Vogtle, Unit 1 - IR16 Inservice Inspection Report Summary. · 1987. 5. 31. · NIS·1 (Back) 8. Examination Dates: October 23.2009 to April 2, 2011 9. Inspection Period Identification:

Mark J. Ajluni. P.E. Nuclear Director

Southern Nuclear Operating Company. Inc. 40 Inverness Center Parkway Post Office Box 1295

Alabama 35201

June 30. 2011

Docket Nos.: 50-424

Tel 205.9927673 Fax 205.9927885

SOUTHERN'\ NL-11-1309 COMPANY

U. S. Nuclear Regulatory ATTN: Document CWashington, D. C.

Commission ontrol Desk

20555-0001

Vogtle Electric Generating Plant-Unit 1 IR16 Inservice Inspection Report Summary

Ladies and Gentlemen:

Southern Nuclear Operating Company (SNC) submits herewith the Vogtle Electric Generating Plant Unit 1, Interval 3, Period 2, Outage 1 Inservice Inspection Summary Report (Enclosure). This report describes and summarizes the inservice inspection activities performed during the fall 2009 maintenance/refueling outage. Paragraph IWA-6240 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, 2001 Edition with addenda through 2003 requires submittal of the enclosed report.

The supporting inservice inspection documentation, e.g., examination plans and schedules, examination results and reports, examination methods and procedures, evaluation results, and corrective action and repairs, is available for review upon request at Vogtle Electric Generating Plant.

This letter contains no NRC commitments. If you have any questions, please advise.

Respectfully submitted,

~i~~

Nuclear Licensing Director

MJAlLPHllac

Enclosure: Vogtle Electric Generating Plant-Unit 1 Inservice Inspection Report Refueling Outage (IR16), Interval 3, Period 2, Outage 1

U. S. Nuclear Regulatory Commission NL-11-1309 Page 2

cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, Vice President-Vogtle Ms. P. M. Marino, Vice President-Engineering RType: CVC7000

U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. P. G. Boyle, NRR Project Manager - VogUe Mr. L. M. Cain, Senior Resident Inspector-Vogtle

Vogtle Electric Generating Plant - Unit 1

IR161nservice Inspection Report Summary

Enclosure

Vogtle Electric Generating Plant - Unit 1

Inservice Inspection Report

Refueling Outage (1R16), Interval 3, Period 2, Outage 1

SOUTHERN A SOUTHERN A COMPANY COMPANY

INSERVICE INSPECTION REPORT

REFUELING 16

INTERVAL 3

PERIOD 2

OUTAGE 1

Vogtle Electric Generating Plant Unit 1

(7821 River Road, P. O. Box 1600, Waynesboro, Georgia 30830)

Southern Nuclear Operating Company

40 Inverness Parkway

Birmingham, Alabama 35242

COMMERCIAL OPERATION DATE: May 31,1987

DOCUMENT COMPLETION DATE: June 2011

I

VOGTLE ELECTRIC GENERATING (VEGP) PLANT 1 R16 FINAL REPORT TABLE OF CONTENTS

SECTION

VOLUME 1 (OWNER'S REPORT)

• INTRODUCTION AND ABBREVIATIONS A

• ASME FORM NIS-1 AND ABSTRACT B

• INSERVICE INSPECTION (OWNER'S REPORT) EXAMINATION SUMMARY

CLASS 1 AND 2 WELDS AND SUPPORT EXAMINATIONS C

SYSTEM PRESSURE TESTS D

REPORTABLE INDICATION SUMMARY E

• OWNER'S REPORT FOR REPAIRS AND REPLACEMENTS (FORM NIS-2) F

VOLUME 2 (151 EXAMINATION DATA)

• EXAMINATION PROGRAM PLAN (TOTAL SCOPE SUMMARY) G

• lSI EXAMINATION DATA H

VOLUME 3 (CERTIFICATIONS)

• PERSONNEL CERTIFICATIONS

• EXAMINATION PROCEDURES {LISTING} J

• EQUIPMENT CERTIFICATIONS & CALIBRATION BLOCKS (LISTING) K

VOLUME 4 (FLOW ACCELERATED CORROSION - FAC)

• FAC EXAMINATION SUMMARY L

• FAC EXAMINATION DATA M

VOLUME 1

CONTAINS THE INFORMATION TO MEET THE REQUIREMENTS OF ASME CODE 2001 EDITION w 2003

ADDENDA, SECTION XI, SUBSECTION IWA-6240 FOR SUBMITTAL OF A SUMMARY REPORT TO THE

NRC FOLLOWING EACH REFUELING OUTAGE.

VOLUMES 2 AND 3

CONTAIN THE SUPPORTING DOCUMENTATION FOR THE EXAMINATIONS PERFORMED (RETAINED

ON SITE BY VEGP)

VOLUME 4

CONTAINS DOCUMENTATION OF THE FLOW ACCELERATED CORROSION {FAC} INSPECTIONS

PERFORMED (RETAINED ON SITE BY VEGP)

1

SOUTHERNA sOUTHERN_ COMPANY COMPANY

SOUTHERN NUCLEAR

OPERA TING COMPANY

ENGINEERING PROGRAMS

DEPARTMENT

INSERVICE INSPECTIONS

PLANT VOGTLE UNIT 1

REFUELING OUTAGE 16

SPRING 2011

Volume 1

Owner's Report

TAB A

INTRODUCTION & ABBREVIATIONS

INTRODUCTION

This report documents the examinations and tests performed at Vogtle Electric Generating Plant, Unit 1 (VEGP-1) between October 23, 2009 {end of the fifteenth (15th ) maintenancelrefueling outage, 1 R 15} and April 2, 2011 {end of the sixteenth (16th) maintenance/refueling outage, 1R16} to meet the requirements of Article IWA-6000 ofthe American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, 2001 Edition with 2003 Addenda (Code).

This report also addresses Code-applicable repairs and/or replacements, which were documented since the last maintenance/refueling outage at VEGP-1 through the completion of the sixteenth maintenance/refueling outage on April, 2,2011 done per the 2001 Edition with 2003 Addenda. The Owner's Reports for Repairs and Replacements (Form NIS-2) are included herein.

This report includes a summary of the steam generator tube inspections which are required per VEGP Technical Specification 5.6.10. The detailed information will be provided in a separate report one hundred eighty (180) days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Technical Specification 5.5.9. A summary of these inspections is included behind Tab B in the Abstract.

1-1

LIST OF ABBREVIATIONS

ACC AD AFW AI AN II ASME ASNT ASTM BC CCSS CCW CE CH CR CS CVCS OS ET EVAL FAC

FB FNF FW FSAR GEO GPC HHSI HL HX HYD lEN

IND INF lSI 1ST ITS 10 IR LB LD LD-I LD-O LMT LU LU-I LU-O MECH MS MT NCI NDE

Acceptable Anchor/Darling Auxiliary Feedwater System GPC Action Item (followed by unique no. denoting Action Item number) Authorized Nuclear Inservice Inspector American Society of Mechanical Engineers American Society for Nondestructive Testing American Society for Testing and Materials Branch Connection Centrifugally Cast Stainless Steel Component Cooling Water Combustion Engineering Closure Head Condition Report Containment Spray Chemical and Volume Control System Downstream Eddy Current Examination Evaluation Flow-Accelerated Corrosion (may also be referred to as "erosion/corrosion") Flange Bolting FAC Notification Report Feedwater System VEGP Final Safety Analysis Report (includes updates thereto) Geometric Indications Georgia Power Company High Head Safety Injection Hanger Lug Heat Exchanger Hydraulic Snubber NRC Information Notice (may also be shown as "IN" followed by unique no. denoting notice number) Indication Indication Notification Form Inservice Inspection Inservice Testing VEGP Improved Technical Specification Inside Diameter Inside Radius Large Bore Longitudinal Seam Weld Extending Downstream Longitudinal Seam Weld Downstream Inside Radius of Elbow Longitudinal Seam Weld Downstream Outside Radius of Elbow Lambert, MacGill and Thomas Longitudinal Seam Weld Extending Upstream Longitudinal Seam Weld Upstream Inside Radius of Elbow Longitudinal Seam Weld Upstream Outside Radius of Elbow Mechanical Snubber Main Steam System Magnetic Particle Examination Nonconformance Item Nondestructive Examination

1·2

NI NRC NRC-B NRI NSCW OR PL PM PR PROF PS PSA PSI PT RCS RCP RHR RI RLW RL RPV RR RWST SAT SB SCS SI SNC SUP T&C TDAFW UNSAT US UT VEGP

VT W

LIST OF ABBREVIATIONS - (continued)

No Indication United States Nuclear Regulatory Commission NRC Bulletin (followed by unique no. denoting Bulletin number) No Recordable Indication Nuclear Service Cooling Water System Outside Radius Pipe Lug Paul-Munroe ENERTECH Pipe Restraint Profile Pipe Support Pacific Scientific Preservice Inspection Liquid Penetrant Examination Reactor Coolant System Reactor Coolant Pump Residual Heat Removal System Recordable Indication Refracted Longitudinal Wave Restraint Lug Reactor Pressure Vessel Relief Request (followed by unique no. denoting relief request number) Refueling Water Storage Tank Satisfactory Examination Results Small Bore Southern Company Services Safety Injection System Southern Nuclear Operating Company Supplemental Data Thickness and Contour Turbine Driven Auxiliary Feedwater (Pump) Unsatisfactory Examination Results Upstream Ultrasonic Examination Vogtle Electric Generating Plant (common unless followed by "-1 If or "-2" to designate a specific plant unit) Visual Examination Westinghouse

1-3

TABB

ASME FORM NIS-1 AND ABSTRACT

• Form NIS-1

• Abstract

FORM NIS·1 OWNER'S REPORT FOR INSERVICE INSPECTIONS

As required by the Provisions of the ASME Code Rules

1. Owner: Southern Nuclear Operating Company (as agent for Georgia Power Company), 40

Inverness Center Parkway, Birmingham, AL 35242

2. Plant: Vogtle Electric Generating Plant, 7821 River Road P. O. Box 1600, Waynesboro, Georgia 30830

3. Plant Unit: One

4. Owner Certification of Authorization: N/A

5. Commercial Service Date: 05/31/87

6. National Board Number for Unit: N/A

7. Components Inspected:

Component or Manufacturer or Manufacturer or Installer State or National Board Appurtenance Installer and Serial Number Province Number

Address Number Reactor Combustion Eng. 8971 N/A 21668 Pressure Vessel Inc.,

Chattanooga, TN

Steam . Westinghouse GAGT 1881, GAGT 1882, . N/A NA Generators 1 Elec., GAGT 1883, GAGT 1884, thru 4 Pensacola, FL

Pressurizer Westinghouse 62189 N/A NA Elec., Pensacola, FL

Residual Heat . Joseph Oat Corp., . 2322-2A N/A NA Removal Heat Camden, NJ Exchanger, Train "An

Selected Piping, Pullman Power i System Numbers 1201, 1204, N/A N/A Components, I Products, 1205,1208,1301,1302,& and Supports Williamsport, PA 1305

i

2-1

FORM NIS·1 (Back)

8. Examination Dates: October 23.2009 to April 2, 2011

9. Inspection Period Identification: Second Period

10. Inspection Interval Identification: Third Inspection Interval

11. Applicable Edition of Section XI 2001 Addenda 2003

12. Date/Revision of Inspection Plan: June 15, 2010/ Version 4.0

13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. (See Abstract and Examination Summary Listings)

14. Abstract of Results of Examinations and Tests. (See Abstract)

15. Abstract of Corrective Measures. (See Abstract)

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) N/A

Date: 2~JlI,.J 2011 Signed: Southern Nuclear Qperatinc Company. Inc.

for Georgia Power CompanX' ~

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the National Board of Boller and Pressure Vessel Inspectors and the State of Georgia and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford. CT have inspected the components described in this Owner's Report during the period October 23, 2009 to April 2. 2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a losS of any kind arising from or connected with this inspection.

~4.kgzH Commission: -:6tt~_7 $'~le",,--~___~___.......

~gnature National Board. State. Province. and Endorsements

2·2

ABSTRACT - ASME CLASS 1 AND 2

Introduction/Status

The ASME Boiler and Pressure Vessel Code, Section XI, 2001 Edition (Code), with the 2003 Addenda, is the applicable code for conducting inservice inspection activities during the third ten-year inspection interval at VEGP-1. Examinations and tests required by the Code are scheduled in accordance with "Inspection Program BU as defined in Code paragraphs IWB-2412 and IWC-2412. This "Owner's Report for Inservice Inspection" is for those third inspection period examinations and tests which were performed between October 23,2009, (end of the 1 R15 maintenance/refueling outage) and April 2, 2011 (end ofthe 1 R 16 maintenance/refueling outage).

VEGP has implemented ASME Section XI, Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," as required by 10CFR 50.55a, amended by the Federal Register Notices 64 FR 51370 dated September 22, 1999, as later modified by 69 FR58804, dated October 1,2004. The initial Rule specified the 1995 Edition with Addenda through 1996 as the applicable edition of ASME Section XI, Appendix VIII. The 2004 Rule incorporated the 2001 Edition with NRC caveats. VEGP has, except where requests for relief, technical alternatives or exemptions have been approved, complied with the requirements for expedited implementation of the applicable Appendix VIII supplements using the EPRI Performance Demonstration Initiative (PDI).

In addition to the summary of inservice inspection activities, this report addresses Code-applicable repairs and replacements documented at VEGP-1 since 1R15 through the end of 1R16. Class 1 and Class 2 Owner's Reports for Repairs or Replacements (Form NIS-2) are provided herein.

It should be noted that Authorized Nuclear Inservice Inspector (ANII) inspection services were provided for those examinations and tests required by the Code. ASME Section XI examinations and tests are itemized in the applicable sections by reference to Examination Category. Examinations which do not meet the Code-required coverage either reference request(s) for relief or indicate that additional relief is required.

Class 1 Examinations

Selected Class 1 components were examined by Southern Nuclear Operating Company (SNC) personnel utilizing ultrasonic testing (UT), magnetic particle testing (MT), liquid penetrant (PT), and visual testing (VT) methods, as applicable. Specific components and examination areas are itemized in the applicable portions of this document.

• During the scope of VEGP-1 examinations conducted, no Class 1 components were observed to have reportable indications. Tab E details and provides a disposition for Class 1 and Class 2 component that were determined to have reportable indication. Since there were no observed Class 1 reportable Indications, there will not be any entries in Tab E for Class 1 components.

Three (3) Class 1 piping and/or equipment welds had limited coverage during examinations because of physical limitations due to the geometric configuration of the welded areas. More than ninety percent (90%) of the required volume must be examined as addressed in ASME Section XI Code Case N-460 for adequate ASME Section XI Code-required examination coverage to be attained. As noted herein, the subject code case has been approved by the NRC for use as documented in NRC Regulatory Guide 1.147. It is impractical to achieve the ASME Section XI Code-required coverage due to the geometric configuration of the welded areas. These limited examinations will be submitted to the NRC through the relief request process as allowed by 10 CFR 50.55a.

Class 1 System Pressure Tests

Table IWB-2500-1, Examination Category B-P of the 2001 Edition with Addenda through 2003 of ASME Section XI requires the performance of a system leakage test (IWB-5221) each refueling outage. This system leakage test (14910-101) was performed prior to plant startup following the refueling outage. These visual examinations revealed minor leakage and boron residue at mechanical connections. These leakage conditions were either corrected or evaluated and determined acceptable for continued system operation.

Class 2 Examinations

Selected Class 2 components were examined by Southern Nuclear Operating Company (SNC) personnel utilizing ultrasonic testing (UT), magnetic particle testing (MT), liquid penetrant (PT), and visual testing (VT) methods, as applicable. Specific components and examination areas are itemized in the applicable portions of this document.

• During the scope of VEGP-1 examinations conducted, no Class 2 components were observed to have reportable indications. Tab E details and provides a disposition for Class 1 and Class 2 component that were determined to have reportable indication. Since there were no observed Class 2 reportable indications, there will not be any entries in Tab E for Class 2 components.

Two (2) class 2 piping and/or equipment welds had limited coverage during examinations because of physical limitations due to the geometric configuration of the welded areas. As with the Class 1 examinations, it is impractical to achieve the ASME Section XI Code-required coverage due to the geometric configuration of the welded areas. These limited examinations will be submitted to the NRC through the relief request process as allowed by 10 CFR 50.55a.

Class 2 System Pressure Tests

Table IWC-2500-1, Examination Category C-H of the 2001 Edition with Addenda through 2003 of ASME Section XI requires system leakage tests. The specific system leakage tests performed are itemized in the System "Pressure Tests" portion of this report document.

The visual examinations performed during these system leakage tests revealed minor leakages at the brazed tube-to-header connections on Containment Coolers 1-1501-A 7 -002-000, 1-1501-A7 -005-000 and 1-1501-A7-006-000. Comparable leakage has been previously identified and evaluated during prior pressure tests and during construction and determined acceptable for use in operation. The remainder of the visual examinations performed during these system pressure tests found only minor leakage or residue at mechanical joints, such as valve stem packing and at flanged connections. These leakage conditions were either corrected or evaluated and determined acceptable for continued system operation.

Steam Generator Tube Inspections

The inspection program addressed the known degradation mechanisms observed in Vogtle 1 in prior inspections as well as those regarded as potential degradation mechanisms. The program also addressed inspection requirements related to the implementation of temporary alternate repair criteria (TARC). The defined scope implemented during 1R16 included the following:

• 100% Bobbin examination of tubes in SGs 1 and 4, full length except for Rows 1 and 2, which were inspected from tube end to top tube support plate (TSP) from both hot leg (HL) and cold leg (CL).

• 100% +Point examination of Row 1 and Row 2 U-bends from the top TSP on the HL to the top TSP on the CL in all SGs.

• +Point examination of Special Interest of bobbin possible flaw locations including U-bends and both the HL and CL.

• 100% +Point examination of HL tubes in all SGs from the top of tubesheet (TTS) to the licensed Temporary Alternate Repair Criteria (TARC) depth for H* (TSH +3/-15.2 inches). This inspection

2-4

captured 100% of the TTS and BLG/OXP populations, as defined below, along with the required periodic sample that came with regulatory approval of the T ARC.

• BLG = differential mix diameter discontinuity signal within the tubesheet of 18 volts or greater as

measured by bobbin coil probe.

• OXP = a tube diameter deviation within the tubesheet of 1.5 mils or greater as measured by bobbin

coil profile analysis.

• 25% +Point examination of SG1 and SG4 CL tubes TTS +3/-3 inches. This inspection was aimed at early warning awareness of TTS degradation mechanisms and was analogous to a similar inspection that was performed in SG2 and SG3 during 1R15.

• 25% +Point examination of dents and dings 2: 2 volts in HL straight length and U-bends of all SGs.

100% visual inspection of tube plugs in all four SGs.

The Vogtle 1 R 16 SG inspection plan met or exceeded the requirements of the EPRI examination

guidelines and was aligned with NMP-ES-004-GL01, Revision 9, "Steam Generator Strategic Plan."

There was no NDE inspection scope expansion required during Vogtle 1R16.

The table below documents the list of plugged tubes and an indication of whether a stabilizer was

installed during Vogtle 1 R16.

I SG R~ Col Ind Outage .Plugging Basis Stabilizer Installed? .•:-1 I 1 26 110 PCT 1R16 Tech. SR.ec. % TW Limit No I l 4 8 57 SAIL 1R16 Plug on Detection No I

Explanation:

1 - Bobbin Volumetric Sizing

2 - Single Axial Crack

2-5

Class 1 and 2 Component Supports

Selected Class 1 and 2 component supports were examined by Southern Nuclear Operating Company (SNC) personnel utilizing the visual testing (VT) method. Specific components and examination areas are itemized in the applicable portions of this document.

• During the scope of VEGP-1 examinations conducted, no component supports were observed to have unsatisfactory results.

Class MC Containment Examinations and Tests (lWE)

During the VEGP-1 Spring 2011 maintenance/refueling outage, General Visual, VT-3 and VT-1 examinations were performed on Class MC Pressure retaining components with their integral attachments. These examinations were performed in accordance with ASME Section XI, Subsection IWE of the 2001 Edition through the 2003 Addenda and were performed using NMP-ES-024-204 "Detailed Visual Examination (lWE)" and NMP-ES-024-207 "General Visual Examination (IWE)". Per procedure NMP-ES-024-204, the pressure retaining bolting and the containment pressure boundary was examined for defects that could violate the leak-tight or structural integrity.

Personnel performing the examinations were qualified in accordance with VEGP procedure NMP-ES-024100 "Qualification and Certification of Nondestructive Examination and Testing Personnel". Optical aids such as flashlights, mirrors and binoculars were used when performing the examinations that included both direct and remote visual examination methods.

Categorv E-A, Containment Surfaces

It was discovered that Vogtle had not been performing IWE examinations on the portion of the containment pressure boundary located in the reactor cavity, i.e. the area under the reactor vessel. The lack of performing these examinations was documented in Vogtle's corrective action program under condition reports 2011103403, 2011104034 and 2011105287. Due to this discovery a General Examination of the Reactor Cavity Area was conducted during 1R16. The General Examination identified areas that required further examination, which were documented under Vogtle's condition report 2011104688. After some prep work was performed to clean the areas in question a Detailed Visual Examination was performed along with Ultrasonic Thickness Measurements. The Detail Visual and the Ultrasonic Thickness measurements were performed and the result was that based on examination the containment pressure boundary had maintained its structural integrity and leak tightness. These examinations are documented under surveillance 84303-101-1101014101. The other areas or anomalies identified consisted of surface rust, scratches, discolorations, etc. and were evaluated as not affecting the structural integrity or leak tightness of the containment pressure boundary.

Only the containment pressure boundary located in the reactor cavity was examined this refueling outage. The entire containment pressure boundary, including the portion in the reactor cavity will be examined during 1R17.

Inspection of the moisture barrier was not performed during refueling outage 1 R 16.

The following containment pressure boundary bolted connections were examined during 1R16 while the connections were disassembled for work activities. VT-1 or VT-3 examinations were performed to fulfill the requirements. No anomalies of the examined components were identified. Examinations were performed under work orders 1100512801,1100513001 and 1100914501. Results of examinations are documented under Surveillance 85053-101-1101012901.

Personnel Air Lock Emergency Air Cover 12101R2014

Escape Air Lock Emergency Air Cover 12101R2015

Dedicated Outage Penetrations 5-M & 55-M

2-6

Class CC Containment Examinations (lWL)

None performed in 1R16

Status of Examinations Required for the current Interval

This 1R16 Outage was the 151 Outage, 2nd Period of the 3rd Interval. The results from this outage, combined with the "scheduled" examinations for the next refueling outages (1R17, Fall 2012 and 1R18, Spring 2014) will represent 100% of the total Class 1 and 2 scope for the current period and interval. VEGP Unit 1 is within ASME Code compliance, pending NRC approval of the volumetric and/or surface examination limitations. Requests for relief will be submitted within the required time frame specified by 10 CFR 50.55a.

Applicable Code Cases

The applicable Code Cases for the 1 R16 Outage are identified in Enclosure 4, Volume 1 of the VEGP Units 1 and 2 Inservice Inspection Plan, Third Inspection Intervals. The Code Cases and limitations of use are derived from Revision 14, 15, and 16 of NRC Regulatory Guide 1.147.

2-7

lABe

INSERVICE INSPECTION EXAMINATION

(OWNER'S REPORT) SUMMARY

• CLASS 1 AND 2 WELD EXAMINATIONS • CLASS 1 AND 2 SUPPORT EXAMINATIONS

Vogtle 1R16 - Examination Summary (Total Piping)

ASME Exam/CalExamination/Area ExaminationSection XI Sheet Results Remarks(Sort) Procedure(s)

~at/ltem _ No(s) R-A 11201-031-3-RB Examined per MRP-146NMP-ES-024-501 S11V1U013 NRI

R1.11H 2" ELBOW TO PIPE requirements. R-A 11201-042-3-RB Examined per MRP-146NMP-ES-024-501 S11V1U018 NRI

R1.11H 2" ELBOW TO PIPE requirements. R-A 11201-046-3-RB Examined per MRP-146NMP-ES-024-501 S11V1U014 NRI

2" ELBOW TO PIPE requirements.r--R1.11H - - R-A 11201-051-3-RB Examined per MRP-146NMP-ES-024-501 S11V1U015 NRI

R1.11H 2" ELBOW TO PIPE requirements. R-A 11204-023-18-RB NMP-ES-024-501 S11V1U031 NRI NAR1.20 6" ELBOW TO PIPE

R-A 11204-023-19-RB NMP-ES-024-501 S11V1U032 NRI NAR1.20 6" PIPE TO ELBOW

R-A 11204-124-2-RB NMP-ES-024-501 S11V1U011 NRI NA _____R1.20 10" PIPE TO ELBOW R-A 11204-124-3-RB NMP-ES-024-501 S11V1U012 NRI NA

l R1.20 10" ELBOW TO PIPE

R-A 11204-125-2-RB

-

NMP-ES-024-501 S11V1UOO7 NRI NAR1.20 10" PIPE TO ELBOW

R-A 11204-125-3-RB NMP-ES-024-501 S11V1UOO8 NRI NAR1.20 10" ELBOW TO PIPE

R-A 11204-126-2-RB

-

NMP-ES-024-501 S11V1UOO5 NRI NA10" PIPE TO ELBOW R-A 11204-126-3-RB NMP-ES-024-501 S11V1UOO6 NRI NA~:=~_ R1.20R1.20 10" ELBOW TO PIPE

-

R-A 11204-127-2-RB NMP-ES-024-501 S11V1UOO9 NRI NAR1.20 10" PIPE TO ELBOW --.-------- --- ---- --R-A 11204-127-3-RB NMP-ES-024-501 S11V1U010 NRI NA

I R1.20 10" ELBOW TO PIPE 11204-243-29-RB Examined base material only (SW)~R.A NMP-ES-024-501 S11V1U021 NRI

~1.11/16 1.5" PIPE TO VALVE per MRP-146. . R-A 11204-243-30-RB

---

Examined base material only (SW)

l NMP-ES-024-501 S11V1U022 NRII R1.11 1.5" VALVE TO PIPE per MRP-146.

11204-243-31-RB ---

NRI Examined weld and base material perR-A NMP-ES-024-501 S11V1 U023_.R1.11H 1.5" PIPE TO ELBOW _ MRP-146.

3-1

Vogtle 1 R16 - Examination Summary (Total Piping)

ASME

Section XI

Cat litem

R-A

R1.11

R-A

R1.11H

f~ R-A

R1.11

R-A

R1.11Hl ! R·A I R1.11

R-A t R1.11H

r R-A R1.11

Examination/Area (Sort)

11204-244-24-RB 1.5" VALVE TO PIPE

11204-244-25-RB 1.5" PIPE TO ELBOW

11204-245-29-RB 1.5" VALVE TO PIPE

11204-245-30-RB 1.5" PIPE TO ELBOW

11204-246-32-RB 1.5" VALVE TO PIPE

11204-246-33-RB 1.5" PIPE TO ELBOW

1120S·009-6-RB 3" PIPE TO BRANCH CONNECTION

Examination

Procedure(s)

NMP-ES-024-501

NMP-ES-024-501

NMP-ES-024-501

NMP-ES-024-501

NMP-ES-024-501

NMP-ES-024-501

NMP-ES-024-501

Exam/Cal Sheet No(s)

S11V1U024

S11V1U025

S11V1U027

S11V1U026

S11V1U028

S11V1U029

S11V1U030

Results

NRI

NRI

NRI

NRI

NRI -

NRI

NRI

Remarks


per MRP-146.

Examined weld and base material per

MRP-146.


Der MRP-146.


MRP-146.


per MRP-146.


MRP-146.

NA

3-2

--

--

--

- -

- -

i

Vogtle 1 R16 - Examination Summary (Total Equipment)

ASME

Section XI

Cat /Item

N-722 i- B15.120

B·D B3.140

f-B-D

B3.140I-- --B-B

B2.40 N-722

f----- _B15.120 N·722

B15.120 N·722

B15.120 C-A

'.- C1.30 B-N·1

B13.CH R-A

R1.15D R·A

R1.1SE R-A

R1.15E R-A

R1.1SD R-A

R1.15D -

R-A

R1.15E

R-A

R1.15E

Examination/Area (Sort)

11201-B6-001·I10·VT Cf-iANNEL HEAD DRAIN TUBE (WCAP 12907)

11201-B6·001 -IR-01 INLET NOZZLE INNER RADIUS

11201·B6·001 -IR-02 INLET NOZZLE INNER RADIUS

11201-B6-001-W08 TUBE PLATE TO CHANNEL HEAD WELD

11201-B6-002-110-VT CHANNEL HEAD DRAIN TUBE (WCAP 12907)

11201·B6·003·I1 O·VT CHANNEL HEAD DRAIN TUBE (WCAP 12907)

11201·B6·004·I10-VT CHANNEL HEAD DRAIN TUBE (WCAP 12907)

11201 -B6·004-W07 LOWER SHELL BARREL TO TUBE PLATE WELD

11201-V6-001-102 VESSEL CLOSURE HEAD INTERIOR (FSAR 5.3.3.7)

11201-V6-001-W33-RB OUTLET NOZZLE N1 SAFE END WELD BMV

11201-V6-001-W34-RB INLET NOZZLE N2 SAFE END WELD BMV


11201-V6·001-W36-RB OUTLET NOZZLE N4 SAFE END WELD BMV

11201-V6-001 -W37 -RB OUTLET NOZZLE N5 SAFE END WELD BMV


11201·V6-001-W39-RB INLET NOZZLE N7 SAFE END WELD BMV

Examination

Procedure(s)

NMP-ES-024-202

NMP-ES-024-S13

NMP-ES-024-S13

NMP-ES-024-S16

NMP-ES-024-202

NMP-ES-024-202

NMP-ES-024-202

NMP-ES·024-S16

NMP-ES-024-203

VENDER

VENDER

VENDER

VENDER

VENDER

VENDER

VENDER

Exam/Cal

Sheet

No(s)

S11V1VOO1

S11V1U043

S11V1U044

S11V1U042

S11V1VOO2

S11V1VOO3

S11V1VOO4

S11V1U041

S11V1VOOS

VENDER

VENDER

VENDER

VENDER

VENDER

VENDER

VENDER

Results

Accept

NRI

NRI

-

NRI

Accept

Accept

Accept

NRJ

Accept

-

NRJ

NRJ

NRI

NRI

NRI

NRI

NRJ

Remarks

NA

NA

NA

80% Code Coverage.

Relief Request required.

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

3-3

--- --

-- -- --

--- ---

--- --- -

--- ----

I

Vogtle 1 Ri6 - Examination Summary (Total Equipment)

, ASME Exam/CalExamination/Area ExaminationSection XI Sheet Results Remarks(Sort) Procedure(s)Cat /Item _ No(!;)

R-A 11201-V6-001-W40-R8 VENDER VENDER NRI NAR1.1SD OUTLET NOZZLE N8 SAFE END WELD BMV cN-729 11201-V6-CRDM(VT-2) NMP-ES-024-202 S11V1V017 Accept NA

B4.10 VT2 VESSEL CLOSURE HEAD EXTERIOR

B-D 11201-V6-002-IR-02 NMP-ES-024-513 S11V1U016 Accept NA

83.120 6" SAFETY NOZZLE INNER RADIUS 1------ f~-B·D 11201-V6-002-IR-03 NMP-ES-024-513 S11V1U017 Accept NA

B3.120 6" RELIEF NOZZLE INNER RADIUS B·D 11201-V6-002-W12 NMP-ES-024-401 S11V1MOO1 NRI 55% Code Coverage.

B3.110 UPPER HEAD TO 6" SAFETY NOZZLE WELD NMP-ES-024-516 S11V1U019 NRI Relief Request required.

B-D 11201-V6-002-W13 NMP-ES-024-401 S11V1MOO2 NRI 55% Code Coverage.

B3.110 UPPER HEAD TO 6" SAFETY NOZZLE WELD NMP-ES-024-516 S11V1U020 NRI Relief Request required.

C-A 11205-E6-001-W01 NMP-ES-024-506 S11V1UOO1 NRI NA

C1.10 TUBE SIDE SHELL TO FLANGE WELD

C-A 11205-E6-001-W02 NMP-ES-024-506 S11V1UOO2 NRI NA

i-------- C 2.1 0 TUBE SIDE SHELL TO FLANGE WELD CoB 11205-E6-001-W04 NMP-ES-024-301 S11V1POO1

--

NRI --

41 % Code Coverage. 1------

Yogtle 1R16 - Examination Summary (Total Supports)

ASME Exam/CalExamination/Area ExaminationSection XI Sheet Results Remarks(Sort) Procedure(s)Cat litem Noes).

F-A 11201-029·H021 NMP-ES-024-203 S11V1VOO7 SAT N/AF1.10S MECHANICAL SNUBBER

F·A 11201·04S-HOO5 NMP-ES-024-203 S11V1VOO8 SAT N/AF1.10S MECHANICAL SNUBBER

F·A 11204·025·H012 NMP-ES-024-203 S11V1VOO6 SAT N/AF1.10S MECHANICAL SNUBBER

1F·A 11204·124-H014

~

NMP-ES-024-203 S11V1V013 SAT N/AI---- F1.10S MECHANICAL SNUBBER

F·A 11204·127·H015 NMP-ES-024-203 S11V1V014 SAT N/AF1.10S MECHANICAL SNUBBER

F·A 11204-24S-HOO1 NMP-ES-024-203 S11V1VOO9 SAT N/A

r--F1.10S MECHANICAL SNUBBER F·A 1120S·009·HOO2 NMP-ES·024·203 S11V1V016 SAT N/AF1.10S MECHANICAL SNUBBER f-F-A 1120S-Q12-H012 NMP-ES-024-203 S11V1V012 SAT N/AF1.10S MECHANICAL SNUBBER

I~-

F·A 11301·104·HOO2 NMP-ES-024-203 S11V1V010 SAT N/Ai--F1.20S MECHANICAL SNUBBER F·A 11301-10S·HOO3

NMP-ES-024-203 S11V1V015 SAT N/Ar------F1.20S MECHANICAL SNUBBER

F·A 11302·110-H019 NMP-ES-024-203 S11V1V011 SAT N/AF1.20S MECHANICAL SNUBBER I---- F-A

11305·0S4-HOO7 NMP-ES-024-203 S11V1V018 SAT N/AF1.20S MECHANICAL SNUBBER L~~ _ -

3·5

TABD



• SYSTEM PRESSURE TESTS

SYSTEM PRESSURE TESTS

The following system pressure tests on Class 1 and Class 2 components were performed after the last refueling outage (1 R15) through the completion of the sixteenth refueling outage (1 R16). The system pressure tests indicated include system leakage tests for: • Class 1 components (IWB-2500-1, Examination Category B-P), • Class 2 components (IWC-2500-1, Examination category C-H) not required to operate during normal

plant operation which are identified as 84003-101 through 84003-117, and, • Class 2 components (IWC-2500-1, Examination category C-H) required to operate during normal

plant operation which are identified as 84003-1AA through 84003-1CR. Boundaries for the system pressure tests are described in the Pressure Test Plan (Inservice Inspection Plan-Volume 3). Examination results are discussed in the applicable sections of this report document. The examination data for these system pressure tests is available at the plant site for review upon request.

, Test Number Exam CatJ Item No.

14910-101 B-P I B15.10 84003-101 C-H I C7.10 84003-104 C-H/C7.10 84003-105 C-H I C7.10 84003-108 C-H I C7.10 84003-112 C-H I C7.10 84003-113 C-H I C7.10 84003-117 C-H I C7.10

84003-1AA C-H I C7.10 84003-1AB C-H I C7.10 84003-1AC C-H I C7.10

84003-1 AD C-H I C7.10

84003-1AE C-H I C7.10

84003-1AF C-H I C7.10

84003-1AG C-H I C7.10

84003-1AH C-H I C7.10

84003-1AI C-H I C7.10 84003-1AJ C-H I C7.10

84003-1AK C-H I C7.10

84003-1AL C-H I C7.10

84003-1 AN C-H I C7.10 84003-1AO C-H I C7.10 84003-1AP C-H I C7.10 84003-1AQ C-H I C7.10 84003-1AW C-H I C7.10

C-H I C7.10

System Pressure Tests)

Test Description

Class 1 System Leakage Test Reactor Head Vent System Leaka~e Test Safety Injection Pump 1204-P6-003 Discharge System Leakage Test Safety Injection Pump 1204-P6-004 Discharge System Leakage Test Penetration 30 (SI to Cold Legs) System Leakage Test Containment Spray Train "A" System Leakage Test Containment Spray Train "B" System Leakage Test Line 1208-133 (HV-8104 to Valve 185 Flow Test) System Leakage Test Charging Line Inside Containment System Leaka~e Test Letdown Line Inside Containment System Leakage Test Reactor Coolant (RC) Pumps 1, 2, 3, and 4 Seal Leakoff Inside Containment System Leakage Test RC Pump 1 Seal Injection from Penetration 54 to Valve 006 System Leakage Test RC Pump 2 Seal Injection from Penetration 53 to Valve 359 System Leakage Test RC Pump 3 Seal Injection from Penetration 52 to Valve 360 System Leakage Test RC Pump 4 Seal Injection from Penetration 51 to Valve 361 System Leaka~e Test Reactor Coolant System (RCS) Hot Leg Sample Lines to Penetration 24 System Leakage Test Sample Line from Valve 101 to Valve HV-3514 S~stem Leakage Test CVCS System Leakage Test with Normal Charging Pump Operating (Outside Containment) Centrifugal Charging Pump 1208-P6-002 (Train "A") Discharge System Leakage Test Centrifugal Charging Pump 1208-P6-003 (Train "B") Discharge System Leakage Test Accumulator Tank 1 (1204-V6-002) System Leakage Test Accumulator Tank 2 (1204-V6-003) System Leakage Test Accumulator Tank 3 (1204-V6-004) System Leakage Test Accumulator Tank 4 (1204-V6-005) System Leakage Test Refueling Water Storage Tank (RWST) System Leakage Test

4·1

Test Number Exam Catl Item No.

84003-1AY C-H I C7.10 84003-1AZ C-H I C7.10

84003-1BA C-H I C7.10

84003-1BC C-H I C7.10 84003-1 BE C-H I C7.10

84003-1BF C-H I C7.10

84003-1BG C-H I C7.10

84003-1BH C-H I C7.10

84003-1BI C-H I C7.10 84003-1BJ C-H I C7.10 84003-1BO C-H I C7.10 84003-1BP C-H I C7.10 84003-1 BO C-H I C7.10 84003-1BR C-H I C7.10 84003-1BS C-H I C7.10

84003-1BU C-H I C7.10

84003-1BV C-H I C7.10

84003-1BW C-H I C7.10

84003-1 BY C-H I C7.10

84003-1BZ C-H I C7.10

84003-1CA C-H I C7.10

84003-1CB C-H I C7.10

84003-1CC C-H I C7.10 84003-1CD C-H I C7.10 84003-1CE C-H I C7.10 84003-1CF C-H I C7.10 84003-1CN C-H/C7.10 84003-1CO C-H I C7.10 84003-1CP C-H I C7.10 84003-1CO C-H I C7.10 84003-1CR C-H I C7.10

Test Description

Sample Line from Valve 097 to Valve HV-3S08 System Leakage Test Penetration 24 Outside Containment System Leakage Test (Post-Accident Sampling) Nuclear Service Cooling Water (NSCW) Train "A" System Leakage Test (Outside Containment) NSCW Train "B" System Leakage Test (Outside Containment) Containment Coolers 1S01-A7-001 and 1S01-A7-002 System Leakage Test Containment Coolers 1S01-A7-003 and 1S01-A7-004 System Leakage Test Containment Coolers 1S01-A7-00S and 1S01-A7-006 System Leakage Test Containment Coolers 1S01-A7-007 and 1S01-A7-008 System Leakage Test Cooling Coils 1S11-E7-001 and 1S1S-A7-001 System Leakage Test Cooling Coils 1S11-E7-002 and 1S15-A7-002 System Leakage Test Steam Generator 1201-B6-001 System Leakage Test Steam Generator 1201-B6-002 System Leakage Test Steam Generator 1201-B6-003 System Leakage Test Steam Generator 1201-B6-004 System Leakage Test Penetration 7 System Leakage Test (Outside Containment Steam Generator 1 Blowdown to Heat Exchanger) Penetration 8 System Leakage Test (Outside Containment Steam Generator 2 Blowdown to Heat Exchanger) Penetration 9 System Leakage Test (Outside Containment Steam Generator 3 Blowdown to Heat Exchanger) Penetration 10 System Leakage Test (Outside Containment Steam Generator 4 Blowdown to Heat Exchanger) Penetration 11B System Leakage Test (Outside Containment Steam Generator 1 Blowdown to Sample) Penetration 11C System Leakage Test (Outside Containment Steam Generator 2 Blowdown to Sample) Penetration 12B System Leakage Test (Outside Containment Steam Generator 3 Blowdown to Sample) Penetration 12C System Leakage Test (Outside Containment Steam Generator 4 Blowdown to Sample) Main Steam Loop 1 System Leakage Test (Outside Containment) Main Steam Loop 2 System Leakage Test (Outside Containment) Main Steam Loop 3 System Leakage Test (Outside Containment) Main Steam Loop 4 System Leakage Test (Outside Containment) Main Feedwater Loop 1 System Leakage Test (Outside Containment) Main Feedwater Loop 2 System Leakage Test (Outside Containment) Main Feedwater Loop 3 System Leakage Test (Outside Containment) Main Feedwater Loop 4 System Leakage Test (Outside ContainmentL Excess Letdown Heat Exchanger System Leakage Test

4-2

lABE



• REPORTABLE INDICATION SUMMARY

REPORTABLE INDICATION SUMMARY

The following Indication Notifications Forms and/or Condition Reports were issued due to reportable indications or conditions being observed during the examination of either Class 1 or 2 components during the sixteenth (16th ) maintenanceirefueling outage at VEGP-1 (referenced attachments are available at the VEGP plant site for review upon request

INF NO. and/or Affected Component/Area INF Disposition

Condition Report

N/A N/A None reported for 1R16

The Indication Notification Form(s) constitute only those reportable indications or conditions observed during the SNC Engineering Programs Department scope of work. With the exception of Steam Generator Tube Inspections any reportable indications or conditions observed by VEGP Site personnel or outside contractors during their scope of work should be identified by/to the VEGP Site in report document(s) which are referenced herein. Additional information related to Steam Generator Tube Inspections are to be provided in a separate report one hundred eighty (180) days after the initial entry into MODE 4 as required VEGP Technical Specification 5.6.10.

5-1

TABF

OWNER'S REPORT FOR REPAIR AND

REPLACEMENTS

(ASME FORM NIS-2)

OWNER'S REPORTS FOR REPAIRS OR REPLACEMENTS (FORM NIS-2)

The following Owner's Reports for Repairs or Replacements (Form NIS-2) are provided for work activities documented at VEGP-1 since the last maintenance/refueling outage (1 R 15) through the completion of the sixteenth maintenancelrefueling outage (1 R16). Reports are identified by their respective traveler number which is denoted on each of the NIS-2 reports. The originals of the NIS-2 reports are filed with their respective traveler packages at the plant site. Only those NIS-2 reports applicable to VEGP-1 are included in this report document. Any attachments, e.g., code data reports, etc., referenced in the NIS-2 reports will be made available for review upon request at the plant site. It should be noted that even throL1gh Site procedures may require the use of an NIS-2 form, Code Case N-508-3 "Rotation of Service Snubbers and Pressure Relief Valves for the Purpose of Testing" does not require the use of an NIS-2 form provided certain conditions are met. Therefore Repair/Replacement activities not requiring NIS-2 forms per Code Case N-508-3 are excluded from this Owner's Report.

:10008 10079 10096 11017 110049 10080 11000 11018 10051 10087 11009 11024 10054 10088 11011 11026 10055 10090 11014 11027 I

110067 10093 11015 10077 10095 11016 I

6-1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required By The Provisions Of The ASME Code Section XI

Traveler II 10008

1. Owner Southern Nuclear Operating Company Date June 02, 2011 Name

40 Inverness Center Parkway. Birmingham, AL Sheet of ,/'3 IiiJt1;V-I Address

2. Plant Vogtle Electric Generating Plant Unit

Name

Waynesboro, GA 30830 1100328801 Address Repair/Replacement Organization P.O. No., Job No., etc.

3. Work Performed by Maintenance Department Type Code Symbol Stamp NiA

Name Authorflation No. NlA

Plant Vog1Je Expiration Date NiA Address

4. Identification of System 1205 - Residual Heat Removal System

5. (a) Applicable Construction Code ASME Sec. /II 1971 Edition, Winter 1972 Addenda, _.......::..::.:..-'-_ Code Case

(b) Applicable Edition of Section XI Used for Repair/Replacement ActIvity _-",2""QO:.1:..ed=.-"2",OO",,3,,-,,,adoo:d~._ (c) Applicable Section XI Code Case(s}

6. Identification Of Components

National Corrected, ASMECode Name of Name of Manufacturer Board Other Year Removed, or Stamped

Component Manufacturer Serial No. No. Identification Built Installed (Yes or No) RELIEF VALVE CROSBY VALVE & N56904-00-0036 NlA 1·PSV·8708A 1977 INSTALLED YES

GAGE CO.

7. Description of Work Serial no. N56904-00-0017 was replaced with N56904-00-0036 under MWO 1081980701;

ref. CR 2009110597. MWO 1100328801 verifies serial no. of valve.

8. Test Conducted: Hydrostatic 0 PneumaticD Nominal Operating Pressure@ ExemptD ______ oFOther 0 Pressure NOPT psi Test Temp.

9. Remarks _V~T~.=2_________________~~~~~~~~_~~__~__~~~~__~~_______~__________ Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCE I certify that the statementa made in the report are correct and that this conforms to the requirements of the ASME

Code, Section XI.

Type Code Symbol Stamp NlA

Certificate (!Authorization No. NIA Expiration Date NIA

r

O"~ Signed L:":'lr~ /\.'-- .J"" i /C) ';~~;;,.L/.. Date C-;: IS { ,

( Owner or Owner's Designee, Title )

\,~j

..-'


I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessellnapectora and the state or Province of Q!lQrgj;;j and employed by HartfQra Stfi{;lm Boiler Ins(2ectiQII and tnsur;;jnQ§. CQ. of CQnnf!QticILt of HaaiQrri, ~Qnn~fi~!L( have inspected the components described in thIs Owner's Report during the period / - 06 -..2011 to La ~ MO -,.;zojel, and state that to the best of my knowledge and belief, the Owner has performed eKaminations and taken corrective measures described In this Owner's Report in accordance with the requirements of the ASME COde, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and correct/ve measures described In this Owner's Report. Furthermore, neither the Inspector nor hili employer shall be liable In any manner for any personal injury or property damage or a los.s of sny kind arising from or connected with this Inspection.

Commissions 6-A '1..S'6~ National Board, State, Province and EndorsementsiliSPec s Signature Date c2.0 ~Vbo.!:l~ ~, 1;~,

,__,""""'"t5 !Q I ~

Serial No. or Material Spec i(lcatlon

rdelltlfic 1:Ion rneludlng Type or Grade

:.lX261B-0032 ASTM A31J-70 Type 316 e. Spring

d. !lolting

e. Other Parts sucil as Pilot Components

Crosby Va 1'lo-! 3t Ga:>e Co. Sy {~_r;/ft?::?::z..;:;1',,-,--___._13 17= Sig;H!d ',(anu(acc'upr QA Manager

Cerufil.a.te ot AU[ltOtlla.tlOll :'

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required By The Provisions Of The ASME Code Section Xl

Traveler # __Ic.::0:.::O..;.4:::..9____

1. Owner Southern Nuclear Operating Company Date May 06.2011

Name

40 Inverness Center Parkway. BirminQ,ham. AL Sheet of Address

2. Plant Vog.t'e Electric Generating Plant Unit

Name

Waynesboro. GA 30830 1100169301 Address Repair/Replacement Organiution P.O. No .• Job No.. etc.

3. Work Pertormed by Maintenance Department Type Code Symbol Stamp NIA

Name Authorization No. NiA

PlantVo~ Expiration Date Ni/" Address

4. Identification of System 1208 - Chemical and Volume Control System

Code Case 5. ~:~ ::',~~:~~: ~~~7~~U~:i~:C~i~~eXI use~~:r~!:~i::~::~:cem~~~t~:'ivity sum;~11:;:200:~~~~da, ___Nl._A__

(c) Applicable Section XI Code Case(s)

6. Identification at Components

National Corrected, ASME Code Name ot Name of Manufacturer Board Other Year Removed, or Stamped

Component Manufacturer Serial No. No. Identitication Built Installed (Yes or No) VALVE DRESSER H201ABH N/A 1·1208·U4·033 1982 REPLACED YES

INDUSTRIES, INC

7. DescriptIon of Work Seal welded valve body to bonnet.

8. Test Conducted: Hydrostatic 0 PneumaticD Nominal Operating pressure[!]

Other 0 Pressure NOP psi Test Temp. NOT

9. Remarks _N~on~e~_________________~~~~~~~____~~__~______~____~~______________________ Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCE

I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME

Code, Section XI. ,Type Code Symbol Stamp NIA Certificate ¢"Authorlzation No. N/~ Expiration Date NIA

i 1

Signed /'~ O. '\J"'-~ ( /. ) 'O~ L)" .. Data (::, «~ (I

t I Owner or Owner'sLlesignee, Title I !

\,j I.


I, the undersigned, holding a valid Commission issued by the National Board of Boller and Pressure Vessel Inspectors and the state or Province of Gf!9.rgJa and employed by Hartford Steam Boiler InsDBction and Insurance Co. of Connecticut of HartfO~ c~nnecJcut have inspected the components described In this Owner's Report during the period ~ /.J'~ /"::1") U"l to £; I 0:40 I, and state that to the beat of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shalf be liable In any manner for any personal injury or property damage or a loss of any kind arising trom or connected with this

'~~ Commissions ~ 7:S"t.

I spector Ignature National Board, State, Province and Endorsements

Data ~(") ;::n:.lI.. ::&'§: cH:>1:l

......~..............,- FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY

As Required By The Provisions Of The ASME Code Section XI Traveler # 10051

1. Owner South em Nuclear Operating Company Date June 03, 2011 Name IJA").!

40 Invemess Center Parkway, Birmingham, AL Sheet of 13 ,,!(J;-;2l/ - II Address

2. Plant VogUe Electric Generating Plant Unit

Name

Waynesboro, GA 30830 1091765401 Address Repair/Replacement Organization P.O. No .. Job No., etc.

3. Work Performed by Maintenance Department Type Code Symbol Stamp NIA

Name Authorb:alion No. NlA

Plant VogUe expiration Date NIA Address

4. Identification of System 1302 - Auxiliary Feedwater System

5. (a) Applicable Construction Code ASME Sec. 1/1 1974 Edition, Summer 1975 Addenda, ___NI._A__ Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 ed. 2003 add. (c) Applicable Section XI Code Case(s)


National Corrected. ASME Code

Name of Name of Manufacturer Board Other Year Removed, or Stamped

Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

STUD MACKSON, INC NIA NIA HTN365740 2010 INSTALLED YES

NUT NOVA MACHINE NIA N/A HT #8994826 2007 INSTALLED YES PRODUCTS CORP

7. Description of Work Replacement of studs/nuts for IFE5288.

B. Test Conducted; Hydrostatic D PneumaticD Nominal Operating PressureD Exempt[!J

Other D Pressure ____psi Test Temp. ______ OF

9. Remarks VT·1 Inspection of studs/nuts

Applicable Manufacturer's Data Reports to be attached



Code, Section XI.

Type Code Symbol Stamp NIA

Certificate of~thorizatiOn No. ______..;.NI.:;;A~-,...'i--__- Expiration Dete NlA 4\ \ - '~l" ,,/ \"-"~"""" _(,/ r--, r I ,~' 'IASigned '':--''-if 1 i\ ',~,,"--- ./,.,/ "'" L I Date ....ll"-l'K;,,'_-_'_''_':""'1_'''_'f_,,-

, Owner or Owner's Designee Title I


I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the state or Province of Georgia and employed by _ Hartford Steam Boiler insoection and InsuranC,tLCQ, of Connect/eLf of Htrtfr;if~2ut have inspected the components described in this Owner's Report during the period S/fS/OlOID to;and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owner's Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certlficete neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions -~Gl""A-'7"'--f':Z-!!"'S,,,,,,,(.~,c:.----=--:----:-=--:----,---~ec~a4f National Board, State, Province and Endorsements

44130

., • ItJ{)5'1 sZ. :3 tI?.:3 8001 R08d·'DU)t-t(.)~l.Qaalo MI tIt,OH

\';-1'-'- D. ~ (".n'TtmIllH!lbl Power and Services

8287320G FAX 216 433 1840

CURTISS·WRIGHT FlOW CONTROL

CERTIFICATION AT! OF COMPUANCEICONFORIWfCI! (!] MATERIAl. l!ST REPORTl!l Cl!ATFICICI!AT t 72908 cut DATE: .2O-NOV.Q1 PO. !7080170 !

rCo. (Vogtle)• Georgia POWtI Vogtte Gone:rallng

7821 River

Plant

Road

REL'

10' 128483 UNIt 1

IWaynetboro I

L GoA 30830 US OTV

200EA

Lor. ! 50123491 - - !

HEAT' !8994828r· -..-DRWG'i

ITra:e CodtI OJA

-. "

I

I CLJSTOCk:

10624

ITEMD!IC: 7/8"-9 UHC 2S HEAVY HEX NUT

MATERW. SPECIFICATIONS: ASUE SA-194(89)Or.2H

HeAT TREAT SPECIFICATIONS Quenched and lel'l1'MtNld.. Minimum temperll'Q len,:l8rature: 850 F

ASM! IPECIFICA11ONI: ASUE SectIott II SubMctlon NC ct2 1989 Ed. no Add.

ANSIf"''' SPECFtCAnoNS: AN$II ASME B1.1, 818.2.2

QUAun' IPECFlCATIONI: Dll1'IIIlVIionallnepection perforrnacf and results al1J accaptable. H'JO% \/iwally examined and accepted per Nova Wodc 1n8t1'ldlon 8.1.3 Rev.S which meets the '*fUlremanta at SA/A.. 8t4Jru. Nx·2S00. F-788 & F-612;; Mee1IIlht applicable PQI1lona 01 tOCFASOAppendix B. ANS. N45.2 & 1OCFA21;

Mt!CfWlICAL 8Pl!CtFlCA11ONS: 24 hi 1000 OEQ. F Hard FIb 98, 98, 911 Hard Rc 32 Proolload 1801 DO PSI (83tOO LB) Cone Strip 17S000 PSI (80500 LB, Macroetch: AoceptabIe

ATTACHMENTS'; 1031822 (MIIf). 3041826

CERT , 72tOI CERT DATE~ 20-N0Y.cr7 Pags: 1 rJ 2

As Required By The Provisions Of The ASME Code Section XI Traveler /I 10054

1. Owner Southern Nuc/ear Operating Company Date Mat. 16, 201 f Name

40 Inverness Center Parlcway. Birmingham, AL Sheet of /1 p~)Ij-1l Address

2. Plant Vogt/e Electric Generating Plant Unit

Name

Waynesboro. GA 30830 1100864801 Address Repair/Replacement Organization P.O. No., Job No., etc.

3. Work Performed by Maintenance Department Type Code Symbol Stamp N/A

Name . Authorization No. N/A

Plant V0fJ!.le Expiration Oate MA Address

4. Identification of System 120 I - Reactor Coolant System

5. (a) Applicable Construction Code ASME Sec. 1111974 Edition, Summer 1975 Addenda, ____NI_A__ Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity .~2001 ed. 2003 add. (c) Applicable Section XI Code Case(s)


National Corrected, ASMECode


Component Manufacturer Serial No. No. Identifioetlon Built Installed (Yes or No)

PUMP WESTINGHOUSE 10-9744035602 NIA 1-1201-P6·OO4 1995 INSTALLED YES

ELECTRIC CORP.

7. Description of Work A replacement #2 seal housing was installed. The replacement #2 seal housing. SIN 2186. is a rotating spare

that has previously been in service.

8. Test Conducted: Hydrostatic 0 PneumatlcD Nominal Operating Pressure[!] Exempt[!]

Other 0 Pressure psi Test Temp. ______ of

9. Remarks ""N:.:.o::;.;n,;.;:e'--_______

Applicable Manufacturer's Data Reports to be attaohed ....

CERTIFICATE OF COMPI.IANCE


Code, Seotion XI.

Type Code SymbOl Stamp NIA

Certificate ofAuthorization No. ____-.-_..;.N"'/'7:4'-r_____Explration Date NlA

( \ ! . \ ( ) i . Signed .';·'''U). ,~-~/-~, ( /\J> ....~ Date G ( S· If

f J Owner or Owner's DesI9,.nee, TItle 1 --'-_-'---'---t.___


I. the undersigned. holding a valid commission issued by the National Board of Boller and Pressure Vessel Inspectors and the state or Province of Georgia and employed by _ Hartford Steam Boiler InsDBction and Insurance Co. of.Connecticut of H~ CQ!1!J!iiQ1icut have Inspected the components described in this Owner's Report during the period 5/;u,/;;lD jl:J to I&/;ilfiabjj, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measure!ll described In this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measurea de!llcrlbed In this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner tor any personal injury or property damage or a loss of any klnd arising from or connected with this

~ Co"",,/Oolo.. -..Jt"'a'-'::'-'o-n~af"'B..aflC.a"'~jL.d-,-S-ta-te-,-P-r-o-v,-,n-ce-a-n-d""E"'n-d""'o-r-se-m-e-nt-s---

http:V0fJ!.le

ORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Aequired By The Provisions Of The ASME Code Section XI

Traveler It 10055

1. Owner Southern Nuclear Operating Company Date Maz:.31,2011 Name j}t{)f . /1

40 Inverness Center Parkway, Birmingham, AL Sheet of I'd ot, ':;''/ Address •


Name

Waynesboro, GA 30830 1092197601 Address RepairIReplacement Organization P.O. No., Job No., etc.

3. Work Performed by Maintenance Deeartment Type Code Symbol Stamp N/A

Name Authorization No. NiA

Plant vogt/e Expiration Date NlA Address

4. Identification of System 1208 - Chemical and Volume Control System

5. (a) Applicable Construction Code ASME Sec. 1//1974 Edition, Summer 1975 Addenda, ___M_A__ Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 ed. 2003 add•.~~~.~ (c) Applicable Section XI Code Case(s)


National Corrected, ASME Code



NUT NOVA MACHINE NIA NlA LOT # 50043678 2005 CORRECTED YES

PRODUCTS CORP HT # 7420694

7. Description of Work ......;.R,;;8..e...;'a,;.;c.;;,8..;,n;.;;ut.;,;;s'-o"'n.;,.;.;.;ha:::.n"'9"'e"'r._______________________________

8. Test Conducted: Hydrostatic D PneumaticD Nominal Operating PressureD Exemptf.!]

______ oFOther D Pressure psi Test Temp.

9. Remarks ~N~o:::.n~e~_________~~~~~~~__~-=_~___~~____~~-----------------------Applicable Manufacturer's Data Reports to be attached


I certify that the statements mede in the report are correct and that this conforms to the requirements of the ASME

Code, Section XI.


Certificate rruthorization No. ___....,,--_---'NI-?',(A='-'-1)______Expiration Date NlA

, L /~ , ~. , " I \ I!\ ( / , {' . f(Signed c/"f (', ;. ."'~" '_.f":, i / j ¥" 't-.

.

" . ..,. /ld55

sA.

C£ATIFICAnON

:1W0P'~ [XJlMlIJIIM.1UTMPORTlll_~ cau 24&51 CPT DAti: 25-Af'R.05 Po. 70lIl$111

O'MH' Co. CVOlf') -,••.... " .. -SOl 1~at/fIg PMnt - ~I 1 _../'Old -.-- --- .-.__.-.- .. -.-.- an 200 F.AG.A 30830 US

LOT' ~I

... HUT' 7.QIfAM-- .. ... --,.. ____h DfIWQ.

..... v ....... ......... ..... ,

~~.-. .. --_ .. _,., ,- ••' __ _ .. ... _ r,,,,,,,,,,_

CL.JSTOCK:

10121

naouc: 112"-13 UNC 2B HEAVY HEX NUT

MATIIIW. SPEClllCA11CIN8: ASME Sl,..194('81) Gr.!H

HUT IHCIlACATION:

Ouenahed and ~. Mn/mUm ~ le/l'12'lrwtu... : 150 F

AaMe'IPECIFICA'T1ON8;

ASMI! SIcIIorIII ~NC eLf 'l1li Eel ncJ ~

AN.....1NCIFICA11DN8: ANSI j ASWE .'.1,.11,3.2

QUAU1'Y 1PECFICA'I'ION8~

,cmI. \IiMIfy...,......1IId ~I*NowII~ NP.VlS , _.15 lIIiHdI",.."" ~ 01 SNIP

814, Nk.2S00. Jl.7II& F"'12;MNI.ItMt~II(Ii'IIOI'IItOf ;OCfRflO~B.ANSI NoMI.:n 1OCFNf,

CHD1IICAL III'IClP'lCATIOHIk

PfDCIUCIlII'IUyIIs

C.'" MN.11 fIA.Mr 8.012 SL 17 HI.01 CR." MO.02 vc:.m CU.01

CAT MN.7'2 P.OfR $.0'2 81." 1111.01 CR.OI MO.. Vc•.01CU.01

IIIICHANICAL 1fII!CIIIGA1'1OHS:

Hatd: no ItProof Load aeoo lB8 (1I0000 PSI) Cone $rio 21300 LeS (",SOOOO PSI)

24 hr UIOO OEO.F: Z' IV Hard FIb ".0

AnACtIllll!ft1a

2Q6I071; 2021114

tEAT' Z44III OIAT DATE: ZSoAP.... Page: 1 or:l

http:25-Af'R.05

OR~'G4II '1 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY

As Required ByThe Provisions Of The ASME Code Section XI Traveler # 10067

1. Owner Southern Nuclear Operating Company Date June 03, 2011

Name /JP{f{t/ II

40 Inverness Center Parkway, Birmingham, AL Sheet of /3 '06-1 ... Address " 2. Plant Vogtle Electric Generating Plant Unit

Name

Waynesboro. GA 30830 1/0/066301

Address Repair/Replacement Organization P.O. No., Job No., etc.

3. Work Performed by Maintenance Department Type Code Symbol Stamp N!A

Name Authorization No. NIA

Plant Vl!fJ.lle Expiration Date N/A Address

4. Identification of System 1201 - Reactor Coolant System

5. (a) Applicable Construction Code ASME Sec. /111977 Edition, Winter 1977 Addenda, NlA Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity ~_2001 ed. 2003 add..~----';';:';"'--(c) Applicable Section XI Code Case(s)


National Corrected, ASMECode



PIPE PULLMAN POWER 260 NIA H201·036·HOI6 1987 INSTALLED YES

SUPPORT PRODUCTS

PIPE PULLMAN POWER HEATN F88 NIA H201-036-HOI6 1990 INSTALLED YES

SUPPORT PRODUCTS

PADDLE

7. Description of Work AO-5503 snubber replaced to support surveillance testing.

8. Test Conducted: Hydrostatic D Pneumatic 0 Nominal Operating pressureD Exempt[!j ______ GFOther D Pressure psi Test Temp.

9. Remarks ~N~on~e~___________~~~~~__~_~~~-=__~__~__~~~_______________________


CERTIFICATE OF COMPLIANCe

I certify that the statement!! made In the report are correct and that this conforms to the requirements of the ASME

Code, Section XI.


Certlficatete&outhor/zalion No. N/A Expiration Date NlA.. ~ i ~ n

Signed' !'vv~ \.. /\ )S"L-!L(."'l Date ! J Owner or Owner's Designee, Title I


I, the undersigned, hoidlng a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the state or Province of G90rqia and employed by ~ H fi II r In inn In ~ n f Conn of. ~J;Qrm..~ut have Inspected the components described In this Owner's Report during the period ~""'-fJ..s....,'-Gou...,I.IJ'-t to i.Ziti jIilbj{) and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this Inspection.

~~nJ~ Commissions (.,A· ZS"'Ce~o}'ifo'=me --:!N':-a"'ti'-'!o=-n":"a'"'lB:::'o"'a""r""d"',"!Si

Fliping Materials Requisition UK'1U5u'f'i) (0 l-1 ewE '" N~ 099590

- NI" I'l..4AGSb

{)A fl~AWIf'.JG NO PEV l"'ATFFltAL CLASS rATt UN. \~v~rfV i>,JO "POJECT ct ASS 'Ie

Eft£. 71L P S"""; 6",4 '/fl> I" ""',.~ "'.., ;:::l< t.'" t· L~, - ~ ..~ ..L';---c7'-1-----1-~i-.----~--'.Qq~.--~2~?~~(j ~~I+ ~ . ~\

_"-+~ f~ EtX..~9_~g__!'.t!QJ!!ft:. WLI.JXIt.. ,RINb 'DOl ._ 4t1~ ZZ~ FeE> "

I Fo~ /Tl:>5503 ;>1J'M55ce"·).\ ~~~\':) v,-'-~'~--'"-'-"-- "-- ...,.,., ---------.-------~--,--------.-----.----- . i~lt "c,,"-:=:' ~

(,II;-,1 --'··-7~.·- ~/'c en, ,,. .~ .,~ ~,:,'t .. 5 d;'r ,0

5664

AJxhaJU-IID. r~rtrls, m It} Ii (;;. '7 '51, .5 d I '1 ''''['I-,ll•. 1',\ I,...f)

£!!lit.l ua Ji._"f$lCJ~~ lAlu~~n t AZM.i!4!.tct?:1i!l!uu j A;;l!;;WW J 4t- t '}•.1It! )I$"JM.~MiJA.Q!"$~

O~l;G!~JJ\L FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY

A!s Required By The Provisions Of The ASME Code Section XI Traveler It _____1..:.0..:.0:....;17'--___

1. Owner Southern Nuclear Operating Company Date June 03. 2011

Name

40 Inverness Center Parkway. Birmingham. AL Sheet of Address


Name

Waynesboro. GA 30830 1101068201 Address Repair/Replacement Organization P.O. No .• Job No.• etc.

3. Work Performed by Maintenance Department Type Code Symbol Stamp NfA Name Authorization No. N/A

Plant Vogpe Expiration Date

Address 4. Identification of System 1204 - Safety Injection System

5. (a) Applicable Construction Code ASME Sec. {// 1977 Edition, Winter 1977 Addenda, ___M_;.'\__ Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity ~~2.:t.OO""1,-e",d",.....2",O",,03::uoad,,,d~'r-_ (e) Applicable Section XI Code Case(s)



Component Manufacturer Serial No. No. Identification Built Installed (Yasor No) PIPE PULLMAN POWER 11646 NIA 1-1204-021-HOI4 1987 INSTALLED YES

SUPPORT PRODUCTS

7. Description of Work Remove snubber PSA-10, SIN 16101 per procedure 27351-C to support snubber testing.

8. Test Conducted: Hydrostatic 0 PneumaticO Nominal Operating PressureD Exempt[!] ______ oFOther 0 Pressure psi Test Temp.

9. Remarks _N~on~e~____________~~~~~~~~~~-=~-=__~~~__~~~_______________________ Applicable Manufacturer'S Data Reports to be attached


I certify that the statements made In the report are correct and that this conforms to the requirements of the ASME

Code, Section XI.

Type Code Symbol Stamp N/A

Certificate 1t'uthorizstion No. . NIA Expiration Date NIA

i I fj J:~, hSigned y,[\.-V-.J

t· ORIG FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY

As Required By The Provisions Of The ASME Code Section XI Traveler # 10079

1. Owner Southern Nuclear Operating Company Date June 03, 2011

Name dJ{J!

40 Inverness Center Parkway. Birmingham. AL Sheet of /J 'r-(i;~J.If~ / ( IAddress

2. Plant VogUe Electric Generating Plant Unit

Name


3. Work Performed by Maintenance Deparlment Type Code Symbol Stamp NfA Name Authorization No. NIA

Plant Vogtle Expiration Dale NlA -~"~"'""---"'--

Address 4. Identification of System 1204 - SAFETY INJECTION SYSTEM

5. (a) Applicable Construction Code ASME Sec. /JI 1977 Edition, Winter 1977 Addenda, __N/.;.;;,;.,"',--_ Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity __2~OOl:!:1.Uilel:!:d,""2003=!:;!...!a~d!l:d!.:..__ (c) Applicable Section XI Code Case(s)





PIPE PULLMAN POWER 215 NlA 1· 1204·243·HOO8 1987 INSTALLED YES

SUPPORT PRODUCTS

7. Description of Work Remove snubber AD-153, SIN 223 per procedure 27353-C to support

snubber testing.

8. Test Conducted: Hydrostatic 0 PneumatlcO Nominal Operating PressureD Exempt[!]

Other 0 Pressure _____ psl TestTemp. ______ OF

9. Remarks _N~on~e~_____________~~~~~__~~~~~~~~~~_~~~____________




Code, Se


Traveler II 10080

1. Owner Southern Nuclear Operating Company Date April 18. 2011 Name JJ/ltfl

40 Inverness Center Parkway, Birmingham, AL Sheet of O(-d't-/it.1 Address

2. Plant VogtJe Electric Generating Plant Unit

Name

Waynesboro, GA 30830 1053337901 Address Repair/Replacement Organization P.O. No., Job No., etc.

3. Work Performed by Maintenance Department Type Code Symbol Stamp NlA

Name Authorization No. NlA

Plant VogUe Expiration Date NIA Address

4. Identification of System 1205 - RESIDUAL HEAT REMOVAL SYSTEM

5. (a) Applicable Construction Code ASME Sec. 1J11974 Edition. Summer 1975 Addenda, __N.;..;v';.;..A,--_ Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 ed. 2003 add. (c) Applicable Section XI Code Case(s)



Component Manufacturer Serial No. No. Identification Built Installed (Yes or No) PIPE PULLMAN POWER 307005611059 NIA 1-1205-030-H035 1987 INSTALLED YES

SUPPORT PRODUCTS

7. Description of Work Remove snubber AO-71, SIN 883 per procedure 27353-C and replace with a Model AO-71 or Lisega Model 301856RF3 to support snubber testing.

8. Test Conducted: Hydrostatic D PneumaticD Nominal Operating PressureD Exempt~

______ DFOther D Pressure psi Test Temp.

9. Remarks ~N~on~e~________~~~~~~__~~~~~-=_~~~_~~~___________ _ Applicable Manufacturer's Data Reports to be attached


I certify that the statements made In the report are correct and that this conforms to the requirements of the ASME

Code, Section XI.


____-'='..-....:.;:;.:...:...++-____ Expiration Date NIA

Signed Date


I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the state or Province of Georqia and employed by _._ H. team Boi er In lion and In urance Co. of n ic of Hartford ~ticut have inspected the components described In this Owner's Report during the period to c.. a I fdiOILl ' and state that to the best of my knowledge and belief, the Owner has performed exam-7in""a'-'ti~o"'n"'s"'a"'n"'d~ta~k""e-n'l correctrve measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermora. neither the Inspector nor his employer shall be liable in any mannar for any personal injury or property damage or a loss ot any kind erising from or connected with this

'~ Comml,,'o", -""~""a'-'t~'-'o'-n"'~I-B~'~"'a"r'-4fr"',"-S-ta-te-.-P,.-r-o-v.,.-in-c-e-a-n-d-E:-n-d-o-r-se-m-e-n-ts---Date 21 J4bJS JDIf


Traveler # _---'1...::008c::.;;;..;..7____

1. Owner Southern Nuclear Operating Company Date April 18, 2011

Name

40 Inverness Center Parkway. Birmingham. AL Sheet of Address


Name


3. Work Performed by __:..;.M:.;;a.;..in..;.;te;.:.n;.;:B";n.;:.ce::...;;;D:.;;e,,,pa:;.rt..;:me...;;.n;...;t:...-_ Tvpe Code Symbol Stamp NlA Name Authorization No. NiA

Expiration Dais ___________.:..:N::.,:!A.:..-______Plant Vogtle Address

4. Identification of System 1301 - MAIN STEAM ;;t;srem

~t'AJlq (j(,·:;.HI5. (a) Applicable Construction Code ASME Sec. /1/ 1917 Edition, 1977 Addenda, ___NI._:4__ Code Case

(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 ed. 2003 add. (c) Applicable Section XI Code Case(s)



Component Manufacturer Serial No. No. Identification Built Installed (Yes or No) PIPE PULLMAN POWER 305002111090 NlA 1·1301·105-H002 1981 INSTALLED YES

SUPPORT PRODUCTS

7. Description of Work Remove/replace snubber AO-5503, SIN 177 per procedure 27355-C with a Model AO-5503 or LlSEGA Model 307256RC7 to support snubber testing.

B. Test Conducted: Hydrostetic D PneumaticD Nominal Operating PressureD Exempt I!] Other D Pressure psi Test Temp. ______ OF

9. Remarks ~N~o~n~e~________~~~~~~~~~~-=~~__~~~__~~~_______________________ Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCE f certify that the statements made In the report are correct and that this conforms to the requirements of the ASME

Code, Section XI.

Type Code Symbol Stamp NlAM~,~ Certificate of Aut ------..".-...:..;:;..:..:...,A----- Expiration Date NIA1f~I~~lr Signed Date


I, the undersigned, holding a valid commissIon issued by the National Board of Boiler and Pressure Vessel Inspectors and the state or Province of Georgia and employed by H rtf ~ i r In . n ~ nn i of Ha~rd q:sn~ticut have inspectad the components described in this Owner's Report during the period .:-G;~B~Jl.7,,:,Sj~t..-:-:::-:-:--::_..,-_--:,~-:-______ Nadonal Board, State, Province and Endorsements

http:j(,�:;.HI

F~r:t: INTERSTATE BOLT ~ NUT INC. SPeCIFICATIONS: 1. ASME SA194 GRADE 2HTEXAS BOLT COMPANY

CISTOME'A P.O. 1'110. :~9:'~4 P.O. BOX 1211 HOUSTON. TEXAS 772S 1-1211

2:j9~j~ ,~~J-oFL T-04 REPORT OF PHYSrCAL AND CHEMICAL TESTS 120 Deg. Cene TIM Hi n i mUl REPORT MAl'I!RIAL QUANTITY

EAVY HEX NUTS • 1 "-9 f-u0 1045 1 1 74,250 106,000 32/33 RC 8S0F

El~vat~d T~mperat~~ Test 24 ""'s at BHN 29:] • , 1-1/2" -8 TR#8B61'..(Q+ 1045 1 1 29/30 RC 8S0F

Elovated Temperat 24 h,.,,,, at F BHN 269 • 2-1/2"-8 TR#SB7~ 1045 1 1 2i'/28 RC 850F

Elpvatp.rl Temperatute Test 24 Mrs at BHN 277

ALL MATERIAL IS OF U. 10 CFR 21 APPLIES AND S." VISUAL EXAMINATION PE ALL MATERIAL IS MANUF EXAS BOLT OMPANY'S CONT~OL MANU CH WAS QUALIFIED, Not@: 'Sp@e No' column indicates

. s pC MI' 5. Ct 1111

.46 .72 .20 .02 I .02

.45 .77 .24 .o2c;4 .01 nOll l600 de3 F. , hour (s I iF mi ute e ) T deg F.

10 1(1 Q 6015214 .46 .75 -~ c:;.79

600 dl!!!g F • ~ no" 1 d.~ F. J h~r'" I•mitt.,455! 5 0 M01243 .80 .01 .....j

Avg Ch m Check .46 .o:al .00 n oil bOO de F. . houres, '- ml 98P deg F. ~ hour!(s) ::SO minL\te(s)

V\ ~.

l').

~ STATE 01' TEXAS In~p.ctor Evaluation Approv@d by;

COUNTY or HARRIS W.E. WINDT NDE LEVEL III INSPECTOR ""-J

I Clfltly 'M Ibwe ,.-aullS /0 be corrte( ..Conl.Nd in the records oIlhe cDI'I'Pln••

~.~L...d-•, .'l'"\f"I't ,-"".,::._=._-:::-:::~~~;;..;jIll:J~!;"'___

http:Elpvatp.rl

Tel: (603) 52~193132 Moulton Sleet Laconia, NH 03246 Fax: (603)52~381


CUSTOMEA SOUTHERN NUCLEAR OPERAnNG COMPANY PAGE 1 OF 3

SUBJECT PLAiIIT

PURCI-IASE ORDER

voonE

10384191001 DATE 314199

FRONEKNDESHOPORDER MPN30IO SHIPMENT DATED 3/4198-;.",;;;.,.;,.~---

IIW NO, QTY. OSSCftlPDON

1 1 FRONEK AlOE • 30158 SUPPORT SLEEVE FOR AN AD-i'ao MECH. SNUBBER

2 1 FRONEK AlOE" .8.1 SEE ATTACHED TELESCOPING SLEEVE SUB-ASSEMBLY FOR AN AO-1S00 MEctfANlCAL SNUBBER

3 9 FRONEK AIDE • 00112 BEARING SHAFT FOR AN AQ..1. MECH. SNUBBER

13 FRONEK AIDE • 0000I x·as BEAR.ING SHAFT FOR AN AD...tO MECH. SNUBBER

5 3 FRONEK AIDE I ,J.4.Q81 BEARING SHAFT FOR AN AD·125OQ MECH. SNUBBER

6 2 FRONEK AlOE "34014 X..caA THRUST RACE FOR AN AD-1250D MECH. SNUBBER

7 1 FRONEK AI'DE • 30014 X62F THRUST RACE FOR AN AD-itOa MICH. SNUBBER

FRONEK AIDE. INC. hereby certi1les tnat all items supplied under the subject P.O. conform I comply with the design. examination. testing and fabrication requirements Of the applicable code(s) and customer oontrad I speciflcafions. as listed heretn. SupportIng documents, to evidence compliance to the ASME code. have been reviewed and upon Issuance of the C of C are considered cotT1!ct and complete QA records.

COIJEfS) ASME secnoN III, SUBSECTION NF v.... 1971 Addenda WINTER 1977

10CFR50 Afp. B, 10CFR21

Coda CIISe(s)

AMAQS. REV.•

FRONEK AIDE, INC. QAM REV. 2 DATED &12119' ASME Certificate N __.....N..;;-28a;;..;.;;..__ ~ratlon Date Augu!t t, 21.. ~~~

,

~",AakAlCE,1J IRQ,m~______"~c~.~~!!2_~,?,,.£~"i""~~c.JZ

~A1A&kAIDE",J~~@~JZ"""

Tel: (603) 528-193132 Mounon Sleet

Laconia, NH 03246 Fax: (B03) 52S-a381


CUSTOAtER SOUTHERN NUCLEAR OPERAnNG COMPANY P4GE 3 OF 3

SUBJECT PLANT VOGT1..E CATE 3/41911

PURCHASE ORDER 703841tlO01

FRONEKAlOE SHOP ORDER MPN30tO SHIPMENT DATED --:3:.:...14I;.;..9.;..;9~___

ITEM NO. Qll. DESCRIPTION Trace Code

21 21 FRONEK AIDE" 41177

HEX NUT FOR AN ADC-5600 PIPE CLAMP

22 2 FRONEK AIDE 111191. SEE ATTACHED

RACK SUB-ASSEMBLY FOR AN AD-40

MECHANICAL SNUBBER

2S 1 FRONEK AIDE • 96111 SEE ATTACHED BALLSCRBN8UB~SeMBLYFORAN

AD-1600 MECHANICAL SNUBBER

FRONEK AlOE. INC. hereby certifies ltIat all Items supplied under the subject P 0. conform I comply with Ihe design. examination. testing and fabricaUon requirements of the applicable code(s) and customer contract J speCifications. as listed herein. Supporting documents, to evidence compliance to the ASME code, have been reviewed and upon issuance of the C ot C are considered correa and compfete QA records.

CCDl!esJ AS,.! SECTION III, SUBSECTION NF Vear 1177 Addenda WINTER 1977

1OCFR50 AI?!. B, 1OCFR21

Code case (5) AX4AQII REV. 8

FRONEK AIDE. INC. QAM REV. 2 DAlEO I12119B ASME Certificate N N-2!M3 £:)cpiratk:ln Date August 1, 2 ... ~~~ a:eL1J&&.;AMAQER

___

"g Materials Requisition j)~10' 5093 CwE.?L-I N! 099586 1 ..0

STOCKDESCRIPTIONrTAG NO. PO NONO,

Z4t!

00I ...... 1""'3 I ~ I --.- --- ~~.• --- ---- --_.. I UI.&lW 1_ I -- t -- PI ~- ~_ I ~

Ilm:~ ~

~ c:.......- ..... """'"

~~~~~~~=-~~~~~--------------~--~~ ~v '1

.... : •• ,"" • ,P II, )t ,.,,":' ••• :f>l (.I",: t. '1P[ E'\I,"~e' ~O""'Ig Rl!!Qui$UIOn. CANARY -OC InspeCIOI, PlNt

I GEORGIA POWER COMPANY PAy-abb4 S-&2

eUSTOMeR' PURCHASE 6nO~fl A 101 SHOP ORO£ft

SEe: BELOId N/4,QU4NTITY LISTED 8ELOW PART dEsCRIPTION SEftfAl Hb.

CERTIFICATE of CONFORMANCE .ATE. Max 30 .. 198b SUPERSEDED

THIS IS TO CERTIfY TNAT ALL "ATEIIAl IN AN. EXA"INATI'N Of. THE C.n'ON(NT ST'NI'R' SUPPORT lIST" HAVC ICEN PROCeSSED IN 'CC'RI'lce WITH THE IICNTIfIC'TION A.I VEllfICATIO. PRO'IA" ACC('TCI I' A.I.ft.(., COVCRC. IV .UALITY 4YSTEns CERTIfICATION '"ATCIIALS) 10•••" CIPIIATI.N lATE 01/31/.7 AN. YOUR PURCHASE.UK.. ~

I' ~'!:~ •ceRTIfICATE Of CO"P~IAN(' I'~ THIS IS TO CCRTI'V THAT THE ITERI RCf'R'NCE' BELOW "AVE 8EEN PROCESSE. IN ACCOR.ANCE WITH YOUI PURCHASE OR.EI AN. THE 1'77 A.S.".E. IOIlER AN' PI'SSUIE VESSEL CODE, WINTEI 1'71, AJJE~JUM.

ceRTI'ICATIOIS fOR THE ftATEIIAl LISTE' AlE ATTACHE ••

ITEft NO. 'VANTITV IESCRIPTION "ATERIAL I·'· NO. 1S& 20 pes. PIN 4],1b2 LOA]) PIN SASb4 TYPE 630 M-1{ 1S& 100··pes. PIN 4111.2 M-bJ" " " " " 1S9 SO pes. PIN 4],163 " " " M-QC" "

...162 9 pes. PIN 411&a " " " I K- 4 " 171 ]'It pes· PIN 41150 " " SAL93 Gr 87 F -1:: 17& 72 pes· PIN 4],047 " SAS61t TYPE 630 M-b1" 11& & pes. PIN 41.047 " " " " " 1(-45

...119 ? pes. PIN 4101& " ... " " J-&2 17' 7& pes. PIN 41018 ... " " " " M-bO

...laO 21l pes. PIN 41192 " " " " 1'- sq l.in 5 pes. PIN 41.206 ft " " " " (-4 201 3 pes· PIN 41032 HEX NUT SAl.'1t Gr 2H f-20

201 5.5 pes- PIN 41032 " '" " " " '1-56 ... " ~_-!34" '" '" ~-:l-'~B~ ~~ g~~: ~~~ ~1,B)1 " " " " " 202 2 pes- pnl '" >q6-i;,03~,~~ "

T. W. BROWN ............ _


Traveler # 10088

1. Owner Southern Nuclear Operating Company Date Ae.ril 20. 2011 Name

40 Inverness Center Parkway. Birmingham, AL Sheet of /1 ~fJ!!~~ II Address


Name

Waynesboro, GA 30830 1053339301 Address Repair/Replacement Organization P.O. No., Job No., etc,

3. Work Performed by __;.:;Mc=a;;..in",te::;.n::;a::,;n.;:.ce::...::Dc;:ec:..e.a::;rt:.:;m.:=enc:;t,--_ Type Code Symbol Stamp NJA

Name Authorization No. NIA Plant Vogtle Expiration Date ___________..:.N::..;A~______

Address

4, Identification of System

"'77 W(~r ,Q17 Klc6-a\~11 5. (a) Applicable Construction Code ASME Sec. II! +fH'tt- Edition, ~mm!i f§i'5 Addenda, NIA Code Case

(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 ed. 2003 add. (c) Applicable Section XI Code Case(s)





PIPE PULLMAN POWER 046165101015 NlA 1· 1301·107·HOOJ 1987 INSTALLED YES

SUPPORT PRODUCTS

7. Description of Work Remove/replace snubber AD-12501 , SIN 118 per procedure 27355-C with a Model

AD-12501 or LlSEGA Model 309253RF4 to support snubber testing.

8. Test Conducted: Hydrostatic D PneumatlcD Nominal Operating PressureD Exempt I!] ______ oFOther D Pressure psi Test Temp.

9. Remarks ~N.::.onc:.:e~_________~~~~~~_~~~~~-=_~~~_~__________________




Code, Section XI.


Certificate Of:.~thorization No. ; '\ NIA .~) Expiration Date NlA

d ,'~ cz:Signed /~'( .} .\'f--·~._7--, I"/,..../' ..~. .,,.... Date

( ! Owner or Owner's Designee, Title /


I, the undersigned, holding a valid commission issued by the National Boerd of Boiler and Pressure Vesse/lnspectors and the state or Province of Georgia and employed by Hartford Steam BOiler InsDection and Insurance Co. of Connecticut of @r.tfor\Crnecticut have Inspected the components described in this Owner's Report during the period J/t'J"i / ~c"il to ~ I.:J~ k,/.QLI, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective m~asures described In this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By Signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this

in~ection.

--=:..;:;;;;...-'-..a:=:..:r,tL-.,-f,.......,~~ii!!·::Io_:r.:::..~L1=wICL Commissions _-\C""'~~-4Z~.:::.IO!-'-'~~:::-:-.,--=---:-__-:--________...~.,.::..-~ nature National Board, State, Province and Endorsements

Date ~«. ;r"U Ale} .gO} l

http:C""'~~-4Z~.:::.IO

)~l

,O~1(0

~~.

FO M NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required By The Provisions Of The ASME Code Section XI

Traveler # _---:Ic..::0c..::0.;:.90=-___

1. Owner Southern Nuclear Operating Company Date June 06. 2011

Name

40 Invemess Center Parkway, Birmingham. AL Sheet of Address


Name

Waynesboro. GA 30830 1101010201 Address Repair/Replacement Organizetion P.O. No., Job No., etc.

3. Work Performed by Maintenance Department Type Code Symbol Stamp N/A

Name Authorization No. NIA

Plant VogUe Expiration Date N/A Address

4. Identification of System 1301 - MAIN STEAM System

5. (a) Applicable Construction Code ASME Sec. 1111971 Edition, Winter 1917 Addenda, NIA Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity _---..!2"'QQ""-'-1-"e~d"-.~20~O!>3,-,a~d~d=._~ (c) Applicable Section XI Code Case(s)


National Corrected, ASME Code Name of Name of Manufacturer Board Other Year Removed, or Stamped

Component Manufacturer Serial No. No. Identification Built Installed (Yes or No) PIPE PULLMAN POWER

Documents

Vogtle, Unit 1 - IR16 Inservice Inspection Report Summary. · 1987. 5. 31. · NIS·1 (Back) 8. Examination Dates: October 23.2009 to April 2, 2011 9. Inspection Period Identification: