ML023250275
| ML023250275 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/08/2002 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML023250275 (117) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 November 8, 2002 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Stop:
- OWFN, P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of Tennessee Valley Authority Docket No.
50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 -
AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
SECTION XI INSERVICE INSPECTION (ISI) PROGRAM -
SUBMITTAL OF PROGRAM UPDATE TVA is submitting, for information, a revision to the BFN Unit 1, ISI Program for the first Ten-Year Inspection Interval in accordance with ASME Section XI, paragraph IWA-1400.
The need for this program update is a result of TVA's recent decision to restart the unit.
As part of the program revision, and pursuant to 10 CFR 50.55a(g) (3) (v),
TVA is adopting portions of a later Code, the 1995 Edition through the 1996 Addenda of the ASME Section XI Code, for the remainder of the first Ten-Year ISI Interval.
The first Ten-Year ISI Interval for BFN Unit 1 is currently in its third period and will end one year following restart of the unit.
This revision adopts the 1995 Edition with Addenda through 1996 of ASME Section XI with the exception of ISI weld selection.
Weld selection for ISI activities remains in accordance with ASME Section XI 1974 Edition with Addenda through Summer 1975 as specified in the enclosed BFN Unit 1 ISI Program.
This revision to the BFN Unit 1 ISI Program provides the basis for completion of the current BFN Pnnted on recycled papr
) )
U.S. Nuclear Regulatory Commission Page 2 November 8, 2002 Unit 1 Inspection Interval and examination of a sample of Class 1 and 2 welds, which are not being replaced, in order to ascertain their structural integrity given the extended shutdown of BFN Unit 1. Additional revisions to the BFN Unit 1 ISI Program will be forthcoming to enhance/update the ISI inspection schedule and to include additional requests for relief once our evaluation of BFN Unit 1 inspection activities is complete.
The enclosure to this letter provides a copy of the BFN Unit 1 ISI Program (1-SI-4.6.G, Revision 3).
There are no new commitments contained in this letter.
If you have any questions, please call me at (256) 729-2636.
U.S. Nuclear Regulatory Commission Page 3 November 8, 2002 (Via NRC Electronic Distribution) cc:
Mr. Paul E.
Fredrickson, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Mr. Kahtan N.
Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 FIRST TEN-YEAR INSERVICE INSPECTION (ISI) INTERVAL ISI PROGRAM UPDATE See Attached 1-SI-4.6.G, Revision 3
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT SURVEILLANCE INSTRUCTION 1-SI-4.6.G INSERVICE INSPECTION PROGRAM UNIT 1 REVISION 3 PREPARED BY: FRED FROSCELLO RESPONSIBLE ORGANIZATION: COMPONENT ENGINEERING APPROVED BY: RONALD K. GOLUB DATE: 10/22/2002 EFFECTIVE DATE: 10/22/2002 LEVEL OF USE: CONTINUOUS USE QUALITY-RELATED
REVISION LOG Procedure Number: 1-SI-4.6.G Revision Number:003 PAGES AFFECTED:
6,8,18,29,30,31,33-40 REASON FOR REVISON:
IC Editorial changes to correct references in text.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page3 ofl13 TABLE OF CONTENTS Owner's Statem ent...........................................................
4
1.0 INTRODUCTION
5 1.1 Purpose..............................................................................
5 1.2 Scope.................................................................................
5 1.3 Frequency..........................................................................
6 1.4 Codes of Record and Code Cases...................................
7
2.0 REFERENCES
11 3.0 PRECAUTIONS AND LIMITATIONS.......................................
19 4.0 PREREQUISITES..............................................................
19 5.0 SPECIAL TOOLS AND EQUIPMENT.......................................
19 6.0 ACCEPTANCE STANDARDS..................................................
19 7.0 INSTRUCTION STEPS...............................................................
20 7.1 Responsibilities..................................
20 7.2 Im plem entation..................................................................
27 7.3 Components Subject to Examination................................
35 7.4 Calibration Standards.........................................................
42 7.5 Records and Reports...........................................................
42 7.6, Requests for Relief (RFR)...................................................
47 7.7 Repairs and Replacements...................................................
47 7.8 ASME Section XI Programs Not Addressed By 1-SI-4.6.G.................................................................
47 7.9 ISI Data Base Maintenance and Update..............................
48 7.10 Corrective Actions 48 7.11 Augmented Examinations..................................................
49 8.0 TABLES/ATTACHMENTS...........................................................
55 8.1 Examination Schedule Tables............................................
56 8.2 Augmented Examination Table..........................................
69 8.3 Listing of Welds for Generic Letter 88-01..........................
70 8.4 Class 2 Exempted Components................................
78 8.5 Class I Valve List.............................................................
79 8.6 Requests for Relief..............................................................
83
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 P-SI-4.6.G Page 4 of 113 Owner:
Address of Corporate Office:
Name & Address of Power Plant:
OWNER'S STATEMENT Tennessee Valley Authority Chattanooga Office Complex 1101 Market St.
Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant P. 0. Box 2000 Decatur, AL 35609 Applicable Nuclear Power Unit: BFN, Unit 1 Construction Permit Date:
Construction Permit was issued prior to May 10, 1967.
Commercial Operation Date August 01, 1974 First 10 Year ISI Interval:
August 01, 1974 to One year after startup from extended outage.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6.G Page 5 of 113
1.0 INTRODUCTION
1.1 Purpose This Inservice Inspection (ISI) Program is an administrative Surveillance Instruction (SI) utilized to obtain data through nondestructive examinations (NIE) required by ASME Section XI. This procedure satisfies portions of the Technical Requirement 3.4.3 (TR 3.4.3.) and to fulfill the requirements of SPP-9.1, related to NDE of Code Class 1, 2, and 3 (equivalent) components in accordance with applicable ASME Section XI requirements. NDE results are used to verify continued structural integrity of the subject components and their acceptability for continued service, and to determine if a flaw is an isolated case or of a generic nature.
This program shall serve as TVA's ISINDE plan and schedule for ASME Code Class 1, 2, and 3 (equivalent),components, in accordance with the requirements of ASME Section XI, IWA-1400 for the first ten year ISI interval.
1.2 Scope This program is in effect for BFN Unit I during the first inspection interval which began August 01, 1974. The unit 2 and 3 ISI programs are contained in 2-, and 3 SI.4.6.G, respectively.
The Inservice Inspection Program (ISI) is designed to comply with the Codes listed in Section 1.4.1.
Relief requests are issued for regulatory review and approval when implementation of ASME Section XI requirements is determined to be impractical or when alternatives are adopted. These programs provide for implementation in accordance with the scheduling requirements of ASME Section XI, IWA-2400. Refer to Section 7.6.
Code Class (equivalent) boundaries are depicted on the color-coded drawings listed in Section 2.7.1. These drawings are prepared and maintained by Component Engineering and are issued and controlled through BFN Records Management (RM).
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6.G Page 6 of 113
1.0 INTRODUCTION
(continued)
The ASME Section XI Code Class (equivalent) Boundary Drawings, and ISI Drawings identify the components and systems to be examined. The Unit 1 ISI Component and Component Support Drawings are listed in Section 2.7.
Certain elements of ASME Section XI (repairs and replacements, system pressure tests, pump and valve inservice testing, snubber examination and inservice testing, and containment inservice inspection) are implemented by other site procedures. Refer to Sections 7.7 and 7.8.
Specifics concerning performance of Nondestructive Examinations (NDE) are not part of this program, but are included in IEP-100, Nondestructive Examination Procedures.
1.3 Frequency 1.3.1 Inspection Interval and Inspection'Periods This inspection interval is from August 01, 1974 to one year after startup from the extended outage that began in March of 1985. This is the first inspection interval for BFN Unit 1. The inspection interval is divided into three periods in accordance with ASME Section XI, Inspection Program B.
The associated inspection period dates are listed below:
Inspection Period Minimum Exams Maximum Exams First (08/4 to 06/8 1) 16%
34%
Second (07/81 to 10/84) 50%
67%
Third (11/84 to one 100%
100%
year after startup)
The minimum and maximum examination percentages are applicable to those examination categories where deferral is not permissible.
The inspection interval may be extended in accordance with IWA-2430.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6.G Page 7 of 113
1.0 INTRODUCTION
(continued) 1.4 CODES OF RECORD AND CODE CASES 1.4.1 Current Code Requirements and Code Cases NDE Requirements Effective May 25, 2001, certification of NDE personnel shall be in accordance with ANSI/ASNT CP-1 89, 1991, Standard for Qualification and Certification of Nondestructive Testing Personnel, as amended by the requirements of Division 1, ASME Section Xl, Division 1, including editions through 1995 Edition, 1996 Addenda.
Effective May 25, 2001 the Nondestructive Examination Program (NDE techniques, qualification of personnel, weld reference system, and standards for examination evaluation) shall be in accordance with ASME Section XI, Division 1, including editions through the 1995 Edition, 1996 Addenda, as stated below. Reference Letter of Intent (RIMS # L44 010810 800) sent to NRC on August 10, 2001.
Examination Methods - All portions of Subarticle IWA-2200 and all portions of Appendix I, III, IV, VII, and VIII.
Qualification of Nondestructive Examination Personnel - All portions of Subarticle IWA-2300.
Weld Reference System - All portions of Subarticle IWA-2600 up to and including Paragraph IWA-2641.
Standards for Examination Evaluation - All portions of Articles IWA-3000, IWB-3000, IWC-3000, IWD-3000, and IWF-3000.
The Performance Demonstration Initiative Program (PDI) that is mandated by 10CFR50.55a affects the performance of ultrasonic examinations byNDE personnel to the following requirements and shall be implemented on the following dates:
Effective May 22, 2000, NDE personnel performing ultrasonic examinations of bolting and piping shall be certified and qualified in accordance with the PDI Program.
Effective November 22, 2000, NDE personnel performing ultrasonic examinations of Reactor Pressure Vessel welds shall be certified and qualified in accordance with the PDI Program
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6.G Page 8 of 113
1.0 INTRODUCTION
(continued)
Effective November 22, 2001, NDE personnel performing ultrasonic examinations of Weld "Overlay" shall be certified and qualified in accordance with the PDI Program.
Effective November 22, 2002, NDE personnel performing ultrasonic examinations of Reactor Pressure Vessel Nozzles and Dissimilar Metal welds shall be certified and qualified in accordance with the PDI Program.
Preservice Inspections (PSI)
The PSI code of record for Unit 1 recovery, beginning with revision 2 of this procedure, is the 1995 Edition with Addenda through 1996 of ASME Section XI for Class 1, 2 and 3 components including their supports.
Repaired or replaced components will receive a preservice examination. The remaining Class 1 and 2 piping will be examined for preservice in accordance with the following" Class I 25% of piping welds accessible without removal of supports or permanent plant features for those systems not being replaced 100% component supports RPV vessel head and longitudinal shell welds, relief is required 100% Bolting 100% accessible RPV interior and interior attachments Class 2 7.5% sample of welds on each system 100% component supports Class 3 100% component supports including attachments Inservice Inspections (ISI)
The ISI code of record for examination performance, including NDE method selection, examination volume/surface area, and evaluation, for Unit 1 recovery, beginning with revision 2 of this procedure, is the 1995 Edition with Addenda through 1996 of ASME Section XI. Examination component (part) selection will remain the 1974 Edition with Addenda through 1975 of ASME Section XI. Examination component (part) selection includes sections IWB/C 1220, IWB-2500 areas subject to examination, and IWC-2520 areas subject to examination.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6.G Page 9 of 113
1.0 INTRODUCTION
(continued)
The following components will receive inservice examination in as currently scheduled in 1 -SI-4.6.G (this will complete the percentage requirements for the first inspection interval):
Class 1 Piping (for those components not replaced)
Integral attachments Pump and valve interiors, Vessel nozzle welds Pump and valve casing welds Class 2 Piping Integral attachments Vessel welds Class 3 Not applicable (100% performed in Preservice)
The following code cases have been approved for use by the NRC in Regulatory Guide 1.147 and have been adopted by TVA for use at BFN Unit 1:
Code Case N-498-1, Alternate Rules for 10- Year Hydrostatic Pressure Testing for Class 1, 2, and 3 SystemsSection XI, Division 1.
1.4.2 Preservice Inspection (PSI) History A PSI program was not required for Unit I based on its construction permit date of May 10, 1967. TVA performed a voluntary PSI for Class 1 components to the 1971 Edition, Summer 1971 Addenda of ASME Section XI.
1.4.3 First Inspection Interval History The first period of the first interval in effect from August 1, 1974 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 AWA-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.
The second period (July 1, 1981 through November 1,1984) and the third period (November 1, 1984 through date to be determined) were to the 1974 Edition with Addenda through Summer 1975 of ASME Section XI.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6 G Page 10 of 113
1.0 INTRODUCTION
(continued)
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 contained in Appendix E), and evaluation per IWA-3000, IWB-3000, and IWC-3000 of the 1977 Edition, Summer 1978 Addenda.
In accordance with TVA's letter to the NRC dated March 1, 1988 (L44 880301 801), the second inspection interval for unit 1 shall commence one year after startup from the extended outages of 1984 to an indeterminate date.
Beginning January 1, 1992, the preservice inspection of pipe welds, including the extent of examination (Examination Categories B-F, B-J, and C-F), shall be performed in accordance with the 1977 Edition, Summer 1978 Addenda, of ASME Section XI, IWA-2232, 1WA-3000, IWB-2200(c), Table IWB-2500-1, and Table IWC-2500-1.
Beginning on June 12, 1992, NDE methods, qualification of personnel, weld reference system, and standards for examination evaluation shall be in accordance with the 1989 Edition of ASME Section XI, as allowed by 10CFR50.55(g)(4)(iv). This shall include all portions of lWA-2200, IWA 2300, IWA-2600, IWA-3000, IWB-3000, IWC-3000, IWD-3000, and IWF 3000, as well as all portions of Appendices III, IV, and VI of ASME Section XI. 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 letter from S. C. Black to 0. D. Kingsley, Jr., dated January 18, 1990 (TAG No. 72833). Class 2 pressure-retaining bolting that exceeds two inches in diameter shall be volumetrically examined in accordance with Table IWC-2500-1, Examination Category C-D of the 1977 Editions, Summer 1979 Addenda of ASME Section XI. Class 2 pressure retaining bolting two inches or less in diameter shall not be examined (Request for Relief ISI-14). Preservice inspection of pipe welds shall be performed in accordance with the 1977 Edition, Summer 1978 Addenda of ASME XI.
Component support integrally welded attachment examinations for piping, pumps, and valves (Category B-K-I) shall be in accordance with the applicable section(s) of Table IWB-2500-1 of the 1977 Edition, Summer 1978 Addenda, of ASME Section XI for the examination requirements/methods.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page 11 of 113
2.0 REFERENCES
2.1 Technical Specifications BFN Unit 1 Technical Requirement 3.4.3.
2.2 Final Safety Analysis Report Browns Ferry Nuclear Plant Updated Final Safety Analysis Report, Volume 2, Section 4.12.
2.3 NRC Documents IOCFR50.55a, Code of Federal Regulations I OCFR50.2, Code of Federal Regulations BWR (Boiling Water Reactor) Vessel and Internals Project, Technical Basis for Revisions to Generic Letter (GL) 88-01 Inspection Schedules (BWRVIP-75).
Reference Safety Evaluation Report (SER), RIMS # L44 020320 001 from NRC dated March 15, 2002 Regulatory Guide 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability ASME Section XI Division I 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 2.4 Plant Procedures and Instructions SDP-NADP-1, Conduct of Quality Assurance SDP-NEDP-3, Drawing Control 1-SI-4.6.H. 1, Visual Examination of Hydraulic and Mechanical Snubbers 2-SI-4.6.G, Inservice Inspection Program for Unit 2
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page 12 of 113
2.0 REFERENCES
(Continued) 3-SI-4.6.G, Inservice Inspection Program for Unit 3 0-TI-140, Monitoring Program For Flow Accelerated Corrosion 0-TI-376, ASME Section XI, Containment Inservice Inspection Program, Units 1, 2, and 3 0-TI-3 65, Reactor Vessel Internals Inspection Units 1, 2, and 3 0-TI-400, ASME Section XI, Inservice Inspection Program Responsibilities And Interface Document.
MSI-0-001-VSL0O1, Reactor Vessel Disassembly and Reassembly MCI-0-068-PMPOO1, Maintenance of Reactor Water Recirculation Pumps IEP-100, Nondestructive Examination Procedures Approved for use on CSSC Items at all Nuclear Plants IEP-200, Qualification and Certification Requirements for NQA NDE Personnel IEP-300, Qualification and Certification of Ultrasonic TVA Nuclear (TVAN)
Personnel for Preservice and Inservice ASME Section XI Examinations.
MCI-0-00 1 -VLV00 1, Main Steam Isolation Valves Atwood Morrill Co. Disassembly, Inspection, Rework, and Reassembly.
MCI-0-001-VLVO02, Main Steam Relief Valves Target Rock Model 7567 Disassembly, Inspection, Rework, and Reassembly 1-MMI-46, Liquid Penetrant Examination of Piping and Components Which were Exposed To Residue From Plant Fire Unit I 2.5 Codes and Standards ASME Boiler and Pressure Vessel Code,Section XI, 1971 Edition with Addenda through Summer 1971.
ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition with Addenda through Summer 1975.
ASME Boiler and Pressure Vessel Code,Section XI, Appendix III, 1977 Edition with Addenda through Summer 1978.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page 13 of 113
2.0 REFERENCES
(Continued)
ASME Boiler and Pressure Vessel Code,Section V, Articles 2, 6, 7, and 9, 1974 Edition with Addenda through Summer 1975.
ASME Boiler and Pressure Vessel Code,Section V, articles 4 and 5, 1977 Edition with Addenda through Summer 1978.
ASME Boiler and Pressure Vessel Code,Section XI, 1986 Edition with No Addenda.
ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition with No Addenda.
ASME Boiler and Pressure Vessel Code,Section XI, 1995 Edition with 1996 Addenda 2.6 General Electric Service Instruction Letters/Procedures GE SIL No. 571 Instrument Nozzle Safe End Inspection
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6.G Page 14 of 113
2.0 REFERENCES
(continued) 2.7 Drawings 2.7.1 Unit I Section XI Code Class Boundary Drawings 1-47E600-57A-ISI, RCS Instrumentation 1-47E3600-301-ISI, Mechanical Instruments and Controls 1-47E3600-302-ISI, Mechanical Instruments and Controls 1-47E610-43-1-ISI, Sampling and Water Quality System 1-47E610-43-6-ISI, Sampling and Water Quality System 1-47E801-1-ISI, Main Steam 1-47E801-2-ISI, Main Steam 1-47E803-1-ISI, Feedwater System 1-47E807-2-ISI, Turbine Drains & Misc. Piping 1-47E8 10-1 -ISI, Reactor Water Clean-up System 1-47E81 1-1-ISI, Residual Heat Removal System 1-47E812-1-ISI, High Pressure Coolant Injection System 1-47E813-1-ISI, Reactor Core Isolation Cooling System 1-47E814-1-ISI, Core Spray System 1-47E817-1-ISI, Nuclear Boiler 1-47E820-2-ISI, Control Rod Drive Hydraulic System 1-47E820-6-ISI, Control Rod Drive Hydraulic System 1-47E822-1-ISI, Reactor Building Closed Cooling Water System 0-47E839-5-1SI, Raw Water Chemical Treatment System 1-47E844-2-ISI, Raw Cooling Water 1-47E852-1-ISI, Floor & Dirty Radwaste Drainage System
INSERVICE INSPECTION PROGRAM UNIT I REV 0003
2.0 REFERENCES
(continued) 1-47E852-2-ISI, Clean Radwaste & Decon. Drainage System 1-47E854-1-ISI, Standby Liquid Control System 1-47E855-1-ISI, Fuel Pool Cooling System 1-47E856-2-ISI, Demineralized Water System 1-47E858-1-ISI, RHR Service Water System 1-47E85 9-1-ISI, Emergency Equipment Cooling Water System 0-1 17C2556-4-ISI, Rack 25-18 0-1 17C2556-5-ISI, Rack 25-18 1-164C5984-4-ISI, Rack 25-56A 1-164C5984-5-ISI, Rack 25-56B 2.7.2 Reactor Vessel CHM-0992-C CHM-2001-C CHM-2002-C CHM-2102-A MSG-0020-A ISI-0443C CHM-1090-A CHM-1091-A CHM-1094 A CHM-1095-A ISI-0414-C I-SI-4.6.G Page 15 of 113 Reactor Vessel Weld and Nozzle Locations Vessel Stud Locations Control Rod Drive Penetrations (Locations)
Closure Head Assembly Reactor Vessel Clad Patches Reactor Vessel Bottom Head Assy.
RPV Control Rod Drive Penetration-BFN RPV Support Shirt Weld-BFN RPV Nozzle to Vessel Welds-BFN RPV Vessel and Head Welds-BFN Reactor Vessel Supports 2.7.3 Residual Heat Removal Heat Exchanges CHM-2418-B RHR Heat Exchanger Welds I
INSERVICE INSPECTION PROGRAM UNIT I REV 0003
2.0 REFERENCES
(continued)
I-SI-4.6.G Page 16 of 113 2.7.4 Piping System Weld Locations CHM-1080-C Feedwater System - Code Class I CHM-1081-C Recirculation System - Code Class I CHM-1082-C Main Steam System - Code Class 1 CHM-1088-C Residual Heat Removal System - Code Class 1 CHM-1089-C Core Spray System - Code Class I CHM-1097-C CRD Hydraulic Return Line - Code Class 1 CHM-1098-C Reactor Water Cleanup and RCIC - Code Class 1 CHM-1099-C High Pressure'Coolant Injection - Code Class 1 ISI-0362-C RHR Shutdown Supply - Code Class 2 CHM-2690-C Main Steam System - Code Class 2 ISI-0029-C Closed Cooling Water System - Code Class 2 ISI-0093-C RCIC - Code Class 2 ISI-0091-C HPCI - Code Class 2 ISI-0095-C Core Spray - Code Class 2 ISI-0036-C CRD Header - Code Class 2 ISI-0409-C Jet Pump Instrumentation Nozzle Class I ISI-0159-A Core Differential Pressure and Liquid Control Nozzle Class 1 ISI-0160-A Instrumentation Nozzles Class 1 MSG-0019-B Recirculation Inlet Nozzles Class 1 ISI-0155-A Jet Pump Instrumentation Nozzle Welds - Code Class I 2.7.5 Piping System Support Locations CHM-2036-C CHM-2037-C CHM-2038-C CHM-2039-C CHM-2040-C Feedwater System - Code Class I Recirculation System - Code Class 1 Main Steam System - Code Class 1 RHR System - Code Class I Core Spray System - Code Class 1
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2.0 REFERENCES
(continued)
CHM-2042-C Reactor Water Cleanup and RCIC - Code Class 1 CHM 2043-C High Pressure Coolant Injection - Code Class 1 ISI-0363-C RHR Shutdown Supply - Code Class 2 ISI-0030-C Closed Cooling Water - Code Class 2 ISI-0049-C Main Steam System - Code Class 2 ISI-0094-C RCIC - Code Class 2 ISI-0092-C HPCI - Code Class 2 ISI-0096-C Core Spray - Code Class 2 ISI-0037-C CRD Header - Code Class 2 ISI-0085-C RHR Service Water - Code Class 3 ISI-0368-C Emeregency Equipment Cooling Water-Code Class 3 ISI-0391-C Raw Cooling Water - Code Class 3 ISI-0090-C Fuel Pool Cooling - Code Class 3 2.7.6 Pipe Bolting ISI-0027-B Main Steam Bolting - Code Class 1 2.7.7 Pump Support ISI-0022-B RHR Pump Support - Code Class 2 2.7.8 Reactor Vessel Support ISI-0414-C Reactor Vessel Support - Code Class 1 2.7.9 Pump Bolting ISI-0420-C Recirculation Pump Bolting - Code Class 1 2.8 Vendor Manuals 2.8.1 BFN-VTM-B014-0010, B&W Reactor Pressure Vessel Manual, Contract 66C60-90744 2.8.2 BFN-VTM-B580-0010 B&J Recirculation Pump Manual, Contract 67C60-91750
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page 18 of 113
2.0 REFERENCES
(continued) 2.8.3 BFN-VTM-B260-0030, Bingham Pump Co RHR Pump Manual, Contract 66C60-90744 2.8.4 BFN-VTM-P160-0010, VTM-P160-0010, Vendor Technical Manual for Perfex Corp. Heat Exchangers, Types NEN, CEU, CES, and CEN 2.9 Reference Documents 2.9.1 ASME Section XI Code Cases as listed in Section 1.4.
2.10 Miscellaneous Documents 2.10.1 BFPER 951466, Inservice Inspection Program Problem Evaluation Report Units 1& 3, Class 3 Pipe Supports for 1st Inspection Period of 1st Interval Are Not Documented.
2.10.2 BFPER 950681, Traceability of Units 1, 2, and 3 Reactor Pressure Vessel Head Studs, Nuts, and Washers 2.10.3 DNE Calculation, Exclusion Criteria for ISI Scope. RIMS R18020405108, R14950829109 and R14010222101. (MD-Q0999 950033) 2.10.4 GE LetterNos.: BFSE 93-143, BFSE 94-001, BFSE 94-002, BFSE 94 005, and BFSE 94-007.
2.11 TVAN Standard Programs and Processes 2.11.1 SPP-2.2, Administration of Site Technical Procedures 2.11.2 SPP-3.1, Corrective Action Program 2.11.3 SPP-3.5, Regulatory Reporting Requirements 2.11.4 SPP-9.1, ASME Section XI 2.11.5 SPP-9.3, Plant Modifications and Design Change Control 2.11.6 SPP-2.4, Records Management
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6.G Page 19 of 113 3.0 PRECAUTIONS AND LIMITATIONS 3.1 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.
3.2 Standard safety practices as outlined in the TVA Health and Safety Manual shall be followed.
3.3 Efforts should be made to ensure proper planning to reduce delays and radiation exposure during performance of examinations.
3.4 Any revisions to this instruction initiated by other groups shall be submitted to Components Engineering for concurrence prior to incorporation.
4.0 PREREQUISITES 4.1 Personnel responsible for performance of 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 IEP-100, Nondestructive Examination Procedures.
5.0 SPECIAL TOOLS AND EQUIPMENT Equipment is specified in the applicable NDE procedure utilized for performance of the examination.
6.0 ACCEPTANCE STANDARDS Acceptance criteria are specified in the applicable NDE procedures of IEP-100, which are in compliance with ASME Section XI, Articles IWA-3000, IWB-3000, IWC-3000, IWD-3000, and IWF-3000 except where ASME Section III or other construction code examinations are employed to satisfy ASME Section XI requirements.
Acceptance by analytical evaluations performed in accordance with IWX-3000 for Class 1, 2, and 3 components and component supports shall be submitted to the regulatory authority having jurisdiction at the plant site. This information may be submitted with the Inservice Inspection Summary Report including Form NIS-1 or if deemed necessary, a separate report shall be submitted.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6.G Page 20 of 113 7.0 INSTRUCTION STEPS/ELEMENTS 7.1 Responsibilities 7.1.1 Corporate Nuclear Engineering A.
Providing ASME Section XI, interpretations as requested by various site organizations or as required in program development and implementation.
B.
Providing assessment and oversight of ISI programs and activities, including review of ISI Program reports and submittals prior to issuance.
C.
Review of relief requests prior to issuance.
7.1.2 Component Engineering A.
Defining ASME Section XI, Code Class 1, 2, and 3 equivalent boundaries in accordance with applicable guidelines (e.g.:
10CFR50.2, IOCFR50.55a, ASME Section X1, Regulatory Guide 1.26, and others).
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 7.1.2.A above.
Reference procedure 0-TI-400. See Section 2.7 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 NDE to comply with ASME Section XI requirements. See Section 2.7 for drawing list.
D.
Preparing/revising this instruction (ISI Program) in accordance with SPP-2.2, and submitting it to:
(1) Site Procedures for approval and issue as a controlled document.
(2) Records Management for subsequent submittal to the ANII for a detailed review per IWA-1400.
(3) Site Licensing for subsequent submittal to the NRC, as required.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6.G Page 21 of 113 7.0 INSTRUCTION STEPS/ELEMENTS E.
Ensuring this program includes the following information, as a minimum:
(1)
The ASME Section XI Code of Record for ISI (2)
Inspection interval number and begin/end dates (3)
List of ASME Section XI code class boundary drawings (4)
List of ASME Section XI ISI drawings (5)
ASME Section XI Examination Category and Item Number for components.
(6)
Examination schedule providing quantities for each applicable code item number distributed over each period of the inspection interval (7)
NDE method required for each code item number (8)
Applicable relief requests (9)
Name and address of Owner (10)
Name and address of generating plant (11)
Name or number designation of the unit (12)
Commercial operation date of the unit (13)
Description of the system utilized for maintaining record of completed examinations (14)
Description of scan plan contents and control (15)
Applicable augmented examination requirements and their basis.
(16)
Code Cases proposed for use and the extent of their application.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page 22 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
F.
Providing a list of components scheduled for examination during each refueling outage to Inspection Services Organization (ISO) for scan plan development. This list shall include the component identifier, ASME Section XI examination category and item number, ISI drawing number and sheet number, and examination requirement source.
G.
Approving scan plan and revisions and submitting copies of the approved scan plan to site management and the ANII.
H.
Determining scope of additional samples and notification of site engineering when an indication(s) results when inservice inspection examinations detect indications.
I.
Notifying site engineering of indications found during the final additional sample examination to allow evaluation for further actions to be taken.
J.
Preparing a Request for Relief (RFR), as required, when deviations from Code requirements is impractical (see section 7.6 below). ISO responsibilities related to identification of limited examinations are listed in section 7.1.5.
K.
Submitting RFRs to Site Licensing in a timely manner to support ISI activities.
L.
Performing NDE in accordance with this instruction.
M.
Ensuring that ISI/PSI examinations are performed in accordance with approved TVA or contractor NDE procedures authorized by ISO.
N.
Administering the Authorized Inspection Agency contract and ensuring that services of AIA are utilized When performing Code required activities. TVA's interface with the Authorized Inspector for ISI, repairs, and replacements is defined in SPP-9. 1.
- 0.
Providing AIA representative (ANII) with access to plant facilities and documentation in accordance with IWA-2130 of ASME Section XI.
P.
Notifying ANII prior to performing ASME Section XI examinations.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page 23 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
Q.
Preparing a Notification of Indication (NOI) to document rejectable indications detected during the performance of ASME Section XI examinations. The NOI process is defined in SPP-9.1.
R.
Preparing examination reports and recording them (report number, date, examiner's initials, and comments/NOI number) in the scan plan. When inservice examinations are implemented by instructions other than this program, copies of the examination data sheets shall be submitted to Component Engineering by the performing organization. These data sheets shall be used as examination reports and incorporated into the scan plan.
S.
Ensuring that scan plan examinations are complete prior to completion of an outage.
T.
Preparing (or ensuring preparation of) the ISI Summary Report including Form NIS-1. Ensuring that Form NIS-1 is signed by the ANII. Submitting the ISI Summary Report to Site Licensing in accordance with site schedules. Preparing augmented examination summary reports, obtaining ANII signature on the NIS-1 form, coordinating summary report review with ISO, and submitting augmented examination summary reports to Site Licensing.
U.
Preparing and submitting the Site Final Report to RM as a QA record.
V.
Ensuring records used as PSI records from manufacturers or construction organizations comply with SPP-9.1.
W.
Ensuring the calculation of component support acceptance ranges, if required, are prepared in accordance with IEP-l 00, N-GP-7 and N-VT-i.
X.
Maintaining calibration blocks stored at the plant site.
Y.
Initiating a pre-outage meeting to identify augmented examinations in accordance with Section 7.11.
Z.
Ownership of the ISI Program, and assignment of an ISI Program Engineer with primary responsibility for ISI activities.
'INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6.G Page 24 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.1.3 Site Engineering A.
Including provisions for inservice inspection access in designs, in accordance with ASME Section XI, IWA-1400(b) and IWA-1500.
B.
Performing engineering evaluations in support of examination indications related to operability and corrective measures.
C.
Performing evaluations of rejectable indications to determine if required action.
D.
Determining those component supports that could be affected by observed failure modes and those nonexempt components that could be affected.
E.
Providing specific written details for augmented requirements (refer to Section 7.11), and determining if a post examination meeting is required.
7.1.4 Site Licensing A.
Filing this instruction, including revisions, with the NRC, in accordance with IWA-1400(c).
B.
Submitting RFRs, the ISI Summary Report, including Form NIS-1 and IW(X)-3600 analytical reports, to the NRC.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G I
Page 25 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.1.5 Inspection Services Organization (ISO)
A.
Developing and maintaining a computerized data base, at the direction of Component Engineering, to include components identified on the ISI weld and support drawings.
B.
Preparing/revising scan plans for each refueling outage of the inspection interval, as directed by Component Engineering, utilizing the computerized data base. 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.
C.
Providing NDE Level III approval of scan plan revisions that affect the additional information of Section 7.1.5..B, above and maintaining a scan plan revision history log.
D.
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 Component Engineering. Reference Section 7.2.3 (D).
E.
Approving contractor NDE procedures (using IEP-100 as a guideline), contractor written practices for qualification and certification of NDE personnel, and certifications of contractor's NDE personnel performing ISI/PSI.
F.
Providing NDE Level III evaluation of successive examination results.
G.
Packaging radiographs for storage and providing them with reader sheets as a life of plant record to RM.
H.
Providing copies of IEP-1 00 NDE procedure revisions and evidence of personnel qualifications to RM as permanent records for the service lifetime of the plant, in accordance with IWA-1400(k).
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page 26 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
I.
Maintaining as-built calibration standard drawings and the calibration standard material certifications.
7.1.6 Site Records Management (RM)
A.
Issuing controlled copies of ASME Section XI Code Class Boundary Drawings and ISI drawings.
B.
Issuing this instruction and providing controlled copies to Component Engineering, ANIANII, and other requesting organizations.
C.
Maintaining the site final report as a life of plant QA document. Other records referenced in the final report (work plans, radiographs, etc.), NDE procedure revisions, and evidence of personnel qualifications shall be retained for the service lifetime of the plant.
7.1.7 Authorized Nuclear Inservice Inspector (ANII)
A.
Performing the duties of IWA-2120, including a detailed review of this instruction and subsequent revisions. He shall submit a report of the review to the Owner, in accordance with IWA-2120.
B.
Having the prerogative and authorization to require requalification of an operator or procedure when he has reason to believe Code requirements are not being met.
7.1.8 Nuclear Assurance A.
Ensuring the adequacy of contractor's QA programs in accordance with the TVA Standard Programs and Processes.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page 27 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.2 Implementation 7.2.1 System for Maintaining Status of Examinations A.
ISI Data Base A computerized data base shall be utilized for identification of the components requiring examination and for maintaining the status of completed examinations for ASME Section XI and/or augmented credit. Maintenance and updating of this data base is detailed in section 7.9.
B.
Scan Plan (1)
The scan plan is developed from the ISI data base and details the examinations scheduled for performance during an outage.
A scan plan may also be used for examinations performed pre outage or between outages. 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 and sheet number.
(2)
Prior to performing examinations, the scan plan shall be approved by Component 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 Component Engineering by the performing organization for assignment of a report number and incorporation into the scan plan.
(4)
During implementation, it may become necessary to revise the scan plan. Scan plan revisions may be initiated by Component Engineering, ISO, or by other personnel involved with implementation of the scan plan. All changes shall be coordinated with Component Engineering and, as needed, with the appropriate plant planning and scheduling personnel for facilitating the use of supporting craft personnel.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6.G Page 28 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
Revisions to the scan plan shall be controlled in the same manner as the original. ISO 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 Component Engineering and a NDE Level III, as required by Section 7.1.2.G and Section 7.1.5.C, respectively. Approving individuals shall initial and date such changes.
C.
Configuration Changes (1)
When portions of existing pipe or supports are replaced or new systems are added, a system walkdown shall be performed under the direction of Component Engineering to identify the pipe configuration, welds, components, and supports that are required to be added to this inspection program.
(2)
If variations in configuration are discovered, or if 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 2.7 by a Component 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 change(s).
(3)
Component Engineering shall be responsible for reviewing the proposed change, revising the drawings as necessary, and ensuring the revised drawings are issued prior to the next refueling outage. The scan plan shall be revised to reflect any PSI examinations performed due to the variations in configuration. The ISI Engineer (or his designee) shall track the ISI field drawing revisions by utilization of a log book.
This log book will utilize the assigned RIMS (Record of Information Management System) number on the NEDP-3 Form, "Request For Administrative Change To Drawings", as the tracking number for the ISI field drawing revisions.
Guidelines for preparation and control of ISI examination drawings are delineated in SPP-9.1, Part A, Appendix C, and NEDP-3 Paragraph 3.9.2, and Appendix C.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6.G Page 29 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.2.2 Notification of Indication (NOI)
A. NOI form, FORM SSP-9.1-2 of SPP-9.1, shall be usedto document indication(s) exceeding the acceptance criteria of Article 1WX-3000 of ASME Section XI. If engineering evaluation determines that the condition is unacceptable for continued service, corrective action shall be initiated Component Engineering shall provide/coordinate dispositions for NOI's in accordance with SPP-9.1 and SPP-3.1. Any Problem Evaluation Reports (PERs) or Work Orders (WOs) generated to support the NOI disposition shall be referenced on the NOI.
B.
Additional Examinations (1)
Additional examinations for Class 1 equivalent components (IWB) shall be in accordance with the requirements of IWB-2430.
Examinations performed in accordance with Table IWB-2500 1 (-2500 74S75), except for Examination Category B-P, that reveal flaws or relevant conditions exceeding the acceptance standards of Table IWB-3410-1 shall be extended to include additional examinations during the current outage. The basis for additional expansion (or no expansion) into additional systems should be documented.
(a) The first additional examination sample shall include an additional number of welds, areas, or parts (welds, areas or parts are those described or intended in a particular inspection item of Table IWB-2500-1 [-2500 74S75])
included in the inspection item (An inspection item, as listed in Table IWB-2500-1 [-2500 74S75], may comprise a number of welds, areas, or parts of a component required to be examined in accordance wvith the inspection plan and schedule listed in IWA-2420) equal to the number of welds, areas, or parts included in the inspection item that were scheduled to be performed during the present inspection period.
The additional examinations shall be selected from welds, area, or parts of similar material and service.
This additional selection may require inclusion of piping systems other than the one containing the flaws or relevant conditions.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 30 of 113 70 INSTRUCTION STEPS/ELEMENTS (continued)
(b)
If the first additional examinations of (1)(a) reveal flaws or relevant conditions exceeding the acceptance the acceptance standards of Table IWB 3410-1, the examinations shall be further extended to include additional examinations during the current outage.
These additional examinations shall include the remaining number of welds, areas, or parts of similar material and service subject to the same type of flaws or relevant conditions.
(c)
For the inspection period following the period in which the examinations of (1)(a) and (b) were completed, the examinations shall be performed as originally scheduled in accordance with IWB-2400.
(d)
If welded attachments are examined as a result of identified component support deformation, and the results of these examinations exceed the acceptance standards of Table IWB-3410-1, additional examinations shall be performed, if determined necessary, based on engineering evaluation.
(2)
Additional examinations for Class 2 equivalent components (IWC) shall be selected in accordance with IWC 2430.
Examinations performed in accordance with Table IWC-2500 1 (-2520 74S75), except for Examination Category C-H (95A96), that reveal flaws or relevant conditions exceeding the acceptance standards of Table IWC-3410-1 shall be extended to include additional examinations during the current outage.
The basis for additional expansion (or no expansion) into additional systems should be documented.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 31 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
(a) The first additional examination sample shall include an additional number of welds, areas, or parts (welds, areas or parts are those described or intended in a particular inspection item of Table IWC-2500-1 [
2520 74S75]) included in the inspection item (An inspection item, as listed in Table IWC-2500-1 (-2520 74S75), may comprise a number of welds, areas, or parts of a component required to be examined in accordance with the inspection plan and schedule listed in IWA-2420) equal to 20% of the number of welds, areas, or parts included in the inspection item that are scheduled to be performed during the interval.
The additional examinations shall be selected from welds, area, or parts of similar material and service.
This additional selection may require inclusion of piping systems other than the one containing the flaws or relevant conditions.
(b)
If the first additional examinations of (2)(a) reveal flaws or relevant conditions exceeding the acceptance the acceptance standards of Table IWC 3410-1, the examinations shall be further extended to include additional examinations during the current outage. These additional examinations shall include the remaining number of welds, areas, or parts of similar material and service subject to the same type of flaws or relevant conditions.
(c)
For the inspection period following the period in which the examinations of (2)(a) and (b) were completed, the examinations shall be performed as originally scheduled in accordance with IWC-2400.
(d)
If welded attachments are examined as a result of identified component support deformation, and the results of these examinations exceed the acceptance standards of Table IWC-3410-1, additional examinations shall be performed, if determined necessary, based on engineering evaluation.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 I-SI-4 6 G Page 32 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
(3)
Additional examinations for Class 3 equivalent components (IWD) will not be required. All Class 3 equivalent supports including attachments will receive 100% preservice examination. Reference Section 1.4.1.
(4)
Additional examinations for component supports shall be in accordance with the requirements of IWF-2430 Component support examinations performed in accordance with Table IWF-2500-1 that reveal flaws or relevant conditions exceeding the acceptance standards of RWF-3400 and which require corrective actions shall be extended to include additional examinations during the current outage.
(a)
The first additional examination sample that exceed the acceptance standards of IWF-3400 shall include the component supports immediately adjacent to those component supports for which corrective action is required.
I The additional examinations shall be extended to include additional supports within the system, equal in number and of the same type and function as those scheduled for examination during the inspection period.
(b)
If the additional examinations of (4)(a) reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400, the examinations shall be further extended to include additional examinations during the current outage. These additional examinations shall include the remaining component supports within the system of the same type and function.
(c)
When the additional examinations of (4)(b) reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400, the examinations shall be extended to include a third additional sample to include all nonexempt supports potentially subject to the same failure modes that required corrective measures in (4)(a) and (4)(b). These additional examinations shall include nonexempt component supports in other systems when support failures requiring corrective measures indicate non-system related failure modes.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6'G Page 33 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
At the request of Component Engineering, Site Engineering shall make the determination of failure mode applicability and select the additional sample (d)
When the additional examinations required by (4)(c) reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400, those exempt component supports that could be affected by the same observed failure modes and could affect nonexempt components examination shall be shall be examined.
At the request of Component Engineering, Site Engineering shall make the determination of failure mode applicability and select an additional sample of exempt component supports that could affect nonexempt components 7.2.3 Examinations A. NDE shall be performed in accordance with IWA-2200 of ASME Section XI utilizing the NDE procedures of IEP-100 or approved contractor procedures, with the exception of NDE procedures for ultrasonic examinations, which shall be qualified to the requirements of Appendix VIII of ASME Section XI, as implemented by the Performance Demonstration Initiative Program (PDI). Reference section 1.4.1 for implementation dates.
B. Personnel performing NDE operations shall be qualified and certified in accordance with IWA-2300 of ASME Section XI, as specified in IEP-200, and qualified to the requirements of the 1991 Edition of ANSI/ASNT CP-189, with the exception of NDE personnel performing ultrasonic examinations, who shall be qualified to the requirements of Appendix VIII of ASME Section XI, as implemented by the Performance Demonstration Initiative Program (PDI).
Reference paragraph 1.4.1 for implementation dates. TVA will perform UT annual training for Appendix VIII qualified personnel in accordance with 10 CFR 50.55a (b) (2) (xiv) requirements in lieu of Subarticle VII-4240 to Appendix VII of the 1995 Edition 1996 Addenda of ASME Section XI. Reference Request For Relief # PDI I.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6.G Page 34 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
C.
The inservice examinations may be performed by Component Engineering, ISO, or contractor personnel. Contract preparation, administration, and supervision shall be the responsibility of Component Engineering.
Inspection plans and/or quality assurance programs submitted by contractors shall be reviewed and approved by Nuclear Assurance prior to use. All contractor NDE procedures used during the inspection program shall be reviewed and approved by ISO using IEP 100 as a guideline.
D.
Every attempt shall be made to provide 100% code coverage (volume or area) when performing an exam. When 100% code coverage is not obtained/obtainable, a NDE Level III shall promptly notify Component Engineering. If the coverage is limited due to an obstruction that is removable, an evaluation shall be performed by Component Engineering to either allow removal of the obstruction or to justify why the obstruction cannot be removed. When less than the required ASME Section XI 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 greater than 90% code coverage was not achieved, the NDE level III representative shall notify Component Engineering immediately to determine if an alternate component can be selected. If an alternate component cannot be selected the examination volume or area is qualified for request for relief action in accordance with Section 7.6.
Reference Section 7.1.5 (D).
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 35 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.3 Components Subject to Examination 7.3.1 ASME Class I Equivalent Components Subject to Examination (iWB)
A ASME Class 1 equivalent systems are listed below:
"* Control Rod Drive Hydraulic System (CRD)
"* Core Spray System (CS)
"* High Pressure Coolant Injection System (HPCI)
"* Main Steam System (MS)
"* Reactor Core Isolation Cooling System (RCIC)
"* Recirculation System (RECIR)
"* Residual Heat Removal (RHR)
"* Reactor Pressure Vessel (RPV)
"* Standby Liquid Control System (SLC)
B.
The specific components subject to examination are identified on ISI drawings listed in Section 2.7. Table 8.5 contains detailed information for selected Class 1 valves. 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 Table 8.1 Examination Schedule - Class 1 Equivalent (IWB) Components.
C.
The component size and shape associated with IWB-1220(a) is determined by the calculation referenced in Subsection 2.10.3. IWB 1220, footnote 1 allows the exemptions from examination in IWC 1220 to be applied for those components.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-S1-4 6.G Page 36 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
D.
Selection and scheduling of ASME Class I equivalent components is in accordance with IWB-2412, Inspection Program B, IWB-1200 exemptions, and applicable requirements of Table IWB-2500 (74S75) or IWB-2500-1 (95A96).
E.
The examination of Class 1 equivalent component supports is in accordance with Section 7.3.4.
F.
ASME Class 1 equivalent piping and components that meet the size exemption listed in reference 2.8.2 are exempt from the Class 1 requirements of 10CFR50.55a(c)(1). The exempted piping
/components would then be considered ASME Class 2 equivalent since they are part of the reactor pressure coolant boundary, but excluded from classification as ASME Class 1.
7.3.1.1 Reactor Vessel Interior The space above and below the vessel core that is made accessible by the removal of components during normal refueling outages shall be visually examined during the first refueling outage and at subsequent refueling outages at approximately three-year intervals.
The welded core support structures and interior attachments (specimen holding bracket, etc.) to the reactor vessel shall be visually examined. The examination shall include 100 percent of the visually accessible attachment welds and core support surfaces.
The attachments are: dryer hold down brackets, dryer support brackets, guide rod brackets, feedwater sparger brackets, core spray sparger brackets, surveillance specimen holder brackets, jet pump riser support brackets and shroud support. The core support structure consists of the top guide and the core plate.
Augmented examination requirements and commitments for BFN vessel internal examinations during the ISI interval are stated in 0-TI-365.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6.G Page 37 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.3.2 ASME Class 2 Equivalent Components Subject to Examination (IWC)
A ASME Class 2 equivalent systems are listed below:
Control Rod Drive Hydraulic System (CRD)
Core Spray System (CS)
SH-igh Pressure Coolant Injection System (HPCI)
"* Main Steam (MS)
"* Reactor Building Closed Cooling Water System (RBCCW)
"* Closed Cooling Water System (RBCCW)
"* Reactor Core Isolation Cooling System (RCIC) a Residual Heat Removal System (RHR)
B.
The specific components subject to examination are identified on ISI drawings listed in Section 2.5. 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 - Class 2 Equivalent (IWC) Components.
C.
Selection and scheduling of ASME Class 2 equivalent components is in accordance with IWC-2412, Inspection Program B, IWC-1200 exemptions, and applicable requirements of Table IWC 2520 (74S75) or Table IWC-2500-1 (95A96).
D.
The examination of Class 2 equivalent component supports is in accordance with section 7.3.4.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6 G Page 38 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.3.3 ASME Class 3 Equivalent Components Subject to Examination (IWD) and Non-Code Class Components A.
ASME Class 3 equivalent systems are listed below:
"* Emergency Equipment Cooling Water System (EECW). See Section 7.3.3.D below.
"* Fuel Pool Cooling System (FPC).
"* Residual Heat Removal Service Water System (RHRSW),
including the unit common headers.
B.
The specific components subject to examination are identified on ISI drawings listed in Section 2.5. 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 - Class 3 Equivalent (IWD) Components.
C.
Selection and scheduling of ASME Class 3 equivalent components is in accordance with IWD-2412, Inspection Program B, IWD-1200 exemptions, and applicable requirements of Table IWD 2500-1.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6.G Page 39 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
D.
The examination of Class 3 equivalent component supports is in accordance with section 7 3.4.
7.3.4 Component Supports Subject to Examination (,VF).
A.
ASME Class 1, 2 and 3 equivalent component and piping supports shall be examined in accordance with IWF-1200.
B.
The specific components subject to examination are identified on ISI drawings listed in Section 2.7. The number of supports 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 4 - Component Supports (IWF).
C.
Selection and scheduling of component supports is in accordance with IWF-24 10 Table IWF-2410-2, Inspection Program B, IWF-1200 exemptions, and applicable requirements of Table IWF 2500-1.
D.
The inservice inspection requirements for snubbers shall be in accordance with the requirements of IWF-5000. Inservice examinations shall be performed in accordance with ASME/ANSI OM, Part 4, using a visual examination (VT-3) method described in IWA-2213. Integral and nonintegral attachments for snubbers, including lugs, bolting, pins, and clamps shall be examined in accordance with the requirements of IWF-5000.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6.G Page 40 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
E.
The acceptance range for constant force and variable springs shall be in accordance with the support drawing. If the setting range is not identified on the drawing the applicable general notes contained in the 47B435-series of drawings shall be utilized in accordance with N-VT-I and N-GP-7.
F.
Component supports that have been adjusted in accordance with IWF 3000, or corrected or modified by repair/replacement activities shall be examined prior to return to service per the applicable examinations listed in Table IWF-2500-1.
Additionally, 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 heat-up and cool-down cycle unless determined unnecessary by evaluation. This examination shall be performed during operation or at the next refueling outage. Component supports requiring an additional preservice examination shall be scheduled for examination and added to the applicable scan plan 7.3.5 Successive Examinations, Class 1, 2, 3, or Component Supports Any corrective actions required as a result of lSI examinations shall be handled in accordance with SPP-3.1.
Successive examinations shall be performed in accordance with the requirements of IWB-, IWC-, IWD, and IWF.
A.
Successive Examinations - Class I Equivalent Components Areas containing flaw indications or relevant conditions evaluated in accordance with IWB-3132.3 or IWB-3142.4 that qualify for continued service shall be re-examined during the next three inspection periods as listed in the inspection schedules of the inspection program of IWB-2400.
If these re-examinations reveal that the flaw indication remain essentially unchanged for three successive inspection periods, then the component examination frequency may revert to the original schedule.
Components requiring successive examinations shall be scheduled for examination and added to the applicable scan plan.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 I-SI-4 6 G Page 41 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (Continued)
If welded attachments are examined as a result of identified component support deformation, and the results of these examinations exceed the acceptance standards of Table IWB-34 10-1, successive examinations shall be performed, if determined necessary, based on an evaluation by BFN Engineering.
B Successive Examinations - Class 2 Equivalent Components Areas containing flaw indications or relevant conditions evaluated in accordance with IWC-3122.3 or IWC-3132.3 that qualify for continued service shall be re-examined during the next inspection period as listed in the inspection schedule If this re-examination reveals that the flaw indications remain essentially unchanged, then the component examination frequency may revert to the original schedule.
Components requiring successive examinations shall be scheduled for examination and added to the applicable scan plan. If welded attachments are examined as a result of identified component support deformation, and the results of these examinations exceed the acceptance standards of Table IWC-3410-1, successive examinations shall be performed, if determined necessary, based on an evaluation by BFN Engineering.
C.
Successive Examinations - Class 3 Equivalent Components Same as Successive Examination - Class 2 Equivalent Components (B. above), except for the references to IWB will be IWC.
D.
Successive Examinations for Component Supports (IWF)
Successive examinations for component supports (IWF) shall be determined in accordance with IWF-2420. (See section 7.3.4.F for component supports requiring an additional preservice examination).
When a component support is accepted for continued service in accordance with IWF-3112.2 or IWF-3122.2, the component support shall be reexamined during the next inspection period listed in the schedules of the inspection programs of IWF-24 10. When these examinations do not require additional corrective measures during the next inspection period, the inspection schedule may revert to the requirements of IWF-2420-(a).
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6.G Page 42 of 113 7.4 Calibration Standards Calibration standards are included in ASME Section XI, Appendix I. This appendix includes references to ASME Section XI, Appendix III and ASME Section V for additional requirements. As-built calibration standard drawings and calibration standard material certifications are maintained by ISO. The calibration blocks are stored at the plant site and maintained by ISI personnel.
7.5 Records and Reports Records and reports shall be prepared in accordance with ASME Section XI, Subarticle IWA-1400, Article IWA-6000.
7.5.1 ISI Summary Report An ISI summary report for Class 1 and 2 (equivalent) Components shall be prepared and submitted to Site Licensing and other review organizations on a schedule that permits submittal to the NRC within 90 days after turbine generator synchronization following a refueling outage. Examinations, tests, replacements, and repairs conducted since the preceding summary report shall be included.
Information related to the Containment Inservice Inspection Program inspection of Class MC (equivalent) components (WE) shall also be included in the ISI summary report as applicable. This information is compiled in accordance with 0-TI-376 for inclusion in the ISI summary report (see section 7.5.1.0).
Each summary report shall be formatted to contain the following:
A.
Cover Sheet A cover sheet stating "ASME Section XI Inservice Inspection Summary Report for Browns Ferry Nuclear Plant, Unit 3, "and the Refueling Outage. The cover sheet shall also provide:
- 1.
Date of document completion.
- 2.
Name and address of owner.
- 3.
Name and address of generating plant.
INSERVICE INSPECTION PROGRAM JUNIT I REV 0003 I-SI-4 6 G Page 43 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
- 4.
Name or number assigned to the nuclear power unit by TVA.
- 5.
Commercial operation date for the unit.
B.
Table of Contents A table of contents for the report should follow the title page.
C.
Form NIS-1 The Owner's Report for Inservice Inspections, Form NIS-1, as shown in Appendix II of ASME Section XI, shall be completed and included D.
Form NIS-2 The Owner's Report for Repair and Replacement, Form NIS-2, as shown in Appendix II of ASME Section XI, shall be completed and included.
E.
Introduction and Summary of the Inspection The introduction should include the following information: Plant, unit number, preservice or inservice examinations, RFO cycle, systems, components, and vessels examined, organizations examinations were performed by, dates examinations were performed, ASME Section Code of Record. The summary should include a brief description of the overall inspection. Included as part of the summary, ASME Class 1, 2, and 3 equivalent components and the integrally welded attachments whose examination results required evaluation analysis (IWB-3132.4 and IWB-3142.4 for Class I and 3; and IWC-3122.4 and IWC-3132.3 for Class 2) shall be submitted to the NRC as required by IWB-3134, IWB-3144, and by IWC-3125 and IWC-3134.
F.
Examination Summary The examination summary shall tabulate the ASME Section XI examinations credited for the applicable period. Items should include the following information: category, total number of examinations required for the inspection interval, total number required for for the applicable period, total number credited for the applicable period, and exclusions, exceptions, or deferrals.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-S14.6 G Page 44 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
G.
Examination Plan The Examination Plan shall give a detailed description of all areas subject to examination during the inspection. It should contain the following information-examination area, Code Category and Item Number, reference drawing, examination method, examination procedure, examination report number, calibration block, date of examination, and examination results. This plan may be submitted as the computerized Outage Report.
H.
Component Re-Examination Reports The component re-examination section shall give a detailed description of all components subject to re-examination due to rework, repair, or replacement resulting from a Notification of Indication (NOI). This section should contain the examination area, Code Category and Item Number, reference drawing, examination method, examination procedure, examination report number, calibration block, date of examination, and examination results.
Summary of Notifications of Indications (NOI's)
The summary of NOI's shall give a short summary of each NOI report along with the indication discrepancy. It should also contain the final disposition, including a reference to the corrective action taken.
J.
Additional Sample The additional sample section, if applicable, shall indicate additional sample examinations performed as a result of a failed component. The summary should include reference to the applicable system, the affected component, the number of components examined as a result of the failure, and a description of additional samples and results of the additional sample examinations K.
Successive Examinations The successive examination section, if applicable, shall indicate examinations performed as a result of ASME Section XI requirements.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 I-SI-4 6.G Page 45 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued)
This section should contain a reference to the applicable system, the affected components, and the results of the successive examinations.
L.
Analytical Evaluation The analytical evaluation section for ASME Class 1, 2, and 3 equivalent components and the integrally welded attachments whose examination results require evaluation analysis, if applicable, shall include a short summary of each analytical evaluation, the indication discrepancy, and its location.
A copy of each analytical evaluation should be included, with a reference to the applicable NOI and the component identifier.
M.
Augmented Examinations As applicable, a brief summary of the augmented examinations reportable to the NRC shall be included N.
Requests for Relief The summary of requests for relief shall give a short summary of each relief request resulting from the inspection. This section shall summarize any components that did not receive the required examination coverage. The results should indicate the applicable component, Code Class, Code Category, Code Item Number, examination method, and calculated examination coverage. In addition, a description should summarize the access limitations and applicable reason why examination coverage cannot be obtained.
- 0.
Containment Inservice Inspection Program (IWE)
This section, if applicable, should contain evaluations performed in accordance with the requirements of 10CFR 50 55a(b)(2)(x)(A),
evaluation of inaccessible areas, and 10CFR50.55a(b)(2)(x)(D),
evaluation for additional examinations.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 46 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.5.2 Site Final Report A site final report shall be prepared following each refueling outage and submitted to Records Management for retention as a permanent record. The site final report should contain, but not be limited to, the following:
"* An index to record file
"* The inservice and preservice NDE examination reports and calibration data sheets
"* The ISI Summary Report with appendices prepared per section 7.5.1
"* Personnel certifications
"* reference to NDE procedures
"* reference to NDE examination records including radiographs and review forms
"* Notification of Indication (NOI) Reports
"* Scan plans and scan plan revision logs (if applicable)
"* Containment Inservice Inspection Report prepared in accordance with 0 TI-376 7.5.4 Radiographs Radiographs shall be packaged by ISO and transmitted to RM for storage as a life of plant record.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4.6 G Page 47 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7 6 Requests for Relief (RFR)
Deviations from Code requirements shall be submitted to NRC as written relief requests in accordance with I OCFR50.55a(g)(5) Alternatives to Code requirements shall be submitted to NRC in accordance with 10 CFR 50.55a(3)(i) and 10 CFR 50.55a(3)(ii). Proposed alternative examinations and information to support the basis and justification for relief shall be included. Relief requests are identified in Section 8.5 of this program and listed in Table 8.1, next to the applicable examination category.
ISO is responsible for notifying Component Engineering of impractical examination requirements and limitations that are encountered during performance of examinations.
Reference Paragraph 7.1.5 (D) and 7.2.3 (D).
RFR's shall be prepared in accordance with SPP-9. 1. Corporate Nuclear Engineering will be provided an opportunity to review RFR's.
7.7 Repairs and Replacements ASME Section XI repair and replacement activities are performed in accordance with SPP-9.1 and 0-TI-363. Preservice examinations required for ASME Code Class 1, 2, and 3 (equivalent) repaired/replaced components are in accordance with the code of record specified in this surveillance instruction. The examination categories and NDE method for preservice examinations may be determined from those listed in Section 8.1.
7.8 ASME Section XI Programs Not Addressed By 1-SI-4.6 G 7.8.1 System Pressure Tests The system pressure test program is identified in SPP-9. 1. Additional details are provided in 0-TI-364.
7.8.2 Pump and Valve Inservice Testing The pump and valve inservice testing program is identified in SPP-9.1 and 0 TI-362.
7.8.3 Snubber Inservice Testing Snubber inservice examination and testing is in accordance with 1-SI-4.6.H.1 and 1-SI-4.6.H.2.A thru D.
7.8.4 Containment Inservice Inspection The containment inservice inspection program is identified in SPP-9 1.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 I-SI-4 6 G Page 48 of 113 70 INSTRUCTION STEPS/ELEMENTS (continued) 7.9 ISI Data Base Update and Maintenance 7.9.1 Component Engineering is responsible for maintaining the ISI Data Base ISO may perform update functions at the direction of Component Engineering.
7.9.2 Changes to the ISI Data Base may become necessary for a number of reasons, such as; maintenance activities requiring Code examinations; repair/replacement activities, design changes adding or deleting components; implementation of Code Cases or requests for relief, or changes in planned examination scope due to additional or supplemental examinations.
7.9.3 All changes or updates shall be authorized by the ISI Program Engineer prior to entry into the ISI Data Base.
7.9.4 Upon completion of examinations for a given operating cycle, the ISI Data Base shall be updated to reflect the actual status of completed examinations.
This should be done in a timely manner following the refueling outage (within 6 months as a guide) to ensure data base integrity. This update should be based on the completed NDE examination reports.
7.9.5 Scan plan revisions shall include a sign-off that the ISI Data Base has been updated as part of the revision approval cycle.
7.9.6 The ISI Program Engineer is responsible for ensuring that the ISI Data Base is updated in conjunction with ISI Program Plan revisions for items such as design changes, adopted Code Cases, and requests for relief.
7.10 Corrective Action Any corrective action required as a result of lSI examinations shall be documented in accordance with SPP-3.1, Corrective Action Program.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 49 of 113 7.0
[NSTRUCTION STEPS/ELEMENTS (continued) 7 11 Augmented Examinations 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 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 Component 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 ISI Program Engineer. 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, high suspect areas, probability of failure, and reporting requirements. Copies of the written request shall be submitted to ISO and Component 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 ISI Program Engineer Meeting attendees shall include the responsible organizations, System Engineering, and ISO. The meeting agenda should include examination plans and schedules, updates on industry experience, and any additional pertinent information.
Following the completion of the augmented examination, Component 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 Component 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 to identify any future actions, such as changes in the frequency of examination.
SIL's and clarification letters listed in this Augmented Examination Section provide GE's recommendation for reactor internals inspection. The actual scope and criteria for reactor internals inspections will be reviewed and approved by TVA Site Engineering prior to each refueling outage. Any indications found during inspections will receive a review and will be dispositioned by TVA Site Engineering. The responsible organization shall report augmented examination results to the NRC as required by the document initiating the examination.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 50 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7 11 1 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 (MSI-0-001-INSOO I). 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. Exam Requirement Source: B01-02.
Generic Letter 88-01 and NUREG-0313, Rev. 2.
7.11.2 CRD Return Line Reroute Responsible organization: Site Engineering. The augmented examination requirements of the CRD return line reroute are included in NUREG-0619. The requirements are a final liquid penetrant examination of the capped nozzle after the modification.
Also, the welded connections joining the rerouted CRD return line to the reactor water cleanup system shall be ultrasonically examined for three consecutive refueling outages. The weld RCRD-1-45 shall be ultrasonically examined, including the base metal on each side within one wall thickness (nominal wall.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-1-3 and RCRD-1-44 shall be ultrasonically examined along with the pipe on the downstream side. The refueling cycles for each unit to be examined are: Cycle 4, Cycle 5, and Cycle 7.
Reporting is required within 6 months of completing an outage during which an inspection was performed. Refer to NUREG-0619, Section 8.3 for information to be included.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 51 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.11.3 Evaluation of Corrosion Damage of Piping Components Exposed to Residue from the March 22, 1975 Fire Responsible organization: Site Engineering. The augmented examination requirements ofpiping components exposed to residue from the March 22, 1975 fire were included in MMI-53 for the first, second, third, and fourth refueling outages.
1 -MMI-46 includes the requirements for the sixth refueling outage.
The performance and documentation of the examinations shall be the responsibility of the M/N Engineering. The metallurgical analysis required shall be the responsibility of Nuclear Engineenng The examination of piping components exposed to residue from the March 22, 1975 fire is a Technical Specification Requirement 4.6.G.3 (TSR 3.4.3.3).
A report is required each outage upon completion of the examinations.
The data sheet is included in the instruction.
7.11.4 CRD Scram Discharge Volume Responsible organization: Site Engineering. The augmented examination requirements of the Scram Discharge Volume (SDV) piping are included in NUREG-0803. The SDV piping shall be examined in accordance with the requirements of ASME Section XI Class 2 components. The inservice examinations of the SDV piping shall begin during the second cycle of the first inspection interval See Table 8.1 for weld size and scheduled examinations. Results to be included with the final report.
7.11.5 HIPCI Pump Discharge Support Inspection Following Injection NRC commitment NC0850144002 for the augmented examination of the supports on the HPCI discharge line following an injection was revised on March 7, 1995. The revised commitment requires the examination of the HPCI discharge line supports in accordance with the normal ASME Section XI requirements. The revised commitment number is NC0950027001.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 52 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7.11.13 Augmented Examination of Austenitic Stainless Steel and Dissimilar Metal Welds Susceptible to IGSCC (Generic Letter 88-01 and NUREG-0313, Revision 2)
Responsible organization: Project Management Austenitic stainless steel and dissimilar metal circumferential welds in piping 4" NPS or larger that contain reactor coolant at a temperature above 200 degrees F during power operation shall be examined in accordance with the requirements of Generic Letter 88-01 and NUREG-0313, Revision 2.
Sample expansion shall be in accordance with Generic letter 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 Table 8.3 Part I by IGSCC category.
Table 8 3, Part 1, depicts the current IGSCC ( Categories D, E, F, and G) weld population for Unit 1. At the time that this unit was shutdown (March 1985), the NUREG-0313, IGSCC Program was being established and examination of the weld population was not completed.
During the Unit 1 Recovery phase, it is planned that the majority of these welds will be replaced with IGSCC resistant materials. These welds, as well as welds that may not be replaced, will receive a baseline examination prior to Unit 1 restart, and will be categorized as required in accordance with NUREG-0313 Rev. 02 and Generic Letter 88-01 requirements.
In addition to the requirements for procedure and personnel qualification in Section 7.2.3..B, the examination procedures and personnel used for IGSCC examinations per NUREG-03 13 Rev. 02 and Generic Letter 88-01, shall be qualified to the requirements of Appendix VIII of ASME Section XI as implemented by the Performance Demonstration Initiative Program (PDI).
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 53 of 113 7.0 INSTRUCTION STEPS/ELEMENTS (continued) 7 11.6 Reactor Vessel Interior Examinations Responsible organization: Site Engineering. In addition to the code required ISI examinations in Section 7.3.1, augmented examinations shall be performed at the frequency specified in accordance with procedure 0-TI-365, Reactor Pressure Vessel Internals Inspection (RPVII) Unit 1, 2, and 3. Examination results shall be included in the augmented summary report (notification of unsatisfactory results may impose additional reporting requirements as denoted by the source requirement).
7.11.7 Instrument Nozzle Safe Ends SIL-571 Perform UT and visual inspection of the stainless steel level instrumentation nozzle safe ends and stainless steel core differential pressure/standby liquid control (SLC) nozzle safe ends per the recommendations of SIL-571. The recommendations are to perform a visual leak check of the safe ends during the drywell leak check effort performed each outage. Insulation removal is not necessary to perform the leak check. A UT inspection of the accessible areas of all the safe and base material shall be performed. Per GE letter no. BFSE 94-005 these stainless steel safe ends should be UT inspected following 15 years of hot operation time and then at a frequency of once every second 24 month fuel cycle or once every third 18 month fuel cycle as applicable.
The implementation interval for Unit-1 shall start with the cycle-6 refueling outage. Leakage inspections shall be performed as described during the cycles-6 outage and during each subsequent refueling outage. Based on current 16-18 month refueling cycles UT inspection shall be performed during the cycle-9 refueling outage and then repeated at every third refueling following the cycle 9 outage. If 24 month refueling cycles are utilized inspection shall be performed during the cycle-9 refueling outage and then at every second refueling cycle following cycle-9.
7.11.8 Core-Spray and Recirc Inlet Safe Ends The replacement Unit I Recirc Inlet and Core Spray Safe Ends shall be inspected at the same interval as Category 'A" weldments. Ideally, the described safe end base material should be inspected in conjunction with the safe end to nozzle welds which will be examined as Category "A",veldments. If replacement is not conducted, the base material of these safe ends shall be examined per the appropriate Generic Letter Category dependent on the safe ends condition (Category "D" for nonresistant material with no cracks. Categorv "E" for cracks with no renai~r)
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 I-SI-4 6 G Page 54 of 113 7 0 INSTRUCTION STEPS/ELEMENTS (continued) 7.11.9 Weld Inspection For Pipe Whip Protection per TSR 3 4.3 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 Requirement (TSR) 3.4 3.2. The welds requiring examination each interval for pipe whip protection are:
DSCS-1-04, DSCS-1-05, DSCS-I-1 1, DSCS-1-12, GFW-1-09, GFW-I-12, GFW-l-15, GFW-1-26, GFW-1-29, GFW-1-32, KFW-1 13, KFW-1-31, KFW-1-38, KFW-l-39, THPCI-1-154, THPCI-I 152, THPCI-1-153, THPCI-I-153B, GMS-1-06, GMS-1-15, GMS-1 24, GMS-1-32, KMS-1-024, KMS-1-104, DSRHR-1-04, DSRHR-I 07, DSRHR-2-08A, DSRWC-1-03X, DSRWC-1-04X, DSRWC-1 05, AND DSRWC-1-06.
A report of these examinations shall be included with the ISI Summary Report.
7.11.10 RPV Shell Weld Examination Responsible organization: M/N Engineering. The RPV shell welds, Examination Category B-A, Item Nos. B1.1 1 and B1.12 shall be examined for Unit 1 in outage Cycle 6 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 (RIMS# 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.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 55 of 113 SECTION 8.0 TABLES/ATTACHMENTS
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 56 of 113 BROWNS FERRY TABLE 8.1 (UNIT 1)
NUCLEAR PLANT CLASS 1 COMPONENTS 40-Year Components Sampl 10-Year Sample Quantity Inspected Method 40 of Insp Month 80 Month 120 Month Exam Category Remarks A.
Reactor Vessel
- 1.
Seam welds not in Core Region
- a. Circumferential
- b. Longitudinal
- 2.
Closure Head Seam Weld
- 3.
Closure Head Meridional Weld
- 4.
Vessel-to-Flange Circumferential Weld
- 5.
Head-to-Flange Circumferential Weld 15.2 ft.
13 ft.
8 ft.
24 ft.
69 ft.
66 ft.
15.2 ft.
13 ft.
2 ft.
6 ft.
69 ft.
66 ft.
1.1 ft.
5ft lft 21 ft.
21 ft.
2 ft.
2.1 ft.
.5 ft.
2 ft.
23 ft.
22 ft.
11.2 ft. (note 1) B-B 9.8 ft.
B-B 1 ft. (note 1)
B-B 3 ft. (note 1)
B-B 25 ft. (note 1) B-C 23 ft. (note 1) B-C CHM-0992-C CHM-1095-A Sheet 1 CHM-1095-A Sheet 5 CHM-1095-A CHM-1095-A Sheet 3 CHM-1095-A Sheet 4
- 6.
Primary Nozzles Main Steam (26") (N3)
- a. Nozzle-to-Vessel and hfside Radii
- b. Nozzle-to-Safe End Core Spray (10") (N5)
- a. Nozzle-to-Vessel and Inside Radii
- b. Nozzle-to-Safe End 4
4 2
2 4
4 2
1 1
1 1
1 2
B-D CHM-1094-A 2 (note 1)
B-J B-D CHM-1094-A Sheet I
- (note 1)
B-F (IWB)
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 57 of 113 TABLE 8.1 (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS (IWB) 40-Year Components Sampe Feedwater (12") (N4)
- a. Nozzle-to-Vessel and Inside Radii
- b. Nozzle-to-Safe End Recirculation Inlet (12") (N2)
- a. Nozzle-to-Vessel and Inside Radii
- b. Nozzle-to-Safe End Recirculation Outlet (28") (N1)
- a. Nozzle-to-Vessel and Inside Radii
- b. Nozzle-to-Safe End Jet Pump Instr. (4") (N8)
- a. Nozzle-to-Vessel and Inside Radii
- a. Nozzle-to-Vessel and Inside Radii
- b.
Nozzle-to-Safe End 6
6 10 10 2
2 2
2 1
1 10-Year Sample 6
6 10 10 2
2 2
2 1
I Method of Insp UT UT UT UT,PT UT UT,PT UT UT,PT UT UT,PT Quantity Inspected 40 80 Month Month 2
2 3
3 2
2 4
4 1
1 1
1 120 Month 2
Exam Category B-D Remarks CHM-1094-A Sheet I 2 (note 1)
B-J 3
B-D CHM-1094-A Sheet 1 3 (note 1)
B-F
-(note 1)
B-D B-F B-D CHM-1094-A Sheet 2 CHM-1094-A Sheet 3 I (note 1)
B-F 1
1 B-D CHIM-1094-A Sheet 5
- (note 1)
B-F
)
_/
I
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 58 o1' 113 TABLE 8.1 (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS (IWB) 40-Year Components Sample 10-Year Sample Method of InsR Quantity Inspected 40 80 Month Month Head Instr. (6") (N6)
- a. Nozzle-to-Vessel and Inside Radii
- b. Nozzle-to-Flange Head Vent (4") (N7)
- a. Nozzle to Vessel and Inside Radii
- b. Nozzle-to-Flange
- 7.
Closure Nuts
- 8.
Closure Studs
- 9.
Closure Washers and Bushings
- 10.
Ligaments between Threaded Stud Holes
- 11.
- 12. Vessel Penetrations
- 14. Support Skirt Weld
- 15. Vessel Cladding 2
2 1
1 92 92 4
92 4
92 40 53 1
4 ft.
6 patches 2
1 1
92 92 4
92 4
92 40 63 1
4 ft.
6 patches UT UT UT UT VT-i UT ST VT-1 VT-I UT VT-2 VT-2 PT UT VT-3 1
1 30 30 30 30 I
1 30 30 4
30 4
30 32 (note 1) 32 (note 1)
B-D B-J B-D B-J B-G-I B-G-I B-G-I CHM-2102-A CHM-1094-A Sheet 6 CHM-2102-A CHM 1094-A Sheet 7 CHM-2001-C When removed 32 (note 1)
B-G-1 B-G-1 32 (note 1)
Inspection During System Pressure Tests Inspection During System Pressure Tests 1
0 2
2 ft.
2 2 ft. (note 1)
B-G-1 B-O B-E B-H B-H 2 (note 1)
B-N-I IS !-0414-C I-ISI-0414-C MSG-0020-A 120 Month Exam Category Remarks I )
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 I-SI-4.6.G Page 59 of 113 TABLE 8.1 (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS I COMPONENTS (IWB 40-Year Components Sample 10-Year Sample Method of Insp Quantity Inspected 40 80 Month Month VT-1, VT-3 General Surveillance B-N-l, B-N-2 B. Piping (note 2)
- 1.
Recirculation Circumferential 28" SS 22" SS 12" SS 4" SS 31 10 30 1
8 3
7 0
1 2
2 1
2 3
1 3
VT-I within belt-line region CHM-1081 C B-J B-J B-J B-J Recirculation Branch Pipe Connection Welds 8
3 2
1 B-J B-J
- 2.
Main Steam CHM-1082-C Circumferential 26" CS 26" CS (Pipe Whip) 6" CS Branch Pipe Connection Welds 56 6
50 1
25 1
14 6
13 1
6 1
UT, ST UT, ST UT, ST UT, ST UT, ST PT or MT 2
3 4
4 2
5 1
2 2
1 8
1 4
2 B-i B-J B-i See Table C B-i B-J B-i
- 16.
Internals 120 Month Exam Category Remarks 12" SS 4" SS 10" CS 6" CS 3" CS
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 60 of I 3 TABLE 8.1 (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS I COMPONENTS (IWB)
Method of Insp Quantity Inspected 40 80 Month Month 120 Month Exam Category Remarks
- 3.
Feedwater Circumferential 24" CS 20" CS 12" CS 12" CS (Pipe Whip)
Branch Pipe Connection Welds 16" CS 8" CS 29 7
26 10 1~
6 2
7 10 1
UT, ST UT, ST UT, ST UT, ST UT, ST UT, ST 2
1 3
I 2
1 3
3 B-J B-J B-J B-J 2
3 4
CHM-1080-C See Table C B-J B-J CHM-1089-C
- 4.
Core Spray Circumferential 10"1 12" 4
23 1
3 B-J B-J 3
- 5.
RHR Circumferential 24" SS 24" SS (Pipe Whip) 20" SS 20" Dissimilar 20" CS 18 1
4 1
2 4
1 1
I UT, ST UT, ST UT, ST UT, ST UT, ST 1
1 1
2 B-J B-J B-J B-F B-J CHM-1088-C See Table C Components 40-Year Sample 10-Year Sample
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 61 of I I TABLE 8.1 (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS I COMPONENTS (IWB) 40-Year Sample Components 10-Year Sample 2
1 Method of Ins.12 Quantity Inspected 40 80 Month Month 120 Month Exam Category
- 6.
CRD Hydraulic Return Circumferential 8" CS 6" CS 4" CS 4" Dissimilar 2
1 7
4 UT, ST UT, ST UT, ST UT, PT I
1 1
Remarks CHM-1097-C B-J B-J B-J B-F
- 7.
RWCU Circumferential 6" DM 8" CS 6" SS 6" SS (Pipe Whip) 4" CS
- 8.
- 9.
HPCI Circumferential 16" CS 14" CS 10" CS 10" CS (Pipe Whip)
- 10.
Pressure Retaining Bolting 2
2 6
4 6
5 2
CHM-1098-C 2
1 4
4 1
I UT, ST UT, ST UT, ST UT, ST UT, ST 1
2 1
4 2
B-F B-J B-A B-J B-J See Table C CHM 1098-C B-J CHM-1099-C 1
3 12 4
17 1
1 2
4 17 UT, ST UT, ST UT, ST UT, ST VT-I 1
1 8
B-J B-J B-J B-J See Table C 9 (note 1)
B-G-2 I
1 1
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 62 of I I TABLE 8.1 (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS (IWB) 40-Year Components Sample 10-Year Sample Method of lnsR Quantity Inspected 40 80 Month Month 120 Month Exam Category Remarks
- 11.
Pipe and Valve Component Supports
- a. Integrally Welded "b. Support Components 101(104*)
25 122(117*)
VT-3 35 8
39 48 (note 1)
B-K-2 C.
Recirculation Pumps
- 1.
Pressure Retaining Studs Nuts
- 2.
Ligaments Between
- 3.
Integrally Welded Supports
- 4.
Pump Casing 32 32 32 6
2 32 32 32 2
6 1
VT-I, UT MT VT-i VT-i UT VT-3 VT-3 10 10 When Removed 10 10 12 (note 1)
B-G-I 12 (note 1)
B-G-1 When connection is disassembled 1 1 2
During Normal Maintenance 1
3 B-G-I B-K-I B-K-2 B-L-2
- 1.
Valve Bodies
- a. Visual 60 Internals Change in numbers due to modifications leading to Unit 2 restart.
During Normal Maintenance 9
B-K-I Appendix E D. Valves B-M-2
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 63 oI 113 TABLE 8.1 (UNIT I, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 1 COMPONENTS (IWB) 40-Year Components Sample
- b. Valve Body Welds
- 2.
Pressure Retaining Bolting 1
31 10-Year Sample 1
31 E
Exempt Components Method of InsR UT VT-I VT-2 Quantity Inspected 40 80 Month Month 0
10 0
10 Inspection During Hydrostatic Testing 120 Month I
Exam Category Remarks B-M-1 11 (note 1)
B-G-2 B-P Note I - A preservice/re-baseline of the identified Class I components will be performed during the Unit I recovery outage. This preservice examination will include 100% of the applicable components, which are accessible. This includes 100% of the accessible reactor vessel welds.
Note 2 - A preservice/re-baseline of the identified Class 1 components will be performed during the Unit 1 recovery outage. This preservice examination will include 25% of the applicable components, which are accessible.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 64 of II TABLE 8.1 (UNIT 1)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS (IWC) 10-Year Sample Method of Insl Quantity Inspected 40 80 Month Month 120 Month Exam Category Remarks A.
RHR Heat Exchangers
- 1.
Circumferential Welds
- 2.
Nozzle-to-Vessel "Welds
- 3.
Integrally Welded Supports B.
Main Steam Piping (note 3)
- 1.
Circumferential Welds 26" CS 24" CS 18" CS 6" CS
- 2.
Branch Pipe Connection Weld 12ft.
.5 ft.
2 3 ft.
5 ft.
1 3
.5 ft.
I ft.
I ft.
C-A C-A C-B CHM-2418-B Bottom Head Fig Weld (RHRG-iI)
C-C CHM-2690-C 2
18 10 28 1
5 2
7 UT, ST UT, ST UT, ST UT, ST 2
1 2
2 2
1 3
C-F C-F C-F C-F 6 C ST I
Components 40-Year Sample
)
C-F 6"1 CS
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6.G Page 65 of 113 TABLE 8.1 (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS (1WC)
Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam Components Sample Sample of Insp Month Month Month Category Remarks C
RHR Piping (note 3)
ISI-0362-C
- 1.
Circumferential Welds 30" CS 6
3 4
5 4
C-F 18" CS 21 5
2 2
C-F 16" CS 6
C-F 14" CS 5
C-F 12" CS 1
-1 C-F 10" CS 6
1 C-F 6" CS 21 5
1 2
C-F D.
Closed Cooling Water ISI-0029-C Pi in (note 3)
- 1.
I C-G E
Scram Discharge Volume ISI-0036-C Tank (note 3)
- 1.
Circumferential 3
C-F Entire Weld Welds F.
Scram Discharge Volume ISI-0036-C Pi in, (note 3) 1 Circumferential 14 5
1 2
C-F Welds
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 66 of 113 TABLE 8.1 (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS (IWC) 40-Year Sample 10-Year Sample Method of Insp Quantity Inspected 40 80 Month Month
- 120, Month Exam Category Remarks G.
Piping and Valve Component Supports I.
Integrally Welded Supports
- 2.
Support Components H.
RHR Pumps 1
Integrally Welded Supports 2
Support Components 110(116*)
28 211(242*)
211 4
4 1
4 I.
Exempt Components J.
Augmented Inspection PT or MT 9
96 1
1 Inspection During Hydrostatic Testing 10 C-E-I 86 (note 4)
C-E-2 C-E-I 2 (note 4)
C-E-2 Section 8.6
- 1.
HPCI Piping (note 3)
20"CS 3
16"CS 2
14"CS 4
12"CS 1
I10CS 4
8"CS 1
- Change in number due to modifications leading to Unit 2 restart.
0 1
1 1
0 I
0 Components ISI-0022-C UT, ST UT, ST UT, ST UT, ST UT, ST UT, ST UT, ST ISI-0091-C I
I 1
1 C-F C-F C-F C-F C-F C-F C-F I
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 67 of I 13 TABLE 8.1 (UNIT 1, CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLASS 2 COMPONENTS (FWC)
Components
- 2.
RCIC Piping (note 3)
Circumferential Welds 12 "CS 1 0"CS 8"CS 6"CS
- 3.
Core Spray Piping (note 3)
Circumferential Welds 16"CS 14"CS 12"CS 1 0"CS 12"SS
- 4.
Integrally Welded Supports
- 5.
Support Components 40-Year Sample 1
3 1
3 4
3 3
1 1
44 (38*)
113 (120*)
10-Year Sample 0
1 0
1 1
1 0
0 5
12 Method of Insn Quantity Inspected 40 80 Month Month UT, ST UT, ST UT, ST UT, ST UT, ST UT, ST UT, ST UT, ST UT, ST I
VT-3 4
4 (note 4)
C-E-2
- Change in numbers due to modifications leading to Unit 2 restart.
Note 3 - A preservice/re-baseline of the identified Class 2 components will be performed during the Unit I recovery outage. This preservice examination will include 7.5% of the applicable components, which are accessible.
Note 4 - A preservice/re-baseline of the identified Class 2 components will be performed during the Unit I recovery outage.
the applicable components, which are accessible.
This preservice examination will include 100% of 120 Month Exam Category Remarks ISI-0093-C C-F C-F C-F C-F 1
1 ISI-0095-C C-F C-F C-F C-F C-F I
3 4
C-E-1 Appendix E Appendix E 1
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 I-SI-4 6.G Page 68 of I113 TABLE 8.1 UNIT I BROWNS FERRY NUCLEAR PLANT CLASS 3 COMPONENTS (IWD)
Quantity Inspected 40-Year 10-Year Method 40 80 120 Exam Components Sample Sample 2f lnsn Month Month Month Category Remarks A.
RHRSW Supports 92(76*)
92 VT-3 92 92 92 (note 5)
IWD-2600 ISI-0085-C B.
EECW Supports 97(111*)
97 VT-3 97 97 98* (note 5)
IWD-2600 ISI-0086-C C.
Fuel Pool Cooling Supports 64(72*)
64 VT-3 64 64 64 (note 5)
IWD-2600 ISI-0090-C Note 5 - A preservice/re-baseline of the identified Class 3 components will be performed during the Unit I recovery outage. This preservice examination will include I 00% of the applicable components, which are accessible.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 TABLE 8.2 AUGMENTED EXAMINATIONS WELD INSPECTION FOR PIPE WHIP PROTECTION System Weld Identification Main Steam GMS-32, GMS-15, GMS-24, GMS-6, KMS-104, KMS-24 Feedwater KFW-39, GFW-15, KFW-38, GFW-9, GFW-12, KFW-13, GFW-26, KFW-31, GFW-29, GFW-32 RHR DSRHR-8A, DSRHR-7, DSRHR-4 Core Spray DSCS-12, DSCS-4, DSCS-1 1, DSCS-5 RWCU DSRWC-1-3X, DSRWC-1-4X, DSRWC-1-5, DSRWC-1-6 HPCI THPCI-154, THPCI-152, THPCI-153, THPCI-153B I-SI-4.6 G Page 69 o1 I I t NOTE: 100% of the pipe whip protection welds must be examined each interval per Technical Requirement Manual (TRM)3.4.3
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 I-SI-4.6 G Page 70 of 113 TABLE 8 3 Part 1 UNIT I WELDS REQUIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM (INCHES)
CONFIG CATEGORY RCRD-1-49 CRD 4
E, V D
DCS-1-04 CS 12 P, P D
DCS-1-05 CS 12 P, V D
DCS-I-06 CS 10 E, V D
DCS-1-14 CS 12 P, V D
DCS-1-15 CS 12 E, V D
DCS-1-16 CS 12 P, V D
DCS-1-17 CS 12 E, V D
DSCS-1-01 CS 12 E, P D
DSCS-1-04 CS 12 E, P D
DSCS-1-05 CS 12 E, P D
DSCS-1-06 CS 10 E, P D
DSCS-1-08 CS 12 E, P D
DSCS-1-09 CS 10 P, P D
DSCS-1-10 CS 12 E, P D
DSCS-1-11 CS 12 E, P D
DSCS-1-12 CS 12 E, V D
DSCS-1-13 CS 10 E, P D
GR-1-07 RECIR
( 4 C, P D
GR-1-08 RECIR 28 T, X D
GR-1-09 RECIR 12 P, S D
GR-1-10 RECIR 12 E, P D
GR-1-12 RECIR 12 P, S D
GR-l-13 RECIR 12 E, P D
GR-l-14 RECIR 12 P, SE D
GR-l-15 RECIR 12 P, R D
GR-1-16 RECIR 12 E, P D
GR-1-17 RECIR 12 P,SE D
GR-1-18 RECIR 22 H, X D
GR-1-19 RECIR 12 P, S D
GR-1-20 RECIR 12 E, P D
GR-1-21 RECIR 12 P, SE D
GR-1-22 RECIR 12 P, S D
GR-1-23 RECIR 12 E, P D
GR-1-24 RECIR 12 P,SE D
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 I-SI4 6 G Page 71 of 113 TABLE 8 3 Part I (Continued)
UNIT I WELDS REQUIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD NUMBER GR-1-25 GR-1-26 GR-1-28 GR-1-29 GR-1-34 GR-1-35 GR-1-36 GR-1-37 GR-1-38 GR-1-39 GR-140 GR-1-42 GR-1-43 GR-1-44 GR-l147 GR 1-48 GR-1-49 GR-1-50 GR-1-51 GR-1-52 GR 153 GR-1-55 GR 1-59 GR 162 GR-1-63 KR-1-13 KR-1-17 KR-I-19 KR-1-33 KR-1-35 KR 1-38 KR--1-39 KR-1-40 KR-1-41 KR-1-43 KR-1-44 KR-1-46 KR-1-50 KR-1-51 SYSTEM RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR RECIR PIPE SIZE (INCHES) 22 22 28 28 28 12 12 12 12 12 12 12 12 22 12 12 12 12 22 22 28 28 28 28 28 12 12 12 22 12 12 12 12 12 12 12 28 28 28 WELD CONFIG H,V H,V P,V E,V P,X P, S E, P P, SE P, S E, P P, SE E, P P, SE H,X P, SE P, S E, P P, SE H,V H, V P, SE P,T P, SE E, V P,V BC E, P BC R,X BC E, P E, P E, P BC E, P E, P P, T E, P E, P IGSCC EXAM CATEGORY D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
D D
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI4.6 G Page 72 of 113 TABLE 8 3 Part 1 (Continued)
UNIT I WELDS REQUIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM (INCHES)
CONFIG CATEGORY DRHR-1-02 RHR 24 P, V D
DRHR-I-06 RHR 24 P, V D
DRHk-I-07 RHR 24 E, V D
DRHR-1-09 RHR 24 P, T D
DRHR-I-11 RHR 24 P, V D
DRHR-1-13 RHR 24 E, P D
DRHR-1-14 RHR 24 E, V D
DRHR-1-16 RHR 24 E, V D
DRHR-1-19 RHR 20 P, T D
DRHR-1-21 RHR 20 P, V D
DRHR-1-22 RHR 20 P, V D
DSRHR-1-01 RHR 24 E, P D
DSRHR-1-02 RHR 24 E, P D
DSRHR-1-03 RHR 24 P, P D
DSRHR-1-05A RHR 24 E, P D
DSRHR-1-06 RHR 24 P, P D
DSRHR-1-07 RHR 24 P, P D
DSRHR-1-08 RHR 6
BC D
TRHR-1-190 RHR 20 E, V D
TRHR-1-191 RHR 20 E, V D
JP-I-IA RPV 4
N,SE D
JP-I-1B RPV 4
N,SE D
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 I-SI-4.6.G Page 73 of 113 TABLE 8 3 Part 1 (Continued)
UNIT I WELDS REQUIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM (INCHES)
CONFIG CATEGORY DRWC-1-01 RWCU 6
P, V D
DRWC-1-04E RWCU 6
P, PEN D
DSRWC-I-0 lAX RWCU 6
E, P D
DSRWC-1-02X RWCU 6
E, P D
DSRWC-1-03X RWCU 6
E, P D
DSRWC-1-04X RWCU 6
E, P D
DSRWC-1-05 RWCU 6
E, P D
DSRWC-1-06 RWCU 6
E, P D
DSRWC-1-07 RWCU 6
E, P D
TRWC-1-01 RWCU 6
E, P D
TRWC-1-02X1 RWCU 6
E, V D
TRWC-1-04 RWCU 6
P, V D
TRWC-1-04A RWCU 6
P, P D
CS-1-69(OL)
CS 12 OL/P, V E
DCS-1-07(OL)
CS 12 OL/P, V E
DCS-1-08(OL)
CS 12 OLJE, V E
GR-1-03(OL)
RECIR 28 OL/E, V E
GR-1-27(OL)
RECIR 28 OLIP, P E
GR-1-41(OL)
RECIR 12 OL/P, R E
GR-1-46(OL)
RECIR 12 OL/E, P E
GR-1-54(OL)
RECIR 28 OL/E, P E
GR-1-56(OL)
RECIR 28 OL/E, V E
GR-1-57(OL)
RECIR 28 OLIP, V E
GR-1-58(OL)
RECIR 28 OL/E, P E
GR-1-60(OL)
RECIR 28 OL/E, P E
GR-1-61(OL)
RECIR 28 OLIP, P E
GR-1-64(OL)
RECIR 28 OL/E, P E
KR-I-03(OL)
RECIR 28 OL/P, T E
KR-1-14(O1)
RECIR 12 OL/BC E
KR-I-15(OL)
RECIR 22 OL/C, H E
KR-1-16(OL)
RECIR 12 OL/E, P E
KR-1-18(OL)
RECIR 12 OL/E, P E
KR-1-20(OL)
RECIR 12 OL/BC E
KR-1-21(OL)
RECIR 12 OL/E, P E
KR-1-22(OL)
RECIR 12 OL/E, P E
KR-1-36(OL)
RECIR 12 OL/BC E
KR-1-37(OL)
RECIR 22 OL/C, H E
KR-1-42(OL)
RECIR 12 OUBC E
KR-1-45(OL)
RECIR 28 OL/E, P E
KR-1-48(OL)
RECIR 28 OL/E, P E
KR-I-52(OL)
RECIR 28 OL/E, P E
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4.6 G Page 74 of 113 TABLE 8 3 Part I (Continued)
UNIT I WELD REQUIRED TO EXAMINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM (INCHES)
CONFIG CATEGORY DRHR-1-05(OL)
RHR 24 OLIE, V E
DRHR-1-08(OL)
RHR 24 OLUP, V E
DRHR-1-15(OL)
RHR 24 OL/P, V E
DRHR-1-17(OL)
RHR 24 OLP, V E
DRHR-I-18(OL)
RHR 24 OLUP, T E
DRHR-I-20(OL)
RHR 20 OL/E, P E
DSRHR-1-04(OL)
RHR 24 OL/E, P E
DSRHR-1-04A(OL)
RHR 24 OL/E, E E
DSRHR-1-05(OL)
RHR 24 OL/E, P E
DSRHR-1-08A(OL)
RHR 24 OL/P, P E
DSRHR-1-08B(OL)
RHR 24 OL/E, P E
DSRHR-1-09(OL)
RHR 20 OL/E, P E
DSRHR-1-IO(OL)
RHR 20 OL/E, P E
DSRHR-I-II(OL)
RHR 20 OL/E, P E
DRWC-1-OIA(OL)
RWCU 6
OL/P, V E
GR-1-01 RECIR 28 P, P F
GR-1-02 RECIR 28 P, V F
GR-1-45 RECIR 12 P, S F
KR-1-02 RECIR 28 E, P F
KR-1-12 RECIR 22 H, X F
KR-1-24 RECIR 28 E, P F
KR-1-25 RECIR 28 P, T F
KR-1-34 RECIR 22 H, X F
KR-1-47 RECIR 28 E, P F
DRHR-1-04 RHR 24 E, P F
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6.G Page 75 of 113 TABLE 8 3 Part 1 (Continued)
UNIT I WELDS REQUIRED TO BE EXAMINED PER GENERIC LETTER 88-01 WELD PIPE SIZE WELD IGSCC EXAM NUMBER SYSTEM (INCHES)
CONFIG CATEGORY RCRD-1-50 CRD 4
E, V G
RCRD-1-52 CRD 4
P, V G
DCS-1-13 CS 12 P, P G
DSCS-1-02 CS 12 E, P G
DSCS-1-03 CS 12 E, P G
DSCS-1-07 CS 12 E, P G
GR-1-04 RECIR 4
C, P G
GR-1-11 RECIR 12 P,SE G
GR-1-30 RECIR 4
C, P G
GR-1-33 RECIR 4
C, P G
GR-1-63A RECIR 4
F, F G
GR-1-63B RECIR 4
BC G
KR-1-01 RECIR 4
BC G
KR-1-04 RECIR 4
BC G
KR-I-1I RECIR 22 R, X G
KR-1-23 RECIR 4
BC G
KR-1-26 RECIR 4
BC G
KR-1-49 RECIR 4
BC G
KR-1-53 RECIR 4
BC G
RCRD-1-33 RPV 4
C, N G
DSRWC-1-OIB RWCU 6
P, S G
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 TABLE 8.3 Part 2 UNIT I STAINLESS AND DISSIMILAR METAL WELDS NOT SUBJECT TO GENERIC LETTER 88-01 EXAMS 1-SI-4 6.G Page 76 of 113 WELD NUMBER CS-1-67 CS-1-68 PIPE SIZE SYSTEM (INCHES)
CS CS DCS-1-01 CS DCS-1-01A DCS-1-02X CS 14 12 12 14 CS 12 DCS-1-03 CS 12 DCS-1-04A CS 10 DCS-1-12 CS 12 DCS-1-12A DSCS-1-14 TCS-1-02A CS 12 CS 12 CS 12 SHPCI-1-1 HPCI 12 SHPCI-1-2 HPCI 12 WELD IGSCC EXAM ISI SHEET CONFIG CATEGORY DRAWING NUMBER E,V E, P E,V E, E P,V N/A N/A N/A N/A N/A PEN, V N/A P, PEN N/A PEN, V N/A P, PEN N/A E, P P, P F, P E, P N/A N/A N/A N/A ISI-0095-C 02 ISI-0095-C 02 ISI-0095-C ISI-0095-C ISI-0095-C CHM-1089-C CHM 1089-C CHM-1089-C CHM-1089-C ISI-0095-C 01 01 01 01 01 01 01 01 ISI-0095-C 01 ISI-0091-C 02 ISI-0091-C 02 COMMENTS TEMPERATURE EXCLUSION TEMPERATURE EXCLUSION.
TEMPERATURE EXCLUSION.
TEMPERATURE EXCLUSION.
TEMPERATURE EXCLUSION.
TEMPERATURE EXCLUSION.
TEMPERATURE EXCLUSION.
INACCESSIBLE IN PENETRATION X-16A.
TEMPERATURE EXCLUSION.
TEMPERATURE EXCLUSION.
INACCESSIBLE PENETRATION X-16B.
TEMPERATURE EXCLUSION, r
TEMPERATURE EXCLUSION.
TEMPERATURE EXCLUSION.
TEMPERATURE EXCLUSION.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 TABLE 8 3 Part 2 UNIT I STAINLESS AND DISSIMILAR METAL WELDS NOT SUBJECT TO GENERIC LETTER 88-01 EXAMS I-SI-4 6 G Page 77 of 113 SHPCI-1-3 HPCI 12 SHPCI-1-4 HPCI 12 SHPCI-1-5 HPCI 12 DSRWC-1-04E RWCU 6 E, P E, P E, F N/A N/A N/A P, PEN N/A ISI-0091-C ISI-0091-C ISI-0091-C 02 02 02 CHM-1098-C 01 TEMPERATURE EXCLUSION.
TEMPERATURE EXCLUSION TEMPERATURE EXCLUSION.
INACCESSIBLE IN PENETRATION.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 78 of 113 TABLE 8.4 CLASS 2 EXEMPTED COMPONENTS CORE SPRAY (47W813-1) r I Chemistry Exemption a
From discharge of pumps A, B, C, and D to FCV 75-25, FCV 75-53, FCV 75-22, and FCV 75-50 (including pumps A, B, C, and D).
- b.
From suppression pool header to the suction of pumps A, B, C, and D and to HCV 75-12, HCV 75-40, and HCV 75-3 1.
- 2.
Components which do not operate, other than ECCS, during normal reactor operation.
a Pump test lines from FCV 75-50 and FCV 75-22 to the suppression pool.
- 1.
Chemistry Exemption
- a.
Pump discharge to FCV 71-40 (including pump).
b Pump drive turbine discharge to suppression pool (including drive turbine).
- 2.
Pressure and Temperature Exemption
- a.
Suppression pool suction from 16-inch core Spray and 71-502 to pump suction.
- 1.
Chemistry Exemption
- a.
Main pump discharge to FCV 73-35 and FCV 73-45 (including pump).
- b.
Booster pump discharge to main pump suction.
- c.
From FCV 73-3 and 73-586 to turbine inlet (including turbine).
- d.
From turbine outlet to suppression pool.
- 2.
Pressure and Temperature Exemption
- a.
From suppression pool suction and 73 -505 to booster pump suction.
END OF TABLE 8.4
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 79 of 113 TABLE 8.5 CLASS I VALVE DATA CODE VALVE
~!AT~t'1df V' 11 'AT PIPING VALVE
- eVeTOv, QT7T?
VALVE VALVE GROUP TVA Dwg No.
VENDOR TVDI*
AC'T
'NAC (WFT fl MAP*
flwi' No MATERIAL VENDOR SPEC VALVE FORGING/
FUNCTION CASTING 24" Ck SA I
CHIM-1080-C 24" 24" 24" Ck Ck Ck SA SA SA 1
CHM-1080-C I
CHtM-1080-C I
CIIM-1080-C 24" Gate Man 2
CHM-1080-C 24" Gate Man 2
CIIM-1080-C Recirc 28" Gate Recirc 28" Gate I
B Recirc I
B Reciro ICV 3-67 HCV 3-66 FCV 68-1 FCV 68-77 FCV 68-3 FCV 68-79 FCV 68-33 FCV 68-35 FCV 1-14 FCV 1-26 FCV 1-37 FCV I-51 FCV 1-15 FCV 1-27 FCV 1-38 FCV 1-52 PCV 1-4 PCV 1-179 PCV 1-5 PCV 1-18 PCV 1-19 PCV 1-22 PCV 1-23 PCV 1-30 PCV 1-31 PCV 1-34 PCV 1-41 PCV 1-180 PCV 1-42 Recirc Recirc M. Stm.
M Stm M. Stmn.
M. Stm M Stm.
M. Stn.
M. Stni.
M. Stm M. Stm M Stn.
M Stm.
M. Sun.
M. Strn.
M Stm M Stm M. Stm M. Stm.
M. Stm M. Stn.
M. Stm M. Stm.
IICV74-69 I
RtIR IICV 74-55 1
RIIR 28" Gate 28" Gate 22" Gate 22" Gate 26" 26" 26" 26" 25" 26" 26" 26" 6"
6" 6"
6" 6"
6" 6"
6" 6"
6" 6"
6" 6"
Globe Globe Globe Globe Globe Globe Globe Globe Rel Rel Rel Rel Rel Rel Rel Rel Rel Rel Rel Rel Rel MO 3
CIIM-1081-C MO 3
CHM-1081-C MO 4
CIIM-1081-C MO 4
CIIM-1081-C MO 5
CIIM-1081-C MO 5
CIIM-1081-C CO co CO CO CO CO CO CO SA SA SA SA SA SA SA SA SA SA SA SA SA 6
CHM-1082-C 6
CIIM-1082-C 6
CHM-1082-C 6
CHM-1082-C 6
CItM-1082-C 6
CITM-1082-C 6
CHM-1082-C 6
CIIM-1082-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 7
ISI-0027-C 24" Gate Man 8
CttM-1088-C 24" Gate Man 8
CIIM-1088-C 20788-11 20788-11 20788-If 20788-H 035879-2 035879-2 94-12086 94-12086 94-12086 94-12086 94-12086 94-12086 20851-11 20851-H 20851-tt 20851-11 20851-11 20851-11 20851-11 20851-H PL-7657F-100 PL-7657F-100 PL-7657F-100 PL-7657F-100 PL-7657F-100 PL-7657F-100 PL-7657F-100 PL-7657F-i 00 PL-7657F.-100 PL-7657F-100 PL-7657F-100 PL-7657F-100 PL-7657F-100 035880-3 035880-3 Atwood&
A-216 WCB Momll Atw&Mor A-216 WCB Atw&Mor A-216 WCB Atw&Mor A-216 WCB PSIV PSIV PSIV PSIV Powell A-216 WCB Maint Powell A-216 WCB Maint.
I 1 I
1 1
I Oper Oper PSIV PSIV Oper.
Oper PSIV PS1V PSIV PSIV PSIV PSIV PSlV PSIV MSRV MSRV MSRV MSRV MSRV MSRV MSRV MSRV MSRV MSRV MSRV MSRV MSRV Powell A.351 CF8M Maint Powell A351 CF8M Maint.
I AC Fdwtr.
- Fdwtr, Fdwtr.
Fdwtr.
3.554 3-558 3.568 3-572 A
A A
A A
A A
A C
C C
C C
C C
C C
C C
C C
Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting Casting ACT NO WELD MAPI Dw No VENDOR SPEC Darling A351 CF8 Darling A351 CF8 Darling A351 CF8 Darling A351 CF8 Darling A351 CF8 Darling A351 CF8 Atw&Mor A216 WCB Atw&Mor A216 WCB Atw&Mor A216 WCB Atw&Mor A216 WCB Atw&Mor A216 WCB Atw&Mor A216 WCB Atw&Mor A216 WCB Atw&Mor A216 WCB Trgt Rck See Note I Trgt Rck Trgt Rck Trgt Rck Trgt Rck Trgt Rck Trgt Rck Trgt Rck Trgt Rck Trgt Rck Trgt Rck Trgt Rck Trgt Rck I
I 1
INSERVICE INSPECTION PROGRAM UNIT 1 CODE VALVE PIPING CLASS CAT.
SYSTEM VALVE VALVE SIZE TYPE REV 0003 TABLE 8 5 (Continued)
CLASS I VALVE DATA VALVE GROUP TVA Dwg No ACT.
NO.
(WELD MAP)
VENDOR Dwe NO VENDOR I-SI-4 6 G Page 80 of' 113 MATERIAL VALVE FORGIN(,
FCV 74-68 FCV 74-54 FCV 74-67 FCV 74-53 IICV 74-49 FCV 74-47 74-691 FCV 74-78 FCV 74-77
- 69-579
RIIR "A
RHR RHR "A
RHR H Spray "A
H Spray "A
H Spray CRD C Spray C Spray AC C Spray AC C Spray "A
C Spray "A
C Spray RWCU A
RWCU A
RCIC 24" 24" 24" 24" 20" 20" 6"
6" 6"
4" 12" 12" 12" 12" 12" 12" 6"
6" 6"
4" 4',
6" Ck Ck Gate Gate Gate Gate Ck Gate Gate Gate Gate Gate Ck Ck Gate Gate Gate Gate Gate Ck Gate Ck SA SA MO MO Man MO SA MO MO Man Man Man SA SA MO MO Man MO MO SA Man SA
- Exempt from B-M-2 examination due to size.
VALVE NO 9
CIIM-1088-C 9
CIIM-1088-C 10 CHIM-1088-C 10 CIIM-1088-C 11 CIIM-1088-C 12 CIIM-1088-C 13 CIIM-1088-C 14 CHM-1088-C 14 CHM-1088-C 15 CIIM-1097-C 16 CIIM-1089-C 16 CIIM-1089-C 17 CUIM 1089-C 17 CIIM-1089-C 18 CItM-1089-C 18 CHM 1089-C 19 CIIM-1098-C 20 CIIM-1098-C 21 CIIM-1098-C 22 CHtM-1098-C 23 CHM-1098-c 24 CHM-1098-C 20800-11 20800-11 A-12334-MIE A-12334-MIE 036207-2 A-12332-MIC P-33160-21 A-12323-M2G A-12323-M2G P-339231-13 036034-2 036034-2 PD-420652 PD-420652 IVP-I 1978 IVP-1 1978 P-33160-20 435KAA-002 P-33160-20 P-35177-4 P-35177-3 PD-420688 Atw&Mor Atw&Mor Walworth Walworth Powell Walworth Velan Walworth Walworth Velan Powell Powell Rockwell Rockwell Walworth Walworth Velan Borg Warner Velan Velan Velan Rockwell A351 CFXM A351 CF8M A351 CF8M A351 CF8M A351 CFrM A216 WCB A182 F316 A351 CFSM A351 CF8M A182 TP316 A351 CF8M A351 CF8M A351 CF8M A351 CF8M A351 CFSM A351 CFXM AI82 F316 SA 105 A182 F316 AI05GRII A216 WCB PSIV PSIV PSIV PSIV Maint PSIV Oper PSIV PSIV Maint Maint.
Maint PSIV PSIV PSIV PSIV Maint PSIV PSIV PSIV Maint.
PStV Caosting Ca-sting Casting Castijg Casting Forging Casting Casting Forging Casting Casting Casting Casting Casting Casting Forging Forging Forging Forging Casting
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 I-SI-4 6 G Page 81 of'l TABLE 8 5 (Continued)
CLASS I VALVE DATA CODE VALVE PIPING VALVE VALVE VALVE GROUP TVA Dwg No VENDOR VALVE NO CLASS CAT.
SYSTEM SIZE TYPE ACT.
NO.
(WELD MAP)
Dwg NO MATERIAL VALVE rORGING/
VENDOR SPEC FUNCTIO CASTING N
1 A
ttPCI I
A HPCI I
A IIPCI I
A RHR RWCU 10" Gate MO 25 CIIM-1099-C PB-139989 10" Gate MO 25 CHM-1099-C PB-139989 14" 20" 4"
Ck CO Gate MO Ck SA Crane Crane A216 WCB PSIV A216 WCB PSIV 26 CHIM 1099-C PD-420687 Rockwell A216 WCB PSIV 27 CHM-1088-C A-12331-MIC Walworth A351 CF8M PSIV 28 ISI-0333-C C-23650 Anchor SA-351 CFSM PSIV Darling 4"
Ck SA 28 ISI-0332-C C-23650 Anchor Darling SA-351 CF8M PSIV
- Exempt from B-M-2 examination due to size.
Note I MSRV's with serial numbers 1014, 1015, 1016, 1032, 1033, and 1034 are complete forgings (AI05). All other MSRV's have cast bodies (A216 WCB) with forged top works (AI05)
Valve Actuation MO -
Motor Operated CO -
Cylinder Operated SA.
Self-Actuating Man -
Manual FCV 73-2 FCV 73-3 FCV 73-45 FCV 74-48 69-628 69-629 RWCU Casting Casting Casting Casting Casting Casting I
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6.G Page 82 of 113 TABLE 8 5A Valve Numbers (Flow Diagram Number)
Feedwater Recirculation Main Steam 96A (3-554), 28A (3-558), 29A (HCV 3-67), 96B (3-568), 28B (3-572), 29B (HCV 3-66) 43A (FCV 68-1), 53A (FCV 68-3), 65A (FCV 68-35), 65B (FCV 68-33), 53B (FCV 68-79), 43B (FCV 68-77)
FCV 1-15, FCV 1-14, PCV 1-5, 1-501, PCV 1-26, PCV 1-23, PCV 1-22, PCV 1-19, PCV 1-37, PCV 1-34, PCV 1-31, PCV 1-30, FCV 1-42, 1-537, PCV 1-41 1-4, FCV 1-27, FCV 1-18, FCV 1-38, FCV 1-52, FCV 1-51, PCV RHR CRD Return Core Spray RWCU RCIC HIPCI 8 IA (HCV 74-69), 46A (FCV 74-68), 25A (FCV 74-67), 81 B (HCV 74-55), 46B (FCV 74-54), 25B (FCV 74-53), HCV 74-49, FCV 74-48, FCV 74-47 85-577,85-576 14A (HCV 75-27), 13A (FCV 75-26), 12A (FCV 75-25), 14B (HCV 75-55), 13B (FCV 75-54), 12B (FCV 75-53)69-500, FCV 69-1, FCV 69-2,69-580 FCV 71-40 FCV 73-2, FCV 73-3, FCV 73-45 END OF TABLE 8.5A System
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 83 of 113 ISI-2 ISI-3 ISI-4 Rev. 01 ISI-5 Rev. 01 ISI-6 ISI-7 ISI-8 ISI-9 ISI-10 ISI-11 ISI-12 ISI-13 ISI-14 ISI-15 ISI-16 Table 8.6 Relief Requests Relief from volumetric examination of RPV welds Code Category B-B Relief from volumetric examination of RPV Support Skirt weld Code Category B-H.
Relief from Visual examination of pump internal pressure boundary, Code Category B-L-2.
Relief from Valve internals visual examination Code Category B-M-2.
Relief from volumetric examination of the CRD Housing welds Code Category B-0.
Withdrawn Volumetric limitations on piping welds Code Categories B-J, B-F, and C-F.
Relief for Volumetric examination of Support attachment welds Code Category B-K-I.
Relief for Ultrasonic Calibration Block Standards.
Relief from surface examination of support members Code Category C-E-1.
Volumetric examination of longitudinal welds in piping Code Category B-J.
Volumetric examination of nozzle to vessel attachment welds Code Category C-B.
Visual, Surface, and Volumetric examination of Class 2 bolting exceeding I" diameter Code Category C-D.
Ultrasonics in piping welds Volumetric examination of longitudinal piping welds Code Category B-J, C F, and C-G.
Inactive Inactive Inactive Inactive Inactive Inactive Inactive Inactive Inactive Inactive Inactive Inactive Inactive
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6.G Page 84 of 113 REQUEST FOR RELIEF ISI-2 Components Class-Function Reactor Pressure Vessel 1
Pressure-retaining component.
Test Requirement Basis for Relief Alternate Inspection:
Volumetric examination of reactor pressure vessel pressure-retaining welds, examination category B-B.
The Browns Ferry Nuclear Plant was designed and under construction before the issuance of Section XI. As a result, only those welds above the sacrificial shield are accessible for inservice inspection. Access has notbeen provided in the sacrificial shield area for external examinations nor does the BWR design permit internal examinations in this area. Only those welds above the sacrificial shield and portions of welds as may be accessible at nozzle access points will be examined during the mservice inspection intervals.
None.
Request for relief ISI-2 is included for historical purposes since it has been superseded by ISI-17 and 3-ISI-20.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 85 of 113 REQUEST FOR RELIEF ISI-2 (SUPPLEMENT)
A.
Welds that Cannot Be Examined Lower head bottom section to lower head center section circumferential seam %Neld (approximately 39 ft long).*
The lower head center section contains four longitudinal welds (approximately 2.5 ft. long each)
- All other welds are identified on Drawing CHM-0992-C (unit 1)** and the inaccessible ones are listed below:
Weld Identification C-S-BH (Circ. Seam approximately 54 ft. long)
V-BH-2 (Long. Seam approximately 6.5 ft. long)
V-BH-3 (Long. Seam approximately 6.5 ft. long)
V-BH-4 (Long. Seam approximately 6.5 ft. long)
V-BH-5 (Long. Seam approximately 6.5 ft. long)
V-BH-6 (Long. Seam approximately 6.5 ft. long)
V-BH-l (Long. Seam approximately 6.5 ft. long)
Category B-B B-B B-B B-B B-B B-B B-B B.
Summary Code Category B-B Code Required Weld Length Accessible 5.9 ft. Long. Seam 7.0 ft. Circ. Seam Code Required weld Length Inaccessible 7.1 ft. Long. Seam 8.1 ft. Circ. Seam Accessible Length Not Required By Code 31.9 ft. Long. Seam 24.5 ft. Cite. Seam
- Category B-B
- CHM-2046-C (Unit 2) and ISI-0220-C (Unit 3) details same weld numbers
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 REQUEST FOR RELIEF ISI-3 Reactor Pressure Vessel Support Skirt Components 1-SI-4.6 G Page 86 of 113 I
Support components.
Test Requirement:
Basis for Relief:
Alternate Inspection:
Volumetric examination of support attachment weld to vessel, examination category B-H.
Approximately 6 feet of the attachment weld would examination to meet coderequirements However, nonremovable reactor vessel insulation limits inservice examination. Two access ports, approximately 180 degrees apart, provide access eamination of two 2-foot lengths. Four feet of the support skirt-to-reactor vessel weld will be ultrasonically examined during each inspection interval None.
Request for relief ISI - 3 is included for historical purposes since the weld attachment was made accessible to complete exam.
Class-Function
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 I-SI-4.6.G Page 87 of 113 REQUEST FOR RELIEF IS1-4 REVISION I Components:
Class Reactor Recirculation Pumps 1
Function Provides a variable reactor power rate by varying core coolant flowrate.
Test Requirement Basis for Relief:
Alternate Inspection:
Visual examination of pump internal pressure boundary surfaces, examination category B-L-2.
During maintenance, if required, visual examination of the recirculation pump internal pressure boundary surface is performed and documented under existing plant procedures.
In the absence of required maintenance, as is the case with the recirculation pumps at Browns Ferry during the first 10-year interval, disassembly of a recirculation pump solely to perform a visual examination of internal surfaces is impractical. This would represent unnecessary exposure of employees to high radiation and contamination areas and excessive expense to TVA.
Disassembly of this pump could require transport of the motor outside of containment; consequently, a possibility of damage to the pump, pump motor, or other safety-related equipment exists. Time required for this major task of disassembly, examination, and reassembly would consume at least three weeks of 24-hours-per-day work. Radiation dose rates of the pump exterior will average 10-20 rem/hour. This would result in a cumulative dose of between 100 and 300 man-rem.
The benefit received from this major effort is minimal considering employees exposure, potential damage to safety-related equipment, and cost. Relief from the visual examination B-L-2 requirement is, therefore, requested A.
None planned. As long as the flows, pressure and temperatures are as specified in the Byron-Jackson recirculation pump manual, no disassembly for routine visual examination is recommended.
B.
Conduct the required Code visual inspection of the interior during the cycle 6 outage.
INSERVICE INSPECTION PROGRAM UNIT 1 INSERVICE INSPECTION PROGRAM UNIT I REV 0003 REQUEST FOR RELIEF ISI-4 (Cont'd)
Alternate Monitoring 1-SI-4.6 G Page 88 of 113 A.
Install monitoring instrumentation on each pump for pump shaft vibration caused by mechanical fatigue driven crack growth with appropriate control room instrumentation.
B. Install monitoring instrumentation for contamination of component cooling water (CCW) by reactor coolant water caused by crack growth in the pump covers to the extent that a leak path develops between the two systems with appropriate control room instrumentation.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 I-SI-4 6 G Page 89 of 113 REQUEST FOR RELIEF ISI-5 REVISION I Components:
Class Function Test Requirement:
Basis for Relief:
Alternate Inspection:
Valves exceeding 4-inch pipe size Various Visual examination of internal pressure boundary surfaces, examination category B-M-2.
During routine maintenance, visual examinations of valve body internal pressure boundary surfaces are performed and documented under existing plant administrative procedures If no valve within a group has been disassemnbled for maintenance as the end of the interval approaches, relief from the visual examination B-M-2 requirements is requested. The attachments hereto present the valve groups requiring visual examination and the specific groups for each Browns Ferry Nuclear Plant unit for which relief is requested.
If no valves from a particular group have been disassembled as the end of the interval approaches, the valves comprising that group shall be visually examined for leakage when the system pressure tests (IWA-5000) are conducted in accordance with the requirements for Category B-P.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 90 of 113 TABLE I REQUEST FOR RELIEF ISI-5 Valve Groups Requiring Internal Pressure Boundary Visual Examination (B-M-2)
Group Number System Valve Type Valve Size Manufacturer Valve Numbers FW 2
3 4
5 6
- Unit 1 only
"**Units 2 & 3 FW Recirc.
Recirc.
Recirc.
MS Check Gate Gate Gate Gate Globe Relief Gate Check Gate Gate Gate Check Gate Gate Check Gate Gate Gate Gate Check Gate Check Gate 24" Atwood & Morrill 24" Powell 28" Darling 28" Darling 22" Darling 26" Atwood & Morrill 6"
Target Rock 24" Powell 24" Atwood & Morrill 24" Walworth 20" Powell 20" Walworth 6"
Velan 6"
Walworth 12" Powell 12" Rockwell 12" Walworth 6"
Velan 6"
Borg-Warner*
6" Velan 6"
Rockwell 10" Crane 14" Rockwell 20" Walworth MS 3-554, 3-558, 3-568, 3-572 HCV3-66, HCV3-67 FCV68-1, FCV68-77 FCV68-3, FCV68-79 FCV68-33, FCV68-35 FCVI-14, FCVI-15, FCV1-26, FCV1-27, FCVI-37, FCV1-38, FCV1-51, FCV-52 PCV1-4, PCVI-5, PCVI-18, PCVI-19, PCV1-22, PCV1 23, PCVI-30, PCV1-31, PCV1-34, PCV1-41, PCV1-42, PCVI-179, PCVI-180 HCV74-69, HCV74-55 FCV74-54, FCV74-68 FCV74-53, FCV74-67 HCV74-49 FCV74-47 74-691 FCV74-77, FCV74-78 HCV75-27, HCV75-55 FCV75-26, FCV75-54 FCV75-25, FCV75-53 69-500 FCV69-1*
FCV69-1**, FCV69-2 FCV71-40 FFCV73-2, FCV73-3 FCV73-45 FCV74-48 8
9 10 11 12 13 14 16 17 18 19 20*
21 24 25 26 27 RHR RHR RRR RHR RHR RHR RHR CS CS CS RWCU RWCU RWCU RCIC HPCI HPCI RHR
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 91 of 113 TABLE 2 Group Number(s)
Later REQUEST FOR RELIEF ISI-5 Unit I Valve Groups Not Opened for Maintenance Function Basis For Relief Later Later
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI4.6 G Page 92 of 113 REQUEST FOR RELIEF ISI-6 Components-Class.
Function Control Rod Drive Housing Welds I
Pressure-retaining component.
Test Requirement:
Basis for Relief:
Alternate Inspection:
Volumetric examination of peripheral CRD housing welds, examination category B-O.
Should the CRD housing weld fail, the leakage path to the failure meets the make-up exclusion criteria and is therefore excluded from volumetric examination in accordance with IWB-1220(b)(1). The make up supply system is equivalent to 4-inch nominal pipe size. The smallest leakage path area would be realized between the guide cap and thermal sleeve as shown on the attached diagrams. The following calculations verify exclusion of volumetric examination in accordance with IWB-1220(b)(1):
For 3-inch nominal pipe size (maximum code exclusion): D = 3.068 inches, A = (1)(D 2/4),
where A = internal transverse area D = inside diameter A3.in. = 7.39 in 2 For the thermal sleeve:
DTS = 4.25 inches ATS= 14.19 in.2 For the guide cap:
DGC
= 4.125 inches AGC
= 13.26 in.2 Total leakage path area:
ALP = ATS - AGC = 14.19 in.2 -13.36 in.2 = 0.83 in.2 A3.in" = 7.39 in.2 ALP = 0.83 in.2 Therefore, ALP < A3.in All peripheral CRD housing welds shall be visually examined during the system hydrostatic pressure tests in accordance with IWB-1220(c).
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6.G Page 93 of 113 BRMMrS FE*RRY NUCL.EAJR PL_,AXT FINJ AL SAFT-T ANAJL=. ;tEPC XT Comm R Eqd0,.SlmwcDU
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI4 6.G Page 94 of 113 REQUEST FOR RELIEF ISI-7 WITHDRAWN
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 I-SI-4 6 G Page 95 of 113 REQUEST FOR RELIEF ISI-8 REVISION 2 Class 1 Piping Welds (Refer to attached list)
Components:
Classification Code Categories Item Numbers" B-F, B-J, and C-F B4.1, B4.5, B4.7, and C2.1 Inspection Requirements-Basis for Relief:
ASME Section XI, Table IWB-2500-1, Examination Categones B-F and B-J piping welds greater than or equal to NPS 4-inch.
In some cases it is not possible to perform the volumetric ultrasonic examination from both sides of the weld due to configuration or permanent features such as piping supports, or fire retardant insulation in the adjacent wall penetration. Also attached is a detailed description of the limitations for each weld listed and a summary of the scans performed.
Alternate inspection:
I See Summary.
I /
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 96 of 113 TABLE 1 REQUEST FOR RELIEF ISI-8 UNIT 1 WELDS REQUIRING ALTERNATE SURFACE EXAMINATION WHEN ACCESSIBLE WELD IDENTIFICATION SCAN LIMITATION Later Later REASON Later
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 I-SI-4 6 G Page 97 of 113 REOUEST FOR RELIEF ISI-9 Components:
Class Function Integrally-Welded External Support Attachments for Piping and Valves I
Support components Y
Test Requirement Basis for Relief:
Alternate Inspection-Volumetric examination of the support attachment welds, examination categories B-K-1.
During the first Browns Ferry baseline inspection, the ultrasonic examinations of the integrally-welded Class 1 supports were meaningless because of the lack of penetration indications that existed for the full length of the support welds. The supports were fabricated to ANSI B3 1.1.0 and General Electric Company specification 21A2 100. The GE specification required a full penetration weld and surface examination requirements, which would not verify penetration. The TVA Division of Engineering Design has taken actual weld dimensions of randomly-chosen piping supports and compared the load capabilities of these welds as installed to the loads based on design the supports would see during operation As indicated in the attached analysis, all supports studied have high factors of safety in their load-carrying capability; therefore, we feel the integrally-welded supports on the primary coolant piping are acceptable as installed. Further ultrasonic examinations of these supports would be meaningless.
Class I integrally-welded supports will be liquid penetrant examined in place of ultrasonic examinations. The liquid penetrant examinations performed during each inspection interval will cover 25 percent of the integrally-welded supports.
Request for relief ISI-9 is included for historical purposes since updating the code of record for Category B-K-1 in Section 4.1 to the 1977 Edition, Summer 1978 Addenda, requires surface examination of Class 1 integral attachments.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 PIPE SUPPORTS-PRIMARY COOLANT PIPING COMPARISON OF DESIGN LOADS AND WELDS TO "AS-BUILT" 1-SI-4.6 G Page 98 of 113 Pipe Design Load Capability of Factor of Support Load Weld As Weld As Safety No Designed Installed As Installed CSR-8 1,000 lb
- 39,188 lb 44,467 lb 44 5 CSR-9 2,000 lb
- 39,188 lb 51,034 lb 25.5 CSR-1 1,000 lb
- 39,188 lb 44,467 lb 44.5 CSR-2 2,000 lb
- 39,188 lb 51,034 lb 25.5 RHR-69 4,200 lb
- I110,000 lb 115,200 lb 24.4 RHR-68 8,400 lb 76,776 lb 9.2 RHR-67 8,000 lb
- 98,129 lb 117,755 lb 14.7 SSAI,2,5, & 6 1,250 lb 57,600 lb 46 1 SSA8 (X) 12,993 lb
- 87,000 lb 57,600 lb 4.4 SSA9 (Z)
SSA7 (Z) 4,375 lb
- 72,194 lb 86,400 lb 19.7 SSB7 (Z)
SSC4 (Z) 17,750 lb
- 72,194 lb 57,600 lb 3.2 SSB4 (Z) 15,000 lb
- 72,194 lb 57,600 lb 3.8 SSB6 (X) 19,900 lb lb 72,000 lb 3.6 SSB5 (Y) 13,800 lb lb 57,600 lb 4.2 SSC1 (Z) 27,500 lb lb 126,000 lb 4.6 SSB2 (X) 30,600 lb lb 151,200 lb 5.0 BLANKS INDICATE INSUFFICIENT INFORMATION AVAILABLE
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-Si-4 6 G Page 99 of 113
- The "Designed" weld would equal or exceed the strength of the attachment if it were a full penetration bevel weld as shown.
The load capacity shown is the tensile or shear strength of the attachment NOTE:
The load capacities of the "as installed" welds are based on an allowable shear strength of 14,500 psi. or 600 lb per 16th of an inch of leg per linear inch of weld for fillet welds.
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6 G Page 100 of 113 ADDITIONAL INFORMATION REGARDING INSERVICE INSPECTION PROGRAM REQUEST FOR RELIEF ISI-9 BROWNS FERRY NUCLEAR PLANT UNIT 3 (DOCKET NO. 50-296)
To provide justification for Request for Relief ISI-9 an analysis was performed on a selection of integral supports that are subject to fatigue loading Integral welds in the latest sample indicated substantially higher stress allowable factors of safety with a minimum factor of 8.3 calculated.
Attached is a list of assumptions used in the analysis and a summary of analysis results. Based on these results, we believe that the integral support welds are entirely acceptable, and relief from the inservice volumetric examination requirements of the ASME Section XI Code is justified ASSUMPTIONS I.
Due to lack of full penetration, fillet welds were assumed with a base dimension equal to the specified penetration grove opening
- 2.
Restraint loads as specified by the support assembly drawings were applied.
- 3.
Effective area of the fillet welds was in accordance with paragraph XVII-2452.5, Appendix XVII,Section III, ASME Code
- 4. Shear and tensile stresses in the welds were combined by the maximum shear stress formula to compare with the fillet weld shear allowables presented in paragraph NF-3291.1-1, Subsection NF,Section III, ASME Code. The minimum specified shear allowable is applied in all cases.
- 5. No stress concentration factors were applied. The high factors of safety more than offset any concentration affects.
SUMMARY
OF RESULTS PIPE INTEGRAL ATTACHMENT WELDS HANGER LOAD(POUNDS)
MAXIMUM SHEAR STRESS SAFETY FACTOR RHR-R-74 840 463 PSI 39 RHR-H-1*
15940 2155 PSI 8.3 RHR-H-3*
11075 1367 PSI 13.2 MS-H-Bl, -CI*
3606 740 PSI 24.3 MS-H-B2, -C2*
6350 1425 PSI 12.6 RWC-H-I*
1300 854 PSI 21.0 HPCI-H-I (H152) 6060 1630 PSI 11.0 HPCI-H-2 (H48) 2368 1070 PSI 16.8 RH-2, - 12*
11800 1780 PSI 10.1 RH-1, -9*
13400 1719 PSI 10.5 RH-10, -11*
8900 1342 PSI 13.4
- For these lugs, drawings call out full penetration plus fillet welds.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 I-SI-4 6.G Page 101 of 113 REQUEST FOR RELIEF ISI-10 Ultrasonic Calibration Standards I and 2 Ultrasonic calibration for examination of welded components Test Requirement Basis for Relief Alternate Inspection:
Ultrasonic calibration blocks fabricated to 1974 Edition, Summer 1975 Addenda, of Section XI, IWA-2232.
Ultrasonic calibration blocks employed for the Browns Ferry baseline examination were fabricated to the 1971 Edition of Section XI. These blocks will continue to be used for future examinations to ensure the repeatability of data The pipe blocks have 5%T sawtooth notches running circumferentially around the inside and outside diameters. One side-drilled hole is placed in the side of the block parallel to the longitudinal axis of the curved blocks. Pipe block curvature is within 0.9 to 1.5 times the diameter of the pipe examined; and thickness and hole size are according to ASME Section III, Figure IX-3432.1 ofthel971 Edition, Summer 1971 Addenda Material for all blocks was the same or equivalent "P" number except as discussed in the attached file note and shown in the mill test report also attached.
Future examinations which require fabrication of new calibration blocks will be performed using calibration blocks which will meet the 1974 Edition, Summer 1975 Addenda of Section XI, except for piping blocks which will as a minimum meet the 1977 Edition, Summer 1978 Addenda of ASME Section XI.
Components Class Function
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 I-SI-4 6 G Page 102 of113 FILE NOTE DETERMINATION OF ACOUSTIC PROPERTIES OF VARIOUS CALIBRATION BLOCKS FOR USE IN INSERVICE INSPECTIONS AT BROWNS FERRY NUCLEAR PLANT.
During recent metallurgical examinations of calibration blocks used for baseline and inservice inspections at Browns Ferry, it was shown that four calibration blocks were not made from material of the same or equivalent P number as the matenal that was examined Since this same or equivalent P number is required by Appendix IX of Section III of the ASME Boiler and Pressure Vessel Code, it was necessary to determine the acoustic properties of these four blocks with respect to material of the components.
Calibration blocks BF-1 IC, BF-12C, BF-13, and Automation Industries AISI 4340 3-inch area amplitude block S.N 1219 were used to examine materials of different P number. The velocity and attenuations in these blocks were compared to the material they were used to examine as described in the following paragraphs.
Block BF-l1 C was made from A515 grade 70 material while block BF-12C was made from A515 grade 55 material Both blocks were used to calibrate for A533 grade B material. To demonstrate similarity, both blocks were compared to BF-10C, which is A533 grade B, for sound velocity and attenuation.
Using a Krautkramer type USIP-1CW ultrasonic flow detector, with an Automation Industries 2.25 MHz, type SFB 3/8-inch effective diameter crystal, these back reflections from the 3.007-inch side of BF-12C were placed at the 3-, 6-, and 9-inch locations on the CRT graticule. The crystal was then placed on the 3.992-inch of BF-1 IC. Back reflections were observed at the 4-and 8-inch locations on the CRT graticule. After this, the crystal was placed on the 4.032-inch side of BF-10C. The first back reflections occurred between 4.000 and 4.050 inches and was interpreted to be 4.025 inches The second back reflection occurred between 8.000 and 8.100 inches and was interpreted to be 8.050 inches By the above process, it was determined that the velocity of sound was essentially the same through all three blocks.
To check attenuation an Automation Industries 5 MHz, type SFB, 3/8-inch effective diameter crystal was placed on the 4-inch thickness of BF-0OC. With the first back reflection set at 60 percent of full scale, the gain setting read 42 dB. The gain was then increased to 51 dB to bring the second back reflection up to 60 percent scale height. This gave an attenuation of 0.75 dB/inch.
This procedure was repeated on the 4-inch side of BF-1 1C with a change in dB from 58 to 42. This gave an attenuation of 2.5 dB/inch The 2.2-inch side of BF-12C was then evaluated and a change in dB from 36 to 45 was necessary to bring the second back reflection up to 60 percent full scale.
This gave an attenuation of 1.5 dB/inch. All three measurements were reported three times with the same results. It can be seen that calibration with BF-11 C or BF-1 2C would give a more sensitive examination than is required.
BF-13, which is A437 grade B4C, is used to calibrate for A540 grade B23 material. Using an Automation Industries 5-MNIz, type SFB, 3/8-inch effective diameter crystal, the 100-inch scale of the ultrasonic instrument was checked for linerity using an Automation Industries' AISI 4340 3-inch block S.N. 1219 and a 65.6-inch reactor closure head stud made from A540 grade B23 material. When the crystal was placed on the 69-inch BF-13, a back reflection was seen within 1 inch of the desired reading, which is as close as the scale can be resolved on the 100-inch scale. To check for attenuation, the back reflection of BF-13 was set at 80 percent scale height with a gain setting of 43 dB. The same amplitude was obtained on the reactor closure head stud using 42 dB On the basis of the above tests, BF-13 is considered a satisfactory calibration block for A540 grade B23 material.
The Automation Industries' AISI 4340 3-inch area amplitude block S N. 1219 is also used for examining recirculation pump nuts made from A194, C1. 24 material. Both nut and block were 3 inches thick. Both distances measured 3 inches by using the USIP-1 CW Krautkramer ultrasonic flow detector with an Automation Industries 5 MH, type SFB, 3/8-inch effective diameter crystal
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 I-SI-4 6 G Page 103 of 113 DETERMINATION OF ACOUSTIC PROPERTIES OF VARIOUS CALIBRATION BLOCKS FOR USE IN INSERVICE INSPECTION AT BROWNS FERRY NUCLEAR PLANT Summary Calibration Block No Material A533, Grade B A515, Grade 70 A515, Grade 55 Attenuation 0.75 dB/inch 2.50 dB/inch 1.50 dB/inch Attenuation is less in BF-10C than in either BF-1 IC or BF 12C. Therefore, use of BF-12 to calibrate a scope for use in testing A533, grade B, material will result in a test more sensitive than required and is acceptable.
Block BF-13 was found to have the same attenuation as the 65.5-inch studs for which it was used as a calibration block I
Block Automation Industries AISI 4340 was formed to have the same attenuation as the nuts for which it was used as a calibration block.
There were no variations or discrepancies in any of the velocity or propagation tests.
Description of the Blocks:
BF-10C A533, Grade B Supplied by Magnaflux Used for flange-to-vessel welds Attenuation - 0.75 dB/inch BF-11C A515, Grade 70 Used for nozzle-to-head, head, and nozzle-to-vessel welds Supplied by SWRI after unit I inspection Attenuation - 2.25 dB/inch BF-12C A515, Grade 55 Used for support skirt welds Attenuation - 1.5 dB/inch BF-13 Crucible 422 Used for 65.5-inch studs Attenuation - same as studs BF-10C BF-1IC BF-12C
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 1-SI-4 6 G Page 104 of 113 Description of the Blocks.
Automation Industries AISI 4340, 3-inch area amplitude block S.N. 1219 Contains 1/8-inch flat bottom hole 3 inches from top surface Total length of block approximately 3-3/4 inches Used for nuts Attenuation - identical to the nuts "The procedure for determining attenuation is given in Krautkramer ultrasonic test instructions.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 COMBUSTION ENGINEERING, INC. (CE)
TVA-BROWNS FERRY ULTRASONIC C I-SI-4.6 G Page 105 of I I 3ALIBRATION BLOCKS Ni Cr TVA Identif.
BF-IC BF-2S BF-3C BF-4S BF-5C BF-6S BF-7C BF-8S BF-9C BF-10C BF-1 IC BF-12C BF-13 CE Identif.
P-14607 P-14608 P-14609 P-14610 P-14611 P-14612 P-14613 P-14614 P-14615 P-14616 P-14617 P-14618, P-14619 Mo C
V Mn 0.96 0.47 0.93 1.66 0.85 1.60 0.0 1 60 0.62 1.22 0.74 0.65 0.87 Comments A106, GR.B A358, 304 SS A106, GR. B A358, 304 SS A106, GR. B A358, 304 SS AI05, GR, B
-A240, 304 SS A36 (A283)
A533 GR. B A515, GR. 70 A515, GR. 55 A437, BR. B4C 0.013 0020 0.11 0.020
<0.01
<0.010 9.940
<0.010 9.600 0.030 10.470
<0.010 0.510 0010 0.470 0.070 0.040 0.750
<0.01 18.67
<0.01 18.54 0.01 10.37
<0.01 10.17
<0.01 0.09 0.02
<0.01 11.19 0.001 0.030
<0.001 0 040
<0.001 0.050
<0.001 0.040
<0.001
<0.003
<0.001
<0.001 0.250 0.204 0.035 0.250 0.048 0.250 0.053 0260 0.035 0.230 0.230 0.330 0.220 0.250
<0.01 0.06
<0.01 0.2
<0.01 0.17
<0.01 0.10
<0.01 0.49
<0.01
<0.01 0.93 P
0.03 0.019 0.019 0.032 0.003 0.021 0.004 0.020 0.007 0.010 0.008 0.011 0.020 S
0.016 0.012 0.021 0.016 0.022 0.018 0.020 0.009 0.017 0.015 0.023 0.024 0.014 Si 0.21 0.41 0.14 0.41 0.17 0.52 0.13 0.53 0.02 0.22 0.21 0.20 0.33 BF-15C P-14620 0.210 0 44
<0.01
<0 001 A519, GR MT 1020
INSERVICE INSPECTION PROGRAM UNIT I I-SI-4 6 G REV 0003 Page 106 of 113 REQUEST FOR RELIEF ISI-I I Main steam 2
Test Requirement:
Basis for Relief.
Surface examination of support members for piping examination category C-E-1.
The main steam system includes four special restraints, each of which is partly embedded in a wall. Each embedded restraint includes 12 guide lugs which are welded to the process pipe. These welds are inaccessible for examination. Each restraint also includes 12 stop plates welded to the process pipe which are accessible for examination. They shall be surface examined during the inspection interval (see attached drawings )
Alternate Inspection:
System.
Class:
None.
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INSERVICE INSPECTION PROGRAM UNIT I 1-SI-4 6 G REQUEST FOR RELIEF ISI-12 REV 0003 Page 108 of113 Pressure retaining longitudinal welds in piping 1
Pressure retaining component Test Requirement:
Basis for Relief Alternate Inspection:
Volumetric examination of pressure-retaining longitudinal welds in piping, examination category B-J.
See the attached supplement for weld identification, estimated extent of code examination, and reason for limitation.
A surface examination will be performed on the accessible code required length of the weld.
Request for Relief ISI-12 is included for historical purposes since it has been superseded by ISI-16.
Components-Class:
Function
INSERVICE INSPECTION PROGRAM UNIT I I-SI-4.6 G REQUEST FOR RELIEF ISI-13 REV 0003 Page 109 of 113 RHR Heat Exchangers 2
Pressure retaining nozzle welds in vessels Test Requirement:
Basis for Relief:
Alternate Inspection-Volumetric examination of nozzle-to-vessel attachment welds, examination category C-B.
The RHR heat exchangers nozzle-to-vessel attachment weld is covered by a reinforcement ring (shown in the attached sketch) which does not allow access to any of the attachment weld The reinforcement ring welds are accessible and will be given a surface examination. Two reinforcement rings on each unit will be examined over the 40-year inspection interval in accordance with IWC-2411 on ASME Section XI.
Components Class-Function-
INSERVICE INSPECTION PROGR.AM UNIT 1 I-SI-4 6 G REV 0003 Page 110 of 113 REQUEST FOR RELIEF ISI-14 Components:
Class:
Pressure-retaining bolting 2
Inspection Requirements:
Basis for Relief:
Alternate Inspection Visual, surface, and volumetric examination of pressure-retaining bolting exceeding one inch in diameter, examination category C D.
Examination of class 2 pressure-retaining bolting in accordance with the Summer 1975 Addenda of Section XI exceeds inspection requirements for class 1 pressure-retaining bolting. We do not feel an increased level of safety is obtained from a more restrictive examination of class 2 components. An examination program for class 2 pressure retaining bolting similar to that for class I would be desirable. This type of examination has been incorporated in later additions of the code which Browns Ferry will be required to meet in the future.
Class 2 pressure retaining bolting exceeding two inches in diameter shall be volumetrically examined in accordance with Table IWC-2500-1, examination category C-D of the 1977 Edition, Summer 1979 Addenda of Section XI. Pressure-retaining bolting two inches or less in diameter will not be examined.
INSERVICE INSPECTION PROGRAM UNIT 1 I-SI-4 6 G REV 0003 Page I llof 113 REQUEST FOR RELIEF ISI-'I5 Ultrasonic examination technique of piping welds.
1 and 2 Function-Test Requirement:
Basis for Relief:
Alternate Inspection:
Ultrasonic calibration and examination of welded piping components.
Appendix III - 111-34 10 Material.
111-3430 Calibration Notches.
111-4450 Inaccessibility Welds.
The ultrasonic examination (IWA-2232(b), IWA-2232(c), and Appendix III) and evaluation (IWA-3000) of piping welds is being updated to the 1977 Edition, Summer 1978 Addenda of ASME Section XI to provide state-of-the-art methods for both. There are existing requests for relief (addressed to the 1974 Edition of the ASME Code) from the test requirements listed above. We do not believe the existing requests for relief (ISI-8 and ISI-10) affect the overall purpose of updating the examinations and evaluation techniques.
We request relief to remain to the 1974 Edition, Summer 1975 Addenda and the existing requests for relief for calibration block material, calibration notches, and inaccessible welds.
As specified in ISI-8 and ISI-10.
Request for relief ISI-15 is included for historical purposes since the exam technique was upgraded to 1986 Code.
Components-Class:
INSERVICE INSPECTION PROGRAM UNIT I REV 0003 1-SI-4 6.G Page 112 of 113 Request for Relief ISI-16 Components Classification:
Code Categories:
Item Numbers-Inspection Requirements:
Basis For Relief:
Longitudinal Welds in Class I and 2 Piping Class 1 and 2 B-J, C-F, and C-G B4.5 and C2.2 ASME Section XI, 1974 Edition, Summer 1975 Addenda, Tables lWB-2500 and IWB-2600 require a volumetric examination to be performed of at least one pipe diameter length but no more than 12 inches of each longitudinal weld that intersects a circumferential weld required to be examined under Code Category B-J.
Longitudinal piping welds are fabricated during the manufacturing process under controlled shop conditions, which produce higher quality welds and more uniform residual stress patterns.
Longitudinal piping welds undergo heat treatment in the manufacturing facility, which enhances the material properties of the weld and reduces the residual stress created by welding.
Results of previous weld inspections throughout the industry indicate that longitudinal welds have not been a safety concern, and there has been no evidence of longitudinal weld defects compromising safety at nuclear power plants.
Longitudinal welds have not been shown to be susceptible to any particular degradation mechanism.
The only areas of a longitudinal weld that may be suspect are the ends of the weld adjacent to the field fabricated circumferential weld.
Longitudinal welds are extremely difficult to locate even when the piping is identified as welded pipe. Typically, the existence and location of longitudinal welds must be determined by acid etching, eddy current examination, or a combination of the two methods.
This results in an increase in personnel radiological exposure and generation of radwaste above that incurred as a result of performing the required examinations of the longitudinal welds.
INSERVICE INSPECTION PROGRAM UNIT 1 REV 0003 Page 113 of 113 Basis For Relief (cont).
Alternate Inspection:
The radiological exposure and cost associated with the inspection of longitudinal welds is dependent on the time it would take to remove and reinstall insulation and interferences, prepare the weld for examination, and perform the examination.
Based on the above, the inspection of longitudinal welds as currently required by ASME,Section XI is not technically warranted. The ASME Code Committee has recognized this fact and has published Code Case N-524, "Alternative Examination Requirements for Longitudinal Welds In Class 1 and 2 Piping Section XI, Division 1."
As an alternative to the existing ASME,Section XI requirements, Browns Ferry Nuclear Plant will adopt the provisions of ASME Code Case N-524 for the examination of Class I and 2 longitudinal piping welds.
LAST PAGE 1-SI-4.6 G