ML18037A766
| ML18037A766 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/21/1993 |
| From: | Froscello F TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18037A765 | List: |
| References | |
| 2-SI-4.6.G, NUDOCS 9403070216 | |
| Download: ML18037A766 (314) | |
Text
TENNESSEE VALLEY AUTHORITY BROMNS FERRY NUCLEAR PLANT SURVEILLANCE INSTRUCTION 2-SI-4,6,G INSERVICE INSPECTION PROGRAN UNIT 2 REVISION 2 PREPARED BY: F. W. FROSCELLO PHONE: 3524 RESPONSIBLE ORGANIZATION: NUCLEAR ENGINEERING APPROVED BY: M. BAJESTANI DATE: 10/21/93 EFFECTIVE DATE: 11/02/93 LEVEL OF USE,'CONTINUOUS USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED 94030702 PDR ADOCh 940222 9 K PQPPP2+
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ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 BFN UNIT 2 INSERVICE INSPECTION PROGRAM REVISION 2
I (2041)
REVISION LOG Procedure Number: 2-SI-4.6.G Revision Number: 2 Pages Affected: 1, 3, 6, 10, ll, 15-26, 28-30, 37, 38, 40-60, 62, 64-66% 68% 70-74% 76-81% 84, 86-90 Pagination Pages: 2, 4, 5, 7-9, 12-14, 27, 31-36, 39, 61, 63, 67, 69, 75, 82, 83, 85 Description of Change:
Paragraph 7.0/8.0 renumbered reference to page numbers.
Paragraph 1.2 6 1.1 organizational changes.
Renumbered paragraphs on ISI drawings.
Change organizational name change, transfer of responsibilities.
Renumber of paragraphs.
Deleted requirement for use of NOI (Notification of Indication) added system to paragraph 7.3.5 and (4).
Section Change numbers.
Organizational responsibilities changes and reference to paragraphs and sections.
Word change page 50 paragraph 7.12.8 and added note and ANII requirement.
Added exam requirement in Voluntary Examinations.
Added a list of and status of request for relief.
Changed sample (inspection) amounts and inspection intervals.
Added inspections and sample amounts.
Deleted inspections.
Changed number of components in Examination schedule.
Change note 1 in notes section.
Changed note 5 in notes class 2 components exam schedule.
Delet inspections and add new inspections (weld numbers) and IGSCC exam category.
Drawing change on Section 8.3.
Add ISI Request for Relief 2-2 thru 2-4.
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2-SI-4.6.G Page 1 ~
TABLE OF CONTENTS Owner I s Statement 2 1 ~0 INTRODUCTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 1.1 Purpose 4 1.2 Scope (Applicabi.lity) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~, 4 1.3 Frequency .............................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5
2.0 REFERENCES
.................".................................. 6 3.0 PRECAUTIONS AND LIMITATIONS .................................. 12 4.0 CODES OF RECORD AND CODE CASES .............. ................ 12 5.0 SPECIAL TOOLS AND EQUIPMENT ........ ... ... ................ 15 6.0 ACCEPTANCE STANDARDS ..... ...o....... . ... o.......... .... ~ 15 7.0 INSTRUCTION STEPS/ELEMENTS 15 7.1 Responsibilities
~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 15 7.2 Implementation ................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 23 31 7.3 Components Subject to Examination ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
7 ' Calibration Standards ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 41 7.5 Records and Reports ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 41 7.6 Requests for Relief (RFR) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 42 7.7 Corrective Action Program ........ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ , ~ 43 43 7.8 Repairs and Replacements ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
7.9 System Pressure Tests ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 43 7.10 Pump and Valve Inservice Testing ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 ~ ~ ~ ~ ~ ~ ~ ~ 43 7.11 Snubber Inservice Testing ........ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 43 44 7.12 Augmented Examinations ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
7.13 Voluntary Examinations ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 52 8.0 TABLES/ATTACHMENTS ........................................... 53 8.1 Examination Schedules ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 54 8.2 Lists of Stainless Steel and Dissimilar Metal Welds )=4" Diameter .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 76 8.3 Class 1 Valve List ......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 81 8.4 Requests for Relief ........ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 84 77(235)
2-SI-4 '.G Page 2 OWNER'S STATEMENT Owner Tennessee'Valley Authority Address of Corporate Office Chattanooga Office Complex 1101 Market Street Chattanooga, TN 37402-2801 Name & Address of Power Plant Browns Ferry Nuclear Plant P.O Box 2000 Decatur, AL 35609 Applicable Nuclear Power Unit: BFN, Unit 2 Commercial Operation Date: March 1, 1975 Construction Permit was issued prior to January 1, 1971
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2-SI-4.6.G Page 3
~Pur ose This Inservice Inspection (ISI) Program is an administrative Surveillance Instruction (SI) employed to obtain data via nondestructive examinations (NDE) of .ASME Section XI Code Class 1, 2, and 3 equivalent components that can be used to determine if a flaw is an isolated case or is of a generic nature. It shall serve as TVA's ISI plan and schedule in accordance with the requirements of IWA-1400. The examinations required by this program shall establish acceptance for continued use of components during operation.
This program is organized to comply with the ISI NDE requirements of the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Division 1, Articles 1000, 2000, 3000, and 6000 in accordance with Title 10 Code of'ederal Regulations (CFR) Part 50, 50.55a(g); to implement the Browns Ferry Nuclear Plant (BFN)
Technical Specifications, Unit 2, Surveillance Requirement 4.6.G.; and to fulfill the requirements of SSP-6.10, ASME Section XI Inservice Inspection Program.
This ISI Program reflects the built-in limitations of the original plant design, geometry, construction, component materials, and the current technology or state-of-the-art nondestructive examination techniques. It specifies the number of components to be examined, the examination methods to be used and provides schedule tables from which specific items are scheduled for examination by Mechanical/Nuclear (M/N) Engineering via lists submitted to Corporate Engineering, Materials E Inspection (M & I). These items are officially documented in scan plans for each refueling outage.
1.2 Sco e (A licabilit )
This program outlines details for planning and performing the second inspection interval NDE for the ASME Section XI Code Class 1, 2, and 3 equivalent components at BFN in accordance with IWA-2432, Inspection Program B.
The ASME Section XI Code Class Boundary Drawings and the ISI Drawings listed in Section 2.5 identify the components and systems to be examined. These drawings are prepared and maintained by M/N Engineering and are issued and controlled
~
through BFN Records Management (RM).
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2-SI-4.6. G Page 4.
1.0 INTRODUCTION
(Continued)
Personnel responsible for performance of the examinations should familiarize themselves with the requirements of this program prior to performing the examinations; Specifics concerning performance of NDE are not a part of this program, but are included in QMP 110.5, NDE Procedures Manual.
Elements of ASME Section XI, Articles 4000, 5000, 6000, and 7000 other than NDE, such as Pump and Valve Inservice Testing, Snubber Inservice Testing, Repairs and Replacements, and System Pressure Tests, are covered by other procedures. See Sections 7.8, 7.9, 7.10, and 7.11.
1.3 ~Fre uecc 1.3.1 Ins ection Interval and Ins ection Periods The ISI examinations required by ASME Section XI, Division 1, IWA-2432, Inspection Program B shall be performed during this inspection interval (May 24, 1992 to May 24, 2001). The inspection interval duration is nine years since the first interval was. extended by one year per IWA-2400(a), 1974 Edition/Summer 1975 Addenda (See IWA-2430(d), 1986 Edition for equivalent rule).
The inspection interval shall be separated into three inspection periods of three years each. Except for examinations that may be deferred to the end of the inspection interval, the required examinations shall be performed in accordance with the following schedule that complies with IWB-2412, Program B and Table IWB-2412-1; IWC-2412, Program B and Table IWC-2412-1; IWD-2412, Program B and Table IWD-2412-1; and (N-491)-2410(b) and (c) and Table -2410-2, Program B.
Inspection Minimum Examinations Maximum Examinations Period Com leted X Com leted First (5/92-5/95) 16 34 Second (5/95-5/98) 50 67 Third (5/98-5/01) 100 100 The examinations deferred to the end of the inspection interval shall be completed before the end of the inspection interval. The inspection interval may be extended in accordance with IWA-2430(e) if unit 2 is out of service continuously for six months or more.
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2.0 REFERENCES
2.1 Technical S ecifications BFN Unit 2 Technical Specifications, Surveillance Requirement 3/4.6.G, Structural Integrity.
2.2 Final Safet Anal sis Re ort Browns Ferry Nuclear Plant Updated'inal Safety Analysis Report, Volume 2, Section 4.12.
2.3 NRC Documents 10 CFR Part 50, 50.55a(g).
10 CFR Part 50.2.
Guide 1.147. 'egulatory IE Bulletin 80-13, Core Spray Spargers.
Generic Letter 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.
NUREG-0313, Rev. 2, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, Final Report.
NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking.
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t 2-SI-4.6.G Page 6
2.0 REFERENCES
(Continued) 2.4 Plant Procedures and Instructions SSP-3.1,, Quality Assurance Program.
SSP-3.4, Corrective Action.
SSP-4.5, Regulatory Reporting Requirements.
SSP-6.9, ASME Section ZI Repairs and Replacements.
SSP-6.10, ASME Section XI Inservice Inspection.
SSP-8.5, ASME Section XI System Pressure Test Program.
SSP-8.6, ASME Section ZI Pump and Valve Inservice Testing.
2-SI-4.6."H.l, Visual Examination of Hydraulic and Mechanical Snubbers.
MCI-0-001-VLV001, Main Steam Isolation Valves Atwood Morrill Co.
Disassembly, Inspection, Rework, and Reassembly.
MCI-0-001-VLV002, Main Steam Relief Valves Target Rock Model 7567 Disassembly, Inspection, Rework, and Reassembly.
MMI-1, Reactor Vessel and Cavity Disassembly and Reassembly.
MMI-13, Main Steam Relief Valves.
MMI-21, Reactor Recirculation Pump Rotating Assembly, Removal, and Replacement; MMI-46, Liquid Penetrant Examination of Piping and Piping Components Which Were Exposed to Residue from Plant Fire Unit 1 and 2.
MMI-53, Evaluation of Corrosion Damage of Piping Components Which Were Exposed to Residue from March 22, 1975 Fire (cancelled).
MMI-182, Reactor Vessel Internals Visual and Ultrasonic Inspection Units 1, 2, and 3.
QMP 102.4, Qualification and Certification Requirements for NQA NDE Personnel.
QMP 110.5, Nondestructive Examination Procedures Approved for use on CSSC Items at all Nuclear Plants.
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2-SI-4.6.G Page 7.
2.5.1 Unit 0 Section XI Code Class Boundary Drawings 47W600-57A-ISI, RCS Instrumentation.
47W600-58A-ISI, RCS Instr.
47W600-135A-ISI, RCS Instr.
47E610-43-1-ISI, Condensate/RHR/RHRSW/RWCU/S&WQ Instr.
47E610-43-4-ISI, MS/FW/S&WQ Instr.
\
47W1600-301-ISI, RCS Instr.
47W2600-302-ISI, RCS Instr.
GE117C2556-ISI, RCS Instr.
GE117C2563-ISI, RCS Instr.
GE117C2564-ISI, RCS Instr.
GE164C5981-ISI, RCS Instr.
GE16405984-ISI, RCS Instr.
GE164C5985-ISI, RCS Instr.
2.5.2 Unit 2 Section XI Code Class Boundary Drawings 2-47E801-1-ISI, Main Steam.
2-47E801-2-ISI, Main Steam.
2-47E803-1-ISI, Feedwater.
2-47E803-5-ISI, Feedwater.
2-47E807-2-ISI, Turbine Drains & Misc Piping.
0 77(235)
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2.0 REFERENCES
(Continued) 2-47E810-1-ISI, Reactor Water Cleanup.
2-47E811-1-ISI, Residual Heat Removal.
2-47E812-1-ISI, High Pressure Coolant Injection.
2-47E813-1-ISI, Reactor Core Isolation Cooling.
2-47E814-1-ISI, Core Spray.
2-47E817-1-ISI, Nuclear Boiler.
2-47E820-2-ISI, Control Rod Drive Hydraulic.
2-47E2820-6-ISI, Control Rod Drive Hydraulic.
2-47E822-1-ISI, Reactor Bldg Closed Cooling Water.
2-47E844-2-ISI, Raw Cooling Water.
2-47E852-1-ISI, Floor and Dirty Radwaste Drainage.
2-47E852-2-ISI, Clean Radwaste & Decon Drainage.
2-47E854-1-ISI, Standby Liquid Control.
2-47E855-1-ISI, Fuel Pool Cooling.
2-47E856-2-ISI, Demineralized Water.
2-47E858-1-ISI, RHR Service Water.
2-47E859-1-ISI, Emergency Equipment Cooling Water.
2.5. 3 Unit 0 ISI Component Support Drawing ISI-0368-C, EECW and RHRSW Pumping Station Class 3.
ISI-0390-C, EECW Unit 3 Class 3.
ISI-0391-C, Raw Cooling Water Unit 1 Class 3.
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2.0 REFERENCES
(Continued) 2.5.4 Unit 2 ISI Bolting, Nozzles, and Welds Drawings CHM-2046-C, Reactor Vessel Nozzle and Weld Locations Class 1.
ISI-0351-A, Instrumentation Nozzles Class 1.
ISI-0312-B, Main Steam Bolting Class 1.
ISI-0347-B, Recirculation Inlet Nozzles Class l.
ISI-0031-C, Reactor Building Closed Cooling Water System Class 2 Welds.
ISI-0040-C, CRD Hydraulic Header Class 2 Welds.
ISI-0103-C, Core Spray System Class 2 Welds.
ISI-0128-C, HPCI System Class 2 Welds.
ISI-0129-C, RCIC System Class 2 Welds.
ISI-0221-C, RHR System Class 1 Welds.
ISI-0222-C, Main Steam System Class 1 Welds.
ISI-0266-C, Vessel Stud Locations Class 1.
ISI-0269-C, Feedwater System Class 1 Welds.
ISI-0270-C, Recirculation System Class 1 Welds.
ISI-0271-Ci Core Spray System Class 1 Welds.
ISI-0272-C, RWCU, RCIC, and CRD Systems Class 1 Welds.
ISI-0273-C, HPCI System Class 1 Welds.
ISI-0292-C, Control Rod Drive Penetrations, Drain Nozzle, and Flux Monitor Nozzles Class 1.
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2-SI-4.6.G Page 10 e
2.0 REFERENCES
(Continued)
ISI-0380-C, Standby Liquid Control* System Class ISI-0383-C, Feedwater Instrumentation Class 1 1 Welds.
Welds.
ISI-0406-C, RHR Heat Exchanger Welds and Supports Class 2.
ISI-0407-C, Recirculation Pump Bolting Class l.
ISI-0408-C, Closure Head Assembly Class l.
ISI-0410-C, Jet Pump Instrument Nozzle Class 1.
MSG-0018-C, RHR System Class 2 Welds.
MSG-0021-C, Main Steam Class 2 Welds.
2.5.5 Unit 2 ISI Component Support Drawings ISI-0310-B, RHR Pump Class 2.
ISI-0032-C, Reactor Building Closed Cooling Water System Class 2.
ISI-0041-C, CRD Header Class 2.
ISI-0079-C, Main Steam System Class 2.
ISI-0105-C, Core Spray System Class 2.
ISI-0130-0% HPCI System Class 2.
ISI-0131-C, RCIC System Class 2.
ISI-0133-C, FPC System Class 3.
ISI-0145-C, RHR Service Water System Class 3.
ISI-0274-C, RWCU, RCIC, and CRD Systems Class 1.
ISI-0275-C, HPCI System Class l.
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2.0 REFERENCES
{Continued)
ISI-0276-C, RHR System Class l.
ISI-0277-C, Feedwater System Class 1.
ISI-0278-C, Recirculation System Class 1.
. ISI-0279-C, Main Steam System Class 1.
ISI-0280-C, Core Spray System Class 1.
ISI-0324-C, RHR System Class 2.
ISI-0379-C, Standby Liquid Control System Class 1.
ISI-0387-C, Feedwater Instrumentation Class l.
ISI-0412-C, Main Steam Relief Valve Blowdown Class 3.
ISI-0415-C, Reactor Vessel Class l.
2.6 Interface Documents 2.6.1 BFN-VTM-B014-0010, BEW Reactor Pressure Vessel Manual, Contract 66C60-90744.
2.6.2 BFN-VTM-B014-0010, NJ Recirculation Pump Manual, Contract 67C60-91750.
2.6.3 BFN-VTM-B260-0030, Bingham Pump Co. RHR Pump Manual, Contract 66C60-90744.
2.6.4 BFN-VTM-B014-0010, Vendor Technical Manual For Prefex Corp. Heat Exchangers Types NEN, CEU, CES, and CEN, Contract 66C60-90744.
2.7 Reference Documents ASME Boiler and Pressure Vessel Code,Section XI,.Division 1, 1986 Edition.
ASME Section XI Code Cases as listed in Section 4.1.
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2-SI-4.6.G Page li 3.0 PRECAUTIONS AND LIMITATIONS RADCON shall be contacted prior to any work in a radiologically controlled area (RCA). RADCON shall determine the requirements for a radiological work permit (RWP) and any other radiological requirements.
4.0 CODES OF RECORD AND CODE CASES 4.1 Current Code Re uirements and Code Cases This program is in effect for unit 2 for the second inspection interval beginning on'May 24, 1992. The Units 1 and 3 program is contained in 1/3-SI-4.6.G.
The Code of Record for the second inspection interval of unit 2 is the 1986 Edition of the ASME Boiler and Pressure Vessel Code,Section XI, Division 1 in accordance with 10 CFR 50, 50.55a(g)(4). Additionally, in accordance with 10 CFR 50, 50.55a(b)(2)(ii), the extent of examination for Examination Category B-J welds shall be in accordance with the 1974 Edition, Summer 1975 Addenda of ASME Section XI. Extent of examination is defined as the cri,teria for the selection of the Class 1 B-J welds to 'be examined. See Section 7.3.2.B.
Certification of NDE personnel shall be in accordance with the 1984 Edition of ASNT SNT-TC-1A as approved by the Nuclear Regulatory Commission's (NRC's) letter from S. C. Black to 0. D.
Kingsley, Jr., dated January 18, 1990 (TAC No. 72833).
TVA shall use the following Code Cases that have been approved'by the NRC per Regulatory Guide 1.147 or by special written permission from the NRC:
A. Code Case N-307-1, Revised Ultrasonic Examination Volume for Class 1 Bolting, Table IWB-2500-1, Examination Category B-G-1, When the Examinations Are Conducted From the Center-Drilled Hole,Section XI, Division l.
B. Code Case N-435-1, Alternative Examination Requirements for Vessels With Wall Thickness 2 in. or Less,Section XI, Division l.
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t 2-SI-4.6.G Page 13 4.0 CODES OF RECORD AND CODE CASES (Continued)
C. Code Case N-445, Use of Later Editions o'f SNT-TC-1A for Qualification of Nondestructive Examination Personnel,Section XI, Division 1.
D. Code Case N-457, Qualification Specimen Notch Location for Ultrasonic Examination of Bolts and Studs,Section XI, Division l.
E. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1.
F. Code Case N-461, Alternative Rules for Piping Calibration Block Thickness,Section XI, Division l.
G. Code Case N-491, Alternative Rules for Examination of Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Power Plants,Section XI, Division l. Use approved by the Nuclear Regulatory Commission's (NRC's) letter from Fredrick J. Hebdon to Dr. Mark 0. Medford, dated May 18, 1992 (TAC Nos. M81952, M81953, and M81954).
4.2 Histor of Codes of Record and Code Cases For unit 2 a preservice inspection (PSI) program was not required. TVA performed a self-imposed PSI program for Class 1 components to the 1971 Edition, Summer 1971 Addenda of ASME Section XI.
For unit 2 the history of the ASME Section XI code of record and Code Cases used are as follows:
A. The first period of the first interval, in effect from March 1, 1975 through July 1, 1981, was to the 1971 Edition, Summer 1971 Addenda of ASME Section XI. The long duration on this period was due to an extension for the fire outage and an additional one year extension in accordance with IWA-2400 to establish concurrent intervals for units 1, 2, and 3 beginning with the second period. See NRC letter dated June 20, 1986 (A02 860630 006) for approval of these adjustments.
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2-SI-4.6.G Page 14 CODES OF RECORD AND CODE CASES (Continued)
B. The second period (July 1, 1981 through"July 7, 1988) and the third period (February 26, 1986 through May 23, 1992) were to the 1974 Edition with Addenda through Summer 1975 of ASME Section XI. Ultrasonic examination and evaluation of piping welds was upgraded to the 1977 Edition, Summer 1978 Addenda of ASME Section XI for these periods. This included examination per IWA-2232(b), IWA-2232(c), and Appendix III (to the extent specified in Request for Relief ISI-15) and evaluation per IWA-3000, IWB-3000, and IWC-3000 of the 1977 Edition, Summer 1978 Addenda.
The overlap of the second and third periods occurred because of the extended outage from September 15; 1984 to May 24, 1991 and TVA's decision to complete the second and third period examinations during this time to close out the first interval. This decision was made since the first interval had been extended twice and it was prudent to end it and commence with a second inspection interval to a current Edition of ASME Section XI.
C. Beginning January 1, 1992, the preservice inspection of pipe welds, including the extent of examination, (Examination Categories B-F, B-J, and C-F) was performed in accordance with the 1977 Edition, Summer 1978 Addenda of ASME Section XI, IWA-2232, IWA-3000, IWB-2200(c), Table IWB-2500-1, and Table IWC-2500-1.
D. Code Cases N-234, 235, 307-1, 308, 341, 356, 416, 435-1, 460, and 461 that were approved by Regulatory Guide 1.147 were used at BFN during the first interval.
5.0 SPECIAL TOOLS AND E UIPMENT t
Equipment shall be specified and controlled by individual NDE Procedures.
6.0 ACCEPTANCE STANDARDS The acceptance criteria shall be in accordance with the individual NDE Procedures of QMP 110.5 that shall comply with the requirements of ASME Section XI, Articles IWA-3000, IWB-3000, IWC-3000, IWD-3000, and (N-491)-3000.
Evaluations of examinations in accordance with IWB-3132.4, IWB-3142.4, IWC-3122.4, IWC-3132.4, (N-491)-3112.3, or (N-491)-3122.1 shall be submitted to the regulatory authority having jurisdiction at the plant site. This information shall be submitted with the Inservice Inspection Summary Report or, if deemed necessary, a separate report shall be submitted.
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t 2-SI-4.6.G Page 15 7.0 INSTRUCTION STEPS/ELEMENTS Any revisions initiated by other groups shall be submitted to M/N Engineering for approval prior to incorporating the revisions into this program.
7.1 Res onsibilities 7.1.1 Corporate Engineering, Materials & Inspection (M & I) responsibilities:
A. Providing ISI and/or PSI ASME Section XI interpretations as requested by various site organizations or as required in program development and implementation.
B. Providing assessments and oversite of this program and ISI activities on site.
C. Review and comment all PSI/ISI Program Requests for relief prior to issuance.
7.1 ~ 2 M/N Engineering responsibilities:
A. Defining ASME Section XI Code Class 1, 2, and 3 equivalent boundaries in accordance with 10 CFR 50.2, 10 CFR 50.55a, ASME Section XI, and Regulatory Guide 1.26, R3.
B. Preparing/revising ASME Section XI Code Class Boundary Drawings to identify the ASME Section XI Class 1, 2, and 3 equivalent boundaries within each plant system as defined in 7.1.1.A. See Section 2.5 for drawing list.
C. Preparing/revising ASME Section XI ISI drawings that identify the Class 1, 2, and 3 equivalent components (including supports) that require inservice and/or preservice nondestructive examination (NDE) to comply with ASME Section XI requirements. See Section 2.5 for drawing list.
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t 2-SI-4.6.G Page 16 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
D. Preparing/revising this instruction (ISI Program) and submitting it to (1) RM for approval and issue as a controlled document (2) RM for subsequent submittal to the ANII for a detailed review per IWA-2110(a)(1) and (a)(2) See Sections 7 ' 5.A and 7 1 S.AD
~ ~ ~ ~
(3) Site Licensing for subsequent submittal to the NRC ~ See Section 7 ' 4.A
~
ED Ensuring that this program provides detailed instructions for ISI including the following information as a minimum (1) The ASME Section XI Code of Record for ISIS (2) The inspection interval (3) A list of the ASME Section XI Code Class Boundary drawings'4)
A list of the ASME Section XI ISI drawings'5) examination schedule providing the total intervaled An number of each Code Item Number, the number of samples for the inspection interval, and the number of samples for each period of the (6) The NDE method to be used for each Item Number (7) The ASME Examination Category and Item Number for each component (8) Copies of all Relief Requests (9) Name and address of the Owner (10) Name and address of generating plant 77(235)
t 2-SI-4.6.G Page 17 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
(11) Name or number designation of the unit.
(12) Commercial operation date of the unit.
(13) A description of the system for maintaining status of completed examinations.
(14) A discussion of scan plans that provide details of required component examinations, such as component identifier, NDE procedure, calibration standard reference, ISI drawing number, sheet number, etc.
(15) Augmented examination requirements closely related to ASME Section XI based on other codes/standards,:regulatory guides, NRC commitments, etc.
F. Providing a list of components scheduled for examination during each refueling outage to M&I for scan plan development. This list shall include the component identifier, ASME Section XI examination category and item number, examination method, ISI drawing number and sheet number, and examination requirement source. See Section 7.2.1.B.
G. Approving the scan plan and revisions and submitting copies of the approved scan plan to site management and the ANII. See Section 7.2.1.B.
H. Providing any additional samples required due to examinations performed. See Section 7.2.2.
I. Notifying Site Engineering of an indication found during the final additional sample examination for their evaluation. See Sections 7.1.3.C and 7.2.2.B.(4).
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,2-SI-4.6.G Page 18 7.P iNSTRUCTION STEPS/ELEMENTS (Continued)
J. Prepa ring a Re q ues t for Relief'(RFR) when required because of areas that are inaccessible or partially inaccessible for examination or because it is determined that conformance with Code requirements is impractical. See Sections 7.1.5.D and 7.2.3.E for M & I responsibilities of notifying M/N Engineering if limited exams indicate the need to initiate an RFR. See Section 7.6.
K. Submitting Requests for Relief to the Site Licensing organization. See Section 7.6.
L. Performing NDE per the requirements of this instruction. See Section 7.2.3.
M. Ensuring that ISI/PSI examinations are performed in accordance with TVA NDE procedures or in accordance with contractor procedures that have been authorized for use by M & I. See Section 7.2.3.
N. Administering AIA contract and ensuring that services of AIA are used when performing Code required activities. TVA's interface with the Authorized Inspector for ISI, repairs, and replacements is defined in SSP-6.9 and SSP-6.10.
- 0. Providing AIA representative with access to plant and documentation in accordance with IVA-2130 of ASME Section XI.
P. Notifying ANII prior to performing examinations.
Q. Preparing IR's, documenting followup examinations, and assuring closure, proper filing, and providing/coordinating dispositions for IR's in accordance with SSP-3.1. See Section 7.2.2.A.
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t 2-SI-4.6.G Page 19 7.0 INSTRVCTION STEPS/ELEMENTS (Continued)
R. Pre P arin g examinati on reports and recording them (report number, date, examiner's initials and comments/IR number) in the scan plan. When inservice examinations are implemented by instructions other than this program (i.e., MMI's),
copies of the examination data sheets shall be submitted to M/N Engineering by the performing organization. These data sheets shall be used as examination reports and incorporated into the scan plan. See Section 7.2.1.B.(3).
S. Ensuring that all scan plan examinations are complete prior to completion of an outage and that all examinations are recorded in the scan plan.
T. Preparing inservice inspection summary reports, preparing augmented examination summary reports, obtaining ANII signature on NIS-1 form, coordinating summary report reviews with M & I, and submitting inservice inspection and augmented examination summary reports to Site Licensing. The- NIS-1 summary report shall be submitted to Site Licensing within 60 days of the end of the outage. See Section 7.5.
0 U. Preparing and submitting the Site Final Report to as a 7.12.4.
QA record. See Sections 7.1.6.C, 7.5, and RM V. Ensuring records used as PSI records from manufacturers, or construction organizations comply with procedures.
W. Calculation of component support acceptance ranges, if required, in accordance with QMP-110.5, N-GP-7 and N-VT-1. See Section 7.3.6.D.
X. Maintaining calibration blocks stored at the plant site. See Section 7.4.
Y. Initiating a pre-outage meeting on augmented examination per Section 7.12.
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t 2-SI-4.6.G Page 20 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.1.3 Site Engineering responsibilities:'.
Designing, fabricating, erecting, and constructing components to quality standards commensurate with the safety function to be performed. This includes designing for access in accordance with ASME Section XI, IWA-1400(b) and IWA-1500.
B. Performing engineering evaluations in support of IR dispositions or other examination indications. See Sections 7.2.2.A and 7.12.
C. Performing evaluations of indications found during final additional sample examinations to determine if further action is required. See Sections 7.1.2.I and 7.2.2.B.(4).
D. Determining those component supports that could be affected by observed failure modes and could affect nonexempt components as prescribed in Section 7.2.2.B.(3).
E. Providing specific written details for any augmented requirements for which they are responsible per Section 7.12 and determining if a post examination meeting is required.
7.1.4 Site Licensing responsibilities:
A. Filing this Surveillance Instruction (2-SI-4.6.G) and revisions with the NRC per IWA-1400(c). M/N Engineering should be included on distribution of correspondence. See Section 7.1.2.D.(3).
B. Submitting Requests for Relief and Summary Reports to the NRC. M/N Engineering should be included on distribution of all related correspondence. See Section 7.1.2.K, 7.1.2.T, and 7.5.
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2-SI-4 ~ 6 ~G Page 21 7.0 'NSTRUCTION STEPS/ELEMENTS (Continued) 7 ' ~ 5 M & I responsibilities Preparing/revising PRISIM Data Base to include all A.
components Section on the 7~2~ 1.A ISI drawings of Section 2' 'ee BE Preparing/revising scan plans for each refueling outage of the inspection interval utilizing PRISIM This includes providing additional information provided by NDE level III personnel to complete the scan plan, such as NDE Procedure references calibration standard references, and UT scanning angles'ee Section 7 ~ 2 ~ 1 ~ B~
CD Providing NDE level III approval of scan plan revisions that affect the additional information of Section 7 '.5 ' and maintaining a scan plan revision history log DE Providing NDE level III determination if a Request for Relief (RFR) is required because of areas that are inaccessible or partially inaccessible for examination or because it is determined that conformance with Code requirements is impractical and notifying M/N Engineering of this fact per Sections 7 ' ' ' and 7 ' 'ee Section 7 ' '.J ~
ED Approving contractor NDE procedures, contractor written practices for qualification and certification of NDE personnel and certifications of contractor's NDE personnel performing ISI/PS'ee Section 7 ' '
Providing NDE level III evaluation of successive examinations' 7 '2 See Sections 7 ' '.E, 7 ' ' ', and
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t 2-SI-4.6.G Page 22 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
G. Packaging radiographs for storage and providing them with reader sheets to RM as a life of plant record.
See Sections 7.1.6.C and 7.5.
H. Providing copies of QMP-110.5 NDE procedure revisions and evidence of personnel qualifications to RM as RIMS records for the service lifetime of the plant in accordance with IWA-1400(k). See Sections 7.1.6.C and 7.5.
I. Maintaining as-built calibration standard drawings and the calibration standard material certifications. See Section 7.4.
7.1.6 Site Records Management (RM) responsibilities:
A. Issuing controlled copies of ASME Section XI Code Class Boundary Drawings and ISI Drawings to specified distribution lists.
B. Issuing this program as an SI and providing controlled copies to M/N Engineering, the ANI/ANII, and other organizations as requested.
C. Maintaining the Site Final Report as a life of plant QA document. Other records referenced in the final report (work plans, radiographs, etc.) and NDE procedure revisions, and evidence of personnel qualifications shall be retained for the service lifetime of the plant. See Sections 7.1.2.U, 7.1.5.G, and 7.5.
7.1.7 Project Management responsibilities:
A. Providing specific written details for any augmented requirements for which they are responsible per Section 7.12 and determining if a post examination meeting is required.
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t 2-SI-4.6.G Page 23 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.1.8 The Authorized Nuclear Inservice Inspector (ANII) responsibilities:
A. Performing the duties of IWA-2110, including a detailed review of this ISI Program (Plan) prior to May 24, 1992 [See IWA-2110(a)(1)] and a review of revisions to this ISI Program [See IWA-2110(a)(2)].
He shall submit a report of the reviews to the Owner
[See IWA-2110(a)(3)]. See Section 7.1.2.D.(2).
B. Having the prerogative and authorization to require requalification of any operator or procedure when he has reason to believe the requirements are not being met.
7.1.9 Nuclear Assurance and Licensing responsibilities:
A+ Nuclear Assurance and Licensing is responsible for reviewing, inspection plans, and/or quality assurance programs submitted by contractors.
7.2 Im lementation 7.2.1 S stem for Maintainin Status of Examinations A. Data Base M 8 I and M/N Engineering shall utilize a computerized data base, PRISIM, for maintaining the status of completed examinations for ASME Section XI credit and for augmented credit. See Sections 7.1.5.A and 7.1.5.B.
B.. Scan Plan The Scan Plan is the primary scheduling document that is developed by M G I from PRISIM. It should contain as a minimum:
components to be examined, Code Examination Category, Code Item Number, methods of examination, NDE procedure reference, calibration standard reference, ISI drawing number and sheet number, and for UT, the scanning angles. See Sections 7.1.2.G, 7.1.2.F, 7.1.5.B, and 7.1.5.C.
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2-SI-4.6.G Page 24 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
(2) Prior to performing examinations, the scan plan shall be approved by M/N Engineering.
(3) When inservice examinations are performed as a result of instructions other than this program (e.g., maintenance instructions, work plans, etc.), copies of the examination data sheets shall be submitted to M/N Engineering by the performing organization for assignment of a report number and incorporation into the scan plan. See Section 7.1.2.R.
(4) During implementation phases, it may become necessary to revise the scan plan. Scan Plan revisions may be initiated by M/N Engineering, M 6 I, or by other personnel involved with implementation of the scan plan. All changes shall be coordinated with an M/N Engineering representative and, as needed, with the appropriate plant planning and scheduling personnel for facilitating the use of supporting craft personnel.
Revisions to the scan plan shall be controlled in the same manner as the original. M 6 I shall maintain a scan plan revision history log. Interim working copies may be handwritten to allow examinations to be performed before a formal revision is issued.
These changes shall be approved by M/N Engineering and/or an NDE Level III, if required by Section 7.1.2.G or Section 7.1.5.C. Approving individuals shall initial and date such changes.
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2-SI-4.6.G Page 25 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
C. Configuration Changes (1) When major portions of existing pipe or supports are replaced or new systems are added, a system walkdown should be performed under the direction of M/N Engineering to
'identify the pipe configuration, welds, components, and supports that shall be included in the inspection program.
(2) If variations in configuration are discovered or modifications (including additions or deletions), repairs or replacements are made during the service lifetime of the unit, the changes shall be marked on field corrected copies of the appropriate drawing listed in Section 2.5 by an M/N Engineering representative. The field corrected copies shall be used in the performance of examinations and as records until the drawing has been revised to reflect the changes.
(3) M/N Engineering shall be responsible for reviewing the proposed change, revising the drawings as necessary, and issuing the revised drawings prior to the next refueling outage.
The scan plan shall be revised per Section 7.2.1.B.(4) to reflect any PSI examinations performed due to the variations in conf iguration.
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t 2-SI-4.6.G Page 26 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.2.2 Ins ection Re ort (IR)
A. An Inspection Report (IR) shall be used to officially document and provide a disposition for an indication that exceeds the acceptance criteria of Article 3000 of the ASME Section XI Code or of -3000 of Code Case -491. M/N Engineering shall provide/coordinate dispositions for IR's in accordance with SSP-3.1. See Sections 7.1.2.Q and
- 7. 7.
B. Additional Examinations Required by IR's (1) Additional examinations for Class 1 equivalent components (IWB) shall be in accordance with the requirements of IWB-2430. The additional examination samples are defined as those items (welds, areas, or parts) in a particular examination category and item number and within the same system. The initial sample is the sample scheduled for examination at a particular outage for ASME Section XI credit.
(a) Examinations of the initial sample that reveal indications exceeding the acceptance standards of IWB-3410-1 shall
.be extended to include additional examinations in the same outage as the initial examinations, except for volumetric and surface examinations where IWB-3112(b) is applicable. The flaws detected by volumetric or surface examinations that meet the nondestructive examination standards of NB-2500 and NB-5300, as documented in QA records, shall be acceptable.
The first additional examination sample shall include items scheduled for this and the subsequent period. If examinations for that item are not scheduled in the subsequent period, the most immediate period containing scheduled examinations of that item shall be examined.
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t 2-SI-4.6.G Page 27 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
(b) If the first additional examinations of (1)(a) reveal indications exceeding the acceptance standards of Table IWB-3410-1, except where IWB-3112(b) is applicable, further additional examinations shall be performed during the outage. The second additional examination sample shall include all the items of similar design, size and function within the system under examination.
(2) Additional examinations for Class 2 equivalent components (IWC) shall be selected per IWC-2430. If it is determined (Section 7.1'.l.I) that additional examinations are required, those examinations shall be performed in the same outage as the initial examinations. The additional examination samples are defined as those items (welds, areas, or parts) in a particular examination category and item number and within the same system. The initial sample is the sample scheduled for examination at a particular outage for ASME Section XI credit.
(a) A first additional sample shall be selected for those initial samples that detect indications exceeding the allowable standards of IWC-3000, except where the flaw is acceptable under IWC-3112(b). The first additional sample shall include approximately the same number of items examined in the initial
'sample. The items selected should be those avai.lable in the interval sample that have the longest service time from its previous inservice examination.
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2-SI-4.6.G Page 28 INSTRUCTION STEPS/ELEMENTS (Continued)
(b) If the additional examinations of (2)(a) detect indications exceeding the acceptance standards of IWC-3000, further additional examinations shall be performed during the outage. The second additional sample shall include the remaining number of items of the interval sample not examined in the initial or first additional sample. If no items remain in the interval sample, a notification of the first additional sample results shall be provided to Site
. Engineering as described in Section 7.2.'2.S.(4).
(3) Additional examinations for component .supports (IWF) shall be in accordance with -2430 of Code Case N-491.
(a) If component supports of the initial sample must be subjected to corrective measures in accordance with (N-491)-3000, the component supports immediately adjacent to those for which corrective action is required shall be examined.
Also, the examinations shall be extended to include a first additional sample that includes supports within the system, equal in number and of the same type and function as those scheduled for examination during the period.
(b) When the additional examinations of (3)(a) require corrective measures in accordance with (N-491)-3000, a second additional sample of the remaining component supports within the system of the same type and function as in {3){a) shall be examined.
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t 2-SI-4.6.G Page 29 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
(c) When the additional 'examinations of (3)(b) require corrective measures in accordance with (N-491)-3000, examinations shall be extended to include a third additional sample of all nonexempt supports potentially subject to the same failure modes that required corrective measures in (3)(a) and (3)(b). These additional examinations shall include nonexempt component supports in other systems when support failures requiring corrective measures indicate non-system related failure modes. At the request of M/N Engineering, Site Engineering shall make the determination of failure mode applicability and select the third additional sample.
(d) When the additional examinations of (3)(c) require corrective measures in accordance with (N-491)-3000, examination shall be extended to those exempt component supports that could be affected by the same observed failure modes and could affect nonexempt components. At the request of M/N Engineering, Site Engineering shall make the determination of failure mode applicability and select a fourth additional sample of all component supports on exempt components that could affect non'exempt components.
See Section 7.1..3.D.
(4) After completion of the additional examinations, ASME Section XI code requirements for additional examinations are complete. If the final sample examinations reveal indications exceeding the acceptance standards of Article 3000 of ASME Section XI, M/N Engineering shall notify Site Engineering to evaluate the indications and make recommendation(s) for further action, if needed. See Section 7.1.2.I.
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2-SI-4.6.G Page 30 7.2.3 Examinations A. NDE shall be performed in accor'dance with IWA-2200 of ASME Section ZI utilizing the NDE procedures of QMP 110.5 or approved contractor procedures.
B. Personnel performing NDE operations shall be qualified and certified in accordance with IWA-2300 of ASME Section ZI as specified in QMP 102.4.
C. The inservice examinations shall be performed by M/N Engineering, M & I, or contractor personnel.
Contract preparation, administration, and supervision shall be the responsibility of M/N Engineering. Inspection plans and/or quality assurance programs submitted by contractors shall be reviewed and approved by Nuclear Assurance and Licensing prior to use. All contractor NDE procedures used during the inspection program shall be reviewed and approved by M 6 I using QMP-110.5 as a guideline. " See Section 7.1.5.E.
D. In accordance with IWA-2600, a reference system shall be established for all welds and areas subject to surface or volumetric examination. Each such weld and area shall be located and identified by a system of reference points. The system shall permit identification of each weld, location of each weld center line, and designation of regular intervals along the length of the weld.
E. When less than the required ASME Section ZI code examination volume or area is examined, the percentage examined shall be documented on the examination data sheet. The cause of the limitation shall be clearly specified as a part of the data sheet documentation. An NDE level III representative shall review the limitations or impractical examinations during the refueling outage and determine if a code examination was achieved If one was'ot achieved, the NDE level III representative shall notify M/N Engineering immediately to determine if a large enough examination volume or area percentage was achieved to quali.fy for request for relief action in accordance with Sections 7.1.5.D and 7.6. Another component may be selected for a substitute examination if sufficient examination coverage was not achieved. See Section 7.1.2.J.
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2-SI-4.6.G Page 31 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.3 Com onents Sub 'ect to Examination 7.3.1 ASME Class 1 E uivalent Com onents Sub ect to Examination (IWB A. ASME Class 1 equivalent systems (including the components and integral attachments contained therein, but excluding the supports) subject to examination are:
(1) Control Rod Drive Hydraulic System (CRD),
(2) Core Spray System (CS),
(4) High Pressure Coolant Injection System (HPCI),
(5) Main Steam System (MS),
(6) Reactor Core Isolation Cooling System (RCIC),
(7) Reactor Pressure Vessel (RPV),
(8) Reactor Water Cleanup System (RWCU),
(9) Recirculation System (RECIR),
(10) Residual Heat Removal System (RHR), and (ll) Standby Liquid Control System (SLC).
B. The specific components subject to examination are
. identified on ISI drawings listed in Section 2.5.
Class 1 valves are further defined in Section 8.3.
The number of components within each system, the number selected for examination during the interval and the number selected for examination by period are provided in Section 8.1 Examination Schedule, Part 1 -Class 1 Equivalent (IWB) Components.
C. The rules of IWB-1220 (a) and (b) have been used to exempt components from examination and establish the numbers in Section 8.1, Part 1. Specifically, piping NPS 1 and smaller and components and their connections in piping NPS 1 and smaller are exempt from NDE examinations.
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2-SI-4.6.G Page 32 7.0
~ INSTRUCTION STEPS/ELEMENTS (Continued)
~
7.3.2
~ ~ Selection of
~
ASME Class 1 E uivalent Com onents A. All Examination Category B-F circumferential welds shall be examined in the Interval with approximately 1/3 examined in each Period. The Code basis for this selection of Item Numbers B5.130, B5.140, and
'B5.150 is Table IWB-2500-1, Examination Category B-F, 1986 Edition of ASME Section XI.
B. All carbon and low alloy steel (similar metal) nozzle to safe end welds shall be examined this interval. Additional Examination Category B-J circumferential welds that were not examined in the first interval shall be selected to provide a 25 percent sample this interval. Continuation of this selection method during the third and fourth intervals shall result in examination of approximately 90K of the Examination Category B-J circumferential welds over the life of the plant.
BFN does not have stress level calculations as required for selection per Table IWB-2500-1, Examination Category B-J, NOTE: (1)(b). The Code basis for this method of selection of Item Numbers B9.11, B9.21, B9.31, B9.32, and B9.40 is Table IWB-2500-1, Examination Category B-J, 1986 Edition of Section XI except the extent of examination is determined by the requirements of Table IWB-2500 and Table IWB-2600, Examination Category B-J, 1974 Edition with Addenda through Summer 1975 as allowed by 10CFR50.55a(b)(2)(ii). See Section 4.1.
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t 2-SI-4.6.G Page 33 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
C. ASME Class 1 equiv alent longitudinal welds, Examination Category B-J, Item Numbers B9.12 and B9.22 shall be selected for examination by virtue of intersecting a circumferential weld (Item Number B9.11 or B9.21) selected for examination. This is interpreted to mean that these Item Numbers do not have to be counted and no particular examination percentage is required to be examined. However, an effort shall be made to select circumferential welds so that approximately 25K of the longitudinal seams shall be examined. The Code basis for this method of selection of Item Numbers B9.12 and B9.22 is Table IWB-2500-1, Examination Category B-J, 1986 Edition of ASME Section XI. This is in compliance with Table IWB-2500 and Table IWB-2600 of the 1974 Edition, Summer 1975 Addenda.
D." The entire length of each circumferential weld selected shall be examined, unless otherwise noted or if a physical limitation exists. Examination shall include an adjoining one pipe diameter section of each intersecting longitudinal weld, not to exceed 12 inches.
E. Successive Inspections of ASME Class 1 equivalent components shall be in accordance with IWB-2420(a),
IWB-2420(a) shall be utilized except for Examination Category B-K-1 integral attachments and Examination Category B-J welds. The reasons are the modification of the integral attachments (B-K-1) in conjunction with the support modifications explained in Section 7.3.6.F and the extent of examination for B-J welds established in Section 7.3.2.B.
(2) Indications, evaluated in accordance with IWB-3132.4 or IWB-3142.4 qualifying for continued service, shall be reexamined in the next three inspection periods.
(3) If the reexaminations reveal essentially no change in the indication for the three periods, the examination schedule shall revert to the original schedule.
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t 2-SI-4 ' '
Page 34 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7 ' ' ASME Class 2 E uivalent Com onents 'Sub 'ect to Examination (IWC)
A. ASME Class 2 equivalent systems (including the components and integral attachments contained therein, but excluding the supports) subject to examination are (1) Control Rod Drive Hydraulic System (CRD)
(2) Core Spray System (CS)
(3) High Pressure Coolant Injection System (HPCI)
(4) Main Steam System (MS)
(5) Reactor Building Closed Cooling Water System (RBCCW)
(6) Reactor Core Isolation Cooling System (RCIC) and (7) Residual Heat Removal System (RHR) ~
0 BE The 2'
specific components subject to examination are identified on ISI drawings identified in Section
'he number of components within each system the number selected for examination during the interval and the number selected for examination by period are provided in Section F 1 Examination Schedule, Part 2 -Class 2 Equivalent (IWC)
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t 2-81-4.6.G Page 35 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
C. The rules of IWC-1 221 for components within RHR and HPCI (includes containment heat removal) and IWC-1222 for components in all other systems have been used to exempt components from examination and establish the numbers in Section 8.1, Part 2.
Specifically, the following components are exempt from NDE examinations:
Vessels, piping, pumps, valves, and other components NPS 4 and smaller in all systems, (2) Component connections NPS 4 and smaller in all systems, (3) Vessels, piping, pumps, valves, other components, and component connections of any size that operate at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200 degrees F in systems other than RHR and HPCI, and (4) Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions in all systems.
7.3.4 Selection of ASME Class 2 E uivalent Com onents A. One hundred percent of the C-F-1 welds shall be examined in the interval. To the extent possible, welds examined in the first interval, second and third periods, shall be selected for reexamination in the respective periods of the second interval.
The first period welds shall be selected at random since the 1971 Edition of the Code was utilized for unit 2 during the first period of the first interval and no Class 2 examinations were performed. The Code basis for this method of selection of Item Numbers C5.11 and C5'.12 is Table IWB-2500-1, Examination Category C-F-1, 1986 Edition of Section XI.
NOTE: There are no 'Excluded'elds (< 3/8" nominal wall) at BFN for Examination Category C-F-1.
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C 2-SI-4.6.G 0" INSTRUCTION STEPS/ELEHENTS B. To (Continued)
Page 36 the extent practical, Examination Category C-F-2, Item Numbers C5.51, C5.70, and C5.80 circumferential welds that have been previously examined shall be in the 7.5 percent sample selected for examination during the second interval in accordance with IWC-2420(a). Welds examined in the first interval, second and third periods, shall be selected to the extent practical for reexamination in the respective periods of the second interval. The first period welds shall be selected at random since the 1971 Edition of the Code was utilized for unit 2 during the first period of the first interval and no Class 2 examinations were performed.
NOTE: Note (2) of Table IWC-2500-1, Examination Categories C-F-2 establishes an category for welds with ( 3/8" nominal
'Excluded'elds wall. Excluded welds shall not be examined for Code credit, since they have no Item Number under the Examination Category. The Item Number is designated as N/A in Section 8.1 Examination Schedule, Part 1 Class 2 IWC Components.
The excluded welds that are not exempt are included in the total count to which the 7.5X was applied to determine the number of C-F-2 welds to be examined in the interval. The Code basis for this method of selection of Item Numbers C5.51, C5.70, and C5.81 is Table IWB-2500-1, Examination Category C-F-2, 1986 Edition of Section XI.
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t 2-SI-4.6.G Page 37 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
C. ASME Class 2 equiv alent longitudinal welds, Examination Category C-F-2, Item Numbers C5.52 and C5.82, shall be selected for examination by virtue of intersecting a circumferential weld (Item Numbers C5.11, C5.41, C5.51 or C5.81) selected for examination. This is interpreted to mean that the Item Numbers do not have to be counted and no particular percentage is required to be examined.
An effort'hall be made to select circumferential welds so that approximately 7.5X of the Class 2 longitudinal welds shall be examined. The Code basis for this method of selection of Item Numbers C5.52 and C5.82 is in accordance with Table IWB-2500-1, Examination Category C-F-2, 1986 Edition of Section XI.
D. The entire length of each circumferential weld shall be examined, unless otherwise noted or if physical a limitation exists. Examinations of longitudinal welds shall cover a 2.5 thickness (t) length from the intersecting circumferential weld.
E. Successive Inspections of ASME Class 2 equivalent components shall be in accordance with IWC-2420(a),
(1) The sequence of component examinations established during the first inservice inspection interval shall be repeated, to the extent practical, as established in this Section, A. and B. above for Examination Categories C-F-1 and C-F-2, respectively.
(2) Indications, evaluated in accordance with IWC-3000, qualifying for continued service shall be reexamined in the next inspection period.
(3) If the reexaminations reveal essentially no change in the indication, the examination schedule shall revert to the original schedule. See Section 7.1.5.F.
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t 2-81-4.6.G Page 38 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.3.5
=-"-
ASME Class 3 E D
uivalent Com onents 'Sub 'ect to A. ASME Class 3 equivalent systems (including the components and integral attachments contained therein, but excluding the supports) subject to examination are:
(1) Emergency Equipment Cooling Water System (EECW),
(2) Fuel Pool Cooling System (FPC), and (3) Residual Heat Removal Service Water System (RHRSW), and (4) Main Steam (MS).
B. The specific integral attachments subject to examination are identified on ISI drawings listed in Section 2.5. The number" of integral attachments within each system, the number selected for examination during the interval and the number selected for examination by period are provided in Section 8.1 Examination Schedule, Part 3 - Class 3 Equivalent (IWD) Components.
C. The rules of IWD-1220.1 and IWD-1220.2 have been used to exempt components from examination and establish the numbers in Section 8.1, Part 3.
Specifically, integral attachments of supports connected to components that are NPS 4 or smaller are exempt from NDE examinations.
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2-SI-4.6.G Page 39 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.3.6 Com onent Su orts Sub 'ect to Examination (IWF Code Case N-491)
A. Component and piping supports shall be examined in accordance with Table -2500-1 (N-491). Component supports to be examined shall be the supports of those components that are required to be examined under IMB-2500, IMC-2500, and IWD-2500 by volumetric, surface, or visual (VT-1 or VT-3) examination methods. Piping supports to be examined shall be the supports of piping not exempted under IWB-1220, IWC-1220, and IWD-1220. These component and piping supports are within the systems identified in Sections 7.3.1.A, 7.3.3.A, and 7.3.5.A. The specific supports subject to examination are identified on ISI drawings listed in Section 2.5. The method of support exemption is given in Section 7.3.6.C below.
B. The number of supports subject to an examination sample plan, the number selected for examination during the interval and the number selected for examination by period are provided in Section 8.1 Examination Schedule, Part 4 Component Supports (IWF, Code Case N-491).
C. Component supports exempt from NDE examinations are those connected to components and items exempted by IWB-1220, IWC-1220, and IWD-1220, and portions of those that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe. Piping supports exempt from examination shall be the supports of piping exempted under IWB-1220, IMC-1220, and IMD-1220 and those that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe.
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t 2-SI-4.6.G Page 40 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
D. Su PP ort examinatio n boundaries"shall be in accordance with (N-491)-1300. Examination and acceptance of variable support settings shall be in accordance with the detailed support drawing. If a total acceptance range is required and is not given on the detail support drawing, it shall be calculated per QMP-110.5, N-GP-7 and N-VT-1. See Section 7.1.2.W.
E. Component supports that have been adjusted in accordance with (N-491)-3000, repaired, or replaced shall be examined prior to return of the system to service per the applicable examinations listed in Table -2500-1. For systems that operate above 200 degrees F during normal operation, an additional preservice examination shall be performed on the affected component supports during or following the subsequent system heatup and cooldown cycle unless determined unnecessary by evaluation. This examination shall be performed during operation or at the next refueling outage.
F. Successive Inspections of component supports shall be in accordance with -2420(b) and -2420(c) of Code Case N-491. Utilization of (N-491)-2420(a) is not practical. The components supports were completely redesigned and modified in the last period of the first interval (forced outage 9/15/84 to 5/24/91) to comply with Generic Letter 79-14. A sequence shall be established this inspection interval that may be used in future intervals.
(1) 'A component support subjected to corrective measures in accordance with (N-491)-3000 shall be reexamined in the next inspection period.
(2) When additional corrective measures are not required by the reexamination of (1) above, the inspection schedule may revert to the original schedule.
77(235)
2-SI-4.6.G Page 41 7.0
~ INSTRUCTION STEPS/ELEMENTS (Continued) 7.4
~ Calibration Standards
~ ~
Calibration blocks- shall be used for ultrasonic examination. The blocks shall be fabricated in accordance with ASME Section V and ASME Section XI. M & I shall maintain as-built calibration standard drawings and calibration standard material certifications (CMTR's). The calibration'locks shall be stored at the plant site and maintained by M/N Engineering personnel.
See Sections 7.1.2.X and 7.1.5.I.
7.5 Records and Re orts Records and reports shall be in accordance with ASME Section XI, Articles IWA-1400(k), IWA-1400(1), and IWA-6000.
A. The Inservice Inspection (ISI) Summary Report shall include, as a minimum, the information required by IWA-6220(c) and IWA-6220(d) and shall be submitted to Site Licensing on a schedule that permits submittal to the NRC within 90 days after the refueling outage. The ISI Summary Report shall contain: (a) the examinations and System Pressure Tests associated with ISI, replacements, and repairs conducted since the preceding summary report; (b) National Board numbers assigned to the components by the manufacturer, if applicable; (c) identifiers of the components examined including size, material, etc.; (d) name and address of manufacturers; (e) manufacturer's component I.D.'s, if applicable; (f) date of completion of examinations; (g) name of Inspector verifying examinations, his company and company address; (h) abstract of examinations and tests performed; conditions recorded; and corrective measures taken; (i) signature of the Inspector; and (j) Owner's Report for ISI (NIS-1). The cover sheet shall contain: (a) the date of document completion, (b) name and address of the Owner, (c) name and address of generating plant, (d) unit designation, and (e) commercial operating date.
77(235)
t 2-SI-4.6.G Page 42 7.0 INSTRUCTION,STEPS/ELEMENTS (Continued)
B. A Sate Final Repor t sh a 11 b e prepared and submitted to RM.
The Site Final Report, and the references therein, shall be maintained as a QA record for the service lifetime of the plant in accordance with IWA-6300. The Site Final Report shall contain: (a) an index to record file, (b) the inservice and preservice NDE examination reports, (c) the NIS-1 and NIS-2 summary reports. The Site Final Report shall also contain, as a minimum, reference to: (a) this ISI Program (inspection plan), (b) repair records and reports, (c) replacement records and reports, (d) NDE Procedures, and (e)
NDE examination records including radiographs and review forms.
C. Radiographs shall be packaged by M & I and provided to RM for storage as a life of plant record. See Sections 7.1.5.G, 7.1.6.C, and 7.5.B.
D. NDE Procedure revisions (QMP-110.5) and evidence of personnel qualifications shall be maintained by RM as RIMS records for the service lifetime of the plant. See Sections 7.1.5.H, 7.1.6.C, and 7.5.B.
E. Reproduction and microfilming shall meet the requirements of IWA-6320.
7.6 Re uests for Relief RFR)
Where TVA has determined that Code requirements or examinations are impractical, TVA shall submit written Requests for Relief (RFR) to the NRC with information to support the need for relief and any proposed alternate examinations. The impractical Code requirements or relief situation shall be identified as a part of the Section 8.1 examination schedules in this program and references to a particular RFR shall be included.
When impractical examination requirements are identified in the field, M & I shall notify M/N Engineering in accordance with Sections 7.1.5.D and 7.2.3.E.
M & I shall review and comment on any new RFR's.
The Requests for Relief are contained in Section 8.4 of this program.
77(235)
t 2-SI-4.6.G Page 43 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.7 Corrective Action Pro ram Any corrective action required as a result of ISI examinations shall be handled in accordance with SSP-3.4.
7.8 Re airs and Re lacements Repair and replacement shall be in accordance with SSP-6.9.
Preservice inspections (PSI) shall be performed on any component that is repaired, replaced, or modified that is of an Examination Category and Item Number as specified in Section 8.1. The NDE method shall be as specified in Section 8.1.
7.9 S stem Pressure Tests System pressure test and VT-2 examinations shall be in accordance with SSP-8.5.
7.10 Pum and Valve Inservice Testin Pump and valve inservice testing shall be in accordance with SSP-8.6.
7.11 ,Snubber Inservice ~Testin IWF-5000 or (N-491)-5000 is not a part of this program. Snubber inservice testing shall be in accordance with 2-SI-4.6.H.l.
77(235)
2-SI-4.6.G Page 44
~ 7.0 INSTRUCTION STEPS/ELEMENTS 7.12 Au mented Examinations (Continued)
Augmented examinations are performed in addition to ASME Section XI code requirements. The augmented examinations may be required by the NRC or be self-imposed by TVA. Typical sources include generic letters, IE Bulletins, technical specifications, vendor recommendations, and industry experience. Section 8.1, Part 5 provides a schedule for augmented examinations.
The responsible organization or owner shall have technical and administrative responsibility for each augmented examination identified in this section. This responsibility shall include scheduling any examinations through the M/N Engineering, tracking the status of examinations, and reporting completed examinations. Responsible organizations requesting inclusion of augmented examinations in this section shall submit a written request to the Lead M/N Engineering. The written request shall include specific details such as requirement source, identification of components requiring examination, examination frequency, examination method, examination area/volume, acceptance criteria, types of flaws anticipated, areas of high suspect, probability of failure, and reporting requirements.
Copies of the written request shall be submitted to' & I and the M/N Engineering to facilitate nondestructive examination procedure preparation, establishment of training programs, and personnel familiarization.
Prior to each refueling outage, a meeting shall be initiated by the M/N Engineering. Meeting attendees shall include the responsible organizations, M/N Engineering, M 6 I, and Site Engineering. The meeting agenda should include examination plans and schedules, updates on industry experience, and any additional pertinent information.
Following the completion of the a'ugmented examination, the M/N Engineering shall report to the responsible organization items ~
such as examination results and changes in results from previous examinations. The responsible organization shall determine if a meeting with the M/N Engineering and/or other appropriate organizations is necessary to discuss items such as additional examinations to be conducted during the current outage, trends, lessons learned, and identify any future actions such as changes in the frequency of examination.
Augmented examinations that require reporting to the NRC shall be the responsibility of the responsible organization.
77(235)
t 2-SI-4.6.G Page 45 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.12.1 Weld DSRHR-2-05A Responsible organization: Site Engineering. Weld DSRHR-2-05A has an indication that was determined to be lack of fusion between layers of welding. It shall receive augmented RT and UT examinations each inspection period to monitor the size of the indication.
Evaluation of the indication shall be performed by an M & I NDE level III by comparison to previous examinations. If there is any change, Site Engineering shall be formally requested to provide additional evaluation. See Sections 7.1.3.B and 7.1.5.F. A report of the examinations shall be forwarded to the NRC with the NUREG-0313 report of Section 7.12.8. [NRC/C]
Reference NRC Inspection Report 86-03, Open Item 86-03-03 (RIMS L29 860925 984)] ~ PRISIM Exam Requirement Source: D01-02 '
'2 ' RPV Claddin Indication Responsible organization: Site Engineering. An indication in the RPV cladding was discovered in August 1988 during the RPV interior examination. It is located at 15 degree azimuth, 32 3/4" below the RPV flange surface. This indication shall receive a VT-1 examination in refueling cycles 6, 7, and 8 to determine if there is any degradation. Evaluation of the indication shall be performed by an M G I NDE level III by comparison to previous examinations. If there is any change, Site Engineering shall be formally requested to provide additional evaluation. See Sections 7 7 1 5 F.
~ ~ ~
' GAB and A report of the examination shall be forwarded to the NRC with the ISI Summary Report. The examination data from the four consecutive cycles shall be evaluated after the cycle 8 refueling outage to determine if further augmented exams shall be required (RIMS W10 880831 850, W10 880908 873, and B22 880920 022) ~ PRISIM Exam Requirement Source: D02-02.
77(235)
t R-SI-4.6.G Page 46 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.12.3 Welds KR-2-14 KR-2-36 KR-2-37 and KR-2-41 Responsible organization: Site Engineering. These welds, which had IGSCC indications that were evaluated to be acceptable for continued operation, shall be reexamined (UT) in the cycle 6 refueling outage per NRC commitment NCO 850264005 (RIMS L44 860311 803).
Evaluation of the indication shall be performed by an M
& I NDE level III by comparison to previous examinations. If there is any change, Site Engineering shall be formally requested to provide additional evaluation. See Sections 7.1.3eB and 7.1.5.F. A report of the examinations shall be forwarded to the NRC with the NUREG-0313 report of Section 7.12.8. PRISIM Exam Requirement Source: D03-02.
7.12.4 HPCI Pum Dischar e Su ort Ins ection Followin
~In 'ection Responsible organization: Site Engineering. The augmented examination of the supports on the HPCI pump discharge line following a HPCI injection is self imposed by TVA memorandum from G. T. Jones to G. R. Hall and J. R. Pittman (R35 841025 878) and NRC commitment number NCO 850144002.
TI-189 references this required inspection and a System Engineer shall notify the M/N Engineering (as required by the TI) to perform the inspection following a HPCI injection. Each support from the HPCI pump (including the HPCI turbine and pump pedestals) to the steam tunnel penetration shall be visually examined after each injection.
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2-SI-4.6.G Page 47 1 7.0 INSTRUCTION STEPS/ELEMENTS A
(Continued) modified VT-3 examin ation shall be performed using gMP 110.5, procedure N-VT-1 as a guideline within three days following'the injection. This examination is only to verify that there is no loss of integrity of the HPCI supports (i.e. Separation from the wall, distortion of structural members, etc.) and it may be performed remotely using optical aids. Any discrepancies shall be reported to a Systems Engineer using an IR form. A report is to be submitted with the Site Final Report following the next scheduled refueling outage. See Sections 7.1.2.U and 7.5.
The supports to be examined are listed below:
Unit 2: 2-47B45580066, H0067, 80068, H0069, H0070, H0071, 80072, H0073, H0074, H0075, 80076, 80077, 80079, 80080; 2-47B455R0024; 2-47B455S0009, S0010, S0011, S0019, and S0024 (Drawing ISI-0130-C). PRISIM Exam Requirement Source: D04-02.
Responsible organization: Si.te Engineering. This structurally over-layed weld shall be one of the IGSCC Examination Category E welds examined during the cycle 6 refueling outage. This was a commitment of ECN P5215 that designed the overlay configuration. Evaluation of the indication shall be performed by an M & I NDE level III by comparison to previous examinations. If there is any change, Site Engineering shall be formally requested to provide additional evaluation. See Sections 7.1.3.B and 7.1.5.F. A report of the examinations shall be forwarded to the NRC with the NUREG-0313 report of Section 7.12.8. PRISIM Exam Requirement Source: D05-02.
77(235)
2-SI-4.6.G Page 48' 7.0 INSTRUCTION STEPS/ELEMENTS ~
(Continued) 7.12.6 CRD Return Line Reroute Responsible organization: Site Engineering. The augmented examination requirements of the CRD return line reroute are contained in NUREG 0619. The welded connections joining the rerouted CRD return line to the reactor water cleanup system shall be ultrasonically examined during the Cycle 6 refueling outage. The weld RCRD-2-45 shall be ultrasonically examined, including the base metal on each side within one wall thickness (nominal wall 0.531"). The pipe into which the CRD return flow is connected shall also be examined by ultrasonic methods to a distance of at least one pipe diameter downstream of the welded connection. Welds RCRDS-2-3 and RCRD-2-44 shall be ultrasonically examined along with the pipe on the downstream side.
Reporting to the NRC is required within 6 months of completing an outage during which an inspection was performed. The report of these examinations shall be included with the ISI Summary Report unless a special report is deemed necessary by M/N.Engineering. Refer to NUREG-0619, Section 8.3 for information to be included.
PRISIM Exam Requirement Source: B01-02.
7.12.7 Feedwater Nozzles Responsible organization: Site Engineering. The augmented examination requirements for the feedwater nozzles is contained in NUREG-0619. An ultrasonic examination of all the feedwater nozzle safe ends, bores, and inside blend radii are required every second refueling outage. The feedwater spargers shall be visually examined every fourth refueling outage (MMI-182). A liquid penetrant examination of the nozzle bore and inner radius is required every nine refueling cycles or within 135 startup/shutdown cycles based on the replacement date. Reporting is required within 6 months after the outage when an inspection was performed. The report of these examinations shall be included with the ISI Summary Report unless a special report is deemed necessary by M/N Engineering. Refer to NUREG-0619, Section 4.4.3 for information to be included. PRISIM Exam Requirement Source: B01-02.
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t 2-SI-4.6.G Page 49 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.12.8 Au mented Examination of Austenitic Stainless Steel and Dissimilar Metal Welds Susce tible to IGSCC (Generic Letter 88-01 and NUREG-0313,'ev. 2)
Responsible organization: Project Management.
Austenitic stainless steel and dissimilar metal circumferential welds in piping four inches or larger NPS that contain reactor coolant at a temperature above 200' during power operation shall be examined in accordance with the requirements of Generic Letter 88-01 and NUREG-0313, Rev. 2. Sample expansion shall be in accordance with Generic Letter 88-01 (GL 88-01) based on the IGSCC Category (A, B, C, D, or E) as defined in the generic letter. The welds requiring examination per this paragraph are listed in Section 8.2 Part l.
Stainless steel and dissimilar metal welds that are exempt from examination because they contain coolant of 200 degrees or less are listed in Section 8.2 Part 2.
In addi.tion to the requirements of Section 7.2.3.A for examination procedures, the examination procedures used for IGSCC examinations shall satisfy the requirements of GL 88-01.
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0 2-81-4.6.G Page 50 (Continued)
In addi. eon to the requirements of 'Section 7.2.3.B for personnel qualifications, personnel shall'e qualified by the program described in GL 88-01 for performing IGSCC examinations. The examination schedule is based on the IGSCC category and shall be as indicated.
IGSCC EXAMINATION CATEGORY EXTENT AND SCHEDULE A 25 percent every 10 years (at least 12 percent in 6 years).
50 percent every 10 years after initial post-stress improvement (SI) examination (at least 25 percent in 6 years).
100 percent within next 2 refueling cycles after initial post-SI examination (at least 50 percent in 6 years).
D 100 percent every 2 refueling cycles.
50 percent next refueling cycle after crack discovery and/or overlay. 100 percent every 2 refueling cycles thereafter.
F 100 percent every refueling outage.
G 100 percent during each outage.*
- The two IGSCC Category G welds (DRHR-2-03B and -13B) are to be examined (VT-2) for leakage during each refueling outage per NRC Letter A02 930223 002.
NOTE: The ANII shall be required to verify these examinations.
Any flaws identified that do not meet the IWB-3500 criteria for continued operation without evaluation, or a change found in the condition of the welds previously known to be cracked, shall be reported to the NRC under the guidelines of NUREG-0313, Rev. 2. PRISIM Exam Requirement Source: B02-02.
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2-SI-4.6.G Page 51 1 7.0 INSTRUCTION STEPS/ELEMENTS 7.12.9 Core S ra S (Continued) ar ers Responsible organization: Site Engineering. The augmented examination requirements of the core spray spargers is included in MNI-182, which implements IE Bulletin 80-13. The spargers shall be visually examined each refueling outage. Volumetric techniques may be used to evaluate any indications. The reporting criteria is listed in MMI-182. If cracks are detected, the NRC resident inspector and the Region II office shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A written report of the examinations shall be submitted to the NRC within 30 days of completion of the examinations. PRISIM Exam Requirement Source: B03-02.
7.12.10 Technical S ecification Surveillance Re uirement 4.6.G.2 Responsible organization: Site Engineering. Additional ultrasonic examinations shall be performed each inspection interval on certain circumferential pipe welds to provide additional protection against pipe whip in accordance with Technical Specification Surveillance Requirement 4.6.G. The welds requiring examination each interval for pipe whip protection are'.
TCS 2 407 $ TCS 2 423 $ TSCS 2 408 $ TSCS 2 424 $ GFW 2 09 $
GFW-2-12, GFW-2-15, GFW-2-26, GFW-2-29, GFW-2-32, KFW-2-13, KFW-2-31, KFW-2-38, KFW-2-39, THPCI-2-070, THPCI-2-070A, THPCI-2-071, THPCI-2-072, GMS-2-06, GMS-2-15, GMS-2-24, GMS-2-32, KMS-2-024, KMS-2-104, DSRHR-2-04$ DSRHR-2-06$ DSRHR-2-07$ DSRWC-2-03$
DSRWC-2-04, DSRWC-2-05, AND DSRWC-2-06.
A report of these examinations shall be included with the ISI Summary Report. PRISIM Exam Requirement Source:
B04-02.
7.12.11 RPV Shell Weld Examination Responsible organization: M/N Engineering. The RPV shell welds, Examination Category B-A, Item Numbers Bl.ll and B1.12 shall be examined in refueling outage cycle 7 in accordance with the guidance of 10 CFR 50.55a(g)(6)(ii)(A) per TVA's commitment to the NRC dated September 27, 1991 (R08 910927 826).
TVA shall take ASME Section XI credit for these examinations as satisfying the requirements of Table 2500-1, Examination Category B-A, Item Number B1.10. A report of these examinations shall be included with the ISI Summary Report. PRISIM Exam Requirement Source:
B05-02.
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t 2-SI-4.6.G Page 52 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.12.12 RPV Interior Examinations Responsible Organization: Site Engineering.
(Text Later)
PRISIM Exam requirement Source: B06-02.
7.13 Voluntar Examinations Certain examinations are done on a voluntary basis to obtain additional information to support inservice inspections or to resolve a problem identified through the corrective action program. Key voluntary examinations are defined and documented in this Section.
7.13.1 Examination of RPV Nuts and Washers based on FIR BF 910238FIR and Other Voluntar Examinations PRISIM Exam Requirement Source: VOl-02. Unit 2 RPV nuts and washers shall be reexamined in cycle 6 based on FIR BFQ910238FIR. This will be a one time volunteer examination to assure that nut and washer records include their unique position (1 through 92) with respect to the RPV stud locations in the flange. In the Core Spray System, welds TCS-2-4XX received a pre-stress improvement voluntary examination during cycle 6 to assure that IGSCC did not exist.
7.13.2 Verification of Lon itudinal Welds Intersectin Circumferential Welds PRISIM Exam Requirement Source: V02-02. Due to'he vintage of BFN, it is not always possible to determine from xecords the existence of longitudinal welds. Much of the pipe was procured to the A-333, Gr. B specification that could be furnished in the seamless or welded condition. A special examination shall be specified in the scan plan when it is necessary to determine the status of existing longitudinal welds.
For austenitic stainless steel, an ultrasonic examination shall be used and for carbon or alloy steel, a visual examination supplemented by an acid etch, where required, shall be used.
If a longitudinal weld is located using this specified examination, it must be included in the scan plan and examined for code credit (PRISIM Exam Requirement Source 86E-02).
77(235)
t 2-SI-4.6.G Page S3 7.0 INSTRUCTION STEPS/ELEMENTS (Continued) 7.13.3 Verification of Lon itudinal Welds Intersectin Circumferential Welds Examined for Code Credit in the First Ins ection Interval PRISIM Exam Requirement Source: V03-02. A special examination shall be specified in the scan plan when it is necessary to verify the status of longitudinal welds adjacent to circumferential welds examined for Code credit in the first inspection interval. A visual examination supplemented by an acid etch, where required, shall be used. Class 1 and 2 circumferential welds specified shall be examined on each side of the weld for the existence of longitudinal welds where piping components exist on each side of the weld.
Valves, pumps, etc. need not be examined for the existence of longitudinal welds.
These examinations shall be spread over refueling outages 7, 8, 9, and 10. The result of the examination shall be reported immediately to M/N Engineering so that a determination of compliance with Code in the first inspection interval may be verified.
8.0 TABLES/ATTACHMENTS This Section contains Examination Schedules (8.1), List of Welds requiring examination by Generic Letter 88-01 (8.2), Class 1 Valve List (8.3), and Requests for Relief (8.4).
A list and status of the Requests for Relief contained in Section 8.4 is presented here:
(1) RFR ISI-2-1, Reactor Pressure Vessel (RPV) Support Integral Attachment. Submitted to the NRC as a part of Revision 0 of this SI.
(2) RFR ISI-2-1, Reactor Pressure Vessel (RPV) Threads in Flange.
Submitted to the NRC as a part of Revision 2 of this SI.
(3) RFR ISI-2-1, Reactor Pressure Vessel (RPV) Nozzle to Vessel Head Weld (N6 Nozzle). Submitted to the NRC as a part of Revision 2 of this SI.
(4) RFR ISI-2-1, Class 1 and/or Class 2 Piping Welds. Submitted to the NRC as a part of Revision 2 of this SI.
77(235)
2-SI-4.6.G Page 54 SECTION 8.1 EXAMINATION SCHEDULE PART 1 - CLASS 1 EQUIVALENT (IWB) COMPONENTS Second Inspection First Second Third Components Exami nati on Item Number of System/ Interval Period Period Period Shown On Exam(s)
Category No. Components Subtotal Sample Sample Sample Sample ISI Drawing 0 Required Remarks B-A B1.11 5 RPV 1 1 CHM-2046-C RPV Shell Circ Held See Section 7.12.11 B-A B1.12 15 RPV CHM-2046-C UT RPV Shell Long Held See Section 7.12.11 B-A Bl . 21 RPV ISI-0408-C RPV Circ Top 'Hd Hld (RCH-2-1C)
RPV Circ Bot Hd Hid (C-S-BH)
B-A B1.22 12 RPV ISI-0408-C UT RPV Mer Top Hd Wld (RCH-2-XV)
RPV Mer Bot Hd Hld (V-BH-X)
B-A B1.30 RPV 1 CHM-2046-C UT RPV Flg Held (C-5-FLG)
B-A B1.40 RPV 1 ISI-0408-C UT RPV Hd-Flg Held (RCH-2-2C)
B-A B1.40 RPV 1 ISI-0408-C PT RPV Hd-Flg Flex Area (RCH-2-2C-FLEX) 77(235)
2-SI-4.6.G Page 55 SECTION 8.1 EXAMINATION SCHEDULE PART 1 CLASS 1 EQUIVALENT (IHB) COMPONENTS (Continued)
Second Inspection First Second Third Components Examination Item Number of System/ Interval Period Period Period Shown On Exam(s)
Category No. Components Subtotal Sample Sample Sample Sample ISI Drawing ¹ Required Remarks 8-A 81.51 N/A RPV N/A RPV Repair Held(s) None B-B N/A N/A None 8-D 83.90 32 RPV 32 10 10 12 CHM-2046-C & UT RPV Noz-Ves Hid ISI-0292-C &
ISI-0380-C 8-D 83.100 32 RPV 32 10 10 12 CHM-2046-C & UT RPV Noz IR ISI-0292-C &
ISI-03&0-C 8-E 84.11 N/A N/A None 8-E 84.12 185 RPV 47 47 ISI-0292-C VT-2 '. CRD Nozzle Interval Hydro 8-E 84.13 RPV 2 CHM-2046-C VT-2 Instrumentation Noz 8-F 85.10 17 RPV 17 6 ISI-2070-C UT & Noz-SE Hld > 4" ISI-2071-C PT ISI-0272-C ISI-0410-C 77(235)
2-SI-4.6.G Page 56 SECTION 8.1 EXAMINATION SCHEDULE PART 1 CLASS 1 EQUIVALENT (INB) COMPONENTS (Continued)
Second Inspection First Second Third Components Examination Item Number of System/ Interval Period Period Period Shown On Exam(s)
Category No. Components Subtotal Sample Sample Sample Sample ISI Drawing ¹ Required Remarks 8-F 85.20 7 RPV 7 2 2 3 ISI-0380-C PT Noz-SE Hld < 4" ISI-0383-C 8-F 85.30 N/A N/A None 8-F 85.130 13 13 UT & Dissim Pipe Nld CRD/3 3 ISI-2072-C PT =) 4" CS/8 8 ISI-0271-C RHR/1 1 ISI-0221-C RNCU/1 1 ISI-0272-C 8-F 85.140 RHCU ISI-0272-C PT Dissim Pipe Hld
) 4 ll 8-F 85.150 1 ISI-0222-C PT Dissim Socket < 4" B-G-1, 86. 10 92 RPV 92 22 35 35 ISI-0266-C NT Clos Hd Nuts 8-G-1 86.20 92 RPV 92 22 35 35 ISI-0266-C UT('2) Studs (In Place)
B-G-1 86.30 92 RPV 4(*2) 4(*2) ISI-0266-C HT & Studs (Hhen 92 (if UT(*2) Removed) studs removed) 8-G-1 86.40 92 RPV 92 22 35 35 ISI-0266-C UT Threads (Nhen Head Removed) 77(235)
2-SI-4.6.G'age 57 SECTION 8.1 EXAMINATION SCHEDULE PART 1 CLASS 1 EQUIVALENT (IWB) COMPONENTS (Continued)
Second Inspection First Second Third Components Examination Item Number of System/ Interval Period Period Period Shown On Exam(s)
Category No. Components Subtotal Sample Sample Sample Sample ISI Drawing ¹ Required . Remarks B-G-1 B6.50 92 RPV 92 22 35 35 ISI-0266-C VT-1 Washer (Sets of 2) sets sets sets sets sets B-G-1 B6.50 92 RPV 92 22 35 35 ISI-0266-C VT-1 Bushings (When Head Removed)
B-G-1 B5.150 N/A N/A None B-G-1 B6.180 32 RECIR 16(*3) 32(*l) 8 8 ISI-0407-C UT Recir Pump Bolting B-G-1 B6.190 2 RECIR 1(*3) 1(*3) ISI-0407-C VT-1 Flange Face B-G-1 B6.200 32 RECIR 16(*3) 32(*1) 8 8 ISI-0407-C UT Recir Pump Nuts B-G-1 B6.200 32 RECIR 16(*3) 32(*1) 8 8 ISf-0407-C UT Recir Pump Washers B-G-1 B6.210 N/A N/A None B-G-2 B7.10 N/A N/A None B-G-2 B7.50 17 17 7 VT-1 Pipe BOlting ( 2" MS/12 12 4 ISI-0312-B RECIR/2 2 1 ISI-0270-C RPV/3 3 2 ISI-0408-C Bolting to RPV Hd Noz B-G-2 B7.60 N/A N/A None 77(235)
2-SI-4.6.G Page 58 SECTION 8.1 EXAMINATION SCHEDULE PART 1 CLASS 1 EQUIVALENT (IWB) COMPONENTS (Continued)
Second Inspection First Second Third Components Examination Item Number of System/ Interval Period Period Period Shown On Exam(s)
Category No. Components Subtotal Sample Sample Sample Sample ISI Drawing ¹ Required Remarks B-G-2 B7.70 46 15(*10) VT-1 Valve Bolting < 2" See Section 8.3 CS/4 2(*10) IS I-0271-C FH/6 2(*10) ISI-0269-C HPCI/1 1(*10) ISI-0273-C MS/8 1(*10) ISI-0222-C FCV-1-??
MS/13 1(*10) ISI-0312-8 PCV-1-???
RECIR/6 3(*10) ISI-0270-C RHR/5 3(*10) ISI-0221-C RHCU/3 2(*10) ISI-0272-C 8-G-2 , 87.80 185 RPV 185(*4) 25(*4) (*4) (*4) ISI-0292-C VT-1 CRD Housing Bolts B-H B8.10 RPV 1(*5) IS I-0415-C PT or RPV IA's UT RFR-ISI-2-1 8-J 89.11 407 102(*6) 33 34 35 ST 5 UT Circumferential Helds > 4" CRD/10 3 1 ISI-0272-C MT 5 UT CS/23 5 IS I-0271-C MT 5 UT FH/78 17 10 ISI-0269-C MT 5 UT HPCI/21 5 ISI-0273-C MT 5 UT MS/120 26 8 ISI-0222-C MT 5 UT RCIC/6 2 ISI-0272-C MT 5 UT RECIR/78 17 10 ISI-0270-C PT Ict UT RHR/35 8 1 ISI-0221-C PT NEt UT RPV/13 13 4 ISI-0222-C
RHCU/23 ISI-0272-C
2-SI-4.6.G Page 59 SECTION 8.1 EXAMINATION SCHEOULE PART 1 - CLASS 1 EQUIVALENT (IHB) COMPONENTS (Continued)
Second Inspection First Second Third Components Examination Item Number of System/ Interval Period Period Period Shown On Exam(s)
Category No. Components Subtotal Sample Sample Sample Sample ISI Drawing ¹ Required Remarks 8-J 89.12 310 66(*7) 10(*7) 22(*7) 34(*7) ST 5 UT Longitudinal Helds > 4" CS/18 (*7) IS I-0271-C HT 5 UT FN/4 (*7) ISI-0269-C MT 8( UT MS/140 (*7) 13 ISI-0222-C MT & UT RECIR/86 (*7) 8 ISI-0270-C PT 8c UT RHR/62 (*7) 13 ISI-0221-C PT 5 UT 89.21 79 20 ST Circumferential Helds < 4" FH/48 ll ISI-0383-C PT HS/3 1 ISI-0222-C MT RCIC/21 5 ISI-0272-C MT RECIR/2 1 ISI-0270-C PT RPV/1 1 ISI-0272-C MT SLC/4 1 ISI-0380-C MT 8-3 89.22 N/A N/A None 89.31 42 ST 5 UT Branch Connections ) 4" HS/26 ISI-0222-C HT & UT RECIR/15 ISI-0270-C PT 5 UT RHR/1 ISI-0221-C PT 5 UT 8-J 89.32 4 ISI-0222-C ST Branch Connections < 4" MS/1 ISI-0222-C RHR/3 ISI-0221-C 77(235)
2-SI-4.6.G Page 60 SECTION 8.1 EXAMINATION SCHEDULE PART 1 CLASS 1 EQUIVALENT (IWB) COMPONENTS (Continued)
Second Inspection First Second Third Components Exami nati on I tern Number of System/ Interval Period Period Period Shown On Exam(s)
Category No. Components Subtotal Sample Sample Sample Sample ISI Drawing ¹ Required Remarks B9.40 222 56 17 18 21 ST Socket Welds MS/61 15 9 6 ISI-0222-C MT RCIC/15 4 ISI-0272-C MT RECIR/12 3 ISI-0270-C PT RHR/13 3 IS I-0221-C PT RWCU/34 9 ISI-0272-C MT SLC/40 10 ISI-0380-C PT FW/47 12 12 ISI-0222-C MT 8-K-1 B10.10 54 14 18 22 ST Piping Integral Attachments (IA's) > 5/8" CS/5 5 ISI-0280-C MT FW/10 10 10 ISI-0277-C MT HPCI/1 1 1 ISI-0275-C MT MS/18 18 18 ISI-0279-C MT RECIR/17 17 17 ISI-0278-C PT RHR/3 3 ISI-0276-C MT B-K-1 B10.20 6 RECIR 6 ISI-0278-C PT Pump IA's > 5/8" 8-K-1 810.30 1 FW 1 ISI-0277-C MT Valve IA > 5/8" 8-K-1 N/A 63 N/A Class 1 IA ( 5/8" 8-L-1 BI2.10 N/A N/A None 8-L-2 B12.20 2 RECIR 1(*8) 1(*8) ISI-0407-C VT-3 Pump Casing Interior 77(235)
2-SI-4.6.G Page 61 SECTION S.l EXAMINATION SCHEDULE PART 1 CLASS 1 EQUIVALENT (INB) COMPONENTS (Continued)
Second Inspection First Second Third . Components Exami nati on Item Number of System/ Interval Period Period Period Shown On Exam(s)
Category. No. Components Subtotal Sample Sample Sample . Sample ISI Drawing ¹ Required Remarks 8-H-1 812.30 N/A N/A None 8-H-1 812.40 N/A N/A None 8-H-2 812.50 55 21(*9) 21(*9) VT-3 Valve Body ) 4" See Secion 8.3.
CS/6 3(*10) ISI-0271-C FH/6 2(*10) ISI-0269-C HPCI/3 2(*10) ISI-0273-C MS/21 2(A10) ISI-0222-C RCIC/1 1(*10) ISI-0272-C RECIR/6 3(*10) ISI-0270-C RHR/9 6(*10) ISI-0221-C RNCU/3 2(%10) ISI-0272-C 8-N-1 813.10 RPV CHM-2046-C VT-3 RPV Interior 8-N-2 813. 20 RPV 1 CHM-2046-C VT-1 RPV Interior Att in Beltline Region 8-N-2 813.30 RPV 1 CHH-2046-C VT-3 RPV Interior Att Beyond Beltline Region 8-N-2 813.40 RPV 1 CHM-2046-C VT-3 Shroud Supp Surfaces 8-0 814.40 40 RPV 4 ISI-0292-C PT CRD Housing Held 8-P ALL -See Section 7. 9 and SSP-8. 5 VT-2 Pressure Test Program 77(235)
2-SI-4.6.G Page 62 SECTION 8.1 EXAMINATION SCHEDULE PART 1 CLASS 1 EQUIVALENT (INB) COMPONENTS (Continued)
NOTES:
(*1) Bolting replaced in cycle 6 refueling outage. Preservice examination performed on all 32 sets of bolting.
(*2) Studs (Bolting) may be examined in place under tension (B6.20), when connection is disassembled (B6.20, or when the bolting is removed (B6.30). Studs shall be surface examined only if removed. The four studs normally removed for refueling have been scheduled under Item Number B6.30. Others shall receive a surface exam if removed in accordance with Table IHB-2500-1, Examination Category B-G-l, NOTE: (1).
(*3) Examine bolting of only one pump in accordance with Table INB-2500-1, B-G-l, NOTE: (3) in conjunction with B-L-2, NOTE: (1).
(*4) Bolts, studs, and nuts in CRD Housing examined only when disassembled in accordance with Table IHB-2500-1, Examination Category B-G-2, Extent and Frequency of Examination.
(*5) UT accessible 24" length of RPV-SUPPORT-IA at two locations (48" total) in accordance with Request for Relief ISI-2-1.
(*6) Approximately 90'L of the B-J welds, within practical limits of accessibility, shall be examined during the life of the plant. All carbon steel or low alloy (similar metal) RPV nozzle-to-safe end welds plus additional welds to comprise a 25% sample shall be examined each interval. All stainless or dissimilar metal welds are examined under Examination Category B-F.
(*7) Class 1 logitudinal welds shall be examined when they intersect a circumferential weld selected for examination in accordance with Table 2500-1 B-3, NOTE: (4). Numbers shown are based on the circumferential welds currently selected for examination.
(*8) Examine only one pump in accordance with Table 2500-1, B-L-2, NOTE: (1) & (2). This examination shall be performed during Cycle 6 in accordance with the NRC SER for Relief Request ISI-4 (letter A02 891030 018) associated with the first inspection interval.
(*9) Examine only one valve per Group in accordance with Table 2500-1, B-M-2, NOTE: (3) ~ There are 21 Groups of Class 1 valves NPS 4 or larger.
(*10) Number of Groups of Class 1 valves exceeding NPS 4 contained within this system (Examination Category and/or Item Number).
77(235)
2-SI-4.6.G Page 63 SECTION 8.1 EXAMINATION SCHEDULE PART 2 CLASS 2 EQUIVALENT (INC) COMPONENTS Second Inspection First Second Third Components Examination Item Number of System/ Interval Period Period Period Shown On Exam(s)
Category No. Components Subtotal Sample Sample Sample Sample ISI Drawing ¹ Required Remarks C-A Cl.10 8 =
RHR 2(*1) 1 ISI-0406-C UT RHRHX RHRG-2-07 Shell RHRG-2-08 Circ.
C-A C1.20 8 RHR 2(*l) 1 ISI-0406-C UT RHRHX RHRG-2-09 Head RHRG-2-10 Circ.
C-A C1.30 N/A N/A None C-B C2.10 N/A N/A None C-B C2.21 4 RHR 1(*2) ISI-0406-C UT&NT RHRHX RHRG-2-11 Head Noz Held.
C-B C2.22 N/A N/A None C-B C2.31 16 RHR 4(*2) 2 ISI-0406-C MT RHRHX RHRG-2-05A Noz Rein RHRG-2-05B forcing RHRG-2-06A Plate RHRG-2-068 Helds.
C-B C2.32 N/A N/A None C-B C2.33 8 RHR 2(*2) 2 ISI-0406-C VT-2 RHRHX RHRG-2-05 5 -06, Noz Reinforcing Plt relief "telltale" hole 8 Press Test.
C-C C3.10 12 RHR 3(*3) 1 IS I-0406-C MT Pres Ves IA's
=> 3/4" RHRHX C-C C3.20 47 15 16 16 Piping IA's
=> 3/4" RHRHX CS/6 . 6 ISI-0105-C MT HPCI/4 4 ISI-0130-C MT MS/8 8 ISI-0079-C MT RCIC/1 1 I S I-0131-C MT RHR/28 28 12 16 ISI-0324-C MT 77(235)
2-SI-4.6.G Page 64 SECTION 8.1 EXAMINATION SCHEDULE PART 2 CLASS 2 E UIVALENT (INC) COMPONENTS Second Components Inspection First Second Third Shown on Examination Item Number of System/ Interval Period Period Period ISI Exam(s)
~Cate or No. Com onents Subtotal Sam le Sam le Sam le ~Sam le Drauin ¹ Re uired Remarks C-C C3.30 4 RHR 4 1 2 I S I-0310-B MT Pump IA's => 3/4" C-C C3.40 N/A N/A None C-C N/A 98 N/A CLASS 2 IA's <3/4" C-D N/A N/A None C-F-1 C5.11 13 13 PT Dissim metal & SS
& UT circ welds > 4" &
>mm 3/8" nom. wall.
CS/6 ISI-0103-C HPCI/5 5 I SI-0128-C RHR/2 MSG-0018-C C-F-1 CS. 12 8 CS 8(*4) 2(*4) 6(*4) -(*4 ISI-0103-C PT Dissim metal & SS
& UT long welds > 4" &
=> 3/8"nom. wall.
C-F-1 C5.20 N/A N/A BNR Plant C-F-1 C5.30 N/A N/A None C-F-1 C5.40 N/A N/A None C-F-2 N/A 151(*6) N/A N/A. < 3/8" nom. wall. J Excluded See Section 7.3.4.B .
CS/21 N/A ISI-0103-C RBCCH/16 N/A ISI-0031-C RCIC/38 N/A ISI-0129-C RHR/76 N/A MSG-0018-C 77(235)
2-SI-4.6.G Page 65 SECTION 8.1 EXAMINATION SCHEDULE PART 2 CLASS 2 E UIVALENT (INC) COMPONENTS Second Components Inspection First Second Third Shown on Examination Item Number of System/ Interval Period Period Period ISI Exam(s)
~Cate or No. Com onents Subtotal Sam le Sam le Sam le ~Sam le Drawin ¹ Re uired Remarks 82 27 27 28 MT & CS Circ Nelds > 4" C-F-2 C5.51 944 (1095)(*5) UT 5 => 3/8" nom. wall.
CRD/72 6 ISI-0040-C CS/144 12 12 ISI-0103-C HPCI/161 14 7 IS I-0128-C MS/115 10. 10 MSG-0021-C RCIC/46 4 4 ISI-0129-C RHR/406 36 20 'I6 MSG-0018-C Includes containment heat removal. ~
3(*4) 2(*4) l(*4) MT 5 CS Long Helds > 4" 5 C-F-2 C5.52 20 UT => 3/8" nom. wall.
MS/8 2(*4) MSG-0021-C, RHR/12 1(*4) MSG-0018-C C-F-2 C5.60 N/A N/A BHR Plant C-F-2 C5.70 N/A N/A None C-F-2 C5.81 2 RHR 1 MSG-0018-C MT Sweep-o-let branch connection C-G C6.10 N/A N/A None C-G C6.20 N/A N/A None C-H ALL ALL See Section 7.9 and SSP-8.5. VT-2 Pressure Test Program.
77(235)
2-SI-4.6.G Page 66 SECTION 8.1 EXAMINATION SCHEDULE PART 2 CLASS 2 E UIVALENT (IWC) COMPONENTS NOTES'*1)
Examinations limited to one vessel of similar design, size, function in accordance with Table IWC-2500-1, Examination Category C-A, NOTE: (3) ~
(*2) Examinations limited to one vessel of similar design, size, function in accordance with Table IWC-2500-1, Examination Category C-B, NOTE: (4).
(*3) Examinations limited to one vessel of similar design, size, function in accordance with Table IWC-2500-1, Examination Category C-C, NOTE: (2).
(*4) Class 2 longitudinal welds wi 11 be examined when they intersect a circumferential weld selected for examination in accordance with Table 2500-1, C-F-l, C5.12, and C-F-2, C5.52, Extent of Examination, "2.5t at the intersecting circumferential weld." Numbers shown are based on the circumferential welds currently selected for examination.
(*5) Total count (1095) of Item Numbers C5.51 (circumferential welds >= 3/8" nominal wall) & Item Numbers N/A (excluded welds due to thickness being < 3/8" nominal wall) to which the 7.5 X sampling rate is applied to arrive at 82 welds to be examined. The second interval sample is prorated to each system by using the ratio of the nonexempt C-F-2 welds for the system to the total of C-F-2 circumferential welds. [i.e. For RHR: (74 + 406)/1095 X 82 = 36]. See Table IWC-2500-1, C-F-2, NOTES: (2).
(*6) Item Numbers N/A are the circumferential welds < 3/8" nominal wall. There are 151 of these welds and they are included here to establish a total weld count. They are not subject to examination. See Section 7.3.4.B.
77(235)
2-SI-4.6.G Page 67.
SECTION 8.1 EXAMINATION SCHEDULE PART 3CLASS 3 E UIVALENT (IWD) COMPONENTS Second Components Inspection First Second Third Shown on Examination Item Number of System/ Interval Period Period Period ISI Exam(s)
~Cate or Ro. Com onents Subtotal Sam 1 e Sam le Sam le ~Sam le Drawin ¹ Re uired Remarks D-A N/A N/A None D-B D2.10 All See Section 7.9 and SSP-8.5. VT-2 Pressure Test Program.
D-B D2.20 94 94 31 31 VT-3 IA's Comp Supports 15 Restraints.
EECW/74 74 12 31 ISI-0368-C RCW/2 2 1 IS I-0391-C, RHRSW/18 18 18 ISI-0145-C D-B D2.30 15 MS 15 ISI-0412-C VT-3 IA's ON SNUBBERS.
D-B D2.40 35 35 12 12 VT-3 IA's Spring Type Piping Comp Supports.
MS/26 26 12 12 ISI-0412-C RHRSW/9 9 I S I-0145-C 77(235)
2-SI-4.6.G Page 68 SECTION 8.1 EXAMINATION SCHEDULE PART 3 CLASS 3 E UIVALENT (IND) COMPONENTS Second Components Inspection First Second Third Shown on Examination Item Number of System/ Interval Period Period Period ISI Exam(s)
~Cate or No. Com onents Subtotal Sam le Sam le Sam le ~Sam le Drauin ¹ Re uired Remarks D-B D2.50 N/A N/A None D-B D2.60 N/A N/A None D-C D3.10 Al 1 See Section 7.9 and SSP-8.5. VT-2 Pressure Test Program.
D-C D3.20 1 FPC 1 IS I-0133-C VT-3 IA's on Comp Supports &
Restraints.
- D-C D3 ~ 30 N/A N/A None thru D3.60 77(235)
2-SI-4.6.G Page 69 SECTION 8.1 EXAMINATION SCHEDULE PART 4 COMPONENT SUPPORTS (IWF CODE CASE N-491)
Second Components Inspection First Second Third Shown on Examination Item Number of System/ Interval Period Period Period ISI Exam(s)
~Cate or No. Com onents Subtotal Sam le Sam le Sam le ~Sam le Drawin ¹ Re uired Remarks F-A F1.10 185 47 15 16 16 VT-3 CLASS 1 PIPE SUPPORTS.
SUBTOTALS FOLLOW BELOW.
F-A F1.10A 14 2 2 VT-3 ONE DIRECTIONAL RIGID SUPPORTS CRD/1 1 ISI-0274-C MS/7 1 ISI-0279-C RCIC/1 1 ISI-0274-C RECIR/1 1 ISI-0278-C RWCU/1 1 ISI-0274-C SLC/3 1 ISI-0379-C F-A F1.10B 35 3 3 VT-3 MULTIDIRECTIONAL RIGID SUPPORTS.
FW/3 1 ISI-0277-C &
ISI-0387-C HPCI/1 1 ISI-0275-C MS/6 1 ISI-0279-C RCIC/2 1 ISI-0274-C RECIR/2 1 ISI-0278-C RHR/4 1 ISI-0276-C RWCU/7 1 ISI-0274-C SLC/10 1 ISI-0379-C 77(235)
2-SI-4.6.G Page 70 SECTION 8.1 EXAMINATION SCHEDULE PART 4 COMPONENT SUPPORTS (IWF CODE CASE N-491)
Second Components Inspection First Second Third Shown on Examination Item Number of System/ Interval Period Period Period ISI Exam(s)
~Cate or No. Com onents Subtotal Sam le Sam le Sam le ~Sam le Drauin ¹ Re aired Remarks F-A F1.10C 136 33 ll 11 ll VT-3 VARIABLE SUPPORTS.
(SNUBBERS, CONSTANT FORCE, SPRINGS, ETC.)
CS/10 ISI-0280-C FW/33 ISI-0277-C &
ISI-0387-C HPCI/3 1 1 ISI-0275-C MS/44 10 10 ISI-0279-C RCIC/5 1 ISI-0274-C RECIR/21 5 ISI-0278-C RHR/11 3 ISI-0276-C RWCU/4 1 ISI-0274-C SLC/5 1 ISI-0379-C F-A F1.20 333 51 17 17 17 VT-3 CLASS 2 PIPE SUPPORTS.
SUBTOTALS FOLLOW BELOW.
77(235)
2-SI-4.6.G Page 71 SECTION &.1 EXAMINATION SCHEDULE PART 4 COMPONENT SUPPORTS (INF CODE CASE N-491)
Examination Item Number of System/
Second Inspection Interval
'irst Period Second Period Third Period Components Shown on ISI Exam(s)
~Cate or Ro. Com onents Subtotal Sam le Sam le Sam le ~Sam le Drawin ¹ Re uired Remarks F-A F1.20A 110 17 6 6 VT-3 ONE DIRECTIONAL RIGID SUPPORTS CRD/14 2 ISI-0041-C CS/16 2 ISI-0105-C HPCI/25 IS I-0130-C RBCCH/2 1 ISI-0032-C RCIC/12 ISI-0131-C RHR/41 ISI-0324-C F-A F1.20B 63 10 VT-3 MULTIDIRECTIONAL RIGID SUPPORTS CRD/13 I SI-0041-C CS/8 ISI-0105-C HPCI/7 ISI-0130-C MS/6 ISI-0079-C RCIC/3 I SI-0131-C RHR/26 ISI-0324-C F-A F1.20C 160 24 VT-3 VARIABLE SUPPORTS.
(SNUBBERS, CONSTANT FORCE, SPRINGS, ETC.)
CS/14 3 ISI-0105-C HPCI/20 3 ISI-0130-C MS/31 4 ISI-0079-C RCIC/9 1 IS I-0131-C RBCCW/1 1 ISI-0032-C RHR/85 12 ISI-0324-C F-A F1.30 446 45 13 17 15 VT-3 CLASS 3'PIPE SUPPORTS. SUBTOTALS FOLLOW BELON.
77(235)
2-SI-4.6.G Page 72 SECTION 8.1 EXAMINATION SCHEDULE PART 4 COMPONENT SUPPORTS (IHF CODE CASE N-491)
Second Components Inspection First Second Third Shown on Examination Item Number of System/ Interval Period Period Period ISI Exam(s)
~Cate or No. Com onents Subtotal Sam le Sam le Sam le ~Sam le Drawin ¹ Re wired Remarks F-A F1. 30A 119 12 VT-3 ONE DIRECTIONAL RIGID SUPPORTS.
EECH/86 7 ISI-0368-C FPC/1 1 ISI-0133-C MS/1 1 ISI-0412-C RCH/4 1 ISI-0391-C RHRSH/27 2 ISI-0145-C F-A F1.30B 261 26 10 10 VT-3 MULTIDIRECTIONAL RIGID SUPPORTS.
EECH/173 17 ISI-0368-C FPC/4 1 ISI-0133-C MS/53 5 ISI-0412-C RCH/5 1 ISI-0391-C RHRSH/26 2 ISI-0145-C F-A F1.30C 66 VT-3 VARIABLE SUPPORTS.
(SNUBBERS, CONSTANT FORCE, SPRINGS, ETC.)
EECH/3 1 1 ISI-0368-C MS/54 4 ISI-0412-C RHRSH/9 2 2 ISI-0145-C 77(235)
2-SI-4.6.G Page 73 SECTION 8.1 EXAMINATION SCHEDULE PART 4 COMPONENT SUPPORTS (IWF CODE CASE N-491)
Second Components Inspection First Second Third Shown on Examination Item Number of System/ Interval Period Period Period ISI Exam(s)
~Cate or No. Com onents Subtotal Sam le Sam le Sam le ~Sam le Drauin ¹ Re uired Remarks F1.40 71 30 11 11 8 ALL CLASSES OF COMPONENT SUPPORTS (NOT PIPE SUPPORTS).
SUBTOTALS FOLLOW BELOW.
F-A F1.40A N/A N/A NONE F-A F1.40B 48 16(*1) VT-3 MULTIDIRECTIONAL RIGID SUPPORTS.
CRD/6 3(*1) ISI-0041-C TANK SUPPORTS.
CS/4 1(*l) ISI-0105-C PUMP SUPPORTS.
EECW/16 2(*1) ISI-0368-C PUMP 1El STRAINER SUPPORTS.
HPCI/3 3 IS I-0130-C TURBINE 5 PUMP SUPPORTS.
RCIC/2 I S I-0131-C TURBINE & PUMP SUPPORTS.
RHR/12 3(*1) ISI-0406-C RHR HX SUPPORTS.
RHR/4 1(*1) ISI-310-B RHR PUMP SUPPORTS RPV/1 1 ISI-0415-A RPV SUPPORT.
F-A F1.40C 23 .14(*1)
FW/2 2 ISI-0277-C VT-3 VALVE SUPPORTS RECIR/2 2 IS I-0278-C VT-3 VALVE SUPPORTS RECIR/18 9(*1) ISI-0278-C VT-3 RECIR PUMP SUPPORTS RPV/1 1 ISI-0415-C VT-3 RPV STABILIZER NOTE:
(*1) For multiple components other than piping, within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined. See Table -2500-1, Examination Category F-A, Note: (3).
77(235)
2-SI-4.6.G Page 74 SECTION 8.1 EXAMINATION SCHEDULE PART 5 AUGMENTED EXAMINATIONS(*1)
Exam Augmented Ref. Reqmt Refueling Refueling Refueling Refueling Refueling Refueling Exam Program Number of Source Cycle 6 Cycle 7 Cycle 8 Cycle 9 Cycle 10 Cycle ll Exam(s)
Cate or Section Com onents Code Sam le Sam le Sam le Sam le Sam le Sam le Re uired Remarks 7.12.8 40 802-02 3 2 3 3 UT Section 8.2.
NUREG-0313 7.12.8 121 802-02 114 20 20 20 UT Section 8.2.
NUREG-0313 7.12.8 802-02 12 UT Section 8.2.
NUREG-0313 7.12.8 15 802-02 9 UT Section 8.2.
NUREG-0313 7.12.8 802-02 8 UT Section 8.2.
NUREG-0313 NA(*2) 7.12.8 12 B02-02 12 12 12 N/A Stainless Welds, Temp.
Exclusion NUREG-0313 B-D 7.12. 6 801-02 UT NUREG-0619 B-3 7.12. 6 801-02 3 UT NUREG-0619 FW Nozzle Safe ends.
B-J 7.12.6 801-02 UT NUREG-0619-Welds at CRD Reroute.
NA 7.12.6 Bol-02 1 UT NUREG-0619 Base metal at CRD Reroute..
77(235)
2-SI-4.6.G Page 75 SECTION 8.1 EXAMINATION SCHEDULE PART 5 AUGMENTED EXAMINATIONS(*l)
Exam Augmented Ref. Reqmt Refueling Refueling Refueling Refueling Refueling Refueling Exam Program Number of Source Cycle 6 Cycle 7 Cycle 8 Cycle 9 Cycle 10 Cycle ll Exam(s)
Cate or Section Com onents Code Sam le Sam le Sam le Sam le Sam le Sam le Re uired Remarks B-N-1 7.12,9 2 B03-02 2 2 2 2 2 VT-1 IEB 80-13 CS Spargers B-J 7.12.10 31- B04-02 2 UT Tech Spec 4.6.G.2 Pipe Hhip B-A 7.12.11 21 B05-02 21 UT RPV Helds 7.12.1 D01-02 UTLRT D02-02 VT-1 B-N-1 7.12.2 D03-02 UT 7.12.3 F-A 7.12 4~ 23 D04-02 Examination frequency based on HPCI injections. Modified VT-1
~
NOTES:
(*1) Most of these components are considered within the Code examination numbers presented in Parts 1 through 4 of this Section. Nhere one examination may serve as Code credit and as Augmented credit, it shall be so credited.
(*2) These stainless steel welds contain coolant at a temperature of 200 degrees or less during power operation and do not require examination under- NUREG-0313. These welds are listed in Section 8.2, Part 2.
77(235)
2-SI-4 ' '
Page 76 SECTION 8 ' PART 1 UNIT 2 WELDS RE UIRED TO BE EXANINED PER GENERIC LETTER 88-01 WELD EXAM PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM METHOD ~INCHES CONFIG CATEGORY 2RAS RECIR UT 12 P,P A 2RA6 RECIR UT 12 PQSE A 2RB5 RECIR UT 12 P,P A 2RB6 RECIR UT 12 PQSE A 2RC5 RECIR UT 12 P,P A 2RC6 RECIR UT 12 PQSE A 2RD5 RECIR UT 12 P,P A 2RD6 RECIR UT 12 PQSE A 2RE5 RECIR UT 12 P,P A 2RE6 RECIR UT 12 PQSE A 2RF5 RECIR UT 12 P,P A 2RF6 RECIR UT 12 PQSE A 2RG5 RECIR UT 12 P,P A 2RG6 RECIR UT 12 PQSE A 2RH5 RECIR UT 12 P,P A 2RH6 RECIR UT 12 PQSE A 2RJ5 RECIR UT 12 PQP A 2RJ6 RECIR UT 12 PQSE A 2RK5 RECIR UT 12 P,P A 2RK6 RECIR UT 12 P,SE A 2RA1 RPV UT 12 N,SE A 2RB1 RPV UT 12 NQSE A 2RC1 RPV UT 12 N%SE A 2RD1 RPV UT 12 NQSE A 2RE1 RPV UT 12 NQSE A 2RF1 RPV UT 12 N,SE A 2RJ1 RPV UT 12 NQSE A 2RK1 RPV UT 12 NQSE A JP-2-1A RPV UT 4 NQSE A JP-2-1B RPV UT 4 NQSE A DRWC-2-07A RWCU UT 6 P,P A DRWC-2-07B RWCU UT 6 P,P A RWC-2-001-G001 RWCU UT 4 VQV A RWC-2-001-G002 RWCU UT 4 E,V A RWCU-2-003-G001 RWCU UT 6 E,P A RWCU-2-003-G002 RWCU UT 6 E,P A RWCU-2-003-G003 RWCU UT 6 PEN, P A RWCU-2-003-G004 RWCU UT 6 PQV A RWCU-2-004-G073 RWCU UT 4 PQV A RWCU-2-004-G074 RWCU UT 4 PQV A 0 77(235)
2-SI-4.6.G Page 77 SECTION 8.2 PART 1 UNIT 2 WELDS RE UIRED. TO BE EXAMINED PER GENERIC LETTER 88-01 WELD EXAM PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM METHOD ~INCHES) CONFIG CATEGORY DCS-2-04 CS UT 12 P,P C DCS-2-05 CS UT 12 P$ V C DCS-2-07 CS UT 12 P,P C DCS-2-13 CS UT 12 P,P C DCS-2-13A CS UT 12 P,P C DCS-2-14 CS UT 12 P%V C DSCS-2-01 CS UT 12 E,P C DSCS-2-02 CS UT 12 E$ P C DSCS-2-09 CS UT 12 P,P C TCS-2-403 CS UT 10 P%SE C TCS-2-405 CS UT 12 E$ V C TCS-2-406 CS UT 12 P%V C TCS-2-410 CS UT 12 E$ V C TCS-2-422 CS UT 12 P$ V C
'CS-2-426 CS UT 12 E,P C TSCS-2-418 CS UT 10 P%SE C GR-2-01 RECIR UT 28 P,PMP C GR-2-02 RECIR UT 28 P%V C GR-2-03 RECIR UT 28 E$ V C GR-2-04 RECIR UT 4 C$ P C GR-2-07 RECIR UT 4 C,P C GR-2-08 RECIR UT 28 T,X C GR-2-09 RECIR UT 12 P,P C GR-2-12 RECIR UT 12 P,P C GR-2-18 RECIR UT 22 H,X C GR-2-19 RECIR UT 12 P,P C GR-2-22 RECIR UT 12 P,P C GR-2-25 RECIR UT 22 H$ V C GR-2-26 RECIR UT 22 H%V C GR-2-27 RECIR UT 28 P,PMP C GR-2-28. RECIR UT 28 P,V C GR-2-29 RECIR UT 28 E$ V C GR-2-30 RECIR UT 4 C$ P C GR-2-33 RECIR UT 4 C%P C GR-2-34 RECIR UT 28 P,X C GR-2-35 RECIR UT 12 P,P C GR-2-38 RECIR UT 12 P,P C GR-2-41 RECIR UT 12 P,R C GR-2-44 RECIR UT 22 H,X C GR-2-48 RECIR UT 12 P,P C GR-2-51 RECIR UT 22 H,V C 77(235)
2-SI-4.6.G Page 78 SECTION 8.2 PART 1 UNIT 2 WELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 MELD EXAM PIPE SIZE MELD IGSCC EXAM NUMBER SYSTEM METHOD ~INCHES ) CONFIG CATEGORY GR-2-52 RECIR UT 22 H,V C GR-2-54 RECIR UT 28 E,P C GR-2-55 RECIR UT 28 P,T C GR-2-56 RECIR UT 28 ESV C GR-2-57 RECIR UT 28 PSV C GR-2-58 RECIR UT 28 E,PMP C GR-2-60 RECIR UT 28 E,P C GR-2-62 RECIR UT 28 E,V C GR-2-63 RECIR UT 28 PSV C GR-2-63A RECIR UT F,F C GR-2-63B RECIR UT 4 BC C GR-2-64 RECIR UT 28 E,Pt1P C KR-2-01 RECIR UT 4 BC C KR-2-02 RECIR UT 28 E,P C KR-2-03 RECIR UT 28 P,T C KR-2-04 RECIR UT 4 BC C KR-2-11 RECIR UT 22 R,X C KR-2-12 RECIR UT 22 H,X C KR-2-13 RECIR UT 12 BC C KR-2-15 RECIR UT 22 CSH C KR-2-19 RECIR UT 12 BC C KR-2-20 RECIR UT 12 BC C KR-2-23 RECIR UT 4 BC C KR-2-24 RECIR UT 28 E,P C KR-2-25 RECIR UT 28 P,T C KR-2-26 RECIR UT 4 BC C KR-2-33 RECIR UT 22 R,X C KR-2-34 RECIR UT 22 H,X C KR-2-35 RECIR UT 12 BC C KR-2-42 RECIR UT 12 BC C KR-2-45 RECIR UT 28 E,P C KR-2-46 RECIR UT 28 P,T C KR-2-47 RECIR UT 28 E,P C KR-2-48 RECIR UT 28 E,P C KR-2-49 RECIR UT 4 BC C KR-2-50 RECIR UT 28 E,P C KR-2-51 RECIR UT 28 E,P C KR-2-52 RECIR UT 28 E,P C KR-2-53 RECIR UT 4 BC C 77(235)
2-SI-4.6.G Page 79 SECTION 8.2 PART 1 UNIT 2 WELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD EXAM PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM METHOD ~(INCHES CONFIG CATEGORY DRHR-2-02 RHR UT 24 P iv C DRHR-2-04 RHR UT 24 E,P C DRHR-2-05 RHR UT 24 Piv C DRHR-2-06 RHR UT 24 Piv C DRHR-2-07 RHR UT 24 Piv C DRHR-2-08 RHR UT 24 P,V C DRHR-2-13 RHR UT 24 E,P C DRHR-2-14 RHR UT 24 E>V C DRHR-2-15 RHR UT 24 P,V C DRHR-2-16 RHR UT 24 Eiv C DRHR-2-17 RHR UT 24 Piv C DRHR-2-18 RHR UT 24 P,T C DRHR-2-19 UT 20 P,T C DRHR-2-21 RHR UT 20 E,V C DRHR-2-23 RHR UT 20 P,V C DSRHR-2-01 UT 24 E,P C DSRHR-2-02 RHR UT 24 P,P C DSRHR-2-03 RHR UT 24 P,P C DSRHR-2-04 UT 24 E,P C DSRHR-2-04A UT 24 E,P C DSRHR-2-05 RHR UT 24 E,P C DSRHR-2-05A RHR UT 24 E,P C DSRHR-2-06 RHR UT 24 P,P C DSRHR-2-07 RHR UT 24 E,P C DSRHR-2-08 RHR UT 6 BC C DSRHR-2-09 RHR UT 20 E,P C DSRHR-2-10 UT 20 E,P C DSRHR-2-11 RHR UT 20 E,P C TRHR-2-191 RHR UT 20 Eiv C N 1A-SE RPV UT 28 N,SE C N 1B-SE RPV UT 28 NESE C TCS-2-401 RPV UT 10 NESE C TCS-2-417 RPV UT 10 NESE C DRWC-2-01 RWCU UT 6 Piv C DRWC-2-01A RWCU UT 6 P,V C DRWC-2-02 RWCU UT 6 Eiv C DRWC-2-03 RWCU UT 6 Piv C DSRWC-2-01 RWCU UT 6 E,P C 77(235)
2-SI-4 ' '
Page 80 SECTION 8 ' PART 1 UNIT 2 WELDS RE UIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD EXAM PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM METHOD ~(INCHES CONFIG CATEGORY DSRWC-2-01A RWCU UT 6 E,P C DSRWC-2-02 RWCU UT 6 E,P C DSRWC-2-06 RWCU UT 6 E,P C RCRD-2-49 CRD UT 4 Eiv D RCRD-2-50 CRD UT 4 Eiv D RCRD-2-52 CRD UT 4 Piv D DRHR-2-03 RHR UT 24 Piv D DRHR-2-11 RHR UT 24 Piv D DRHR-2-12 RHR UT 24 Piv D RCRD-2-33 RPV UT 4 CSN D TCS-2-421(OL) CS UT 12 Eiv E GR-2-15(OL) RECIR UT 12 P,R E GR-2-45(OL) RECIR UT 12 P,P E GR-2-53 RECIR UT 28 PSSE E GR-2-59(OL) RECIR UT 28 PSSE E GR-2-61(OL) RECIR UT 28 P,P E KR-2-14 RECIR UT 12 BC E KR-2-36 RECIR UT 12 BC E KR-2-37 RECIR UT 22 CSH E KR-2-41 RECIR UT 12 BC E DRHR-2-09 RHR UT 24 P,T E DRHR-2-22 RHR UT 20 Piv E DSRWC-2-03(OL) RWCU UT 6 E,P E DSRWC-2-04(OL) RWCU UT 6 E,P E DSRWC-2-05(OL) RWCU UT 6 E,P E DRHR-2-03B RHR VT-2 24 P,P G DRHR-2-13B RHR VT-2 24 P,P G 77(235)
2-SI-4.6.G Page 81 SECTION 8.2 PART 2 UNIT 2 STAINLESS AND DISSIMILAR METAL WELDS NOT SUBJECT TO GENERIC LETTER 88-01 EXAMS WELD PIPE SIZE WELD IGSCC 'XAM NUMBER SYSTEN ~INCHES) CONFIG CATEGORY NETHOD CONNENTS DCS-2-01 CS 12 P,V NA N/A TEMPERATURE EXCLUSION DCS-2-02 CS 12 ESV NA N/A TEMPERATURE EXCLUSION DCS-2-03 CS 12 PSV NA N/A TEMPERATURE EXCLUSION DCS-2-10 CS 12 ENV NA N/A TEMPERATURE EXCLUSION DCS-2-11 CS 12 PSV NA N/A TEMPERATURE EXCLUSION DCS-2-12 CS 12 PRV NA N/A TEMPERATURE EXCLUSION DSCS-2-14 CS 12 E,P NA N/A TEMPERATURE EXCLUSION DSCS-2-15 CS 12 E,P NA N/A TEMPERATURE EXCLUSION DSCS-2-16A CS 12 P,PEN NA N/A INACCESSIBLE IN PENETRATION X-16A.
TEMPERATURE EXCLUSION.
DSCS-2-16B CS 12 P,PEN NA N/A INACCESSIBLE IN PENETRATION X-16A.
TEMPERATURE EXCLUSION.
SHPCI-2-1 HPCI 12 FEP N/A TEMPERATURE EXCLUSION SHPCI-2-2 HPCI . 12 E,P NA N/A TEMPERATURE EXCLUSION SHPCI-2-3 HPCI 12 E,P NA N/A TEMPERATURE EXCLUSION SHPCI-2-4 HPCI 12 E,P NA N/A TEMPERATURE EXCLUSION SHPCI-2-5 HPCI 12 E,P N/A TEMPERATURE EXCLUSION 77(235)
2-SI-4.6.G Page 82 SECTION 8.3 ASME CLASS 1 E UIVALENT VALVE LIST GROUP VALVE SIZE ISI DWG VENDOR MATERIAL VALVE NUMBER NUMBER INCH SYSTEM NUMBER VENDOR DWG NO. SPEC: TYPE COMMENTS 3-554 24 FW ISI-0269-C ATWOOD & 20788-H A-216 WCB CHECK 3-558 MORRILL 3-568 3-572 HCV3-66 24 FW ISI-0269-C POWELL 035879-2 A-216 WCB GATE HCV3-67 FCV68-01 28 RECIR ISI-0270-C DARLING 94-12086 A351 CF8 GATE FCV68-77 FCV68-03 28 RECIR ISI-0270-C DARLING 94-12086 A351 CF8 GATE FCB68-79 FCV6&-33 22 RECIR ISI-0270-C DARLING 94-12086 A351 CFB GATE FCV68-35 FCV1-14 26 MS IS I-0222-C ATWOOD 5 20851-H A216 WCB GLOBE FCV1-15 MORRILL FCV1-26 FCV1-27 FCV1-37 FCV1-38 FCV1-51 FCV1-52 77(235)
2-SI-4.6.
Page 83 SECTION 8.3 ASME CLASS 1 E UIVALENT VALVE LIST (Continued)
GROUP VALVE SIZE ISI DHG VENDOR MATERIAL VALVE NUMBER NUMBER INCH SYSTEM NUMBER VENDOR DNG NO. SPEC. TYPE COMMENTS PCV1-004 6 MS IS I-0312-B TARGET ROCK PL-7657-100 A216 NCB PILOT PCV1-005 & A105 OPERATED PCV1-018 RELIEF PCV1-019 PCV1-022 PCV1-023 PCV1-030 PCV1-031 PCV1-034 PCV1-041 PCV1-042 PCV1-179 PCV1-180 HCV74-69 24 RHR IS I-0221-C PONELL 035880-3 A351 CF8M GATE HCV74-55 FCV74-54 24 RHR I SI-0221-C ATHOOD & 20800-H A351 CF8M CHECK FCV74-68 MORRI LL FCV74-52 24 RHR ISI-0221-C HALHORTH A-12334-MlE A351 CFBM GATE No B-G'-2 10 FCV74-67 Bolting.
HCV74-49 20 RHR IS I-0221-C PONELL 036207-2 A351 CF8M GATE FCV74-47 20 RHR ISI-0221-C HALHORTH A-12332-MlC A216 NCB GATE No B-G-2 12 bolting.
15 85-577 4 CRD ISI-0272-C VELAN P-339231-13 A182 TP316 GATE Exempt from 8-M-2 exams.
Size <= 4".
77(235)
2-SI-4.6.G Page 84 SECTION 8.3 ASME CLASS 1 E UIVALENT VALVE LIST (Continued)
GROUP VALVE SIZE ISI DNG VENDOR MATERIAL VALVE NUMBER NUMBER INCH SYSTEM NUMBER. VENDOR DNG NO. SPEC. TYPE COMMENTS 16 HCV75-27 12 CS ISI-0271-C POHELL 0360334-2 A351 CF8M GATE HCV75-55 17 FCV75-26 12 CS ISI-0271-C ROCKNELL PD-420652 A351 CF8M CHECK FCV75-54 18 FCV75-25 12 CS IS I-0271-C HALNORTH IVP-1198 A351 CF8M GATE No 8-G-2 FCV75-53 bolting.
19 69-500 6 RHCU ISI-0272-C VELAN P-33160-20 A182 F316 GATE 21 FCV69-01 6 RNCU ISI-0272-C VELAN P-33160-20 A182 F316 GATE FCV69-02 22 69-579 4 RNCU ISI-0272-C VELAN P-35177-4 A105 GRll CHECK Exempt from 8-M-2 exams.
Size < 4".
23 69-580 4 RHCU ISI-0272-C VELAN P-35177-3 A105 GR11 GATE Exempt from B-M-2 exams.
Size <= 4".
24 FCV71-40 6 RCIC ISI-0272-C ROCKHELL PD-420688 A216 WCB CHECK 25 FCV73-02 10 HPCI ISI-0273-C CRANE PB-139989 A216 HCB GATE No 8-G-2 FCV73-03 bolting.
26 FCV73-45 14 HPCI ISI-0273-C ROCKNELL PD-420687 A216 HCB CHECK FCV74-48 20 RHR ISI-0221-C HALNORTH A-12331-MlC A351 CFBM GATE No 8-G-2 27 bolting.
28 69-630 4 RHCU ISI-0272-C ANCHOR/ C23650 SA351 CF8M CHECK Exempt from DARLING 8-M-2 exams.
Size <= 4"
2-SI-4.6.G Page 85 SECTION 8.4 REQUESTS FOR RELIEF 77(235)
2-SI-4.6;G Page 86.
RE VEST FOR RELIEF ISI-2-1
~Com onents: Reactor Pressure Vessel Integral Attachment
'upport Class:
Ins ection Re uirements: ASME Section XI, Table IWB-2500-1, Examination Category B-H, Item Number B8.10, Surface examination on two sides, Figure IMB-2500-13.
Basis for Relief: Nonremovable RPV insulation limits the access to the integral attachment weld of the support skirt to the RPV. Only two access ports, approximately 180 degrees apart, provide access to the O.D. for examination of two 24"'ections of the integral attachment weld. Also, the I.D. is totally inaccessible.
Alternate Ins ection: UT of the four feet of accessible O.D. surface during the interval. Examination of one 24" section shall be scheduled in the second period and other 24" section shall be scheduled in the third periods 77(235)
2-SI-4.6.G Page 87.
RE VEST FOR RELIEF ISI-2-2
~Com onents: Reactor Pressure Vessel Threads in Flange Classification:
B-G-1 Item Number. B6.40 Ins ection Re uirements: ASME Section XI, Table IWB-2500-1, Examination Category B-G-1, Item Number B6.40, Volumetric Examination, Figure IWB-2500-12.
Basis for Relief: The configuration of the raised cladding sealing surface on the face of" the flange and the stud hole locations with respect to each other limit the accessible volume of examination to 68X.
Alternate Ins ection: None.
0 77(235)
2-SI-4.6eG Page 88'E UEST FOR RELIEF ISI-2-3
~Com onents: Reactor Pressure Vessel Nozzle to Vessel Head Weld (N6 Nozzle)
Classification:
B-D Item Number.'3.90 Ins ection Re uirements: ASME Section XI, Table IWB-2500-1,, Examination Category B-D, Item Number B3.90, Volumetric Examination, Figure IWB-2500-7.
Basis for Relief: The nozzle to head contour limits the accessible volume of examination performed from the O.D. to 60X.
Alternate Ins ection: None.
77(235)
2-SI-4.6.G Page 89'E UEST FOR RELIEF ISI-2-4
~Com agents: Class 1 and/or Class 2 Piping Welds Classification: lor2 Code Cate pries: B-F, or B-J, and C-F-1, or C-F-2 Item Numbers: B5.130, B9.10, or B9.30, and C5.10, or C5.50 Ins ection Re uirements: ASNE Section XI, Table IWB-2500-1, Examination Categories B-F and B-J > NPS 4" or Table IWC-2500-1, Examination Categories C-F-1 and C-F-2
) NPS 4" and >= 3/8" nominal wall.
Basis for Relief: In some cases it is not possible to perform the volumetric ultrasonic examination from both sides due to weld configuration, nonremovable support interference, nonremovable fire retardant insulation in adjacent wall penetration, elbow, valve, or pump adjoining the weld; etc. The surface examination was completed without limitation unless otherwise noted. See attached table for details of each weld.
None.
77(235)
2-SI-4.6.G
~ ~
Page 90 REQUEST FOR RELIEF ISI-2-4 (Continued)
ISI CODE HELD CODE ITEM SIZE DRAHING NUMBER CAT. NUMBER MATL NPS S amp 1 e CONFIG Remarks DCS-2-03 8-J 89.11 SS 12 ISI-0271-C VLV to BELLOHS 37.4 No scan 3 or 4, limited scans 5 & 6.
DCS-2-12 8-3 89.11 SS 12 ISI-0271-C VLV to BELLOHS 37.4 No scan 3 or 4, limited scans 5 & 6.
TCS-2-422 8-F 85.130 DM 12 ISI-0271-C PIPE to VLY 86.5 No scan 4, limited scans 5 & 6.
GMS-2-10 8-3 89.11 CS 26 ISI-0222-C VLY to PIPE 86 No scan 3 and surface restriction.
GMS-2-10-LS 8-3 89. 12 CS 26 ISI-0222-C LONGITUDINAL HELD 16.7 Only 2" of weld was accessible due to fire retardant material in an adjacent penetration. This limitation extended to the volumetric and surface examinations.
DRHR-2-03 8-3 89.11 SS 24 ISI-0221-C VLV to FLUED HEAD 52 Limited due to surface contour.
DRHR-2-12 8-J 89.11 SS 24 ISI-0221-C VLY to FLUED HEAD 55 Limited due to surface contour.
TRHCU-2-02 8-J 89. ll SS 4 ISI-0272-C VLY to VLV 50 No scans 3 or 4.
RHC-2-001-G002 8-F 85.130 DM 4 ISI-0272-C VLY to ELL 75 PSI exam. Held replaced DRHC-2-58 No scans 3 or 4, limited scans 5 & 6.
Construction radiograph used to accept weld on volumetric basis.
RHCU-2-004-G073 8-3 89.11 SS 4 ISI-0272-C PIPE to VLV 87.2 PSI exam. No scan 4, limited scans 5 & 6. Construction radiograph used to accept weld on volumetric basis.
RHCU-2-004-G074 8-3 89. 11 SS 4 IS I-0272-C VLV to TEE 32 PSI exam. Held replaced DRHCU-2-60 No scans 3 or 4, limited scans 5 & 6.
Construction radiograph used to accept weld on volumetric basis.
LAST PAGE 77(235)
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 EXAMINATION
SUMMARY
AND RESOLUTION SHEET INSPECTION REPORTS
INDEX The following is a matrix that correlates the relief requests to the applicable inspection report(s).
Relief Re uest Com onent Weld Number Re ort Number ISI-2-2 Reactor Pressure Vessel R-0034 Threads in Flange ISI-2-3 Reactor Pressure Vessel R-0064 Nozzle to Vessel Head Weld (N6 Nozzle)
ISI-2-4 DCS-2-03 R-0072 DCS-2-12 R-0066 TCS-2-422 R-0281 GMS-2-10 R-0194 GMS-2-10-LS R-0195 DRHR-2-03 R-0099 DRHR-2-12 R-0100 TRWCU-2-02 R-0260 RWC-2-001-G002 R-0328 RWCU-2-004-G073 R-0240 RWCU-2-004-G074 R-0241
EXAMINATlON REPORT NO.
7ENNESSEE VAllEY AUTHORITY
SUMMARY
AND RESOLUTlON SHEET R-oozy PROJECT: UNIT: LV:
SYSTEM:
7P-E'XAMINER:
EXAMI LV:
WELD I.D.: EXAMINER: LV:
CONFIG: TO: EXAMINER: LV:
PROCEDURE:
NDE METHOD:
N-~~
NUT FLOW REV.:
0 PT
~7 TC:
/'~ 7 7ioA .
ace a
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r O C
r O e i,*~2 /h gc lP EVALUATOR: LEVEL: DATE:
DATE: Q- I t C CURRENCE: LEVEL: DATE:
PAeE~OV 5 TVA 19670C (NP 7/92) 050
o6< OO3d/
DIGITAL ULTRASONIC CALIBRATION NO.
CALIBRATION TENNESSEE VALLEYAUTHORITY DATA SHEET C-oop PROJECT: UNIT: c2. CAUBRATION DATE:
PROCEDURE: N-UT- I8 REVJ ~l TC: ~ 42 CAUBRATION BLK NO.: TEMP:. ~OD F SIMULATOR BLOCK NOJ INSTRUMENT:
/O THERMOMETER SERIAL NO.:
gb~/A I/jO MODEL/TYPE:
SERIAL NUMBER:
COUP LANT: / BATCH:
EXAM TYPE: Q SHEAR H LONG. Q RL TRANSDUCERMANUF:
ANGLE VERIFICATION:
SERIAL NO:
SIZE: / FREQUENCY: . O Mhz BLOCK TYPE: SERIAL NO.: P
~+~
~
CABLE TYPE: LENGTH:
NOMINALANGLE: / ACTUALANGLE:
DAC INSTRUMENT SElTINGS 100 REFLECTOR REFERENCE MEMORY ORIENTATION SENSITIVITY STORE NO.'
80 AXIAL dB
~
~
CIRC dB M
P 60 FREQUENCY: C MhZ ANGI.E: O DEG.
L DELAY:, uS FILTER:
~s~
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U D
20 REJECT: ~D. G .DAMPING! 5OC7 ohms E
TCG: Q ON ~FF DUAL: Q ON [5OFF DISPLAY WIDTH INITIALTIME: ~o7>>: :/
INITIALCALIBRATION FIEF. REFLECTOR: 5 o/L 22I/GAIN: ~/dS VERIFICATION TIMES 4
AMPLITUDE: % METAL PATH:
8)
L SIGNAL 1 100 90 80 70 60 50 40 30 20 10 N
I C SIGNAL 2 60 Q WO 3g 30 3 PI/I /O E H A E GAIN SET -12 SET +12 SET +6 ATTENUATOR 32TO48 16 TO24 20% 64 TO 96 40% 64 TO 96 II C SIGNAL AMP 80%
I K T
Y REFER TO CALIBRATIONREPORT /If FOR PREVIOUS SATISfACTORY LINEARITY COMMENTS: WELDS EXAMINED:
sn o o 2-0
/j O<
ANIL,g~
EXAMINER:
'XAMINE LEVEL:
DATE g I REVI ED BY: LEVEL: DATE: PAGE 0 OF S TVA 19674A (NP 10/92) 05 j.
TVA PROJECT: 8 SYSTEM: REPORT NO.:
Office of Nuclear Power Unit: WELD NO.: 8/ /i 08 7b//shd~d ggSW d/ $ 7'(d.
( a.5 g~ ~Dr
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GDS- 8q7~ 'J~ piy~s/zn/ PoTc< / n'Shan K A'Raw z/ $ 7~~
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3 PAGE 3 OF w TVA 69 (ONP.6.88)
TVA PROJECT: 8/ ~ SYSTEM: REPORT NO.:
Office of Nuclear Power Unit: WELD NO.: Roc gy g pg g Ey/ 88E'+
pgEA'1~J
.Bush'~p 7yfic.AI S/ ud'ooFip'as+ 7,o<
r~z 8gc=a zF go Fg+~ Fc g 6 zwissr F) es b8 Po oF ~As E~ ~ Z~d os p ~ ~~
BY: LEVEL: DATE: cP D PAGE F OF W TV 9669 (ONP-6.88)
TVA MANUAL ULTRASONIC EXAMINATION DATA SHEET REPORT NO.
Poo3q project: Bi Material Type: [E5S Q SS I7 Other System: Exam Surface: HID [BOD Weld I.Det surface Temp: 2i&F Pyro No: ~S~fFD Conf lg: To: Exam Start: O Cal Sheet No: COo Exam End: /Z 5'0 Circ. Scan Sens:
Procedure: Rev:~ PDR~F Ax Scan Sens: db Lo Reference Si C/O p 7o 0 Wo Reference Ind L (In) From Ref At Max Amp Max Nominal Indication Type No Amp Scanning Remarks 1 Max 2 W
Max MP Max % DAC Angle Sketch: Remarks:
/PE ~Sushi yy q
-o8 .V z 5Tud Y
~~>~ ExN CduEiitp w'd Rebel Level: Date: Q- ~- I t-M Date:
mid,.- . c/w Level: Date: ~-( Level: DTf- Date: ~t3 Page M of TVA 40078 (ONP 10 88) 1-1 08.999.49
4 4
EXAMINATION REPORT NO.
TENNESSEE VALLEYAUTHORITY
SUMMARY
AND RESOLUTION SHEET R- oc'cq PROJECT: BI- hJ P UNIT: EXAMINER: Ko hl SYSTEM: R P V EXAMINER: A WELD I.D.: EXAMINER:
OK EXAMINER:
~ ~
TO:
FLOW CAL SHT NO'S: C C>
PROCEDURE: N-UE-~ REV.: TC:
NDEMETHOD: HUT 0 PT Cl MT 0 VT 0 T L- 4lAV AQ Li A Axxo l 0 oe kl 40to VE A ~
-UT F Coy 45= ZG I 4S = 55.4%
CuO = o) 4 G% + 445E hhM ,S,zS + (q z.s')~>7 t,(~~) + 46 S(.zS)=go>
(n % + (. "s=16.5 EVALUATOR LEVEL DATE:
DATE+
CONCURR CE: LEVEL: +ZZ DATE:
PAGE~OF lB TVA 196 (NP 7I92) 131
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TVA 19670A (NP 7/92) 142
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MANUALULTRASONIC REPORT NO.
lENNESSEE VAILEYAlllHORITY PIPING EXAMINATION DATA SHEET R-oo7@
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DIGITALULTRASONIC CALIBRATIONNO.
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MANUALULTRASONIC NO.
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REPORT TENNESSEE VAILEYANHORITY PIPING EXAMINATION DATA SHEH R-opgi UNIT: EXAMIMATIOMDATE: o Il SYSTEM: Ce M, 5&km. STARTTIME: o~ QS'S END TIME: ca55 Qa l WELD I.D.: WC. EXAM SURFACE: Q ID lg OD CONFIG: 0 RE e.5. TO: A.cU 5. MATERIALTYPE: 69 CS 13 SS 0 CSCL 0 CCSS FLOW PROCEDURE: N-UT- Ut REU.; I+ TC: sllA.
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SUMMARY
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ROJECT: EXAMINER:
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TVA 19674A (NP 10/92)
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MANUALULTRASONIC REPORT NO.
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REVIEWED BY: LEVEL: DATE: + /5 PAGE 'f OF~
TVA 1967D (NP 7/92) 6
0 REPORT NO WALL THICKNESS TVA 0'eld PROFILE SHEET go/9p PROJECT: WELD NO:
UNIT: SYSTEM:
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DATE:g MINER: LEVEL gg REVIEWED BY: LEVEL: DATE: 2-/Z PAGE ~OF ~
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REVIEWED BY: LEVEL: DATE: PAGE 3 OF S TVA 19674A (NP 10/92) 480
MANUALULTRASONIC REPORT NO.
TENNESSEE VAIIEYANHORITY PIPING EXAMINATION DATA SHEET R- o/95 ECT:
SYSTEM:
WELD I.D.:
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START TIME:
EXAM SURFACE:
0' Q
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NO. Ll L MAX L2 W MAX MP MAX %DAC 5-14 ANG. NRI TYPE DAMPING ETC.
6o' REMARKS/UMITATIONS:
ANII EXAMINER: LEVEL INER: LEVEL: DATE gg REVIEWED BY: LEVEL: DATE: 3-~~XZ V OF 3'AGE
~
IVA19670 (NP 7/92)
~,
WALL THICKNESS REPORT NO:
TVA 0'eld PROFILE SH EET Ro/9s PROJECT WELD NOI UNIT: SYSTEM:
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0 EXAttIIIERr DATE:
TVA 19668 (NP.$ .89)
REVIEWED BY 3V< D. AIIII:
DATE'AGE 2 OF 482 I 108 99984
R3MGNATION REPORT NO.
Tegznessee Valley Authonty
SUMMARY
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RESOLUTION SHEET R-o~q q.
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ECT: UNI: CAUBRATION DATE:
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DATE:
EXAMINER; PAGE~OF Rc
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REVIEWED BY: DATE; TVA 19674A (NP 10/92)
MANUALULTRASONIC REPORT NO.
TENNESSEE VAILE1'NHORITY PIPING EXAMINATION DATA SHEET R- goqq PROJECT; c5 MMJ UNIT: EXAMINATIONDATE: O Z. /V SYSTEM:
WELD I.D.: 9Zh 8 Z. O~ EXAM SURFACE: Q ID ~D coNFIG: U>re~ , ~r'usual ~r>
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PAGE l OF~O TVA 19670 (NP 7/92) 269
)e&'anF v ~oo I f Dl8lTALULTRASONlC CALlBRATlON NO.
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LE EL: DATE:
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TVA 19674A (NP 10/92) 270
MANUALULTRASONIC REPORT NO.
TENNESSEE VAILEYA fJTHORlTY PIPING EXAMINATION ~/~i g/3/e DATA SHEH goo<9 PROJECT: B WK/ UNIT: EXAMINATIONDATE: > 2. / 7 0 8 SYSTEM: START TIME: / 6 /0 END TIME: /6 9/
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SERIAL NUMBER ~c /94'.
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REVIEWED BY: LEVEL'ATE: REPASS rIATGTdr PAGE~/" OF'X>""
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MANUALULTRASONIC REPORT NO.
TENNESSEE VAlLEVAUTHORITY PIPING EXAMINATION DATA SHEET R- oo9p PROJECT: W/ W7 UNIT: EXAMINATIONDATE: OZ, ~
SYSTEM: START TIME: // 0 O'ND TIME: /1/O
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REPORT NOI
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l400.9994 TVA 196Ql(NP 5 09) ~
t;-";:: 284
RUMINATION RBPORT NO.
Tennessee VaUey Authonty SUhHEARY AND RBSOI.UTION SHEETS/or- R-o(o~
k Examiner. meQ4 LwLv: ~
zt.
Sysbm: RramincT: Lv:
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~
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EXAMlNATlON REPORT NO.
TENNESSEE VAllEYAUTHORITY
SUMMARY
AND RESOLUTlON SHEET R-O(OO ECT: ro V:
SYSTEM: EXAMINER: LV:
WELD I.D.: KQUNI~ LV:
TO: EXAMINER: LV:
PROOEOURE N //~7/~ REV FLOW
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DATE "/
PaeE N OF~4 TVA 19670C (NP 7/92)
h6Poev +P.ojo DlGlTAL ULTRASONlC CAl.lBRATlON NO.
TENNESSEE VALLFYAl/THORlIV CAl.lBRATlON DATA SHEET C- cq7 FN P 2 3
~
CVECT: UNIT: CALIBRATIONDATE:
PROCEDURE: N-UT- ~~ REV.: ~~ TC: ~~~ CAUBRATION BLK NO.: ~- 9 TEMP.: F INSTRUMENT: SIMULATORBLOCKNO.: 4 O&0 "8 MODE47YPE: THERMOMETER SERIAL NO.: 5 3I 4' no SERIAL NUMBER: I COUPLANT: +v e XC BATCH: 908 8 EXAM TYPE: Pf SHEAR Q LONG. Q RL TRANSDUCERMANUF:
ANGLE VERIFICATION:
SERIAL NO:
BLOCK TYPE:
CABLE TYPE: G-- NC- ha DT'ENGTH: NOMtNALAMQLE: N~ AC7UALANGLE; DAC
~~'NSTRUMENT SETTINGS REFLECTOR REFERENCE MEMORY ORIENTATION SENSITIVITY STORE NO.
80 AXIAL o~H. dB A CIRC o~ p3. 5 dB M
P L
I 60 FREQUENCY: ~~'~ MhZ ANGLE: ~~ DEG.
40 SOUND VELOCITY: ~g~~ uS POWER: ~c46 D ohms E 20 TCG: Q ON Qf OFF DUAL: Q ON )(OFF INITIALCALIBRATION VERIFICATION TIMES
- 1) P3 O 2) 3) <</A- 4) W/Z
- 6) A/W 6) ~In 7) /W L
SIGNAL 1 100 90 80 70 60 50 40 30 20 10 I VERTICAL N C SIGNAL 2 80 OO 3K /5 10 5 E H A 6 GAIN SET +12 R C AWENUATOR SIGNAL AMP 80% 32 TO 48 16 TO 24 20% 64TO96 '0% 64TO96 K
~~~
I T
Y REFER TO CALIBRATIONREPORT FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: WELDSEXAMINED: ~RII 'R /Z-XAMINER: e~ + LEVEL:
ANII irj EXAMINER: LEVEL:
DATE: +j REVIEWED BY: cP LEVEL: DATE: W >2 PAGE 3 OF /4 TVA 19674A (NP 10/92)
MANUALVLTRASONIC REPORT NO.
TENNESSEE VAllEYAUTHORITY PIPING EXAMINATION DATA SHEET R-O/oo ECT: UNIT: EXAMINATIONDATE: ~ P 3 SYSTEM: START TIME:
WELD LD.: 2 EXAM SURFACE'Q ID Qf OD MATERIALTYPE: E3 CS E SS C3 CSCL 0 CCSS PROCEDURE: N-UT- gg 8 I4 FLOW REV:. ~f TC: ~~ CAUBRATIONSHEET NO. C-Og7 Wo
REFERENCE:
EXAMINATIONANGLE DEG. e A. DEG.
Lo
REFERENCE:
C CIRC. SCAN SENSITlVITY 3e.c +G dB ll dB AXIALSCAN SENSITMTY hr W dB L (In) FROM REF. AT MAX AMP MAX EXAM IND. AMP NO. NOM INDICATIONINFORMATION:
NO. Ll MAX L2 W MAX MP MAX %DAC 5-14 ANQ. NRI TYPE DAMPINS ETC.
REMARKS/LIMITATIONS: 0 0I OM ~
Elhi fa 0 eve' I ee ANII MINER:
iXWINER:
REVIEWED BY:
LEVEL:
LEVEL LEVEL
~ Z sz/yp DATE:
DATE:
PAGE 0 OF~
TVA 19670 (NP 7i92) 28'
R&o~7 <POlm DlGlTALULTRASONlC CALIBRATlONNO.
'NIT:
TENNESSEE VAllEYAUTHDRITY CALlBRATlON DATA SHEET C- 0'/B ECT: Z CAUBRATION DATE: OZ PROCEDURE: N-UT- ~l REV.: /M TC: A3FT 8o CAUBRATION BLK NO.: TEMP.: 70 F INSTRUMENT: SIMUlATOR BLOCK NO.: &C)Z 4 MODEL/TYPE: D~io THERMOMETER SERIAL NO.:
SERIAL NUMBER 5C] H4 COUPLANT: A> i BATCH: O 9>o 8/
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SERIAL NO: S~c sa ANGLE VERIFICATION:
~ ioM18 Z-SIZE:
CABLE TYPE: ~- E'-~o FREQUENCY:
LENGTH:
Mhz NOMINALANGLB E5 L ACTUALANGLM ~f DAC INSTRUMENT SHTINGS I. 9IO7 REFLECTOR REFERENCE MEMORY
~wh8 ORIENTATION SENSITIVITY STORE NO.
/,gq 1 AXIAL dB A
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P I. Sty FREQUENCY: Z .GM MhZ ANGLE: W I DEG.
L I PROBE DELAY: '7. ZCn 7 uS FILTER: 0 SOUNOVELOCITY: ~RA e uS POWER:
REJECT: OO % DAMPING ~o ~ ohms E 20 TCG: 0 ON Ef OFF DUAL ~ON Q OFF INITIALCALIBRATION AMPLITUDE:
, ~AM:
DISPLAY WIDTH Ba % METALPATH:
'I J
INITIALTIME:
- 1) OSOC 78 2 FINALTIME:
VERIFICATION TIMES SIGNAL 1 100 90 80 70 60 50 40 30 20 10 I
N C SIGNAL2 50 Vp 5Q Do w'I zo p7 E H A E GAIN SET '+12 +6 R C ATTENUATOR SIGNAL AMP. 80% 32 TO 48 16TO24 20% 64TO96 '0% 64 TO 96 I
T K
78 Y REFER TO CALIBRATIONREPORT ~A FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: ~~Q oa jm WELDS EXAMINED: ~ + ~Z 2 /~
/C'EAFY ~/
ANII MINER: LEVEL:
DATE:
EXAMlNER: LEVEL REVIEWED BY: DATE: PAGE < OF~C TVA 19674A (NP 10192) 290
~ '
MANUALULTRASONIC REPORT NO.
TENNESSEE VALLEYA NHORITY PIPING EXAMINATION DATA SHEET R-o(oo PROJECT: UNIT: EXAMINATIONDATE: Oz. z.g g~
SYSTEM: START TIME: D SO7
~ 4A'8- R. (Z EXAM SURFACF: Q ID 3EOD WELD I.D.:
CONF IQ: QPO/Q ~ TO. ~)r ~ P~ / MATERIAI.TYPE: Q CS C3 CSCL F PYRO NP:
Q CCSS SURFACE TEMP:
FLOW PRm:EoURE; N UT IQ R~, ~g CAUBRATION SHEET NO.
Wo
REFERENCE:
MW/cC EXAMINATIONANGLE WSA'~ DEG. DEG.
Lo
REFERENCE:
CIRC. SCAN SENSITIVITY WqwrO dB dB AXIALSCAN SENSITIVITY dB L (In) FROM REF. AT MAX AMP MAX EXAM IND. AMP NO. NOM. INDICATION INFORMATION:
NO. MAX L2 W MAX MP MAX %DAC W14 ANQ. NRI TYPE DAMPINS HC.
REMARKS/LIMITATIONS: ~~
k~ W~/ ~~~.
eQ ~ ~ &+/~a- ~a ia XAMINER:
NAMINER: LEVEL: DATE:
REVIEWED BY: LEVEL: DATE:
PAGE ~ OF /0 TVA 19670 (NP 7/92) 291
~
DIGITALULTRASONIC CALIBRATIONNO.
TENNESSEE VALLEYAUTHORlTY CALIBRATION DATA SHEET C- ayg OJECT: UNIT: CALIBRATIONDATE: O 2 l'8 g
- PRocEDURE: N-UT- is REY:. i"I Tc: CAUBRATION BLK NO.: F TEMP.: bf 6 F INSTRUMENT:
SIMULATOR BLOCK NO.: 006 88 MODELflYPE: THERMOMETER SERIAL NO.: '
II 6 COUP LANT:
SERIAL NUMBER:
EXAMTYPE: Q SHEAR Q LONG. Q RL
~
TRANSDUCERMANUF:
ANGLE VERIFICATION:
SERIAL NO:
BLOCK TYPE; MhZ CABLE TYPE:
NOMINALANSLB 60 N AOTUALANSLB DAC INSTRUMENT SHTINSS 100 REFLECTOR REFERENCE MEMORY
~~ ~
ORIENTATION SENSITIVITY STORE NO.
80 AXIAL dB 0
A CIRC 6 da M 60 P FREQUENcY! Mhz ANELB 0 2 DED.
L I
PROBE DELAY; uS FILTER:
40 4 Itr SOUND VELOCITY: 0 uS POWER:
D E ZO TCG: Q ON l5 OFF DUAL: Q ON Q OFF INITIALCALIBRATION DISPLAY WIDTH D FINALTIME:
VERIFICATION TIMES l SIGNAL 1 100 90 80 70 60 50 40 30 20 10 VERTICAL N
I C
'H SIGNAL2 SO ~ yo 3$ zo ZS a I 1Q Io E
A E GAIN SET -12 +12 SET t6 II C A TENUATOR SIGNALAMP. 80 32 TO 48 16 TO 24 64TO96 '0% 64 TO 96 I K T
Y REF ER TO CALIBRATIONREPORT FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: 8 WELDS EXAMINED: +~++ ~ r Z-MZJ E~Z Qa&orjrZd04o A O'A W~i~
'A'g, Z<S,'Od- K~> o'~ AWZ,= <.+O" e7 Ear GoM ~~++.
LEVEL:
EXAMINER:
DATE: /
REVIEWED BY: LEVEL: DATE: ~ ~3 PAGE r OF~
TVA 19674A (NP IOIt92) 292.
MANUALULTRASONIC REPORT NO.
TENNESSEE VALLEYAUTHORITY PIPING EXAMINATION DATA SHEET R- o(o~
ROJECT: H W MP UNIT: EXAMINATIONDATE: oz/
SYSTEM: START TIME: /0 OQ END TIMF jQ? Cn WELD I.D,: 2IEA 8 EXAMSURFACE: Q ID ~OD
--'.~cJ /e TO: W/ MATERIALTYPE: 0 CS QKSS Cl CSCL 0 CCSS FLOW PROCEDURE: R-UT- ~J REV.: ~/ TC: A3PT CAUBRATIONSHEH'O.
Wo REFERENCE; 4C3K / EXAMINATIONANGLE &O DEG. DEG.
Lo
REFERENCE:
CIRC. SCAN SENSITIVITY MA aB AXIALSCAN SENSITIVITY <~/4 aB L (In) FROM REF. AT MAX AMP MAX EXAM IND. AMt NO. NOM INDICATIONINFORMATION:
NO. Ll MAX 1V MAX Mt MAX %DAC 5-14 ANO. NRI TYtE DAMPINS ETC.
O.o g.5o Z.P gg Cn9 W;u@N. s&e Agua, a,o)C PQ REMARKS/LIMITATIONS: ~~~0 WX~ WP+Z4- OKJK .
MINER: LEVEL:
EXAMINER: LEVEL DATE:
/
REVIEWED LEVEL DATE:
BY'VA IAGE 8 OF~
19670 (NP 7/92)
Pgg
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~
DIGITALUI.TRASONIC CAt.lBRATION NO.
TEhlIIIESSEE VALLEYAUTHORITY CAUBRATION DATA SHEET C- ohio OJECT: UNIT: CALIBFIATIONDATE! O 2 8 PROCEDURE: N-UT- /Eh REV.: /U TC: ~A aG/ 7g+GI7EP
.IO-PS'IMUlATOR INSTRUMENT:
BLOCK NO:. 602 MODEIJnPE: THERMOMETER SERIAL NO.;
COUP LANT:
SERIAL NUMBER:
TRANSDUCER MANUF!
EXAMTYP¹ Q SHEAR g LONG. Q RL ANGLE VERIFICATION:
SERIAL NO:
BLOCK TYPE:
. FREQUENCY: MhZ
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REVIEWED BY: DAT¹ + + ~ FM PAGE ~ OF
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TVA 19674A (NP IOIt92)
MANUALULTRASONIC REPORT NO.
TENNESSEE VAIIEY ANHORITY PIPING EXAMINATION DATA SHEET R- o/oo PFKXIECT: W ~Hi UNIT: EXAMINATIONDATE: oz./8 qa SYSTEM:
WELD I.D.: 3 8+M R ~ / Z EXAM SURFACEi Cl ID GOD
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REFERENCE:
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Lo
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REPORT NO:
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DIGITALULTRASONIC CALIBRATION NO.
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TVA 19674A (NP 50(92)
~98
MANUALULTRASONIC REPORT NO.
TENNESSEE VA1lEY AIJTHORlTY PIPING EXAMINATION DATA SHEET R- o(oo PROJECT: UNIT: EXAMINATIONDATE: OM ~Q g K SYSTEM: 'TART TIME: // 0 4y END TIME: /llD
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SUMMARY
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TENNESSEE VAILEYAUTHORITY CALIBRATION DATA SHEET C-)p,g ECT: SW~ ~ UNIT: CAUBRATION DATE'S PROCECURB N-UT- ~l REV.: I I TC: ~A CAUBRATION BLK NO.: 6l tW ~ TEMP.:W I F INSTRUMENT: SIMULATOR BLOCKNO.: + tto99 MODEUTYPE: 'D 6 L> THERMOMETER SERIAL NO.: 3 SERIAL NUMBER: COUPLANT: 0 + BATCH: 9 EXAMTYPE: @SHEAR Q LONG. Q RL
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- 5) A 6) + 7) A 8) A L
SIGNAL 1 100 90 80 70 60 50 40 30 20 10 I VERTICAL N C SIGNAL2 50 E H A E GAIN SET -12 +12 +6 ATTENUATOR R C SIGNAL AMP. 80% 32 TO 48 16 TO24 20% 64 TO 96 64 TO 96 I K T Y. REFER TO CAUBRATION REPORT FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: WELDS EXAMINED: MINER: P +LEVEL: LEVEL: DATE:
/~y ~MINER'EVIEWED BY: LEVEL: DATE: PAGE + OF TVA 19674A (NP 10/92)
g<l ag ~ >4'OR&0 DIGITALULTRASONIC CALIBRATIONNO. TENNESSEE VALLEYAUTHORlTY CALIBRATION DATA SHEET C- /3o Ear: G,I- QR UNIT: ck CA VBRATION PROCEDURE: N-UT- l9 RET.: g T~C: AL DATF'AVBRATION BLK NO. ( ~ TEMP.: W~ F INSTRUMENT: KK SIMULATOR BLOCK NO.: THERMOMETER SERIAL NO.: ad Q MODEL/TYPE: SERIAL NUMBER: 1 K COUPLANT: L) A'ATCH: 3l TRANSDUCER MANUF: EXAMTYPE: P SHEAR P LONG. g RL SERIAL NO: I W~ ANGLE VERIFICATION: SIZE: +WN FREQUENCY: Mhz BLOCK TYPE: il ~ SERIAL NO.: NOMlNALANGLE: ~fb ~i~L
~
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~
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% METALPATE:
GAIN: ~+ dB 1) 5)
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gK VERIFICATION TIMES A 3) 7) g A 4) 8) L 100 90 70 60 50 40 SIGNAL 1 80 30 20 10 I N C SIGNAL2 50 3 I I E H A E GAIN SET -12 +12 +6 ATTENUATOR R C SIGNAL AMP. 80% 32 TO 48 16 TO 24 20% 64 TO 96 40% 64 TO 96 I K T Y. REFER TO CALIBRATIONREPORT FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: WELDS EXAMINED: CD~ D MINER: 8-6 VARRR5 LEVEL: EXAMINER: LEVEL: DATE: f-f-fQ REVIEWED BY: LEVEL DATE: PAGE 3 OF T TVA 19674A (NP 10/92)
R~poR 7 +BocRG G D181TAL ULTRASONlC CALIBRATIONNO. TENNESSEE VAllE) AUTHORlPf CALIBRATION DATA SHEET C- /31 ECT: PROCEDURE: INSTRUMENT: N-UT- ++ FIEF.: I UNIT: I TC: ~ CAUBRATION DATE: CAUBRATION BLK NO.: SIMULATOR BLOCK NO.:
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~
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4) 8) SIGNAL 1 100 90 80 70 60 50 40 30 20 10 I VERTICAL N C SIGNAL2 50 M E H A 5 GAIN SET -12 +12 +6 ATTENUATOR R C SIGNAL AMp. 80g 32 TO 48 16 TO 24 20% 64 TO 96 40% 64 TO 96 I K T Y. REFER TOCAUSRATION REPORT ~+/ FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: WELDS EXAMINED: I (VI 4 5 LEVEL:
/~
MINER: LEVEL: DATE: MINER: yves REVIEWED BY: LEVEL: DATE: + +~ ~+ PAGE~OF TVA 19674A (NP 10/92)
MANUALULTRASONlC REPORT NO. TENNESSEE VAllEYANHORITY PlPNG EXAMlNATtON DATA SHEET R-og@o ECT: EXAMINATIONDATE: 6 AR 8 W SYSTEM: START TIME: END TIM¹ t WELD I D:. EXAM SURFACE: 0 ID QUOD CONFIG: 4c J~ TO: c~~ ~~ MATERIALTYPE: g CS 0 SS 0 CSCL 0 CCSS PROCEDURE N-UY- ~+ FLOW REV:. TC: A SURFACE YEMP: ~4 4Q'I F PYRO NO: c )So c CAUBRATIONSHEET N y/i g~ Wo
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~~
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L SIGNAL 1 l00 90 80 70 60 80 40 80 20 10 I VERTICAL II C SIGNAL2 50 9O 35 i{G /O 8 8 A E GAIN SET -12 +12 ATTENUATOR R C SIGNAL AMP 80~ 32 TO 48 16 TO 24 20% 64 TO 96 40% 64 TO 96 I II T Y. REFER TO CAUSRATION REPORT ~MA FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: It. Zu+E e4<<SR A~0~ ~O
-oOI- {- ool ANI ~+ ~
EXAMINER: LEVEL: I MINER: OATEN'~ REVIEWED BY: LEVEL PAGE 2 OF 8 TVA 19674A {NP 10/92) 4
DIGITALULTRASONlC CALIBRATION NO. TEIIINf$$ $E VAllEYAVTHORITY CALIBRATION DATA SHEET C-g 3i INSTRUMENT:
~
RE: N-UT- +1LL REV.: ~ 1 UNIT: TC: 3. NIR. CAUBRATION DATE: SIMULATOR BLOCK NO.: TEMP.: ~7 F MODEL/TYPE: us<- g THFRMOMETER SERIAL NO.: 1i ial SERIAL NUMBER: EXAM TYPE: Q SHEAR Q LONG. fg RL
~
TRANSDUCERMANUF: ANGLE VERIFICATION: SERIAL NO: SIZE: CABLE TYPE: 'RC
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- 1 "I FREQUENCY:
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- 3. 5 LENGTH:
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~~ W/~ Jl A, CIRC dB A ~
M F L 60 FREQUENCY: MhZ ANGLE: M~ DEG. I 40 SOUND VELOClTY: ~OSO. US POWER: ~LD D 20 TCG: Q ON Q OFF DUAL Q ON IERIOFF INITIALCALIBRATION DISPLAY WIDTH INITIALTIME: hH b4 FINALTIME:
tu VERIFICATION TIMES AMPLITUDE: ~~ % METALPATH: . '/SO 1) 5)
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SIGNAL 1 100 90 80 70 60 50 40 30 20 10 N E I C H SIGNAL 2 50 op+ c(g 3. I ~ ITEL IO A E GAIN SET -12 +12 +6 C ATTENUATOR II SIGNAL AMP. 80% 32 TO 48 16 TO 24 20% 64 TO 96 40% 64 TO 96 I K T Y, REFER TO CALIBRATIONREPORT ~l ~ FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: PILE,>> ~LCE ~J<A~U A~0 WELDS EXAMINED: Ob l
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EXAMINEFL LEVEL: 3E MINER: c~ ck LEVEL: ~ ~/+fate DATE:g ~~ ~ EVIEWED BY: LEVEL: PAGE S OF TVA 19674A (NP 10)92)
(i&i AYAH' r. SO >PE 5
~
DIGITALULTRASON)C CALIBRATIONNO. TENNESSEE VAIEEYATTTHORITY CALIBRATION DATA SHEET C-g3p T: PRUCECURB N-UT-F'NIT:
~~ REV.: I4 TC: ~IA CAUBRATION DATE:
lb - I C CAUBRATlON BLK NO.: TEMP.: 73 F INSTRUMENT: SIMULATORBLOCK NO.: 5 ID 5 THERMOMETER SERIAL NO.: 5'9 I 9 I /ie/ MODEIfrYPE: SERIAL NUMBEFL /FF EXAM TYPE: f3 SHEAR Q LONG. Q RL TRANSDUCER MANUF: ANGLE VERIFICATION: SERIAL NO: SIZE: CASLETYPB BL kC ~.
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100 REFLECTOR REFERENCE MEMORY ORIENTATION SENSITIVITY STORE NO. AXIAL IA. d8 A CIRC 5'4.O d8 M P
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L I 40 SOUND VELOCITY: 3.;$ ~ US POWER: ~A.L. TCG: Q ON Q OFF DUAL 8 ON QOFF INITIALCALIBRATION DISPLAY WIDTH INITIALTIME: 'l H(0 FINALTIME: VERIFICATION TIMES REF. REFLECTOR Co~s ~S u GAIN: 52.Q dB Vl~ 4)
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SIGNAL 1 100 90 80 70 60 50 40 30 20 10 I N C SIGNAL2. 50 q qy Is Ie 5 E II A E GAIN SET R C SIGNAL AMP. 80% 32TO46 16 TO 24 20% 64 TO 96 64 TO 96 I II 'lI'V T I F5 REFER TO CALISRATIONREPORT ~hI IA FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: MET 2ul i nA gEJQ WELDS EXAMINED: MC. - - Ob
~V iM Ih,mOW T=XAMINER: LEVEL 2C ANIL F MINER: LEVEL ~ K/I~ DATE:
g REVIEWED BY: LEVEL PAGE V OF 8 'TVA 19674A (NP 10/92)
I
'5l ~
MANUALULTRASONIC REPORT NO. TENNESSEE SYSTEM: WELDI.D.: VAllEYANHORITY Pw9
%LE.A.c'tsA RVC oL - OGl O'YEA UNIT:
C.LCAA
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~ u9 PIPING EXAMINATION (CXo I DATA SHEET EXAMINATIONDATE:
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START TIME: /$ 3'7 EXAM SURFACE: ico lo Q ID R-oszs coo Rl EI OD q5'gl CROkt MATERIALTYPE: S CS E SS 0 CSCL C3 CCSS PROCEOURE: N-UT-Wo REFERENCEl
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~ Q.E&TE.R TC: UIA CAUBRATIONSHEET NO.
EXAMINATIONANGLE C-23o ~3< v$'e DEG. e/ DEG. Lo
REFERENCE:
4 E,t 'b &'YEAl QC 1 P CIRC. SCAN SENSITIVITY 5'5 W/A. dB AXIALSCAN SENSITiVITY 5P R3/* dB Log, dB L gn) fROM REF. AT MAXAMP MAX EXAM IND. AMP NO. NOM. INDlCATlON Ll W MAX MP MAX '%DAC lNFORMATlON'YPE NO. L MAX L2 3-14 ANS. NRI DAMPINS ETC.
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REVIEWED BY: LEVEL'ATE + ~~ PAGE WOF 8 'IVA19870 {NP 7/92)
TVA PROJECT: SYSTEM: REPOkT NO.: Office of Nuclear Po~er Unit: MELD NO.: <M -- 5 - aG Ro3g8 t,~ 4 4 4 4 4 I
'l I I Ifii Imhp'Iii I
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REPORT NO: WALL THlCKNESS TVA 0'eld PROFlLE SHEET go~ay'ROJECT: WELD NDI
'YSTEM: v vP e Wold Edge Rocord Thickness Measurements As Indlcatod, Including Weld Width, Edge-To Edge At fG E.E "~IG Contorllne 3
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R'&os< >g ~~~ Radiographic Examination Report Page l I RT Repolt I of THICKNESS PENETRAMETER FILM VIEWING LOCATION INSTRUCTION DATE
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EXAMINATION REPORT NO.
'lENNESSEE VAILEYANHORITY
SUMMARY
AND RESOI.VTION SHEET R- o ~so ROJECT: UNIT: EXAMINER: uaEJ a. tkaca LV: Z SYSTEM: QLca EJ aJP EXAMINER S M LV: WELD I.DJ EXAMINER TRIA. LV: CONFIG: 'OaPC TO: afar vV LV: FLOW CAL SHT NO'S: C e 2 o Ca PROCEDURE: N- Ila REMI.: IM TO; mlA NDE METHOD: l3 UT isaac 0 PT 0 MT 0 VT TH (5 6 f-Y' AC 'Essa' V> V CWc AJ 'P~ gdR Irra. IEJco TAAPJIAJa IJ.a. R EN IJlc MNs5 6'J oC EA+wcs gasJ OP Q Ca Q C.u. -O-- r uaR WCM CAC P SISlraE - SE'Crsbaj Cs a aAJ A. b ~ PERFaR.IAA PA PJ- G 'kA a, U 'base taa as Avu cput aa,as@. A:n '4 C kC 5 A ASIA 'VTIAES\aSQ kasC ASIA I~ IASaJ AA a k. OM +CO 5LrsaaJ LJARI %a P~ aJ Aa.t E<AmaaJ +mOO5 'rHG PaPT to vaJ IJE 0.auP'acoasR Ara~. Sc.aaJ 5 la x vsse's'5 SJ T'LAJ ATIR I ~ L d as Aco Z6'C 5SSLaraR. C.aaa.W aaSAWOEJ a~0 9 aoY CcI~Cwkaa'J 'roc. I5 3r0 M4, ou %ca.NJ 8 Was aa ~o& 5 A. c Al I a ac a c'c Q,aa< 06'5CCOCD ' IJ'TK4.aaa w ECRJ~L UARIaaaaJS ATUaPLa asQ . ZuOaalampaJ S. 6 eauCo Av- iaaASE'R aMia~a b-s cuW w.arqurc. Ocs vEJOaaaoaJ> au R. COOL aJ 5e.Lad 5 aarO Q THE, LI QC RCC A as 4 aMJCA 'I aS Iar 6 NAIA a EJ 1 Q 444 gas Ak/soka. 5aa asgvL '5 aAJaarac 6 wKkc UCkiF a 0 aAJa~ A. cRo Ca'Nclcc r AQ5 Qu sL o.aacl ckoaNA- vs'R s-I RJE. asJ n'Ia b a,o aaas the bF ~ JAP I O WOd. 4a Kwp<aw0E'<~lorn 0ooaurCR ok< 4) a a OPX 56RIJEO LNJ n'apa 'rid % rrskEE 5'fP&4k EI t AaAJ.a< wTteIQ. Q L.Q No OF aSLC'0 C Y.aa u a~A.~OH UOI IJ - aSJ ~ AC. i 9 SC,IEaaaJ5 5 Aas uscII.c. a awny o uc pcs rtt6 vaa a-o - c LJ FN, ua.awed W CX G,OEJC S6~ m eke. OOS8/C~Q. EVALUATOR DATE: CONCURRENCE: DATE: g PAGE J OF~ TVA 19670C (NP 7/92) 108
e~I'~~~ ~go pro DlGlTALULTRASONlC CALlBRATION NO. TENNESSEE VALLEYAUTHORITY CALlBRATlON DATA SHEET C-09@, 2. ECT: PRCCECURB N-UT-INSTRUMENT:
~g REV.: ~/
UNIT: TC: ~/~ CAUBRATION DATE: SIMULATORBLOCK NO.:
- ~F 75 2
TEMP.: ~ F MODELIIYPE: THERMOMETER SERIAL NO.: SERIAL NUMBER COUP LANT: BATCH: EXAM TYPE: Q SHEAR Q LONG. Q RL
~
TRANSDUCER MANUF: ANGLE VERIFICATION: SERIAL NO: O2/ CABLE TYPE: 8 DAC LENGTH: Mhz BLOCK TYPE: NOMINALANGLE: ~~ ACTUALANGLE: INSTRUMENT SElTINGS REFLECTOR REFERENCE MEMORY ORIENTATION SENSITIVITY STORE NO. eo AXIAI dB
~~
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~L 5) 6) 7} 8)
SIGNAL 1 '100 90 80 70 60 50 40 30 20 10 I VER ICAL N C SIGNAL2 50 O / /O E K A E GAIN SET -12 +12 C ATTENUATOR 32 TO 48 16 TO 24 64 TO 96 R SIGNAL AMP. 80% 20% 40% 64 TO 96 I K T Y, REFER TO CALIBRATIONREPORT FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: 'PRE.- geAuLcC a T a.a c WELDS EXAMINED: OM Pf TL FQL~f QfC.TOOM MINER: LEVEL: LEVEL:
~ 5 /pe ANI ~
DATE'Q -R
~ ~MINER:
REVIEWED BY: LEVEL: DATE: ~~~ PAGE~OF~ TVA 19674A (NP 10/92)
1 OI'<<f A DlG1TAL ULTRASONlC CALlBRATION NO. VAllEYAUTHORITY CAUBRATION TENNESSEE DATA SHEET C-c g3 ECT: uNIT: Z CAUBRATION DATE: PROCEDURE: N-UT- ~Q REV.: ~i~ TC: ~/~ TEMP.: ~~F INSTRUMENT: SIMULATOR BLOCK NO.: MODElllYPE THERMOMETER SERIAL NO.: SERIAL NUMBER: EXAM TYPE: Q SHEAR gg LONG. Q RL TRANSDUCERMANUF: ANGLE VERIFICATION: SERIAL NO: CABLE TYPE: FREQUENCY: DAC LENGTH: MhZ BLOCK TYPE: NOMINALANGLE: ~~ ACTUALANGLE: INSTRUMENT SEmNGS
~~
REFLECTOR REFERENCE MEMORY cl ORIENTATION SENSITIVITY STORE NO. AXIAL '7 dB
~~
A CIRC dB M P FREQUENCY: MhZ ANGLE: ~~ DEG. L I E 40 20 SOUND VELOCITY: ~~/ uS POWER ~~ TCG: 0 ON g OFF DUAL: Q ON @OFF INITIALCALIBRATION DISPLAY WIDTH INITIALTIME: FINALTIME: VERIFICATION TIMES REF. REFLECTOR: GAIN: ~)~dB 2) 3) 4)
- 5) 6) 7) 8)
L 100 90 50 30 SIGNAL 1 80 70 60 40 20 10 I VERTICAL N C SIGNAL 2 50 E H A E GAIN SET -12 SET +12 C ATTENUATOR R SIGNAL AMP. SPY, 32 TO 48 16 TO 24 20% 64 TO 96 40% 64 TO 96 I K T Y. REFER TO CAUBRATIONREPORT FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: C.E. - CRui 0 s a oaD WELDS EXAMINED: wA.~ W D ~a& PER 3~ - 6~~0+ fR~6I. MINER: ANllg c DATE:
~MINER: LEVEL: 3 2 REVIEWED BY: LEVEL: DATE: ~ ~ W PAGE 3 OF~
TVA 19674A (NP 10/92) 1 j.o
e MANUALULTRASONIC REPORT NO. TENNESSEE VAllEYAUTHORITY PIPING EXAMINATION DATA SHEET R-c a~o ECT: UNIT' EXAMINATIONDATE: ~ Z8 5 c. 5 SYSTEM: 8'4/C START TIME: 2' g END TIME: Z WELD I.D.: - 2-0 EXAM SURFACE: Q ID 8 OD CONFIG: TO: MATERIALTYPE: H CS Q SS C3 CSCL 0 CCSS FLOW PROCEDURE: N-UT- ~~
'C REV.: ~~ ~Q TC:
CAUBRATIONSHEET NO. C-O9> Wo
REFERENCE:
EXAMINATIONANGLE EG. DEG. Lo
REFERENCE:
CIRC. SCAN SENSITIVllY dB dB AXIALSCAN SENSITIVITY gg dB dB L gn) FROM REF. AT MAX AMP MAX EXAM IND. AMP NO NO M. INDICATION INFORMATION: NO. Ll L MAX l2 W MAX MP MAX %DAC 5-li ANG. NRI TYPE DAMPING HC. RcpT Cg40&ETCg $ 4ckaf, f4 Q) D'Q~eg~ o" w icmutv Mixe. vMuwc. v Q, aalu
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V REMARKS/LIMITATIONS: < d e 5c.w~ 'DoE. ~ P jPC Ao a UC Co 4 Fi uk A mba MINER: LEVEL AMINER: DATE:3 gg.q REVIEWED BY: LEVEL: .
~2C 5M PAGE~OF ~
TVA 19670 tNP 7J92)
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DIGITALULTRASONIC CALIBRATIONNO. TENNESSEE VAllEVAUTHORlTY CALIBRATION C- O9q DATA SHEET ECT: UNIT: CAUBRATION DATE: PROCEDURE: N-UT- ~Q REV.: ~>~ TC: ~i~ TEMP.: ~9 F INSTRUMENT: 8 SIMUlATOR BLOCK NO.: THERMOMETER SERIAL NO MODEUTYPE: SERIAL NUMBER: E/ 70 0 EXAM TYPE: Q SHEAR gg LONG. Q RL
~
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-8 FREQUENCY:
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~~ MhZ ANGLE:
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I 40 SOUND VELOCITY: ~/~~3 uS POWER: ~l 20 TCG: 0 ON 8 OFF DUAL 0 ON I/OFF INITIALCALIBRATION DISPLAY WIDTH FINALTIME: VERIFICATION TIMES REF. REFLECTOR: g GAIN: ~i~dB 2) 3) 4) Mla 5) 6) 7) 8) l SIGNAL 1 100 90 80 70 60 50 40 30 20 10 I N C SIGNAL 2 50 Zo 2b 2o H E GAIN SET -12 +12 +6 A E ATTENUATOR 2 C SIGNAL AMP. 80 32 TO 48 16TO24 20% 64TO96 4096 64 TO 96 I K T REFER TO CAUBRATIONREPORT FOR PREVIOUS SATISFACTORY LINEARITY Y. COMMENTS: 'PRE.-QCQo<C.C CAv< @em u WELDS EXAMINED:
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TVA 19674A (NP 10/92)
MANUALULTRASONIC REPORT NO. TENNESSEE VALLEYANHORITV PIPING EXAMINATION DATA SHEET P-Ogqo EXAMINATIONDATE: SYSTEM: WELD I.D.: EXAM SURFACE: Q ID gg OD CONFIG: TO: MATERIALTYPE: 8 CS Cl SS Cl CSCL Q CCSS PROCEDURB N-UT-Wo
REFERENCE:
~/
FLOW REV.: j~ TC: ~IL CAUBRATION SHEET NO. EXAMINATIONANGLE C-o 9 y scabs DEG. DEG. Lo
REFERENCE:
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~ k.7 INER: LEVEL: DATE: g REVIEWED BY: LEVEL: DATE:
PAGE 6 OF 9 TVA 19670 (NP 7)92) 113
TVA PROJECT: b~mP SYSTEM: ~v~e. ~ ~g ~p ()i,q REPORT NO.: Office of Nuclear Power Unit: WELD NO.: ~<<- - o~ I I lt I Ill-I i i C Ill i I Ii; I' i
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DIGITALULTRASONIC CALIBRATIONNO. TENNESSEE VAlLEYAUTHORln CALIBRATION DATA SHEET C- os ECT: PROCEDURE: N-UT-INSTRUMENT: BFHP
~ REV:. ~ ~ UNIT:
TC: CAUBRATION DATE: SIMULATORBLOCK NO.: 3 994 su 0 TEMP.: ~2 F MODELflYPE') 3D THERMOMETER SERIAL NO.: l e 9-30-'ll SERfAL NUMBEFL E 1 +0I EXAMTYPE: Q SHEAR Q LONG. Q RL
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L SIGNAL 1 100 90 80 70 60 50 40 80 20 10 I N C SIGNAL2 50 Q tEF )0 4 30 8 H A E GAIN SET SET +12 SET II C SIGNALAMP. 80% 82 TO 48 16 TO 24 20% 64 TO 96 40% 64 TO 96 I K T Y. REFER TO CAUBRATIONREPORT FOR PREVIOUS SATISFACTORY LINEARITY WELDS EXAMINED:
&A'5 eq COMMENTS:
ANffg ~ MINER.'RMINER: LEVEL: DATE~ REVIEWED'BY: LEVEL DATE: ~~ PAGE ~ OF S TVA 19674A (NP 10/92)
DIGITALUI.TRASONIC CAL1BRATION NO. TENNEsszz vAua AurHoanY CALIBRATION DATA SHEET C-opt INSTRUMENT: ECT: PROCEDURE: N-UT-BFHP J$ REY.: ~l UNIT: 3E TC:
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ORIENTATION SENSITIVITY STORE NO. 9 .5 dB A CIRC dB N M P L FREQUENCY: MhE ANGLE: ~5 DEG. I 40 ROUND VELOCITY: ~R. TL uE POWER ~i E 20 TCG: Q ON Q OFF DUAL Q ON EfOFF INITIALCALIBRATION
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6) 3) 7) p 8) l SIGNAL 1 100 90 80 70 60 50 40 30 20 10 I N C SIGNAL 2 50 XO I IO 4 E H A E GAIN SET +12 +6 ATTENUATOR II C SIGNAL AMP 32 TO 48 16 TO 24 64 TO 96 40% 64 TO 96 I K T Y. REFER TO CAUBRATIONREPORT FOR PREVIOUS SATISFACTORY LINEARITY COMMENTS: WELDS EXAMINED: MINER: LEVEL ANI g ~+ LEVEL DATE:g BRMINER: REVIEWED BY: LEVEL: DATE 9"~~ F+ PAGE~OF~ TVA 19674A {NP 10/92)
MANUALULTRASONIC REPORT NO. lENNESSEP VAllEYAlllHORITY PIPING EXAMINATION DATA SHEET R- ops( CT: EXAMINATIONDATE: 3
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) S REMAFNS/LIMITATIONS: W ZX'/m A7 LEVEL INER REVIEWED SY:
LEVEL DATE: DATE: g ~ SQ PAGE f OF S TVA10670 (NP 7j92)
h r REPORT NO: VfALL TH ICKNESS TVA PROFjLE SHEET . Po gq'(. WELD NOt O - Or9 SYSTEM: Weld + 'eVeia Edge Recara Thickness Rloasvrernents As Inaicsted. Inc:valng Weia Width. Centerline I Ecge 70 Edge At 0 5 3l Pasttlan i 0' 90 I 30 i 2TO'IN(~ l,s.z~ l I I
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ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1 AND 3 BFN UNITS 1 AND 3 INSERVICE INSPECTION PROGRAM REVISION 3}}