-
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
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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
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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
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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
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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
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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
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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
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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
Examined base material only (SW)
per MRP-146.
Examined weld and base material per
MRP-146.
Examined base material only (SW)
Der MRP-146.
Examined weld and base material per
MRP-146.
Examined base material only (SW)
per MRP-146.
Examined weld and base material per
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-W35-RB INLET NOZZLE N3 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-W38-RB INLET NOZZLE N6 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
INSERVICE INSPECTION EXAMINATION
(OWNER'S REPORT) SUMMARY
• 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
INSERVICE INSPECTION EXAMINATION
(OWNER'S REPORT) SUMMARY
• 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
..-'
CERTIFICATE OF INSERVICE INSPECTION
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.
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 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)
6. Identification Of Components
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
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 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
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 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
-
'1J
-
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)
6. Identification Of Components
National Corrected, ASMECode
Name of Name of Manufacturer Board Other Year Removed, or
Stamped
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
I certify that the statements made in the report are correct and
that this conforms to the requirements of the ASME
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.___
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 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 •
2. Plant Vogt/e Electric Generating Plant Unit
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)
6. Identification Of Components
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)
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
CERTIFICATE OF COMPLIANCE
I certify that the statements mede in the report are correct and
that this conforms to the requirements of the ASME
Code, Section XI.
Type Code Symbol Stamp NlA
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)
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)
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~___________~~~~~__~_~~~-=__~__~__~~~_______________________
Applicable Manufacturer's Data Reports to be attached
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.
Type Code Symbol Stamp NIA
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
CERTIFICATE OF INSERVICE INSPECTION
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
2. Plant Vogt/e Electric Generating Plant Unit
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)
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 (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
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 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
Waynesboro. GA 30830 1101068801 Address Repair/Replacement
Organization P.O. No., Job No., etc.
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)
6. Identification Of Components
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 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~_____________~~~~~__~~~~~~~~~~_~~~____________
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, Se
-
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As
Required By The Provisions Of The ASME Code Section XI
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)
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) 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
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 NlA
____-'='..-....:.;:;.:...:...++-____ Expiration Date NIA
Signed Date
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 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
-
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As
Required By The Provisions Of The ASME Code Section XI
Traveler # _---'1...::008c::.;;;..;..7____
1. Owner Southern Nuclear Operating Company Date April 18,
2011
Name
40 Inverness Center Parkway. Birmingham. AL Sheet of Address
2. Plant Vogt/e Electric Generating Plant Unit
Name
Waynesboro. GA 30830 1053338901 Address Repair/Replacement
Organization P.O. No., Job No., etc.
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)
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) 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
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 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
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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••
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-
Tel: (603) 52~193132 Moulton Sleet Laconia, NH 03246 Fax:
(603)52~381
CERTIFICATE OF COMPLIANCE
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.. ~~~
-
,
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-
~A1A&kAIDE",J~~@~JZ"""
Tel: (603) 528-193132 Mounon Sleet
Laconia, NH 03246 Fax: (B03) 52S-a381
CERTIFICATE OF COMPLIANCE
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
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"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 ~
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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 ............ _
-
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As
Required By The Provisions Of The ASME Code Section XI
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
2. Plant Vogtle Electric Generating Plant Unit
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)
6. Identification Of Components
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 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~_________~~~~~~_~~~~~-=_~~~_~__________________
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 Of:.~thorization No. ; '\ NIA .~) Expiration Date
NlA
d ,'~ cz:Signed /~'( .} .\'f--·~._7--, I"/,..../' ..~. .,,....
Date
( ! Owner or Owner's Designee, Title /
CERTIFICATE OF INSERVICE INSPECTION
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
-
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,O~1(0
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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
2. Plant Vogtle Electric Generating Plant Unit
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)
6. Identification Of Components
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