Text

EOC 24 Refueling Outage Inservice Inspection Report Fourth Ten-Year Inservice Inspection Interval
	ML092320364
Person / Time
Site:	Oconee
Issue date:	08/14/2009
From:	Baxter D; Duke Energy Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML092320364 (220)
	v • d • e

-Duke DAVE BAXTER OEnergy Vice President Oconee Nuclear Station Duke Energy ON01 VP / 7800 Rochester Highway Seneca, SC 29672 864-873-4460 864-873-4208 fax dabaxter@dukeenergy.

com August 14, 2009 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 3 Docket No. 50-287 Unit 3 EOC 24 Refueling Outage Inservice Inspection Report Fourth Ten-Year Inservice Inspection Interval Please find attached a copy of the Inservice Inspection Report for Oconee Unit 3 End of Cycle 24 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.

An additional summary report which documents the Steam Generator Tube Inservice Inspection of the Unit 3 EOC-24 Refueling Outage will be transmitted separately.

If there are any questions you may contact Corey Gray at (864) 873-6325.Sincerely, A/ Dave Baxter, Site Vice-President Oconee Nuclear Station Attachment 40L-7 www. duke-energy.

corn U. S. Nuclear Regulatory Commission August 14, 2009 Page 2 xc wo/attachment:

Luis Reyes Region II Administrator U.S. Nuclear Regulatory Commission 61 Forsyth Street, S. W., Suite 23T85 Atlanta, GA 30303 John Stang Project Manager U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Eric Riggs NRC Senior Resident Inspector (acting)Oconee Nuclear Station R INSERV ICE-INSPECTION REPORT DUKE ENERGY CAROLINAS OCONEE NUCLEAR STATION UNIT 3 TWENTY-FOURTH REFUELING OUTAGEDuke oEnergy Owner's Report For INSERVICE INSPECTIONS OCONEE UNIT 3 2009 REFUELING OUTAGE EOC24 (OUTAGE 3)Plant Location:

7800 Rochester Highway, Seneca, South 'Carolina 29672 NRC Docket No. 50-287 Commercial Service Date: December 16,1974 Document Completion Date "71V{ OZ'4 Owner: Duke Energy Carolinas 526 South Church St.Charlotte, N. C. 28201-1006 Revision 0 Prepared By: Reviewed By: Approved By: co /1Th Date 16-o Date 7-119o'-y Date 7-/-1-6R 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: 3 4. Owner Certificate of Authorization (if required)

N/A 5. Commercial Service Date: December 16, 1974 7. Components Inspected:

6.National Board Number for Unit N/A 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 217 PFORM NIS-1 (Back)8. Examination Dates'December 18, 2007 to May 21, 2009 9. Inspection Period Identification:

10. Inspection Interval Identification:

11. Applicable Edition of Section Xl 12. Date/Revision of Inspection Plan: Second Period Fourth Interval 1998 Addenda 2000 January 26, 2008/Revision 1 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 Date Signed Duke Energy Carolinas Owner By 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 SorM CAILoLiA,, employed by Hartford Steam Boiler of Connecticut (HSBCT) have inspected the components described in this Owner's Report during the period/Z.-. & -07 to T-2/- -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 prope ge or a loss of any kind arising from or connected with this inspection Commissions ,SL Z..? L_1nspecto's Signature National Board, State, Province, and Endorsements Date 7- Z /- 0 9 HSBCT 200 Ashford Center North Suite 205 Atlanta, GA. 30338-4860 (800) 417-3721 www.hsbc.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)

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 3 EOC 24 (Outage 3 of the Fourth Interval).

This is the First Outage in the Second, Inspection Period of the Fourth Ten-Year Interval.

ASME Section XI, 1998 Edition with the 2000 Addenda, was the governing Code for selection and performance 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 620-0009-51-52 N/A N-1 25 Reactor Vessel Babcock & Wilcox 068S-03 N/A 200 Head (replaced head)Steam Generator A Babcock & Wilcox 006K05 N/A 211 Steam Generator B Babcock & Wilcox 006K06 N/A 212 Pressurizer Babcock & Wilcox 620-0009-59 N/A N-126 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 I I I I EOC 24 Refueling Outage Report Oconee Unit 3 Section 1 Page 1 of 4 Revision 0 July 16, 2009 Manufacturer Item Manufacturer or Installer State or National or Installer Serial No. Province No. Board No.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 I EOC 24 Refueling Outage Report Oconee Unit 3 Section 1 Page 2 of 4 Revision 0 July 16, 2009 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 the 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 the1998 Edition with the 2000 Addenda through the Performance Demonstration Initiative (PDI) for components under the scope of Appendix VIII.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 Energy'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 Energy's Corporate Office in Charlotte, North Carolina.The reactor coolant flywheels were examined (UT and MT methods) by Areva.The copies of the certification records for Areva can be obtained by contacting Duke Energy'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 (Alternative Examination Coverage For Class 1 and Class 2 Welds.) 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-665 (Alternative requirements for beam angle measurements using refracted longitudinal wave search units).Code Case N-722 (Additional examinations for PWR pressure retaining welds in Class 1 components fabricated with alloy 600/82/182 materials)

Items are identified by the use of B135 summary numbers.PIP Serial Number 0-09-04780.

This PIP was written to track the corrective action ,for limited examination coverage for the UT of welds inspected during Unit 3 EOC-24.EOC 24 Refueling Outage Report Page 3 of 4 Oconee Unit 3 Revision.

0 Section 1 July 16, 2009 PIP Serial Number 0-09-03035.

This PIP was written to document the thermal sleeve gaps found during RT augmented examinations.

This Gap measurement will be used as a baseline when exams are performed in the future. (Component ID # 3A1-Therm Sleeve, Summary Number 03.G2.1.0026 and Component ID #3A2-Therm Sleeve, Summary Number 03.G2.1.0029)

Request for Relief 04-ON-01 5 (Allows Duke relief from performing B3.160 examinations during the 4th interval.)

Request for Relief 03-006 (Allows Duke an Alternative for the Snubber Examinations required in IWF-5000 for the 4th 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 Insoection Aaencv I I im I Hartford Steam Boiler of Connecticut (HSB CT) is responsible for the third party inspections required by ASME Section XI.Authorized Nuclear Inservice Inspector(s),Name: Employer: Business Address: Gary Brouette, Jacob Scholl HSB CT.200 Ashford Center North Suite 205 Atlanta, GA 30338-4860 (800) 417-3721 www.hsbct.com EOC 24 Refueling Outage Report Oconee Unit 3 Section 1 Page 4 of 4 Revision 0 July 16, 2009 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/Elective 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 5 Welds 50% No in Vessels Other than Reactor Vessel B-D Full Penetration Welds of 54 20 37% 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 43.33 Items 34% Yes Greater than 2 Inches in Diameter B-G-2 Pressure Retaining Bolting 20 Items 10 Items 50% No 2 Inches and Less in Diameter B-J Pressure Retaining Welds 158 Welds 62 Welds 39% No I in Piping I B-K Welded Attachments for 12 6 50% No Vessels, Piping, Pumps and Valves _Deferral of inspection to the end of the interval as allowed by ASME Section XI Table IWB 2500-1.EOC 24 Refueling Outage Report Oconee Unit 3 Section 2 Page 1 of 4 Revision 0 July 16, 2009 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 1 Valves 33% 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-O Pressure Retaining Welds 12 Housing 8 Housing 67% 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 F-A Class 1 Component 37 Supports 16 Supports 43% 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 XI Table IWB 2500-1.Inspected under Selected License Commitment 16.9.18 per Relief Request 03-006.Steam Generator Tubing is examined and documented by Nuclear Technical Services as required by ASME Section XI and the Oconee Improved Technical Specifications and is not included in this report.EOC 24 Refueling Outage Report Oconee Unit 3 Section 2 Page 2 of 4 Revision 0 July 16, 2009 Class 2 Inspections Examination Inspections Inspections Percentage Category Description Required Completed Completed C-A Pressure Retaining Welds 11 Welds 8 Welds 73%in Pressure Vessels C-B Pressure Retaining Nozzle 4 Welds 2 Welds 50%Welds in Vessels C-C Integral Attachments for 37 16 43%Vessels, Piping, Pumps Attachments Attachments and Valves C-D Pressure Retaining Bolting 2 Items 2 Items 100%Greater Than 2 Inches in Diameter C-F-1 Pressure Retaining Welds 164 Welds 67 Welds 41%in Austenitic Stainless Steel or High Alloy Piping C-F-2 Pressure Retaining Welds 67 Welds 27 Welds 40%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 147 Supports 69 Supports 47%F1.020 & F1.040 Supports (Except items. Snubbers)F-A Class 2 Component

- F1.050 items Supports, Snubbers Inspected under Selected License Commitment 16.9.18 per Relief Request 03-006.**AugmentedlElective Inspections Augmented and Elective Examination Information found within this Inservice Inspection Report is not required by the ASME Section Xl Code; therefore, it is exempt from ANII review, verification, and/or record certification.

EOC 24 Refueling Outage Report Oconee Unit 3 Section 2 Page 3 of 4 Revision 0 July 16, 2009 Augmented/Elective Inspections Item Number Description Percentage Complete 03.B4.30 ASME Code Case N-729-1 Bare Metal None scheduled for EOC 24 Visual on RV Head 03.B4.40 ASME Code Case N-729-1 UT None scheduled for EOC 24 Examination 03.B15.80 ASME Code Case N-722 BMI Nozzles 100% of EOC 24 Requirements 03.B15.210 ASME Code Case N-722 on Hot Legs 100% of EOC 24 Requirements 03.B15.215 ASME Code Case N-722 on Cold 100% of EOC 24 Requirements Legs O3.G1.1 Reactor Coolant Pump Flywheel 100% of EOC 24 Requirements 03.G2.1 HPI Nozzle Safe End Examinations 100% of EOC 24 Requirements O3.G3.1 Pressurizer Surge Line Examinations None scheduled for EOC 24 03.G4.1 Thermal Stress Piping (NRC Bulletin None scheduled for EOC 24 88-08)03.G1 1.1.0001 Reactor Pressure Vessel Head None scheduled for EOC 24 Penetration Nozzle by UT Examination per NRC Order EA-03-009.03.G11.1.0002 Bare Metal Visual Examination of the None scheduled for EOC 24 Reactor Pressure Vessel Head Surface per NRC Order EA-03-009.

03.G12.1 UT Examination per MRP-139 None scheduled for EOC 24 O3.G12.2 UT Examination per MRP-139 None scheduled for EOC 24 03.G13.1 VT-2 Bare Metal Visual per MRP-139 100% of EOC 24 Requirements 03.G13.2 VT-2 Bare Metal Visual per MRP-139 None scheduled for EOC 24 03.G13.3 VT-2 Bare Metal Visual per MRP-139 100% of EOC 24 Requirements O3.G13.4 VT-2 Bare Metal Visual per MRP-139 100% of EOC 24 Requirements 03.G15.1 UT Examination per MRP-192 None scheduled for EOC 24 03.G16.1 UT Examination per MRP-146 None scheduled for EOC 24 03.H2.1 Class 1 RTE Mounting Bosses 100% of EOC 24 Requirements 03.H3.1 Main Feedwater Piping in the East None scheduled for EOC 24 and West Penetration Rooms per QA-513J (ER-ONS-04-03) 03.H4.1 Main Feedwater and Main Steam 100% of EOC 24 Requirements Piping Supports and Attachment Welds per QA-513J (ER-ONS-04-05) 03.H5.1 East Penetration Main Feedwater None scheduled for EOC 24 I piping welds and attachments 03.H6.1 Main Feedwater rupture restraint None scheduled for EOC 24 I attachment welds EOC 24 Refueling Outage Report Oconee Unit 3 Section 2 Page 4 of 4 Revision 0 July 16, 2009 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.The information shown below is a field description for the reporting format included in this section of the report: Summary Num Component ID Class/System Iso /Dwg. Numbers Procedure Description Comments Insp Req.Material Sched Thick/NPS Cal Blocks Component ID 2= ASME Section Xl Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2), IWF-2500-1 (Class 1 and Class 2 ), Augmented/Elective Requirements

= Unique Identification Number= ISI Class and Component System Identification

= Location and/or Detail Drawings= Examination Procedures

= Configuration of Weld (Nozzle to Pipe)= General and/or Detail Description

= Examination Technique

-Magnetic Particle, Dye Penetrant, etc.= Material Type (CS, SS, Inconel, etc.)= Description of Material Thickness= Thickness/Diameter

= Calibration Block Number= Previous Interval Item Number EOC 24 Refueling Outage Report Oconee Unit 3 Section 3 Page 1 of 1 Revision 0 July 16, 2009 9 DUKE ENRGY NUCLEAR TECHNICAL SERVICES ScheduleWorks Inservice Inspection Database Management System Plan Report Oconee 3, 4th Interval, Outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class / System Description Comments Category AUG 03.B15.210.0001 3RC-287-6 Class 1 50 3RC-287 NDE-68 VT-2 SS-Inconel 1.250 / 1.000 OM 2201-1395 Dissimilar OM 2201-1404 Nozzle to Pipe 1 inch HL SB-166 Pressure Boss to CS HL pipe weld & SS 1 inch pipe weld. (Examine the Nozzle (Boss) to Hot Leg weld and the Nozzle (Boss) to SS Pipe weld.) These welds are branching off of Unit 3 "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.03.B15.210.0002 3RC-287-7 Class 1 50 3RC-287 NDE-68 VT-2 SS-Inconel 1.250 / 1.000 OM 2201-1395 Dissimilar OM 2201-1404 Nozzle to Pipe 1 inch HL SB-166 Pressure Boss to CS HL pipe weld & SS 1 inch pipe weld. (Examine the Nozzle (Boss) to Hot Leg weld and the Nozzle (Boss) to SS Pipe weld.) These welds are branching off of Unit 3 "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.Printed 07/13/09 Ick8302 v. 06/18/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 1 of 61 9 9 S Oconee 3, 4th Interval, outage 3 (EOC-24)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 03.B15.210.0003 3RC-286-14 Class 1 50 3RC-286 NDE-68 VT-2 SS-Inconel 1.250 /1.000 OM 2201-1395 Dissimilar OM 2201-1404 Nozzle to Pipe 1 inch HL SB-166 Pressure Boss to CS HL pipe weld & SS 1 inch pipe weld. (Examine the Nozzle (Boss) to Hot Leg weld and the Nozzle (Boss) to SS Pipe weld.) These welds are branching off of Unit 3 "B" 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.03.B15.210.0004 3RC-286-15 Class 1 50 3RC-286 NDE-68 VT-2 SS-Inconel 1.250 / 1.000 OM 2201-1395 Dissimilar OM 2201-1404 Nozzle to Pipe 1 inch HL SB-166 Pressure Boss to CS HL pipe weld & SS 1 inch pipe weld. (Examine the Nozzle (Boss) to Hot Leg weld and the Nozzle (Boss) to SS Pipe weld.) These welds are branching off of Unit 3 "B" 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.Printed 07/13/09 Ick8302 v. 06118/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 2 of 61 Oconee 3, 4th Interval, outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 03.B15.210.0005 3RC-287-3 Class 1 50 3RC-287 NDE-68 VT-2 SS-Inconel 1.250 /1.000 OM 2201-1395 Dissimilar OM 2201-1404 Nozzle to Pipe 0.75 inch ID HL Flowmeter SB-166 Nozzle Boss to CS HL pipe weld & SS pipe weld. (Examine the Nozzle (Boss) to Hot Leg weld and the Nozzle (Boss) to SS Pipe weld.) These welds are branching off of Unit 3 "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 iterm 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.03.B15.210.0006 3RC-287-63V Class 1 50 3RC-287 NDE-68 VT-2 SS-Inconel 1.250 / 1.000 OM 2201-1395 Dissimilar OM 2201-1404 Nozzle to Pipe 0.75 inch ID HL Flowmeter SB-166 Nozzle Boss to CS HL pipe weld & SS pipe weld.,(Examine the Nozzle (Boss) to Hot Leg weld and the Nozzle (Boss) to SS Pipe weld.) These welds are branching off of Unit 3 "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.Printed 07/13/09 Ick8302 v. 06/18/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 3 of 61 Oconee 3, 4th Interval, outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 03.B15.210.0007 3RC-286-11 Class 1 50 3RC-286 NDE-68 VT-2 SS-Inconel 1.250 / 1.000 ---OM 2201-1395 Dissimilar OM 2201-1404 Nozzle to Pipe 0.75 inch ID HL Flowmeter SB-166 Nozzle Boss to CS HL pipe weld & SS pipe weld. (Examine the Nozzle (Boss) to Hot Leg weld and the Nozzle (Boss) to SS Pipe weld.) These welds are branching off of Unit 3 "B" 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.03.B15.210.0008 3RC-286-58V Class 1 50 3RC-286 NDE-68 VT-2 SS-Inconel 1.250 / 1.000 OM 2201-1395 Dissimilar OM 2201-1404 Nozzle to Pipe 0.75 inch ID HL Flowmeter SB-166 Nozzle Boss to CS HL pipe weld & SS pipe weld. (Examine the Nozzle (Boss) to Hot Leg weld and the Nozzle (Boss) to SS Pipe weld.) These welds are branching off of Unit 3 "B" Hot Leg.Per the requirements of 1O'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 07/13/09 Ick8302 v. 06/18/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 4 of 61 w

-Oconee 3, 4th Interval, outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 03.B15.210.0009 3-PHA-13 Class 1 50 ISI-0CN3-005 NDE-68 VT-2 CS-Inconel 2.875 / 9.000 0-ISlN4-100A-3.1 Dissimilar OM 2201-1404 Nozzle RTE Nozzle to Pipe A Hot Leg X-axis RTE Mounting Boss SB-166 to 690 Drywell Weld on 3A 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 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.03.B15.210.0010 3-PHA-14-Class 1 50 ISI-OCN3-005 NDE-68 VT-2 CS-Inconel 2.875 / 9.000 0-ISIN4-100A-3.1 Dissimilar OM 2201-1404 Nozzle RTE Nozzle to Pipe A Hot Leg Y Z-axis RTE Mounting Boss SB-166 to 690 Drywell Weld on 3A Hotleg (Y-Z Axis)Hot Leg (Piece 7) toRTE 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 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 07/13/09 Ick8302 v. 06/18/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 5 of 61 Oconee 3, 4th Interval, outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 03.B15.210.0011 3-PHA-15 Class 1 50 ISI-OCN3-005 NDE-68 VT-2 CS-Inconel 2.875 / 9.000 O-ISIN4-100A-3.1 Dissimilar OM 2201-1395 Nozzle RTE Nozzle to Pipe A Hot Leg Z W-axis RTE Mounting Boss SB-166 to 690 Drywell Weld on 3A Hotleg ( 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 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.03.B15.210.0012 3-PHB-13 Class 1 50 ISI-OCN3-006 NDE-68 VT-2 CS-Inconel 2.875 / 9.000 0-ISIN4-100A-3.1 Dissimilar OM 2201-1395 Nozzle RTE Nozzle to Pipe B Hot Leg X -axis RTE Mounting Boss SB-166 to 690 Drywell Weld on 3B 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 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 07/13/09 Ick8302 v. 06/18/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Paae 6 of 61 Oconee 3, 4th Interval, outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 03.B15.210.0013 3-PHB-14 Class 1 50 ISI-OCN3-006 NDE-68 VT-2 CS-Inconel 2.875 / 9.000 0-ISIN4-100A-3.1 Dissimilar OM 2201-1395 Nozzle RTE Nozzle to Pipe B Hot Leg Y Z -axis RTE Mounting Boss SB-166 to 690 Drywell Weld on 3B 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 augment their tSI 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.03.B15.210.0014 3-PHB-15 Class 1 50 ISI-OCN3-006 NDE-68 VT-2 CS-Inconel 2.875 / 9.000 O-ISIN4-100A-3.1 Dissimilar OM 2201-1395 Nozzle RTE Nozzle to Pipe B Hot Leg Z W -axis RTE Mounting Boss SB-166 to 690 Drywell Weld on 3B 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 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 07113/09 Ick8302 v. 06/18/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 7 of 61 0 Oconee 3, 4th Interva!, outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class / System Description Comments Category AUG 03.B15.210.0015 3SGA-HL-CON-36 Class 1 50 OM-2201-0095.001 NDE-68 VT-2 CS-Inconel 0-ISIN4-100A-3.1 Dissimilar OM-2201-1404.001 RTE Hot Leg Thermal well Steam Generator A Hot Leg Connection

36 on drawing OM 2201-0095.001 and Mark # 10 on drawing OM-2201-1404.001 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.03.B15.210.0016 3SGB-HL-CON-27 Class 1 50 OM-2201-0095.001 NDE-68 VT-2 CS-Inconel 0-ISIN4-100A-3.1 Dissimilar OM-2201-1404.001 RTE Hot Leg Thermal well Steam Generator B Hot Leg Connection

27 on drawing OM 2201-0095.001 and Mark # 10 on drawing OM-2201-1404.001 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 07/13/09 Ick8302 v. 06/18/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 8 of 61 0 '0 0 Oconee 3, 4th Interval, outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 03.B15.215.0015 3B1-CON-3 Class 1 50 OM 2201-220 NDE-68 VT-2 SS-Inconel 0.250 /1.000 0-ISIN4-100A-3.1 Dissimilar Elbow to Nozzle 1 inch LCL SB-166 Pressure Boss to CS LCL pipe weld & SS pipe weld. Reactor Coolant Pump 3B1 Suction Piping, Connections 3 on Flow Diagram OFD-100A-3.1.

Examine the Pressure Boss to Cold Leg weld and the Pressure Boss to 1 inch SS 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 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.03.B15.215.0016 3B2-CON-7 Class 1 50 OM 2201-220 NDE-68 VT-2 SS-Inconel 0.250/1.000 0-ISIN4-100A-3.1 Dissimilar Elbow to Nozzle 1 inch LCL SB-166 Pressure Boss to CS LCL pipe weld & SS pipe weld. Reactor Coolant Pump 3B2 Suction Piping, Connections 7 on Flow Diagram OFD-100A-3.1.

Examine the Pressure Boss to Cold Leg weld and the Pressure Boss to 1 inch SS 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 item is totbe examined once per interval.For additional information, contact Chris Cruz from the Materials and NDE Services Section, Nuclear Technical Services Division.Printed 07/13/09 Ick8302 v. 06/18/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 9 of 61 Oconee 3, 4th Interval, outage 3 (EOC-24)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 03.B15.215.0017 3-PIAl-10 Class 1 50 ISI-OCN3-007 NDE-68 VT-2 CS-Inconel 2.250/ 12.000 0-ISIN4-100A-3.1 Dissimilar Nozzle to Pipe Pump 3A1 Suction Piping. Drain Nozzle Pc. 64 to Pipe Pc. 63. The NPS of the branch line is 1.5 inches.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.03.B15.215.0018 3-50-21-23 Class 1 50 3-50-2i NDE-68 VT-2 SS-Inconel 0.281 / 1.500 0-ISIN4-100A-3.1 Dissimilar Elbow to Nozzle 1.5 inch SS pipe weld that is down-stream from weld 3-PIAl-10.

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 07/13/09 Jck8302 v. 06/18/09 SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 10 of 61 Oconee 3, 4th Interval, outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 03.B15.215.0019 3-PIA2-10 Class 1 50 ISI-OCN3-008 NDE-68 VT-2 CS-Inconel 2.250 / 12.000 0-ISIN4-100A-3.1 Dissimilar Pipe to Nozzle Pump 3A2 Suction Piping. Pipe Pc. 63 to Drain Nozzle Pc. 64. The NPS of the branch line is 1.5 inches.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.03.815.215.0020 3-50-21-1 Class 1 50 3-50-21 NDE-68 VT-2 SS-Inconel 0.281 / 1.500 0-ISIN4-100A-3.1 Dissimilar Elbow to Nozzle 1.5 inch SS pipe weld that is down-stream from weld 3-PIA2-10.

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._PýritedUll 3-'-/09 Ick`8_3_0_2_-v.

06118-*-/0-9--

SDQA Cat "C" Oconee 3 7/13/2009 9:31:22 AM Page 11 of 61 Oconee 3, 4th Interval, outage 3 (EOC-24)Summary Num Component ID ISO/DWG Numbers Procedure Insp Req Material Sched Thick/NPS Cal Blocks Componenet ID 2 Class I System Description Comments Category AUG 03.B15.215.0021 3-PIB2-10 Class 1 50 ISI-OCN3-010 NDE-68 VT-2 CS-Inconel 2.250 / 12.000 ISIN4-100A-3.1 Dissimilar Pipe to Nozzle Pump 3B2 Suction Piping. Pipe Pc. 63 to Drain Nozzle Pc. 64. The NPS of the branch line is 1.5 inches.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.03.B15.215.0022 3-50-20-9 Class 1 50 3-50-20 NDE-68 VT-2 SS-Inconel 0.281 /1.500 0-ISIN4-100A-3.1 Dissimilar Elbow to Nozzle 1.5 inch SS pipe weld that is down-stream from weld 3-PIB2-10.

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 07/13/09 Ick8302 v. 06/18/09 SDQA Cat "C" vOconee 3 7/13/2009 9:31:22 AM Page 12 of 61 S Summary Num Component ID ISO/DWG Numbers Class / System Oconee 3, 4th Interval, outage 3 (EOC-24)Procedure Insp Req Material Sched Description Comments Thick/NPS Cal Blocks Componenet ID 2 Category AUG 03.B15.80.0001 3-RPV-BMI NOZZLES Class 1 50 O-ISIN4-100A-3.1 NDE-68 VT-2 Alloy 600 0.000 / 0.000 RPV Bottom Head BMI Nozzles 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 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 aminimum 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." Procedure NDE-68 in conjunction with MP/O/A/1 150/030 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.03.G1.1.0004 3-RCP-3B2 Class 1 50 OM-201 D-038 O-ISIN4-100A-3.1 54-ISI-271 MT CS 9.500 / 72.000 GO1.001:004, G01.001.004,1 Reactor Coolant Pump 3B32 Flywheel.

Reference Section 7 Paragraph 7.1.1 of the ISI Plan -Volume 1.03.G1.1.0004 3-RCP-3B2 Class 1 50 OM-201 D-038 O-IS IN4-100A-3.1 54-ISI-117 UT CS 9.500 / 72.000 Component G01.001.004, G01.001.004?

Reactor Coolant Pump 3B2 Flywheel.

Reference Section 7 Paragraph 7.1.1 of the ISI Plan -Volume 1.03.G 13.1.0026 Circumferential Dissimilar 3RC-287-6 Class 1 50 3RC-287 NDE-68 VT-2 SS-Inconel 1.250 / 1.000 G13.001.02(Nozzle to Pipe 1 inch HL SB-166 Pressure Boss to CS HL pipe weld & SS 1 inch pipe weld. (Examine the Nozzle (Boss) to Hot Leg weld and the Nozzle (Boss) to SS Pipe weld.) Augmented Inspection Per MRP-1 39. Contact Jody Shuping for additional information on this examination.