Text

Unit 1 End of Cycle (EOC) 26 Refueling Outage, Inservice Inspection (ISI) Report, Fourth Ten-Year Inservice Inspection Interval
	ML11257A261
Person / Time
Site:	Oconee
Issue date:	09/07/2011
From:	Gillespie T; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML11257A261 (189)
	v • d • e

T. PRESTON GILLESPIE, JR.Vice President SEnergy, Oconee Nuclear Station Duke Energy ON01 VP / 7800 Rochester Hwy.Seneca, SC 29672 864-873-4478 September 7, 2011 864-873-4208 fax T. Gillespie@duke-energy.

com U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Duke Energy Carolinas, LLC.Oconee Nuclear Station, Unit 1 Docket No. 50-269 Unit 1 End of Cycle (EOC) 26 Refueling Outage Inservice Inspection (ISI) Report Fourth Ten-Year Inservice Inspection Interval Duke Energy Carolinas, LLC (Duke Energy) is providing a copy of the Inservice Inspection Report for the Oconee Nuclear Station (ONS), Unit 1 EOC-26 Refueling Outage. This report is submitted pursuant to Section XI of the ASME Boiler and Pressure Vessel Code, 1998 Edition, with 2000 addenda, Subsubarticles IWA-6230 and IWA-6240.This report does not include activities specific to the Steam Generator Tube Inservice Inspection.

Duke Energy will transmit separately, a summary report that documents the Steam Generator Tube Inservice Inspection of the ONS, Unit 1 EOC-26 Refueling Outage.If there are any questions you may contact Corey Gray ONS Regulatory Compliance group, at (864)-873-6325.

Sincerely, T1:6LLQ"PIL T.VPreston Gillespie, Jr.Vice President Oconee Nuclear Station Attachment A4J~www. duke-energy, com U. S. Nuclear Regulatory Commission September 7, 2011 Page 2 Xc w/ attachment:

Victor McCree Region II Administrator U. S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Ga 30303-1257 John Stang Project Manger U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Xc w/o attachment Andy Sabisch NRC Senior Resident Inspector Oconee Nuclear Station Susan Jenkins Section Manager Division of Waste Management Bureau of Land and Waste Management SC Dept. of Health & Environment Control 2600 Bull St.Columbia SC 29201 FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 1. Owner. Duke EnerwvCarolinias.

526 S. Church St.. Chalotte.

NC 28201-1006 (Name and Address of Owner)2. PlantL Oconee Nuclear Station. 7800 Rochester Highway. Seneca. SC 29672 (Name and Address of Plant)3. Plant Unit 1 4. Owner Certificate of Authorization (if required)

NIA 5. Commercial Service Date: Jul, I.819 6. National Board Number for Unit NIA 7. Components Inspected:

Component or Appurtenance Manufacturer Installer Manufacturr Installer Serial No.State or Province No.National Board No.See Section 1.1 in the Attached Rpr Note: Supplemental sheets in the form of lists, sketches, or drawings maybe used provided (1) size is 8112 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 187E.

FORM NIS-1 (Back)8. Examination Dates December 4.2009 to June 9. 2011 9. Inspection Period Identification:

10. Inspection Interval Identification:

11. Applicable Edition of Section XI 12. Date/Revision of Inspection Plan: Third Period Fourth Interval 1998 Addenda 2000 January 26. 2008/Revision I 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. See Sections 4.0 and 6.0 15. Abstract of Corrective Measures.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 Xl, 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 Dat V/7/0&( Siged Duke Energy By Date Ou e .& sine J"Y Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issue by the National Board of Boiler and Pressure Vessel Inspectors and the State Province of _ / rAc empIoyedbyHSqGolaI§Wndadshave insi components described In t~ir- Owieres Report during the period y-'elzoI-to , and state that to the best of my knowledge and belief, the Omer has perfofmed'examinations and tests and taken corrective measures described in the Owner's Report in accordance with the Inspecti Plan and as required by the ASME Code, Section Xl.By signinots r ane e Inspector nor his employer makes any warranty, expressed or implied, c olling the emion, test, and corrective measures described in this Owners Report.Furthermo ri n er theh r or his employer shall be liable in any manner for any personal injury or ppr0 7 dpmJ or- 0 ny ind arising from or connected with this Inspection YV Commissions A041AA f'I A4_£~, lh~e§oiUgnrefTr' N oand. State, Pro~ir,, and Endorsements Date HSB Global Standards 200 Ashford Center North Suite 205 Atlanta, GA. 30338-4860 (800) 417-3721 www.hsbglobalstandards.com Owner's Report For INSERVICE INSPECTIONS OCONEE UNIT 1 2011 REFUELING OUTAGE EOC26 (OUTAGE 5)Plant Location:

7800 Rochester Highway, Seneca, South Carolina 29672 NRC Docket No. 50-269 Commercial Service Date: July 15, 1973 Document Completion Date 9 Z-Of Owner-. Duke Energy Carolinas 526 South Church St.Chadotte, N. C. 28201-1006 Revision 0 Originated By: Checked By.Approved By-A-uv Date Date Date 9-1-7. IOf DISTRIBUTION LIST 1. Duke Energy Carolinas Nuclear Technical Services Division Section XI Inspection Program Section 2. NRC Document Control Desk 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 Services (ISI Coordinator)

HSB Global Standards (AIA)C/o ANII at Oconee TABLE OF CONTENTS Section Title Revision 1.0 General Information 0 2.0 Fourth Ten Year Interval 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 I EOC 26 (Outage 5 of the fourth interval).

This is the first outage in the third 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.

This report includes 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 which contains completed NIS-2 forms.1.1 Identification Numbers Manufacturer Item Manufacturer or Installer State or National or Installer Serial No. Province No. Board No.Reactor Vessel Babcock & Wilcox 620-0003-51-52 N/A N-101 Reactor Vessel Babcock & Wilcox 068S-01 N/A 202 Head (replaced head) _Steam Generator A Babcock & Wilcox 006K01 N/A 205 Steam Generator B Babcock &Wilcox 006K02 N/A 206 Pressurizer Babcock & Wilcox 620-0003-59 N/A N-102 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 Vents and Exhaust Duke Power NA NA NA System EOC 26 Refueling Outage Report Oconee Unit 1 Section 1 Page 1 of 4 Revision 0 August 4, 2011 Manufacturer Item Manufacturer or Installer State or National or Installer Serial No. Province No. Board No.Condenser Duke Power NA NA NA Circulatinq 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 26 Refueling Outage Report Oconee Unit 1 Section 1 Page 2 of 4 Revision 0 August 4, 2011 1.2 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 Energy's Corporate Office in Charlotte, North Carolina.Code Case N-460 / Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division I. Applicable to items in this report where less than 100% coverage of the required weld examination volume was achieved.Code Case N-504-2 / Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping. (Applicable to welds that received weld overlay.)Code Case N-609 / Alternate Requirements to Stress-Based Selection Criteria for Category B-J Welds, Section Xl, Division 1 Code Case N-624 / Alternative to the requirements of IWB-2420(a), IWC-2420(a), IWD-2420(a), and IWF-2420(a).

This will allow the sequence of component examinations that were established during the first inspection interval to be modified, provided that the percentage requirements are still met.Code Case N-663 / Alternative Requirements for Classes I and 2 Surface Examinations,Section XI, Division I Code Case N-665 / Alternative Requirements for Beam Angle Measurements using Refracted Longitudinal Wave Search Units Code Case N-683 (Method for Determining Maximum Allowable False Calls when Performing Single Sided Access Performance Demonstration in Accordance With Appendix VIII, Supplements 4 and 6.)Code Case N-685 / Lighting Requirements for Surface Examinations Code Case N-695 / Qualification Requirements for Dissimilar Metal Piping Welds,Section XI, Division I Code Case N-700 / Alternative Rules for Selection of Classes 1, 2 and 3 Vessel Welded Attachments for Examination Section XI, Division 1. (Categories B-K, C-C, and D-A)Code Case N-706 / Alternative Examination Requirements of Table IWB-2500-1 and Table IWC-2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers..

For Oconee it affects Category C-A. This code case will be used only on C1.10 items on the Decay Heat Coolers for all 3 Oconee Units.EOC 26 Refueling Outage Report Page 3 of 4 Oconee Unit I Revision 0 Section 1 August 4, 2011 Code Case N-722 / Additional Examinations for PWR Pressure retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 MaterialsSection XI, Division 1) 1 0CFR Part 50, Federal Register, Final Rule that was issued September 10, 2008 mandates the use of this code case. (Effective Date is October 10, 2008)Duke Power Company Problem Investigation Process (PIP) Report 0-11-06923.

This PIP was written to track the evaluation process and resolution for limited coverage on UT examinations of welds that were inspected during EOC-26 for Unit 1. This will include processing relief request if it is determined that greater than ninety percent of coverage cannot be achieved.

The welds with limited coverage are listed in Section 4.4 of this report.PIP 0-09-0848 was written to incorporate Code Case N-609 into the Fourth Interval ISI Plan.PIP G-08-0185 was written to incorporate Code Case N-663 into the Fourth Interval ISI Plan.PIP 0-10-1242 was written to remove C2.32 items as a result of an SER received for RFR 10-ON-001.

PIP 0-11-09131 was written to document the work orders that had work completed during the 1 EOC-26 report period but the documentation was not completed in time for the NIS-2 forms to be incorporated into I EOC-26 report.Request for Relief 03-006 / Allows Duke an Alternative for the Snubber Examinations required in IWF-5000 for the 4 interval.Request for Relief 07-ON-001

/ Allows Duke an Alternative for Section XI inspection requirements to support the application of Structural Weld Overlays on Nozzle to SE Welds (Summary Numbers O1.Q1.1).Request for Relief 1 0-ON-001 / Allows Duke an Alternative to the required ultrasonic (UT) inspection of the LPI Cooler nozzle welds.EOC 26 Refueling Outage Report Page 4 of 4 Oconee Unit 1 Revision 0 Section 1 August 4, 2011 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 XI 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 I Inspections Examination Inspections Inspections Percentage (1) Deferral Category Description Required Completed Completed Allowed B-A Pressure Retaining Welds 13 0.5 4% Yes in Reactor Vessel B-B Pressure Retaining Welds 10 6 60% ..No in Vessels Other than Reactor Vessel ....B-D Full Penetration Welds of 54 38 70% Partial Nozzles in Vessels Inspection Program B B-F Pressure Retaining 2 0 0% Yes Dissimilar Metal Welds B-G-1 Pressure Retaining Bolting 125 125 100% Yes Greater than 2 Inches in Diameter B-G-2 Pressure Retaining Bolting 22 22 100% No 2 Inches and Less in Diameter B-J Pressure Retaining Welds 151 139 92% No in Piping B-K Welded Attachments for 9 8 89% No Vessels, Piping, Pumps and Valves EOC 26 Refueling Outage Report Oconee Unit 1 Section 2 Page 1 of 4 Revision 0 August 4, 2011 Class I Inspections (Continued)

Examination Inspections Inspections Percentage (1) Deferral.Category Description Required Completed Completed Allowed B-L-1 Pressure Retaining Welds 1 1 100% Yes in Pump Casings B-L-2. Pump Casings 1. 0 0% Yes B-M-1 Pressure Retaining 1 1 100% Yes Welds in Valve Bodies B-M-2 Valve Bodies 3 3 100% Yes B-N-1 Interior of Reactor Vessel 3 2 67% No B-N-2 Welded Core Support 3 0 0% Yes Structures and Interior Attachments to Reactor Vessels B-N-3 Removable Core Support 1 0 0% Yes Structures B-0 Pressure Retaining Welds 12 8 67% Yes in Control Rod Housings 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 I Component 37 Supports 34 Supports 92% No F1.10 & F1.040 Supports (Except items. Snubbers)F-A Class 1 Component F1.050 items Supports, Snubbers (2)Weld Overlay per Section Xl Appendix Q EOC 26 Refueling Outage Report Oconee Unit 1 Section 2 Page 2 of 4 Revision 0 August 4, 2011 Class 2 Inspections Examination Inspections Inspections Percentage Category Description Required Completed Completed C-A Pressure Retaining Welds 11 9 82%in Pressure Vessels C-B Pressure Retaining Nozzle 4 4 100%Welds in Vessels C-C Integral Attachments for 37 35 95%Vessels, Piping, Pumps and Valves C-D Pressure Retaining Bolting 2 1 50%Greater Than 2 Inches in Diameter C-F-1 Pressure Retaining Welds 175 144 82%in Austenitic Stainless Steel or High Alloy Piping C-F-2 .Pressure Retaining Welds 72 61 85%in Carbon or Low Alloy Steel Piping C-G Pressure Retaining Welds 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 138 115 83%F1.020 & F1.040 Supports (Except items_ Snubbers)F-A Class 2 Component Fl.050 items Supports, Snubbers (2)EOC 26 Refueling Outage Report Oconee Unit 1 Section 2 Page 3 of 4 Revision 0 August 4, 2011 Augmented/Elective Inspections Item Number Description Percentage Completed 01.B4.30 Head with Nozzles and Partial No items scheduled for EOC 26 Penetration Welds, Bare Metal Visual per Code Case N-729-1 01 .B4.40 Head with nozzles and Partial No items scheduled for EOC 26 Penetration Welds, Volumetric/Surface exam per Code Case. N-729-1 01 .B15.80 Reactor Vessel Bottom Head Bare 100% of EOC 26 Requirements Metal Visual per Code Case N-722 01 .B15.140 Pressurizer, Bare Metal Visual per 100% of EOC 26 Requirements Code Case N-722 01 .B15.210 Hot Leg Full Penetration Weld, Bare 100% of EOC 26 Requirements Metal Visual per Code Case N-722 01.B15.215 Cold Leg Full Penetration Weld, Bare 100% of EOC 26 Requirements Metal Visual per Code Case N-722 O1 .G1.1 Reactor Coolant Pump Flywheel No items scheduled for EOC 26 O1.G2.1 HPI Nozzle Safe End Examinations

100% of EOC 26 Requirements O1 .G3.1 Pressurizer Surge Line Examinations No items scheduled for EOC 26 O1.G4.1 Thermal Stress Piping (NRC Bulletin 100% of EOC 26 Requirements 88-08)O1.G12.1 UT Examination per MRP-139 No items scheduled for EOC 26 01 .G12.2 UT Examination per MRP-139. No items scheduled for EOC 26.01.G16.1 UT Examination per MRP-146 100% of EOC 26 Requirements

.01 .H2.1 Class I RTE Mounting Bosses 100% of EOC 26 Requirements 01..H3.1 Main Feedwater Piping in the East No items scheduled for EOC 26 and West Penetration Rooms per QA-513J (ER-ONS-04-03) 01.1-14.1 Main Feedwater and Main Steam 100% of EOC 26 Requirements Piping Supports and Attachment Welds per QA-513J (ER-ONS-04-05) 01..H5.1 East Penetration Main Feedwater 100% of EOC 26 Requirements piping welds and attachments I 01 .H6.1 Main Feedwater rupture restraint 100% of EOC 26 Requirements attachment welds (1) Deferral of inspection to the end of the interval as allowed by ASME Section XI Tables IWB and IWC 2500-1.(2) Inspected under Selected License Commitment 16.9.18 per Relief Request 03-006.(3) All weld overlays are scheduled and examined per Appendix Q.EOC 26 Refueling Outage Report Oconee Unit 1 Section 2 Page 4 of 4 Revision 0 August 4, 2011 3.0 Final Inservice Inspection Plan The final Inservice Inspection Plan Report shown in this section lists all ASME Section XI Class 1, Class 2, Class 3, and Augmented/Elective Examinations credited for this report period.EOC 26 Refueling Outage Report Oconee Unit 1 Section 3 Page 1 of 1 Revision 0 August 4, 2011 ScheduleWorks DUKE ENERGY NUCLEAR TECHNICAL SERVICES Inservice Inspection Database Management System Plan Report Oconee 1, 4th Interval, Outage 5 (EOC-26)This report includes all changes through addendum ONSI-137 Summary Num Category AUG 01..B15.140.0001 Component ID ISOIDWG Numbers Class I System Procedure Insp Req Material Sched ThicklNPS Cal Blocks Description Comments Componenet ID 2 1-PZR-HTR PLATES Class 1 50 NDE-68 VT-2 CS-Inconel 0.000 / 0.000 OM 201-288 Dissimilar Nozzle to Safe End Heater Diaphragm Plate to PZR SS Clad welds located on the Pressurizer.

(3 welds total)Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program Implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector of the PZR welds per the requirements of Code Case N-722. (Item Number B15.140).B15.140 Items are to be examined every refueling outage from the start date.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.01 .B15.140.0002 1-PZR-HTR-SLEEVES Class 1 50 OM 201-288 OM 201-152 NDE-68 VT-2 CS-Inconel 0.000 / 0.000 Dissimilar Nozzle to Safe End PZR heater sleeves to diaphragm welds and SS heater sheath welds located on the Pressurizer. (total of 117 welds)Per the requirements of 10 CFR 50.55a (g) (6) (1i) (E), all licensees of PWRs shall augment their ISI program Implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector of the PZR welds per the requirements of Code Case N-722. (Item Number B16.140).B1 5.140 items are to be examined every refueling outage from the start date.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferdtic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." For additional Information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/11 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7t25/2011 11:03:04 AM -Page 1 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThickINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG O1.B15.210.0001 1RC-269-125V Class 1 50 1 RC-269 NDE-68 VT-2 SS-Inconel 0.250 11.000 OM 201-0738 Dissimilar OM 201-0181 Pipe to Safe End 1 inch HL SB- 66 Pressure Tap SE to CS Nozzle weld and SS pipe weld. This weld is located on piping that branches off of "A" Hot Leg.(Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 6001821182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." This B15.210 item Is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.01.115.210.0002 1-50-4-125 Class 1 50 1-50-4(3)

NDE-68 VT-2 SS-Inconel 1.187 11.000 OM 201-0181 Dissimilar OM 201-0738 Pipe to Safe End 1 Inch HL SB- 66 Pressure Tap SE to CS Nozzle weld and SS pipe weld. This weld is located on piping that branches off of "A" Hot Leg.(Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Per the requirements of 10 CFR 60.55a (g) (6) (11) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector per the requirements of applicable item numbers listed In Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This B15.210 item is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/11 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011-11:03:04 AM Page 2 of 78 This report Includes all changes through addendum ONSI.137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG __......O1.B15.210.0003 1RC-273-143V Class 1 50 1RC-273 NDE-68 VT-2 SS-Inconel 1.187 /1,000 OM 201-0181 Dissimilar OM 201-0738 Pipe to Safe End 1 inch HL SB-166 Pressure Tap SE to CS Nozzle weld and SS pipe weld. This weld is located on piping that branches off of "B" Hot Leg.(Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified In paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training In detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This B15.210 item is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.01.115.210.0004 1-50-4-143 Class 1 50 1-50-4(1)

NDE-68 VT-2 SS-Inconel 0.250 /1.000 OM 201-0181 Dissimilar OM 201-0738 Pipe to Safe End 1 Inch HL SB-166 Pressure Tap SE to CS Nozzle weld and SS pipe weld. This weld is located on piping that branches off of "B" Hot Leg.(Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600182/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." This B16.210 item is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/11 1gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04 AM Page 3 of 78 This report includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThIckINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG-01.B15.210.0005 1-50-4-131 Class 1 50 1-50-4(1)

NDE-68 VT-2 SS-Inconel 0.250 / 1.000 OM 201-0181 Dissimilar OM 201-0738 Pipe to Safe End 3/4 inch ID HL SB-166 Flowmeter Noz SE to CS Nozzle weld and SS pipe weld.(Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)This weld is located on piping that branches off of "A" Hot Leg.Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This B15.210 item Is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.01.B15.210.0006 1-50-4-135 Class 1 50 1-50-4(3)

NDE-68 VT-2 SS-Inconel 0.250/ 1.000 OM 201-0181 Dissimilar OM 201-0738 Pipe to Safe End 3/4 inch ID HL SB-166 Flowmeter Noz SE to CS Nozzle weld and SS pipe weld.(Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)This weld Is located on piping that branches off of "A" Hot Leg.Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table I of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." This B15.210 item Is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/11 gds5841 v. 06/18/09 SDQA Cat "C". Oconee 1 7/25/2011 11:03:04 AM Page 4 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThlckINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 01.B15.210.0007 1-50-4-44A Class 1 50 1-50-4(1)

NDE-68 VT-2 SS-Inconel 0.250/ 1.000 OM 201-0181 Dissimilar OM 201-0738 Pipe to Safe End 3/4 inch ID HL SB-166 Flowmeter Noz SE to CS Nozzle weld and SS pipe weld.(Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)This weld is located on piping that branches off of "B" Hot Leg.Per the requirements of 10 CFR 50.55a (g) (6) (1i) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training In detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." This B15.210 item is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.O1.B15.210.0008 1-50-4-150 Class 1 50 1-50-4(1)

NDE-68 VT-2 SS-Inconel 0.250 / 1.000 OM 201-0181 Dissimilar OM 201-0738 Pipe to Safe End 3/4 Inch ID HL SB-166 Flowmeter Noz SE to CS Nozzle weld and SS pipe weld.(Examine the Nozzle to Safe-End weld and the Safe-End to Pipe weld.)This weld is located on piping that branches off of "B" Hot Leg.Per the requirements of 10 CFR 50.55a (g) (6) (i) (E), all licensees of PWRs shall augment their ISI program Implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent feritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This B15.210 Item is to be examined each refueling outage.For additional Information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/11 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04AM Page 5of78ý_rinied 6-7/2-5/1

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v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11ý.03:04 AM Page 5 of 78 This report includes all changes through addendum ONS1-137 Oconee 1, 4th Interval, outage 5 (EOC.26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThickINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG O1.B15.210.0009 1-PHA-13 Class 1 50 ISI-OCNI-005 NDE-68 VT-2 CS-Inconel 2.875/ 9.000 OM-201-2296 Dissimilar OM 201-0181 Pipe to Pipe RTE Mounting Boss SB-166 to 690 Drywell Weld on 1A Hotleg (X-Axis)Hot Leg (Piece 7) to RTE Mounting Boss (piece 12).Per the requirements of 10 CFR 50.58a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (11) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable Item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This B15.210 Item Is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.O1.B15.210.0010 1-PHA-14 Class 1 50 ISI-OCN1-005 NDE-68 VT-2 CS-Inconel 2.875/9.000 OM-201-2296 Dissimilar OM 201-0181 Pipe to Pipe RTE Mounting Boss SB-166 to 690 Drywell Weld on 1A Hotleg ( Y-Z Axis)Hot Leg (Piece 7) to RTE Mounting Boss (piece 12).Per the requirements of 10 CFR 50.65a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified In paragraphs (g) (6) (iI) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." This B15.210 item Is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/11 gds5841 v. 06/18/09 SDQACaI"C" Oconee 1 7/25/2011 11:03:04 AM Page 6 of 78 This report includes all changes through addendum ONS1-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG .._._......01.B15.210.0011 1-PHA-15 Class 1 50 ISI-OCN1-005 NDE-68 VT-2 CS-Inconel 2.8751 9.000 OM-201-2296 Dissimilar OM 201-0181 Pipe to Pipe RTE Mounting Boss SB-166 to 690 Drywell Weld on 1A Hotleg (Z-W Axis)Hot Leg (Piece 7) to RTE Mounting Boss (piece 12).Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table I of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training In detection of borated water leakage from alloy 600/821182 components and the resulting boric acid corrosion of adjacent feritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage.*This B15.210 item is to be examined each refueling outage.For additional Information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.01.815.210.0012 1-PHB-13 Class 1 50 ISI-OCN1-006 NDE-68 VT-2 CS-lnconel 2.875/9.000 OM-201-2296 Dissimilar OM 201-0181 Pipe to Pipe RTE Mounting Boss SB-166 to 690 Drywell Weld on 1B Hotleg (X-Axis)Hot Leg (Piece 7) to RTE Mounting Boss (piece 12).Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT.2 visual examiners and shall have completed a minimum of four hours of additional training In detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferrltic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This B15.210 item is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/11 gds5841 v. 06/18109 SDQA Cat "C" Oconee 1 7125/2011 11:03:04 AM Page 7 of 78 This report Includes all changes through addendum ONS1-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThickINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG O1315.210.0013 1-PHB-14 Class 1 50 ISI-OCN1-006 NDE-68 VT-2 CS-Inconel 2.8751 9.000 OM-201-2296 Dissimilar OM 201-0181 Pipe to Pipe RTE Mounting Boss SB-166 to 690 Drywall Weld on 1B Hotleg ( Y-Z Axis)Hot Leg (Piece 7) to RTE Mounting Boss (piece 12).Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augmeni their ISI program Implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table I of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600182/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This B15.210 item is to be examined each refueling outage.___.__ For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.O1.B15.210.0014 1-PHB-15 Class 1 50 ISI-OCNI-006 NDE-68 VT-2 CS-Inconel 2.875 / 9.000 OM-201-2296 Dissimilar OM 201-0181 Pipe to Pipe RTE Mounting Boss SB-1 66 to 690 Drywall Weld on 1B Hotleg ( Z-W Axis)Hot Leg (Piece 7) to RTE Mounting Boss (piece 12).Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified In paragraphs (g) (6) (1i) (E) 2 through 4.Bare Metal Visual inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed In Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferrItic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." This B15.210 item is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/111 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04 AM Page 8 of 78 This report Includes all changes through addendum ONS1-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThicklNPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 01..B15.210.0015 1SGA-HL-CON-27 Class 1 50 OM-201-0351.001 NDE-68 VT-2 CS-Inconel O-ISIN4-10OA-1I.1 Dissimilar OM-201-0181.001 RTE Hot Leg Thermal Well Steam Generator A Hot Leg Connection

27 on drawing OM 201-0351.001 and Mark # 10 on drawing OM-201-0181.001 Abandoned RTE Thermal Well Connection Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600182/182 components and the resulting boric acid corrosion of adjacent feritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This B15.210 Item Is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.O1.B15.210.0016 1SGB-HL-CON-36 Class 1 50 OM-201-03511.001 NDE-68 VT-2 CS-Inconel O-ISIN4-100A-1.1 Dissimilar OM-201-0181.001 RTE Hot Leg Thermal Well Steam Generator B Hot Leg Connection

36 on drawing OM 201-0351.001 and Mark # 10 on drawing OM-201-0181.001 Abandoned RTE Thermal Well Connection Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This B15.210 item is to be examined each refueling outage.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/11 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04 AM Page 9 of 78 This report includes all changes through addendum ONS1-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thlck/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 01.B15.215.0010 1-PDA2-2 Class 1 50 ISI-OCN1-012 NDE-68 VT-2 SS-CS 2.330 1 33.500 0-ISIN4-100A-1.1 Dissimilar OM-201-1844 Stress Weld Safe End to Elbow Reactor Coolant Pump 1A2 Discharge Piping. Safe End Pc. 213 to 13 Degree Elbow Pc. 212.Per the requirements of 10 CFR 50.558 (g) (6) (1i) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified In paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable Item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." This item is to be examined once per interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.O1.B15.215.0011 1-PDBl-2 Class 1 50 ISI-OCN1-013 NDE-68 VT-2 SS-CS 2.330 133.500 0-ISIN4-100A-1.1 Dissimilar OM-201-1845 Stress Weld Safe End to Elbow Reactor Coolant Pump 1B1 Discharge Piping. Safe End Pc. 213 to 13 Degree Elbow Pc. 212.Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training In detection of borated water leakage from alloy 600/821182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." This item is to be examined once per interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.ýr-inted 6745-111 gds'5'8'-41v.

0-6/-1-8/-O'g-SDQA Cat "C" Oconee 1 7/25/2011 11:03:04 AM Page 10 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThickINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 01.B15.215.0012 1-PDB2-2 Class 1 50 ISI-OCN1-014 NDE-68 VT-2 SS-CS 2.330 33.500 O-ISIN4-100A-1.1 Dissimilar OM-201-1844 Stress Weld Safe End to Elbow Reactor Coolant Pump 1B2 Discharge Piping. Safe End Pc. 213 to 13 Degree Elbow Pc. 212.Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable Item numbers listed In Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent feritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This item Is to be examined once per interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.O1.B15.215.0015 1-PDA1-11 Class 1 51A ISI OCN1-011 NDE-68 VT-2 SS-Inconel 0.750/ 3.600 OM-201-597 Dissimilar Nozzle to Safe End 1A1 Make-Up Nozzle Pc. 46 to Safe End Pc. 47.Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program Implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector per the requirements of applicable Item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training In detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This item is to be examined once per interval.For additional Information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.This exam was moved from EOC27 to EOC-26 per request from Max Hipps at Oconee. Chris Cruz was in agreement with the schedule being changed. See Plan addenda ONS1-122.Printed 07/25/11 gds5841 v.06/18/09 SOQA Cat C" Oconee 1 7/25/2011 11:03:04AM Page 11 of 78 Printed 07/25111 gds5841 v. 06118/09 SDQA Cat "C" Oconee 1 7125/2011 111:03:04 AM Page 11 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThickINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG O1.B15.215.0016 1-PDA2-11 Class I 51A ISI OCN1-012 NDE-68 VT-2 CS-SS 0.7501 3.500 OM-201-597 Dissimilar Nozzle to Safe End 1A2 Make-Up Nozzle Pc. 46 to Safe End Pc. 47.Per the requirements of 10 CFR 50.55a (g) (6) (i1) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified In paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600182/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This item is to be examined once per Interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.This exam was moved from EOC27 to EOC-26 per request from Max Hipps at Oconee. Chris Cruz was in agreement with the schedule being changed. See Plan addenda ONS1-122.O1.B15.215.0017 1-50-4-115 Class 1 50 1-50-4(3)

NDE-68 VT-2 SS-Inconel 0.250 /1.000 Dissimilar Pipe to Safe End 1 inch LCL SB-166 Pressure Tap SE to CS Nozzle and SS pipe weld. This piping is branching off of Pump 1A1 Suction piping.(Examine the nozzle to Safe-End Weld and the Safe-End to Pipe weld.)Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their 181 program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This item is to be examined once per interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.i5nnted '07/25/11 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04 AM Page 12 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Inap Req Material Sched ThickINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 01.115.215.0019 1-PIAl-11 Class 1 50 ISI-OCNI-007 NDE-68 VT-2 CS-Inconel 0.816/3.500 O-ISIN4-100A-1.1 Dissimilar OM-201-1870 Stress Weld Nozzle to Safe End Reactor Coolant Pump 1A1 Suction Piping. Drain Nozzle Pc. 64 to Safe End Pc. 65.Per the requirements of 10 CFR 50.55a (g) (6) (il) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector per the requirements of applicable item numbers listed In Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." This Item is to be examined once per interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.01.B15.215.0020 1-50-01-34 Class 1 50 1-50-01(1)

NDE-68 VT-2 SS-Inconel 0.281 /1.500 O-ISIN4-100A-1.1 Dissimilar ISI-OCN1-007 Stress Weld Safe End to Elbow Reactor Coolant Pump 1Al Suction Piping. Safe End Pc. 65 to Elbow.Per the requirements of 10 CFR 50.55a (g) (6) (ii) (E), all licensees of PWRs shall augment their ISI program Implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This item Is to be examined once per interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25/11 gds5841 v.06/18/09 SOQA Cat C" Uconee I 7125/2W 1 11 :u3:U4 AM I~age 13 0? 7~Printed 07/25/11 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04 AM Page 13 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC.26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThickINPS Cal Blocks Class I System Description Comments Componenet ID 2 Category AUG 01.B15.215.0021 1-PIA2-11 Class 1 50 Dissimilar Stress Weld ISI-OCN1-008 0-ISIN4-10OA-1.1 OM-201-1870 NDE-68 VT-2 CS-Inconel 0.816 / 3.500 Nozzle to Safe End Reactor Coolant Pump 1A2 Suction Piping. Drain Nozzle Pc. 64 to Safe End Pc. 65.Per the requirements of 10 CFR 50.55a (g) (6) (I1) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed In Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training In detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent feritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This item is to be examined once per Interval.For additional informatlon, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.01.B15.215.0022 1-50-01-21 Class 1 50 Dissimilar Stress Weld 1-50-01(1) 0-ISIN4-100A-1.1 ISI-OCN1-008 NDE-68 VT-2 SS-Inconel 0.281 / 1.500 Safe End to Elbow Reactor Coolant Pump 1A2 Suction Piping. Safe End Pc. 65 to Elbow.Per the requirements of 10 CFR 50.55a (g) (6) (11) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector per the requirements of applicable item numbers listed in Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training In detection of borated water leakage from alloy 600/82J182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This item is to be examined once per interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/25111 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04 AM Page 14 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThIclINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 01.B15.215.0029 1-PIB1-12 Class 1 50 ISI-OCN1-009 NDE-68 VT-2 CS-lnconel 2.250/8.750 OM-201-1845 Dissimilar Salvaged Pipe to Pipe RTE Mounting Pipe (Piecce 58 to Piece 215). This weld is located at the Z-W Quadrant on Pump 181 Suction Piping.Per the requirements of 10 CFR 50.55a (g) (6) (1i) (E), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified In paragraphs (g) (6) (II) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified Inspector per the requirements of applicable item numbers listed In Table 1 of Code Case N-722.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria is "no evidence of borated water leakage." This item is to be examined once per Interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.01.B15.80.0001 1-RPV-BMI-NOZZLES Class 1 50 0-ISIN4-100A-1.1 NDE-69 Alloy 600/SS NA/ NA Dissimilar RPV Bottom Head BMI Nozzles Per the requirements of 10 CFR 50.55a(gX6)(iiXE), all licensees of PWRs shall augment their ISI program implementing ASME Code Case N-722 subject to the conditions specified in paragraphs (g) (6) (ii) (E) 2 through 4.Bare Metal Visual Inspection by VT-2 qualified inspector of the BMI Nozzles per the requirements of Code Case N-722. (Item Number B15.80).B15.80 Items, bare metal visual examinations are on the reactor vessel bottom head, bottom mounted instrument nozzles and alloy 600 transition weld between the alloy 600 tube and the stainless steel tube.B15.80 Items are to be examined every other refueling outage from the start date.Personnel performing the visual examination shall be qualified as VT-2 visual examiners and shall have completed a minimum of four hours of additional training in detection of borated water leakage from alloy 600/82t182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Procedure NDE 68, Acceptance Criteria Is "no evidence of borated water leakage." Procedure NDE-68 In conjunction with MP/0/AII11501030 should be used to perform the Bare Metal Visual Inspection.

For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Item was rescheduled from 1 EOC27 to 1EOC26 per QA-513J/ER-ONS-11-03.

FriMed /ý-5/1 1 gds5841 v. 06/1 SDOA Cat "C" POcnee 1 7-/25/2011 11:03:04 AM Page 15 of 78 This report Includes all changes through addendum ONS1-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThicklNPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG O1.G16.1.0001 1-50-01-21 Class 1 50 1-50-01(1)

NDE-995 UT SS-Inconel 0.281 1 1.500 50202 O-ISIN4-100A-1.1 Dissimilar ISI-OCN1-008 Stress Weld Safe End to Elbow Reactor Coolant Pump 1A2, Suction Piping (J-Leg), Safe End Pc. 65 to Elbow.Augmented Inspection by ultrasonic examination to identify thermal fatigue cracking on the inside surface of RCS drain line piping downstream of the RCS connection on 1A2 cold leg. This examination is for weld 1-50-01-21.

See Figure 1 in procedure NDE-995 for details on the areas to be examined for this weld.NRC Commitment for MRP-146 requires an ultrasonic examination to identify thermal fatigue cracking on the Inside surface of RCS drain line piping downstream of the RCS connection.

Examination includes both welds (located at each end of the elbow)and the elbow base metal. Procedure NDE-995 shall be used to perform the UT examination.

For additional information, contact Dave Peltola from the Oconee Civil Engineering Section.The welds/areas for G16.1 items are to be examined once every ten years from the start date (Unit 1 EOC-26). The examinations should be performed during refueling outage. See QA-513-J form with tracking number ER-ONS-08-09 for more details.O1.G16.1.0002 1-50-01-258 Class 1 50 1-50-01(1)

NDE-995 UT SS 0.281 11.500 50202 Elbow to Pipe Drain Line Piping that branches off of Reactor Coolant Pump 1A2 Suction Piping (J-Leg). On weld Iso 1-50-01(1) examine weld #258.Augmented Inspection by ultrasonic examination to Identify thermal fatigue cracking on the Inside surface of RCS drain line piping downstream of the RCS connection on 1A2 cold leg. This examination is for weld 1-50-01-258.

See Figure 1 In procedure NDE-995 for details on the areas to be examined for this weld.NRC Commitment for MRP-146 requires an ultrasonic examination to identify thermal fatigue cracking on the inside surface of RCS drain line piping downstream of the RCS connection.

Examination includes both welds (located at each end of the elbow)and the elbow base metal. Procedure NDE-995 shall be used to perform the UT examination.

For additional information, contact Dave Peltola from the Oconee Civil Engineering Section.The welds/areas for G16.1 items are to be examined once every ten years from the start date (Unit 1 EOC-26). The examinations should be performed during refueling outage. See QA-513-J form with tracking number ER-ONS-08-09 for more details.Printed 07125/11 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04AM Page 16 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sc'hed Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG O1.G16.1.0003 1-50-01-ELBOW Class 1 50 1-50-01(1)

NDE-995 UT SS 0.281 11.500 50202 0-IS1N4-100A-1.1 Dissimilar ISI-OCN1-008 Stress Weld Elbow Base Metal Drain Line Piping that branches off of Reactor Coolant Pump 1A2 Suction Piping (J-Leg). On weld Iso 1-50-01(1) examine the elbow base metal on the elbow associated with welds 21 and 258.Augmented Inspection by ultrasonic examination to identify thermal fatigue cracking on the inside surface of RCS drain line piping downstream of the RCS connection on 1A2 cold leg. This examination is for the elbow base metal on the elbow associated with welds 21 and 258. See Figure 5 in procedure NDE-995 for details on the areas to be examined for this elbow.NRC Commitment for MRP-146 requires an ultrasonic examination to identify thermal fatigue cracking on the Inside surface of RCS drain line piping downstream of the RCS connection.

Examination Includes both welds (located at each end of the elbow)and the elbow base metal. Procedure NDE-995 shall be used to perform the UT examination.

For additional information, contact Dave Peltola from the Oconee Civil Engineering Section.The welds/areas for G16.1 items are to be examined once every ten years from the start date (Unit 1 EOC-26). The examinations should be performed during refueling outage. See QA-513-J form with tracking number ER-ONS-08-09 for more details.O1.G16.1.0004 1RC-261-266 Class 1 50 1RC-261 NDE-995 UT SS-Inconel 0.281 /1.500 50202 O-ISIN4-100A-1.1 Dissimilar ISI-OCN1-010 Stress Weld Safe End to Elbow Reactor Coolant Pump 1B2, Suction Piping (J-Leg), Safe End Pc. 65 to Elbow.Augmented Inspection by ultrasonic examination to identify thermal fatigue cracking on the Inside surface of RCS drain line piping downstream of the RCS connection on 1B2 cold leg. This examination is for weld 1RC-261-266.

See Figure 1 in procedure NDE-995 for details on the areas to be examined for this weld.NRC Commitment for MRP-146 requires an ultrasonic examination to identify thermal fatigue cracking on the inside surface of RCS drain line piping downstream of the RCS connection.

Examination includes both welds (located at each end of the elbow)and the elbow base metal. Procedure NDE-995 shall be used to perform the UT examination.

For additional information, contact Dave Peltola from the Oconee Civil Engineering Section.The welds/areas for G16.1 Items are to be examined once every ten years from the start date (Unit 1 EOC-26). The examinations should be performed during refueling outage. See QA-513-J form with tracking number ER-ONS-08-09 for more details.Printed 07/25/11 gds5841 v.06/18/09 SOQA Cat 'C" Oconee 1 7/25/2011 11:03:04 AM Page 17 of 78 Printed 07125/11 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04 AM Page 17 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Component ID ISOIDWG Numbers Procedure Insp Req Material Sched ThIckINPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG O 1 .16 ..0 0 5 R C 2 6 1 2 6 7 .... --....... ...... ... .. .. ............

... ... .........

-.. .. ... ........ ... ...O1.G16.1.0005 1 RC-261-267 Class 1 50 1RC-261 NDE-995 UT SS 0.281 / 1.500 50202 O-ISIN4-100A-1.1 Elbow to Pipe Drain Line Piping that branches off of Reactor Coolant Pump 1 B2 Suction Piping (J-Leg). On weld iso 1 RC-261 examine weld #267.Augmented Inspection by ultrasonic examination to Identify thermal fatigue cracking on the inside surface of RCS drain line piping downstream of the RCS connection on 1B2 cold leg. This examination is for weld 1RC-261-267.

See Figure 1 in procedure NDE-995 for details on the areas to be examined for this weld.NRC Commitment for MRP-146 requires an ultrasonic examination to identify thermal fatigue cracking on the inside surface of RCS drain line piping downstream of the RCS connection.

Examination includes both welds (located at each end of the elbow)and the elbow base metal. Procedure NDE-9g5 shall be used to perform the UT examination.

For additional Information, contact Dave Peltola from the Oconee Civil Engineering Section.The welds/areas for G16.1 items are to be examined once every ten years from the start date (Unit 1 EOC-26). The examinations should be performed during refueling outage. See QA-513-J form with tracking number ER-ONS-08-09 for more details.O1.G16.1.0006 1RC-261-ELBOW Class 1 50 1RC-261 NDE-995 UT SS 0.281 / 1.500 50202 O-ISIN4-100A-1.1 Dissimilar ISI-OCN1-010 Stress Weld Elbow Base Metal Drain Line Piping that branches off of Reactor Coolant Pump 1B2 Suction Piping (J-Leg). On weld iso 1RC-261 examine the elbow base metal on the elbow associated with welds 266 and 267.Augmented Inspection by ultrasonic examination to Identify thermal fatigue cracking on the inside surface of RCS drain line piping downstream of the RCS connection on 1B2 cold leg. This examination Is for the elbow base metal on the elbow associated with welds 266 and 267. See Figure 5 In procedure NDE-995 for details on the areas to be examined for this elbow.NRC Commitment for MRP-146 requires an ultrasonic examination to identify thermal fatigue cracking on the insidesurface of RCS drain line piping downstream of the RCS connection.

Examination includes both welds (located at each end of the elbow)and the elbow base metal. Procedure NDE-995 shall be used to perform the UT examination.

For additional information, contact Dave Peltola from the Oconee Civil Engineering Section.The welds/areas for G16.1 items are to be examined once every ten years from the start date (Unit 1 EOC-26). The examinations should be performed during refueling outage. See QA-513-J form with tracking number ER-ONS-08-09 for more details.Printed 07/25/11 gds5841 v. 06/18/09 SDQA Cat "C" Oconee 1 7125/2011 11:03:04 AM Page 18 of 78 This report Includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC.26)r Procedure Insp Req Material Sched ThickINPS Cal Blocks Description Comments Summary Num Component ID ISOIDWG Number Class I System Componenet ID 2 Category AUG O1.G2.1.0021 1A1-THERM SLEEVE Class 1 51A ISIOCN1-011 NDE-105 RT SS 0.750 / 3.500 G02.001.011P Circumferential 0-ISIN4-10OA-1.1 Make-Up Nozzle WAl. Perform RT between the nozzle to safe end and safe end to pipe weld in the thermal sleeve expansion area as described in procedure NDE-105. This schedule cannot be changed. Reference Section 7 of the ISI Plan, General Requirements.

RT schedule changed from 1EOC-27 to 1 EOC-26 per QA 513J ER-ONS-1 1-01.O1.G2.1.0022 181-THERM SLEEVE Class 1 51A ISI OCN1-013 NDE-105 RT SS 0.750 / 3.500 G02.001.011C Circumferential 0-ISIN4-100A-1.1 HPI Nozzle 1B1. Perform RT between the nozzle to safe end and safe end to pipe weld in the thermal sleeve expansion area as described in procedure NDE-1 05. This schedule cannot be changed. Reference Section 7 of the IS I Plan. General Requirements.

RT schedule changed from lEOC-27 to 1EOC-26 per QA 513JER-ONS-11-0l..

.. ...O1 .G2.1.0023 1B2-THERM SLEEVE Class 1 51A ISI OCN1-014 NDE-105 RT SS 0.750 3.500 G02.001,011E CircumferenUal O-ISIN4-100A-1.1 HPI Nozzle 1B2. Perform RT between the nozzle to safe end and safe end to pipe weld In the thermal sleeve expansion area as described In procedure NDE-105. This schedule cannot be changed. Reference Section 7 of the ISI Plan, General Requirements.

RTschedule changed from 1EOC-27 to 1EOC-26 per QA.513J ER-ONS-11-01.

O1.G2.1.0024 1A2-THERM SLEEVE Class 1 51A ISI OCN1-012 NDE-105 RT SS 0.750 / 3.500 G02.001.011E Circumferential 0-ISIN4-100A-1.1 Make-Up Nozzle 1A2. Perform RT between the nozzle to safe end and safe end to pipe weld in the thermal sleeve expansion area as described in procedure NDE-105. This schedule cannot be changed. Reference Section 7 of the ISI Plan, General Requirements.

RT schedule changed from 1EOC-27 to 1EOC-26 per QA 513J ER-ONS-11-01.

Printed 07/25/11 gds5841 v. 06/18109 SDQA Cat "C" Oconee 1 7/25/2011 11:03:04 AM Page 19 of 78 This report includes all changes through addendum ONSI-137 Oconee 1, 4th Interval, outage 5 (EOC-26)Summary Num Category AUG Component ID ISOIDWG Numbers Class I System Procedure Insp Req Material Sched Thick/NPS Cal Blocks Description Comments Componenet ID 2 O1 .G4.1.0005 1 HP-255-6 Class i 51A 1HP-255 NDE-995 UT SS 0.375 / 2.500 G04.0011.001 0-ISIN4-101A-1.4 40378 Circumferential Elbow to Pipe Inspect 100% of weld & 1" of base material (axial & circumferential).

This weld was 1-51A-10-6 until iso 1-51A-10 was deleted and welds were transferred to iso 1HP-255. Reference Section 7 of the ISI Plan, General Requirements.

O1 .G4.1.0006 1HP-190-12 Class 1 51A 1HP-190 NDE-995 UT SS 0.375/2.500 G04.001.01, 40378 Circumferential Pipe to Elbow Inspect 100% of weld & 1" of base material (axial & circumferential).

This weld was 1-51A-5-77C until iso 1-51A-5 was deleted and welds transferred to iso 1HP-190. Reference Section 7 of the ISI Plan, General Requirements.

O1.G4.1.0009 1HP-190-16 Class 1 51A 1HP-190 NDE-995 UT SS 0.375/2.500 G04.001.01,1 0-ISIN4-101A-1.4 40378 Circumferential Pipe to Valve IHP-488 Inspect 100% of weld & 1" of base material (axial & circumferential).

Reference Section 7 of the ,SI Plan. Volume 1.O1.G4.1.0010 1HP-190-13 Class 1 51A 1HP-190 0-ISIN4-101A-1.4 NDE-995 UT SS 0.375 / 2.500 G04.001.01(40378 Circumferential Elbow to Pipe Inspect 100% of weld & 1" of base material (axial & circumferential).