ML20063A675
| ML20063A675 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/31/1993 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20063A668 | List: |
| References | |
| NUDOCS 9401260253 | |
| Download: ML20063A675 (386) | |
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i 8
OWNER'S REPORT FOR INSERVICE INSPECTION Document Completion Date: December 1993 Owner: Georgia Power Company 333 Piedmont Avenue, N.E.
P. O. Box 4545 Atlanta, Georgia 30302 Generating Plant: Vogtle Electric Generating Plant, Unit 2 River Road 9 P. O. Box 1600 Waynesboro, Georgia 30830 Commercial Operation Date: May 20, 1989 O
OWNER'S REPORT TOR INSERVICE INSPECTION-Document Completion Date: December 1993 Owner: Georgia Power Company 333 Piedmont Avenue, N.E.
P. O. Box 4545 Atlanta, Georgia 30302 Generating Plant: Vogtle Electric Generating Flant, Unit 2 River Road 9 F. O. Box 1600 Waynesboro, Georgia 30830 Commercial Operation Date: May 20, 1989 l
O
TABLE OF CONTENTS Introduction 1-1 ASME NIS-1 Form with Classes 1 and 2 Abstract 2-1 ASME Class 3 and Augmented Examinations Summary 3-1 Examination Summary Listings Introduction to Summary Listings 4-1 ASME Class 1 Equipment Examinations 5-1 Piping L:aminations 6-1 ASME Class 2 Equipment Examinations 7-1 Piping Examinations 8-1 Supports Introduction and Equipment 9-1 Support Examinations Introduction and Piping Support Examinations 10-1 1 l
Snubber Functional Examinations j l
Introduction to Snubber Functional 11-1 1 Testing Listings I Inspection Type I 12-1 Inspection Type II 13-1 Inspection Type III 14-1 Inspection Type IV 15-1 Pressure Tests 16-1 Indication Notification Forms 17-1 Examination Drawings 18-1 NIS-2 Forms 19-1 11
TABLE OF CONTENTS - (continued)
Volume 2*
Class 1 Equipment Examination Data Class 1 Piping Examination Data Class 2 Equipment Examination Data volume 3* l Class 2 Piping Examination Data Equipment Support Examination Data Piping Support Examination Data Nuclear Service Cooling k'ater System Examination Data Volume 4*
UT Calibration Sheets UT Qualification Sheets MT Qualification Sheets Volume 5*
Personnel Certifications Equipment Certifications UT Scopes Search Units NDE Equipment Consumables Volume 6*
NDE Procedures Southern Nuclear Operating Company Georgia Power Company Volume 7*
Balance of Plant Erosion / Corrosion Examinati.n Data
- Volumes 2 through 7 are available for review at t = plant si e upon request.
O ui
~ . _ . . . .
LIST OF ABBREVI ATIONS ACC Acceptable AD Anchor-Darling AFW Auxiliary Feedwater System
! AI GPC Action Item (followed by unique no, denoting Action Item number)
ASME American Society of Mechanical Engineers ASNT American Society for Nondestructive Testing ASTM American Society for Testing and Materials BC Branch Connection CCSS Centrifugally Cast Stainless Steel CCW Component Cooling Water CE Combustion Engineering CH Closure Head CS Containment Spray CVCS Chemical and Volume Control System DS Downstream ET Eddy Current Examination EVAL Evaluation FB Flange Bolting FW Feedwater System CEO Ceometric Indications CPC Georgia Power Company HHSI High Head Safety Injection HL Hanger Lug HX Heat Exchanger Hydraulic Snubber O HYD IEN NRC Information Notice (may also be shown as "IN" followed by unique no. denoting notice number)
IND Indication INF Indication Notification Form ISI Inservice Inspection ,
IST Inservice Testing i ID Inside Diameter l IR Inside Radius ;
1 LB Large Bore LD Longitudinal Seam Weld Extending Downstream LD-I Longitudinal Seam Weld Downstream Inside of Elbow LMT Lambert, MacGill and Thomas LU Longitudinal Seam Weld Extending Upstream LU-0 Longitudinal Seam Weld Upstream on Outside of Fibow MECH Mechanical Snubber MS Main Steam System MT Magnetic Particle Examination NCI Nonconformance Item NDE Nondestructive Examination NI No Indication NRC United States Nuclear Regulatory Commission NRC-B NRC Bulletin (followed by unique no, denoting Bulletin number)
NRI No Recordable Indication NSCW Nuclear Servic a Cooling Water System iv
LIST OF ABBREVI ATIONS - (continued)
OR Outside Radius PL Pipe Lug PM Paul-Munroe ENERTECH PR Pipe Restraint PROF Profile PS Pipe Support PSA Pacific Scientific PSI Preservice Inspection PT Liquid Penetrant Examination RCS Reactor Coolant System RCP Reactor Coolant Pump RHR Residual Heat Removal System RI Recordable Indication RLW Refracted Longitudinal Wave RL Restraint Lug RPV Reactor Pressure Vessel RR Relief Request (followed by unique no. denoting relief request number)
RWST Refueling Water Storage Tank SAT Satisfactory Examination Results SB Small Bore SCS Southern Company Services SI Safety Inj ection System SSI Sonics Systems International SNC Southern Nuclear Operating Company 6 SUP T&C Supplemental Data Thickness and Contour UNSAT Unsatisfactory Examination Results US Upstream UT Ultrasonic Examination VT Visual Examination H Westinghouse v
i Introduction This report documents the examinations and tests performed at the Vogtle Electric Generating Plant, Unit 2 (VEGP-2) between May 8, 1992 (date of last examination performed during the second maintenance / refueling outage, 2R2) and October 17, 1993 (date of last examination performed during the third maintenance / refueling outage, 2R3) to meet the requirements of Article IWA-6000 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 1983 Edition with Addenda through Summer 1983. In addition, a summary of the following augmented examinations are included in this report:
- Technical Specification 4.4.5.0 - Steam Generator Tube Inspections,
- Technical Specification 4.5.10.2 - Reactor Coolant Pump Flywheel Keyway and Bore Examinations, 1
)
e Technical Specification 4.5.10.3 - Main Steam and Feedwater Line Volumetric Examinations, t
l
- Technical Specification 4.7.8 - Snubber Examinations, 1
- Georgia Power Company Action Item No. 1739 - Feedwater Line Cracking, e Georgia Power Company letter GN-1345 (February 9, 1987) - Augmented Examinations of Class 3 NSCW Systems, e Georgia Power Company, VECP-2 Inservice Inspection Program document ISI-P-014, Paragraph 1.10.3 - Volumetric Examination of Additional Class 2 Piping Welds, e United States Nuclear Regulatory Commission (NRC) Bulletin 88 Thimble Tube Thinning in Westinghouse Reactors,
- Westinghouse Technical Bulletin NSD-TD-90 BMI Conduit Guide Tube Leaks,
- Westinghouse WCAP No. 12907, " Alloy 600 PWSCC Susceptibility Assessment of Vogtle 1 and 2 Primary Components",
Georgia Power Company Action Item No. 85-2515 - Crack Growth in Steam Generator Girth Welds, e Georgia Power Company Action Item Nos. 87-0131 and 87-0931 - Stagnant Borated Water Systems Cracking, e Georgia Power Company Action Item No. 18270 - Examination Techniques and Personnel Qualifications for Cold Leg Accumulator Piping (10-inch Sch.
140, ASTM SA-376, Type 316), ,
1 1
- NRC Information Notice No. 91-05, "Intergranular Stress Corrosion Cracking in Pressurized Water Reactor Safety Injection Accumulator Nozzles", and j e Balance of Plant Erosion / Corrosion Examinations.
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l This report also addresses Code-applicable repairs or replacements which were documented since the last maintenance / refueling outage at VEGP-2 through the completion of the third maintenance / refueling outage in October 1993.
However, it should be noted that several NIS-2 reports were inadvertently omitted from the previous inservice inspection summary report. The inadvertently omitted NIS-2 reports may have been documented prior to the completion of the second maintenance / refueling outage at VEGP-2. The Owner's Reports on Repairs and Replacements (Form NIS-2) are provided in Volume 1 of this report. )
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I V 1-2
J i FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS l As required by the Provisions of the ASME Code Rules
- 1. Owner: Georgia Power Company, 333 Piedmont Avenue, N.E.
P.O. Box 4545, Atlanta, Georgia 30302
- 2. Plant: Vogtle Electric Generating Plant, P.O. Box 1600, Waynesboro, Georgia 30830
) 3. Plant Unit: Two
- 4. Owner Certification of Authorization: N/A i
j 5. Commercial Service Date: 05/20/89 i jN
{
- 6. National Board Number for Unit: N/A
- 7. Components Inspected:
Component or Manufacturer Manufacturer State or National Appurtenance or Installer Or Installer Province Board and Address Serial No. Number Number Reactor Combustion Eng. Inc. 7372 N/A 22004 Pressure Chattanooga, TN Vessel
() Steam Generators Westinghouse Elec.
Tampa, FL 77743, 77744, N/A 36, 33, 1 and 4, respectively Reactor Westinghouse Elec. 6-9744D35G01 N/A 38 Coolant Pump 2 Cheswick, PA Reactor Westinghouse Elec. *(See ASME Class Coolant Pumps Cheswick, PA 3 and Augmented 1 through 4, Examination respectively Summary)
RHR Heat Joseph Oat Corp. 2322-2D N/A 1051 Exch. Camden, NJ Train "B" RHR Pump Ingersoll-Rand Co. 087730 N/A 512 Train "A" Phillipsburg, NJ Regenerative Joseph Oat Corp. 2380-2B N/A 2054 lleat Exch. Camden, NJ Selected Pullman Power Prod. 1201, 1202, N/A N/A Piping and Williamsport, PA 1204, 1205 O Components 1206, 1208, 1301, 1302, 1305 2-1
i
'l FORM NIS-1 (BACK)
- 8. Examination Dates: 05/08/92 to 10/17/93
- 9. Inspection Interval: 05/20/89 to 05/19/99 I
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. (See Abstract and l Examination Summary Listings) i
- 11. Abstract of Conditions Noted (See Abstract) l l
- 12. Abstract of Corrective Measures Recommended and Taken (See Abstract)
We certify that the statements mado in this report are correct and the examinations and corrective measures taken conform to.the rules of the ASME Code,Section XI.
Certificate of Authorization No. (if applicable) N/A I Expiration Date N/A l Date //7p / ,
19 Signed Geornia Power Company Owner By I 7 ' N 2 T, - r
, CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Georgia and employed by The Hartford Steam Boiler Inspection and Insurance Company of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period 05/08/92 to 10/17/93, and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures descr,1 bed 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.
- CSl L A Commission Georgia 127 N/I
( s %
l Inspector's Signature National Board, State, Province, Date [in 7 19 M
/
- Non ASMEsSdction XI Examinations not inspected by ANII.
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ABSTRACT
, INTRODUCTION / STATUS
- The ASME Boiler and Pressure Vessel Code,Section XI, 1983 Edition with Addenda through Summer 1983 (Code), is be applicable code for conducting inservice inspection activities duri.g the first ten-year inspection interval at VEGP-2. Examinations and tests required by the Code are scheduled in accordance with " Inspection Program B" as defined in paragraphs IWB-2412 and IWC-2412 in the Code. This " Owner's Report for Inservice Inspection" is for those second inspection period examinations and tests which were performed between May 8, 1992 (date of last examination performed during the second maintenance / refueling outage, 2R2) and October 17, 1993 (date of last examination performed during the third maintenance / refueling outage, 2R3).
The remaining second period examinations are expected to be completed by the end of the fourth maintenance refueling outage which should occur within the second inspection period time frame. In addition to the summary of inservice inspection activities, this report addresses Code-applicable repairs and replacements documented at VEGP-2 since 2R2 through the end of 2R3. It should be noted that several NIS-2 reports were inadvertently omitted from the previous inservice inspection summary report. The inadvertantly omitted NIS-2 reports may have been documented prior to the completion of Outage 2R2 at VEGP-2. The Owner's Reports on Repairs or Replacements (Form NIS-2) are located in Volume 1 of this report document.
It should be noted that Authorized Nuclear Inservice Inspector (ANII) inspection services were provided for those examinations and tests required by the Code except for functional testing of snubbers which were tested in accordance with VEGP Technical Specification 4.7.8.
CIASS 1 EXAMINATIONS Selected Class 1 components were examined by Southern Nuclear Operating Company (SNC), Georgia Power Company (GPC),and Westinghouse personnel utilizing UT, PT, MT, and VT, as applicable. Specific components and examinations areas are itemized in the applicable portions of this document.
A summary of those components examined are listed below:
. Steam Generator # 1 Primary Inlet and Outlet Nozzle Inner Radii e Steam Generators # 1 and 4 Tube Plate to Channel Head Welds e Reactor Pressure Vessel Flange Ligaments
. Reactor Pressure Vessel Shell to Outlet Nozzle Welds e Reactor Pressure Vessel Outlet Nozzle Inner Radii e Reactor Pressure Vessel Outlet Nozzle To Safe End Welds e Reactor Pressure Vessel Closure Head Studs, Nuts & Washers e Reactor Pressure Vessel Closure Head and Interior Surfaces e Piping Welds e Valve Body Internal Surfaces During the scope of VECP-2 examinations conducted, one Class 1 weld and three RPV closure head studs were observed to have either reportable ultrasonic or magnetic particle indications. For details on the non-geometric indications 2-3 i _ __ . _ . - _ , , _ _ . _ _ . , .,. _ _._, _ _ _ _ _ _
observed, refer to the respective Indication Notification Forms (INFs) found in the INF section of this report. The components having reportable
\
/ indications are as follows: ,
- 1. RPV Closure Head Studs - (Component Numbers 21201-V6-001-B30, B32 and ,
B33). During the magnetic particle examinations of RPV closure head )
stud numbers B30, B32, and B33 linear indications ranging from 1/16 to 3/16 inches were observed. The indications were evaluated to the requirements of ASME Section III (per NRC Regulatory Guide 1.65), and were determined to be of an acceptable size. No corrective action was taken, (Refer to INF 193V2016) l
- 2. Reactor Coolant System - Line 053 - 14" Reducer to Pipe - (Weld No.
21201-053-5). During the ultrasonic examination of weld 21201-053-5, two non-geometric indications were observed . The indications were categorized as sub-surface planar in accordance with ASME Section XI.
The indications were evaluated to ASME Section XI and were determined to be of an acceptable size. No corrective action was taken. (Refer !
to INF 193V2020)
During the third maintenance / refueling outage at VEGP-2, Westinghouse performed mechanized ultrasonic examinations associated with RPV outlet i nozzles during the period from September 26, 1993 through September 28, 1993.
The following examinations were performed for RPV outlet nozzles N1, N4, N5, and N8: the inner radius, vessel-to-outlet nozzle welds, outlet nozzle-to-safe end walds, and safe end-to-pipe welds. The examinations were conducted using the Westinghouse Reactor Vessel Mini-Tool and utilizing UDRPS 2, an ultrasonic O data recording and processing system, to provide continuous multi-channel digital data acquisition. The examinations were conducted using the contact ultrasonic method, to the extent practical, with the access provided and within the limitations of the component geometry.
System calibration, calibration conformation, and examinations associated with the RPV outlet nozzles were performed in accordance with Westinghouse procedure GBE-ISI-254, " Remote Inservice Inspection of Reactor Vessel Outlet Nozzles for Vogtle Unit 2." That procedure is based on Section XI of the ASME Boiler and Pressure Vessel Code, 1983 edition, Summer addenda, and NRC Regulatory Guide 1.150, Rev. 1.
One indication having peak amplitude, which required that bounding measurements be taken for through-wall and length dimension, was recorded on the N1 nozzle to safe-end weld (21201-V6-001-WO33). This indication was characterized in accordance with the requirements of ASME Section XI, IWA-3000. The dimensions were compared to the applicable standards of ASME Section XI, IWB-3000 and were found to be acceptable. The inner radius and vessel-to-outlet nozzle examinations were limited to a volume of 90% and 91%,
respectively, due to nozzle configuration. Code Case N-460 utilized.
Details on the RPV examinations performed by Westinghouse, procedures utilized, equipment, material and personnel certifications, etc., may be found in the Westinghouse Reactor Vessel Inservice Inspection Field Service Report for VEGP-2. The Westinghouse report is available at the plant site for review upon request.
2-4
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The Eddy Current (ET) examinations of steam generator tubing, as required by VEGP Technical Specification 4,4.5,0, were performed by Westinghouse and are O
i discussed in the " Class 3 and Augmented Examinations" portion of this l document.
CLASS 1 PRESSURE TEST i A system leakage test (Test # LT-1) as required by ASME Section XI, Table IWB-2500-1, Examination Category B-P, was performed on the' Class 1 pressure retaining boundary. The visual examination (VT-2) revealed minor leakage and boron residue coming from mechanical connections. Appropriate corrective action was initiated to correct the minor leakage.
CLASS 2 EXAMINATIONS Selected Class 2 components were examined utilizing MT, PT, and UT, as applicable. Specific components and examination areas are itemized in the l applicable portions of this report document. A summary of those components examined are listed below:
- Steam Generator No, 4 Upper Shell Barrel "C" to Transition Cone Weld, )
Lower Shell Barrel "A" to Tube Plate Veld, Auxiliary Feedwater Nozzle to Shell Weld and Trunion to Shell weld
+ RHR Heat Exchanger Train "B" Welds e RHR Pump Train "A" Integral Attachment Support Wold I e CVCS Regenerative Heat Exchanger Welds
- Piping Welds
()
- Integral Attachment Support Welds The Class 2 examinations resulted in several welds having reportable indications. Eight welds had indications which were detectable by either liquid penetrant, magnetic particle or ultrasonic examinations. For details on the reportable non-geometric indications , observed, refer to the respective INF found in the INF section of this report document. The eight welds having reportable indications are discussed below:
- 1. Steam Generator No. 4 - Upper Shell Barrel "C" to Transition Cone Weld No. 21201-B6-004-WO3. During the ultrasonic examination of weld 21201-B6-004-WO3, several non-geometric indications were observed and were categorized as sub-surface planar flaws in accordance with ASME Section XI. The indications were observed using a 2.25 megahertz (mhz) transducer. A supplemental examination was performed as allowed by ASME Section XI, IWB-3200 in order to better characterize flaw sizes.
The initial rejectable areas were re-examined using a 4 mhz transducer.
The indications were evaluated to ASME Section XI and were determined 1 to be of an acceptable size. No corrective action was taken. (Refer l to INF 193V2021)
- 2. Steam Generator No. 4 - Auxiliary Feedwater to Shell Weld No. 21201-B6-004-W26. During the ultrasonic examination of weld 21201-B6-004-W26, two non-geometric indications were observed. The indications were categorized as sub-surface planar flaws in accordance with ASME Section 2-5
The indications were evaluated to ASME Section XI and were determined to be of an acceptable size. No corrective action was taken. (Re fe r to INF 193V2019)
- 3. Residual Heat Removal Heat Exchanger - Flange to Tube Side Shell Weld No. 21205-E6-002-WO1. During the ultrasonic examination of weld 21205-E6-002-W01, several non-geometric indications were observed. The indications were categorized as sub-surface planar flaws in accordance with ASME Section XI. The indications were evaluated to ASME Section XI and were determined to be of an acceptable size. No corrective action was taken. (Refer to INF 193V2005)
- 4. Residual Heat Removal Heat Exchanger - Tube Shell to Head Weld No.
21205-E6-002-WO2, During the ultrasonic examination of weld 21205-E6-002-WO2, several non-geometric indications reflectors were observed.
The indications were categorized as sub-surface planar flaws in accordance with ASME Section XI. The indications were evaluated to ASME Section XI and were determined to be of an acceptable size. No corrective action was taken. (Refer to INF 193V2005)
- 5. Safety Injection System - Line 039 - 6" Pipe. tc Elbow Weld No. 21204-039-35. During liquid penetrant examination of weld 21204-039-35, a linear indication was observed. The indication was categorized as a linear flaw in accordance with ASME Section XI. The indication was evaluated to ASME Section XI and determined to be of an acceptable size. No corrective action was taken. (Refer to INF 193V2012)
- 6. Main Steam System - Line 004 - 6" Outlet to Flange Weld No. 21301-004-
[)
'- 5. During the ultrasonic examination of weld 21301-004-5, one non-geometric indication was observed. The indication were categorized as sub-surface planar flaw in accordance with ASME Section XI. The indication was evaluated to ASME Section XI and determined to be of an acceptable size. No corrective action was taken. (Refer to INF I93V2023)
- 7. Main Steam System - Line 004 - 28" Valve to Pipe Wold No. 21301-004-14.
During the ultrasonic examination of weld 21301-004-14, several non-geometric indications were observed. The indications were categorized as sub-surface planar flaws in accordance with ASME Section XI. The indications were evaluated to ASME Section XI and were determined to be of an acceptable size. No corrective action was taken. (Refer to INF 193V2022)
- 8. Auxiliary Feedwater System - Line 109 - 6" Transition Piece to Nozzle Weld No. 21302-109-44. During magnetic particle examination of weld 21302-109-44, a linear indication was observed. The indication was categorized as a linear flaw in accordance with ASME Section XI. The indication, observed by the surface examination method, was rejectable per ASME Section XI. Supplemental ultrasonic sizing methods were utilized, as allowed by IWB-3514-2, resulting with the indication being ecceptable per ASME Section XI. The indication was removed by flapping and the area re-examined with the magnetic particle method with acceptable results. No further corrective action was taken. (Refer to s_ INF 193V2018) 2-6
CLASS 2 PRESSURE TESTS Listed below are the Class 2 system pressure tests.
The visual examinations performed during these system pressure tests found only minor leakage at mechanical joints such as valve stem packing and at flanged connections. These leaks were evaluated and determined acceptable for l continued system operation. However, where appropriate, corrective action was initiated to correct these minor leakages.
System Function Tests (FTs)
FT Number Test Description 1 Reactor Head Vent Functional Test 3 Penetration 32 Functional Test (High Head Safety Injection (HHSI) to Cold Legt) 4 Safety Injection (SI) Pump 1204-P6-003 (Train "A") Discharge Functional Test 5 SI Pump 1204-P6-004 (Train "B") Discharge Functional Test 6 Penetration 33 Functional Test (SI to Hot Legs 1 & 4) 7 Penetration 31 Functional Test (SI to Hot Legs 2 & 3) 8 Penetration 30 Functional Test (SI to Cold Legs) 9 Penetration 56 Functional Test (Residual Heat Removal (RHR) Hot Leg Inj ec tion) 10 SI Pump Suction Functional Test 11 RHR to Chemical and Volume Control System (CVCS) Suction Functional Test 13 containment Spray Train "B" Functional Test 14 **T.rbine-Driven Auxiliary Feedwater (AFW) Pump 1302-P4-001 Functional Test 16 Line 1208-135 Functional Test (HV-8439 to Valve 499 Flow Test) 17 Line 1208-133 Functional Test (HV-8104 to Valve 185 Flow Test)
System Hvdrostatic Tests (hts)
HT Number Test Description 11 Containment Spray Train "A" Nozzle Open Flow Test (required by Technical Specification 4.6.2.1d) 12 Containment Spray Train "B" Nozzle Open Flow Test (required by Technical Specification 4.6.2.1d) 73 **AFW Pump Train "C" Discharge Hydrostatic Test 92 Charging Pump Train "A" Alternate Miniflow Hydrostatic Test 93 Charging Pump Train "B" Alternate Miniflow Hydrostatic Test Svstem Inservice Tests (ITs)
IT Number Test Description 1 Charging Line Inside Containment Inservice Test 2 Letdown Line Inside Containment Inservice Test 3 Reactor Coolant Pumps 1, 2, 3, and 4 Seal Leakoff Inside Containment Inservice Test 4 Reactor Coolant Pump 1 Seal Injection from Penetration 54 to Valve 006 Inservice Test 2-7
System Inservice Tests (ITs) - continued t
I \ Test Description IT Number 5 Reactor Coolant Pump 2 Seal Injection from Penetration 53 to Valve 359 Inservice Test 6 Reactor Coolant Pump 3 Seal Injection from Penetration 52 to Valve 360 Inservice Test 7 Reactor Coolant Pump 4 Seal Injection from Penetration 51 to Valve 361 Inservice Test 8 Reactor Coolant System Hot Leg Sample Lines to Penetration 24 Inservice Test 9 Sample Line from Valve 101 to Valve HV-3514 Inservice Test 10 CVCS Inservice Test with Positive Displacement Charging Pump operating (Outside Containment only) 11 Centrifugal Charging Pump 1208-P6-002 (Train "A") Discharge Inservice Test 12 Centrifugal Charging Pump 1208-P6-003 (Train "B") Discharge Inservice Test 14 Accumulator Tank 1 (1204-V6-002) Inservice Test 15 Accumulator Tank 2 (1204-V6-003) Inservice Test 16 Accumulator Tank 3 (1204-V6-004) Inservice Test 17 Accumulator Tank 4 (1204-V6-005) Inservice Test 18 RHR Train "A" Inservice Test 19 RHR Train "B" Inservice Test 23 Refueling Water Storage Tank Inservice Test 24 Sample Line from Valve 097 to Valve HV-3508 Inservice Test O 25 Penetration 24 Outside Containment Inservice Test (Post-Accident Sampling) 26 ** Nuclear Service Cooling Water (NSCW) Train "A" Inservice Test (Outside Containment Only) 30 **NSCW Train "B" Inservice Test (Outside Containment Only) 64 **AFW Inservice Test With Pump 1302-P4-002 Operating 65 **AFW Inservice Test With Pump 1302-P4-003 Operating 79 Excess Letdown Heat Exchanger Inservice Test 80 RHRS Cleanup Inservice Test
- Portions of these pressure test boundaries are also Class 3, O 2-8
CLASS 1 AND 2 COMPONENT SUPPORTS Snubber examinations and functional tests required by Technical Specification 4.7.8 are discussed in the " Class 3 and Augmented Examinations" portion of this document.
Visual examinations were performed on supports for the following Class 1 and 2 l components
- Reactor Coolant Pump st2 i
+ Residual Heat Removal Pump - Train "B" l
+ Reactor Coolant System Piping
- Nuclear Service Cooling Water System Piping
- Safety Injection System Piping
+ Residual Heat Removal System Piping
- Containment Spray System Piping
+ Chemical and Volume Control System Piping
- Auxiliary Feedwater System Visual examinations resulted in three supports having initial unacceptable conditions. The supports are listed below:
- 1. Nuclear Service Cooling Vater System - Line 220 - Support H028 (21202-220-H028). Frozen spherical bearings were observed during visual examination of support 21202-220-H028 The condition was evaluated and determined not to impact the operability of the support, thereby not constituting a failed support. The condition was corrected per Maintenance Work Order (MWO) 29303325. (Refer to b INF 192V2010).
- 2. Safety Injection System - Line 021 - Support H003 (21204-021-H003) .
Frozen spherical bearings.were observed during visual examination of support 21204-021-H003'. The condition was evaluated and determined not to impact the operability of the support, thereby not constituting a failed support. The snubber was removed for functional testing and replaced under the functional testing program per MWO 29302546. (Refer to INF 192V2011).
- 3. Reridual Heat Removal System - Line 004 - Support H016 (21205-004-H016). A missing cotter pin was observed during visual examination of support 21205-004-H016. The condition was evaluated and determined to require a scope expansion of four additional supports. The condition was corrected per MWO 29303260. (Refer to INF 193V2009).
O 2-e
CLASS 3 AND AUCMENTED EXAMINATIONS
SUMMARY
CLASS 3 EXAMINATIONS CLASS 3 PRESSURE TESTS Listed below are the Class 3 system pressure tests.
The visual examinations performed during these system pressure tests found only minor leakage at mechanical joints such as valve stem packing and at flanged connections, These leaks were evaluated and determined acceptable for continued system operation. However, where appropriate, corrective action was initiated to correct these minor leakages.
System Function Tests (FTs)
FT Number Test Description 14 ** Turbine-Driven AFW Pump 1302-P4-001 Functional Test 15 Main Steam (Jalve HV-5106) to Turbine-Driven AFW Pump Turbine Functional Test System Hydrostatic Tests (hts) i HT Number Test Description 59 AFW Pump Train "A" Hydrostatic Test O 60 61 AFL' Pump Train "B" Hydrostatic Test AFW Pump Train "C" Hydrostatic Test 62 AFW Line 1302-054 Hydrostatic Test 63 AFW Line 1302-042 Hydrostatic Test 64 AFW Line 1302-027 Flow Test 65 AFW Line 1302-022 Flow Test 66 AFW Line 1302-015 Flow Test 67 Condensate Storage Tank 1302-V4-002 Hydrostatic Test 68 Condensate Storage Tank 1302-V4-001 Hydrostatic Test 69 AFW Line 1302-037 Hydrostatic Test 70 AFW Line 1302-008 Hydrostatic Test 71 AFW Line 1302-060 Hydrostatic Test 72 AFW Line 1302-055 Hydrostatic Test 73 **AFW Pump Train "C" Discharge Hydrostatic Test 74 AFW Pump Train "A" Discharge Hydrostatic Test 75 AFW Pump Train "B" Discharge Hydrostatic Test 76 Auxiliary Feedwater Pump Turbine Flow Test 78 NSCW Train "B" Hydrostatic Test 97 Essential Chilled Water System Train "B" Hydrostatic Test System Inservice Tests (ITs)
IT Number Test Description 13 Boric Acid Transfer Pump Suction Inservice Test 22 Spray Additive Tank Inservice Test 26 **NSCW Train "A" Inservice Test (Outside Containment Only) 29 NSCW Line 184 Inservice Test (Train "A" Tower Bypass) 3-1
System Inservice Tests (ITs) (continued)
Test Description
( IT Number 30 **NSCW Train "B" Inservice Test (Outside Containment Only) 33 NSCW Line 185 Inservice Test (Train "B" Tower Bypass) 61 Condensate Storage Tank 1302-V4-001 Inservice Test 62 Condensate Storage Tank 1302-V4-002 Inservice Test 64 **AFW Inservice Test With Pump 1302-P4-002 Operating 65 **AFW Inservice Test With Pump 1302-P4-003 Operating 66 Main Steam to Turbine Driven AFW Pump Turbine Isolation Valve HV-5106 Inservice Test 67 Essential Chilled Water System Train "A" Inservice Test 81 NSCW Pump 1202-P4-001 Inservice Test 82 NSCW Pump 1202-P4-002 Inservice Test 83 NSCW Pump 1202-P4-003 Inservice Test 84 NSCW Pump 1202-P4-004 Inservice Test 85 USCW Pump 1202-P4-005 Inservice Test 86 NSCW Pump 1202-P4-006 Inservice Test 87 NSCW Pump 1202-P4-007 and Piping Inservice Test 88 NSCW Pump 1202-P4-008 and Piping Inservice Test 93 Boric Acid Transfer Pump Inservice Test With Pump 1208-P6-007 Operating 94 Boric Acid Transfer Pump Inservice Test With Pump 1208-P6-006 Operating
- Portions of these pressure test boundaries are also Class 2.
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Q CLASS 3 COMPONENT SUPPORTS AND INTEGRAL ATTACHMENTS Visual examinations were performed on cupports and integral attachments for the Class 3 components listed below:
- Component Cooling Water - Pump No. 1
- Spray Additive Tank e Spent Fuel Pit Pump - Train "B" e Essential Chilled Water Pump - Train "A"
- Essential Chilled Water Expansion Tank - Train "B"
- Nuclear Service Cooling Water System Piping e Spent Fuel Cooling System Piping
- Auxiliary Feedwater System Piping j e Essential Chilled Water System Piping j The visual examinations for the VECP-2 2R3 Maintenance / Refueling Outage did not reveal any unsatisfactory conditions with the supports or integral attachments, AUGMENTED INSPECTIONS Technical Specification 4.4.5.0 - Steam Generator Tube Inspections I
During the third maintenance / refueling outage at VEGP-2, the Steam Generator Primary Services Group of the Westinghouse Nuclear Services Division performed eddy current testing of two Model F steam generators in parallel from September 19, 1993 through October 2, 1993. Randomly selected tubes from two 3-2
steam generators were inspected rather than only one steam generator as
- required by VEGP Technical Specification Table 4.4-1. The extent of i examinations and their results are summarized in Table I (refer to page 3-24) including the location and the accumulative number of previously plugged steam generator tubes. Although not examined during the third maintenance / refueling outage at VEGP-2, information is provided in Table I for Steam Generator Nos.
2 and 3 and is included for historical purposes.
Tables II and III identify the steam generator tubes with indications by location and percent of wall thickness penetration for Steam Generator Nos. 1 and 4, respectively. Information is provided only for the steam generators examined during the third maintenance / refueling outage at VEGP-2.
Applicable procedures, personnel qualifications, material and equipment certifications, sign-off sheets, and supporting data, etc. can be found in Westinghouse Steam Generator Primary Services Field Service Report, MRS 4.4 GBE-6, " Steam Generator Nozzle Dam Refurbishment, Installation and Removal, Eddy Current Inspection, Mechanical Plug Removal and Mechanical Plugging," ,
which is available at the plant site for review upon request.
Bobbin Coil Inspection Inspection Plan Description Steam generator tubing inspections conducted during the third maintenance / refueling outage at VEGP-2 were performed in accordance with a program recommended by the Electric Power Research Institute (EPRI) which was adopted by GPC. The EPRI ISI Guidelines NP-6201 (as interpreted by GPC) were further clarified in letters to EPRI and Westinghouse dated August 5, 1992.
In this program, fifty percent (50%) of the tube population is inspected from two generators each outage rather than 20% of the tube population from four steam generators each cycle such that after four cycles of plant operation, each of the tubes will have been tested. This alternative inspection plan ;
offers advantages in shorter inspection time in order to achieve complete steam generator inspection and offers an improved sensitivity to degradation ,
that might be initiating within a particular steam generator. In addition, :
the Guidelines recommend additional testing for any areas of concern. Plant !
Technical Specifications also require that reportable defects be inspected.
Each of the tubes in the inspection plan were tested full length. !
In addition, steam generator no. 4 required sixteen tubes located adjacent to tube R57C68 to be inspected as part of a " loose part" program. These tubes were inspected from the cold leg side of the steam generator. The extent of the inspection was tube-end-cold (TEC) to the first support plate.
Inspection Plan Implementation To summarize the inspection plan, most tubes were inspected with a 0.560 inch diameter probe throughout their entire length. This included each of the tubes above row two in steam generator Nos. 1 and 4. Generally, the straight i I
lengths were tested with a 0.560 inch diameter probe and where possible, also the U-bends. Vhere restrictions were encountered, a 0.540 inch diameter probe was used to traverse the U-bends. Each of the remaining tubes were tested using a 0.520 inch diameter probe. The inspections were performed in accordance w th GPC MWO 29301274.
i 3-3
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3 l The eddy current bobbin inspection was conducted in accordance with ,
i Westinghouse procedure MRS 2.4.2 GPC-3, ' Eddy Current Inspection of Preservice '
)
) and Inservice Heat Exchanger Tubing", using Westinghouse Job Data Sheet GBE-001-093. Per the Job Data Sheet, the withdrawal rate was 24 inches per l second and the test frequencies were 630 kilohertz (KHz), 320 KHz, 160 KHz, and 10 KHz.
I j The bobbin probes used in the inspection of the steam generator tubes werc manufactured by Echoram. The probe used for most of the testing was an EB-
] 560-BBM-UF. The U-bends in steam generators 1 and 4 were inspected using EB-1 540-BBM-UF and EB-520-BJFM-UF probes .
Inspection Summary j S/G S/G Extent of Inspection 1 4 i
Full Length 2984 3008
}
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+
Straight Length --- 16 Motorized Rotating Pancake Coil -- 1 i
d The above actual meets or exceeds the original test program. In some cases, either the required minimum extent was exceeded or additional tubes were tested.
Data Evaluation Westinghouse performed both the primary and' secondary analysis of the eddy current data utilizing their analysis software, ANSER. Data management was !
accomplished using SUPERTUBIN software. GPC site-specific Data Analysis Guidelines were used to perform the analysis.
Each of the analysts were required to complete a training session and then be tested on their performance. Analysts training meets the requirements of EPRI Guidelines NP-6201, Appendix G and H. Previously, Westinghouse prepared a program which included training tapes, test tapes and a training manual for GPC. Analysts are required to pass the testing prior to analyzing any new ,
data. Each of the analysts were trained and tested in bobbin analysis. Part of the analysis group also received the Rotating Pancake Coil training and ;
testing. l In a effort to minimize cost, the secondary analysis was performed off-site at ;
a remote site. The remote analysis was performed at the Westinghouse Waltz i Mill site. Remote analysis is accomplished using a 1.54 megabyte data l transmission line (T-1 line) to communicate between the site and the remote l location. Data analysts at the remote facility analyze data in the same 3-4
1 4
i i !
fashion as analysts on site. Due to the speed of the T-1 line, data is received at the remote station almost instantly. Data management and primary l
analysis were still performed on site, t
[ The inspection conducted during the third maintenance / refueling outage at l
VECP-2 identified no pluggable indications in Steam Generators Nos. 1 and 4 as a result of eddy current testing. The following table summarizes the l j
l j indications found:
\
Indication S/G 1 S/G 4 l
i l i
q 40% and greater wall 0 0 thickness penetration l
4 20-39% wall thickness 7 12 l penetration Less than 20% wall 14 26
?
thickness penetration ,
it should be noted that the above table is based on the largest indication per tube.
i More details regarding indication distributions can be found in the maps which follow the steam generator tubing inspections discussion. :
Motorized Rotating Pancake Coil Testing There were no plans to perform inspection utilizing the rotating pancake coil in the original inspection program. However, analysis revealed the presence of a foreign object on the secondary side on the baffle plate adjacent to the tube located at R57C68. An expanded bobbin inspection scope was performed on sixteen tubes adjacent to location R57C68 and Rotating Pancake Coil was performed on the affected tube. The RPC of the questionable tube confirmed a wear indication on the tube. Since the foreign object was successfully removed from the steam generator and the percent wall thickness penetration was less than the VEGP Technical Specifications plugging limit, the tube was l not removed from service.
The rotating pancake coil testing was conducted with an A-560-KRPC-KU motor unit and a 560-MRPC-PH probe.
Mechanical Plug Removal and Plugging As noted above, there were no pluggable indications identified during the third maintenance / refueling outage as a result of eddy current testing.
However, two tubes in Steam Generator No. 1 that had been previously plugged with Inconel 600 plugs were re-plugged with Inconel 690 plugs. This reflects )
our implementation of a previous commitment to NRC Bulletin 89-01, " Failure of j.
3-5
. . - . . - _ = _ - - . - . . . . . . . _ . - . . . . . - . - - -. ... - - _. - -. . _ . _ -__.
1 l
1, Vestinghouse Steam Generator Tube Mechanical Plugs" The tubes with replaced j
l plugs are located at Row 1, Column 1 and Row 27, Column 42. The work was 4 performed in accordance with GPC MWO #29303170. The plug removal was performed in accordance with Westinghouse Procedure MRS 2.3.2 GPC-2, j " Machining of Steam Generator Tubes and Plugs". The re-plugging of the tubes was performed in accordance with Westinghouse Procedure MRS 2.3.2 GPC-1,
" Mechanical Plugging of Steam Generator Tubes."
The U.S. Nuclear Regulatory Commission was notified by Special Report
(
Reference:
GPC letter LCV-0179 dated October ?.4, 1993 to NRC) as required by i VEGP Technical Specification 4.4.5.5.a of the troes that were plugged during j the third maintenance / refueling outage at VECP-2.
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- 1. Steam Generator No. 1 - Bobbin Inspection Plan - Hot Leg (page 3-9)
- 2. Steam Generator No. 1 - Bobbin Inspection Plan - U-Bend (page 3-10)
- 3. Steam Generator No. 1 - Bobbin It.spection Plan - Cold Leg (page 3-11)
- 4. Steam Generator No. 1 - Bobbin Test Extents (Actual) (page 3-12 and 3-13)
- 5. Steam Generator No. 1 - Indications (page 3-14 and 3-15)
- 6. Steam Generator No. 4 - Bobbin Test Program - Hot Leg (page 3-16) j 7. Steam Generator No. 4 - Bobbin Test Program - U-Bend (page 3-17) i
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- 8. Steam Generator No. 4 - Bobbin Test Program - Cold Leg (page 3-18) i 1
j 9. Steam Generator No. 4 - RPC Inspection Program (page 3-19)
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- 10. Steam Generator No. 4 - Bobbin Test Extents (Actual) (page 3-20 and 3-21) j 11. Steam Generator No. 4 - Indications (page 3-22 and 3-23)
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i NOTE The preceding discussion on the steam generator tubing inspections, in addition to fulfilling the reporting requirements of ASME Section XI for inservice inspection activities, constitutes the Special Report required by VEGP Technical Specificatic.n 4.4.5.5.b to be submitted to the NRC within twelve months following completien of the steam generator tube inspections. Accordingly, a separate submittal is not being made to the NRC on the inspection of j the steam generator tubes performed during the third maintenance / refueling outage at VEGP-2. A copy of. selected volumes of this report containing the above steam generator t examination discussion is being provided to the NRC Regional Administrator; thus, compliance with the requirements of VEGP Technical Specification 6.8.2 for submittal of Special Reports to the Regional Administrator of the appropriate NRC Region office is met.
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Steam Generator No. 1 Total No. of Tubes: 5,626
- No. of Tubes Inspected: 2,984 2,984 tested from Tube End Hot (TEH) through Tube End Cold (TEC)
No. of Tubes Degraded: 7 l
I No. of Tubes Defective: 0 No. of Tubes Plugged Prior to Outage 2R3: 2 No. of Tubes Plugged during Outage 2R3: 2*
l l
l Total No. of Tubes Plugged: 2 j
- Replugged tubes located at Row 1, Column 1 and Row 27, Column 42 which were
- originally plugged prior to Outage 2R3.
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. Steam Generator No. 2
! Total No. of Tubes: 5,626 No. of Tubes Inspected: Not inspected during VEGP-2 Outage 2R3
. No. of Tubes Degraded: 0 No. of Tubes Defective: 0 t
No. of Tubes Plugged Prior to Outage 2R3: 4*
No. of Tubes Plugged during Outage 2R3: 0 Total No. of Tubes Plugged: 4 l
l 1
- Plugged tubes located at Row 51, Column 32; Row 2, Column 48; Row 5, Column 48; and Row 16, Column 103, i
3-24 1
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TABLE I (continued)
Steam Generator No. 3 Total No, of Tubes: 5,626 No. of Tubes inspected: Not inspected during VEGP-2 Outage 2R3 No. of Tubes Degraded: 0 No. of Tubes Defective: 0 No. of Tubes Plugged Prior to Outage 2R3: 1*
No. of Tubes Plugged during Outage 2R3: 0 Total No. of Tubes Plugged: 1
- Plugged tube located at Row 25, Column 102.
Steam Generator No. 4 Total No. of Tubes: 5,626 No. of Tubes inspected: 3,008 3,008 tested from TEH through TEC 16 tested from lc through TEC No. of Tubes Degraded: 12 No. of Tubes Defective: 0 No. of Tubes Plugged Prior to Outage 2R3: 8*
No of Tubes Plugged during Outage 2R3: 0 Total No. of Tubes Plugged: 8 i
- Plugged tubes located at Row 3, Column 35; Row 12, Column 36; Row 8, Column l 56; Row 16, Column 57; Row 48, Column 64; Row 23, Column 67; Row 22, Column 1 90; and Row 24, Column 93.
O 3-25
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l
' TABLE II Steam Generator No. 1 Reference Distance from Wall Thickness Plugged Column Point (1) Reference (in.)(2) Penetration (t) (Y/N)
E93 30 10 AV6 0.00 16 N l
! 31 12 AV5 0.00 18 N i
f 36 17 AV6 0.00 18 N 41 20 AV2 -0.06 11 N
]
42 20 AV2 0.00 17 N
- 41 23 4H 3.46 12 N i
- 44 23 AV5 0.00 16 N 34 25 AV1 0.00 19 N l
'r 48 26 AV4 0.00 26 N i 47 27 AV2 0.00 19 N a
48 28 AV2 0.00 10 N
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! 50 28 AV4 0.00 23 N 53 33 AV4 0.00 15 N I
53 34 AV3 0.00 17 N 55 39 7C -0.76 22 N i 54 41 6C 27.08 31 N 52 57 SC 18.15 27 N 47 65 7C -0.98 31 N 55 83 AV5 0.00 12 N 54 86 1H 1.46 15 N 27 105 TSC 10.13 22 N 3-26 l
r l
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_ _ . . .._ _ _ . . _ ___ _ _ _ . . . _ _ _ _ _ . _ . . . _ _ _ _ _ . _ . _ _ _ _ _ - -- _ _ _.~._._._ __. _ _._ _ _ .
t The above information is based on the largest indication observed for the respective tube during the third maintenance / refueling outage at VECP-2.
Note 1: Reference Point Location Description l
TSH, TSC - Top of Tubesheet Hot and Cold l
BPH, BPC - Baffle Plate Hot and Cold
- H , #C - (# - Number) of Support Plate Hot and Cold, e.g., 2H, 2C AV1, AV2, AV3, AV4, AV5, AV6 - Anti-vibration Bars Note 2: Unless indicated otherwise, distance is above Reference Point, A negative number, e.g., -2.00, indicates that the distance is below the Reference Point, 1
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TABLE III Steam Generator No. 4 Reference Distance from Wall Thickness Plugged Row Colwrn Point (1) Reference (in.)(2) Penetration (%) (Y/N) 16 4 6 11 37.83 11 N 34 12 6C 36.70 14 N 13 15 SH 20.50 18 N 1
44 21 AV3 0.00l 24 N 45 22 AV2 0.00 11 N 15 23 6 11 37.62 14 N l
48 28 AV5 0.00 25 N )
45 32 AV3 0.00 10 N 52 33 AVS 0.00 17 N 54 35 AV5 0.00 20 N ;
54 37 AV6 0.00 11 N 35 38 6 11 37.88 28 N 27 39 AV5 0.00 14 N 44 42 AV5 0.00 13 N 53 43 AV3 0.00 23 N 57 46 AV4 0.00 31 N 44 48 AV6 0.00 23 N 57 48 AV5 0.00 1,5 N 51 54 AV5 0.00 11 N 50 55 AV3 0.00 11 N 51 55 AV3 0.00 11 N 12 56 6H 37.62 9 N 44 59 AV3 0.00 10 N 3-28
i TABLE III (continued) l j
g Steam Generator No. 4 l Reference Distance from Wall Thickness Plugged-
]
Column Point (1) Ee ference (in. )(2) Penetration (%) (Y/N) h 51 59 AV3 0.00 28 N
! 39 64 AV3 0.00 23 N 52 66 AV2 0.00 16 N l l
53 66 5C 1.45 14 N i
50 67 AV4 0.00 22 N l
43 68 AV3 0.00 12 N ;
57 68 BPC 0.65 38 N j 52 72 AV2 0.00 18 N 51 73 AV2 0.00 33 N 43 76 AV5 0.00 14 N 52 78 AV4 0.00 12 N 43 83 AV4 0.00 27 N i
i 44 85 AV3 0.00 9 N l
30 94 6 11 36.71 13 N 18 104 6H 32.53 12 N The above information is based on the largest indication observed for the respective tube during the third maintenance / refueling outage at VECP-2. .
(1) See Note 1, page 3-27.
(2) See Note 2, page 3-27.
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Technical Specification 4.7.8 - Snubber Inspections As required by Technical Specification 4.7.8, each snubber (483 total) was visually examined during the VEGP-2 third mainterance/ refueling outage. The examinations revealed some degraded conditions such as rusted spherical bearings, slight misalignments, frozen-up loadpins, etc., none of which '
impaired the operability of the snubbers. The appropriate actions were taken to correct the degraded conditions. Technical Specification 4.7.8 also requires functional testing of snubbers. The snubbers were categorized into four types as follows:
Type I -
Pacific Scientific mechanical snubbers (All sizes)
Type II - Anchor-Darling mechanical snubbers (Models AD-40 through AD-500)
Type III - Anchor-Darling mechanical snubbers (Models AD-1600 through AD-12500)
Type IV - Paul-Munroe ENERTECH 1000 kip steam generator hydraulic snubbers Each of the snubber types were functionally tested utilizing a test plan (as detailed in Technical Specification 4.7.8e.1) which requires that an initial representative random sairple of ten percent (10%) of the population to be functionally tested. The results of the functional testing of the snubber types follows:
Tvne I - Eleven snubbers were included in the initial representative random sample to be functionally tested for the Type I snubbers. The eleven snutbers were functionally tested and each met the functional test acceptance criteria with the exception of one snubber. In accordance with the requirements of Technical Specification 4.7.8e.1, the functional test scope was increased. Subsequent testing of eleven additional snubbers resulted in no failures. Appropriate engineering evaluation as required by Technical Specification 4.7.8g and subsequent corrective action was performed for the Type I snubber which failed functional testing. To summarize, a total of twenty-two Type I snubbers were functionally tested with each meeting the functional test acceptance criteria except as noted above. No additional functional testing of Type I snubbers was performed.
Tyne II - Twenty-six snubbers were included in the initial representative random sample to be functionally tested for the Type II snubbers. The twenty-six snubbers were functionally tested and each met the functional test acceptance criteria.
No additional functional testing of Type II snubbers was performed.
3-30
l 4
l 1
Tyne III - Twelve snubbers were included in the initial representative !
random sample to be functionally tested for the Type III 1
snubbers. The twelve snubbers were functionally tested and
]
each snubber passed. No additional functional testing of Type III snubbers was performed.
Tvoe IV - One snubber was included in the initial representative random sample to be functionally tested for Type IV snubbers. The j 4 snubber was functionally tested and passed. Therefore, no )
additional functional testing of Type IV snubbers was i performed.
4 The specific Types I through IV snubbers which were functionally tested in ;
j response to Technical Specification 4.7.8 are itemized on pages 12-1, 13-1, 14-1, and 15-1 of this report document.
In accordance with VEGP Technical Specification 4.7.8g, an engineering evaluation was performed by SCS, with assistance from Westinghouse for the snubber that failed functional testing. The engineering evaluation was performed in order to determine the cause(s) of the failures and to determine if the piping system to which the failed snubber was attached was adversely j affected. The affected piping system having the f ailed snubber was returned to its design configuration by replacing the failed snubber with an operable snubber. The following is a listing of correspondence associated with the engineering evaluation which is available at the plant site for review upon request:
() Affected SNC/GPC Transmittal Applicable SCS Letter /Date to Plant Site Evaluation Letter /Date Applicable Request for Encineering Review (RER)
Enubbe r( s )
21204-021-H003 MSV-01556 SG-12771 93-0348 10/25/93 9/22/93, SG-12798 9/30/93 Technical Specification 4.4.10.2 - Reactor Coolant Pump Flywheel and Keyway Bore Examinations The flywheel keyway and bore areas for Reactor Coolant Pumps 21201-P6-001, 003 and 004 were ultrasonically ' examined during the 2R3 maintenance / refueling outage. No recordable indications were observed. The examinations performed during the third VEGP-2 maintenance / refueling outage are itemized with the Class 1 equipment.
Prior to the VEGP-1 fourth maintenance / refueling outage, a spare Reactor Coolant Pump motor was purchased to be included in a rotational maintenance program for VEGP-1 and 2. The ten year examinations per NRC Regulatory Guide 1.14 are scheduled to be performed during rotational maintenance program activities while the flywheels are removed. The motor assembly, including flywheel, for Reactor Coolant Pump 21201-P6-002 was replaced during the third '
VEGP-2 maintenance / refueling outage with the motor assembly (Reactor Coolant 3-31
Pump motor serial no. 91-P123) previously removed during the VEGP-1 fourth maintenance / refueling outage and refurbished by Westinghouse. Prior to installation of the refurbished motor assembly, the flywheel was disassembled.
Surface and volumetric examinations were performed by Westinghouse. No recordable indications were observed. Details of the surface and volumetric examinations performed by Westinghouse are available at the plant site for review upon request.
NRC Bulletin 88 Thimble Tube Thinninn in Westinthouse Reactors In response to NRC concerns with thinning in Bottom-Mounted Instrumentation (BMI) flux thimbles in Westinghouse reactors, eddy current examination of each of the fifty-eight thimbles was performed during the third maintenance / refueling outage at VECP-2. The purpose of the examinations was to detect and size indications of possible wear on the outer diameter of the flux thimbles. The examination of the flux thimbles was performed by Westinghouse in accordance with their procedure MP 2.3.1 CAE/GBE-1, Revision 0, " Thimble Tube Eddy Current Inspection at Vogtle Units 1 and 2."
An evaluation was performed by SNC using Westinghouse WCAP-12688, " Bottom Mounted Instrumentation Flux Thimble Wear", on BMI flux thimbles which were found to have indications of wear after the third fuel cycle. VEGP-2 has forty-four flux thimbles with some indication of wall loss. The maximum indication being forty-eight percent wall loss on Thimble No. 6 (core location P-09). The next highest indication is forty-three percent wall loss on Thimble No. 46 (core location D-03). Wear rate projections through the end of the fourth and fifth fuel cycles indicate that the forty-four flux thimbles will remain below the eighty percent (80%) maximum wall loss acceptance criteria established in Westinghouse WCAP-12688. Therefore, it was concluded that no corrective action, e.g., repositioning of flux thimbles, was required during the third maintenance / refueling outage at VEGP-2.
The SNC evaluation was transmitted to the plant site by letter MSV-01547 dated September 22, 1993 and is available at the plant site for review upon request. !
Westinzhouse Technical Bulletin NSD-TD-90 BMI Conduit Guide Tube Leaks In accordance with the recommendations in Westinghouse Technical Bulletin NSD-TD-90-02, the bottom mounted instrumentation (BMI) conduit (flux thimbles) guide tubes were visually examined for any signs of leakage. The examination was performed by GPC personnel utilizing VEGP procedure 93290-C, Rev.3, "Incore Flux Thimble Cleaning / Lubrication and Inspection". No signs of leakage were observed.
GPC Action Item No. 1739 - Feedwater Line Crackinz Since some Westinghouse plants have a history of steam generator nozzle cracking, GPC has elected to examine selected piping welds in the Auxiliary Feedwater and Feedwater Systems. Selected welds were examined with ultrasonic and magnetic particle techniques. No non-geometrical indications of a recordable size were detected during the ultrasonic examinations. However, surface indications were detected during the magnetic particle examinations on weld 21302-109-44.. Refer to the Class 2 Examination Summary (Section 2) for O details.
3-32
- - . . - _ _ . ~_ . - _ _ _ . - ._._ __ -. - . _ . _ _ _ .- __. -._ -.
I The specific welds examined in response to GPC Action Item No. 1739 are itemized with the Class 2 piping welds.
GPC Letter CN-1345 (February 9. 1987) - Auzmented Examinations of Class 3 i l
! Nuclear Service Cooling Water System 1 In the subject letter, GPC committed to perform an augmented ultrasonic )
l examination on one Nuclear Service Cooling Water System piping veld on VEGP-2 every 40 months. The ultrasonic examination was performed during the third maintenance / refueling outage. Visual examinations were performed during the 2R3 outage on accessible Class 3 portions of the NSCW piping as committed to by the subject GPC letter. The visual examinations were performed during )
normal system operation and no leaks were found except for mechanical l connections such as bolted flanges. Appropriate corrective action was 1 initiated to correct these leaks. l VEGP-2 Inservice Inspection Procram (ISI-P-014) Paragraph 1.10.3 - Volumetric Examination of Additional Class 2 Pipine Welds Selected Class 2 piping welds in the Safety Injection, Residual Heat Removal, Containment Spray, and Chemical and Volume Control systems were examined using ultrasonic examination techniques. No non-geometrical indications of a recordable size were found.
The specific welds examined are itemized with the class 2 piping welds.
GPC Action Item Nos. 87-0131 and 87-0931 - Stannant Borated Water Systems Crackinn As a result of generic concerns of pipe cracking in stagnant borated water systems in pressurized water reactors, several welds in Class 2 piping systems were examined in response to GPC Action Items Nos. 87-0131 and 87-0931.
Nondestructive examination methods utilized included ultrasonic and/or liquid penetrant examination techniques.
In Class 2 systems (Safety Injection System, Residual Heat Removal System, Containment Spray System, and Chemical and Volume control System), several welds were examined. There were no non-geometric indications observed during the ultrasonic examination of the Class 2 welds subject to ultrasonic examination. However, a surface indication was observed during the liquid penetrant examination on weld 21204-039-35. Refer to the Class 2 Examination Summary (Section 2) for details.
The specific welds examined as a result of GPC Action Item Nos. 87-0131 and 87-0931 are itemized with the class 2 piping welds.
Westinthouse WCAP No. 12907 "A11ov 600 PWSCC Susceptibility Assessment of Vontle Unit 1 and 2 Primary Components" In accordance with recommendations found in Section 6 of Westinghouse WCAP No.
12907, a visual examination was performed on the channel head partition plate on Steam Generator No. 1. No reportable indications were observed. )
f The sp%cific weld examined is itemized with the Class 1 equipment welds. 1 l
l l
3-33 !
CPC Action Item No, 18270 - Examination Techniaues and Personnel O Oualifications for Cold Lee Accumulalpr J_ipine (10-inch Schedule 140. ASTM SA-376. Tvoe 316)
As a result of GPC Action Item No. 18270, selected ultrasonic examinations were performed using nondestructive examination procedures and examination i personnel qualified in the detection of intergranular stress corrosion cracking (IGSCC). No reportable indications were observed.
The specific welds examined are itemized with the Class 1 piping welds.
Technical Specification 4,4,10.3 " Main Steam and Feedwater Volumetric Examinations" In accordance with VEGP Technical Specification 4.4.10.3, six Main Steam line welds and seven Feedwater line welds located from the containment penetration flued head outboard welds to the first five-way restraint were examined. No reportable indications were observed with the exception Main Steam weld 21301-004-14 Refer to the Class 2 Examination Summary (Section 2) for details.
The specific welds examined are itemized with the Class 2 piping welds.
NRC Information Notice 91 Interzranular Stress Corrosion Crackinc in Pressurized Water Reactor Safety Iniection Accumulator Nozzles As a result of the information provided in NRC Information Notice 91-05, selected " Nozzle to Accumulator" welds were ultrasonically examined. No O reportable indications were observed.
The specific welds examined are itemized with the Class 2 equipment welds, galance of Plant Erosion / Corrosion Insnections Ultrasonic thickness measurements were performed on selected components (fittings and/or piping) in the Condensate, Heater Drain, Main Feedwater, Turbine Drain, MSR Pocket Drain, Main Steam, and Extraction Steam systems.
Included in the initial inspection plan were eighteen new components which were examined for the first time based upon information resulting from modeling using the EPRI CHECHATE computer program or from high-wear experiences on VEGP-1. In all, thirty-eight large-bore components were examined during the 2R3 maintenance / refueling outage, In addition, at the request of the VEGP Technical Support Department, ultrasonic examinations were performed on fifteen small-bore areas. The inspections were performed using SNC procedure UT-V-466, " Ultrasonic Erosion / Corrosion Examination Procedure".
Several large-bore components were identified to have wall thickness measurements which indicated possible wear due to erosion / corrosion. The affected components had wall thickness readings which were at or below the
" Action Level" wall thickness value assigned to each of the components. The
" Action Level" value was defined as the wall thickness which is fifty percent The (50%) of the difference between the nominal wall and code minimum wall.
examination results for large-bore components which had wall thickness 3-34 T
- - - -. ,e- --% , * - . - -- --.,y -e--- . , - - %. ,- - - - - - . - - - - y-. - - . - - -
readings at or below their " Action Level" were reported by SNC to GPC by means O of INFs which can be found in the applicable section of this report.
general, SCS engineering personnel were requested to evaluate the continued In acceptability of these components. The continued acceptability of small-bore components was determined by VEGP Technical Support Department personnel. The following is a listing of correspondence associated with the engineering evaluations which are available at the plant site upon request:
SNC/GPC Applicable Transmittal Request Affected Component SCS Eval. Letter /Date for Engineering Tvne and System INF Number Letter Date to Plant Site Review (RER) 2-HD-02 193V2001 SG-12768 MSV-01555 93-0327 8"x20" expander 09/27/93 10/13/93 Heater Drain System 2-HD-10 193V2002 SG-12768 MSV-01555 93-0326 8"x20" expander 09/27/93 10/13/93 Heater Drain System 2-CND-12 193V2003 SG-12777 MSV-01555 93-0336 8"x14" expar.er 09/24/93 10/13/93 Heater Drain Systen 2-CND-13 193V2004 SG-12777 MSV-01555 93-0339 8"x14" expander 09/24/93 10/13/93 0 Heater Drain System 2-M FW-08 193V2006 SG-12783 MSV-01555 93-0356 l 6"x10" expander 09/28/93 10/13/93 Main Feedwater System ,
2-HD-06 193V2007 SG-12784 MSV-01555 93-0353 6"x12" expander 09/28/93 10/13/93 Heater Drain System 2-CND-10 193V2008 SG-12789 MSV-01555 93-0354 14" pipe 09/29/93 10/13/93 Heater Drain System 2-M FW-06 193V2013* N/A N/A N/A 36" x 26" reducer Main Feedwater System l 1
2-MFV-01 193V2014 SG-12801 MSV-01555 93-0352 1 34"x34"x20" tee 09/30/93 10/13/93 Main Feedwater System O 3-35
i 2-CND-03 193V2015 SG-12789 MSV-01555 93-0354 i
14" elbow 09/S9/93 10/13/93
- . Heater Drain System 2-MFW-13 193V2017 SG-12814 MSV-01562 93-0367 24"x24"x16" tee 10/13/93 10/25/93 .
Main Feedwater '
4 System
- INF dispositioned by site Technical Support Department personnel. No RER was written; thus, no SCS and SNC/GPC correspondence were required.
Each RER concerning the affected components was evaluated to determine appropriate action. Six large-bore components in the Heater Drain System were determined to have indications of wear that would indicate the code minimum wall thickness would be reached during the next two 18-month fuel cycles. The six large-bore components were recommended for replacement during the 2R3 ,
maintenance / refueling outage. In addition, to avoid projected future replacement, the piping immediately downstream of two of the components was also recommended for immediate replacement. The components were subsequently replaced with erosion / corrosion-resistant materials and baseline examinations performed. In addition, several small bore lines showed signa of significant wear. These lines were associated with the MSR Pocket Drains, Extraction Steam Drains, or Main Steam Drains. The affected portions of those small bore lines were subsequently replaced with carbon steel piping.
3-36 i
~
Augmented Corponent or Exam Cat ASME Sect. XI Examination Weld No./ Exam Procedure Cal. Sheet Exam i tem No./ Cat. Requirement Dmeription Method No./Rev. Blocks No.(s) Sheet No(s). Results Remarks See Note See Note See Note See Note See Note See Note See Note See Note See Note See Note A B L D E F G H I J NOTES:
A. The ASME Section XI Item No. and Category of the examination area are listed in this column.
B. The implementing docurent, e.g., Tech Specs, NRC Bulletin. etc., requiring performance of augmented examinations is referenced here.
Each examination area is listed in this column. The component or weld nunter typically is similar to the drawing rusnber, e.g., weld ruber C.
21201-005-8 is found on drawing ruber iSI-21201-005.
D. The NDE method used during the examination is listed in this column.
E. This colum lists the applicable NDE procedures and revisions used for the examination.
F. This column lists the calibration block that was used.
G. This colum references the calibration sheet (s) which records calibration, examiner, and any pertinent remarks.
H. This colum references the examination data sheet (s) whhh records exam data, examiners, and any pertinent remarks.
.l. The results of the examinations are indicated in this column. The aosence of indications is indicated in the cotum as "NI" or " SAT". The presence of nonrelevant indications or indications which are less than the recording level is indicated in the colum as "NRI". The presence of indications deemed recordable are indicated in the colum as "RI" or "UNSAT" and are explained in the remarks colunr1 of the sumary table.
J. The remarks column is used to describe any pertinent features of the examination such as limitations, INFs, etc. Refer to INF section in this report for their disposition.
FIGURE 1. EXPLANATION OF
SUMMARY
TABLE FORMAT t
4-1
VECP-2 TMIRD MAINTENANCE / REFUELING OUTAGE CLASS 1 EQUIPMENT EXAMINATIONS EXAM CAL EXAM AUGMENTED COMPONENT OR EXAM PROCEDURE CALIBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD N0/
METHOD NO./ REY. BLOCKS No.(S) NO,(S) RESULTS REMARKS ITEM NO/ CAT. PEOUIREMENT DESCRIPTION N/A N/A $93V2V630 SAT N/A
- W WCAP 21201-86-001-104 VT-1 VT-V-715/01 i 4 - 12907 PARTITION PLATE N/A N/A S93V2V632 SAT RR-42 B3.140 N/A 21201-B6-001-IR-01 VT-3 VT-V-735/02 B-D INLET N0Z2LE 1R VT-3 VT-V-735/02 N/A N/A $93V2V631 SAT RR-42 33.140 N/A 21201-86-001-IR-02 B-D OUTLET N0ZZLE IR VENDOR 806A,B,C,0 VENDOR VENDOR SEE ASME CLASS 3 AND B16.20 TECH SPEC 21201-86-001-T01 ET AUGMENTED EXAM SLpmARY 807A,8 B-o 4.4.5.0 TUBING - ENTIRE SECTION FOR DETAILS.
LENGTH OF SELECTED TUBES UT-V-411/05 410A S93v2C080 $93V2UO99 NRI UT SCAN LIMITED /RR-19 21201-86-001-WO8 UT 82.40 N/A
$93V2C082 $93V20101 NRI B-8 TUBE PLATE /CM HEAD
$93V2C084 593V2U103 WRI ET VENDOR 806A,B,C,0 VENDOR VENDOR SEE ASME CLASS 3 AND B16.20 TECM SPEC 21201-86-004-T01 807A,8 AUGMENTED EXAM SU8 MARY ,
B-o 4.4.5.0 TUBING - ENTIRE SECTION FOR DETAILS. .
LENGTH OF SELECTED TUBES i
UT UT-V-411/05 410A 593V2COS1 593V20100 NRI UT SCAN LIMITED /RR-19 B2.40 N/A 21201-B6-004-WO8 593V2C083 S93V2U102 NRI B-B TUBE PLATE /CH MEAD
$93V2C085 593V2U104 WRI UT UT-V-417/02 N/A N/A $93V20113 NRI N/A
- TECH SPEC 21201-P6-001-F03
- 4.4.10.2 FLY WHEEL KEY WAY ,
UT UT-V-417/02 N/A N/A $93V2U113 NRI N/A
- TECM SPEC 21201-P6-001-F04 t
- 4.4.10.2 FLY WHEEL KEY WAY (RG 1.14) (SER NO 91-P121) 5-1
a a VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE CLASS 1 EQUIPMENT EXAMINATIONS AUGMENTED COMPONENT OR EXAM CAL EXAM PROCEDURE CALIBRATION SHEET SNEET ASME SECT XI EXAMINATION QLD NO/ EXAM ITEM N0/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS 21201-P6-001-F05 UT U T -V-417/02 N/A N/A $93V2U113 NRI N/A TECH SPEC 4.4.10.2 FLY WHEEL KEY WAY (RG 1.14) (SER NO 91-P121) pi VENDOR N/A VENDOR VENDOR ACC EXAMINATIONS PERFORMED BY
- TECH SPEC 21201-P6-002-F01 WESTINGHOUSE DURING
- 4.4.10.2 FLY WHEEL KEY WAY ROUTINE MAINTENANCE. SEE (RG 1.14) (SER NO 91-P123)
CLASS 3 AND AUGMENTED EXAMINATION
SUMMARY
FOR IETAILS.
VENDOR N/A VENDOR VENDOR ACC EXAMINATIONS PERFORMED BY
- TECH SPEC 21201-P6-002-F02 PT WESTINGHOUSE DURING
- 4.4.10.2 FLY WHEEL KEY WAY ROUTINE MAINTENANCE. SEE (RG 1.14) (SER NO 91-P123)
CLASS 3 AND AUGMENTED EXAMINATION
SUMMARY
FOR DETAILS.
UT VENDOR N/A VENDOR VENDOR ACC EXAMINATIONS PERFORMED BY
- TECH SPEC 21201-P6-002-F03 WESTINGHOUSE DURING 4.4.10.2 FLY WHEEL KEY WAY ROUTINE MAINTENANCE. SEE (RG 1.14) (SER NO 91-P123)
CLASS 3 AND AUGMENTED EXAMINATION
SUMMARY
FOR DETAILS.
UT VENDOR N/A VENDOR VENDOR ACC EXAMINATIONS PERFORMED BY TECH SPEC 21201-P6-002-F04 WESTINGHOUSE DURING 4.4.10.2 FLY WHEEL KEY WAY ROUTINE MAINTENANCE. SEE (RG 1.14) (SER NO 91-P123)
CLASS 3 AND AUGMENTED EXAMINATION
SUMMARY
FOR DETAILS.
5-2
O O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE C
CLASS 1 EQUIPMENT EXAMINATIONS EXAM CAL EXAM AUGMENTED COMPONENT OR EXAM PROCEDURE CALIBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD NO/
NO./REV. BLDCKS NO.(S) NO.(S) RESULTS REMARKS ITEM E0/ CAT. REQUIREMENT DESCRIPTION METHOD VENDOR N/A VENDOR VENDOR ACC EXAMINATIONS PERFORMED BY
- TECH SPEC 21201-P6-002-F05 UT WESTINGHOUSE DURING
- 4.4.10.2 FLY WHEEL KEY WAY ROUTINE MAINTENANCE. SEE (RG 1.14) (SER NO 91-P123)
CLASS 3 AND AUGMENTED EXAMINATION
SUMMARY
FOR DETAILS.
UT-V-417/02 N/A N/A $93V2U114 NRI N/A
- TECH SPEC 21201-P6-003-F03 UT
- 4.4.10.2 FLY WHEEL KEY WAY (RG 1.14) (SER NO 1S-89P925)
UT UT -V-417/02 N/A N/A $93V2U114 NRI N/A
- TECH SPEC 21201-P6-003-FD4
- 4.4.10.2 FLY WHEEL KEY WAY (RG 1.14) (SER NO 15-899925)
UT-V-417/02 N/A N/A S93v2U114 NRI N/A TECH SPEC 21201-P6-003-F05 UT
- 4.4.10.2 FLY WHEEL KEY WAY (RG 1.14) (SER NO 1S-89P925)
UT UT-V-417/02 N/A N/A 593V2U115 NRI N/A TECH SPEC 21201-P6-004-F03 4.4.10.2 FLY WHEEL KEY WAY (RG 1.14) (SER NO 91-P124)
UT UT-V-417/02 N/A N/A S93V2U115 NRI N/A TECH SPEC 21201-P6-004-F04 4.4.10.2 FLY WHEEL KEY WAY (RG 1.14) (SER NO 91-P124)
UT UT-V-417/02 N/A N/A 593V2U115 NRI N/A
- TECH SPEC 21201-P6-004-F05
- 4.4.10.2 FLY WHEEL KEY WAY (RG 1.14) (SER NO 91-P124) 5-3
VEGP-2 THIRD MAINTENANCE /REFUEllNG OUTAGE CLASS 1 EQUIPMENT EXAMINATIONS COMPONENT OR EXAM CAL EXAM AUGMENTED EXAM PROCEDURE CAllBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD WO/
REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS ITEM NO/ CAT.
MT-V-505/03 408A 593v2M033 NRI MT RI/ LINEAR INDICATIONS B6.30 N/A 21201-V6-001-B19 - B36 MT UT UT-V-422/02 593v2M034 RI ON STUDS 830, B32 & 833.
B-G 1 CLOSURE NEAD STUDS S93v2M035 NRI SEE INF 193V2016.
S93V2M036 RI ACCEPTABLE AS 15.
S93V2M037 RI S93v2M038 NRI 593V2C204 593v2U239 NRI S93V2C205 S93v2U240 NRI S93v2C206 S93v20241 NRI
$93v2C207 S93v2U242 NRI vi-3 VT-v-735/02 N/A N/A S93V2V608 SAT N/A B13.10 N/A 21201-V6-001-101 B-N-1 VESSEL INTERIOR VT-3 VT-V- 735/02 N/A N/A S93v2V526 SAT N/A 813.10 N/A 21201-V6-001-102 B-N-1 VESSEL HEAD INTERIOR VENDOR 404A VENDOR VENDOR NRI UT EXAMINATIONS PERFORMED B3.100 N/A 21201-V6-001-IR01 di 401A BY WESTINGHOUSE. SEE B-D OUTLET N0Z N1 IR CLASS 1 EXAMINATION
SUMMARY
FOR DETAILS.
i UT VENDOR 404A VENDOR VENDOR NRI UT EXAMINATIONS PERFORMED 83.100 N/A 21201-V6-001-IR04 401A BY WESTINGHOUSE. SEE B-D OUTLET N0Z N4 IR CLASS 1 EXAMINATION SU MARY FOR DETAILS.
1 UT VENDOR 404A VENDOR VENDOR NRI UT EXAMINATIONS PERFORMED B3.100 N/A 21201-V6-001-IR05 401A BY WESTINGHOUSE. SEE B-D OUTLET N0Z N5 IR CLASS 1 EXAMINATION
SUMMARY
FOR DETAILS.
VENDOR 404A VENDOR VENDOR NRI UT EXAMINATIONS PERFORMED B3.100 N/A 21201-V6-001-!R08 UT 401A BY WESTINGHOUSE. SEE B-D OUTLET NOZ N8 IR CLASS 1 EXAMINATION l
SUMMARY
FOR DETAILS.
5-4
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VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE CLASS 1 EOUIPMENT EXAMINATIONS AUGMENTED COMPONENT OR EXAM CAL EXAM WELD NO/ EXAM PROCEDURE CALIBRATION SHEET SHEET ASME SECT.XI EXAMINATION ITEM NO/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS PT-V-605/02 405A N/A S93V2P089 NRI UT EXAMINATIONS PERFORMED B5.10 N/A 21201-V6-001-WO36 PT VENDOR 331A VENDOR VENDOR NRI BY WESTINGHOUSE. SEE B-F OUTLET NOZ N4 TO SE UT CLASS 1 EXAMINATION
SUMMARY
FOR DETAILS.
PT PT-V-605/02 405A N/A S93V2P090 NRI UT EXAMINATIONS PERFORMED 85.10 N/A 21201-V6-001-WO37 OUTLET NOZ N5 TO SE UT VENDOR 331A VENDOR VENDOR NRI BY WESTINGHOUSE. SEE B-F CLASS 1 EXAMINATION
SUMMARY
FOR DETAILS.
PT PT-V-605/02 405A N/A $93V2P086 NRI UT EXAMINATIONS PERFORMED 85.10 N/A 21201-V6-001-WO40 UT VENDOR 331A VENDOR VENDOR NRI BY WESTINGHOUSE. SEE B-F OUTLET NOZ N8 TO SE CLASS 1 EXAMINATION
SUMMARY
FOR DETAILS.
5-6
~!
VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE CLASS 1 PIPING EXAMINATIONS i
COMPONENT OR EXAM CAL EXAM AUGMENTED EXAM PROCEDURE CALIBQATION SHEET SHEET ASME SECT Xi EXAMINATION WELD N0/
NO.(S) NO.(S) RESULTS REMARKS ITEM N0/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCK 3 PT-V-605/02 331A N/A 593V2P084 NRI UT EXAMINATIONS PERFORMED B9.11 N/A 21201-001-1 PT '
UT VENDOR 405A VENDOR VENDOR NRI BY WESTINGHOUSE. SEE B-J SAFE END TO PIPE CLASS 1 EXAMINAtl0N
SUMMARY
FOR DETAILS.
PT PT-V-605/02 331A N/A S93V2P087 NRI UT EXAMINATIONS PERFORMED 89.51 N/A 21201-002-1 UT VENDOR 405A VENDOR VENDOR NRI BY WESTINGHOUSE. SEE B-J SAFE END TO PIPE CLASS 1 EXAMINATION
SUMMARY
FOR DETAILS. ,
PT PT-V-605/02 331A N/A S93V29088 NRI UT EXAMINATIONS PERFORMED B9.11 N/A 21201-003-1 UT VENDOR 405A VENDOR VENDOR NRI BY WESTINGHOUSE. SEE B-J SAFE END TO PIPE CLASS 1 EXAMINATION S'.,tetARY FOR DETAILS.
r PT PT-V-605/02 331A N/A $93v2P083 NRI UT EXAMINATIONS PERFORMED J B9.11 N/A 21201-004-1 UT VENDOR 405A VENDOR VENDOR NRI BY WESTINGHOUSE. SEE B-J SAFE END TO PIPE CLASS 1 EXAMINATION
SUMMARY
FOR DETAILS.
PT PT-V-605/02 331A S93v2P073 NRI UT SCANS LIMITED /RR-21.
89.31 N/A 21201-004-2 UT UT-V-406/04 353A S93V2C212 593V2U248 NRI B-J PIPE TO BC UT UT-V-413/02 593V2C186 S93V2U221 NRI PT PT-V-605/02 331A 593V2P037 NRI UT SCANS LIMITED /RR-21.
.B9.31 N/A 21201-004-3 UT UT-V-406/04 353A S93V2C079 593V2UO98 NRI B-J PIPE TO BC UT UT-V-413/02 S93V2C187 593V20222 NRI PT PT-V-605/02 N/A N/A 593V2P074 NRI N/A 89.32 N/A 21201-004-5 B-J PIPE TO BC .
i-PT PT-V-605/02 331A S93V2P100 NRI UT SCANS LIMITED /RR-17 99.11 N/A 21201-004-6 UT UT-V-406/04 $93V2C200 593V20235 NRI B-J ELBOW TO Il0ZZLE S93V2C203 S93V2U238 NRI 6-1 I -
f
+
i . .. ..
O O VEGP-2 THIRD MAINTENANCE /RETUELING OJTAGE O
CLASS 1 PIPING EXAMINATIONS AUGMENTED COMPONENT OR EXAM CAL EXAM EXAM PROCEDURE CAllBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD N0/
DESCRIPTION METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS PEMARKS ITEM N0/ CAT. REQUIREMENT PT-V-605/02 331A S93V2P029 NRI UT SCANS LIMITED /RR-17 99.11 N/A 21201-005-1 PT UT UT-V-406/04 $93V2C198 593V2U233 NRI B-J N0ZZLE TO ELBOW S93V2C201 S93V2U236 NRI 21201-008-1 PT PT V-605/02 331A S93V2PO46 NRI UT SCANS LIMITED /RR-17 B9.11 N/A UT UT-V-406/04 593V2C199 593V2U234 NRI B-J N0ZZLE TO ELBOW S93V2C202 593V2U237 NRI 21201-008-5 PT PT-V-605/02 N/A N/A S93V2P072 NRI N/A B9.32 N/A B-J PIPE TO BC 21201-008-8 PT PT-V-605/02 331A S93V2P066 NRI N/A B9.11 N/A UT UT-V-406/04 593V2C111 S93V20133 NRI B-J ELBOW TO N0ZZLE 593V2C112 593V2U134 NRI PT PT-V-605/02 331A $93V2P032 NRI UT SCANS LIMITED /RR-24.
B9.11 N/A 21201-012-1 N0ZZLE TO PIPE UT UT-V-406/04 S93V2C223 S93v2U259 RI UT Rl/ GEOMETRY.
B-J S93V2C224 S93V2U260 NRI 21201-012-3 PT PT-V-605/02 N/A N/A 593v2P033 NRI N/A 89.32 N/A B-J PIPE TO BC PT-V-605/02 351A S93V2P034 NRI UT SCANS LIMITED /RR-21.
B9.31 N/A 21201-012-4 PT PIPE TO BC UT UT-V-413/02 593V2C188 593V2U223 RI UT Rl/ GEOMETRY B-J 21201-012-5 PT PT-V-605/02 N/A N/A S93v29035 NRI N/A B9.32 N/A B-J PIPE TO BC PT-V-605/02 331A $93V2P071 NRI UT SCANS LIMITED /RR-21 B9.31 N/A 21201-012-6 PT UT UT-V-406/04 S93V2C213 593v2U249 NRI B-J PIPE TO BC PT-V-605/02 N/A N/A S93V2P036 NRI N/A B9.32 N/A 21201-012-7 PT B-J P!PE TO BC 6-2
O O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE O
CLASS 1 PIPING EXAMINATIONS COMPONENT OR EXAM CAL EXAM AL'GMENTED EXAM PROCEDURE CALIBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD NO/
METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS ITEM NO/ CAT. REQUIREMENT DESCRIPTION PT-V-605/02 303A 593V2P070 NRI UT RI/ GEOMETRY B9.11 N/A 21201-030-1 PT UT-V-404/06 593V2C164 $93V2U195 RI B-J BC TO PIPE UT S93V2C165 S93V20196 R1 PT PT-V-605/02 303A 593V2P081 NRI UT RI/ GEOMETRY B9.11 N/A 21201-030-16 UT UT-V-404/06 S93V2C166 593V2U197 RI B-J PIPE TO ELBOW S93V2C167 593V20198 RI PT PT-V-605/02 303A S93V2PO43 NRI UT RI/GE WETRY B9.11 N/A 21201-030-17 UT UT-V-404/06 593V20062 $93V2UGB1 RI B-J ELBOW TO PIPE S93V2C063 593V2UO82 RI J
PT-V-605/02 303A $93V2PO45 NRI UT RI/ GEOMETRY 89.11' N/A 21201-030-19 PT UT UT-V-404/06 593V2C064 593v2UO83 RI B-J VALVE TO PIPE 593V2C065 593V2U0S4 RI PT PT-V-605/02 303A 593v2P067 NRI UT Rt/ GEOMETRY B9.11 N/A 21201-030-20 UT ~ UT-V-404/06 S93V2C090 593V2U109 Rt B-J PIPE TO ELBOW S93V2C091 593V2U110 RI PT PT-V-605/02 303A S93V2P068 NRI UT RI/ GEOMETRY B9.11 N/A 21201-030-21 UT UT-V-404/06 S93V2C092 S93V2U111 RI B-J ELBOW TO PIPE S93v2C093 S93V2U112 RI PT PT-V-605/02 303A S93V29082 NRI UT RI/ GEOMETRY C9.11 N/A 21201-030-22 UT UT-V-404/06 593V2C168 593V2U199 RI B-J PIPE TO ELBOW S93v2C169 S93v20200 RI PT PT-V-605/02 303A S93V2P114 NRI UT RI/ GEOMETRY f,9.11 N/A 21201-030-49 UT UT-V-404/06 326A S93V2C232 593V2U268 NRI B-J P!PE TO SAFE END S93V2C233 S93V2U269 NRI S93v2C234 $93V2U270 RI 593v2C235 S93V2U271 NRI 6-3
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VEGP-2 THIRD MAINTENANCE /RETUELING OUTAGE O
CLASS 1 PIPING EXAMINATIONS AUGMENTED COMPONENT OR EXAM CAL EXAM WELD N0/ EXAM PROCEDURE CALIBRATION SHEET SHEET ASME SECT XI EXAMINATION ITEM N0/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS PT-V-605/02 307A S93V2P051 NRI UT Rl/ GEOMETRY B9.11 Al#87-131 21201-049-1 PT BC TO PIPE UT UT-V-404/06 S93V2C105 593V2U127 Rt B-J 593V2C107 593v2U129 NRI 21201-049-3 PT PT-V-605/02 307A 593V2P062 NI N/A 89.11 Af#87-131 TEE TO PIPE UT UT-V 404/06 593V2C113 593V2U135 NRI B-J S93v2C114 593v2U136 WRX 21201-049-4 PT PT-V-605/02 307A 593V2P063 NI UT RI/ GEOMETRY B9.11 Af#87-131 PIPE TO ELBOW UT UT-V-404/06 $93V2C106 593V20128 RI B-J 593V2C108 593V2U130 RI 21201-049-5 PT PT-V-605/02 307A S93v2P064 NI UT RI/ GEOMETRY B9.11 Al#87-131 UT UT-V-404/06 593V2C075 593V2UO94 RI ,
B-J ELBOW TO PIPE S93V2C077 593V2UO96 NRI 21201-049-7 PT PT-V-605/02 307A S93V29052 NI N/A B9.11 At#87-131 VALVE TO PIPE UT UT-V-404/06 593V2C076 593V2UO95 NRI B-J
$93v2C078 593V2UO97 NRI 21201-049-10 PT PT-V-605/02 307A 593V29053 NI UT RI/ GEOMETRY B9.11 Al#87-131 PIPE TO ELBOW UT UT-V-404/06 593V2C073 593V2UO92 Rt B-J 593v2C074 593V2UO93 NRI 21201-051-6 PT PT-V-605/02 N/A N/A $93V2P069 NRI N/A B9.40 N/A B-J PIPE TO VALVE 21201-053-1 PT PT-V-605/02 316A $93V2P108 NRI UT RI/ GEOMETRY 89.11 N/A UT UT-V-404/06 S93V2C225 S93v2U261 NRI B-J BC TO PIPE 593V20227 593v2U263 RI PT PT-V-605/02 316A $93V2PO65 NI N/A 89.11 N/A 21201-053-3 UT UT-V-404/06 593v2C226 $93V2U262 NRI B-J PIPE TO PIPE
$93V2C228 S93v20264 NRI 6-4
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O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE O
CLASS 1 PIPING EXAMINATIONS l
AUGMENTED COMPONENT OR EXAM CAL EXAM WELD N0/ EXAM PROCEDURE CALIBRATION SHEET SHEET K.SME SECT XI EXAMINATION ITEM N0/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS PT-V-605/02 316A 593V2P101 NRI UT RI/ GEOMETRY B9.11 N/A 21201-053-3A PT PIPE TO PIPE UT UT-V-404/06 593v2C196 S93V2U231 RI B-J 593V2C197 593V20232 RI 21201-053-4 PT PT-V-605/02 316A S93V2P060 NRI UT RI/CEOMETRY B9.11 N/A PIPE TO REDUCER UT UT-V-404/06 S93V2C129 593v2U152 RI B-J s93v2C130 593v2U153 RI i
21201-053-5 PT PT-V-605/02 315A $93V2P061 NRI UT RI/ SUBSURFACE PLANAR B9.11 N/A REDUCER TO PIPE UT UT-V-404/06 S93v2C131 593V2U154 RI FLAWS. SEE INF 193V2020.
B-J S93V2C132 593v2U155 RI ACCEPTABLE AS 15.
N/A 21201-056-6 PT PT-V-605/02 304A 593V2P075 NRI UT RI/ GEOMETRY 89.11 ELBOW TO FLANGE UT UT-V-404/06 S93V2C152 593V2U175 RI B-J S93V2C156 S93V20179 NRI 21201-056-6 FB VT-1 VT-V-715/01 N/A N/A $93V2V641 SAT EXAMINED WHILE B7.50 N/A DISASSEMBLED.
B-G-2. FLANGE BOLT ASSEMBLY 21201-057-8 PT PT-V-605/02 304A $93V2P076 NRI N/A B9.11 N/A UT UT-V-404/06 s93V2C153 593V2U176 NRI B-J ELBOW TO FLANGE S93V2C157 593V2U180 NRI VT-1 VT V-715/01 N/A N/A S93V2V640 SAT EXAMINED WHILE B7.50 N/A 21201-057-8 FB DISASSEMBLED.
B-G-2 FLANGE BOLT 21201-059-12 PT PT-V-605/02 304A s93V2P080 NR1 PT EXAM LIMITED /RR-20.
B9.11 N/A UT UT-V-404/06 593v2C154 593v2U177 NRI UT Rl/ GEOMETRY.
B-J TEE TO PIPE 593V2C158 593V2U181 RI 21201-059-13 PT PT-V-605/02 304A s93V2P079 NRI UT Rl/ GEOMETRY B9.11- N/A P!PE TO REDUCER UT UT-V-404/06 593V2C155 593V2U178 Rt B-J 593V2C159 593V2U182 RI VT-1 VT-V-715/01 N/A N/A S93V2V609 SAT EXAMINED IN PLACE.
B7.70 N/A 21201HV8702B B-G-2" VALVE BOLTING 6-5
O O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE O
CLASS 1 PIPING EXAMINATIONS COMPONENT OR EXAM CAL EXAM AUGMENTED WELD N0/ EXAM FROCEDURE CALIBRATION SHEET SHEET ASME SECT XI EXAMINATION BLOCKS NO.(S) NO.(S) RESULTS REMARKS ITEM N0/ CAT. REQUIREMENT DESCRIPfl04 METHOD NO./REV.
VT-1 VT-V-715/01 N/A N/A $93V2V643 SAT EXAMINED IN PLACE.
B7.70 N/A 21201PSV8010C B-G-2 VALVE BOLT [NG VT-1 VT-V-715/01 N/A N/A S93V2V610 SAT EXAMINED IN PLACE.
B7.70 N/A 21201PV04558 B-G-2 VALVE BOLTING PT-V-605/02 305A 593V2P078 NRI UT RI/ GEOMETRY 89.11 Al#87-131 21204-021-1 PT VALVE TO PIPE UT UT-V-404/06 593V2C147 593v20170 RI B-J S93V2C148 S93V20171 RI PT PT-V-605/02 305A S93V2P028 NI UT RI/ GEOMETRY B9.11 At#87-131 21204-021-4 UT UT-V-404/06 $93V2C049 S93V2UO68 RI B-J EtBOW YO PIPE S93V2C051 $93V2UO70 Rt PT-V-605/02 304A S93V2P038 NRI UT Rl/ GEOMETRY 89.11 Al#87-131 21204-021-11 PT REDUCER TO P!PE UT UT-V-404/06 $93V2C053 593v2UO72 R1 B-J 593V2C057 S93v2UO76 RI PT PT-V-605/02 304A S93V2PO40 NRI UT Rt/ GEOMETRY 89.11 Al#87-131 21204-021-17 UT UT-V-404/06 593V2C054 593V2OO73 Rt B-J VALVE TO PIPE S93V2C058 S93V2UO77 RI PT-V-605/02 304A 593V2P039 NRI UT Rt/ GEOMETRY B9.11 At#87-131 21204-021-18 PT UT UT-V-404/06 S93V2C055 S93V2UO74 RI B-J PIPE TO ELBOW S93V2C059 593V2UO78 RI 21204-021-19 PT PT-V-605/02 304A $93v2P106 NRI UT Rl/ GEOMETRY 89.11 Al#87-131 UT UT-V-404/06 S93V2C219 S93V2U255 RI B-J ELBOW TO PIPE S93V2C221 $93V20257 NRI PT PT-V-605/02 304A S93V2P077 NRI UT RI/ GEOMETRY B9.11 AI#87-131 21204-021-20 UT UT-V-404/06 593V2C220 S93V20256 RI B-J PIPE TO ELBOW S93V2C222 593V2U258 RI 6-6
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VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE CLASS 1 PIPING EXAMINAil0NS AUGMENTED COMPONENT OR EXAM CAL EXAM EXAM PROCEDURE CAllBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD NO/
METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS ITD1 N0/ CAT. REQUIREMENT DESCRIPTION 21204-021-26 PT PT-V-605/02 304A $93V2PO41 NI UT RI/CEOMETRY 89.11 Al#87-131 PIPE TO REDUCER UT UT-V-404/06 S93V2C056 593V2OO75 RI B-J S93v2C060 S93V2UO79 NRI 21204-021-26A PT PT-V-605/02 307A S93V2PO42 NI UT RI/GEOMETRT B9.11 Al#87-131 REDUCER TO PIPE UT UT-V-404/06 S93V2C115 593V2U137 Rt B-J S93V2C116 S93V2U138 R1 21204-076-35 PT PT-V-605/02 N/A N/A S93v2P005 NRI N/A 89.21 N/A B-J PIPE TO ELB0u 21204-076-36 PT PT-V-605/02 N/A N/A S93V2P009 NRI N/A 09.21 N/A B-J ELBOW TO PIPE 21204-077-98 PT PT-V-605/02 N/A N/A S93V2P006 NRI N/A B9.21 N/A B-J ELBOW TO PIPE 21204-077-10 PT PT-V-605/02 N/A N/A 593V2P007 NRI N/A 89.21 N/A B-J PIPE TO FLANGE VT-1 VT-V-715/01 N/A N/A S93v2V611 SAT EXAMINED IN PLACE.
B7.50 N/A 21204-077-10 FB D-G-2 FLANGE BOLT ASSEMBLY 21204-077-11 PT PT-V-605/02 N/A N/A S93V2P008 NRI N/A 09.21 N/A B-J FLANGE TO PIPE 21204-079-1 PT PT-V-605/02 N/A N/A $93V2P096 NRI N/A 09.21 N/A B-J REDUCER TO PIPE 21204-127-18 PT PT-V-605/02 306A S93v2PO47 NRI N/A B9.11 Al #87-131 UT UT-V-404/06 S93V2C097 593V2U119 NRI B-J Al#18270 ELBOW TO PIPE S93V2C101 593V20123 NR]
PT-V-605/02 306A S93V2PO48 NRI UT Rl/ GEOMETRY 89.11 Al#87-131 21204-127-19 PT UT-V-404/06 S93V2C098 593v20120 RI UT SCANS LIMITED /RR-26.
B-J Al#18270 PIPE TO VALVE UT S93v2C102 S93v20124 RI 6-7
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O O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE O
CLASS 1 PIPING EXAMINATIONS EXAM CAL EXAM AUGMENTED COMPONENT OR EXAM PROCEDURE CALIBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD N0/
BLOCKS NO.(S) NO.(S) RESULTS REMARKS ITEM N0/ CAT. REQUIREMENT DESCRIPil0N METHOD NO./REV.
306A S93V2PO49 NRI UT RI/GEOMETRT 89.11' Al#87-131 21204-127-20 PT PT-V-605/02 U T -V-404 /06 593V2C099 593V20121 RI UT SCANS LIMITED /RR-26.
B-J Al#18270 VALV TO PIPE UT S93V2C103 593V20125 NRI PT PT-V-605/02 306A S93V2P050 NRI UT R!/GEOMETRT B9.11 Al#87-131 21204-177-22 UT UT-V-404/06 593v2C100 S93V2U122 RI B-J Al#18270 ELBOW 10 BC S93V2C104 593V20126 NR!
PT-V-605/02 N/A N/A S93V2P012 NI N/A B9.21 N/A 21204-246-25 PT B-J PIPE TO ELBOW PT PT-V-605/02 N/A N/A S93V2P013 NI N/A 89.21 N/A 212ua-246-26 B-J ELBOW TO 'IPE PT-V-605/02 N/A N/A $93V2P014 NI N/A 89.21 N/A 21204-246-27 PT B-J PIPE TO ELBOW PT-V-605/02 N/A N/A S93V2P015 NI N/A B9.21 N/A 21204-246-28 PT B-J ELBOW TO PIPE PT PT-V-605/02 N/A N/A S93V2P109 NRI N/A B9.40 N/A 21204-246-32 B-J VALVE TO PIPE PT PT-V-605/02 N/A N/A 593V2P110 NRI N/A 89.21 N/A 21204-246-33 B-J PIPE TO ELBOW PT PT-V-605/02 N/A N/A 593V2P111 NRI N/A B9.21 N/A 21204-246-34 B-J ELBOW TO PIPE PT-V-605/02 N/A N/A S93V2P112 NRI N/A 09.21 N/A 21204-246-36 PT B-J REDUCER TO BC VT-1 VT-V-715/01 N/A N/A $93V2V633 SAT EXAMINED IN PLACE.
B7.70 N/A 21204HVB808B B-G-2 VALVE BOLTING l
6-8
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VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE CLASS 1 PIPING EXAMINATIONS i
COMPONENT OR EXAM CAL EXAM AUGMENTED EXAM PROCEDURE CALIBRATION SHEET SHEET ASME SECT XI EXAMINAT!ON WELD NO/
NO.(S) NO.(S) RESULTS REMARKS ITEM N0/ CAT. REOUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS VT-1 VT-V-715/01 N/A N/A $93V2V612 SAT EXAMINED IN PLACE.
B7.70 N/A 21204U4025 !
B-G-2 VALVE BOLTING VT-3 PER MWO N/A N/A N/A SAT RR-27/ EXAMINED WHILE B12.50 N/A 21204U6079 29302838 DISASSEMBLED B-M-2 VALVE INTERNAL SURFACES VT-3 PER MWO N/A N/A N/A SAT RR-27/ EXAMINED WHILE B12.50 N/A 21204U6080 29303083 DISASSEMBLED B-M-2 VALVE INTERNAL SURFACES r
VT-1 VT-V-715/01 N/A N/A S93V2V630 SAT EXAMINED IN PLACE.
87.70 N/A 2120406082 B-G-2 VALVE BOLTING VT-3 PER MWO N/A N/A N/A SAT RR-27/ EXAMINED WHILE B12.50 N/A 21204U6083 29301045 DISASSEMBLED B-M-2 VALVE INTERNAL i
SURFACES I
VT-1 VT-V-715/01 N/A N/A 593V2V631 SAT EXAMINED IN PLACE.
B7.70 N/A 21204U6086 B-G-2 VALVE BOLTING 4
1 PT PT-V-605/02 N/A N/A $93V2P022 E N/A B9.21 N/A 21208-007-1
! B-J VALVE TO PIPE PT PT-V-605/02 N/A N/A S93V2P023 NI N/A B9.21 N/A 21208-007-2 i B-J PIPE TO VALVE PT PT-V-605/02 N/A N/A $93V29024 NI N/A 09.21 N/A 21208-007-3 B-J VALVE TO PIPE PT-V-605/02 N/A N/A $93V2P025 NI N/A E9.21 N/A 21208-007-6 PT
! B-J PIPE TO BC PT-V-605/02 N/A N/A S93V2P021 NI N/A 89.40 N/A 21208-012-2 PT l
B-J PIPE TO VALVE l 6-9 ,
4
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VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE O
CLASS 1 PIPING EXAMINATIONS AUGMENTFD COMPONENT OR EXAM CAL EXAM WELD N0/ EXAM PROCEDURE CALIBRATION SHEET SHEET ASME SECT XI EXAMIWiTION ITEM N0/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS 21208-012-3 PT PT-V-605/02 N/A N/A $93V2P020 NI N/A 89.40 N/A B-J VALVE TO PIPE 21208-012-4 PT PT-V-605/02 N/A N/A S93V2P019 NI N/A 89.21 N/A B-J PIPE TO ELBOW 21208-012-5 PT PT-V-605/02 N/A N/A $93V2P018 NRI N/A 89.21 N/A B-J ELBOW TO PIPE 21208-012-6 PT PT-V-605/02 N/A N/A S93V2P017 NRI N/A 89.40 N/A B-J PIPE TO VALVE 21208-012-7 PT PT-V-605/02 N/A N/A $93V2P016 NRI N/A B9.40 N/A B-J VALVE TO PIPE 21208-012-8 PT PT-V-605/02 N/A N/A S93V2P055 NI N/A 89.40 N/A B-J PIPE TO ELBOW 21208-012-9 PT PT-V-605/02 WA N/A $93V2P056 NI N/A B9.40 N/A B-J ELBOW TO PIPE 21208-012-10 PT PT-V-605/02 N/A N/A 593V2P057 NI N/A 89.21 N/A B-J PIPE TO ELBOW 21208-012-11 PT PT-V-605/02 N/A N/A S93V2P058 NI N/A 89.21 N/A B-J ELBOW TO PIPE 21208-012-12 PT PT-V-605/02 N/A N/A S93V29059 NI N/A 89.21 N/A B-J PIPE TO BC 21208-043-7 PT PT-V-605/02 N/A N/A S93v2P099 NRI N/A 09.21 N/A B-J PIPE TO ELBOW 21208-043-8 PT PT-V-605/02 N/A N/A S93v2P098 NR1 N/A 89.21 N/A B-J ELBOW TO PIPE 6-10
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VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE
~
CLASS 1 PIPING EXAMINATIONS COMPOWENT OR EXAM CAL EXAM AUGMENYED EXAM PROCEDURE CAllBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD NO/
NO (S) NO.(S) RESULTS REMARKS ITEN NO/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS PT-V-605/02 N/A N/A S93V2P097 NRI N/A B9.21 N/A 21208-043-9 PT B-J PIPE TO ELBOW PT-V-605/02 N/A N/A S93V2P054 NI N/A B9.21 N/A 21208-047-18 PT B-J ,
PIPE TO FLANGE VT-1 VT-V-715/01 N/A N/A $93V2V607 SAT EXAMINED IN PLACE.
BT.60 N/A 21208-047-18 FB B-G-2 FLANGE BOLT ASSEMBLY VT-1 VT-V-715/01 N/A N/A S93V2V634 SAT EXAMINED IN PLACE.
B7.70 N/A 21208U6038 B-G-2 VALVE BOLTING 6-11
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VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE CLASS 2 EQUIPMENT EXAMINATIONS
-i COMPONENT OR EXAM CAL EXAM j AUGMENTED EXAM PROCEDURE CAllBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD N0/
NO.(S) NO.(S) RESULTS PEMARKS REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS ITEM N0/ CAT. >
UT UT-V-411/05 409A 593V2C160 S93v2U183 NRt UT Rl/ LAM!NAR AND SUB-C1.10 At#852515 21201-B6-004-WO3
$93V2C161 S93V20184 RI SURFACE PLANAR. SEE INF C-A IEN 85-65 UPPER SHELL/TRANS S93V2C162 S93V2U185 RI 193V2n21. ACCEPTABLE AS 593V2C163 S93V2U188 R1 15. UT SCAMS LIMITED / CODE 593V2C172 S93V2U203 RI CASE W-460 UTILIZED.
UT-V-411/05 409A 593V2C094 593V2U116 NRI UT RI/ GEOMETRY.
N/A 21201-86-004-WO7 UT C1.30
$93V2C095 593v2U117 RI UT SCANS LIMITED /RR-29.
C-A LOWER SHELL/ TUBE PL S93V2C096 S93V20118 R1 MT MT-V-505/03 N/A N/A $93V2M050 NRI N/A C3.10 N/A 21201-86-004-W25 t
< C-C TRUNNION TO SNELL MT MT-V-505/03 409A S93Y2M030 NRI UT RI/SUB-SURFACE PLANAR C2.21 N/A 21201-B6-004-W26 UT UT-V-411/05 593V2C149 593V2U172 NRI FLAWS. SEE INF 193V2019.
C-8 N0ZZLE TO SHELL 593/2C150 S93v20173 RI ACCEPTABLE AS 15.
S93v2C151 593V2U174 Rt UT SCANS LIMITED.
UT UT-V-470/00 SK-145 593V2C229 593V2U265 NRI N/A
- IN 91-05 21204-V6-002-1 THRU 7 SK-146 593V2C230 593V2U266 NRI
- N0ZZLE TO ACCUMULATOR 312A S93V2C231 593V2U267 NRI i UT UT-V-404/06 412A 593V2C017 593V2UO34 Rt UT RI/SUB-SURFACE PLANAR C1.10 N/A 21205-E6-002-WO1 S93V2C020 593V2UO38 Rt FLAWS. SEE INF 193V2005.
C-A FLANGE TO TUBE SIDE 593V2UO39 N/A ACCEPTABLE AS IS.
SHELL WELD UT UT-V-404/06 412A 593v2C018 $93V2UO35 Rt UT RI/SUB-SURFACE PLANAR C1.20 N/A 21205-E6-002-WO2 S93V2C019 593v2UO36 Rt FLAWS. SEE INF 193V2005.
C-A TUBE SIDE SHELL TO S93V2UO37 N/A ACCEPTABLE AS IS.
HEAD WELD PT PT-V-605/02 N/A N/A S93V2P001 NRI N/A C3.30 N/A 21205-P6-001-WO2 C-C INTEGRAL WELD UT UT-V-404/06 417A $93V2CO31 593V2OO50 NRI N/A C1.10 N/A 21208-E6-001-WO4 593v2CO35 S93v2OO54 NRI C-A COLLAR TO MAIN SHELL 7-1
_ _ _ _ _ . _ _ _ _ _ __ -. - _ . _ __ _ i
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O O O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE CLASS 2 PIPING EXAMINATIONS COMPONENT OR EXAM CAL EXAM AUGMENTED EXAM PROCEDURE CAllBRATION SHEET SHEET ASME SECT XI EXAMINATION WELD N0/
NO.(S) NO.(S) RESULTS REMA0KS ITEM N0/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS PT-V-605/02 414A 593v2P102 NRI SUP EXAM. UT RI/ GEOMETRY.
- ISI-P-014 21202-188-4 PT UT UT-V-404/06 593v2C214 593V20250 RI UT SCANS LIMITED /RR-36.
- PAR 1.10.3 FLUED HEAD TO PIPE UT-V-404/06 414A $93v2C215 S93V2U251 Rt SUP EXAM. UT RI/ GEOMETRY.
ISI-P-014 21202-192-40 UT
- PAR 1.10.3 PIPE TO ELBOW PT PT-V-605/02 414A 593V2P103 NRI SUP EXAM. UT R!/ GEOMETRY.
ISI-P-014 21202-192-42 UT UT-V-404/06 593V2C216 593V2U252 RI UT SCANS LIMITED /RR 36.
- PAR 1.10.3 PIPE TO FLUED HEAD PT PT-V-605/02 414A 593V2P104 NRI SUP EXAM. UT RI/ GEOMETRY.
!$1-P-014 21202-196-4 UT UT-V-404/06 S93V2C217 S93v2U253 RI UT SCANS LIMITED /RR-36.
PAR 1.10.3 FLUED HEAD TO PIPE PT-V-605/02 414A S93v2P105 NRI SUP EXAM. UT RI/CEOMETRY.
- ISI-P-014 21202-196-6 PT UT UT-V-404/06 593V2C218 S93V2U254 RI UT SCANS LIMITED /RR-36.
- PAR 1.10.3 ELBOW TO VALVE UT UT-V-404/06 414A S93V2C003 S93V2U003 RI SUP EXAM. UT RI/ GEOMETRY.
ISI-P-014 21202-212-33 593V20006 T&C PAR 1.10.3 ELBOW TO PIPE PT PT-V-605/02 414A S93V2P002 NI SUP EXAM. UT RI/ GEOMETRY.
ISI-P-014 21202-212-34 UT UT-V-404/06 593V2C004 593v20004 RI UT SCANS LIMITED /RR-36.
PAR 1.10.3 PIPE TO FLUED HEAD S93V2U007 T&C UT-V-404/06 346A S93V2C021 S93v2UO40 NRI SUP EXAM ISI-P-014 21204-016-20 UT PAR 1.10.3 PIPE TO ELBOW UT-V-404/06 346A S93V2C022 $93V2UO41 RI SUP EXAM. UT RI/ GEOMETRY.
ISI-P-014 21204-016-21 UT l
PAR 1.10.3 ELBOW TO PIPE 346A S93V2CO23 593V2UO42 NRI SUP EXAM ISI-P-014 21204-016-22 UT UT-V-404/06 PAR 1.10.3 PIPE TO ELBOW l
8-1
_ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ __ -_m
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ITEM N0/ CAT. REQUIREMENT UT-V-404/06 346A S93V2C024 S93V2UO43 RI SUP EXAM. UT RI/ GEOMETRY.
ISI-P-014 21204-016-23 UT
- PAR 1.10.3 ELBCW TO PIPE UT-V-404/06 346A S93V2C025 593V2UO44 NRI SUP EXAM
- ISI-P-014 21204-016-25 UT
- PAR 1.10.3 PIPE TO ELBOW UT-V-404/06 346A S93v2CO26 S93V2UO45 RI SUP EXAM. UT RI/ GEOMETRY.
ISt-P-014 21204-016-26 UT
- PAR 1.10.3 ELBOW TO PIPE UT-V-404/06 346A S93V2C027 S93V2UO46 NRI SUP EXAM ISI-P-014 21204-016-27 UT
- PAR 1.10.3 PIPE TO ELBOW UT-V-404/06 346A S93v20028 593v2UO47 NRI SUP EXAM ISI-P-014 21204-016-28 UT PAR 1.10.3 ELBOW TO PIPE UT-V-404/06 346A S93v2C029 S93V2UO48 RI SUP EXAM. UT RI/ GEOMETRY.
ISI-P-014 21204-016-29 UT PAR 1.10.3 P!PE TO ELBOW UT-V-404/06 346A 593V2CO30 $93v2UO49 NRI SUP EXAM ISI-P-014 21204-016-30 UT PAR 1.10.3 ELBOW TO PIPE 21204-039-35 PT PT-V-605/02 304A S93V2P027 R1 PT RI/ LINEAR INDICATION.
C5.21 Al#87-131 UT UT-V-404/06 $93V2CO39 593V2OO58 RI SEE INF 193V2012.
C-F PIPE TO ELBOW 593V2C041 S93V2UO60 RI ACCEPTABLE AS IS.
UT RI/ GEOMETRY.
PT PT-V-605/02 304A S93V2P026 NRI UT RI/ GEOMETRY C5.21 At#87-131 21204-039-36 UT UT-V-404/06 $93V2C040 S93v2OO59 RI C-F ELBOW TO P!PE S93v20042 593V2UO61 Rt 8-2
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METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS ITEM N0/ CAT. REQUIREMENT DESCRIPTION PT-V-605/02 305A 593V2P030 NI UT RI/ GEOMETRY C5.21 Al#87-131 21204-041-9 PT UT UT-V-404/06 593v2C050 593V2UO69 RI C-F TEE TO PIPE S93V2C052 $93V2UO71 RI 21204-041-51 PT PT-V-605/02 N/A N/A $93V2P095 NRI N/A C3.20 N/A C-C SUPPORT H001 UT-V-404/06 334A $93V2C001 593V2U001 RI SUP EXAM. UT RI/ GEOMETRY.
ISI-P-014 21204-063-42 UT S93V2U005 T&C
- PAR 1.10.3 PIPE TO elbow UT-V-404/06 334A S93V2C002 S93V20002 NRI SUP EXAM 1SI-P-014 21204-063-43 UT
- PAR 1.10.3 ELBOW TO PIPE 21204-121-1 PT PT-V-605/02 N/A N/A $93V2P107 NRI N/A C5.11 N/A CF SAFE END TO PIPE PT-V-605/02 307A S93V2P003 NRI UT itI/ GEOMETRY C5.21 Al#87-131 21204-201-8 PT PIPE TO REDUCER UT UT-V-404/06 S93V2C005 593V2UO12 RI C-F
$93V2C006 593V2UO14 NRI S93V2UO13 T&C 21204-201-11 PT PT-V-605/02 305A $93V2P004 NRI UT RI/ C @ETRY C5.21 Al#87-131 UT UT-V-404/06 S93V2C007 593V2UO15 RI C-F ELBOW TO PIPE 593V2C008 $93V2UO19 RI
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DESCRIPTION METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS ITEM N0/ CAT. REQUIREMENT PT-V-605/02 340A $93V2P011 NRI SUP EXAM. UT Rl/ GEOMETRY.
- ISI-P-014 21206-004-4 PT UT UT-V-404/06 $93V20009 593V2UO22 Rt UT SCANS LIMITED /RR-36.
- PAR 1.10.3 VALVE TO REDUCER 593v20023 T&C Al#87-131 UT-V-404/06 341A S93v2C010 $93V2OO24 RI SUP EXAM. UT RI/ GEOMETRY.
- ISI-P-014 21206-004-5 UT 593v2OO25 TEC
- PAR 1.10.3 REDUCER TO TEE Al#87-131 UT-V-404/06 341A 593V2C011 593V2UO26 NRI SUP EXAM
- ISI-P-014 21206-004-5 LD UT
- PAR 1.10.3 LONGITUDINAL AI#87-131 UT-V-404/06 341A S93V2C012 593V2UO27 NRI SUP EXAM
- ISI-P-014 21206-004-5 LDIR UT
- PAR 1.10.3 LONGITUDINAL Al#87-131 PT-V-605/02 341A 593V2P115 NRI SUP EXAM. UT RI/ GEOMETRY.
- ISI-P-014 21206-004-11 PT UT UT-V-404/06 593v20013 593V2OO28 RI UT SCANS LIMITED /RR-36.
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- ISI-P-014 21206-004-11 LD UT
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ISI-P-014 21206-004-12 UT UT-V-404/06 593V2C016 593v2UO32 RI UT SCANS LIMITED /RR-36.
- PAR 1.10.3 REDUCER TO FLANGE S93V2UO33 T&C UT UT-V-404/06 340A $93V2C015 593V2UO31 NRI SUP EXAM
- ISI-P-014 21206-004-12 LU
- PAR 1.10.3 LONGITUDINAL 8-4
O O O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE CLASS 2 PIPING EXAMINATIONS AUOMENTED COMPONENT OR EXAM CAL EXAM WELD N0/ EXAM PROCEDURE CALIBRATION SHEET SHEET ASME SECT XI EXAMINATION ITEM NO/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REV. BLOCKS NO.(S) NO.(S) RESULTS REMARKS C5.11 ISI-P-014 21208-139-8 PT PT-V-605/02 337A $93V2P092 NRI UT SUP EXAM. UT Rl/
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$93V2C211 S93V2U247 RI ACCEPTABLE AS IS.
21301-004-10 MT MT-V-505/03 314A S93v2M052 NRI UT SCANS LIMITED /RR-34.
C5.21 TECH SPEC UT-V-404/06 S93v2C180 593v2U211 NRI UT AI/ GEOMETRY.
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NO.(S) NO.(S) RESULTS REMARKS ITEM NO/ CAT. REQUIREMENT DESCRIPTION METHOD NO./REv. BLOCKS MT MT-V-505/03 314A S93v2M039 NRI UT RI/ GEOMETRY C5.21 TECH SPEC 21301-004-11 593V2C181 S93v20212 NRI C-F 4.4.10.3 YALVE TO PIPE UT UT-V-404/06 S93V2C184 S93V20215 Rt MT-V-505/03 N/A N/A $93v2M044 NRI N/A C3.20 N/A 21301-004-12 MT C-C SUPPORT N002 MT-V-505/03 314A S93v2M043 NRI UT SCANS LIMITED /RR-34.
C5.21 TECH SPEC 21301-004-13 MT UT-V-404/06 S93v2C182 593v20213 NRI UT Rt/ GEOMETRY C-F 4.4.10.3 PIPE TO VALVE UT S93v2C185 593v2U216 R1 MT MT-V-505/03 313A S93v2M042 NRI UT RI/ SUBSURFACE PLANAR -
C5.21 TECH SPEC 21301-004-14 UT UT-V-404/06 S93v2C175 S93v2U206 Rt FLAWS. SEE INF 193v2022.
C-F 4.4.10.3 VALVE TO PIPE S93v2C177 593v2U208 Rt ACCEPTABLE AS IS.
MT-V-505/03 313A S93v2M041 NRI UT RI/ GEOMETRY C5.21 TECH SPEC 21301-004-15 MT UT UT-V-404/06 S93v2C176 593v2U207 RI C-F 4.4.10.3 PIPE TO P!PE FORGING MT MT-V-505/03 310A S93v2M054 NRI UT RI/ GEOMETRY C5.21 - N/A 21301-016-1 UT UT-v-404/06 593v2C208 593v2U244 NRI C-F BC TO P!PE S93v2C209 593v2U245 R1 MT MT-V-505/03 N/A N/A S93v2M053 NRI N/A C5.11 N/A 21301-016-3 C-F REDUCER TO PIPE MT-V-505/03 309A $93v2M015 N! N/A C5.21 At#1739 21302-107 MT.
UT UT-V-404/06 593V2C123 593v2U145 NRI -
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$93v2C069 S93v2UO88 RI MT MT-v-505/03 311A $93v2M005 NI UT Rl/ GEOMETRY C5.21 TECH SPEC 21305-058-6 UT UT-V-404/06 593v2C044 593v2UO63 NRI C-F 4.4.10.3 PIPE TO VALVE S93v20047 593v2UO66 R1 MT MT-V-505/03 311A 593v2N006 NI UT Rl/ GEOMETRY C5.21 TLCH SPEC 21305-058-7 UT UT-v-404/06 593v20045 593v2UO64 NRI C-F 4.4.10.3 VALVE TO PIPE S93v2C048 $93v2OO67 RI MT-v-505/03 311A 593v2M011 NRI UT Rl/ GEOMETRY C5.21 TECH SPEC 21305-058-8 MT UT-V-404/06 593v2C071 593v2UO90 RI C-F 4.4.10.3 PIPE TO PENETRATION UT MT-v-505/03 N/A N/A S93v2M049 NRI N/A C3.20 N/A 21305-058-14 MT C-C SUPPORT N002 MT MT-v-505/03 311A 593v2M027 NRI N/A C5.21 Al#1739 21305-058-21 UT UT-V-404/06 593v2C133 593v2U156 NRI C-F PIPE TO ELBOW MT MT-V-505/03 311A S93v?M028 NRI N/A C5.21 Al#1739 21305-058-22 UT UT-v-404/06 593v2C134 593v2U157 NRI C-F ELBOW TO PIPE MT MT-V-505/03 318A S93v2M029 NRI UT Rl/ GEOMETRY C5.21 Al#1739 21305-058-23 UT UT-V-404/06 593v2C135 593v?U158 RI C-F PIPE TO N0ZZLE S93v2C136 593v20159 RI MT MT-V-505/03 311A S93v2M020 NRI N/A C5.21 Al#1739 21305-060-21 UT UT-V-404/% 593v2C137 S93v2U160 NRI C-F PIPE TO ELBOW 8-9
\
VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE CLASS 2 PIPING EXAMINATIONS AUGMENTED COMPONENT CR EXAM CAL EXAM ASME SECT XI EXAMINATION WELD N0/ EXAM PROCEDURE CALIBRATION SHEET SHEET ITEM N0/ CAT. REQUIRFMENT DESCRIPTION METHOD NO./REV. STOCKS NO.(S) NO.(S) RESULTS REMARKS C5.21 Al#1739 21305-060-22 MT MT-V-505/03 311A S93v2M021 NRI N/A C-F ELBOW TO PIPE UT UT-V-404/06 $93v2C138 S93V2U161 NRI C5.21 Al#1739 21305-060-23 MT MT-V-505/03 318A S93v2M022 NRI UT Rl/ GEOMETRY C-F PIPE TO N0ZZLE UT UT-V-404/06 $93v2C139 S93V2U162 NRI S93V2C140 $93v2U163 RI C5.21 Al#1739 21305-062-24 MT MT-V-505/03 311A S93v2M045 NRI N/A C-F PIPE TO ELBOW UT UT-V-404/06 593V2C178 S93Y2U209 NRI C5.21 Al#1739 21305-062-25 MT MT-V-505/03 311A S93Y2M046 NRI UT RI/ GEOMETRY C-F ELBOW TO PIPE UT UT-V-404/06 S93v2C179 S93v2U210 RI C5.21 At #1739 21305-062-26 MT MT-V-505/03 318A S93V2M023 NRI UT Rl/ GEOMETRY C-F PIPE TO N0ZZLE UT UT-V-404/06 S93V2C141 S93V2U164 NRI
, S93V2C142 S93v2U165 RI 4
l C5.21 Al#1739 21305-064-22 -MT MT-V-505/03 311A S93V2M024 NRI N/A C-F PIPE TO ELBOW UT UT-V-404/06 593v2C143 593V2U166 NRI C5.21 Al#1739 21305-064-23 MT MT-V-505/03 311A S93V2M025 NRI N/A C-F ELBOW TO PIPE UT UT-V-404/06 593v2C144 593v20167 NRI
- C5.21 At#1739 '21305-064-24 MT MT-V-505/03 318A S93V2M026 NRI UT RI/ GEOMETRY l C-F PIPE TO NOZZLE UT UT-V-404/06 S93V2C145 $93V2U168 NRI i 593V2C146 S93V2U169 RI i
! C5.21 N/A 21305-156-1 MT MT-V-505/03 309A $93v2M048 NI UT RI/ GEOMETRY C-F BC TO PIPE UT UT-V-404/06 S93V2C192 S93V2U227 NRI l
$93V2C195 S93V2U230 RI i
i i
8-10 l
i
-- -- . . ~ - - . . . . _ _ _ - . _ _ _ -.. . _ _ . .
O ASME Sect. Support Part Part Exam Data ISI Class Ntrter Descrintinn Examined Method Sheet No. Results Remarks XI Cat.
See Note See Note See Note See Note See Note See Note See Note See Note See Note B C D E F G H I A
NOTES:
A. The ASME Section XI category designation for the equipment support is listed in this colum. In addition, ASME Section XI Class 3 examinations required by Table IWD-2500-1 for integral attachments are also indicated by examination category.
B. The ASME Section XI class no., e.g., 1, 2, or 3, for the system on which the equipmant suoport being examined is listed in this colunn.
C. The equipment support nunber is listed in this colunn.
D. This cotten lists the purpose of the equipment support being examined.
E. This coltsm lists the specific type of the equipment support being examined.
F. This coltsm lists the applicable NDE method used during the examination.
G. This coltsm references the examination data sheet (s) which serve to doctsnont the examination and lists the examiner, any pertinent remarks, etc.
H. The results of the examinations are indicated in this column.
I. The remarks column is used to describe any pertinent features of the examination such as timitations, reportable results, INFS, etc. Refer to INF section in this report for their disposition.
FIGURE 2. EXPLANATION OF EQUIPMENT SUPPORT
SUMMARY
TABLE FORMAT 9-1 l
r
-_____ - - . _ _ - _ _ - _ - - - w - __ _ _ _ _ _ _ . _- . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ m O O VEGD-2 THIRD MAINTENANCE / REFUELING OUTAGE EQUIPMENT SUPPORT EXAMINATICNS SUPPORT PART PART EXAM DATA ASME SECT.
EXAMINED NETH00 SHEET NO. RESULTS REMARKS XI CAT. ISI CLASS NUMBER DESCRIPTION Restraint Tie rod VT-3 593V2V614 SAT N/A F-B 1 21201-P6-002-T01 Tie rod 21201-P6-002-T02 Restraint Tie rod VT-3 593v2V615 SAT N/A F-B 1 Tie rod 21201-P6-002-T03 Restraint Tie rod VT-3 593V2V616 SAT E/A F-8 1 Tie rod Pump support Linear support VT-3 S93V2V617 SAT N/A F-B 1 21201-P6-002-SP01 Linear support Ptrp support Linear support VT-3 593v2V618 SAT N/A F-B 1 21201-P6-002-SP02 Linear support 21201-P6-002-SP03 Punp support Linear support VT-3 $93v2V619 SAT N/A F-B 1 Linear support F-B 3 21203-P4-001-S01 Ptsrp support Linear support VT-3 $93V2V620 SAT N/A I Linear support Linear support VT-3 593V2V622 SAT N/A F-B 3 21203-P4-001-S02 Ptstp support Linear support Ptrp support Linear support VT-3 S93V2V625 SAT N/A F-B 2 21205-P6-002-SP02 Linear support Support skirt Shelt-type supp VT-3 593V2V623 SAT N/A F-A 3 21206-T6-001-501 Shell-type supp Punp support Linear support VT-3 S93v2V624 SAT N/A F-B 3 21213-P6-005-501 Linear support Linear support VT-3 S93V2V621 SAT N/A F-B 3 21213-P6-005-502 Ptstp support Linear support I
9-2
U O
VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE O
EQUIPMENT SUPPORT EXAMINATIONS ASME SECT. SUPPORT PART PART EXAM DATA XI CAT. ISI CLASS NUMBER DESCRIPTION EXAMINED METHOD SHEET NO. RESULTS REMARKS F-B 3 21592-P7-001-501 Ptsp support Linear support VT-3 $93V2V604 SAT N/A Linear support F-B 3 21592-P7-001-s02 Ptsnp support Linear support VT-3 593V2V603 SAT N/A Linear support F-A 3 21592-17-002-501 Tank support Saddle vi-3 $93v2v606 SAT N/A Saddle F-A l 3 21592-T7-002-S02 Tank support Saddle VT-3 $93V2v605 SAT N/A Saddle 9-3
O O ~
ASME Sect. ISI NPS Support Support Exam Exam Description Method Sheet No. Results Remarks XI Cat. Class (In.) No.
See Note See Note See Note See Note See Note See Note See Note See Note See Note A B C D E F G H I NOTES:
A. The ASME Section XI category designation for the piping support is listed in this column. In addition, ASME Section XI Class 3 examinations required by Table IWD-2500-1 for integral attachments are also indicated by examination category.
B. The ASME Section XI class no., e.g., 1, 2, 3, for the system on which the piping support being examined is listed in this column.
C. This coltsnn indicates the nominal pipe size in inches for the piping on which the piping support is being examined.
D. The piping support ntsnber is listed in this coltsnn.
E. This colunn lists the type of piping support which was examined, e.g., rigid strut, variable spring hanger, etc.
F. This coltsnn lists the applicable NDE method used during the examination.
G. This column references the data sheet (s) which serve to document the examination and list the examine , any pertinent remarks, etc.
H. The results of the examinations are indicated in this coltsnn.
I. The remarks colts'n is used to describe any pertinent features of the examination such as limitations, reportable results, INFs, etc. Refer to INF section in this report for their disposition.
FIGURE 3. EXPLANATION OF P! PING SUPPORT
SUMMARY
TABLE FORMAT i
10-1
O O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE O
PIPING SUPPORT EXAMINATIONS ASME SECT. 151 NPS SUPPORT SUPPORT EXAM EXAM DESCRIPTION METHOD SHEET NO. RESULTS REMARKS XI CAT. CLASS (IN.) NUMBER F-B 1 02.00 21201-012-H601 2-D RESTRAINT VT-3 593V2V554 SAT N/A 02.00 21201-012-H603 2-D RESTRAINT VT-3 $93v2V552 SAT N/A F-8 1 02.00 21201-012-H604 VAR SPRING VT-3,4 593V2V569 SAT N/A F-C 1 F-8 1 02.00 21201-012-H605 2-D RESTRAINT VT-3 593v2V551 SAT N/A 02.00 21201-012-H607 1-D RESTRAINT VT-3 593V2V550 SAT N/A F-8 1 F-C 1 02.00 21201-012-H608 MECH SNUBBER VT 3,4 593v2V553 SAT N/A 04.00 21201-030-H630 1-D RESTRAINT VT-3 593V2V549 SAT N/A F-B 1 F-C 1 12.00 21201-049-H016 MECH SNUBBER VT-3,4 593V2V528 SAT N/A F-C 1 12.00 21201-049-H017 MECH SNUBBER VT-3,4 $93v2V527 SAT N/A F-C 1 12.00 21201-049-H020 MECH SNUBBER VT-3,4 $93V2V531 SAT N/A F-C 1 12.00 21201-049-H023 MECH SNUBBER VT-3,4 593v2V530 SAT N/A F-C 1 12.00 21201-049-H025 MECH SNUBBER VT-3,4 593V2V529 SAT N/A F-C 1 14.00 21201-053-H001 MECH SNUBBER VT-3,4 $93V2V524 SAT N/A F-C 1 16.00 21201-053-H005 MECH SNUBBER VT-3,4 593v2V525 SAT N/A F-C 1 16.00 21201-053-H006 MECH SNUBBER VT-3,4 S93V2V568 SAT N/A 3 08.00 21202-005-H007 3-D RESTRAINT VT-3 593V2V597 SAT N/A F-8/D-B 3 08.00 21202-005-H010 2-D RESTRAINT VT-3 $93V2V599 SAT N/A F-B/O-B 3 08.00 21202-005-H017 3-D RESTRAINT VT-3 S93V2V581 SAT N/A F-B/D-B 3 08.00 21202-005-H020 2-D RESTRAINT VT-3 $93V2V582 SAT N/A F-B/D-B 10-2
l
(%
~
VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE PIPING SUPPORT EXAMINATIONS SUPPORT EXAM EXAM ASME SECT. ISI NPS SUPPORT METHOD SHEET NO. RESULTS REMARKS XI CAT. CLASS (IN.) NUMBER DESCRIPTION 3-D RESTRAINT VT-3 S93V2v586 SAT N/A F-B/D-B 3 16.00 21202-006-H022 1-D RESTRAINT VT-3 S93V2V571 SAT N/A F-B/D-B 3 24.00 21202-006-H031 3-D RESTRAINT VT-3 593V2V572 SAT N/A F-8/D-B 3 24.00 21202-006-H032 3-D RESTRAINT VT-3 593V2V573 SAT N/A F-8/D-B 3 24.00 21202-006-H033 UNDERSUPPORT VT-3 S93V2V574 SAT N/A F-8/D-S 3 24.00 21202-006-H034 1-D RESTRAINT VT-3 593V2V575 SAT N/A F-B/D-B 3 24.00 21202-006-H035 UNDERSUPPORT VT-3 $93V2V579 SAT N/A F-B/D-B 3 24.00 21202-006-H036 2-D RESTRAINT VT-3 593V2V578 SAT N/A F-B/D-B 3 24.00 21202-CD6-H038 3-D RESTRAINT VT-3 593V2V577 SAT N/A F-0/D-B 3 24.00 21202-006-H039 2-D RESTRAINT VT-3 $93v2V576 SAT N/A F-B/D-B 3 24.00 21202-006-H041 3-D RESTRAINT VT-3 593v2V600 SAT N/A F-B/D-B 3 08.00 21202-072-H016 3-D RESTRAINT VT-3 S93v2V601 SAT N/A F-B/D-B 3 08.00 21202-072-H026 3-D RESTRAINT VT-3 593V2V602 SAT N/A F-B/D-B 3 08.00 21202-072-H027 21202-072-H034 3-D RESTRAINT VT-3 S93v2V585 SAT N/A F-8/D-B 3 08.00 3-D RESTRAINT VT-3 S93V2V584 SAT N/A F-B/D-B 3 08.00 21202-072-H036 3-D RESTRAINT VT-3 S93V2V583 SAT N/A F-B/D-B 3 08.00 21202-072-H038 2-D RESTRAINT VT-3 $93V2V546 SAT N/A F-8 2 08.00 21202-140-H003 MECH SNUBBER VT-3,4 593V2V548 SAT N/A F-C 2 08.00 21202-140-H009 VT-3,4 $93V2V547 SAT N/A F-C 2 08.00 21202-140-H011 MECH SNUBBER 10-3
.- ._ ._m . _ _ . _ . . _ _ . , _ . _ _
O O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE PIPING SUPPORT EXAMthATIONS ASME SECT. ISI NPS SUPPORT SUPPORT EXAM EXAM METHOD SHEET NO. RESULTS REMARKS XI CAT. CLASS (IN.) NUMBER DESCRIPTION F-C 2 08.00 21202-140-H013 VAR SPRING VT-3,4 S93v2v570 SAT m/A 3 16.00 21202-151-H025 MECH SNUBBER VT-3,4 593V2v502 SAT N/A F-C VT-3,4 S93v2v500 UNSAT FROZEN SPHERICAL BEARING.
F-C 2 08.00 21202-220-H028 MECH SNUBBER S93v2v645 SAT REFERENCE INF 193v2010.
CONDITION CORRECTED. RE-EXAM ACCEPTABLE.
06.00 21204-021-H002 SWAY STRUT VT-3 S93v2v536 SAT N/A F-C 1 F-C 1 06.00 21204-021-H003 MECH SNUBBER VT-3,4 S93v2v535 UNSAT FROZEN SPHERICAL BEARING.
S93v2v646 SAT REFERENCE INF 193v2011.
CONDITION CORRECTED. RE-EXAM ACCEPTABLE.
06.00 21204-021-H004 2-D RESTRAINT VT-3 S93v2v537 SAT N/A FB 1 F-C 1 06.00 21204-021-H005 MECH SNUBBER VT-3,4 593v2v534 SAT N/A
} F-C 1 06.00 21204-021-H006 MECH SNUBBER VT-3,4 593v2v533 SAT N/A F-C 1 06.00 21204-021-H008 SWAY STRUT VT-3 593v2v538 SAT N/A 06.00 21204-021-H009 2-D RESTRAINT VT-3 S93v2v539 SAT N/A F-B 1 06.00 21204-021-H011 SWAT STRUT VT-3 593v2v540 SAT N/A F-C 1 08.00 21204-021-H012 SWAY STRUT vi-3 593v2v541 SAT N/A F-C 1 F-C 1 08.00 21204-021-H013 MECH SNUBBER VT-3,4 593v2v532 SAT N/A 08.00 21204-021-H014 SWAY STRUT VT-3 593v2v542 SAT N/A F-C 1 08.00 21204-021-H015 SWAY STRUT VT-3 $93v2v501 SAT N/A F-C 1 08.00 21204-021-H016 2-D RESTRAINT VT-3 $93v2v543 SAT N/A F-B 1 10-4
. _ _ . ., .,-~. - - . . - _ _ . ~ , . - ~ ~ . . - . _ _ _ - _ . - - _ . . . -
- O VEGP-2 THIRD MAINTENA%CE/ REFUELING OUTAGE PIPING SUPPORT EXAMINATIONS SUPPORT EXAM EXAM ASME SECT. ISI NFS SUPPORT METHOD SHEET NO. RESULTS REMARKS XI CAT. CLASS (IN.) NUMBER DESCRIPTION vi-3,4 593v2v642 SAT N/A F-C 2 08.00 21204-192-H001 MECH SNUBBER SWAY STRUT VT-3 $93v2V634 SAT EXPANDED SCOPE F-C 2 14.00 21205-003-H004 VAR SPRING VT-3,4 593v2v518 SAT N/A F-C 2 14.00 21205-004-H001 SWAY STRUT VT-3 593v2V519 UNSAT MISSING COTTER PIN.
F-C 2 14.00 21205-004-H016 S93v2V644 SAT REFERENCE INF 193v2009.
CONDITION CORRECTED. RE-EXAM ACCEPTABLE.
SWAY STRUT VT-3 S93v2v633 SAT EXPANDED SCOPE F-C 2 14.00 21205-004-H019 SWAY STRUT VT-3 S93v2v635 SAT EXPANDED SCOPE F-C 2 08.00 21205-005-H003 21205-006-H009 SWAY STRUT VT-3 S93v2v517 SAT N/A F-C 2 08.00 3-D RESTPAINT VT-3 S93v2v504 SAT N/A F-8 2 08.00 21205-007-H021 21205-007-H022 2-D RESTRAINT VT-3 593v2V545 SAT N/A F-8 2 08.00 F-C 2 08.00 21205-007-H025 SWAY STRUT '!T-3 593V2V636 SAT EXPANDED SCOPE 2-D RESTRAINT VT-3 593v2v506 SAT N/A F-8 2 08.00 21205-008-H001 21205-008-H002 3-0 RESTRAINT VT-3 S93v2V566 SAT N/A F-B 2 08.00 08.00 21205-008-H003 2-D RESTRAINT VT-3 S93v2V567 SAT N/A F-B 2 1-D RESTRAINT VT-3 S93v2V505 SAT N/A F-8 2 08.00 21205-008-H023 VAR SPRING VT-3,4 S93v2v508 SAT N/A F-C 2 08.00 21205-008-H039 21205-010-H015 2-D RESTRAINT VT-3 $93v2V588 SAT N/A F-8 2 12.00 F-C 2 12.00 21205-010-H016 VAR SPRING VT-3,4 593v2v589 SAT N/A 10-5
V /
VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE PIPING SUPPORT EXAMINATIONS ASME SECT. ISI NPS SUPPORT SUPPORT EXAM EXAM DESCRIPTION METH00 SHEET NO. RESULTS REMARKS XI CAT. CLASS (IN.) NUMBER F-C 2 12.00 21205-010-H605 SWAY STRUT VT-3 S93V2V587 SAT N/A F-C 2 12.00 21206-002-H002 MECH SNUBBER VT-3,4 $93V2V503 SAT N/A 2 12.00 21206-002-H004 VAR SPRING VT-3,4 S93V2V559 $AT N/A F-C F-C 2 12.00 21206-002-H008 SWAY STRUT VT-3 S93V2V560 SAT N/A F-8 2 12.00 21206-002-H009 UNDERSUPPORT VT-3 593V2V561 SAT N/A F-B 2 12.00 21206-002-H011 2-D RESTRAINT VT-3 S93V2V598 SAT N/A F-C 2 12.00 21206-002-H016 SWAY STRUT VT-3 S93V2V562 SAT N/A F-C 2 12.00 21206-002-H019 SWAY STRUT VT-3 593V2V592 SAT N/A 2 12.00 21206-002-H021 SWAY STRUT VT-3 $93V2V563 SAT N/A F-C F-8 2 12.00 21206-002-H022 2-D RESTRAINT VT-3 593V2v593 SAT N/A F-C 2 12.00 21206-004-H005 VAR SPRING VT-3,4 593V2V507 SAT N/A F-B 2 10.00 21206-004-H006 1-D RESTRAINT VT-3 593V2V512 SAT N/A F-C 2 08.00 21206-008-H096 SWAT STRUT VT-3 593V2V544 SAT N/A F-C 1 03.00 21208-007-H002 MECH SNUBBER VT-3,4 593V2V523 SAT N/A F-B 2 03.00 21208-139-H004 2-D RESTRAINT VT-3 S93V2V516 SAT N/A F-8 2 06.00 21208-139-H009 1-D RESTRAINT VT-3 593V2VS15 SAT N/A 04.00 21208-141-H011 3-D RESTRAINT VT-3 $93V2V514 SAT N/A F-8 ,
2 i
04.00 21208-141-H012 2-D RESTRAINT VT-3 593V2VS13 SAT N/A F-8 2 2 03.00 21208-146-H001 2-D RESTRAINT VT-3 593V2V510 SAT N/A F-B 10-6
O VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE O
PIPING SUPPORT EXAMINATIONS ASME SECT. ISI NPS SUPPORT SUPPORT EXAM EXAM METHOD SHEET NO. RESULTS REMARKS XI CAT. CLASS (IN.) NUMBER DESCRIPTION 21208-146-H303 2-D RESTRAINT VT-3 593V2V509 SAT N/A F-8 2 03.00 21208-146-H004 2-D RESTRAINT VT-3 S93V2V511 SAT N/A F-B 2 03.00 21208-146-H006 2-D RESTRAINT VT-3 S93V2V626 SAT N/A F-B 2 03.00 21208-146-H007 VT-3 593v2V627 SAT N/A F-B 2 03.00 UNDERSUPPORT 03.00 21208-146-H009 2-D RESTRAINT VT-3 S93v2V555 SAT N/A F-8 2 21208-146-H010 3-D RESTRAINT VT-3 593V2V556 SAT N/A F-8 2 03.00 1-D RESTRAINT VT-3 593V2V557 SAT N/A F-B 2 03.00 21208-146-H011 VT-3 S93V2V558 SAT N/A F-C 2 03.00 21208-146-H013 ANCHOR 21208-146-H015 UNDERSUPPORT VT-3 593V2V628 SAT N/A F-B 2 03.00 03.00 21208-146-H016 2-D RESTRAINT VT-3 S93v2V629 SAT N/A F-8 2 21213-002-H001 2-0 RESTRAINT VT-3 593V2V591 SAT N/A F-B/D-C 3 10.00 21213-0%-H002 2-D RESTRAINT VT-3 $93V2v590 SAT N/A F-B/D-B 3 10.00 21302-015-H003 3-D RESTRAINT VT-3 S93V2V564 SAT N/A F-B/D-A 3 C2.50 10.00 21302-023-H002 2-D RESTRAINT VT-3 593V2V565 SAT N/A F-B/D-A 3 F-C 2 06.00 21302-107-H010 MECH SNUBBER VT-3,4 593v2V521 SAT N/A 2 06.00 21302-107-H011 MECH SNUBBER VT-3,4 593V2V522 SAT N/A l F-C ,
l F-C 2 06.00 21302-107-H012 MECH SNUBBER VT-3,4 593V2V520 SAT N/A
(
2-0 RESTRAINT VT-3 593V2V637 SAT N/A F-B 2 06.00 21501-038-H002 06.00 21501-038-H004 UNDERSUPPORT VT-3 593V2V638 SAT N/A F-B 2 10-7
/
O N
VEGP-2 THIRD MAINTENANCE / REFUELING OUTAGE PIPING SUPPORT EXAMlWATIONS NPS SUPPORT SUPPORT EXAM EXAM ASME SECT. Ist METHOD SHEET NO. PESLLTS PEMARKS XI CAT. CLASS (14,} NUMBER DESCRIPTIO*l 1-0 RESTRAINT VT-3 S93V2V639 SAT N/A F-8 2 06.00 21501-038-HOO6 10-8
l l l
Tag ISI Snubber Scope Number Class M f rr/S i:*e Examined- Results See Note A See Note B See Note C See Note D See Note E i
i NOTES:
A. The unique tag number for the snubber being examined is listed in this column.
j B. The ASME Section XI class no., e.g., 1, 2, 3, for the system on which '
the anubber being examined is listed in this column.
C. This column lists the name of the manufacturer of any snubbers functionally tested and the size of the snubber, e g., PSA 1/4. )
Manufacturer designations are abbreviated and can be found in the i List of Abbreviations.
D. This column lists the scope of examination in which the snubber is functionally tested, i.e., original scope or expanded scope. Snubbers included in the expanded scope of examination are generally as a result of other snubber functional test failures.
E. The results of the functional test of the snubber tested is listed in this column.
FICURE 4. EXPLANATION OF SNUBBER FUNCTIONAL TEST RESULTS
SUMMARY
TABLE FORMAT 1
d 11-1
VEGP 2 THIRD MA4NTENANCE/ REFUELING OUTAGE SNUGFER FUNCTIONAL TESTS TYPE I SNUBBERS ISI SNUBBER SCOPE TAG MFCR/ SIZE EXAMINED RESUtil Q NUMBER CLASS ORIGINAL PASSED 1
21201 012-H608 1 PSA 1/2 EXPANDED PASSED 21201-029 H605 1 PSA 1 PSA 3 ORIGINAL PASSED 21201 030-H613 1 PSA 35 EXPANDED PASSED 21201 049 H023 1 ORfGINAL PASSED 21201-049-H025 1 PSA 100 EXPANDED PASSED 21201-053 H001 1 PSA-IS PSA 3 ORIGINAL PASSED 21202 002 H008 3 l EXPANDED PASSED 21202 487 H003 3 PSA 3 PSA 3 EXPANDED PASSED 21202-4SS-H003 3 i PSA-10 ORIGINAL FAILED 21204 021 H003 PSA-10 EXPANDED PASSED 21204 021 H005 1 PSA 10 EXPANDED PASSED 21204-021 H006 1 PSA 3 CRIGINAL PASSED 21204-025-H002 1 PSA 1 EXPANDED PASSED 21204 1 M-H003 2 PSA 1 ORIGINAL PASSED 21205 008 H006 2 2 PSA 3 EXPANDED PASSED 21206-001 H009A PSA 3 EXPANDED PASSED 21206 001 H0098 2 PSA 3 ORIGINAL PASSED 21301 014 H006 2
- PSA 35 ORIGINAL PASSED 21305-057 HOO5A PSA 35 ORIGINAL PASSED 21305-057-H005B PSA-1 EXPANDED PASSED 21305 110 H056B -
PSA-1/4 ORIGINAL PASSED 22402 196 H003 -
l Page 12-1 l
E l
l j
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' SNUBSER FUNCTIONAL TES1$
i TYPE 11 SNUBBERS 1
ISI SNUBBER SCOPE i TAG MFGR/ SIZE EXAMINED RJ.S.,Ujd1 l NUMBER CLASS 1
AD 41 ORIGINAL PASSED 21201 014 H641 2 AD 501 ORIGINAL PASSED 21201 030 H626 1 j
AD 503 ORIGINAL PASSED l 21202 196 H018 2 ORIGINAL PASSED 21202 196-H029 2 AD-151 i
AD-501 ORIGINAL PASSED 2)2G2 229 H004 2 ORIGINAL PASSED 21202 231-H044 2 AD 153 i.
AD-71 ORIGINAL PASSED 21204 030 H009 2 AD 501 ORIGINAL PASSED 21206 002-H0056 2 AD 73 ORIGINAL PASSED
! 21208 006 H040 2 AD-41 ORIGINAL PASSED 21208-011-H050 2 l
i AD 43 ORIGINAL PASSED 21208 066-H019 2 AD 501 ORIGINAL PASSED 4 p 21217 037-H001 -
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AD 41 ORIGINAL PASSED
. 21217-072 w6195 3 AD-73 ORIGINAL PASSED j 21301 109 H002 2 AD 153L ORIGINAL PASSED l 21301 126-H037 2 AD-71 ORIGINAL PASSED 21301 127 H071 2 i
2 AD 151L ORIGINAL PASSED 21301 128 H075 1
AD 153 ORIGINAL PASSED 21301 138 H006 2 i
AD - 73 OR]GINAL PASSED 21301 166 H022 -
AD 41 ORIGINAL PASSED l 21301 168 H001 -
AD 43 ORIGINAL PASSED 21302-002 H004 -
2 AD 501 CRIGINAL PASSED
] 21302 107 H013 AD 503 ORIGIN 4l. PASSED 21305-117 H002 -
AD-151 ORIGINAL PASSED 21901-221 H006 -
Page 13 1 a
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VEGP 2 THIRO MAINTENANCE / REFUELING OUTAGE SNUBBER FUNCTIONAL TESTS TYPE Ill SNUBBERS 151 SNUBBER SCOPE TAG NUMBER J C AS} MFGR/512E EXAMikEQ ELSUM
- A0 1603 ORIGINAL PASSE 0 21?01 064-W628A
- A0 1603 ORIGINAL PASSED i 21201 064 H6288 l A0 1601 ORIGINAL PASSED 21204 023 H002 1 ORIG!k Al. PASSED 21301 096 H003 - AD-1603 ORIGINAL PASSED l 21301 104 H003 2 AD 12501 ORIGINAL PASSE 0 21301-10? H003 2 AD 12501 ORIGINAL PASSED I 21302 108-N012 2 A0-1601 l
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- AD 1603 ORIGINAL PASSED 21305-119 H007
+ AD 1601 ORIGINAL PASSED 22403 036 F601 1
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l System Pressure Tests Vogtle Elcetric Generating Plant - Unit 2 O Third Maintenance / Refueling Outage (Period 2/ Interval 1)
The following pressure tests were included in the scope of the third maintenance / refueling outage at VEGP-2. These pressure tests included system functional tests, system hydrostatic tests, system inservice tests, and system leakage tests as required by Section XI of the ASME Code. Boundaries for these pressure tests are described in the VEGP-2 Inservice Inspection Plan document (ISI-P-013). Examination results are discussed in the applicable sections of the "NIS-1 Abstract" and the " Class 3 and Augmented Examinations" portions of this report document. The examination data for these pressure tests is availabic for review at the plant site upon request.
System Function Tests ( FTs )
FT Number Test Description 1 Reactor Head Vent Functional Test j 3 Penetration 32 Functional Test (HHSI to Cold Legs) j 4 Safety Injection Pump 1204-P6-003 (Train "A") Discharge Functional Test 5 Safety Injection Pump 1204-P6-004 (Train "B") Discharge Functional Test 6 Penetration 33 Functional Test (SI to Hot Legs 1 & 4) 7 Penetration 31 Functional Test (SI to Hot Legs 2 & 3)
Penetration 30 Functional Test (SI to Cold Legs)
O 8 9
10 Penetration 56 Functional Test (RHR Hot Leg Injection)
Safety Injection Pump Suction Functional Test 11 RHR to CVCS Suction Functional Test 13 Containment Spray Train "B" Functional Test 14 Turbine-Driven AFW Pump 1302-P4-001 Functional Test 15 Main Steam (Valve HV-5106) to Turbine-Driven AFW Pump Turbine Functional Test 16 Line 1208-135 Functional Test (HV-8439 to Valve 499 Flow Test) 17 Line 1208-133 Functional Test (HV-8104 to Valve 185 Flow Test)
System Hydrostatic Tests (hts)
HT Number Test Description 11 Containment Spray Train "A" Nozzle Open Flow Test (required by Technical Specification 4.6.2.1d) 12 Containment Spray Train "B" Nozzle Open Flow Test (required by Technical Specification 4.6.2.1d) 59 AFW Pump Train "A" Hydrostatic Test 60 AFW Pump Train "B" Hydrostatic Test 61 AFW Pump Train "C" Hydrostatic Test 62 AFW Line 1302-054 Hydrostatic Test 63 AFW Line 1302-042 Hydrostatic Test 64 AFW Line 1302-027 Flow Test 65 AFW Line 1302-022 Flow Test O 66 67 AFW Line 1302-015 Flow Test Condensate Storage Tank 1302-V4-002 Hydrostatic Test 16-1
_ - _ _ _ . , _ . _ . _ _ _ _ ,__. _ .. ~_
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System Hvdrostatic Tests (hts) (continued) l HT Number Test Description 68 Condensate Storage Tank 1302-V4-001 Hydrostatic Test 69 AFW Line 1302-037 Hydrostatic Test 70 AFW Line 1302-008 Hydrostatic Test 71 AFW Line 1302-060 Hydrostatic Test 72 AFW Line 1302-055 Hydrostatic Test 73 AFW Pump Train "C" Discharge Hydrostatic Test 74 AFV Pump Train "A" Discharge Hydrostatic Test 75 AFW Pump Train "B" Discharge Hydrostatic Test 76 Auxiliary Feedwater Pump Turbine Flow Test 78 NSCW Train "B" Hydrostatic Test 92 Charging Pump Train "A" Alternate Miniflow Hydrostatic Test 93 Charging Pump Train "B" Alternate Miniflow Hydrostatic Test 97 Essential Chilled Water System Train "B" Hydrostatic Test System Inservice Tests (ITs)
IT Number Test Description 1 Charging Line Inside Containment Inservice Test 2 Letdown Line Inside Containment Inservice Test 3 Reactor Coolant Pumps 1, 2, 3, and 4 Seal Leakoff Inside Containment Inservice Test g 4 Reactor Coolant Pump 1 Seal Injection from Penetration 54 to Valve 006 Inservice Test 5 Reactor Coolant Pump 2 Seal Injection from Penetration 53 to Valve 359 Inservice Test 6 Reactor Coolant Pump 3 Seal Injection from Penetration 52 to Valve 360 Inservice Test 7 Reactor Coolant Pump 4 Seal Injection from Penetration 51 to Valve 361 Inservice Test 8 RCS Hot Leg Sample Lines to Penetration 24 Inservice Test 9 Sample Line from Valve 101 to Valve HV-3514 Inservice Test 10 CVCS Inservice Test with Positive Displacement Charging Pump Operating (Outside Containment only) 11 Centrifugal Charging Pump 1208-P6-002 (Train "A") Discharge Inservice Test 12 Centrifugal Charging Pump 1208-P6-003 (Train "B") Discharge Inservice Test 13 Boric Acid Transfer Pump Suction Inservice Test 14 Accumulator Tank 1 (1204-V6-002) Inservice Test 15 Accumulator Tank 2 (1204-V6-003) Inservice Test 16 Accumulator Tank 3 (1204-V6-004) Inservice Test 17 Accumulator Tank.4 (1204-V6-005) Inservice Test 18 RHR Train "A" Inservice Test 19 RHR Train "B" Inservice Test 22 Spray Additive Tank Inservice Test 23 Refueling Water Storage Tank Inservice Test 24 Sample Line from Valve 097 to Valve HV-3508 Inservice Test
> 25 Penetration 24 Outside Containment Inservice Test (Post-Accident Sampling) 26 NSCW Train "A" Inservice Test (Outside Containment Only) 16-2
- _ _ . -_ . ~ . - . - . .- .- .- .. ..- .- - . - . . -
i l System Inservice Tests (ITs) (continued)
IT Number Test Description i
29 NSCW Line 184 Inservice Test (Train "A" Tower Bypass) 30 NSCW Train "B" Inservice Test (Outside Containment only) 33 NSCW Line 185 Inservice Test (Train "B" Tower Bypass) 61 Condensate Storage Tank 1302-v4-001 Inservice Test 62 Condensate Storage Tank 1302-V4-002 Inservice Test 64 AFW Inservice Test With Pump 1302-P4-002 Operating 65 AFW Inservice Test With Pump 1302-P4-003 Operating 66 Main Steam to Turbine Driven AFW Pump Turbine Isolation Valve HV-5106 Inservice Test 67 Essential Chilled Water System Train "A" Inservice Test 79 Excess Letdown Heat Exchanger Inservice Test 80 RHRS Cleanup Inservice Test 81 NSCW Pump 1202-P4-001 Inservice Test 82 NSCW Pump 1202-P4-002 Inservice Test 83 NSCW Pump 1202-P4-003 Inservice Test 84 NSCW Pump 1202-P4-004 Inservice Test 85 !!SCW Pump 1202-P4-005 Inservice Test 86 NSCW Pump 1202-P4-006 Inservice Test i 87 NSCW Pump 1202-P4-007 and Piping Inservice Test 88 NSCW Pump 1202-P4-008 and Piping Inservice Test 93 Boric Acid Transfer Pump Inservice Test With Pump 1208-P6-007 Operating 94 Boric Acid Transfer Pump Inservice Test With Pump 1208-P6-006
() Operating System Leakare Tests (LTs)
LT Number Test Description 1 Class 1 System Leakage Test i
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l INDICATION NOTIFICATION FORMS The following Indication Notification Forms (INFs) were issued to Georgia Power Company (GPC) by Southern Nuclear Operating Company (SNC) due to
- reportable indications being observed during the examination of either Class 1, 2, or 3, or Balance of Plant (BOF) components, during the third maintenance / refueling outage at VEGP-2
INF No, Affected Component / Area INF Disnosition 193V2001 2-HD-02 Measurements reported below " Action Level". Component was replaced during the 2R3 Outage. (Reference letter MSV-01555) 193V2002 2-HD-10 Measurements reported below " Action '
Level" Component was replaced during the 2R3 Outage. (Reference letter MSV-01555) 193V2003 2-CND-12 Measurements reported below " Action Level". Component was rep 1;ced during the 2R3 Outage. (Reference letter MSV-01555) 193V2004 2-CND-13 Measurements reported below " Action Level" Component was replaced during the 2R3 Outage. (Reference letter MSV-O- 01555) 193V2005 21205-E6-002-WO1 Sub-surface planar flaws acceptable 21205-C6-002-WO2 per ASME Section XI.
r 193V2006 2-M FW-0 8 Measurements reported below " Action Level". No corrective action necessary. (Reference letter MSV-01555) 193V2007 2-HD-06 Measurements reported below " Action Level" No corrective action necessary. (Reference letter MSV-01555) 1 193V2008 2-CND-10 Measurements reported below " Action Level". Component was replaced during the 2R3 Outage. (Reference letter MSV-01555) 193V2009 21205-004-H016 Missing cotter pin corrected per MWO 29303260. Four additional supports examined, t 17-1 )
. . - - . -- .. . - _ - ~ - - - - . . - . - - .- .. ~- . - -
INF Nt s Affected Component / Area IFF Disposition 193V2010 21202-220-11028 Frozen spherical bearings corrected per MWO 29303325.
193V2011 21204-021-11003 Frozen spherical bearings corrected per MWO 29302546.
193V2012 21204-039-35 Surface indication acceptable per ASME Section XI.
193V2013 2-MFW-06 Measurements reported below " Action Level". No corrective action necessary.
193V2014 2-MFW-01 Measurements reported below " Action Level". No corrective action necessary. (Reference letter MSV-01555) 193V2015 2-CND-03 Measurements reported below " Action Level". Component was replaced during the 2R3 Outage. (Reference letter MSV-01555) 193V2016 21201-V6-001-B30 Surface indications acceptable per 21201-V6-001-B32 ASME Section III. (Regulatory Guide O 21201-V6-001-B33 1.65) 193V2017 2-MFW-13 Measurements reported below " Action Level". No corrective action necessary. (Reference letter MSV-01562) 193V2018 21302-109-44 Surface indication removed by buffing / flapping.
193V2019 21201-B6-004-W26 Sub-surface planar flaws acceptable per ASME Section XI. f l
193V2020 21201-053-5 Sub-surface planar flaws acceptable per ASME Section XI.
193V2021 21201-B6-004-WO3 Sub-surface planar flaws acceptable per ASME Section XI.
193V2022 21301-004-14 Sub-surface planar flaws acceptable per ASME Section XI.
l 17-2
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- INF No. Affected Component / Area INF Disposition 193V2023 21301-004-5 Sub-surface planar flaws acceptable per ASME Section XI.
Copies of the INFs and their attachments are provided in this report document.
Refer to the respective INFs for details on the nature of the indications.
The INFs in this section constitute only those reportable indications observed during the SNC scope of work. Any reportable indications observed by outside contractors during their scope of work should be identified to GPC in the contractor's report document (s) which are referenced in this report document.
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I Southern huclear Operating Corpany INF form-002 A 1
INF No. 193V2001 I Indication Notification Paet 1 Findines
( Exam Cate NDE Method Procedure / Revision PT MT RT ET VT OTHER UT-V-466/01 09/13/93 X UT 4
Cement s :
During the erosion / corrosion inspection of conponent 2 HD-02, measurements were detected which were below the pre assigned " action" level. See attached reports f or f urther information.
Signat- e Lead NDE Levtl 111 Date Alcw .m
'I b'$3 115 Supervision /Date Date Sign re 7 ITS Enfineercate
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- I b' Feet 2 - N tification Actification Acknowledged By Title Date W f vfmM S,- Pla & B 12n,- 1tc h kwet 'I - l 5 '8 set 3 - Disposition tv Operatino Company
'*'"'"; Pet SCS t@er 56-I2'M ddled 9-2l-93, the 8 X 20" e4dndW i3 espwencwy conderable Iccah se,j weac and cc4 ceat h codc., m n ,t'* wawt(crt
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Part 4b - Additional EreHnations (Seone Erosasica)
C ~ (, s - E i II I + 4 la OE hE'i f Smi H6 0 k S4.5 [6IC Peet 4e - Successive f reminations (Future Exam Reouirements) 10 b6 ht 1 & c ~ i wi p ( ch 6 PC l- v b 8
- E 6 C . - l Date O Signature D T- -.bGAHA.
ITS Engineer t- r lE t t c0u , / /) ( lD-13 9 3 Date Part 5 AN!! Review NfA I4 A Date Fort 6
- INF Final Review /ITS Engineer ;pg Title DY Sihvr~ ?& (i RttGl_c. W. E H i s ~ f f tt_ .5 M ( l313 h 3
INF-Form-002-A Southern Nuclear Operating Conpany INF ho.193V?Q07 )
Irdication Notification Part 1 - Findings Procedure / Revision !
MT RT ET VT OTHER UT-V 466/01 9/ 93 x UT PT Coment s:
During the Erosion / Corrosion inspection of rorponent 2 HD 10, measurements were detected which were below the pre assigned ** action" level. See attached reports for further information.
Date 11 Signature yad NOE Level ~
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Part 4b Additional Examinettons (Scope Eroension) l To h k 1tra ,.tr s b L6 !6PL E 8 0 ' s t e r. i e 6 Part &c - Successive Eneminations (Futu*e Exem Reautremarits) l
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Signature - ITS Engineer Date D9 bCAHA* Yf r 1t E ( J e (_. IC-@ 9 3 Date s Part 5 AN!! Review H A b d Part 6 - INF Fidal Review /ITS Engineer Title Date D 9. b [ A ti A m Set"T(utc~ d( N E 9tt wH E HC IC-13 di '*>
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Southern Nuclear Operating Ccerpany INF form 002 A INF No. 193V2003 In:fication Notification ,
CPeet Exam Date 1 - Findig NDE Method Procedure / Revision x M1 Rt ET vi OTHER UT-V-466/01 j 09/13/93 UT PT Corrent s :
During the erosion / corrosion inspection of corponent 2 CND 12, neasurements were detected which were below the pre-assigned action" Level. See attached rsrarts for further information, j l
l Signatur Lead NDE Level !! Date
~ _ _ _ _ _ . _ _
~! b*b 3 i g r - ITS ngiNeer/C e 115 Supervision /Date Date
(( b b. b, (h A"16 .h EC 94 3 l Port 2 - Netification hetification Ackno=le ed By Title Date
< . % 7 5 c, Pla,d 6 T e c h 4 /O pe d 4-ll-43 Part 3 Disposition by OMretino Corrany J Corrent s :
i'e e S C5 l e u e e S G- i 2 Vil da gd 4 24-93, %e 8 Xit" e x pandu I
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O Corrective Actie : {g gcp 4hg gggggg p 4 h,g ggg g4h g { g { . q , ,, ) q 4 vnah e,a\( Ref ' MP 9 CI3' V A NOS ; MWO d M 3 03 / 4Y), NO Scope e x pa 10c'1 h c e e, g n1 Actas h ead 3 i d e nm i el 4 be ' n ye ca cd d15$ hecpbW owlc( be )pec ivred a ba$f;qf l eAAnondicq of 4he new t emponed avec wA a n& c n ', s c mgle h e .
Signature Operating Co. Representitive Title Date 4K't A uf se, Plant ena - Ted Suppcc4 4-2tfA3 Pert 48 - Re-exemination efter Corrective Action 10 ki f7tG^itWEV h -( b[b b' N b
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- Part 4b - Additionel Examinations (Scope Expension) h htifCMt9fp y '- I M4f + F t Ct* C Part 4e - Successive Einminations (Future Exam acOJirements) l' E t's t C m a ~~ L G b( bf' ($l {
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1 Southern Nuclear Operating Conpany INF* Form-002 A INF No.193v2004 Irdication Notification Port 1 - Findinas Procedure / Revision OExamDate 09/16/93 NDE Method X UT PT MT RT ET VT OTHER UT V 466/01 Corrent s: ,
During the erosion / corrosion inspection cf conponent 2-CND*13, measurements were detected which were below the pre assigned " action" level. See attached reports for further information.
l I
Date Signat Lead NDE Level III h --
9-17o13 l ITS Supervision /Date Date igptur - ITS i er/
%e/n h3 '
R. 6. rw a t e B< Su 9-o-93 '
Part ? - hetification hetification Acknowledged By Title Date ,
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W/ f m N e. ?{ G etN St\4 i '~
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'l Part 3 - Disposition bv Operatino Comany c - ": Per sc5 lence SG-12911, daid 9-M 'l3, Ac Ol>f 4 e >.p a n d u b ey per : e ,w.43 c en s'.de c4 b k lo cal: v el wea r ad c c at/ b e w :@,1 6,0l" c.; ccde m.e m u m we ll 4h:c K nen w'.4 1 4he ne rt 4vc h ( cy cle, l O Co reettve Action: Rf the t# X f.2 nge e < W, 3 ced #,+h a FAC- cesl34 nt mMet;al(Re? p(a(dMOD 4 3-V2Mt(,S S MWC 4 M3 C3 95), Nc 5 cope beycd cApa 4 acus antaag :6e e.d n k .epeaed ,s cey Mi hwevw, a u 3e n ,t g c g mau H m c4 At n e a> c o 'mp e,r* shcaid b pec&<*ml aDec . o 5 4 A H 4A '.61 's i ( c +N/ 64 6 ,
Title Date Sign!a 4< ure opder ting Co. Sepresentitive 4 Sc. P%4 Em. TE c h knce4 9 '.78-43 Part 4e Pe evamination ef ter Corrective Action O 6E htu T-m i es-tp b SC.S[C-fC E N ' s +4 t e r. . . (
Part 4b - Additional Ereminations (Secoe Eroansion)
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Part 4e Successive Examinations (Future Eram pecuiremants) 30 Sc c f E C h e ~ s ;? h.( blb fl i n G W G L it *
- l Date O signature VE D Cn- ut ITS A = Engineer
. o P. %i A iM )D L 1 C G Li 3 Part 5 ANil Review Date
^ ' E*. HA Part 6 - INF Final Review /ITS Engineer Title Date !
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INV F orm-002- A Seuthern Nuclear Operating Cenpany INF No.193v2005 Indication Notification Part 1 - Findinos Procedure / Revision NCE Method OExamDate 09/14/93 X UT PT MT R7 ET V1 OTHER U1-V 404/06 Lom,ents:
During ultrasonic examination of welds 21205 E6-002 WO1 and 21205 E6 002 V02, subsurf ace planar flaws were recorded in both welds. These indications were recorded and evaluated during PSI.
These indications are all allowable per IWB-3514-2.
Date Signature - Lead CE-Level 111
, l l',A .' f ' ) Lff7 9fI' h/ ]
Date Signature - ITS Enginegr/ tate p y pervision/Date
- 9. R . bF-ARM w &c LI 9) woo p %cha Paat 2 - hetification Date W cation Acknow ed ed By Title b' M 'I
.t v%., .' (1-Part 3 - Dispetition by Operating Company C m mts:
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RGt EPT AA ~I. 5 O Corrective Artier:
HbHE Date re Operatin Representitive Title i M llCcR 4 %c -Im /c Peet La - Ee ews*? ration efter terrective Action NDuE Pa r t 46 - A ddi t i ons t E r emi nat i ons ( Sc ope E xpens i oe )
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Hone l Part 4e - Successive Eneminations (Future Exam Peavirements)
NoHE 40 # Date Si Jg %u -ITSEngipee g
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'% Date Part 5 ANil Review 1'T tmr bh@) l0-1J-93
' Title Date Fart se. ra w ,, /s a a 6d-/ I 'F F' .at = Re iew/11$ Yngineer io- z v-v
Southern Nuclear Operating Cocpany INF-Form-002 A 1rdication Notification INF No.193V?006 Port 1 - Firdincs Procedure / Revision OExamDate09/20/93 NDE Method X UT PT MT RT ET VT OTNER UT-V-466/01 Coment s:
During the erosion / corrosion inspection of conponent 2-MFW-08, measurements were detected which were below the pre-assigned action" level. See attached reports for further infortration.
Signature Lead NDE Level III Date J_ 9 'L3 ')3 Signature - ITS Engineer /Date O S Supervision /cate Date 3.3 . b t a M Di M bwN')Dou h O3*l3 Part 2 - Notification hetification AcLaowled ed Title Date
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Part 3 - Discesition by Oceretino Conceny Co m mts: Fe c 5 C6 leuu S Cv 1216 3, cla r d 4-2S- 4 3, dhe b X 10 " u po nde e skces scme \ nb caccas y Mc e - a cc e l e rakect conc m.'t wee. Mcsewe' (d\ (ul AP445 'n i .'i(di d 4bd Ot t %f4ndie de ll d ck PCd C k c cdg eW .H vw rq n'd \k 4 k.( S li d ) (l u e'.dj 0- li f fi kNC Ek CdI De l'j Y blC I 0 'Y M4 O 'Ij 6 cn 4hc 10"cf a mde r P' Pt e A4 e u.cq pe belic d 4 he duc 40 ccu ,e er bv.~( ,
Corrective action: gf g(p pg ., p Q { ( l .p ., 3 ( 4 J h'. ', C u b aj g . Alh, nC %A-ipc k a Scape espan Cc>1 lS wf d ttd, Signature operating Cc. Representitive title Date J,Ij { $ . nj Sn". NC Ak $nf - Y$l h bd@QC f + lh"bYb Part 4e - Re-eve-instion efter Corrective Action non Part 4b - Additional Examinations (Scope Expension)
NDME Port 4e - Successive Eneminations (Future Exam em;treaents)
]O hg h 69 f51 HW l b MI4EE-(t W b f Signature - ITS Engineer q Date 2 ^
\ Nf (-nt, <~ Se ~h e 1n n /:t ts Part 5 ANil Review Date H /A e It Part 6 - INF Final Review /ITS Engineer Title Date T {_
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Southern Nucltar Operating Conpiny ]NF form-002-A trdication kotification 1NF Wo. 193V2007 Part 1 - Firdines Exam Date kDE Method ,
Procedure / Revision MT RT ET VT OTHER UT-V 466/01 09/21/93 X UT P1 l
Cornents:
During the erostor / corrosion inspection of conponeni 2-HD 06, measurements were detected whict wer* below the pre assigned 8' action" level. See attached reports f or ..;-**,er information.
Signatur - Lead WDE vel !!! Date Ad hi bDd3 Signature - ITS Ekgineer/Date S upervision/Date Cate 9.9-. bKRMAm %v .O(zt. u alru % met. v .
93043 Part 2 hetification Title Date kotificajlonAcknowledge,dBy WW.dmbtl Sr. Pf a d lir14 - Tec h h wed '
4- 2 ? -O Peet 3 - Disposition by Operat ino Corrany U
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E, 4 r1 k %~,s El 'Q Al lI y a Part 4a - Re eramination af ter Corrective Action NoyE Part 4b - Additional Examinations (Scope Espansion)
YOHG Part 4e - Successive Ereminations (Future Exam peovirenents)
O h6 I6'T 6 C M t 9 W bb P/,. 6 % b l 9 E E CA W, Signature - ITS Engineer Date C 7- -FN4- 7, r 7pttf,s ,, j// f j c t7 C' Part.5 ANII Review Date 0h p l4 Part 6 - INF Final Review /ITS Engineer Title Date EC. [- f. A 6 - Prt 7 t ( v e s; us( SE E ,4 % e i g c_ 6 + (_ I C 13 9 3
Southern Nuclear Operating Co:rpeny INF-Form-002 A Indication Notification INF No. 193V2008 Part 1 - Findinos Exam Date NDE Method Procedure / Revision 09/23/93 X UT PT MT RT ET VT OTHER UT-V 466/01 Coment s:
During the erosion / corrosion inspection of conponent 2 CND 10, measurements were detected which were below the pre-assigned " action" level. See attached reports for further information.
Date L
Signaturehead NDE Le(vel 111-vcL ci-2te9 3 Signature-ITSEng(neer/Date 115 Supervision /Date Date D.7. bf'AWA- IE r TEtt em Oc !.('ves Y 'r%d,p- 9 M7 C #
Fart 2 - Netifica,t_icn e ed Title Date Notification M _r-A.knowledg!<[By 4s - S c, PL 44 f it4. - Tec h 5'cwc c 4 '
4-2'?~43 Part 3 - D'snesition by operatino Correny c o"~t 5 Ps eb e n c e '. I N F 54 14 3 v 10 t 5 'i s 3
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nature Dperating Co. epresentitive Title Date Sig A%h1 Ss* , LR A n4 E sta,- Te c.h _S wps e , 4 Q .3 6 - 4.3 Pe*t 4a - Re-cwamination after Corrective Action 1c BE &n e n m, + w i; .( .St s lL rt I n w t e r , r t, l Part 45 - Additionai Examinations ($ cope Eroension) 10 b ei t 'i t C e . + ( p hf f (; [Q b '* bib'*
Part 4e - Successive Exaa'instions Uuture Esem Recutreets) a r C1 L C +i MD ,43 hk [ +bl A t t C'
- b h Signature - I S Engineer Date D D _ Le f A v / m b r- lEL f ( c. _. At II -tE O >
Part 5 AN!! Review Date .
, A .~ f d a Date Part 6 - INF Final Review /ITS Engineer 3,?{ Title DE [SENA- Et c 'I t L E ( 2- (E f ~ l, l ~ E r t. .4~C tD'13 #1 5
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Southern Nuclear Operating Compcny INF Form-002 A Indication Notification INF No. 193V2009 Part 1 Findinos Exam Date NDE Method Procedure / Revision 09/18/93 UT PT MT RT ET X VT OTHER VT V 735/02 Connents:
During visual examination of piping s@ port 21205 004 H016, a missing cotter pin / clip was noted.
i Signature - Lead NDE Level III Date A be h 7 4 -63 4
Signature ITS Enginekr/Date ITS Supervision /Date Date D 9. bfLA g a u g rL T p W y * .OAL 9-?M 4 3 Part 2 - Notification Notif ation Ack i ged By Title Date SH 61 ^J EF C 10 h Wcy3
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Part 3 Dise2sition by Oper Nina Corrany J
Coments; Cotter pin to be installed and VT 3 performed. Due to this thF, a scope expansion was developed (reference Deviation Request No. 002) that added 21205 004 H019, 21205 003 H004, 21205-005 H003, and 21205 007 Hf)25. These scMitional visual exams were satisf actory.
l Corrective action:
WO 29303260 was written to instalt cetter pin and perform VT 3. Cotter !
pin was installed satifactority per CC VT-3, IR # 09891, 9/29/93.
DC-2-93-151 doctrents this corrective action and the RCCA (root cause corrective action) per GPC procedure VEGP 00058-C, Rev. 7.
Signa re operati o. Representitive Title Date t'i 1 wu Cy c, i MEED. / C lf Tl9f Part 4a ReN xamination oft P Corrective Action See Sheet $93V2V644.
Part 46 - Additional Examinations (Seoce Exoansion)
As required by IWF-2430(a), examine adjacent supports and an additional three rigid struts in 1205 system (Incitxied in Dev, 002 to the 2R3 Outage Plan).
Part de - Successive Examinations (Future Exam Reovirements)
None required other than normal ISI Plan requirements.
Signature ITS Engineer Date D . 7- . b /LA tl A ~ h0 rl 7 E(A,to. /2 c 10-1543 Part 5 ANII Review l ,
Date U,% b Part 6 INF F t e ew/IUSEhneer Title Date l). Y $E. &r, su ew EC lO ' IV# D
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INF Form-002 A Southsrn Nucitar Operating Cornpany INF No. 193v2010 Irdication Notification Pert 1 Firdinas Procedure / Revision NDE Method VT V 735/02 RT ET X VT OTHER (f) Exam09/10/93Date UT PT MT Cervent s:
During visual examination of piping support 21202 220 H028 (srdber SN 686), frozen s,;nerical bearings were noted not allowing the stdter to rotate f reely.
1 Date Signature - ead NDE Level 111 o.- -
4 ~2 % 'h 3 ITS Supervision /Date Date Signature ITS EngNeer/Date p{
ADc_g A v [ . /h A?_ s- $c rL TELt,9- 4 7.~)- 9 3 D. C . b f! A M A s ht-L l t R ( W 01 Part 2 - Notification Title Date Not[ficationAc Jedged By c'f / m/ CNkiNrfL /0 /15 ) 93 PY t 3 - O d sition by coe M ino Coreaay Corrent s :
As the nature of the macceptable condition noted per this INF did not render the subject snubber inoperable, it was not doctanented by a deficiency card. Also, a tech. spec. visual was performed on all the tech. spec. snW bers, therefore, no scope expansion was required.
Corrective Action:
Muo 29303325 was written to verify that spherical bearing not fro:en by removing pin, cleaning rust / corrosion, lubricating bearing end reinstalling pin. Work was cocpleted satisfactorily 10/9/93.
Title Date Shignaure-operatingJijpRepresentitivesay2V EWc,iMEEL
% , ,- to / / 5'/9 5 Part 4a - Re esamination after rective Action See sheet $93V2V645 l
Part 4b - A titional Examinations (Scope ENDansion)
None reqJired.
Part 4c - Successive Examinations (Future Esam peo;irecents) 6fone reqJired other than normal 151 Plan requirements.
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Date Signature - ITS Engineer k blLAHAs he, /L lt o t> c u - t?( 10- 15 $'$ 1 Part 5 ANil Review , , 's Date l
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Part 6 - INF inal ' view /ITS Engineer Title Date
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Southern Nuclear operating Company INF-Form 002 A
]NF No.193V?011 Indication Notification Part 1 - Findinas NDE Method -
- Procedure / Revision Exam Date 09/20/93 UT PT MT RT ET X VT OTHER vi V 735/02 l
4 comments:
i During visual examination of piping support 21204 021+H003 .
5 (srstber SW 8484), frozen spherical bearings were noted not allowire the snubber to rotate freely.
Signatur - Lead NDE Level !!! Date e _ b, a S-27-9 3 Signature-ITSkngineer/Date ITS Supervision /Date Date USs. bCAHAr Tr *_1 t. t t, t o s 0A L AQ%Au (, hatr et T t. t t- (s- % 22 r1 3 Part 2 Notification N6 s edEEk /Qfl$ b Pert 3 - Disdchition by OperatN Comany Cerrents:
Reference RER 93 0348.
Corrective Action:
kwo 29302546 pulled snubber for testing and replaced existing unubber with operable snubber SN 15980. Snubber failed functional test due to powdery, metallic material in ball cock area causing snubber to lockup. An additionat 11 snutters were tested as an expanded scope. All passed.their functional test. As a tech, spec. visual exam was performed on all tech.
spec. sn@ bers, no expansion of visual exams is necessary.
SignaJurs-operati Title Date
/W WRepreentitive d cuc,.au e io/t5/93 Pert 4a - Re Yuamination af ter [2rrective Action I
See sheet $93V2V646.
i Port 4b - Additional Examinations (Scope Espens ten)
None RegJired Part 4e - Successive Ex,aninations (Future Exam peoutrements)
None other than normal ISI Plan requirements Signature - ITS Engineer Date b E. b /? A H S/W O tfL lect 20s Mr l 0'l$ 'I3 Part 5 ANil Review , s Date T~ hv ld52 10-!C43 Title Date Part6-INFFElR$
.o-A A A~ view /ITS'Ingineer 3x n .' >
/saa h-n- rs
! s ttern Nuclear Operating Cocpany INF Form-002 A INF No. 193V?O12 Indication Notification Part 1 Findines Procedure / Revision
[oment s:
During liquid penetrant examination of weld 21204-039 35, an indication 4:as recorded which is acceptable per ASME Section XI.
Date Signa {tre Lead ND Levet III sJW 0 -C 2- h 3 Signature - ITI Engineer /Cate I w rvision/Date Date k E. [Rbt A m kEL 7ELElvv h s IbjU rv N & r__ h- A 7 9 f Part 2 - Netification
- fication Ackn wle$ ed By Tit e Date Y Al* 0 3
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. ure-Operating Co. presentitive Title Date
'j 2 /-93
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Pert 4e - Re evedration af ter Cecreetive Action .
c Part 4b - Aetional Eneminetions (Seone Expension) l l
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Part 4e - Successive Era-instions (Future f rom Reautrewnts)
Nb Signature ITS Engineer Date Oi D.E.bCAMAe Part 5 AN!! Review fe t 7 6 t, t'4 v O(
Date 10-13 4 3 f
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Q%.L f> l0 ' 5 h l Part 6 - INF Fi t Revi /1 S Engineer Title Date ,
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i Southern Wuclear Operating Corpany INF Form-002 A 1 Indication Notification INF Wo. 193V20))
, Peet 1 Findings Procedure /Revis ion bem Date WOE Method UT V 466/01 MT RT ET VT OTHER 09/23/93 X UT PT l
Cors,ents: 1 During the erosion / corrosion inspection of conponent 2 MFW 06, measurements were detected which were below the pre assigned " action" level. See attached reports f or f urther inf ormation.
I Signatur Date Lead WOE LLvel III m C~,k cl-2 6 9 3 Signature - ITS Enhneer/Date Date
/t , supervision /Date N 05b Nhih S1 Tillerd hu i. f_W ?Y O.* t v O *1 'l * ?
Feet 2 - hetification hetification Acknowledged B Title Date
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SG-it'R O . dated 4-2I-42. The low read / np ec <cqck/</ vc be d<c s afd c Corrective Act(ent gr , j , \ ge egd c4 hs'*l/I6'=eff(/Wv'(8 ,
Signature-opera. ting Co. Re esentitive Title Date hf. .~
h, A V1h d Ak $ l k I+QOf N Feet 4e pe ene-instion eftee Cerrective Artien BoM P_ art 4b - Additionel Eneminations (Seone Espensipal l NO9E i
Part 4e - Successive Examinations (Future Eram Deavirements)
O h6 h5'lECMiHEp h(.6 d.PC b M b i M6 DElb d Signature - ITS Engineer - Date
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- A ~ br 1t t t( o u ( f ? /_ IC-l3 0 3 Part 5 AWII Review Date Fart 6 !WF Final Review /ITS Engineer Title Date i 9 . (,I' A u h ft r. 7 t* Q (c _ d. .] h p. . b 4 (.i u f-g R 1D' 13 6 2 I
Southern Nuclear Operating Corpany INF Form-002 A INF No. 193v2014 Indication Notification Part 1 - Findings
- NDE Method Procedure / Revision Exam Date
\ 09/23/93 X UT PT Mi RT ET VT OTHER UT-V 466/01 Corv'ent s :
During the erosion / corrosion inspection of corponent 2 MFW 01, measurements were detected which were below the pre-assigned " action" level. See attached reports for further information.
Signature ead NDE Level !!! Date A h O 7 6 'i 3 Signature - ITS Engheer/Date S,.Supervi s i on/Dat e Date f) A . C 2n U Ain Pra T li t r> O'\L P , J iX wn v a m3 Pa t 2 - Netifiention Notification Acknowledged By Title Date
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& clear 1T 5 N D F L e vel U 1 L e v el III . n d v',ci u 4\ 5, 4ht ceu(:np t c t 4he desorrean 3 4" ha. $P 6'd fi te "d elk W dch were bc6 cede Nn, s h owtd be c e n nvend t
a3 7as 3e " r e a.O np o nce A c lose. a q mmakc q c onh e mecL the pee 3ence c; A #9 m 4 c %nausn" lager '. n 4 e r n d 4 . +h e p'.pe w,ll wh:ch p e e d ac ut 4 44 bra c' s $a\ se i c e ,' e u cG ^ A A4 dese lcca hcn s , If Cerrective Artica: g1a t c + r e ck ve ac 5:ca e qa wed, Dis v'eaud 9
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<+ IC'VU Part La - Re exe+ination efte* Corrective Action N O pE Part 4b Additional Ereminations (Scopa Exoansion)
NOW Part 4e - Successive Ereminations (Future Eram Reauirements)
O h6 C,T Ei(% t v E:tp ET M6 Q @ 8 M M6&l H(+
Signature - ITS Engineer Date i
O\ D C . b /t A H e m on 1C-(tim - /h ..
Date I C l 9 3
{ Part 5 ANIX Review A/LA l
+/ 4 Part 6 - INF Final Review /ITS Engineer Title Date U . [-f A s+ YJ htuc~ % bi' Fw m,r
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Southern Nuclear Operating Cocpany INT Form 002 A INF No. 193V2015 Indication Notification Part 1 - Firdinas NDE Method Procedure / Revision Exam Date x PT MT RT ET VT OTHER UT-V 466/01 09/25/93 UT Coment s :
During the erosion / corrosion inspection of cocponent 2 CND 03, measurements were detected which were below the pre assigned " action" level. See attached reports for further information.
Signatur - eadNDELevel,)ll Date Ov__ _ bw 9'?6 93 Signature-ITSEngiheer/Date upervision Date DL c.am a rw. mo d'um a/Dateme </ n M s Part 2 hetification Notification Acknowledged By Title Date b e f AMIC( S s', f k 56t: YP t h b&or N 44kA5 Faet3-Disksitionbyomratingtemsay c - ts: Pe c s c s W e c 5 6- 111 N , dd ed 9 9 3, +he lH " ci.4 mp e e Aw s hc e; q .ts J 5.pr.Dcatt lo ccN. v el Wa4 4ky,W 9 A nd. c calcl ces c h t e cte M. n '. m u m w.ot W, c R nm d v. $ 4he ned he( c 3 c(e ,
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e ipaas' cn , n y ad area $ a \ + ead3 iie 1MQ 4 o he ' nygec + e6 , '15 r ft ' 6k -
Wc we 'e c, a bl3c h ne ua mme r c n d the mw component shJ k pe E c mod AI AC c insA a h d4t c 4 M c 0 mpl6kt .
Signature-D Title Date
@ff bper ting ak. Col. epresentitive Sc. Pla d En a, - h ck %u u A- IC-lM ,
rert 4e - #e-eve =f netion af ter Cerrective Action C b' b t 'i t- r- m e - t '= b' $[h (. IG ( . 4 (. t e c i . 4.
Part t.b - AMitional Eneminations (Scope Ernensien) 3/ Oc Tsr m , s s, Q {>( bl$ (4( t ~ L. i ~ V i c , , l.
Part 4e - Successive Examinations (Future Enam Reavirements) 30 hf titc%~n7 h3 [6 d 0 + b i - E t r.i 4 4 Signature - ITS Engineer Date D, C (N;' A ,s r+ d.n %Lticm ,Jfr l$'IS d ? l Date l Part 5 ANIX Review fA 4 .
g Part 6 - INF Final Review /ITS Engineer Title Date f
i nc. ec,.u nr ,t.m ~ N, ec w. /s c rs,= 4 3 !
INF Form 002 A Southern Nuclear Operating Conpany INF Wo. 193V2016 Indication Notifiestion Poet i - Findinos Procedure / Revision Exam Date NDE Method OTHER MT-V+505/03 MT RT ET VT UT PT X 09/28/93 Conmente: ,
DURING MAGNETIC PARTICLE EXAMINATIONS OF THE RPV STUDS, INDICATIONS WERE DETECTED AND REPORTED (SEE ATTACHED REPORTS) ON STUDS 21201 V6 001+B30, 832 Am 833. THE INDICATIONS ARE ACCEPTABLE PER ASME SECTION III (REFERENCE REG GUIDE 1.65).
Date ,
Signaty e - Lead NDE Levet !!! &*30 0 h
_ n_ - _
ITS Supervision /Date Date Signature ITS 9ngireer/Date br IEt %>v b & Av b. MA2r ca I6Lt ue If h~3Od3 Ni b hAi4 6 s Q Part 2 - Notification Date Notification Acknowledged By Title 1 0 - W '\ b w Y& % Gs y .
Port 3 - Disposition by operatina correny Corr,ent s !
NONE P
i Cerrective Action:
NONE Title Date Signature operating Co. Representitive Part 4a - Re-examination ef ter Corrective Action NONE Part ab Ackfitional Examinations (Scope Excension)
NONE Part 4e - Successive Examinations (Future Exam #eoufrements)
NONE
_~
Signature - ITS Engineer Date 10-15-9 3 D. S , [, BA s4 4 - kbfL T E t4 Cow ( !~ ile 3 Date Part 5 ANil Review . [ g 10-IF- f 3
. d'h/ ew t Date Part 6 - INF Fi l ede ITSY'ngineer Title AW r~ Sp.. Ena.%< ,
/ S a c- M-u-9R l
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Southern Nuclear Operating Cortpany INF Form 002 A INF No. 193V2017 Indication Notification Part 1 Findings Proced:,tre/ Revision Exam Date NOE Method PT MT RT ET VT OTHER UT V 466/01 D9/24/93 X UT Corrwant s t During the erosion / corrosion inspection of corponent 2 MFW-13, measurements trere detected which were below the pre assigned " action" level. See attached reports for further information.
Signa. e - Lead N;I Level 111 Date A bwh h' 7A T3 Signature - ITh Engineer /Date rvision/Date Date I g5 nR (:rA% Prn fww h,LP tbs liw % YYlos u 4 39 9R Part 2 - Netificatien Notifi ation Acknowledged y Title Date bf. "
SC A bubM OT ' 'Y ~5
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.Aeth' cationan M Acknowledged By s, Emr. khl93 Pa7 b Disposition bY Operatina Coroamy Cmmts:
N/A Corrective Attice:
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gna e Operati C Representitive Title Date i 3 fr [Ey f, eclg.l13 Pak 4a - Re examination after Corrective Action N/A Part 4b - Additional Examinations (Seone Espansion)
N/A Part 4e Successive Examinations (Future Esam peouf rements)
N/A
'. Signature - 17S Engineer Date D . E- . b f7 A H A m C rL TE L0 40v ( IO~lE A 3 Part 5 AWit Review A Date j
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Southern Euctsar Operatine Ccapsny INF Form 002 A j
INF No. 193v2020 Indication kotification Poet 1 Findinas NDE Method Procedure / Revision Exam Date PT MT RT ET VT OTHER UT*V 404/06 09/25/93 X UT
[,o,. ment s t DURING ULTRASONIC EXAMINATION OF WELD 21201 053 5, INDICATIONS WERE RECORDED. THE INDICATIONS WERE ALSO DETECTED DURlhG PSI. THE INDICAfl0NS ARE ACCEPTABLE PER ASME SECTION XI.
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N/A Part 4e - Successive Ereminations (Future Exam Reavirem*nts)
N/A l
Signature
- ITS Engineer Date D. S . (' /L A t t 4 % I t. A b tJ / o ~ A l 0 -l3-6 3 Part 5 ANil Review ._
Date l Revie !TS EnolNer Title Date j Part
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INF Form 002 A Southern Nuclear Operating Company INF No. 193V7071 Irdicatico Notification Part 1 - Findincs Procedure / Revision NDE Method OTHER UT V 411/05 PT Mi RT ET VT 10/04/93 X UT OExamDate l Cor9ents:
DURING ULTRASONIC EXAMINAfl0N (BASELINE) 0F STEAM GENERATOR WELD 21201 86 004 WO3, NON GEOMETRIC INDICAil0NS WERE RECORDED. FURTHER EXAMINATIONS AND EVALUATIONS WITH OTHER TECHNIQUES, AS ALLOWED IN IWB 3200 of ASME SECTION MI, RESULTED WITH ALL INDICAfl0NS SEING CODE ACCEPTABLE.
SEE ATTACHED REPORTS FOR FURTHER INFORMATION.
ew _ a 10 b O 3 Date Signature ITS Edineer/Date ITS ServistorVDate DS. 6,(l e n th hc1 Ituuy b/ /_ D.b.MA2r oc_ S t /v v MC ID d/ 3 Part 2 - Notification Title Date kdTTicat'on Acknowl ged By
%7. $n a r . 10 h _3 I w .
Paat 3 Discesition by Doerotina cercany
[orv'ents:
h A Corre*tive Action:
I g Date A gnat e Operati Title I A A bg $C . Representitive Sc. Eog ick/93
( N 4a Re exed nation efter Coerective action Mh Peet 4b - Additionel Examinations (Scope Exoension)
H Part 4e - Successive Enemination? (future Exem Reauirements) wA Date Signature ITS Engineer D E . [' C A t t A + L- t .YELrdv- oc t o-13 -9 3 Y Date Part 5 ANIX Review T ik $O /O-If '/3 ITSEngfneer # Date Part 6 1'F Fi l'RN Title
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INF Form-002 A South $rn Nuclear Operating Conpany INF No. 193v2022 i Indication Notification Part 1 - Findings l
Procedure / Revision !
Exam Date NDE Method OTHER UT-V-404 /06 MT RT ET VT 10/07/93 X UT PT Corrent s :
DURlWG ULTRASONIC EXAMINATION OF WELD 21301 004 14, INDICATIONS WERE RECORDED. ALL INDICATIONS ARE ACCEPTABLE PER ASME SECTION XI.
SEE ATTACHED REPORTS.
Date Signatu - Lead NDE vel 111
.it a= _ .
\ 0-& n3 ITS Supervision /Date Date Signature-ITSEnhneer/Date 0 (L7 E L F f v v [r h , b M A"2 E E R il t f[4 v L IO-b*b 3 D.h . b IL AL A A w Pa*t 2 kotification Date
- ification Acknowl d;ed By Title 57- ( 0.- -
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Part 3 - Dismsition by Operating Crroany Coment s :
N/A J_ Corrective Action:
N/A Date l
'J' - ure Operating C . Representitive Title
' 2% h b ;r bn ,e
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Part 4e - Pe-eventination ef ter Corrective Action I N/A Part 4b - additional Eseminations (Seone Expension)
N/A Port 4e - Successive Eneminations (Future Exem Pecuirements) l W/A Date Signature ITS Engineer l' C lO'N-O 3 d D.E. b/LAn% eft lf Lt,(0 +
Date Part 5 ANil Review /s Y- ~ tmufUi6 Date l0-Ik
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Swchsrn Euclose Operating Company INF-Form-002 A lNF No.19,lgp))
Indication Notification Part 1 - Findines Procedure / Revision NDE Method OExamDate 10/06/93 X UT PT MT RT ET VT OTHER UT v 404/06 ConperitsI During ultrasonic examination of weld 21301 004 5, an indication was recorded telch le acceptable per ASME Section XI.
Date Stonet Lead NDE Level Ill
, A ,(n .
10-l5*3 )
signature ITs kngineer/Date ITS Supervision /Date Date D. E (2 f-A H A- ftdE L twc 'OL A . ly. /b A tr fv- TtLsi f L IU'I'I'N )
Part 2 - Notifiestion A444stion Acknowledged By Title Date I MN 5;e. %. Gm ts 10 G *15 Per[3 - DisDosition by Operatina Corpeny Cernent s :
N/A i
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O Corrective Action:
N/A A ture Operating Co. Representitive Title Date d kk _
SD- (ngt. IC 15 *'83 Part 4e Re examination efter Corrective Action N/A Part 4b Additional Examinations (Scope Excension) l N/A Port 4e - Successive Examinations (Future Exam Reevirements)
N/A signature - ITS Engineer Date D. h . b /L A W A s Ptw Ti ce cas SBc l o ts co
, Date Part5AN!!Revdiewitt vu MA 10-!T-p Part 6 1 F F'l Review /Ts}ngine[r Title Date
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) DRAWINGS
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The drawings in this section represent Class 1, 2 and 3 equipment and piping included in the outage scope. These drawings give the identification number and location of welds, supports, and other items that require examination.
The drawings are intended for ISI use only and should not be confused with !
design drawings.
The drawings which follow are listed by system designation, drawing number, and drawing revision number.
EQUIPMENT DRAVINGS Drawing Drawing Revision System Number Number Reactor Coolant ISI-21201-B6-001 (Sh. 1) 2 ISI-21201-B6-001 (Sh. 2) 1 ISI-21201-B6-001 (Sh. 3) 0 ISI-21201-B6-001 (Sh. 4) 0 ISI-21201-B6-002 (Sh. 1) 2 ISI-21201-B6-002 (Sh. 2) 1 ISI-21201-B6-002 (Sh. 3) 0 ISI-21201-B6-002 (Sh. 4) 0
,s ISI-21201-B6-003 (Sh. 1) 2
(
) ISI-21201-B6-003 (Sh. 2) 1 ISI-21201-B6-003 (Sh. 3) 0 ISI-21201-B6-003 (Sh. 4) 0 ISI-21201-B6-004 (Sh. 1) 2 ISI-21201-B6-004 (Sh. 2) 1 ISI-21201-B6-004 (Sh. 3) 0 ISI-21201-B6-004 (Sh. 4) 0 ISI-21201-P6-001 1 ISI-21201-P6-002 1 ISI-21201-P6-003 1 ISI-21201-P6-004 1 ISI-21201-V6-001 (Sh. 1) 0 ISI-21201-V6-001 (Sh. 2) 0 ISI-21201-V6-001 (Sh. 3) 0 ISI-21201-V6-001 (Sh. 4) 0 Component Cooling ISI-21203-P4-001 0 Residual Heat Removal ISI-21205-E6-002 (Sh. 1) 3 ISI-21205-E6-002 (Sh. 2) 0 ISI-21205-P6-001 0 ISI-21205-P6-002 0 Containment Spray ISI-21206-T6-001 0 Chemical and 4 Volume Control ISI-21208-E6-001 o 18-1
EQUIPMENT DRAVINGS - (continued)
Drawing Drawing Revision System Number Number Spent Fuel Cooling ISI-21213-P6-002 0 Safety Related (ESF) ISI-21592-P7-001 0 ISI-21592-T7-001 0 Chillers PIPING DRAWINGS 151-21201-001 2 Reactor Coolant ISI-21201-002 2 ISI-21201-003 2 151-21201-004 2 ISI-21201-005 2 ISI-21201-008 2 ISI-21201-012 2 1S1-21201-030 (Sh. 1) 3 151-21201-030 (Sh. 2) 2 ISI-21201-049 1 ISI-21201-051 1 ISI-21201-053 2 ISI-21201-056 1 ISI-21201-057 2 O ISI-21201-058 1 Nuclear Service 151-21202-140 1 Cooling Water ISI-21202-188 (Sh. 1) 2 151-21202-188 (Sh. 2) 2 ISI-21202-192 (Sh. 1) 1 ISI-21202-192 (Sh. 2) 1 ISI-21202-192 (Sh. 3) 1 ISI-21202-192 (Sh. 4) 1 ISI-21202-196 (Sh. 1) 1 ISI-21202-196 (Sh. 2) 1 ISI-21202-196 (Sh. 3) 1 151-21202-212 (Sh. 1) 1 ISI-21202-212 (Sh. 2) 1 ISI-21202-212 (Sh. 3) 1 ISI-21202-231 (Sh. 1) 2 151-21202-231 (Sh. 2) 2 ISI-21202-231 (Sh. 3) 2 Safety Injection 151-21204-016 3 ISI-21204-021 2 ISI-21204-023 2 ISI-21204-025 4 151-21204-030 (Sh. 1) 2 1S1-21204-030 (Sh. 2) 3 O 18-2
1 4
PIPING DRAWINGS - (continued)
Drawing l Drawing Revision System Number Number l
Safety Injection ISI-21204-039 (Sh. 1) 1 l
(continued) ISI-21204-039 (Sh. 2) 1 ISI-21204-041 (Sh. 1) 1 ISI-21204-041 (Sh. 2) 1 ISI-21204-063 (Sh. 1) 2 ISI-21204-063 (Sh. 2) 1 ISI-21204-076 (Sh. 1) 2 ISI-21204-076 (Sh. 2) 2 ISI-21204-077 1 ISI-21204-079 1 ISI-21204-121 1 ,
ISI-21204-127 1 151-21204-201 1 ISI-21204-246 1 Residual Heat Removal 1S1-21205-003 (Sh. 1) 1 ISI-21205-003 (Sh. 2) 3 15I-21205-003 (Sh. 3) 2 1S1-21205-003 (Sh. 4) 2 ISI-21205-004 (Sh. 1) 1 ISI-21205-004 (Sh. 2)
O 2
151-2]205-004 (Sh. 3) 2 ISI-21205-005 (Sh. 1) 1 ISI-21205-005 (Sh. 2) 1 ISI-21205-006 (Sh. 1) 2 151-21205-006 (Sh. 2) 2 ISI-21205-007 (Sh. 1) 1 ISI-21205-007 (Sh. 2) 3 151-21205-007 (Sh. 3) 1 .
ISI-21205-007 (Sh. 4) 2 ISI-21205-007 (Sh. 5) 2 151-21205-008 (Sh. 1) 1 151-21205-008 (Sh. 2) 1 151-21205-008 (Sh. 3) 3 ISI-21205-008 (Sh. 4) 2 ISI-21205-010 (Sh. 1) 2 151-21205-010 (Sh. 2) 2 Containment Spray ISI-21206-002 (Sh. 1) 1 ;
ISI-21206-002 (Sh. 2) 2 ISI-21206-004 2 :
ISI-21206-008 2 l Chemical and 151-21208-007 1 Volume Control ISI-21208-012 1 151-21208-043 1 18-3
PIPING DRAVINGS - (continued)
Drawing Drawing Revision System Number Number j l
Chemical and ISI-21208-047 2 l Volume Control ISI-21208-139 1 (continued) ISI-21208-141 2 ISI-21208-146 (Sh. 1) 2 ISI-21208-146 (Sh. 2) 2 Main Steam ISI-21301-004 (Sh. 1) 1 ISI-21301-004 (Sh. 2) 1 j ISI-21301-014 1 ISI-21301-016 2 :
ISI-21301-104 2 l l
ISI-21301-107 2 Auxiliary Feedwater 151-21302-107 (Sh. 1) 2 .
151-21302-107 (Sh. 2) 2 l 151-21302-107 (Sh. 3) 1 ISI-21302-108 (Sh. 1) 1 ISI-21302-108 (Sh. 2) 2 ISI-21302-108 (Sh. 3) 1 ISI-21302-109 (Sh. 1) 2 O ISI-21302-109 (Sh. 2)
ISI-21302-109 (Sh. 3) 1 1
ISI-21302-110 (Sh. 1) 1 ISI-21302-110 (Sh. 2) 1 ISI-21302-110 (Sh. 3) 1 Condensate and 151-21305-058 (Sh. 1) 1 Feedwater ISI-21305-058 (Sh. 2) 1 ,
151-21305-060 (Sh. 1) 1 1 ISI-21305-060 (Sh. 2) 1 I ISI-21305-062 (Sh. 1) 1 ISI-21305-062 (Sh. 2) 1 15I-21305-064 (Sh. 1) 1 ISI-21305-064 (Sh. 2) 1 ISI-21305-156 1 Containment Heat ISI-21501-038 1 Removal (NSCW)
O 18-4 i
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