833955 Size 5, Fig. 201 extension piece Anvil N/A UNK UTC / UNK Installed No 1845586 7. Description of Work S/R was redesigned per OE200140.8. Test Conducted] Hydrostatic D Pnuematic

[ Nominal Operating Pressure D Excempt [ Other Visual Pressure PSI Test Temperature Deg. F Form NIS-2 Owner's Report for Repair/Replacement Activities As required by the provisions of the ASME Code Section XI work Order Numbe Sheet a 3 01621909 18 Page/of'7. Remarks (Applicable Manufactueres Data Reports to be attached)(1) New item installed in lieu of existing.(2) New item installed in lieu of existing.(3) New item installed in lieu of existing.(4) New item installed in lieu of existing.(5) New item installed in lieu of existing.(6) New item installed in lieu of existing.(7) New item installed in lieu of existing.CERTIFICATION OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI Type Code Symbol Stamp Not Applicable Certificate of Aytherization Number Not Applicable Expiration Date Not Applicable Signed _________________

D ate ________Owner or Owner's Designee.

Title CERTIFICATION OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and State or province of oiA. -.,"' _tt .-and employed by HSB CT of Hartford, Connecticut have inspected the components described in the Owner's Report during the period / 3-lo 7 to ""e 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the inspector nor his employer make any warrenty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind rising from or connected with this inspection.

~~~~Commision(s) .,, ::I_ lnsp-ci gature~ommi on National Board, State, Province, and Endorsements Date Form NIS-2 Owner's Report for Repair/Replacement Activities s required by the provisions of the ASME Code Section XI Work Order Numbe 01621909)- 19 jSeet Page 1 ofA ,11 1. Owner Duke Power Company 526 South Church Street Charlotte, NC 28201-1006

2. Plant Oconee Nuclear Station 7800 Rochestor Hwy Seneca, SC 28672 Unit 2 Date 5/21/2007/- t -3. Work Performed By Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable
4. Identification of Systems, ASME Class Reactor Coolant , ASME Class 1 5.(a) Applicable Construction Cod USAS B31.7 1967: Edition, No Addenda No Code Case (b) Applicable Edition Section Xi Utilized For R/R Activity 1998: Edition 2000 Addenda (c) Applicable Section Xl Codes Cases(s) None 6. Identification of Coimponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)(1) Glastic isolation plate. N/A N/A UNK N/A UNK Removed Noý2) Size 5 rear bracket assemblies Grinnell N/A UNK N/A UNK Removed No (2).(3) Size 5 rear bracket assembly w/ N/A N/A UNK N/A UNK Removed No ears removed.(4) #3 Fig. 211 Sway Strut N/A N/A UNK N/A UNK Removed No Assembly.(5) 6" Dia. Sch 160 pipe. N/A N/A UNK N/A UNK Removed No 1 1/2" plate. N/A N/A UNK UTC UNK Installed No 1823969 8" Dia. Sch 160 pipe. N/A N/A UNK UTC UNK Installed No 1845716 Glastic isolation plate. N/A N/A UNK UTC UNK Installed No 1090272 Size 5 rear bracket assembly.

Anvil N/A UNK UTC UNK Installed No 1847075 Size 5 rear bracket assembly.

Anvil N/A UNK UTC UNK Installed No 1831825 Form NIS-2 Owner's Report for Repair/Replacement Activities

  • required by the provisions of the ASME Code Section XI Work Order Numbe 01621909 -19 Sheet Page 2 off 1. Owner Duke Power Company 2. Plant Oconee Nuclear Station unit 2 526 South Church Street 7800 Rochestor Hwy Date Charlotte, NC 28201-1006 Seneca, SC 28672 5/21/2007 3. Work Performed By Type Code Symbol Stamp I Not Applicable Duke Power Company N Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable
4. Identification of Systems, ASME Class Reactor Coolant , ASME Class 1 5.(a) Applicable Construction Cod USAS B31.7 1967: Edition, No Addenda No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 1998: Edition, 2000 Addenda (c) Applicable Section Xl Codes Cases(s) None 6. Identification of Coirnponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)Size 5, Fig. 201 extension piece. Anvil N/A UNK UTC UNK Installed No 1845586 Description of Work S/R was redesigned per OE200140.8. Test Conducted D Hydrostatic FD Pnuematic D Nominal Operating Pressure D Excempt [ Other Visual Pressure PSI Test Temperature Deg. F

.Q Form NIS-2 Owner's Report for Repair/Replacement Activities e s required by the provisions of the ASME Code Section Xl Work Order Numbe Sheet 01621909 -19 PageLofgZ (7. Remarks (Applicable Manufactuer's Data Reports to be attached)(1) New item installed in lieu of existing.(2) New item installed in lieu of existing.(3) New item installed in lieu of existing.(4) Item is no longer required due to redesign.(5) Item is no longer required due to redesign.CERTIFICATION OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI Type Code Symbol Stamp Not Applicable Certificate of Lumber Not Applicable Expiration Date Not Applicable Signed __ __ _ __ _ Date ..s-__,/07 Owner or Owner's Designee, Title CERTIFICATION OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and State or province of ,.V,,rv ,,'-* , ,, and employed by HSB CT of Hartford, Connecticut have inspected the components described in the Owner's Report during the period /I3-.2 7 to >-,d-a , , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the inspector nor his employer make any warrenty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind rising from or connected with this inspection.

Commision(s) .J .Inspectors Signature National Board, State. Province, and Endorsements Date ;" &, 07

.orm NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1723280 Sheet I of 2 i Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/24/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class RC, ASME Class I 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) Code Cases N-504-2 and N-638-1 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)PZR-WP9I-WSI None None None 2007 Corrected NO WOL 2-PZR-WP9 i-2-WOL WS1 None None None 2007 Corrected NO WOL 2-PZR-WP9I-WS! None None None 2007 Corrected NO 3WOL 7. Description of Work OD201085 -Weld Overlay on Pressurizer Safetly Relief valve nozzles Test Conducted-]Hydrostatic D Pneumatic N Nominal Operating Pressure 1-1 Exempt El Other Pressure PSI Test Temperature

°F Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1723280 Sheet 2 of 2 19. Remarks (Applicable Manufacturer's Data Reports to be attached)0 0 0§0 0 0 PI CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed //ý- William W. Foster Jr Engineer Date 5/24/2007-t3neror Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of .,V.e7,-, .and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period z --e 7 to 7 -7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions National Board, State, Province, and Endorsements IF e Signature Date 7/c cC Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI U Work Order Number 1723281 Sheet lof 2-- a 1. Owner Duke Power Company 526 South Church Street Charlotte, NC 28201-1006

2. Plant Oconee Nuclear Station 7800 Rochester Hwy Seneca, SC 29672 Unit ONS- 2 Date 5/23/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable
4. Identification of System, ASME Class RC, ASME Class I 5.(a) Applicable Construction Code: USAS B3 1.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section X1 Code Case(s) Code Cases N-504-2 and N-638-1 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)2-RC-0266-23V WSI None None None 2007 Corrected NO 7. Description of Work OD201086 -Weld overlay of the pressurizer spray nozzle butt welds between the Class I nozzle, the safe end, and the pipe.-U U P8. Test Conducted F] Hydrostatic F] Pneumatic Z Nominal Operating Pressure L-- Exempt [ Other Pressure PSI Test Temperature

_F Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number Sheet 1723281 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 0 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed _-/ William W Foster Jr Engineer Date 5/23/2007 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ,,.47,rw 4 A.., v and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 1- $ -0 to 7-.,,, -o 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

___________________________

Commissions

_i"tpector's Signature National Board, State, Province, and Endorsements Date '

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1723282 Sheet I of 2.Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/24/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street

  • Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable
4. Identification of System, ASME Class RC, ASME Class I 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) Code Cases N-504-2 and N-638-1 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)RC-0326-21V WSI None None None 2007 Corrected NO 2-RC-0326-22V WSI None None None 2007 Corrected NO 7. Description of Work OD201087 -Weld overlay of hot leg and pressurizer surge nozzles Test Conducted E]- Hydrostatic

-- Pneumatic Z Nominal Operating Pressure E-- Exempt '- Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section X1 I Work Order Number 1723282 Sheet 2 of 2* Remarks (Applicable Manufacturer's Data Reports to be attached)0 0 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed g/_,_4/.Zj-

_Z William W Foster Jr Engineer Date 5/24/2007 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of -, and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period .2 to 7_-__-__ ? , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

`----ýpector's Signature Commissions

,,,//6 / ,,",-f .National Board, State, Province, and Endorsements Date 7_-/1, O 7 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Y Work Order Number 1719288 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/15/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class High Pressure Injection, ASME Class 1 5.(a) Applicable Construction Code: USAS B331.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)rifice Flanges Duke Energy Upstream of 2HP- Cororation N/A N/A N/A 1973 Corrected NO 334 (1) Corporation
7. Description of Work Replace existing nuts due to missing or unreadable markings 8. Test Conducted E Hydrostatic E] Pneumatic

[II Nominal Operating Pressure E] Exempt []Other Functional Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1719288 Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 1 inch, SA194 Grade 2H Nuts; S/C 131798; UTC 1079050; HT # 7240626 0 0 0 0 0 o 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorizgtion Number 4 Not Applicable Expiration Date Not Applicable Signed /3 5a 'i r" , Z/ Senior Engineer Date 5/15/2007 Owner orOwnereagnee.

Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of l,', ,,, and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period ,5K- -/,-z;-- o 7 to 6-7-o7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

0 Commissions

---'ý'ector's Signature National Board, State, Province, and Endorsements Date "2 0 "

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section X1 Work Order Number 01753158 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/18/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class High Pressure Injection System, ASME Class I 5.(a) Applicable Construction Code: ASME Section III 19 83 Edition, W84 Addenda, Code Case (b) Applicable Edition Section XI Utilized For RJR Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)I )Valve 2H P-487 Anchor/Darling EZ496-1-2 1908 None 1996 Corrected YES 7. Description of Work OE201820, replace portion of equalization piping (2 1/2" elbows and 2 pieces of 1/2" pipe) on valve 2HP-487.'. Test Conducted[] Hydrostatic E Pneumatic

[ Nominal Operating Pressure E Exempt [l- Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1753158 Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 Removed (2) pieces of 1/2" pipe, UTC unknown, and (2) 1/2" SW elbows, UTC unknown.Installed (2) pieces of 1/2" pipe, UTC# 1848210. Cat ID# 149458 and (2) 1/2" elbows, UTC# 907660, Cat ID# 80514 0 0 C O COMPLIANCE 0 0 0 0 0 II certify that the statements made in the report are correct and that this conforms to the requirements of the 7ASME Code, Section X1.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration.

Date Not Applicable Signed /Z William W Foster Jr Engineer Date 5/25/2007 Owner or Ownef's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of e , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period .c-- ?-o 7 to , -.,--- , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

b ~~;s~1i~Commissions AJCA'"KQ/,-Vd.-

Inspector's Signature National Board, State, Province, and Endorsements Date .4 ',oo/-c'2 C Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1752788 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -,2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 7/12/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Reactor Coolant System, ASME Class I 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 9 Edition, 2-06c) Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)2RC-4 (PZR Relief Block Westinghouse (kg/K DMV-1 136 Corrected YES Valve 7. Description of Work Performed seal weld of body to bonnet. No parts changed 8. Test Conducted["- Hydrostatic E] Pneumatic

[-1 Nominal Operating Pressure Li Exempt ,&Other Visual Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI-ri W CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section X1.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable.Signed C)J -~ /Cj Expiration Date Not Applicable Date 7/1 z/o7 Owner or Owner's Designee, Title 4-'7 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , and employed by HSB CT of Hartford, Connecticut have inspected the components describe(d in this Owner's Report during the period ,_,-7-o 7 to __-__- ___, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions , C/ 9J/, ,J, National Board, State, Province, and Endorsements le"- -ý -n-pector's Signature Date _7-/3: ? 7 4"J ....*Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI U Work Order Number 1666017 Sheet 1 of. 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 7/12/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class High Pressure Injection, ASME Class 1 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xi Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)rifice Flange Upstream 2HP- DEC None None None UNK Corrected NO 334 7. Description of Work Seal weld plug in instrument taps on the orifice flanges. These plugs have a history of leak and they are not used.8. Test Conducted D Hydrostatic

[-1 Pneumatic 0 Nominal Operating Pressure LI Exempt [I Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number Sheet 1666017 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o No new parts were used. Weld filler metal only item added.0 0 Q 0 0 0 o 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed /e..p-,(4'

.Senior Engineer Date 7/12/2007 Owner or Own 4's Jisignee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of .. o,,e7-)e e! .A and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period //_-,1"- _ _ _to 7-,? ,o-;, , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this' certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.Commissions

_____________'__.___,__,_'_

Inspector's Signature National Board, State, Province, and Endorsements Date 7-.J-3o 7

.A Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI F --Work Order Number 1753203 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 7/12/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class High Pressure Injection, ASME Class 1 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6! Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)2 HP 486 Anchor Darling UNK UNK DMV-1048 UNK Corrected YES+ .4 4 1 4 4 4..4 .4 1 1 I 4 .4..4 1 1 & 1 1 +7. Description of Work Change weld configuration to establish a 2:1 taper.-8. Test Conducted Li Hydrostatic

-]Pneumatic E Nominal Operating Pressure Exempt E] Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section X32 Work Order Number Sheet I 1753203 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o Weld Filler Metal 0 Q CO 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number J Not Applicable Expiration Date Not Applicable Signed ,/* (0 J Senior Engineer Date 7/12/2007 Owner or Own s e inee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of AL¢Px , and employed by HSB CT of Hartford.

Connecticut have inspected the components described in this Owner's Report during the period -2 to --C7 2 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing thig certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

______________________________________

Commissions

.)f-_., V.4A. 4 ' c-.Inspector's Signature National Board, State, Province, and Endorsements Date 7-a'3--'2 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1753204 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 7/12/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class High Pressure Injection, ASME Class 1 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)2HP-488 Anchor Darling UNK UNK DMV-1048 UNK Corrected YES 7. Description of Work Changed weld configuration to obtain 2:1 taper.Test Conducted Fii Hydrostatic E]' Pneumatic

[ Nominal Operating Pressure L-' Exempt Li] Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number Sheet 1753204 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 0 0 0 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl..Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed , Senior Engineer Date 7/12/2007 Owner or Ow ris De gnee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Re-port during the period __ -___--____to

-7, , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing thig certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_______________

______________

Commissions , '. .," Inspector's Signature National Board, State, Province, and Endorsements Date __ _ _ _ _ _ _

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI-U --Work Order Number 1753205 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 7/12/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class High Pressure Injection, ASME Class 1 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)2 HP 489 Anchor Darling UNK UNK DMV-1048 UNK Corrected YES 7. Description of Work Change weld configuration to establish a 2:1 taper.Test Conducted Fl1 Hydrostatic

[j] Pneumatic 0 Nominal Operating Pressure 0IZ Exempt E] Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number Sheet 0 1753205 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o Weld Filler Metal 0 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed -/.. Senior Engineer Date 7/12/2007 Owner or OwK.ri' esignee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ,tl,,er' 4,e,,.,,w and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period __-_/,______

to 7-,,f-o 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing thii certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions

-spector's Signature National Board, State, Province, and Endorsements Date 7-15y-o 2

&Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1719290 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/15/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class High Pressure Injection, ASME Class 1 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)Wrifice flange up DueErg stream of 2HP- Duke Energy N/A N/A N/A 1973 Corrected NO 326 (1) Corporation
7. Description of Work Replace existing nuts due to missing or unreadable markings 8. Test Conducted El Hydrostatic E Pneumatic L-- Nominal Operating Pressure EI] Exempt Other Functional Pressure PSI Test Temperature OF 1ý I Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 1719290 Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o 1 inch, SA194 Grade 2H Nuts; SIC 131798; UTC 1079050; HT # 7240626 Q 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorii ation Number Not Applicable Expiration Date Not Applicable Sine ASenior Engineer Date 5/15/2007 IOwnerr or 0 Designee, Title t9I CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of A,.-,,-//

and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period .r-, 9 to -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

I Commissions ,C.'K ./,4 C-National Board, State, Province, and Endorsements Date -/ ,.% o ;9'-- Tnspector's Signature Date -1/5oý Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I. --Work Order Number 01680260-07 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 2820 1-1006 Seneca, SC 29672 5/22/07 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Reactor Coolant System, ASME Class 1 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)kRC-66 Consolidated BY-93618 none none UNK Removed YES 0 2RC-66 Consolidated BS-08032 none none UNK Installed YES 7. Description of Work Valve, serial number BY-93618, was removed for ASME Code testing. Replaced with new spare'valve, serial number BS-08032 from stock.urn W.Test Conducted E] Hydrostatic L Pneumatic E] Nominal Operating Pressure Li Exempt E Other RCS Visual Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number Sheet 01680260-07 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)O Replaced existing valve with a new spare from stock.0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed I~~j J .,Engineer Date .-e?677' ~Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ,Jri ~and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Re6port during the period Z-- / 7- 07 to 7- J- cl2 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing thiý certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

________________________Commissions

________________

Inspector's Signature National Board, State, Province, and Endorsements Date >7 -?-a' -

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 98763544-01 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -0 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/24/2W6" 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class High Pressure Injection system, Letdown Cooler, ASME Class 1 5.(a) Applicable Construction Code: ASME Section 111 19 80 Edition, S 80 Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)Spare Letdown Graham Manufacturing 44773-1 12767 None 1983 Corrected YES Cooler 0 Corp.Im 7. Description of Work O etLsne tube was remnoved from service by plugging wvith mechanical tube plugs., Pop-A-Plugs.
8. Test Conducted"-I Hydrostatic E Pneumatic 1 Nominal Operating Pressure 1-- Exempt LII Other Pressure PSI Test Temperature

_F No test post-plugging Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number Sheet 98763544-01 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o Form N-I attached for cooler S/N 44773-1. Pop-A-Plugs, stock code 353623, UTC 0001060674, quantity of 2, were used to remove the degraded tube from service.0 o 0 o o 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed ,/ Engineer Date 5/24/06 KOwner or Owner's'Designeec Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of / and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period ,3 -Z,7-o e to .7-zs'.o. , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing ths certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

__________e_________________

Commissions

_,,____,_--/_____.__,,,,,______

--"insp Signature National Board, State, Province, and Endorsements Date 7 -,,e--,

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI U Work Order Number 01737857 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 4/30/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class RC, ASME Class 1 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No))2-0R M-DPCo None None. None UNIK Removed NO H6604 2.) T 2-50-RCPM-D ~ oeNn oeUK Rmvd N 2.) 2-50-RCPM-DPCo None None None 2007 Corrected NO H6604 7. Description of Work OE201547; S/R 2-50-RCPM -H6604 -Temporarily remove and reinstall with additional shim to rocker washers.Test Conducted Hydrostatic 0 Pneumatic

[I Nominal Operating Pressure M Exempt 0 Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 01737857 Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o S/R 2-50-RCPM-H6604:Temporarily remove O S/R 2-50-RCPM-H6604:Reinstall with additional shim washers 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed C-q Signed ..-Date 5'-- 7 C Ownr or 0 's Designee, Title " CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , /-_,A),' and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period J--o -o 7 to Z , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

I _ _ _ _ _ _ _ _ _ Com m issions _ _ _ _ _ _ _ _ _ _'i---spector s Signature National Board, State, Province, and Endorsements Date 4?7o 2 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1 1752010 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 2820 1-1006 Seneca, SC 29672 5/23/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Reactor Coolant (RC), ASME Class 1 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No);.) 2RC-77 Anchor/Darling E069T- 1-2 2432 UTC# 1021733 2000 Installed YES 2.) 2RC-77 Velan Unk Unk Unk Unk Removed NO+ 4 4 4 .1- 1 1 + 4 4 1 .4- 1 1 4 .4- 1 .4- L 7. Description of Work'Removed 3/4" valve 2RC-77. Installed 1/2" valve 2RC-77 Test Conducted D Hydrostatic Pneumatic 1L Nominal Operating Pressure Exempt Other Pressure PSI Test Temperature

°F Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 1752010 Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 Installed 1/2" valve -serial #E069T-I-2

@ Removed 3/4" Velan valve.§0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed .ý David Hubbard/Technical Specialist II Date 5/23/2007 Owner or Ow ier's Designee.

Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period -to ,5--_ Z_..-7-- 0 _ _ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

________________________________________Commissions /'c-/'.d ndseIn n_Date Silature National Board, State, Province, tnd Endorseients Date -

t.I 0 Form NIS-2 Owner's Report for Repair/Replacement Activities As required by the provisions of the ASME Code Section XI U I Work Order Numbe 01682510 -06 Sheet Page 1 of 2 1. Owner Duke Power Company 2- Plant Oconee Nuclear Station unit I2 526 South Church Street 7800 Rochestor Hwy Date Charlotte, NC 28201-1006 Seneca, SC 28672 5/15/2007 3. Work Performed By Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of Systems, ASME Class;ure Injection

-High Pressure Portion , ASME Class 1 5.(a) Applicable Construction Cod USAS 831.7 1967: Edition, No Addenda No Code Case (b) Applicable Edition Section XI Utilized For RJR Activity 1998: Edition, 2000 Addenda (c) Applicable Section XI Codes Cases(s) None 6. Identification of Coimponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)(1) 51A-0-1479E-H1E, Size 2-1/2 x Grinnell 16030 UNK N/A UNK Removed No 5 Hydraulic Snubber Cylinder (New Miller)S 1A-0-1479E-H1E, Size 2-1/2 x 5 Anvil 36542 UNK UTC UNK Installed No Hydraulic Snubber Cylinder (Config. 1823529 A) -7 Description of Work Rebuilt existing snubber cylinder with a Config. A pressurized cylinder.8. Test Conducted E! Hydrostatic El Pnuematic LJ Nominal Operating Pressure [i Excempt [] Other Visual Pressure PSI Test Temperature Deg. F Form NIS-2 Owner's Report for Repair/Replacement Activities 6-1' required by the provisions of the ASME Code Section XI Work Order Numbe Sheet 01682510 -06 Page 2 of 2 7, Remarks (Applicable Manufactuerrs Data Reports to be attached)(1) Replaced existing snubber cylinder with Config. A type.CERTIFICATION OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI Type Code Symbol Stamp Not Applicable Certificate of Autherization Number Not Applicable Expiration Date Not Applicable Signed Date _ _ _ _Owner or Owner's Designee, Vie CERTIFICATION OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and State or province of IVeforl , and employed by HSB CT of Hartford, Connecticut have inspected the components described in the Owner's Report during the period -- 7-0 to 6 -/? -o ? , , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section X1.By signing this certificate neither the inspector nor his employer make any warrenty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind rising from or connected with this inspection.

Commision(s)

,) -'.',,)/#,.

i!D t,-Sl gnature National Board, State. Province, and Endorsements Date ,

t 'C Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI SWork Order 1708 r Number 341-01,-14,-03 Sheet I of 3 1. Owner 2. Plant Unit Duke Energy Carolinas, LLC Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/17/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Energy Carolinas, LLC Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class LPSW, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)o@ 2C tube bundle, a C C Aerofin None None "part" of S/N 1993 Removed YES RBCU Coil # 1 940510* 2C C C Aerofin 070214 2157 Tube bundle 2007 Installed YES R13CU Coil # I o 2C tube bundle, a R 2 Aerofin None None "part" of S/N 1993 Removed YES R13CU Coil # 2 940509* 2C R C Aerofin 070215 2158 Tube bundle 2007 Installed YES RBCU Coil # 2 o 2CA tube bundle, a R Co Aerofin None None "part" of S/N 1993 Removed YES R13CU Coil # 3 940503*9 2CA C Co Aerofin 070216 2159 Tube bundle 2007 Installed YES RBCU Coil # 3 0 2C tube bundle, a R C Aerofin None None "part" of S/N 1993 Removed YES R13CU Coil # 4 1 1 1 940508 1 1 1@ 2c RBCU Coil #4 , Aerofin 070217 2160 Tube bundle 2007 Installed YES 7. Description of Work-Planned replacement of the 2C RBCU Coil tube bundles required removal/reinstahation of the cooler waterbox.

This VOlved disassembling the Low Pressure Service Water (LPSW) piping to the coils. The 5/8-inch & 3/4-inch diameter PSW piping bolting material for the piping-to-coil waterbox flanges required replacement due to surface degradation.

-All 4 of the 2C RBCU coil tube bundles were replaced with new bundles due to extensive tube degradation.

8. Test Conducted F"1 Hydrostatic

[--- Pneumatic

[ Nominal Operating Pressure 1 Exempt El- Other Pressure PSI Test Temperature

°F Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1 1708341 Sheet 2 of 3 1. Owner 2. Plant Unit Duke Energy Carolinas, LLC Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/17/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Energy Carolinas, LLC Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class LPSW, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped 46L. (Yes I No)0 2C 940503,940508, 548,553,554, RBCU coils Aerofin 940509, 940510 555 None 1993 Corrected YES (all 4) 940509,_940510_555 0 .0 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 1708341 Sheet 3 of 3 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o 2C RBCU Coils # 1, 2, 3 & 4 had the tube bundles removed (due to extensive tube degradation) and replaced with new tube bundles. The waterboxes to the coils were not replaced, only the tube bundles. The waterboxes from the4 old coils were reused.Note that the waterbox is the subcomponent of the entire coil assembly that has the N-stamp nameplate attached to it.0 2C RBCU Coils # 1, 2, 3 & 4 -new tube bundles were installed.

The tube bundle is a subcomponent of a RBCU coil. The coils are N-stamped components. (Form N-I's attached).

The waterboxes to the coils were not replaced, only the tube bundles (NPT stamped parts, Form N-2's attached).

The waterboxes from the 4 old coils were reused and were bolted up to the new bundles.O) Replaced 5/8-inch diameter nuts (SA 194 Gr 2H) and studs (SA 193 B7 threaded rod) on the 2C RBCU Coil waterbox-to-LPSW piping flanges. (Cat ID# 293556, UTC # 0001846136, and Cat ID# 297412, UTC # 0001846130).

Replaced 3/4-inch diameter nuts (SA 194 Gr 2H) and studs (SA 193 B7 threaded rod) on the 2C RBCU LPSW piping flanges. (Cat ID# 131796, UTC #0001831665 and Cat ID# 297413, UTC # 0001846529 and 0001846063.)

0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed ,_aM13O or engineer Date 511g7e /Z 07 J7 Owner or 6 wner's Designee.

Title'U CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of A,b Apr "I,/, and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period ,5- f-o 7 to o7 , and state that to the best of my- knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions

/C/. -, )/,04T c..National Board, State. Province, and Endorsements i I Date 7-/3-o "2 p Inspector's Signature Date 7-1-3-o 7

}.1 cr Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI U Work Order Number 1708343-02,-14,-03 Sheet 1 of 3 1. Owner 2. Plant Unit Duke Energy Carolinas, LLC Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 2820 1-1006 Seneca, SC 29672 5/17/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Energy Carolinas, LLC Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class LPSW, ASME Class 2 5.(a) Applicable Construction Code: USAS B331.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)~o2B tube bundle, a 0 Coi Aerofin None None "part" of S/N 1993 Removed YES RBCU Coil # 1 940504 O 2B RBCU Coil # Aerofin 070210 2153 Tube bundle 2007 Installed YES 0 2B tube bundle, a 0 Coi Aerofin None None "part" of S/N 1993 Removed YES R13CU Coil # 2 940502@ 2B Aerofin 070211 2154 Tube bundle 2007 Installed YES RBCU Coil # 2 o 2B tube bundle, a R Cl3 Aerofin None None "part" of S/N 1993 Removed YES R13CU Coil # 3 940501@ 2B@ Coi Aerofin 070212 2155 Tube bundle 2007 Installed YES RBCU Coil # 3 O02B tube bundle, a 0 Ci B Aerofin None None "part" of S/N 1993 Removed YES RBCU Coil # 4 940507 1 1@ 2B Aerofin 070213 2156 Tube bundle 2007 Installed YES RBCU Coil # 4 L 7. Description of Work-Planned replacement of the 2B RBCU Coil tube bundles required removal/reinstallation of the cooler waterbox.

This involved disassembling the Low Pressure Service Water (LPSW) piping to the coils. The 5/8-inch & 3/4-inch diameter IPSW piping bolting material for the piping-to-coil waterbox flanges required replacement due to surface degradation.

All 4 of the 2B RBCU coil tube bundles were replaced with new bundles due to extensive tube degradation.

8. Test Conducted D Hydrostatic D Pneumatic M Nominal Operating Pressure E] Exempt M Other Pressure PSI Test Temperature

_F Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1708343 Sheet 2 of 3 1. Owner 2. Plant Unit Duke Energy Carolinas, LLC Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 L Seneca, SC 29672 5/17/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Energy Carolinas, LLC Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class LPSW, ASME Class 2 5.(a) Applicable Construction Code: USAS B331.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)O0 -2B 940501, 940502, 546, 547, 549, RBCU coils Aerofin 940504,940507 552 None 1993 Corrected YES (all 4) 940507 552 p Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1708343 Sheet 3 of 3 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o 2B RBCU Coils # 1, 2, 3 & 4 had the tube bundles removed (due to extensive tube degradation) and replaced with new tube bundles. The waterboxes to the coils were not replaced, only the tube bundles. The waterboxes from the 4 old coils were reused.Note that the waterbox is the subcomponent of the entire coil assembly that has the N-stamp nameplate attached to it.0 2B RBCU Coils # 1, 2, 3 & 4 -new tube bundles were installed.

The tube bundle is a subcomponent of a RBCU coil. The coils are N-stamped components. (Form N-I's attached).

The waterboxes to the coils were not replaced, only the tube bundles (NPT stamped parts, Form N-2's attached).

The waterboxes from the 4 old coils were reused and were bolted up to the new bundles.O Replaced 5/8-inch diameter nuts (SA194 Gr 2H) and studs (SA193 B7 threaded rod) on the 2B RBCU Coil waterbox-to-LPSW piping flanges. (Cat ID# 293556, UTC # 0001846136, and Cat ID# 297412, UTC # 0001824477,0001090837, 0001088217.)

Replaced 3/4-inch diameter nuts (SA 194 Gr 2H) and studs (SA 193 B7 threaded rod) on the 2B RBCU LPSW piping flanges. (Cat ID# 131796, UTC # 0001831665 and Cat ID# 297413. UTC # 0001846063.)

0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed Owyner orAo //ners engineer Date 5/17 Z007 Owner or Owner's Designee, fTitle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 6- -to 7-13-o 0 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ _e_ý_ __ Commissions AlYe'-- v1,4,,4 c-'pector's Signature National Board, State, Province, and Endorsements Date 7 -/3 ?

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI~Work Order 1708.U'Number 344-o0,-15,-26 Sheet I of 3 1. Owner 2. Plant Unit Duke Energy Carolinas, LLC Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/17/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Energy Carolinas, LLC Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class LPSW, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped___(Yes I No)o 2A tube bundle, a R Ci Aerofin None None "part" of S/N 1993 Removed YES RBCU Coil # 1 940505@ 2A Aerofin 070206 2149 Tube bundle 2007 Installed YES RBCU Coil # I 0 2A tube bundle, a 0 Ci Aerofin None None "part" of S/N 1993 Removed YES R13CIJ Coil # 2 940506* 2A U Ci Aerofin 070207 2150 Tube bundle 2007 Installed YES RBCUJ Coil # 2 o 2A tube bundle, a R Ci Aerofin None None "part" of S/N 1993 Removed YES R13CU Coil #3 940511 O9 2A@ Ci Aerofin 070208 2151 Tube bundle 2007 Installed YES R13CU Coil #3 o 2A tube bundle, a RBCU Coil # 4 Aerofin None None "part" of S/N 1993 Removed YES RBCU Coil__ # 4940512 0 2A R Ci Aerofin 070209 2152 Tube bundle 2007 Installed YES R13CIJ Coil # 411 11 7. Description of Work-Planned replacement of the 2A RBCU Coil tube bundles required removal/reinstallation of the cooler wate-rbox.

This pvolved disassembling the Low Pressure Service Water (LPSW) piping to the coils. The 5/8-inch & 3/4-inch diameter P SW piping bolting material for the piping-to-coil waterbox flanges required replacement due to surface degradation.

-All 4 of the 2A RBCU coil tube bundles were replaced with new bundles due to extensive tube degradation.

8. Test Conducted i Hydrostatic

[-] Pneumatic 0 Nominal Operating Pressure.

L Exempt I-: Other Pressure PSI Test Temperature

_ 0 F Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI 9Work Order I Number 708344 Sheet 2 of 3 1. Owner 2. Plant Unit Duke Energy Carolinas, LLC Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/17/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Energy Carolinas, LLC Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class LPSW, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Component Name of Manufacturer Manufacturer Serial Number National Board No.Other Identification Year Built Corrected, Removed, or Installed ASME Code Stamped (Yes I No)O 2A 940505,940506, 550,551,556, RBCU coils Aerofin 940511,940512 557 None 1993 Corrected YES (all 4) 940511,_940512_557 4 1 I I 4 4 t 4- I I 4 4 4 4- I I 4 1 4 4--U Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI* Work OrdE r Number I1708344 Sheet 3 of 3 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 2A RBCU Coils # 1, 2, 3 & 4 had the tube bundles removed (due to extensive tube degradation) and replaced with new tube bundles. The waterboxes to the coils were not replaced, only the tube bundles. The waterboxes from the 4 old coils were reused.Note that the waterbox is the subcomponent of the entire coil assembly that has the N-stamp nameplate attached to it.0 2A RBCU Coils # 1, 2, 3 & 4 -new tube bundles were installed.

The tube bundle is a subcomponent of a RBCU coil. The coils are N-stamped components. (Form N- I's attached).

The waterboxes to the coils were not replaced, only the tube bundles (NPT stamped parts, Form N-2's attached).

The waterboxes from the 4 old coils were reused and were bolted up to the new bundles.§ Replaced 5/8-inch diameter nuts (SA 194 Gr 2H) and studs (SA 193 B7 threaded rod) on the 2A RBCU Coil waterbox-to-LPSW piping flanges. (Cat ID# 293556, UTC # 0001846136, and Cat ID# 297412, UTC # 0001821109, 0001834700, 0001092000, 0001846062, 0001846130, 0001821577).

Replaced 3/4-inch diameter nuts (SA 194 Gr 2H) and studs (SA 193 B7 threaded rod) on the 2A RBCU LPSW piping flanges. (Cat ID# 131796, UTC # 0001831665 and Cat ID# 297413, UTC # 0001846529).

0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date -Not Applicable Signed engineer Date 5 /7 /2007 Ower or Owner's Designee.

Title U CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ,oe- , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period ,s-,9- o 7 to , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing thi. certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

!ýctor's Signature Commissions A,) C//, ,'/-National Board, State, Province, and Endorsements Date 7 :4, -

6 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section X1~Work Order U Number Sheet I of 2 1 1712246-01

1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -1 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/6/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable
4. Identification of System, ASME Class Main Steam System, ASME Class 2 5.(a) Applicable Construction Code: USAS B3 1.1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)Valve 2MS-033 Velan Drawing P012- None Cat ID 490583 2001 Corrected NO-l 4') 996590-N04
7. Description of Work 2MS-035 was being disassembled for seat inspection.

Two studs and two nuts were damaged during the disassembly.

8. Test Conducted F-1 Hydrostatic L-] Pneumatic L-" Nominal Operating Pressure L-- Exempt M Other Visual Pressure PSI Test Temperature

° OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section Xl Work Order Number Sheet 1712246-01 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)O Valve body/bonnet studs, Cat ID #494225, UTC #0001041169 0 Valve body/bonnet nuts, Cat ID #494300, UTC #0001041192 0 0 0 0 o 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of A horiza n mber Not Applicable Expiration Date Not Applicable Signed MCE Valve Engineer Date 5/7/2007\1 Nv er's Desiee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ,U, _7, o, and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 7- F--, 7 to 7- F- o 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this O'iner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.~~____ ____.-_ Commissions ztJC/ zfc-)Y,?4.pector's Signature National Board, State, Province, and Endorsements Date ,

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI 62 U Work Order Number 01680487-01 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/7/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date I "Not Applicable

4. Identification of System, ASME Class High Pressure Injection, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Component Name of Manufacturer Manufacturer Serial Number National Board No.Other Identification Year Built Corrected, Removed, or Installed ASME Code Stamped (Yes I No)4 1 4 4 4 4 4 Valve -2HP-31 Fisher Controls 4768610 None None 1969 Corrected NO 7. Description of Work PM work on the valve was being performed and the maintenance techs found the valve plug eroded.8. Test Conducted'- Hydrostatic

[] Pneumatic

[] Nominal Operating Pressure [j] Exempt Other Visual Pressure PSI Test Temperature OF 4 --a Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 01680487-01 I Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o Valve plug/stem assembly, catalog ID # 18079, UTC # 0001061883 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed OA44 Jý Date ;Own~er or Ownier's Designee, Title T CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of -and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's-Report during the period o -7 to 7- 5'-o 2 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

___Commissions

.,Cc c-Inspector's Signature National Board, State, Province, and Endorsements Date 7 -f. e;,

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI p Work Order Number 1672596 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/24/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Low Pressure Service Water, ASME Class 2 5. 4 4? .,0 &(a) Applicable Construction Code: USAS B31.7 19 6< Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)2AI RCP Motor Westinghouse 4S-76P1 U,.( CA, &A (Alk/( Removed NO 2A 1 RCP Motor Westinghouse 1 S-89P686 bj, ,, ilpA' K *..' Installed NO 7. Descrotion of Work., Remove 2,k Motor and install refurbished motor. The refurbishment included installation of a new upper bearing tube bundle. New air coolers were installed in the refurbished motor on-site prior to plant installation.

The old LPSW flange kardware (nuts and bolts) was replaced with new hardware.8. Test Conducted E Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure El Exempt [ Other Pressure PSI Test Temperature OF 4 1 .'6 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1672596 I Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 Upper Bearing Oil Cooler Tube Bundle -SC#591424 (Thermal Engineering Vendor PN# 30 1-G-040)* Air Cooler -SC# 567690 (Thermal Engineering Vendor PN# 500-L-201-lH) 0 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of 4thorization Number Not Applicable Expiration Date Not Applicable Signed 6 H..y_,, /c /- Date g/a, /o" I -Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of AJ0,o0 ..v7 and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 5- -, ? to 7-5 1.- o 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

~ ____ ---- _____________________

Commissions ,v c-_*"=nspector's Signature National Board, State, Province, and Endorsements Date 7- -,>

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1641998-12 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 1/9/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Unit 2 "A" Building Spray Pump, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.1 19 74 Edition, 1975 Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)ON2BSPU0001 Ingersoll-Rand LUNK UNK UNK UNK Removed NO ON2BSPU0001 Ingersoll-Rand UNK LINK LUNK UNK Installed NO 7. Description of Work The rotating assembly of the 2A Reactor Building Spray Pump will be replaced.

All other parts involved in the work cope will be inspected and replaced as necessary.

Test Conducted El Hydrostatic 1 Pneumatic 1 Nominal Operating Pressure F Exempt E Other Pump Flow Testing Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section X1 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed -ie , Assistant Engineer Date 1/9/2007 9%ner or Owner's- Dy~gnee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period /- 9'-o 7 to 7-f.-'o2 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this, certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

I Commissions Inspector's Signature Date 7- r- C 2 National Board, State, Province, and Endorsements Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1665331 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/24/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class 51A-, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)mANGER 2-51A-3 D.E.C NONE NONE NONE 1973 Installed NO 1444A-H75 7. Description of Work REPLACED BENT ROD 8. Test Conducted El Hydrostatic L-I Pneumatic

[-" Nominal Operating Pressure N Exempt El Other Pressure PSI Test Temperature OF 6 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1665331 I Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 UTC # 1821912, HT # 502193, ASTM A36-Carbon Steel 1/2" 0 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamo Not Appliclable

.... .. ..... ......Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed 4--ýW ý ASHCRAFT-ASSISTANT ENGINEER Date 5/24/2007-" Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ,,rw , .and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period -to 4-/J-.. 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions AI'-f O/A%'"---hispector's Signature National Board. State. Province, and Endorsements Date "-d-' -, 7 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI U Work Order Number 01666173 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/24/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class 03-Feedwater, ASME Class 2 5.(a) Applicable Construction Code: USAS B331.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)2-71480B3-265718; D.E.C NONE NONE NONE 1973 Installed NO H6618; Hanger 7. Description of Work Replaced U-bolt 8. Test Conducted D Hydrostatic Pneumatic Nominal Operating Pressure Exempt DOther Pressure PSI Test Temperature

°F Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number Sheet 01666173 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)O 1 1/2" U bolt UTC 1037417 PN# 137N 0 0 C 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed Z. Ashcraft-Assistant Engineer -Date 5/24/2007 Owner or Owner's Desigifee, Title'CERTIFICATE OF INSERVICE INSPECTION i, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of /,,,7- eeov and employed by HSB CT of Hartford.

Connecticut have inspected the components described in this Owner's Report during the period S- -/ ýF- 2 to !. /3. o 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this' certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any' manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

______ ..... ________________

Commissions

.tMpector Signature National Board. State, Province.

and Endorsements Date '- o Form NIS-2 Owner's Report for Repair/Replacement Activities E 40 required by the provisions of the ASME Code Section Xl Work Order Numbe 01748968 -01 Sheet Page I of 2 1. Owner Duke Power Company 2. Plant Oconee Nuclear Station unit I 2 526 South Church Street 7800 Rochestor Hwy Date Charlotte, NC 28201-1006 Seneca, SC 28672 5/15/2007 3. Work Performed By Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of Systems, ASME Class Main Steam , ASME Class 2 (a) Applicable Construction Cod USAS B31.7 W Edition, No Addenda No Code Case (b) Applicable Edition Section Xl Utilized For RJR Activity 1998: Edition, 2000 Addenda (C) Applicable Section XI Codes Cases(s) None 6. Identification of Coimponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)(1) Lisega Size 305253 RF3 Lisega 61316-73 UNK N/A UNK Removed No Hydraulic Snubber (2-01A-0-1441-R2-2)T isega Size 305253 RF3 Hydraulic Lisega 01615040-049 UNK UTC UNK Installed No Snubber (2-01A-0-1441-R2-2) 1045116 7. Description of Work Snubber was replaced due to leaking hydraulic fluid 8. Test Conducted FD Hydrostatic D Pnuematic L] Nominal Operating Pressure D- Excempt [ Other Visual Pressure PSI Test Temperature Deg. F

  • ID Form NIS-2 Owner's Report for Repair/Replacement Activities required by the provisions of the ASME Code Section Xl Work Order Numbe Sheet 01748968 -01 Page 2 of 2 7. Remarks (Applicable Manufactuetfs Data Reports to be attached)(1) Removed snubber due to depleted hydraulic fluid CERTIFICATION OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl Type Code Symbol Stamp Not Applicable Certificate of Autherization Number Not Applicable Expiration Date Not Applicable Signed , -Date __________._.__

Owner or Owner's Designee, Title CERTIFICATION OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and State or province of /o-.,' and employed by HSB CT of Hartford, Connecticut have inspected the components described in the Owner's Report during the period __)"to___

_. ___ _? to , , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the inspector nor his employer make any warrenty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind rising from or connected with this inspection.

~~~~~~~~Commision(s)

.,/ .,,,,_/ -.,,,,, ..Inspectors Signature National Board, State, Province, and Endorsements Date 62 Form NIS-2 Owner's Report for Repair/Replacement Activities s required by the provisions of the ASME Code Section Xl Work Order Numbe 01682510 -02 Sheet Pagel of 2 1. Owner Duke Power Company 2. Plant Oconee Nuclear Station Unit I 2 526 South Church Street 7800 Rochestor Hwy Date Charlotte, NC 28201-1006 Seneca, SC 28672 1 5/15/2007 3. Work Performed By Type Code Symbol Stamp I Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of Systems, ASME Classas 6t'r-D07 Main Steam ,ASME Class~Z.~(a) Applicable Construction Cod USAS B31.7 ,16W: Edition, No Addenda No Code Case (b) Applicable Edition Section Xl Utilized For RJR Activity 1998: Edition, 2000 Addenda (c) Applicable Section Xl Codes Cases(s) None 6. Identification of Coimponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)(1) 2-01A-2-1-0-1401A-SR3, Size 2- Grinnell 30210 UNK N/A UNK Removed No 1/2 x 10 Hydraulic Snubber Cylinder (New Miller)b -01A-2-1-0-1401A-SR3, Size 2-1/2 Anvil 36134 UNK UTC UNK Installed No x 10 Hydraulic Snubber Cylinder 1081152 (Config. A)7. Description of Work Rebuilt existing snubber cylinder with a Config. A pressurized cylinder.8. Test Conducted Li Hydrostatic Fi Pnuematic F] Nominal Operating Pressure El Excempt V1 Other Visual Pressure PSI Test Temperature Deg. F Form NIS-2 Owner's Report for Repair/Replacement Activities As required by the provisions of the ASME Code Section XI Work Order Numb. Sheet 01682510 -02 Page 2 of 2 7. Remarks (Applicable Manufactuerr's Data Reports to be attached)(1) Replaced existing snubber cylinder with Config. A type.CERTIFICATION OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI Type Code Symbol Stamp Not Applicable Certificate of Autherization Number Not Applicable Expiration Date Not Applicable Signed __ __ __ __ __ __ __ __ Date 5/A'4 Owner or Owner's Designee, Title CERTIFICATION OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and State or province of ,or,, , , and employed by HSB CT of Hartford, Connecticut have inspected the components described in the Owner's Report during the period 2 to -,/,f -C, ) , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the inspector nor his employer make any warrenty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind rising from or connected with this inspection.

Commision(s)

Inspector's Signature National Board. State, Province.

and Endorsements Date ,r ;

Form NIS-2 Owner's Report for Repair/Replacement Activities s required by the provisions of the ASME Code Section Xl Work Order Numbe 01682510 -07 Sheet Pagel of 2 1. Owner Duke Power Company 2. Plant Oconee Nuclear Station Unit I I 2 526 South Church Street 7800 Rochestor Hwy 2 Date Charlotte, NC 28201-1006 Seneca, SC 28672 5/15/2007 3. Work Performed By Type Code Symbol Stamp WorkPerfrmed-ITNot Applicable Duke Power Company N Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of Systems, ASME Class Main Steam , ASME Class 2 5.(a) Applicable Construction Cod USAS B31.7 .Edition, No Addenda No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 1998: Edition 2000 Addenda (c) Applicable Section Xt Codes Cases(s) None 6. Identification of Coimponents Name of Component Manufactur:

Manufacture National Other Year Corrected, ASME Code Serial Number Board No identification Built Removed or Stamped Installed (Yes/No)(1) 2-01A-0-1401B-R12(B), Size 3- Grinnell 18594 UNK N/A UNK Removed No 1/4 x 5 Hydraulic Snubber Cylinder (New Miller)12-0A-0-1401B-R12(B), Size 3-1/4 Anvil 36329 UNK UTC UNK Installed No x 5 Hydraulic Snubber Cylinder 1091794 Config. A)7 Description of Work Rebuilt existing snubber cylinder with a Config. A pressurized cylinder.8. Test Conducted D7 Hydrostatic D Pnuematic

[ Nominal Operating Pressure ED Excempt W Other Visual Pressure PSI Test Temperature Deg. F*

Form NIS-2 Owner's Report for Repair/Replacement Activities

's required by the provisions of the ASME Code Section X Work Order Numbe Sheet 01682510 -07 Page 2 of 2 7. Remarks (Applicable Manufactuer's Data Reports to be attached)(1) Replaced existing snubber cylinder with Config. A type.CERTIFICATION OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl Type Code Symbol Stamp Not Applicable Certificate of Autherization Number Not Applicable Expiration Date Not Applicable Signed .Date Owner or Owner's Designee, Title CERTIFICATION OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and State or province of -<Jo.rAV 6...'4,'A' and employed by HSB CT of Hartford, Connecticut have inspected the components described in the Owner's Report during the period '7 -c to -0 2 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the inspector nor his employer make any warrenty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind rising from or connected with this inspection.

Commision(s)

-',.,/,, Inspector's Signature National Board. State. Province, and Endorsements Date _.

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI 7 Work Order Number 1733130 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/10/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Low Pressure Service Water, 2LP-94, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 -K Edition, N Addenda.(c) Applicable Section XI Code Case(s) None 7tO" 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)2-LP-94 Aloyco/Watwor n/a n/a N2116-SP UNK Corrected NO th 7. uescripuon OT WOrK Inspect and replace body to bonnet bolting that have been damaged by corrosion on 2LP-94. Nuts 5/8 inch SC# 293556, studs were 5/8 inch all thread rod SC# 297412 p. Test Conducted F-1-Hydrostatic

[ Pneumatic D Noinal Operating Pressure 0 Exempt [ Other F/V leak check Pressure PSI Test Temperature -F 62 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 1733130 I Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 Inspect and replace body to bonnet bolting that have been damaged by corrosion on 2LP-94. Nuts 5/8 inch SC# 293556 SA194 Gr 2H UTC # 0001846136;, studs were 5/8 inch all thread rod SC# 297412, SA 193 Gr B7 UTC# 0001824477 0§0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed .,ee Date ,5-/2 -12 Owner or Owner's Designee, Title (CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of / -and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period %T- o 7 to . , 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASMECode, Section Xl..By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the. examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.-Inspector's Signaure Date ý- )Commissions

/',, _National Board, State, Province, and Endorsements

'Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI p Work Order Number 01667011 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date-Charlotte, NC 28201-1006 Seneca, SC 29672 9/5/2006 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class 2LP-7 2C Low Pressure Injection Pump Suction (LPI System), ASMEE Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 89 Edition, No Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year* Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)emove existing Powell N/A N/A N/A N/A Removed NO wedge on 2LP-7 Installed new wed n Pratt UTC # 1048310 N/A N/A 2002 Installed NO wedge on 2LP-7 7.- Description of Work Replace the old wedge on 2LP-7 with a new wedge that has hardfacing added to the guides to improve dynamic Serformance.

2LP-7 is installed with the stem in a horizontal orientation.

The hardfaced guide rail elliminates concerns r galling between the wedge guide rail and the body guide slot.!r 8. Test Conducted 0l Hydrostatic DI Pneumatic Ri Nominal Operating Pressure E Exempt Z Other Courtesy hydro test.Pressure 150 PSI Test Temperature 70 OF m m Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 01667011 Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)O Replaced old wedge with new wedge (stock code # 496900), UTC #1048310.Q 0 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of ..thoriza0ionNu b Not Applicable Expiration Date Not Applicable Signed / /i ~c.cDate 9 /?--,Cc'6 S- Owner Owner-- ' D6signee, Title , I CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 41 w , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period ___ __ ,-__ to , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expre~sed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither .the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions

.)C//A,/,-

-Inspector's Signattire National Board, State, Province, and Endorsements Date -

For nNIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI U Work Order Number 1667011-4 Sheet 1 of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/22/2006 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Low Pressure Service Water System, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 68 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)* anger 2-53B- Duke Energy None None None unk Removed NO 435B-EMO-H-50 Corporation Hanger 2-53B- Duke Energy 435B-EMO-H-50 DukeaEn None None None 2006 Installed NO (1) Corporation
7. Description of Work 8. Test Conducted D Hydrostatic E] Pneumatic

[-1 Nominal Operating Pressure N Exempt El Other Pressure PSI Test Temperature OF 0 &Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number Sheet 1667011-4 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o 1/2 inch threaded rod; SA193 Grade B7; S/C 297411; UTC 1089881 1/2 inch heavy hex. nut; SA194 Grade 2H; SIC 313135; UTC # 1088726 0 0 0 0 0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authprization Nu tier Not Applicable Expiration Date Not Applicable Signed I/3.4., Basil W. Carney, Jr. Senior Engineer Date 9/25/2006 Owner r Lner's Designee, Title/*CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period E.3.,-,S- -c,__ to _ _, __. __,__ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

0 -Commissions

.4<.. .. -Inspector's Signature National Board, State, Province, and Endorsements Date /- ,

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1635328 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC. 29672 2/23/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Main Steamr, ASME Class 2 5.(a) Applicable Construction Code: USAS B3 1.1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition Section Xl Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section Xl Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes / No)Thermowell (2) Unk Unk Unk Unk Removed NO Half Coupling (2) Unk Unk Unk Unk Installed YES Plug (2)" Unk Unk Unk Unk Installed YES 7. Description of Work OE-18468, Removed two 1-1/2" thermowells and installed two 2" 6000# threaded half couplings, two 2" plugs and four 3/4" 3000# threaded half couplings.

w.Test Conducted F Hydrostatic D Pneumatic Z Nominal Operating Pressure R Exempt E Other Pressure PSI Test Temperature OF Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 1635328 I Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 Removed two thermowells, 1-1/2" dia.0 Installed two 2" Treaded Half coupling (CAT ID 595028, UTC 1845729) and two 2" Threaded Plug (CAT ID 588792, UTC 1822410).0 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed /____10 ____1___________

Date ________________

Owner or Owner's DesT1:_,ieK'itle I ýCERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of U,,,-e7-, and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period Is- -y f to ---3 -0 ? , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing thit certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

I Commissions

..Z/'d.., I Inspector's Signature National Board, State, Province.

and Endorsernents Date

  • 0j 4 c'7 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI U --Work Order Number 01737857 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 4/30/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable
4. Identification of System, ASME Class LPSW, ASME Class 2 5.(a) Applicable Construction Code: USAS B331.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)I. 1480C-H.) DPCo None None None UNK Removed NO H6537 2. 40- DPCo None None None 2007 Installed NO H6537 3.)2-14B-1480C-DPCo None None None UNK Removed NO H6538 4.)2-141-1480C-DPCo None None None 2007 Installed NO H6538 7. Description of Work OE201547; S/R 2-14B-1480C-H6537

-Temporarily remove and reinstall with additional 3/4" plate.S/R 2-14B-1480C-H6538

-Temporarily remove and install with a new welded beam attachment.

Test Conducted D Hydrostatic E] Pneumatic 1 Nominal Operating Pressure [ Exempt D Other Pressure PSI Test Temperature OF A Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 01737857 Sheet 2 of 2 9. Remnarks (Applicable Manufacturer's Data Reports to be attached)0 S/R 2-14B-1480C-H6537:Temporarily remove 0 S/R 2-14B-1480C-H6537:Reinstall with new 3/4" thick plate.0 S/R 2-1413-1480C-H6538:Temporarily remove 0 S/R 2-14B-1480C-H6538:Reinstall with new welded beam attachment.

0'0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section X1.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed C-, ~ :e Date 5- r -j L-04er or 0 ~er's Designee, Title/ F CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ,,/. ,,W and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period .--/,-- to 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions________

_____< ectoT's Signature National Board, State, Province, and Endorsements Date ?5-o -

Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI Work Order Number 01675527 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/22/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte, NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class MS, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For R/R Activity 19 j Edition, 2 Addenda.(c) Applicable Section Xl Code Case(s) None y .) ? C.A- 7R:-t,.. DA v'o1745Ay JA-37 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No).) 2-OIA-1441-DPCo None None None 2007 Installed NO H4346 2.) 2-0 1A- 1441 -2.) DPCo None None None 2007 Installed NO H4347 I I I t I I I I I I 4 4 4 I I I I 4 4 4 I I I 1 I I I I I 1 I 4 4 7. Description of Work OD20071 1; Install new S/Rs 2-OIA-1441-H4346 and H4347.Test Conducted D Hydrostatic 0 Pneumatic

[ Nominal Operating Pressure Exempt Other Pressure PSI Test Temperature OF Jul 17 07 01:59p QA/QC-ONS 864-885-4018 p.2 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section X1 I Work Order Number ISheet-VT'Uý21yuy f k 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)0 2-OIA-1444-H4346; Fig 216 pipe clamp, TS 3x2xl/4, Plate, 1/2, 3/4" 0 2-OIA-1444---4347;Fig 216 pipe clamp, TS 3x2xli4, Plate, U/2, 3/4" G 0 0 0 0§§CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.Type Code Symbol Stamp Not Applicable Certificate of Autho ' tion Number Not Applicable Expiration Date Not Applicable Signed Date 5--Z?.1-07

,.k..- o,<,.: r' Desigioo.

Title"°7"V~u;,/ C&- 7lU CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ,e,,v , ,,,# and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period ,,,/- r :1, to 5-- e._-C;'? , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

p 1f; I-*ýnspector'_s Signature Commissions

, National Board, State, Province, and Endorsements Date Jul 18 07 08:29a QA/QC-ONS 864-885-4018 p.2 Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section X[U Work Order Number 01651472-01 Sheet I of 2 1. Owner 2. Plant Unit Duke Power Company Oconee Nuclear Station ONS -2 526 South Church Street 7800 Rochester Hwy Date Charlotte, NC 28201-1006 Seneca, SC 29672 5/24/2007 3. Work Performed by Type Code Symbol Stamp Not Applicable Duke Power Company Authorization Number 526 South Church Street Not Applicable Charlotte.

NC 28201-1006 Expiration Date Not Applicable

4. Identification of System, ASME Class Main Steam, ASME Class 2 5.(a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, No Code Case (b) Applicable Edition Section XI Utilized For RIR Activity 19 98 Edition, 2000 Addenda.(c) Applicable Section XI Code Case(s) None 6. Identification of Components Name of Name of Manufacturer National Other Year Corrected, ASME Component Manufacturer Serial Number Board No. Identification Built Removed, Code or Installed Stamped (Yes I No)MS-12 Crosby none none none UNK Corrected NO 2MS5-12 onStud UNK none none none LNK Installed NO Bonnet Studs 7. Description of Work Bonnet was replaced due to degraded compression screw threads. New bonnet studs were installed to provide proper nut to stud thread engagement.

T est C o n d u cted IL c k EjD Hydrostatic

[] Pneumatic

[] Nominal Operatinig.Pressure D Exempt Z Other F/V Leak check and Peustroke retest Pressure _______PSI Test Temperature

_______

864-885-4018 p.3 Jul 18 07 08:30a QA/QC-ONS Form NIS-2 Owner's Report for Repair/Replacement Activity As required by the provisions of the ASME Code Section XI I Work Order Number 01651472-01 Sheet 2 of 2 9. Remarks (Applicable Manufacturer's Data Reports to be attached)o Bonnet, Catalog ID: 586771, serial number: N9001 17-31-0001, UTC f: i846691* Bonnet Studs, Catalog ID: 297388, UTC #: 1092005 0 0 0 0 o 0 0 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization Number Not Applicable Expiration Date Not Applicable Signed , Engineer Date 5124/2007 O-i.iwncr or Owners Iesignce, TiLle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of /-.o.e7-,'

_ and employed by HSB CT of Hartford, Connecticut have inspected the components described in this Owner's Report during the period S'-_-./0-0_7 to 7-16'--o7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_______________________Commissions

./s-/,o/A.dc DTnaptctor's Signature National Board. State, Province, and Endorsements Date 7 Iil I

6.0 Pressure

Testing Table 6-1 shows the number of Class 1 (Category B-P) and Class 2 (Category C-H)pressure tests completed for refueling outage EOC 22. There was no through-wall leakage observed during these pressure tests Table 6-1 Outaoe Specific Summarv Examination Category Test Requirement Total Completed EOC22 B-P System Leakage Test (IWB-5220) 1 C-H System Leakage Test (IWC-5220) 101 Table 6-2 shows a completion status of pressure tests conducted during the first period o'the fourth ten-year interval.Table 6-2 Period Specific Summary Total Total (%)Examination Test Examinations Examinations Examinations Category Requirement Required For Credited For Complete For This Period This Period This Period B-P System Leakage 2 2 100%Test (IWB-5220)

C-H System Leakage 52 52 100%Test (IWC-5220)

Section 6 Prepared By: Date: Section 6 Reviewed By: Date: 1 Six pressure test zones were completed during the Refueling Outage Report EOC21 cycle but were not included in that report. As such, those tests are being included in this outage report. See Table 6-4 for identification of those tests.Refueling Outage Report EOC22 Oconee Unit 2 Section 6 Page 1 of 5 Revision 0 June 13, 2007 The Class 1 (Category B-P) leakage test is required each refueling outage. Table 6-3 shows the completion data of the Class 1 (Category B-P) leakage test conducted during refueling cycle EOC22.Table 6-3 Detailed Class 1 Listing EOC22 Zone Completion EOC22 VT-2 Code Case(s)Number Boundary Dwg Status Examination Date Used OZ2L-1A O-ISIL4-100A-2.1 Complete 5/28/2007 None O-ISIL4-100A-2.2 Complete 5/28/2007 None O-ISIL4-100A-2.3 Complete 5/28/2007 None O-ISIL4-101A-2.1 Complete 5/28/2007 None O-ISIL4-101A-2.4 Complete 5/28/2007 None 0-ISIL4-102A-2.1 Complete 5/28/2007 None O-ISIL4-102A-2.3 Complete 5/28/2007 None O-ISIL4-11 OA-2.1 Complete 5/28/2007 None O-ISIL4-110A-2.4 Complete 5/28/2007 None OZ2L-1AA O-ISIL4-101A-2.4 Complete 5/28/2007 None OZ2L-1V 0-ISIL4-100A-2.2 Complete 5/28/2007 None OZ2L-1Z 0-ISIL4-101A-2.4 Complete 5/28/2007 None OZ2L- 16 0-ISIL4-101A-2.4 Complete 5/28/2007 None The Class 2 (Category C-H) leakage tests are required each period. Table 6-4 shows the completion data of the Class 2 (Category C-H) leakage tests required for the 1st Period.Table 6-4 Detailed Class 2 Listing VT-2 Code Zone Examination Case(s)Number Boundary Dwg Completion Status Date Used 1 IZ2L-10 0-ISIL4-101A-2.3 Completed in EOC21 11/14/05 None 2 IZ2L-11 O-ISIL4-101A-2.3 Completed in EOC21 11/14/05 None 3 IZ2L-12 2 O-ISIL4-101A-2.3 Completed in EOC21 01/16/06 None O-ISIL4-101A-2.4 Completed in EOC21 01/16/06 None 4 IZ2L-13 0-ISIL4-101A-2.3 Completed in EOC21 07/25/05 None 5 IZ2L-14A 0-ISIL4-101A-2.3 Completed in EOC21 11/11/05 None 6 IZ2L-14B 0-ISIL4-101A-2.3 Completed in EOC21 11/11/05 None 7 IZ2L-20 0-ISIL4-101A-2.3 Completed in EOC21 07/27/05 None Refueling Outage Report EOC22 Oconee Unit 2 Section 6 Page 2 of 5 Revision 0 June 13, 2007 VT-2 Code Zone Examination Case(s)Number Boundary Dwg Completion Status Date Used 8 IZ2L-22 2 O-ISIL4-101A-2.3 Completed in EOC21 03/09/06 None O-ISIL4-102A-2.1 Completed in EOC21 03/09/06 None O-ISIL4-102A-2.2 Completed in EOC21 03/09/06 None O-ISIL4-104A-1.2 Completed in EOC21 03/09/06 None 9 IZ2L-24 O-ISIL4-102A-2.1 Completed in EOC21 08/23/05 None O-ISIL4-103A-2.1 Completed in EOC21 08/23/05 None 10 IZ2L-25 O-ISIL4-102A-2.1 Completed in EOC21 08/25/05 None O-ISIL4-103A-2.1 Completed in EOC21 08/25/05 None 11 IZ2L-27A O-ISIL4-102A-2.1 Completed in EOC21 11/19/05 None O-ISIL4-102A-2.2 Completed in EOC22 05/26/07 None 12 IZ2L-27B O-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None 13 IZ2L-4 O-ISIL4-101A-2.1 Completed in EOC21 07/25/05 None 14 IZ2L-41 2 O-ISIL4-109A-1.1 Completed in EOC21 12/11/06 None 15 IZ2L-48 O-ISIL4-122A-2.1 Completed in EOC21 06/27/05 None O-ISIL4-122A-2.2 Completed in EOC21 06/27/05 None O-ISIL4-122A-2.3 Completed in EOC21 06/27/05 None O-ISIL4-122B-2.1 Completed in EOC21 06/27/05 None O-ISIL4-122A-2.4 Completed in EOC21 06/27/05 None 16 IZ2L-5 2 O-ISIL4-101A-2.1 Completed in EOC21 01/09/06 None O-ISIL4-101A-2.3 Completed in EOC21 01/09/06 None 17 IZ2L-60 O-ISIL4-124B-2.2 Completed in EOC21 09/06/05 None O-ISIL4-124B-2.4 Completed in EOC21 09/06/05 None 18 OZ2L-14B O-ISIL4-101A-2.4 Completed in EOC21 11/11/05 None 19 OZ2L-15 O-ISIL4-101A-2.4 Completed in EOC21 11/23/05 None 20 OZ2L-16 O-ISIL4-101A-2.4 Completed in EOC21 11/22/05 None 21 OZ2L-17 O-ISIL4-101A-2.2 Completed in EOC21 11/21/05 None 22 OZ2L-17B O-ISIL4-101A-2.2 Completed in EOC21 11/11/05 None 23 OZ2L-18 O-ISIL4-101A-2.2 Completed in EOC21 11/19/05 None Refueling Outage Report EOC22 Oconee Unit 2 Section 6 Page 3 of 5 Revision 0 June 13, 2007 VT-2 Code Zone Examination Case(s)Number Boundary Dwg Completion Status Date Used 24 OZ2L-19A O-ISIL4-104A-1.1 Completed in EOC21 11/14/05 None O-ISIL4-101A-2.5 Completed in EOC21 11/14/05 None 25 OZ2L-19B O-ISIL4-101A-2.5 Completed in EOC21 11/15/05 None 26 OZ2L-1A O-ISIL4-101A-2.1 Completed in EOC21 11/23/05 None O-ISIL4-101A-2.1 Completed in EOC21 11/23/05 None O-ISIL4-101A-2.5 Completed in EOC21 11/23/05 None 27 OZ2L-2 O-ISIL4-101A-2.1 Completed in EOC21 11/23/05 None O-ISIL4-101A-2.4 Completed in EOC21 11/23/05 None O-ISIL4-101A-2.5 Completed in EOC21 11/23/05 None 28 OZ2L-21 O-ISIL4-102A-2.1 Completed in EOC21 11/19/05 None O-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None O-ISIL4-104A-1.2 Completed in EOC21 11/19/05 None 29 OZ2L-23 O-ISIL4-101A-2.2 Completed in EOC21 11/19/05 None O-ISIL4-102A-2.1 Completed in EOC21 11/19/05 None O-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None 30 OZ2L-26 O-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None 31 OZ2L-28 O-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None 32 OZ2L-29 O-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None 33 OZ2L-29A O-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None O-ISIL4-102A-2.3 Completed in EOC21 11/19/05 None 34 OZ2L-3 O-ISIL4-101A-2.1 Completed in EOC21 11/20/05 None 35 OZ2L-30 O-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None 36 OZ2L-30A O-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None O-ISIL4-102A-2.3 Completed in EOC21 11/19/05 None 37 OZ2L-31A O-ISIL4-102A-2.3 Completed in EOC21 10/22/05 None 38 OZ2L-31B O-ISIL4-102A-2.3 Completed in EOC21 10/22/05 None 39 OZ2L-31C O-ISIL4-102A-2.3 Completed in EOC21 10/22/05 None 40 OZ2L-39 2 O-ISIL4-104A-1.1 Completed in EOC22 05/12/07 None 41 OZ2L-42A O-ISIL4-11OA-2.1 Completed in EOC21 11/23/05 None 42 OZ2L-42B O-ISIL4-11OA-2.1 Completed in EOC21 11/23/05 None Refueling Outage Report EOC22 Oconee Unit 2 Section 6 Page 4 of 5 Revision 0 June 13, 2007 VT-2 Code Zone Examination Case(s)Number Boundary Dwg Completion Status Date Used 43 OZ2L-44 O-ISIL4-11OA-2.1 Completed in EOC22 05/28/07 None O-ISIL4-121 B-2.3 Completed in EOC22 05/28/07 None O-ISIL4-121 B-2.5 Completed in EOC22 05/28/07 None O-ISIL4-121D-1.2 Completed in EOC22 05/28/07 None O-ISIL4-121 D-2.1 Completed in EOC22 05/28/07 None O-ISIL4-122A-2.1 Completed in EOC22 05/28/07 None 0-ISIL4-133A-2.5 Completed in EOC21 11/19/05 None 44 OZ2L-62 2 -ISIL4-101A-2.1 Completed in EOC21 11/19/05 None O-ISIL4-101A-2.2 Completed in EOC21 11/19/05 None O-ISIL4-109A-1.1 Completed in EOC21 11/19/05 None 45 OZ2L-64 0-ISIL4-124B-2.2 Completed in EOC21 11/23/05 None 46 OZ2L-65 O-ISIL4-124B-2.4 Completed in EOC22 05/28/07 None 47 OZ2L-7 O-ISIL4-101A-2.2 Completed in EOC21 11/11/05 None O-ISIL4-101A-2.3 Completed in EOC21 11/11/05 None 48 OZ2L-7B 0-1SIL4-101A-2.3 Completed in EOC21 11/11/05 None 0-ISIL4-102A-2.1 Completed in EOC21 11/11/05 None O-ISIL4-102A-2.2 Completed in EOC21 11/11/05 None 49 OZ2L-89 O-ISIL4-116C-2.1 Completed in EOC21 11/04/05 None 50 OZ2L-9 0-ISIL4-101A-2.3 Completed in EOC21 11/19/05 None 0-ISIL4-102A-2.1 Completed in EOC21 11/19/05 None 0-ISIL4-102A-2.2 Completed in EOC21 11/19/05 None 51 OZ2L-90 O-ISIL4-116C-2.1 Completed in EOC21 11/04/05 None 52 OZ2L-91 O-ISIL4-116C-2.1 Completed in EOC21 11/04/05 None 2 This zone was completed during the Refueling Outage Report EOC21 cycle but was not included in that report. As such, this test is being included in Outage Report EOC22.Refueling Outage Report EOC22 Oconee Unit 2 Section 6 Page 5 of 5 Revision 0 June 13, 2007